ML18038A422

Rev 4 to Offsite Dose Calculation Manual. W/Two Oversize Figures

ML18038A422
Person / Time
Site:	Nine Mile Point
Issue date:	02/27/1987
From:	Duell J, Roman T, Stuart C NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17055E248	List: ML17055E247 ML17055E250 ML18038A422 ML18038A423
References
PROC-870227, NUDOCS 8810210146
Download: ML18038A422 (234)

Text

NINE MILE POINT'UCLEAR STATION NINE MIl.E PONT UNIT 1 OFF-SITE DOSE CALCULATION MANUAL (ODCM)

DATE AND INITIAl.S APPROVALS SIGNATURES REVISION 3 REVISION 4 REVISION 5 Supervisor Chemistcy and Radiochemistry J. N. Duell ~

7 Chemistry and Radiat'on Management Supeci C. L. Stuact Station Supec'intende NMPNS Unit l T. W. Roman General Supecintendent Nuclear Genecation T. J. Perkins Summac of Pa es Revision 4 (Effective ~~~7i 87 )

~Pa es Date 1- 116 February 1987 NIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE USED AFTER FEBRUARY 1989 SUBJECT TO PERIODIC REVIEW.

88 1021014b 880830 PDR ADOC~ 05000220PNU R

OFF-SITE DOSE CALCULATION MANUAL NINE MILE POINT UNIT 1 February, 1987

t ODCM NINE MILE POINT MILE 1 TABLE OF CONTENTS

~pa e

1.0 INTRODUCTION

2' LIQUID EFFLUENTS 2 ' Setpoint Determinations 2.1 ~ 1 Basis 2' ~ 2 Service Water System Effluent Alarm Setpoint 2.1.3 Liquid Radwaste Effluent Alarm Setpoint 2.1.4 Discussion 2,1.4.1 Control of Liquid Effluent Batch Discharges 2.1.4.2 Simultaneous Discharges of Radioactive Liquids 2.1.4.3 Sample Representativeness 2.1.4.4 Liquid Radwaste System Operation 2.1.4.5. Service Water System Coptamination 10 2.2 Liquid Effluent Concentration Calculation 2.3 Dose Determinations 12 2.3.1 Maximum Dose Equivalent Pathway 12 3.0 GASEOUS EFFLUENTS 19 j

3.1 Setpoint Determinations 19 3.1.1 Basis 19 3.1.2 Stack Monitor Setpoints 20 3.1.3 Recombiner Discharge (Off Gas) Monitor Setpoints 22 3.1.4 Emergency Condenser Vent Monitor Setpoint 3.1.5 Discussion 24 3.1.5.1 Stack Effluent Monitoring System Description 24 3~1~ 5. 2 RAGEMS 24 3.1.5.3 Stack Sample Flow Path and OGESMS 25

ODCM NINE MILE POINT MILE 1 TABLE OF CONTENTS (Cont'd)

~Pa e 3.1.5. 4 Sample Frequency/Sample Analysis 27 3.1.5.5 I-133 Estimates 27 3.1.5.6 Gaseous Radwaste Treatment System Operation 28 3.2 Dose and Dose Rate Determination 29 3.2.1 Dose Rate 31 3.2.1 ~ 1 Noble Gases 32

3. 2.1. 2 Tritium, Iodines and 'Particulates 32 3 ~ 2.2 Dose 34 3.2.2.1 Noble Gas Air Dose 34 3 ~ 2.2.2 Radioiodine, Tritium and Particulates 36

3. 2. 2:3 Accumulating Doses 37 3.3 Critical Receptors 38 3~4 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 39 l

4,0 40 CFR 190 REQUIREMENTS 40 4.1 Evaluations of Doses From Liquid Effluents 43 4.2 Evaluation of Doses From Gaseous Effluents 46 4.3 Evaluation of Doses From Direct Radiation 46 4,4 Doses to Members of the Public Within the Site Boundary 47 5.0 ENVIRONMENTAL MONITORING PROGRAM ~

52 5.1 Sampling Stations 52 5 ' Interlaboratory Comparison Program 53 5.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements.

7 ODCM NINE MILE POINT MILE 1 TABLE OF CONTENTS (Cont'd)

Table l-l Rap ap3 i Values for the NMP-1 Fac i 1 i ty 57 Table 1-2 Parameters for the Liquid Effluent Pathway 58 Table 2-1 Average Energy Per Disintegration 59 Table 3-1 Critical Receptor Dispersion Parameters for Ground Level and Elevated Releases 60 Table 4-1 Dose Factors for Noble Gases 61 Tables 4-2 to 4-20 R Values 62 Table 5-1 NMP-1 Radiological Environmental Monitoring Program Sampling Locations 81 Appendix A Dose Parameters for Iodine 131 and 133, Particulates and Tritium 85 Appendix B Diagrams of Liquids and Gaseous Radwaste Treatments Systems 98 Appendix C Dispersion Calculation Tables 109

i) 1 o0 INTRODUCTION The Offsite Dose Calculation Manual (ODCM) provides the methodology to be used for demonstrating compliance with the Radiological Effluent Technical Specifications (RETS), 30 CFR 20, 10 CFR 50, and 40 CFR 190 ~ The contents of the ODCM are based on Draft NUREG-0472, Revision 3, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors," September 1982; Draft NUREG-0473, Revision 2, "Radiological Effluent Technical Specifications for BWR's," July 1979; NUREG 0133, "Preparation of Radiological Effluent Technical Specifica'tions for Nuclear Power Plants," October 1978; the several Regulatory Guides referenced in these documents; and, communication with the NRC staff.

Section 5 contains a detailed description'of the Radiological Environmental Monitoring (REM) sampling locations ~

Should it be necessary to revi'se the ODCM, these revisions will'e made in accordance with Technical Specifications.

E P 2.0 LIQUID EPPLUENTS 2.1 Setpoint Determinations 2.1.1 Basis Monitor setpoints will be established such that the concentration of radionuclides in the liquid effluent releases in the discharge canal will not exceed those concentrations as specif i ed in 10 CPR 20, Appendix B, Table II, Column 2.

Setpoints for the Service Water System Effluent Line will be calculated quarterly based on the radionuclides identified during the previous year's 'eleases from the liquid radwaste system or the isotopes identified in the most recent radwaste release or other identified probable source. Setpoints for the Liquid Radwaste Effluent Line will be based on the radionuclides identified in each batch of liquid waste prior to its release.

After release, the Liquid Radwaste monitor setpoint may remain as set, or revert back to a setpoint based on a previous Semi-Annual Radioactive Effluent Release Report, or install blank flange in the discharge line and declare inoperable in accordance with the technical specification.

Since the Service Water System effluent monitor and Liquid Radwaste effluent monitor can only detect gamma radiation, the alarm setpoints are calculated by using the concentration of gamma emitting isotopes only (or the corresponding MPC values for the same isotopes, whichever are higher) in the E( Cilml) expression (Section 2.1.2, 2.1.3)'.

~2

JI 2.1.1 (Cont'd)

The Required Dilution Factor is calculated using concentrations of all isotopes present (or the corresponding HPC values for the same isotopes, whichever are higher) including tritium and other non-gamma emitters to ensure that all radionuclides in the discharge canal do not exceed 10 CFR 20 limits.

2.1.2 Service Water System Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Service Water System Effluent Line Honitor shall be contained in the Nine Hile Point Station Procedures. These methods shall be in accordance with the following:

Setpoint (Hi-Hi alarm)<0.9 Setpoint (Hi alarm) <0.7 7(<<Ci/ml) i (CF) w(<<Ci/ml) i (CF)

~

TDF /F I;

TDF/Fsw I

+

+

background background Z [(iiCi/ml) T/HPC j

( Ci/ml) i+ ~ concentration of gamma emitting isotope i in the sample, or the corresponding HPC of gamma emitting isotope i (HPC)i~,whichever is higher (units ~ uCi/ml).

(vCi/ml)iT ~ conc'entration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or corresponding HPC of isotope i, HPCi, whichever is higher (units ~ pCi/ml).

TDF ~ Total Dilution Flow (units ~ gallons/min)

Fsw Service Water Flow (units ~ gallons/min)

CF monitor calibration factor (units = net cpm/sCi/ml) liquid e ftluent radioac t ivity concentrations limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.

~

I

2.1.2 (Cont'd)

Sample ~ Those nuclides present in the previous batch release from the liquid radwaste effluent system or those nuclides present in the last Semi-annual Radioactive Effluent Release Report (units ~ pCi/ml) or those nuclides present in the service water system.>>

(MPC)i ~ same as MPCi but for gamma emitting nuclides only.

0.9 and 0.7 ~ factors of conservatism to account for inaccuracies.

Z[(yCi/ml)iT/MPCi] = Required Dilution Factor. If MPC valves are used in the Z(yCi/ml)i , they must also be used in calculating RDF (numerator).

F/Fsw ~ hctual Dilution Factor For periods with known 'reactor water to RCLC system leakage, RCLC maximum permissible concentration may be prudently substituted for the above.

2.1.3 Liquid Radwaste Effluent Line hlarm Setpoint The detailed methods for establishing setpoints for the Liquid Radwaste Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures. These methods shall be in accordance with the following:

Setpoint (Hi-Hi alarm), <0.9 Z(MCi/ml)i~ (CF) TDF/Fre

+background Z ((pCi/ml)iT/MPCi)

Setpoint (Hi alarm) <0.7 Z(yCi/ml)i~ (CF) TDF/Fre +background Z [ (yCi/ml)iT/MPCi~

(yCi/ml)ig ~ concentration of gamma emitting isotope i in the sample or the corresponding MPC of gemma emitting isotope i (MPC)i whichever is higher.

(yCi/ml)iT ~ concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or the corresponding MPC of isotope i MPCi whichever is higher. (units ~ yCi/ml)

TDF ~ Total Dilution Flow (units ~ gallons/min)

Fre Radwaste Effluent Flow (units ~ gallons/min) monitor calibration factor (units ~ net cps/yCi/ml)

T MPCi liquid effluent radioactivity concentration limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2, for those nuclides detected by spectral analysis of the contents of the radwaste tanks to be released. (units ~ yCi/ml)

~

(MPC)ig ~ same as MPCi but for gamma emitting nuclide only.

0.9 and 0.7 ~ factors of conservatism to account for inaccuracies.

[(yCi/ml)iT/MPCi] =Required Dilution Factor. If MPC values are used in the E(pCi/ml)i, they must also be used in calculating RDF (numerator).

Notes; (a) If TDF/Fre I [(yCi/ml)iT/MPCi ]

the discharge could not be made, since the monitor would be continuously in, alarm. To avoid this situation, F re will be reduced (normally by a factor of 2) to allow setting the alarm point at a concentration higher than tank concentration. This will also result in a discharge canal concentration at approximately 507 maximum permissible concentrat'ion.

(b) The value .used for TDF will be reduced by the fractional quantity (1-FT), where FT is tempering fraction (i.e.,

diversion of some fraction of discharge flow to the intake canal for the purpose of temperature control).

2.1.4 Discussion 2.1.4.1 Control of Liquid Effluent Batch Discharges At Nine Mile Point Unit 1 Liquid Radwaste Effluents are released only on a batch mode. To prevent the inadvertent release of any liquid radwaste effluents, radwaste discharge is mechanically isolited (blank flange installed or discharge valve chain-locked closed) following the completion of a batch release or series of batch releases.

This mechanical isolation remains in place and will only be removed P

prior to the next series of liquid radwaste discharges after all analyses required in station procedures and Technical Specification Table 4.6.15-1A are performed and monitor setpoints have been properly adjusted.

2.1.4.2 Simultaneous Discharges of Radioactive Liquids.

If during the discharge of any liquid radwaste batch, there is an indication that the service water canal has become contaminated (through a service water monitor alarm or through a grab sample analysis in the event that the service water monitor is inoperable) the discharge shall be terminated immediately. The liquid radwaste discharge shall not be continued until the cause of the service water alarm (or high grab sample analysis result) has been determined and the appropriate corrective measures taken to ensure 10CFR20, Appendix B, Table II, Column 2 (Technical Specification Section 3.6.15.a(1))

limits are not exceeded.

2.1.4.3 Sampling Representativeness This section covers Technical Specification Table 4.6.15-1 Note b concerning thoroughly mixing of each batch of liquid radwaste prior to sampling.

Liquid Radwaste Tanks scheduled for discharge at Nine Mile Point Unit/1 are isolated (i.e ~ inlet valves marked up) and at least two tank volumes of entrained fluids are recirculated prior to sampling.

Minimum recirculation time is calculated as follows:

Minimum Recirculation Time ~ 2.0(T/R)

Where:

2.0 Plant established mixing factor, unitless Tank volume, gal Recirculation flow rate, gpm.

It should be noted that the Waste Sample Tanks (WST) at Nine Hile Point Unit 1, the most common tanks utilized for liquid batch releases, contain a sparger spray ring which assist the mixing of the tank contents while it is being recirculated prior to sampling. This sparger effectively mixes the tank faster than simple recirculation.

Addit'ionally, the Hi Alarm setpoint of the Liquid Radwaste Effluent Radiation Monitor is set at a value corresponding to not more than 70K of its calculated response to the grab sample or corresponding HPC values. Thus, this radiation monitor will alarm if the grab sample, or corresponding MPC value, is significantly lower in activity than any part of the tank contents being discharged.

t 2.1.4.4 Liquid Radwaste Systems Operation Technical Soecification 3.6.16.a requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge, as necessary, to meet the concentration and dose requirements of Technical Specification 3.6.15 of the radwaste system will be based on the capability of 'tilization the indicated components of each process system to process contents of the .respective low conductivity and high conductivity collection Fight tanks:

1) Low Conductivity (Equipment Drains): Radwaste Filter and Radwaste Demin. (See B-l)

2) High Conductivity (Floor Drains): Waste Evaporator (see Fig. B-1)

Cumulative dose contributions from liquid ef fluents for the current calendar quarter and the current calendar year shall be determined as described in Section 2.3 of this manual prior to the release of each batch of liquid waste. This same dose projection of Section 2.3 will also be performed in the event that untreated liquid waste is discharged, to ensure that the dose limits of Technical Specification 3 '.15.a(2) are not exceeded. (Thereby implementing the requirements of 10CFR50.36a, General Design Criteria 60 of Appendix A and the Design Objective given in Section II-D of Appendix I to 10 CFR50).

"8-

2.1.4.4 (Cont'd)

For the purpose of dose pro)ection, the following assumptions shall be made with regard to concentrations of non"gamma emitting radionuclides subsequently analyzed off-site:

a) [H-3] >. H-3 Concentration found recent condensate storage tank analysis.

b) [Sr-89] > 4 x Cs-137 Concentration c) [Sr-90] > 0.5 x Cs-137 Concentration d) [Fe-55] > 1 x Co-60 Concentration

'Assumed Scaling Factors used in b, c, and d above represent conservative estimates derived from analysis of historical data from process waste streams. Following receipt of off-site H"3, Sr-89, Sr-90 and Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations and actual tank volumes discharged.

l '

2.1.4.5 Service Mater System Contamination Service water is normally non-radioactive. If contamination l

is suspected, as indicated by a significant increase in service water effluent monitor response, grab samples will be obtained from the service water discharge lines and a gamma isotopic analysis meeting the LLD requirements of Technical Specification Table 4.6.15-1 completed'f it is determined that an inadvertent radioactive discharge is occurring from the service water system, then:

a) h 50.59 safety evaluation shall be performed (ref. ISE Bulletin 80-10),

b) Daily service water effluent samples shall be taken and analyzed for principal gamma emitters until the release is terminated, c) hn incident composite shall be prepared for H-3, gross alpha, Sr-89, Sr-90 and Fe-55 analyses and d) Dose projections shall be performed in accordance with Section 2.3 of this manual.

hdditionally, service water effluent monitor setpoints may be recalculated using the actual distribution of isotopes found from sample analysis.

2.2 Liquid Effluent Concentration Calculation This calculation documents compliance with Technical Specification Section 3.6.1.5.a (1).

The concentration of radioactive material released in liquid effluents to unrestricted areas '(see Figure B-7) shall be limited to 6he concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2 E-4 microcurie/ml total activity.

The concentration of radioactivity from Liquid Radwaste batch releases and, if applicable, Service Water System inadvertent discharges are included in the calculation. The calculation is performed for a specific period of time. No credit taken for averaging over the calendar year as permitted by 10CFR20.106. The limiting concentration is calculated as follows:

MPC Fraction~E [Z ((pCi/ml) "F )/(MPC."E (F ))]

i s is s 1 s s Where:

MPC Fraction ~ The limiting concentration of 10 CFR 20, Appendix B,'able II, for radionuclides other than dissolved or entrained noble gases. For noble gases, the concentration shall be limited to 2 E-4 microcurie/ml total activity.

2.2 (Cont'd)

(u Ci/ml) is The concentration of nuclide i in particular effluent stream s, nCi/ml.

F The flow rate of a particular effluent s

stream s, gpm.

MPCi ~ The limiting concentration of a specific nuclide i from 10CFR20, Appendix b, Table II, Column 2 (noble gas limit is 2E-4 uCi/ml)

Z (( Ci/ml)is F )- The total activity rate of nuclide i, in all s s effluent streams s, uCi/ml*gpm z,(F,) ~ The total flow rate of all effluent streams s, gpm (including those streams which do not contain radioactivity).

A value of less than one for MPC fraction is considered acceptable for compliance with Technical Specification Section 3.6.15.a.(1).

2.3 Dose Determination 2.3.1 Maximum Dose Equivalent Pathway A dose assessment report was prepared for the Nine Mile Point Unit 1 facility by Charles T. Main, Inc., of Boston, MA. This report presented the calculated dose equivalent rates to individuals as well as the population within a 50-mile radius of the facility based on the radionuclides released in liquid and gaseous effluents during the time periods of 1 July 1980 through 31 December 1980 and from 1 January 1981 through 31 December 1981. Utilizing the effluent data

1

2. 3. 1 (Cont 'd) contained in the Semi-Annual Radioactive Effluent Release Reports as source terms, dose equivalent rates were determined using the environmental pathway models specified in Regulatory Guides 1 ~ 109 and 1 ~ 111 as incorporated in the NRC computer codes LADTAP for liquid pathways, and XOQDOQ and GASPAR for gaseous effluent pathways. Dose equivalent rates were calculated for the total body as well as seven organs and/or tissues for adults, teenagers, children, and infants ~

Prom the standpoint of liquid effluents, the pathways evaluated included fish ingestion, drinking water, and external exposure to water and sediment.

Based on the findings of the above referenced report, the maximum total body dose from all liquid pathways is received by an adult.

Similarly, the maximum total do'se to any organ is received by the teen liver. In both of these cases (i.e., adult whole body dose and teen liver dose), 99K and 98K respectively of these doses were rece ived via the fish ingestion pathway.

In order to determine the dose contribution from the release of liquid effluents, the annual dose to an adult whole body and a teen liver will be calculated for each of the significant nuclides (see Table 1-1) identified in the liquid waste based on the fish ingestion pathway utilizing the following formula:

apji ap P ip aipj exp "i p IL Where R apj 1 total annual dose (per Curie released) to organ "j" of individuals of age group "a" from all .of the nuclides "i" in pathway "p" (units =

mrem/year Ci)

U ap usage factor specifying the exposure time or intake rate for an individual of an age group "a" associated with pathway "p" (units ~ kg/year)

M mixing rates (reciprocal of dilution factor) at the point of exposure or point of harvest (units

~ dimensionless) flow rate of the liquid effluent (units ~ ft3 /sec)

B.

ip equilibrium bioaccumulation factor for nuclide "i" in pathway "p" units ~ liters/kg)

D the dose factor, specific to a specific age group aipj "a", radionuclide "i", path'way "p", and organ "j", which can be utilized to calculate the radiation dose from an intake of a radionuclide (units ~ mrem/pCi) radi'oactive decay constant of nuclide "i." (units

~ hours )

tP the average transit time required for nuclides to reach the point of exposure. For internal dose, tP is the total time elapsed between the release of the nuclides and the ingestion of the food and/or water (units ~ hours) 1100 = factor to convert from (Ci/year)/(ft 3 /sec) to PCi/liter Values for R apj i are contained in Table 1-1. All of these values of R apj i are on a per Curie basis for each of the nuclides released. Table 1-2 indicates those parameters used for selected factors of the formula.

Prior to each radioactive liquid discharge, each liquid waste tank to be discharged will be analyzed for isotope content utilizing a gamma spectroscopy system. On the basis of this analysis, projected doses to an adult whole body and a teen liver will be calculated using the following relationships:

PD i ~ 1.05 R ..

apj 1 (WB)

C.

i Li 'pj 1 (L) i Nlere PD Projected dose expected to the whole body of an adult due to the release of the identified concentration of nuclide "i".

(units ~ mrem/year) l PD Li Projected dose expected to the liver of a teenager due to the release of the identified concentration of nuclide "i" (units ~ mrem/year R ..

&pg 1 (MB) total annual dose (per Curie released) to the whole body of an adult caused by the ingestion of nuclide "i" (units = mrem/year-Curie)

R apj

..(L) 1 total annual dose (per Curie released) to the liver of a teenager caused by the ingestion of nuclide "i" (units = mrem/year-Curie)

C.

1 quanity of nuclide "i" identified as present in the release (units ~ Curies) 1.05 correction factor to account for 100% of dose, assuming that 95% of dose received is delivered via the fish ingestion pathway.

The value of 1.05 is used in the equation as a conservative factor to increase the projected dose from an anticipated release to 100%. As long as the 1.05 factor is used, doses received via the drinking water pathway (eg, tritium) need not be accounted for separately.

All projected doses calculated in this manner for each batch of liquid effluent will be summed for comparison with quarterly and annual limits, added to the doses accumulated from other releases in the quarter and year of interest. In all cases, the following relationships will hold:

Por a calendar quarter:

D <1.5 mrem total body t-D < 5 mrem for any organ Por the calendar year:

D < 3.0 mrem total body D

tc 10 mrem for any organ where D t total dose received due to liquid effluent releases If these limits are exceeded, a special report will be submitted to the NRC identifying the cause and proposed corrective actions. In addition, if these limits are exceeded by a factor of two, calculations shall be made to determine if the dose limits contained in 40 CFR 190 have been exceeded. Dose limits, as contained in 40 CFR 190 are total body and organ doses of 25 mrem per year and a thyroid dose of 75 mrem per year.

"17-

2.3.1 (Cont'd)

These calculations will include doses as a result of liquid and gaseous pathways as well as doses from direct radiation. Liquid, gaseous and direct radiation pathway doses will consider the James A. FitxPatrick and Nine Mile Point Unit II facilities as well as Nine Mile Point Unit I Nuclear Station.

In the event the calculations demonst'rate that the 40 CFR 190 dose limits, as defined above,'ave been exceeded, then a report shall be prepared and submitted to the Commission within 30 days as specified in Section 3.6.15,d of the Technical Specifications.

Section 4.0 of the. ODCM contains more information concerning calculations for an evaluation of whether 40 CFR 190 limits have been exceeded.

3.0 GhSEOUS EFFLUENTS 3.1 Setpoint Determinations 3.1.1 Basis Stack gas and off gas monitor setpoints will be established such that the instantaneous release rate of radioactive materials in gaseous effluents does not exceed the 10 CFR 20 limits for annual release rate. The setpoints will be activated if the instantaneous dose rate't or beyond the (land) site boundary would exceed 500 mrem/yr to the whole body or 3000 mrem/yr to the skin from the continuous release of radioactive noble gas in the gaseous effluent.

Emergency condenser vent monitor setpoints will be established such that the release rate for radioactive mat'erials in gaseous effluents do not exceed the 10 CFR 20 limits for annual release rate over the projected longest period of release.

Monitor setpoints from continuous release points will be determined once per quarter under normal release rate conditions and will be based on the isotopic composition of the release and/or a more conservative default composition specified in the pertinent procedure. If the calculated setpoint is higher than the existing setpoint, it is not mandatory that the setpoint be changed.

Monitor setpoints for emergency condenser vent monitors are conservatively fixed at 5 mr/hr for reasons described in Sections 3.1.4 and therefore do not require periodic recalculations.

I Under abnormal site release rate conditions, monitor alarm setpoints from continuous 'release points will be recalculated and, if necessary, reset at more frequent intervals as deemed necessary by CHIRP Supervision. In particular, contributions from both JhF and NMP-2 and the Emergency Condenser Vents shall be assessed.

During outages and until steady state power operation is again realized, the last operating setpoint shall be used.

3.1'1 (Cont'd)

Since monitors respond to noble gases only, monitor alarm points are set to alarm prior to exceeding the corresponding total body dose rates.

The skin dose rate limit is not used in setpoint calculations because it is never limiting.

3.1.2 Stack Monitor'Setpoints The detailed methods for establishing setpoints shall be contained in the station procedures. These methods shall apply the following general criteria:

(1) Rationale for Stack monitor settings is based on the general equation:

release rate, actual release rate max. allowable corresponding dose rate, actual corresponding dose rate, max.

allowable

~Z (a) 500 mrlyr X/Q Z(Q Mi) where:

Qi nCi/sec released rate for each isotope, i X/Q highest land sector site boundary dispersion parameter 3

equal to 2.4 E-6 Sec/m Mi gamma air dose factor in units of mr/yr/uCi/m3 (See Table 4-1)

(Q) instantaneous release rate limit.

3.1.2 (Cont'd)

(2) To ensure that 10 CFR 20 and Technical Specifications dose rate limits are not exceeded, the hi hi alarms on the stack monitors shall be set lower than or equal to (0.9) (Q) max . Hi alarms shall be set lower than or equal to (0.5) (Q) max'3)

Based on the above conservatism, the dose contribution from JAF and NMP-2 can usually be ignored. During Emergency Classifications at JAF or NMP-2 due to airborne effluent, or after emergency condenser vent releases of significant proportions, the 500 mr/yr value may be reduced accordingly.

(4) To convert monitor gross count rates to uCi/sec release rates, the following general formula shall be applied:

(C -B) K Q ~ yCi/sec release rate m s where:

C m

~ monitor gross count rate in cps or cpm B ~ monitor background count rate K

s

~ stack monitor efficiency factor with units of uCi/sec-cps or uCi/sec-cpm.

(5) Monitor Ks factors shall be determined using the general formula:

Qi/(Cm -B) where:

Qi individual radionuclide stack effluent release rate as determined by isotopic analysis.

Ks factors more conservative than those calculated by the above methodology may be assumed.

21~

3.1.3 Recombiner Discharge (Off Gas) Monitor Setpoints (1) The hi hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 UCi/sec. This alarm point may be set equal to or less than 1 Ci/sec for a period of time not to exceed 60 days provided the offgas treatment system is in operation .

e hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 vCi/sec (3) To convert monitor mR/hr readings to gCi/sec, the formula below shall be applied:

R.K QR uCi/sec r'ecombiner discharge release rate.

where:

R ~ mR/hr monitor indicator efficiency factor in units of nCi/sec/mR/hr determined prior to setting monitor alarm points (4) Monitor KR factors shall be determined using the general formula:

Q /R where: b Q

i m individual radionuclide recombiner discharge release rate as determined by isotopic analysis and flow rate monitor.

K factors more conservative than those calculated by the above methodology may be assumed.

3.1.4 Emergency Condenser Vent Monitor Setpoint The monitor setpoint was established by calculation ("Emergency Condenser Vent Monitor Alarm Setpoint", January 13, 1986, NHPC File Code 816199). Assuming a hypothetical case with (1) reactor water iodine concentrations higher than the Technical Specification Limit, (2) reactor water noble gas concentrations higher than would be expected at Technical Specification iodine levels, and (3) leakage of reactor steam into the emergencp condenser shell at 300K of rated 6

flow (or 1.3 x 10 lbs/hr), the calculation predicts an emergency condenser vent monitor response of 20 mr/hr." Such a release would result in less than 10 CFR 20 dose rate. values at the site boundary and-beyond for typical emergency condenser cooldown periods.

Since a 20 mr/hr monitor response can, in theory, be achievable only when reactor water iodines are higher than permitted by Technical Specifications, a conservative monitor setpoint of 5 mr/hr has been adopted.

3.1.5 Discussion 3,1.5.1 Stack Effluent Monitoring System Description The NMP-1 Stack Effluent Honitoring System consists of two subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEHS) and the old General Electric Stack Monitoring System (OGESHS). Both systems may operate concurrently in series from one sample tap or OGESHS may operate alone. Either configuration ensures compliance with Technical Specification requirements ~

The RAGEMS is the front end system and can be activated for use in high range monitoring during acciden't situations in compliance with NUREG 0737 criteria. Under this configuration, stack sample gas is pumped from RAGEHS under slight positive pressure thru the OGESHS.

Overall system schematic is shown on Figure B-9. A simplified view of RAGEMS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure B-8.

3.1.5.2 RAGEHS The RAGEMS provides continuous monitoring and on-line isotopic analysis of NHP-1 stack effluent oarticulates, iodines and noble gases at Lower Levels of Detection less than Technical Specification

-13 Table 4.6.15-2 limits. Activities as low as 10 uCi/cc for

-8 particulates and iodines and 5 X 10 for noble gases and as high as 12uCi/cc for particulates and iodines and 2 X 10 ~Ci/cc for gas'es are detectable by the system. Thus, it is functional 'oble during both normal operation and accident conditions'24-

3.1.5.3 Stack Sample Flow Path and OGESMS The effluent sample is obtained inside the stack at elevation 530'sing an isokinetic probe with four orifices. The sample line then bends radially out and back into the stack; descends down the stack and out of the stack at approximately elevation 257'; runs horizontally (enclosed in heat tracing) some 270'long the off gas tunnel; and enters the RAGEMS located on the Tubbine Building cabinet Unit 0) and Off Building 247'Particulate, 250'Dilution Gas Iodine, Noble Gas stations Units 1-3 ).

Zn the Dilution cabinet of the RhGEMS, the stack gas may be diluted during accident situations approximately 100-200X (first stage) or 10000-40000 X (first and second stage) with gaseous nitrogen supplied from an on-site liquid nitrogen storage tank (see Figure B-9).

From Unit 0, the sample gas enters Unit 1-3 of RhGEMS and flows thru in-line particulate and iodine cartridges and then thru either a 6 liter (low range) or 30 cc (high range) noble gas chamber.

The sample gas next fl'ows back thru Unit 0 and the off gas tunnel; along the base of the 'stack; and up to the OGESMS on Turbine Building 261'.

In the OGESMS, sample flows thru a particulate/iodine cartridge housing (normally unloaded when RAGEMS is operating) and four noble gas scintillation detectors (ie, 07 and 08 low range detectors which are in direct contact with sample gas and ll and 12 high range detectors), From OGESMS, the stack sample flows back into the stack at approximately elevation 257'onsistent with Technical Specification 3.6.14(b).

All OGESMS detector outputs are monitored and recorded remotely in the Main Control Rooom. Alarming capabilities are provided to alert Operators of high release rate conditions prior to exceeding Technical Specification 3.6.15.b (1) a dose rate limits.

In the event either the RAGEMS becomes inoperable or is taken out of service for repairs, maintenance or testing, valve line-up at the base of the stack can be changed to permit flow thru OGESMS only.

Under this configuration, stack particulate and iodine samples are retrieved manually and analyzed in the laboratory using gamma spectroscopy at frequencies, LLD's specified in Table 4.6.15-2 of the Technical Specifications.

3.1.5.4 Sampling Frequency/Sample Analysis Regardless of which stack monitoring subsystem is utilized, radioactive gaseous wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Technical Specification Table 4.6.15-2. Particulate samples are saved and analyzed for principal gamma emitters, gross alpha, Fe-55, Sr-89, Sr-90 at monthly intervals minimally. The latter thr'ee analyses are performed off-site from a composite sample. Sample analysis frequencies are increased during elevated release rate conditions, following startup, shutdown and in conjunction with each drywell purge.

Consistent with Technical Specification Table 4.6.15-2, stack effluent tritium is sampled monthly, during each drywell purge, and weekly when fuel is off loaded until stable release rates are demonstrated. Samples are analyzed off-site.

Line loss correction factors are applied to all particulate and iodine results. Correction factors of 2.0 and 1.5 are used for data obtained from RAGENS and OGESMS respectively. These correction factors are based oa empirical data from sampling conducted at NMP-1 in 1985 (memo from J. Blasiak to RAGEMS File, 1/6/86, "Stack Sample Representativeness Study: RAGEHS vs. In-Stack Auxiliary Probe Samples" ) .

3.1.5.5 I-133 Estimates Monthly, the stack effluent shall be sampled for iodines over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and the I-135/I"133 and the I-133/I-131 ratios calculated. These ratios shall be used to calculate I-133, I-135 release for longer acquisition samples collected during the month.

3.1.5,6 Gaseous Radwaste Treatment System Operation Technical Specification 3.6.16.b requires that the gaseous radwaste treatment system shall be operable and shall be used to reduce radioactive materials in gaseous waste prior to their discharge as necessary to meet the requirements of Technical Specification 3,6.1'5.b.

To ensure Technical Specification 3.6.15.b limits are not exceeded, and to confirm proper radwaste treatment system operation as applicable, cumulative dose contributions for the current calendar quarter and current calendar year'hall be determined monthly in accordance with section 3.2 of this manual. Initial dose calculations shall incorporate the following assumptions with regard to relea'se rate's of non-gamma emitting radionuclides subsequently analyxed off-site:

a) H-3 release rate > 4uCi/sec b) Sr-89 release rate > 4 x Cs-137 release rate c) Sr-90 release rate > 0.5 x Cs-137 release rate d) Fe-55 release rate > 1 x Co-60 release rate hssumed release rates represent conservative estimates derived from analysis of historical data from process waste streams. Following receipt of off-site H-3, Sr-89, Sr-90, Pe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations.

~ ~

Dose and Dose Rate Determinations In accordance with specifications 4.6.15.b.(2) and 4.6.15.b.(3), dose and dose rate determinations will be made monthly in order to determine:

(1) Total body dose rates and gamma air doses at the maximum X/Q land'ector site boundary interface and beyond.

(2) Skin dose rates and beta air doses at the maximum X/Q land sector site boundary interface and beyond.

(3) The critical organ dose and dose rate at the maximum X/Q land sector site boundary interface and at'a critical receptor location beyond the site boundary.

Either average meteorological data Lie, maximum five year annual average X/Q and D/Q values in the case of elevated releases or 1985 annual average X/Q and D/Q values, in the case of ground level releases) or real time meteorological data shall be utilized for dose and dose rate calculations. Where average meteorological data is assumed, dose and dose rates due to noble gases at locations beyond the site boundary will be lower than equivalent site boundary dose and dose rates. Therefore, under these conditions, calculations of noble gas dose and dose rates beyond the maximum X/Q land sector site boundary locations can be neglected.

3.2 (Cont'd)

The frequency of dose rate calculations will be upgraded when elevated release rate conditions specified in subsequent sections 3.2.1.1 and 3.2.1.2 are realized.

Emergency condenser vent release contributions to the monthly dose and dose rate determinations will be considered only when condenser return isolation valves have been opened the'mergency for reactor cooldown or if Emergency Condenser tube leaks develop with or without the system's return isolation valve opened.

Without tube leakage or opening of the return isolation valves, releases from this system are negligible and the corresponding dose contributions do not have to be included.

When releases from the emergency condenser have occurred, dose and dose rate determinations shall be performed using methodology in 3.2.1 and 3.2.2. Furthermore, enviromental sampling may also be initiated to refine any actual contribution to doses. See Section 3.4.

3.2 (Cont'd)

Critical organ doses and dose rates may be conservatively calculated by assuming the existence of a so-called "moving" critical receptor.

At this "moving" critical receptor location, it is assumed that all pathways are applicable and the highest X/Q and/or D/Q value for actual pathways as noted in Table 3-1 are in effect. A person's dose at the "moving" critical receptor locations is equal to the same dose that person would receive if they were simultaneously subjected to the highest pathway dose at each critical receptor identified for each pathway.

If dose or dose rates calculated, using the assumptions noted above, reach Technical Specification limits, actual pathways will be evaluated, and dose/dose rates shall be calculated at separate critical receptor locations and compared with applicable limits.

3.2.1 Dose Rate Not all pathways need be considered in dose and dose rate calculations at each critical receptor location. For example, when calculating land sector site boundary doses and dose rates for particulates, iodines and tritium, only the ground deposition and inhalation pathways apply.

3.2.1.1 Noble Gases En accordance with the provisions of 10 CFR 20 the dose rates from noble gas release from the site to unrestricted areas are to be limited to 500 mrem/yr to the skin. Dose rate calculation will be performed monthly, or when the Hi Hi stack monitor alarm point is reached, using the following equations:

For total body dose rates (in mr/yr):

~

-8 DR/ 3.17 x 10 Mi(X/Q)Qi/sec For skin dose rates:

DR~+B [3.17 x 10 Ni(X/Q)Qi/sec]+ DR I

where:

-8 Mi j Ni f ~/Q, Qi, 3. 17 x 10 are as defined in section

3. 2. 2. 1 3.2.1.2 Tritium, Zodines and Particulates (1) The dose rate in unrestricted areas from the release of tritium, iodine-131, iodine-133 and all radionuclides in particulate form with half lives greater than 8 days is limited to 1500 mrem/year to any organ.

3.2.1.2 (Cont'd)

(2) In order to ensure that the 1500 mrem/year dose rate limit is not exceeded, particulate, iodine and tritium off site dose rate calculations shall be performed monthly and whenever particulate and iodine release rates exceed 10 uCi/sec using the equation given in Section 3.2.2.2 with Q expressed in pCi/sec.

-2 When the release rate exceeds 1- pCi/sec, the dose rate assessment shall also include JAF and NMP<<2 contribution.

-2 (3) The use of the 10 uCi/sec release rate threshold to perform dose rate calculations is justified as follows: The 1500 mrem/yr organ dose rate limit corresponds to a minimum release rate limit of 0.30 uCi/sec calculated using the equation:

1500 ~ (Q/sec) x (R..W.) max ij j where:

1500 site boundary dose rate limit in mrem/year (R..W the maximum curie to dose conversion ij j )

max factor equal to 4900 mrem-sec/yCi-yr for Sr-90, child bone at the "moving" critical receptor location beyond the site boundary.

3.2. 2 Dose Calculations will be performed monthly at a minimum, to demonstrate that doses resulting from .the release of noble gases, tritium, I-131, I-133 and particulates with half lives greater than 8 days are within the limits specified in 10 CFR 50, Appendix I. These limits are:

Noble Gas Air Dose 5 mr gamma/calendar quarter 10 mrad beta/calendar quarter 10 mr gamma/calendar year 20 mrad beta/calendar year Radioiodines, Tritium & Particulates 7.5 mrem to any organ/calendar quarter 15 mrem to any organ/calendar year 3.2.2.1 Noble Gas Air Dose The air dose at the critical receptor due to noble gas releases is determined as follows:

1 3.2.2.1 (Cont'd)

For gamma radiation D ~ 3.17 x 10 E M. X/Q 1

Q i

For beta radiation Dg 317 x 10 E N. X/Q 1 Qi where M ~ air gamma dose factor in (mr/year per uCi/m3 ) for each isotope i (Table 4-1)

N.

1

~ air beta dose factor (mrad/year per uCi/m 3 ) for each isotope i (Table 4-1)

X/Q ~ the relative plume concentration (in units of sec/m 3

) at'he land sector site boundary or beyond. Either average meteorological data (Table 3-1 or hppendix C), or real time values may be assumed. "Elevated" X/Q values are used for stack releases; "Ground" X/Q values are used for Emergency Condenser Vent releases.

Q ~ the total quantity of isotope i released during the period, (yCi)

-8 3.17 x 10 ~ the inverse of the number of seconds in a year.

3.2.2.2 Radioiodine, Tritium & Particulates" The doses to an individual from I-131, I-133, tritium, and particulates with half lives greater than 8 days will be calculated as follows:

-8 Dose 3.17 x 10 E)ziRi) kW)Qi Where 3

WJ dispersion parameter either X/Q (sec/m ) or D/Q 2

( 1/m ) depending on pathway and receptor location assumed. Either average meteorological data (Table 3-1, or Appendir C) or real time values may be assumed. "Elevated" W values are used for stack releases; "Ground" W values are used for Emergency Condenser Vent releases.

the total quanity of isotope i released during the period, (uCi)

Riigakk the dose factor for each isotope i, pathway j, age group a, and organ k (Table 4-2, through 4-20)

-8 3.17 x 10 ~ the inverse of the number of seconds in a year The R values contained in Tables 4-2 through 4-20 were calculated using the methodology defined in NUREG-0133 and Regulatory Guide 1.109, Revision 1.

3.2.2.3 Accumulating Doses Doses will be calculated monthly, at a minimum, for gamma air and beta air, the identified critical organ, and age group. Results will be summed for each calendar quarter and year.,

It has been historically demonstrated that the critical pathway is usually the grass-cow-milk pathway and the critical organ is the infant's thyroid. For this reason, monthly infant thyroid dose estimates will normally be made prior to receipt of all analysis data (i.e., strontium and tritium). The critical doses are based on the following pathways:

noble gas plume air dose ground plane dose (deposition) inhalation dose cow s milk dose goat's milk dose meat consumption dose vegetation (food crops) dose The quarterly and annual results shall be compared to the limits listed in paragraph 3.2.2. If the limits are exceeded, special reports, as required by Section 6.9.3 of the Technical Specification, shall be submitted.

3.3 Critical Receptors In accordance with the provisions of 10 CFR 20 and 10 CFR 50, Appendix I, the critical receptors have been identified and are contained in Table 3-1.

For noble gas doses, one of two critical receptor locations will be assumed. When maximum five year average annual X/Q values are used, the critical receptor is the maximum X/Q land sector site boundary interface. When real time meteorological X/Q values are used, the critical receptor may either be the maximum X/Q land sector site boundary location, or the downwind location of greatest X/Q residence (e.g., 1.5 miles east), whichever is higher.

For I-133, I-131, tritium and parti'culate radionuclides with half life greater than eight days, the critical pathways are milk (cow and goat), meat, vegetation, inhalation and direct radiation (ground plane) as a result of ground deposition.

The cow milk and goat milk pathway will be based on the greatest D/Q milk cow and milk goat location as determined by technical specification 3.6.22. The inhalation dose pathway. will be bas'ed on the greatest X/Q residence as determined by technical specification .

3.6.22 since this location would have the greatest potential occupancy time. The ground plane dose pathway will be calculated as the greatest D/Q residence because of the greatest potential occupancy time.

3,4 (Cont'd)

Other environmental samples may also be collected and the resultant calculated doses to the maximum exposed individual compared to the dose calculated per 3.2.2. Other environmental sample media may include milk,. vegetation (such as garden broadleaf vegetables), etc.

The adjustment factors from these pathways may be applied to the doses calculated per 3.2,2 on a pathway by pathway basis or several pathway adjustment factors may be averaged and used to adjust calculated doses.

Doses calculated from actual environmental sample media will be based on the methodology presented in Regulatory Guide'1.109. The regulatory guide equations may be slightly modified to account for

'short intervals of time (less than one year) or modified for simplicity purposes by deleting decay factors. Deletion of decay factors would yield more conservative results.

4.0 40 CFR 190 REQUIREMENTS The "Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b) as follows:

"Uranium fuel cycle means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing,of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes minin'g operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear 'and by-product materials from the cycle."

Section 3.6.15.d of the Technical Specifications requires that when the calculated doses associated with the effluent releases exceed .

twice the limi'ts of sections 3.6.15.a.(2)(b), 3.6.15.b.(2)(b) and 3.6.15.b.(3)(b), then calculations shall be made including direct radiation contributions from the reactor units and outside storage tanks (as applicable) to determine whether the 40 CFR 190 dose limits have been exceeded.

4.0 (Cont'd)

If such is the case, Niagara Mohawk shall submit a Special Report to the NRC and limit subsequent releases such that the dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over the calendar year. This report is to demonstrate that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190.

If releases that result in doses exceeding the 40 CFR 190 limits have occurred, then a variance from the NRC to permit. such releases will be requested and if possible, action will be taken to reduce subsequent releases.

The report to the NRC shall contain:

1) Identification of all uranium fuel cycle facilities or operations within 5 miles of the nuclear power reactor units at the site that contribute to the annual dose of the maximum exposed member of the public.

2) Identification. of the maximum exposed member of the public and a determination of the total annual dose to this person from existing pathways and sources of radioactive effluents and direct radiation.

4.0 (Cont'd)

The maximum total body and organ doses resulting from radioactive material in liquid effluents from Nine Mile Point Unit 1 will be with the maximum doses resulting from the releases of noble 'ummed gases, radioiodines, and particulates for the other calendar quarters (as applicable) and from the calendar quarter in which twice the limit was exceeded. The'irect dose components will be determined by either calculation or actuaI. measurement. Actual measurements will utilize environmental TLD dosimetry. Calculated measurements will utilize engineering calculations to determine a projected direct dose component. Zn the event calculati'ons are used, the methodology will be detailed as required in Section 6.9.1.e of the Technical Specif ications.

The doses from Nine Mile Point Unit 1 will be added to the doses to the maximum exposed individual that are contributed from other uranium fuel cycle operations within 5 miles of the site.

For the purpose of calculating doses, the results of the Radiological Bnviromental Monitoring Program may be included for providing more refined estimates of doses to a real maximum exposed individual.

Estimated doses, as calculated from station effluents, may be replaced by doses calculated from actual enviromental sample results.

Evaluation of Doses From Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, the fish consumption and shoreline sediment ground dose will be considered. Since the doses from other aquatic pathways are insignificant, fish consumption and shoreline sediment are the only two pathways that will be considered. The dose associated with fish consumption may be calculated using effluent data and Regulatory Guide 1.109 methodology or by calculating a dose to man based on actual fish sample analysis data. The dose associated with shoreline sediment is based on the assumption that the shoreline would be utilized as a recreational area. This dose may be derived from liquid effluent data and Regulatory Guide 1.109 methodology or from actual shoreline sediment sample analysis data.

Equations used to evaluate doses from actual fish and shoreline sediment samples are based on Regulatory Guide 1.109 methodology.

Because of the sample medium type and the half-lives of the radionuclides historically observed, the decay corrected portions of the equations are deleted. This does not reduce the conservatism of the calculated doses but increases the simplicity from an evaluation point of view.

The dose from fish sample media is calculated as:

<1) Rwb ~ 7i (Cif x p x 1000 x Diwb x fj Where:

Rwb ~ The total dose to the whole body of an adult in mrem per year.

(Cont'd)

Cif = The concentration of radionuclide i in fish samples in pCi/gram.

~ The consumpt'ion rate of fish for an adult (21 kg per year).

1000 ~ Grams per kilogram Diwb = The dose factor for radionuclide i for the whole body of

~

an adult (R.G. 1.109, Table E-ll).

The fractional portion of the year over which the dose is applicable.

(2) Rl I'i (C fx <i x 1000 x D.l x fj Where:

Rl = The total dose to the liver of an adult (maximum exposed organ) in mrem per year.

Cif ~ The concentration of radionuclide i in fish samples in pCi/gram.

~ The consumption rate of fish for an adult (21 kg per year).

1000 ~ Grams per kilogram

~ The dose factor for radionuclide i for the liver of an adult (R.G. 1.109, Table E-11)

~ The fractional portion of the year over which the dose is applicab le.

The dose from shoreline sediment sample media is calculated as:

Cis x u x 40,000 x 0 3 x Diwb x f]

and Rsk Cis x <i x 40,000 x 0.3 x Disk x f Where:

~ The total dose to the whole body of a teenager (maximum exposed age group) in mrem per year.

Rsk ~ The total dose to the skin of a teenager (maximum exposed age group) in mrem per year.

Ci ~ The concentration of radionuclide i in shoreline sediment in pCi/gram.

l (Cont'd)

~ The usage factor. This is assumed as 67 hours per year by a teenager.

40/000 ~ The product of the assumed density of shoreline sediment (40 kilogram per square meter to a depth of 2.5 cm) times the number of grams per kilogram.

0.3 ~ The shore width factor for a lake.

Diwb ~ The dose factor for radionuclide i for the total body (R.G. 1.109, Table E-6)

Disk = The dose factor for radionuclide i for the skin (R.G. 1.109, Table E-6)

~ The fractional portion of the year over which the dose is applicable.

4.2 Evaluation of Doses From Gaseous Effluents For the evaluation of doses to real members of the public from gaseous effluents, the pathways contained in section 3.2.2.3 of the ODCM will be considered. These include the ingestion, inhalation and deposition pathways. However, any updated field data may be utilized that concerns locations of real individuals, real time meteorological data, location of critical receptors, etc. Data from the most recent census and sample location surveys should be utilized. Doses may also be calculated from actual enviromental sample media, as available. Enviromental sample media data such as TLD, air sample, milk sample and vegetable (food crop) sample data may be utilized in lieu of effluent calculational data.

Doses to member of the public from the pathwasy contained in ODCM section 3.2.2.3 as a result of gaseous effluents will be calculated using the dose factors of Regulatory Guide 1.109 or the methodology of the ODCM, as applicalble. Doses calculated from environmental sample media will utilize the methodologies found in Regulatory Guide 1.109.

4.3 Evaluation of Doses From Direct Radiation Section 3.6.15.d of the Technical Specifications requires that the dose contribution as a result of direct radiation be considered when evaluating whether the dose limitations of 40 CFR 190 have been exceeded.

Direct radiation doses as a result of the reactor, turbine and radwaste buildings and outside radioactive storage tanks (as applicable) may be evaluated by engineering calculations or by evaluating enviromental TLD results at critical receptor locations, site boundary or other special interest locations. For the evaluation of direct radiation doses utiliz,ing environmental TLDs, the critical receptor in question, such as the critical residence, etc., will be compared to the control locations. The comparison involves the difference in environmental .TLD results between the receptor location and the average control location result.

4 ' Doses to Members of the Public Within the Site Boundary.

Section 6,9.l.e of the Nine Mile Point Unit 1 Technical Specifications requires that the'emiannual Radioactive Effluent Release Report include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary as defined by Figure 5.1-1 of the specifications. A member of the public, as defined by the Technical Specifications, would be represented by an individual who visits the sites'nergy Information Center for the purpose of observing the educational displays or for picnicing and associated activities.

~ ~

4.4 (Cont'd)

Fishing is a major recreational activity in the area and on the Site as a result of the salmonid and trout populations in Lake Ontario.

Fishermen have been observed fishing at the shoreline near the Energy Information Center from April through December in all weather conditions. Thus, fishing is the major activity performed by members of the public within the site boundary. Based on the nature of the fishermen and undocumented observations, it is conservatively assumed that the maximum exposed individual spends an average of 8 hours per week fishing from the shoreline at a location between the Energy Information Center and the Unit 1 facility. This estimate is considered conservative but not necessarily excessive and accounts for occasions where individuals may fish more on weekends or on a few days in March of the year.

The pathways considered for the evaluation include the inhalation pathway with the resultant lung dose, the ground dose pathway with the resultant whole body and skin dose and the direct radiation dose pathway with the associated total body dose. The direct radiation dose pathway, in actuality, includes several pathways. These include: the direct radiation gamma dose to an individual from an overhead plume, a gamma submersion plume dose, possible direct radiation dose from the facility and a ground plane dose (deposition). Because the location is in close proximity to the site, any beta plume submersion dose is felt to be insignificant.

,W 4.4 (Cont'd)

Other pathways, such as the ingestion pathway, are not applicable.

In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here. These include swimming and wading which are prohibited at the facility.

The inhalation pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate time period. The radionuclide concentrations are then multiplied by the appropriate X/Q value, inhalat'ion dose factor, air intake rate, and the fractional portion of the year in question.

Thus, the inhalation pathway is evaluated using the following equation adapted from Regulatory Guide 1.109.

NOTE: The following equation is adapted from equations C-3 and C-4 of Regulatory Guide 1.109. Since many of the factors 3 3 are in units of pCi/m , m /sec., etc., and since the radionuclide decay expressions have been deleted because of the short distance to the receptor location, the equation presented here is not identical to the Regulatory Guide equations.

R $ i[CiF X/Q DFA i R t]

where:

the maximum dose for the. period in question to the lung (j) for all radionuclides (i) for the adult age group (a) in mrem per time period.

4.4 (Cont'd) ci The average concentration in the stack release of radionuclide i in pCi/m for the period in question.

F i Unit 1 average stack flowrate in m 3

/sec.

X/Q = The plume dispersion parameter for a location approximately 0.50 mi'les west of NMP-1 (The plume dispersion parameter is 8.9E-06 and was obtained from the C.T. Main five year average annual X/Q tables. h X/Q value based on real time meteorology may also be utilized for the period in question, if desired).

DFh..

1ja the inhalation dose factor for radionuclide i, the lung j, and adult age group a in mrem per pCi found on Table E-S of Regulatory Guide 1,109, R

a annual air intake for individuals in age group a in 3 3 M per year (this value is 8,000 m per year and was obtained from Table E-5 of Regulatory Guide 1.109).

I fractional portion of the year for which radionuclide i was detected and for which a dose is to be calculated (in years).

The ground dose pathway (deposition) will be evaluated by obtaining at least one soil or shoreline sediment sample in the area where fishing occurs; The dose will then be calculated using the sample results, the time period in question, and the methodology based on Regulatory Guide 1.109 as presented in Section 4.1. The resultant dose may be'adjusted for a backg'round dose by subtracting the applicable off-site control soil or shoreline sediment sample radionuclide activities. In the event it is noted that fishing is not performed from the shoreline, but is instead performed in the water (i.e., the use of waders); then the ground dose pathway (deposition) will not be evaluated.

The direct radiation gamma dose pathwayincludes any gamma doses from an overhead plume, submersion in the plume, possi.ble radiation from the facility and ground plane dose (deposition). This general pathway will be evaluated by average environmental TLD readings. At least two environmental TLDs will be utilized at one location in the approximate area where fishing occurs. The TLDs will be placed in the field on approximately the beginning of each calendar quarter and removed on approximately the end of each calendar quarter (quarter 2, 3, and 4).

The average TLD readings will be adjusted by the average control TLD readings. This is accomplished by subtracting the average quarterly control TLD value from the average fishing location TLD value. The applicable quarterly control TLD values will be utilized after adjusting for the appropriate time period (as applicable). In the event of loss or theft of the TLDs, results from a TLD or TLDs in the area may be utilized.

5.0 ENVIRONMENTAL MONITORING PROGRAM 5.1 Sampling Stations The current sampling locations are specified in Table 5-1 and Figures 5.1-1, 5.1-2, The meterological tower is shown in Figure 5.1-1. The location is shown as TLD location 17. The Radiological Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New Xork Power Authority, the owners and operators of the Nine Mile Point Unit 1 and the James A. FitzPatrick Nuclear Power Plant, respectively. Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from, both units. The environmental sampling location coordinates shown on Table 5-1 are based on the NMP-2 reactor centerline.

The average dispersion and deposition parameters have been calculated for a 5 year period, 1978 through 1982 'hese dispersion calculations are attached as Appendix C.

The calculated dispersion or deposition parameters will be compared to the results of the annual land use census. If it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g. 50%) calculated D/Q rate, the. new milk.

sampling location will be added to the monitoring program within 30 days.

If a new location is added, the old location that yields the lowest calculated D/9 may be dropped from the program after October 31 of that year.

5.2 Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such as the EPA Crosscheck Program. Participation shall be only for those media, e.g., air, milk, water, etc., that are included in the Nine Mile Point Environmental Monitoring Program and for which crosscheck samples are available. An attempt will be made to obtain a gC sample to program sample ratio of 5% or better. The site identification symbol or the actual Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.

Specific sample media for which EPA Cross Check Program samples are available include the following:

gross beta in air particulate filters gamma emitters in air particulate filters I-131 in milk gamma emitters in milk gamma. emitters in food product gamma emitters in water tritium in water I-131 in water I

5.3 Capabilities for Thermoluninescent Dosimeters Used for Environmental Measurements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by Table 4.6.20-1, footnote b of the Technical Specifications are based on ANSI Standard 'N545, section 4.3. TLDs are defined as phosphors packaged for field use.

In regard to the detection capabilities for thermoluminescent dosimeters, only one determination is required to evaluate'he above capabilities per type of TLD. Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs. Required detection capabilities are as follows:

5.3.1 Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. The responses obtained shall have a relative standard deviation of less than 7.5%. A total of at least 5 TLDs shall be evaluated.

5.3.2 Reproducibility shall be determined by giving TLDs repeated exposures equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. The average of the relative standard deviations of the responses shall be less than 3.0f. A total of at least 4 TLDs shall be evaluated.

5.3.3 Dependence of exposure interpretation on the length of a field cycle shall be examined by placing TLDs for a period equal to at least a field cycle and a period equal to half the same field cycle in an area where the exposure rate is known to be constant. This test shall be conducted under approximate average winter temperatures and approximate average summer temperatures. Por these tests, the ratio of the response obtained in the field cycle to twice that obtained for half the field cycle shall not be less than 0.85. At least 6 TLDs shall be evaluated 5.3.4 Energy dependence shall be evaluated by the response of TLDs to photons for several energies between'approximately 30 keV and 3 MeV.

The response shall not differ from that obtained with the calibration source by more than 25% for photons with energies greater than 80 keV and shall not be enhanced by more than a factor of two for photons with energies less than 80 keV. A total of at least 8 TLDs shall be evaluated.

5.3.5 The directional dependence of the TLD response shall be determined by comparing the response of the TLD exposed in the routine orientation with respect to the calibration source with the response obtained for different orientations. To accomplish this, the TLD shall be rotated through at least two perpendicular planes. The response averaged over all directions shall not differ from the response obtained in the standard calibration position by more than 10%. A total of at least 4 TLDs. shall be evaluated.

5.3.6 Light dependence shall be determined by placing TLDs in the field for a period equal to the field cycle under the four conditions found in ANSI N545, section 4.3.6. The results obtained for the unwrapped TLDs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10K. A total of at least 4 TLDs shall be evaluated for each of the four conditions.

5.3.7 Moisture dependence shall be determined by placing TLDs (that is, the phosphors packaged for field use) for a period equal to the field cycle in an area where the exposure rate is known to be constant.

The TLDs shall be exposed under two conditions: (1) packaged in a thin, sealed plastic bag, and (2) packaged in a thin, sealed plastic bag with sufficient water to yield observable moisture throughout the field cycle. The TLD or phosphor, as appropriate, shall be dried before readout. The response of the TLD exposed in the plastic bag containing water shall not differ from that exposed in the r'egular plastic bag by more than.lOX. A total of at least 4 TLDs sh'all be evaluated for each condition.

5.3.8 Self irradiation shall be determined by placing TLDs for a period equal to the field cycle in an area where the exposure rate is less than 10 uR/hr and the exposure during the field cycle is known. If necessary, corrections shall be applied for the dependence of exposure interpretation on the length of the field cycle (ANSI N545, section 4.3.3). The average exposure inferred from the responses of the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. A total of at least 3 TLDs shall be evaluated.

TABLE 1-1 R VALUES FOR THE NINE MILE POINT UNIT 1 FACILITY apj i ADULT - TOTAL BODY TEEN LIVER NUCLIDE ~R~i (MREM/YR-Ci I" 89 2.05 E - 3 N/h Sr 90 4.37 E 1 N/A Sr 134 1.89 E + 0 2,35 E + 0 Cs 137 1.12 E + 0 1.78 E + 0 Cs 58CCo 6.47 E - 4 2.87 E 4 60 Co 1.85 E - 3 8.38 E 4 54 2.72 E 3 1.40 E 2 7.40 E 7 5.69 E 7 Cr<<51 4.05 E 6 N/A Fe-59 3.01 E 3 8.03 E 3 Zn-65 1.09 E 1 237 E-1 Zr-95 1.69 E 7 2.53 E 7 I-131 3.64 E 4 6.65 E 4 I-133 3.53 E - 5 1.22 E 4 Cs-136 2.73 E 1 3.80 E 1 Ba-140 3.92 E - 5 7.81 E 7 Ce-141 5.49 E 9 5.17 E 8 Fe-55 3.47 E 4 1.60 E -3 Ni-63 3.41 E 3 7..46 E -'3 I

~ ~

TABLE 1-2 PARAMETERS FOR THE LIQUID EFFLUENT PATHWAY REFERENCE (REG. GUIDE 1.109)

Adult ~ 21.0 Kg/yr Table E-5 Uap Teen 16.0 Kg/yr Mp 0.2 Site Specific 590 ft. /second Site Specific Bip Each Element Table A-1 Daipi Each radionuclide Tables E-11 to E-14 Tp 26.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Site Specific

TABLE 3-1 Critical Receptor Dispersion Parameters For Ground Level and Elevated Releases ELEVATED ELEVATED GROUNDe GROUNDe 3 LOCATION DIR MILES D/I/m-2 D~lm 2 Residences E (984) 1.4 1 8 E 07b 5.2 E-09b 4.02 E-07 8.58 E-09 Dairy Cows SE (130') 2.6 2 2 E-08c 7.0 E-10c 6.00 B-08 1.64 E-09 Milk Goats E (88 ) 7.9 1.3 E-08c 1.6 E-10c 2.57 B-08 6.10 E-lo Meat Animals BSB (115 ) 1.8 5 1 B-08c 1.7 E-09c 1.16 E-07 3.54 E-09 Gardens E (97 ) 1.8 1.0 E-07c 3.5 E-09c 2.53 B-07 5.55 E-09 Site Boundary BNE (674) 0.4 2 4 E-06b'd 4.4 E-OSc,d 6.63 E-06 6.35 E-08

a. These values will be used in dose calculations beginning in April 1986 but may be revised periodically to account for changes in locations of farms, gardens or critical residences.

b. Values based on 5 year annual meteorological data (C.T. Main, Rev. 2)

c. Values based on 5 year average grazing season meteorological data (C.T. Main Rev. 2)

d. Value are based on most restrictive X/Q lend-based sector (ENE). (C.T. Main, Rev. 2)

e. Values are based on average annual meteorological data for the year 1985.

'la

TABLE 4-1 DOSE FACTORS FOR NOBLE GASES Gamma Air 'eta Air Dose Factor Dose Factor

~

Mi Ni E1 R mrad-m3 Radionuclides uCi-yr p Ci-yr Kr-83m 1.93E+01 2.88E+02 Kr-85m 1.23K+03 1.97E+03 Kr-85 1.72E+01 1.95E+03 Kr-87 6.17E+03 1.03E+04 Kr-88 1.52K+04 2.93E+03 Kr-89 1.73E+04 1.06E+04 Kr-90 1.63E+04 7.83E+03 Xe-131m 1.56E+02 1.11E+03 Xe-133m 3.27E+02 1.48E+03 Xe-133 3.53E+02 1.05E+03 Xe-135m 3.36E+03 7.39E+02 Xe-135 1.92E+03 2.46E+03 Xe-137 1.51E+03 1.27E+04 Xe>>138 9.21E+03 4.75E+03 Xe-139 5.28K+03 6.52E+04 Ar-41 9.30E+03 3.28E+03

• 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," dated October 1977, page 1.109-21.

TABLE 4-2 R VALUES CON'S MILK INFANT 2

md~rem/

uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3* 2.40E 03 2.40E 03 2.40E 03 2.40E 03 2.40E 03 2.40E 03 Cr 51 7.46B 04 2.17E 06 1.06E04 4.87E 04 4.47E 04 Mn 54 4.54E 06 7.36E 06 2.00E 07 4.44E 06 Fe 55 1.45E 07 6.91B 06 8.43E 07 5.44E 07 z.sss o~)c Fe 59 7.21E 07 8.74E 07 1.05B 08 5.41E 07 Co 58 2.88E 07 2.88E 07 1.15E 07 Co 60 1.11E 08 1.12E 08 4.71E 07 Zn 65 5.26E 09 9.63E 09 3.32E 09 1.14E 10 5.53E 09 Sr 80 1.70E 08 1.22E 08 5.94B 09 Sr 90 1.79E 10 8.75E 08 7.01E 10.

Zr 95 5.58E 02 3.92E 05 .3.23E 03 7.87B 02 8.48E 02 I 131 6.92E 08 5.62E 07 1.34E 09 1.57E 09 1.84E 09 5.17E 11 I 133 7.91E 06 4.57B 06 1.85E 07 2.70E 07 3.17E 07 4.91E 09 Cs 134 3.59E 09 9.65E 07 1.90E 10 3.55E 10 9;14E 09 3.75E 09 Cs 136 1.03E 09 4.19E 07 9.37E 08 2.76B 09 1.10E 09 2.25E 08 Cs 137 2.37E 09 1.04E 08 2.85E 10 3.34E 10 8.96B 09 3.63E 09 Ba 140 5,94E 06 2.83E 07 1.15E 08 1.15E 05 2.74E 04 7.03E 04 Ce 141 1.44B 03 6.30E 06 2.00E 04 1.22E 04 3.76B 03

>m~reml r uCi/m

R VALVES COM'S MILK CHILD 2

md~rem/ r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3" 1.58E 03 1.58E 03 1.58E 03 1.58E 03 1.58E 03 1.58E 03 1.58E 03 Cr 51 4.71E 04 2.50E 06 7.14E 03 2.61E 04 4.77E 04 Mn 54 2.87E 06 9.04E 06 1.08E 07 3.02E 06 Fe 55 1.15E 07 6.85E 06 6.97E 07 3.07E 07 2.09E 07 4

'e 59 4.52E 07 9.45E 07 5.61E 07 9.08E 07 2.63E 07 Co 58 1.77E 07 3.37E 07 5.77E 06 Co 60 6.81E 07 1.28E 08 2.31E 07 Zn 65 4.10E 09 1.16E 09 2.47E 09 6.59E 09 4.15E 09 Sr 89 8.93E 07 1.21E 08 3.13E 09 Sr 90 1.63E 10 8.68E 08 6 '4E 10 Zr 95 3.56E 02 4.17E 05 1.82E 03 4.00E 02 5.72E 02 I 131 3.66E 08 5.73E 07 6.40E 08 6 '4E 08 1.06E 09 2.13E 11 I 133 4.11E 06 4.38E 06 8.78E 06 1.09E 07 1.81E 07 2.02E 09 Cs 134 4.09E 09 1.05E 08 1.18E 10 1.94E 10 6.01E 09 2.16E 09 Cs 136 8.53E 08 4.63E 07 4.80E 08 1.32E 09 7.07E 08 1.05E 08 Cs 137 2.52E 09 1.07E 08 1.79E 10 1.71E 10 5.57E 09 2.00E 09 Be 140 3.27E 06 2.84E 07 5.60E 07 4.91E 04 1.60E 04 2.93E 04 Ce 141 7.47E 02 6.28E 06 1.01E 04 5.03E 03 2.21E 03

• m~reml r 3

uCi/m

TABLE 4-5 R VALUES - COW'S MILK ADULT 2

md~rem/

uCi-sec NUCLIDE T. BODY GI-TRACT . BONE LIVER KIDNEY THYROID LUNG H 3" 7.69E 02 7.69E 02 7.69E 02 7.69E 02 7.69E 02 7.69E 02 Cr 51 1.32E 04 3.32E 06 2.91E 03 7.90E 03 1.75E 04 Mn 54 8.25E 05 1.32E 07 4.32E 06 1.29E 06 Fe 55 2.52E 06 6.21E 06 1.57E 07 1.08E 07 6.04E 06 Fe 59 1.25E 07 1.09E 08 1.39E 07 3.26E 07 9.10E 06 Co 58 5.03E 06 4.56E 07 2.24E 06 P

Co 60 1.93E 07 1.65E 08 8.77E 07 Zn 65 1.18E 09 1.65E 09 8.21E 08 2.81E 09 1.75E 09 Sr 89 1.97E 07 1.10E 08 6.85E 08 Sr 90 6.62E 09 7.80E 08 2.70E 10 Zr 95 9.72E 01 4.55E 05 4.48E 02 1.44E 02 2.25E 02 I 131 1.19E 08 5.49E 07 1.45E 08 2.08E 08 3.57E 08 6.82E 10 I 133 1.05E 06 3.09E 06 1.98E 06 3.44E 06 6.01E 06 5.06E 08 Cs 134 5.74E 09 1.23E'8 2.95E 09 7.02E 09 2.27E 09 7.54E 08 Cs 136 3.55E 08 5.60E 07 1.25E 08 4.93E 08 2.74E 08 3.76E 07 Cs 137 3.65E 09 1.08E 08 4.09E 09 5.59E 09 1.90E 09 6.31E 08 Ba 140 8.43E 05 2.65E 07 1.29E 07 1.62E 04 5.49E 03 9.25E 03 Ce 141 1.71E 02 5.78E 06 2.24E 03 1.51E 03 7.02E 02 em~rem/ r uCi/m

TABLE 4-6 0

R VALUES GOAT'S MILK INFANT 2

md~rem/ r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3+ 4.90E 03 '4.90E 03 4.90E 03 4.90E 03 4.90E 03 4.90E 03 Cr 51 8.95E 03 2.61E 05 1.28E 03 5.84E 03 1.14E 04 Mn 54 5.4SE 05 8.83E 05 2.40E 06 5.33E 05 Fe 55 1.89E 05 8.98E 04 1.10E 06 7.08E 05 3.46E 05 Fe 59 9.37E 05 1.14E 06 1.36E 06 2.38E 06 7.03E 05 .

Co 58 3.45E 06 3.45E 06 1.38E 06 Co 60 1.34E 07 1.35E 07 5.65E 06 Zn 65 6.31E 08 1.16E 09 3.99E 08 1.37E 09 6.63E 08 Sr 89 3.58E 08 2.57E 08 1.25E 10 Sr 90 3.57E 10 1.84E 09 1.47E 11 Zr 95 6.70E 01 4.70E 04 3.88E 02 9.45E 01 . 1.02E 02 I 131 8.31E 08 6.74E 07 1 ~ 60E 09 1.89E 09 2.21E 09 6.21E ll I 133 9.49E 06 5.48E 06 2.23E 07 3.24E 07 3.81E 07 5.89E 09 Cs 134 1.08E 10 2.89E 08 5.71E 10 1.07E 11 2.74E 10 1.12E 10 Cs 136 3.09E 09 1.26E 08 2.81E 09 8.27E 09 3.30E 09 6.74E 08 Cs 137 7.10E 09 3.13E 08 8.55E 10 '1.00E 11 2.69E 10 1.09E 10 Be 140 7.13E 05 3.40E 06 1.38E 07 1.38E 04 3.29E 03 8.50E 03 Ce 141 1.72E 02 7.57E 05 2.40E 03 1.46E 03 4.52E 02

• m~reml r 3

uCi/m

~ 1 ~

~

TABLE 4-7 R VALUES GOAT'S MILK CHILD 2

md~rem/ r uCi-sec NUCLIDE T. BODY GI-TRACT .BONE LIVER KIDNEY THYROID LUNG H 3" 3.23E 03 3.23E 03 3.23E 03 3.23E 03 3.23B 03 3.23E 03 Cc'1 5.65E 03 3.00E 05 8.57E 02 3.14E 03 5.73E 03 Mn 54 3.44E 05 1.08E 06 1.29E 06 3.62E 05 Fe 55 1.49E 05 8.91E 04 9.06E 05 4.81E 05 z.ns osi4 Fe 59 5.88E 05 1.23E 06 7.29E 05 1.18E 06 3.42E 05 Co 58 2.12B 06 4.04E 06 6.92E 05 Co 60 8.17E 06 1.53E 07 2.77E 06 Zn 65 4.92E 08 1.39B 08 2.97E 08 7.91E 08 4.98E 08 Sr '89 1.87E 08 2.54B 08 6.56E 09 Sr 90 3.43E 10 1.82E 09 11 '.35E Zr 95 4.27E 01 5.01E 04 2.18E 02 4.80E Ol 6.87E 01 I 131 4.39E 08 6.88E 07 7.68B 08 7.72B 08 1.27E 09 2.55B 11 I 133 4.93E 06 5.25E 06 1.05E 07 1.30E 07 2.17E 07 2.42E 09 Cs 134 1.23E 10 3.14E 08 3.55E 10 5.82E 10 1.80E 10 6.47B 09 Cs 136 2.56E 09 1.39B 1.44E 09 3.96E 09 2.11E 09 3.14E 08 6.01E 09 08'.21E Cs 137 7.57E 09 08 5.36E 10 5.13E 10 1.67E 10 Ba 140 3.92E 05 3.41E 06 6.72E 06 5.89E 03 1.92E 03 3.51E 03 Ce 141 8.97E 01 7.54E 05 1.21E 03 6.04E 02 2.65E 02

• m~reml r uCi/m

~ l ~ ~

TABLE 4-8 R VALUES - GOAT'S MILK TEEN 2

m~~eem/ e uci-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3" 2.04E 03 2.04E 03 2.04E 03 2.04E 03 2.04E 03 2.04B 03 Cr 51 2.77E 03 4.66E 05 6.07E 02 1.54E 03 3.95E 03 Mn 54 1.71E 05 1.77B 06 8.64E 05 2.58E 05 Fe 55 5.97E 04 1.11E 05 3.61E 05 2.56E 05 1.62E 05t4 Fe 59 2.83E 05 1.74E 06 3.14E 05 7.34E 05 2.31E 05 Co 58 1.04E 06 6.25E 06 4.63E 05 Co 60 4.02B 06 2.32E 07 1.78E 06

'Zn 65 2.45B 08 2.22E 08 1.51E 08 5.25E 08 3.36E 08 Sr 89 7.59E 07 3.16B 08 2.65B 09 Sr 90 1.98E 10 2.25E 09 8.81E 10 Zr 95 2.04E 01 6.84E 04 9.40E 01 2.97E 01 4.36E 01 I 131 2.38E 08 8.77E 07 3.17E 08 4.43E 08 7.63E 08 1.29E 11 I 133 2.24E 06 5.57E 06 4.34E 06 7.36B 06 1.29B 07 1.03E 09 Cs 134 1.68E 10 4.50E 08 1.54E 10 3.62E 10 1.15E 10 4.39B 09 Cs 136 1.69E 09 2.02B 08 6.38E 08 2.51E 09 1.37E 09 2.15E 08 Cs 137 1.03E 10 4.21E 08 10 '.22E 2.96E 10 1.01E 10 3.91E 09 Ba 140 1.80E 05 4.30E 06 2.97E 06 3.41E 03 1.16E 03 2.30B 03 Ce 141 3.77E 01 9 '9K 05 4.92E 02 3.28E 02 1.55E 02

• m~eem/ e uCi/m E

TABLE 4-9 R VALUES GOAT'S MILK ADULT 2

m~~eem/ e uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3* 1.578 03 1.578 03 1.578 03 1.578 03 1.578 03 1.578 03 Cr 51 1.598 03 3.99E 05 3.49E 02 9.488 02 2.118 03 Mn 54 9.898 04 1.59E 06 5.198 05 1.548 05 Fe 55 3.288 04 8.078 04 2 '48 05 1.418 05 7.858 04)4 Fe 59 1.628 05 1.418 06 1.808 05 4.238 05 1.188 05 Co 58 6.038 05 5.468 06 2.698 05 Co 60 2.328 06 1.988 07 1.058 06 Zn 65 1.428 08 1.978 08 9.858 07 3.148 08 2.108 08 Sr 89 4.138 07 2.318 08 1.448 09 Sr 90 1.398 10 1.648 09 5.67E 10 Zr 95 1.17E 01 5.46E 04 5.37E 01 1.728 01 2.708 01 I 131 1.43E 08 6.598 07 1.74E 08 2.50E 08 4.288 08 8.188 10 I 133 1.268 06 3.71E 06 2.378 06 4.138 06 7.218 06 6.07E 08 Cs 134 1.728 10 3.698 08 8.85E 09 2.118 10 6.828 09 2.268 09 Cs 136 1.068 09 1.688 08 3.75E 08 1.48E 09 8.238 08 1.138 08 Cs 137 1.108 10 3.258 08 1.258 10 1.688 10 5.708 09 1.898'9 Be 140 1.018 05 3.188 06 1.548 06 1.948 03 6.598 02 1.118 03 Ce 141 2.068 01 6.948 05 2.688 02 1.818 02 8.438 01 em~rem/

uci/m

TABLE 4-10 R VALUES MEAT. CHILD 2

md~rem/ r uCi-sec NUCI IDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3* 2.368 02 2.368 02 2.368 02 2.368 02 2.368 02 2.368 02 Cr 51 4.07E 03 2.168 05 6.178 02 2.268 03 4.128 03 Mn 54 1.098 06 3.458 06 4.11E 06 1.158 06 Fe 55 4.748 07 2.848 07 2.898 08 1.538 08 8.668 07)4 Fe 59 1.428 08 2.978 08 1.768 08 2.858 08 8.268 07

\

Co 58 2.398 07 4.56K 07 7.828 06 Co 60 1.098 08 2.058 08 3.708 07 Zn 65 3.728 08 1.05E 08 2.258 08 5.99E 08 3.778 08 Sr 89 6.558 06 8.878 06 2.298 08 Sr 90 1.528 09 8.088 07 6.008 09 Zr 95 2.488 05 2.918 08 1.278 06 2:79E 05 3.998 05 I 131 4.648 06 7.298 05 8.148 06 8.19E 06 1.348 07 2.718 09 I 133 1.558-01 1.668-01 3.328-01 4.118-01 6.858-01 7.638-01 CQ 134 1.678 08 4.26E 06 4.818 08 7.90E 08 2.458 08 8.788 07 CQ 136* 1.358 07 7.348 05 7.608 06 2.098 07 1.118 07 1.668 06 CB 137 1.048 08 4.43E 06 7.398 08 7.078 08 2.308 08 8.298 07 Be 140 1.228 06 1 '68 07 2.108 07 1.848 04 5.988 03 ~

1.10E 04 Ce 141 7.578 02 6.36E 06 1.028 04 5.108 03 2.248 03 em~rem/ r 3

uCi/m

TABLE 4-11 R VALUES MEAT TEEN 2

m~~eem/ r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY- THYROID 'LUNG H 3" 1.95E 02 1.95E 02 1.95E 02 1.95E 02 1.95E 02 1.95E 02 Cr 51 2.61E 03 4.39E 05 5.72E 02 1.45E 03 3.73E 03 Mn 54 7.12E 05 7.37E 06 3.59E 06 1.07E 06 Fe 55 2.49E 07 4.62E 07 1.50E 08 1.07E 08 6.77E 07 4 Fe 59 8.95E 07 5.48E 08 9.93E 07 2.32E 08 7.31E 07 Co 58 1.54E 07 9.22E 07 6.69E 06 Co 60 7.03E 07 4.06E 08 3.12E 07 Zn 65 2.43E 08 2.20E 08 1.50E 08 5.20E 08 3.33E 08 Sr 89 3.47E 06 .1.44E 07 1.21E 08 Sr 90 1.15E 09 1.30E 08 4.64E 09 Zr 95 1.55E 05 5.20E 08 7.15E 05 2.25E 05, 3.31E 05 I 131 3.30E 06 1.22E 06 4.39E 06 6.14E 06 1.06E 07 1.79E 09 I 133 9.25E-02 2.30E-01 1.79E-01 3.03E-01 5.32E-01 4.23E 01 Cs 134 2.98E 08 7.99E 06 2.73E 08 6.42E 08 2.04E 08 7.78E 07 Cs 136 1.16E 07 1.40E 06 4.41E 06 1.73E 07 9.44E 06 1.49E 06 Cs 137 1.86E 08 7.59E 06 4.01E 08 5.34E 08 1.82E 08 7.06E 07 Ba 140 7.33E 05 1.75E 07 1.14E 07 1.39E 04 4.72E 03 9.37E 03 Ce 141 4.14E 02 1.04E 07 5.43E 03 3.63E 03 1.71E 03 em~rem/ r 3

uCi/m t

'ABLE 4-12 R VALUES MEAT ADULT 2

m~~eem/ e uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3" 3.27E 02 3.27E 02 3.27E 02 3.27E 02 3.27E 02 3.27E 02 Cr 51 3.26E 03 8.21E 05 7.19E 02 1.95E 03 4.33E 03 Mn 54 8.98E 05 1.44E 07 4.71E 06 1.40E 06 Fe 55 2.98E 07 7.34E 07 1.85E .08 1.28E 08 7.14E 0714 Fe 59 1.12E 08 9.73E 08 1.24E 08 2.92E 08 8.16E 07 Co 58 1.95E 07 1.76E 08 8.68E 06 Co 60 8.87E 07 7.56E 08 4.02E 07 Zn 65 3.06E 08 4.27E 08 2.13E 08 6.78E 08 4.53E 08 Sr 89 4.12E 06 2.30E 07 1.43E 08 Sr 90 1.76E 09 2.07E 08 7.17E 09 Zr 95 1.94E 05 9.07E 08 8.92E 05 2.86E 05 4.49E 05 I 131 4.33E 06 1.99E 06 5.28E 06 7.55E 06 1.29E 07 2.48E 09 I 133 1.13E-01 3.34E-01 2.14E-01 3 '2E-01 6.49E-01 5.46E 01 Cs 134 6.68E 08 1.43E 07 3.43E 08 8.15E 08 2.64E 08 8.78E 07 Cs 136 1.61E 07 2.53E 06 5.65E 06 2.23E 07 1.24E 07 1.70E 06 Cs 137 4.33E 08 1.28E 07 4.83E 08 6.61E 08 2.24E 08 7.46E 07 Ba 140 9.01E 05 2.83E 07 1.38E 07 1.73E 04 5.87E 03 9.89E 03 Ce 141 4.96E 02 1.67E 07 6.47E 03 4,.38E 03 2.03E 03

• m~eem/ e 3

uCi/m

~ ~

TABLE 4-13 R VALUES VEGETATION CHILD 2

md~rem/

uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3" 4.04E 03 4.04E 03 4.04E 03 4.04E 03 4.04E 03 4.04E 03 Cr 51 1.16E 05 6.15E 06 1.76E 04 6.44E 04 1.18E 05 Mn 54 1.73E 08 5.44E 08 6.49E 08 1.82E 08 Fe 55 1.25E 08 7.50E 07 7.63E 08 4.05E 08 Z ZSS OS[4 Fe 59 3.17E 08 6.62E 08 3.93E 08 6.36E 08 1.84E 08 Co 58 1.92E 08 3.66E 08 6.27E 06 Co 60 1.11E 09 2.08E 09 3.76E 08 Zn 65 1.70E 09 4.81E 08 1.03E 09 2.74E 09 1.73E 09 Sr 89 1.03E 09 1.40E 09 3.62E 10 Sr 90 3.49E 11 1.86E 10 1.38E 12 Zr 95 7.44E 05 8.71E 08 3.80E 06 8.35E 05 1.20E 06 I 131 8.16E 07 1.28E 07 1.43E 08 1.44E 08 2.36E 08 4.75E 10 I 133 1.67E 06 1.78E 06 3.57E 06 4.42E 06 7.36E 06 8.21E 08 Cs 134 5.40E 09 1.38E 08 1.56E 10 2.56E 10 7.93E 09 2.84E 09 Cs 136 1.43E 08 7.77E 06 8.04E 07 2.21E 08 1.18E 08 1.76E 07 Cs 137 3.52E 09 1.50E 08 2.48E 10 2.39E 10 7.78E 09 2.80E 09 Ba 140 1.61E 07 1.40E 08 2.76E 08 2.42E 05 7.87E 04 1.44E 05 Ce 141 4.75E 04 3.99E 08 6.42E 05 3.20E 05 1.40E 05

• m~reml r uCi/m

TABLE 4-14 R VALUES VEGETATION TEEN 2

m~~rem/ r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3* 2.61E 03 2.61E 03 2.61E 03 2.61E 03 2.61E 03 2.61E 03 Cr 51 6.11E 04 1.03E 07 1.34E 04 3.39E 04 8.72E 04 Mn 54 8.79E 07 9.89E 08 4.43E 08 1.32E 08 Fe 55 5.13E 07 9.53E 07 3.10E 08 2.20E 08 1.40E 08I4 Fe 59 1.60E 08 9.78E 08 1.77E 08 4.14E 08 1.30E 08 Co 58 9.79E 07 5.85E 08 4.25E 07 Co 60 5.57E 08 3.22E 09 2.47E 08 Zn 65 8.68E 08 7.88E 08 5.36E 08 1.86E 09 1.19E 09 Sr 89 4.36E 08 1.81E 09 1.52E 10 Sr 90 2.05E ll 2.33E 10 8.32E 11 Zr 95 3.68E 05 1.23E 09 1.69E 06 5.35E 05 7.86E 06 I 131 5.77E 07 2.13E 07 7.68E 07 1.07E 08 1.85E 08 3.14E 10 I 133 1.01E 06 2.51E 06 1.96E 06 3.32E 06 5.83E 06 4.64E 08 Cs 134 7..54E 09 2.02E 08 6.96E 09 1.62E 10 5.16E 09 1.97E 09 Cs 136 1.13E 08 1.35E 07 4.28E 07 1.68E 08 9.16E 07 1.44E 07 Cs 137 4.90E 09 2.00E 08 1.06E 10 1 ~ 41E 10 4.78E 09 1.86E 09 Ba 140 8.88E 06 2.12E 08 1.38E 08 1.69E 05 5.72E 04 1.14E 05 Ce 141 2.12E 04 5.29E 08 2.77E 05 1.85E 05 8.70E 04 em~rem/ r 3

uCi/m

~

1, .

I TABLE 4-15 0

R VALUES VEGETATION - ADULT 2

m~~eeml e uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG e

H 3>> 2.28E 03 2.28E 03 2.28E 03 2.28E 03 2.28E 03 2.28E 03 Cr 51 4.60E 04 1.16E 07 1.01E 04 2.75E 04 6.10E 04 Mn 54 5.83E 07 9.36E 08 3.05E 08 9.09E 07 Fe 55 3.22S 07 7.91E 07 2.00E 08 1.38E 08 7.69E 07 4 Fe 59 1.12E 08 9.75E 08 1.24E 08 2.93E 08 8.17S 07 Co 58 6.71E 07 6.07E 08 2.99E 07 Co 60 3.67E 08 3.12E 09 1.66E 08 Zn 65 5.77E 08 8.04E 08 4.01E 08 1.28E 09 8.54$ 08 Sr 89 2.87E 08 1.60E 09 1.08B 10 Sr 90 1.64E 11 1.93E 10 6.70E 11 Zr 95 2.51E 05 1.17E 09 1.16E 06 3,71E 05 5.82B 05 I 131 6.61E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 I 133 1.12E 06 3.30B 06 2.11E 06 3.67E 06 6.40E 06 5.39E 08 Cs 134 8 '3B 09 1.89S 08 4.54E 09 1.08E 10 3.49E 09 1.16E 09 Cs 136 1.19E 08 1.88E 07 4 '9E 07 1.66B 08 9.21E 07 1.26E 07 Cs 137 5.94E 09 1.76E 08 6.63E 09 9.07E 09 3.08E 09 1.02E 09 Ba 140 8.40S 06 2.64E 08 1.28E 08 1.61E 05 5.47E 04 9.22E 04 Ce 141 1.48E 04 4.99E 08 1.93E 05 1.31E 05 6.07E 04 em~rem/ e uCi/m

-7f

~

I.

R VALUES INHALATION INFANT 2

md~rem/

uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3" 6.468 02 6.468 02 6.46E 02 6 '6E 02 6.468 02 6.468 02 Cr 51 8.938 01 3.568 02 1.328 01 5.758 01 1.288 04 Mn 54 4.988 03 7.058 03 2.538 04 4.988 03 9.988 05 Fe 55 3.338 03 1.09E 03 1.978 04 1.178 04 B.698 04 4 Fe 59 9.46E 03 2.478 04 1.35E 04 2.368 04 1.018 06 Co 58 1.828 03 1.118 04 1.228 03 7.768 05 Co 60 1.188 04 3.188 04 8,018 03 4.508 06 Zn 65 3.108 04 5.13E 04 1.938 04 6.258 04 3.248 04 6'.468 05 Sr 89 1.148 04 6.398 04 3.97E 05 2.038 06 Sr 90 2.59E 06 1.318 05 4.088 07 1.128 07 Zr 95 2.038 04 2.178 04 1.158 05 2.788 04 3.10E 04 1.758 06 I 131 1.968 04 1.068 03 3.798 04 4.438 04 5.178 04 1.488 07 I 133 5.598 03 2.158 03 1.328 04 1.92E 04 2.248 04 3.558 06 Cs 134 7.448 04 1.338 03 3.968 05 7.028 05 1.908 05 7.958 04 Cs 136 5.2BE 04 1.438.03 4.82E 04 1.348 05 5.638 04 1.178 04 Cs 137 4.548 04 1.338 03 5.48E 05 6.118 05 1.728 05 7.128 04 Ba 140 2.898 03 3.838 04 5.598 01 5.598 01 1.348 01 1.598 06 Ce 141 1.998 03 2.158 04 2.778 04 1.668 04 5.248 03 5.16E 05 em~rem/ r 3

uCi/m I

TABLE 4-17 R VALUES INHALATION CHILD m~rem/

3 uCi/m NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 Cr 51 1.54E 02 1.08E 03 2.43E 01 8.53E 01 1.70E 04 Mn 54 9.50E 03 2.29E 04 4.29E 04 1.00E 04 1.57E 06 Fe 55 7.77E 03 2.87E 03 a.74E oa 2.52E 04 1.11E 05) 4 Fe 59 1.67E 04 7.06E 04 2.07E 04 3.34E 04 1.27E 06 Co 58 3.16E 03 3.43E 04 1.77E 03 1.10E 06 Co 60 2.26E 04 9.61E 04 1.31E 04 7.06E 06 Zn 65 7.02E 04 04 '.63E 4.25E 04 1.13E 05 7.13E 04 9.94E 05 Sr 89 1.72E 04 1.67E 05 5.99E 05 2.15E 06 Sr 90 6.43E 06 3.43E 05 1.01E 08 1.47E 07 Zr 95 3.69E 04 6.10E 04 1.90E 05 4.17E 04 5.95E 04 2.23E 06 I 131 2.72E 04 2.84E 03 4.80E 04 a.8oE oa 7.87E 04 1.62E 07 I 133 7.68E 03 5.47E 03 1.66E oa 2.03E 04 3.37E 04 3.84E 06 Cs 134 2.24E 05 3.84E 03 6.50E 05 1.01E 06 3.30E 05 1.21E 05 Cs 136 1.16E 05 4.17E 03 6.50E 04 1.71E 05 9.53E 04 1.45E 04 Cs 137 1.28E 05 3.61E 03 9.05E 05 8.24E 05 2.82E 05 1.04E 05 Ba 140 4.32E 03 1.02E 05 7.39E 6.47E 01 2.11E 01 1.74E 06 Ol,';92E Ce 141 2.89E 03 5.65E 04 04 1.95E 04 8.53E 03 5.43E 05

~ pe

TABLE 4-18 R VALVES - INHALATION TEEN m~reml r 3

uCi/m NUCLIDE T. BODY BONE .l IVER KIDNEY THYROID LUNC H 3 1.27B 03 1.27B 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 Cr 51 1.35E 02 3.00E 03 3.07E 01 7.49E 01 '2.09E 04 Mn 54 8.39E 03 6.67E 04 5.10B 04 1.27E 04 1.98E 06 Fe 55 5.54E 03 6.39E 03 3;34E 04 2.38E 04 1.24E 05 Fe .59 1.43E 04 1.78E 05 1.59E 04 3.69E 04 1.53E 06 Co 58 2.77E 03 9.51E 04 2.07E 03 1.34E 06 Co 60 1.98E 04 2.59E 05 1.51E 04 8.71E 06 Zn 65 6.23B 04 4.66E 04 3.85E 04 1.33E 05 8.63E. 04 1.24E 06 Sr 89 1.25E 04 3.71E 05 4.34E 05 2.41E 06 Sr 90 6.67E 06 7.64E 05 1.08E 08 1.65E 07 Zr 9S 3.15E 04 1.49E 05 1.45E 05 4.58E 04 6.73E 04 2.68E 06 I 131 2.64E 04 6.48E 03 3.54E'04 4.90E 04 8.39E 04 1.46E 07 I 133 6.21E 03 1.03E 04 1.21E 04 2.05E 04 3.59E 04 2.92E 06 Cs 134 5.48E 05 9.75E 03 5.02E 05 1.13E 06 3.75E 05 1.46E 05 Cs 136 1.37E 05 1.09E 04 5.14E 04 1.93E 05 1.10E OS 1.77E 04 Cs 137 3.11E 05 8.47E 03 6.69E 05 8.47E 05 3.04E 05 1.21E 05 Ba 140 3.51E 03 2.28E 05 5.46B 04 6.69E Ol 2.24E Ol 2.03E 0 r 141 2.16E 03 1.26E 05 2.84E 04 1.89E 04 8.87E 03 6.13B 0

R VALUES - INHALATION - ADULT m~reml r 3

uci /m NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26S 03 Cr 51 9.99E 01 3.32E 03 2.28E OI 5.94E 01 1.44E 04 Mn 54 6.29E 03 7.72E 04 3.95E 04 9.83E 03 1.40B 06 Fe 55 3.94E 03 6.03E 03 2.46E 04 1.70E 04 7.21E 0$ 4 Fe 59 1.05B 04 . 1.88E 05 1.17E 04 2.77E 04 1.01E 06 Co 58 2.07E 03 1.06B 05 1.58E 03 9.27E 05 Co 60 1.48E 04 2.84E 05 1.15E 04 5.96E 06 Zn 65 4.65S 04 5.34S 04 3 '4B 04 1.03E 05 6.89E 04 8.63E 05 Sr 89 8.71B 03 3.49E 05 3.04E 05 1.40E 06 Sr 90 6.09E 06 7.21B 05 9.91E 07 9.59S 06 Zr 95 2.32E 04 1.50E 05 1.07E 05 3.44E 04 5.41B 04 1.77E 06 I 131 2.05B 04 6;27E 03 2 '2E 04 3.57E 04 6.12E 04 1.19S 07 I 133 4.51E 03 8.87E 03 8.63E 03 1.48E 04 2.58E 04 2.15E 06 CQ 134 7.27B 05 1.04E 04 3.72E 05 8.47E 05 2.87E 05 9.75E 04 Cs 136 1.10E 04 1.17B 04 3.90E 04 1.46E 05 8.55E 04 1.20E 04 Cs 137 4.27E 05 . 8.39E 03 4.78E 05 6.20E 05 2.22E 05 7.51E 04 Ba 140 2.56E 03 2.18E 05 3.90E 04 4.90S 01 1.67E OI 1.27E 06 Ce 141 1.53E 03 1.20E 05 1.99B 04 1.35E 04 6.25E 03 3.61E 05

TABLE 4-20 R VALUES GROUND - ALL AGE GROUPS 2

N ~nrem/ e i Ci/sec NUCLIDE 1. BODY Cr 51 4.66E 06 Mn 54 1.34E 09 Fe 55 Fe 59 2.75E 08 Co 58 3.79E 08 Co 60 2.15E 10 Zn 65 7.49E 08 Sr 89 2.23E 04 Zr 95 2.49E 08 I 131 1.72E 07 I 133 2.47E 06 Cs 134 6.82E 09 Cs 136 1.49E 08 Cs 137 1.03E 10 Ba 140 2.05E 07 Ce 141 1.36E 07 I 135 Later Ba/La -140 Later Nb 95 Later Sb 125 Later I

Nine Hile Point Nuclear Station Unit 1 Radiological Environmental Monitoring Program Sampling Locations Table 5.1 Type of *Hap (Env.

Sam le Location Collection Site Pro ram No.) Location Radioiodine and Nine Mile Point Road 1.8 mi 9 88' Particulates (air) North (R-1)

Radioiodine and Co. Rt. 29 6 Lake Road (R-2) 1.1 mi Q 104'SE Particulates (air)

Radioiodine and Co, Rt ~ 29 (R-3) 1.5 mi Q 132'E Particulates (air)

Radioiodine and Village of Lycoming, NY (R-4) 1.8 mi 9 143'E Particulates (air)

Radioiodine and I

Hontario Point. Road (R-5) 16.4 mi 9 42'IE Particulates (air)

Direct Radiation (TLD) 6 North Shoreline Area (75) O.1mi 8 5':.

Direct Radiation (TLD) 7 'North Shoreline Area (76) 0.1 mi g 25 NNE Direct Radiation (TLD) 8 North Shoreline Area (77) 0.2 mi Q 45'E Direct Radiation (TLD) 9 North Shoreline Area (23) 0.8 mi Q 70'iRE Direct Radiation (TLD) 10 JAF East Boundary (78) 1.0 mi Q 90' Direct Radiation (TLD) 11 Rt. 29 (79) 1. 1 mi 8 115'SE Direct Radiation (TLD) 12 Rt. 29 (80) 1.4 mi 9 133'E Direct Radiation (TLD) 13 Miner Road (81) 1 ~ 6 mi (> 159'SE Direct Radiation (TLD) 14 Niner Road (82) 1.6 mi 9 181' Direct Radiation (TLD) 15 Lakeview Road (83) 1.2 mi g 200'SW Direct Radiation (TLD) 16 Lakeview Road (84) 1.1 mi 9 225'W Direct Radiation (TLD) 17 Site Heteorological Tower (7) 0.7 mi 9 250'SW Direct Radiation (TLD) 18 Energy Information Center (18) 0.4 mi 9 265'

• Map - See Figures 5.1-1 and 5. 1-2 I r Nine Mile Point Nuclear Station Unit 1 Radiological Environmental Monitoring .Program Sampling Locations Table 5.1 (Continued)

Type of "Map (Env.

Sample Location Collection Site Pro ram No.) Location Direct Radiation (TLD) 19 - North Shoreline (85) 0.2 mi 8 294'NW Direct Radiation (TLD) 20 North Shoreline (86) O.l mi 8 315'W Direct Radiation (TLD) 21 North Shoreline (87) O.l mi 8 341'NW Direct Radiation (TLD) 22 Hickory Grove (88) 4.5 mi 8 97' Direct Radiation (TLD). 23 Leavitt Road (89) 4.1 mi 8 ill'SE Direct Radiation (TLD) 24 Rt. 104 (90) 4.2 mi 8 135'E Direct Radiation (TLD) 25 Rt. 51A (91) 4.8 mi 8 156'SE Direct Radiation (TLD) 26 Maiden Lane Road (90) 4.4 Gii 8 183' Direct Radiation (TLD) '27 Co. Rt. 53 (93) 4.4 mi 8 205'SW Direct Radiation (TLD) 28 Co. Rt. 1 (94) 4.7 mi 8 223'W Direct Radiation (TLD) 29 Lake Shoreline (95) 4.1 mi 8 237'SW Direct Radiation (TLD) 30 Phoenix, NY Control (49) 19.8 mi 8 170' Direct Radiation (TLD) 31 S. W. Oswego, Control (14) 12.6 mi 8 226'W Direct Radiation (TLD) 32 Scribe, NY (96) 3.6 mi 8 199'SW Direct Radiation (TLD) 33 Alcan Aluminum, Rt. 1A (58) 3.1 mi 8 220'W Direct Radiation (TLD) 34 Lycoming, NY (97) 1.8 mi 8 143'E Direct Radiation (TLD) 35 New Haven, NY (56) 5.3 mi 8 123'SE Direct Radiation (TLD) 36 W. Boundary, Bible Camp (15) 0.9 mi 8 237'SW Direct. Radiation (TLD) 37 Lake Road (98) 1.2 mi 8 101' Surface Water 38 OSS Inlet Canal (NA) 7.6 mi 8 235'W Surface Water 39 JAFNPP Inlet Canal (NA) 0.5 mi 8 70 ENE (NA) ~ not applicable

• Map ~ See Figures 5.1-1 and 5.1-2

Nine Mile Point Nuclear Station Unit 1 Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)

Type of <<Map (Env.

Sam le Location Collection Site Pro ram No.) Location Shoreline Sediment 40 Sunset Bay Shoreline (NA) 1.5 mi 9 80 E Fish 41 NMP Site Discharge Area (NA) 0.3 mi 9 315 NW and/or Fish 42 .NMP Site Discharge Area (NA) 0.6 mi 9 55 NE Fish Oswego Harbor Area (NA) 6.2 mi 9 235'W Milk 44 Milk Locatien ¹50 (NA) 9.3 mi 9 93 E Milk 45 Milk Location ¹7 (NA) 5.5 mi 9 107 ESE Milk Milk Location ¹16 (NA) 5.9 mi 9 190 S Milk Milk Location ¹65 (NA) 17.0 mi 9 220 SW Food Product 48 Produce Location ¹6>> 1.9 mi 9 143 SE (Bergenstock) (NA)

Food Product 49 Produce Location ¹1>> 1.8 mi 9 96' (J. Parkhurst) (NA)

Food Product 50 Produce Location ¹2>> 1.9 mi 9 101 E (Vitullo } (NA)

Food Product 51 Produce Location ¹5>> b 1.5 mi 9 114 ESE (C.S. Parkhurst) (NA)

Food Product 52 Produce Location ¹3~~ 1.6mi 984 E (C. Narewski)

Food Product 53 Produce Location ¹4>> 2.0 mi 9 120 ESE (S. Morris) (NA)

Food Product (CR) Produce Location ¹7>> 15.0 mi 9 223 SW (Mc Millen) (NA)

I r Nine Mile Point Nuclear Station Unit 1 Radiological Environmental Monitoring Program Sampling Locations Table S.l (Continued)

Type of ~Map (Env.

Sam le Location Collection Site Pro ram No. Location Food Product (CR) 55 Produce Location ¹8>> 12.6 mi 9 225'M (Denman) (Nh)

Food Product 56 Produce Location ¹9>> 1.6 mi 9 171 S (O'onnor) (Nh)

Food Product 57 Produce Location ¹10>> 2.2 mi 9 123 ESE (C. Lawton) (Nh)

Food Product 58 Produce Location ¹ll>> 2.0 mi 9 122 ESB (C. R. Parkhurst) (Nh)

<<Map See Figures 5.1-1 and 5.1-2

>>Food Product Samples need not necessarily be collected from all listed locations. Collected samples will be of the highest calculated site average D/Q.

.(N/h) ~ not applicable f

APPENDIX A DOSE PARAMETERS FOR IODlNE 131 AND 133 (

PARTICULATES AND TRITIUM S

APPENDIX A DOSE PARAMETERS FOR IODINE - L31 AND - 133'ARTICULATES AND TRITIVM This appendix contains the methodology which was used to calculate the dose parameters for Z-L31, I-133, particulates, and tritium. The dose parameter, Ri, was calculated using the methodology outLined in NUREG&L33 and Regulatory Guide 1.109, Revision 1. The radioiodine and particulate Technical Specification (Section 3.6.15) is applicable to the location in the unrestricted area where the combination, of existing pathways and receptor age groups indicates the maximum potential exposure occurs, i.e., the critical receptor. The inhalation and ground plane exposure pathways are considered to exist at all locations but the critical location will be used for dose purposes. The grass-goat~33c, the grass-cow-mi33c, giass-co~eat, and vegetation pathway's are considered to exist at specific locations. Ri values have been calculated for the adult, teen, child and infant age groups for all pathways. The methodology used to calculate these values follows:

A.l Inhalation Pathwa K(BR) (DFA )

where+

dose factor for each identified radionuclide of the i organ of interest (units ~ mrem/hr per yCi/m3 );

K' ~ a constant of unit conversion.

~ 10 6 pCi/gCi; (BR) ~ Breathing rate of the receptor of age group a, 3

(units ~ M /yr);

(DFAi) ~ organ inhalation dose factor for radionuclide i for the receptor of age group a, (units ~ mrem/pCi).

e

The breathing rates (BR) a for the various age groups, as given in Table E-5 of Regulatory Culde 1.109 Revision 1, are tabulated below.

A e Crou (a) Breathin Rate (m~/yr )

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalat>on dose factors (DFA.) i a for the various age groups are given in Tables E-7 through E-10 of Regulatory Cuide 1.109 Revision l.

A.2 Cround Plane Pathwa i

t R = K'K"(SF) DFG. ( I-e )

where:

dose factor for the ground plane pathway for each identified radionuclide i f6r the organ of interest (units = mrem/yr per uCI/sec per m )

K' a constant of unit convei sion;'0 pCi/uCI; K" = a constant of unit conversion; 8760 hr/year;

the radiological decay constant for radionuclide i, (units = sec )

t = 'he exposure time, sec; 8

4.73 x 10 sec (15 years);

DFCi the g round plane dose conversion factor for radionuclide i; (units = mrem/hr per .pCI/m~)

SF = the shielding factor (dimensionless);

I A,shielding factor of 0.7 Is discussed in Table E-15 of Regulatory Cuide

1.109 Revision 1. A tabulation of DFC. values is presented in Table E-6 of Regulatory Guide 1.109 Revision 1.

I A.3 Crass>>Cow or Coat>>Milk Pathwa

-XE t

-XItf r l~ + B (1-e Rl >> K'QF U F- (DFL ) e Y I

b t I h (I-f f ) r(lm ) + B. (I-e )

Y E

i where:

M Rl dose factor for the cow milk or goat milk pathway, for each identf fied radlonuclide I for the organ of Interest, (units 0 mrem/yr per uCI/sec per m )

C K' a constant of unit conversion; 10 pCi/uCi QF = The cow's or goat's feed consumption rate, (units = Kg/day-wet weight) the receptor's milk consumption rate for age group a, (units =

ap liters/yr);

Y = the agricultural product>vity by unit area of pasture feed grass, (units = kg/m~);

Y -" the agricultural productivity by unit area of stored feed, (units I -"kg/m~);

F the stable element transfer coefficients, (units = pCi/liter per pCi/day);

r = fraction of deposited activity retained on cow's feed grass; (DFL.,)

i a

= the organ ingestion "dose factor for radionuclide i for the receptor in age group a, (units = mrem/pCi);

the radiological decay constant . for radionuclide i, (units = sec );

the decay constant for removal of activity on lea f and plant.

w surfaces by weathering 5.73 x 10 sec (corresponding to a 10 day half-life);

-92>>

~ ~ tf = the transport time from feed to cow or goat to milk, to receptor, (units

~

= sec);

th = the transport time from harvest, to cow or goat, to consumption, (units = sec);

tb = period of time that soil is exposed to gaseous effluents, (units =

sec);

iv concentration factor for uptake of radionuciide i from the soil by the edible parts of crops, (units = pCi/Kg (wet weight) per pCi/Kg (dry soil);

P = effective surface density for soil, (units = Kg (dry soil)/m~);

f = fraction of the year that the cow or goat is on pasture*;

fs = fraction of the cow feed that is pasture grass while the cow is on pasture; t = period of pasture grass and crop exposure during the growing season, (units = sec);

<<Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1;109 Revision 1, the value of f was considered unity in lieu of s

s/te-specific information. The value of f was 0. 667 based upon an p

8-month grazing period.

Table A-1 contains the appropriate values and their source in Regulatory Guide 1.109 Revision 1.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q:

R -" K'K"'F Q U (DFL.) 0.75(0.5/H)

>> 93>>

c Where:

dose factor for the cow or goat milk pathway for tritium for the organ of interest, (units = mrem/yr per uCi/m'):

K'" = a constant of unit conversion; 10s gm/kg H = absolute humidity of the atmosphere', (units = gm/m');

0.75 = the fraction of total feed that is water; 0.5 = .the ratio of the specific activity of the feed grass water to the atmospheric water.

Other values are given above; A value of H of 8 grams)meter~, was used ln Heu of site-specific information.

.A.¹ Grass-Cow-Meat Pathwa lE t e i + B. ( I m

's Y I

t -X.th (l-f f ) r(lm B iv (l-e Y

s E i

B.

Rl dose factor for the meat ingestion pathway for radionuclide i for

-2 .

any organ of interest, (units ~ mrem/yr per uCi/sec per m );

the stable element transfer coefficients, (units = days/Kg):

U the receptor's meat consumption rate for age group a (units =

ap kg/year; t = the transport time from slaughter to consumption, (units = sec);

th = the transport time from harvest to animal consumption, (units = sec):

t = period of pasture grass and crop exposure during the growing season, (units = sec)

All other terms remain the same as defined for the milk pathway. Table A-2 contains the values which were used in calculating R..

I The concentraCion of -tritium in meat is b'ased on airborne concentration rather Chan deposition. Therefore, the R. is based on X/Q.

1 R "-K'K"'FPFU (DFL ) (0.75(O.S/H)

T ]

where:

B RT dose factor for the meat ingestion pathway for tritium for any organ. of interest, (units = mrem/yr per uCi/m~).

All terms are defined above.

A.S V etation Pathwa The integrated concentration in vegetation consumed by man follows thc expression developed for milk. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the'ime period beCween harvest and consumption, therefore:

itb L

itL E lm R

i

= K'(DFL ) UafL e Y AE I

-IE t -X. t S Kith r(l e )

~iv ('

U a

f e g Y.v X h.

i where:

~

V dose factor for vegetable pathway for radionucfide i for the organ of interest, (units = mrem/yr per uCi/sec per m );

K' a constant of unit conversion; 6

10 pC1/uCi:

U the consumption rate of fresh leafy'egetation by the receptor in age group a, (units = kg/yr);

fL = the fraction of the annual intake of fresh leafy vegetation grown locally; the fraction of the annual intake of stored vegetation g rown locally; the average time between harvest of leafy vegetation and its consumption, (units = sec);

average time between harvest of stored vegetation and its consumption, (units = sec);

the vegetation area density, (units = kg/m~);

t = period of leafy vegetable exposure during growing season (units = sec);

All other factors are defined above.

Table A-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.

ln lieu of site-specific data, values for f and f of 1.0 and 0.?6 ~

L g

~

respectively, were used in the calculation. These values were obtained from Table E-IS of Regulatory Guide 1.109 Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the R.i is based on X/Q:

V K'K" + f 0'75 0'5/H RT U fL U (DFLi) where:

R V = dose factor for the vegetable pathway for tritium for any T

organ of interest, (units = mrem/yr per uCi/m~).

All other terms are defined in preceeding sections.

~

~

TABLE A-1 Parameters for Cow and Goat Milk Pathways Parameter Value Reference (R . Guide 1.109 Rev. I)

QF (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 (kg/m') 0.7 Table E-15 tf (seconds) 1.73 x 10 (2 days) Table E-15 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFLi) (mrem/pCi) Each radionuclide Tables E-ll to E-10 F (pCi/day per pCl/liter) Each stable element Table E-1 (cow)

Table E-2 (goat) 8 t (seconds) 4.73 x 10 (15'yr) Table E-15 Y (kg/m~) 2.0 Table E-15 Y (kg/m~) 0.7 Table E-15 t (seconds) 7.78 x 10 (90 days) Table E-15 U (lltef s/yr) 330 infant Table E-5 330 child Table E-5 000 teen ~ Table E-5 310 adult Table E-5 te (seconds) 2.59 x 1066 (pasture) Table E-15 5.18 x 10 (stored feed)

B; (pCi/Kg (wet weight) Each stable element Table E-l per pCi/Kg (dry soil))

P (Kg dry soil/m~) 200 Table E-15

I TABLE A>>2 Parameters for .the Meat Pathway Parameter Value Reference (R . Guide 1.109 Rev.

'.0 (radioiodines) 1'able E-15 0.2 (particulates) Table E-15 Ff (pCl/Kg per pCi/day) Each stable element Table E-1 U

ap (Kg/yr) 0 infant Table E-5 01 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL ) (mrem/pCi) Each radionuclide Tables E-11 to E-14'able Y (kg/m~) 0.7 E-15 Y (kg/m~) 2.0 Table E-15 t (seconds) 0.73 x 10 (15 yr) Table E-15 t (seconds) 1.73 x 10 6 (20 days) Table E-15 (seconds) 7.78 x 10 (90 days) Table E-15 t (seconds) 2.59 x 10 6

(pasture) Table E-15 5.18 x 10 (stored feed)

QF (kg/day) 50 Table E-3 (pCi/Kg (wet weight Each stable element Table E-1 per pCi/Kg (dry soll))

P (Kg (dry soil)/m~) 200 Table E-15

-99"

e TABLE A-3 Parameters for the Vegetable Pathway Parametei Value Reference (R . Guide 1.109 Rev. 1 r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFL ) (mrem/Ci) Each radionuclide Tables E-11 to E U (kg/yr) - infant 0 Table E-5

- child 26 Table E-5

- teen 42 Table E-5

- adult 64 Table E-S S

U (kg/yr).- infant

- child 0 Table E-5 520 Table E-5

- teen 630 Table E-5 a dult 520 Table E-5 j

t (seconds) . 8.6 x 10 (1 day) Table E-15 t(seconds) 5.18 x 10 (60 days) Table E-15 Y (kg/m') .2.0 Table E-15 t (seconds) 5.18 x 10 (60 days) Table E-15 t (seconds) 4.73 x 10 (15 yr) Table E-15 P(Kg(dry soil) /mi) 240 Table E-15 81 (pCi/Kg (wet weight) Each stable element Table E-1 per pCi/kg (dry soll))

-100-

APPENDIX B QfAGFVUNS OF UQUlD AND GASEOUS RADWASTE TREATMENT SYSTEMS

-101-

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- I 02- NINE MILE. POINT-UNIT 1 OFFSITE DOSE CALC. MANUAL

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-109-

NOTES TO FIGURE B (a) NHPl Stack (height is 350')

(b) NHP2 Stack (height is 430')

(c) JAFNPP Stack (height is 385')

(d) NHPl-Radioactive Liquid Discharge (Lake Ontario, bottom)

(e) NHP2 Radioactive Liquid Discharge (Lake Ontario, bottom)

(f) JAFNPP Radioactive Liquid Discharge (Lake Ontario, bottom)

(g) Site Boundary (h) Lake Ontario Shoreline (i) Meteorologi'cal Tower (j) Training Center (k) Energy Information Center Additional Information:

- NHP2 Reactor Building Vent is located 187 feet above ground level

- JAFNPP Reactor and Turbine Building Vents are located 173 feet above ground level

- JAFNPP Radwaste Building Vent is 112 feet above ground level

- The Energy Information Center and adjoining picnic area are UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC

- Lake Road, a private road, is an UNRESTRICTED AREA within the SITE BOUNDARY accessible to HEHBERS OF THE PUBLIC 5-6

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C APPENDlX -C DlSPERSloN CALCULATlON TABLES

-113-

l TABLE C-I D/q TABLE (ANNUAL METEOROLOGICAL DATA)

HttP UtlIT+I SIhCK CORRECTKD FOR OPEH TERRh!N RECIRCULh11OH otooootooooottotoooo ~ RKLhTIVE DKPOSTTTON PER UHIT hREh Itt~ ~ -21 AT FIXED POINTS SY OOUHUINO SECTORS ~ too ~ otto ~ ooo ~ ~ o ~ ~ to DIRKCT ION DISTANCES IN NILKS FROtl SITE .so I.oo I.so e.oo R.50 3.00 3.50 4.00 4.50 5. ~ 8 5.50 8 1.040E-OS 3.260E-09 I.RC4E- ~ 9 C.TSIE-IO 4.RR9E-IO R.89lf-lo 2.10IE-IO I 594K-10 1.25IE-IO 1.0 ~ TE-I ~ S.RTRE-II Sstt 1.206E-OS 3.72TE-Ot 1.4CRE- ~ '9 '1.$ 7IE-I ~ 4.9RIE-IO 3.36TE-I ~ 2.44TE-IO 1.856K-IO 1.454E-IO I . I CSE-I ~ '9.5$ 6E-II SQ 7.44IE-09 8.403K- ~ 9 't. ~ 52E I ~ 5.443E-IO 3.459K-IO 2 390E-Io 1.147E-IO 1.328E-IO 1.042K-IO $ .366E-II C. 85 IE- I I lt 8lt 2. 169E- ~ 9 T. C32E-I ~ 3.843E-I ~ 1.835E-I ~ I. 1$ 4E-I ~ S.RCOE-I I C. O14E-I I 4.63$ E-I I 3.645K-I I R.932E-II R.40RE-II IJ R. 456E- ~ 9 ~ . 5'9 IE-I ~ 3. CSOE-I ~ e. ~ OSE-I 0 I.'349E-10 9.420K-ll C.tRTK-II 5.2$ $ E-II 1.155K-II 3. 339K-I I R.734E-II UNII 5.076E-09 1.744E-O9 7.43$ E-I ~ 4.805E 10 R.TIIK-I~ 1.890E-IO 1.3$ 9E-IO 1.059E-IO 8.31$ E-II C.CSRE-II 5.4C9E-II Htt 1.666E-08 4.947K- ~ 9 1.9CIE- ~ 9 1.857E-09 C.C05E-IO 4.514E-I ~ 3.R74E-IO R.417E-IO 1.936K-I ~ 1.552E-I ~ 1.869E-IO Ntt tt I .Sbef-ob 4.CCRE-Ot I. ~ 14f ~ 9 t. CC'tf-I ~ C.003E-IO 4.086E I ~ 2.951E-IO R.236K-IO 1.741E-IO 1.40'IE-I ~ I . 14$ E-I ~

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~

ESE 2.837E-OS 7.97IE- ~ 9 3. ~ TRE-Ot I.CROE-Ot '9. 9$ 2E-I 0 C. 155K-I ~ 4. 8CTE-I 0 3. CCTE-10 R. $ 57E-I ~ R.ROTE-I ~ '1.$ 69E-I ~

CK 2.122E-OS C.RSRE- ~ 9 8.43OE-Ot I.R95E- ~ 9 $ .$ 35E-I ~ 5.4Ctf-le 3.957E-I ~ R.t'98E-10 8.338E-I ~ 'I . STSE-I ~ 1.536K-IO SSE 1.073E-OS 3.302E- at I.RTSE- at 6.832K-I ~ 4.R5IE-IO R.tOIE-I ~ 8.105E-IO 1.596E-IO 1.25IE-I ~ 1. ~ OCE-I ~ S.RCIE-II DIRECTION DISTANCES IH NILES FRON SITE 6.00 6.50 7.0 ~ T.SO $ .00 8.50 9.00 9.50 10.00 15. ~0 eo.oo 8 6.917E-II 5.999E-II 5.898K-ll 4.71$ E-I I 4.RSRE-II 3.Self-l I 3.470E-II 3.ICTE-II 2.904E-II 1.533E-II 9.C64E-I2 Sstt 8.00IE-II C. 934f-I I C. Ie IE-11 5.449E-II 4.$ $ CE-II 4.409E-II 4. ~ OIE-II 3.650E-II 3.344E-II 1.154E-I I 1.099E-II SU 5.704E-II 4 963K-II 4. 319 E-I I 3.$ 96E-II 3. 492K - I I 3.149K-II R.SSCE"II 2.604K-II 2.384E-II 1.842E-II 7.742E-IR W SII R.OOOE-II 1,749E.-I I 1.544E-I I 1.373E-II I.R31E II I . I I OE- I I I.OOTE-II t.i$ 3f-le 8.4leE-te 4.393E-IR R. 146E- I 2 U 2 274E-ll 1.988E-II 1.754E-I I 1.5C IE-I I I . 398E-I I I 26IE-II 1.144E-II 1.042E-II 9.546E-IR 4.tCSE-IR 3. 097E-IR IIHU 4.547K-II 3.973E-II 3.505E-II 3. I I SE- I I 2.794E-II 2.519E- I I 2.284K-II 2.082K-II 1.906E II 9.'tOTE-Ie C. 'I 68E- IR NU 1.056E-I ~ 9.127E-II $ .052E-II T.IC3E-II C.4'ITE-II 5. 7SSK - I I S.R45E-I'I 4.77tf ll 4.375E-II 2.RCCE-II 1.405K-i I NHQ 9.565E-II 8.256E-II 7.286E-II C.483K-I I 5.810E"II 5.240E-II 4.753E-I'I 4.333E-II 3.968K-ll R. ~ CCE-ll 1.286E-II H 1.048E-IO 9.092K-II ~ .883E-II 7. 139E- I I C.39$ E-II 5.770E-II 5.234E-I I 4.77IE-II 4.369K II e.eTCK-II I . 418E-I I NNE 5.23lf-! I 4.SSSE-II 4. ~ IOE II 3.5'73f-I I 3.20lf-l I 2.$ $ 6E-II R. C I 6E-I I 2.3$ 4E-II 2.1$ 2E-II 1.130E-II 1. 0 I ef- lz HE 5.879E-II 5.083E-II 4.4$ ef-li 3.9$ 5E-II 3.5CSE-II 3. 214E" I I R. 912E- I I R.CSRE-II 2.425K"Il I . R45f -I I T.CC3E-IR EHE I . 1$ IE-10 1.535E-I ~ 1.354E-I ~ I.eosf-le I. ~ 19E-10 9.728K-II 8. 8 I SE- I I $ .034E-II 7.352E-II 3.19tE-I I R. 351 K-I I E 2.3$ 5E-I ~ R. 050K-I ~ I.SOOK-I ~ I.COOE-I ~ 1.440E-IO 1.298K-l 0 I . 176E-I 0 I.OTRE-IO 9.805E-II 5.054E-II 3. 119E- I I ESE 1.555K-IO I . 336K-I ~ 1.179E-I 1. 048E- I ~ 9.390E-II 8.464E-II 7.672E-II C.989K-II 6.395K-II 3.30IE-II R. ~ 40E-II

~

SE 1.280E-I 0 I . I OSE-I ~ 9.751E-I I b. CTTK-I I 7.116E-II 7. 0 I 4K -I I 6.362E-II 5.799K-ll 5.3llf-ll 8.765E-II I.TRRE-I I SSE 6.903E-II 5.979E-I'I S.'e79E-11 4. 70 IE-I I 4.P ICE-I I 3.806E-II 3.455E-II 3. 153K -11 2. 890K-I I 1.522K-II 9.5C9E-IR

I I TABLE C-2 D/Q TABLE (GRAZING SEASON METEOROLOGICAL DATA)

NNP UN)l ool STACK CORRECIED FOR OPEH TERRAIN RECIRCULAT)OH

~ ooooo ~ oooooooooooooo RELATIVE DEPOS)TTOH PER UNIT AREA INo ~ -2) AT FIXED POINTS BY DOWNU)HD SECTORS ~ ooooooooooo ~ ooo ~ o ~ ~

DIRECT IO)i D)STANCES IH )IILKS FROH SITE .50 I.o ~ 1.50 R.OS R.5 ~ 3.00 3.50 O.o ~ 4.50 5. ~ 0 5.50 8 I. ~ 79E-08 3.320E-49 I .RTOE-O'9 C.TOOK-I ~ O.ISRE-I .R.bobf-)0 2.064K-IO 1.565K-IO I.RRTE-IO 9. 81CE-I I

~ 8.)eoE-)i SSU I. ~ 30E-08 3.2%RE- at 1.270E- at 4.849K-I ~ 4.247E 10 R.93&E-I ~ R. 136K-I 0 I.CRRE"lo 1.278E-IO ).oe3E-t ~ 8. 00 IE-I I SU 5.999E- ~ 9 ).970K- at S.OTHE-I ~ O.ocof-t ~ 2.839K-I ~ I tcof-lo ).436K-Io I. ~ 93K-lo 8.580K-i I 4.89$ E-II S.CSSE-II USH I.C58E-09 5. 939E- I ~ R.SRCK-I ~ ).432K-I ~ 9.253E-II C.O63f-)I O. Tsrf-) I 3.C35E-II R.859E-)1 8.304K-II 1.88CE-II U I.STRE- at C.73CE-I ~ e. 9lef-I ~ I.CCRE-I ~ I. ~ 18f-lo 7.548K-) I 5.560E-II 4.249K-tl 3.300E II R.CS&K ll R.ROOE-II UHU O.&29K-ot 1.519E- ~ 9 C. CTTE-I ~ 3.744E-I ~ 2.4)bf-)0 I.C$ 3f-)0 ).236E-IO 9.023K-II 7.398E-) I 5.965K-) I A.SCTE-II HU 1.586E-OS 4.7$ 2f-ot I.t ~ CE" ~ 9 1.032E-O'9 C.OCSE-) ~ 4.430K-IO 3. 2 I TE-)0 R.437E-)0 1.906E-')0 I.SRSE"I ~

4.458E" at I. 8l SE- ~ 9 9.788K-I ~ C.OSSE-IO O.)etf-lo 2.993K-I 0 R.RCSE-IO 1.772K-I ~ ).beef-) ~

I.R5lf"I 0 I. ICSK-I ~

NNU I.SS&E-Ob N I.C3IE-OS 5.07CE- at R. 03)E.- ~ 9 1.105E-09 4.\53E-I ~ 4.77&E-I ~ 3. @17K "10 e.c39E-IO R.ocrf-) ~ 1.459K-i ~ 1.340E-I ~

NHK C.saaf-ot 2.113E- at d. ~ ORE-I ~ 4.899E-) ~ 3.)RTE-IO R. ICTE"10 1.585E-I 0 I.RO&E-IO 9.15)f-)1 1.58SE-II C. ROSE- I I NE 7.276E"0'9 a.aeaf-ot t. I 4IK-I~ s.oasf-l ~ 3 185E-10 2.)94E-I ~ 1.598E-I 0 1.212E-IO 9.418K-II 7.5'OIE-II

~ C.I99E-II EHE 2.955K-OS ~ .799E-09 3.Obtf- at I.bbof- at 1.116E-09 8.036E-IO 5.829E-IO 4.4)RE-IO 3.i%Sf-IO 8:Tcof"14 e.ec)f-io E 3.971E-OS I . 143K-OS O.OCIE- at 2.375K-ot ).073K-ot I.OOIE-09 7.23&E-'10 5.463K-IO 4.263K-I ~ 3.4)OK-I ~ 8.792E-IO ESE R.305E-OS C.59SE- at 8.5S3E-09 1.353E-09 8.3CIE-I ~ 5.672E-I ~ 4.094K"I'.46<K-I 3.obtE-io 8.1)of-)0 1.930E-I ~ 1.579K-I ~

CE ).SSOK-OS 5.SSTE- ~ 9 R. 143E-09 I. 138E- at 7. ~ 4SE-I ~ 4.789K-) ~ ~ e.cltE-)o 8.0<sf-) ~ I.COOK-I ~ ).341K-IO SSE 'I . IROE-08 3.36IE- at I . Rl'TE- ~ 9 C.143E-I ~ 4.)CIE-IO R.SRIE-I ~ R. OGRE- I 0 1.545E-IO I.RIOE-I ~ 9.728E-II 7.993E-II DIRECTION DISTAHCES IN NILES FRO)1 S)TE 6.0 ~ 6.5 ~ T. ~ 0 7.54 8.00 8.50 9.00 t.50 lo. 0 ~ 15.0 ~ eo.oo 8 6. 19&E- I I 5.880E-II 5.191E-I I 4.428E-II 4.)53f-il 3.150E-II 3.4 ~ 6K-II 3.'149E-II R. $ 5 IE-I I 1.508E-II 9. 52 I E- I 8 SSU T.OISE-II 4.090E-II S. 371E- I I 4.181E-I I 4.294K-) I 3.$ 76E-II 3. 518E-I I 3.RIOE-II 2.943K-II ).549E-I'I 9. 1 4 I E-12 SU 4. 7 I ef- I I 4.) USE-II 3.C23E-II 3.2ROE-I I e.btOE-)I e.corF.-it 2.366E-II R.ISTE-II 1.976E-II ).034K-II C.OCTE-IR USQ 1.57)E-I I 1.375K-ll I.e)OE II ).OSOE-'I I 9.682K-IR 8.730K-)2 T.tasf-ia 7. RRTE- I 8 c.ceif-ie 3.165K-)e e.irof-ta 1I 1.830E-II I.C03E-II I . 010K- I I I.R58E-II I.ielE-II I.oirE-ii 9.2ROE-IR 8;OOSE-Ie 7.698f-le 4. ~ IRE-le R.soof-)e UNU 0 069K-II 3.53&E-II 3. )ROE-I I R.TTCf-l I R.obrf-)I 2.203K-II 2.030E-II ).850K-I I I.C9$ E-il S. 83$ f-I2 S.509E-IR NU I . 00 IE-,I ~ 9.007E-II T.torf-)I T.OCOE-II 4.334K"II 5.7IIE-II 5.178E-II O.TIOE-I I 4.380K-)1 e. 84)E- I I 1.392E- I I NNIJ 9.7)AE-II 8.397E-II T.OIIE-II C.595K-I) S.OIIE-II 5.332E-II 4. 831E-I I 4. 41 I E- I I 4.040K-II R. IOSE-ll 1.315K-) I H I. )33E-10 9.$ 28E-II S.C73E-II 1.7)rf-it C. 917E-I I C.239E-I I 5.659E-II 5. I COE-I I 4.726E-II 2.165K-)1 1.538E-II NNE S. I SSE-I I 4.49)E"II 3.9CRE-II 3.520K-II 3.157E II R.SOCK-II R.SSOE-II 8.351K-I I R. I SRE-I I I . 116E-I I C.930E-IR HE S. 116K-I I O.ACRE-II 3.93SE-II 3.499E-)l 3.133E-II 8.823K-ll e.ssbf-i) 2.330E-II R. 13 IE-I I I . 097E" 11 C.TC6E-IR ENE I . 882E-I 0 ) .Calf-) 0 ).435K-I ~ I .RTTE-) ~ I.iOAE-I~ 1.03IE-I4 9.350E-)l 8.520K-ll 7.799E-II O. ~ Oef-t) R.548K-ll E 2 323E-I ~ R.O ~ IE-I ~ 1.1CSE-I ~ I .STOE-I ~ I.oorf-)0 1.268E-) ~ I . ISOE-I 0 1.007K Io 9.587E II 4.957K-II 3. ~ COE-II E&E I . 3)4E-I ~ I. 13)E-I ~ t.tSRK-II ~ . 819K -I I T. '955E- I ) 7. 17RE- I I 6. 542E-I I 5.'925E-II 5.424K-II R.SOSK-II ).700K-II SE I )ROE-I ~ 9.TORE-II S.SCOE"II T.CRRE-II C.S33E-II C.i65E"II 5.593E-II 5. I ~ IK-II 0.613K-II e.<<ef-ii 1.52SE-II SSE C.&SOE-II 5.114E-II S. ~ 99K-II O.SOOE-) I 4.073K-II 3.477E-II 3.338E-II 3.007K-II R.793E-II ).473K-II t.ecsf-ia

TABLE C-3 x/q (ANNUAL METEOROLOGICAI. DATA)

NHP UNIT ~ I STACK HO DECAT, UHDEPLETKD CORRECTED FOR OPEN TERRAIN RECIRCULATION ANNUAL AVERACE SEC'IOR 4

.5'.

CHI/O I SEC/HETER CUSEDI

4. I OTE-07 F 00 1.50 9.910K-OS 4.264E-OS

'.ooo DISTAHCE IN HILES R.500 R.558E-04 I . 802E-08 3.000 3.500 4.000

'1.386E-OS I . 124K-08 9.449E-09 4.500 5.'000 5.500 8.144E-OS 7.158E-OS C.3$ $ E-09 SSU 4.880E-OT 1.209E-47 5.133E-OS 3.052E-OS R. 132E-08 1.626K-OS 309E-08 i.oteE-08 9.34$ E-09 d. 166E-09 7.244K-09 SU 3. 851E-01 9.4$ 6E-I4 4.04CE-O4 R.4C3E-OS I .VC6E-08 1.3VVE-OS 1.12$ E-OS 9.545E-09 S.eoof-ot V.eTCE-OS 6.4' VE-09 USU 2.014E-OV 4.984E-OS R. ~ 92E-Ob I.R73E-OS 9.2$ 9E-09 1.436E-09 6.26SE-OS 5.444K-OS 4.8RSE-09 4.349E-OS 3.9CIE-09 W R.SOM-O' C. 73 I E-I8 R.TSVE-48 I.CTSE-OS I . 2 I IE-OS 9.590E-09 S.OOSE-09 6.90SE-OS 6.09lf-ot 5.457E-OS 4.948E"09 IJNU 4.206E-OT I . OR8E-47 4.3RCE-04 R.CITE-OS I.STOE-OS 1.456E-OS 1.192E-OS I . OOSE-OS 8. 7 I SE- ~ 9 7. CVVE-Ot C. SSIE-09 HU I. 119E-06 2.695E- ~ 1 I. ~ STE- ~ 7 C.RSRE-OS 4.340K-OS 3.292E- ~ 8 R.C43E-OS 2.203K-OS I.SSSE-OS I.C44E-OS l.457E-OS NNU 1.062E-OC R.555E-OV I . IRTE-IT 5.898E-OS 4.041E-IS 3.052E-OS R.445E-OS R.037E-OS 1.743E-OS I.S22E-OS 1.35IE 0$

H I . 113E-OC 2.105E-IT I . I ~ IE- ~ 7 C.422E 0$ 4.459E-OS 3.403K-ob R. 141E-Od R.301K-OS I.tTTE-OS I.732K-OS 1.540E-OS NNE C.CC4E-OT I . C I IE-I'7 6.5COK-OS 3.859K-OS 2.711K-ob 2.092E-OS 1.706E-OS I 441E-08

~ 1.247E-OS I ~ 99K-OS 9 SICE-09

~ ~

NE 7. 774E-IV I . 855E-01 1. 43IE-04 4.275E-OS R.939E-08 2.228K-OS 1.192E-OS 1.494E-OS I.RSVE-IS I. IRSE-OS 1.004K-OS EHE 1.390E-OC 3. 376E-IT 1.367E-IT 7.477E-OS 5.38IE-OS 4.03&E-OS 3.ROSE-OS R.C44E-OS R.R4RE-OS 1.942E-IS 1.7IOE-OS E 1.550E-OC 3.VSSE-OV I .S4IE-OT 4.870E-OS C.O36E-OS 4.507E-OS 3.564E-OS 2.930E-OS 2.4'FTE-OS R.140K-ob I.SSOE-OS

8. 385E-IV R. I44E-07 4.38CE-OS 4.462E-OS 3.323E-OS 2.486E-OS I.SCTE-OS I.CITE-OS 1.3C6E-OS I.IVSE-OS 1.035E-OS ESE SE 5.921E-OT 1.4SSF.-OV C. IbRE-0$ 3.679E-OS R.559E-OS 1.936K-OS 1.544K-OS i.eisr.-ob I.oblf-oo 9.36sf-ot 8.241K'-ot SSE 3.64VE-OV $ .79$ E-OS 3.1CRK-IS R.RCOE 08 1.593E-OS I.RRSE-OS 9.926E-OS 8.333E-OS 1.113E- ~ 9 C.300E 49 S.CITE-0'9 AHHUAL AVERACE SEAR IHC 6.0'.50 CNl/0 I SEC/NETFR CUSED)

I

~ ~

7.5'ISTANCE 8.I'D IH HILES 8.500 9.000 .S.soo Io.ooo is.ooo eo.ooo 8 5.765E- ~ 9 S.RFVK-IS 4.499E-ot 4.568K-ot 4.215E-09 4.014E-09 3.180E-O'9 3. 510E-09 3. 3$ 0E-O'9 R.RC9E-09 1.689E-09 SSU C.503E- ~ 9 5.923E-49 5.473E- ~ 9 5.480E- ~ 9 4.735E-09 4.429E-OS 4.155E-09 3.910E-09 3.690E-OS R.414E-O9 1.764E-O9 CU 5. 863E-09 5.363E-09 '4. 915E- ~ 9 4. C33E-It 4.330E-09 4.060E-OS 3.81$ E-OS 3.COOE-O'9 3.403E- ~ 9 e.es4E-IS 1.659E-09 USU 3.C40E-09 3.384E-49 3.184E- ~ 9 3.005E- ~ '9 2.$ 42E-09 R.C95E-O9 2.560E-O'9 2.436E-OS 2.323E-OS I.C35E-O'9 1.241E-OS U 4.529E-09 4.191E-OS 3.939E- ~ 9 3.VISE-OS 3.500E-09 3.31M- ~ 9 3.i4IE-09 R.SSSE-09 2.842E-ot 1.983E-OS I.SOCE"09 IJHU C. I 8 I E-09 5.653E- ~ 9 S.R4RE-IS 4.48IE-OS 4.5CRE-OS 4.27VE-OS 4. 022E-It 3.192E-OS 3.585E-OS 2.37SE-OS 1.144K-09 NU 1.306K-OS l. 189K-OS I. ~ STE-08 1. I I SE-08 9.417E-OS S.SSSE-OS 8.307K-09 7.813E-OS 1.368E-09 4.4OM-I9 3.498K-OS NHU I.RI3E-OS 1.105E-OS I.IRRE-IS 9.49CE-09 8.859E- ~ 9 S.R94E-OS 1.790E-09 7.33SE-OS 6.'931K-09 4.513E- ~ 9 3.362E-09 H I. 386E-IS 1.265E-.O4 I. I TIE-08 I. ~ 89E-04 I.OITE-IS 9.526E-09 8.953E- ~ '9 8.437E-09 7.972E-O'9 S.RTOE-OS 3.81CE"09 NNE S.SCFK-OS S.IRRE-OS 7.542E- ~ 9 7.033E-09 C.5$ 2E-OS C.I79E-09 5.$ ISE-09 5.493E-09 5. 198E-09 3.474K-OS R.SVOE-09 HE '9.039E"09 S.R63E-OS 'T.CC4E-IS 7. 14 IE" 09 C.68IE- ~ 9 6.213E-OS S.SISK-O'9 S.SSOE-09 5.284E-OS 3.566E-09 R.666E-OS EHE 1.525E-OS 1.3$ 1E-IS I.RVOE-IS I . 174E-0$ I.OSOE-IS I.IICE-OS 9.507K-IS 8.924K-ot $ .402E-OS 5.4R9E- ~ 9 3.950K-ot E I.C73E-OS 1.512E-08 1.388E-IS I .Rb1f-08 I . I SVE-08 I. IOSE-08 1.033K-OS S.CTSE-09 9.099E-09 S.SIOE- ~ 9 4. 191E-09 ESE 9 ISSE-09 8.30$ E-IS T.CISE- ~ 9 T.oe3E-OS 6.505E-09 C. 05IE-09 5 64$ E-09 5.290E-OS 4.970E-OS 3.159K-ot R.RVSE"09 SE. 1.344E-09 C.C44E"09 C. IORE 09 S.C33E-OS 5.223E-09 4.863E-09 4.544E"09 4.259K-09 4.004K-ot R.SCOE-OS 1.852E-OS SSE 5.065K- ~ 9 4.C33E-OS 4.R91E- ~9 4.004E-OS 3.744E-09 3.513K-09 3.306E-09 3. 119E-09 R.SSIE-OS I.SC9E-OS I 4cvs-aa

3 171, 71 7 9 )), >> 1 0 51.1\ 12 13 15 105.

I' (METOR LOCiC L TO(NEP) 711 7 'I . II 71).7)"

O 0

FIGURE, 5.l I Nine Mile POint On-Site Map

,O Yy oO, Envfronmenta I Sample Location 5 W Compass Coordinate (M) '. Sector Designation 180 Radian Angle from North A rrxc)x. ac A (a F(( I 0 000 1200 M(F(RS 0 200 (00 I IIXII ml J

'0 K

/Li N c) fl c0 z

I I 0 OC z

O P

v 3'30'/I)IF'TTT 2

ROAD SI M(HER APERTURE ROAD 2 3 ~

t(ER ts 7 10 11 12 0 CARD l

III I 13 14 15 I 16

~ ~ ~

~ ~ ~

~ ~

~ ~