ML18038A323

Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM

ML18038A323
Person / Time
Site:	Nine Mile Point
Issue date:	08/30/1990
From:	Firlit J NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17056A964	List: ML17056A963 ML17056A965 ML17056A966 ML17056A967 ML18038A323
References
NMP67505, NUDOCS 9009110036
Download: ML18038A323 (513)

Text

ACCELERATED DISTSJBUTION DEMONSTFWTION SYSTEM REGULATOR INFORMATION DZSTRIBUTZONeSTEM (RIDE)

/~, ACCESSION NBR:9009110036 DOC.DATE: 90/08/30 NOTARIZED: NO DOCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05 00220 AUTH. NAME AUTHOR AFFILIATION FIRLITFJ.F. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards "Semiannual Radioactive Effluent Release Rept for Jan-June 1990" & Rev 6-8 of ODCM.

I DISTRIBUTION CODE: ZE48D TITLE: 50.36a(a)(2)

COPIES RECEIVED:LTR Semiannual Effluent Release

) ENCL g Reports SIZE: 4' f NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA PD1-1 PD 1 1 MARTIN,R.

D INTERNAL: ACRS 1 1 AEOD/DSP/TPAB 1 1 TECH ADV NRR/DREP/PRPB11 2 2 D RE~ 01 1 1 RES BROOKS,B 1 1 RGN1 DRSS/RPB 2 2 RGN1 FILE 02 1 1 EXTERNAL: BNL TICHLER,J03 1 1 EG&G SIMPSON,F 2 2 NRC PDR 1 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LINIS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL

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i4 NINE MILE POINT NUCLEAR STATION/P.O. BOX 32, LYCOMING, N.Y. 13093/TELEPHONE (315) 343-2110 August 30, 1990 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit g1 Docket No. 50-220 DPR-63 Gentlemen:

In conformance with the Nine Mile Point Nuclear Station Unit gl Techni~cal Specifications, we are enclosing the Semi-Annual Radioactive Effluent Release Re ort for the period January 1, 1990, through June 30, 1990. Included in this report is a summary of liquid, gaseous and solid effluents released from the station during the reporting period (Tables 1-3), a description of and justification for recent revisions to the Offsite Dose Calculation Manual (ODCM) (Table 4), an explanation as to the cause and corrective actions regarding the inoperability of any Station Liquid and/or Gaseous Effluent Monitoring instrumentation (Table 5, and Attachment 1), a description of recent revisions to the Process Control Program (PCP) (Table 6), and an update of actual data for the month of December used in the fourth quarter of the July December 1989 Semi-Annual Radioactive Effluent Release Report (Table 7). Copies of revision 6, 7 and 8 of the Unit 1 ODCM and required technical review documentation are also enclosed.

I The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. Dose assessments were made in

,accordance with the NMP-1 Off-Site Dose Calculation Manual.

Distribution is in accordance with Regulatory Guide'0.1, 10CFR50.4 (b)(1) and the Technical Specifications.

If you have any questions concerning the attached report, please contact Gary Corell, Chemistry Unit Supervisor, at Nine Mile Point Unit 1 (315) 349-2070.

Very truly yours, 900911003b 900830 ADQCN, 05000220 oseph F Firlit PDR PNU Vice President Nuclear Generation R

JFF/lmc Enclosures (3 copies)

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, Page 2 t U.S. Nuclear Regulatory Commission August 30, 1990 xc: Director, Office of Nuclear Reactor Regulation (1)

Director, Office of Inspection and Enforcement (1)

Mr. Thomas T. Martin, Regional Administrator, United States Nuclear Regulatory Commission, Region I, Allendale Rd., King of Prussia, Pennsylvania 19406 (1)

NRC Resident Inspector, Nine Mile Point Nuclear Station Unit 51 (1)

New York State Energy Office, 2 Rockefeller Plaza, Albany, NY 12223 Attn: Ms. Donna Ross

OFF-SITE DOSE CALCULATION MANUAL NINE MILE POINT UNIT. 1

~v r" <<.J'qw(,W~Pg ODCH - NINE MILE POINT UNIT 1 TABLE OF CONTENTS

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1. 0 INTRODUCTION 2.0 LIQUID EFFLUENTS 2.1 Setpoint Determinations 2.1.1 Basis 2.1.2 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 Contamination ~ -10

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'iquid Effluent Concentration Calculation 2.3 Dose Determinations 12 2.3.1 Maximum Dose Equivalent Pathway 12 3.0 GASEOUS EFFLUENTS 17 3.1 'Setpoint Determinations 17 3.1.1 Basis 17 3.1.2 Stack Monitor Setpoints 18 3.1.3 Recombiner. Discharge (Off Gas) Monitor Setpoints 21 3.1.4 Emergency Condenser Vent Monitor Setpoint 22 3.1.5 Discussion 23 3.1.5.1 Stack Effluent Monitoring System Description 23 3.1.5.2 Stack .Sample Flow Path - RAGEHS

. 3.1.5.3 .Stack Sample Flow Path OGESHS 25

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

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Sample Frequency/Sample Analysis= 26 3.1.5.5 I-133 Estimates 27 3,1.5.6 Gaseous Radwaste Treatment System Operation 27 3.2 Dose and Dose Rate Determination 28 3.2.1 Dose Rate 31 3.2.1.1 Noble Gases 31 3.2.1.2 Tritium, Iodines and Particulates 33 3.2.2 Dose 35 3.2.2.1 Noble Gas Air Dose 36 3.2.2.2 Tritium Iodines and Particulates 37 3.2.2.3 Accumulating Doses 38 3.3 Critical Receptors 39 e 3.4 4.O Refinement of Offsite Emergency Condenser 40 CFR 190 REQUIREMENTS Doses Resulting From Vent Releases 41 42 4.1 Evaluation of Doses From Liquid Effluents 4.2 Evaluation of Doses i

From Gaseous Effluents 48

'.3 Evaluation" of Doses From Direct Radiation 48 4.4 Doses to Members of the Public Nithin the Site Boundary 49 5.0 ENVIRONMENTAL MONITORING PROGRAM 5.1 Sampling Stations 53 5.2 Interlaboratory Comparison Program 55 5.3 Capabilities for Thermoluminescent Dosimeters 56 Used for Environmental Measurements.

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

~Pa e Table l-l Average Energy Per Disintegration 59 Tables 2-1 Aiat Values for the NMP-1 Facility 60.

to 2-8 Table 3-1 Critical Receptor- Dispersion Parameters for Ground .Level and Elevated Releases 68 Table 3-2 Gamma Air and Hhole Body Plume Shine Dose Factors for Noble Gases (Bi and Vi) 69 Table 3-3 Immersion Dose Factors for Noble Gases 70 Tables 3-4

'to 3-22 ">>Organ Dose and Dose Rate Factors (Ri) 71 Table 5-1 NMP-1 Radiological Environmental Monitoring Program Sampling Locations 90 Figure 5.1-1 Nine Mile'oint On-S/te Hap 94 Figure 5.1-2 .Nine Mile Point Offsite Hap 95 Appendix A Liquid Dose Factor Derivation (Aiat) 97 Appendix B Plume Shine Dose Factor Derivation 100 (Bi and Vi)

...Appendix C . Organ Dose and Dose Rate Factors for Iodine 131 and 133, Particulates and Tritium 104 Derivation (Ri)

Appendix D Diagrams of Liquid and Gaseous Radwaste Treatment Systems 115

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1.0 INTRODUCTION

'he Offsite Dose Calculation Manual (ODCM) provides the methodology to be used for demonstrating compliance with the Radiological Effluent Technical Specifications (RETS), 10 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 Hater

...Reactors,"'September 1982; DraftNUREG-0473, Revision 2. "Radiological Effluent Technical Specifications for BNR's", "July 1979; NUREG 0133, "Preparation of Radiological Effluent Technical Specifications 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 revise the ODCM, these revisions wi 11 be made in accordance with Technical Specifications.

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2.0 LIQUID EFFLUENTS 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

- specified in 10 CFR 20, Appendix 8, Table II, Column 2.

Setpoints for the Service Hater System Effluent Line will be calculated quarterly based on the radionuclides identified during the previous year's releases from the liquid radwaste system or the isotopes identified in the most recent radwaste I

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 Hater 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 X>(uC1/mi)i> expression (Section 2.1.2, 2.1.3).

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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 emi tters 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 Monitor shall be contained in the Nine Mile Point Station Procedures. These methods shall be in accordance with the following:

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Setpoint (Hi alarm)<0.9 (uC1/m1>sy <CF)l TDF/Fsw + background 2-[(uCi/ml)iT/MPCi]

il Setpoint (Alert alarm)<6.7 (UCi/ml)i~ (CF) TOF/Fsw + background Z;[(uCi/ml)iT/HPCi]

(uCi/ml)ig concentration of gamma emitting isotope i in the sample, or the

.." -. -'corresponding MPC of, gamma emitting isotope i (HPC)ig ,

whichever is higher (units uCi/ml).

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

'OF . 'Total Oilution Flow (units gallons/min)

Fsw Service Water Flow (units gallons/min)

CF monitor calibration factor (units net cpm/uCi/ml)

HPCi liquid effluent radioactivity concentrations limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.

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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 uCi/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.

[(uCi/ml)iT/MPCi] Required Dilution Factor. If MPC values are used in the Z(uCi/ml)i y, they must also be used in calculating ROF (numerator).

TDF/Fsw Actual Dilution Factor 2.1.3 Liquid Radwaste Effluent Line Alarm Setpoint The;detailed methods for establishing setpoints for the Liquid Radwaste

'ffluent 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 (uCi/ml)ig (CF) TDF/Fre background

[ (uCi/ml)iT/MPC ]

Setpoint (Hi alarm) <0.7 (uCi/ml)ig (CF) TDF/Fre + background Z;[ (uCi/ml)iT/HPCi]

(uCi/ml)i y concentration of gamma emitting isotope i in the sample or

, the corresponding MPC of gamma emitting isotope i (HPC)i

." whichever is higher.

(uCi/ml)iT concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or the corresponding HPC of isotope i HPCi whichever is high'er.

(units uCi/ml)

TDF Total Dilution Flow (units gallons/min)

Fre .Radwaste Effluent Flow (units gallons/min)

CF monitor calibration factor (units net cps/uCi/ml)

• • For periods with known reactor water to RCLC system leakage, RCLC maximum permissible concentration may be prudently substituted for the above.

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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 uCi/ml)

(HPC)i. same as HPCi but for gamma emitting nuclide only.

0.9 and 0.7 factors of conservatism to account for inaccuracies.

X;[(uCi/ml)iT/HPCi] Required Dilution Factor. If HPC values are used in the X (uCi/ml)ix', they must also be used in calculating RDF (numerator).

Notes:(a) If TDF/Fre gf(uCi/ml)iT/MPCi]

the discharge could not be made, since the monitor would be continuously in alarm. To avoid this situation, F will be reduced (normally by a factor of 2) to allow setting the alarm point at a concentration higher than tank concentration. Thi's

. wil.l also 'result in a discharge canal concentration at approximately 50K maximum permissible concentration.

(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).

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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

'n a batch mode. To prevent the inadvertent release of any liquid radwaste effluents, radwaste discharge is mechanically isolated (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 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 ad]usted.

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 8, Table II, Column 2 (Technical Specification Section 3.6.15.a(1))

limits are not exceeded.

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2.1.4.3 Sampling Representativeness This section covers Technical Specification Table 4.6.15-1 Note b concerning thoroughly mixing'f 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)

Hhere:

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

Additionally. the Hi Alarm setpoint of the Liquid Radwaste Effluent Radiation Monitor is set at a value corresponding to not more than

-- ""'.70'L of-~its calculated response to the grab sample or corresponding MPC 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.

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2.1.4.4 Liquid Radwaste Systems Operation Technical Specification 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.

Utilization of-the radwaste"system will be based on the capability of the indicated components of each process system to process contents of the respective low conductivity and high conductivity collection tanks:

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

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

Cumulative dose contributions from liquid effluents for the current l

-'alendar '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 pro]ection 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 3.6.15.a(2) are not exceeded. (Thereby implementing the requirements of 10CFR50.36a, General Design Criteria 60 of Appendix A and the Design Ob)ective given in Section II-D of Appendix I to 10 CFR50).

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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.

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2.1.4.5 Service Water System Contamination Service water is normally non-radioactive. If contamination 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 LLO requirements of Technical Specification Table 4.6.15-1 completed. If it-'is-determined. that an inadvertent radioactive discharge is occurring from the service water system, then:

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

b) Oaily service water effluent samples shall be taken and analyzed for principal gamma emitters until the release is terminated, c) An incident composite shall be prepared for H-'3, gross alpha, Sr-89, Sr-90 and Fe-55 analyses and I

-'d) " Oose projections shall be performed .in accordance with Section 2.3 of this manual (using estimated concentrations for H-3, Sr-89, Sr-90 and Fe-55 to be conservatively determined by supervision at the time of the incident).

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

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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 the '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/milliliter (uCi /ml) total activity.

The concentration of radioactivity from Liquid Radwaste batch releases and, if applicable, Service Hater System and emergency condenser start-up vent 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:

~PC Fr ti " 11< ~s((" i/ml)is*Fs)/( P i* Z s(Fs Hhere:

HPC Fraction The limiting concentration of 10 CFR 20, Appendix 8, Table 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.

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(uCi/ml)iis The concentration of nuclide i in particular effluent stream s, uCi/ml.

F The flow rate of a particular effluent 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)

X ((uCi/ml)i *F ) The total activity rate of nuclide i, in all effluent streams s, uCi/ml*gpm

$ (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 January 1981 through 31 December 1981; The radwaste liquid 'releases are based on a canal di.scharge rate of 590 ft /sec which affects near field and far field dilution; therefore, this report is specific to this .situation. Utilizing the effluent data contained in the 12

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2.3.1 (Cont'd)

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'ody as well as seven organs and/or tissues---

for the adult, teen, child, and infant age groups. From the standpoint of liquid effluents, the pathways evaluated included fish and drinking water ingestion, and external exposure to water and sediment.

The majority of the dose for a radwaste liquid batch release was received via the fish pathway. However, to comply with Technical Specifications for dose projections, the drinking water and sediment pathways are included. Therefore, all doses due to- liquid effluents are calculated monthly for the fish and drinking water ingestion pathways and the sediment external pathway from all detected nuclides

" <<in liquid effluents released to the unrestricted areas to each organ. The dose projection for liquid batch releases will also include discharges from the emergency condenser vent as applicable, for all pathways. Each age group dose factor, Ai t, is given in tables 1-1 to 1-8. To expeditetime the, dose is calculated for a maximum individual instead of each age group. This maximum individual will be a composite of the highest dose factor of each age group for each organ, hence Ait. The following expression from NUREG 0133, Section 4.3 is used to calculate dose:

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2.3.1 (Cont'd)

Nhere:

Ot The cumulative dose commitment to the total body or any organ, from the liquid effluents for the total time period (dT1), mrem dT1 The length of the 1 th time period over which Cil and Fl are averaged for all liquid releases, hours Cil The average concentration of radionuclide, i, in undiluted liquid effluents during time period dT1 from any liquid release, uCi/ml Ait The site related ingestion dose commitment factor to the total body or any organ t for each identified principal gamma or beta emitter for a maximum individual, mrem/hr per uCi/ml Fl The near field average dilution factor for Cil during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the

.average flow from the site discharge structure to unrestricted receiving waters, unitless.

Ai t values for radwaste liquid batch releases at a discharge rate of 295 ft /sec (one circulating water pump in operation) are presented in table's 1-1 to 1-4. Aiiat values t for an emergency condenser vent release are presented in tables 1-5 to 1-8. The

'mergency condenser vent releases are assumed to travel to the perimeter drain system and released from the discharge structure at a rate of .33 ft3 /sec. See Appendix A for the dose factor Ai t derivation. To expedite time the dose is calculated to a maximum individual. This maximum individual is a;composite'of -the highest-."

dose factor Ai t of each age group a for each organ t and each nuclide i. If a nuclide"is detected for which a factor is not listed, then it will be calculated and included in a revision to the OOCN.

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2.3.1 (cont'd)

All 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:

For a calendar quarter:

0t < 1.5 mrem total body 0 < 5 mrem for any organ For the calendar year:

Ot < .3.0 mrem total body 0t < 10 mrem for any organ

-" <~where 0 'otal;dose received due to liquid effluent releases to the total body or any organ,

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2.3.1 (Cont'd)

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.

= These calculations will include doses as a result of liquid and gaseous pathways as well as doses from direct radiation. The liquid pathway analysis will only include the fish and sediment pathways since the drinking water pathway is insignificant. This pathway is

. only included in the. station's effluent dose projections to comply "with Technical Specifications. Liquid, gaseous and direct radiation.

pathway doses will consider the James A. FitzPatrick and Nine Mile Point Unit II facilities as well as Nine Mile Point Unit I Nuclear .

Station.

In the event the calculations demonstrate that the 40 CFR 190 dose limits, as defined above, have 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.

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'"",i.'Section, 4.,0'of the ODCM contains more information concerning calculations for an evaluation of whether 40 CFR 190 limits have been exceeded.

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3.0 GASEOUS 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 at 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 materials 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 actual release in progress, or an offgas isotopic distribution or a more conservative default composition specified in the pertinent procedure. If the calculated setpoint ts 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.

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 .

CORM Supervision. In particular, contributions from both JAF and NMP-2 and the Emergency Condenser Vents shall be assessed:

"During outages and until power. operation is again realized, the last operating stack and off gas monitor alarm setpoints shall be used.

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< ~ P

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

( )max 500 mrem/yr where:

release rate for each isotope i, uCi/sec Vi gamma'hole body dose factor in units of mrem/yr per uCi/sec (See Table 3-2)

(Q)max instantaneous release rate limit uCi/sec 18

+ a

'v

'1 ~ I I Q% ltl

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) . Hi alarms be set lower than or equal to (0.5) (Q) max'hall max'3)

Based on the above conservatism, the dose contribution from JAF and NMP-2 can usual,ly 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 mrem/yr value may be reduced accordingly.

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

(C -B) K Q uCi/sec release rate where:

Cm monitor gross count rate in cps or cpm; cps counts per second, cpm counts per minute

'B monitor background count rate Ks stack monitor efficiency factor with units of uCi/sec-cps or uCi/sec-cpm (5) Monitor K factors shall be determined using the general formula:

K QiQi/(C -8) where:

individual radionuclide stack effluent

.release rate as determined by isotopic analysis.

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

-19

,b t

'4 r

~II 4U

3.1.2 (Cont'd)

Alternatively, when stack release rates are near the lower limit of detection, the following general formula may be used. to calculate k:

1/Ks E ~(i i ~kYkEk) 3.7E4d f f '-uCi where:

f stack flow in cc/sec E efficiency in units of cpm-cc/uCi or cps-cc/uCi (cpm counts per minute; cps counts per second)

Ek cpm-cc/bps or cps-cc/ ps From energy calibration curve produced during NBS traceable primary gas calibration or transfer source calibration (bps beta per second; ps gammas per second)

Yk b/d (betas/disintegration) or V/d (gammas/d)

Fi Activity fraction of nuclide i in the mixture i nuclide counter k . discrete energy beta or gamma emitter per nuclide counter s i ~ seconds This monitor calibration method assumes a noble gas distribution typical of a recoil release mechanism. To ensure that the calculated efficiency is conservative, beta or gamma emissions whose energy is above the range of calibration of the detector are not included in the calculation.

Q}

4

3.1.3 Recomb)ner Discharge <Dff 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 I

not to exceed 60 days provided the offgas treatment system is in operation.

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

<R)(KR) QR uCi/sec recombiner discharge release rate "where:

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

KR Qi /R where:

Qi - individual radionuclide recombiner discharge release rate as determined by isotopic analysis and flow rate monitor.

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

J 4 jC I f 4

/

Qi

'la ~

pp g 'I A

l

3.1.3 (Cont'd)

(5) The setpoints chosen provide assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a very small fraction of the limits of 10CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment (thereby implementing the requirements of General Oesign Criteria 60 and 64 of Appendix A to 10CFR Part, 50) .. Additionally, these setpoints serve to,limit buildup of fission product activity within the station. systems which would result if high fuel leakage were to be permitted over extended periods.

3.1.4 Emergency Condenser Vent Honitor Setpoint The monitor setpoint was established by calculation (" Emergency

,Condenser Vent Honitor Alarm Setpoint", January 13, 1986, NHPC File Code ¹'l61*99). Assuming a hypothetical case with (1) reactor water t

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 emergency condenser shell at 300'A of rated flow (or 1.3 E6 lbs/hr), the calculation predicts an emergency condenser vent monitor response of 20 mR/hr. Such a release would result in less than'0 CFR 20.dose rate values at the site boundary and beyond for typical"emergency condenser cooldown periods.

Since a 20 mR/hr mon'itor 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.

IIC of~

h VWII, a IT WI r

'T r~'t. I T T

\ Il tt I

0

3.1.5 Discussion 3.1.5.1 Stack Effluent Moni tori ng System Description

-The NMP-1 Stack 'EffluentaMonitoring System consists of two subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEMS) and the old General Electric Stack Monitoring System (OGESMS). During normal operation, the OGESMS shall be used to monitor station noble'as effluents and collect particulates and iodine samples in compliance with Technical Specification requirements.

The RAGEMS.is designed to be promptly activated from the Main Control

" Room for use in high range monitoring during accident situations in compliance with NUREG 0737 criteria. Overall system schematic for the OGESMS and RAGEMS are shown on Figure B-9. A simplified view of RAGEMS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure B-S.

The RAGEMS can provide continuous accident monitoring and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specification Table 4.6.15-2 limits. Activities as low as 5.0E-B and as high as 2.0E5 uCi/cc for noble gases are detectable by the system.

&jan" i

J P I

~ .0 y ~ y I

~ * 'I le t gled bl 4 II

3 T.5.2 Stack Sample flow Path - RAGEHS

'" 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 RAGEHS located on the Turbine Building cabinet - Unit 0) and Off Gas Building 247'Particulate, 250'Dilution Iodine, Noble Gas stations - Units 1-3).

'In the 'Dilution cabinet'of the RAGEHS, 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 8-9).

From Unit 0, the sample gas enters Unit 1-3 of RAGEHS 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 flows back thru Unit 0 and the off gas tunnel; and back into the stack.

I 1 + 4g VL 1 w p fT J' 1 4

k S

t I'

3.1.5.3 Stack Sample Flow Path OGESHS The OGESHS sample is obtained from the same stack sample probe as the RAGEHS. From the exit of the stack at elevation 257', the sample line runs east approximately 20'nd then vertically approximately 8'o the OGESMS skid. In the OGESMS, sample flows thru a particuate/,

iodine cartridge housing and.four noble gas scintillation detectors (i.e.. 07 and 08 low range-beta detectors and RN-03A and RN-038 high range gamma detectors). From OGESHS, the stack sample flows back into the stack at approximately elevation 257'.

All OGESMS detector outputs are monitored and recorded remotely in the Hain Control Room. 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.,

Stack particulate and iodine samples are retrieved manually from the OGESMS and analyzed in the laboratory using gamma spectroscopy at frequencies and LLOs specified in Table 4.6.15-2 of the Technical Specifications.

I't I*

P' t

F

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 three 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

"* "i ,iodine. results. -

Correction factors of 2.0 and 1.5 are used for data obtained from RAGEHS and OGESHS respectively. These correction factors are based on empirical data from sampling conducted at NHP-1 in 1985 (memo from J. Blasiak to RAGEHS File, 1/6/86, "Stack Sample Representativeness Study: RAGEHS vs. In-Stack Auxiliary Probe Samples" ).

~k(

I ~

1

'i

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-131,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.

Additionally, the I-135/I-131 and I-133/I-131 ratios should also be determined after a significant change -in the ratio is suspected (eg, plant status changes from prolonged shutdown to power operation or fuel damage has occurred).

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 3.6.15.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 shall be determined monthly in accordance with section 3.2 of this manual. Initial dose calculations shall incorporate. the following- assumptions with,regard to release rates of non-gamma emitting radionuclides subsequently analyzed off-site:

$l 4

gP ">> "wh'w'N~y'~~ ~

'oi "pt,

3.1.5.6 (Cont'd) a) H-3 release rate 2 4uCi/sec b) Sr-89 release rate Z 4 x Cs-137 release rate c) Sr-90 release rate Z 0.5 x Cs-137 release rate d) Fe-55 release rate 2 1 x Co-60 release rate Assumed release rates represent conservative estimates derived from analysis of historical data from effluent releases and process waste streams (See NAP 34023, C. Hare to J. Blasiak, April 29, 1988, "Dose Estimates for Beta-Emitting Isotopes" ). Following receipt of off-site H-3, Sr-89, Sr-90,,Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations.

3.2 Dose and Dose Rate Determinations In accordance with specifications 4.6.15.b. (1), 4.6.15.b. (2), and 4.6.15.b.(3) dose and dose rate determinations will be made monthly to determine:

(1) Total body dose rates and gamma air doses at the maximum X/Q

'land sector 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..

28

'p Ev

3.2 (Cont'd)

Average meteorological data (ie, 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) 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.

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.

r Emergency condenser vent release contributions to the monthly dose and dose rate determinations will be considered only when the emergency condenser return isolation valves have been opened 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.

I

I

• me' q <a < ~"< ~,q " ".'l F t

gv,

3.2 (Cont'd)

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

Critical organ doses .and dose rates may be conservatively calculated..

by assuming .the existence of a maximum individual. This individual is a composite of the highest dose factor of each age group, for each organ and total body, and each nuclide. It is assumed that all pathways are applicable and the highest X/Q and/or 0/Q value for actual pathways as noted in Table 3-1 are in effect. The maximum individual's dose is equal to the same dose that person would receive if they were simultaneously sub]ected to the highest pathway dose at each critical receptor identified for each pathway. The pathways include grass-(cow and goat)-milk, grass-cow-meat, vegetation, ground plane and inhalation. To comply with Technical Specifications we will calculate the maximum individual dose rate at the site boundary and

" 'eyond at the critical residence.

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.

30

eked AI 6

'lt II I,

3.2.1 Dose Rate

'ose 'rates will be-calculated. monthly, at a minimum, or when the Hi-Hi stack monitor alarm setpoint is reached, to demonstrate that dose rates resulting from the release of noble gases, tritium, iodines, and particultes with half lives greater than 8 days are the limits specified in 10CFR.20. These limits are: 'ithin Noble Gases Hhole Body Dose Rate 500 mrem/yr Skin Dose Rate 3000 mrem/yr Tritium Iodines and Particulates Organ Dose Rate 1500 mrem/yr 3.2.1.1 Noble Gases The following noble gas dose rate equation includes the contribution from the stack (s) elevated release and the emergency condenser vent (v) ground level release when applicable (See .section 3.2).

31

P f~

for total body dose rates (mrem/sec):

OR g

(mrem/sec) - 3.17E-8 ii Zi.[ViQiis',+ Ki (X/Q) v Qiiv ]

For skin dose rates (mrem/sec):

OR~+8(mrem/sec)- 3.17E-8 Zi[(Li(X/Q)s+1.118i)Qis+(Li+1.11Ni)<X/Q)vQiv~

where:

OR~ total body gamma dose rate (mrem/sec).

OR~+6 skin dose rate from gamma and beta radiation (mrem/sec).

=='he .constant, accounting for the gamma whole body dose rate from stack radiation, for an elevated finite plume releases for each identified noble gas nuclide, i.

Listed on Table 3-2 in mrem/yr per uCi/sec..

Ki the constant accounting for the gamma whole body dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table 3-3 in mrem/yr per uCi/m3 (from Reg. Guide 1.109)

Qi the release of isotope i; (uCi; s stack, v vent).

X/Q - the relative plume concentration <in units of sec/m3) at the land sector site boundary or beyond.

'Average meteorological data (Table 3-1) is used.

'"Elevated" X/Q values are used for stack releases (s

",'stack); "Ground" X/Q values are used for Emergency Condenser Vent releases (v vent).

the constant accounting for the beta skin dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table 3-3

in mrem/yr per uCi/m3 (from Reg. Guide 1.109),

.the constant .accounting for, the 'air gamma radiation from the elevated Finite plume resulting from stack releases for each identified noble gas nuclide, i.

Listed in Table 3-2 in mrad/yr per uCi/sec.

Hi the constant accounting for the gamma air dose rate from-immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table 3-3 in mrem/yr per uCi/m3 (from Reg. Guide 1.109)

See Appendix 8 for derivation of Bi,and Vi.

32

sr f

P.

Ag<

3.2.1.2 Tritium, lodines and Particulates To ensure that the'500 'mrem/year site dose rate limit is not exceeded, offsite dose rates for tritium, iodine and particulates with half lives greater than 8 days shall be calculated monthly and when release rates (Q) .exceed 0.34 uCi/sec using the following equation.

Oak (mrem/sec) 3.17E-8$~(~i Rijak [Ws + Wv iv is Where:

oak Total dose to each organ k of an individual in age group a (mrem/sec).

dispersion parameter either X/Q (sec/m3) or 0/Q (1/m2) depending on pathway and receptor location assumed. Average meteorological data is used (Table 3-1). "Elevated" W~ values are used for stack releases (s stack); "Ground" Wg values are used for Emergency Condenser Vent releases (v vent).

Qi the total quantity of isotope i released, (uCi/sec; s stack, v vent)

Ri]ak the dose factor for each isotope i, pathway ],

age group a, and organ k (Table 3-4, through 3-22; m2-mrem/yr per uCi/sec for all pathways except inhalation, mrem/yr per uCl/m3.

3. 17E-.S the inverse of the number of seconds in a year

.,The R. values contained in Tables 3-4 through 3-22 .were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision 1; as presented in Appendix C.

When-the release rate exceeds 0.34 uCi/sec, the dose rate assessment shall also include JAF and NMP-2 contribution.

33

Pp4 S

A

+v, 1<

The use of the 0.34 uCi/sec release rate threshold to perform dose rate calculations is justified as follows:

(a) The 1500 mrem/yr organ dose rate limit corresponds to a minimum release rate limit of 0.34 uCi/sec calculated using the equation:

1500 (Q/sec) x (Ri )N))

where:

1500 site boundary dose rate limit (mrem/year)

(Ri]"])max the maximum curie-to-dose conversion factor equal to 4.45E3 mrem-sec/uCi-yr for Sr-90, child bone at the critical residence receptor location beyond the site boundary.

(b) The use of 0.34 uCi/sec release rate threshold and the 4.45E3 mrem-sec/uCi-yr curie-to-dose conversion factor is conservative since curie-to-dose conversion factors for other isotopes likely to be present are significantly lower.

b f I s

'4

3.2.2 Dose

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

Noble Gases 5 mR gamma/calendar quarter

'0 mrad beta/calendar quarter 10 mR gamma/calendar year

'0 mrad beta/calendar year Tritium Iodines and Particulates 7.5 mrem to any organ/calendar quarter 15 mrem to any organ/calendar year

l+%

i 'I d4 II

'Pt I 1'

3.2.2.1 Noble Gas Air Dose The following Noble Gas air dose equation includes contributions from the stack (s) elevated .release.and the emergency condenser vent (v) ground level release when applicable (see section 3.2):

For gamma radiation. (mrad):

Dg (mr d) 3 17E 8 ~i Hi(X Q)v Qiv + Bi Qis For beta radiation (mrad):

08(mrad) 3.17E-S X)Ni (X Q)v +

iv s is where:

0 y gamma air dose (mrad) 0> beta air dose (mrad) the constant accounting for the air gamma radiation from the elevated finite plume resulting from stack releases for each identified noble gas nuclide, i. Listed in Table 3-2 in mrad/yr, per uCi/sec.

Ni The constant accounting for the air beta dose from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed on Table 3-3 in mrad/yr per uCi/m3 (from Reg. Guide 1.109).

Qi the total quantity of isotope i released, (uCi/sec.)

Note that the units for the gamma air dose are in mrad compared to the units for the limits are in mR. The NRC recognizes that mR 1 1 mrad, for gamma radi'ation.

36

4 q(

gi

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

the constant accounting for the air gamma dose from immersion in the semi-infini te cloud for each identified noble gas nuclide, i. Listed on Table 3-3 in mrad/yr per uCi/m3 <from Reg.

Guide 1.109).

All other parameters are as defined in section 3.2.1.1.

3.2.2.2 Tritium, Iodines and Particulates

'o ensure that the 15 mrem/yr facility dose limit is not exceeded, offsite doses for tritium, iodines, and particulates with half lives greater than 8 days shall be calculated monthly using the following

. << equation:

0ak (mrem) 3.17E-8 Z~( Si Ri]ak Ws is + Wv iv Where:

0ak Total dose to each organ k of an individual in age group a(mrem).

Wg dispersion parameter either X/Q (sec/m3) or 0/Q (1/m2) depending on pathway and receptor location assumed. Average meteorological data is used (Table 3-1). "Elevated" W~ values are used .for stack releases (s stack); "Ground" W~ values are used for Emergency Condenser Vent releases (v vent).

Qi the total quantity of isotope i released,

<uCi/sec; s - stack, v vent)

Ri ~ ak the dose factor for each isotope i, pathway ],

age group a, and organ k (Tables 3-4, through 3-22; m2-mrem/yr per uCi/sec)

3. 17E-8 'the inverse of the number of seconds in a year 37

fI I~

0 h

ly CE'

The R values contained in Tables 3-4 through 3-22 were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision 1; as presented in Appendix C.

3.2.2.3 Accumulating Doses Doses will be calculated monthly, at a minimum, for gamma air, beta air, and the critical organ for each age group. Dose estimates will, also, be calculated monthly prior to receipt of any offsite analysis data i.e., strontium, tritium, and iron-55. Results will be summed for each calendar quarter and year.

The critical doses are based on the following:

noble gas plume air dose direct radiation from ground plane deposition inhalation dose cow milk ingestion dose goat milk ingestion dose

'cow meat ingestion dose vegetation (food crops) ingestion 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.

38

A ~"

I

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 elevated noble gas releases the critical receptor is the site boundary.

Hhen 1985 average annual X/Q values are used for ground level noble gas releases, the critical receptor is the maximum X/Q land sector site boundary interface.

For tritium, iodines, and particulates with half lives greater than eight days, the critical pathways are grass-(cow and goat)-milk, grass-cow meat, vegetation, inhalation and direct radiation (ground plane) as a result of ground deposition.

The grass-(cow and goat)-milk, and grass-cow-meat pathways will be based on the greatest 0/Q location. This location has been determined in con]unction with the land use census (technical specification 3.6.22) and is sub]ect to change. The vegetation (food crop) pathway is based on the greatest 0/Q garden location from which

,samples are taken. This location may also be modified as a result of

- vegetation sampling surveys.

39

P C4 gi

+1

3.3 (Cont'd)

To comply with Technical Specifications, the inhalation and ground

'lane dose pathways will .be .,calculated at the site boundary and beyond at the critical residence.

Because the Technical Specifications state to calculate "at the site boundary and beyond", instead of "at the site boundary or beyond",

such as Unit 2, the doses and/or dose rates must be calculated for a maximum individual who is exposed to all pathways at the site boundary and at the critical residence. The maximum individual is a composite of the highest dose factor of each age group, for each

'rgan and total body, and each nuclide. Since the critical residence location would have the greatest occupancy time, the resultant dose at the residence including all pathways is limiting. However, due to the technical specif1cation wording, the inhalat1on and ground plane dose at the site boundary along with all other pathway's, will be calculated assuming a continuous occupancy time.

t In 11eu of correcting the landsite boundary ground plane and inhalation dose factors for occupancy t1me, a Technical Specif1cation change will be submitted to change the requirement from calculating "at the site boundary and beyond" to "at the site boundary or beyond" . Unit l will then calculate at the critical 'res1dence since this should be the 11mit1ng dose. Until this change is effective, the dose and/or dose rate calculations for trit1um, iodines, and particulates with half lives greater than 8 days will conservatively assume that the ground plane and inhalation pathway cr1tical receptors are at the site boundary, i.e. X/Q and 0/Q, respectively,

~ are calculated at the s1te boundary.

40

V f

I V

IC '*

3,4 Refinement of Offsite Doses Resulting from Emergency Condenser Vent Releases.

The doses resulting from .the operation of the emergency condensers and calculated in accordance with 3.2.2 may be refined using data from actual environmental samples. Ground deposition samples will be obtained from an area or areas of maximum projected deposition.

These areas are anticipated to be at or near the site boundary and .

near projected plume centerline. Using the methodology found in Regulatory Guide 1.109, the dose will be calculated to the maximum exposed individual. This dose will then be compared to the dose calculated in accordance with 3.2.2. The comparison wi 1 1 result in an adjustment factor of less than or greater than one which will be used to adjust the other doses from other pathways. 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 woul'd yield more conservative results.

c ~ 1*

III

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 mining operations, operations at waste P

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 limits 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.

1%

4.0 (Cont'd)

If such is the case, Niagara Mohawk shall submit a Special Report to th'e'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) 'dentification 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.p (Cont'd)

The maximum total body and organ doses resulting from radioactive material in liquid effluents"from Nine Hile Point Unit 1 will be summed with the maximum doses resulting from the releases of noble gases, radioiodines, and particulates for the other calendar quarters (as applicable) and from the calendar quarter in which twice the was exceeded. The direct dose components will be- determined by

'imit either calculation or actual measurement. Actual measurements will utilize environmental TLO dosimetry. Calculated measurements will Utilize engineering calculations to determine a projected direct dose component. In the event calculations are used, the methodology will be detailed as required in Section 6.9.3.e of the Technical Specifications.

The doses from Nine Hile 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 Enviromental Honitoring 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..

44

p ~

if

1 E

)It

\I

,*% l P

Cq

Evaluation of Ooses From Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, the fi'sh 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 ~ Zi [Cif x U x 1000 x Oiwb x fl Nhere:

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

l 8

k. 1 l r "Ui i g -f4" 4%9'

',v v

t f,V S

(Cont'd)

Ci f 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 Diwb - The dose factor for radionuclide i for the whole body of an adult (R.G. 1.109, Table E-11).

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

(2) Rl gi (Cif x U x 1000 x Dil x f]

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

- The fractional portion of the year over which the dose is

.applicable.

The dose from shoreline sediment sample media is calculated as:

I~

Rwb X[iCis x U x 40,000 x 0.3 x Diwb x f]

and Rsk XhiCis x U x 40,000 x 0.3 x Disk x f]

Where:

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

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

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

Ci

'L k

(Cont'd)

The usage factor. This is assumed as 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year by a teenager or adult.

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'ose factor for radionuclide i for the whole body (R.G. 1.109, Table E-6) 0is - The dose'actor 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.

NOTE: Because of the nature of the receptor location and the extensive fishing activity in the area, the critical individual may be a teenager or an adult.

47

Qfl 4'4 vp ~

.l P

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 deposition, inhalation and ingestion 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

'he 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 TLO, 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 pathways contained in OOCM section 3.2.2.3 as .a result of gaseous effluents will be calculated

'sing the dose factors of Regulatory Guide 1.109 or the methodology of the ODCM, as applicable . 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'echnical- Specificationsrequires 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.

Cg I

P I

'1L 4 A

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 utilizing environmental TLDs, the critical receptor in question, such as the critical residence, etc., wi 11 be'ompared to .the control locations. The comparison

-involves the difference'in environmental TLD results between the receptor location and the average control location result.

4,4 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 Semiannual Radioactive Effluent Release Report include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the publi'c due to their activi,ties 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..

49

1'4 g'

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 Oecember 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 wi th the resultant whole body and skin dose and the direct radiation dose

, pathway wi th the associated whole 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.

WS 4

I 1 6 U II I fI p

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, boating and wading which are prohibited at the facility.

-The 1nhalation pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate t1me per1od. The radionuclide concentrations are

~

then multiplied by the appropriate X/Q value, 1nhalatton 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 1s 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 ident1cal to the Regulatory Guide

..equations.

R ~ gi['CiF X/Q DFA 1)

R t]

where:

R 'the maximum dose for the period in question to the lung (])

for all radionuclides (1) for the adult age group (a) in mrem per time period.

l t"

r$

C 1

w w, CA'f

~I Tk P

k

4.4 (Cont'd)

The average concentration in the stack release of radionuclide 1 in pCi/m3 for the period in question.

Unit l average stack flowrate in m3/sec.

X/Q The. plume;dispersion parameter for a location approximately 0.50 miles west of NHP-1 (The plume dispersion parameter is 8.9E-06 and was obtained from the C.T. Hain five year average annual X/Q tables.

The stack (elevated) X/Q is conservat1ve when based on 0.50 miles because of the close proximity of the stack and the receptor location).

OFAiga .the inhalation dose factor for radionuclide 1, the lung ], and adult age group a in mrem per pCi found on 6 Table E-7 of Regulatory Guide 1.109.

Ra annual air intake for individuals in age group a in m3 per year (this value is 8,000 m3 per year and was obtained from Table E-5 of Regulatory Guide 1.109).

fractional portion of the year f'r which radionuclide 1 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 us1ng 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 ad)usted for a background dose by subtracting the

"'applicable off-site control soil or shorel1ne sediment sample rad1onuclide 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 .

(depos1t1on) will not be evaluated.

52

1

<<l l

I

~ '

A

The direct radiation gamma dose pathway includes any gamma doses from an overhead plume, submersion in the plume, possible radiation from the facility and ground plane dose (deposition). This general pathway will be evaluated'y average environmental TLD readings. At least two environmental TLDs will be utilized at one location in the approximate area where fishing occurs. The TLOs 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 ad]usted by the average control TLD readings. This is accomplished by subtracting the average quarterly control TLD value from the average fishing location TLO value. The applicable quarterly control TLD values will be utilized after ad]usting for the appropriate time period (as applicable). In the event of loss or theft of the TLDs, results from a TLD or TLOs in the area may be utilized.

E V 1

P t 4 pl +{I %') ll ~1

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 York 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 histo'rical 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. These dispersion calculations are attached as Appendix E.

" """'->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. 50'4) calculated 0/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/Q may be dropped from the program after October 31 of that year.

g.

.~

't

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,'tc., that are included in the Nine Nile Point Environmental Monitoring-Program and for which crosscheck

"=samples are available. 'An attempt will be made to obtain a QC sample to program sample ratio of 5'L or better. The site identification symbol or the actual guality Control sample results shall be reported

~ in the Annual Radiological Environmental Operating Report so that the

'ommission staff may evaluate the results.

a 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 gamma emitters in milk

, 0 , gamma emitters in water tritium in water I-131 in water l JPP l~ V 'K

~K II 0

5.3 Capabilities for Thermoluninescent Dosimeters Used for Env/ronmental 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. TLOs are defined as phosphors packaged for field use.

In regard to the "detection capabilities for thermoluminescent dosimeters, only, one determination is required to evaluate the 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 TLOs 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. A total of at least 5 TLOs 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 3.0'X. A total of at least 4 TLOs shall be evaluated.

11p,,A l j 1! Cf Wf

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. For 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 HeV.

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

'omparing .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 10K. A total of at least 4 TLDs shall be evaluated.

V~(

I

~lg s

S

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 TLOs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10K. A total of at least 4 TLOs shall be evaluated for each of the four conditions.

5.3.7 Moisture dependence shall be..determined by placing TLDs (that ls, 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 regular plastic bag by more than 10'L. A total of at least 4 TLOs shall be evaluated for each condition.

.,'.3.8 .=,Self irradiation shall-be determined. by placing TLOs 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.

I~ '

+I I I

~ ll ltd ~ ~ l& III&R I fl" l . I+I I ~ l~ P II+5 IIllI I I If I

'rC

TABLE 1-1 Average Energy Per Disintegration ISOTOPE ~Emev/di s (Ref) EGmev/dis<4) (Ref)

Ar-41 1.294 (3) 0.464 (3)

Kr-83m 0.00248 0.0371 Kr-85 0.0022 0.250 Kr-85m 0.159 0.253 Kr-87 0.793 1.32 Kr-88 1.95 0.377 Kr-89 2.22 (2) 1.37 (2)

Kr-90 2.10 (2) 1.01 (2)

Xe-'131M '0.0201 0.143 Xe-133 0.0454 0 135

~

Xe-133m 0.042 0.19 Xe-135 0.247 0. 317 Xe-135m 0.432 0.095 Xe-137 0.194 1.64 Xe-138 1.18 0.611 (1) ORNL-4923, Radioactive Atoms - Su lement I, M.S. Martin, November 1973.

(2) NED0-12037, "Summary of Gamma and Beta Emi tters and Intensity Data"; M.E.

Meek, R.S. Gilbert, January 1970. <The average energy was computed from the maximum energy using the ICRP II equation, not the 1/3 value

.: assumption used, in this reference).

(3) NCRP Report No. 58,-,"A-Handbook of. Radioactivity Measurements Procedures"; 1978 (4) The average energy includes conversion electrons.

59

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ag 2sp I

4

'4 \ A 4 A\

p g yA ~ lb ~la -,I S

TABLE 2-1 VALUES - LIQUID*

Ai t RADHASTE TANK INFANT

, mrem ml hr uCi NUCLIDE BONE LIVER T BODY THYROID KIDNfY LUNG GI- TRACT H3 2. 90E-1 2. 90E-1 2. 90E-1 2. 90E-1 2.90f-l 2.90E-1 Cr 51 1.29E-2 8.39E-3 1.83E-3 1.63E-2 3.75E-1 Cu 64 1.13E-l 5.23E-2 1.91E-l 2.32 Mn 54 1.87E+1 4.23 4.14 6.86 FE 55 1.31E+1 8.44 2.26 4.13 1.07 Fe 59 2.84E+1 4.96E+1 1.96E+1 1.47E+1 2.37E+1 Co 58 3.34 8.34 8.33 Co 60 1.02f+1 2.40E+1 2.42E+1 Zn 65 1.72f+1 5.91E+1 2.73E+1 2.87E+1 5.00E+1 Sr 89 2.32E+3 6.66E+1 4.77E+1 Sr 90 1.74E+4 4.43E+3 ~ 2.17E+2 Zr 95 1.91E-l 4.66E-2 5.02E-2 2.32E+1 3.30E-2'.15E-5 Mn 56 2.40E-4 2.07E-4 2.18E-2 Mo 99 2.34E+1 4.57 3.50E+1 . 7.71 Na 24 '2.37 2.37 2.37 2.37 2.37 2.37 2.37 I 131 3.03E+1 3.54E+1 1.57E+1 1.17E+4 4.17E+1 1.28 I 133 4.22 6.15 1.80 1.12E+3 7.23 1.04 Ni 65 1.33E-3 1.51E-4 6.85E-5 1.15E-2 I 132 1.58E-4 3.21E-4 1.14E-4 1.50E-2 3.58E-4 2.60E-4

's'134

'3. 54E+2 .6.60E+2 6. 67E+1 1.70E+2 6.97E+1 1.79 Cs 136 4.05f+1 1.19f+2 4.45E+1 4.75E+1 9.71E+1 1.81 Cs 137 4. 91E+2 5.75E+2 4.07E+1 1.54E+2 6.24E+1 1.80 Ba 140 1. 50E+2 1. SOE-1 7. 74 3.57E-2 9.23E-2 3.69E+1 Ce 141 7.21E-2'. 4.40E-2 5.17E-3 1.36E-2 2.27E+1 Nb 95 3.85E-2 1.59E-2 9.18E-3 1.14E-2 1.34E+1 La 140 1.18E-2 4.67E-3 1 ~ 20E-3 5.48E+1 Ce 144 2.79 1.14 1.57E-1 4.62E-l 1.60E+2

• Calculated in accordance with NUREG 0133, Section 4.3. 1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

60

~ .

kV t VQ QI

'p 9 g'0%(V>>

sQ/

TABLE 2-2 VALUES LIQUID*

Ai t RADHASTE TANK CHILD mrem - ml hr uCi NUCLIDE BONE LIVER T BODY THYROID . KIDNEY LUNG GI-TRACT H3 4.39E-1 4.39E-l 4.39E-1 4.39E-1 4.39E-1 4.39E-l Cr 51 2.13E-2 2.13E-2 1.40 7.86E-1 2.30E-1 1.42 7 '1E+1 CU 64 2.51E-6 2.70 1.63 2.51E-6 6.52 2.51E-6 1.27E+2 Mn 54 6.92 3.38E+3 9.06E+2 6.92 9.53E+2 6.92 .2.84E+3 Fe 55 9.21E+2 4.88E+2 1.51E+2 2.76E+2 9.05E+1 Fe 59 1.30E+3 2.11E+3 1.05E+3 1.34 1.34 6.12E+2 2.19E+3 Co 58 1.89 7.46E+1 2.24E+2 1.89 1.89 1.&9 4.26E+2 Co 60 1.12E+2 3.28E+2 7.4&E+2 1.12E+2 1.12E+2 1.,12E+2 1.31E+3

'r Zn 65 89 2.15E+4

'" 3.'26E+4 5.73E+4

'1.10E-4 3.56E+4 9.32E+2 3.85 1.10E-4 3.61E+4 1;10E-4 3.85 1.10E-4 1.01E+4 1.26E+3 Sr 90 4.26f+5 1.0&f+5 5.74E+3 Zr 95 1.70 1.33 1.32 1.23 1.38 1.23 1.08E+2 Mn 56 1.65E-l 3.73E-2 2.00E-1 2.39E+1 Mo 99 5.35E-3 9.57E+1 2.37E+1 5.35E-3 2.04E+2 5.35E-3 7.91E+1 Na 24 1.52E+2 '1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 I 131 2.09E+2 2.10E+2 1.19E+2 6.94E+4 3.45E+2 5.60E-2 1.87E+1 I 133 3.39E+1 4.19E+1 1.59E+1 7.7&E+3 6. 98E+1 1. 38f-4 1. 69E+1 Ni 65 2.67E-l 2.51E-2 1.47E-2 3.08 I 132 6.13E-3 1.13E-2 5.18E-3 5.22E-1 1.72E-2 1.32E-2

='Cs 134 ~ ;3.68E+5  ;,6.04E+5 1..27E+5 3.54E+1 1.87E+5 6.72E+4 3.29E+3 Cs 136 3.52E+4 9. 67E+4 6. 26E+4 6. 21E-1 5.15E+4 7.68E+3 3.40f+3 Cs 137 5.15E+5 4. 93E+5 7. 28E+4 5. 37E+1 1.61E+5 5.78E+4 3.14E+3 Ba 140 3.61E+2 3.96E-1 2.11E+1 7 '6E-2 1. 82E-1 2.68E-l 1.83E+2 Ce .141 1.50f-l  : 1.07E-1 6.99E-Z 6.34E-Z 8.24E-2 6.34E-2 . 5.40E+1 Nb 95 5.21E+2 2.03E+2 1.45f+2 6.39E-l 1.91E+2 6.39E-1 3.75E+5 La 140 1.50E-l 5.93E-2 2.6&E-2 1.03E-2 1.03E-2 1.03E-2 1.36E+3 Ce 144 5.00 1.81 6.06f-l 3.58E-1 1.16 3.58E-l 3.80E+2 Calculated in accordance with NUREG 0133, S ection 4.3. 1; and Regulatory Guide 1.109, Regu latory posi'tion C, Section l.

61

b ~ 4 TABLE 2-3 VALUES LIQUID*

Ai t RADHASTE TANK TEEN mrem ml hr uCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 3.28E-1 3.28E-1 3.28E-1 3.28E-1 3.28E-1 3.28E-1 Cr 51 1.02E-l 1.02E-l 1.39 . 8.16E-l 3.84E-l 1:94 2.1'6E+2 Cu 64 1.20E-S 2.89 1.36 1.20E-5 7.32 1.20E-S 2.24E+2 Hn 54- 3.3lf+1 4.34E+3 8.87E+2 3.31E+1 1.32E+3 3.'31E+1 8.86E+3 Fe,55 -

6.94E+2 4.92E+2 1.15E+2 3.12E+2 2.13E+2 fe 59 1.07E+3 2.49E+3 9.64E+2 6.41 6.41 7.89E+2 5.87E+3 Co 58 9.03 9.82E+1 2.15E+2 9.03 9.03 9.03 1.24E+3 Co 60 5.36E+2 7.96E+2 1.12E+3 5.36E+2 5.36E+2 5.36E+2 3.93E+3

'rZn 65 89 2.10E+4 2.44E+4 7.28E+4

'.24E-4

, 3.40E+4 6.98E+2 1.84E+1 4.66E+4 5.24E-4, 5.24E-4 1.84E+1 5.24E-4 3.08E+4 2.90E+3 Sr 90 4.66E+5 1. 15E+5 1.31E+4 Zr 95 6.20 6.00 5.97 5.90 6.04 5.90 2.28E+2 Hn 56 1.81E-1 3.22E-2 2.29E-l 1.19E+1 Ho 99 2.56E-2 9.22E+1 1.76E+1 2.56E-2 2.11E+2 2.56E-2 1.65E+2

'Na 24 1.39E+2 '1':39E+2 1.39E+2 1.39E+2 1.39E+2 1.39E+2 1.39E+2 I 131 1.55E+2 2.17E+2 1.16E+2 6.31E+4 3.73E+2 2.68E-l 4.30E+1 I 133 2.53E+1 4.29E+1 1.31E+1 5.99E+3 7.52E+1 6.60E-4 3.25E+1 Ni 65 2.08E-l 2.66E-2 1.21E-2 1.44 I 132 4.90E-2 1.28E-2 4.60E-3 4.32E-1 2.02E-2 5.59E-3

' Cs'34 '3.05f+5 '7. 18E+5 "3.33E+5 1.69E+2 2 .28E+5 8. 73E+4 9. 10E+3 Cs 136 2.98E+4 1.17E+5 7.88E+4 2.97 6.38E+4 1.01E+4 9.44E+3 Cs 137 4.09E+5 5.44E+5 1.90E+5 2.57E+2 1.85E+5 7.21E+4 7.99E+3 Ba 140 2.35E+2 4.10E-l 1.55E+1 3.81E-l 4.79E-1 5.75E-l 3.63E+2 3.46E-1 '- 3.32E-l 3.07E-1, 3.17E-l 3.04E-1 Ce. 141 3.04E-1 . 8.16E+1 Nb 95 4.44E+2 . 2.48E+2 .1..18E+2 3.06 2.40E+2 3.06 1.05E+6 La 140 1.57f-l 1.02E-l 6.35E-2 '.94E-2 '.94E-2 4.94E-2 3.05E+3 Ce 144 3.99 2.65 1.83 1.71 2.27 1.71 5.74E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1 and Regulatory Guide 1.109, Regulatory posi tion C, Section 1.

62

~ 4 V

f,)

n E J sl $ k

-Pi'w

TABLE 2-4 Ai t VALUES - LIQUID*

RADWASTE TANK ADULT mrem ml hr - uCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 4.45E-1 4.45E-1 4.45E-1 4.45E-l 4.45E-l 4.45E-1 Cr 51 1.82E-2 1-82E-2 1.27 7.64E-1 2.93E-1 1. 67 3.14E+2 CU 64 2.75 1.29 6.94 2.35E+2 Mn 54 5.94 4.38E+3 8. 41E+2 5.94 1.31E+3 5.94 1.34E+4 Fe 55 6.64E+2 4.58E+2 1.07E+2 2.56E+2 2.63E+2 Fe 59 1.03E+3 2.43E+3 9.31E+2 1.15 1 ~ 15 6.79E+2 8.09E+3 Co 58 1.62 9.15E+1 2.03E+2 1.62 1.62 1.62 1.82E+3 Co 60 9.60E+1 2.57E+2 6.71E+2 9.60E+1 9.60E+1 9.60E+1 4.99E+3 Zn 65 2.31E4 7.36E+4 3.32E+4 3.30 4.92E+4 3.30 4.63E+4 Sr 89 2.25E+4 9.39E-5 6.45E+2 9.39E-5 9.39E-S 9.39E-5 3.60E+3 SI 90 5.60E+5 1.37E+5 1.62E+4 Zr 95 1.36 1.15E 1.12 1.06 1.21 1.06 3.06E+2 Mn 56 1. 73E-1 3.07E-2 2.20E-1 5.52 Mo 99 4.58E-3 8. 70E+1 1.66E+1 4.58E-3 1.97E+2 4-58E-3 2.02E+2 Na 24 '.35E+2 1.35E+'2 1.35E+2 1.35f+2 1.35E+2 1.35E+2 1.35E+2 I 131 1.45E+2 2.07E+2 1.19E+2 6. 79E+4 3. 55E+2 4. 80E-2 5. 47E+1 I 133 2.35E+1 4.09E+1 1.25E+1 6.02E+3 7.14E+1 1.18E-4 3. 68E+1 Ni 65 1.93E-l 2.51E-2 1.14E-2 6. 36E-1 I 132 4.68E-3 1.25E-2 4.38E-3 4.38E-l 2.00E-2 2.35E-3 Cs"134 -2:98E+5 '7".OBE+5 . 5.79f+5 3.03E+1 2.29E+5 7.61E+4 1.24E+4 Cs 136 2.96E+4 1.17E+5 8.42E+4 5.32E-1 6.51E+4 8.93E+3 1.33E+4 Cs 137 3.82E+5 5.22E+5 3.42E+5 4.60E+1 1.77f+5 5.90E+4 1.02E+4 Ba 140 2.24E+2 3.49E-l 1.47E+1 6.83E-2 1.64E-1 2.29E-1 4.61E+2 Ce..141 9.53E-2 8.20E-2 5.75E-2 5.44E-2 6.72E-2 5.44E-2 1. 06E+2 Nb 95 4.39E+2 2.44f+2 1.32E+2 5.47E-1, 2.41E+2 5 '7E-1 1.48E+6 La 140 l.llf-l 6.03E-2 2.24E-2 8.84E-3 8.84E-3 8.84E-3 3..78E+3 Ce 144 2.48 1.22 4.24E-1 3.07E-1 8.47E-l 3.07E-l 7.37E+2 Calculated in accordance with NUREG 0133, S ection 4.3.1; and Regulatory Guide 1.109, Regu latory position C, Section 1.

63

~a 0 TABLE 2-5 VALUES - LIQUID*

Ai t EHERGENCY CONDENSER VENT INFANT mrem - ml hr - uCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 7.43E-4 7.43E-4 7.43E-4 7.43E-4 7.43E-4 7.43E-4 Cr 51 3.30E-5 2.15E-5 4.70E-6 4.18E-5 9.61E-4, Cu 64 2.89E-4 1.34E-4 4. 89E-4 5.94E-3 Hn 54 4.79E-2 1.'08E-2 1.06E-2 1.76E-2 Fe 55 , 3.35E-2 2.16E-2 5.78E-3 1.06E-2 2.75E-3 Fe 59 7.29E-2 1.27E-1 5.02E-2 3.76E-2 6.08E-2 Co 58 8.58E-3 2.14E-2 2.14E-2 Co 60 2.60E-2 6.15E-2 6.19E-2 Zn 65 4.42E-2 1.52E-1 6.99E-2 7.35E-2 1.28E-l Sr 89 5.95 1.71E-l 1.22E-1 Sr 90 4.46E+1 1.14E+1 5.57E-l Zr 95 4.90E-4 1.19E-4 8. 47E-5 1.29E-4 5.95E-2 Hn 56 6.17E-7 1.06E-7 5.30E-7 5.60E-5 Ho 99 6.00E-2 1.17E-2 8.97E-2 1.98E-2 Na 24 . 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 I 131 7.77E-Z 9.16E-2 4.03E-2 3.01E+1 1.07E-1 3.27E-3 I 133 1.08E-2 1.58E-2 4.62E-3 2.87 1.85E-2 2.67E-3 Ni 65 3.41E-6 3.86E-7 1.76E-7 2.94E-5 I 132 4.05E-7 8.22E-7 2.93E-7 3.85E-5 9.17E-7 6.66E-7

'Cs '134 '.'OBE-1 '.1.69 "'.71E-l ' 4.36E-1 1.79E-1 4.60E-3 Cs 136 1.04E-1 3.06E-1 1.14E-l 1.22E-1 2.49E-2 4.64E-3 Cs 137 1.26 1.47 1.04E-1 3.95E-I 1.60E-1 4.61E-3 Ba 140 3.85E-l 3. 85E-4 1.99E-2 9.15E-5 2.37E-4 9.47E-2 Ce 141 1.85E-4 1.13E-4 1.33E-5 3.48E-5 5.82E-2 Nb 95 9.88E-5 4.07E-5 2.35E-5 2.92E-5 -- 3.43E-2 La 140 3.03E-5 1.20E-5 3.08E-6 1.41E-l Ce 144 7.16E-3 2.93E-3 4.02E-4 1.19E-3 4.11E-l

• Calculated in accordance with NUREG 0133,= Section 4.3.1; and Regulatory A

Guide 1.109, Regu latory position C, Section l.

64

lp'l

~ 'U

>>'t I Ig Q","

ht

TABLE 2-6 VALUES LIQUID*

Ai t EMERGENCY CONDENSER VENT CHILD

,mrem - ml hr uCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 1.44E-1 1.44E-l 1.44E-l 1.44E-l 1.44E-1 1.44E-l Cr 51 3.78E-5 3.78E-5 1.37 7.58E-1 2.07f-l 1.38 7.24E+1 Cu 64 2.63 1.59 6.35 1.23E+2 Mn 54 1.23E-2 3.36E+3 8.95f+2 1.23E-2 9.42E+2 1.23E-2 2.82E+3 fe 55 9.04E+2 4.79E+2 1.49E+2 2.71E+2 8.88E+1 Fe 59 1.28E+3 2.07E+3 1. 03E+3 2.38E-3 2.38E-3 6.00E+2 2.15E+3 Co 58 3.36E-3 7.01E+1 2. 15E+2 3.36E-3 3.36E-3 3.36E-3 4.09E+2 Co 60 1.99E-l 2.08E+2 6.14E+2 1.99E-1 1.99E-1 1.99E-1 1.15E+3 Zn 65 2.15E+4 5.73E+4 3.56E+4 6.84E-3 3.61E+4 6.84E-3 1.01E+4 Sr 89 3.07E+4 8.78E+2 1.19E+3 Sr 90 4.01E+5 1.02E+5 5.40E+3 Zr 95 3.01E-1 6.78E-2 6.06E-2 2.19E-3 9. 61E-2 2.19f-3 6.84E+1 Mn 56 1.65f-l 3.73E-2 2.00E-1 2.39E+1 Mo 99 8.16f+1 2.02E+1 1.74E+2 6.75E+1 Na 24 1.50E+2 l.'50E+2 1.50E+2 1. 50E+2 1.50f+2 1. 50E+2 1.50E+2 I 131 1.86E+2 1.87E+2 1.06E+2 6.19E+4 3.08E+2 1.67E+1 I 133 3.08E+1 3.81E+1 1.44E+1 7.07E+3 6.35E+1 1.53E+1 Ni 65 2.66E-1 2.50E-2 1.46E-2 3.07 I 132 6.01E-3 1.10E-2 5.08E-3 5.12E-1 1.69E-2 1.30E-2 Cs 134 "3 "68E+5 6:04E+5 1.27E+5 6.29E-2 . 1.87E+5 6.71E+4 3.25E+3 Cs 136 3.51E+4 9.66E+4 6.25E+4 1.10E-3 5.14E+4 7.67E+3 3.40E+3 Cs 137 5.14E+5 4.92E+5 7.27E+4 9.55E-2 1.60E+5 5.77E+4 3.08E+3 Ba 140 2.48E+2 2.17E-1 1.45E+1 1.42E-4 7.09E-2 1.30E-1 1.26E+2 Ce '141 3. OBE-2 '1.54E-2 2.39E-3 1.13E-4 6.83E-3 1.13E-4 1.91E+1 Nb 95 5.21E+2 2.03E+2 1.45E+2 1.14E-3 1.90E+2 1.14E-3 3.75E+5 La 140 1.31f-l 4.59E-2 1.55E-2 1.83E-S 1.83E-5 1.83E-5 1.28E+3 Ce 144 1.64 5.15E-1 8.81E-2 6.36E-4 2.85E-1 6.36E-4 1.34E+2 Calculated in accordance with NUREG 0133, Section 4. 3.1; and Regulatory Guide 1.109, Regu latory position C, Section l.

65

I R'

+v t > 5 >of~

TABLE 2-7 Ai t VALUES - LIQUID*

EMERGENCY CONDENSER VENT TEEN

,... mrem - ml hr - uCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 1. 74E-1 1. 74E-1 1. 74E-1 1.74E-l 1. 74E-1 1. 74E-1 Cr 51 1.81E-4 1.81E-4 1.28 7.12E-l 2.81E-l 1.83 2.15E+2 Cu 64 2.86 1.35 7.24 2.22E+2 Mn 54 5.89E-2 4.29E+3 8.52E+2 5.89E-2 1.28E+3 -5.89E-2=- -8.81E+3 Fe .55 6.89E+2 4.88E+2 1.14f+2 3.10f+2 2.11E+2 Fe 59 1.05E+3 2.46E+3 9.50E+2 1.14E-2 1 . 14E-2 7. 76E2 5.82E+3 Co 58 1.61E-2 8.78E+1 2.02E+2 1.61E-2 1. 61E-2 1. 61E-2 1.21f+3 Co 60 9.53E-l 2.57E+2 5.78E+2 9.53E-1 9.53E-1 9.53E-1 3.34E+3 Zn 65 2.10E+4 7.28E+4 3.39E+4 3.28E-2 4.66E+4 3.28E-2 3.08E+4 Sr 89 '.'38E+4 6.81E+2 2.83E+3 Sr 90 4.54E+5 1.12E+5 1.27E+4

'I Zr 95 2.56E-l 8.80E-2 6 '8E-2 1.05E-2 1.24E-l 1.05E-2 1.79E+2 Mn 56 1.81E-1 3.22E-2 2.29E-1 1.19E+1 Mo 99 8.57E+1 1.63E+1 1.96E+2 1.54E+2 Na'24 1.38E+2 1. 38E+2 '.38E+2 1.38E+2 1. 38E+2 1.38E+2 1.38E+2 I 131 1.47E+2 2.0642 1.10E+2 6.00E+4 3.54E+2 4.77E-4 4.07E+1 I 133 2.42E+1 4.11E+1 1.25E+1 5.74E+3 .7.21E+1 3.11E+1 Ni 65 2.08E-1 2.66E-2 1.21E-2 1.44 I 132 4.86E-3 1.27E-2 4.56E-3 4.29E-1 .2.00E-2 5.54E-3

's:134 '" 3!05E+5 i '"7:1 8E+5 3. 33E+5, 3. 01E-1 2.28E+5 8.71E+4 8.93E+3 Cs 136 2.98E+4 1. 17E+5 7.87E+4 5.28E-3 6.38E+4 1.01f+4 9.43E+3 Cs 137 4.09E+5 5.44E+5 1.89E+5 4.57E-l 1.85E+5 7.19E+4 7.73E+3 Ba 140 1.96E+2 2.47E-2 1.27E+1 6.77E-4 8.23E-2 1.62E-l 3.03E+2 Ce-141 2.43E-2 1.64E-2. 2.36E-3 5.40E-4 8.02E-3 5.40E-4 4.54E+1 Nb 95 4.41E+2 2.45E+2

1.15E+2 5.43E-3 2.37E+2 5.43E-3 1.05E+6 La 140 1.05E-1 5.17E-2 1'.38E-2 '.78E-5 8.78E-5 8.78E-5 2.96E+3-Ce 144 1.27 5.28E-1 7.12E-2 3.04E-3 '.17E-l 3.04E-3 3.19E+2

• Calculated in accordance with NUREG 0133, Section '4.3.1; and Regulatory Guide 1.109, Regu latory position C, Section l.

66

AS

~l

~ I Q'ki tS S

tS c,

TABLE 3-1 Critical Receptor Dispersion Parameters>

For Ground Level and Elevated Releases ELEVATED ELEVATED GROUNDe GROUNDe LOCATION . DIR MILES (sec/m3) (m-X)

~XI ~0/ XA/(sec/m~) D/(/ (m X)

Residences E (98') 1.4 1.8 E-07b 5.2 E-09b 4.02 E-07 8.58 E-09 Dairy Cowsf SE (130') 2.6 2.2 E-08c 7.0 E-10c 6.00 E-08 1.64 E-09 Milk Goatsf SE (130') 2.6 2.2 E-08c 7.0 E-10c 6.00 E-08 1.64 E-09 8 Heat Animals ESE (115') 1.8 5.1 E-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 E-07 5.55 E-09 Site Boundary ENE (67') 0.4 ~

2 4 E-06b,d 4 4 E 08c,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)

I

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

d. Value are based on most restrictive X/9 land-based sector (ENE). (C.T. Hain, Rev. 2)

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

f. Conservative location based on past dairy cow and goat milk history.

68

'Cl II

'lÃgL f t

1

TABLE 3-2 Gamma Air and Whole Body Plume Shine Dose Factors'or Noble Gases Gamma Whole Gambia Air Bi Body Vi

~mrad/ r m~rem/ r Nuclide uCi/sec uCi/sec Kr-85 2.23E-6 Kr-85m 1.75E-3 1.68E-3 Kr-87 1.02E-2 9.65E-3 Kr-88 2.23E-2 2.17E-2 Kr-89 2.50E-2 Kr-83m 2.26E-6 Xe-133 2.80E-4 2 '1E-4 Xe-133m 2.27E-4 1.87E-4 Xe-135 2.62E-3 2.50E-3 Xe-135m 5.20E-3 4.89E-3 Xe-137 2.30E-3 2.20E-3 Xe-138 1.32E-2 1.26E-2 Xe-131m 1.74E-S 1.47E-6 Ar-41 1.64E-2 1.57E-2

• Calculated in accordance with Regulatory Guide 1.109. (See Appendix B) k f-4g f

TABLE 3-3 IMMERSION DOSE FACTORS*

Nuclide K>~( l-Bad >'" Li(6-Skin)** H>~( -Alr>*** N> 0>-A>r>*'*

Kr 83m 7.56E-02 1 ~ 93E1 2.88E2 Kr 85m 1.17E3 1.46E3 1.23E3 1.97E3 Kr 85 1.61El 1.34E3 1.72E1 1.95E3 Kr 87 5.92E3 '9.'73E3 6.17E3 1.03E4 Kr 88 1.47E4 2.37E3 1.52E4 2.93E3 Kr 89 1.66E4 1.01E4 1.73E4 1.06E4 Kr 90 1.56E4 7.29E3 1.63E4 7.83E3 Xe 131m 9.15El 4.76E2 1.56E2 1.11E3 Xe 133m ':51E2 9.94E2 3.27E2 1.48E3 Xe 133 2.94E2 3.06E2 3.53E2 1.05E3 Xe 135m 3.12E3 7.11EZ 3.36E3 7.39E2 Xe 135 1.81E3 1.86E3 '1.92E3 2.46E3 Xe 137 1.42E3 1.22E4 1.51E3 1.27E4 Xe 138 8.83E3 4.13E3 9.21E3 4.75E3 Ar 41 8.84E3 2.69E3 9.30E3 3.28E3

• from, Table B-l.Regulatory Guide 1.109 Rev. 1

~

• • mrem/yr per uCi/m .

• • • mrad/yr per uCi/m .

70

~ '

5%

.A<~c>lh

~ 1%

I

TABLE 3-4 Ri VALUES INHALATION - INFANT *

~mreml r uCi/m NUCLIDE ..BONE LIVER,T. BODY TNYROID KIDNEY LUNG GI-LLI H 3 6.47E2 6.47E2 6.47E2 6. 47f2 6. 47E2 6. 47E2 C 14 2.65E4 5.31E3 5.31E3 5.31E3 5.31E3 5.31E3 5.31E3 Cr 51 8.95E1. 5.75E1 1.32El 1.28E4 3.57f2 Mn 54 2.53E4 4.98E3 4.98E3 1.00E6 7.06E3 Fe 55 1.97E4 1.17E4 3.33E3 8.69E4 1.09E3 Fe 59 1.36E4 2.35E4 9.48E3 1.01E6 2.48E4 Co 58 1.22E3 1.82E3 7.77E5 1.11E4 Co 60 8.02E3 1.18E4 4.51E6 3.19E4 "Zn "65 '.93E4 - 6.26E4"'3.11E4 3.25E4 6.47E5 5.14E4 Sr 89 3.98ES 1.14E4 2.03E6 6.40E4 Sr 90 4.09f7 2.59E6 1.12E7 1.31E5 Zr 95 1.15E5 2.79E4 2.03E4 3.11E4 1.75E6 2.17E4

• Nb 95 1.57E4 6.43E3 3.78E3 4.72E3 4.79E5 1.27E4 Mo 99 1.65E2 3.23E1 2.65E2 1.35ES 4.87E4 I 131 3.79E4 4.44f4 1.96E4 1.48E7 5.18E4 1.06E3 I 133 1.32E4 1.92E4 5.60E3 3.56E6 2.24E4 2.16E3 Cs 134 3.96ES 7.03f5 '.45E4 1.90ES 7.97E4 1.33E3 Cs 137 5.49E5 6.12E5 4.55E4 1.72E5 7.13E4 1.33E3 Ba 140 5.60E4 5.60E1 2.90E3 1.34El 1.60E6 3.84E4

'La 140 5.05E2 '.00E2 5.15E1 1.68E5 8.48E4 Ce 141 2.77E4 1.67E4 1.99E3 5.25E3 5.17E5 2.16E4 Ce 144 3.19E6 1.21E6 1.76E5 5.38E5 9.84E6 1.48E5 Nd 147 7.94E3 8.13E3 , 5.00E2 3.15E3 3.22E5 3.12f4

• Daughter Decay Product.

• • This and following Ri Tables Calculated in accordance with NUREG 0133, Section 5.3.1, except C 14 values in accordance with Regulatory Guide 1.109 Equation C-8.

71

N" 1

I>>

TABLE 3-5 R) VALUES INHALATION CHILD m~reml r uCf /m NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 1.12E3 1.12E3 1.12E3 1.12E3 1.12E3 1,12E3 C 14 3 '9E4 6.73E3 6.73E3 6.73E3 .6.73E3 6.73E3 .6.73E3 "

Cr 51 '1.54E2 8:55E1 2.43E1 1.70E4 1.08E3 Hn 54 4.29E4 9.51E3 1.00E4 1.58E6 2.29E4 Fe 55 4.74E4 2.52E4 7.77E3 1.11E5 2.87E3 Fe 59 2.07E4 3.34E4 1.67E4 1.27E6 7.07E4 Co'58 1.77E3 3.16E3 1.11E6 3.44E4 Co 60 1.31E4 2.26E4 7.07E6 9.62E4 Zn 65 4.25E4 1.13ES 7.03E4 7.14E4 9.95E5 1.63E4 Sr 89 5.99E5 1.72E4 2.16E6 1.67E5 Sr 90 1.01EB 6.44E6 1.48E7 3.43E5 Zr 95 1.90E5 4.18E4 3.70E4 5.96E4 2.23E6 6.11E4

• Nb 95 2.35E4 9.18E3 6.55E3 8.62E3 6.14E5 3.70E4 Ho 99 1.72E2 4.26El 3.92E2 1.35ES 1.27E5 I 131 4.81E4 4.81E4 2.73E4 1.62E7 7.88E4 2.84E3 I 133 1.66E4 2.03E4 7.70E3 3.85E6 3.38E4 5.48E3 Cs 134 6.51ES 1.01E6 2.25E5 3.30E5 1.21E5 3.85E3 Cs 137 9.07E5 '8.25E5 , 1.28E5 2.82E5 1.04E5 3.62E3 Ba 140 7.40E4 6.48E1 4.33E3 2.11E1 1.74E6 .1.02E5

• La 140 6.44E2 2 '5E2 7 'SEl 1.83ES 2.26E5 Ce 141 3.92E4 1.95E4 - 2.90E3 8.55E3 5.44E5 5.66E4

'Ce 144 6.77E6 . 2.12E6 3.61E5 1.17E6 1.20E7 3.89ES Nd 147 1:OBE4 '8.73E3 6.81E2 4.81E3 3.28E5 8.21E4

• Daughter Decay Product.

72

I IJ

~ a I I

~ I f

If

~II-I-" I

~ 'I I I "I'I I

I*'f rI 4

~ I

TABLE 3-6 Rt VALUES

- INHALATION - TEEN

~mreml r uC)/m NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 1.27E3 1.27E3 l.'27E3 1.27E3 1.27E3 1.27E3 C 14 2.60E4 4.87E3 4.87E3 '4.87E3 4.87E3 4.87E3 '4.87E3 Cr Sl 1.35E2 7.50E1 3.07E1 '.10E4 3.00E3 Mn 54 5.11E4 8.40E3 1.27E4 1.98E6 6.68E4 Fe 55 3.34E4 2.38E4 5.54E3 1.24fS 6.39E3 Fe 59 1.59E4 3.70f4 1.43E4 1.53E6 1.78E5 Co 58 '.07E3 2.78E3 1.34E6 9.52E4'.72E6 Co 60 1.51E4 1.98E4 2.59E5 Zn 65 3.86E4 1.34E5 6.24E4 8.64E4 1.24E6 4.66E4 Sr 89 4.34f5 1.25E4 2.42E6 3.71E5 Sr 90 1.08EB 6.68E6 1.65E7 7.65fS Zr 95 1.46E5 4.58E4 3.15E4 6.74E4 2.69E6 1.49E5

• Nb 95 1.86E4 1.03E4 5.66E3 1.00E4 7.51ES 9.68E4 Mo 99 - 1.69E2 3.22El 4.11E2 1.54E5 2.69E5 I 131 3.54E4 4.91E4 2.64E4 1.46E7 8.40E4 6.49E3 I 133 1.22E4 2.05E4 6.22E3 2.92E6 3.59E4 1.03E4 Cs 134 5.02E5 1.13E6 5.49E5 3.75ES 1.46E5 9.76E3 Cs 137 6.70E5 8.48E5 3.11E5 3.04E5 1.21E5 8.48E3 Ba 140 5.47E4 6.70El 3.52E3 2.28E1 2.03E6 2.29ES

• La 140 4.79E2 2.36E2 6.26El 2.14E5 4.87ES

" 1.26E5 Ce 141 2.84E4 1.90E4 2.17E3 8.88E3 6.14E5 Ce 144 4.89E6 2.02E6 2.62ES 1.21E6 1.34E7 8.64E5 Nd 147 7.86E3 8.56E3 5 13E2 5.02E3 3.72E5 1.82E5

• Daughter Decay Product.

73

~ r'

~

fbi J

TABLE 3-7 R) VALUES

- INHALATION - AOULT

~mreml r uC) /m NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 1.26E3 '.26E3 1.26E3 1.26E3 1.26E3 1.26E3 "C 14 '.82E4 3.41E3 3.41E3 '.41E3 3.'41E3 3.41E3 3.41E3" Cr 51 1.00E2 5.95E1 2.28E1 1.44E4 3.32E3 Mn S4 3.96E4 6.30E3 9.84E3 1.40E6 7.74E4 Fe 55 2.46f4 1.70E4 3.94E3 7.21E4 6.03E3 Fe S9 1.18E4 2.78E4 1.06E4 1.02E6 1.88ES Co 58 1.58E3 '.07E3 9.28E5 1.06E5 Co 60 1.15f4 1.48E4 5.97E6 2.85E5 Zn 65 3.24f4 1.03ES 4.66f4 6.90E4 8.64E5 5.34E4 Sr 89 3.04E5 8.72E3 1.40E6 3.50E5 Sr 90 '.92E7 6.10E6 9.60E6 7.22E5 Zr 95 1.07ES 3.44E4 2.33E4 5.42E4 1.77E6 1.50E5

• Nb 95 1.41E4 7.82E3 4.21E3 7.74E3 5.05E5 1.04E5 Mo 99 1.21E2 2.30E1 2.91E2 9.12E4 2.48ES I 131 2.52E4 3.58E4 2.05E4 1.19E7 6.13E4 6.28E3 I 133 8.64E3 1.48E4 4.52E3 2.15E6 2.58E4 8.88E3 Cs 134 3.73ES 8.48E5 7.28ES 2.87ES 9.76E4 1.04E4 Cs 137 4.78E5 6.21ES 4.28E5 2.22E5 7.52E4 8.40E3 Ba 140 3.90E4 4.90El 2.57E3 1.67E1 1.27E6 2.18E5

'La 140 3.44E2 1 ~ 74E2 4.58E1 1.36ES 4.58ES Ce 141 1.99E4 1.35f4 1.53E3 6.26E3 3.62ES 1.20E5 Ce 144 3.43E6 1.43E6 1.84ES 8.48E5 7.78E6 8.16E5

'Nd'147 '.27E3 6.10E3 '3:65E2 3.56E3 2.21E5 1.73E5

• Daughter Oecay Product.

74

F li C

sQ

~ -'I

TABLE 3-8 R) VALUES

- GROUND PLANE ALL AGE GROUPS 2

m ~mreml r uC)/sec NUCLIDE TOTAL BODY SKIN H 3 C 14 Cr 51 4.68E6 5.53E6 Hn 54 1.39E9 1.63E9 Fe 55 Fe 59 2.75E8 3.23EB Co 58 3.82E8 4.47E8 Co 60 2.15E10 2.53E10 Zn 65 7.49E8 8.62E8 Sr 89 2.26E4 2.62E4 Sr 90 Zr 95 2.50E8 2.90E8

• Nb 95 1.36EB 1.61E8 Ho 99 4.04E6 4.67E6 I 131 1.72E7 2.09E7 I 133 2.39E6 2.91E6 Cs 134 6.81E9 7.94E9 Cs 137 1.03E10 1.20E10 Ba 140 2.06E7 2.35E7

*La 1.40 ,1.92E7 2.18E7 Ce 141 1.37E7 1.54E7 Ce 144 6.95E7 8.03E7 Nd 147 8.46E6 1.01E7

.. *Daughter Decay Product.

75

tr TABLE 3-9 R) VALUES

- CON MILK INFANT m ~mreml r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 3.10E3 3.10E3 3.10E3 3.10E3 3.10E3 3.10E3

• C 14 3.23E6 6.89E5 6.89E5 6.89E5 6.89E5 6,89E5 . '6.89E5 Cr 51 8.37E4 ,5.46E4 . 1.19E4 1.06E5 2.44E6 Mn 54 2.51E7 5.69E6 5.56E6 9.22E6 Fe 55 8.98E7 5.80E7 1.55E7 2.83E7 7.36E6 Fe 59 1.22EB 2.14ES 8.42E7 6.31E7 1.02EB Co 58 1.39E7 3.47E7 3.47E7 Co 60 5.90E7 1.39E8 1.40E8'.02E10 Zn 65 3.53E9 1.21E10 5:58E9 5.87E9 Sr 89 7.04E9 2.02E& 1.45E8 Sr 90 8.19E10 2.09E10 1.02E9 Zr 95 3.88E3 9.45E2 6.70E2 1.02E3 4.71E5

• +Nb 95 3.14E5 1.29E5 7.48E4 9.27E4 1.09E8 Mo 99 1.05E8 2.06E7 1.58E8 3.47E7 I 131 1.36E9 1.60E9 7.06E8 5.27E11 1.87E+9 5.73E7 I 133 1.70E7 2.48E7 7.27E6 4.51E9 2.92E7 4.20E6 Cs 134 2.41E10 4.49E10 4.54E9 1.16E10 4.74E9 1.22EB Cs 137 3.47E10 4.06E10 2.88E9 1.09E10 4.41E9 1.27E8 Ba 140 1;21E8 1.21E5 6.23E6 2.87E4 7.42E4 2.97E7

• • La 140 2;03El 7.99 2.06 9;39E4-Ce 141 2.28E4 1.39E4 1.64E3 4.29E3 7.18E6 Ce 144 1.49E6 6.10E5 8.35E4 2.46E5 8.55E7 Nd 147 4.43E2 . 4.55E2 2.79E1 1.76E2 2.89E5

• mrem/yr per uCI/m3.

• • Daughter Decay Product.

76

TABLE 3-10 Ri VALUES - CON MILK - CHILD 2

m ~mreml r uCi/sec NUCLIOE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 2.05E3 2.05E3 2.05E3 2.05E3 2.05E3 2.05E3

• C 14 1.65E6 3.29E5 3.29E5 3.29f5 3.29E5 3.29E5 3.29E5 Cr 51 5-29E4 2.93E4 8.02E3 5.36E4 2.&OE6 Mn 54 1.35E7 3.59E6 3.78E6 1.13E7 Fe 55 7.43E7 3.94E7 1.22E7 2.23E7 7.30E6 Fe 59 6.55E7 1.06EB 5.28E7 3.07E7 1.10E&

Co 58 6.96E6 2.13E7 4.06E7 Co 60 2.89E7 8.52E7 1.60EB Zn 65 2.63E9 7 'OE9 4.35E9 4.41E9 1.23E9 Sr 89 3.70E9 1.06EB 1.43EB SI 90 7.53E10 1.91E10 1.01E9 Zr 95 2.18E3 4.&OE2 4.27E2 6.87E2 5.01E5

• • Nb 95 1.6&E5 6. 55E4 4.68E4 6.15E4 1.21EB Mo 99 4.13E7 1.02E7 8.81E7 3.41E7 I 131. 6.52EB 6.56EB , 3.73EB 2.17Ell 1.08E9 5.84E7 I 133 8.07E6 9.98E6 3.78E6 1.85E9 1.66E7 4.02E6 Cs 134 1.50f10 2.46E10 5.18E9 7.61E9 2.73E9 1.32E&

Cs 137 2.17E10 2.08E10 3.07E9 6.78E9 2.44E9 1.30EB Ba 140 5.&BE7 5.15E4 3.43f6 1.68E4 3.07E4 2.98E7 .

• • La 140 9.70 3.39 1.14 9.45E4 Ce 141 1.15E4 5.74E3 8.52E2 2.51E3 7.15E6 Ce 144 1.04E6 3.26E5 5.55E4 1.80E5 8.50E7 Nd 147 2.24E2 1.8lf2 1.40EI 9.94E1 2.87E5 e *mrem/yr per uCi/m3.

• • Daughter Oecay Product.

77

0 AT

\>

r 4 4

A 4 4

TABLE 3-11 Ri VALUES - CON MILK TEEN 2

m ~mrem/ r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 1.29E3 1.29E3 1.29E3 1.29E3 1.29E3 1.29E3

'C 14 6.70E5 1.34E5 1.34E5 1.34E5 1.34E5 1.35E5 1.34E5 Cr 51 2.59E4 1.44E4 5.68E3 3.70E4 4.35E6 Mn 54 9.02E6 1.79E6 2.69E6 1.85E7 Fe 55 2.96E7 2.10E7 4.89E6 1.33E7 9.08E6 Fe 59 2.82E7 6.59E7 2.55E7 2.08E7 1.56EB Co 58 4.55E6 1.05E7 6.28E7 Co 60 1.86E7 4.19E7 2.42E8 Zn 65 1.34E9 4.65E9 2.17E9 2.98E9 1.97E9 Sr 89 1.50E9 4.28E7 1.78E8 Sr 90 4.46E10 1.10E10 1.25E9 Zr 95 9.40E2 2.97EZ 2.04E2 4.36E2 6.85E5

• • Nb 95 7.45E4 4.13E4 2.27E4 4.01E4 1.77E8 Mo 99 2.27E7 4.32E6 5.19E7 4.06E7

, I 131 2.69EB

• 3.77EB 2.02E8 1.10E11 6.48EB 7.45E7 I 133 3.32E6 5.64E6 1.72E6 7.87E8 9.88E6 4.26E6 Cs 134 6.49E9 1.53E10 7.08E9 4.85E9 1.85E9 1.90E8 i

Cs 137 9.02E9 , 1.20EIO 4.18E9 4.08E9 1.59E9 1.71EB Ba 140 2.43E7 2.98E4 1.57E6 1.01E4 2.01E4 3.75E7

• • La 140 4.05 1.99 5.30E-1 1.14E5 Ce 141 4.67E3 3.12E3 3.5&E2 1.47E3 8. 92f 6 Ce 144 4.22E5 1.74E5 2.27E4 1.04E5 1.06E8 Nd 147 9.12E1 9.91E1 5.94EO 5.82E1 3.58E5

• mrem/yr per uCi/m3.

• • Daughter Decay Product.

78

I' ~ i Jl~

~'

TABLE 3-12 Ri VALUES

- CON HILK - ADULT 2

m ~mreml r uCi/sec NUCLIDE BONE LIVER T. DODY THYROID KIDNEY LUNG GI-LLI

• H 3 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2

• C 14 3.63E5 7.26E4  :.7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 Cr 51 1.48E4 8 '7E3 3.27E3 1.97E4 3.73E6 Hn 54 5 '1E6 1.03E6 1.61E6 1.66E7 Fe 55 1.67E7 1.15E7 2.69E6 6.43E6 6.6lf6 Fe 59 1.62E7 3.80E7 1.46E7 1.06E7 1.27E8 Co 58 2.70E6 6.06E6 5.48E7 Co 60 1.10E7 '2.42E7 2.06E8 Zn 65 8.72E8 2.78E9 1.25E9 1.86E9 1.75E9 Sr 89 8.11E8 2.33E7 1.30E8 Sr 90 3.15E10 7.74E9 9.11E8 Zr 95 5.38E2 1.72E2 1.17E2 2.71f2 5.47E5

• • Nb 95 4.37E4 2.43E4 1.31E4 2.40E4 1.47E8 Ho 99 1.26E7 2.39E6 2.84E7 2.91E7 I 131 1.48E8  ; 2.12E8 =. 1.22E8 ~ 6.95E10 3.63E8 5.59E7 I 133 1.82E6 3.16E6 9.64E5 4.65E8 5.52E6 2.84E6 Cs 134 3.74E9 8.89E9 7.27E9 2.88E9 9.55E8 1.56E8 Cs 137 4.98E9 6.80E9 4.46E9 2.31E9 7.68E8 1.32E8 Ba 140 1.35E7 1.69E4 8.83E5 5.76E3 9.70E3 2.78E7

• • La 140 2.26 1.14 3.01E-1 8.35E4 Ce 141 2.55E3 1.72E3 1.95E2 8.00E2 6.58E6 Ce 144 2.29fS 9.58E4 '.23E4 5.68E4 7.75E7 Nd 147 4.74E1 5.48E1 3.28EO 3.20E1 2.63f5

• mrem/yr per uCi/m3.

• • Daughter Decay Product.

79

Qlt

~7f~

TABLE 3-13 Ri VALUES GOAT MILK - INFANT m ~mreml r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIONEY LUNG GI-LLI

<<H 3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3

• C 14 3.23E6 6.89E5 .6.89E5 . 6.89E5 6.89E5 6.89E5 6.89E5 Cr 51 1.00E4 6.56E3 1.43E3 1.28E4 2.93E5 Mn 54 3.01E6 6.82f5 6.67E5 1.11E6 Fe 55 1.17E6 7.54E5 2.01E5 3 '9E5 ,

9.57E4 Fe 59 1.59E6 2.78E6 1.09E6 8 '1E5 1.33E6

. Co 58 . 1.67E6 . 4.16E6 4.16E6 Co 60 7.08E6 1.67E7 1.68E7 Zn 65 4.24E8 1.45E9 6.70E8 7.04E8 1.23E9 Sr 89 1.48f10 4.24E8 3.04E8 Sr 90 .1.72E11 4.38E10 2.15E9 Zr 95'.66E2 1.13E2 8.04EI 1.22E2 5.65E4

• • Nb 95 3.77E4 1.55E4 8.97E3 1.11E4 1.31E7 Mo 99 1.27f7 2.47E6 1.89E7 4. 17E6 le "I '131 --1.63E9 -

',1.93E9 '.47EB, 6.33E11 2.25E9 6.87E7 I 133 2.05E7 2.98E7 8.72E6 5.42E9 3.50E7 5.04E6 Cs 134 7.23E10 1.35E11 1.36E10 3.47E10 1.42E10 3.66E8

..Cs 137 1.04E11 " 1.22E11 8.63E9 3.27E10 1.32E10 3.81E8 Ba 140 1.45E7 1.45E4 '7.48E5 3.44E3 8.91E3 3.56E6

• • La 140 2.430 9.59E-l 2.47E-l 1.13E4 Ce 141 2.74E3 1.67E3 1.96E2 5.14f2 8.62E5 Ce 144 1.79E5 7.32E4 1.00E4 2.96E4 1.03E7 Nd 147 5.32E1 5.47E1 3.35EO 2.11El 3.46E4

• mrem/yr per uCi/m3.

'*Daughter Decay Product.

80

4 f

~ W, i

i I

A' i

• i fI

~: f f

k/i ~'f ~'" ~ <LQ'~)

f I fg if fQ,

TABLE 3-14 Ri VALUES GOAT MILK - CHILD m ~mreml r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3

• C 14 1.65E6 3.29E5 3.29E5 3.29ES 3.29E5 3.29E5 3.29E5 Cr 51 6.34E3 3.52E3 9.62E2 6.43E3 3.36E5 Hn 54 1.62E6 4.31E5 4.54E5 1.36E6 Fe 55 9.65E5 5.12E5 1.59E5 2.90E5 9.49E4 Fe 59 8.52E5 1.38E6 6.86E5 3.99E5 1.43E6 Co 58 8.35E5 2.56E6 4.87E6 Co 60 3.47E6 1.02E7 1.92E7 Zn 65 3.15E8 8.40EB 5.23EB 5.29E8 1.48E8 Sr 89 7.77E9 2.22E8 3.01E8 Sr 90 . 1.58E11 4.01E10 2.13E9 Zr 95 2.62E2 5.76E1 5.13El 8.25E1 6.01E4

• • Nb 95 2.02E4 7.86E3 5.62E3 7.38E3 1.45E7 Mo 99 4.95E6 1.22E6 1.06E7, 4.09E6

..I 131 .. 7.83EB .. 7.87EB . 4.47EB 2.60E11 1.29E9 7.01E7 I 133 9.69E6 1.20E7 4.53E6 2.23E9 2.00E7 4.83E6 Cs 134 4.49E10 7.37E10 1.55E10 2.28E10 8.19E9 3.97E8

. Cs 137 6.52E10 .. 6.24E10 9.21E9 2.03E10 7.32E9 3.91E8 Ba 140 7.05E6 6.18E3 4.12E5 2.01E3 3.68E3 3.57E6

• • La 140 1.16 4.07E-1 1.37E-1 1.13E4 Ce 141 1.38E3 - 6.88E2 1.02E2 3.02E2 8.59E5 Ce 144 1 ~ 25E5 3.91E4 6.66E3 2.16E4 1.02E7 Nd 147 2.68E1 2.17E1 1.68EO 1.19E1 3.44E4

• mrem/yr per uCi/m3.

• • Daughter Decay Product.

81

AAI II rp A Vf

TABLE 3-15 Ri VALUES GOAT MILK TE N m ~mreml r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 '.64E3 2.64E3 2.64E3 2.64E3 2.64E3 2.64E3

• C 14 6.70E5 1.34E5 1..34E5 1.34E5 1.34E5 1.35E5 1.34E5

.Cr 51 3.1.1E3 1.73E3 ...6.82E2 4.44E3 .5.23E5 Mn 54 1.08E6 2.15E5 3.23E5 2.22E6 Fe 55 3.85E5 2.73E5 6.36E4 1.73E5 1.18E5 Fe 59 3.67E5 8.57E5 3.31E5 2.70E5 2.03E6 Co 58 5.46E5 1.26E6 7.53E6 Co 60 2.23E6 5.03E6 2.91E7 Zn 65 1.61E8 5.58E8 2.60EB 3.57E8 2.36E8 Sr 89 3.14E9 8.99E7 3.74E8 Sr 90 9.36E10 2.31E10, 2..63E9 Zr 95 1.13E2 3.56El 2.45E1 5.23E'1 8.22E4

• • Nb 95 8.94E3 4.96E3 2.73E3 4.81E3 '2.12E7

~ ~

Mo 99 2.72E6 5.19E5 6.23E6 4.87E6 I I131  :'.3.23E8 R 4.52EB . 2.43E8 1.32E11 7.78EB 8 '4E7 I 133 3.99E6 6.76E6 2.06E6 9.44E8 1.19E7 5.12E6 Cs 134 1.95E10 4.58E10 2.13E10 1.46E10 5.56E9 5.70EB

.Cs 137 2.71E10 .. 3.60E10 1. 25E10 1.23E10 4.76E9 5.12EB Ba 140 2.92E6 3.58E3 1.88E5 1.21E3 2.41E3 4.50E6

• • La 140 4.86E-1 2.39E-l 6.36E-2 1.37E4 Ce 141 5.60E2 3.74EZ 4.30El 1.76E2 1.07E6 Ce 144 5.06E4 2.09E4 2.72E3 1.25E4 1.27E7 Nd 147 1.09El 1.19El 7.13E-1 6.99EO 4.29E4

• mrem/yr per uCi/m3.

• • Daughter Decay Product.

82

~ 4.

k jg \

~A I'l F4

TABLE 3-16 R) VALUES GOAT MILK - ADULT m ~mreml r uCl /sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG i GI-LLI

• H 3 . 2.03E3 2.03E3 2 '3E3 2.03E3 2.03E3 2.03E3

• C 14 3.63E5 7.26E4 7.26E4 7 '6E4 7.26E4 7.26E4 7.26E4 Cr 51 1.78E3 1.06E3 3.92E2 2.36E3 4.48E5 Mn 54 6.50E5 1.24E5 1.93E5 1.99E6 Fe 55 2.17E5 1.50E5 3.49E4 8.36E4 8 60E4 Fe 59 2.10E5 4.95E5 1.90E5 1.38E5 1.65E6 Co 58 .- 3.25E5 , 7.27E5 6.58E6 Co 60 1.32E6 2.91E6 2.48E7 Zn 65 1.05E8 3.33E8 1.51E8 2.23EB 2.10E8 Sr 89 1.70E9 4.89E7 2.73E8 Sr 90 6.62E10 1.63E10 1.91E9 Zr 95 6.45E1 2.07E1 1.40E1 3.25EI 6.56E4

• • Nb 95 5.24E3 2.92E3 1.57E3 2.88E3 1.77E7 Mo 99 1.51E6 2.87E5 3.41E6 3.49E6

~q

I 131 41:78E8 "., 2. 54EB ~1.46E8 . 8.34E10 4.36EB 6.71E7 I 133 2.18E6 3.80E6 1.16E6 5.58EB 6.62E6 3.41E6 Cs 134 1.12E10 2.67E10 2.18E10 8.63E9 2.86E9 4.67E8

.Cs 137 1.49E10 " 2.04E10 1.34E10 6.93E9 2.30E9 3.95E8 Ba 140 1.62E6 2.03E3 1.06E5 6.91EZ 1.16E3 3.33E6

• • La 140 2.71E-l 1.36E-1 3.61E-2 1.00E4 Ce 141 3.06E2 2.07E2 2.34E1 9.60E1 7.90E5 Ce 144 2.75E4 1.15E4 1.48E3 6.82E3 9.30E6 Nd 147 5.69EO 6.57EO 3.93E-1 3.84EO 3.15E4

• mrem/yr per uCf/m3.

• • Daughter Decay Product.

83

I q p

)

'I 1

~ ~

C'I

~

4 4

TABLE 3-17 Ri VALUES COW MEAT CHILD 2

m ~mreml r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 3.04EZ 3.04E2 3.04E2 3.04E2 3.04E2 3 '4E2

• C 14 5.29ES 1.06E5 1.06E5 . 1.06E5 .1.06E5 1.06E5 1.06E5 Cr 51 4'.57E3 2.54E3 6.93E2 4.63E3 2.42E5 Mn 54 5.36E6 1.43E6 1.50E6 4.50E6 Fe 55 3.04ES 1.61EB 4.99E7 9.11E7 2.98E7 Fe 59 2.06E8 3.33E8 1.66ES 9.64E7 3.46ES Co 58 9.43E6 2.89E7 5.50E7 Co 60 4.67E7 1.38ES 2.59E8 Zn 65 2.39ES 6.36E8 3.96E8 4.01E8 1.12E8 Sr 89 2.72ES 7.77E6 1.05E7 Sr 90 7.01E9 1.78E9 9.44E7 Zr 95 1.53E6 3.35E5 2.98E5 4.80ES 3.50E8

• • Nb 95 1.64E6 6.38E5 4.56E5 5.99E5 1.18E9 Mo 99 6.11E4 1.51E4 1.31E5 5.06E4 I,131, 8.30E6 << 8.35E6 -- 4.75E6 2.76E9 1.37E7 7.43E5 I 133 1.88E-1 2.32E-1 8.78E-2 4.31E1 3.87E-1 9.35E-2 Cs 134 6.09E8 1.00E9 2.11ES 3.10ES 1.11ES 5.39E6 Cs 137 8.99E8 8.60E8 1.27ES 2.80ES 1.01ES 5.39E6 Ba 140 2.20E7 1.93E4 1.28E6 6.28E3 1.15E4 1.12E7

• • La 140 2.80E-2 '.78E-3 3.30E-3 2.73E2 Ce 141 1.17E4 5.82E3 8.65E2 2.55E3 7.26E6 Ce 144 1.61E6 "

5.04E5 8.57E4 2.79E5 1.31E8 Nd 147 5.93E3 4.80E3 3.72E2 2.64E3 7.61E6

• mrem/yr per uCi/m3.

• • Daughter Decay Product.

84

~C CL .

I ~

C IC

TABLE 3-18 Rt VALUES CON HEAT - TEEN 2

m ~mreml r uCi/sec NUCLIDE BONE LIVER T. BODY TNYROIO KIDNEY LUNG GI-LLI

'H 3 2.52E2 2.52E2 2.52E2 2.52E2 2.52E2 2.52E2

• C 14 '2E4 2.81E5 5 5.62E4 . 5.62E4 5 '2E4 , 5.62E4 ,.5..62E4 Cr 51 2.93E3 1.63E3 6.42E2 4.19E3 4.93E5 Hn 54 4.69E6 9.30E5 1.40E6 9.62E6 Fe 55 1.58ES 1.12ES 2.62E7 7.12E7 4.86E7 Fe 59 1.16ES 2.71ES 1.04ES 8.53E7 6.40E8 Co 58 8.07E6 1.86E7 1.11ES

. Co 60 3.93E7 8.86E7 5.12E8 Zn 65 1.59E8 5.52ES 2.58ES 3.54E8 2.34E8 Sr 89 1.44E8 4.12E6 1.71E7 Sr 90 5.42E9 1.34E9 1.52E8 Zr 95 8.59E5 2:71E5 1.86E5 3.98E5 6.25E8

• • Nb 95 9.49E5 5.26E5 2.90E5 5.10ES 2.25E9 Ho 99 4.39E4 8.38E3 1.01E5 7.87E4 I. 131 m 0 4.48E6 6.27E6 3.37E6 -

1.83E9 1.08E7 1.24E6 I 133 1.01E-1 1.71E-1 5.23E-2 2.39E1 3.00E-1 1.30E-1 Cs 134 3.46ES 8.13ES 3.77ES 2.58E8 9.87E7 '1.01E7 Cs 137 4.88E8 6.49E8 2.26E8 2.21E8 8.59E7 9.24E6 Ba 140 1.19E7 1.46E4 7.69E5 4.96E3 9.83E3 1.84E7

• • La 140 1.53E-2 7.51E-3 2.00E-3 4.31E2 Ce 141 6.20E3 4.14E3 4.76E2 .1 .95E3 1.18E7 Ce 144 8.52E5 3.53E5 "

4.58E4 2.11E5 2.14ES Nd 147 3.16E3 3.44E3 2.06E2 2.02E3 1.24E7

• mrem/yr per uC)/m3.

• • Oaughter Oecay Product.

85

C, TABLE 3-19 Ri VALUES CON HEAT ADULT m ~mreml r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

'H 3 4.22f2 4.22E2 4.22E2 4.22E2 4.22E2 4.22E2

• C 14 3.33E5 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 Cr 51 3.67E3 2.19E3 .8.08E2 4.86E3 ..9.22E5 Mn 54 6.15E6 1'.17E6 1.83E6 1.88E7 Fe 55 1.95ES 1.36ES 3.14E7 7.51E7 7.72E7 Fe 59 1.45ES 3.4lfS 1.31ES 9.53E7 1.14E9 Co 58 1.05E7 2.35E7 2.12E8 Co 60 5.07E7 1.12fS 9.52E8 Zn 65 2.26ES 7.20ES 3.25ES 4.81ES 4.53E8 Sr 89 1.70E8 4.89E6 2.73E7

.Sr 90 8.38E9 2.06E9 2.42E8 2r 95 1.07E6 3.44E5 2.33E5 5.40E5 1.09E9

• • Nb 95 1.22E6 6.76E5 3.63ES 6.68ES 4.10E9 Ho 99 5.31E4 1.01E4 1.20E5 1.23E5

• I 131 '.39E6 , 7.71E6 ,: 4.42E6 . 2 '3E9 1.32E7 2.03E6 I 133 1.21E-1 2.10E-1 6.40E-Z 3.09E1 3.66E-1 1.89E-1 Cs 134 4.35ES 1.03E9 8.45E8 3.35E8 1.11ES 1.81E7

,Cs 137 5.88E8 .. 8.04E8 5.27ES 2.73E8 9.07E7 1.56E7 Ba 140 1.44E7 1.81E4 9.45E5 6.16E3 1.04E4 . 2.97E7

• • La 140 1.86E-2 9.37E-3 2.48E-3 6.88EZ Ce 141 7.38E3 4.99E3 5.66EZ 2.32E3 1.91E7 Ce 144 1.01E6 4.23E5 5.43E4 2.51E5 3.42ES Nd 147 3.59E3 4.15E3 2.48f2 2.42E3 1.99E7

• mrem/yr per uCi/m3.

'*Daughter Decay Product.

86

l~

~ ~

Ai~

TABLE 3-20 Ri VALUES - VEGETATION - CHILD m ~Nrem/ r uC1/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 5.22E3 5.22E3 5.22E3 5.22E3 5.22E3 5.22E3

• C 14 3.50E6 7.01E5 '.01E5 7;01ES '.01ES 7.01E5 7.01E5 Cr 51 1.18f5

'* 6;54E4.79E4 1.19E5 6.25E6 Mn 54 6.65E8 1.77E8 1.86E8 5.58E8 Fe 55 8.01E8 4.25E8 1.32E8 2.40E8 7.87E7 Fe 59 4.01f8 6.49E8 3.23E8 1.88E8 6.76E8 Co 58 6.47E7 1.98E8 3.77E8 Co 60 '.78E8 1.12E9 2.10E9 ZA 65 8.13E8 2.17E9 1.35E9 1.36E9 3.80E8 Sr 89 3.74E10 1.07E9 1.45f9 Sr 90 1.24E12 3.15E11 1.67E10 Zr 95 3.92E6 8.63E5 7.68ES 1.23E6 9.00E8

• • Nb 95 4.10ES 1.60E5 1.14E5 1.50ES 2.95E8 Mo 99 7.80E6 1.93E6 1.67E7 6 '5E6 m I 131 '1.43E8 1.44E8 8.18E7 4.76E10 2.36E8 1.28E7 I 133 3.39E6 4.19E6 1 ~ 58E6 7.78E8 6.98E6 1.69E6 Cs 134 1. 60E10 2. 63E10 5. 55f 9 8.15E9 2.92E9 1.42E8 Cs 137 2.39E10 2.29E10 3.38E9 7.46E9 2.68E9 1.43E8 Ba'40 2.77EB 2.43E5 '1;62E7 7.91E4 1.45E5 1.40EB

• • La 140'3.'25E3 1.13f3 3.83E2 3.16E7 Ce 141 6.56ES 3.27E5 4.86E4 1.43E5 4.08EB Ce 144 1.27EB 3.98E7 " 6.78E6 2.21E7 1.04E10 Nd 147 7.23E4 5.86E4 4.54E3 3.22E4 9.28E7

• mrem/yr per uC1/m3.

• • Daughter Oecay Product.

87

4 TABLE 3-21 Rl VALUES - VEGETATION- TEEN m ~mreml r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

'H 3 3.37E3 .3.37E3 3.37E3, 3.37E3 3.37E3 3.37E3

'C 14 1.45E6 2.91E5 2 '1E5 2.91E5 2.91E5 2.91E5 . 2.91E5 Cr 51 6.20E4 3.44E4 1.36E4 8.85E4 1.04E7 Mn 54 4.55E8 9.01E7 1.36ES '.32E8 Fe 55 3.26ES 2.31ES 5.39E7 1.47E8 1.00E8 Fe 59 1.81ES 4.22ES 1.63E8 1.33EB 9.99EB Co 58 4.38E7 1.01E8 6.04EB Co 60 2.49ES 5.60ES 3.24E9 Zn 65 4.24E8 1.47E9 6.87E8 9.42ES 6.24EB Sr 89 1.57E10 4.50ES 1.87E9 Sr 90 . 7.51Ell 1.85E11 2.11E10 Zr 95 1.75E6 5.52E5 3.80E5 8.11E5 1.27E9

• • Nb 95 1.92E5 1.06E5 5.86E4 1.03E5 4.55EB Mo 99 5.71E6 1.09E6 1.31E7 1.02E7 I 131 ,".

7.70E7 . 1.08E8 5.79E7. 3.14E10 1.86EB 2.13E7 I 133 1.86E6 3.15E6 9.61E5 4.40ES 5.52E6 2.38E6 Cs 134 7.10E9 1.67E10 7.75E9 5.31E9 2.03E9 2.08EB Cs 137 1.01E10 .. 1.35E10 4.69E9 4.59E9 1.78E9 1.92EB Ba 140 1.38EB 1.70E5 8.91E6 5.75E4 1.14E5 2.13EB

• • La 140 1.81E3 8.88E2 2.36E2 5.10E7 Ce 141 2.83E5 1.89E5 2.17E4 8.90E4 5.41EB Ce 144 5.27E7 2.18E7 2.83E6 1.30E7 1.33E10 Nd 147 3.66E4 3.98E4 2.38E3 2.34E4 1.44E8

• mrem/yr per uCl/m3

• • Daughter Decay Product.

88

t

'))

l

%V I~

i if lit

~ l V)V( 4 t) I I

• <)')<<rkiP

~ F-A) ~

C A

t aj E

e it t) l

'l

TABLE 3-22 Ri VALUES - VEGETATION ADULT 2

m ~mrem/ r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 2.26f3 2.26E3 2.26E3 2.26E3 2.26E3 2.26E3

• C 14 8.97ES 1.79E5 1.79E5. 1.79E5 1,79E5 1.79E5 . 1.79E5 Cr 51 4.67E4 2.79E4 1.03E4 6.'19E4 1.17E7 Mn 54 3.13f8 5.97E7 9.31E7 9.59f8 Fe 55 2.10ES 1.45ES 3.38E7 8.08E7 8.31E7 Fe 59 1.27ES 2.99ES 1.15E8 8.35E7 9.96E8 Co 58 , 3.09E7 6.92E7 6.26EB Co 60 1.67E8 3.69ES 3.14E9 Zn 65 3.18E8 1.01E9 4.57E8 6.76ES 6.36EB Sr 89 1.03E10 2.96E8 1.65E9 Sr 90 6.04Ell 1.48E11 1.75E10 Zr 95 1.19E6 3.83E5 2.59E5 6.00E5 1.21E9

• Nb 95 1.42ES . 7.91.E4 4.25E4 7.82E4 4.80ES Mo 99 6.22E6 1.18E6 1.41E7 1.44E7 I'131 8;09E7 ', 1.16ES 6.63E7 3.79E10 1.98ES 3.05E7 I 133 2.00E6 3.48E6 1.06E6 5.11ES 6.07E6 3.13E6 Cs 134 4.66E9 1.11E10 9.07E9 3.59E9 1.19E9 1.94EB

.Cs 137 6.36E9 .. 8.70E9 5.70f9 2.95E9 9.81EB 1.68f8 Ba 140 1.29ES 1.62ES 8.43E6 5.49E4 9.25E4 2.65ES

• • La 140 1 ~ 98E3 9.97E2 . 2.63E2 7.32E7 Ce 141 1.97E5 1.33ES 1.51E4 6.19E4 5.10EB Ce 144 3.29E7 1.38f7 1.77E6 8.16E6 1.11E10 Nd 147 3.36E4 3.88E4 2.32E3 2.27E4 1.86E8

• mrem/yr per uCi/m3

• • Daughter Decay Product.

&9

I I

1 lk

.w4 C4,

'I

$h e "

f

• F 5.g 8

" ~

VI

~ C E

Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 Type of *Map (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 & Lake Road (R-2) 1.1 mi 8 104'SE Particulates (air)

Radioiodine and Co. Rt. 29 (R-3) 1.5 mi 9 132'.SE Particulates (air)

Radioiodine and Village of Lycoming, NY (R-4) 1.8 mi 8 143'E Particulates (air)

Radioiodine and Hontario Point Road (R-5) 16.4 mi 9 42'E Particulates (air)

"Direct'Radiation '(TLD) '6 North Shoreline Area (75) 0.1 mi 9 5' Direct Radiation (TLD) 7 North Shoreline Area (76) ~

0.1 mi 9 25'NE Direct Radiation (TLD) 8 North Shoreline Area (77) 0.2 mi 9 45'E Direct Radiation (TLD) North Shoreline Area (23) 0.8 mi 9 70'NE Direct Radiation (TLD) 10 JAF East Boundary (78) 1.0 mi 9 90 E Direct Radiation (TLD) ll Rt. 29 (79) 1.1 mi 9 115'SE Direct Radiation (TLD) 12 Rt. 29 (80) 1.4 mi 8 133'E Direct Radiation (TLD) 13 Hiner Road (81) 1.6 mi 9 159'SE Direct Radiation (TLD) '4 Miner Road (82) 1.6 mi 8 181' Direct Radiation (TLD) 15 Lakeview Road (83) 1.2 mi 9 200'SW Direct Radiation (TLD) 16 Lakeview Road (84) 1.1 mi 8 225'W Direct'Radiation (TLD) 17 Site Meteorological Tower (7) 0.7 mi 9 250 WSW Direct Radiation (TLD) 18 Energy Information Center .(18) 0.4 mi.8 265;W;

• Map - See Figures 5.1-1 and 5.1-2 h

I E.

~ I4 0

)~

Cj Fc'

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

Type of 'Map (Env.

Sam le Location Collection Site Pro ram No.) Location Direct Radiation (TLD) 19 North Shoreline (85) 0.2 mi 9 294'NH Direct Radiation (TLD) 20 North Shoreline (86) 0.1 mi 8 315 NW Direct Radiation (TLD) 21 -North Shoreline (87) .0.1 mi 8 341.'NNW Direct Radiation (TLD) 22 Hickory Grove (88) 4.5 mi 9 97, E, Direct Radiation (TLD) 23 Leavitt Road (89) 4.1 mi 8 ill'SE Direct Radiation (TLD) 24 Rt. 104 (90) 4.2 mi 9 135'E Direct Radiation (TLO) 25 Rt. 51A (91) 4.8 mi 8 156'SE

'Direct Radiation.(TLD), 26 Maiden Lane Road (92) 4.4 mi 8 183' Direct Radiation (TLD) 27 Co. Rt. 53 (93) 4.4 mi 9 205'SH Direct Radiation (TLO) 28 Co. Rt. 1 (94) 4.7 mi 9 223'H Direct Radiation (TLO) 29 Lake Shoreline (95) 4.1 mi 8 237 WSH 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 SH Direct Radiation (TLD) 32 Scriba, NY (96) 3.6 mi 8 199'SH Direct Radiation (TLO) 33 Alcan Aluminum, Rt. 1A (58) 3.1 mi 9 220'H Direct Radiation (TLD) 34 Lycoming, NY (97) 1.8 mi 8 143'E Direct Radiation <TLD) 35 New Haven, NY <56) 5.3 mi 9 123'SE Direct Radiation (TLD) 36 H. Boundary, Bible Camp (15) 0.9 mi 8 237'SH Direct'adiation (TLD) 37 Lake Road (98) 1.2 mi 9 101' Surface Water 38 OSS Inlet Canal (NA) 7.6 mi 9 235'H Surface Hater 39 JAFNPP Inlet Canal (NA) 0.5 mi 8 70'NE (NA) not applicable

• Map See Figures 5.1-1 and 5."l-2 w't h

7 pV

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

Type of *Map (Env.

Sam le Location Collection Site Pro ram No.) Location Sediment 40 Sunset Bay Shoreline (NA) 1.5 mi 8 80'

'horeline Fish 41 NMP Site Discharge Area (NA) 0.3 mi 9 315'N and/or Fish 42 NMP Site Discharge Area (NA) 0.6 mi 8 55'E Fish 43 Oswego Harbor Area (NA) 6.2 mi 8 235'H Hi lk 44 Milk Location ¹50 8.2 mi 9 93' Mi 1 k 45 Milk Location ¹7 5.5 mi 8 107'SE Mi 1 k 46 Milk Location ¹16

5.9 mi 8 190' Milk 47 Milk Location ¹65 17.0 mi 8 220'H Food Product 48 Produce Location ¹6** 1.9 mi 8 141'E (Bergenstock) (NA) .

Food Product 49 Produce Location ¹1** 1.7 mi 8 96' (Culeton) (NA)

Food Product 50>> Produce Location ¹2** 1.9 mi 9 101' (Vitullo) (NA)

Food Product 51 Produce Location ¹5** 1.5 mi 8 114'SE

't (C.S. Parkhurst) (NA)

Food Product 52 Produce Location ¹3** 1.6 mi 8 84' (C. Narewski)

Food Product 53 Produce Location ¹4** 2.1 mi 9 110'SE (P. Parkhurst) (NA)

Food Product (CR) Produce Location ¹7** 15.0 mi 8 223 SN (Mc Hillen) (NA)

Fb Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (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'W (Denman) (NA)

Food Product 56 Produce Location 1.6 mi 8 171'

¹9*'O'onnor)

(NA)

Food Product 57 Produce Location ¹10** 2.2 mi 8 123 ESE (C. Lawton) (NA)

Food Product 58 Produce Location ¹11** 2.0 mi 8 112'SE (C. R. Parkhurst) (NA)

Food Product 59 Produce Location ¹12** 1.9 mi 8 103 ESE (Johnson) (NA)

Food Product (CR) 60 Produce Location ¹13** 15.6 mi 8 225'W (Flack) (NA)

Food Product 61 Produce Location 1.7 mi 8 82'

¹14*'Dickenson)

(NA)

Food Product 62 Produce Location ¹15** 1.7 mi 9 136'E (Whaley) (NA)

• 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/A) not applicable CR Control Result (location) t )y II

=-

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-r APPENDIX A LIQUID DOSE FACTOR DERIVATION 97

1l "

IP"== +**4 QVf p

ly

Appendix A Liquid Effluent Dose Factor Derivation, Aiat Aiat (mrem/hr per uCi/ml) which embodies the dose conversion factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, 'and dilution factors for the points of pathway origin takes into account the dose from ingestion of fish and drinking water. The total body and organ dose conversion factors for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109. To expedite time, the dose is calculated for a maximum individual instead of each age group. The maximum individual dose factor is a composite of the highest dose factor, Aiat, t nuclide i, Ait. equation for of'ach age group a, organ and hence The calculating dose contributions given in Section, 2.3 requires the use of the composite dose factor Ait for each nuclide, i. It should be noted that the fish ingestion pathway is the most significant pathway for dose from, liquid effluents. The water consumption and the external'sediment exposure pathways are included-for consistency with Unit 1 technical specifications. The dose factor equation for a fresh water site is:

Aiat Ko (Uw(e- i Pw) + UfBFi(e i Pf)](DFL)iat +

Dw

..: + 69.3 UsW e

~i t Ps(1-e- gti b) (DFS)i (Ds)(gi)

Hhere:

Aiat Is the dose factor for nuclide i, age group a, total body or organ t, for all appropriate pathways, (mrem/hr per uCi/ml)

Ko Is the unit conversion factor, 1.14E5 1E6pCi/uCi x 1E3 ml/kg -:- 8760 hr/yr Uw Hater consumption (1/yr); from Table E-5 of Reg. Guide 1.109 Uf Fish consumption (Kg/yr); from Table E-5 of Reg. Guide 1.109 Us Sediment Shoreline Usage (hr/yr); from Table E-5 of Reg. Guide 1.109 Bioaccumulation factor for nuclide, i, in fish, (pCi/kg per pCi/1), from Table A-1 of Reg. Guide 1.109 (DFL)iat Dose conversion factor for nuclide, i, age group a, total body or organ t, (mrem/pCi); from Table E-ll of Reg. Guide 1.109 (DFS)i Dose conversion factor for nuclide i and total body, from standing on contaminated ground (mrem/hr per pCi/m2); from Table E-6 of Reg. Guide 1.109 Dw Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption. This is the Metropolitan Hater Board, Onondaga County intake structure located west of the City of Oswego.

(Unitless)

Ds Di.lution factor from the near field area within one quarter mile of the release point to the shoreline deposit (taken at the same point where we take environmental samples 1.5 miles; unitless) 98

4

%4 k II ~

o~ .v l, 7 pa" :e

Appendix A (Cont'd) tpw tpf or tps Average transit time required for each nuclide to reach the point of'exposure for internal dose, it is the total time el,apsed from release of the nuclides to either ingestion for water (w) and fish (f) or shoreline deposit '(s), (hr) tb Length of time the sediment is exposed to the contaminated water, nominally 15 yrs (approximate midpoint of facility operating life), (hrs).

decay constant for nuclide i (hr-1)

Shore'width factor (unitless) from Table 1-2 of Reg.

Guide 1.109 Example Ca 1 cu1 ation For I-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluents exposure:

(OFS)i 2.80E-9 mrem/hr per pCi/m2 (DFL)iat 1.95E-3 mrem/pCi tpw 30 hrs. (w water)

BFi 15 pCi/Kg per pCi/1 tpf 24 hrs. (f fish)

Uf 21 Kg/yr tb 1.314E5 hr (5.48E3 days)

Ow 40 unitless Uw 730 1/yr Ds 12 unitless Ko 1.14E5 ( Ci/uCi)(ml/k )

Us 12 hr/yr (hr/yr)

N ~.3 ~i . 3 61E-3hr-1 tps 5.5 hrs (s Shoreline Sediment)

These values will yield an Aiat Factor of 6.79E4 mrem-ml per uCi-hr as listed in Table 2-4. It should be noted that only a limited number of nuclides are listed on Tables 2-1 to 2-8. These are the most common nuclides encountered in effluents. If a nuclide is. detected for which a factor is not listed, then it will be calculated and includhd in a revision to the ODCH.

In addition, not all dose factors for each age group are used for the dose calculations.. A maximum individual is used, which is a composite of the maximum dose factor"'of each age g'oup for each organ as reflected in the applicable chemistry procedures.

99

0 APPENDIX 8 PLUME SHINE DOSE FACTOR DERIVATION 100

X, tl "n

+4 4.

J

+"

APPENDIX B For elevated releases the plume shine dose factors for gamma air (Bi) and whole body (Vi), are calculated using the finite plume model with an elevation above ground equal to the stack height. To calculate the plume shine factor for gamma whole body doses, the gamma air dose factor is ad)usted for the attenuation of tissue, and the ratio of mass absorption coefficients between tissue and air. The equations are as follows:

Gamma Air sl - $ <ua< la where: K* conversion factor (see s R8 Vs below for actual value).

td tissue depth (g/cm2) ua energy absorption coefficient (cm-i; air for Bi, tissue for Vi)

~Whole Hod E Energy of gamma ray per disintegration (Mev)

Vi 1.11SFBie-uatd Vs average wind speed for each stability class (s), m/s e

R'ownwind di,stance (site boundary, m) sector width (radians)

SF shielding factor from structures (unitless) s subscript for stability class Is I function Il + kI2 for each stab)lity class.

(unitless, see Regulatory Guide 1.109)

Fraction of the attenuated energy that is actually absorbed in air (see Regulatory Guide 1.109, see below for equation)

Ratio of mass absorption coefficients between tissue and air.

K conversion factor 3.7 E10 293 g Ci-s m/3 dis I 00 l1.6 E-6

~er g-ragd

~er Mev .46 k ~ u-ua ua where: u energy attenuation coefficient (cm-1; air for Bi, tissue for Vi) 101

"2j APPENDIX 8 (Cont'd)

There are seven stability classes, A thru F. The percentage of the year that each stability class occurs is taken from the U-2 FSAR. From this data, a plume shine dose factor is calculated for each stability class and each nuclide, multiplied by its respective fraction and then summed.

The wind speeds corresponding to each stability class are, also, taken from the U-2 FSAR. To confirm the accuracy of these values, an average of the 12 month wind speeds for 1985, 1986, 1987 and 1988 was compared to the average of the FSAR values. The average wind speed of the actual data. is equal to 6.78 m/s, which compared favorably to the FSAR average wind speed equal to 6.77 m/s.

,The average gamma energies were calculated using a weighted average of all gamma energies emitted from the nuclide. These energies were taken"fromthe handbook "Radioactive Decay Data Tables", David C. Kocher. These energies compared favorably to those given in Table 1-1.

The absorption (ua) and attenuation (u) coefficients were calculated by multiplying the mass absorption (ua/g) and mass attenuation (u/P) coefficients given in the Radiation Health Handbook by the air density equal to 293 E-3 g/cc or the tissue density of g/cc where applicable.

1 ~ 1 The downwind distance is the site boundary.

102

5 i'

~ OL id'

APPENDIX B (Cont'd)

SAMPLE CALCULATION Ex. Kr-89 F STABILITY CLASS ONLY - Gamma Air

-DATA E 2.22 k ~ u-ua ~ .871 k .46 ua a 2.943 E-3m-1 ua Vf 5.55 m/sec U 5.5064E-3m-l R ~ 644m e- .39 o~~ 19m.......vertical plume spread taken from "Introduction to Nuclear, Engineering", John R. LaMarsh

-I Function U~ -.06 I 1

.33 I2 ~ .45 I ~ Il + kI2 ~ .33 + (.871) (.45) ~ .72

~er s Bi 0.46 (Ci-sec)(Mev ) (2.943E-3m-l)(2.22(Mev))(.72)

(g/m ) (~er s) (5.55 m/s) (.39) (644m)

(g-rad) 1.55(-6) rad/s (3600 s/hr) (24 h/d) (365 d/ ) (lE3mrad/rad)

Ci/s (1E6uCi)

Ci 2.50(-2) ~mrad/ r uCi/sec 103

5

'c

APPENDIX C DOSE PARAMETERS FOR IODINE 131 and 133, PARTICULATES AND TRITIUM 104

'a eW V

p" II Q:

VI T

"I ~P+ 1I a <<,b,y,"

APPENDIX C DOSE PARAHETERS FOR IODINE - 131 AND 133, PARTICULATES AND TRITIUH This appendix contains the methodology which was used to calculate the organ dose factors for I-131, I-133, particulates, and tritium. The dose factor, Ri, was calculated using the methodology outlined in NUREG-0133. 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 landsite boundary critical location will be used for dose purposes. The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered to exist at critical specific locations. Hashout was calculated and determined to be negligible. 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 Ri(I) ~ K(BR)a(DFA)iat where:

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

a constant of unit conversion, lE6 pCi/uCi (BR)a Breathing rate of the receptor of age group a, (units m3/yr);

(DFA)iat The inhalation dose factor for nuclide i age group a, and total body or organ t (units mrem/pCi).

105

V l'

U C

$ 1 0

APPENDIX C (Cont'd)

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

A e Grou (a) Breathin Rate (m3~/ r)

Infant 1400 Chi 1 d 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAi)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.

A.2 Ground Plane Pathwa

- jilt Ri(G) K'K(SF)(DFG)i (1-e )

where:

Ri(G) dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest (units

- m2-mrem/yr per uCi/sec)

K'l a constant of unit conversion, 1E6 pCi/uCi; I

a constant of unit conversion, 8760 hr/year; it the radiological decay constant for radionuclide i, (units sec-1) li

," the exposure time, sec, 4.73EB sec (1S years);

(DFG)i the ground plane dose conversion factor for radionuclide i (units mrem/hr per pCi/m2)

SF the shielding factor (dimensionless);

106

J giga N

,(

4 s i, wr +lcrc~~w i~ : a.s t 4 44

APPENDIX C (Cont'd)

A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision 1. A tabulation of OFGi values is presented in Table E-6 of Regulatory Guide 1.109 Revision l.

A.3 Grass-(Cow or Goat)-Milk Pathwa R<<C) where:

K'()f~<U <)> Fe(r)(DFL)le

<>~ + qw) ifpfe+< )gaffe)e- <th "I

e ltf Ri<C) dose factor for"the cow milk or goat milk .pathway, for=each-identified radionuclide i for the organ of interest, (units-m2-mrem/yr per uCi/sec) a constant of unit conversion, 1E6 pCi/uCi; K'f The cow's or goat's feed consumption rate, (units Kg/day-wet weight)

Uap the receptor's milk consumption rate for age group a, (units liters/yr);

'he Yp agricultural productivity by unit area of pasture feed grass, (units kg/m2);

e"Ys the agricultural productivity by unit area of stored feed, (units kg/m2) the stable element transfer coefficients, (units pCi/liter per pCi/day);

fraction of deposited activity retained on cow's feed grass; (OFL)iat the ingestion dose factor for nuclide i, age group a, and total body or organ t (units mrem/pCi);

'the radiological'ecay constant for radionuclide i, (units sec -1);

the decay constant for removal of activity on leaf and plant surfaces by weathering equal to 5.73E-7 sec -1 (corresponding to,a 14 day ha 1 f-1 i fe);

th'e transport time from pasture to cow or goat, to milk, to receptor, (units sec);

th the transport time from pasture, to harvest, to cow or goat, to milk, to receptor (units sec);

107

I

'a fig

$ p~ k II

'l

'. M>1+'t tf

APPENDIX C (Cont'd) fp fraction of the year that the cow or goat is on pasture (dimensionless);

fs fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless);

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 fs is considered unity in lieu of site specific information. The value of fp is 0.5 based on 6 month grazing period. This value for fp was obtained from the environmental group.

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

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

RT(C) ~ K'KmQfUap(DFL)iat 0.75(0.5/H)

'where:

RT(C) dose factor for the cow or goat milk pathway. for tritium for the organ of interest, (uni ts mrem/yr per uCi/m3);

K a constant of unit conversion, lE3 g/kg; H - 'bsolute humidity of the atmosphere, (units g/m3);

0.75 the fraction of total feed that is water; 0.5 the rati'o of the specific activity of the feed grass water to the atmospheric water.

Other values are given previously. A site specific value of H equal to 6.14 g/m3 is used. This value was obtained from the environmental group "using actual'site data.

108

h

'I f

I

'L 1',1,'I '>TV+~ IV, 4 i/I <<AVHl-WfI ~

'I Q ' II V

APPENDIX C (Cont'd)

A.4 Grass-Cow-Meat Pathwa Ri(H) ~ K'QfUap (s~ +~)

Ff(r)(DFL)iat ff (1-ff)e-4 tf

+

5 e p

Ri(H) dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, (units m~-mrem/yr per uCi/sec);

Ff the stable element transfer coefficients, (units days/Kg);

Uap the receptor's meat consumption rate for age group a, (units kg/year);

th the transport time from harvest, to cow, to receptor, (units sec) tf the transport time from pasture, to cow, to receptor, (units sec)

All other terms remain the same as defined for the milk pathway. Table C-2 contains the values which were used in calculating Ri(H).

The concentration of tritium in meat is based"on airborne concentration rather than 'deposition. Therefore, the RT(H) is based on X/Q.

RT(H) ~ K K FfQfUap(DFL) i at k0 75(0 5/H) )

~

where:

RT(M) dose factor for the meat ingestion pathway for tritium for any organ of interest, (units mrem/yr per uCi/m3).

All other terms are defined above.

A.S Ve etation Pathwa

"'.'",'"'The"i'n'tegrated'concentration in vegetation consumed by man follows the expression developed for milk. Han is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and, consumption, therefore:

.'Ri(V) (DFL)iat UL)aFLe + US)aFge K'v(ki+Xw) 109

(k wlw 3

1)

APPENDIX C (Cont'd) where:

Ri.<V) dose factor for vegetable pathway for radionuclide i for the organ of interest, (units m~-mrem/yr per uCi/sec);

a constant of unit conversion, lE6 pCi/uCi; K'L) the consumption rate of fresh leafy vegetation by the receptor in age group a, (units kg/yr);

Us) the consumption rate of stored vegetation by the receptor in age group a (units kg/yr).

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

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

Yv the vegetation area density, <units kg/m~);

All other factors are defined previously.

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

In lieu of site-specific data, values for fL and fg of, 1.0 and 0.76, respectively, were used in the calculation. These values were obtained from Table E-15 of Regulatory Guide 1.109 Revision l.

110

'k g*

I I

APPENDIX C (Cont'd)

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the RT(V) is based on X/Q:

RT(V) ~ K'K") fL + Us)a f DFL)iat 0.75(0.5/H) where:

RT(V) dose factor for the vegetable pathway for tritium for any organ of interest, (units mrem/yr per uCi/m3).

All other terms are defined in preceeding sections.

Pjg 1'V V

TABLE C-1 Parameters for Grass-(Cow or Goat)- Hilk Pathways Reference Parameter Value (Re . Guide 1.109 Rev. 1)

Qf (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (OFL)iat (mrem/pCi) Each radionuclide Tables E-11 to E-14 Fm (pCi/liter per pCi/day) Each stable element Table E-1 (cow)

Table E-2 (goat)

Ys (kg/m2) 2.0 Table E-15 Yp (kg/m2) 0.7 Table E-15

'h (seconds) 7 78 x 106 (90 days) Table E-15 tf (seconds) 1.73 x 105 (2 days) Table E-15 Uap (liters/yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 112

0 7

~F h'l

'h f'.

TABLE C-2 Parameters for the Grass-Cow-Heat Pathway Reference Parameter Value (Re . Guide 1.109 Rev. 1) 1.0 <radioiodines) Table E-15 0.2 (particulates) Table E-15 ff (pCi/Kg per pCi/day) Each stable element Table E-1 "ap (Kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5

<DFL)iat (mrem/pCi) Each radionuclide Tables E-ll to E-14 Yp (kg/m ) 0.7 Table E-15 Ys <kg/m2) 2.0 Table E-15 th (seconds) 7.78E6 (90 days) Table E-15 tf (seconds) 1.73E6 (20 days) Table E-15 Qf (kg/day) 50 Table E-3 113

~ A CA i f

/

'1

TABLE C-3 Parameters for the Vegetable Pathway Reference Parameter .Value (Re . Guide 1.109 Rev. 1) r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFL) i at (mrem/pCi ) Each"radionuclide Tables E-11 to E-14 UL) (kg/yr) infant 0 Table E-5

- child 26 Table E-5

- teen 42 Table E-5

- adult 64 Table E-5 Us)a (kg/yr) infant 0 Table E-5 child 520 Table E-5 teen 630 Table E-5 adult 520 Table E-5 tL .(seconds) 8.6E4 (1 day) Table E-15 th (seconds) 5.18E6 (60 days) Table E-15 Yv (kg/m2) 2.0 Table E-15 114

r

'I(

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APPENDIX D DIAGRAMS OF LIQUID AND GASEOUS RADWASTE TREATMENT SYSTEMS 115

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I~ I oa wA"T4l'oW + Ps 9 t! 9 <<O o>> L::3 lg=-'"g- . ,I,-C)"' L:! -'t-=--] To <<Io o <> PP [r '-".I ~ ~a I I>> Po 1 )F'I Q W <<wlj>>o<  ;,l i+I P>>%>><PI )I'IIO IO I l. la lm] .; 1 W >p>>>>o L <<II >>>> j l>>>>a "I L:-3 l >>o>>po ~ >>>> I <<>>>>P>>O P>> ~ >> I>> V p.k: f"" & C~ ~ O<<W>>OI fIGU)lf NASIf OISPOSAI NUllUING VfNfII AIION SfhfIN )OIAOIAAA <AVI<AW<) ) VWL)1 Cv<lvuHA)IVH NINE Mil.l: I'OINr-I/Nlt 1 OFF SITE DOSE CALC. )4AHUAL t. ~ II, t e .. .I n I 4Iy~ ~" Q .1 I," lt STACK " PLAN AND ELEVATlON ~TIOOM ~ I,AH CLCV+TlON CRAPNIC ISaIIIN CTIC rIIaaC pLiTsaa II hATsaaN CIVIC,CIIVceea A.J504'TD CL TSaIs ~ass ass UNCS ~PA M ~.cavo ~ TOr aS SlJkRIs T' I R'S I s FIG URE D-5 OIO VAT(ON LOOK INO NORTH SI 1 Stack NIAGARA MOHAWK POWER CORPORATION -121-NINE MILE POINT UNIT OFFIITR DOIlf CALC MANUAL j 4fk i l Ib I t OFF CAS BUILOINC VENTILATION SYSTEM awwa) w la 44 ~ ~ a AAI I' ~ Da ~ laaaaa aaata ~ wa 4 Ka 'v ~aa Njt waafs w ~ WaafK ll L'" AAII~ W 4aaa II aa AAAIK Aa44aaO ~ Aat V ~ wat ~ ~I+ W 5 Jaa'V ~ DCa'V ItlIt I F CURE OffGAS BUIIDIBG VfllllIAIIOIISYSllN wwawa wlaa Wa W Aa I'IIAOAA* IawIAwI4 I owLH CoIII ulIA1IoH NINE MILE I'OINt-LJNlf 1 OFFSITE OOSE CALC MANUAL ~ alta r 4'J ~ tg P ~ ~ ~( ~) OL) ~ (b) NIACARL QCN awe KPNQt C~afOR Li HACH (s) t (s) Mfner Road D"7 Sita Boundaries NNGARA MOtNWK POWER CORPORAL lO> -123- NINE MILE POINT-UNIT 1 NINE MLLE POINT OFFSlTE OOSS CAt.C MANUAL lC <<f ~W I' k 0U i' ~ M NOTES TO FIGURE D" > (a) NMP1 Stack (height is 350') (b) NMP2 Stack (height is 430') (c) JAFNPP Stack (height is 385') (d) NMP1 Radioactive Liquid Discharge (Lake Ontario, bottom) (e) NMP2 Radioactive Liquid Discharge (Lake Ontario, bottom) (f) JAFNPP Radioactive Liquid Discharge (Lake Ontario, bottom) (g) Site Boundary (h) Lake Ontario Shoreline (i) Meteorological Tower (j) Training Center (k) Energy Information Center Additional Information: - NMP2 Reactor Building Vent is located 187 feet above ground level - JAFNPP Reactor and Turbine Building Vents are located 173 feet above ground level - JAFNPP Radwaste Building Vent is 112 feet above ground level - The Energy Information Center and adjoining picnic area are UNRESTRICTED '-.-"". AREAS:.wi.thin, 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 MEMBERS OF THE PUBLIC -l24- 0 '* ~ a, sac,r 4 r NV 41% ~ 5'>> ~ ., ~ ~ ~ )I l~ I) 8) ~~I Og ill C ~ I ~ ) I I ~ . I I t Q ~ 0 ~ ~ 0 0 ~ I I &E w'4 I ill a ~ otal C V 'I IO RAG EMS RAGEMS Ditution 11241 Return ISOKINETIC PROBE RN 21 112-131 ] 112-52 Sample Return 112-55 Drain 112.30 112-132 OGESMS Intet 11243 112.57 112-133 OGESMS Outtet 112-56 Figure D-9 Stack Sample and Sample Return NIAGARAMOHAWK POWER CORPORATION NINE MILE POINT - UNIT 1 OFFSlTE DOSE CALC. MANUAL 126- S lit F' ~ ~ J tel OV3 OV1 OV13 RAG EMS 112-169 112-165 t 1248 RAG EMS inlet Dilution Ne Supply Inlet OVS OV8 C 112-173 112-178 OV4 112.130 112-171 OFS1 1 2-1 112-101A 112-51 OV2 Pl 112-167 PCV 112-21 112-106 112-110 OFS4 112- 04A OFC1 112-101 OFC4 PCV 112-104 112-107 112-111 Pl 11 -122 112-116 OFS2 OFC3 OCF2 112-102A 112-103 OFS3 112-102 112-103A 112-151 OV12 OV16 Senlpte 112+7 RAG EMS 112-150 Return Outlet 112-112 Pl 112- 24 Pl 112-113 "11 - 23 112-118 112-117 OP2 OP1 OV6 11 - 44 112-175 Figure 0-1 0 RAGEMS Dilution Schematic NIAGARAMOHAWK POWER CORPORATION NINE MlLE POINT- UNIT 1 OFF SITE DOSE CALC. MANUAL 127 IP' ~ ) ~ir 14 gl g Qalhn2 Tritium 3V16 112-73 112-74 112-218 Pl 112-125 112-72 1V3 1V4 2V4 112-183 112-185,'V3 112-199 112-201 3FS1 1FS1 112-105A 112-129 3V 112-96 112-114 3V3 112. 7 Pl 1V1 1V2 2VI 2 3VI 3VS 112-126 12-'I81 3 3 112-1 112-195 112-197 112 -95 112-99 .75 2.77 3GVI 6 Uter 112-105 112-119 1V5 1V6 2VS 2V6 11 76 I -78 112-186 112-187 112-202 112-203 3 3 3V4 3V6 3V7 2V11 112.98 112-100 112-211 112-208 1V11 112-192 Pl 11244 Pl 11247 3PI 'l12-108 1V17 11249 3V11 112-215 3VIO 112-21 I Fi Ure D-11 3VI 112-217 3VI2 112-216 RAGEMS Schematic 112-109 NIAGARAMOHAWK POWER CORPORATION NINE MILE POINT- UNIT 1 OFFSITE DOSE CALC. MANUAL 128 P+ A. J a tA t 'a ~ <<a 1 0 11242 112-10 AM43A FS 11249 11266 112-11 67 11 43 112-147 112-59 FL1 112-58 112-148 12-149 'l 1244 11245 Inlet 112-146 u 112-u u 112 u u 11261 11240 62 63 12-112-152 1 BA-112-137 153 112-154 Pl G-3 11248 FGV 112-137 112-91 112-161 11244 112-163 112-134 BR G-3 PS2 112-138 Fl 112-139 112-140 11246 11 -135 11 4i 1'l2-FS Tritium 135 112-94 112-22 112.21 112-155 V/Pl 12-158 q 11245 112-156 112-20 112-142 l12-141 FL3 11240 112-159 112-'157 112- 3 112-19 112-1 112.14 112.18 112-15 12 11249 112-70 12- 1 11247 11248 Fi ure D-12 OGESMS Schematic 112-12 NIAGARAMOHAWK POWER CORPORATION NINE MILE POINT - UNIT 1 OFFSITE DOSE CALC. MANUAL 129 '1 y l,ll if ~ 8 J SUPERSKOEQ A Ol4 N M P I T N REPLICA General Superintendent Nuclear Generation K. A. Dahlberg for L. Will 1 s 3 1 1,2,5,6,8,9,11-13,15-18, 36-44,47-49, 52-63,65-76,79-81,86-116 February 1987 3,4,7,10,14,20,23 27-28,30-35 December 1987 45,46,50,51,82-85 January 1988

• 29 May 1988 (Reissue)

• 64,77,78 May 27, 1988 (Reissue) i,19,21,22A,22B,24,25 26,112 February 1990 THIS PROCEDURE NOT TO BE USED AFTER March 1992 SUBJECT TO PERIODIC REVIEW 9PP9110036

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1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS 2 ~ 1 Setpoint Determinations 2.1.1 Basis 2.1.2 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 Contamination 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 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 22B I

~

'3 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 Stack Sample Flow Path - RAGEHS 3.1.5.3 Stack Sample Flow Path - OGESHS 26

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TAB F T (Cont'd) 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 4.0 40 CFR 190 REQUIREMENTS 40 4.1 -:Evaluations of Doses From Liquid Effluents '6 4.2 Evaluation of Doses From Gaseous Effluents 4.3 Evaluation of Doses From Direct Radiation 46

'.4 Doses to Members of, the Public Hithin the Site Boundary 47 5.0 ENVIRONMENTAL MONITORING PROGRAM 52 5.1 Sampling Stations 5.2 Interlaboratory Comparison Program 53 5.3 Capabilities for 'Thermoluminescent Dosimeters 54 Used for Environmental Measurements.

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

~Pa e Table 1-1 Rapj 1 Values . for the NMP-1 Facility 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 Progrem 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

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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), 10 CFR 20, 10 CFR 50, and 40 CFR 190 'he contents of the ODCM are based on Draft NUREG-0472, Revision 3, "Standard Radiological Effluent Technical Specifications for Pressurized Water'eactors,"

September 1982; Draft NUREG-0473, Revision 2, -"Radiological

. Effluent Technical S'pecifications for BWR's," July 1979; NUREG 0133, "Preparation of Radiological Effluent Technical Specifications 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'hould it be necessary to revise the ODCM, these revisions will be made in accordance with Technical Specifications

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2.0 LIQUID EFFLUENTS 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 specified in 10 CFR 20, Appendix B, Table II, Column 2.

Setpoints for the Service Water System Effluent Line will be calculated'uarterly based on the radionuclides identified during the previous year's releases 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 tl 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( Ci/ml) expression (Section 2.1.2, 2.1.3).

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2.1.1 (Cont'd)

The Required Dilution Factor is calculated using concentrations of all isotopes present (or the corresponding MPC 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 Monitor shall be contained in the Nine Mile Point Station Procedures. These methods shall be in accordance with the following:

Setpoint (Hi alarm)<0.9 z(nCi/ml)i CF) TDF/Fsw background

/

Setpoint (Alert alarm)<0.7 E(pCi/ml)i (CF) TDF/Fsw + background (

5 E f (p Ci/ml)j T/MPCi J (liCi/ml)i ~ concentration of gamma emitting isotope or the corresponding MPC of gamma emitting isotope i in the sample, i'MPC)i ',whichever is higher (units ~ uCi/ml)-

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

.higher (units ~ vCi/ml).

Total Dilution Flow (units gallons/min)

Fsw Service Water Flow (units gallons/min)

CF ~ monitor calibration factor (units ~ net cpm/uCi/ml)

MPCi liquid effluent radioactivity concentrations limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.

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~ 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.**

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

O.a and 0.7 ~ factors of conservatism to account for inaccuracies.,

T f (uCi/ml) T/MPCi]

i Required Dilution Factor. If MPC values )s are used in the ~(uCi/ml)i, they must also be used in calculating RDF (numerator).

TDF/Fsw ~ Actual 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 Alarm 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 >(uCi/ml)i (CF) TDF/Fxe

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

Setpoint (Hi alarm) <0 ' 7(pCi/ml)i (CF) TDF/Fre +background Z [ (v Ci/ml)j T/MPCj ]

(vCi/ml)i sample

~ concentration of or, the corresponding gamma MPC emitting isotope of gamma emitting i in the isotope i (MPC)i~whichever is higher.

(<<Ci/ml)iT sample

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

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

Fre Radwaste Effluent Flow (units ~ gallons/min)

CF monitor calibration factor (units ~ net cps/pCi/ml) h n

4 4s

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.

f(uCi/ml)iT/MPCij in the E(uCi/ml) in calculating i,

~Required Dilution Factor. *If MPC values are used RDF they must also be used (numerator).

Notes:(a) If TDF/Fre ~ E [(pCi/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 50'aximum permissible concentration.

(b) The value used for TDF will be reduced by the fractional

'uantity (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).

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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 isolated (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 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 gr'ab 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.

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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.

Additionally, the Hi Alarm setpoint of the Liquid Radwaste Effluent Radiation Monitor is set at a value corresponding to not more than 70X of its calculated response to the grab sample or corresponding MPC 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.

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2.1.4.4 Liquid Radwaste Systems Operation Technical Specification 3.6.16.a requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid

~astes prior to their discharge, as necessary, to meet the concentration and dose requirements of Technical Specification 3.6.15 ~

"Utilization of the radwaste system will be based on the capability of the indicated components of each process system to process contents of the respective low conductivity and high conductivity collection tanks:

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

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

"-'" >>" "'>'Cumulative .dose contributions from liquid effluents 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 3.6.15.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).

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2.1.4.4 (Cont'd)

For the purpose of dose projection, 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.

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2.1.4.5 Service Water System Contamination Service water is"normally non-radioactive. If contamination is suspected, as indicated by a sfgnificant 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. If 'it is 'determined that an inadvertent radioactive discharge is occurring from the service water system, then:

a) A 50.59 safety evaluation shall be performed (ref. IGE Bulletin

'0-10),

b) Daily service water effluent samples shall be taken and analyzed for principal gamma emitters until the release is terminated, H

c) An 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 (using estimated concentrations for H-3, Sr-89, Sr-90 and Fe-55 to be conservatively determined by

=

supervision at the. time of the incident).

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

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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.

the 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 1 s

((yCi/ml) is ~F s )/(MPC iI s (F

s

))l Where:

MPC Fraction ~ The limiting concentration of 10 CFR 20, Appendix B, Table II, for radionuclides other than dissolved or entrained noble gases. For noble gases, the concentration shall be limited to 2 8-4 microcurie/ml total activity.

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2.2 (Cont'd)

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

F The flow rate of a particular effluent s

stream s, gpm.

MPCi The limiting concentration of a specific i

nuclide from 10CFR20, Appendix b, Table II, Column 2 (noble gas limit is 2E-4 pCi/ml)

Z ((ICi/ml)is "Fs ) The total activity rate of nuclide i, in all s

effluent streams s, pCi/ml"gpm

~ 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~ile 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,.l January '1981 through"'31'December:1981. Utilizing the. effluent. data

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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

'.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.

From 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 dose 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

" '""-~ -".~"'received.via.the fish ingestion pathway.

In order to determine the dose contribution from the release of liquid,effluents, the'nnual 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:

R ..

apji

~ 1100U M ap P Z B. .

ipDaipj. exp

(-g.t i p )/F yt, t'.

'fjl t

IK

Where R 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) tJ 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) 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) 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", pathway "p", and organ "j", which can be utilized to calculate the radiation dose from an intake of a radionuclide (units ~ mrem/pCi) radioactive decay constant of nuclide "i" (units

~ -1 hours )

k 4i' yl

~ r+ II cd MINI p I

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 Eood and/or water (units ~ hours) 1100 ~ factor to convert from (Ci/year)/(Et 3 /sec) to pCi/liter Values for R apj i are contained in Table 1-1. All of these values of for apj.ii R are on a per Curie basis each of the nuclides released. Table 1-2 indicates those parameters used for selected Eactors 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 j i( ) Ci PDLi 1.05 R ji(L)C Where 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)

~

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P, ty

~ \ 0 ~ ~

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

apj

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

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All pro5ected doses calculated in this manner for each batch of liquid effluent will be'ummed for comparison with quarterly and annual limits, added to the doses accumulated from other releases in

'he quarter and year of interest. In all cases, the following relationships will hold-For a calendar quarter:

D <1.5 mrem total. body r

t-D < 5 mrem for any organ For the calendar year:

D < 3.0 mrem total body' D < 10 mrem for any organ where D 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 CPR 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.

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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. Fitzpatrick and Nine Mile Point Unit II facilities as well as Nine Mile Point Unit I Nuclear Station.

In the 'event -the calculations demonstrate that the 40 CFR 190 dose limits, as defined above, have 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'DCM contains more information concerning calculations for an evaluation,of=whether 40 CFR 190 limits. have been exceeded.

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3.0 GASEOUS EFFLUENTS

3. l Setpoint Determinations 3.1.1 Bas1s Stack gas and off gas monitor setpoints will be established such that the instantaneous release rate of rad1oactive 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 at or beyond the (land) s1te 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 1n the gaseous effluent.

Emergency condenser vent monitor setpoints will be established such that the release rate for radioactive materials in gaseous effluents do not exceed the 10 CFR 20 limits for annual release rate over the pro)ected longest period of release.

Monitor setpoints from continuous release points w111 be determined once per quarter under normal release rate cond1tions and will be based on the isotopic composition of the actual release in progress, or an offgas isotopic distribution, or a more conservative default compos1tion specif1ed in the pertinent procedure. If the calculated

" setpoint's 'higher than the existing setpoint, is not mandatory it that the setpoint be changed.

Monitor setpoints for emergency condenser vent monitors are

'conservatively f1xed at 5 mr/hr for reasons described in Sections 3.1.4 and.therefore do not require.per1odic recalculations.

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 CORM Superv1sion. In part1cular, contr1butions from both JAF and

'MP-2 and the Emergency Condenser Vents shall be assessed.

Dur1ng outages and until power operation is again realized, the last operating stack and off gas monitor alarm setpoints shall be used.

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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

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'X/Q E(e M )

Mnax 500 mr/yr where:

,yCi/sec released rate for each isotope, i X/Q highest land sector site boundary (elevated) dispersion parameter (see Table 3-1)

Mi gamma air dose factor in units of mr/yr/yCi/m3 (See Table 4-1)

(9) max instantaneous release rate limit.

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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) . Hi alarms be set lower than or equal to (0.5) (Q) max'hall max (3) Based on the above conservatism, the dose 'contribution from JAF and NMP-2 can usually be ignored. During Emergency

'lassifications at JAF or NHP-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 pCi/sec release rates, the following general formula silall be applied:

(C -B) K Q pCi/sec release rate where:

C monitor gross count rate in cps or cpm B ~ - monitor background count rate K stack monitor efficiency factor with units of pCi/sec-cps or pCi/sec-cpm.

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

K s Ei(Q)i (C -8) where:

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

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

3.1.2 (Cont'd)

Alternatively, when stack release rates are near the lower limit of detection, the following general formula may be used to calculate k

s f ( Yf') ~Hd f

where:

f stack flow in cc/sec E - effic1ency 1n units of cpm cc/pC1 or cps cc/pC1 Ek cpm cc/bps or cps cc/gs from energy calibration curve produced dur1ng NBS traceable pr1mary gas calibration or transfer source calibration Yk b/d (betas/disintegration) or W /d (gammas/d)

I Fi Activity fraction of nuclide 1 in the m1xture nuclide counter k discrete energy beta or gamma emitter per nuc11de counter s "seconds This monitor cal1bration method assumes a noble gas.distribut1on-typical of a recoil release mechan1sm. To -ensure that the calculated efficiency is conservative, beta or gamma emissions whose energy is above the range of calibration of the detector are not included in

"*the calculation.

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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 pCi/sec. This alarm point may be set equal to or less than l Ci/sec for a period of time not to exceed 60 days provided the offgas treatment system is in operation.

(2) The h1 alarm points shall act1vate with recombiner discharge rates equal to or less than 500,000 pCi/sec (3) To convert monitor mR/hr readings to pCi/sec, the formula below shall be applied:

(R)(KR) QR pCi/sec recombiner discharge release rate where:

R mR/hr monitor indicator KR efficiency factor in units of pCi/sec/mR/hr determined pr1or to sett1ng monitor alarm points (4) Monitor KR factors shall be determined using the general

""'formula:

KR Z Qi/R where:

'- individual noble gas radionuclide recombiner

<<; discharge release rate as determined by isotop1c analysis and flow rate mon1tor.

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

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3.1.3 (Cont'd)

(5) The setpoints chosen provide assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a very small fraction of the limits of 10CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment (thereby implementing the requirements of General Design Criteria 60 and 64 of Appendix A to 10CFR Part '50). Additionally, these setpoints.serve to.limit buildup of fission product activity within the station systems which would result if high fuel leakage were to be permitted over extended periods.

3.1.4 Emergency Condenser Vent Monitor Setpoint The monitor setpoint was established by calculation ("Emergency

,Condenser Vent Monitor Alarm Setpoint", January 13, 1986, NMPC File Code 816199). Assuming a hypothetical case with (1) reactor water iodine concentrations higher than the Technical Specification Kimit, (2) reactor water noble gas concentrations higher than would be

'!'~'expected at Technical Specificationiodine levels, and (3) leakage of reactor steam into the emergency condenser shell at 300% 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.

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3.1.5 Discussion 3.1.5.1 Stack Effluent Monitoring System Description The NMP-1 Stack'Effluent Monitoring System consists of two subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEHS) and the old General Electric Stack Monitoring System-(OGESHS). During normal operation, the OGESHS shall be used to monitor station noble gas effluents and collect particulate and iodine samples in compliance with Technical Specification

,. requirements.

The RAGEHS is des1gned to be promptly activated from the Main Control Room for use in high range monitoring during acc1dent situations in compliance with,NUREG 0737. crtter1a. Overall system schematic for the OGESHS and RAGEHS are shown on Figure S-9. A simplified view of RAGEHS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure S-8.

he'AGEHS can provide continuous accident monitor1ng and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specificat1on Table 4.6.15-2 lim1ts.. Activities as low as 5 X 10 and as h1gh as 2- X 10 pCi/cc for noble gases are detectable by the 'system.

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3.1.5.2 Stack Sample Flow Path - RAGEHS 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) s'ome 270'long the off gas tunnel; and enters the RAGEHS located on the Turbine Building Unit 0) and Off Building 247'Particulate, 250'Dilution cabinet Gas Iodine, Noble Gas stations Units 1-3 ).

In the Dilution cabinet of the RAGEHS, 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

- ': 'rom an on-site liquid nitrogen storage tank (see Figure 8-9).

From Unit 0,'the sample gas enters Uni,t 1-3 of RAGEMS 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 flows back thru Unit 0 and the off gas tunnel; and back into the stack.

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3.1.5.3 Stack Sample Flow Path OGESHS The OGESHS sample is obtained from the same stack sample probe as the RAGEHS. From the exit of the stack at elevation'257', the sample line runs east approximately 20'nd then. vertically approximately 8'o the OGESHS skid. In the OGESHS, sample flows thru a particulate/iodine cartridge'ousing and four noble gas scintillation detectors (ie, 07 and 08 low range beta detectors and 11 and 12 high range gamma detectors). From OGESMS, the stack sample flows back into the stack at approximately elevation 257'.

All OGESHS detector outputs are monitored and recorded remotely in the Hain Control Room. 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.

Stack particulate and iodine s'amples are retrieved manually from the

.OGESHS and analyzed in the laboratory using gamma spectroscopy at

"'"frequencies and LLDs 'specified in Table 4.6.15-2 of the Technical Specifications.

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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 three analyses are performed off-site from a composite sample. Sample

".analysis frequencies are.increased during elevated release rate conditions, following startup, shutdown,and in con]unction witheach drywell purge.

'-'onsistent 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 RAGEHS and.OGESHS respectively. These correction factors are based on empirical. data from -sampling conducted, at -NMP-1 in 1985 (memo from 3. Blastak to RAGEHS File, 1/6/86, "Stack Sample Representativeness Study: RAGEHS vs. In-Stack Auxiliary Probe Samples" ).

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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-131 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.

Additionally,-the I-135/I-131 and I-133/I-131 ratios should also be 5

determined after a significant change in the ratio is suspected (eg, plant status changes from prolonged shutdown to power operation or fuel damage has occurred).

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 3.6.15.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 shall be determined monthly in accordance with section 3.2 of this manual. Initial dose calculations shall incorporate the following assumptions with regard to release rates of non-gamma emitting radionuclides subsequently analyzed off-site:

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3.1.5.6 (Cont'd) 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 Assumed release rates represent conservative estimates derived from analysis of historical data from effluent releases and process waste streams (See NMP 34023, C. Mare to J. Blasiak, April 29, 1988, "Dose Estimates for Beta-Emitting Isotopes".). Following receipt of V

off-site H-3, Sr-89, Sr-90, Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations.

3.2 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 sector '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.~

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3.2 (Cont 'd)

Either average meteorological data (ie, 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'ite 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-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 the emergency condenser return isolation valves have been opened 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.

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3.2 (Cont'd)

'hen releases from the emergency condenser have occurred, dose and do'se 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.

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

'"*'pa'thways "are. applicable and the highest X/Q and/or D/Q value for r

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

--"'"calcul'ating land sector site. boundary doses and dose rates for particulates, iodines and tritium, only the ground deposition and inhalation pathways apply.

/jism 3.2.1.1 Noble Gases In'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):

DR+ ~ 3.17 x 10 f[Mi(X/Q)Qi/ ]

For skin dose rates (in mRad/yr):

DR

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

where:

-8 Mi, Ni, X/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'rom 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.

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3. 2.1.2 (Cont 'd)

(2) En 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 0.3 pCi/sec using the equation given in Section 3.2.2.2 with Q expressed in iiCi/sec. When the "release rate exceeds 0.3 uCi/sec, the dose rate assessment shall also include JAF and NMP-2 contribution.

(3) The use of the 0.3 vCi/sec release rate threshold to perform

" "" "dose rate calculations is )ustified as follows:

P (a) The 1500 mrem/yr organ dose rate limit corresponds to a minimum release rate limit of 0.30 nCi/sec calculated using the equation:

1500 (Q/sec) x (Ri)W))

where:

1500 site boundary dose rate limit in mrem/year (Ri )W)) "

the maximum curie-to-dose'conversion factor equal to 4900 mrem-sec/uCi-yr for Sr-90, child bone at the "moving" critical receptor location beyond the site boundary.

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3.2.1.2 (Cont'd)

(b) The use of 0.3 iiCi/sec release rate threshold and the 4900 mrem-sec/vCi~r curie-torose conversion factor is conservative since curie-torose conversion factors for other isotopes likely to be present are significantly .

lower. For example, I-131 has the second highest curie-to-dose factor equal to 465 mrem-sec/uCi-yr for the infant thyroid. This corresponds to a release rate limit of approximately 3nCi/sec.

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

'0 mrad beta/calendar year Radioiodines, Tritium & Particulates 7.5 mrem to any organ/calendar quarter

"'15'mrem-to any organ/calendar. year 4 NQ Si I

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3.2.2.1 Noble Gas Air Dose

-- The-air 'dose at the critical. receptor due to noble gas releases is determined as follows:

For gamma radfation D

g 3.17 x 10 7 Mi X/Q For beta radiation D<~ 3.17 x 10 E'i X/Q Qi where M

i air gamma dose factor in (mr/year per uCi/m3 ) for each isotope i (Table 4-1) 3 N ~ air beta dose factor (mrad/year per uCi/m ) for each isotope i (Table 4-1)

X/Q the relative plume concentration (in units of sec/m 3 ) at the land sector site boundary or beyond. Either average meteorological data (Table 3-1 or Appendix 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, (pCi)

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

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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 R~EiRi~akW~Qi Where WJ dispersion parameter either X/Q (sec/m 3 ) or D/Q (1/m 2 ) depending on pathway and receptor location assumed. Either average meteorological data (Table 3-1, or Appendix 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) izaak the dose factor for each isotope i, pathway j, age group a, and organ k (Table 4-2, through 4-20) 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.

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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.

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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 1

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 particulate 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

~ ... *'ilk,.cow and milk goat location as determined by technical specification'.3.6.22.',.The'inhalation 'dose pathway, will.be based-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.

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3.3 (Cont'd)

For the meat consumption dose pathway, the critical receptor is the greatest D/Q meat animal location. This location has been determined in conjunction with the land use census (technical specification 3.6.22) and is subject to change. The vegetation (food crop) dose is based on the greatest-D/Q garden location from which samples are

.taken. This location also.may be modified:as a result. of .vegetation sampling surveys.

3.4 Refinement of Offsite Doses Resulting from Emergency Condenser Vent Releases The doses resulting from the operation of the emergency condensers and calculated in accordance with 3.2.2 may be refined using data from actual enviromental samples.

Ground deposition samples will be obtained from an area or areas of maximum projected deposition. These areas are anticipated to be at

<, <or..near. the site boundary and near projected plume centerline. Using the methodology found in Regulatory Guide 1.109, the dose will be calculated to the maximum exposed individual. This dose will then be compared to the dose calculated in accordance with 3.2.2. The comparison will result, in an adjustment factor of less than or .

greater than one which will be used to adjust" the'other doses from other pathways.

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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.

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

"Uranium fuel cycle'eans 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'ower for public use utilizing nuclear energy, but excludes mining operations, operations .at waste disposal sites, transportation of any radioactive material in support

. of these operations, and the reuse of recovered non-uranium special r

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 limits 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.

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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

'perations 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.

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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 summed with the maximum doses resulting from the releases of noble gases, radioiodines, and particulates for the other calendar quarters

~ >> ~ -- (as. applicable)...and, from .the calendar.,quarter in, which twice the ..

limit was exceeded. The direct dose components will be determined by either calculation or actual measurement. Actual measurements will utilize environmental TLD dosimetry. Calculated measurements will utilize engineering calculations to determine a projected direct dose component. Zn the event calculations are used, the methodology will be detailed as required in Section 6.9.1.e of the Technical Specifications.

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,'he results of the Radiological Enviromental 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.

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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, fi'sh'onsumption'and "shoreline'ediment>> are the only

'wo 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 ~ Fi [Cif x u x 1000 x Diwb x f]

Where:

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

A

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(Cont'd)

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

'Diwb ~ The dose factor for radionuclide::i for the whole body of an adult (R.G. 1.109, Table E-11).

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

(2) Rl ~ ~i [Cif x y x 1000 x Dil x Where:

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

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

The dose from shoreline sediment sample media is calculated as:

- E [Ci, x ll x -40,000 x 0.3 x Diwb x f]

and

~ g [Cis x y x 40,000 x 0.3 x Disk x f]

Where:

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

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

Cis ~ The-concentration of radionuclide i in shoreline sediment in pci/gram.

4" 0 A

gR

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(Cont'd)

~ The usage factor. This is assumed as 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year I by a teenager or adult.

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.

NOTE:

'ecause of the nature of the receptor location and the extensive fishing activity in the area, the critical individual-may be a teenager or an adult.

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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 TID, 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.

1

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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-utilizing environmental'-TLDs,

-':the'ritical 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.

4~4 Doses to Members of the Public Mithin the Site Boundary.

Section 6.9.l.e of the Nine Mile Point Unit 1 Technical Specifications requires that the Semiannual 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.

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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

'onditions." 'Thus," fishing is -the'ajor 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

'hat 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 l 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 resultantlung 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.

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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,'oating 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, inhalation 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 F

... presented here, is., not.identical .to the Regulatory Guide equations.

R ~y. i[CiF X/Q DFA .

i]aR a t]

where:

R 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 ~ f P

I II k

~ s, A

4' (Cont'd)

The'average concentration in the stack release of radionuclide i in pCi/m3 for the period in question.

~ 3 F Unit 1 average stack flowrate in m /sec.

'X/Q . The:plume dispersion"parameter for a location approximately 0.50 miles 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. A X/Q value based on real time meteorology may also be utilized for the period in question, if desired. The stack (elevator) X/Q is conservative when based on 0.50 miles because of the close J

proximity of the stack and the receptor location).

DFAi) the inhalation dose factor for radionuclide i, the lung j, and adult age group a in mrem per pCi found on Table E-7 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).

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

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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 background-dose by subtracting the

""-applicable -off-si'te 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 pathway includes any gamma doses from an overhead plume, submersion in the plume, possible radiation from the facility and ground plane dose (deposition). This general pathway will be evaluated by average environmental TI,D readings. At least two environmental TIDs will be utilized at one location in the

' approximate area where fishing occurs. The TIDs 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 TI.D 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). Zn the event of loss or theft of the TLDs, results from a TLD or TLDs in the area may be utilized.

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5.0 ENVIRONMENTAL MONITORING PROGRAM 5 ' Sampling Stations The current sampling locations are specified in Table 5-1 and Figures S.l-l, 5.1-2. The meterological tower is shown in Figure 5.1-1. The.

location is shown as"TLD'ocation 17. The Radiological Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New York 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. These 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/Q may be dropped from the program after October 31 of that year.

~ Ef 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'or 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 QC 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

- ~ 'amma 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 v'$

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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-,iare..based.;,on. ANSI Standard.N545,';~..-.>

'", section 4;3."-'" TLDs are'efined as phosphors packaged for Field use.>,'n regard to the detection capabilities for thermoluminescent dosimeters, only one determination is required to evaluate the 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 4

i,'~ "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

'ield cycle. The..average, of the relative'standard" deviations of, the responses shall be less than 3.0%. h total of at least 4 TLDs shall, be evaluated.

f} III l 4 e

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. For 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 'nergy 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

" 'di'fferent -orientations;

• To"accomplish this,-the, TLD -shall. be.,rotated through at least two perpendicular planes. 'he response averaged-over all directions shall not differ from the response obtained in the standard calibration position by more than 1(C. A total of at least 4 TLDs shall be evaluated.

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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'oisture 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 regular plastic bag by more than 10X. A total of at least 4 TLDs shall be evaluated for each condition.

'."5;3".8.- "a'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.

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TABLE l-l R VALUES FOR THE NINE MILE POINT UNIT 1 FACILITY apj i ADULT TOTAL BODY TEEN LIVER NUCLIDE 89 R~i {MREM/YR-Cx 2.05 E 3

,I" N/A Sr 90 4.37 E 1 N/A Sr 134 Cs 1.89 E+ 0 2.35 E + 0 137 Cs 1.12 E + 0 1.78 E + 0 58 6.47 E 4 2.87 E 4 Co 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 H

Cr-51 4.05 E 6 N/A Fe-59 3.01 E 3 8.03 E 3 Zn-65 1.09 E-l 2.37 E - 1 Zr-95 1.69 E - 7 2.53 E 7 I-131 3 '4 E 4 6.65 E 4 I-133 3.53 E 5 1.22 E 4 Cs-136 2 '3 - 1 E 3.80 E 1 Ba-140 3..92 E-5 7.81' 7 Ce-141 5.49 E 9 5.17 E - 8

'e-55 3.47 E - 4 .1.60 E 3 Ni-63 3.41 E 3 7.46 E 3

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TABLE 1-2 PARAMETERS FOR THE LIQUID EFFLUENT PATHWAY REFERENCE PARAMETER VALUE (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-ll 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 I

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Ak.

TABLE 2-1 Average Energy Per Disintegration ISOTOPE E mev/dis ~Ref EBmev/dis(4 5Ref)

Ar-41 1.294 (3) 0.464 (3)

Kr-83m 0.00248 0.0371 Kr-85 0.0022 0.250 Kr-85m 0.159 0.253 Kr-87 0.793 1.32 Kr-88 1.95 0.377 Kr-89 2.22 (2) 1.37 (2)

Kr-90 '2. 10 (2) 1.01 (2)

Xe-131M 0.0201 0.143 Xe-133 0.0454 0.135 Xe-133m 0.042 0.3.9 Xe-135 0.247 18'.64 0.317 Xe-135m 0.432 0.095 Xe-137 0. 194 Xe-138 l. 0.611 (1) ORNL-4923, Radioactive Atoms Su lement I, M.S. Martin, November 1973.

(2) NEDO-12037, "Summary of Gamma and Beta Emitters and Intensity Data"; M.E.

""', ". Meek, R.S. 'Gilbert, January 1970. (The. average energy..was computed from

-'the maximum energy using. the ICRP

..assumption used in this reference).

II equation,. not the .1/3 value (3) NCRP Report No. 58, "A Handbook of Radioactivity Measurements Procedures"; 1978 (4) The average energy includes conversion electrons.

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TABLE 3-1 Critical Receptor Dispersion Parsmetersa For Ground Level and Elevated Releases ELEVATED ELEVATED GROUNDe GROUNDe LOCATION DIR MILES D~/m-2 D/I/Dm~

Residences E (98O) 1.4 1.8 E-07b 5.2 E-09b 4.02 E-07 8.58 E-09 Dairy Cows SE (1300) 2.6 2.2 E-08c 7.0 E-10c 6.00 E-08 1.64 E-09 Milk Goats E (88') 7.9 1.3 E-08c 1.6 E-10c 2.57 E-08 6.10 K-10 Meat Animals ESE (115 ) 1.8 5.1 E-08c 1 7 E 09c 1.16 E-07 3.54 E-09 Gardens E (97m) 1.8 1.0 E-07c 3.5 E-09c 2.53 E-07 5.55 E-09 Site Boundary ENE (67 ) 0.4 2.4 E-06bDd 4.4 E-08cDd 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 land-based sector (ENE). (C.T. Main, Rev. 2)

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

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TABLE 4-1 DOSE FACTORS POR NOBLE GASES Gamma Air Beta Air Dose Factor Dose Factor Mi Ni BIZ d mrad m Radionuclides pCi-yr p Ci-yr Kr-83m 1.93E+01 2.88E+02 Kr-85m 1.23E+03 1.97E+03 Kr-85 1.72E+01 1.95E+03 Kr-87 6.17E+03 1.03E+04 Kr-88 1.52E+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 4.75K+03 Xe-139 5.28E+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 CPR Part 50, Appends.x I," dated October 1977, page 1.109-21.

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e TABLE 4-2 R VALUES COW'S MILK INFANT 2

md~rem/ r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3" 2.408 03 2.40E 03 2.408 03 2.40E 03 2.408 03 2.408 03 Cr 51 7.468 04 2.178 06 1.06804 4.878 04 4.478 04 Mn 54 4.548 06 7.368 06 2.008 07 4.44E 06 Fe 55 1.458 07 6.918 06 8.438 07 5.448 07 2.668 07)

Fe 59 7.218 07 8.748 07 1.05E 08 5.418 07 Co 58 2.888 07 2.888 07 1..158 07 Co 60 1.11E 08 1.128 08 4.71E 07 Zn 65 5.268 09 9.638 09 3.32E 09 1.148 10 5.53E 09 Sr 80 1.708 08 1.228 08 5.948 09 Sr 90 1.798 10 Se758 08 7.018 10 Zr 95 5.588 02 3.92E 05 3.238 03 7.878 02 Be48E 02 I 131 6.928 08 5.628 07 1.348 09 1.57E 09 1.848 09 5.178 ll I 133 7.918 06 4.578 06 1.85E 07 2.708 07 3 '78 07 4.918 09 CH 134 3.598 09 9 '5E 07 1.908 10 3.558 10 9.14E 09 3.758 09 Cs 136 1.038 09 4.19E 07 9.37E 08 2.768 09 1.10E 09 2.258.08 Cs 137 2.378 09 1.048 08 2.858 10 3.348 10 8.968 09 3.638 09 Ba 140 5.948 06 2.838 07 1.158 08 1.158 05 2.74E 04 7.038 04 Ce 141 1.448 03 6.30E 06 2.008 04 1.228 04 3.76E 03 em~rem/ r uCi/m

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ThBLE 4-3 R VhLUES COM'S MILK CHILD 2

m~~remj r QCi-sec NUCLIDE T. BODY CI-TRhCT BONE LIVER KIDNEY THYROID LUHC H 3> 1.58E 03 1.58E 03 1.58E 03 1.58E 03 1.58E 03 1.58S 03)<

Cr 51 4.71B 04 2.50S 06 7.14E 03 2.61E 04 4.77E 04 Mn 54 2.87E 06 9.04E 06 1.08B 07 3.02S 06 Pe 55 1.15E 07 6.85E 06 6.97E 07 3.07E 07 2.09E 07 Pe 59 4.52E 07 9.45B 07 5.61E 07 9.08E 07 2.63E 07 Co 58 1.77E 07 3.37E 07 5.77S 06 Co 60 6.81S 07 1.28E 08 2.31E 07 Zn 65 4.10E 09 1.16S 09 2.47E 09 6.59E 09 4.15E 09 Sr 89 8.93E 07 1.21S 08 3.13E 09 Sr 90 1.63B 10 8.68E 08 6.44$ 10 Zr 95 3.56B 02 4.17E 05 1.82S 03 4.00E 02 5.72E 02 I 131 3.66E 08 5.73E 07 6.40E 08 6.44E 08 1.06E 09 2.13E ll I 133 4.11S 06 4.38E 06 8.78E 06 1.09E 07 1.81E 07 2.02E 09 Cs 134 4.09E 09 1.05B 08 1.18E 10 1.94E 10 6.01E 09 2.16E 09 Cs 136 8.53E 08 4.63E 07 4.80S 08 1.32E 09 7.07S 08 1.05E 08 CQ 137 2.52B 09 1.07B 08 1.79E 10 1.71E 10 5.57B 09 2.00S 09 Ba 140 3.27E 06 2.84B 07 5.60E 07 4.91E 04 1.60E 04 2.93E 04 Ce 141 7.47B 02 6.28E 06 1.01E 04 5.03E 03 2.21E 03

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TABLE 4-4 R VALUES COW'S MILK TEEN 2

m~~rciml e uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG 8 3> 1.00E 03 1.00E 03 ,

1.5&E 03 1.00E 03 1.00E 03 1.00E 03 1.00E 03 Cc'1 2.31E 04 3.88E 06 5.06E 03 1.2&E 04 3.30E 04 Mn 54 1.43B 06 1.4&E 07 1.20E 06 2.15E 06 Fe 55 4.59E 06 8.52B 06 2.7&E 07 1.97E 07 1.25E 07 Pe 59 2.1&E 07 1.34E 08 2.42E 07 5.65E 07 1.7&E 07 Co 5& &.10E 06 5.21E 07 3.78E 06 Co 60 3.35E 07 1.94E 08 1.49E 07 Zn 65 2.04E 09 1.85E 09 1.26E 09 4.3&E 09 2.&OE 09 Sr 89 3.62E 07 1.50E 08 1.26E 09 Sr 90 9.42E 09 1.07E 09 3.81E 10 Zr 95 1.70E 02 5.70E 05 7.83E 02 2.47E 02 3.63E 02 I 131 1.98E 08 7.31E 07 2.64B 08 3.69B 08 6.36E 08 1.0&E ll I 133 1.87E 06 4.64B 06 3.61E 06 6.13E 06 1 0&E 07

~ 8.56E 08 Cs 134 5.60E 09 1.50E 08 5.12E 09 1.21E 10 3.83E 09 1.46E 09 Cs 136 5.62B 08 6.73E 07 2.13E 08 8.37E 08 4.55E 08 7.1&E 07 Cs 137 3.44E 09 1.40E 08 7.42E 09 9.87E 09 3.36E 09 1.30B 09 Ba 140 1.5&E 06 3.5&E 07 2.32E 07 2.84E 04 9.65E 03 1.91E 04 Ce 141 3.14E 02 7.83E 06 4.10E 03 2.74E 03 1.29E 03

• miami 3

uCi/m ll I pl x

g5.i J

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

md~rem/

uci-sec NUCLIDE T. BODY GI-TRACT "

SONS LIVER KIDNEY THYROID LUNG H 3~ 7.69E 02 7.69S 02 7.69E 02 7.69E 02 7.69E 02 7.69E 02 Cr 51 1.32E 04 3.32E 06 2.91S 03 7.90E 03 1.75E 04 Mn 54 8.25E 05 1.32E 07 4.32E 06 1.29E 06 Pe 55 2.52E 06 6.21E 06 1.57E 07 1.08E 07 6.04E 06 Fe 59 1.25E 07 1.09B 08 1.39E 07 3.26E 07 9.10B 06 Co 58 5.03B 06 4.56B 07 2.24E 06 Co 60 1.93E 07 1.65B 08 8.77E 07 Zn 65 1.18S 09 1.65E 09 8.21E 08 2.81E 09 1.75E 09 Sr 89 1.97B 07 1.10E 08 6.85E 08 Sr 90 6.62E 09 7.80S 08 2.70E 10 Zr 95 9.72E 01 4.55E 05 4.48E 02 1.44B 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 5.06B 08 Cs 134 5.74E 09 1.23E 08 2.95E 09 7.02E 09 2.27E 09 7.54E 08 CQ 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 9.25S 03 Ce 141 1.71E 02 5.78E 06 2.24E 03 1.51E 03 7.02E 02

>m~rsml r uci/m

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~,J

/

TABLE 4-6 R VALUES GOAT'S HILK INFANT 2

mm~eeml e uCi-sec NUCLIDS T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3~ 4.90E 03 4.90B 03 4.90S 03 4.90E 03 4.90E 03 4.90E 03 Cr 51 8.95B 03 2.61E 05 1.28E 03 5.84B 03 1.14E 04 Mn 54 5.45E 05 8.83E 05 2.40E 06 5.33S 05 Fe 55 1.89S 05 8.98E 04 1.10E 06 7.08E 05 3.46B 05 Fe 59 9.37E 05 1.14B 06 1.36E 06 2.38E 06 7.03B 05 Co 58 3.45B 06 3.45E 06 1.38E 06 Co 60 1.34E 07 1.35E 07 5.65S 06 Zn 65 &.31S 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 Ol 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 5.89S 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 3.30B 09 6.74E 08 CQ 137 7.10S 09 3.13E 08 8.55E 10 1.00E 11 2.69E 10 1.09E 10 e

Ba 140 7.13E 05 3.40E 06 1.38E 07 1.38E 04 3.29S 03 8.50E 03 Ce 141 1.72E 02 7.57E 05 2.40E 03 1.46E 03 4.52E 02 em~eeml e 3

uCi/m 0

ql I

4i

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r L OFT l g 1

I ~

N

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

m~~raml 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

~

3.23E 03 3.23E 03 Cr 51 5.65E 03 3.00B 05 8.57E 02 3.14E 03 5.73E 03 i

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 2.72E 05 Fe 59 5.88B 05 1.23E 06 7.29E 05 1.18E 06 3.42E 05 Co 58 2.12E 06 4.04E 06 6.92E 05 Co 60 8.17E 06 1.53E 07 2.77E 06 Zn 65 4.92S 08 1.39E 08 2.97B 08 7.91E 08 4.98E 08 Sr 89 1.87B 08 2.54B 08 6.56S 09 Sr 90 3.43E 10 1.82E 09 1.35E ll Zr 95 4.27E 01 5.01S 04 2.18S 02 4.80E 01 6.87E 01 I 131 4.39E 08 6.88E 07 7.68E 08 7.72E 08 1.27S 09 2.55E ll I 133 4.93E 06 5.25B 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 6.47E 09 Cs 136 2.56S 09 1.39E 08 1.44E 09 3.96E 09 2.11E 09 3.14E 08 Cs 137 7.57E 09 3.21B 08 5.36E 10 5.13E 10 1.67E 10 6.01E 09 Ba 140 3.92E 05 3.41E 06: 6.72E 06 5.89E 03 1.92E 03 3.51S 03 Ce 141 8.97E 01 7.54E 05 1.21E 03 6.04E 02 2.65E 02

• m~rrmj r uCi/m V

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r 1

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ThBLE 4-8 R VhLUES GOhT'S MILK TEEN 2

m~~rmm/

uCi-see NUCLIDB T. BODY GI-TRhCT BONE LIVER KIDNEY THYROID LUNG H 3" 2.04E 03 2.04E 03 2.04E 03 2.04E 03 2.04E 03 2.04E 03 Cr 51 2.77S 03 4.66B 05 6.07E 02 1.54E 03 3.95E 03 Mn 54 1.71E 05 1.77E 06 8.64E 05 2.58E 05 Fe 55 5.97B 04 1.11E 05 3.61E 05 2.56E 05 1.62E 05I4 Fe 59 2.83E 05 1.74B 06 3.14E 05 7.34E 05 2.31E 05 Co 58 1.04B 06 6.25E 06 4.63E 05 Co 60 4.02E 06 2.32E 07 1.78E 06 Zn 65 2.45E 08 2.22S 08 1.51E 08 5.25E 08 3.36E 08 Sr 89 7.59S 07 3.16E 08 2.65E 09 Sr 90 1.98B 10 2.25E 09 8.81B 10 Zr 95 2.04E 01 6.84E 04 9.40E Ol 2.97E 01 4.36E Ol I 131 2.38B 08 8.77E 07 3.17B 08 4.43E 08 7.63E 08 1.29E ll I 133 2.24S 06 5.57E 06 4.34B 06 7.36E 06 1.29E 07 1.03E 09 Cs 134 1.68E 10 4.50E 08 1.54E 10 3.62E 10 1.15E 10 4.39E 09 CH 136 1.69S 09 2.02E 08 6.38E 08 2.51B 09 1.37E 09 2.15E 08 Cs 137 1.03E 10 4.21E 08 2.22E 10 2.96E 10 1.01E 10 3.91E 09 BR 140 1.80E 05 4.30E 06 2.97E 06 3.41E 03 1.16E 03 2.30E 03 Ce 141 3.77E Ol 9.39E 05 4.92E 02 3.28E 02 1.55E 02

• m~ram/

uCi/m3 (1

II J h

0 J

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

mm~eeml uci-sec NUCLIDE T. BODY GI-TRACT e BONE LIVER KIDNEY THYROID LUNG H 3" 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 Cr 51 1.59E 03 3.99E 05 3.49E 02 9.48E 02 2.11E 03 e

Mn 54 9.89E 04 1.59E 06 5.19E 05 1.54E 05 Fe 55 3.28E 04 8.07E 04 2.04E 05 1.41E 05 7.85E 04I Fe 59 1.62E 05 1.41E 06 1.80E 05 4.23E 05 1.18E 05 Co 58 6.03E 05 5.46E 06 2.69E 05 Co 60 2.32E 06 1.98B 07 1.05E 06 Zn 65 1.42E 08 1.97E 08 9.85B 07 3.14E 08 2.10E 08 Sr 89 4.13E 07 2.31E 08 1.44E 09 Sr 90 1.39E 10 1.64E 09 5.67E 10 Zr 95 1.17E Ol 5.46E 04 5.37E.Ol 1.72E 01 2.70E Ol I 131 1.43E 08 6.59E 07 1.74E 08 2.50E 08 4.28E 08 8.18E 10 I 133 1.26B 06 3.71B 06 2.37E 06 4.13E 06 7.21E 06 6.07E 08 Cs 134 1.72E 10 3.69E 08 8.85E 09 2.11E 10 6.82E 09 2.26E 09 Cs 136 1.06E 09 1.68E 08 3.75E 08 1.48E 09 8.23E 08 1.13E 08 Cs 137 1.10E 10 3.25E 08 1.25E 10 1.68E 10 5.70E 09 1.89E 09 Ba 140 1.01E 05 3.18E 06 1.54E 06 1.94E 03 6.59E 02 1.11E 03 Ce 141 2.06E 01 6.94B 05 2.68E 02 1.81E 02 8.43E Ol em~rem/

uCi/m Pt r

1 C

i

TABLB 4-10 R VALUES MEAT CHILD 2

m~~reml r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3< 2.36B 02 2.36B 02 2.36E 02 2.36E 02 2.36B 02 2.36E 02 Cr 51 4.07E 03 2.16E 05 6.17E 02 2.26E 03 4.12B 03 Mn 54 1.09E 06 3.45B 06 4.11E 06 1.15E 06 Fe 55 4.74B 07 2.84B 07 2.89B 08 1.53E 08 8.66B Fe 59 1.42E 08 2.97B 08 07)'.26E 1.76B 08 2.85E 08 07 Co 58 2.39B 07 4.56E 07 7.82E 06 Co 60 1.09E 08 2.05E 08 3.70E 07 Zn 65 3.72B 08 1.05E 08 2.25E 08 5.99E 08 3.77E 08 Sr 89 . 6.55E 06 8.87E 06 2.29$ 08 Sr 90 1.52E 09 8.08B 07 6.00E 09 Zr 95 2.48E 05 2.91E 08 1.27B 06 2.79E 05 3.99E 05 I 131 4.64E 06 7.29E 05 8.14B 06 8.19E 06 1.34B 07 2.71B 09 I 133 1.55B-01 1.66E-Ol 3.32B-01 4.11B-01 6.85B-01 7. 63E-01 Cs 134 1.67E 08 4.26E 06 4.81B 08 7.90B 08 2.45E 08 8.78B 07 Cs 136 1.35B 07 7.34B 05 7.60E 06 2.09E 07 1.11E 07 1.66E 06 Cs 137 1.04B 08 4.43B 06 7.39B 08 7.07B 08 2.30E 08 8.29E 07 Ba 140 1.22B 06 1.06B 07 gelOE 07 1.84E 04 5 '8E 03 1.10E 04 Ce 141 7.57E 02 6.36B 06 1.02B 04 5.10E 03 2.24E 03 em~rem/ r 3

uCi/m J'

WP wp,t g.

yl 4

'I p

TABLE 4-11 R VALUES MBAT TEEN 2

m~~reml r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG 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 074 Fe 59 8.95E 07 5.48B 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 2.43B 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 6.14B 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 1.16B 07 1.40E 06 4.41E 06 1.73E 07 9.44E 06 1.49E 06 CB 137 1.86B 08 7.59E 06 4.01E 08 5.34B 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 '7E 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

CAr 4r

TABLE 4-12 R VALUES MEAT ADULT 2

md~rem/ r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3~ 3.27E 02 3.27B 02 3.27E 02 3.27B 02 3.27E 02 3.27E 02 Cr 51 3.26B 03 8.21E 05 7.19E 02 1.95K 03 4.33$ 03 Mn 54 8.98E 05 1.44E 07 4.71E 06 1.40E 06 Fe 55 2.98E 07 7.34B 07 1.85E 08 1.28E 08 7.14B 07].

Fe 59 1.12E 08 9.73B 08 1.24E 08 2.92E 08 8.16E 07 Co 58 1.95E 07 1.76E 08 8.68E 06 Co 60 8.87B 07 7.56E 08 4.02E 07 Zn 65 3.06E 08 4.27B 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 2.07B 08 7.17E 09 Zr 95 1.94E 05 9.07E 08 05 '.92E 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-Ol 3.34E-01 2.14E-01 3.72E-01 6.49B-01 5.46E 01 CH 134 6.68E 08 1.43E 07 3.43E 08 8.15K 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 1.28B 07 4.83E 08 6.61E 08 2.24E 08 7.46E 07 Ba 140 9.01B 05 2.83E 07 1.38K 07 1.73E 04 5.87E 03 9.89E 03 Ce 141 4.96E 02 1.67B 07 6.47E 03 4.38E 03 2.03E 03

• m~reml r uCi/m A

T

ThBLE 4-13 R VhLUES VSGSThTION CHILD 2

md~rem/ r uCi-sec NUCLIDE T. BODY GI-TRhCT BONE LIVER KIDNEY THYROID LUNG H 3* 4.048 03 4.048 03 4.048 03 4.048 03 4.048 03 4.048 03 Cr 51 1.168 05 6.15E 06 1.768 04 6.448 04 1.188 05 Mn 54 1.73E 08 5.44E 08 6.498 08 1.82E 08 Fe 55 1.258 08 7.50E 07 7.638 08 4.05E 08 2.298 0814 Fe 59 3.17E 08 6.628 08 3.938 08 6.36E 08 1.848 08 Co 58 1.928 08 3.668 08 6.278 06 Co 60 1.118 09 2.088 09 3.768 08 Zn 65 1.70S 09 4.818 08 1.03E 09 2.748 09 1.738 09 Sr 89 1.03E 09 1.408 09 3.628 Se 90 3.498 ll 1.868 10 10'.388 12 Zr 95 7.448 05 8.718 08 3.808 06 8.358 05 1.208 06 I 131 8.168 07 1.288 07 1.438 08 1.44E 08 2.368 08 4.758 10 I 133 1.678 06 1.788 06 3.578 06 4 '28 06 7.368 06 8.218 08 Cs 134 5.408 09 1.388 08 1.568 10 2.568 10 7.93E 09 2.848 09 Cs 136 1.438 08 7.77E 06 8.048 07 2.218 08 1.18E 08 1.768 07 Cs 137 3.528 09 1.50E 08 2.488 10 2.398 10 7.78E 09 2.808 09 Ba 140 1.618 07 1.408 08 2.768 08 2.428 05 7.878 04 1.448 05 Ce 141 4.75E 04 3.998 08 6.42E 05 3.20E 05 1.40E 05 em~rem/ r 3

uCi/m F4-elf/

0 c4

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'~

e ThBLE 4-14 R VhLUES VEGEThTION TBEN 2 .

m~~eeml e uci-sec NUCLIDE T. BODY GI-TRhCT HONE 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 Hn 54 8.79E 07 9.89E 08 4.43E 08 1.32E 08 Fe 55 5.13E 07 9.53B 07 3.10E 08 2.20E 08 1. 40B 08I E 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 8.68B 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 ll Zr 95 3.68E 05 1.23E 09 1.69E.06 5.35B 05 7.86E 06 I 131 5.77E 07 2.13B 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 CQ 136 1.13E 08 1.35B 07 4.28E 07 1.68E 08 9.16E 07 1.44E 07 Cs 137 4.90B 09 2.00B 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

• deem/e uCi/m3 S>>

I I r

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1 P

t S

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tAa J

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0

e TABLE 4-15 R VALUES VEGETATION ADULT 2

m~~reml r uCi-sec NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG N 3< 2.28E 03 2.28S 03 2.28E 03 2.28E 03 2.288 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 3.05S 08 9.09E 07 Fe 55 3.22S 07 7.91E 07 2.00E 08 1.38S 08 7.69E 07 <

Pe 59 1.12E 08 9.75S 08 1.24E 08 2.93E 08 8.17E 07 Co 58 6.71E 07 6.07E 08 2.99E 07 Co 60 3.67E 08 3.12$ 09 1.66E 08 Zn 65 5.77S 08 8.04E 08 4.01E 08 1.28E 09 8.54E 08 Sr 89 2.87E 08 1.60E 09 1.08E 10 Sr 90 1.64E ll 1.93S 10 6.70E ll Zr 95 2.51S 05 1.17E 09 1.16E 06 3.71E 05 5.82E 05 I 131 6.61E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 I 133 1.12S 06 3.30E 06 2.11E 06 3.67E 06 6.40E 06 5.39E 08 Cs 134 8.83E 09 1.89E 08 4.54E 09 1.08S 10 3.49E 09 1.16E 09 CB 136 1.19E 08 1.88E 07 4.19E 07 1.66E 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 8.40E 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.$ 1E 05 6.07E 04 em~rem/

uCi/m3

~ Ot kt l

4!

a

TABLE. 4-16 R VALUES INHALATION - INFANT I~ram/ r 3

uCi/m NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3 6.468 02 6.468 02 6.468 02 6.46E 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 4.98E 03 9.98E 05 Pe 55 3.338 03 1.098 03 1.978 04 1.178 04 8.698 04 Fe 59 9.468 03 2.478 04 1.358 04 2.368 04 1.018 06 Co Ss 1.82E 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 5.138 04 1.938 04 6.258 04 3.248 04 6.468 05 Sr 89 1.148 04 6.398 04 3.978 05 2.038 06 Sr 90 2.598 06 1.318 05 4.OSS O7 1.128 07 Zr 95 2.038 04 2.178 04 1.158 05 2.788 04 3.10E 04 1.758 06 I

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 CQ 134 7.448 04 1.338 03 3.968 05 7.02E 05 1.908 05 7.958 04 Cs 136 5.288 04 1.438 03 4.828 04 1.348 05 5.638 04 1.178 04 Cs 137 4.548 04 1.338 03 5.4SS OS 6.118 05 1.728 05 7.128 04 Ba 140 2.898 03 3.83E 04 5.59E 04 5.598 01 1.348 Ol 1.598 06 P Ce 141 1.998 03 2.158 04 2.778 04 1.668 04 5.248 03 5.168 05

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CC>

4r

ThBLB. 4-17 R VhLUES INHhLhTION CHILD masm/r uCi/m 3 NUCLIDB T. BODY CI-TRhCT BONE LIVER KIDNEY THYROID LUNG H 3 1.128 03 1.128 03 1.128 03 1.128 03 1.128 03 1.128 03 Cr 51 1.548 02 1.088 03 2.43E 01 8.538 01 1.708 04 Mn 54 9.508 03 2.298 04 4.298 04 1.008 04 1.57S 06 Fe 55 7.778 03 2.878 03 4.748 04 2.528 04 1.118 05 Fe 59 1.678 04 7.068 04 2.078 04 3.348 04 1.278 06 Co 58 3.168 03 3.438 04 1.778 03 1.10E 06 Co 60 2.268 04 9.618 04 1.318 04 7.068 06 Zn 65 7.028 04 1.638 04 4.258 04 1.138 05 7.138 04 9.948 05 Sr 89 1.728 04 1.678 05 5.998 05 2.158 06 Sr 90 6.438 06 3.438 05 1.018 08 1.478 07 Zr 95 3.698 04 6.108 04 1.908 05 4.178 04 5.958 04 2.238 06 I 131 2.728 04 2.848 03 4.808 04 4.808 04 7.878 04 1.628 07 I 133 7.688 03 5.478 03 1.668 04 2.038 04 3.378 04 3.848 06 CQ 134 2.248 05 3.848 03 6.50E 05 1.01S 06 3.308 05 1.218 05 CQ 136 1.168 05 4.178 03 6.508 04 1.718 05 9.538 04 1.458 04 CQ 137 1.288 05 3.618 03 9.058 05 8.248 05 2.828 05 1.048 05 Ba 140 4.328 03 1.028 05 7.398 04 6.478 Ol 2.118 Ol 1 748 061*

Ce 141 2.898 03 5.658 04 3.92E 04 1.958 04 8.538 03 5.438 05 V

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TABLE 4-18 R VALUES INHALATION TEEN m~mami m 3

uCi/m NUCLIDE T. BODY GI-TRACT BONE LIVER KIOMEY THYROID LUNG H 3 1.27E 03 1.278 03 1.27E 03 1.278 03 1.278 03 1.27E 03 Cr 51 1.358 02 3.008 03 3.078 Ol 7.498 01 2.098 04 Mn 54 8.398 03 6.678 04 5.108 04 1.278 04 1.988 06 Fe 55 5.548 03 6.398 03 3.348 04 2.388 04 1.248 05 Fe 59 1.438 04 1.788 05 1.598 04 3.698 04 06 '.538 Co 58 2.778 03 9.518 04 2.078 03 1.348 06 Co 60 1.98E 04 2.598 05 1.518 04 8.718 06 Zn 65 6.238 04 4.668 04 3.858 04 1.338 05 8.63E 04 1.248 06 Sr 89 1.25E 04 3.718 05 4.348 05 2.41E 06 Sr 90 6.678 06 7.648 05 1.08E 08 1.65E 07 Zr 95 3.158 04 1.498 05 1.458 05 4.588 04 6.738 04 =-2.688 06 I 131 2.648 04 6.488 03 3.548 04 4.908 04 8.39E 04 1.468 07 I 133 6.218 03 1.038 04 1.218 04 2.05E 04 3.59E 04 2.928 06 CH 134 5.488 05 9.758 03 5.028 05 1.138 06 3.75E 05 1.468 05 Cs 136 1.378 05 1.098 04 5.148 04 1.938 05 1.108 05 1.778 04 Cs 137 3.118 05 8.478 03 6.698 05 8.478 05 3.048 05 1.218 05 Ba 140 3.518 03 2.288 05 5.468 04 6.698 01 2.248 Ol 2.038 06 Ce 141 2.168 03 1.268 05 2.848 04 1.898 04 8.878 03 6.13E 05 k~

I

+vs.

f1

TABLE 4-19 R VALUES INHALATION ADULT m~rem/ r 3

uC1/m, e

NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3 1.268 03 1.268 03 1.268 03 1.268 03 1.26E 03 1.268 03 Cr 51 9.998 Ol 3.32E 03 2.288 01 5.948 Ol 1.448 04 Mn 54 6.29E 03 7.72E 04 3.958 04 9e838 03 1.408 06 Fe 55 3.948 03 6.038 03 2.468 04 1.708 04 7.218 pg c Fe 59 1.058 04 1.888 05 1.178 04 2.778 04 1.018 06 Co 58 2.078 03 1.068 05 1.588 03 9.278 05 Co 60 1.488 04 2.848 05 1.158 04 5.968 06 Zn 65 4.658 04 5.348 04 .3.248 04 1.03E 05 6e898 04 8.638 05 Sr 89 8.718 03 3.498 05 3.048 05 1.408 06 Sr 90 6.09E 06 7.218 05 9.91E 07 9.59E 06 Zr 95 2.328 04 1.508 05 1.078 05 3.44E 04 5.418 04 1.778 06 I 131 2.058 04 6.278 03 2.528 04 3.578 04 6.12E 04 1.198 07 I 133 4.518 03 8.878 03 8.638 03 1.488 04 2.588 04 2.158 06 Cs 134 7.278 05 1.048 04 3.728 05 8.478 05 2e878 05 9.758 04 Cs 136 1.108 04 1.17E 04 3.908 04 1.468 05 8.558 04 1.208 04 Cs 137 4.27E 05 8.398 03 4.788 05 6.208 05 2.22E 05 7.518 04 Ba 140 2.568 03 2.188 05 3.908 04 4.908 Ol 1.678 Ol 1.278 06 Ce 141 1.53E 03 1.20E 05 1.998 04 1.358 04 6.25E 03 3.618 05 lpga TABLE 4-20 R VALUES GROUND - ALL AGE GROUPS 2

M ~modem/ e

>>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 PYf 4

4 0 1 etr"'

g'i,~

Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 Type of *Map (Env.

Sample Location Collection Site Pro am No.) Location Radioiodine and Nine Mile Point Road 1.8 mi 8 88' Paxticulates (air) North (R-1)

Radioiodine and Co. Rt. 29 & Lake Road (R-2) 1.1 mi 8 104'SE Particulates (aix')

Radioiodine and Co. Rt. 29 (R-3) 1.5 mi 8 132'E Particulates (air)

Radioiodine and Village of Lycoming, NY (R-4) 1.8 mi 8 143'E Particulates (air)

"Radioiodine and 5 . Montario Point Road (R-5) 16.4 mi 8 42'E Particulates (air)

Direct Radiation (TLD) 6 North Shoreline Area (75) 0.1 mi 8 5' Direct Radiation (TLD) 7 North Shoreline Area (76) 0.1 mi 8 25'NE Direct Radiation (TLD) 8 Noxth Shoreline Area (77) 0.2 mi 8 45'E Direct Radiation (TLD) 9 North Shoreline Area (23) 0.8 mi 8 70'NE Direct Radiation (TLD) 10 JAP East Boundary (78) 1.0 mi 8 90' Direct Radiation (TLD) ll Rt. 29 (79) 1.1 mi 8 115'SE Direct Radiation (TLD) 12 Rt. 29 (80) 1.4 mi 8 133'E

.Direct Radiation (TLD) 13 . Miner Road (81) 1.6 mi 8 159'SE Direct Radiation (TLD) 14 Miner Road (82) 1.6 mi 8 181' Direct Radiation (TLD) 15 Lakeview Road (83) 1.2 mi 8 200'SW Direct Radiation (TLD) 16 Lakeview Road (84) 1.1 mi 8 225'W Direct Radiation (TLD) 17 Site Meteorological Tower (7) 0.7 mi 8 250'SW Direct Radiation (TLD) 18 Energy Information Center (18) 0.4 mi 8 265'

~p - See Figures 5.1-1 and 5.1-2 I"

Ill I

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+!8 W+

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

Type of *Map (Env.

Sample Location Collection Site Program No.) Location Direct Radiation (TLD) 19 North Shoreline (85) 0.2 mi 8 294'NW

'Direct Radiation (TLD) 20 ,North Shoreline (86) 0.1 mi 8 315'W Direct Radiation (TLD) 21 North Shoreline (87) 0.1 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'adiat'ion"(TLD) 25 Rt. 51A (91) 4-8 mi 8 156'SE Direct Radiation (TLD) 26 Maiden Lane Road (92) 4 4 mi 8 183' 6 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

'irect 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'NE (NA) ~ not applicable

• Map ~ See'igures 5.1-1 and 5.1-2 J

gv

• l 1

1 I

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SI

Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1

'Continued)

Type of *Map (Env.

Sample Location Collection Site Pro ram No.) Location Shoreline Sediment 40 Sunset Bay Shoreline (NA) 1.5mi 8 80 E Fish 41 NMP Site Discharge Area (NA) 0.3 mi 8 315'W and/or Fish 42 NMP Site Discharge Area (NA) 0.6 mi 8 55'E Fish  : 43, Oswego Harbor Area (NA) 6.2 mi 8 235'W Milk 44 Milk Location 850 9.3 mi 8 93' Milk 45 Milk Location 87 5.5 mi 8 107'SE 46 Milk Location 816 5.9 mi 8 190' Milk 47 Milk Location 865 17.0 mi 8 220'W Food Product 48 Produce Location 86** 1.9 mi 8 141'E (Bergenstock) (NA)

Food Product 49 Produce Location 81** 1.8 mi 8 96' (J. Parkhurst) (NA)

Food Product 50 Produce Location 82<+ 1.9 mi 8 101' (Vitullo) (NA)

Food Product 51 Produce Location 85*" 1.5 mi 8 114'SE (C.S. Parkhurst) (NA)

Food Product 52 Produce Location III3** 1.6 mi 8 84' (C. Narewski)

Food Product .Produce'Location 84** 2.0 mi 8-110'SE (S. Morris) (NA)

Food Product (CR) 54 Produce Location 87*" 15.0 mi 8 223'W (Mc Millen) (NA)

1 d

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

Type of *Map (Env.

Sample Location "

Collection Site "'-"Pro am No.)

. Location Food Product '(CR) 55  :. Produce. Location /$ 8"* 12.6 mi 8 225'W (Denman) (NA)

Food Product 56 Produce Location /P9"* 1.6 mi 6 171' (O'onnor) (NA)

'ood Product 57 .. Produce Location 810** 2.2 mi 8 123'SE (C. L ~on) (NA)

Food Product 58 Produce Location 811** 2.0 mi 8 112'SE (C. R. Parkhurst) (NA)

Food Product 59 Produce Location 812*" 1.9 mi 8 103 ESE 6 (Johnson) (NA)

C I

• Map See Figures 5.1-1 and 5.1-2

• • Food Product Samples need not necessarily be col1ected from all listed locations. Collected samples will be of the highest calculated site average D/Q.

(N/A) ~ not applicable CR ~ Control Result (location)

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APPENDlX A DOSE PARAMETERS FOR lODlNE 131 AND 'l33 g PARil CULATES AND TBlTl liras 0

t t 4, HAh TI 's 't 0+49& iA w.jL <rW$ sa'~

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DOSE PAiUMETERS FOR IODINE - 131 AND - L33i PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for I-L31, I-L33, particulates, and tritium..The dose parameter, Ri, was-calculated using the methodology outlined in NUREG&L33 and

'Regulatory "Guide L.L09,.Revision'L.-. 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

~ i . . groups indicates, the maximum potential exposure occurs, i.e., the critical receptor. The inhs1ation 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-misc, the grass-cow mQ3c, grass-caveat, and vegetation pathways 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:

i,,:.',. ,,'i,, A.L,Inhalation Pathwa R. ~ K(BR) (DFA )

where~+

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

a'constant of unit conversion:

K'BR)

- 10 6 pCi/qCi;

~ Breathing rate of the receptor of age group a, 3

(units M /yr);

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

89-

mr

~~t W:L~ e4q1 t+,i A

~; The breathing rates (BR) for the various age groups, as given in Table a

E-5 of Regulatory Guide 1.109 Revision 1, are tabulated below.

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

Infant 1rr00 Child 3700 Teen 8000

- Adult 8000 lnhalatron dose factors (DFA.) for the various age groups are given in i a "Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.

A.2 Ground Plane Pathwa I( R = K'K"(SF) DFG i (Im XI t

)

where:

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

K' . a-constant of unit conversion:

6 10 pCI/uCi; K" = a constant of unit conver sion; 8760 hr /year;

g4 I

l.l 0

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

t = the exposure ttme, sec; 4

8 4.73 x 10 sec (IS years);

DFC., = the ground plane dose conversion factor for radionuclide i; (units = mr em/hr per pCi/m~)

e'F

= the shielding factor (dlmensionless);

I A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Cuide 1.109 Revision 1. A tabulation of DFGi values is presented in Table E-6 of Regulatory Guide 1.109 Revision l.

A.3 Grass-Cow or Coat-Milk Pathwa

-Altf + B. (1-e Ri K'QF U F (DFL ) e Y I

t th

.(I-f fs,) r(tm' + Bi (lm ) e

~

p Y

E i

where:

M =

R dose factor for the cow milk or goat milk pathway, for each l

" "'" 'identified radionuctide ' 'for the organ of interest, (units mrem/yr per uCi/sec per m )

l 5~"

0

~4

~-

I

~ e 'u e'

t@I E

K' a constant of unit conversion:

6 10 pCi/uCi QF = The cow's or goat's feed consumption rate, (units = Kg/day-wet weight)

U

'he receptor's milk consumption rate'or-age group a, (units =

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~);

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

r = fraction of deposited activity retained on cow's feed grass:

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

'he radiological decay -constant for . radionuclide- -

i, (units = sec );

the decay constant for removal of activity on leaf and plant.

surfaces by weathering

~7 5.73 -x 10 sec .,(corresponding to a 10 day. half-life);,

~ rtl~q n

a

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);

8. concentration factor for uptake of radionuclide 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*;

f = "

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 Cuide 1;109 Revision 1, the value of f was considered unity in lieu of s

site-specifi .information. The value of f was. 0.667 .based upon, an 8-month grazing period. ,p Table A-1 contains the appropriate values and their source in Regulatory Cuide 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 = KsKts'F Q U (DFL ) 0 75(0 5/H)

'l 4 Aw vv ml'ls k%k

}cher.e:

M RT 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; l0~ 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.

,.OC Other values are given above. A value of H of 8 grams/meter3, was used in lieu of site-specific information.

A.O Crass-Cow-Meat Pathwa

-Xitf + B. (1m Y XE Ri K'~F ap " i Kith tb e 8 iv (l e ) e (l-f f ) r(lm +

s E i

R~ = dose factor for the meat ingestion pathway for radlonuclide i for l -2

.-any organ:ofinterest, (units."- mrem/yr per uCi/sec per m ):.

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

=S>>

1 1 I\

l f, ~ 4 l~ g )AVIPA I I Q f 4 t g} e V

~~

@Ok>

t

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

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

the, transport time-. from .,harvest.. to, animal " consumpt>on.

(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 concentration of tritium in meat is based on airborne concentration rather than deposition. Therefore, the Ri is based on X/Q.

R T = K'K"'FfQ U (DFLi) (0.75(0.5/H) J where:

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

,. All terms are defined above.

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

(I f

i h.% 4.

4g Ale

-X.tb XitL t R.,

"-K'(DFL ) U f e lm +

E l a L Y PX1 I

t -A t

'ith r(l-e B (le ib )

S )

Ua fge Y A hi where:

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

K' a constant of unit conversion; 6

l0 pCi/uCi:

L =

Ua the consumption rate of fresh leafy vegetation by the recepCor in age group a, (units = kg/yr);

fL = the fraction of the annual intake of fresh leafy vegetation grown locally; fg the fraction o f the annual intake of sto red vegetation grown locally

~ .. tL ... =., Che.,average . time between, harvest --of leafy vegetation and its consumption,. (units = sec);

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

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

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

~ 7I All other factors are defined above.

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

In lieu of site-specific data, values for fL and;f of, 1.0'nd '.76,

'respectively, were used in the calculation. These values were obtained from Table E-15 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:

R = K'K" U fL + U f (DFL ) 0.75(0.5/H)

T a ag where:

V dose factor for the vegetable pathway for tritium for any RT organ of interest, (units = mrem/yr per uCI/m~).

Atl other terms are defined in preceeding sections.

Jl R

~~i'o

[5 4 ~ 1 Ik 4 I

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

QF (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 Y (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 (DFL ) (mrem/pCi) Each radionuclide Tables E-11 to E-14 F (pCl/day per pCi/liter) Each stable element Table E-1 (cow)

Table E-2 (goat) t (seconds) 0.73 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

(liters/yr) 330 infant Table'-5 330 child Table E-5 000 teen Table E-5 310 adult Table E-5 t (seconds) 2.59 x 1066 (pasture) Table E-15 5.'18 x 10 (stored feed)

Bl(pCl/Kg (wet weight) Each- stable element Table E-I per pCi/Kg (dry soil))

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

II g

+~a~

A'

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TABLE A-2 a

Parameters for the Meat. Pathway Parameter Value Reference (R . Cuide 1.109 Rev. 1)

',1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/Kg per pCi/day) Each stable element Table E-1 U (Kg/yr) 0 infant Table E-5 ap 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 Y (kg/m~) 0.7 Table E-15 Y (kg/mi) 2.0 Table E-'lS tb (seconds) x 10 (15 yr) Table E-15 t (seconds) 1.73 x 10 (20 days) Table E-15

.t (seconds) 7.78 x 10 (90 days) Table E-15

, a t .-(seconds) 2.59 x 1066 (pasture) Table E-15 5.18 x 10 (stored feed) 1 QF (kg/day) 50 Table E-3 B., (pCi/Kg (wet weight Each stable element Table E-1 per pCi/Kg (dry soil))

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

/'i 4)e"

'C

TABLE A-3 Parameters for the Vegetable Pathway Parameter 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-10 U (kg/yr) - infant 0 Table E-5

- child 26 Table E-5

- teen %2 Table E-5 A

adult 64 Table E-5 U

S (kg/yr)- - infant 0 Table E-5

~

child 520 Table E-5

- teen Table E-5

- adult 630'20 Table E-5 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) ~

.."Oe73 x 10.8 (15 yr) Table E-15 P(Kg(dry soil) /m~) 2ao Table E-15 81~ (pCl/ Kg (wet weight) Each stable element Table E-1 per pCi/kg (dry soll))

.100-

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APPENKNX- B

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(b) NMP2 Stack (height is 430')

(c) JAFNPP Stack (height is 385')

(d) NMPl 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) Meteorological Tower

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(j) Training Center (k) Energy Information Center Additional Information:

- NMP2 Reactor Building Vent is located 187 feet above level

-. JAFNPP Reactor and Turbine Building Vents are located ground 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

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

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APPENDlX.-C Df SPERSt ON CALCULATION TABt.ES

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TABLE C-1 D/q TABLE (ANHVAL METEOROLOGICAL DATA) NNP UN I T +I S I AC K CORREC'IKD FOR OPEN TERRAIN RECIRCULATION tooeeryoooooottooo ~ to RELATIVE DKPDST jlDH PER UNlT AREA INt ~ -2) AT FIXED POINTS SY DOLINWIND SECTORS I

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DISTANCES IH NILES 2.50 3.00 3.50 4.00 4.50 5.00 5.50 8 > 1.040E-0$ 3.2608-09 I.RC<E-I9 6.78)E-IO 4.2R9K-IO 2.$ 9)E-IO 2. I 0 I E-10 I 594E-Io 1.25IE-IO I.OOTE-IO 8.878E-II SSl) 1.806E-OB'3.78TE-09 I.<CRE-O'9 T.STIE-IO 4.9RIE-IO 3.367E-IO R.<<TE-I 0 1.856E-IO ).45<E-)0 I . I CSE-I I 9.5S6E-II SD 7. 14 I E-09 R. 4038-09 9. 852E-I ~ 5. 413K-I I 3.459E-IO 2.390E-IO 1.747E-IO 1.328E-IO 1.042K-IO 8.366K-II C.SSIE-II LJSD 2. 169K-09 V. C32E" I I 3. 843K-I I I . 835E-I I I.IS<E-IO 8.260E-II 6. 07<E- I I 4.638E-II 3.645E-II 8.932E-)l e.<oef-ll

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SE R. 122K-OS C.R5RE-O'9 R.43OE- ~ I ).895K-09 8.035E-IO 5.169E-IO 3.957E-I0 2.9'92E Io 8.338E-IO I . 875E-I I 1.536E-IO SSE 1.073E-OS 3.302E-09 I.RTSE I9 C.83RE-IO <.R5IE lo R.90IE-IO R. 105K" 10 1.596E-IO 1.25)E-IO I.OOCE Io 8. 861E- I I DIRKCT)OH DISTANCES )N tl)LES FROtl SITE 6.00 6.50 7.00 7.50 8.00 8.50 9.00 9.50 10.00 IS. 00 eo.oo 8 6.9)TE-II 5.999E-II 5.RISE-II <. VISE-I I 4.832E-II 3.BRIE-II 3. <TOE- I I 3.167K-ll 2.904K-ll 1.533E-)l 9. 66<E- I R SSH S.OOIE"II 6.93<E-II C. I 8 I E" I I S. 119E-I I <.SBCE-II 1.109E-I I <.OOIE-II 3.650E"II 3. 31 <E" I I 1.754K-II 1.099E-II Sl) 5.704E-II 4.963E-II 4.379K-II 3.896E"II 3.<92E-II 3. 149E-I I R.BS&E-II 2. 604K-I I 2.384E-II I . 2<RE- I I 7.742E-IR llSD 8.000E-II I . 749f" 'I I I . 514E- I I 1.373K-II I . 23)E- I I I. I I OE-I I I.OOTE"11 9.183K-IR 8.412E-IR 4.393E-IR e.V<6E-le D 2.27<F.-II 1.988E-II 1.754E-I) 1. 56 IE-I I 1.39SE" I I I . 26 I K- I I I . I <<E" 11 1. 0<RE-I I 9.5<6E-I2 4.9&SE-IR 3.097E"le DHIJ 1.5<VE-I I 3.973E-II 3.505E-I) 3.)ISE-II R.794E-II R. 5 I '9E- I I 2. 28<E-I I R.OSRE-II 1.906E-II 9.907E-)2 6.168K-le Nl) 1.056E-'10 9.127E-II B. I52E-I I 7. )63E-I I 6.<I VE-I I S.VSSE-II 5.2<5E-II 4.779E II 4.375E-II 2.866E-II I . 105K" I I NNll 9.565E-II 8.256E-II 7.886E-)I C.<83E" I I 5.81OE-I I 5.240E-)l 1.753K-ll 4.333E-II 3.968E-II R.OCCE-II ).286K"ll N I . 0<BE-I I 9.092E-I) S. IR3E-I I 7. 139E-I I 6.39SE-II 5.770E-II 5.834E-II 1. 77 I E- I I 4.369E"II 8.8'16E-II I . 4 I BE- I I NNE 5.23)E-II <.SSSE-II 4 ~ Ibf II 3.573E-II 3. 80 IE-I I R.BS6E-II

                                                 ~                                                 2. 616E- I I 2.38<E-II      8.)822-11 1.130E         II    T.OIRE IR NE           5.879E-II     5.083E-II 4.<seE-)i 3.985E-)l 3.568E-II 3. el <E-11                e. 912K- I I e.&52E-II      R. 125E- I I I.R45E-)l 7.663E-IR KNE              I . 78 IK-II  1.535E-IO 1. 35<E-I ~ I.ROSE-IO 1.079K-IO 9.788E-II               8. 8 I BE- I I 8. 03<E- I I 7.352E-II 3.799E 11 8.35')E-II f           R. 385 E-10   8.050E-IO I . BOSE-I ~ 1.60BE-IO I .<<Of-l 0 1.298E-IO             I . 176E- I  I 1. 072E-10   9.805E-II S. 054K-I I 3. 119E-I I ESE              1.555E-I   I 1.336E"10 I . 179K-)O I.0<BE"10 9.390E-II 8. 16<E- I I             7.678E"II 6.989E-II         6.395E-II 3. 30 I E- I I 8.040E-II Sf            I . RBOE-10   I . I OSE" 10 9. 75 I E- I I 8.677K-II 7.776K-II 7.01<E-II        6.3&RE-)l 5.799E-II         5.31)E-II 8.765E-II I.TRRK-II SSE             6.903E-II     5.979E-II 5.e79E-I) <.TOIE-I I 4.R)6E-I I 3.80&E-II                3.455E-)1 3. 153E-I I       2.890E-II 1.522E-II 9.569E-IR
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TABLE C-2 D/g TABLE (GRAZING SEASON METEOROLOGICAL DATA) HHP UNIT <4 I STACK CORRECTED FOR OPEH TERRAIN RECIRCUL AT)ON ~ tttt1 ~ 10 ~ 00 ~ ~ 10ttrO ~ I RELAT)VE DEPO817)ON PER UN)T AREA )Nil-Rf AT FIXED POINTS BY DOUIIUIHD SECTORS 0 ~ ~ 00 ~ ~ 11I ~ t ~ ~ 1 ~ OtttO D)RECT)ON DISTANCES 1N I)ILES FRON 81'TE .50 '1.00 1.54 2.00 R.50 3.00 3.50 <.00 <.50 5.00 5.50 8 1.079E-OS 3.3e<E-09 I.RTOE-09 6.7<BE-IO <. )82K-IO R.8<BE-IO 2.06<E-IO 1.565E-IO I.RRTE-IO 9.876E-II S.)ROE-II SSll ).030K-OS 3.R<RE-O'9 I.RTOE- ~ 9 C.B<9E 10 <.RSTE-Io 2.93&E-IO R.)36E-)O ).622E-IO I.eVef-lo 1.023E-IO 8.<OIE-II SU 5.999E-09 1.97<K-ot S. 47< E-I 4 <<.C<E-IO 2.839E-IO 1.96<E-)0 I.<36E-IO 1.093K-I ~ 8.580E-II 6.898E-II 5.65SE-II USU 1.658E-09 5;t39K-10 R.SRCE-I ~ I.<3RE-I ~ 9.253E-)l 6.<63E-II <.757E-II 3.63SE-II 2.859E-II 8.300E-)l 1.88&E-II I.sVRE-09 6.736E-IO R. 918E-I ~ I . C6RE-I 0 I.OVSE-'Io 7.5<BE-I'I 5.5&OE-II <.2<9E-II 3.3<OE-II R.&86K-II R.ROOE-II UNU <.629E-09 1.579E- ~ 9 C.CTTE-I ~ 3.7&OE-I4 2.<ISE-IO 1.683K-IO 1.236K-IO 9.<23E-II 7.39SE-II 5.9<5E-II <.867E-II Nil ).586E-OS <.VBRE- ~ '9 1.90&E"09 ).032E-09 6.<68E 10 <<.30E"lo 3.217K-IO 2. <37E-10 1.906E-IO 1.5RSE-IO I.RSIE-I0 Hkli 1.556E-OB <.658E-09 I . 8 I SE-09 9.78SE-IO 6.055E-IO <.129E-Io 2.993E"10 R.265E-IO I . 77ef- I o 1.<eeE-IO I . I &5E-10 1.63)K-OS 5.076E-09 R.03)f-ot I . 105E-09 C.953E-IO <.776E-10 3.<TVE-IO e.&39E-lo 2.067E-IO 1.659E-14 1.360E-IO

                                                                  <.899E-14 3.IRTE-!0 R.l&VE-IO 1.585E-IO l.eo&f-lo 9. <5)K" I I 7.585E II 6.205E-II N

NNE 6.522E-09 2.113E-49 S.BORE-I ~ NE 7.276E-09 R.Reef-ot 9. I < IK-14 5.028E-14 3.18SE-IO 2.)9<E-IO 1.598E-)0 I .Rlef I 0 9.<TBE-II 7.59IE-I I 6.1')9E-Il EHK 2.9SSE-OS 8.799K-O'9 3.<89E-09 I.BBOK-09 I. 176E-09 8.036E-)0 5.829E-IO <<. IRE-)4 3.<<SE-IO 2.76<E"lo 2.26 )K-I 0 E 3.971E-OB I. 1<3E-08 <<.CIE- at 8.375K-ot I.<73E-09 I.OOIE-09 7.236E Io 5.<63E Io <.263E-IO 3.<I<E IO 8.798E-IO ESE 2.30SE-OS C.595E-09 8,553E- at 1.3538-09 $ .361K-IO 5.672E-IO <.09<K-IO 3.089E Io e. < I of- I o I . 930E-10 1.579K-)4 SE 1.880E-OB 5.557E-49 R.l<3E-09 I. 138E-09 7.0<5E-IO <.789E-IO 3.<6<E-IO R. & I tf-10 2.0<BE-IO I . 6<<E-10 1.3<TE-IO SSE 1.120E-OB 3.3&IE"09 I.RTTE-49 C. 7<3E-I ~ <.16)E-Io 2.82<K-IO 2.0<RE-IO 1.5<SE-)0 I.RIOE-IO t.TRSE-II 7.'993E-II DIRECT)OH D)STANCES IH H)LES 6.00 6.50 7.0 ~ 7.50 8.00 8.50 9.00 9.50 10. 00 )5.00 20.00 FROH SITK 8 6.796E-)l 5.88<E II 5.197E-II <.Ceif-Ii <.153E If 3.750E-II 3.<06f-ll 3. 149E-1 I 2.85)E-)l 1.508E-II 9. 52) f-I2 SSll 7.0)SE-II 6.090E-II 5.377K-II <.78TE-I I <.29<E-II 3.876E-II 3. 518E- I I 3.210E-II 8.9<3E-II 1.5<9E-)l 9.7< IE-12 SII <. 7)RE-I I <. IOSE-I I 3. CR3E-I I 3.22<K )1 8.890E-I) 8.60TE-)l 8.366E-II 2.157E II 1.976E-)f 1.03<K-II 6. <67E-12 I)SU I . 57 I E-I I 1.375E-II I .RI <E-'I I 1.080E-II 9.682K-le S.73<K-IR T.tesf-ie 7.2RTE-)8 6. 62)E-IR 3.<65E-IR 2.)TOE IR U 1.830E-II 1.603E"II I.<I<E II 1.858E-II I . 0 I TK-I I 9.220E-IR 8.<05E-IR 7. 698E-)8 <. ~ IRK-)2 R.so<f-le UHU <.0<9E-II 3.536E-II 3.)ROE-II 8.77&E-II I.IRTE"II'.<BVE-)l 2.2<3E-II 2.03<K-II 1.85<E-II I . 698E- I I 8. 838E-I 2 5.509K-IR NU I . 0< IE" I 0 9.007E-II 7.9<TE-II 7.069E-II 6.33<E"II 5.71)E-fl 5.)TSE-II <.7)9K-II <.320E-ll R. 2< IE-11 1.392K-I) NHll 9. 71<E-I I 8.397K-II 7.<IIE-II C.595E-II 5.91)E-II 5.332K-ll <.837E-II <<.IIE"II <.0<OE-II R. IOSE-f I 1.3)5E-I I

     .H                 1.133K 10 9.828K-II 8.673E-II             7.717E-II   C.t)TK-II 6.239E-I) 5.659E"II             5.164K-ll <.726E-If R.<65f-ll 1.538E-I I Hkf                  5.158E-II <<.9)K-11 3.tCRE-II              3.52<E-II   3.157K"II R.B<6E-)l 2.580K-II             2.35)E-II R. 152E"ll I . I ) 6E-I) 6.930E-IR NE                 5. I <6E-I I <<.CRE-II 3.935E-II           3.<99E-II   3. 133E- I I 2.823K-ll e.ssBE-)l          R.370E-II 8.13)E-II 1.097E-II 6.766E-IR ENE                  1.882E"10 1.627E-IO I.@35E-I4 I.eTTE-io               I. I <<E-I 0      1.03IE-10 9.350E-II B.seof-ll 7.799E-II <.0<2E-II 2.508E-II
                                                                                                                                                  <.957E-ll 3.069K-lf E                 8.323E-)0 R.OOIE-IO I.TCSE-I ~ I . STOE-14            1. <OTE-10 I.R&SE-IO I . 150K-I 0 1.0<VE-IO 9.58TE-II 1.31<E-I 0 I . 13)E-I ~ 't.tSRK-II 8.879K-II          7.95SE-I) 7. ITRE-I I 6.542E-II 5.985K-II 5.<2<E-II                 2.808K-ll 1.7<OE-II ESK SE                 I . IR<E-10 9.702E-II 8.56<E-II 7.622E-II             C.833E-II 6. I &5E-I I 5.593K-ll 5. )0 I E-I I <.673E-)1            e.<<ef-l I 1.585E-II SSE                 6.68<K-II 5.77<K-II S.ottf-ll <.5<OE-II               <.473E-ll 3.677K-ll 3.338K-ll 3.0<7K-II R.793E"II I . <73E-I I t.ecSE-IR
                                                                                            -115-

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          <<I

TABLE C-3 x/q (hHNUAL HETEOROLOGICM. DATA) NNP UIIIT O'I STACK ND DECAY, UNDEPLETEQ CDRREC1EO f QR QPEII 1fRRhlN RECIRCULATION 4 hlttIUAL AVERACK Ctlt/0 IBKC/NETER CUSEOl DISTANCE IN NILES BEC10R .500 I.ooo I.50 e.ooo e.5oo 3.ooo 3.500 4. 000 4.500 5.'000 5.500 8 07 '9.910K-DS 4.R64K-OS 2.558E-OS

                                                        '.I07E I.BDRE-OB l.386E-DB I.I24E-OB       '9.449K 09 S. I44E-09 T.ISBE-D'9 C.3885-09 SSM          4.880K-OT I.209E-OT 5.I33E-OS 3.052K-OS              2. I32E-08 I.626K-DB I.309E-OB      I'92E-08 9.34BE-O9 S.I66E-09 7.244E-09 BM         3.851K-or 9.486K-os 4.o46f-os R.463E-OS              I.766E-OS l.317E-DB I.IRBE-OS       9.545E-09 8.260K-ot   7.276K-ot 6. 4t Yf-09 MSM          R.o<<f-or 4.984K-os e.092E-os I.R73E-OS               9.289K-ot 7.436E-09 6.265K-09       5 444E-09   4.829E-D9 4.349K"09   3. 96 IE-09 M        2.802K-or 6.13IE-DS R.TSTK-OS I.678E-OS              l.e<<f-oo 9.590K-09 B.DOBE-09        6.908E-09 6.09IE-09   5.451E-09   4.94SE-09 MNM          4.206E"Dl I.028E-OY 4.3RCE-DS 2.6lrf-os              l.s'YDK-DB 1.45fE-OS I. I92E-OB     I OOBK-OS B.1I9E"09
                                                                                                             ~                   1.611E-09   6.85IE-09 NM         I . I I tf-06 2.695K-OY 1. DBTE-OT C.292E-OS         4.340K-OS   3.292E-DB 2.643K-OO 2.203E-OS I.885E-DB       l.644K-OB   I . 457K -08 IttIM        l.062E-DC R.555K-OT I.ORYE"01 5.89SE-OB              4.04IE-OB   3.052K-OB 2.445E-OB 2.03'IE-08 I.743K-OB      I.SRRE"08 I . 35 IE-08 II       I. I I3E-06 2.705K-OT I. IOIE-07 C.422E-OB           4.459K-DB   3.403E"08 2.747E-DB e.3olE-oa I . 9 7TE-08    I . 732E-08 I.540E-OB ttttE        6.664E-DT I.6llf-or 6.5COE-OS 3.859E-OS              R.7IIE-OS   2.092E-DB l.706K-OB I.44IE-OS I.247E-OS       I.099E-OB 9.8ICE-09 NE         7.774E-DY I.855E-OY 7.430K-OB 4.275E-OS              2.939K-OB   R.RRBE-OB I.Y92E-OB I.498E-OB I.RBYE-oa       I.leaf-os   l.004E-OS Etlf         I.390E-DC 3.316E- ~ 7 l.3CTK-DT 7. 817E-08           5.38IE-OB 4.036E-OS     3.ROSE"08   R.644E-DB R.e42f-oa I.942K-os I .1 I OE-08 E        l.550E-06 3.789K-O7 I.54lf-~ 7 8.87DE-DS             6.036K-OB 4.501E" 08    3.564E-OS   2.930E"08 R.477E-OB R.140K-OS I.SSOE-OS ESE          8.385E-OT 2.044K-OT 8.386K-OS 4.86RE 08              3.323K-OS 2.486K-os    'I . 961K-OS I.CITE-OS I.366K"08 I.I79E-DS I.035K"08 Sf         5:921E-or I.459K-or 6. lace-oa 3. Cl 9f-08           R.559K-DB I.936K-OB     I.544E-OB   I . R75E-08 I.OSIE-OS '9.365f-ot 8. 24 I E- 09 5SE          3.641E-07 S.'l98f-08 3.7CRK-OS e.eoof-oa I.593E-OS I.225E-OS                 9.926E-09   8.333K-ot Y.I73E-09 6.300E-09 5. 6 I TE" 09 hlttlUAL AVERACK   Cttl/0      IBEC/METER CUBKQl                        Q  !STANCE Itl tllLES SEAR INC            6.000           6.500      7 ~ Oo ~      7.500       S.DDD      8.500        9.00D       9.500     I0.000    I5.000      eo.ooo 5.765K-09       5.27TK-O'9 4.89'TE-Ot 4.568E-D9 4.275K-09 4.0I4E-09 3.780E-09 3.570E 09 3.380E-09 2.269K-O'9 l.689E-09 BSM          6.503E-09       5.'923E-09 5.413K-ot 5.080E-09       4.735K-09 4.429E-09 4.I55E"09 3.9IOE"09 3.C90E-09 R.414E-09           l.764K-09 CM        5.863E-09       5.363K-09 4.975K-ot 4.633K-09        4.330E"09 4.060E-09 3.BISE-09 3 CDOE-09 3.403K-09 2.254K 09           1.659K-09 UOM          3.640E-09       3.384E-ot 3.I84K-09 3.005K-O'9       2.842K-ot 2.695K"09 2.560K-09 2.436E"09 2.323E-09 I.C35E 09           l.e47E-09 It       4.5R9E-09       4.l'trf-09 3.939K-09 3.708K-D9       3.500K-O'9 3.3I2K-09 3.I4IE-09 2.985E-09 2.842E-09 I.983E 09          I.506E-09 MtlM         6.IBIE-09       5.653E- ~ 9 5.242K-O'9 4.88IE-09     4.562E-D9 4.277E-09 4.022E-09 '3.792K-09 3.585E-09 2.375E-09          1.748E-09 IIM        I.306E-DB        I.189E-OS I.DOTE-OS I.OIBE-DS       9.417K-09 8.858E-09 8.307K-09 Y.BI3E"09 7.368E-D'9 4.SORE 09          3.498E-09 tMIM         I.RI3K-OS        I. I05E-OB I.ORRE-DS 9.496E-O'9     8.859E-09 S.R94f-ot 7.7'tOE-09 7.338E 0'9 6.93IK"09 4.573E-09         3.362E-09 tl       l.386E-DS        I.265K-.OS I. ITIK-08 I.089K-DS     I.OITE-OB 9.526E-09 8.953E-09 8.437E Dt 7.972E-09 5.210E-09           3.876E-09 tttlf        8.86tf-09       S.IRRE-09 7.542K-09 1.0'33E-0'9      6.'582K-09 6. I 79E-09 5.BISE-09 5.493E-09 S.I98E-09 3.474E"09        2.570E-09 NE         9.039E-09       S.R63E-09 T.CC4K-09 7. I4IE-09       6.68IK-09 6.273E-09 5.908K-09 5.580E-09 5.2$ 4f-ot 3.5&6E-09          2.666E-09 Ettf         I.525K-OB        l.38IE-DB I.RTDK OS l.l74E-OB       l.090K-OS I . DICE-08 9.5075-0'I 8.924E-09 8.40RE-09 5.4Rtf-09        3.950E-09 E        1.673E-OS        I.5IRE-OS l.38SK-OS l.28IE-OS       l.lsrf-oa I. ID5E-08 I.O'33E"08 9. CYBE-09 9.099E-09 5.SIDE"09        4. I 91E-09 EBE          9   l99f-09     8.308E-Ot T.CISE- ~ 9 7.023E-09      6.505E-09 6.050E-09 5.648E-09 5.R90E"09 4.970E"09 3.I59E-09           R.ersf-ot SE.       7.3442-09       6.644K-ot C.'IDRK Ot S.C33f-o'9      5.223K-09 4.863K-09 4.544E-09 4.P59K 09 4.004E-09 R.S60E-09           I.852K-09 SOE          5.065E-09       4.633E"09 4.Rtlf-ot 4.004E-09        3.744E-09 3.5I3E-09 3.306E-09 3. I I 9E-09 R.95IE-09 I.OCOK 09        I 4h7F 44

~ ~ K xl

                %t I 4 ~ ~
                       ~ a <<g I
          ~ ~ 4- lk  E JJ p II

                                                                             'j.'ABLE  C" 3 (ANNUAL HETEIJROLOGICAL DATA)

NNP UIIIT Dl STACK NO DECAYS UNDKPLETED CORRECIED FOR OPEII 'IERRAIN IIECIRCULATTON AIIHUAL AVERACK Ctll/0 I SEC/NETER CUBED I Dl slhttCK lH tl1 LES SECTOR .500 I - tt 00 I 500

                                                      ~        e.ooo      R.540         3.040        3.540      4.000      4.500       5.'040     5.500 8        4. I OTE-07 'S.'914E-08 4.264K-OS R.558E"08 1.842E-OB 1.386K"48 1.124K-OS 9.44'JK-49 8. 144K-09 7 . 158K-09 6.388E-09 SSM           4.OBOE-DT I.R09E-DT 5.133E-OB 3.052E-OS P..I32E-DB I.L26E-DB I 309K-os t.o'JRE-08 9.348K-09 S.I&6E-09 7.244E-09 SM         3.851K'-OT 9.4S6E-OS 4.046E-DS 2.463E"08 1.76&E-OS t.311K-os t. IRDE-OS 9.54SE-Dt S.e&oa-ot 7.216K-ot 6.4tTE-09 IJSM          2.014K-DT   4.9s4a-os e.otea-os         I.R73K-OS 9.289K"49       7.436E-09 L.P&SE-49 5.444E-OS 4.829E-09 4.349E-09 3.9&IE-09 M        2.802E-OF   C.73IE-OS R.TSTE-OS 1.678E-OS I .Rl IE" OO            9.590E-09 B.oosa-ot 6.948K-OS 6.09IE"09 5.457E-09 4.948E-09 MNM           4.20&E-07   1.028K"07 4.3RLE-OS R.LITE-OS I . STDE-OS             1.45&E-OB I 192K-08 I.DOBE-DB 8.119E-09 7. 671E-09 6.851K-OS JJM        I. 119E-06  R.69SE-OF I.DBTE"07 C.R92E-OB 4.340E-DB               3.292E-OB   2.643E-DS   2.203E-OB I.BSSE-OB 1.644E-OS     1.457E-OB IRIIJ         1.062K-O&   2.555E-OF 1.027K-OT 5.898E-DS 4.041E-OS               3.452E-DB   2.445K-DS   2. 031E-08 1.743E"08 1.522K-DB 1.35IE-DB tl       1.113E-06   2.705E-OT I.IDIE-OT 6.422E-OB 4.459E-DB               3.403E-DS   P.. 741K-08 2.341K-OS  1.911E-DS   1.732K-DB 1.540E-OB ttttE         6.664E-DT   1.61IE-DT IL.5COE-OB 3.859E-OB 2.71IE-OB              2.092E-OB   1.706K-OB   1.441K-oe  1.247E-OS   1.09'lE-08 9.816E"09 ttE        7,774E-OT   I.SSSE-OT 7.430E 08 4.275K-OS 2.939E-DB               e.RRSE-oe   1.192K-OB   1.498E-OS  I.RSTE-OS   I. Ieea-08 1.004K-OB Etta          1.394K~06   3.376K-DT I.'3CTE-07 7 . 8TTE-08 5.3SIK-OS            4.036E-OB   3.245E-DS   2.&44E-48  2.242K-OB   1.942K-OS I.TIDE-OS E        1.55OE-DC   3.78$ E-OT 1.54IE-DT S.STDK-DB 6.036K-DB              4.SOTE-DS 3.564E 00     2.93OE-OS  2.477K-DS   2. 14oa-os I.BSOE-DS ESE           8.385K-OT   2.044E-07 8.38CE-DS 4.862K-OS 3.323E-OS               2.486K-os 1.96JE-DS     1.611E-DS  1.366E-DB   I. 179E-0$ '1.435E-DB SE         5.921E-OT   1.459E-DT 6. ISRE-08 3.67$ E"08 2.559K-OS             1.936E-DB I.s44a-os     I .RTSE-08 I.OBIK-OB   9.365E-09 8.24IE-DS SBF.          3.647E-ol   $ .798K-DB 3.1C2E-DB e.e64E-oe 1.593E-OB              1.225E-DB 9.926K-09     8.333E-DS  7. 173E-O'I 6.300E-09 5.611E"O'9 AtttlUAL AVEIJACK   Cttl/0 I SEC/tIE IER      CUBEDI                    DISTAIICK IN tIILES SEAR I JIC          6.400        6.500            1.000      7.5DO     .8.000         $ .500       94DO      9.500     14.000      15.000     RO.OOO 5.7&5E-09   5.217E-09        4.899E-09 4.568K-09 4.275E-09        4. 414E-09  3. TBOE-09 3.510E-0'9 3.380E-49    R.269K-09 1.689E-09 SSM           6.503E 09   5.923E-09        5.473E-09 5.OBOE-09 4.735E-DS        4.429E-09   4.155E-OS 3.9IDE-OS 3.690E-09      2.414E-09 1.764K-09 SM         5.863E"09   5.363K-09        4.STSE 09 4.633E-09 4.330K-09        4.060E-49   3.8IBK-O9 3 LODE-0$ 3.403K-09      2.254E-09 1.659K-09 IJSIJ         3.640E-09   3.384E-09        3.184E-09 3'.045E-0'9 2.842K-09      2.695E-49   2.560E-09 2.436E-DS 2.323E-09      1.635K-OS 1.247E-09 M        4.529E-09   4.191E"09        3.939E-09 3.TOBE-09 '3.504E-O'9      3.312E-49   3.141K"09 2.9$ 5E-DS 2.842E-09     1.983K-09 1.506K"0'9 IJIIM         6.18IE-O'I  5.653K-OS 5.24RE 0$ 4.88IE-49 4.5&2E"49               4 '77E-O'J 4 022K-Ot 3.192E-09 3.585E-OS       2.375E-OS  1.74BE-09 ttM         t.306K-o'8  l. Ieta-oe 1.091E-oe I.OIBE-OB 9. 417K-09             8. 858K" 09 B. 301E-D9 7.813E-O'9 7.3&BE-09 4.802K-09     3.498E"09 lt IIM        1.213K-OS I.tosa-oe I DRRE"08 $ .496E-09 8.859E-09
                                                  ~                                  S.R94E-09 1 790E-09 7.338K-09 6. 9'3 IE-09 4.513K-09      3.36RE-09 tl       1.386K-OB I.R&5E-.OS         I. ITIK OS 1.089E-OS 1.011K-OB 9.526K-09 8.953E-09 8.437E-OS 7.912a-ot s.eloa-ot               3.876E-O'9 NJIE          8.8&la-ot 8.122E"09 7.542E-09           7.033E-O'9 6.582E-49 6.119E-49 S.BISE-09 5.493K-09 5. 198E-09 3.414E-09             2.570E-09 ttE         9.039K"09 S.R63E-09 7.6C4E-O'9          7.14IE-09 6.6BIE-09 6.R13E-O'J S.tosa-49 5.580E-OS S,RD4E-09 3.566E-OS              R.6L6E 0'9 EHE           1.525E-os 1.3sta-os I.eloa-os           I . 174E-08 I.D90K-OS 1.416K-OB 9.507K-09 8.$ 24E-OS 8.402E-09 5.429K-09            3.950E-DS E        1.673E-OS I.stea-os 1.388E-DB           I.RBIE-OB I.IBTE-OS 1.105K-DB 1.033E-OB 9.67OE"0$ 9.099E-09 S.BIDE"09               4.191K-O'9 KBE           9  I'SSE-09 8.34BE-09 '1.618K 09        7.023K-09 6.505K-09 6.450K-09 5 64SE-09 5.290E"0$ 4.974E"09 3. 159E-09              R. 215E-09 SE         7.344E-OS 6.644E"Ot C.142E 0'9          5.633E-09 5.223E-49 4.863E-OS 4.544K-09 4.25$ E-OS 4.004E-09 2.560K-09              1.852E-DS SSE           5.065K-09 4.63]E-OS 4.291E 0$           4.004E-09 3.744E-09 3.513E-09 3.30&E-DS 3.119E"09 2.95IE-09 1.969K-09                  4avc-nn

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