ML20108B285

Rev 5 to Offsite Dose Calculation Manual

ML20108B285
Person / Time
Site:	Perry
Issue date:	11/22/1995
From:	Mack J CENTERIOR ENERGY
To:
Shared Package
ML20108B280	List: ML20108B277 ML20108B282 ML20108B285
References
PROC-951122, NUDOCS 9605030241
Download: ML20108B285 (197)

Text

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- Clarify and correct typographical errors in RDF Program

- Remove refermee to EPA cit 6sde Program (no longer available)

- Allow for the use of annual average atmospheric conditions for the determination of gaseous dose.

- Ihis change vill make the entire ODW reflect what the Bases section currmtly states.

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ODCM Page: i t

Rev.: 5 The Cleveland Electric Illuminating Company PERRY OPERATIONS MANUAL Offsite Dose Calculation Manual TITLE:

OFFSITE DOSE CALCULATION MANUAL

/

REVISION:

5 EFFECTIVE DATE:

]/-@ T3 PREPARED:

Michael Doty

/pe w /

12-1-94 f '

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Date IN-DEPTH

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Ddte PORC REVIEW AND RECOMMENDATION FOR APPROVAL MEETING NUMBER:

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i ODCM Page:

ii

-Rev.: 5 Offsite Dose Calculation Manual Table of Contents Section Title Pagee

1.0 INTRODUCTION

1

[

2.0 LIQUID EFFLUENTS 2

2.1 Batch Releases "2

4 2.1.1 Monitor Alarm Setpoint Determination 2

j i

2.1.1.1 Determination of the Minimum Acceptable 8-Dilution Factor-3 2.1.1.2 Determination of the Maximum Allowable Radwaste l

Tank Discharge Flow Rate 3

1 2.1.1.3 Liquid Radwaste Discharge Flow Monitor Alarm I

Setpoint 4

2.1.1.4 Liquid Radwaste Discharge Radiation Monitor i

Alarm / Trip Setpoint 5

2.1.2 Compliance with-10CFR20 - Liquid Effluent

)

Concentration 6

2.1.2.1 Concentration of Radionuclides in Prerelease 6

2.1.2.2 Post Release 7

2.2 Continuous Releases-8-

2.3 Compliance with 10CFR50, Appendix I - Liquid Effluent Dose 11-2.3.1 Dose Calculations 11 2.3.2 Cumulation of Doses 13 2.3.3 Projection of Doses 13 2.3.4 Population-Dose 14 3.0 GASEOUS EFFLUENTS 32 3.1 Monitor Alarm Setpoint Determination 34 3.1.1.

Determination of the ' Mix" (Noble Gas Radio-nuclide Composition) of the Gaseous Effluent-35 3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radio-nuclides in Gaseous Effluent Based on Total.

Body Dose Rate Limit) 35 3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radio-nuclides in Gaseous Effluent Based on Skin Dose Rate Limit) 36 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas

~

Radionuclides in Gaseous Effluent 37 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides 37 1

3.1.5.1 Determination of the Monitor High Alarm Setpoint 38 3.1.5.2 Determination of the Monitor Alert Setpoint 38

ODCM j

Page:

iii Rev.:

5 Offsite Dose Calculation Manual Table of Contents (Cont.)

Section Title Page 3.2 Compliance with 10CFR20 - Gaseous Effluent Dose Rate 41 3.2.1 Noble Gases 41 1

3.2.2 Radionuclides, Particulates, and Other i

Radionuclides 41 3.2.3 Dose Rate Calculations 42 3.3 Compliance with 1~0CFR50 Appendix I - Gaseous l

Effluent. Dose 69 3.3.1 Noble Gases 69 3.3.2 Radionuclides, Particulates, and Other Radionuclides 70 3.3.3 Dose Calculations 70 3.3.4 Cumulation of Doses 71 3.3.5 Projection of Doses 72 3.4 Population Dose 72 4.0 TOTAL DOSE 74 4.1 Compliance with 40CFR190 - Uranium Fuel Cycle l

Dose 74 4.2 Direct Radiation Dose from PNPP 76 l

4.3 Dose to Members of the Public While Onsite 77' 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 78 I

5.1 Monitoring Program 78 l

5.2 Land Use Census Program 79 5.3 Inter Laboratory Comparison Program 80 APPENDIX A Atmospheric Dispersion and Deposition Parameters 92 APPENDIX B Lower Limit of Detection 108 APPENDIX C Controls 112 REFERENCES 188 i

1

ODCM Page:

iv Rev.:

5 List of Tables Table Title Page 2.3-1 Organs Used for Liquid Effluent Dose Calculations 15 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations 15 2.3-3 Liquid Effluent Dose Pathways 15 2.3-4 Biaccumulation Factors (Bip) (pCi/kg per pCilliter) 16 2.3-5 Ingestion Dose Factors for Adult (mrem /pCi ingested) 17 2.3-6 Ingestion Dose Fa'ctors for Teenager (mrem /pCi ingested) 19 2.3-7 Ingestion Dose Factors for Child (mrem /pCi ingested) 21 2.3-8 Ingestion Dose Factors for Infant (mrem /pCi ingested) 23 2.3-9 External Dose Factors for Standing on Contaminated Ground 25 2.3-10 Liquid Effluent Dilution Factors (M )

27 p

2.3-11 Transit Times Required for Nuclides to Reach the Point of Exposure (t )

27 p

2.3-12 Usage Factors (Uap}

20 2.3-13 Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP 29 2.3-14 Dilution Factors for the Fish Ingestion Patl..

Individual Grid Locations 30 2.3-15 Dilution Factors for the Shore Exposure Pathwap 31

~

3.1-1 Total Body c9d Skin Dose Factors 40 3.2-1 Organs Used for Gaseous Effluent Dose Calculations 47 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations 47 3.2-3 Gaseous Effluent Dose Pathways 48 3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 48.

3.2-5 External Dose Factors for Standing on Contaminated Ground 49 3.2-6 Inhalation Dose Factors for Adult (mrem /pCi inhaled) 51

ODCM Page: y Rev.:

5 List of Tables (Cont.)

Table Title Pace 3.2-7 Inhalation Dose Factors for Teenager (mrem /pCi inhaled) 53 3.2-8 Inhalation Dose Factors for Child (mrem /pCi inhaled) 55 3.2-9 Inhalation Dose Factors for Infant (mrem /pci inhaled) 57 3.2-10 Ingestion Dose Factors for Adult (mrem /pCi inhaled) 59 3.2-11 Ingestion Dose Factors for Teenager (mrem /pci inhaled) 61 3.2-12 Ingestion Dose Factors for Child (mrem /pCi inhaled) 63 3.2-13 Ingestion Dose Factors for Infant (mrem /pCi inhaled) 65 3.2-14 Annual Usage Factors for the Maximum Exposed Individual 67 3.2-15 Annual Usage Factors for the Average Individual 67 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite Plume 73 5.1-1 Radiological Environmental Monitoring Program 81 5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 86 5.1-3 Detection Capabilities for Environmental Sample Analysis and Lower Limit of Detection (LLD) 87 A-1 Atmospheric Depletion and Deposition Factors 95 A-2 Site Boundary Atmospheric Dispersion (g/Q) and.

Deposition Parameters (D/Q) for PNPP Unit 1 97 A-3 AtmosphericDisgersion(x/Q)asaFunctionof Distance (s/m )

98 A-4 AtmosphericDigpersion(D/Q)asaFunctionof Distance (m' )

103

l l

l ODCM i

Page: vi Rev.: 5 List of Figures Figures Title'

Page, a

2.1-1 Liquid Radioactive Waste (LRW) Discharge System 10 3.0-1 Gaseous Effluent System Flow Diagram 33 3.2-1 PNPP Site Boundary and Unrestricted Area

_68 5.1-1 Technical Specification Required Radiological Environmental Monitoring Program Sampling l

Locations within Two Miles of the Plant Site 89 i

5.1-2 Technical Specification Required Radiological Envire mental Monitoring Program Sampling Locations Between Two and Eight Miles from the Plant Site 90 5.1-3 Technical Specification Required Radiological Environmental Monitoring Program Sampling Locations Greater Than Eight Miles from the Plant Site 91 i

Om i

G l

ODCM Page: vii Rev.: 5 SCOPE OF REVISION:

Rev. 5 - 1.

Revised in its entirety, no rev bars needed.

2.

This revision incorporates the procedural details of the RETS into the ODCM, in accordance with guidance of G. L. 89-01, Letter PY-CEI/NRR-1655L.

e e

i e

e-

=

l l

l ODCM l

Page:

1 Rev.:

5

1.0 INTRODUCTION

This Offsite Dose C31culation Manual (ODCM) contains information and i

methodologies to be used by the Perry Nuclear Power Plant (PNPP),

l Unit 1, to ensure compliance with PNPP Radiological Effluent Technical Specifications. The Technical Specifications and this ODCM are written to satisfy 10CFR20, 10CFR50.36 and Appendix I, and 40CFR190 requirements.

Sections 2 and 3 of this manual deal with liquid and gaseous' radiological effluents, respectively. Each of these sections contain alam setpoint determination, radiation dose and dose rate,

calculation methodologies, as well as limits and requirements.

Section 4 covers uranium fuel cycle related radiation dose limits including direct dose.

7 Also included in this manual, in Section 5, is information relating to the Radiological Environmental Monitoring Program (REMP). The figures and tables contained therein designate specific sample types and locations currently used to satisfy the Technical Specification requirements for the REMP as well as sampling reporting and detection capability limits. The sample types and locations are subject to change based on factors including the results of the annual Land Use Census.

The ODCM has been prepared, as generally as possible, in order to minimize future revisions. However, any such changes will be reviewed and approved as per the Administrative Control Section of the PNPP Technical Specifications.

Supplemental information needed to support calculations is contained in the appendices at the end of this manual. Appendix A contains atmospheric dispersion and deposition parameters and Appendix B presents the methodology for determining the lower limit of detection (LLD).

Appendix C of the ODCM was prepared ba' sed on guidance of NUREG-1302,

'Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent _ Controls for Boiling Water Reactors," Generic Letter 89-01, Supplement No. 1.

This appendix along with plant procedures will be used by plant personnel to demonstrate compliance with Specifications 6.8.4.d (Radiological Effluent Controls Program) and 6.8.4.e (Radiological Environmental Monitoring Program) of the PNPP i

Technical Specifications.

i

1 m

ODCM Page: 2 Rev.: 5 2.0 LIQUID EFFLUENTS 2.1 Batch Releases A batch release is the discharge liquid radioactive waste of a discrete volume. Batch releases from the liquid radwaste system may occur from any of the following tanks: waste sample tank, floor drain sample tank, chemical waste distillate tank, and detergent drain tank (see Figure 2.1-1).

The maximum release rate possible, due to pump capacity, is 200 gallons per minute from all release tanks except the detergent drain tanks, which have a maximum release rate of 50 gallons per minute. All of the above liquid radwaste releases go to the Dmergency Service Water discharge which is then released through the discharge tunnel after mixing with Service Water effluent and/or and blowdown from Circulating Water system, if present.

The type and frequency of sampling and analysis required by the ODCM Appendix C is given in Table 4.11.1.1.1-1.

Prior to sampling for analysis, each batch should be isolated, and thoroughly mixed to assure representative sampling. For mixing, the contents of the tank are recirculated by isolating the tank and turning on equipment that takes suction from and discharges back into the tank. Recycle i

lines are provided with one or more mixing eductors located near the bottom of the tanks to promote better mixing as well as reducing recirculation time. This ensures that the water in the tank will be mixed and will be representative of the activity in the tank. The minimum recirculation performed is the equivalent of two volumes of the tank contents.

Monitor alarm setpoints will be determined in order to ensure compliance with 10CFR20. The radioactive content of each batch release will be determined prior to ze. case in accordance with Table 4.11.1.1.1-1 of the ODCM Appendix C.

Concentrations for tritium and other non-gamma emitting isotopes will be those most recently determined (previous month / quarter).

2.1.1 Monitor Alarm Setpoint Determination The following methodology is used to calculate the setpoints for the Radwaste Discharge Radiation Monitor - ESW Discharge and Liquid Radwaste Adjustable High Flow Trip Unit to ensure that liquid radwaste effluent releases from the site to unre-stricted areas are below the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other -

than noble gases. An MPC of 2.0E-4 pCi/ml has been established for dissolved and entrained noble gases.

The Radwaste Dis-charge Radiation Monitor - ESW Discharge provides alarm and automatic termination of releases prior to exceeding these limits.

i ODCM Page: 3 Rev.: 5 l

NOTE:

Liquid radwaste discharge flow rate shall be verified at least once per four hours, whenever the flow rate measuring device (s) is inoperable during actual releases.

1 2.1.1.1 Determination of the Minimum Acceptable Dilution Factor Ci DF

=

E MW 0

i MPCg Where:

DF

= the minimum acceptable dilution factor determined from analysis of the liquid effluent to be released; C.

= the concentration of radionuclide 'i' in the batch 1

to be released, in pCi/ml; HPC. = the limiting maximum permissible concentration of 1

radionuclide 'i', from Appendix B, Table II, I

Column 2 of 10CFR20, in pCi/ml and (2.0E-4 pCi/ml l

for noble gases).

DF = 10 DF (2.1-2) g Where:

DF = the conservative dilution factor used by PNPP to calculate the maximum release rate prior to release in order to ensure compliance with 10CFR20; DF = the minimum acceptable dilution factor, as per g

equation 2.1-1; 10 = a factor of ten less than 10CFR20 limits as specified in Appendix B, Table II, Column 2; this factor represents an order of magnitude of conservatism for liquid radwaste releases from PNPP.

NOTE:

If the concentration of a radionuclide is below the lower limit of detection the radionuclide shall not be included as a source term in the setpoint calculation.

l 2.1.1.2 Determination of the Maximum Allowable Radwaste Tank Discharge Flow Rate (0.64)( mdf) f

=

DF (2.1-3) l g

i

ODCM Page:

4 Rev.: 5 Where:

f""* = the maximum allowable radwaste tank discharge flow rate for the batch to be released, in gpm; DF

= the conservative dilution factor, per t

equation 2.1-2; mdf = the minimum dilution flow - supplied by the. Service Water system, Emergency Service Water system, or i

Circulating Water system blowdown, e.g., the low flow alarm setpoint of the Service Water Flow Transmitter P41-N443 = 30,000 gpm; 0.64 = an engineering factor to prevent spurious alarms.

2.1.1.3 Liquid Radwaste Discharge Flow Monitor Alarm Setpoint Monitor alarm setpoints are determined to ensure that the concentration of radionuclides in the liquid radwaste effluent t

released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table II, Column 2 for i

radionuclides other than dissolved or entrained noble gases.

An MPC of 2.0E-4 pCi/ml has been established for noble gases i

dissolved and entrained in liquid effluents, i

SPg = (1.25) (fact)

(2.1-4)

Where:

SP

= Liquid Radwaste Adjustable High Flow Trip Unit g

(G50-K805A/B or G50-K926/7) alarm setpoint, in gpm;,

fact = the actual allowable radwaste tank discharge flow rate for the batch to be releasad, not to exceed the maximum allowable radwaste discharge flow rate (fmax) as defined in equation 2.1-3; j

1.25 = the engineering safety factor to prevent spurious alarms.

The liquid radwaste ttnk discharge flow should be maintained at or below this f value by proper regulation of the high voldmeorlowv87bedischargethrottlevalves(G50-F153or G50-F155).

ODCM Page:

5 Rev.: 5 2.1.1.4 Liquid Radwaste Discharge Radiation Monitor Alarm / Trip Setpoint Monitor alarm / trip setpoints are determined to ensure that the concentration of radionuclides in the liquid radwaste effluent released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

An MPC of 2.0E-4 pCi/ml has been established for noble gases dissolved end entrained in liquid effluents.

CR

{

(C;) (E;)

(2.1-5)

=

c 1

Where:

CR = the calculated monitor count rate above background, c

in cpm; C.

= the concentration of radionuclide 'i' in the batch 1

to be released, in pCi/ml; E.

= the detector efficiency of the monitor for 1

radionuclide "i" in cpm /(pCi/ml).

9.R CR = (R )(F )

C; (2.1-6) x g

x Where:

CR* = the cross-calibrated monitor count rate above background, in cpm;

)

~

F*

= the cross-calibration factor used to ratio the Liquid Radwaste Discharge Radiation Monitor actual response to the Cs-137 calibrated response; the response of the Liquid Radwaste Discharge R

=

s Radiation Monitor to a Cs-137 calibrated standard, in cpm /(pCi/ml).

SP = (1.25) (fmax/ fact) (CR } *

(*~}

r n

Where:

SP

= the Radwaste Discharge Radiation Monitor - ESW Discharge (OD17K0606) alarm / trip setooint, in cpm; BG

= the background count rate due to internal contamination and radiation levels in the area of the monitor;

ODCM Page: 6 i

Rev.: 5 CR" = the monitor net count rate, either CR or CR*, as c

l per equation 2.1-5 or 2.1-6; 1.25 = the engineering safety factor to prevent spurious alarms; f""* = an adjustment factor (to account for the difference between an actual radwaste discharge flow rate to f

be used for the discharge and maximum allowable act radwaste discharge flow rate) to allow operational flexibility and to minimize spurious alarms; Where:

fact = the actual radwaste discharge flow rate; this value must always be less than or equal to f

i max f, = the maximum allowable radwaste discharge flow rate, per equation 2.1-3.

2.1.2 Compliance with 10CFR20 - Liquid Effluent Concentration In order to show compliance with 10CFR20, the concentrations of radionuclides in liquid effluents will be determined and compared with the limiting maximum permissible concentrations i

(MPC) as defined in Appendix B, Table II, Column 2 of 10CFR20 (2.0E-4 pCi/ml for entrained and dissolved noble gases).

Concentrations of radioactivity in effluents prior to dilution j

will be determined. Concentration in diluted effluent will be calculated using these results prior to each batch release, and following each batch release. PNPP has no continuous releases.

2.1.2.1 Concentration of Radionuclides in Prerelease l

The radioactivity content of each batch release will be determined prior to release.

PNPP will show compliance with 10CFR20 in the following manner:

The concentration of the various radionuclides in batch releases prior to dilution is divided by the minimum dilution flow to obtain the concentration at the unrestricted area.

l This calculation is shown'in the following equation:

l (C )(f) g Conc. =

(2.2-1) 1 j

Mf i

I

ODCM Page: 7 j

Rev.: 5 Where:

i Conc. = the concentration of radionuclide 'i' at the 1

unrestricted area, in pCi/ml; C.

= the concentration of radionuclide 'i' in the batch i

1 to be released, in pCi/ml; f

= the radwaste tank discharge flow rate for the batch to be released, in gpm; mdf

= the minimum dilution flow, per equation 2.1-3, in' gpm.

The projected radionuclide concentrations in the unrestricted I

area are compared to the maximum permissible conc ntrations.in-Appendix B, Table II, Column 2 of 10CFR20 (2.0E-4 pCi/ml for

-dissolved and entrained noble gases) in order to give a final 10CFR20 compliance check, i.e., the following equation must be met:

Conc.

(2.2-2)

MPC.1 1

i Where:

Conc. = the concentration of radionuclide 'i' at the 1

unrestricted area, in pCi/ml; i

MPC.

= the limiting maximum permissible concentration of i

1 radionuclide 'i', from Appendix B, Table II,.

l Column 2 of 10CFR20 (2.0E-4 pCi/ml for dissolved and entrained noble gases), in pCi/ml.

2.1.2.2 Post Release The actual radioactivity content of'each batch release will be i

determined following release to show final compliance with 10CFR20.

The concentration of the various radionuclides in batch releases prior to dilution is divided by the actual dilution to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:

I (C;)(v d ir Conc. =

(2.2-3) 1-Vdil

l L

l ODCM I

Page: 8 l

Rev.: 5 Where:

Conc. = the actual concentration of radionuclide 'i' at 1

the unrestricted area for the release, in pCi/ml; C.

= the concentration of radionuclide "i' in the batch 1

released, in pCi/ml; i

V

= the actual volume of dilution water during the.

dil release (total plant discharge flow, including l

Service Water, Emergency Service Water, and cooling tower blowdown), in gallons; I

V

= the actual volume of the liquid radwaste tank irt discharged for the batch, in gallons.

The concentrations in the unrestricted area are compared to the maximum permissible concentrations in Appendix B, Table II, Column 2 of 10CFR20 (2.0E-4 pCi/ml for dissolved and entrained noble gases). In order to demonstrate final compliance with 10CFR20, the following equation must be met:

Conc.

(2.2-4)

MPC; i

Where:

conc *. = the concentration of radionuclide 'i' at the i

unrestricted area, in pCi/ml; MPC.

= the limiting maximum permissible concentration of 1

radionuclide 'i', from Appendix B, Table II, Column 2 of 10CFR20, in pCi/ml.

2.2 Continuous Releases A continuous release is the discharge of fluid wastes of a non-discrete volume, i.e., from a volume or system that has an input flow during the continuous release. Continuous radioactive releases are not planned for PNPP although the potential does exist for RHR heat exchanger leakage into the Emergency Service Water system.

Potentially contaminated discharges from the ESW are monitored by an installed radiation monitoring system. This system consists of two channels, one for monitoring downstream of equipment in Emergency Service Water System Loop A and the other for Emergency Service.

Water Loop B.

If radiation is detected, the affected Emergency O'g ;

Service Water line can be manually isolated. The decision of whether to isolate or not is dependent upon other conditions. The PNPP staff will take appropriate action to limit release.

PIC-1/VAX/Page 1 of 13

ODCM Page: 9 Rev.: 5

%e Emergency Service Water discharged will be sampled and analyzed in accordance with ODCM Appendix C, Table 4.11.1.1.1-1.

To show compliance with 10CFR20, the sum of the concentrations of g

radionuclide 'i' in unrestricted areas due to both continuous and batch releases divided by that isotope's MPC aust again be less than 1.

2.2.1 Monitor Alarm Setpoint Determination The following methodology is used to calculate the setpoints.

for the Emergency Service Water loops A & B Radiation Monitors.,

This methodology ensures an alarm will be received prior to exceeding the concentration limits listed in Appendix'B, i

Table II, Column 2 of 10CFR20.

L 1.

Emergency Service Water Radiation Monitor Alarm Setpoint CR = (BG + MR)(0.75) c l

Where:

CR

=

the calculated monitor count rate in cpm; c

BG the background count rate due to internal

=

contamination and radiation levels in the area of the monitor in cpm; g,1 MR expected monitor response due to 1.0 MPC of

=

a typical reactor water isotopic mix; O.75 =

engineering safety factor i

2.

Minimum Allowable Background of the Emergency Service Water Radiation Monitor BG

= CR - MR min c

Where:

minimum allowable background to ensure BG,1"

=

monitor will alarm prior to exceeding 1.0 MPC; CR the calculated monitor count rate in epm;

=

g MR expected monitor response'due to 1.0 MPC of

=

a typical reactor water isotopic mix; t,

i I

PIC-1/VAX/Page 2 of 13-

I l

ODCM l

Page:

9a Rev.:

5 l

l 3.

Determination of the Expected Monitor Response based on j

the Reactor Water Source Term l

I l

decayed x Eff"O" l

MR = I Idecayed g

MPC l

~

g Where:

expected monitor response due to 1.0 MPC of MR

=

a typical reactor water isotopic mix; I

decaged activity of isotope (I) after decaying a i

given time; Eff i

• E radiation monitor detector efficiency for isotope (I);

MPC. =

MPC value for isotope (I), Appendix B, 1

Table II, Column 2, 10CFR20 4.

Minimum Allowable Setpoint based on Monitor Background

. b,\\

i CR,gg = BG + ( 23 BG/2K )

Where:

tnin Minimum allowable setpoint for a given CR

=

monitor background (BG);

1 l

BG the background count rate due to

=

j internal contamination and radiation levels in the area of the monitor in l

cpm; l

2 95% confidence level;

=

1 2TC two times the instrument time constant

=

where (Log 10BG - Log 10TC IIEhicpm - ElominI locpm E*

+E lomin (Log 10TChicpm - W 10Klocpm)

Tim Constets:

10 cpm - 75 sec.

10000 cpm - 12 sec.

100 cpm - 75 sec.

100000 cpm - 2.5 sec.

1000 cpm - 75 sec.

1000000 cpm - 0.2 sec.

PIC-1/VAX/Page 3 of 13

i 7

l ODCM I

Page:

10 l

Rev.: 5 Figure 2.1-1 Liquid Radioactive Waste (LRW) Discharge System 1

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ODCM Page:

11 Rev.:

5 2.3 Compliance with 10CFR50, Appendix I - Liquid Effluent Dose Doses resulting from liquid effluents will be calculated at least monthly to show compliance with 10CFR50, Appendix I.

A cumulative summation of total body and organ doses for each calendar quarter and calendar year will be maintained. Additionally, doses due to liquid releases are projected monthly.

2.3.1 Dose Calculations Radiation doses due to. liquid radioactive effluents from PNPP are calculated based on three main dose pathways: potable water, aquatic foods (namely fresh water. fish ingestion), and exposure to shoreline deposits.

Irrigated food pathways, as discussed in Regulatory Guide 1.109, will not be of concern at PNPP as little or no water from Lake Erie is used'for i

irrigation in the nearby Ohio counties of Lake, Ashtabula, Cuyahoga and Lorain. Nursery businesses and other agricultural activities that require supplemental water generally rely on water drawn from small ponds and streams.

Radiation dose to members of the public for liquid radioactive releases from PNPP will be calculated for the potable water, aquatic food, and shoreline deposit pathways using the following equations:

1.

Potable Water:

U R,jp = 1100 (g p)

(Qg)(D,gpg) exp (- if t) (2.3-1) p p

i 2.

Aquatic Foods:

U R,$p = 1100 gg p)

(Qg)(Bgp)(D,gpj) exp (-1 t )

(2.3-2)

E g p 3.

Shoreline Deposits:

(U,p)(W)

R,$p = 110,000 (M )(F)

• IO ) (T ) (D,gp3) *

(2.3-3) i g

g P

[exp (-A t )] * [1 - exp (-A t Il

~~

g p g b Where:

R.

= the dose to individuals of age group 'a' to a3p organ "j" from all the radionuclides in pathway

'p',

in mrem;

ODCM Page: 12 Rev.: 5 l-B.

= the equilibrium biaccumulation factor for l

1p radionuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/1), from Table 2.3-4, in 1/kg; D*193

= the dose factor, specific to a given age group

'a', radionuclide 'i', pathway

'p', and organ "j", which chn be used to calculate the radiation dose from an intake of a radionuclide,-

in mrem /pCi; or from exposure to a given i

i concentration of a radionuclide in sediment, expressed as a ratio of the dose rate, in mrem /h,andthearealrgdlonuclide concentration, in pCi/m, from Tables 2.3-5 l

through 2.3-9; 3

F

= the flow rate of the liquid effluent in ft 7,,

NOTE:

The normal dilution flow will be between 30,000 L

and 61,500 gpm (USAR 11.2.3.2)

M

= the dilution factor at the midpoint of exposure p

(or the point of withdrawal of drinking water or l

point of harvest of aquatic food), from i

Table 2.3-10, dimensionless; t

Qi

= the release of radionuclide 'i', in Ci; t

= the period of time for which the sediment or b

soilisepsedtothecontaminatedwater, 1.75 x 10 h (20 years);

4 T

= the half-life of radionuclide 'i', in days; i

I t

= the average transit time required for p

L radionuclides to reach the point of exposure,

'from Table 2.3-11; for internal dose, t is the o

total time elapsed between release of the l

radionuclides and the ingestion of food or i

water, in h; U

= the usage factor that specifies the exposure ap time or intake rate for an individual of age group a associated with pathway

'p', from

~

Table 2.3-12, in h/yr, 1/yr, or kg/yr; l

l W

= the shoreline width factor, 0.3 (from Regulatory Guide 1.109);

f V

1

=theradioagtivedecayconstantofradionuclide 1

'i', in h ;

l l'

J I

ODCM Page:

13 Rev.: 5 3

1100

= a factor to convert from (Ci/yr)/(ft /s) to pCi/1; i

3 110,000 = a factor to convert from (Ci/yr)/(ft /s) to pCi/l and to account for the proportionality constant used in the sediment radioactivity i

model.

l 2.3.2,

Cumulation of Doses The dose contribution from liquid effluents will be calculated at least monthly. Calculations will be performed to determine' the maximum total body as well as the maximum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. These results will be summed with the doses cumulated from the other months in the quarter of interest and in the year of interest. To assure compliance with the dose limits of 10CFR50, Appendix I the following relationships shall hold:

for the quarter:

l Dose s 1.5 mrems total body; Dose s 5 mrems any organ; 1

for the calendar year:

Dose s 3 mrems total body; Dose s 10 mrems any organ.

The quarterly limits given above represent one-half of the annual design objective.

If these quarterly or annual limits are exceeded, a special report will be submitted to the NRC, in accordance with ODCM Appendix C controls, stating the reason and corrective action to be taken.

2.3.3 Projection of Doses Anticipated doses resulting from the release of liquid efflu-ents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.

l l

l

ODCM Page: 14 Rev.: 5 If the projected dose, when averaged over 31 days, exceeds 0.06 mrem to the total body or 0.2 mrem to any organ, the liquid radwaste system will be used to process waste..The values for the projected dose impact levels correspond to approximately one forty-eighthLof the Appendix I design objective.

If continued at this rate for one year, the projected impact would correspond to less than one-fourth of the Appendix I limit. The projected doses will be calculated using equations 2.3-1, 2.3-2, and 2.3-3.

In this case, the source term will be adjusted to reflect this, information and the justification for the adjustment noted.

This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming month.

2.3.4 Population Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for radioactive effluent releases. The total population dose and average individual doses will be calculated using average individual transit times and usage factors, Table 2.3-12, (as compared to maximum exposed individual factors used for individual doses).

The total population dose will be calculated by dose pathway and organ, with pathway doses being corrected _for the fraction of the population assumed to be in each age group (adult, teen, child and infant:

0.71, 0.11, 0.18, 0.0 respectively).

OO

ODCM Page:

15 Rev.: 5 Table 2.3-1 Organs Used for Liquid Effluent Dose Calculations 1.

Bone t

2.

GI Tract 3.

Kidney 4.

Liver 5.

Lung 6.

Thyroid 7.

Total Body 8.

Skin I

i Table 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations 1.

Adult (17 yrs. and older) 2.

Teen (11 - 17 yrs) 3.

Child (1 - 11 yrs)

'd.

Infant (0 - 1 yr) t j

Table 2.3-3 Liquid Effluent Dose Pathways 1.

Water Ingestion 2.

Shore Exposure

~

3.

Fresh Water Fish Ingestion l

1 l

ODCM Page:

16 Rev.: 5 Table 2.3-4 Biaccumulation Factors (B; ) (pCi/kg per pCi/ liter)

Element Fish H

9.0E-01 C

4.6E+03 Na 1.0E+02 4

P 1.0E+05 Cr 2.0E+02

~

Mn 4.0E+02 i

Fe 1.0E+02 i

Co 5.0E+01 1

Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 Rb 2.0E+03 Sr 3.0E+01-Y 2.5E+01 Zr 3.3E+00 Nb 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 Te 4.0E+02 I

1.5E+01 Cs 2.0E+03 Ba 4.0E+00 La 2.5E+01 Ce 1.0E+00 Pr 2.5E+01 Nd 2.5E+01 W

1.2E+03 Np 1.0E+01 4

1 ODCM Page:

17 Rev.: 5 Table 2.3-5 Ingestion Dose Factors for Adult (mrem /pCi ingested)

TOTAL ISOTOPE 80NE LIVER BODY THYROID KIONEY LUNG GI-LLI H3 0.00E+00 1.05E-07

1. 05 E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E"07 5.68E-07 NA24 1.70E-06 1.70E-06

1. 70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 ?.17E-05 CR51 0.00E+00 0.00E+00 2.66E-09 1.59E-09

5. 86 E-10 3.53E-09 6.69E-07 MN54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 MN56 0.00E+00 ' 15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 FESS 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 FES9 4.34E-06 1.02E-05 3.91 E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 l

C058 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 C060 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 NI63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 j

NI65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 CU64 0.00E+00 8.33E-08 3.91 E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 IN65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 2N69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 BR83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 BR84 0.00E+00 0.00E+00 5.21 E-08 0.00E+00 0.00E+00 0.00E+00 4.09 E-13 BR85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R886 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 RB88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00

8. 36 E-19 RB89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 SR89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.'00E+00 4.94E-05 SR90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 SR91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E +00 2.70E-05 SR92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y91M

9. 09 E-11 0.00E+00

3. 52E-12 0.00E+00 0.00E+00 0.00E+00

2. 67 E-10 i

Y91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E&O0 0.00E+00 7.67E-05 Y92

8. 4 5 E-10 0.00E+00 2.47 E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y93 2.68E-09 0.00E+00 7.40E-11 0.00E +00

.0.00E+00 0.00E+00 8.50E-05 ZR95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 ZR97 1.68E-09

3. 39 E-10 1.55E-10 0.00E+00 5.12 E-10 0.00E+00 1.05E-04 N895 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09

0. 00E +00 2.10E-05 M099 0.00E+00

4. 31 E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 TC99M

2. 47 E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07

ODOH Page:

18 Rev.:

5 Table 2.3-5 (Cont.)

Ingestion Dose Factors for Adult (mrem /pCi ingested)

TOTAL ISOTOPE BONE LIVER 80DY THYROID KIDNEY LUNG GI-LLI TC101

2. 54 E-10

3. 66 E-10 3.59E-09 0.00E+00 6.59E-09

1. 87 E-10 1.10E-21 RU103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 RU105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 RU106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 AG110M 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 TE125M 2.68E-06 9.17E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 TE127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 1131 4.16E-06 5.95E-06 3.41 E-06 1.95 E-03 1.02E-05 0.00E+00 1.57E-06 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 1133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00

2. 51 E-10 1135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 CS134 6.22E-05 1.48E-04 1.21 E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09

4. 65 E-13 BA139 9.70E-08 6.91E-11 2.84E-09 0.00E+00

6. 4 6 E-11 3.92E-11 1.72[-07 BA140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05

~

BA141 4.71E-08 3.56E-11 1.59E-09 0.00E+00

3. 31 E-11

2. 02 E-11

2. 22 E -17 BA142 2.13E-08 2.19E-11 1.34E-09 0.00E+00

1. 85 E-11

1. 24 E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 LA142

1. 28 E-10 5.82E-11

1. 4 5 E-11 0. 00 E +00 0.00E+00 0.00E+00 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 i

CE143

1. 65 E -09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 PR144

3. 01 E-11 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 l

i ND147 6.29E-09 7.27E-09 4.35E-10 0.00E&00 4.25E-09 0.00E+00 3.49E-05 W187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 NP239 1.19E-09 1.17E-10

6. 4 5 E -11 0. 00 E +00

3. 65 E-10 0.00E+00 2.40E-05

ODCM Page:

19 Rev.: 5 Table 2.3-6 Ingestion Dose Facters for Teenager (mrem /pCi ingested)

TOTAL ISOTOPE BONE LIVER BODY THYR 01D KIDNEY LUNG GI-LLI H3 0.00E+00 1.06E-07

1. 06 E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 CR51 0.00E+00 0.00E+00 3.60E-09 2.00E-09

7. 89 E-10 5.14E-09 6.05E-07 MN54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 MN56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 FESS 3.78E-06 2.68E-06 6.2SE-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 FE59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 C058 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 C060 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 NI63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00

0. 00E +00 1.99E-06 N165 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 CU64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 ZN65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 ZN69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 BR83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 R888 0.00E&00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 l

RB89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43 E-17 SR89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 SR90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 i

SR91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 SR92 3.05E-06 0.00E+00 1.30E-07 0.00E+00

0. 00 E +00 0.00E+00 '7.77E-05 Y90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00

0. 00E +00 1.13E-04 Y91M 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E&00 0.00E+00 6.09E-09 Y91 2.01E-Oi 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y92 1.21E-09 0.00E+00

3. 50 E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 ZR95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 ZR97 2.37E-09

4. 69 E-10 2.16E-10 0.00E+00 7.11 E -10 0.00E+00 1.27E-04 NB95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 M099 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 TC99M

3. 32 E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14 E-10 6.08E-07 i

ODCM Page: 20 Rev.:

5 Table 2.3-6 (Cont.)

Ingestion Dose Factors for Teenager (mrem /pCi ingested)

TOTAL ISOTOPE 80NE LIVER BODY THYROID KIDNEY LONG GI-LLI TC101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75 E-17 RU103 2.55E-07 0.00E+00 1.09E-07 0.00E&00 8.99E-07 0.00E+00 2.13E-05 RU105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 RU106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 AG110M 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E&00 0.00E+00 1.13E-05 TE127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E400 2.41E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 TE129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08

1. 88E-07 0.00E&00 2.45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 1130

1. 03 E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E +00 2.29E-06 l

1131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 1133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.90E-06 0.00E+00 2.58E-06 1134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 1135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 CS134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 CS136 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08

6. 76E-11 BA139 1.39E-07 9.78E-11 4.05E-09 0.00E+00

9. 22 E-11 6.74 E-11 1.24E-06 8A140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 8A141 6.71E-08

5. 01 E -11 2.24E-09 0.00E+00

4. 65 E-11 3.43E-11 1.43E-13 8A142 2.99E-08 2.99E-11 1.84E-09 0.00E+00

2. 53 E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71E-09 4.55E-10 0.00E+00

0. 00 E +00 0.00E+00 9.82E-05 LA142

1. 79 E-10 7.95E-11

1. 98 E-11 0. 00E+00 0.00E+00 0.00E+00 2.42E-06 CE141

1. 33 E -08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E&00 2.54E-05 CE143 2.35E-09 1.71E-06 1.91 E-10 0.00E+00 7.67E-10. 0.00E+00 5.14E-05 CE144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 PR143 1.31E-08 5.23E-09

6. 52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 PR144

4. 30 E-11

1. 7 6 E-11 2.18E-12 0.00E+00

1. 01 E-11 0.00E F00

4. 74 E -14 N0147 9.38E-09 1.02E-08 6.11 E-10 0.0CE+00 5.99E-09 0.00E&00 3.68E-05 W187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 NP239 1.76E-09

1. 66 E -10

9. 22 E -11 0. 00E +00

5. 21 E-10 0.00E+00 2.67E-05 i

j

1 ODCM Page: 21 Rev.:

5 Table 2.3-7 Ingestion Dose Factors for Child (mrem /pci ingested)

TOTAL ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07)

C14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00

0. 00E +00 2.28E-05 CRS1 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35I-09 9.02E-09 4.72E-07 MN54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 MN56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 FESS 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 i

FE59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05

)

C058 0.00E+00 1.80E-06

5. 51 E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 C060 0.00E+00 5.29E-06

1. 56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 NI63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 NI65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 CU64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 2N65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 i

ZN69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 i

BR83 0.00E+00 0.00E+00 1.71 E-07 0.00E+00 0.00E+00 0.00E+00

0. 00E +00 8R84

0. 00E +00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 R888 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 RB89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00

1. 02 E -09 SR89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+C0 0.00E+00 5.11E-05 SR90 1.70E-02 0.00E+00 4.31 E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 SR91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 SR92 9.03E-06 0.00E+00 3.622-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 Y90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y91M

3. 82 E-10 0.00E+00

1. 39 E-11 0. 00E+00 0.00E+00 0.00E+00 7.48E-07 Y91 6.02E-07 0.00E+00 1.61 E-08 0.00E+00 0.00E+00 0.00E +00 8.02E-05 YS2 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 Y93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 -0.00E+00 1.70E-04 2R95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 ZR97' 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 NB95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 M099 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 TC99H 9. 23 E -10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19 E-10 1.03E-06

y ODCM Page: 22 Rev.:

5 Table 2.3-7 (Cont.)

Ingestion Dose Factors for Child (mrem /pCi ingested) l TOTAL

{

ISOTOPE 80NE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 RU103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+0.0 1.89E-05 RU105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05

)

RU106 1.17E-05 0.00E+00 1.46E-06 0.00E&00 1.58E-05 0.00E+00 1.82E-04 AG110M 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05

{

TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05

)

TE127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 l

TE129M 4.87E-05 1.36E-05

7. 56 E-06 1. 57 E-05 1.43E-04 0.00E+00 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08

2. 51 E-07 0.00E+00 4.36E-07 i

TE132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 1131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 1132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 1133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 1135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 CS134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 CS136 2.35E-05 6.46 E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 8A139 4.14E-07

2. 21 E-10 1.20E-08 0.00E+00

1. 93 E-10 1.30E-10 2.39E-05 8A140 8.31E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 BA141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11

6. 58 E-10 1.14E-07 8 A142 8.74E-08 6.29E-11 4.88E-09 0.00E+00

5. 09 E-11 3.70E-ll 1.14E-09 LA140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 LA142

5. 24 E -10

1. 67 E-10

5. 23 E-11 0.00E +00 0.00E+00 0.00E+00 3.31E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-10 0.00E+00

1. 59 E-09 0.00E+00 5.55E-05 CE144 2.08E-06 6.52E-07 1.11 E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 PR144

1. 29 E -10 3.99E-11 6.49E-12 0.00E+00 2.11 E -11 0.00E+00 8.59E-08 ND147 2.79E-08 2.26E-08 1.75E-09 0.00E+00

1. 24 E -08 0.00E+00 3.58E-05 W187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 NP239 5.25E-09

3. 7 7 E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05

ODCM Page:

23 Rev.:

5 Table 2.3-8 Ingestion Dose Factors for Infant (mrem /pCi ingested)

~

TOTAL ISOTOPE BONE LIVER BODY THYR 010 KIONEY LUNG GI-LLI H3 0.00E+00 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA24 1.01E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01E-05 1.01E-05 1.01E-05 P32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 CRS1 0.00E+00 0.00E+00 1.41 E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN54 0.00E+00 1.99E-05

4. 51 E-06 0.00E+00 4.41E-06 0.00C +00 7.31E-06 HN56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.000+00 7.43E-05 FESS 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 FE59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 C058 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 C060 0.00E+00 1.08E-05 2.55E-05 0.00E+00

'O.00E+00 0.00E+00 2.57E-05 NI63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 NI65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 CU64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E +00 1.25E-05 ZN65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 ZN69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 BR83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR84 0.00E+00 0.00E&00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8R85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00. 0.00E+00 R886 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 RS88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E&00 0.00E+00 4.85E-07 RB89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 SR89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E&00 0.00E+00 5.16E-05 SR90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 SR91 5.00E-05 0.00E+00 1.81 E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 SR92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00Et00 2.07E-04 Y90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y91H 8.10E-10 0.00E+00

2. 76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y93 2.43E-08 0.00E+00

6. 62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 ZR95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 2R97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 N895 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 P,099 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 TC99M 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06

ODCM Page: 24 Rev.: 5 Table 2.3-8 (Cont.)

Ingestion Dose Factors for Infant (mrem /pCi ingested)

TOTAL ISOTOPE 80NE LIVER BODY THYROIO KIDNEY LUNG GI-LLI TC101 2.27E-09 2.86E-03 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 RU105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 RU106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 AG110M 9.96E-07 7.27E-07 4.81 E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 j

TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 TE129M 1.00E-04 3.43E-05

1. 54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 j

TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 TE131M 1.52E-05 6.12 E-06

5. 05 E-06 1. 24 E-05 4.21E-05 0.00E+00 1.03E-04 TE131 1.76E-07 6.50E-08 4.94 E-08 1. 57 E-07 4.50E-07 0.00E+00 7.11E-06 TE132 2.08E-05 1.03E-05

9. 61 E-06 1. 52 E-05 6.44E-05 0.00E+00 3.81E-05 1130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 1131 3.59E-05 4.23E-05

1. 86 E-05 1. 39 E-02 4.94E-05 0.00E+00 1.51E-06 1132 1.66E-06 3.37E-06

1. 20E-06 1. 58 E-04 3.76E-06 0.00E+00 2.73E-06 1133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E&00 1.84E-06 1135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 CS134 3.77E-04 7.03E-04 7.10E-05 0.00E+00

1. 81 E-04 7.42E-05 1.91E-06 CS136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 CS137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 CS138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 BA139 8.81E-07

5. 84 E-10 2.55E-08 0.00E+00

3. 51 E-10

3. 64 E-10 5.58E-05 BA140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 8A141 4.25E-07 2.91 E-10 1.34E-08 0.00E+00

1. 7 5 E-10

1. 7 7 E-10 5.19E-06 BA142 1.84E-07 1.53E-10 9.06E-09 0.00E+00

8. 81 E-11 9.26E-11 7.59E-07 i

LA140 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 LA142 1.10E-09 4.04E-10

9. 67 E-11 0. 00E+00 0.00E+00 0.00E+00 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 CE143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 PR143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 PR144

2. 74 E -10

1. 06 E -10

1. 38E-11 0. 00E +00

3. 84 E -11 0.00E+00 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00

3. 69 E -05 NP239 1.11E-08 9.93E-10

5. 61 E-10 0.00E +00 1.98E-09 0.00E+00 2.87E-05

ODCM Page: 25 Rev.:

5 Table 2.3-9 External Dose Factors for Standing on Contaminated Ground 2

(mrem /h per pCi/m )

Element Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 NA-24 2.50E-08

,2.90F-08 P-32 0.0 0.0 Er 51 2.20E-10 2.60E-10 Mn 54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09.

Co 58 7.00E-09 8.20E-09 Co 66 1.70E-08 2.00E-08 0.0 0.0 s

Ni-63 3.70E-09 4.30E-09 Mr-65 1.50E-09 1.70E-09 Cu-64 Zn-65 4.00E-09 4.60E-09 In-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Ab-88 3.50E-09

'4.00E-09 Ab-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9;00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91H 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11

~

7 92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 l

2r-95 5.00E-09 5.80E-09 Ir-97 5.50E-09 6.40E-09 Mb 95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99H 9.60E-10 1.10E-09 Tc-101 ~

2.70E-09 3.00E-09 Rv-103 3.60E-09 4.20E-09 Au-105 4.50E-09 5-5.10E Ru-106 1.50E-09 1.80E-09 l

Ag 110N 1.80E-08 2.10E-08 l

Te-125M 3.50E-11 4.80E-11 Te-127H 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129H 7.70E-10 9.00E-10

~

Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06

. Te-132 1.70E-09 2.00E-09

\\

l i

3 ODCM Page: 26 Rev.: 5 Table 2.3-9 (Cont.)

External Dose Factors for Standing on Contaminated Ground 2

(mrem /h per pCi/m )

tienent Total 806 Wa 1-130 1.40E-08 1.700-08 I-131 2.80E-09 3.4M4 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 i

I-134 1.60E-08 1.90E-08 I-135 1.20E-08

1. W -08 Cs-134 1.2x-08 1.40 W Cs-136 1.50E-08

1. M 4 Cs-137 4.20E-09 4.90E-09, Cs-138 2.10E-08 2.W-M 2.40E-09 2.70E-09

.139 40 2.ix.09

2. =-a Ba-141 4.30E Og 4.90E-09 8a-142 7.90E-09 9.00E-09 4

La 140 1.50E-08 1.70E-08 La 142 1.50E-08 1.80E-08 5.50E-10 6.20E-10

.in 4

2. 2x.m

2. 5*+

Ce-144 3.20E-10 3.M-10

[0 Pr-143 00E 10

.W-10 d

7 1.00E-09 1.20E-M W187

3. W -09 3.M-M Mp-239 9.50E-10

1. M-M

[

d

.~

4

ODCM Page:

27 Rev.:

5 Table 2.3-10 Liquid Effluent Dilution Factors (M )

p Maximum Individual Dilution Factors Pathway Location E

Potable Water Ingestion 3.9 mile WSW of site 32.2 Fresh Water. Fish Ingestion Near Discharge Structure 10.9 Shoreline Exposure 0.7 mile ENE of Site 14.5 Population Dose Dilution Factors p

Pathway Location Potable Water Ingestion Population Weighted Average 314 Fresh Water Fish' Ingestion Catch Weighted Average 77.4 Shoreline Exposure 7.7 mile WSW of site 162 i

Table 2.3-11 Transit Times Required for Nuclides to Reach the PointofExposure(ty Maximum Exposed Average Exposed Individual Individual

• Eventual transit time for water ingestion 12 h 24 h Eventual transit time for fish ingestion 24 h 168 h Eventual transit time for shore exposure 0h 0h

.)

• for total population and average individual dose calculations

)

i i

E I

ODCM

{

Page: 28 l

Rev.: 5 Table 2.3-12 Usage Factors (U l

Maximum Exposed Average Exposed i

Individual Individual

• i l

I l

Water ingestion (1/yr) Adult 730 370 Water ingestion (1/yr) Teen 510 260 Water ingestion (1/yr) Child 510 260

~

Water ingestion (1/yr) Infant 330 I

f Fresh water fish ingestion (kg/yr) Adult 21 6.9 Fresh water fish ingestion (kg/yr) Teen 16 5.2 i

Fresh water fish ingestion (kg/yr) Child 6.9 2.2 Fresh water fish ingestion (kg/yr) Infant Shore exposure (h/yr) Adult 12 8:3 Shore exposure (h/yr) Teen 67 47 Shore exposure (h/yr) Child 14 9.5 Shore exposure (h/yr) Infant

• for total population and average individual dose calculations i

I i

l 1

~

i

ODCM Page: 29 Rev.: 5 Table 2.3-13 Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP The total population dilution factor of 314 is population weighted using dilution factors for each of the potable water intakes within 50 miles of PNPP.

Weighted Dist.

Fraction Dilution Dil.

Intake (Mi)

Dir Population of Pop Factor Factor' Ohio American 20 ENE 38,500 2.12E-2 187.7 3.98E+0 Water Serv. Co.

Conneaut 33 ENE 13,500 7.43E-3 238.2' 1.77E+0 '

Avon Lake 50 WSW 99,500 5.48E-2 388.5 2.13E+1 Cleveland 35 SW 1,437,000 7.92E-1 326.7 2.59E+2 i

Fairport Harbor 7

WSW 3,200 1.76E-3 154.2 2.71E-1 Lake County East 3.5 WSW 10,258 5.65E-3 107.4 6.07E-1 Lake County West 15 WSW 85,000 4.68E-2 220.0 1.03E+1 1

Ohio Water Serv.

10 WSW 60,000 3.30E-2 181.9 6.00E+0 Painesville 7.5 WSW 27,000 1.49E-2 159.3 2.37E+0 i

Kent County 50 NW 42,000 2.31E-2 388.5 8.97E+0 j

Water Supply l

TOTALS 1,815,958 1.00E+0 TOTAL D.F 3.14E+2 Dist, Dir Population = distance, direction, and population values obtained from

{

the 1989 Engineering Report " Lake Erie Potable Water Facilities and Intakes I

within 50 Miles of PNPP' (Ref. S0-11552 *E').

Fraction of Population = The ratio of the population receiving drinking water from that intake to the total population number for all drinking water intakes located within 50 miles of PNPP.

Dilution Factor = Values obtained from the Perry Environmental Report -

Operating License Stage, Table 5.1-10 " Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP' and Q&R Page 2.1-2.

Lake County West dilution factor per interpolation. Kent County Water Supply dilution factor i

was estimated.

i The Weighted Dilution Factor = (Fraction of Population) x (Dilution Factor),

based on the population for each drinking water intake; the sum of which is to be used as the potable water total population dilution factor for radioactive i

liquid effluent releases from PNPP.

L 1

ODCM Page: 30 Rev.:

5 Table 2.3-14 l

Dilution Factors for the Fish Ingestion Pathway Individual l

Grid Locations The total population dilution factor of 77.4 is catch distance and volume weighted using dilution factors at those locations. Fish harvest is l

based on Ohio Department of Natural Resources the total angler catch (1987 annual) values for Lake Erie within 50 mile of PNPP.

l No. of Fraction Dist.

Dilution (FracFish)x Grid Fish of Fish (mi)

Factor (Di1 Factor) ~

j 617 52823 3.91E-2 29 92 3.60E+0 i

I 618 76004 5.63E-2 36 100 5.63E+0 714 102522 7.59E-2 9

52 3.96E+0 715 10743 7.95E-3 9

52 4.13E-1 716 19817 1.47E-2 11 56 8.21E-1 717 73401 5.43E-2 24 83 4.51E+0 718 118676 8.78E-2 33 95 8.34E+0 809 0

0.00E+0 48 115 0.00E+0 810 3953 2.93E-3 39 105 3.07E-1 811 13648 1.01E-2 30 92 9.29E-1 812 33923 2.51E-2 22 78 1.96E+0 813 182663 1.35E-1 13 61 8.25E+0 814 164369 1.22E-1 4

34 4.14E+0 909 8075-5.98E-2 50 116 6.93E+0 l

910 43800 3.24E-2 42 110 3.57E+0 1

911 117430 4.69E-2 33 95 8.26E+0 912 256529 1.90E-1 24 83 1.58E+1 TOTAL 1351054 1.00E+0 TOTAL D.F.

7.74E+1 Grid No. and No. of Fish = Total angler catch (1987 annual) for each grid i

l location; per letter from Michael R. Rawson, Fairport Fisheries Research l

Station, Ohio Department of Natural Resources to Richard Cochnar (6/20/88). Commercial harvest data were not used as they were differentiated by harbor location only, not by geographical grid l

location.

Fraction of Fish = The ratio of the fish caught in that grid to the total number of fish caught in all grids located within 50 miles of PNPP.

Distance = Distance to the center of that grid from PNPP, in miles.

Dilution Factor = Derived, for the appropriate distance (center of each grid), from annual average dilution factor data (non-adjusted), per Perry Environmental Report - Operating License Stage, Table 5.1-10 " Annual.

Average Diltition Factors for Lake Water Intakes within 50 Miles of PNPP."

i (Fraction of Fish) x (Dilution Factor) = The weighted dilution factor, based on catch, for each grid; the sum of which is to be used as the fish ingestion total population dilution factor for radioactive liquid j

effluent releases from PNPP.

]

i

1 I

i ODCM Page: 31 i

Rev.:

5 l

Table 2.3-15 4

Dilution Factors for the Shore Exposure Pathway i

l MAXIMUM EXPOSED INDIVIDUAL DILUTION FACTOR The point of exposure assumed for this pathway is the shoreline at the PNPP site boundary 0.7 miles down shore from the plant discharge structure.

Interpolation of the data presented in the Perry Environmental Report - Operating License Stage, Table 5.1-10, " Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP' yields a maximum individual dose dilution factor of 14.5 (dilution factor unadjusted for current frequency).

TOTAL POPULATION DILUTION FACTOR The total population dilution factor of 162 is that of the Headlands Beach State Park, 7.7 miles WSW of PNPP (interpolated, adjusted WSW l

dilution factor). This location was selected because of its lake site I

location and it has, by far, the highest attendance of any park located in vicinity of PNPP (Perry Environmental Report - Operating License State, Table 2.1-2

• Major Camps and Parks within 10 Miles of the PNPP').

i

ODCM Page: 32 Rev.:

5 3.0 GASEOUS EFFLUENTS There are four environmental release points for gaseous effluents used for Unit 1 operation of the Perry Nuclear Power Plant:

Vents (see Figure 3.0-1). Bay / Turbine Building Vent, Offgas Vent Heater i

on the top of the Intermediate Building, Elevation 753'9".The U 1

Heater Bay / Turbine Building Vent is located on the top of the Heater The Bay Building, Elevation 722'0".

the top of the Offgas Building, Elevation 723'0".The Offgas Vent Pipe is i

Site ground level elevation is 620'0'.

monitored by a noble gas radiation monitor. Radiological releases fr All gaseous effluent releases from PNPP will be continuous releases Containment /drywell purges and vents will be considered periods of i

increased radiological release as they are vented through the Unit 1 Vent concurrent with normal, continuous releases.

All releases ar considered to be long-term, i.e., greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year,e and ground level.

i I

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Figure 3.0-1 ODCM I P yl f Page: 33 ao.co cno Gaseous Effluent System Flow Diagram orvcis vo<r erec us.ooo cno Rev..

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ODCM Page: 34 Rev.:

5 3.1 Monitor Alarm Setpoint Determination i

The following calculation methods provide a means of determining the high alarm setpoint (HSP) and the alert setpoint (ASP) to ensure compliance with 10CFR20 dose rate limits to areas at or beyond the site boundary for the following noble gas monitors:

1 1.

Heater Bay / Turbine Building Vent radiation monitor (1D17K0856) 2.

Offgas Vent Pipe radiation monitor (1D17K0836) 3, Unit 1 Vent radiation monitor (1D17K0786)

~

4.

Unit 2 Vent radiation monitor (2D17K0786).

The Unit 2 Vent Radiation Monitor is included for the operation of Unit 1 of the Perry Nuclear Power Plant because the second train of the Unit 1 Annulus Exhaust and the Control Complex and Intermediate i

Building ventilations are exhausted through the Unit 2 Vent.

The High Alarm Setpoint (HSP) for each release point radiation monitor will be set at 70 percent of the 10CFR20 dose rate limits and the Alert Setpoint (ASP) will be set at 10 percent of these limits.

This procedure determines the monitor alarm setpoints that indicate if the dose rate beyond the site boundary due to noble gas radio-nuclides in gaseous effluent released from the site exceeds 500 mrem / year to the total body or 3000 mrem / year to the skin.

NOTE:

The values of 70 percent for the HSP and 10 percent for the ASP are set as fractions of the total activity that may be released via the monitored pathways to ensure that the site boundary dose rate limits are not exceeded. Any single ASP can be exceeded without the 10CFR20 limits being exceeded. Upon receipt of an alert alarm a sample from the alarming effluent path will be obtained and analyzed.

If two or more monitors exceed the ASP, or any one monitor exceeds the HSP, it is possible that the limits have been exceeded. In this case all four effluent paths will be sampled and analyzed. Appropriate action will be taken to limit gaseous releases to below 10CFR20 limits.

NOTE:

If an HSP or two or more ASP's continue to be exceeded, verification shall be made at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> via the gaseous effluent radiation monitors that plant releases are below ODCM Appendix C 3.11.2.1 dose rate.

limits, and sampling and analysis shall be performed on the four gaseous effluent release points at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l D

oDcM Page: 35 l

Rev.: 5 3.1.1 Determination of the ' Mix' (Noble Gas Radionuclide Composition) l of the Gaseous Effluent a.

The gaseous source terms that are representative of the l

' mix" of the gaseous effluent are determined. Gaseous source terms are the concentrations of the noble gas radionuclides in the effluent as determined by analysis of the various sources of gaseous effluents. During the early period of plant operation, before a sufficient operational effluent source term data base has been obtained, source terms will be those generated by the GALE code, Revisicn 0 for PNPP (FSAR Tables 11.3-9 and 11.3-10).

b.

Determination of the fraction of the total radioactivity in the gaseous effluent for each noble gas radionuclide in the gaseous effluent.

A S =

i (3.1-1) fAi 1

Where:

S*. = the fraction of the total for radionuclide 'i' in the effluent; Ai = the activity of radionuclide 'i' in the gaseous effluent.

l NOTE:

If the activity of a noble gas radionuclide is below the lower limit of detection the noble gas radionuclide is not included as a source term in this setpoint calculation.

3.1.2 Determination of the Maximum Acceptable Total' Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Total Body Dose Rate Limit 500 (3.1-2)

Ob = (z/0) y (K )(S )

g i

1 Where:

b the maximum acceptable total activity release rate O

=

of all noble gas radionuclides in the effluent (for total body exposure), in pCi/s; ti> total body dose factor for a semi-infinite cloud K.

e 1

.ragionuclide"i'(includestheattenuationof 5g/cm oftissuejfromTable3.1-1,in (mrem /yr)/(pCi/m );

1 ODCM Page: 36 j

Rev.:

5

\\

S.

= the fraction of the total for radionuclide *i", as 1

per equation 3.1.1; g/Q = the highest annual average relative dispersion-i facgorfgrareasatthesiteboundary=5.8x 10~ s/m (from Appendix A, NE direction at the site boundary);

NOTE:

The dispersion parameters (z/Q) used in these calculations are the highest calculated site boundary values for any of the land-based 4

i sectors only. At PNPP the site boundary

]

locations in the following sectors are totally 1

l over water:

N, NNE, NNW, NW, W, WNW.

l 500 = the total body dose rate limit, in mrein/yr.

j l

3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Nob?e Gas Radionuclides in Gaseous Effluent Based on Skin Dose Rate Limit 1

3000 (3.1-3 )

i O

• II/OI Z Ibi + 1.11 M;) (S )

s g

1 1

1

\\

Where:

Q

= the maximum acceptable total activity release rate i

s of all noble gas radionuclides in the effluent (for skin exposure), in pCi/s; 1

.L.

= the beta skin dose factor for a semi-infinite cloud 1

of radionuclide "i" (includes attenuation by the 3

outer ' dead' layer of skin), in (mrem /yr)/(pci/m ),

j i

i M

= the gama air dose factor for a uniform g

i semi-infinitecigudofradionuclide'i',in (mrad /yr)/(pCi/m );

S.

= the fraction of the total for radionuclide 'i', per 1

equation 3.1.1;

=thehighestannualaverggerelativedispersion g/Q factor = 5.8 x 10-6 s/m, per equation 3.1-2 i

l 1.11 = the air dose to tissue dose equivalent conversion factor, in mrem / mrad; 3000 = the skin dose rate limit, in mrem /yr, i

g + 1.11 M ) values are shown in Table 3.1-1.

)

(L g

s

\\

\\*

i

m ODCM Page: 37 Rev.: 5 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent (2.12 x 10-3)I0 I t

Ct*

I *1~0I f

Where:

Ct = the maximum acceptable total radioactivity concentration of cll noble gas radionuclides in the _

effluent, in'pCi/cc; f

=theflowrateforthereleasepointfgomthe respective flow rate recorders, in ft / min; NOTE:

Design flow rate may be used in lieu of actual flow rate. These design flow rate values incorporate a 10% flow rate inaccuracy correction.

Release Path Flow Rate (cfm)

- Heater Bay / Turbine Building Vent 400,000 (summer) 220,000 (winter)

- Offgas Vent Pipe 19,000

- Unit i Vent 140,000

- Unit 2 Vent 47,000 t = the smaller of Q Q

and 0, calculated in equations 3.1-2 and3.1-3,respehtively in pCi/s; s

-3 2.12 x 10

= thg/ min) to pCi/cc. conversion factor to convert (pCi/s) ft 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides CR = (0.8) (C )

c t

(E )

(3.1-5)

Where:

CR = the calculated monitor count rate above background c

attributed to noble gas radionuclides, in cpm;

ODCM Page: 38 Rev.: 5 C

= the maximum acceptable radioactivity concentration, t

per equation 3.1-4, in pCi/cc; E"

= the detector efficiency of the monitor for the ' mix" of noble gas radionuclides in the effluent, in cpm /(pCi/cc);

= the total pCi/cc concentration divided into the net monitor count rate taken at the time the sample was taken; during the early period of operation,'before a sufficient operational effluent source term data base has been obtained, the value will be calculated using monitor calibration data; 0.8 = an engineering safety factor.

3.1.5.1 Determination of the Monitor High Alarm Setpoint HSP = (0.70)(CR ) + BG (3.1-6) c Where:

HSP = the high alarm setpoint (including background), in cpm; BG

= the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in cpm; CR

= the calculated monitor net count rate, per c

equation 3.1-5, in cpm; 0.70 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.

3.1.5.2 Determination of the Monitor Alert Setpoint ASP = (0.10)(CR

(*

C Where:

ASP = the alert setpoint (including background), in -

cpm; BG

= the background count rate due to internal.

contamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in cpm;

4 l

ODCM Page: 39 Rev.: 5 CR

= the calculated monitor net count rate, per c

equation 3.1-5, in epm; 0.10 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.

h i

l 2

.=

I

1 ODCM Page: 40

)

Rev.: 5 Table 3.1-1 Total Body and Skin Dose Factors Total Body Total Skin Dose Factor (L 1.11 M Dose Factor (mrek+/yr/pCifm) )

Radionuclide (K )(mrem /yr/pCi/m )

g Kr-83m 7.56E-02 2.14E+01 l

Kr-85m 1.17E+03 2.82E+03 Kr-85 1.61E+01 1.36E+03 Kr-87 5.92E+03 1.66E+04 Kr-88 1.47E+04 1.92E+04 Kr-89 1.66E+04 2.93E+04 Xe-131m 9.15E+01 6.49E+02

~

Xe-133m 2.51E+02 1.36E+03 Xe-133 2.94E+02 6.97E+02 Xe-135m 3.12E+03 4.44E+03 Xe-135 1.81E+03 3.99E+03 Xe-137 1.42E+03 1.39E+04 Xe-138 8.83E+03 1.44E+04 Ar-41 8.84E+03 1.30E+04 1

i l

ODCM Page: 41 Rev.: 5 3.2 Compliance With 10CFR20 - Gaseous Effluent Dose Rate Dose rates resulting from the release of noble gases, radioiodines, tritium, and radionuclides in particulate form must be calculated to show compliance with 10CFR20. The limits of 10CFR20 are conservatively applied for the release period at the controlling location.

3.2.1 Noble Gases The dose rate in unrestricted areas resulting from noble gas ~

effluents is limited, by ODCM Appendix C controls, to 500 mrem /yr to the total body and 3000 mrem /yr to the skin.

only the external dose pathway will be considered for noble gases. Because all gaseous effluent releases from PNPP are i

considered ground level, the controlling location ~for these i

dose rate limits is the site boundary location (see Figure 3.2-1) with the highest relative dispersion factor (x/Q).

(See Appendix A for elaboration on atmospheric i

dispersion.)

The alarm setpoint determinations discussed in the previous section should ensure compliance with these dose rate limits.

However, if any one high alarm or two or more alert alarms

(

occur, the dose rates in unrestricted areas resulting from the release of noble gas radionuclides from all vents will be calculated. The calculations will be based on the results of analyses obtained pursuant to the ODCM Appendix C controls.

i 3.2.2 Radionuclides, Particulates, and Other Radionuclides l

The dose rate in unrestricted areas resulting from the release of iodine-131, iodine-133, tritium, and all radionuclides in l

particulate form with half-lives greater than eight days is l

limited, by ODCM Appendix C controls, to 1500 mrem /yr to any I

organ. The calculation of dose rate from these radionuclides will be performed based on results of analyses obtained pursuant to those Appendix C controls. The controlling location for this limit is the location of the highest relative deposition (D/0) for the period of release as well as the actual receptor pathway. The receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of nearest residences, garden, and farm aninal locations in each sector.

i f

i

ODCM Page: 42 Rev.:

5 3.2.3 Dose Rate Calculations The following is the equation used to calculate the dose rate resultant from the release of radioactive materials in gaseous effluents to areas at or beyond the site boundary for the purpose of showing compliance with ODCM Appendix C controls as related to 10CFR20.

1 D,$p = (3.15 x 10 ) (x/Q or D/Q) I (DF,gjp) (Q )

{3.2-1) g Where:

= the organ "j" dose rate as a function of age D ).ap group *a" and pathwayp*, in mrem /yr; DF.. = the dose factor for organ type 'j', age group a13p

'a', pathway "p" for isotope 'i' (see Tables 3.2-1 through 3.2-3); units and equations used (equations 3.2-2 through 3.2-6) are provided later in this section; I/0orD/Q=thenormalordepletgdrelativedispersion factor (x/Q)2 in s/m,

r relative deposition (D/Q), in m', at the receptor distance (see Appendix A);

1 3.15 x 10 = the conversion factor to convert (mrem

• pCi)/(Ci

• s) to mrem /yr; Q. = the release rate of isotope 'i', (annualized) in 1

pCi/s

= (472)(C )(f) g Where:

C

= the concentration of radionuclide 'i' in i

the gaseous effluent, in pCi/cc; f

=thegaseouseffluentflowrateduringthe release, in ft / min; 3

472 = the conversion factor (cc/ft )fg,f,gn),

The following relationships are used to derive the dose factors -

(DF.. ) for noble gases, tritium, radioiodines and parENPilates used in equation 3.2-1.

ODCM Page:

43 Rev.: 5 a.

Total Body Dose Factors from Exposure to a Semi-Infinite Plume T

DFg = (S ) (x() (DFB )

(3.2-2) p i

Where:

T DF.

= the total body factor due to immersion'in a 1

semi-infigitecloudofradionuclide'i",in,

(mrem

• m )/(Ci

• s);

DFB. = the total body gamma dose factor for a 1

semi-infinitecloudofradionuclige'i'which includes the attenuation of Sg/cm ofgissue from Table 3.2-4, in mrem /yr per pCi/m ;

S

= the attenuation factor that accounts for the F

dose reduction due to the shielding provided by residential structures, optional, dimensionless:.. maximum exposed individual =

0.7, population dose 0.5 (Regulatory Guide 1.109);

=theannualaverageconcentratignof x.1 radionuclide'i'inair(pCi/m),foragnit releasg) rate (Ci/yr)3)ndaunitx/Q(s/m),in a

(pci/m /(Ci/yr) (s/m b.

Skin Dose Factors for Exposure to a Seni-Infinite Plume S

y (DFS ) ] g = (x g)

DF

[(1.11) (S ) (DF (3.2-3)g) +

p g

Where:

S i

DF.

= the skin dose factor due to immersion in a l

semi-infigitecloudofradionuclide'i',in (mrem

• m )/(Ci

• s);

7 DF.

= the gamma air dose factor for a uniform 1

semi-infinitecloudofradionuclige'i',from

~

Table 3.2-4, in mrad /yr per pCi/m ;

DFS. = the beta skin dose factor for a semi-infinite 1

cloud of radionuclide 'i' (includes I

attenuation by the outer " dead' layer of 3

skin), from Table 3.2-4 in mrem /yr per pCi/m,

ODCM j

Page: 44 Rev.: 5 S

= the attenuation factor that accounts for the F

dose reduction due to the shielding provided by residential structures, optional, dimensionless:

maximum exposed individual = 0.7, population dose = 0.5 (Regulatory Guide 1.109);

I

=theannualaverageconcentratignof l

x.1 radionuclide 'i' in air (pCi/m )',foragnit releasg) rate (Ci/yr)3)ndaunitx/Q(s/m),in a

(pCi/m /(Ci/yr) (s/m 1

1.11 =.the air dose to tissue dose equivalent conversion factor, in mrem / mrad.

c.

Dose Factors from External Irradiation from Radionuclides Deposited onto the Ground Surface i

G G

l DFig = (8760) (C ) (DFGgg) (S )

(3.2-4) g p

Where:

i G

DF..

= the dose factor for radionuclide 'i' to organ

'l 13 "j" resulting from exposure to radionuclides I

deposited onto the ground surface, in I

2 l

(mrem

• m )/Ci; G

2 i

C.

= the ground plane concentration (pCi/m ) of 1

radionuclide 'i' for a unit release rate (Ci/yr) and a itD/Q,relgtiveground deposition (m~p), in (pci/m )/(Ci/yr)(m-2),

DFG.. = the open field ground plane dose conversion 13 factor for organ 'j" from radionuclide

'I

2 from Table 3.2-5, in mrem /yr per pCi/m ;

S

= the attenuation factor that accounts for the F

dose reduction due to the shielding provided by residential structures, optional, dimensionless: maximum exposed individual =

~

l 0.7, population dose = 0.5 (Regulatory Guide 1.109),

3 1

8760 = the number of hours in a year.

I d.

Dose Factors from Inhalation of Radionuclides in Air A

DF,gg = (DFAaij) (R I (I )

(3.2-5) a i

r i

ODCM Page: 45 Rev.:

5 Where:

A l

DF"13

= the dose factor for radionuclide 'i' to organ"j'ofanindividualinagegroup'"a" due to inhalation, in (mrem

• m )/(Ci

• s) 3

[ -- equivalent to (mrem /yr)(yr/Ci)(m /s)];

DFA"l3 = the inhalation dose factor for radionuclide

• i', organ "j', and age group 'a' (tihe value for skin is assumed to be 0), from.

Tables 3.2-6 through 3.2-9, in mrem /pci; R"

=theannualairintakeforindividualsjn age group

'a', from Table 3.2-14, in a /yr;

=theannualaverageconcentratignof z.1 radionuclide 'i' in air (pci/m ), for a unitrelgaserate(Cifyr)andaunig l

z/Q (s/m ), in (pCi/m )/(Ci/yr)(s/m ).

I Dose Factors from the Ingestion of Atmospherically e.

Released Radionuclides in Food D

F F

L L

M M

DFaij = DFIaij I( a} (i +I a'( L} I i}

• I a)(C ) +

g V

V (U }II )(C )]

(3.2-6) a V

g l

Where:

D DF"13,. = the dose factor for radionuclide 'i' to organ

'j' of an individual in age group 'a' from the ingestion of meat, leafy vegetables, l

milk, and produce (non-leafy veggtables, fruits, and grains) in (mrem

• m )/Ci, or in the cases of H-3 and C-14 in 3

(mrem

• m )/(Ci

• s);

i I

F L

M V

l C, C, C, C. = the concentrations of radionuclide g

g g

l

'i' in meat, leafy vegetables, milk, and produce, respectively (pCi/kg or,_ -

pCi/1) for a unit release rate (Ci/yr) and a unit D/, relative grounddeposition(mg),orincases i

of H-3 and C-14, a unit z/0, relagiveground-levelconcent3ation (s/m ), in (pci/kg)(gi/yr)(m- ) or (pCi/kg)/(Ci/yr)(s m ) or (pCi/1)/(Ci/yr)(m- ) or (pCi/1)(yr/Ci)(s/m /);

ODCM Page:

46 Rev.:

5

)

DFI"U.. = the ingestion dose factor for radionuclide

• ia, organ aj", and age group

'a', from Tables 3.2-10 through 3.2-13, in mrem /pCi; f,fy = the respective fractions of the ingestion g

rates of afy vegetables and produce that i

are produced in the garden of -interest,1.0 and 0.76 respectively (Regulatory Guide 1.109);

l F

L M

V i

U,, U,, U,, U, = the annual intake (usage) of meat, i

leafy vegetables, milk, and produce respectively,_for individuals in age group 'a',.from Table 3.2-14, in kg/yr or 1/yr.

f.

Dose rate example problem:

1)

For the purpose of this sample problem, the following assumptions are utilized: a release of Xe133 at 3

1.0E-SuCi/cc, a flow rate of 1.0E5ft / min, and a total body dose factor of 2.94E-4 mrem /yr per pCi/m.

A dose rate and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cumulative dose are calculated.

2)

Total Body Dose Factor Dose factor per ODCM equation 3.2-2, 2.94E-4 mrem x (.7) x 1.0E-12 pCi 6.52 mrem m2

=

yr iP _

Ci sec pCi Ci 3.15E7sec m3 yr m2 3)

Dose Rate per ODCM equation 3.2-1.

i 3.15El x 5.8E-6s x 6.52 mrem m2 x 472cc min x -->

j m2 Ci sec ft2 sec 1.0E-5uci x 1E5ft2 0.562 mrem

=

cc min yr 0.562 mrem x (1hr) x lyr 6.42E-5 mrem

=

yr 8760hr

i ODCM Page:

47 Rev.: 5 l

Table 3.2-1

^

l i

Organ Used for Gaseous Effluent Dose Calculations l

l l

1.

Bone 2.

GI Tract 3.

Kidney l

4.

Liver 5.'

Lung 6.

Thyroid 7.

Total Body

(

8.

Skin i

l Table 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations 1.

Adult (17 yr and older) 1 2.

Teen (11-17 yr) 3.

Child (1-11 yr)

.4.

Infant (0-1 yr) 1 I

l odes l

Page: 48 l

Rev.: 5 Table 3.2-3 Gaseous Effluent Dose Pathways 1.

Plume 2.

Ground Shine 3.

Vegetables

(

4.

Heat l

~

5.

Cow Milk 6.

Goat Milk l-7.

Inhalation l

l Table'3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases

-Total Body Beta Skin Gamma Air **

l Nuclide Gamma Dose Dose Factor Dose Factor

~

Factor (DFB l (DFS L

. y g

g (DF )

g Kr-83m 7.56E-08 1.93E-05 Kr-85m 1.17E-03 1.46E-03 1.23E-03 Kr-85 1.61E-05 1.34E-03 1.72E-05 Kr-87 5.92E-03 9.73E-03 6.17E-03 i

~

i Kr-88 1.47E-02 2.37E-03 1.52E-02 l

Kr-89 1.66E-02 1.01E-02 1.73E-02 Kr-90 1.56E-02 7.29E-03 1.63E-02 Xe-131m 9.15E-05 4.76E-04 1.56E-04 Xe-133m 2.51E-04 9.94E-04 3.27E-04 Xe-133 2.94E-04 3.06E-04 3.53E-04 Xe-135m 3.12E-03 7.11E-04 3.36E-03 Xe-135 1.81E-03 1.86E-03 1.92E-03 Xe-137 1.42E-03 1.22E-02 1.51E-03 i

Xe-138 8.83E-03 4.13E-03 9.21E-03 Ar-41 8.84E-03 2.69E-03 9.30E-03 3

mrem /yr per pCi/m mrad /yr per pCi/m 1

r r

r 1

ODCM Page:

49 i

Rev.: 5 Table 3.2-5 External Dose Factors for Standing on Contaminated Ground 2

(mrem /h per pCi/m )

M Total toe

$Hn -

n-3 0.0 G.0 C-14 O.0 0.0 mA-24 2.90E-08 2.90E-08 p.32 0.0 0.0 l

Cr-51 2.20E-10 2.50E-10 i

Mn 54 5.00E-09 6.80E-09 Mn-56 1.1M-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 7.00E-09 8.20E-09 Cp.58

(

Co-8D

1. M -08 2.00E-08 n3-63 0.0 0.0 l

Nr-65 3.70E-09 4.30E-09 Co-6g 1.5M-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 l

2n-69 0.0 0.0 l

Br-83 6.40E-11 9.30E-11 i

tr-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Ab-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E 13 6.50E-13 Sr-91 7.1M-09 2.30E-09 I

sr-92 9.00E-09 1.00E-08 I

Y-90 2.20E-12 2.60E,12 l

Y-91M 3.00E-09 4.40E-09

~

T-91 2.40E-11 2.70E-11 T-92 1.60E-09 1.90E-09 T-93 5.?M-10 7.00E-10 Zr-95

.5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99N 9.60E-10 1.10E-09 Tc.101 2.70E-09 3.00E-09 Re-10:1 3.60E-09 4.20E-09 Re-101 4.50E-09 5.10E-05 Re-105 1.50E-09 1.80E-09 A9-110N 1.8M-08 2.1K-08 Te-125M 3.50E-11 4.00E 11 Te-12 m 1.10E-12 1.30E-12 Te-121 1.00E-11 1.10E-11 Te-17.H 7.70E-10 9.00E-10

~

Te-ug 7.1M-10 8.40E-10 Ye-131M 8.4M-09 9.90E-09 Te-131 2.20E-09 2.60E-06 l

Te-132 1.70E-09 2.00E-09 i

4

l ODCM Page:

50 Rev.:

5 Table 3.2-5 (Cont.)

External Dose Factors for Standing on Contaminated Ground 2

(mrem /h per pCi/m )

Element Total Body

$ttn 3-130 1.40E-08 1.70E-08 I-131 2.80E W 3.40E-09 l

I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 l

I-134 1.60E-08 1.90E-08 l

I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 i

l Cs 136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 l

Cs-138 2.10E-08 2.40E-08 Sa-139 2.40E-09 2.70E-09 Sa-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Sa-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-06 Ce-141 5.50E 10 6.20E-10 Ce-143 2.20E-09' 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 J.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 NP-239 9.50E-10 1.10E-09 t

l l

i l

l

l ODCM Page:

51 Rev.:

5 i

Table 3.2-6 Inhalation Dose Factors for Adult (mrem /pCi inhaled)

\\

NUCL10E SONE LIvf A T.ADDY THYROID KtDNEY

- LtM88 GI-LL1 N

3 NO DATA 1.58E-07 1.58F-0 7 1.58E-C7 1 58E-07 1.58E-07 1 58'E-07 C 14 2 27E-06 4.26E-07 4.26E-0 7. 4.26E-07 4 26E-07 4.26E-07 4.2 6E-07 l

14 24 1 28E-06 1.28E-06 1.28 E-06 1 28E-06 1 28E-06 1 28E-06 1 28E-06 P 32 1 65E-04 9.64E-06 6'.26 E-0 6 NO DATA ' NO DATA NO DATA 1.00E-05 CR 51 NO DATA NO DATA 1.25E-08 7.44E-09 2 85E-09.1 80E-06.4.15E-07 BN 54 NO DATA 4.95E-06 T.8 FE-O F NO DATA 1.231-06 1.75E-04 9.67E-06 l

MN 56 NO DATA 1.55E-10 2.29E-11 NO OATA 1.63E-10 1.18E-04 2.53E-06 FE 55 3 0TE-06 2.12t-06 4.91E-0 7 NO DATA NO DATA 9.01E-06 7.54E-07 l

FE 59 1 4TE-06 3.47E-06 1 32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 NO DATA 1.98E-07 2.5 9E-07 NO DATA NC OATA 1.16E-04 1.33E-05.

CD 60 ND DATA 1.44E-06

.1. 85E-0 6 NO DATA NO DATA 7.46E-04 1.56E-05 N1 63 5.40E-05 3.93E-06 1 81E-06 NO DATA NO DATA 2.23E-05 1.67E-06 N165

'1.92E-10 2.62E-11 1 14E-11 NO DATA NO DATA 7.00E-07 1.545-06 CU 64 NO DATA 1.83E-10 7.69E-11 NO DATA 5 78E-10 8.48E-07 6.12E-06 2N 65 4.05E-06 1.29E-05

5. 82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 2N 69 4.23E-12 8.14E-12 5.65E-13 NO DATA 5.27E-12 1.15E-07 2.04E-09 SA 83 NO DATA NO DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08 SR 44 NO DATA NO DATA 3.91E-0 8 NO DATA NO DATA NO DATA 2.05E-13 SR 85 NO DATA MO DATA

1. 60E-09 Nd DATA NO DATA NO DATA LT E i 48 86 NO DATA 1 69E-05

7. 37E-06 NO DATA NO DATA NO DATA 2.08E-06 RO 88 NO DATA 4.84E-08 2.41E-08 NO DATA NO DATA NO DATA 4.18E-19 RS 89 ~ NO DATA 3.20E-04 2.12E-08 NO DATA NO DATA NO DATA 1.16E-21 5A 89 3.80E-05 NO DATA.

1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1 20E-03 9 02E-05 5 A.91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO DATA S.64E-11 NO DATA NO DATA 2.06E-04 5.38E-06 Y 90 2.61E-07 NO DATA 7.01E-09 NO DATA NO DATA 2.128-05 6.32E-05 7

Y 91M 3.26E-11 NO DATA 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.785-05 NO DATA 1 55E-06 40 DATA NO DATA 2.13E-04 4.81E-05 Y 92 1 29E-09 MO DATA 3 77E-11 NO DATA NO DATA 1 96E-06 _9.19E-06 Y 93 1 18E-0B NO DATA 3.26E-10 NO DATA

'NO DATA 6.06E-06. 5 27E-05 ZR 95 1 34E-05 4 3CE-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1 88E-05 1R 97 1.21E-08 2.45E-09 1 13E-09 NO E!ATA 3 71E-09 9.84E-06 6.54E-05 MS 95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1 30E-05 MO 99 NO DATA 1.51E-08

2. 87E-09 NO DATA 3.64E-08 1.14E-05 3.10E-05, TC 99M 1.29E-13 3.64E-13 4.63E-12 NO DATA 5 52E-12 9.55E-08 5.20E-07 I

i

I ODCM Page:

52 Rev.:

5 Table 3.2-6 (Cont.)

Inhalation Dose Factors for Adult (mrem /pCi inhaled)

NUCL1DE SONE.

LIVER T.8007 THVA0!O KIONEY

'tv4G G1-LLI FC101 5.22E-15 7.52E-15 7.3st-14 NO DATA-1.35E-13 4.99E-08 f.36E-21

.AU103 1.91E-07 NO DATA 4.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05 RU105

,9.88E-11 NO Data 3 89E-11 NO DATA 1.77E-10 1 3?E-06 6.02E-06 RU106 8.64E-06 NO DATA 1.01E-0 6 NO DATA 1 67E-05 1.17E-03 1.14E-04 AC110p 1.35E-06 1.25E-06 ' 7.43E-07 NO DATA 2.46E-04 5.79E-04 3.74E-05

. TE125M 4.27E-07 1.98E-07 5 84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 TE127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TEtti 1 75E-10 8.01E-11 3 87E-11 1 32E-10 6.37E-10 8.14E-07 7.17E-06 TE129p 1.22E-06 5.84E-07 1 98E-0 7 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1'.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE131M 8.74E-09 5.45E-09 3 63F-09 6.88E-09 3.86E-08 1.82E-05' 6.95E-05 J E131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.746-07 2.30E-09 TE132 3.25E-08 2.69E-08 2 02E-08 2,37E-08 1 82E-07 3.60E-05 6.37E-05

! 130 5.72E-07 1 68E-06 6.60E-07 1 42E-04 2.61E-06 NO DATA 9.61E-07 1 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7 66E-06 NO DATA 7.85E-07 I 132 1.45E-07 4.07E-07 1 4bE-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 I 133 1 08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 1 134 0 05E-08 2.16E-07 7.69E-08 3 73E-06 3.44E-07 NO DATA 1.26E.10 I 135 3b5E-07 8 73E-07 3.21E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 C5134 4.66E-05 1 06E-04 9.10E-05 NO DATA 3 59E-05 1.22E-05 1.30E-06 C5136 4.88E-06 1 83E-05 1 38E-05 NO DATA 1 07E-05 1.50E-06 1 46E-06 i

C5137 5 90E-05 7.76E-05 5.35E-05 NO DATA. 2.78E-05 9.40E-06 1.05E-06 C5138 4 14E-08 7.76E-08 4.05E-08 NO DATA 6.00E-08 6.07E-09 2.33E-13 8A139 1 17E-10 8.32E-14 3.42 E-12 NO DATA

.7.78E-14 4.70E-07 1 12E-07

._..w-6A140 4.88E-06 6.13E-09 l.21E-07 NO DATA 2.04E-09 1.59E-04 2.73E-05 4A141 1.25E-11 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1 45E-17 RA142 3.29E-12 3.38E-15 2.07E-1B NO DATA 2 86E-15 1.49E*07 1 96E-26 LA140 4 30E-08 2.17E-08 s.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 L A142 8 54E-11 3 88E-11 9.6SE-12 No DATA NO DATA 7.91E-07 2.64E-07 CE141 2.49E-06 1.69E-06 1.91 E-0 7 NO DATA 7.83E-07 4.52E-05 1.50E-05 CE143 2.33E-04 1.72E-08 1.91E-09 NO DAT6 7.60E-09 9.97E-06 2.83E-05 CE144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1 06E-04 9.72E-04 1.02E-04 PA143 1 17E-06 4.69E-07 5.80E-08 540 DATA 2 70E-07 3.51E-05 2.50E-05 PA144 3.76E-12 1.56E-12 1.91E-13 40 OATA 8.81E-13 1.27E-07 2.69E-15 40147 6.b9E-07 7.62E-07 4.66E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA NO DATA 3 63E-06 1.94E-05 NP239 2.17E-08 2.82E-09 1.55E-49 NO DATA 8.75E-09 4.70E-06 1.49E-05 l

ODCM i

Page:

53 l

Rev.:

5 Table 3.2-7 Inhalation Dose Factors for Teenager (mrem /pci inhaled)

J f

i I

NUCLICE SONE LtWER T.000Y THYROID KIONEY

...LUNO.

.Gl=ELI I

N 3

NO DATA I.595-0T 3.59E-07. 1 59E-07 1 59E-07 1.59E-07 1 59E-07 l

C 14 3.2bE-06 6.C9E-07 6.09E-07 6.09E-07 6.ft9E-07 6.09E-07 6.09E-07 NA 24 1.72E-06 8.72C-06 1.72E-06 1 72E-06 1 72E-06 L.72E-06 1 72E-06 l

P,12 2 36E-04 1.376-09 8.95f-06 N0 DATA NC DATA NO DATA 1.1'4F-05 CA b1 NO DATA NO DATA 1.69F-08 9.37E-09 3.84E-09 2 62E-06 '3.75E-07 l

F4 54 NO DATA 6.39E-06

1. 0 >E-0 6 NO DATA 1 59E-06 2 48E-04 8.35E-06 i

MN 56 NO DATA-2.124-30 3.15E-Il NO DATA 2 24E-10 1 90E-06 7.18E-06 i

{

FE $5 4.18E-06 2.98E-06 6.93E-0T NO CATA NO DATA 1.55E-05 7.99E-07 FE 59 1.991-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 3

l CD SC NO OtTA 2.39F-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 i

J CD 60 NO DATA 1.89E-06 2 48E-06 NO DATA NO DATA 1 09E-03 3.24E-05 NI 63 7.25E-05 ~5.43E-06 2.47 E-0 6 NO DATA NO DATA 3 84E-05 1 77E-06 i

l M1 65 2.73E-10 3.o6F-11 1.59E-11 NO DATA NO DATA 1.17E-06 6.59E-06 L

i CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA 8.01E-10 1 39E-06 7.68E-06 2N 65 4.82E-06 1.67E-05 7.80E-0 6

• NO DAT A 1 08E-05 1 55E-04 5 83E-06

.... ~.....

... -... ~............

IN 69 6.04E-12 1 15F-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 3 56E-08 i

4 A8 83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-26

?

l 84 84 NO DATA NO DATA 5.4LE-08 NO DATA NO DATA NO DATA LT E-24 I

l BR SS NO DATA NO DATA 2.2 9E.09 NO DATA NO DATA NO DATA LT'E-24 l

48 86 NO DATA 2.38E.05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 AS 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 j

^ NO DATA NO DATA 4.22E-17 I

R8 89 NO DATA 4.40E-08 2.91E-08 NO DATA 5R 89 5.43E-05 NO DATA 1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 54 90 1*.35 E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05

.~

. -. ~. -

SR 91 1.10E-08 NO DATA 4.19E-10 NO DATA NO DATA 7 59E-06 3.24E-05 l

5R 92 1 19E-09 NO DATA 5.08E-11 NO DATA NO DATA 3 438-06 1.49E-05 Y 90 3.73E-07 NO DATA 1.00E-08 NO DATA MO DATA 3 66E-05 6.99E-05 g

Y 91M 4.63E-11 NO DATA

1. 77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 N0 DATA MO DATA 3.6TE-04 5.11E-05 i

Y 92 1.84E-09 NO DATA 5.36E-18 NO DATA NO DATA 3.35E-06 2.OAE-05 1

9 93 1.69E-08 NO DATA 4.65E-1D NO DATA NO DATA 1.04E-05 7.24E-05 l

2R 95 1.82E-05 5.73E-06 3.94E-06. NO DATA 8.42E-04 3 36E.04 1.86E-05 2R 97 1.72E-08 3.40E-09 1.57E-09 o!O DATA 5 15E-09 1 62E-05 7.88E-05 l

j M8 96 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05

~

I

. - ~ ~. -

.~

MD 99*

NO DATA 2.11E-05 4.03E-09 No DATA 5.14E-08 1.92E-05 1.36E-05 TC 99M 1.73E-13 4.83E.19 6.24E-12 NO DATA 7.2 0E-12 1.44E-0F 7.66E-07 1

s 4

i 4

l t

i ODCM Page:

54 l

Rev.:

5 i

Table 3.2-7 (Cont.)

1

{

Inhalation Dose Factors for Teenager (mrem /pCi inhaled)

I I

i i

i s

a i

'seUCLIOE SONE Livf4 T.400f

' THYADID E1DNEY

~ 1.Useg ~

C1-LLI l

i TC401 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1 09E-16 i

AU103 2.63E-07 40 DATA 1.12E-07 NO Data 9.29E-07 9.79E-05 1 36E-05 i

RU105 1 40E-10 NO DATA 5.42E-11 NO DATA 1.7&E-10 2.27E-06.1.13E-05 r

RU1' 6 1.23E-05 NO DATA 1.55 E-06 No feATA 2.38E-05 2.01E-03 4 20E-04 l

0

.O DATA 3.13E-06 8.44E-04 3 41E-05 j

AG110M 1.73E-06 1.64E-06 9.99E-07 TE125p 6.10E-07 2.80E-07

8. 34 E-0 8. 1. 75E-07 40 DATA 6.70E-05 9.34E-06 3

l i

TE127M 2.25E-06 1.026-0+

2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127.

2.51E-10 1.14E-10 f,. 52 E-1 1 1.77E-10 9.10E-10 1.40E-06 1.01E-05

. TE129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 T E129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE131P 1.23E-08 7.51E-09 5.03Eb09 9.06E-09 5.49E-00 2 97E-05 7.76E-05 TE131 1 97E-12 1.04E-12 6.30E-13 '1.55E-12 7.72E-12 2.92E-07 1 89E-09 TE132 4.50E-08 1.e3E-08 2.T4E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 1 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 3

1 1 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.0$E-05 NO DATA 3.11F-07 i

[132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1 59E-07 i

1 133 1.52E-06 2.96E-06

7. 78 E-0 7 3.65E-04 4.49E-06 NO DATA 1.29E-06 1 134 1.11E-07 2.90E-07 1.05E-07 4 94E-06 4.58E-07 h0 DATA 2.55E-09 1 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 C5134 6.28E-05 1.41E-04 6 86E-05 NO DATA 4.69E-05 1.83E-05 1 22E-06 C5116 6.44E-06 2.42E-05 1 71E-05 NO DATA 1.38E-05 2.22E-06 1 36E-06 C5137 8.30E-05 1 06E-04

3. 89E-05 NO DATA 3.80E-05 1 51E-05 1 06E-06 C5138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-11 8A139 1.67E-10 1.18E-13 4 87E-12 No DATA 1.11E-13 8.08E-07 8 06E-07 SA140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2 54E-04 2.86E-05 54141 1.78E-11 1.s2E-14 6.9AE-13 NO DATA 1.23E-14 4.11E-07 9.33E-14 h4142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3 92E-15 2 39E-07 5.99E-20 LA140 5.99E-08 2.95E-08

7. 82C-09 NO DATA NO DATA 2.68E-05 6.09E-05 L 4142 1.20E-10 5.31E-11 1.32E-11 NO DATA 40 DATA 1.27E-06 1.50E-06

~

CE141 3.55E-06 2.37C-06 2.71E-07 NO DATA 1.11E-06 7.67E-05 -1 58E-05 CE143 3.J2E-00 2.42E-08 2.70E-09 NO DATA 1.00E-08 1.63E-05 3.19E-05 CE144 6.11E-04 2.53E-04 3.2 0 E-0 5 NO DATA 1.51E-04 1.67E-Oi 1.08E-04 P9143 1 67E-06 6.64E-07 8.20E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PJt144 5.37E-12 2.20E-12 2.72E-13 10 DATA 1.26E-12 2.19E-07 2.94E-14 se0147 9.83E-07 1.07E-06 6.41E-08 880 DATA 6 20E-07 4.65E-05 2.28F-05 W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 PP239 4.23E-08 3.99E-09 2 21E-09 40 DATA 1.25E-08 a.11E-06 1 65E-05 l

1

ODCM Page:

55 Rev.:

5 Table 3.2-8 Inhalation Dose Factors for child (mrem /pci inhaled)

.a vuEL30E SO9E L1WER T.800T

.TNYR010 A10NEY LUNC 01-Lt,1 H

3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3 04E-07 3.04E-07 C to 9.70E-06 1.82E-06 1 82E-06 1 82E-06 1.82E-06 1 8?E-06 1 82E-06

%A to 4.35E-06 4.35"-06

4. )>E-0 6 4.35E-06 4.35E-c6 4.35E-06 4 35E-06 P '32 7.04E-04 9.09E-05 2.8;7E-05 NO DATA NO DATA Nn DATA 1.14E-05 CA 51 NO DATA NO DATA 4 17E-08 2 31r-08 6.57E-09 4.59E-06 2 93E-07 NN 54 40 DATA 1.16E-05 2 57E-oe No 04TA 2.71E-06 4.26E-04 6.19F-06 MN $6 NU O A TA 4.48E-10 8 43Ee!! NO OstA 4.52E-10 3 55E-06 5.33E-05 f t 55 1.28E-05 6.80E-06 2.10E-06.40 DATA NO DATA 3 00E-05 7.75E-07 FE 59 5.59E-06.9.C4E-06 4.51E-06 40 DAT&

NO DATA 3 43E-04 1 91E-05 CO 58 NO DATA

4. 7 9E-07 8 55E-07 No DAT'4 No DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 ' 6 12E-06 No CATA NO DATA 1.91E-03 2.60E-05 N163 2.22E-04 1.15E-05

7. 56E-0 6 NO DATA NO DATA 7.43E-05 1.71E-06

. _.. ~

.. ~... -

.. ~

NI 65 8.08E-10 7.99E-11

4. 4 4 E-11 Nn DATA NO DATA 2 21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2 90E-10 NO DATA 1.63E-09 2 59E-06 9.92E-06 2N 65 1.15E-05 3.06E-05. 1.90E-0 5 NO DATA 1.93E-05 2 69E-04 4.41E-06 24 69 1.81E-11 2.61E-11 2.41E-12 NO DATA 1.58E-11 3 84E-07 2 75E-06 MR 83 NO DATA

.No DATA 1.2 8E-0 7 N3 OATA NO DATA ND DATA LT E-24 sA 84 NO DATA NO DATA 1 48E-07 NO DATA NO DATA NO 04TA LT E-24

..:.~...

No DATA NO DATA NO DATA LT E-24 ER 85 NO DATA NO DATA 6.84E-0 9 AD 86 NO DATA 5.36E-05 3 09E-05 NO DATA NO DATA NO DATA 2 16E-M AD 88' NO DATA 52E-0T 9 90E-08 NO DATA

.NO DATA N'O DATA 4.661-09 RS 89" NO DATA 9.331-08 7.8)E-08 NO DATA NO DATA NO DATA 5.11E-10 54 89 1.62E-04 NO DATA

4. 66E-0 6 NO DATA NO DATA 5.81E-04 4.52E-05 SR 90 2.73E-02 NO. DATA 1.74E=O3 NO DATA NO DATA 3 99E-03 9 28E-05 SP 91 3.28E-08 40 DATA 1 24E-09 NO DATA NO DATA 1 44E-05 4.70E-05 SR 92 3.>4E-09 NO DATA 1 42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y 90 1.18E-06 No DATA 2 99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y 917 1.37E-10 NO DATA 4 98E-12 NO DATA NO DATA 7.60F-07 4.64Ee07 Y 91 2.47E-04 40 DATA 4 59E-@6 NO DATA M0 DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1 5fE-10 NO DATA NO DATA 6.46E-Os,.6.46E-05 Y 91 5.04E-08 NO DATA 1 38E-09 NO DAT4' NO DATA

~2 01E45 1.05E-04 2A 95 6.13E-05 1.13E-05 1 00E-05 40 DATA 1.61E-05 6.03E-04 1.65E-05 2R 97 5 07E-08 7.d4E-09 4 32E-09 NO DATA 1.05E-08 3 06E-05 9.49E-05 NS 95 6.35E-06 2.48E-06 1 77E-06 40 DATA 2.33E-06 1 66E-04 1.00E-05 MO 99 NO DATA 4.66E-08 1 1>E-08 WO Daft 1.06E-07 3.66E-05 9.42E-05 TC 997 4.81E-13 9.41E-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06

i 1

ODCM I

Page:

56 i

Rev.:

5 Table 3.2-8 (Cont.)

Inhalation Dose Factors for Child (mrem /pci inhaled)

WUCLtBE CONE L IVE R T.dODf IHYA010 KIONEY LtMC Gl*LLI TClot 2.19E-14, 2.30E-14 2 91E-13 NO DATA 3.92E-13 1.b8E-07 4.41E-09

~

AU103 7.55E-07 No 04TA 2.90E-07 NO DATA t.90E-06 t.79E-04 1.21E-05 AU105 4.13E-10 NU CATA 1.>0E-10 'NO DATA 3.63E-10 4.30E-06 2.69E-05 AUl06 3 68E-0) NO 04fA 4.57E-06 40 DATA 4.97E-05 3.87E-03 1.16E-04 ACitov 4.56E-06 3.08E-06 2.47E-06 40 DATA 5.74L-06 1.48E-03 2.71E-05 TE125M 1.82E-06 6.29f*07 2.47E-07 5.201-07 4G DATA 1.29E-04 9 13E-06 TE1278 6.72E-06 2.3tE-Os

8. lee-07 1 64E-06 1.72E-05 4.00E-04 1.93E-05 TE127 7.49E-10 2.97E-10 1.65E-10 5.30E-10 1.91E-09 2 7tE-06 1.52E-05 1El2?r 5.19E-06 1.85E-06 8.22E-07 1.7tE-06 1.16E 4.*76E-04 4.9tE-05 TE129 2.64E-11 9.45E-12 s.44E-12 1 93E-11 6.94E-11 7.98E-07 6.89E-06 TE13tr 1.63E-08 1.60E-08 1.37E-08 2.64E-08 1 08E-07 5.56E-05 8.32E-05 TE131 5 87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3 60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08' 4.79E-07 1.02E-04 3.72E-05 t 130 2.21E-06 4.435-06 2.28E-06 4.99E-04 6.61E-06 NO,0ATA 1.3BE-06 t 131 1 30E-05 1.30E-05 7.37 E-0 6 4.39E-03 2.13E-05 NO DATA 7.68E-07 8 132 5.72E-07 1.10E-06 5.0fE-07 5.2 3E-05 1.69E-06 NO DATA. 8.65E-07 I 133 4.48E-06 5 49E-06 2 08E-06 1 04E-03 9.13E-06 No DATA 1.48E-06

! 134 3 17E-07 5.845-07 2 6?E-07 1 37E-05 8.92E-07 NO DATA 2.5BE-07 i

i 135 1.33E-06 2.66E-06 1.12 E-06 2.14E-04 3.62E-06 NO DATA 1.20E-06 C5134 1 76E-04 2 74E-04

6. 0 7E-0 5 40 OATA 8.93E-C5 3.27E-05 1 04E-06 C5136 1.76E-05 4.62E-06 3.14E-05 NO DATA, 2.58E-05 3.93E-06 1.43E-06 C5137 2.45E-04 2 23E-04 1.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 1.71E-07 2 2FE-07

1. 50E-0 7 NO DATA 1.68E-07 1.84E-08 7.29E-08 C5138 ~ 4.98E-10 2.66F-13 1.4 5E-11 NO DATA. 2.33E-13 1 56E-06 1.56E-05 AA139

'SA140 2 00E-05 1.75E-08 1.t rE-06 NO DAT A 5.71E-09 4.71E-04 2.75E-05

' Sat 41 5.29E-11 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-04

• 84142 1.35E-11 9.73E-15 7.>4E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 LA140 1.74E-07 6 08E-08 2.04E-04 NO DafA M0 DATA 4.94E-05 6.10E-05 LAt42

).50E-10 1.41E-10 3.49E-11 NO DATA NO DATA 2.35E-06 2 05E-05 CE141 1 06E-05 5.28E-06

7. 8 3E=0 F NO DATA 2.31E-06 1.47E-04 1.53E-05 CE143 9.89E-08 5.37E-08 7.7FE-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE144 1 03E-03 5.72E-04 9.77E-05 40 DATA 3.17E-04 1.23E-03 1.05E-04 PA143 4.99E-06 1.50E-06 2.47E-07 NO DATA

,,8.116-07 1 17E-04 2 63E-05 PA144 1.6tE-11 4.99E-12 8.10E-t3 40 DATA 2.64E-12 4 23E-67

>.32E-08

+

Not47 2.92H-06 2.36E-06 1 84 E-0 7 NO DATA 1 30E-06 8.87L-05 2.22E-05 N IST 4.*1E-09 2 61E-09 1.17E-0 9 NO DATA NO DATA 1.11E-05 2.46E-05

. - - - - - -.. ~..

NP239 1.26E-07 9.04f-09 6.35E-09 NO DATA 2 63E-08 1.57E-05 1.73E-05

ODCM Page: 57 Rev.:

5 Table 3.2-9 j

Inhalation Dose Factors for Infant (mrem /pCi inhaled)

NUCLICE SONE L1WER T.80CY TMYRO10 R10NEY LUNG'

'Cl-LLl*

N 3

NO DATA 4.62E-07 4.62E-07 4.62F-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79C-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 NA 24 7.64E-06 7.54E-06 7.54E-06 2.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 8.03E-05 S.5JE-Ob NO DATA NO DATA ko DATA 1.15E-05 CR 51 NO DATA NO DATA 6.31E-08.4.11E-08 9.45609 9.17E-06 2.55E-07 MN 54 NO DATA 1.81E-05 3.56C-06 NO DATA 3.561-06 7 14E-04 5.04E-06

.. * -. ~. -. _

MN 56 NO DATA 1.10E-09 1.5 8E-10 NO DATA 7.86E-10 8.95E-06 5.12E'05 FE $5 1.41E-05 8.39E-06 2 38E-06 N;; OAfA NO DATA 6.21E-05 7.82E-07 F E 31 9.69E-06 1.68E-05 6.7 TE-06 NO DATA NO DATA 7.25E-04 1.77E-05

.. _ _... -.. -.. - -. ~. -.

CD is NU OATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 CO 60 NO DATA 5.73E-06 8.41 E-06 NO DATA NO DATA 3.22E-03 2.28E-05 N163 2.42E-04 1.46E-05 8.29E-0 6 NO DATA NO DATA 1.49E-04 1 73E-06 N165 1.71E-09 2.03C-10 8.79E-11 40 DATA NO DATA 5.00E-06 3.58E-05 CU 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 24 65 1.30E-05 4.47E-05 2.22 E-0 5 NO DATA 2.32E-05 4.62E-04 3.67E-05 ZN 69 3.05E-11 te.91E-11 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.44E-06 BR 83 NO DATA' NO DATA

2. 72 E-0 7 MO DATA NO DATA NO DATA LT E-24 SR 84 NO DATA NO O'ATA

2. 86E-0 7 NO DATA NO DATA NO DATA LT E-24 84 85 NO DATA N J 0/ (A 1 46E-08 ' NO DATA NO DATA NO DATA LT.E-24 A8 86 ND'OATA

.341-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 R$ 88 NO DATA 3.9,E-07

2. 05E-0 7 NO DATA NO DATA NO DATA 2.42E-07 R$ 89 NO DATA t.29E-07 1.47E-0 7 NO DATA NO DATA NO DATA 4.87E-08 SR 49 2.84E-04 NO DATA 8.15C-06 NO DATA NO DATA' 1.45E-05 4.57E-Of,;

SR 90 2.92E-02 NU DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91

'6.83E-08 NO DATA 2 47E-09 NO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1 00E-04 Y 90 2.35E-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E45 Y 91R 2 91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06 Y 91 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-O'5-9.04E Y 95 1 07E-07 NO DATA 2.91E-0 NO DATA NO DATA 5.46bE5 1 19E-04 LR 95 8.24E-05 1.99E-05 1.45E-L'S NO DATA 2.22E-05 1.2SE-03 1.55E 149 T 1.07E-07 1.83E-08 8.36E-09 N0 DATA.1.85E-08 7.88E-05 1.00E-04 48 95 1.12E-05 4 59E-06 2.70E-06 NO DATA 3.s?E-06 '3.42E-04 9.05E-06 MO 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3 48E-05 TC 99p 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-87 1.45E-06

i ODCM Page: 58 Rev.: 5 Table 3.2-9 (Cont.)

Inhalation Dose Factors for Infant (mrem /pCi inhaled) l i

I i

i e

NUCLicE SONE LIVER T.500f THYROAD KIONEY LUNG Cl*LLI TC101 4.65E-14 5.9BE-14

5. 80E-13 NO DATA 6.99E-13 4 17E-07 4.03E-07 AU103 1.44E-06 NO CATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 RU105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05 3 46E-05 l

.... ~..... _.... - -. - - - - -..

- - - - - - - - - - - - - ~.

,AU106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.01E-05 8 26E-03 1.17E-04 AG11088 7.13E-06 5.16E-06 3.57E-06 40 DATA 7.80E-06 2.62E-03 2.36E-05 TE125N 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 TE127M 1.19E-05 4.93E-06 1 48E-06 3.4BE-06 2.6BE-05 9 37E-04 1 95E-05 TE127.

1.59E-09 6 81E-10 3 49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129F 1.01E-05 4 35E-06 1 59E-06 3.91E-06 2.27E-05 1.20E-03, 4'.93E-05 TE129 5.63E-11 2 48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE131N 7.62E-08 3 93E-08. 2.59E-08 6.38E-08 1 89E-07 1 42E-04 8.51E-05 TE131 1 24E-11 5.87E-12 3 57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.2&E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 l

1 130 4.54E -06 9.91E-06 3-98E-06 1 14E-03 1.09E-05 NO DATA 1.42E-06

! 131 2.71E*05 3.17E-05 1.40E-05 1.06E-02' 3.70E-05 No DATA 7.56E-07 i

1 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.42E-06 NO DATA 1.36E-06 1 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA *1.54E-06 l

1 134 6.58E-07 1.34E-06 4.75E-07 5.18E-05 1.49E-06 NO DATA 9.21E-07 I 135 2 76E-06 5.63E-06 1.9BE-06 4 97E-04 6.05E-06 NO DATA 1.31E-06 l

C5134 2 83E-04 5.02E-04

5. 32 E-0 5 NO DATA 1 36E-04 5.69E-05 9.53E-07 t

i C5136 3 45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 l

C5137 3.92E-04 4.37F-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 l

C5138 3 61E-07 5 58E-07 2.84E-07 MO DATA 2.93E-07 4.67E-08 6.26E-07 BA139 1.06E-09 7.03E-13 3.07E-11*ND DATA 4.73E-13 4.25E-06 '3.64E-05 mA160 4.00E-05 4.00E-04 2.07E-0 6 NO DATA 9.59E-09 1.14E-03 2.74E-05 l

cA141 1.12E-10 7.70r-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 na142 2.84E-11 2.36E-14 1.40E-12

'NO. DATA 1.36E-14 "1.11E-06 4.95E-07 LA140 3.61E-07 1 4 3t-07 3 6BE-08 No DATA MO DATA 1.20E 6.06E-05 LA142 7.36E-10 2 69E-10 6.46E-11 NO DATA No DATA 5.87E-06 ~'4.2 5Ea05 CE141 1 98E-0),1.19E-05 1 42 E-06 MO DATA 3.75E-06 3.69E-04 1.54E-05

............~.....

CE143 2.09E-07 1 98E-07 1.5AE-08 MO DATA 4.03E-08 8.30E-05 3.55E-05 l

• E144 2.28E-03 8.e5E-04 1.26E-04 40 DATA 3.84E-04 7.03E-03 1.06E-04 FA143 1 00E-05 1.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11

1. 72 E-12 NO DATA 4.A0E-12 1.15E-06 3.06E-06 N014F 5.67E-06 5.81F-06 3 57E-07 NO DATA 2.25E-D6 2.30E-04 2.23E-05 w 187 9.26E-09 6.44E-09 2.2 3E-0 9 NO DATA NO DATA 2.83E-05 2.54E-05 MP239 2.65E-07 2.37E-08 1 34 E-0 8 NO DATA 4.73L-08 4.25E-05. 1.78E-05 i

i i

ODCM Page:

59 Rev.:

5 1

Table 3.2-10 Ingestion Dose Factor for Adult (mrem /pCi ingested)

TOTAL ISOTOPE BONE LIVER BODY THYROID KIONEY LUNG GI-LLI H3 0.00E+00 1.05E-07 1.05E-07.1.05E-07 1.05E-07 1.05E-07 1.05E-07 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA24 1.70E-06 1.70E-06

1. 70E-06 1. 70E-06 1.70E-06 1.70E-06 1.70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 CRS1 0.00E+00 0.00E+00 2.66E-09 1.59E-09

5. 86 E-10 3.53E-09 6.69E-07 MN54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 MN56

0. 00E +00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 FESS 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 C058

0. 00E +00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 C060 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 NI63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 NI 65-5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 CU64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 ZN65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E400 9.70E-06 ZN69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 BR83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 8R84 0.00E+00 0.00E+00 5,21 E-08 0.00E +00 0.00E+00 0.00E+00 4.09 E-13 BR85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R886 0.00E+00 2.11 E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 RB88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 R889 0.00E+00 4.01E-08 2.82E-08 0.00E+00

0. 00E +00 0.00E+00 2.33E-21 SR89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 SR90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00EF00 0.00E+00 2.19E-04 SR91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E400 2.70E-05 SR92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y91M

9. 09 E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.67E-05 Y92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 ZR95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 ZR97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12 E-10 0.00E+00 1.05E-04 N895 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 M099 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 TC99M

2. 47 E-10 6.98E-10 8.89E-09 0.00E+00

' 06E-08 3.42E-10 4.13E-07 1

ODCM Page:

60 Rev.:

5 Table 3.2-10 (Cont.)

Ingestion Dose Factor for Adult (mrem /pCi ingested)

TOTAL ISOTOPE BONE LIVER BODY THYROID KIONEY LUNG GI-LLI TC101

2. 54 E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 RU105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 RU105 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00

1. 78E -04 AG110M 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 TE125M 2.68E-06 9.17E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 TE127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 0.00E+00 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 TE132 2.52E-06 1.63E-06

1. 53 E-06 1. 80E-06

1. 57 E -05 0.00E+00 7.71E-05 1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 I131 4.16E-06 5.95E-06

3. 41 E-06 1.95 E-03 1.02E-05 0.00E+00 1.57E-06 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 1133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 1

1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00

2. 51 E-10 1135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 I

CS134 6.22E-05 1.48E-04 1.21 E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 0.00E+00

8. 01 E-08 7.91E-09

4. 65 E-13 BA139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 8A140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11

1. 59E-09 0.00E+00

3. 31 E-11 2.02E-11

2. 22 E -17 8A142 2.13E-08 2.19E-11 1.34E-09 0.00E+00

1. 85 E-11

1. 24 E-11 3.00E-26 LA140 2.50E-39 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E440 9.25E-05 LA142 1.28E-10 5.82E-11

1. 4 5 E-11 0.00E +00 0.00E+00 0.00E+00 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 CE143

1. 65 E -09 1.22E-06 1.35E-10 0.00E+00

5. 37 E-10 0.00E+00 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 0.00E+00

1. 21 E-07 0.00E+00 1.65E-04 PR143 9.20E-09 3.69E-09

4. 56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 PR144 3.01E-11 1.25E-11

7. 53E-12 0.00E+00 7.05E-12 0.00E+00

4. 33 E-18 ND147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W187 1.03E-07 8.61E-08 1.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 NP239 1.19E-09 1.17E-10

5. 4 5 E-11 0.00E+00

3. 65 E-10 0.00E+00 2.40E-05 l

l l

ODCM Page:

61 Rev.: 5 Table 3.2-11 Ingestion Dose Factors for Teenager (mrem /pCi ingested) i TOTAL ISOTOPE BONE LIVER BODY THYROID KIONEY LUNG GI-LLI H3 0.00E+00 1.06E-07

1. 06E-07 1. 06E-07 1.06E-07 1.06E-07 1.06E C14 4.06E-06 8.12E-07 8.12 E-07.8.12 E-07 8.12E-07 8.12E-07 8.12E-07 NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 CR51 0.00E+00 0.00E+00 3.60E-09 2.00E-09

7. 89 E-10 5.14E-09 6.05E-07 MN54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 MN56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 FESS 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E +00 1.70E-06 1.16E-06 FE59 5.87E-06 1.37E-05 5.29E-06 0.00E440 0.00E+00 4.32E-06 3.24E-05 C058 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 C060 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 NI63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 NI65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 CU64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 ZN65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 2N69 1.47E-08 2.80E-08 1.96E-09 0.00E&OO 1.83E-08 0.00E+00 5.16E-08 BR83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR84 0.00E+00 0.00E+00 7.22E-08 0.00E+00

0. 00E +00 0.00E+00 0.00E+00 BR85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 RB88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 R889 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 SR89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 SR90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 SR91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E +00 0.00E+00 3.66E-05 SR92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.'00E+00 7.77E-05 Y90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y91H

1. 29 E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y92

1. 21 E-09 0.00E+00

3. 50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y93 3.83E-09 0.00E+00 1.05E-10 0.00E&00 0.00E+00 0.00E+00 1.17E-04 2R95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 ZR97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11 E-10 0.00E+00 1.27E-04 NB95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 M099 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14 E-10 6.08E-07 l

I

ODCM Page: 62 Rev.: 5 Table 3.2-11 (Cont.)

Ingestion Dose Factor for Teenager (mrem /pCi ingested) i TOTAL ISOTOPE BONE LIVER BODY THYROID KIONEY LUNG GI-LLI TC101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10

8. 7 5 E-17 RU103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05 RU105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 RU106 3.92E-06 0.00Ee00 4.94E-07 0.00E+00

7. 56 E-06 0.00E+00 1.88E-04 AG110M 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 TE125M 3.83E-06 1.38E-06 5.12 E-07 1. 07 E-06 0.00E+00 0.00E+00 1.13E-05 TE127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 TE129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 1130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06

0. 00E +00 2.29E-06 1131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 1133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 1134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 1135 6.10E-07 1.57E-06

5. 82 E-07 1. 01 E-04 2.48E-06 0.00E+00' 1.74E-06 CS134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05.2.45E-06 CS136 8.69E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 BA139 1.39E-07 9.78E-11 4.05E-09 0.00E+00

9. 22 E-11

5. 74 E-11 1.24E-06 BA140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 8A141 6.71E-08 5.01E-11 2.24E-09 0.00E+00

4. 6 5 E-11 3.43E-11

1. 43 E-13 BA142 2.99E-08 2.99E-11 1.84E-09 0.00E+00

2. 53 E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 LA142

1. 79 E-10 7.95E-11

1. 98E-11 0.00E+00 0.00E&00 0.00E+00 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 CE143 2.35E-09 1.71E-06 1.91 E-10 0.00E+00

7. 67 E-10 0.00E+00 5.14E-05 CE144 6.96E-07 2.88E 'J7 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 PR143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 PR144 4. 30E-11

1. 7 6 E-11 2.18E-12 0.00E+00 1.01 E-11 0.00E+00

4. 74 E -14

'~

ND147 9.38E-09 1.02E-08 6.11 E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 W187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00

0. 00E +00 3.22E-05 NP239 1.76E-09 1.66E-10

9. 22 E-11 0. 00E+00

5. 21 E-10 0.00E+00 2.67E-05

f l

ODCM Page:

63 Rev.:

5 Table 3.2-12 Ingestion Dose Factors for Child (mrem /pCi ingested)

TOTAL ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 E.42E-06 NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 2

i P32 8.25E 04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 l

CR51 0.00E&00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 l

MN56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 FESS 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 l

FES9 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 C058 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 C060

0. 00 E +00 5.29E-06

1. 56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05

)

NI63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 NI65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00Et00 0.00E+00 2.56E-05 CU64 0.00E&00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 2N65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 ZN69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 i

BR83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E400 0.00E+00 0.00E+00 BR84

0. 00E +00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

R886 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 R888 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 R889 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E&00 0.00E+00 1.02E-09~

SR89 1.32E-03 0.00E+00 3.77E-05 0.00E&00 0.00E+00 0.00E+00 5.11E-05 SR90 1.70E-02 0.00E+00 4.31E-03 0.00E+00

.0.00E+00 0.00E+00 2.29E-04 SR91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 SR92 9.03E-06 0.00E400 3.62E-07 0.00E&00- 0.00E+00 0.00Et00 1.71E-04 Y90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E&00 0.00E+00 1.17E-04 Y91M

3. 82 E-10 0.00E+00

1. 39 E-11 0. 00E+00 0.00E+00 0.00E+00 7.48E-07 Y91 6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 Y93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 2R95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 ZR97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 N895 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 M099 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05

(

TC99M

9. 23 E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19 E-10 1.03E-06 l

l

(

l l

ODCM Page:

64 Rev.:

5 Table 3.2-12 (Cont.)

Ingestion Dose Factors for Child (mrem /pci ingested) i i

TOTAL ISOTOPE BONE LIVER BODY THYROID KIONEY LUNG GI.LLI TC101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92 E-10 3.56E-09 RU103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 RU105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 RU106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04 AG110M 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06

0. 00E +00 0.00E+00 1.10E-05 TE127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 TE129M 4.87E-05 1.36E-05

7. 5 6E-06 1. 5 7 E-05 1.43E-04 0.00E+00 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00

8. 34 E -06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 j

TE132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 l

1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 1131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 1132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 1133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 1

1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16 E-07 1135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E&00 2.40E-06 CS134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 CS136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5,13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.57E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 BA139 4.14E-07

2. 21 E-10 1.?GE-08 0.00Er00

1. 93 E-10 1.30E-10 2.39E-05 8A140 8.31E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 BA141 2.00E-07 1.12E-10 S.51E-09 0.00E+00 9. 69 E-11

6. 58E-10 1.14E-07 BA142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11

3. 70E-11 1.14E-09 LA140 1.01E-08 3.53E-09 1.19E-09 0.00E+00-0.00E+00 0.00E+00 9.84E-05 LA142

5. 24 E-10 1.67E-10

5. 23E-11 0. 00E +00 0.00E+00 0.00E+00 3.31E-05 i

CE141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09

0. 00E +00 5.55E-05 CE144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11 E -11 0.00E+00 8.59E-08 ND147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 l

NP239 5.25E-09

3. 7 7 E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 l

I l

l l

ODCM l

Page:

65 t

Rev.:

5 Table 3.2-13 1

Ingestion Dose Factors for Infant (mrem /pCi ingested) l TOTAL ISOTOPE 80NE LIVER 80DY THYROID KIDNEY LUNG GI-LLI i

H3 0.00E+00 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-0T C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA24

1. 01 E-05 1.01E-05

1. 01 E-05 1.01 E-05 1.01E-05 1.01E-05 1.01E-05 P32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 CR51

0. 00 E +00 0.00E+00 1.41 E-08 9.20E-09 2.01E-09

1. 79 E'-08 4.11E-07 MN54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 MN56 0.00E+00 8.18E-07 1.41 E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 FESS 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 FE59 3.08E-05 5.38E-05 2.12E-05 0.00E&00 0.00E+00 1.59E-05 2.57E-05 i

C058 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 C060 0.00Et00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 N163 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 NI65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 CU64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05

)

IN65 1.84E-05 6.31E-05 2.91 E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 2N69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 8R83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E&O0 8R34

0. 00 E +00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8R85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R886 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 R888 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 RB89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E&00 0.00E+00 9.74E-08 SR89

2. 51 E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 SR90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E&00

0. 00E +00 2.31E-04 SR91 5.00E-05 0.00E+00 1.81 E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 SR92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0'.00E+00 2.07E-04 Y90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y91M 8.10E-10 0.00E+00

2. 76 E-11 0.00E+00 0.00E&00 0.00E+00 2.70E-06 Y91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y92 7.65E-09 0.00E&00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 ZR95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 ZR97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 NB95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05

~

M099 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 TC99M 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 l

i I

ODCM Page:

66 Rev.:

5 Table 3.2-13 (Cont.)

Ingestion Dose Factors for Infant TOTAL ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 RU105 1.36E-07 0.00E+00 4.58E-08 0.00E&00 1.00E-06 0.00E+00 5.41E-05 RU106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 AG110M 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 TE129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 i

TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 TE131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 TE131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 TE132 2.08E-05 1.03E-05

9. 61 E-06 1. 52 E-05 6.44E-05 0.00E+00 3.81E-05 1130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 1131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00

1. 51 E-06 1132

1. 66 E -06 3.37E-06

1. 20 E-06 1. 58 E-04 3.76E-06 0.00E+00 2.73E-06 1133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E +00 1.84E-06 1135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 CS134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06 CS136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 CS137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05

1. 91 E-06 CS138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 BA139 8.81E-07

5. 84 E-10 2.55E-08 0.00E+00

3. 51 E-10

3. 5.4 E-10 5.58E-05

+

8A140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 BA141 4.25E-07

2. 91 E-10 1.34E-08 0.00E+00

1. 7 5 E-10 1.77 E-10 5.19E-06 l

8A142 1.84E-07

1. 53E-10 9.06E-09 0.00E+00

8. 81 E-11 9.26E-11

7. 59 E-07 i

LA140 2.11E-08 8.32E-09 2.14E-09 0.00E+40 0.00E+00 0.00E+00 9.77E-05 LA142 1.10E-09 4.04E-10

9. 67 E-11 0. 00E+00 0.00E+00 0.00E+00 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 CE143

1. 4 8 E -08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 PR143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 PR144

2. 74 E -10 1.06E-10

1. 38E-11 0.00E +00

3. 84 E-11 0.00E+00 4.93E-06 ND147

5. 53 E -08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W187 9.03E-07 6.28E-07 2.17E-07 0.00Ee00 0.00EF00 0.00E+00

3. 69 E -05 NP239 1.11E-08 9.93E-10 5.61 E-10 0.00E &O0 1.98E-09 0.00E+00 2.87E-05

ODCM Page: 67 Rev.:

5 Table 3.2-14 Annual Usage Factors for the Maximum Exposed Individual Pathway Infant Child Teen Adult Fruits, vegetables &

grain (kg/yr)*

520 630 520 Leafy vegetables (kg/yr) 26 42 64 Milk (1/yr) 330 330 400 310 Meat & poultry (kg/yr) 41 65 110 3

Inhalation (m /yr) 1400 3700 8000 8000

• Consists of the following (on a mass basis):

22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.

Table 3.2-15 Annual Usage Factors for the Average Individual Pathway child Teen Adult Fruits, vegetribles, &

grain (kg/yr)*

200 240 190 Milk (1/yr) 170-200 110 Meat & poultry

. 95 (kg/yr) 37 59 3

Inhalation (m /yr) 3700 8000 8000

• Consists of the following (on a mass basis):

22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.

• • For total population and average individual dose calculations.

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ODCM Page:

69 Rev.: 5 3.3 Compliance With 10CFR50 Appendix I - Gaseous Effluent Dose i

Doses resulting from the release of noble gases, radioiodines, tritium and radionuclides in particulate form must be calculated to show compliance with Appendix I of 10CFR50. The calculations will j

be performed at least monthly for all gaseous effluents.

3.3.1 N ble Gases o

Section II.B.1 of Appendix I of 10CFR50 limits the releases of gaseous effluents from each reactor to unrestricted areas such.

that the estimated annual gamma air dose is limited to i

10 millirads and the b6ta air dose is limited to 20 millirads.

l l

The external dose pathway only will be considered for noble gases. The controlling location for the above stated dose limits is the site boundary location with the highest relative dispersion factor (x/Q) for the period of release.

l ODCM Appendix C controls limit the dose resulting from the l

release of noble gas radionuclides in gaseous effluents to the l-following:

a.

For gamma radiation, during any calendar quarter:

D s 5 mrads, air b.

For beta radiation, during any calendar quarter:

Sair s 10 mrads, c.

For gamma radiation, during any calendar year:

D s 10 mrads, air d.

For beta radiation, during any calendar year:

Eair s 20 mrads.

l l

l l

F i

i ODCM Page: 70 Rev.: 5 3.3.2 Radiciodines, Particulates, and Other Radionuclides L

Section II.C of Appendix I of 10CFR50 limits the annual release of radioiodines and radioactive materials in particulate form from each reactor such that estimated dose or dose commitment I

to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. The controlling location for this organ dose limit is the location of the highest relative dispersion (x/Q) or deposition (D/Q) l for the period of release, as well as the actual receptor j

pathway. Receptor pathway locations will be reviewed once per.

year following the performance of the Land Use Census to include consideration 6f nearest residences, garden, and farm j

aninal locations in each sector.

l ODCM Appendix C controls limit the dose resultant'from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days to the following:

l l

a.

During any calendar quarter:

Dose to Any Organ s 7.5 mrems b.

During any calendar year:

l Dose to Any Organ s 15 mrems.

3.3.3 Dose Calculations The following calculations are used to determine gamma and beta i

air doses resultant from noble gas release to areas at or beyond the site boundary for purpose of showing compliance with~

10CFR50, Appendix I.

The equations used to calculate organ doses resultant'from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than eight days are those found in Section 3.2.3.

Dose values are obtained by applying the dose rates over the appropriate surveillance or sampling time period.

l t

ODCM Page: 71 Rev.:

5 a.

Gamma Air Dose from Noble Gas Releases

{

7 1

7

'l Dair = (3.15) (10 ) (x/Q) ? (Q ) (DF )

i i

1 Where:

7 D**.

= the annual gamma air dose due to noble gas radionuclides, in mrad /yr; 7

DF

= the gama air dose factor for a ~ uniform g

semi-infinite cloud of radionuc Table'3.3-1,inmrad/sperCi/m}ide'i',from Q.

= the release rate of radionuclide 'i', in 1

pCi/s; 3

z/Q = the normal relative dispercion factor, in s/m (see Appendix A);

1 3.15 x 10 = the conversion factor to convert (mrad

• pCi)/(Ci

• s) to mrad /yr.

b.

Beta Air dose from Noble Gas Releases 0

p 1

Dair = (3.15 x 10 ) (x/Q) I (Qg) (DF )

g 1

Where:

0 D"l* = the annual beta air dose due to noble gas radionuclides, in mrad /yr; E

DF.

= the beta air dose factor for a uniform 1

semi-infinite cloud of radionuc Table 3.3-1,inmrad/sperCi/m}ide"i",from i

Q.

= the release rate of radionuclide 'i', in 1

l pCi/s; x/Q = the normal relative dispersion factor, in 3

s/m ; (see Appendix A);

1 3.15 x 10 = the conversion factor to convert

~

(mrad

• pCi)/(Ci

• s) to mrad /yr.

3.3.4 Cumulation of Doses The dose contribution from gaseous effluents will be calculated at least monthly. Calculations will be performed to determine the maximum air dose as well as the maximum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. To assure

ODCM Page: 72-Rev.: 5 compliance with 10CFR50, Appendix I, the dose limits for air dose and organ dose are those found in Sections 3.3.1 and 3.3.2, respectively. The quarterly limits specified in those sections represent one half of the annual design objectives.

If these limits are exceeded, a special report will be submitted to the NRC in accordance with ODCM Appendix C controls.

3.3.5 Projection of Doses Anticipated doses resulting from the release of gaseous effluents will be projected monthly. The doses calculated for the present month will:be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.

In this case the source term will be adjusted to reflect this information and the justifica-i tion for the adjustment noted.

l If the sum of the projected doses for the 31-day period exceeds O.3 mrem to any organ, appropriate portions of the ventilation exhaust treatment system will be operated to reduce releases.

The values for the projected dose impact levels correspond to about one forty-eighth of the Appendix I limits.

If continued for a year, these values would correspond to_less than i

one-fourth of the Appendix I limits.

3.4 Population Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for all radioactive gaseous effluent releases. The total population dose.and average individual dose will be computed, taking into account geographical population distribution and pathway (s) using the equations in Section 3.2.

However, the dose factors, DF differ; total population and averageindividualdosesare8kY8u,latedinamannersimilartothat used for maximum individuals except that Regulatory Guide 1.109, Revision' 1 assumptions for average individuals are used rather than for maximum exposed individuals and they are averaged over all age groups after weighting by the fraction of population in each age group.

l W

l.

i l

ODCM Page: 73 Rev.: 5 l

Table 3.3-1

(

Gamma and Beta Air Dose Factors for Semi-Infinite Plume 3

(mrad /s per Ci/m )

Gamma Air Beta Air-Dose Factor Dose Factor l

Nuclide (F)

(Dd)

I g

g Ar-41 2.95+2 1.04+2 Kr-83m 6.12-1 9.13+0 l

Kr-85m 3.90+1 6.24+1 Kr-85 5.45-1 6.18+1 Kr-87 1.96+2 3.27+2 Kr-88 4.82+2 9.29+1 Kr-89 5.48+2 3.36+2 Kr-90 5.14+2 2.48+2 Xe-131m 4.95+0 3.53+1 Xe-133m 1.04+1 4.69+1 Xe-133 1.12+1 3.33+1 Xe-135m 1.07+2 2.34+1 Xe-135 6.09+1 7.80+1 Xe-137 4.79+1 4.03+2 Xe-138 2.92+2 1.51+2 r

ODCM Page: 74 Rev.: 5 4.0 TOTAL DOSE 4.1 Compliance With 40CFR190 - Uranium Fuel Cycle Dose Annual dose contributions from liquid and gaseous effluent releases, as discussed in Sections 2.3.2 and 3.3.4, are summed to evaluate compliance with the 40CFR190 annual limit of 25 mrem total body or any organ (except the thyroid, which is 75 mrem).

PNPP does not intend to exceed 40CFR190 limits during normal' operation. However, if such a situation should occur, violations would be handled as per ODCM Appendix C Control 3/4.11.4a. which requires the following:

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a.

or 3.11.2.3b., calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded.

If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10CFR20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEHBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

This Special Report shall contain:

1.

A determination of which fuel cycle facilities or operations, in addition to the nuclear power reactor unit (s) at the site, contribute to the annual dose to the maximum exposed

~

individual. Nuclear fuel facilities over five miles from PNPP need not be considered in this determination.

2.

A determination of the maximum exposed individual.

ODCM Page: 75 Rev.: 5 3.

A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation using the methodologies described in this ODCM. Where additional information on pathways and nuclides is needed, the best available information will be used and documented.

Adeterminationofthedoseresultingfromdirechradiation 4.

from the plant and storage facilities.

The total body and organ doses resulting from liquid effluents from.

the PNPP will be sumed with the doses resulting from gaseous releases of noble gases, radioiodines, tritium, and particulates with half-lines greater than eight days when any of the dose limits outlined in Sections 2.3.2, 3.3.1 or 3.3.2 are exceeded by a factor of two. The doses from the PNPP will be summed with the dose to the maximum exposed individual contributed from other operations of the uranium fuel cycle.

e e mm 0

t t

ODCM~

Page: 76 Rev.: 5 4.2 Direct Radiation Dose from PNPP i

Potential direct radiation dose to individuals outside PNPP will arise from (a) skyshine and direct dose from the turbines, L

(b) direct dose from the external surfaces of' buildings, and (c) direct dose from stored radwaste.

Coolant activation by high energy neutrons, the 016 (n,p)N16 reaction, is of interest in boiling water reactors, like PNPP, i

because it can result in turbine skyshine and direct dose. The N-16 present in the steam of a direct cycle BWR is carried with the steam into the turbine moisture separators, and associated equipment.

Although N-16 has a 7.13 second half-life, its gamma emission can present a radiation dose problem to the site boundary as a result of i

l the high energy gamma scatter from structures and the atmosphere.

All external walls of buildings at PNPP have been designed to l

attenuate radiation sources from within the plant to maximum of l

0.5 mrem /h outside, with an expected radiation dose not to exceed 0.25 mrem /h.

j Projected direct radiation dose assessment for normal operations was performed, based on 80% load factor and 100% occupancy, for the l

closest site boundary location (WSW sector). Direct dose from l

turbine skyshine was calculated to be 1.3 mrem /yr and direct dose j

from the surface of buildings was calculated to be 2.2 E-3 mrem /yr.

Direct radiation doses at PNPP will be measured by self-contained dosimeters encircling the site located in the general area of the site boundary. These self-contained dosimeters will be of the thermoluminescent variety (TLDs) with analyses performed quarterly and annually.

i l-l l

ODCM 1

l i

Page: 77 Rev.: 5 l

4.3 Dose to Members of the Public While Onsite l

l ODCM Appendix C Control 6.9.1.7 requires " assessment of the i

radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary.' This assessment is included in Annual Radioactive Effluent Release Reporting.

A member of the public is defined in ODCM Appendix C to include l

anyone who is not occupationally associated with the plant, i.e.,

l not a utility employee, contractor or vendor. Also excluded from.

l this category is any person who enters the site to service equipment l

or make deliveries.

l Maximum dose to member of the public while onsite is conservatively assessed relative to offsite dose values. The assessment methodology incorporates use of appropriate dilution, dispersion, and occupancy factors for onsite activities.

The only liquid effluent dose pathway affecting members of the public while onsite is shore exposure.

Fishing on the Lake Erie shoreline is the assumed activity for this exposure. Onsite dose assessment is made via ratio to the maximum calculated offsite shore l

exposdre dose incorporating adjustments for occupancy factor and l

liquid effluent dilution.

Several cases.are considered for gaseous effluent dose assessment to member of the public while onsite including:

traversing a public road within the site boundary, lakeshore fishing, non-PNPP related training sessions at the Training and Education Center, car pooling to the Primary Access Control Point (PACP) parking lot, and job applicant interviews. This evaluation is made using ' relative z/Q' (atmospheric dispersion) values.

" Relative I/Q' values are the product of the highest annual average z/0 for the point of concern, l

and occupancy factor for the case. An adjustment factor is derived by ratioing this highest onsite ' relative z/Q' to the highest site boundary " relative z/Q'.

(A unity occupancy factor is used in the

~

determination of the highest site boundary " relative z/Q').

Conservative onsite dose determination is made by applying the

" relative I/Q" adjustment factor for the highest potential onsite dose activity to the highest calculated gaseous effluent offsite dose.

l i

j i

- - -. _ -.. -. -... -. - -... -. ~.

-. ~.

-. ~

d ODCM i

Page: 78 Rev.:

5 1

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3

i 5.1 Monitoring Program J

Environmental samples shall be collected and' analyzed according to Table 5.1-1 at locations shown in Figures 5.1-1, 5.1-2 and 5.1-3.

i The Radiological Environmental Monitoring Program (RENP) sample i

locations are controlled by REMP-0013. A list and figures of the j

specific locations are contained in the Master List of Sampling i

Locations in the REMP file. Analytical techniques used shall ensure that the detection capabilities in Table 5.1-3 are achieved.

1 i

Ground water sampling will not be conducted as part of PNPP's REMP l

because this source i.s not tapped for drinking or irrigation y

purposes in the area of the plant. The position of the plant and the underdrain system with respect to the hydraulic gradient is such that any leakage or overflow from the underdrain system will flow north towards Lake Erie.

Local domestic wells outside the exclusion i

area boundary are up-gradient from the plant. As part of the REMP,

(

samples will be routinely collected from the closest potable water intakes on Lake Erie.

The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent i

monitoring by verifying that the measurable concentrations of j

radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation-and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the' station operation. The initial radiological environmental monitoring program was conducted for the first three years of commercial operation; program changes may now be proposed based on operational experience.

cA l

1 PIC-1/VAX/Page 4 of 13

I occM Page:

79 Rev.:

5 l

5.2 Land Use Census Program A Land Use Census shall be conducted annually to identify, within a lcA distance of 8 km (5 miles), the location in each of the meteorglogicalcectorsojtheneagestresidence,thenearest garden greater than 50m (500 ft ) and the nearest milk-producing c,t animal.

If a Land Use Census identifies a location (s).that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at the location from which samples are currently being obtained the new location (s) will be added to the radiological.

environmental monitoring program within 30 days. The sampling l

location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

,g I

The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aetlal survey, general observations, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

I Broad leaf vegetation sampling of at least three different i

types of vegetation may be performed at the site boundary in j

each of two different sectors with the highest predicted D/Qs i

in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5.1-1 shall be followed, including l

analysis of control samples.

l l

l l

l l

l PIC-1/VAX/Page 5 of 13 l

ODCM Page:

80 Rev.: 5 5.3 Inter-Laboratory Comparison Program The laboratories of the licensee and/or licensee's contractors which perform analyses shall participate in an Interlaboratory Comparison Program which has been approved by the Commission. This participation shall include all of the determinations (sample v\\

medium-radionuclide combinations) that are included in the monitoring program. The results of analysis of these comparison samples shall be included in the Annual Radiological Environmental Operating Report.

If the results of a determination in the comparison crosscheck program are outside the spec ~ified control limits, the laboratory g

shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the Annual Radiological Environmental Operating Report.

PIC-1/VAX/Page 6 of 13 l

3o k

Table 5.1-1 M%

RADIOIOGICAL DNIR0tNENTAL MONFIORDG PROGRAM 8*

Number of Sanples Exposure Pathway and 0,,

and/or Sanole Sanole Locationgy)

Sangling and Type and Frequency Collection Frequency of Analysis 1.

Direction

'1%nty eight routine nonitoring Quarterly Cansna dose quarterly.

y Radiation I2I w

stations either with two or nore dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

- An inner ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NE, ISE, N, NW, W, C'I WNN), in the general area of the SITE BOUNDMtY; An outer ring of stations, one in each meteorological sector, other' than those sectors entirely over water (N, M, M, NW, W, hNN),

in the 6-to 8-km range fran the site; and

'Ihe balance of the stations to be placed in special interest areas

{

i such as population centers, nearby

,,o residences, schools, and in one or agR two areas to serve as control

, a M stations.

m co O

9

__a

Table 5.1-1 (Cont.)

RADIOIDGICAL DWIROM4 ENTAL M)NI'IORItB PROGRAM Number of Sanples Exposure Pathway and Sampling and Type and Frequency gy) and/or Sanole Sanole Iocation Collection Frequency of Analysis 2.

Airborne Radioiodine and Sanples frm five locations:

Continuous sanpler Radiciodine Canister:

Particulates operation with sanple I-131 analysis weekly

'Ihree sanples from close to collection weekly, or the three SITE BOUNDARY loca-nore frequently if tions, in different sectors, of required by dust Particulate Sanpler:

the highest calculated annual loading Gross beta radioactivity average ground-level D/Q; analysis following one sanple frm the vicinity filter change;I I and of a cormunity having the highest ganma isotopic analysis (4) calculated annual average ground-of cmposite (by location) level D/Q; and quarterly.

One sanple from a control location, as for exanple 15 to 30 kra distant and in the least prevalent wind direction.

3.

Waterborne

!?2'

.Eh a.

Surface

'No sanples Cmposite sanp1pr Gamna isotopic analysis, I 1-nonth period.

nonthly. Cmposite for tritium analysis quarterly.

mg 4

m 4

3o k

Table 5.1-1 (Cont.)

MN RADIOINICAL DWIRGMNTAL MON 1TRING PROGRAM a**

Number of Sanples Expocure Pathway and 0,,

and/or Sanple Sanole Imationgy)

Sanpling and Type and Frequency Collection Frequency of Analysis 3.

Waterborne (Continued) w b.

Drinking One sanple of each of one to three Canposite sample I-131 analysis on each tri of the nearest water supplies over 2-week period (5) conposite when the dose that could be affected by its d en I-131 analysis calculated fr m the consunption discharge.

.s performed; monthly of the water is y ter than G er m ite otherwise.

1 mrem per year.

Conposite One sanple frm a control for gross beta and p isotopic analysis g monthly.

location.

Conposite for tritium analysis quar.terly c.

Sediment One sample from area with existing Semiannually Gama isotopic analysis frm or potential recreational value.

shoreline semiannually.

4.

Ingestion a.

Milk Sanples frm milking animals in Semimonthly when Gama isotopic and I-131 II three locations within Skm distance animals are on pasture; analysis seminathly when animals having the highest dose potential.

Monthly at other times. are on pasture; nonthly at other If there are none, then one sanple times.

fran milking animals in each of three areas between 5 to 8 km distantwheredosesarecalculateq6)

.o.o o 0E

.

• h to be greater than 1 mrem per yr.

One sanple from milking animals at a control location 15 to 30 km distant and in the least prevalent wind ui$

direction.

4 g

d

Table 5.1-1 (Con *. ;

RADIOIOGICAL ENVIRCNENTAL MONI'KRIfG PROGRAM Number of Sanples Exposure Pathway and Sangling and Type and Frequency and/or Sanple Sanole location (1)

Collection Frequency of Analysis 4.

Ingestion (Continued)

II b.

Fish and On sanple of each connercially Sanple in season, or Ganna isotopic analysis Inverte-and recreationally inportant semiannually if they en edible portions.

brates species in vicinity of plant are not seasonal.

discharge area.

One sanple of same species in areas not influenced by plant discharge.

I4I c.

Food Sanples of three different kinds

}t>nthly during Ganna isotcpic and I-131 prcducts of broad leaf vegetation grown growing season.

analysis, nearest to each of two different offsite locations of highest predicted annual average ground level D/Q if milk sanpling is not performed.

I4I One sanple of each of the similar Monthly during Ganna isotopic and I-131 broad leaf vegetation grown growing season.

analysis.

15 to 30 km distant in the least prevalent wind direction if milk E7 sanpling is not performed.

4%..h F

ODCM Page:

85 Rev.:

5 Table 5.1-1 (Cont.)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table Notations (1)

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment.

If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to <0DCM l

Appendix C Control 6.9.1.6>.

It is recognized that, at times, it may may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made with in the thirty days.

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thennoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

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

gamma isotopic analysis shall be performed on the individual

~ gg samples.

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

(5) A composite. sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquotr shall be collected at time intervals that are very short (e.g., hocrly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(6) The dose shall be calculated for the maximum organ and age groop, using the methodology and parameters within this manual.

PIC-l/VAX/Page 9 of 13

Table 5.1-2 Reporting Levels for Radioactivity Concentrations in Envirornnental 9@les MTER AIRBORNEPARTICgTE FISH MILK FOOD PRODUCTS MALYSIS (pCi/l)

OR GSES (pCi/m )

(pCi/kg, wet)

(pCi/l)

(pCi/kg, wet)

H-3 2 x 10 (a) 4 3

4 Mn-54 1 x 10 3 x 10 2

4 Fe-59 4 x 10 1 x 10 3

4 Co-58 1 x 10 3 x 10 2

4 Co-60 3 x 10 1 x 10 2

4 Zn-65 3 x 10 2 x 1G 2

Zr-Nb-95 4 x 10 0

-1 0

2 I-131 2 x 10 9 x 10 3 x 10 1 x 10 1

1 3

1 3

Cs-134 3 x 10 1 x 10 1 x 10 6 x 10 1 x 10 1

1 3

1 3

Cs-137 5 x 10 2 x 10 2 x 10 7 x 10 2 x 10 o

{gl 2

2 Ba-La-140 2 x 10 3 x 10 (a) For drinking water sanples. 'Ihe value given is the 40CFR141 value.

. - ~...

. s

m E3 k

Table 5.1-3 b

Detection rannhilities for Divironmental Sanple Analysis and (a) W j

Lower Limit of Detection (LLD)

E 5

WATER AIRBORNEPARTICg/m)

TE FISH MILK FOOD PRODUCIS SEDDENT 0

ANALYSIS (c)

(pCi/1)

OR GASES (pCi (pCi/kg, wet)

(pCi/l)

(pCi/kg, wet)

(pCi/kg, dry) m 0

0

-2 Gross Beta

-4 x 10 1 x 10 H-3 2 x 10 (d) 3 1

2

!!n-54 1.5 x 10 1.3 x 10 1

2 Fe-59 3 x 10 2.6 x 10 1

2 Co-58, 60 1.5 x 10 1.3 x 10 1

2 Zn-65 3 x 10 2.6 x 10 1

Nb-95 1.5 x 10 1

Zr-95 3 x 10 I-131 1 x 10 (e) 7 x 10 1 x 10 6 x 10 0

-2 0

1 1

-2 2

1 1

2 Cs-134 1.5 x 10 5 x 10 1.3 x 10 1.5 x 10 6 x 10 1.5 x 10 1

-2 2

1 1

1.8x10gg 2

t,A l Cs-137 1.8 x 10 6 x 10 1.5 x 10 1.8 x 10 8 x 10 1

1-Ba-140 6 x 10 6 x 10 1

1 La-140 1.5 x 10 1.5 x 10 t

8

Table 5.1-3 (Cont.)

Table Notations aRequired detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the rea-- -htions of Regulatory Guide 4.13, except for specification regarding energy dependence.

Correction factors shall be provided for energy ranges not meeting the energy dependence specification.

b methodology for determining the LLD is contained in Appen('ix B.

c,Ihis list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.

For these radionuclides in ODW Appendix C Table 4.12-1 which are not detected, the typical LLDs for the measurement system will be separately reported in the annual report.

d 3

If no drinking water pathway exists, a value of 3 x 10 pCi/1 my be used.

i e

1 lf no drinking water pathway exists, a value of 1.5 x 10 pCi/1 may be used.

WE FW$

3o NNW N

NNE 2

NW i

NE LEGEND:

k STATION NO.

MEDIA DIRECTION m

E 3

TLD SE co s

4 AIR, TLD S

/

o 5

TLD SW n

WNW ENE 7

AIR, TLD NE 5

Lockwooo

'3 n 34 8

TLD E

~

PERR NUCLEAR

.,58k 62 9

TLD ESE POW R PLAN X;

b'I 10 TLD SSE W

2 MILES 1 MILE 30' E

e 1

e 77 12 g

i 11 TLD SSW 5'

12 TLD WSW y

• 4

=

E.

11'

[

Nqrth* Pe rry 25 SED,FSH NNW 20 r"~

10. Y llag WSW

/,

(

~3 ESE 34 WTR NW A

4 ali 35 AIR, TLD E

)

g fa L

ggc61 a

g g

j

\\

53 TLD WSW f.

<I b

58 TLD ENE l

g

=

iii 20

{

g 62 FP ENE SW 6

"__o.

SE 77 pp g

SSW S

SSE wmo 1

0 1

2 MILES

. e

=e:

TECHNICAL SPECIFICATION REQUIRED REMP SAMPLING LOCATIONS WITHIN TWO MILES OF THE PLANT SITE 8

l l

hd NNW N

NNE NE LEGEND:

8 MILES STATION NO.

MEDIA DIRECTION 7

l 1

AIR, TLD ENE e

13 TLD ENE 14 TLD E

' 15 TLD ESE WNW 4

ENE 21 TLD wsW 23 TLD WSW 8

k'~

29 TLD SSE I

l 30 TLD SSW l

(

3 I-3 M

31 TLD SE

(

/

6?\\

g{

g6 33 TLD S

7...

1**

j b

~

36 WATER, TLD WSW g

d e

(~7 5

/

}

54 TLD SW

[

~

15.

6 ESE 2

y, 23

.w g

7 g

/

3..]N n

9

'/,E

,. ~ '

'o 3

ESE T

• - 33 WSW

.~

-y

,}

\\_

w

/

i i

0..

i 3

m.,

t

/ L }'g

%V. 4 W

7 1

s,

SW SSW S

SSE SE wmo I

0 1

2 3

,4 5

10 MILES S

ung TECHNICAL SPECIFICATION REQUIRED REMP l

SAMPLING LOCATIONS BETWEEN TWO AND EIGHT MILES FROM THE PLANT SITE.

t

t nn im =

WNW ENE con,,

28 i

tabut Geneva /

07' LAKE E E

ft f,,,,

1 go.

Mad, son de etions on-he-Lak,f i

q f

Saybroo Per di Ae m (s) 2 3 W

Mi eS iunion-E

=

ii 8

M, e a 4e Gid

/

vent!r,,

2 ninr "3

"f in s=

t+La y 1[

[,

TV,gs,, lh"'

N t-'

s "2

if

,1,

p-

,, L,;,

a wmuc f

"8 Y 8

• " l'

-/

O' t"n ESE L

a h

t O

WSW Eucli,W 70

"H'"

4.,,,,N

's.re.,r n,.

Kirtland 4mmaa (Igh b

y Dodge-1Wil.ou b e

Chard h

@ Wim A

WD.

46 Brate r

is Eut I

s 4

8nd

'Msyfield G :

Fewte h

'ia'd ciriaen t _ i w;ng

.Drwett g i Q-Eucljd Hgts.

Hs un surf g

iren.

A \\c0,stq"'

GE GA

\\

y,,,,[

)

t,%,

SW SSW S

SSE SE

,,o co w 5

0 5

10 15 20 MILES h

M LEGEND:

STATION NO.

MEDIA DIRECTION 1/8" = 1 MILE

[

• 0 6

AIR, TLD SSW 24 TLD

,8 SW 28 WATER ENE 32 FISH WSW TECHNICAL SPECIFICATION REQUIRED 70 FP SSW REMP SAMPLING LOCATIONS GREATER THAN EIGHT MILES FROM THE PLANT SITE

l oocs Page:

92 Rev.:

5 l

i l

Appendix A Atmospheric Dispersion and Deposition Parameters 1

l

i ODCM i

Page: 93 Rev.: 5 The atmospheric dispersion and deposition parameters used to calculate gaseous effluent doses will be calculated using the following equations.

Dose calculations will be performed using meteorological conditions concurrent with the time of release of-radioactive materials in gaseous pg effluents or using historical average atmospheric conditions. All.

atmospheric releases at PNPP are considered to be ground-level releases, a.

Constant Mean Wind Direction Relative Dispersion Factor

[

(2.32) (T )

g /Q =

g gg,1)

(6) (x) (o)

Where:

r/0

= the relative dispersion factor at ground level, in 3

s/m ;

T

= the terrain correction factor, from FSAR Table 2.3-26, g

dimensionless; 6

= the wind speed (measured at 10m), in m/s; x

= the distance of calculation, in m; 2.032 = (2/N) N divided by the width in radians of a 22.50 sector 2

2 H

H

+

or (o 3) (3 N) c a = the lesser of a,

2N Where:

H = the building height (44.8m);

e a = the vertical dispersion coefficient, per Regulatory z

Guide 1.111, in m.

b.

Depleted Relative Dispersion Factor x/Qd = (x/Q)(DPL )

(A-2) j Where:

d = halogens and particulates),thedepletedrelativedispersionfgetor(fo I/Q in s/m ;

PIC-1/VAX/Page 12 of 13

ODCH l

Page:

94 Rev.:

5 i

DPL. = the ground depletion factor for the 'j'th distance, J

interpolated from Table A-1, dimensionless; e

z/Q = the relative dispersion factor, per equation A-1.

i c.

Ground Deposition (DEP )(T )

3 g

D/Q =

(A-3) j (0.3927) (x)

Where:

i D/0 l

=therelativedepositiongerunitarea(forhalogens and particulates), in m~ ;

j DEP.

=thegrounddepositionfactorfortge"j'thdistance, 3

j interpolated from Table A-1, in m' ;

i 4

T

= terrain correction factor, from FSAR Table 2.3-26, g

dimensionless; x

= the "j'th distance, in m; 1

0.3927 = radians per 22.50 sector D6

L r

Table A-1 L usderic Depletion and Deposition Factors i

Pasquill Distance (meters)

Stability Class 200 500 1,000 2,000 3,000 6,000 10,000 30,000 50,000 80,000 Depletion Factors (DPL )

All 0.970 0.936 0.900 0.860 0.832 0.770 0.714 0.590 0.517 0.440 j

Deposition Factors (DEP )(m~ ) All 1.25E-4 8.0E-5 5.4E-5 3.2E-5 2.6E-5 1.5E-5 9.9E-6 4.5E-6 3.0E-6 2.0E-6 3

[

t if 2

$W$

i I

l

~

ODCM Page: 96 Rev.:

5 The following tables contain annual average atmospheric dispersion and deposition parameters for long-term releases at PNPP.

Long-term releases are those that occur greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year. The highest annual average relative concentration (z/Q) value at the site boundary for sectors over land shall be used for radioactive gaseous effluent monitor setpoint calculations. The dispersion model used was X00D00, with PNPP FSAR site-specific terrain adjustment factors included. Dispersion values are based on seven years of meteorological data (May 1, 1972 through April 30, 1974 and September 1, 1977 through August 31, 1982),

ground-level releases, sector spread for purge calculations, and twelve wind speed classes.

ODCM Page: 97 Rev.:

5 Table A-2 Site Boundary Atmospheric Dispersion (r/0) and Deposition Parameters (D/Q) for PNPP Unit 1 SECTOR DISTANCE X/0

- D/0 (N!LES)

(SEC./.CUS. METER 3 (PER SG.METERI N

O.18 5.7E-05" 1.6E NNE O.25 1.BE-05' 7.9E-08

~ NE O.42 5.BE-06 3.1E-OS ENE O.67 2.1E-06 1.6E-08 E

O.67 2.2E-06 1.BE-OB ESE O.67 1.6E-06 1.3E-OB SE' O.79

'1.4E-06 1.1E-OB SSE O.82 2.2E-06 1.4E-08 l

S 0.81 2.7E-06 1.6E-OB SSW O.80 1.3E-06 6.BE-09 SW O.65 2.3E-06 1.1E-08 WSW O. 56 4.2E-06 1.5E-OB W

O.27 2.5E-05 4.6E-OB WNW O.18

5. 9E 8.4E-OB NW

NNW, O.17 6.6E-05

~ 1.1E-07 O.17 5.9E-05 1.2E-07 4

I 4.

ODCM Page:

98 Rev.: 5 b ble A-3 Atmospheric Dispersion (r/0) as a Function of Distance (s/m )

SECTOR O. 2

0. 3 O. 4

0. 5

0. 6 (MILES)

(MILES)

(MILES)

(MILES)

(M.ILES)

N

4. 904E-05 2. 453E-05 1. 525E-05 1. 057E-05 7. 918E-06 NNE

2. 656E-05 1. 360E-05 B. 640E-06 6. OS2E-06 4. 612E-06 NE

1. 859E-05 9. 760E-06 6. 293E-06 4. 460E-06 3. 383E-06 ENE

1. 327E-OS 7.129E-06 4. 636E-06 3. 293E-06 2. 490E-06 E

1. 363E-05 7. 362E-06 4. 760E-06 3. 367E-06 2. 53G;'-06 ESE

1. 025E-05 5. 566E-06 3. 602E-06 2. 547E-06 1. 916E-06 1.113E-05 6. 061E-06 '. 935E-06 2. 788E-06' 2.100E-06 I

'SE J

SSE

1. 894E-05 1. 022E-05 6. 647E-06 4. 718E-06 3. 560E-06 !

i S

2. 2BSE-05 1. 227E-05 7. 932E-06 5. 615E-06 4. 238E-06 !

SSW 1.142E-05 6.079E-06 3.925E-06 2.777E-06 2.097E-06 l SW

1. 449E-05 7. 663E-06 4. 920E-06 3. 479E-06 2. 622E-06 WSW 2.151E-05 1.111E-05 7. 031E-06 4. 934E-06 3. 733E-06 W

4.184E-05 2. 081E-05 1. 281E-05 8. 87JE-06 6. 606E-06 WNW

4. 669E-05 2. 298E-05 1. 401E-05 9. 573E-06 7. 093E-06

)

NW

4. 90SE-05 2. 423E-05 1. 482E-05 1. 015E-05 7. 521E-06 NNW

4. SBOE-05 2. 266E-05 1. 390E-05 9. 541E-06 7. 083E-06 j

SECTOR O. 7 O. 8 O. 9

1. O 1.1 (MILES)

(MILES)

(MILES)

(MILES)

(MILES) i N

6.13BE-06 4. 96BE-06 4. 203E-06 3, 636E-06"1. 949E-06 '.i NNE

3. 622E-06 2. 947E-06 2. 481E-06 2.132E-06 1. 27BE-06,

NE

2. 662E-06 2.165E-06 1. B15E-06 1. 552E-06 9. 269E-07 ENE

~ 1. 957E-06 1,. DBSE-06 1. 325E-06 1.129E-06 6. 710E-07 E

1.991E-06 1.613E-06 1.343E-06 1.141E-06 6.7hBE-07 ESE

1. SO1E-06 1. 215E-06 1. 010E-06 8. 571E-07 5. ' OBOE-07 SE

1. 647E-06 1. 334E-06 1.10BE-06 9. 402E-07 4. 456E-07 i

SSE

2. 796E-06 2. 266E-06 1. 885E-06 1. 601E-06 5; 524E-07 S

3. 327E-06 2. 697E-06 2. 247E-06 1. 911E-06 7. 340E,07 SSW

1. 646E-06 1. 335E-06 1.114E-06 9. 486E-07 5. 223E-07 SW

2. 053E-06 1. 664E-06 1. 391E-06 1.188E-06 5. 667E-07 WSW

2. 927E-06 2. 300E-06 2. OO2E-06 1. 719E-06 8. 671 E-07 '

W 5.110E-06 4.135E-06 3. SO4E-06 3. 036E-06 1. 630E-06 WNW

3. 434E-06 4. 378E-06 3. 719E-06 3. 235E-06 1. 845E-06 NW 5,764E-06 4.643E-OS 3.941E-06 3.425E-06 1.952E-06 NNW

3. 439E-06 4. 385E-06 3. 720E-06 3. 230E-06 1.839E-06!

i j

ODCM Page:

99 l

Rev.:

5 1

Table A-3 (Cont.)

t Atmospheric Dispersion (i/0) as a Function of Distance (s/m )

1. 2

1. 3

1. 4

1. 5

1. 6

'; SECTOR (MILES)

(MILES)

(MILES)

(MILES)

(MILES)

'N

1. 729E-06 1. 54'9E-06 1. 399E-06 1. 273E-06 1.166E-06 i

NNE 1.128E-06 1. OO6E -06 9. 05DE-07 8. 202E-07 7. 485E-07

~

NE 8.150E-07 7. 243E-07 6. 494E-07 5. 867E-07 5. 340E-07 ENE

5. 878E-07 5.*205E-07 4. 652E-07 4.190E-07 3. 803E-07 E

5. 917E-07 5. 230E-07 4. 667E-07 4.197E-07 3. BO4E-07 ESE

4. 437E-07 3. 919E-07 3. 494E-07 3.140E-07 2. 843E-07 SE 3/W91E-07 3. 436E-07 3. 062E-07 2. 751E-07 4. 491E-07 SSE

4. 829E-07 4. 267E-07 3. 807E-07 3. 423E-07 3.102E-07 5

6.424E-07 5.684E-07 5.076E-07 4.569E-07 4.145E-07 SSW

4. 576E-07 4. 054E-07 3. 624E-07 3. 266E-07 2. 965E-07 SW

4. 976E-07 4. 417E-07 3. 955E-07 3. 570E-07 3. 246E-07 WSW

7. 64BE-07 6. 814E-07 6.125E-07 5. 547E-07 5. 060E-07 W

1. 44SE-06.1. 299E-06 1.175E-06 1. 070E-06 9. 809E-07 WNW

1. 644E-06 1. 479E-06 1. 341E-06 1. 274E-06 1.124E-06 NW

1. 73SE-06 1. 563E-06 1. 416E-06 1. 292E-06 1.186E-06 NNW

1. 637E-06 1. 471E-06 1. 332E-06 1. 2214E-06 1.115E-06 l

l SECTOR

1. 7

1. 8

1. 9

2. O 2.1

' MILES).

(MILES)

(MILES)

(MILES)

(MILES)

(

N

1. 074E-06 9. 931E-07 9. 226E-07 8. 604E-07 '8. 052E-07 NNE

6. 867E-07 6'. 331E-07. 5. 864E-07 5. 453E-07 5. 090E-07 NE 4, 886E-07 ai. 494E-07 4.153E-07 3. 854E-07 3. 263E-07 ~

ENE

3. 471E-07 3.184E-07 2. 936E-07 2. 718E-07 2. 526E-07 E

3. 467E-07 3. 277E-07' 2. 925E-07 2. 705E-07 2. 283E-07 ESE

2. 590E-07 2. 37 ! E-07 2.182E-07 2. 017E-07 1. 871E-07 SE

2. 268E-07 2. 076E- 07.1. 910E-07 1. 765E-07 1. 637E-07 SSE

2. 827E-07 2. 590E-07 P 384E-07 2. 205E-07 1. 407E-07 5

3.* 780E-07 3. 466E-07 3.194E-07 2. 955E-07 1. 373E-07 SSW

2. 706E-07 2. 4 94E-07 ~2. 290E-07 2.121E-07 1. 409E-07 SW

2. 968E-07 2. 727E-07 2. 518E-07 2. 335E-07 2.173E-07 WSW

4. 639E-07 4. 275E-07 3. 957E-07 3. 678E-07 5. 303E-07 W

9. 037E-07 8. 365E-07 7. 777E-07 7. 258E-07 1. 050E-06 WNW 1.038E-06 9.622E-07 8.960E-07 8.375E-07 1.142E-06 NW 1.095E-06 1.015E-06 9.445E-07 8.826E-07 8.275E-07 NNu

1. 028E-06 9. 527E-07 8. 865E-07 B. 281E-07 7. 761E-0,7

ODCM Page:

100 Rev.: 5 Table A-3 (Cont.)

Atmospheric Dispersion (r/0) as a Function of Distance (s/m )

SECTOR,

2. 2

2. 3 '.

2. 4

2. 5

2. 6 (MILES)

(MILES)

(MILES)

(MILES)

(MILES)

'N

7. 560E-07 7.118E-07 6. 720E-07 6. 359E-07 6; 033E-07 NNE 4, 766E-07 4. 477E-07 4. 2'17E-07 3. 982E-07 3. 770E-07 NF

3. 050E-07 2. 859E-07 2. 688E-07 2. 534ErO7 2. 395E-07 ENE

2. 356E-07 2~ 20SE-07. 2. 069E-07 1. 947E-07 1. 837E-07 E

2.127E-07 1. 988E-07 1. 864E-07 1. 752E-07 1. 652E-07 ESE

1. 743E-07 1. 628E.07 1. 525E-07 1. 433E-07 1. 351E-07 SE

1. 324E-07 1. 424E-07 1. 334E-07 1. 253E-07 1.181E-07 SSE'

1. 311E-07 1. 225E-07 1.149E-07 1. 080E'-07 1. 018E-07

~

5 1.200E-07 1.197E-07 1.123E-07 1.056E-07 9.963E-08

'SSW

1. 314E-07 1. 230E-07 1.154E-07 1. 087E-07 1. 025E-07 SW

2. 030E-07 1. 902E-07 1. 787E-07 1. 683E-07 1. 390E-07 kSW

4. 964E-07 '4. 651E-07 4. 388E-07 4.142E-07 3. 920E-07 W

9. 867E-07 9. 296E-0.7 8. 780E-07 8. 313E-07 7. 891E-07 WIM

1. 075E-06 1. 014E-06 9. 387E-07 9. 088E-07 8. 636E-07 NW

7. 782E-07 7. 339E-07 6. 939E-07 6. 576E-07 6. 247E-07 NTM

7. 297E-07 6. 879E-07 6. 502E-07 6.161E-07 5. 852E-07 SECTOR

2. 7

2. 8

2. 9

3. O '

3.1 (MILES)

(MILES)

(MILES)

(MILES 3 (MILES 3*

~

N 5.734E-07 5.460E-07 5.208E-07 4.976E-07 4.762E-07 NNE Q. 576E-07 3,398E-07 3. 235E-07 3. 086E-97 2. 948EE-07 NE

2. 268E-07 2.152E-07 2. 046E-07 1. 949E-07 1. 859E ENE 1.737E-07 1.645E-07 1.562E-07 1.485E-07 1.415E-0.7 :

E,

1. 560E-07 1. 477E-07 1. 401E-07 1. 331E-07 1. 267E-07; ~

ESE 1.275E-07 1.207E-07 1.144E-07 1.087E-07 9.399E-08 SE 1.115E-07 1.054E-07 9.996E-08 9.493E-08 9.031E-082.s SSE 9.613E-08 9.099E-08 8.630E-OB 8.2OOE-OB 7.805E-08 S

9. 415E-08 8. 917E-08 8. 462E-08 8. 044E-08 7. 661E-08..

SSH

9. 697E-08 9.189E-08 8. 725E-08 8. 299E-08 7. 907E-08 SW

1. 505E-07 1. 428E-07 1. 357E-07 1. 291E-07 1. 231E-07 WSW 3.716E-07 3.331E-07 3.360E-07 3.204E-07 2.520E-07 W

7. 503E-07 7.147E-07 6. 820E-07 6. 519E-07 5. 874E-07 WNW O. 220E-07 7. B38E-07 7. 487E-07 7.164E-07 7. 722E-07 NW

5. 945E-07 5. 66BE-07 5. 413E-07 5.17.8E-07 5. 412E-07 NNW 3.567E-07 5.307E-07 5.067E-07 4.046E-07 4.642E-07

.~. - -

I ODcx

]

Page:

101 Rev.:

5 i

Table A-3 (Cont.)

i l

Atmospheric Dispersion (r/0) as a Function of Distance (s/m )

i l

1

]

8EC1h1

3. 4

3. 5

3. 6

3. 2

3. 3 l

(MILES)

(MILES)

(MILES)

(MILES)

(MILES) l j

H

4. 563E-07 4. 379E-07 4. 208E-07 4. 047E-07 3. 899E-07 i

Ni4E I. 820E-07 2. 702E-07 2. 592E-07 2. 489E-07 2. 395E-07 i

NE 1.77'7E-07,1.700E-07 1.629E-07 1.562E-07 1.501E-07 i

Et4E

1. 350E-07 1. 290E-07 1. 234E-07 1.182E-07 1.135E-07 4

E

1. 208E-07 1.154E-07 1.103E-07 1. 056E-07.1. 013E-07

.ESE

8. 958E-08. 8. 550E-08 8.173E-08 7. 821E-08. 7. 499E-08 i

SE B. 60&E -08' 8. 213E-08 7. 849E-08 7. 510E-08 7. 200E-08 i

SSE

7. 441E-08 7.105E-08 6. 794E-08 6. 503E-08 6. 237E-08 i

i S

7. 307E-08 6. 980E-08 6. 678E-08 6. 395E-08 6.136E-08 SSW

7. 546E-08 7. 212E-08 6. 902E-08 6. 613E- 08 6. 348E-08 i

SW 1.176E-07 1.125E-07 1. 077E-07 1. 033E-07 9. 922E-OB i

WSW

2. 410E-07 2. 308E-07 2. 214E-07 2.125E-07 2. 044E-07 4

W

5. 631E-07 5. 406E-07 5.'196E-07 4. 999E-07 4. 818E-07 j

Wr4W 7.'409E-07 7.118E-07 6: 84BE-07 6. 593E-07 6. 359E-07 i

!M 5.192E-07 4. 987E-07 4. 797E-07 4. 618E-07 4. 454E-07 NNW

4. 452E-07 4. 276E-07 4.112E-07 3. 958E-07 3. 817E-07 I

i 5

(

i f

SECTOR

3. 7

3. 8

3. 9

4. 0 (MILES)

(MILES)

(MILES)

(MILES)

(MICES) 4 i

N

3. 759E-07 3. 628E-07 3. 504E-07 3. 388E-07 b981E'-07' 4

i NNE.

2. 306E-07 2. 222E-07 2.144E-07 2. 670E-07 1. 819E-07 i

NE

1. 444E-07 1. 390E-07 1. 339E-07 1. 292E-07 1. 247E-07 ENE

1. 090E-07 1. 048E-07 1. OO9E-07 9. 718E-08 9. 373E-08 E

9. 722E-08 9. 342E-OB B. 987E-08 8. 653E-08 8. 341E-08 ESE 7.196E-08 6. 912E-08 6. 647E-08.6. 399E-08 6.166E-08 li SE

6. 90BC-08 6. 635E-08 6. 380E-08. 6.1A0E-08 5. 378E-08 SSE

5. 987E-08 5. 753E-08 5. 533E-08 5. 328E-08 5.135E-08 1

1 S

5. 692E-08 5. 664E-08 5. 451E-08 5. 251E-08 5. 063E-08

{

SSW

6. 098E-08 5. 865E-08 5. 646E,-08 5. 441E-08 5. 24BE-08 SW

9. 537E-08 9.178E-08 8. 841E-08 8. 525E-08 8. 228E-08 i

WSW

1. 967E-07 1. 896E-07 1. 828E-07' t. 765E-07 1. 462E-07 W

4. 646E-07 4. 485E-07 4. 334E-07 4.191E-07 3. 043E-07

{

Wre '

6.137E-07 5. 929E-07 5. 733E-07 5. 548E-07 4.1BOE-07 j

NW

4. 298E-07 4.153 E-07 4. 013E-07 3. 883E-07 3. 761E-07 j

NNN

3. 682E-07 3. 556E-07 3. 438E-07 3. 326E-07 2. 928E-07 i

i i

ODCM Page:

102 Rev.: 5 Table A-3 (Cont.)

Atmospheric Dispersion (r/0) as a Function of Distance (s/m )

SECmR

4. 2 v

4. 3

4. 4

4. 5

4. 6 (MILES)

(MILES)

(MILES)

(MILESF (MILES)

~

N 2.887E-07 2.798E-07 2.714E-07 2.634E-07 2.559E-07 NNE 1.759E-07 1.703E-07 1.650E-07 1.599E-07 1.552E-07'- '

NE 1.205E-07.1.166E-07 1.128E-07 1.093E-07 1.059E-07 ENE 9.047E-08 8.740E-OB B.451E-08 8.176E-08 7.921E-08 E

8.046E-08 7.769E-OS 7.508E-08 7.260E-08 7.030E-08 ESE

5. 946E-08 5. 740E-08 5. 545E-OB 5. 361E-08' 5.189E-08 SE 5.186E-08 5.OOSE-OB 4.835E-OS 4.'673E-OB 4.523E-OB SSE 4.954E-08 4.783E-OS 4.622E-OS 4.469E-08'4.327E-08 S

4.886E-08 4.719E-OB~4.562E-OS 4.413E-08 4.274E-08 SSW

5. 067E-08 4. 896E-08 4. 735E-08 4. 581E-08 4. 439E-08 SN 7.94SE-08 7.684E-OB'7.435E-08 7.198E-08 6.978E-OB WSW 1.413E-07 1.368E-07 1.325E-07 1.284E-07 1.246E-07 W

2. 948E-07 2. 858E-07 2. 773E-07 2. 691E-07 2. 616E-07 WNW 4.051E-07 3.930E-07 3.815E-07 3.706E-07 3.603E-07 NW

3. 645E-07 3. 536E-07 3. 432E-07 3. 333E-07 3. 241E-07 NNW 2.837E-07 2.752E-07 2.671E-07 2.593E-07 2.521E-07 SECTOR-4, 7 4, 8

4. 9

5. O (MILES)

(MILES)

(MILES)

(MILES)

N 2.487E-07 2.419E-07 2.354E-07 2.292E-07, NNE

1. 507E-07 1. 464E-07 1. 423E-07 1. 384E F NE

1. 02SE-07 9. 975E-OB 9. 689E-08 9. 416E-08 I

ENE

7. 676E-08 7. 443E-08 7. 223E-OB 7. 014E-08 i

E

6. 809E-08 6. 600E-OB 6. 402E-OB 6. 214E-08 ESE

5. 025E-08 4. 869E-08 4. 722E-OB 4. 582E-08 SE

4. 379E-08 4. 244E-OB 4.115E-OS 3. 992E-OB SSE 4.191E-08 4. 063E-08 3. 941E-OB 3. 825E-08 5

4.141E-OS 4. 015E-OB 3. 896E-OB 3. 782E-08 SSW

4. 302E-08 4.173E-OB 4. 050E-OB 3. 934E-08 SM b.767E-08 6.567E-OB 6.377E-OB 6.196E-OB WSU 1.210E-07 1.175E-07 1.142E-07 1.110E-07 W

2. 543E-07 2. 474E-07 2. 408E-07 2. 345E-07 WNW

3. 505E-07 3. 411E-07 3. 322E-07 3. 237E-07 NW 3.152E-07 3.06BE-07 2.987E-07 2.910E-07 NNW 2 452E-07 2 336E-07 2. 323E-07 2. 263E-07

ODCM Page:

103 Rev.:

5 Table A-4 Atmospheric Dispersion (D/0) as a Function of Distance (m )

~

SECTOR ~

0. 2

0. 3

0. 4

0. 5

0. 6

, MILES)

(

(MILES)

(MILES)

(MILES)

(MILES)

N

1. 396E-07 ' 7. 578E-08 4. 836E-08, 3. 383E-08 2. 516E-08

~

NNE 1.107E-07 6. 000E-08 3. 834E-08 2. 682E-08 1. 995E-08 NE

9. 733E-08 5. 284E-08 3. 372E-08 2. 359E-08 1. 755E-08

1. 067E-07 5. 795E-08 3. 698E-08 2. 587E-08 1. 924E-08 1

ENE E

1.194E-07 6. 429E-08 4.103E-08 2. 870E-08 2.135E-08 ESE

8. 865E-08 4. 813E-08 3. 071E-08 2.149E-08 1. 598E-08 SE

9. 402E-08 5.105E-08 3. 258E-08 2. 279E-08 1. 695E-08 SSE 1.338E-07 7.266E-08 4.637E-08 3.244E-08 2.413E-08 S

1.429E-07 7.757E-08 4.951E-08 3.463E-08 2.576E-08 SSW 6.094E-08 3.309E-08 2.111E-08 1.477E-08 1.099E-08 SW

7. 267E-08 3. 945E-OB 2. 518E-08 1. 761E-08 1. 310E-08 WSW 7.117E-08 3. 864E-08 2. 466E-08 1. 725E-08 1. 283E-08 H

7.129E-08 3. 870E-08 2. 470E-08 1. 728,E-08 1. 285E-08 WNW 6.970E-08 3.784E-08 2.415E-08 1.689E-08 1.256E-06 NW 8 904E-08 4.834E-08 3.085E-08 2.'15BE-08 1.605E-08 NNW 9.623E-08 5.225E-08 3.334E-08 2.332,E-08 1.735E-08 SECTOR

0. 7

0. B

0. 9

1. 0 1.1 (MILES)

(MILES)

(MILES)

(MILES)

(MILES)

E' N

1. 954E-08 1. 560E-Oe 1. 277E-08 1. 068E-08. 3. 545' -09 NNE

1. 549E-08 1 237E-08 1. 013E-08 8. 465E-09 4. 945E-09. -

NE

1. 362E-08 1. 08BE-08 8. 907E-09 7. 445E-09 4. 350E-09 ENE 1,494E-08 1.193E-08 9.768E-09 8.164E-09 4.770E-09 E

1. 65BE-08 1. 323E-08 1. 084E-08 9. 05BE-09 5,. 292E-09 j

ESE

1. 241E-08 9. 905E-09 8.112E-09 6. 781E-09 3. 961E-09 SE

1. 316E-08 1. 051E-08 8. 605E-09 7.192E-09 3. 361E-09 SSE

1. 874E-08 1. 496E-08 1. 225E-08 1. 024E-08 3. 480E-09 S

2.000E-08 1.597E-08 1.30SE-08'1.093E-08 4.128E-09 SSW

8. 531E-09 6. 810E-09 5. 577E-09 4. 662E-09 2. 521E-09 SW 1.017E-08 8.120E-09 6.651E-09 5.559E-09 2.598E-09 WSW 9.963E-09 7.953E-09 6.513E-09 5.444E-09 2.67BE-09 W

9.980E-09 7.966E-09 6.524E-09 5.453E-09 2.832E-09 WNW 9.757E-09 7.78BE-09 6.379E-09 5.332E-09 2.932E-09 NW 1.246E-08 9.949E-09 8.14BE-09 6.811E-09 3.745E-09 Nr.*W 1.347E-08 1.075E-08 8.BO7E-09 7.361E-09 4.047E-09

- - - - - - - ~ -. - - _. -

ODCM Page:

104 Rev.: 5 Table A-4 (Cont.)

Atmospheric Deposition (D/0) as a Function of Distance (i )

~ 55

1. 6 8ENR

1. 2

1. 3

1. 4 1

(MILES)

(MILES)

(MILES)

(MILES)

(MILES)

N

4. 777E-09 4.163E-09 3. 664E-09 3. 252E-09 2. 910E-09 NNE

4. 260E-09 3. 713E-09 3. 26BE-09 2. 900E-09 2. 595E NE

3. 747E-09 3. 265E-09 2. 874E-09 2. 551E-09 2. 283E-09 ENE 4.109E-09 3 591E-09 3 151E-09 2. 797E-09 2. 503E-09 g

E

4. 359E-09 3. 973E-09 3. 497E-09 3.104E-09 2. 777E-09 ESE

3. 413E-09 2. 974E-09 2. 617E-09 2. 323E-09 2. 079E-09 SE

2. 896E-09 2. 524E-09 2. 221E-09 1. 971E-09 1. 764E-09 SSE

2. 99BE-09 2. 612E-09 2. 299E-09 2. 041E-09 1. 826E-09 5

3. 556E-09 3. 099E-09 2. 727E-09 2. 421E-09 2.166E-09 SSW 2.172E-09 1. B92E-09 1. 666E-09 1. 478E-09 2. 323E-09 SW

2. 23SE-09 1. '950E-09 1. 717E-09 1. 524E-09 1. 363E-09 WSW

2. 307E-09 2. 011E-09 1. 770E-09 1. 571E-09 1. 406E-09 W

2. 440E-09 2.126E-09 1. 871E-09 1. 661E-09 1. 486E-09 WNW

2. 325E-09 2. 201E-09 1. 937E-09 1. 719E-09 1. 538E-09 NW

3. 226E-09 2. 811E-09 2. 474E-09 2.196E-09 1. 965E-09 NNW

3. 497E-09 3. 039E-09 2. 674E-09 2. 374E-09 2.' 124E-09 SECTOR

1. 7

1. 8

1. 9

2. O 2.1 (MILES)

(MILES)

(MILES)

(MILES)

(NILES)

N

2. 619E-09 2. 371E- 09 2.159E-09 1. 973E-09,1. 812E-09

~

NNE

2. 336E-09 2.115E-09 1. 925E-09 1. 760E-091. 616E.

NE

2. 055E-09 1. 860E.-09 1. 693E-09 1. 54BE-09 1. 292E-09 ENE

2. 253E-09 2. 040E-09 1. 856E-09 1. 697E-09 1. 558E-09 '-

E

2. 500E-09 2. 263E-09 2. 059E-09 1. 983E-09 1. 572E-09 ESE 1.871E-09 1.694E-09 1.542E-09 3.410E-09 1.294E-09 SE

1. 5BSE-09 1. 437E-09 1. 30SE-09 1.196E-09 1. 09BE-09 SSE

1. 644E-09 1. 4BBE-09 1. 354E-09 1. 23GE,b9 7. 816E-10 5

1. 950E-09 1. 765E-09 1. 606E-09 1. 469E-09 6. 743E-10

~

SSW 1.191E-09 1. 07BE-09 9. 810E-10 B. 969E-10 5. 883E-10 l

SW 1.227E-09 1.111E-09 1. 011E-09 9. 244E-10 B. 408E-10 WSW

1. 265E-09 1.145E-09 1. 042E-09 9. 330E-10 1. 352E-09 s

W 1.338E-09 1.211E-09 1.102E-09 1. OOBE-09 1. 430E-09 Wi.*W 1.385E-09 1.254E-09 1.141E-09 1. 043E-09 1. 393E-09 NW 1.769E-09*1.601E-09 1.457E-09 1.333E-09 1.223E-09 NNW 1.912E-09 1.731E-09 1.375E-09 1.440E-09 1.322E-09

ODCM Fage:

105 P.ev. :

5 Table A-4 (Cont.)

Attnospheric Deposition (D/Q) as a Function of Distance (m" )

l l

SECTOR

2. 2

2. 3

2. 4

2. 5

2. 6 (NILES)

(NILES)

(MILES)

(MILES)-

(NILES)

N

1. 670E-09 1. 544E-09 1. 433E-09 1. 334E-09 1. 245E-09 NMF 1.48?E-09 1.377E-09 1.278E-09 1.189E-09 1.110E-09 NE 1.191E-09 1.101E-09 1. 022E-09 9. 511E-10 8. 879E-10 ENE

1. 436E-09 1. 328E-09 1. 233E-09 1.147E-09 1. 071E-09 E

1. 449E-09 1. 340E-09 1. 243E-09 1.157E-09 1. OBOE-09 ESE 1.193E-09 1.103E-09 1. 024E-09 9. 528E-10 8. 895E-10 SE 1.012E-09 9.362E-10 8.687E-10 8.085E-10 7.54BE-10 SSE

7. 204E-10 6. 663E-10 6.183E-10 5. 754E-10 5. 372E-10 j

S 6.215E-10 5.749E-10 5.334E-10 4.964E-10 4.634E-10 SSW 5.422E-10 5.015E-10 4.653E-10 4.331E-10 4.043E-10 SW

7. 823E-10 7. 236E-10 6. 714E-10 6. 249E-10 5. 834E-10 WSW 1.246E-09 2.153E-09~1.070E-09 9.956E-10 9.294E-10 i

W 1.318E-09 1.219E-09 1.131E-09 1.053E-09 9.827E-10 WNW

'1. 284E-09 1.188E-09 1.102E-09 1. 026E-09 9. 575E-10 NW 1.128E-09 1. 043E-09 9. 678E-10 9. OO7E-10 8. 409E-10 NNW

1. 219E-09 1.127E-09 1. 046E-09 9. 735E.e10 9. 089E--10 SECTOR

2. 7

2. B

2. 9

3. O 3.1 l

(MILES)

(MILES)

(MILES)

- (MILES )

(NILES) l N

1.165E-09 1. 092E-09 1. 026E-09 9. 666E-10 9_120E--10.

NNE -

1. 039E-09 9. 742E-10 9.155E-10 8. 621E-10 8.134E-10 l

NE 8.307E-10 7.789E-10 7.320E-10 6.893E-10 6.504E-10 ENT 1.OO2E-09 9.396E-10 8.830E-10 8.315E-10 7.845E-10 E

1. 011E-09 9. 477E-10 8. 906E-10 8. 387E-10 7. 913E-10 ESE B. 322E-10 7. 804E-10 7. 334E-10 6. 906E-10 5. 923E-10 SE

7. 061E-10 6. 622E-10 6. 223E-10 5. 860E-10 5. 529E-10 SSE" 5.026E-10 4.713E-10 4.429E-10 4.171E-10 3.935E-10 S

4. 336E-10 4. 066E-10 3. 821E-10 3. 398E-10 3. 395E-10

-~

SSW

3. 782E-10 3. 547E-10 3. 333E-10 3.139E-10 2. 961E-10 SW

5. 459E-!O 5.118E-10 4. 810E-10 4. 529E-10 4. 273E-10 WSW B.695E-10 8.154E-10 7.663E-10 7.216E-10 3.607E-10 i

W 9.194E-10 8. 621E-10 8.102E-10 7. 630E-10 6. 775E-10 l

WWW 8.958E-10 8.400E-10 7.894E-10 7.434E-10 7.890E-10 NW 7.867E-10 7.377E-10 6.933E-10 6.520E-10 6.719E-10 a

NUW 8.503E-10 7.973E-10 7.493E-10 7.056E-10 6.657E-10

t ODCM Page:

106 Rev.: 5 Table A-4 (Cont.)

Atmospheric Deposition (D/0) as a Function of Distance (m" )

1 SECTOR

3. 2 II.3..

3. 4

3. 5

3. 6 (MILES)

(MILES)

(MILES)

(MILES)

(MILES)

N B. 620E-10 B.161E-10 7.'739E-10 7. 347E-10 6. 991E-10 NNE

7. 68SE-10 7. 279E-10 6. 902E-10 6. 352E-10 6. 235E-10 NE 6.147E-10 5.B20E-10 5.518E-10 5.239E-10 4.985E-10 ENE

7. 415E-10 7. 020E-10 6. 657E-10.6. 320E-10 6. 014E-10 E

7. 479E-10 7. 081E-10 6. 714E-10 6. 374E-10 6. 066E-10 ESE 5.59BE-10 5.3OOE-10 5.026E-10 4.771E-10 4.541E-10 l

SE 5.225E-10 4.947E-10 4.691E-10 4.454E-10 4.238E-10 SSE

3. 719E-10 3. 521E-10 3. 33?E-10 3.170E-!O 3. 016E-10 S

3.20?E-10 3.03BE-10 2.BBOE-10 2.735E-10 2.602E-10 SSW

2. 799E-10 2. 650E-10 2. 513E-IO 2. 386E-1Q 2. 270E-10 SW

4. 039E-10 3. 824E-10 3. 626E-!O 3. 442E-10 3. 276E-10 QSW

3. 299E-10 5. 017E-10 4. 757E-10 4. 516E-10 4. 298E-10 M'

6. 403E-10 6. 062E-10 5. 749E-10 5. 458E-10 5.193E-10 WWJ 7.457E-10 7.060E-10 6.695E-10 6.356E-10 6.048E-10 N4"

6. 351E:-10 6. 013E-10 5. 702E-10 5. 413E-10 5.151E-10 NNW

6. 292E-10 5. 957E-10 5. 649E-10 5. 363E-10 5.103E-10 9

SECTOR

3. 7

3. S

3. 9

4. O 4.1 (MILES)

(MILES)

(MILES)

(MILES)

(MILES)

N

6. 657E-10 6. 347E-10 6. 059E-10 5. 791E-10 5. 036E-10 "-

NNE 5.937E-10 5.661E-10 5.404E-10 5.165E-10 4.492E-10 NE

4. 747E-10 4. 5268-10 4. 321E-10 4.129E-10 3. 951E-10

~

ENtr.

5.727E-10 5.460E-10 5.212E-10 4.981E-10 4.766E-10 E

5, 776E-10 5. 507E-10 5. 257E-!O 5. 024E-10 4. BO7E-10 ESE

4. 324E-10 43122E-10 3. 935E-10 3. 761E-10 3. 398E-10 SE

4. 036E-10 3. 848E-10 3. 673E-10 3. 510E-10 3. 053E-10 SSE

2. 872E-10 2. 739E-10 ~2. 414E-10 2. 498E-10 2. 390E-10 E

2. 478E-10 2. 363E-10 2. 255E-10 2.155E-10 2. 062E-10 SSW 2.162E-10.2.061E-10 1.968E-10 1.BBOE-10 1.799E-10 SW

3. '.19E-10 2. 974E-10 2. 839E-10 2. 713E-10 2. 596E-10 WSW

4. 093E-10 3. 902E-10 3. 725E-10 3. 360E 10 2. 919E-10 W

4. 945E-10 4. 715E-10 4. 501E-10 4. 302E-10 3. 087E-10 WNW

5. 759E-10 5. 491E-10 5,242E-10 5. O!OE-10 3. 728E-10 MJ 4.905E-10 4.677E-10 4.464E-10 4.266E-10 4.082E-10 NNW

4. 859E-10 4. 633E-10 4. 423E-10 4. 227E-10 3. 676E-10

ODCM Page:

107 Rev.:

5 Table A-4 (Cont.)

Atmospheric Deposition (D/0) as a Function of Distance (m- )

SECTOR

4. 2

4. 3

4. 4 4.5

4. 6 (MILES)

(MILES)

(MILES)

(MILES)

(N!LES)

N 4.623E-10 4.624E-10 4.437E-10 4.260E-10 4.097E-10 M E:

i 4.302E-10'4.124E-10 3.957E-10 3.BOOE-10 3.654E-10 NE 3.784E-10 3.627E-10 3.4BOE-10 3.342E-10 3.21.4E-10 l

ENE 4.564E-10 4.375E-10 4.19EE-10 4.031E-10 3.877E-10 E

4.603E-10 4.413E-10 4.234E-10 4.066E-10 3.910E-10 ESE 3.446E-10 3.;303E-10 3.170E-10 3.044E-10 2.927E-10 SE 2.924E-10 2.903E-10 2.690E-10 2.583E-10 2.484E-10 SSE 2.289E-10 2.195E-10 2.106E-10 2.022E-10 1.944E-10 1.975E-1'O1.893E-101.817E-1b1.744E-101.677E-10 S

SSN 1.723E'10 1.652E-10 1.585E-10 1.522E-10 1.463E-10 SW 2.486E-10 2.333E-10 2.287E-10 2.196E-10 2.112E-10 WSW 2.796E-10 2.6SOE-10 2.572E-10 2.469E-10 2.375E-10 W

2.956E-10 2.834E-10 2.719E-10 2.611E-10 2.511E-10 WNW

3. 570E-10 3. 422E-10 3. 284E-10 3.153E-10 3. 032E-10 NW

3. 909E-10 3. 747E-10 3. 596E-10 3. 453E-10 3. 320E-10 M n3 3.521E-10 3.375E-10 3.239E-10 3.110E-10 2.991E-10

)

SECTOR

4. 7

4. B

4. 9

5. O (MILES)

(MILES)

(MILES)

(MILES)

N 3.941E-10'3.795E-10 3.656E-10 3.525E-1'O tud:

3. 515E-10 3. 384E-10 3. 261E-10 3.144E-10' -

NE

3. 092E-10 2. 977E-10 2. 86BE-10 2. 765E-10

~

ENE

3. 729E-10 3. 591E-10 3. 460E-10 3. 336E-10 E

3.762E-10 3.622E-10 3.469E-10 3.364E-10 ESE 2.816E-10 2.711E-10 2.612E-10 2.51fE-10 SE 2.339E-10 2.3 DOE-10 2.216E-10 2.137E-10 SSE 1.871E-10 1.801E-10 1.735E-10 1.673E-10 S

1.614E-10 1.554E-10 1.497E-10 1.443E-10 SSN 1.40BC-10 1.355E-!O 1.306E-10 1.259E-10 SW 2.031E-10 1.956E-10 1.BB4E-10 1.817E-10 WSW 2.285E-10 2.199E-10 2.119E-10 2.043E-10 l

W 2.415E-10 2.326E-10 2.241E-10 2.160E-10 WNW

2. 917E-10 2. 839E-10 2. 706E-10 2. 609E-10 NW 3.194E-10 3. 075E-10 2. 963E-10 2. 857E-10 NRW 2.877E-10 2.770E-10 2.669E-10 2.573E-10

ODCM Page:

108 Rev.:

5 l

Appendix B Lower Limit of Detection

OttCM Page:

109 Rev.:

5 The lower limit of detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with a 95 percent probability with a 5 percent probability of falsely concluding that a blank observation represents a 'real* signal.

j For a measurement system (which may include radiochemical separation) based on gross beta, gross alpha, liquid scintillation, or other analyses where a background count determined by a separate measurement with no sample (or blank sample) is subtracted from the gross sample count to obtain a net count due to sample activity:

rb rb 3.3

+

(B-1) kd s

LLD =

j (C)(E)(V)(Y I

• • 9 I

}

c l

Where:

LLD = the 'apriori" lower limit of detection, as defined above; C

= the conversion factor of transformations per unit time per uCi or pCi; E

= the detector efficiency; b = the background count rate in units of transformations per r

unit time; t

= the counting time of background; b

t

= the counting time of the sample;

]

s V

= the sample size, in units of mass or volume; Y

= the fractional radiochemical sample collection or c

concentration yield (when applicable);

At = for plant effluents, the elapsed time between the midpoint of sample collection and time of counting; for environmental samples, the elapsed time between sample collection (or end of the sample collection period) and time of counting; 1

= the radioactive decay constant for the radionuclide in question.

oDCu Page:.110

'l Rev.:

5 For the purpose of routine analyses, count times for both the sample (s) and background (s) are equal. This satisfies the given ODCM Appendix C control for lower limit of detection definition, as the numerator of j

equation B-1 simplifies to 4.66 S, where S is the standard deviation of h

b the background count rate or the count rate of a blank sample as i

appropriate.

l The LLD is defined as an 'apriori" (before the fact) limit representing i

the capability of a measurement system and not as an "a posteriori"

}

(after the fact) limit for a particular measurement.

For gama ray spectroscopy analyses:

~

t L

exp (0.693 At/t M)

LLD =

D (B-2) 4 (C)(E)(t)(V)(Y } 5 I}

c Where:

i LLD = the lower limit of detection, in pCi or pCi per unit mass or volume; C

= the conversion factor of transformations per unit time per pC1 or pC1; E

= the detector efficiency tor the energy in question; j

t

= the data collection (counting) time of sample; t M = the half-life of the radionuclide in question;

]

V

= the sample size, in units of mass or volume; Y

= the fractional radiochemical, sample collection, or l

concentration yield (when applicable);

i c

<J,

Y7

= the yield of the gamma ray in question;~

1 At = for plant effluents the elapsed time between midpoint of

}

sample collection and time of counting; for environmental samples, the elapsed time between sample collection (or i

end of the sample collection period) and the time of i

counting; L

= the detection limit D

2'M

=k2 + 2k

[

(1 +

)

(B1 + B ) + I + 'I (B-2a) 2 s

ODCM j

Page:

111 l

Rev.:

5 Where:

l By = the number of counts in 'n' background channels below the i

peak due to Compton scattering, etc., determined at the i

same time a photopeak is measured; i

B2 = the number of counts in the 'n' background channels above the peak, k = an abscissa of the normal distribution corresponding to l

confidence level,

= 1.645 at a confidence level of 95%;

I = the measured value of interference in the photopeak of interest due to environmental background, detector contamination, etc., determined by a separate measurement with no sample; N = the number of channels in the photopeak of interest;

= the number of background channels on each side of the i

n photopeak of interest; 7 = the standard deviation of I.

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

I In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).

Analyses shall be performed in such a manner that the LLD's listed in Tables 4.11.1.1.1-1, 4.11.2.1.2-1, and 4.12.1-1 of the ODCM Appendix C controls for the Perry Nuclear Power Plant will be achieired under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

l

)

I

ODCM Pign:

112 Rev.:

5 e

Appendix C Controls 9

ODCM Page:

113 Rev.:

5 INDEX DEFINITIONS SECTION 1.0 DEFINITIONS PAGE 1.1 ACTION.......................................................

1-1 1.4 CHANNEL CALIBRATION..........................................

1-1 1.5 CHA! GEL CHECK................................................

1-1

~

1.6 CHANNEL FUNCTIONAL TEST......................................

1-1 1.10 DOSE EQUIVALENT I-131........................................~

1-1 1.17 FREQUENCY NOTATION...........................................

1-2 1.19 GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM...................

1-2 1.24 LIQUID RADWASTE TREATMENT SYSTEM.............................

1-2 1.26 MEMBER (S) OF THE PUBLIC......................................

1-2 1.28 OFFSITE DOSE CALCULATION MANUAL..............................

1-2 1.29 OPERABLE - OPERABILITY.......................................

1-2 1.30 OPERATIONAL CONDITION - CONDITION............................

1-3 l

1 1

1.35 PURGE - PURGING..............................................

1-3 1.36 RATED THERMAL POWER..........................................

1-3 1.38 REPORTABLE EVENT.............................................

1-3 1.42 SITE BOUNDARY................................................

1-3 1.44 SOURCE CHECK.................................................

1-3 1.46 THERMAL POWER................................................

1-3 1.49 UNRESTRICTED AREA............................................

1-3 l

1.50 VENTILATION EXHAUST TREATMENT SYSTEMS........................

1-4 1.51 VENTING......................................................

1-4 Table 1.1, Surveillance Frequency Notation........................

1-5 Table 1.2, Operational Conditions.................................

1-6 PERRY - UNIT 1 i

i i

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114 Rev.: 5 CONTROLS AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY..............................................

3/4 0-1 1

3/4.3 INSTRUMENTATION Radioactive Liquid Effluent Monitoring Instrumen-tation..................................................

3/4 1-1 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation........

3/4 1-2 Table 4.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.........

3/4 1-4 1

Radioactive Gaseous Effluent Monitoring Instrumen-

]

tation..................................................

3/4 1-6

)

Table 3.3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation.......

3/41-7 Table 4.3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements........

3/4 1-10 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration..........................................

3/4 2-1 Table 4.11.1.1.1-1 Radioactive Liquid Uaste Sampling and.e-i sis f

Program.......................

3/4 2-2 Dose...................................................

3/4 2-5 Liquid Radwaste Treatment System.......................

3/4 2-6 3/4.11.2 GASEOUS EFFLUDTPS Dose Rate...............................................

3/4 2-7 Table 4.11.2.1.2-1 Radioactive Gaseous Waste Sampling and Analysis Program........................

3/4 2-8 Dose - Noble Gases......................................

3/4 2-11 Dose - Iodine-131, Iodine-133, Tritium,.and l

Radionuclides in Particulate Form.....................

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115 Rev.:

5 l

CONTROLS AND SURVEILLANCE REQUIREMENTS SECTION PAGE RADIOACTIVE EFFLUENTS (Continued)

Gaseous Radwaste (Offgas) Treatment.....................

3/4 2-13 Ventilation Exhaust Treatment Systems...................

3/4 2-14 3/4.11.4 TOTAL D0SE..............................................

3/4 2-17 3/4.12 RADIOLOGICAL ENVIRONMEffI'AL MONITORING 3/4.12.1 MONITORING PR0 GRAM......................................

3/4 3-1 Table 3.12.1-1 Radiological Environmental

~

Monitoring Program..................

3/4 3-3 Table 3.12.1-2 Reporting Levels for Radioactivity Concentrat, ions In Environmental Samples.............................

3/4 3-9 Table 4.12.1-1 Maximum Values for the Lower Limits of Detection (LLD)..................

3/4 3-10 3/4.12.2 LAND USE CENSUS.........................................

3/4 3-13 3/4.12.3 INTERLABORA'IORY COMPARISON PR0 GRAM......................

3/4 3-14 BASES SECTION PAGE 3/4.0 APPLICABILITY..............................................

B 3/4 0-1 3/4.3 INSTRUMENTATION l

Radioactive Liquid Effluent Monitoring Instrumentation........................................

B 3/4 1-1 Radioactive Gaseous Effluent Monitoring Instrumentation.........................................

B 3/4 1-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration...........................................

B 3/4 2-1 Dose....................................................

B 3/4 2-1 l

Liquid Radwaste Treatment System........................

B 3/4 2-2 PERRY - UNIT 1 iii

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116 Rev.:

S BASES l

SECTION PAGE RADIOACTIVE EFFLUEDTS (Continued) 3/4.11.2 GASEOUS EFFLUENTS Dose Rata...............................................

B 3/4 2-3 Dose - Noble Gases......................................

B 3/4 2-3 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form.......................

~

B 3/4 2-4 Gaseous Radwaste Treatment (Offgas) System and i

Ventilation Exhaust Treatment Systems...................

B 3/4 2-5 1

3/4.11.4 TOTAL D0SE..............................................

B 3/4 2-6 3/4.12 RADIOLOGICAL ENVIRONMEffrAL MONI'IORI_NG 3/4.12.1 MONITORING PR0 GRAM......................................

B 3/4 3-1 3/4.12.2 LAND USE CENSUS.........................................

B 3/4 3-1 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM...................... B 3/4 3-2 ADMINISTRATIVE CONTROLS SECTION PAGE

_6.9 REPORTING REQUIREMENTS 6.9.1.6 Annual Radiological Environmental Operating Report......

4-1 6.9.1.7 Annual Radioactive Effluent Release Report..............

4-1 6.9.2 SPECIAL REP 0RTS.........................................

4-2 6.10 RECORD RETENTION............................................

4-3

_6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS........

4-3 1

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117 Rev.:

5 SECT. TON 1.0 DEFINITIG:C m

ODCM Page:

118 Rev.: 5 1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these Controls may be achieved. The defined terms appear in capitalized type and shall be applicable throughout these Controls.

ACTION 1.1 ACTION shall be that part of a control which prescribes reredial measures required under designated conditions.

CHANNEL CALIBRATIO]

1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION s

shall encompass the entire channel including the sensor and alarm 'and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where pos-sible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:

Analog channels - the injection of a simulated signal into the channel-a.

as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.

b.

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

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

DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, ' Calculation of Distance Factors tvi Power and Test Reactor Sites."

PERRY - UNIT 1 1-1

ODCM Page:

119 Rev.:

5 DEFINITIONS FREQUENCY NOTATICN 1.17 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

GASEOUS RADWASTE TREA MENT (OFFGAS) SYSTEM 1.19 THE GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgasses from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to

~

release to the environment.

LIQUID RADWASTE TREATMENT SYSTEM 1.24 The LIQUID RADWASTE TREATMENT SYSTEM is any process or control equipment used to reduce the amount or concentration of liquid radioactive materials prior j

to their discharge to UNRESTRICTED AREAS.

It involves all the installed and available liquid radwaste management system equipment, as well as their controls, power instrumentation, and services that make the system functional.

MEMBER (S) OF THE PUBLIC 1.26 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

l OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.28 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the radiological environmental monitoring program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Specification 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.6 and 6.9.1.7.

OPERABLE - OPERABILITY 1.29 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

PERRY - UNIT 1 1-2

ODCM Page:

120 Rev.:

5 DEFINITIONS OPERATIONAL CONDITION - CONDITION 1.30 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1.2.

PURGE - PURGING 1.35 PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or

~

other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.36 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3579 MWT.

l REPORTABLE EVENT

{

1.38 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.

SITE BOUNDARY 1.42 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SOURCE CHECK 1.44 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

THERMAL POWER 1.46 THERMAL POWER shall be the total reactor core heat transter rate to the reactor coolant.

UNRESTRICTED AREA 1.49 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUlOARY access to which is not controlled by the licensee for purposes of protection of MEMBERS OF THE PUBLIC 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.

I PERRY - UNIT 1 1-3

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121 Rev.:

5 DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEMS 1.50 A VDRILATION EXHAUST TREATMEIR SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup systems'are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components provided the ESF system is not utilized to treat normal releases.

~

VENTING l

1.51 VENTING is the controlled process of discharging air or gas ~from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

PERRY - UNIT 1 1-4

ODCM Page:

122 l

Rev.:

5 TABLE 1.1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S

At last once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

W At least once per 7 days.

M At least once per 31 days.

Q At 'least once per 92 days.

SA At least once per 184 days.

A At least once per 366 days.

R At least once per 18 months (550 days).

S/U Prior to each reactor startup.

P Completed prior to each release N.A.

Not applicable.

PW PERRY - UNIT 1 1-5

ODCM

)

Paga:

123 Rev.:

5 TABLE 1.2 OPERATIONAL CONDITIONS MODE SWITCH AVERAGE REACER CONDITION POSITION COOLANT TEMPERAWRE 1.

POWER OPERATION Run Any temperature 2.

STARTUP Startup/ Hot Standby" Any temperature I"*

3.

HOT SHUTDOWN Shutdown '

> 2000F I

4.

COLD SHUTDOWN Shutdown 'II'*"

s 2000F 5.

REFUELING

• Shut'down or Refuel"'I s 140'F

1. The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position'to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.

1. 1. The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per PNPP Unit 1 Technical Specification 3.9.10.1.

• Fuel in the reactor vessel with the vessel head closure' bolts less than fully tensioned or with the head removed.

• • See Special Test Exceptions 3.10.1 and 3.10.3 of PNPP Unit 1 Technical Specifications.

• "The reactor mcde switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out interlock is OPERABLE.

PERRY - UNIT 1 1-6 i

ODCM P:gn:

124 Rev.: 5 i

SECTIONS 3.0 and 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS

ODCM Page:

125 Rev.:

5 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the Controls contained in the succeeding controls is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

j 3.0.2 Noncompliance with a control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals.

If the Control is restored prior to expiration of the specified time intervals, completion of the Action requirements is not required.

3.0.3 When a Control is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the control does not apply by placing it, as applicable, in:

1.

At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control.

Exceptions to these requirements are stated in the individual controls.

This control is not applicable in OPERATIONAL CONDITIONS 4 or 5.

3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Control are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval.

Entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This l

provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual controls.

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126 l

Rev.:

5 I

APPLICABILITY I

SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Controls unless otherwise stated in j

an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

)

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by control 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Control have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

.m PERRY - UNIT 1 3/4 0-2

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ODCM Page:

127 Rev.:

5 INSTRUMENTATION RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.9 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.d.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.9-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

With a radioactive liquid effluent monitoring instrumentation channel a.

alarm / trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.9-1.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

c.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.9-1.

l

@m i

PERRY - UNIT 1 3/4 1-1

i i

E' TABLE 3.3.7.9-1 B

RADIOACTIVE LIQUID EFFLUENT MONI'IORING INSTRLMENTATION i

E MINIMUM U

CHANNELS INSTRUMENT OPERABLE ACTION 1.

GROSS RADIOACTIVITY MONI'IORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Discharge Radiation Monitor -

1 110 ESW Discharge 2.

GROSS BETA OR GAMMA RADIOACTIVITY MONI'IORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.

Emergency Service Water Loop A Radiation Monitor 1

111 b.

Emergency Service Water Loop B Radiation Monitor 1

111 3.

FLOW RATE MEASUREMENT DEVICES 4

a.

Radwaste Discharge Header 1.

Radwaste High Flow Discharge Header Flow 1

112 2.

Radwaste Low Flow Discharge Header Flow 1

112 b.

Service Water Discharge Header Flow 1

113 c.

Unit 1 Emergency Service Water Flow Monitor 1

113 i'?

..E..E 5

l ODCM Page:

129 Rev.:

5 TABLE 3.3.7.9-1 (Continued) l RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMEtTPS ACTION 110 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance.

with Control 4.11.1.1.1, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving:

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 111 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, grab samples are collected and analyzed for gross radio 9ctivity (beta or gamma) at a limit of detection of at least 10 microcuries/ml.

ACTION 112 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this i

pathway may continue provided the discharge valve position is verified to be consistent with the flow rate provisions of the release permit at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Prior to initiating another release, at least two technically qualified members of the Facility Staff shall independently verify the discharge line valving and that the discharge valve position corresponds to the desired flow rate..Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 113 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least i

once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Pump performance curves generated in place may be used to estimate flow.

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l l

PERRY - UNIT 1 3/4 1-3

E TABLE 4.3.7.9-1

%)

RADIOACTIVE LIQUID EFFLUENT MONI70 RING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL U

CHANNEL SOURCE CHANNEL FUNCTIONAL

- INSTRUMENT CHECK CHECK CALIBRATION TEST 1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Discharge Radiation D

P R(3)

Q(1)

Monitor - ESW Discharge 2.

GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.

Emergency Service Water Loop A Radiation D

M R(3)

Q(2)

Monitor w

s

[

b.

Emergency Service Water Loop B Radiation D

M R(3)

Q(2) l A

Monitor.

j 3.

FLOW RATE MEASUREMENT DEVICES a.

Radwaste Discharge Header 1.

Radwaste High Flow Discharge Header Flow D(4)

N.A.

R Q

o o o 2.

Radwaste Low Flow Discharge Header Flow D(4)

N.A.

R Q

. ?

b.

Service Water Discharge Header Flow D(4)

N.A.

R Q

mg c.

Unit 1 Emergency Service Water Flow D(4)

N.A.

R Q

o Monitor l

ODCM P:gn:

131 Rev.:

5 TABLE 4.3.7.9-1 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS I

TABLE NOTATION (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

1.

Instrumert indicates measured levels above the alarm / trip setpoint.

2.

Instrument indicates a downscale failure.

3.

Instrument controls not set in operate mode except in high voltage position.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Instrument indicates a downscale failure.

3.

Instrument controls not set in operate mode, except in high voltage position.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been 'telated -

to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which continuous, periodic or batch releases are made.

)

PERRY - UNIT 1 3/4 1-5

ODCM Page:

132 Rev.: 5 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.10 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.d.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The alarm / trip setpoints of applicable channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3.7.10-1 ACTION:

With a radioactive gaseous effluent monitoring instrumentation channel a.

alarm / trip setpoint less conservative than required by the above specification, declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

The provisions of Control 3.0.3 are not applicable.

c.

SURVEILLANCE REQUIREMEtTPS 4.3.7.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.

i PERRY - UNIT 1 3/4 1-6

m e

TABLE 3.3.7.10-1 U

RADIOACTIVE GASEOUS EFFLUENT MONIERING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.

OFFGAS VENT RADIATION MONITOR a.

Noble Gas Activity Monitor 1

121 b.

Iodine Sampler 1

122 c.

Particulate Sampler i

122 d.

Effluent System Flow Rate Monitor 1

w 123 2

e.

Sampler Flow Rate Monitor 1

y 123 4

2.

UNIT 1 VENT RADIATION MONIE R a.

Noble Gas Activity Monitor 1

1,2,3 125 4, 5 121 b.

Iodine Sampler 1

122 c.

Particulate Sampler 1

n m o 122

• gg d.

Effluent System Flow Rate Monitor 1

123 e.

Sampler Flow Rate mg w

Monitor 1

123 e

l 5

TABLE 3.3.7.10-1 (Continued)

E*

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION i

h MINIMUM CHANNELS H

INSTRUMENT OPERABLE APPLICABILITY ACTION s-3.

UNIT 2 VENT RADIATION MONITOR a.

Noble Gas Activity Monitor 1

121 b.

Iodine Sampler 1

122 c.

Particulate Sampler 1

122 d.

Effluent System Flow Rate Monitor 1

123 i

e.

Sampler Flow Rate Monitor 1

123 4.

HEATER BAY / TURBINE BUILDING VENT RADIATION MONI'IOR j

y a.

Noble Gas Activity Monitor 1

121 b.

Iodine Sampler 1

122 c.

Particulate Sampler 1

122 d.

Effluent System Flow Rate Monitor 1

+

123

,,o e.

Sampler Flow Rate Monitor 1

123

= t.:

0

ODCM Prgs:

135 Rev.:

5 TABLE 3.3.7.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION At all times.

During main condenser offgas treatment system operation.

ACTION 121 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 122 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with auxiliary sampling equipment as required by Table 4.11.2.1.2-1.

ACTION 123 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent release via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 124 -

NOT USED 1

ACTION 125 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, except as a result of a non-conservative setpoint, immediately suspend containment /

drywell purge and vent.

Prior to resuming containment /drywell purge and vent, ensure compliance with the requirements of Control 3.11.2.1.

If compliance with Control 3.11.2.1 is met, containment /drywell purge and vent may continue provided grab samples are taken 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 these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.'

PERRY - UNIT 1 3/4 1-9

E E

TABLE 4.3.7.10-1

)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMDirATION SURVEILLANCE REQUIREMENTS h

CHANNEL MODES IN WHICH 8

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

- INSTRUMENT

__ CHECK CHECK CALIBRATION TEST REQUIRED 1.

OFFGAS VENT RADIATION MONITOR a.

Noble Gas Activity Monitor D

M R(2)

Q(1) b.

Iodine Sampler W(4)

N.A.

N.A.

N.A.

c.

Particulate Sampler W(4)

N.A.

N.A.

N.A.

d.

Effluent System Flow Rate Monitor D

N.A.

R Q

e.

Sampler Flow Rate Monitor D

N.A.

R Q

2.

UNIT 1 VENT RADIATION MONITOR a.

Noble Gas Activity Monitor D

M R(2)

Q(1) b.

Iodine Sampler W(4)

N.A.

N.A.

N.A.

c.

Particulate Sampler W(4)

N.A.

N.A.

N.A.

d.

Effluent System Flow Rate Monitor D

N.A.

R Q

,,o

. !" h e.

Sampler Flow Rate Monitor D

N.A.

R Q

mg 4

cn l

~..

TABLE 4.3.7.10-1 (Continued)

)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

U CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

- INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 3.

UNIT 2 VENT RADIATION MONITOR a.

Noble Gas Activity Monitor D

M R(2)

Q(1) b.

Iodine Sampler W(4)

N.A.

N.A.

N.A.

c.

Particulate Sampler W(4)

N.A.

N.A.

N.A.

d.

Effluent System Flow Rate Monitor D

N.A.

R Q

e.

Sampler Flow Rate Monitor D

N.A.

R Q

4.

HEATER BAY / TURBINE BUILDING VENT RADIATION MONITOR y

.L a.

Noble Gas Activity Monitor D

M R(2)

Q(1)

~

b.

Iodine Sampler W(4)

N.A.

N.A.

N.A.

l c.

Particulate Sampler W(4)

N.A.

N.A.

N.A.

d.

Effluent System Flow Rate Monitor D

N.A.

R Q

o e.

Sampler Flow Rate Monitor-D N.A.

R Q

f$

t:

u s

ODCM Page:

138 Rev.: 5 TABLE 4.3.7.10-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION At all times.

During main condenser offgas treatment system operation.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm.

annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alann setpoint.

2.

Instrument indicates a downscale failure.

3.

Instrument controls not set in operate mode.

(2)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3)

NOT USED (4)

The iodine cartridges and particulate filters will be changed at least once per 7 days.

Performance of this CHANNEL CHECK does not render the system inoperable, and the applicable ACTION statements need not be entered.

• uip PERRY - UNIT 1 3/4 1-12

1 ODCM Page:

139 Rev.: 5 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUE!RS i

CONCENTRATION i

CONTROLS 3.11.1.1 In accordance with Perry Nuclear Power Plant TS 6.8.4.d.3 and d.3, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1.1-1 of Technical Specifications) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For i

disgolved or entrained noble gases, the~ concentration shall be limited to 2 x 10- microcuries/ml total activity.

APPLICABILITY: At all times, i

i l

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREME!CS 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 4.11.1.1.1-1.

The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 3.11.1..

l 4.11.1.1.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11.1.1.1-1.

The results of the i

i radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.

4.11.1.1.3 Continuous releases of radioactive liquid effluents shall be sampled and analyzed in accordance with Table 4.11.1.1.1-1.

The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.

t

\\

l PERRY - UNIT 1 3/4 2-1 l

1

ODCM Paga:

140 Rev.: 5 TABLE 4.11.1.1.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Lower Limit Liquid Release Sampling Analysis Activity of Detection Type

' Frequency Frequency Analysis (LLD)

(pCi/ml)"

-7 A.

Batch Waste P

P Principagnamma 5x10 Releage Each batch Each batch Emitters Tanks I-131 1x10-6 P

M Dissolved and

-5 One Batch /M Entrained Gases 1x10 (Gama emitters)

P M

H-3 1x10-5 b

Each Batch Composite Gross Alpha 1x10-7 P

Q Sr-89, Sr-90 5x10 8 b

Each Batch Composite Fe-55

'1x10-6 B.

Continuogs D

W Principag Gama 5x10-7 g

b Releases Grab Sample Composite 'f Emitters RHR Heat Exchanger ESW Outlet I-131 1x10-6 M

M Dissolved and 1x10-5 Grab Sample Entrained Gases (Gamma Emitters)

D M

H-3 1x10-5 b

Grab Sample Composite Gross Alpha 1x10-7 D

Q Sr-89, Sr-90 5x10-8 b

Grab Sample Composite

-6 Fe-55 1x10 PERRY - UNIT 1 3/4 2-2

ODCM Page:

141 Rev.: 5 TABLE 4.11.1.1.1-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION a.

The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a 'real' signal.

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

i LLD =

6 E

V 2.22 x 10 y

exp(-lat) where LLD is the 'a priori

• lower limit of detection as defined above (as pCi per unit mass or volume).

is the standard deviation of the background counting rate or of sb the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 6 2.22 x 10 is the number of disintegrations per minute per microcurie Y

is the fractional radiochemical yield (when applicable) 1 is the radioactive decay constant for the particular radionuclide (sec-2)

At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec)

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

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

PERRY - UNIT 1 3/4 2-3

ODCM P;ge:

142 Rev.: 5

{

l TABLE 4.11.1.1.1-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM j

1 TAPL E CTATION (Continued) b.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waare discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c.

A batch release is the discharge of liquid wastes of a discrete

~

volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

d.

The principal gamma emitters for which the LLD specifica' tion applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-13 and Ce-141. Ce-144 shall also be measured, but with an LLD of 5x10-),. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Annual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7 in the fornat outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

l e.

A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release. Sampling / Analysis of RHR Heat Exchanger is only applicable when there is ESW flow thru the RHR Heat i

Exchanger.

I f.

Sampling and analysis is required of the RHR heat exchanger ESW outlet-i every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the samples indicate levels greater than LLD.

PERRY - UNIT 1 3/4 2-4

ODCM Pegs:

143 i

Rev.:

5 RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.d.4 and d.5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.1-1 of Technical Specifications) shall be limited:

1 a.

During any calendar quarter to less than or equal to 1.5 mrems to the ~

total body and to less than or equal to 5 mrems to any organ, and j

b.

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

APPLICABILITY:

At all times.

ACTION:

I a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Spccial I

Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the corrective actions to be taken to ensure that future releases will be in compliance with the above limits.

b.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters of the ODCM at least once per 31 days.

PERRY - UNIT 1 3/4 2-5

I l

ODCM Page:

144 Rev.:

5 RADIOACTIVE EFFLUENTS LIQUID RADWAS'"E TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.d.6, the LIQUID RADWASTE TREATME!TT SYSTEM shall be OPERABLE and appropriate portions of the system shall be used to reduce the release of radioactivity when the projected doses due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS (see Figure 5.1.1-1 of Technical Specifications) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ, in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a.

With radioactive liquid waste being discharged without treatment and in excess of the above limits, and any portion of the liquid radwaste j

treatment system not in operation, prepare and submit to the 1

Commission, within 30 days pursuant to Control 6.9.2, a Special Report which includes the following information:

1.

Explanation of why liquid radwaste was being discharged without i

treatment, identification of any inoperable equipment or i

subsystems, and the reason for the inoperability, and 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

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

The provisions of Control 3.0.3 are not applicable, l

i SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with methodology and parameters in the ODCM.

4.11.1.3.2 The installed LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.

PERRY - UNIT 1 3/4 2-6

ODCM Page:

145 Rev.:

5 RADIOACTIVE EFFLUE!TPS 3/4.11.2 GASEOUS EFFLUEITTS DOSE RATE CONTROLS 3.11.2.1 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.d.3 and d.7, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1'1 of Technical Specifications) shall be limited to the following:

a.

For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and b.

For all iodine-131, iodine-133, tritium and all radionuciides in particulate form with half lives greater than 8 days:

Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTION:

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

SURVEILLANCE REQUIREMENTS i

4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM.

4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium and to radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in.accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1.

PERRY - UNIT 1 3/4 2-7

TABLE 4.11.2.1.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM m

M E-i MINIMUM LOWER LIMIT O DETECTION (LLD){a) j

)GASEOUSRELEASEPATH SAMPLING ANALYSIS TYPE OF FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/mL)

E ID

-4 5 A.

Drywell and Each PURGE Each PURGE Principakepmma 1x10 Primary Containment and VENT and VENT Emitters PURGE and VENT Grab Sample i

-6 M

M H-3 1x10 Grab Sample t

IDI Vent, Unit 2 Vent Grab Sample E(b)

Principal ( D e) 1x10-4 B.

Offgas Vent, Unit 1 M

Emitters and Turbine Building / Heater

-6 Bay Vent H-3 1 x 10

~

Y

[ C.

All Release Paths Continuous (d) g(c)

I-131 1x10-12 4

as listed in B above

_yg Charcoal Sample I-133 1x10 Continuous (d)

(c)

-11 Principal ( p 1x10 Particulate Emitters Sample

-11 Continuous (d)

M Gross Alpha 1x10 Composite Par-g ticulate Sample

,, to :t e

-11 Continuous (d)

Q Sr-89, Sr-90 1x10

,g Composite Par-'

m ticulate Sample Continuous (d)

Noble Gas Noble Gases 1x10-6 Monitor (f)

Gross Beta or Gamma (Xe-133

[

equivalent) i 1.

ODCM Paga:

147 Rev.:

5 TABLE 4.11.2.1.2-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM i

TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample a.

that will yield a net count (above system background) that will be detected

{

with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real' signal, 4

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

4 4*"

b LLD =

6 E

V 2.22 x 10 y

exp(-lat) where LLD is the "a priori" lower limit of detection as defined above (as pCi per unit mass or volume).

b is the standard deviation of the background counting rate or of the s

count,ing rate of a blank sample as appropriate (as counts per minute) i E

is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 6 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 (sec-2) 1 At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec)

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

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

posteriori (after the fact) limit for a particular measurement.

~

PERRY - UNIT 1 3/4 2-9 j

ODCM Pag 3:

148 Rev.: 5 TABLE 4.11.2.1.2-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued) b.

Analyses shall also be performed following startup, shutdown, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. This requirement does not apply if (1) analysis shows that 1

the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

Samples shall be changed at least once per 7 days and analyses shall be c.

completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler.

Sampling and analyses shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

d.

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 Control 3.11.2.1, 3.11.2.2 and 3.11.2.3.

The principal gamma emitters for which the LLD specification applies e.

exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above riuclides, shall also be identified and reported in the Annual Radiological Effluent Release Report pursuant to Control 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

f.

Sampling and analysis of gaseous release points shall be performed initially whenever a high alarm setpoint is exceeded or whenever two or more of the alert setpoints are exceeded.

If the high alarm setpoint or two or more of the alert setpoints continue to be exceeded, verify at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> via the radiation monitors that plant releases are below the Control 3.11.2.1 dose rate limits and sampling and analysis shall be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

PERRY - UNIT 1 3/4 2-10

ODCM Pags:

149 Rev.:

5 RADIOACTIVE EFFLUE!TPS DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.d.5 and d.8, the air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1 of Technical Specifications) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b.

During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

With the calculated air dose from the radioactive noble gases in a.

gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases will be in compliance with control 3.11.2.2.

b.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIRDIENTS 4.11.2.2 pose Calculations. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

PERRY - UNIT 1 3/4 2-11

ODCM Page:

150 Rev.: 5 RADIOACTIVE EFFLUE!US DOSE - IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.d.5 and d.9, the dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1 of Technical Specifications) shall'be limited to the following:

a.

During any calendar quarter: 'Less than or equal to 7.5 mrems to any organ, and b.

During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of iodine-131, iodine-133, a.

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, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with Control 3.11.2.3.

b.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMEIRS 4.11.2.3 Dose Calculations. Cumulative dose contributions from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

PERRY - UNIT 1 3/4 2-12

ODCM Paga: 151 Rev.: 5 RADIOACTIVE EFFLUEN'I'S GASEOUS RADWASTE (OFFGAS) TREA'IMENT CONTROLS 3.11.2.4 The GASEOUS RADWASTE TREA'IMENT (OFFGAS) SYSTEM shall be in operation.

The Charcoal bypass mode shall not be used unless the offgas post-treatment i

radiation monitor is OPERABLE as specified in Table 3.3.7.1-1.

APPLICABILITY: Whenever the main condenser air ejector evacuation system is in.

operation.

ACTION:

^

With gaseous radwaste from the main condenser air ejector system being a.

i discharged without treatment for more than 7 consecutive days, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which includes the following information:

1.

Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or I

subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for-inoperability.

2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

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

b.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The readings of relevant instrumentation shall be checked at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the main condenser air ejector is in use to ensure that the gaseous radwaste treatment system is functioning.

PERRY - UNIT 1 3/4 2-13

ODCM Page:

152 Rev.: 5 RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEMS l

CONTROLS 3.11.2.5 The VENTILATION EXHAUST TREA'INENT SYSTEMS shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected dose due to gasecus effluent releases from each reactor unit to areas at and beyond the SITE BOUN0ARY (see Figure 5.1.1-1 of Technical Specifications) in a 31 day period would exceed 0.3 mrem to any organ.

of a MEMBER OF THE PUBLIC.

i APPLICABILITY: At all times.

ACTION:

a.

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which includes the following information:

1.

Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

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

b.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEMS shall be demonstrated OPERABLE by meeting Controls 3.11.2.1 and 3.11.2.3.

PERRY - UNIT 1 3/4 2-14

ODCM Paga:

153 Rev.:

5 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.d.10, the annual (calendar year) dose or dose commitment to any MEMBER or THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a, or 3.11.2.3b., calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded.

If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.

This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 If the cumulative dose contributions exceed the limits defined in 3.11.4, ACTION a, cumulative dose contributions from direct radiation from unit operation including outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM.

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ODCM Page:

154 Rev.:

5 3/4.12 RADIOLOGICAL E!NIRONMENTAL MONI1DRING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.e.1, the radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.

APPLICABILITY: At all times.

ACTION:

~

With the radiological environmental monitoring program not being a.

conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the annual Radiological Environmental Operating Report per Control 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, b.

Wit;. the level of radioactivity as the result of plant effluents in an environmu/;?1 sampling medium at a specified location exceeding the reporting leveic of Table 3.12.1-2 when averaged over any calendar l

quarter, prepare and cubmic to the Commission within 30 days pursuant to Control 6.9.2 a Speciu Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Control 3.11.1.2, 3.11.2.2 and 3.11.2.3.

When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1)

+ concentration (2) reporting level (1) reporting level (2) +... t 1.0 When radionuclides other than those in Table 3.12.1-2 are detected and I

are the result of plant effluents, this report shall.be submitted if

)

the potential annual dose

• to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Control 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Control 6.9.1.6.

• The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

PERRY - UNIT 1 3/4 3-1 t

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ODCM Pege:

155 Rev.:

5 RADIOLOGICAL DNIRONMENTAL MONITORING CONTROIS With milk or broad leaf vegetation samples unavailable from one or c.

more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable nay then be deleted from the monitoring program.

Pursuant to Control 6.14, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table f6r the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

d.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMD1TS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figures in the ODCM and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.

PERRY - UNIT 1 3/4 3-2

m.

g TABLE 3.12.1-1

=

RADICIDGICAL DnTIRCNENTAL ENITORING PROGRAM

• e Number of Sa @les Exposure Pattwoy and Samling arx1 Type and Frequency M

gg) 4 and/or Sanole,

Samle Iccations Collection FreeJency of Analysis e*

1.

Direction Twenty-eight routine monitoring Quarterly.

Gamma dose quarterly.

g)

Radiation stations either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, FNE, R#f, NW, W, WNW),

in the general area of the SITE BOUNDARY An outer ring of stations, one in i

each meteorological sector, other than those sectors entirely over w

water (N, NE, l@lE, Met, !#f, W, WNW),

g

- in the 6-to 8-km range from the sites and w

0 The balance of the stations to be.

placed in special interest areas such as population centers, nearby residences, schools, and in one or

- two areas to serve as control stations.

I

=mo 29 4 40.i u, ~

U1 m-e t

e t

e 6

4 i

s

.m

TABLE 3.12.1-1 (Continued) 20 M

RADIOIDGICAL DWIRCMENTAL MJNIMRDC PROGRAM E

@ Exposure Pathway Number of Sa gles M

and Sacpling and Type and Frequency g

8 and/or Samle Samle Iocations Collection Frecaency of Analysis s

2.

Airborne Radioiodine ard Sa@les from five locations:

Continuous sanpler Radiciodine Canister:

Particulates operation with sam le I-131 analysis weekly.

Three sam les from close to the collection weekly, or three SITE BOUNDMtY locations, more frequently if in different sectors, of the required by dust Particulate Ser.plers highest calculated annual loading.

Gross beta radioactivity average ground-level D/Qs analysis following I3I one samle from the vicinity filter changes ami g43 of a comunity having the highest gama isotopic analysis calculated annual average ground-of composite (by location) level D/Q: and quarterly.

One sa mle from a control location, as for exanple 15 to 30 km distant w

and in the least prevalent wind g

direction.

W 3.

Waterborne I4) a.

Surface Two samples Cocposite sanple over Gama isotopic analysis m nthly. Couposite for 1-month period.(5) tritium analysis quarterly.

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a a

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m M

TABLE 3.12.1-1 (Continued)

N<

RADIOIOGICAL DNIRO'4 ENTAL MDNI'N)RDC PROGRAM e

Nurter of Sa@les

@ Exposure Pathway and

, Sa@ ling and type and Frequency gg) y and/or Sanple Samle Locations Collection Frecuency of Analysis s

3.

Waterborne (Continued) b.

Drinking One sa@le of each of one to Co @csite sa@ le I-131 analysis on each three of the nearest water over 2-week period (5) corrposite when the dose supplies that could be when I-131 analysis calculated from the consuirp-affected by its discharge.

is performeds m nthly tion of the water is greater cortposite othemise.

(6) Com-y One sanple from a control posite for gross beta gg) location.

and game isotopic analyses monthly. Conposite for tritium analysis quarterly.

III c.

Sediment One sanple from area with semiannually.

Gama isotopic analysis from existing or potential semiannually.

shoreline recreational value.

4.

Ingestion w

III a.

Milk Sanples from milking animals Seminenthly when Gama isotopic and I-131 1

in three locations within Skm animals are on analysis s =t=r*hly when W

distance having the highest pastures monthly at animals are on pastures dose potential. If there are other times.

monthly at other times.

none, then one sanple from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.(6)

One sanple from milking animals at a control location 15 to 30 km distant and in the gyO least prevalent wind, direction.

<: ioe

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l i

'og TABLE 3.12.1-1 (Continued)

o W

RADIOLOGICAL DWIROtMDfrAL M21I'IORDG PPOGRAM i

@ Exposure Pathway Number of Sanples H

and Sanpling and Type and Frequency ggy 8

and/or Sanole Sanole Locations Collection Frecuency of Analysis v

4.

Ingestion (Continued)

III b.

Fish and One sat:ple of each comercially Sanple in season, or Ganrna isotopic analysis Inverte-and recreationally inportant semiannually if they on edible portions.

brates species in vicinity of plant are not seasonal.

discharge area.

One sample of same species in areas not influenced by plant discharge.

I4I c.

Food Sample of three different kinds Monthly during Gama isotopic ard I-131 Products of broad leaf vegetation grown growing season.

analysis.

nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sanpling is w

not perfonred.

s" I4I One sanple of each of the simi-Monthly during Ganna isotopic and I-131 w

lar broad leaf vegetation grown growing season.

analysis.

15 to 30 km distant in the least prevalent wind direction if milk sampling is not performed.

E'2'

.o8

.D.

E;

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9

ODCM Page: 160 Rev.: 5 l

TABLE 3.12.1-1 (Continued) l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

TABLE NOTATIONS Sample locations are given on the figure and the table in the ODCM.

i l

(1)

Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,' October 1978, and to '

Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling ec;uipment.

If specimen's are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.

It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made with 30 days in the Radiological Environmental Monitoring Program given in the ODCM.

Pursuant to Control 6.14, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM, including a revised figure (s) and j

table for the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location (s) for obtaining

)

samples.

(2) 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 1

addition to, integrating dosimeters. For the purposes of this tab', a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

(The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.)

(3)

Airborne particulate sample filters shall be analyzed for gross beta

~

radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.

If gross beta activity in air particulate samples is l

greater than 10 times the yearly mean of control samples, gamma isotopic I

analysis shall be performed on the individual samples.

l r

PERRY - UNIT 1 3/4 3-7

l ODCM Pign:

161 Rev.:

5 TABLE 3.12.1-1 (Continued)

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

(5) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow.

In this program composite sample aliquots shall be collected.

at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly)'in order.to assure obtaining a representative sample.

(6) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

I h

f

+=

PERRY - UNIT 1 3/4 3-8

m M

TABt2 3.12.1-2 I

W REPORTING LEVELS FOR RADI0 ACTIVITY CCNCENTRATIONS IN ENVIR0t4GNTAL SAMPLES Reporting Ievels k

4 l

18ater Airborne Particulate Fish Milk Food Pro & acts g

3 Analysis (pCi/1) or Gases (pCi/m )

(pCi/Kg, wet)

(pC1/1)

(pCi/kg, wet) a 4

H-3 2 x 10 m

m m

m M

4 Mn-54 1x1 m

3 x 10 m

m 4

I Fe-59 4 x 10 m

1 x 10 m

m 3

4 co-58 1 x 10 m

3 x 10 m

m 2

4 i

Co-60 3 x 10 m

1 x 10 m

m 2

4 Zn-65 3 x 10 m

2 x 10 m

m 2

Zr-Nb-95 4 x 10 NA m

m m

g" I-131 2

0.9 2

m 3

1 x 10 3

3 w

Cs-134 30 10 1 x 10 60 1 x 10 I

3 3

Cs-137 50 20 2 x 10 70 2 x 10 2

2 Ba-La-140 2 x 10 m

m 3 x 10 g

"For drinking water sanples. This is a 40 CFR Part 141 value.

ll? ;F

. 2.. U

?

m e

m t9 TABLE 4.12.1-1 (a), (b), (c) l MAXIMLN VALUES FOR 'lHE IDWER LIMITS OF DETECTION (LI.D)

IN ENVIROtHDfrAL SAMPLES e

i Airborne Particulate Broad Imaf W

Water or Gas Fish Milk Vegetation Sediment Analysis (pC1/1)

(pCi/m )

_(pCi/kg, wet)

(pC1/1)

(pCi/kg, wet)

(pCi/kg dry) 4 Gross beta 4

1 x 10-2 NA NA NA E

H-3 2000*

NA NA NA NA NA Mn-54 15 NA 130 NA NA NA Fe-59 30 NA 260 NA NA NA Co-58,60 15 NA 130 NA NA NA 2n-65 30 NA 260 NA NA NA Zr-95 30 NA NA NA NA NA R

Nb-95 15 NA NA NA Nk NA a

I-131 1**

7 x 10-2 NA 1

60 NA w

h Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6 x 10-2 150 18 80 180 Ba-140 60 NA NA 60 NA NA Ia-140 15 NA NA 15 NA NA

• If no drinking water pathway exists, a value of 3000 pCi/1 may be used.

• • If no drinking water pathway exists, a value of 15 pCi/1 may be used.

m,o us w i

O i

s

m...

i ODCM l

Page:

164 l

Rev.:

5 i

i TABLE 4.12.1-1 (Continued)

HAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

TABLE NOTATION aAcceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

bTable 4.12-1 indicates acceptable detection capabilities for radioactivs materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely. concluding that a blank observation represents a 'real' signal.

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

4.66 sb "E

V 2.22-Y exp(-AAt) where LLD is the "a priori' lower limit of detection as defined above (as pCi per unit mass or volume).

s is the standard deviation of the background counting rate or of the b

counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration) i V

is the sample size (in units of mass or volume) 2.22 is the number of disintegrations per minute per picocurie Y

is the fractional radiochemical yield (when applicable) 1

.is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of s used in the calculation of the LLD for a particular measurement w

system should 15e based on the actual observed variance of the background l

counting rate or of the counting rate of the blank samples (as appropriate) i rather than on an unverified theoretically predicated variance.

I I

PERRY - UNIT 1 3/4 3-11

T I

ODCM Paga:

165 l

Rev.:

5 TABLE 4.12.1-1 (Continued) 1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

TABLE NOTATION (continued)

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

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

>osteriori (after the fact) limit for a particular measurement. Occasionally

.)ackground fluctuations, unavoidable small sample size, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors should be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.

~

c I

This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall i

also be analyzed and reported in the Annual Radiological Environmental

)

Operating Report pursuant to Control 6.9.16.

{

PERRY - UNIT 1 3/4 3-12

ODCM Page:

166 Rev.:

5 RADIOLOGICAL ElWIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.e.2, a land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest 2

milk anjnal, the nearest residence and the nearest garden

• of greater than 50 m (500 ft ) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, identify the new location (s)* in the next Annual Radioactive Effluent Release Report, pursuant to Control 6.9.1.7.

b.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which milk and/or broad leaf vegetation samples are currently being obtained in accordance with Control 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days.

If no milk and/or brord leaf vegetation samples are identified in the new sector with the highest D/0 value, then the next sector with the highest D/Q value will be considered and so on until a sampling location can be established. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s),

via the same exposure pathway may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.*

Identify the new location (s) in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table (s) for the ODCM reflecting the new location (s),

c.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.

• Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 3.12.1-1 shall be followed, including analysis of control samples.

PERRY - UNIT 1 3/4 3-13 i

(

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l ODCM Page:

167 Rev.:

5 RADIOLOGICAL EINIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 6.8.4.e.3, analyses shall be performed on radioactive materials that correspond to samples required by Table 3.12.1-1.

These materials are supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

j i

APPLICABILITY: At all times.

1

\\

ACTION:

I With analy;,es not being performed as required above, report the a.

corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to control 6.9.1.6.

b.

The provisions of Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required j

Interlaboratory Comparison Program shall be included in the Annual Radiological i

Environmental Operating Report pursuant to Control 6.9.1.6.

t PERRY - UNIT 1 3/4 3-14

l l^

occM Page:

168 Rev.: 5 t

l l

I BASES FOR l

l SECTIONS 3.0 AND 4.0 CONTROLS AND l

SURVEILLANCE REQUIREMENTS I

NOTE l

The BASES contained in succeeding pages summarize l

the reasons for the Control.s in Section 3.0 and 4.0, but are not part of these Controls.

l l

i l

i

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l l

l 9

w

ODCM Page:

169 Rev.:

5

_3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY BASES Controls 3.0.1 through 3.0.4 establish the general requirements applicable to the Appendix C Controls. These requirements are derived from the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36(c)(2) for plant Technical Specifications.

Control 3.0.1 establishes the Applicability statement within each individual control as the requirement for when (i.e., in which OPERATIONAL i

CONDITIONS or other specified conditions) conformance to the Control is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Control are not met.

It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary remcval of a system (s) or component (s) from service in lieu i

of other alternatives that would not result in redundant systems or components being inoperable.

There are two basic types of ACTION requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements.

In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met. The second type of ACTION requirement specifies a time limit in which

~

conformance to the conditions of the Control must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits.

If these actions are not completed within the allowable outage time limits, a shutdown is rcquired to place the facility in an OPERATIONAL CONDITION or other specified condition in which the control no longer applies.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Control is not met..The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems.

Individual controls may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed.

When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new control becomes applicable.

In this case, the time limits of the ACTION requirements would apply from the point in time that the new control becomes applicable if the requirements of the Control are not met.

PERRY - UNIT 1 B 3/4 0-1

ODCM Page:

170 Rev.:

5 3/4.0 APPLICABILITY BASES (Continued)

Control 3.0.2 establishes that noncompliance with a control exists when the requirements of the Control are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this control is to clarify that (1) implementation of the ACTION requirement within the specified time interval constitutes compliance with a control, and l,

(2) completion of the remedial measures of the ACTION requirements is not required when compliance with a control is restored within the time interval l

specified in the associated ACTION requirements.

Control 3.0.3 establishes the shutdown ACTION requirements that must be I

implemented when a Control is not met and the condition is not specifically l

addressed by the associated ACTION requirements. The purpose of this control is to delineate the time limits for placing the unit in a safe shutdown CONDITION l

when plant operation cannot be maintained within the limits for safe operation defined by the Control and its ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coclant system and the potential for a plant upset that could challenge safety systems under conditions for which this control applies.

If remedial measures permitting limited continued operation of the facility-under the provisions of the ACTION requirement are completed, the shutdown may l

be terminated. The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Control. Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

The time limits of Control 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in COLD l

SHUTDOWN when a shutdown is required during POWER operation.

If the plant is in a lower CONDITION of operation when a shutdown is required, the time limit for reaching the next lower CONDITION of operation applies. However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable ~

time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced.

For example, if STARTUP is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach HOT l

SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Therefore, if I

r 'edial measures are completed that would permit a return to POWER operation, a l

pelalty is not incurred by having to reach a lower CONDITION of operation in less than the total time allowed.

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171 Rev.:

5 3/4.0 APPLICABILITY BASES (Continued)

The same principle applies with regard to the allowable cutage time limits of the ACTION requirements, if compliance with the ACTION requirements for one control results in entry into an OPERATIONAL CONDITION or condition of operation for another control in which thc requirements of the Control are not met.

If the new control becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second control.

However, the allowable outage time limits of ACTION requirements for a higher CONDITION of operation may not be used to extend the allowable outage time that.

is applicable when a Control is not met in a lower CONDITION of operation.

The shutdown requirements of Control 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual controls define the remedial measures to be taken.

Control 3.0.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a control is not met.

It precludes placing the facility in a higher CONDITION of operation when the requirements for a Control are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in CONDITIONS were permitted. The purpose of this control is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered when corrective action is being taken to obtain compliance with a control by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPERATIONAL CONDITION or other specified condition may be made in accordance with the provisions of the ACTION requirements. The provisions of this control should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of Control 3.0.4 do not apply because they would delay placing the facility in a lower CONDITION of operation.

Controls 4.0.1 through 4.0.5 establish ~he general requirements applicable c

to Surveillance Requirements. These requirements are derived from those for Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3) for plant Technical Specifications.

Control 4.0.1 establishes the requirement that surveillances must be

~

performed during the OPERATIONAL CONDITIONS or other conditions for which the requirements of the Controls apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this control is to ensare that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Controls are applicable.

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3R,O APPLICABILITY BASES Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Control do ist apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a control.

Control 4.0.2 establishes the limit for which the specified time intierval for Surveillance Requirements may be extended.

It permits an allowable extension of the specified surveillance interval to facilitate surveillance scheduling and consideration of plant opcrating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length cf a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Control 4.0.2 is j

based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

Control 4.0.3 establishes that the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Control 4.0.2, is a condition that constitutes a failure to meet the OPERABILITY requirements for a Control. Under the provisions of this control, systems and components are assumed to be OPERABLE when Surveillance Requirements-have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are foand or known to be inoperable although still meeting the Surveillance Requirenents. This control also clarifies that the ACTION requirements are applicable uhen Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Control 4.0.3.

However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Control 4.0.2.,

constitutes a failure to meet the OPERABILITY requirements for a Control and any reports required by 10 CFR 50.73 shall be determined based on the length of time the surveillance interval has been exceeded, and the corresponding Control ACTION time requirements, similar to those discussed in NUREG-1022, Supplement 1.

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173 Rev.:

5 3/4.0 APPLICABILITY BASES (Continued)

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g., Control 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate-time limit to complete Surveillance Requirements that have not been performed. The purpose of j

this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remsdial measures would be required that may preclude the completion of a surveillance.,

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit.for the i

completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Control 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply. However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

Contrcl 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement. The purpose of this control-is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well as startup.

Ur. der the provisions of this control, the applicable Surveillance Requirements must be performed within the specified surveillance interval to assume that the Controls are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Control 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation.

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174 Rev.: 5 INSTRUMENTATION i

BASES 3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.9 RADIOACTIVE LIQUID EFFLUENT MONI'IORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior j

to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this t

instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.7.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l

The radioactive gaseous effluent instrumentation is provided to monitor and j

control, as applicable, the releases of radioactive materials in gaseous i

effluents during actual or potential releases of gaseous effluents. The alarm setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

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175 Rev.: 5 3/4.11 RADIOACTIVE EFFLUEtES BASES 3/4.11.1 LIQUID EFFLUEIRS 3/4.11.1.1 CONCENTRATION This Control 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 Part 20, Appendix B, Table II, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A. design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

This Control applies to the release of radioactive materials in liquid effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).

Detailed discussion of the LLD, and other detection limits, can be found in:

(1) Currie, L.

A.., " Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,' NUREG/CR-4007 (September, 1984).

(2)

HASL Procedures Manual, HASL-300 (revised annually).

3/4.11.1.2 DOSE This Control is provided to implement the requirements of. Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.A of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I which assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept 'as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of -

the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEHBER OF THE PUBLIC through appropriate pathwa3s is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive PERRY - UNIT 1 B 3/4 2-1

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176 Rev.: 5 RADIOACTIVE EFFLUDTPS BASES 3/4.11.1.2 DOSE (Continued) materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,' Revision I, October 1977 and Regulatory Guide 1.113,

" Estimating Aquatic Dispersion of Effluent from Accidental and Routine Reactor

^

Releases for the Purpose of Implementing Appendix I," April 1977.

This Control applies to the releass of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

3/4.11.1.3 LIQUID RADWASTE TREA'IMENT SYSTEM The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept 'as low as is reasonably achievable.' This Control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limit goyerning the use of appropriate portions of the liquid radwaste treatment system.

.E specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

This Control applies to the release of liquid effluents from each reactor 1

at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing the i

system.

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177 Rev.:

5 RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This Control is provided to ensure that the dose any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The ann'ual dose rat.a limits are those associated with the concentrations of those MPCs as.

described in Regulatory Guide 1.109. These limits provide reasonable assurance that radioactive material discharged in~ gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.

This Control applies to the release of radioactive materials in gaseous effluents from all reactors at the site. The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limit of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in:

(1) Currie, L.

A., ' Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and. Environmental Measurements,* NUREG/CR-4007 (September 1984).

(2)

HASL Procedures Manual, HASL-300 (revised annually).

3/4.11.2.2 DOSE - NOBLE GASES This Control is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.B of Appendix I.

The ACTION statements provide the

~

required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept 'as low as is reasonably achievable.' The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways PERRY - UNIT 1 B 3/4 2-3

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178 Rev.:

5 RADIOACTIVE EFFLUEtTPS BASES 3/4.11.2.2 DOSE - NOBLE GASES (Continued) is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, ' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,' Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are made using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or are based upon the historical average atmospheric conditions.

This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseaus effluents from the shared system are proportioned among the units sharing that system.

3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM This Control is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section II.C of Appendix I.

Tne ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably-achievable.' The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A. of Appendix I that conformance with the guides of Appendix I be shown by calculational procures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methedology provided in Regulatory Guide 1.109, ' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with'10 CFR Part 50, Appendix I,' Revision 1, October 1977 and Regulatory Guide 1.111, ' Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,' Revision 1, July 1977. These equations also provide for determining the actual doses using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or are based upon the historical average atmospheric conditions.

The release rate specifications for iodine-131, iodine-133, tritium and radionuclides in particulate form are dependent on the existing radionuclide pathway to man in the areas at and beyond the SITE BOUNDARY.

The pathways which were examined in the development of these PERRY - UNIT 1 B 3/4 2-4

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179 Rev.:

5 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE - 10 DINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (Continued) calculations were:

(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man', and (4) deposition on the ground with subsequent exposure of man.

This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

3/4.11.2.4 AND 3/4.11.2.5 GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM AND VENTILATION EXHAUJT TREA'IMENT SYSTEMS The OPERABILITY OF THE GASEOUS RADWASTE TREA'IMENT (OFFGAS) SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEMS ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of the systems be used, when specified, provides reasonable assurance that the releases of radio-active materials in gaseous effluents will be kept 'as low as is reasonably achievable."

This Control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportional among the units sharing that system.

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180 Rev.:

5 RADIOACTIVE EFFLUENTS BASES 3/4.11.4 TOTAL DOSE This Control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units including outside storage tanks, etc. are kept small.

The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR e'v.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

[

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181 Rev.:

5 l

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials _

and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation.

Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in tenns of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories.

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

Detailed discussion of the LLD, and other detection limits, can be found in:

(1) Currie, L. A. ' Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,' NUREG/CR-4007 (September 1984).

(2) HASL Procedure Manual, HASL-300 (revised annually).

3/4.12.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program given in the ODCM are made if required by the results of the census. The best information from door-to-door survey, visual or aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of

~~

Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:

(1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2 PERRY - UNIT 1 B 3/4 3-1

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182 Rev.:

5 RADIOLOGICAL ENVIRONMENTAL MONI'IORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM

]

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

i 4

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183 Rev.:

5 l

l i

6.0 ADMINISTRATIVE CONTROLS

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e

>W

ODCM l

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184 Rev.: 5 ADMINISTRATIVE CONTROLS ANNUAL REPORTS ANNUAL RADIOLOGICAL EINIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality and shall include copies of reports of the preoperational Radiological Environmental Monitoring Program of the Onit for at least two years prior to initial criticality in addition to the following.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate).

and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by control 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all locations specified in the table and figures in the Offsite Dose Calculation 1

Manual, as well as summarized and tabulated esults of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some individual results are not available for inclusion with the report, the report shall be' submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary i

report.

The reports shall also include the following: a summary description of the i

Radiological Environmental Monitoring Program; at least two legible maps

• covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12.1-2 but are not the result of plant effluents, pursuant to ACTION b of Control 3.12.1; and discussion of all analyses in which the the LLD required by Table 4.12.1-1 was not achievable.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

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6.9.1.7 Routine radioactive release reports covering the operation of the unit during the previous calencar year shall be submitted annually. The report must be submitted as specified in 10CFR50.4 and the time between submission of reports must be no longer than 12 months.

• 0ne map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

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185 Rev.:

5 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Annual Radioactive Effluent Release Report shall include a summary of the yG :tities of radioactive liquid and gaseous effluents released from the unit as outlined in Regulatory Guide 1.21, ' Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with da:a summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report submitted each year shall include a summary of hourly meteorological data collected over the previous calendar year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions 1

of wind speed, wind direction, and atmospheric stability.* This report shall include an assessment of the radiation doses due to the radioactive liquid and i

gaseous effluents released from the unit or station during the previous calendar year. This report shall also include an assessment of the radiation doses from 4

radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their j

activities inside the SITE BOUNDARY (Figure 5.1.1-1 of Technical Specifications)

M during the report period. All assumptions used in making these assessments, L

i.e., specific activity, exposure time, and location, shall be included in these reports. The assessment of radiation doses shall be performed in accordance j

with the methodology and parameters in the OFFSITE DOSE CALCULATION i

MANUAL (ODCM).

i l

The Annual Radioactive Effluent Release Report submitted each year shall also include an assessment of radiation doses to the likely most exposed MEHBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental

)

Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

• In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

PERRY - UNIT 1 4-2 PIC-1/VAX/Page 13 of 13

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186 Rev.:

5 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM),

pursuant to PNPP Technical Specification 6.14, as well as any major change to Liquid or Gaseous Treatment Systems pursuant to Control 6.15.

It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 3.12.2.

The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was'not corrected within the time specified in Control 3.3.7.9 or 3.3.7.10, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of Specification 3.11.1.4.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted in accordance with 10 CFR50.4 within the time period specified for each report.

t 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10 Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

Records of surveillance activities, inspections, and calibrations a.

required by these Controls.

6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREA'IMENT SYSTEMS

• 6.15.1 Licensee initiated major changes to the radioactive waste systems, liquid, gaseous and solid:

• Licensee may choose to submit the information called for in this Control as part of the annual USAR cpdate.

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ODCM l

P:g3: 187 Rev.: 5 ADMINISTRATIVE CONTROLS MAJOR CHANGES TO RADIOACTIVE WASTE TREATMEfff SYSTEMS (Continued) 1.

Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each change shall contain:

A summary of the evaluation that led to the determination a.

that the change could be made in accordance with 10CFR50.59; b.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.

A detailed description of the equipment, components and processes involved and the interfaces with other plant systems d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; An evaluation of the change which shows the expected maximum e.

exposures to MEMBERS OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto; f.

A comparison of the predicted releases of rsdioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and h.

Documentation of the fact that the change was reviewed and

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found acceptable by the PORC.

2.

Shall become effective upon review and acceptance by the PORC.

Records The following records are generated by this document:

Quality Assurance Records Annual Radioactive Effluent Release Report Non-Ouality Records l

l None t

6 k

PERRY - UNIT 1 4-4 l

l l

ODCM Page:

188 i

Rev.: 5 REFERENCES 1.

Title 10, ' Energy," Chapter 1, Code of Federal Regulations; Part 20, U.S. Government Printing Office, Washington, D.C.

20402, January 1, 1984.

2.

Title 10, ' Energy,' Chapter 1, Code of Federal Regulations; Part 50; U.S. Government Printing Office, Washington, D.C.

20402, January 1, 1984.

3.

Title 40, " Protection of Environment," Chapter 1, Code of Federal Regulations, Part 190, Federal Register, Vol. 42, Washington, D.C.

20402, January 13, 1977.

4.

U.S. Nuclear Regulatory Commission, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," USNRC NUREG-0133, Washington, D.C.

20555, October, 1981.

5.

U.S. Nuclear Regulatory Commission, " Draft Radiological Effluent Technical Specifications for PWR's," USNRC NUREG-0473, Revision 2, Washington, D.C.

20555, February, 1980.

6.

Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-cooled Nuclear Power Plants," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, June 1974.

7.

Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 0, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, March 1976.

Regulatory Guide 1.109, " Calculation of Annual Doses to Man from 8.

Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, ' Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, October 1977.

9.

Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, July 1977

10. Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,' Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, April 1977.

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ODCM Page:

189 - LAST Rev.:

5 REFERENCES (Cont.)

11. Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Streams and the Environment,* U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, February 1979.

3 12.

U.S. Nuclear Regulatory Commission, " Branch Technical Position,*

Revision 1, Washington, D.C.

20555, November 1979.

13. Perry Nuclear Power Plant, Unit 1 and 2, " Final Safety Analysis Report,* Amendment 14, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, August 1984.

14.

Perry Nuclear Power Plant, Units 1 and 2, " Environmental Report, Operating License S bge,* Supplement 3, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, November 1981.

15.

Perry Nuclear Power Plant, Units 1 and 2, " Radiological Environmental Monitoring Program Manual,* The Cleveland Electric Illuminating Company, Perry, Ohio 44081, February 1985.

l 16.

' Midas User's Manual, for the Cleveland Electric Illuminating Company, Perry Nuclear Power Plant,* Pickard, Lowe and Garrick, Washington, D.C.

20036, July 1983.

17.

Kocher, D.C., ' Radioactive Decay Data Tables,* Technical Information Center, U.S. Department of Energy, Springfield, Virginia 22161, j

September 1985.

i 18.

1989 Engineering Report ' Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP, (Ref. S0-11552 "E').

19.

Perry Environmental Report Operating License Stage, Table 5.1-10

" Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP and Q&R Page 2.1-2.

20.

PNPP Ohio Power Siting Commission application of August 1974, Appendix 1304-C-2, Table IV-A-2.

21. Total angler Catch (1987 annual) for Each Grid Location; per letter from Michael R. Rawson, Fairport Fisheries Research Station, Ohio Department of Natural Resources (6-20-88).

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