Nuclear Regulatory CommissionITEM SUMMARY (Page 2 of 3) 2) A paragraph was added to Section 3.1.3, "Recombiner Discharge (Offgas) Monitor Setpoints" to reflect the Technical Specification

ITEM SUMMARY(Page 1 of 3)

DOCUMENT:

TITLE:

PRESENTER:

Unit 1 Offsite Dose Calculation Manual

Revision 12 to the Offsite Dose Calculation Manual

Elizabeth D. Thomas

EXECUTIVESUMMARY: Revision 12 to the Unit 1 ODCM was completed to

include commitments made to the NRC in the NMPCResponse, dated 1/15/93, to the Technical EvaluationReport prepared by EGRG Idaho under contract by theNRC (TER ¹EGG-PHY-10286). In addition, various textchanges were completed for clarification purposes to theEnvironmental Section 4.0 to ensure consistency withthe Unit 2 ODCM, and a typographical error wascorrected in Appendix B.

BACKGROUND: The Unit 1 ODCM contains the methodology andparameters to determine gaseous and liquid setpoints foreffluent streams, In addition, the Unit 1 ODCM containsdose and dose rate equations and parameters fordetermining compliance with 10CFR20, 10CFR50 and40CFR190, in accordance with the requirements of theUnit 1 Technical Specifications.

DESCRIPTIONCHANGE l<EYPOINTS: As a result of a Technical Evaluation Review completed

by EGSG Idaho, under contract with the NRC, thefollowing items were added to the Unit 1 ODCM:

1) A sentence was added to Section 2.1.4.2,"Simultaneous Discharges of Radioactive Liquids" tostate that simultaneous batch releases areprohibited per site radwaste and chemistryprocedures. (p. 5)

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9309070162 930827PDR ADOCK 08000220''R PDR'


2) A paragraph was added to Section 3.1.3,"Recombiner Discharge (Offgas) Monitor Setpoints"to reflect the Technical Specification (Section3/4.6.14, Table 4.6.14-2, Note C) requirement thatautomatic isolation of the condenser air ejectoroccurs if two channels are above the Hi-Hi alarmsetpoint or one channel is above the Hi-Hi alarmsetpoint and one channel downscale. Thisautomatic isolation is tested once per operatingcycle in accordance with N1-ST-C8, "OffgasRadiation Monitor Channel Function Test". (p. 13)

3) A paragraph was added to Section 3.2.1.1, "NobleGases", to state the site chemistry procedural(N1-CSP-M350, "Noble Gas Dose Calculations" ),actions taken if Noble Gas Dose Rates exceed 10%of the 10CFR20 limits. This was completed todemonstrate that Nine Mile Point Unit 1 hasprovisions to add their doses to Unit 2 andFitzpatrick doses to ensure the site 10CFR20 limit isnot exceeded. This is in place of using allocationfactors on alarm setpoints. In addition, a sentencewas added to state that Hi alarm setpoints are setat 50% of the dose rate limit to account fordetector inaccuracies and to ensure that theTechnical Specification site dose rate limit is notexceeded.(p. 18)

4) A sentence was added to Section 3.2.1.2, "Tritium,lodines and Particulates", to state the site chemistryprocedural (N1-CSP-M351, "Particulate Iodine andTritium Dose Calculations" ), actions taken if thedose rates exceed 5% of the site TechnicalSpecification limit. This was done to demonstratethat the dose contributions from Unit 2 andFitzpatrick are added to the Unit 1 doses to ensurethe Technical Specification site dose rate limit is notexceeded. (p. 20)

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5) The Section 4.0 was revised to add clarificationstatements to state that Technical Specification3.6.15.d required reports will include all significantdetails of the dose determination if radiologicalsampling and analyses are used to determine if thedose limits of 40CFR190 are exceeded. In addition,general text changes were made to Section 4.0 toensure consistency with the Unit 2 ODCIVI, and aTable 3-23 was added for clarification purposes topresent the parameters used in the dose calculationsin Section 4.0. These parameters were previouslyin the text of Section 4.0. (pp. 25-30, 65)

6) A typographical error was corrected in Appendix Bto change the site boundary distance from 1600mto 644m. This value of 644m was correctly used todetermine the plume shine parameters; however1600m was incorrectly typed in the examplecalculation.

ATTACHIVIENTS: The revised Unit 1 ODCM - pp. 5, 13, 18, 20, 25-30,65, 79.

TECHNICALREVIEWPERFORIVIED BY: Hugh Flanagan, Environmental Manager; Carl Senska,

Supervisor Unit 1 Chemistry; and Jack Torbitt, GeneralSupervisor Radwaste Operations.

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NINE MILE POINT NUCLEAR STATION

NINE MILE POINT UNIT 1

OFF-SITE DOSE CALCULATION MANUAL ODCM

DATE AND INITIALS

APPROVALS SIGNATURES REVISION 12

K. A. DahlbergPlant Manager Unit 1

C. D. TerryV.P. Nuclear Engineering

NIAGARA MOHAWK'POWER CORPORATION

003856LL

Unit 1 ODCMRevision 12June 1993

SUMMARY OF REVISIONS

PAQE

6/30/93Revision 12 EffectiveDATE

1g2i5g6i8i9i 11 13/15 18i21i 24'5'6 44'7

49'2-81,86-116

3i4i7i10i14g19i20i22i23i26 3545i46i50g51i82 85*29*64,77,78ii19i21i22Ai22Bi124i25i26i112iiiiiiiit12 16'8'8 40'5 47i52'5'9 89i92i93g97

129'1-93,95

3,4,21,92,95a-c10,16-20Si13i18i20i25 30i65i79

February 1987December 1987January 1988May 1988 (Reissue)May 27, 1988 (Reissue)February 1990

June 1990June 1992February 1993March 1993June 1993

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ODCM - NINE MILE POINT UNIT 1

TABLE OF CONTENTS

1.0

2.0

2 1

2.1 1

2 ~ 1.2

2. 1.3

2 ~ 1.4

2 '.4.12.1.4.2

2 '.4.32.1.4.4

2.1.4.52.2

2.3

2.3 '

3.0

3.1

3 '.13.1.2

3.1.3

3.1.4

3.1.5

3.1.5.1

3.1.5.23.1.5.3

INTRODUCTION

LIQUID EFFLUENTS

Setpoint Determinations

Basis

Service Water System Effluent Alarm Setpoint

Liquid Radwaste Effluent Alarm Setpoint

Discussion

Control of Liquid Effluent Batch Discharges

Simultaneous Discharges of Radioactive Liquids

Sample Representativeness

Liquid Radwaste System Operation'I

Service Water System Contamination

Liquid Effluent Concentration Calculation

Dose Determinations

Maximum Dose Equivalent Pathway

GASEOUS EFFLUENTS


Basis

Stack Monitor Setpoints

Recombiner Discharge (Off Gas) Monitor Setpoints

Emergency Condenser Vent Monitor Setpoint

Discussion

Stack Effluent Monitoring System Description

Stack Sample Flow Path — RAGEMS

Stack Sample Flow Path — OGESMS

Pacae

13

14

14

14

15

15

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TABLE OF CONTENTS(Cont'd)

3 1 ~ 5 '

3 '.5 '3 '.5.63.2

3.2 '

3.F 1.1

3.2.1.2

3.2.2

3 '.2 '3.2 '.23 '.2.33.3

3.4

4.0

4.1

4.2

4 '4.4

5.0

5.1

5 '5.3

Sample Frequency/Sample Analysis

I-133 Estimates

Gaseous Radwaste Treatment System Operation

Dose and Dose Rate Determination

Dose Rate

Noble Gases

Tritium, Iodines and Particulates

Dose

Noble Gas Air Dose

Tritium Zodines and Particulates

Accumulating Doses

Critical Receptors

Refinement of Offsite Doses Resulting FromEmergency Condenser Vent Releases

40 CFR 190 REQUIREMENTS

Evaluation of Doses From Liquid Effluents

Evaluation of Doses From Gaseous Effluents

Evaluation of Doses From Direct Radiation

Doses to Members of the Public Within theSite Boundary

ENVIRONMENTAL MONITORING PROGRAM

Sampling Stations

Interlaboratory Comparison Program

Capabilities for Thermoluminescent DosimetersUsed for Environmental Measurements

Pacae

15

16

16

16

17

18

19

20

21

22

22

23

23

25

26

27

28

31

31

31

31

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TABLE OF CONTENTS(Cont'd)

Table 1-1

Tables 2-1to 2-8

Average Energy Per Disintegration

~ Values for the NMP-1 Facility

Pacae

34

35

Table 3-1

Table 3-2

Table 3-3

Critical Receptor Dispersion Parametersfor Ground Level and Elevated Releases

Gamma Air and Whole Body Plume Shine DoseFactors for Noble Gases (B, and V,)

Immersion Dose Factors for Noble Gases

Tables 3-4to 3-22

Table 3-23

Table 5.1

Organ Dose and Dose Rate Factors (g)

Parameters for the Evaluation of Doses toReal Members of the Public from Gaseous andLiquid EffluentsNMP-1 Radiological Environmental MonitoringProgram Sampling Locations

46

65

66

Figure 5.1-1 Nine Mile Point On-Site Map

Figure 5.1-2 Nine Mile Point Offsite Map

Figure 5.1.3-1 Site Boundaries

70

71

72

Appendix A

Appendix B

Liquid Dose Factor Derivation (~)Plume Shine Dose Factor Derivation(B, and V)

73

76

Appendix C Organ Dose and Dose Rate Factors for Iodine — 131 6133, Particulates and Tritium (g) 80

Appendix D Diagrams of Liquid and Gaseous RadwasteTreatment Systems 90

003856LL -iii-Unit 1 ODCMRevision 12June 1993

1 ~ 0 INTRODUCTION

The Offsite Dose Calculation Manual (ODOM) provides the methodologyto be used for demonstrating compliance with the RadiologicalEffluent Technical Specifications (RETS), 10 CFR 20, 10 CFR 50, and40 CFR 190. The contents of the ODOM are based on DraftNUREG-0472, Revision 3, "Standard Radiological Effluent TechnicalSpecifications for Pressurized Water Reactors," September 1982;Draft NUREG-0473, Revision 2, "Radiological Effluent Technk.calSpeck.fications for BWR's g July 1979'UREG 0133, "Preparation ofRadiological Effluent Technical Specifications for Nuclear PowerPlants," October 1978; the several Regulatory Guides referenced inthese documentsg and, communication with the NRC staff.Section 5 contains a detailed description of the RadiologicalEnvk.ronmental Monitoring (REM) sampling locations.

Should it be necessary to revise the ODOM, these revisions will bemade in accordance with Technk.cal Specifications.

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Unit 1 ODCMRevisk.on 12June 1993

2o0

2.1+1

LIQUID EFFLUENTS


Basis

Monitor setpoints will be established such that the concentrationof radionuclides in the liquid effluent releases in the dischargecanal will not exceed those concentrations as specified in 10 CFR20, Appendix B, Table II, Column 2. Setpoints for the ServiceWater System Effluent Line will be calculated quarterly based onthe radionuclides identified during the previous year's releasesfrom the liquid radwaste system or the isotopes identified in themost recent radwaste release or other identified probable source.Setpoints for the Liquid Radwaste Effluent Line will be based onthe radionuclides identified in each batch of liquid waste prior toits release.

2 ~ 1 ~ 2

After release, the Liquid Radwaste monitor setpoint may remain asset, or revert back to a setpoint based on a previous Semi-AnnualRadioactive Effluent Release Report, or install blank flange in thedischarge line and declare inoperable in accordance with thetechnical specification.Since the Service Water System effluent monitor and Liquid Radwasteeffluent monitor can only detect gamma radiation, the alarmsetpoints are calculated by using the concentration of gammaemitting isotopes only (or the corresponding MPC values for thesame isotopes, whichever are higher) in the E>(pci/ml)+ expression(Section 2.1.2, 2.1.3).The Required Dilution Factor is calculated using concentrations ofall isotopes present (or the corresponding MPC values for the sameisotopes, whichever are higher) including tritium and othernon-gamma emitters to ensure that all radionuclides in thedischarge canal do not exceed 10 CFR 20 limits.Service Water System Effluent Line Alarm Setpoint

The detailed methods for establishing setpoints for the ServiceWater System Effluent Line Monitor shall be contained in the NineMile Point Station Procedures. These methods shall be inaccordance with the following:

Setpoint (Hi alarm) <0.9 E Ci ml CF TDF F[(pCi/ml)n/MPC))

I

+ background

Setpoint (Alert alarm) <0.7 E Ci ml CF TDF F + background[(pC m )s MPC,)

I

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2. 1. 2 (Cont'd)

(pCi/ml)>

(pCi/ml)n

TDF

concentration of gamma emitting isotope i inthe sample, or the corresponding MPC of gammaemitting isotope i (MPC)„ whichever is higher(units ~ pCi/ml) .

concentration of any radioactive isotope i inthe sample including tritium and othernon-gamma emitters or corresponding MPC ofisotope i, MPC„ whichever is higher (units =

pCi/ml) .

Total Dilution Flow (units = gallons/minutes) .

Service Mater Flow (units ~ gallons/minutes) .

CF

MPC<

Sample

monitor calibration factor (units = netcpm/pci/ml ) .

liquid effluent radioactivity concentrationslimit for radionuclide i as specified in 10 CFR20, Appendix B, Table II, Column 2.

Those nuclides present in the previous batchrelease from the liquid radwaste effluentsystem or those nuclides present in the lastSemi-annual Radioactive Effluent Release Report(units ~ pCi/ml) or those nuclides present inthe service water„system.**

(MPC)i,

0.9 and 0.7

same as MPC< but for gamma emitting nuclidesonly.

~I

factors of conservatism to account forinaccuracies.

E,[(pCi/ml)z/MPC,j ~ Required Dilution Factor. If MPC values areused in the (pCi/ml)+, they must also be used incalculating RDF (numerator).

TDF/F~ Actual Dilution Factor

2o1.3 Liquid Radwaste Effluent Line Alarm Setpoint

The detailed methods for establishing setpoints for the LiquidRadwaste Effluent Line Monitor shall be contained in the Nine MilePoint Station Procedures. These methods shall be in accordancewith the followingc

E

I( (PCi/») rr/MPCl)

E

~[ (pCi/ml)n'/MPCi)

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

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2.1.3 (Cont'd)

(pCi./ml)+ concentration of gamma emitting isotope i in thesample or the corresponding MPC of gammaemitting isotope i, (MPC)i whichever is higher.

(pCi/ml ) n

TDF

concentration of any radioactive isotope i inthe sample including tritium and other non-gammaemitters or the corresponding MPC of isotope iMPQ whichever is higher. (units = pCi/ml).

Total Dilution Flow (units ~ gallons/minutes).

CF

MPCi

Radwaste Effluent Flow (units =gallons/minutes).

monitor calibration factor (units = netcps/pCi/ml).

liquid effluent radioactivity concentrationlimit for radionuclide i as specified in 10 CFR20, Appendix B, Table II, Column 2, for thosenuclides detected by spectral analysis of thecontents of the radwaste tanks to be released.(units = pCi/ml)

(MPC) I„

0.9 and 0.7

same as MPC, but for gamma emitting nuclideonly.factors of conservatism to account forinaccuracies.

E[(pCi/ml)n/MPC,] Required Dilution Factor. If MPC values areused in the (pci/ml)pi they must also be used incalculating RDF (numerator).

Notes: ( a) If TDF/F„~ E> [ (pCi/ml)z/MPC,)

the discharge could not be made, since the monitorwould be continuously in alarm. To avoid thissituation, F„ will be reduced (normally by a factor of2) to allow setting the alarm point at a concentrationhigher than tank concentration. This will also resultin a discharge canal concentration at approximately 50%maximum permissible concentration.

(b) The value used for TDF will be reduced by thefractional quantity (1-FT), where FT is temperingfraction (i.e., diversion of some fraction of dischargeflow to the intake canal for the purpose of temperaturecontrol).

2.1.4

2 ~ 1 ~ 4 ~ 1

Discussion

Control of Liquid Effluent Batch Discharges

At Nine Mile Point Unit 1 Liquid Radwaste Effluents are releasedonly on a batch mode. To prevent the inadvertent release of anyliquid radwaste effluents, radwaste discharge is mechanicallyisolated (blank flange installed or discharge valve chain-lockedclosed) following the completion of a batch release or series ofbatch releases.

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2.1.4.1 (Cont'd)

This mechanical isolation remains in place and will only be removedprior to the next series of liquid radwaste discharges after allanalyses required in station procedures and Technical SpecificationTable 4.6.15-1A are performed and monitor setpoints have beenproperly ad)usted.

2.1.4.2 Simultaneous Discharges of Radioactive Liquids.

If during the discharge of any liquid radwaste batch, there is anindication that the service water canal has become contaminated(through a service water monitor alarm or through a grab. sampleanalysis in the event that the service water monitor is inoperable)the discharge shall be terminated immediately. The liquid radwastedischarge shall not be continued until the cause of the servicewater alarm (or high grab sample analysis result) has beendetermined and the appropriate corrective measures taken to ensure10CFR20, Appendix B, Table II, Column 2 (Technical SpecificationSection 3.6.15.a(1)) limits are not exceeded.

In accordance with Site Chemistry procedures, controls are in placeto preclude a simultaneous release of liquid radwaste batch tanks.In addition, an independent verification of the discharge valveline-up is performed prior to discharge to ensure that simultaneousdischarges are prevented.

2.1.4.3 Saapling Representativeness

This section covers Technical Specification Table 4.6.15-1 Note bconcerning thoroughly mixing of each batch of liquid radwaste priorto sampling.

Liquid Radwaste Tanks scheduled for discharge at Nine Mile PointUnit 1 are isolated (i.e. inlet valves marked up) and at least twotank volumes of entrained fluids are recirculated prior tosampling. Minimum recirculation time is calculated as follows:

Minimum Recirculation Time ~ 2.0(T/R)

Where:

2.0 ~ Plant established mixing factor, unitlessT ~ Tank volume, galR ~ Recirculation flow rate, gpm

Additionally, the Hi Alarm setpoint of the Liquid Radwaste EffluentRadiation Monitor is set at a value corresponding to not more than70% of its calculated response to the grab sample or correspondingMPC values. Thus, this radiation monitor will alarm if the grabsample, or corresponding MPC value, is significantly lower inactivity than any part of the tank contents being discharged.

2.1.4.4 Liquid Radwaste Syateas Operation

Technical Specification 3.6.16.a requires that the liquid radwastesystem shall be used to reduce the radioactive materials in liquidwastes prior to their discharge, as necessary, to meet theconcentration and dose requirements of Technical SpecificationF 6.15.

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2.1.4.4 (Cont'd)

Utilization of the radwaste system will be based on the capabilityof the indicated components of each process system to processcontents of the respecti.ve low conductivity and high conductivitycollection tanks:

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

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

Cumulative dose contributions from liquid effluents for the currentcalendar quarter and the current calendar year shall be determinedas described in Section 2.3 of this manual prior to the release ofeach batch of liquid waste. This same dose projection of Section2.3 will also be performed in the event that untreated liquid wasteis discharged, to ensure that the dose limits of TechnicalSpecification 3.6.15.a(2) are not exceeded. (Thereby implementingthe requirements of 10CFR50 ~ 36al General Design Criteria 60 ofAppendix A and the Design Ob)ective given in Section II-D ofAppendix I to 10 CFR50).

For the purpose of dose pro)ection, the following assumptions shallbe made with regard to concentrations of non-gamma emittingradionuclides subsequently analyzed off-site:a) [H-3) s H-3 Concentration found recent condensate storage

tank analysis

b) [Sr-89) S 4 x Cs-137 Concentration

c) [Sr-90) 5 0.5 x Cs-137 Concentration

d) [Fe-55] 5 1 x Co-60 Concentration

Assumed Scaling Factors used in b, c, and d above representconservative estimates derived from analysis of histori.cal datafrom process waste streams. Following receipt of off»site H-3,Sr-89, Sr-90 and Fe-55 analysis information, dose estimates shallbe revised using actual radionuclide concentrations and actual tankvolumes discharged.

2.1.4.5 Service Water System Contamination

Service water is normally non-radioactive. If contaminati.on issuspected, as indicated by a significant increase in service watereffluent monitor response, grab samples will be obtained from theservice water discharge lines and a gamma isotopic analysis meetingthe LLD requi.rements of Techni.cal Specification Table 4.6.15-1completed. If it i.s determined that an inadvertent radioactivedischarge is occurring from the service water system, then:

a) A 50.59 safety evaluation shall be performed (ref. 1&E Bulletin80-10),

b) daily service water effluent samples shall be taken andanalyzed for principal gamma emitters until the release isterminated,

c) an incident composite shall be prepared for H-3, gross alphaiSr-89, Sr-90 and Fe-55 analyses and,

003856LL


2 '.4 ' (Cont'd)

d) dose pro)ections shall be performed in accordance with Section2.3 of this manual (using estimated concentrations for H-3,Sr-89, Sr-90 and Fe-55 to be conservatively determined bysupervision at the time of the incident).

Additionally, service water effluent monitor setpoints may berecalculated using the actual distribution of isotopes found fromsample analysis.

Liquid Effluent Concentration Calculation

This calculation documents compliance with Technical SpecificationSection 3.6.1.5.a (1).The concentration of radioactive material released in liquideffluents to unrestricted areas (see Figure B-7) shall be limitedto the concentrations specified in 10CFR20, Appendix B, Table II,Column 2, for radionuclides other than dissolved or entrained noblegases. For dissolved or entrained noble gases, the concentrationshall be limited to 2 E-4 microcurie/milliliter (pCi/ml) totalactivity.The concentration of radioactivity from Liquid Radwaste batchreleases and, if applicable, Service Water System and emergencycondenser start-up vent discharges are included in the calculation.The calculation is performed for a specific period of time. Nocredit taken for averaging over the calendar year as permitted by10CFR20.106. The limiting concentration is calculated as follows:MPC Fraction ~ E,((E, C„F,)/(MPC, E, F,) )

Where:

MPC Fraction ~ The limiting concentration of 10 CFR 20, AppendixB, Table II, for radionuclides other than dissolvedor entrained noble gases. For noble gases, theconcentration shall be limited to 2 E-4microcurie/ml total activity.

C„~(pCi/ml)„The concentration of nuclide i in particulareffluent stream s, pCi/ml.

F, The flow rate of a particular effluent stream s,gpmo

MPCi The limiting concentration of a specific nuclide ifrom 10CFR20, Appendix B, Table II, Column 2 (noblegas limit is 2E-4 pCi/ml).

E,(pCi/ml)„F,) ~ The total activity rate of nuclide i, in alleffluent streams s.

The total flow rate of all effluent streams s, gpm(including those streams which do not containradioactivity).

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

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2 ~ 3 Dose Determination

2.3.1 Maximum Dose Equivalent Pathway

A dose assessment report was prepared for the Nine Mile Point Unit1 facility by Charles T. Main, Inc., of Boston, MA. This reportpresented the calculated dose equivalent rates to individuals aswell as the population within a 50-mile radius of the facilitybased on the radionuclides released in liquid and gaseous effluentsduring the time periods of 1 July 1980 through 31 December 1980 andfrom January 1981 through 31 December 1981. The radwaste liquidreleases are based on a canal discharge rate of 590 ft~/sec whichaffects near field and far field dilution; therefore, this reportis specific to this situation. Utilizing the effluent datacontained in the Semi-Annual Radioactive Effluent Release Reportsas source terms, dose equivalent rates were determined using theenvironmental pathway models specified in Regulatory Guides 1.109and 1.111 as incorporated in the NRC computer codes LADTAP forliquid pathways, and XOQDOQ and GASPAR for gaseous effluentpathways. Dose equivalent rates were calculated f'r the total bodyas 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 wasreceived via the fish pathway. However, to comply with TechnicalSpecifications for dose projections, the drinking water andsediment pathways are included. Therefore, all doses due to liquideffluents are calculated monthly for the fish and drinking wateringestion pathways and the sediment external pathway from alldetected nuclides in liquid effluents released to the unrestrictedareas to each organ. The dose projection for liquid batch releaseswill also include discharges from the emergency condenser vent asapplicable, for all pathways. Each age group dose factor, A , isgiven in Tables 1-1 to 1-8. To expedite time the dose iscalculated for a maximum individual instead of each age group.This maximum individual will be a composite of the highest dosefactor of each age group for each organ, hence A;,. The followingexpression from NUREG 0133, Section 4.3 is used to calculate dose:

Di = EL (%St (hTLCsFg) )

Where:

D, ~ The cumulative dose commitment to the total body or any .

organ, from the liquid effluents for the total time period(dT„), mrem.

dTi I The length of the L th time period over which C~ and F„areaveraged for all liquid releases, hours.

CL . ~ The average concentration of radi.onuclide, i, in undilutedliquid effluents during time period dT„ from any liquidrelease, pCi/ml.

The site related ingestion dose commitment factor to thetotal body or any organ t for each identified principalgamma or beta emitter for a maximum individual, mrem/hrper pci/ml.

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2.3.1 (Cont'd)

Fg The near field average dilution factor for Cz during anyliquid effluent release. Defined as the ratio of themaximum undiluted liquid waste flow during release to theaverage flow from the site discharge structure tounrestricted receiving waters, unitless.

~ values for radwaste liquid batch releases at a discharge rate of295 ft~/sec (one circulating water pump in operation) are presentedin tables l-l to 1-4. ~ values for an emergency condenser ventrelease are presented in tables 1-5 to 1-8. The emergencycondenser vent releases are assumed to travel to the perimeterdrain system and released from the discharge structure at a rate of.33 ft~/sec. See Appendix A for the dose factor A derivation. Toexpedite time the dose is calculated to a maximum individual. Thismaximum individual is a composite of the highest dose factor A ofeach age group a for each organ t and each nuclide i. If a nuclideis detected for which a factor is not listed, then it will becalculated and included in a revision to the ODCM.

All doses calculated in this manner for each batch of liquideffluent will be summed for comparison with quarterly and annuallimits, added to the doses accumulated from other releases in thequarter and year of interest. In all cases, the followingrelationships will hold:

For a calendar quarter:

D, < 1.5 mrem total body

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 to the total body or any organ due toliquid effluent releases.

If these limits are exceeded, a special report will be submitted tothe NRC identifying the cause and proposed corrective actions. Inaddition, if these limits are exceeded by a factor of two,calculations shall be made to determine if the dose limitscontained in 40 CFR 190 have been exceeded. Dose limits, ascontained in 40 CFR 190 are total body and organ doses of 25 mremper year and a thyroid dose of 75 mrem per year.

These calculations will include doses as a result of liquid andgaseous pathways as well as doses from direct radiation. Theliquid pathway analysis will only include the fish and sedimentpathways since the drinking water pathway is insignificant. Thispathway is only included in the station's effluent dose projectionsto comply with Technical Specifications. Liquid, gaseous anddirect radiation pathway doses will consider the James A.FitzPatrick and Nine Mile Point Unit II facilities as well as NineMile Point Unit I Nuclear Station.

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Zn the event the calculations demonstrate that the 40 CFR 190 doselimits, as defined above, have been exceeded, then a report shallbe prepared and submitted to the Commission within 30 days asspecified in Section 3.6.15.d of the Technical Specifications.

Section 4.0 of the ODCM contains more information concerningcalculations for an evaluation of whether 40 CFR 190 limits havebeen exceeded.

003856LL 10


3 ~ 0

3el

3+i ~ 1

GASEOUS EFFLUENTS


Basis

Stack gas and off gas monitor setpoints will be established suchthat the instantaneous release rate of radioactive materials ingaseous effluents does not exceed the 10 CFR 20 limits for annualrelease rate. The setpoints will be activated if the instantaneousdose rate at or beyond the (land) site boundary would exceed 500mrem/yr to the whole body or 3000 mrem/yr to the skin from thecontinuous release of radioactive noble gas in the gaseouseffluent.Emergency condenser vent monitor setpoints will be established suchthat the release rate for radioactive materials in gaseouseffluents do not exceed the 10 CFR 20 limits for annual releaserate over the pro)ected longest period of release.

Monitor setpoints from continuous release points will be determinedonce per,quarter under normal release rate conditions and will bebased on the isotopic composition of the actual release inprogress, or an offgas isotopic distribution or a more conservativedefault composition specified in the pertinent procedure. If thecalculated setpoint is higher than the existing setpoint, it is notmandatory that the setpoint be changed.

Monitor setpoints for emergency condenser vent monitors areconservatively fixed at 5 mr/hr for reasons described in Sections3.1.4 and therefore do not require periodic recalculations.

Under abnormal site release rate conditions, monitor alarmsetpoints from continuous release points will be recalculated and,if necessary, reset at more frequent intervals as deemed necessaryby C&RM Supervision. In particular, contributions from both JAFand NMP-2 and the Emergency Condenser Vents shall be assessed.

During outages and until power operation is again realized, thelast operating stack and off gas monitor alarm setpoints shall beused.

Since monitors respond to noble gases only, monitor alarm pointsare set to alarm prior to exceeding the corresponding total bodydose rates.

3.1+2

The skin dose rate limit is not used in setpoint calculationsbecause it is never limiting.Stack Monitor Setpoints

The detailed methods for establishing setpoints shall be containedin the station procedures. These methods shall apply the followinggeneral criteria:(1) Rationale for Stack monitor settings is based on the general

equation!

release rate actualcorresponding dose rate, actual

release rate max. allowablecorresponding dose rate, max. allowable

Ill(Vl+(SF)w(~/()).)max

500 mrem/yr

003856LL


3.1.2 (Cont'd)

Where:

Q< release rate for each isotope i, pCi/sec.

Vi gamma whole body dose factor in units of mrem/yr per pCi/sec.(See Table 3-2).

instantaneous release rate limit pci/sec.

(2) To ensure that 10 CFR 20 and Technical Specifications dose ratelimits are not exceeded, the Hi Hi alarms on the stack monitorsshall be set lower than or equal to (0.9) (Q) . Hi alarms shall beset lower than or equal to (0.5) (Q)

(3) Based on the above conservatism, the dose contribution from JAF andNMP-2 can usually be ignored. During Emergency Classifications atJAF or NMP-2 due to airborne effluent, or after emergency condenservent releases of significant proportions, the 500 mrem/yr value maybe reduced accordingly.

To convert monitor gross count rates to pCi/sec release rates, thefollowing general formula shall be applied:

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

Where:

C~BK,

monitor gross count rate in cps or cpmmonitor background count ratestack monitor efficiency factor with units ofpCi/sec-cps or pCi/sec-cpm

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

~IQI/ ( Cw-8 )

Where:

Q, ~ individual radionuclide stack effluent release rate asdetermined by isotopic analysis.

I

K, factors more conservative than those calculated by the above methodologymay be assumed.

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

1/K, ~ Ef

Z F E Y 3.7E4daf Sec.-pCi

Where:

f = stack flow in cc/sec.

E efficiency in units of cpm-cc/pCi or cps-cc/pCi (cpm =

counts per minute; cps = counts per second).

E„ = cpm-cc/bps or cps-cc/yps.

From energy calibration curve produced during NZST traceable primary gascalibration or transfer source calibration (bps ~ beta per second;@ps gammas per second).

003856LL 12


3.1.2 (Cont'd)

Y„ ~ b/d (betas/disintegration) or y/d (gammas/disintegration).

F, ~ Activity fraction of nuclide i in the mixture.

i ~ nuclide counter.

k ~. discrete energy beta or gamma emitter per nuclide counter.

s ~ seconds.

This monitor calibration method assumes a noble gas distributiontypical of a recoil release mechanism. To ensure that thecalculated efficiency is conservative, beta or gamma emissionswhose energy is above the range of calibration of the detector arenot included in the calculation.

F 1+3 Racombiner Discharge (Off Gas) Monitor Setpoints

The Hi-Hi alarm points shall activate with recombinerdischarge rates equal to or less than 500,000 pCi/sec. Thisalarm point may be set equal to or less than 1 Ci/sec for aperiod of time not to exceed 60 days provided the offgastreatment system is in operation.

(2) The Hi alarm points shall activate with recombiner dischargerates equal to or less than 500,000 pCi/sec. According tothe Unit 1 Technical Specifications, Note (C) to Table4.6.14-2, the channel functional test of the condenser aire)ector radioactivity monitor shall demonstrate thatautomatic isolation of this pathway occurs if either of thefollowing conditions exist:

i) Instruments indicate two channels above the Hi-Hi alarmsetpoint,

ii) Instruments indicate one channel above Hi-Hi alarmsetpoint and one channel downscale.

This automatic isolation function is tested once peroperating cycle in accordance with station procedures.

(3) To convert monitor mR/hr readings to pCi/sec, the formulabelow shall be appliede

(R)(K„) ~ g~ pCi/sec recombiner discharge release rate

Where:

R ~ mR/hr monitor indicator.

Kz efficiency factor in units of pCi/sec/mR/hr determinedprior to setting monitor alarm points.

(4) Monitor K„ factors shall be determined using the generalformula:

Ka ~ E(Qi/R

Where:

Q ~ individual radionuclide recombiner discharge release rateas determined by isotopic analysis and flow rate monitor.

003856LL 13


3.1.3 (Cont'd)

K„ factors more conservative than those calculated by the abovemethodology may be assumed.

(5) The setpoints chosen provide assurance that the total bodyexposure to an individual at the exclusion area boundary willnot exceed a very small fraction of the limits of 10CFR Part100 in the event this effluent is inadvertently dischargeddirectly to the environment without treatment (therebyimplementing the requirements of General Design Criteria 60and 64 of Appendix A to 10CFR Part 50). Additionally, thesesetpoints serve to limit buildup of fission product activitywithin the station systems which would result if high fuelleakage were to be permitted over extended periods.

3.1.4

3 ~ 1.5

Emergency Condenser Vent Monitor Setpoint

The monitor setpoint was established by calculation ("EmergencyCondenser Vent Monitor Alarm Setpoint", January 13, 1986, NMPC FileCode f16199). Assuming a hypothetical case with (1) reactor wateriodine concentrations higher than the Technical SpecificationLimit, (2) reactor water noble gas concentrations higher than wouldbe expected at Technical Specification iodine levels, and (3)leakage of reactor steam into the emergency condenser shell at 300%of rated flow (or 1.3 E6 lbs/hr), the calculation predicts anemergency condenser vent monitor response of 20 mR/hr. Such arelease would result in less than 10 CFR 20 dose rate values at thesite boundary and beyond for typical emergency condenser cooldownperiods.

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

Discussion

3.1.5.1 Stack Effluent Monitoring System Description

The NMP-1 Stack Effluent Monitoring System consists of twosubsystems; the Radioactive Gaseous Effluent Monitoring System(RAGEMS) and the old General Electric Stack Monitoring System(OGESMS). During normal operation, the OGESMS shall be used tomonitor station noble gas effluents and collect particulates andiodine samples in compliance with Technical Specificationrequirements.

The RAGEMS is designed to be promptly activated from the MainControl Room for use in high range monitoring during accidentsituations in compliance with NUREG 0737 criteria. Overall systemschematic for the OGESMS and RAGEMS are shown on Figure B-9. Asimplified view of RAGEMS Showing Unit 0, 1, 2, 3 and 4 can befound on Figure B-8.

The RAGEMS can provide continuous accident monitoring and on-lineisotopic analysis of NMP-1 stack effluent noble gases at LowerLevels of Detection less than Technical Specification Table4.6.15-2 limits. Activities as low as S.OE-8 and as high as 2.0ESpCi/cc for noble gases are detectable by the system.

003856LL 14


3 ' F 2 Stack Sample Flow Path - RAGEMS

The effluent sample is obtained inside the stack at elevation530'singan isokinetic probe with four orifices. The sample line then

bends radially out and back into the stack; descends down the stackand out of the stack at approximately elevation 257'g runshorizontally (enclosed in heat tracing) some 270'long the off gastunnel; and enters the RAGEMS located on the Turbine Building

250'Dilutioncabinet - Unit 0) and Off Gas Building 247'Particulate,Iodine, Noble Gas stations - Units 1-3).

In the Dilution cabinet of the RAGEMS, the stack gas may be dilutedduring accident situations approximately 100-200X (first stage) or10000-40000 X ( first and second stage) with gaseous nitrogensupplied from an on-site liquid nitrogen storage tank (see FigureB-9) ~

From Unit 0, the sample gas enters Unit 1-3 of RAGEMS and flowsthru in-line particulate and iodine cartridges and then thru eithera 6 liter (low range) or 30 cc (high range) noble gas chamber. Thesample gas next flows back thru Unit 0 and the off gas tunnel; andback into the stack.

3 ' ~ 5 ' Stack Sample Flow Path - OGESMS

The OGESMS sample is obtained from the same stack sample probe asthe RAGEMS. From the exit of the stack at elevation 257', thesample line runs east approximately 20'nd then verticallyapproximately 8'o the OGESMS skid. In the OGESMS, sample flowsthru a particulate/iodine cartridge housing and four noble gasscintillation detectors (i.e., 07 and 08 low range beta detectorsand RN-03A and RN-03B high range gamma detectors). From OGESMS,the stack sample flows back into the stack at approximatelyelevation 257'. I

All OGESMS detector outputs are monitored and recorded remotely inthe Main Control Room. Alarming capabilities are provided to alertOperators of high release rate conditions prior to exceedingTechnical Specification 3.6.15.b (1) a dose rate limits.

3.1 ~ 5 '

Stack particulate and iodine samples are retrieved manually fromthe OGESMS and analyzed in the laboratory using gamma spectroscopyat frequencies and LLDs specified in Table 4.6.15-2 of theTechnical Specifications.

Sampling Frequency/Sample Analysis

Regardless of which stack monitoring subsystem is utilized,radioactive gaseous wastes shall be sampled and analyzed inaccordance with the sampling and analysis program specified inTechnical Specification Table 4.6.15-2. Particulate samples aresaved and analyzed for principal gamma emitters, gross alpha,Fe-55, Sr-89, Sr-90 at monthly intervals minimally. The latterthiee analyses are performed off-site from a composite sample.Sample analysis frequencies are increased during elevated releaserate conditions, following startup, shutdown and in con)unctionwith each drywell purge.

Consistent with Technical Specification Table 4. 6. 15-2, stackeffluent tritium is sampled monthly, during each drywell purge, andweekly when fuel is off loaded until stable release rates aredemonstrated. Samples are analyzed off-site.

003856LL 15


3.1.5.4 (Cont'd)

3 ~ 1 ~ 5 ~ 5

Line loss correction factors are applied to all particulate andiodine results. Correction factors of 2.0 and 1.5 are used fordata obtained from RAGEMS and OGESMS respectively. Thesecorrection factors are based on empirical data from samplingconducted at NMP-1 in 1985 (memo from J. Blasiak to RAGEMS File,1/6/86, "Stack Sample Representativeness Study: RAGEMS vs.In«Stack Auxiliary Probe Samples" ).I-133 Estimates

Monthly, the stack effluent shall be sampled for iodines over a 24hour period and the I-135/I-131 and the I-133/I-131 ratioscalculated. These ratios shall be used to calculate I-133, I-135release for longer acquisition samples collected during the month.

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

3.1.5.6 Gaseous Radwaste Treatment System Operation

Technical Specification 3.6.16.b requires that the gaseous radwastetreatment system shall be operable and shall be used to reduceradioactive materials in gaseous waste prior to their discharge asnecessary to meet the requirements of Technical Specification3.6.15.b.

To ensure Technical Specification 3.6'.15.b limits are not exceeded,and to confirm proper radwaste treatment system operation asapplicable, cumulative dose contributions for the current calendarquarter and current calendar year shall be determined monthly inaccordance with section 3.2 of this manual. Initial dosecalculations shall incorporate the following assumptions withregard to release rates of non-gamma emitting radionuclidessubsequently analyzed off-site:a)b)c)d)

H-3 release rateSr-89 release rateSr-90 release rateFe-55 release rate

s 4 pCi/secs 4 x Cs-137 release rates 0.5 x Cs-137 release rate5 1 x Co-60 release rate

Assumed release rates represent conservative estimates derived fromanalysis of historical data from effluent releases and processwaste streams (See NMP 34023, C. Ware to J. Blasiak, April 29,1988, "Dose Estimates for Beta«Emitting Isotopes" ). Followingreceipt of off«site H-3, Sr-89, Sr-90, Fe-55 analysis information,dose estimates shall be revised using actual radionuclideconcentrations.

3 ' Dose and Dose Rate Determinations

In accordance with specifications 4.6.15.b.(1), 4.6.15.b.(2), and4.6.15.b.(3) dose and dose rate determinations will be made monthlyto determine:

(1) Total body dose rates and gamma air doses at the maximum X/gland sector site boundary interface and beyond.

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

003856LL 16


3.2 (Cont'd)

(3) The critical organ dose and dose rate at the maximum X/Q landsector site boundary interface and at a critical receptorlocation beyond the site boundary.

Average meteorological data (ie, maximum five year annual averageX/Q and D/Q values in the case of elevated releases or 1985 annualaverage X/Q and D/Q values, in the case of ground level releases)shall be utilized for dose and dose rate calculations. Whereaverage meteorological data is assumed, dose and dose rates due tonoble gases at locations beyond the site boundary will be lowerthan equivalent site boundary dose and dose rates. Therefore,under these conditions, calculations of noble gas dose and doserates beyond the maximum X/Q land sector site boundary locationscan be neglected.

The frequency of dose rate calculations will be upgraded whenelevated release rate conditions specified in subsequent sections3.2.1.1 and 3.2.1.2 are realized.

Emergency condenser vent release contributions to the monthly doseand dose rate determinations will be considered only when theemergency condenser return isolation valves have been opened forreactor cooldown or if Emergency Condenser tube leaks develop withor 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 dosecontributions do not have to be included.

When releases from the emergency condenser have occurred, dose rateand dose determinations shall be performed using methodology in3.2.1 and 3.2.2. Furthermore, environmental sampling may also beinitiated to refine any actual contribution to doses. See Section3.4.

Critical organ doses and dose rates may be conservativelycalculated by assuming the existence of a maximum individual. Thisindividual is a composite of the highest dose factor of each agegroup, for each organ and total body, and each nuclide. It isassumed that all pathways are applicable and the highest X/Q and/orD/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 personwould receive if they were simultaneously subjected to the highestpathway 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 TechnicalSpecifications we will calculate the maximum individual dose rateat the site boundary and beyond at the critical residence.

If dose or dose rates calculated, using the assumptions notedabove, reach Technical Specification limits, actual pathways willbe evaluated, and dose/dose rates shall be calculated at separatecritical receptor locations and compared with applicable limits.Dose Rate

Dose rates will be calculated monthly, at a minimum, or when theHi-Hi stack monitor alarm setpoint is reached, to demonstrate thatdose rates resulting from the release of noble gases, tritium,iodines, and particulates with half lives greater than 8 days arewithin the limits specified in 10CFR.20. These limits ares

003856LL 17


3.F 1 (Cont'd)

ob e Gases

Whole Body Dose Rate:Skin Dose Rate:

500 mrem/yr3000 mrem/yr

T i um Iodi es and Particulates

Organ Dose Rates

3.2.1.1 Noble Gases

1500 mrem/yr

The following noble gas dose rate equation includes thecontribution from the stack (s) elevated release and the emergencycondenser vent (v) ground level release when applicable (Seesection 3.2).To ensure that the site noble gas dose rate limits are not exceeded,the following procedural actions are taken if the offsite dose ratesfrom Unit 1 exceed 10% of the limi.ts:

1) Notify the Unit 1 SSS (Station Shift Supervisor) and Unit 1

Supervisor Chemistry.

2) 'Notify the Uni.t 2 SSS and Unit 2 Supervisor Chemistry and requestthe Unit 2 contribution to offsite dose.

3) Notify the SSS of the James A. Fi.tzpatrick Nuclear Plant andrequest the Fitzpatrick contribution to offsite dose.

4) Increase the frequency of performing noble gas dose calculati.ons,if necessary, to ensure Site (Nine Mile Point Units 1 and 2 andFitzpatrick) limits are not exceeded.

Additionally, alarm setpoints are set at 50% of the dose rate limit toensure that site limits are not exceeded. This alarm setpoint isadjusted if the noble gas dose rate from Unit 1 is greater than 10% ofthe limit.For total body dose rates (mrem/sec):

DR„(mrem/sec) ~ 3. 17E-8Ei ( (V) + (SF) Q(X/Q),)Q„+ (SF) Q (X/Q)„Q„]

For skin dose rates (mrem/sec):

DR >(mrem/sec) 3.17E-BE,[(L,(X/Q), + 1.11(SF)(B, + g(X/Q),))Q +wee(Li + 1 'l(SF)g)(X/Q)„Q„]

Wherei

total body gamma dose rate (mrem/sec).

skin dose rate from gamma and beta radiation (mrem/sec) .

V) the constant accounting for the gamma whole body doserate from stack radiation for an elevated finite plumereleases for each identified noble gas nucli.de, i..Listed on Table 3-2 i.n mrem/yr per pCi/sec.

003856LL 18


3.2.1.1 (Cont'd)

the constant accounting for the gamma whole body doserate from immersion in the semi-infinite cloud for eachidentified noble pas nuclide, i. Listed in Table 3-3 inmrem/yr per pCi/m (from Reg. Guide 1.109)

Q~i Q»

SF

X/Q

L,

B(

the release rate of isotope i from the stack(s) orvent(v) g (pCi/sec)

structural shielding factor.the relative plume concentration (in units of sec/m') atthe land sector site boundary or beyond. Averagemeteorological data (Table 3-1) is used. "Elevated" X/Qvalues are used for stack releases (s = stack)g "Ground"X/Q values are used for Emergency Condenser Vent releases(v ~ vent).the constant accounting for the beta skin dose rate fromimmersion in the semi-infinite cloud for each identifiednoble gas nuclide, i. Listed in Table 3-3 in mrem/yr perpCi/m~ (from Reg. Guide 1.109)

the constant accounting for the air gamma, radiation fromthe elevated Finite plume resulting from stack releasesfor each identified noble gas nuclide, i. Listed inTable 3-2 in mrad/yr per pCi/sec.

the constant accounting for the gamma air dose rate fromimmersion in the semi-infinite cloud for each identifiednoble gas nuclide, i. Listed in Table 3-3 in mrem/yr perpCi/m~ ( from Reg. Guide 1. 109)

See Appendix B for derivation of Bi and VI.

3.2.1.2 Tritium, Zodines and Particulates

that the 1500 mrem/year site dose rate limit is notoffsite dose rates for tritium, iodine and particulateslives greater than 8 days shall be calculated monthly and

To ensureexceeded,with half

D~ (mrem/sec) ~ 3.17E-BE>[E, a~ (W, Q., + W„ Q„j)

Where:

when release rates (Q) exceed 0.34 pCi/sec using the followingequation.

WJ

Total dose rate to each organ k of an individual in agegroup a (mrem/sec).

dispersion parameter either X/Q (sec/m') or D/Q (1/m~)depending on pathway and receptor location assumed.Average meteorological data is used (Table 3-1)."Elevated" Wj values are used for stack releases(s ~ stack); "Ground" Wj values are used for EmergencyCondenser Vent releases (v ~ vent).the release rate of isotope i, from the stack (s) orvent(v); (pCi/sec).

003856LL 19


3.2.1.2 (Cont'd)

R ~ the dose factor for each isotope i, pathway j, age groupa, and organ k (Table 3-4, through 3-22; m'-mrem/yr perpCi/sec for all pathways except inhalation, mrem/yr perpCi/m'. The R values contained in Tables 3-4 through3-22 were calculated usi.ng the methodology defined inNUREG-0133 and parameters from Regulatory Guide 1.109,Revision 1; as presented in Appendix C.

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

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

The use of the 0.34 pci/sec release rate threshold to perform doserate calculations is justified as followss

(a) The 1500 mrem/yr organ dose rate limit corresponds to aminimum release rate limit of 0.34 pCi/sec calculated usingthe e'quation:

1500 ~ (Q, pCi/sec) x (+Wj)

Where:

1500

(RgWj)~site boundary dose rate limit (mrem/year).

the maximum curie-to-dose conversion factor equal to4.45E3 mrem-sec/pCi-yr for Sr-90, child bone at thecritical residence receptor location beyond the si.teboundary.

(b) The use of 0.34 pCi/sec release rate threshold and the 4.45E3mrem-sec/pCi-yr curie-to-dose conversion factor isconservative since curie-to-dose conversion factors for otherisotopes likely to be present are significantly lower.

In addition, if the organ dose rate exceeds 5% of the annuallimit, the following procedural actions will be taken:

1) Notify the Unit 1 SSS (Station Shi.ft Supervisor) andUnit 1 Supervisor Chemistry.

2) Notify the Unit 2 SSS and Unit 2 Supervisor Chemistryand request the Unit 2 contribution to offsite dose.

3) Notify the SSS of the James A. Fitzpatrick contributionto offsite dose.

4) Increase the frequency of performing dose calculati.onsif necessary to ensure site (Nine Mile Point Units 1

and 2 and Fitzpatrick) limits are not exceeded.

3 ~ 2 ~ 2 Dose

Calculations wi.ll be performed monthly at a minimum, to demonstratethat doses resulti.ng from the release of noble gases, tritium,iodines, and particulates with half lives greater than 8 days arewithin the limits specified in 10 CFR 50, Appendix I. These limitsares

003856LL 20


3 ~ 2.2 (Coat'd)

oble Gases

5 mR gamma/calendar quarter10 mrad beta/calendar quarter10 mR gamma/calendar year20 mrad beta/calendar year

Tr tium Iodines and Particulates

7.5 mrem to any organ/calendar quarter15 mrem to any organ/calendar year

3.2.2.1 Noble Gas Air Dose

The following Noble Gas air dose equation includes contributionsfrom the stack (s) elevated release and the emergency condenservent (v) ground level release when applicable (see section 3.2):

For gamma radiation'mrad):

D, (mrad) ~ 3.17E-SE,[Q(X/Q)„ Q„ + (B, + Q(X/Q),) Q ] ~ t

For beta radiation (mrad):

D>(mrad) = 3.17E-SEiN>[ (X/Q)„Q„+ (X/Q), Q ) ~ tf

Where:

D gamma air dose (mrad).

beta air dose (mrad).

B) the constant accounting for the air gamma radiationfrom the elevated finite plume resulting from stackreleases for each identified noble gas nuclide, i.Listed in Table 3-2 in mrad/yr per pCi/sec.

N) The constant accounting for the air beta dose fromimmersion in the semi-infinite cloud for eachidentified noble gas nuclide, i. Listed on Table3-3 in mrad/yr per pCi/m'from Reg. Guide 1.109).

Q, Q„ =, the release rate of isotope i, from the stack (s) orvent (v)i (pCi/sec).

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

the constant accounting for the air gamma dose fromimmersion in the semi-infinite cloud for eachidentified noble gas nuclide, i. Listed on Table3-3 in mrad/yr per pCi/m'from Reg. Guide 1.109).

total time during release period, sec.

All other parameters are as defined in section 3.2.1.1.

003856LL 21


3.2.2.2 Tritium, Zodines and ParticulatesTo ensure that the 15 mrem/yr facility dose limit is not exceeded,offsite doses for tritium, iodines, and particulates with halflives greater than 8 days shall be calculated monthly using thefollowing equation:

D~ (mrem) ~ 3.17E-8ZJ(E, ~ [W, Q + W„Q„] ) ~ tWhere>

Wi

total dose to each organ k of an individual in agegroup a(mrem).

dispersion parameter either X/Q (sec/m~) or D/{} (1/m~)depending on pathway and receptor location assumed.Average meteorological data is used (Table 3-1)."Elevated" Wj values are used for stack releases(s ~ stack)g "Ground" Wj values are used for EmergencyCondenser Vent releases (v ~ vent).the release rate of isotope i from stack(s) orvent (v) g (pCi/sec) .

3. 17E-8

the dose factor for each isotope i, pathway ), agegroup a, and organ k (Tables 3-4, through 3-22;m~-mrem/yr per pCi/sec). R values contained in Tables3-4 through 3-22 were calculated using themethodology defined in NUREG-0133 and parameters fromRegulatory Guide 1.109; Revision 1; as presented inAppendix C.

the inverse of the number of seconds in a year.

total time during the release period, sec.

3.2.2.3 Accumulating Doses

Doses will be calculated monthly, at a minimum, for gamma air, betaair, and the critical organ for each age group. Dose estimateswill, also, be calculated monthly prior to receipt of any offsiteanalysis data i.e., strontium, tritium, and iron-55. Results willbe 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 depositioninhalation dosecow milk ingestion dose

— goat milk ingestion dosecow meat ingestion dosevegetation (food crops) ingestion dose

The quarterly and annual results shall be compared to the limitslisted in paragraph 3.2.2. Zf the limits are exceeded, specialreports, as required by Section 6.9.3 of the TechnicalSpecification, shall be submitted.

Note that the units for the gamma air dose are in mrad compared tothe units for the limits are in mR. The NRC recognizes that 1 mR 1mrad, for gamma radiation.

003856LL 22


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 arecontained in Table 3-1.

For elevated noble gas releases the critical receptor is the siteboundary.

When 1985 average annual X/Q values are used for ground level noblegas releases, the critical receptor is the maximum X/Q land sectorsite boundary interface.For tritium, iodines, and particulates with half lives greater thaneight days, the critical pathways are grass-(cow and goat)-milk,grass-cow meat, vegetation, inhalation and direct radiation (groundplane) as a result of ground deposition.

The grass-(cow and goat)-milk, and grass-cow-meat pathways will bebased on the greatest D/Q location. This location has beendetermined in conjunction with the land use census (technicalspecification 3.6.22) and is subject to change. The vegetation(food crop) pathway is based on the greatest D/Q garden locationfrom which samples are taken. This location may also be modifiedas a result of vegetation sampling surveys.

The inhalation and ground plane dose pathways will be calculated atthe critical residence.

3 '

Because the Technical Specifications state to calculate "at thesite boundary ~a d beyond", the doses and/or dose rates must becalculated for a maximum individual who is exposed to all pathwaysat the site boundary and at the critical residence. The maximumindividual is a composite of the highest dose factor of each agegroup, for each organ and total body, and each nuclide. Since thecritical residence location has the greatest occupancy time, theresultant dose at the residence including all pathways is limiting.However, due to the Technical Specification wording, the inhalationand ground plane dose at the site boundary along with all otherpathways, will be calculated assuming a continuous occupancy time.

In lieu of correcting land site boundary ground plane andinhalation dose factors for occupancy time, a TechnicalSpecification change will be submitted to change the requirementfrom calculating "at the site boundary and beyond" to "at the siteboundary or beyond". Unit 1 will then calculate at the criticalresidence since this should be the limiting dose. Until thischange is effective, the dose and/or dose rate calculations fortritium, iodines, and particulates with half lives greater than 8days will conservatively assume that the ground plane andinhalation pathway critical receptors are at the site boundary,i e, X/Q and D/Q, respectively, are calculated at the siteboundary.

Refinement of Offsite Doses Resulting from Emergency Condenser VentReleases

The doses resulting from the operation of the emergency condensersand calculated in accordance with 3.2.2 may be refined using datafrom actual environmental samples. Ground deposition samples willbe obtained from an area or areas of maximum projected deposition.These areas are anticipated to be at or near the site boundary andnear projected plume centerline. Using the methodology found inRegulatory Guide 1.109, thedose will be calculated to the maximumexposed individual. This dose will then be compared to the dose

003856LL 23


3.4 (Cont'd)

calculated in accordance with 3.2.2. The comparison will result inan adjustment factor of less than or greater than one which will beused to adjust the other doses from other pathways. Otherenvironmental samples may also be collected and the resultantcalculated doses to the maximum exposed individual compared to thedose calculated per 3.2.2. Other environmental sample media mayinclude milk, vegetation (such as garden broadleaf vegetables),etc. The adjustment factors from these pathways may be applied tothe doses calculated per 3.2.2 on a pathway by pathway basis orseveral pathway adjustment factors may be averaged and used toadjust calculated doses.

Doses calculated from actual environmental sample media will bebased on the methodology presented in Regulatory Guide 1.109. Theregulatory guide equations may be slightly modified to account forshort intervals of time (less than one year) or modified forsimplicity purposes by deleting decay factors. Deletion of decayfactors would yield more conservative results.

003856LL 24

Unit 1 ODOMRevision 12June 1993

40 CFR 190 REQUIREMENTS

The "Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b) asfollowers

"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 alight-water-cooled nuclear power plant using uranium fuel, andreprocessing of spent uranium fuel, to the extent that thesedirectly support the production of electrical power for public useutilizing nuclear energy, but excludes mining operationsioperations at waste disposal sites, transportation of anyradioactive material in support of these operations, and the reuseof recovered non-uranium special nuclear and by-product materialsfrom the cycle."Section 3.6.15.d of the Technical Specifications requires that whenthe calculated doses associated with the effluent releases exceedtwice the applicable quarter or annual limits, the licensee shallevaluate the calendar year doses and, if required, submit a SpecialReport to the NRC and limit subsequent releases such that the dosecommitment to a real individual from all uranium fuel cycle sourcesis limited to 25 mrem to the total body or any organ (except thethyroid, which is limited to 75 mrem). This report is todemonstrate that radiation exposures to all real individuals fromall uranium fuel cycle sources (including all liquid and gaseouseffluent pathways and direct radiation) are less than the limits in40 CFR Part 190. If releases that result in doses exceeding the 40CFR 190 limits have occurred, then a variance from the NRC topermit such releases will be requested and if possible, action willbe taken to reduce subsequent releases.

The report to the NRC shall contain:

1) Identification of all uranium fuel cycle facilities oroperations within 5 miles of the nuclear power reactor units atthe site that contribute to the annual dose of the maximumexposed member of the public.

12

2) Identification of the maximum exposed member of the public anda determination of the total annual dose to this person fromexisting pathways and sources of radioactive effluents anddirect radiation.

The total body and organ doses resulting from radioactive materialin liquid effluents from Nine Mile Point Unit 1 will be summed withthe maximum doses resulting from the releases of noble gases,radioiodines, and particulates for the other calendar quarters (asapplicable) and from the calendar quarter in which twice the limitwas exceeded. The direct dose components will be determined byeither calculation or actual measurement. Actual measurements willutilize environmental TLD dosimetry. Calculated measurements willutilize engineering calculations to determine a projected directdose component. In the event calculations are used, themethodology will be detailed as required in Section 6.9.1.e of theTechnical Specifications.The doses from Nine Mile Point Unit 1 will be added to the doses tothe maximum exposed individual that are contributed from otheruranium fuel cycle operations within 5 miles of the site. Other ) ]p

003856LL 25


4.0 (Cont'd)

uranium fuel cycle facilities within 5 miles of the Site includeNine Mile Point Nuclear Station Unit 2 and the James A. Fitzpatrick ]2Nuclear Power Plant. Doses from other facilities will becalculated in accordance wi.th each facilities'DCM.For the purpose of calculating doses, the results of theRadiological Environmental Monitoring Program may be i.ncluded forproviding more refined estimates of doses to a real maximum exposedindividual. Estimated doses, as calculated from station effluents,may be replaced by doses calculated from actual environmentalsample results. Reports will include all significant details ofthe dose determination if radiological sampling and analyses areused to determine if the dose limits of 40CFR190 are exceeded.

12

4+1 Evaluation of Doses Froa Liquid Effluents

For the evaluation of doses to real members of the public fromliquid effluents, the fish consumption and shoreline sedimentground dose wi.ll be considered. Since the doses from other aquaticpathways are insignificant, fish consumption and shoreline sedimentare the only two pathways that wi.ll be considered. The doseassociated with fish consumption may be calculated usi.ng effluentdata and Regulatory Guide 1.109 methodology or by calculating adose to man based on actual fish sample analysis data. Because ofthe nature of the receptor location and the extensive fishing inthe area, the critical i.ndividual may be a teenager or an adult.The dose associated wi.th shoreline sediment i.s based on theassumption that the shoreline would be uti.lized as a recreationalarea. This dose may be derived from liquid effluent data andRegulatory Guide 1.109 methodology or from actual shorelinesediment sample analysis data.

Equations used to evaluate doses from actual fish and shorelinesediment samples are based on Regulatory Guide 1.109 methodology.Because of the sample medium type and the half-lives of theradionuclides historically observed, the decay corrected portionsof the equations are deleted. This does not reduce theconservatism of the calculated doses but increases the simplicityfrom an evaluation point of view. Table 3-23 presents theparameters used for calculating doses from liquid effluents.

12

The dose from fish sample media is calculated ass

Where<

~I (Clf (U) (D~) f) (1E+3)

Cv

~ The total annual dose to organ $ , of an individualof age group a, from nuclide i, via fish pathway p,in mrem per year.

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

12

U The consumption rate of fish in kg/yr.

1E+3 ~ Grams per ki.logram.

003856LL 26


4.1 (Cont'd)

(D~) ~ The ingestion dose factor for age group a, nuclidei, fish pathway p, and organ j, (Reg. Guide 1.109,Table E»ll) (mrem/pCi).

The doseas'hefractional portion of the year over which the

dose is applicable.

from shoreline sediment sample media is calculated

~ Z) [C„(U) (4E+4) (0.3) (D~) f )

Where:

R ~ The total annual dose to organ j, of an individualof age group a, from nuclide i, via the sedimentpathway p, in mrem per year.

C~ ~ The concentration of radionuclide i in shorelinesediment in pCi/gram.

The usage factor, (hr/yr) (Reg. Guide 1.109).

4E+4 ~ The product of the assumed density of shorelinesediment (40 kilogram per square meter to a depth of2.5 cm) times the number of grams per kilogram.

0.3 ~ The shore width factor for a lake.

D< ~ The dose factor for age group a, nuclide i, sedimentpathway s, and organ j. (Rep. Guide 1.109,Table E-6)(mrem/hr per pCi/m ).

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

4.2 Evaluation of Doses Proa Gaseous EffluentsFor the evaluation of doses to real members of the public fromgaseous effluents, the pathways contained in section 3.2.2.3 of theODCM will be considered. These include the deposition, inhalationcows milk, goats milk, meat, and food products (vegetation) .However, any updated field data may be utilized that concernslocations of real individuals, real time meteorological data,location of critical receptors, etc. Data from the most recentcensus and sample location surveys should be utilized. Doses mayalso be calculated from actual environmental sample media, asavailable. Environmental sample media data such as TLD, air sample,milk sample and vegetable (food crop) sample data may be utilized inlieu of effluent calculational data.

003856LL 27


4 ~ 2 (Coat')Dos es to member of the public from the pathways contained in ODCMsection 3.2.2.3 as a result of gaseous effluents will be calculatedusing the dose factors of Regulatory Gui.de 1.109 or the methodologyof the ODCMi as applicable. Doses calculated from environmentalsample media will be based on the methodologies found in RegulatoryGuide 1.109.

I12

4.3 Evaluation of Doses Froa Direct Radiation

The dose contribution as a result of direct radiation shall be I12considered when evaluating whether the dose limitations of 40 CFR 190have been exceeded.

4+4

Direct radiation doses as a result of the reactor, turbi.ne andradwaste buildi.ngs and outside radioactive storage tanks (asapplicable) may be evaluated by engineering calculations or byevaluating environmental TLD results at criti.cal receptor locations,site boundary or other special interest locations. For theevaluation of direct radiation doses utilizing environmental TLDs,the critical receptor in question, such as the critical residence,etc., will be compared to the control locations. The comparisoninvolves the difference in environmental TLD results between thereceptor location and the average control location result.Doses to Members of the Public Within the site Boundary

The Semi,-Annual Radioactive Effluent Release Report shall include anassessment of the radiation doses from radioactive liquid and gaseouseffluents to members of the public due to their activities inside thesite boundary as defined by Figure 5.1-1 of the specifications. Amember of the public, as defined by the Technical Specifications,would be represented by an individual who visits the sites'nergyCenter for the purpose of observing the educational displays or forpicnicking and associated acti.vities.Fishing is a ma)or recreational activity in the area and on the Siteas a result of the salmonoid and trout populations in Lake Ontario.Fishermen have been observed fishing at the shoreline near the Energy i]2Center from April through December in all weather conditions. Thus,fishing is the ma)or activi.ty performed by members of the publi.cwithin the site boundary. Based on the nature of the fishermen andundocumented observations, it is conservatively assumed that themaximum exposed indivi.dual spends an average of 8 hours per weekfishing from the shoreline at a location between the Energy Center F12and the Unit 1 facility. This estimate is considered conservativebut not necessarily excessive and accounts for occasions whereindividuals may fish more on weekends or on a few days in March ofthe year.

The pathways considered for the evaluation include the i.nhalationpathway, the ground dose pathway with the resultant whole body andskin dose and the direct radiation dose pathway with the associ.atedwhole body dose. The direct radiation dose pathway, in actuality,i.ncludes several pathways. These include: the direct radiationgamma dose to an individual from an overhead plume, a gamma i 12submersion plume dose (as applicable), possible direct. radiation dosefrom the facility and a ground plane dose (deposition). Because thelocation is in close proximity to the site, any beta plume submersiondose i.s felt to be i.nsignificant.

003856LL 28


4.4 (Cont'd)

other pathways, such as the ingestion pathway, are not applicablesince these doses are included under calculations for doses tomembers of the public outside of the site boundary. In addition,pathways associated with water related recreational activities, otherthan fishing, are not applicable here. These include swimming,boating.and wading whi.ch are prohibited at the facility.The inhalation pathway is evaluated by identifying the applicableradionuclides (radioiodine, triti.um and particulates) in the effluentfor the appropriate time period. The radionuclide concentrations arethen multiplied by the appropriate X/Q value, inhalation dose factor,air i.ntake rate, and the fractional portion of the year in question.Thus, the inhalation pathway is evaluated using the followingequation adapted from Regulatory Guide 1.109. Table 3-23 presentsthe reference for the parameters used in the following equation.~OTE c The following equation is adapted from equations C-3 andC-4 of Regulatory Guide 1.109. Since many of the factors

are in units of pCi/m', m'/sec., etc., and since theradionuclide decay expressions have been deleted becauseof the short distance to the receptor location, theequation presented here is not identical to the RegulatoryGuide equations.

Where~

Zl ( (Cl) F (X/Q) (DFA)U,(BR) It)

Dj, The maximum dose from all nuclides to the organ jand age group (a) i.n mrem/yr.

C, The average concentration in the stack release ofnuclide i for the period in pCi/m'.

Unit, 1 average stack flowrate in m'/sec.

X/Q The plume dispersion parameter for a locationapproximately 0.50 mi.les west of NMP-1; the plumedispersion parameter is 8.9E-06 (stack) and wasobtained from the C.T. Main five year averageannual X/Q tables. The stack (elevated) X/{} isconservative when based on 0.50 miles because ofthe close proximity of the stack and the receptorlocation.

(DFA)U, The dose factor for nuclide i, organ j, and agegroup a in mrem per pCi (Reg. Guide 1.109, TableE-7) ~

(BR) ~ Annual air intake for individuals in age group ain m3 per year (obtained from Table E-5 ofRegulatory Guide 1. 109) .

Fractional portion of the year for whichradionuclide i was detected and for which a doseis to be calculated (in years).

003856LL 29


4.4 (Coat'd)

The ground dose pathway (deposition) will be evaluated by obtainingat least one soi.l or shoreline sediment sample in the area wherefishing occurs. The dose wi.ll then he calculated using the sampleresults, the time period in question, and the methodology based onRegulatory Guide 1.109 as presented in Section 4.1. The resultantdose may be adjusted for a background dose by subtracting theappli.cable off-site control soil or shoreline sediment sampleradionuclide activities. In the event it is noted that fishing isnot performed from the shoreline, but is instead performed in thewater (i.e., the use of waders), then the ground dose pathway(deposition) may not be evaluated.

The direct radiation gamma dose path~ay i.ncludes any gamma doses froman overhead plume, potential submersion in the plume, possible directradiati.on from the facility and ground plane dose (deposition). Thisgeneral pathway will be evaluated by average envt.ronmental TLDreadings. At least two environmental TLDs will be utilized at onelocation in the approximate area where fishing occurs. The TLDs willbe placed in the field on approximately the beginning of a calendarquarter and removed on approximately the end of the calendar quarter.For the purposes of this evaluation, TLD data from quartezs 2, 3, and4 will he utili.zed.The average TLD readings will he adjusted by the average control TLDreadings. This is accompli. shed by subtracting the average quarterlycontrol TLD value from the average fishi.ng location TLD value. Theapplicable quarterly control TLD values will be utilized afteradjusting for the appropriate time period (as applicable). In theevent of loss or theft of the TLDs, results from a TLD or TLDs in anearby area may be utilized.

003856LL 30


5 ~ 0

F 1

ENVIRONMENTAL MONITORING PROGRAM

Sampling Stations

The current sampling locations are specified in Table 5-1 and Figures5.1-1, 5.1-2. The meteorological tower is shown in Figure 5.1-1.The location is shown as TLD location 17. The RadiologicalEnvironmental Monitoring Program is a joint effort between theNiagara Mohawk Power Corporation and the New York Power Authority,the owners and operators of the Nine Mile Point Unit 1 and theJames A. Fit@Patrick Nuclear Power Plant, respectively. Samplinglocations are chosen on the basis of historical average dispersion ordeposition parameters from both units. The environmental samplinglocation coordinates shown on Table 5-1 are based on the NMP-2reactor centerline.

The average dispersion and deposition parameters have been calculatedfor a 5 year period, 1978 through 1982. These dispersioncalculations are attached as Appendix E.

The calculated dispersion or deposition parameters will be comparedto the results of the annual land use census. If it is determinedthat a milk sampling location exists at a location that yields asignificantly higher (e.g. 50%) calculated D/Q rate, the new milksampling location will be added to the monitoring program within 30days ~

If a new location is added, the old location that yields the lowestcalculated D/Q may be dropped from the program after October 31 ofthat year.

5 ' Interlaboratory Comparison Program

Analyses shall be performed on samples containing known quantities ofradioactive materials that are supplied as part of a Commissionapproved or sponsored Interlaboratory Comparison Program, such as theEPA Crosscheck Program. Participation shall be only for those media,e.g., air, milk, water, etc., that are included in the Nine MilePoint Environmental Monitoring Program and for which crosschecksamples are available. An attempt will be made to obtain a QC sampleto program sample ratio of 5% or better. The site identificationsymbol or the actual Quality Control sample results shall be reportedin the Annual Radiological Environmental Operating Report so that theCommission staff may evaluate the results.Specific sample media for which EPA Cross Check Program samples areavailable include the following:

— gross beta in air particulate filters- gamma emitters in air particulate filters— gamma emitters in milk— gamma emitters in water— tritium in water- I-131 in water

5 ~ 3 Capabilities for Thermoluninescent Dosimeters Used for EnvironmentalMeasurements

Required detection capabilities for thermoluminescent dosimeters usedfor environmental measurements required by Table 4.6.20-1, footnote bof the Technical Specifications are based on ANSI Standard N545,section 4.3. TLDs are defined as phosphors packaged for field use.Zn regard to the detection capabilities for thermoluminescentdosimeters, only one determination is required to evaluate the above

003856LL 31


0

5.3 (Cont'd)

capabilities per type of TLD. Furthermore, the above capabilitiesmay be determined by the vendor who supplies the TLDs. Requireddetection capabilities are as follows:

5 ~ 3 ~ 1 Uniformity shall be determined by giving TLDs from the same batch a'

exposure equal to that resulting from an exposure rate of 10 mR/hrduring the field cycle. The responses obtained shall have a relativestandard deviation of less than 7.5%. A total of at least 5 TLDsshall be evaluated.

5 ~ 3 ~ 2 'eproducibility shall be determined by giving TLDs repeated exposuresequal to that resulting from an exposure rate of 10 uR/hr during thefield cycle. The average of the relative standard deviations of theresponses shall be less than 3.0%. A total of at least 4 TLDs shallbe evaluated.

5,3 ~ 3 Dependence of exposure interpretation on the length of a field cycleshall be examined by placing TLDs for a period equal to at least afield cycle and a period equal to half the same field cycle in anarea where the exposure rate is known to be constant. This testshall be conducted under approximate average winter temperatures andapproximate average summer temperatures. For these tests, the ratioof the response obtained in the field cycle to twice that obtainedfor half the field cycle shall not be less than 0.85. At least 6TLDs shall be evaluated

5.3.4 Energy dependence shall be evaluated by the response of TLDs tophotons for several energies between approximately 30 keV and 3 MeV.The response shall not differ from that obtained with the calibrationsource by more than 25% for photons with energies greater than 80 keVand shall not be enhanced by more than a factor of two for photonswith energies less than 80 keV. A total of at least 8 TLDs shall beevaluated.

5 3 ' The directional dependence of the TLD response shall be determined bycomparing the response of the TLD exposed in the routine orientationwith respect to the calibration source with the response obtained fozdifferent orientations. To accomplish this, the TLD shall be rotatedthrough at least two perpendicular planes. The response averagedover all directions shall not differ from the response obtained inthe standard calibration position by moze than 10%. A total of atleast 4 TLDs shall be evaluated.

5.3.6 Light dependence shall be determined by placing TLDs in the field fora period equal to the field cycle under the four conditions found inANSI N545, section 4.3.6. The results obtained for the unwrappedTLDs shall not differ from those obtained for the TLDs wrapped inaluminum foil by more than 10%. A total of at least 4 TLDs shall beevaluated for each of the four conditions.

5 ~ 3o7 Moisture dependence shall be determined by placing TLDs (that is, thephosphors packaged for field use) for a period equal to the fieldcycle in an area where the exposure rate is known to be constant.The TLDs shall be exposed under two conditions: (1) packaged in athin, sealed plastic bag, and (2) packaged in a thin, sealed plasticbag with sufficient water to yield observable moistuze throughout thefield cycle. The TLD or phosphor, as appropriate, shall be driedbefore readout. The response of the TLD exposed in the plastic bagcontaining water shall not differ from that .exposed in the regularplastic bag by more than 10%. A total of at least 4 TLDs shall beevaluated for each condition.

003856LL 32


5+3+8 Self irradiation shall be determined by placing TLDs for a periodequal to the field cycle in an area where the exposure rate is lessthan 10 uR/hr and the exposure during the field cycle is known. Ifnecessary, corrections shall be applied for the dependence ofexposure interpretation on the length of the field cycle (ANSI N545,section 4.3.3). The average exposure inferred from the responses ofthe TLDs.shall not differ from the known exposure by more than anexposure equal to that resulting from an exposure rate of 10 uR/hrduring the field cycle. A total of at least 3 TLDs shall beevaluated.

003856LL 33


TABLE 1-1Average Energy Per Disintegration

ISOTOPEAr-41

Kr-83m

Kr;85

Kr«85m

Kr-87

Kr-88

Kr-89N

Kr-90

Xe-131M

Xe-133

Xe-133m

Xe-135

Xe-135m

Xe-137

Xe-138

1 ~ 294

0.00248

0.0022

0.159

0.793

1.95

2.22

2.10

0.0201

0.0454

0.042

0.247

0.432

0.194

1.18

fRRef(3)

(2)

(2)

~Eev dice)0.464

0.0371

0.250

0.253

1.32

0.377

1.37

1.01

0.143

0.135

0.19

0.317

0.095

1.64

0.611

~Ref(3)

(2)

(2)

(2)

(3)

(4)

ORNL-4923, Radioactive Atoms — Su lement I, M. S. Martin,November 1973.

NEDO-12037, "Summary of Gamma and Beta Emitters and Intensity Data";M.E. Meek, R.S. Gilbert, January 1970. (The average energy wascomputed from the maximum energy using the ICRP II equation, not the1/3 value assumption used in this reference).

NCRP Report No. 58, "A Handbook of Radioactivity MeasurementsProcedures"; 1978

The average energy includes conversion electrons.

003856LL 34


NUCLIDE BONE

H3

Cr 51

Cu 64

Mn 54

LIVER2.90E-1

1.13E-11.87E+1

FE 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Mn 56

Mo 99

Na 24

I 131

I 133

Ni 65

I 132

Cs 134

Cs 136

Cs 137

Ba 140

Ce 141

Nb 95

La 140

Ce 144

2 '72.40E-42.34E+12 '7

3.03E+1 3.54E+14.22 6. 15

1 ~ 33E-3 1 ~ 51E-4

1 ~ 58E-4 3.21E-43.54E+2 6.60E+24.05E+1 1.19E+24.91E+2 5.75E+21.50E+2 1.50E-17. 21E-2 4. 40E-23.85E-2 1.59E-21.18E-2 4.67E-32 '9 1.14

1.31E+1 8.442 '4E+1 4.96E+1

3.341 ~ 02E+1

l.72E+1 5 ~ 91E+1

2.32E+31.74E+41 ~ 91E-1 4.66E-2

5.23E-24.232.261.96E+18.342 '0E+12.73E+16.66E+14.43E+33.30E-24.15E-54 '72 '7 2.37

1.91E-l4.14

2.87E+1

5.02E-22.07E-43.50E+12.37

1.57E+1 1.17E+4 4.17E+11. 806.85E-5

1.12E+3 7.23

1.14E-4 1.50E-2 3.58E-46.67E+14.45E+14.07E+17.745.17E-39.18E-31.20E-31.57E-1

1.70E+24.75E+11.54E+23.57E-21.36E-21.14E-2

4,62E-1

TABLE 2-1ALL VALUES - LIQUID*

RADWASTE TANKINFANT

mrem - mlhr - pCi

T BODY THYROID KIDNEY

2.90E-1 2.90E-1 2.90E-11.29E-2 8.39E-3 1.83E-3

LUNG GI-TRACT

2.90E-1 2.90E-11.63E-2 3.75E-1

2.326.86

4. 13 1.07

2.37

8.332.42E+15.00E+14.77E+12.17E+22.32E+12.18E-27.712.371.281.041.15E-22.60E-4

6.97E+1 1.799.71E+1 1.816.24E+1 1.809.23E-2 3.69E+1

2.27E+11.34E+15.48E+11.60E+2

1.47E+1 2.37E+1

* Calculated in accordance with NUREG 0133, Section 4.3.1; and RegulatoryGuide 1.109, Regulatory position C, Section l.

003856LL 35


NUCLIDE

H3

Cr 51

Cu 64

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

BONE LIVER4.39E-1

2 '3E-2 2 '3E-22.51E-6 2.706.92 3.38E+39.21E+2 4.88E+21.30E+3 2 '1E+31.89 7.46E+11.12E+2 3.28E+22.15E+4 5.73E+43.26E+4 1.10E-4

1.401. 63

7.86E-1 2.30E-12.51E-6 6.52

9.06E+2 6.921.51E+21.05E+3 1.342 '4E+2 1.89

9.53E+2

1.341.89

7.48E+2 1.12E+2 1.12E+23 '6E+4 3.85 3.61E+49.32E+2 1.10E-4 1.10E-4

TABLE 2-2A„, VALUES - LIQUID"

RADWASTE TANKCHILD

mrem - mlhr - pCi

T BODY THYROID'IDNEY4.39E-1 4 '9E-1 4 39E-1

LUNG GI-TRACT4.39E-1 4-39E-11.42 7.31E+12.51E-6 1.27E+26.92 2.84E+32 '6E+2 9.05E+16.12E+2 2.19E+31 ~ 89 4.26E+21.12E+2 1.31E+33.85 1.01E+4lilOE-4 1.26E+3

Sr 90

Zr 95

Mn 56

Mo 99

Na 24

I 133

Ni 65

I 132

Cs 134

4.26E+51.70 1.33

1.65E-15.35E-3 9 '7E+11.52E+2 1.52E+22.09E+2 2.10E+23.39E+12.67E-1

4.19E+12.51E-2

6 13E-3 1 ~ 13E-23.68E+5 6 '4E+5

Cs 136 3.52E+4 9.67E+4Cs 137

Ba 140

5.15E+5 4.93E+53.61E+2 3.96E-l

Nb 95

La 140

Ce 144

5.21E+2 2.03E+21.50E-1 5.93E-25.00 1.81

Ce 141 1.50E-1 1.07E-l

1 08E+5

1.323.73E-2

1.23 1.382.00E-1

2.37E+1 5.35E-3 '.04E+21.52E+2 1.52E+2 1.52E+21.19E+2 6.94E+4 3.45E+21.59E+1 7.78E+3 6.98E+11.47E-25.18E-3 5.22E-1 1.72E-21 ~ 27E+5 3.54E+1 1.87E+56. 26E+4 6 ~ 21E-1 5. 15E+4

7.28E+4 5.37E+1 1.61E+52.11E+1 7.96E-2 1.82E-16.99E-2 6.34E-2 8.24E-21.45E+2 6.39E-1 1.91E+22.68E-2 1 ~ 03E-2 1.03E-26.06E-1 3.58E-1 1.16

1.235.74E+31.08E+22.39E+1

5.35E-3 7.91E+11 ~ 52E+2 1.52E+25.60E-2 1.87E+11.38E-4 1.69E+1

3.081.32E-2

6.72E+4 3.29E+37.68E+3 3.40E+35.78E+4 3.14E+32.68E-1 1.83E+26.34E-2 5.40E+16.39E-1 3.75E+51 ~ 03E-2 1.36E+33.58E-1 3.80E+2


003856LL 36


NUCLIDE BONE LIVER3.28E-1H3

Cr 51

Cu 64

Mn 54

1.02E-1 1.02E-11.20E-5 2.893.31E+1 4.34E+36.94E+2 4.92E+21 '7E+3 2.49E+3

Fe 55

Fe 59

Co 58

Co 60

9.03 9 82E+1

Zn 65

Sr 89

5 '6E+2 7.96E+22.10E+4 7.28E+42.44E+4 5.24E-4

1.391.36

8.16E-1 3.84E-11.20E-5 7.32

8.87E+2 3.31E+1 1.32E+31.15E+29.64E+2 6.412.15E+2 9.03

6. 41

9.031.12E+3 5.36E+2 5.36E+23.40E+4 1.84E+1 4.66E+46.98E+2 5.24E-4 5.24E-4

TABLE 2-3A VALUES — LIQUID*

RADWASTE TANKTEEN

mrem - mlhr — pci


3.28E-1 3.28E-1 3.28E-1LUNG GI-TRACT

1.94 2.16E+21.20E-S 2.24E+23.31E+1 8.86E+33.12E+2 2.13E+27.89E+2 5.87E+39.03 1.24E+35.36E+2 3.93E+31.84E+1 3.08E+45.24E-4 2.90E+3

3.28E-1 3.28E-1

Sr 90Zr 95

Mn 56

Mo 99

Na 24

I 131

I 133

Ni 65

I 132

Cs 134

Cs 136

Cs 137

Ba 140

Ce 141

Nb 95

La 140

Ce 144

4. 66E+5

6.20 6.001.81E-1

1.15E+55.973.22E-2

5.90 6.042.29E-1

2.56E-2 9.22E+11.39E+2 1.39E+2

1.76E+1 2.56E-2 '.11E+21.39E+2 1.39E+2 1.39E+2

2.53E+1 4.29E+12.08E-1 2.66E-24.90E-2 1.28E-23 05E+5 7.18E+52.98E+4 1.17E+54.09E+5 5.44E+52.35E+2 4.10E-13.46E-1 3.32E-14.44E+2 2.48E+21.57E-1 1.02E-1

1.31E+1 5.99E+3 7.52E+11.21E-24.60E-3 4.32E-1 2.02E-23.33E+5 1.69E+2 2.28E+57.88E+4 2.97 6.38E+41.90E+5 2.57E+2 1.85E+51.55E+1 3.81E-1 4.79E-13.07E-1 3.04E-1 3.17E-1

2.40E+21.18E+2 3.066.35E-2 4.94E-2 4.94E-2

3.99 2 '5 1.83 1.71 2.27

1.55E+2 2.17E+2 1.16E+2 6.31E+4 3.73E+2

5.901.31E+42.28E+21.19E+1

3.06 1.05E+64.94E-2 3.05E+3

5.74E+21.71

2.56E-2 1.65E+21.39E+2 1.39E+22.68E-1 4.30E+16.60E-4 3.25E+1

1.445.59E-3

8.73E+4 9.10E+31.01E+4 9.44E+37 '1E+4 7 '9E+35.75E-1 3.63E+23.04E-1 8.16E+1

* Calculated in accordance with NUREG 0133, Section 4.3.1; and RegulatoryGuide 1.109, Regulatory position C, Section 1.

003856LL 37


0

NUCLIDE

H3

Cr 51

Cu 64

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Mn 56

Mo 99

Na 24

I 131

I 133

Ni 65

I 132Cs 134

Cs 136

Cs 137

Ba 140

Ce 141

Nb 95

La 140

Ce 144

BONE LIVER4.45E-1

1.82E-2 1-82E-2

5.942 '54.38E+3

6 64E+2 4.58E+21.03E+3 2.43E+31.62 9.15E+19.60E+1 2.57E+22.31E4 7 '6E+42.25E+4 9.39E-S5.60E+51.36 1.15E

1 ~ 73E-1

2 '8 1.22

4.58E-3 8.70E+11.35E+2 1.35E+21.45E+2 2.07E+22 35E+1 4.09E+11.93E-1 2.51E-24 68E-3 1.25E-22.98E+5 7.08E+52.96E+4 1.17E+53.82E+5 5.22E+52.24E+2 3.49E-19.53E-2 8.20E-24.39E+2 „,2.44E+21.11E-1 6.03E-2

1.27 7.64E-1 2 '3E-11.298.41E+2 5.941.07E+29.31E+2 1.152.03E+2 1.62

6.941.31E+3

l. 15

1.626.71E+2 9.60E+1 9.60E+13.32E+4 3.30 4.92E+46.45E+2 9.39E-5 9 '9E-51.37E+51.123.07E-2

1.06 1.212.20E-1

l. 66E+1 4. 58E-3 1. 97E+2

1.35E+2 1.35E+2 1.35E+21.19E+2 6.79E+4 3.55E+21 25E+1 6.02E+3 7.14E+11.14E-24.38E-3 4.38E-1 2.00E-25.79E+5 3.03E+1 2.29E+58 '2E+4 5.32E-1 6.51E+43.42E+5 4.60E+1 1.77E+51.47E+1 6.83E-2 1.64E-15.75E-2 5.44E-2 6.72E-21.32E+2 5.47E-1 2.41E+22.24E-2 8.84E-3 8.84E-34.24E-1 3.07E-1 8.47E-1

TABLE 2-4A„, VALUES - LIQUID*

RADWASTE TANKADULT

mrem — mlhr — pCi


4.45E-l 4.45E-1 4.45E-1LUNG GI-TRACT

4.45E-1 4.45E-11.67

5 '43.14E+22.35E+21.34E+4

2.56E+2 2.63E+26.79E+2 8.09E+31.62 1.82E+39.60E+1 4.99E+33.30 4.63E+49.39E-5 3.60E+3

1.061.62E+43.06E+25 '2

4-58E-3 2.02E+21.35E+2 1.35E+24.80E-2 5.47E+11.18E-4 3.68E+1

6.36E-12.35E-3

7.61E+4 1.24E+48.93E+3 1.33E+45.90E+4 1.02E+42.29E-1 ,4.61E+25.44E-2 1.06E+25.47E-1 1.48E+68.84E-3 3.78E+33.07E-1 7.37E+2


003856LL 38


NUCLIDE

H3

Cr 51

Cu 64

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90Zr 95

Mn 56

Mo 99

Na 24

I 131

I 133

Ni 65

I 132

Cs 134Cs 136

Cs 137

Ba 140Ce 141

Nb 95

La 140

Ce 144

BONE LIVER7.43E-4

1.08E-23.41E-6

1.58E-23.86E-7

4.05E-7 8.22E-79.08E-1 1.691 04E-1 3 06E-11.26 1.473.85E-1 3.85E-41.85E-4 1.13E-49.88E-5 ,4.07E-S3.03E-5 1.20E-57.16E-3 2.93E-3

2.89E-44.79E-2

3.35E-2 2.16E-27.29E-2 1.27E-1

8.58E-32.60E-2

4.42E-2 1.52E-15.954.46E+14.90E-4 1.19E-4

6.17E-76.00E-2

6.07E-3 6.07E-37.77E-2 9.16E-2

1.34E-41.08E-25.78E-35 '2E-22.14E-26.15E-26.99E-21.71E-l1.14E+18.47E-S1.06E-71 ~ 17E-2

4.89E-41.06E-2

7.35E-2

1.29E-45.30E-7

'.97E-26.07E-3 6.07E-3 6.07E-34.03E-2 3.01E+1 1.07E-14.62E-3 2.871.76E-7

1.85E-2

2.93E-7 3.85E-S 9.17E-71. 71E-11.14E-11.04E-11.99E-21.33E-S2 35E-53.08E-64.02E-4

4.36E-11 22E-13.95E-19.15E-53.48E-S2.92E-5

1.19E-3

TABLE 2-5+, VALUES — LIQUID*

EMERGENCY CONDENSER VENTINFANT

mrem - mlhr - pCi


7.43E-4 7.43E-4 7.43E-43.30E-S 2.15E-5 4.70E-6

LUNG GI-TRACT7.43E-4 7.43E-44.18E-5 9.61E-4

5 '4E-31.76E-2

1.06E-2 2.75E-33.76E-2 6.08E-2

2.14E-26 '9E-21.28E-11.22E-15.57E-15.95E-25.60E-51.98E-2

6.07E-3 6.07E-33.27E-32.67E-32.94E-56 '6E-7

1.79E-1 4.60E-32.49E-2 4.64E-31.60E-1 4.61E-32.37E-4 9.47E-2

5.82E-23.43E-21 41E-14.11E-1


003856LL 39


NUCLIDE

H3

Cr 51

Cu 64

Mn 54

Pe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Mn 56

Mo 99

Na 24

I 131

I 133

Ni 65

I 132

Cs 134

Cs 136

Cs 137 .

Ba 140Ce 141Nb 95

La 140

Ce 144

BONE LIVER1.44E-1

1.64 5.15E-1

3.78E-S 3.78E-52.63

1 23E-2 3.36E+39.04E+2 4.79E+21.28E+3 2.07E+33.36E-3 7 ~ 01E+1

1.99E-1 2.08E+22 '5E+4 5.73E+43.07E+44.01E+53.01E-1 6.78E-2

1.65E-18.16E+1

1 ~ SOE+2 1.50E+21.86E+2 1 ~ 87E+2

3 '8E+1 3.81E+12.66E-1 2.50E-26. 01E-3 1 ~ 10E-2

3 68E+5 6 '4E+53 '1E+4 9.66E+45.14E+5 4 92E+5

2.48E+2 2.17E-13.08E-2 1.54E-25.21E+2 2.03E+21.31E-1 4 '9E-2

1.371.59

7.58E-1 2.07E-16.35

8.95E+2 1.23E-2 9.42E+21.49E+21.03E+3 2.38E-3 2.38E-32.15E+2 3.36E-3 3.36E-36.14E+2 1.99E-1 1.99E-13.56E+4 6.84E-3 3.61E+48.78E+21.02E+56.06E-2 2.19E-3 9.61E-23.73E-22.02E+1

2.00E-11 ~ 74E+2

1.50E+2 1.50E+2 1.50E+21 06E+2 6.19E+4 3.08E+21 44E+1 7 '7E+3 6.35E+11.46E-25.08E-3 5.12E-1 1.69E-21.27E+5 6 '9E-2 1.87E+56.25E+4 1.10E-3 5.14E+47.27E+4 9.55E-2 1.60E+51.45E+1 1.42E-4 7 '9E-22.39E-3 1.13E-4 6.83E-31.45E+2 1 ~ 14E-3 1.90E+21.55E-2 1.83E-5 1.83E-58.81E-2 6.36E-4 2.85E-1

TABLE 2-6VALUES — LIQUID*

EMERGENCY CONDENSER VENTCHILD

mrem - mlhr — pCi


1.44E-1 ~ 1.44E-1 1.44E-1LUNG GI-TRACT

1.44E-l 1.44E-11.38 7.24E+1

1.23E+21.23E-2 2.82E+32.71E+2 8.88E+16.00E+2 2.15E+33.36E-3 4.09E+21.99E-1 1.15E+36.84E-3 1.01E+4

1.19E+35.40E+3

2.19E-3 6.84E+12.39E+16.75E+1

1.50E+2 1.50E+21.67E+11.53E+13.071.30E-2

6.71E+4 3.25E+37.67E+3 3.40E+35.77E+4 3.08E+31.30E-1 1.26E+21.13E-4 1.91E+11.14E-3 3 '5E+51.83E-S 1.28E+36.36E-4 1.34E+2


003856LL 40


NUCLIDE BONE LIVERH3 1.74E-lCr 51 1.81E-4 1.81E-4Cu 64 2 '6 1.35 7.24

TABLE 2-7VALUES — LIQUID*

EMERGENCY CONDENSER VENTTEEN

mrem — mlhr — pci


1 '4E-1 1.74E-1 1.74E-11.28 7.12E-1 2.81E-1

LUNG GI-TRACT

1.83 2.15E+22.22E+2

1.74E-1 1.74E-1

Fe 55 6.89E+2 4.88E+2Fe 59 1.05E+3 2.46E+3Co 58 1.61E-2 8.78E+1Co 60 9.53E-1 2.57E+2Zn 65 2.10E+4 7.28E+4Sr 89 2.38E+4Sr 90 4.54E+5Zr 95 2.56E-1 8.80E-2Mn 56 1.81E-1Mo 99

Na 24

I 133

Ni 65

I 132

Cs 134

Cs 136

Cs 137

Ba 140Ce 141

Nb 95

La 140

Ce 144

8.57E+11.38E+2 1.38E+21.47E+2 2.06E+22.42E+1 4.11E+12.08E-1 2.66E-24.86E-3 1.27E-23.05E+52.98E+4

7.18E+51.17E+5

4.09E+5 5.44E+51.96E+2 2.47E-22.43E-2 1.64E-24.41E+2 2.45E+21 '5E-1 5.17E-21.27 5.28E-1

1.14E+29.50E+2 1.14E-2 1.14E-22.02E+2 1 61E-2 1.61E-25.78E+2 9.53E-1 9.53E-13.39E+4 3.28E-2 4.66E+46.81E+21.12E+56.38E-2 1.05E-2 1.24E-13.22E-21.63E+1

2.29E-1'.96E+2

1.38E+2 1.38E+2 1.38E+21 10E+2 6.00E+4 3.54E+21.25E+1 5.74E+3 7.21E+11 '1E-24.56E-3 4.29E-1 2.00E-23.33E+5 3.01E-1 2.28E+57.87E+4 5.28E-3 6.38E+41.89E+5 4.57E-1 1.85E+51.27E+1 6.77E-4 8.23E-22.36E-3 5.40E-4 8.02E-31.15E+2 5.43E-3 2.37E+21.38E-2 8.78E-5 8 '8E-57.12E-2 3.04E-3 3.17E-1

Mn 54 5.89E-2 4.29E+3 8.52E+2 5.89E-2 1.28E+3 5.89E-2 8.81E+33.10E+2 2.11E+27.76E2 5.82E+31.61E-2 1.21E+39.53E-1 3.34E+33.28E-2 3.08E+4

2.83E+31.27E+4

1.05E-2 1.79E+21. 19E+1

1.54E+21.38E+2 1.38E+24.77E-4 4.07E+1

3.11E+11.445.54E-3

8.71E+4 8.93E+31.01E+4 9.43E+37.19E+4 7.73E+31.62E-1 3.03E+25.40E-4 4.54E+15.43E-3 1.05E+68 '8E-5 2.96E+33.04E-3 3.19E+2


003856LL 41


NUCLIDE

H3

Cr 51

Cu 64

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90Zr 95

Mn 56

Mo 99

Na 24

I 131

I 133

Ni 65

I 132

Cs 134Cs 136

Cs 137

Ba 140

Ce 141

Nb 95

La 140

Ce 144

BONE LIVER2.27E-1

1.17 4.89E-1

3.24E-S 3.24E-S2 '2

1.06E-2 4.37E+36 '8E+2 4.55E+21.02E+3 2.41E+32.88E-3 8.83E+11.71E-1 2.56E+22 '1E+4 7.36E+42.18E+45 '4E+52 '0E-1 7.81E-2

1.73E-18.04E+1

1 34E+2 1.34E+21.37E+2 1.96E+22.25E+1 3.91E+11 ~ 93E-1 2.50E-24 64E-3 1.24E-22.98E+5 7.08E+52.96E+4 1 17E+5

3 '2E+5 5.22E+51.84E+2 2.32E-12.21E-2 1.50E-24.38E+2 2.44E+29.90E-2 4.99E-2

1.241.28

7. 43E-1 2. 74E-16.86

8 '3E+2 1.06E-2 1.30E+31-06E+29.22E+2 2.04E-3 2.04E-31.98E+2 2.88E-3 2.88E»35.65E+2 1.71E-1 1.71E-13.32E+4 5.87E-3 4.92E+46.27E+21.34E+55.35E-2 1.88E-3 1.22E-13. 07E-21.53E+1

2.20E-11.82E+2

1 34E+2 1.34E+2 1.34E+21.12E+2 6.43E+4 3.36E+21.19E+1 5.75E+3 6.82E+11.14E-24 34E-3 4.34E-1 1.98E-25.79E+5 5.39E-2 2.29E+58.42E+4 9.46E-4 6.51E+43.42E+5 8 '9E-2 1.77E+51.21E+1 1.21E-4 7.88E-21.78E-3 9.67E-5 7 ~ OOE-3

1.31E+2 9.73E-4 2.41E+21.32E-2 1.57E-5 1.57E-56.33E-2 5.45E-4 2.90E-1

TABLE 2-8~, VALUES - LIQUID»

EMERGENCY CONDENSER VENTADULT

mrem — mlhr — pCi


2.27E-1 2.27E-1 2.27E-11 65 3.12E+2

2.32E+21.06E-2 1.34E+42.54E+2 2.61E+26.72E+2 8.02E+32.88E-3 1.79E+31.71E-1 4.81E+35.87E-3 4.63E+4

3.50E+31.57E+4

1.88E-3 2.42E+25. 52

1.86E+21.34E+2 1.34E+2

5.17E+13'.51E+16.36E-l2.33E-3

7.61E+4 1.24E+48.92E+3 1.33E+45.89E+4 1.01E+41.33E-1 3.79E+29.67E-S 5.68E+19.73E-4 1.48E+61.57E-5 3.66E+35.45E-4 3.95E+2

LUNG GI-TRACT

2.27E-1 2.27E-1


003856LL 42


TABLE 3-1Critical Receptor Dispersion

Parameters'or

Ground Level and Elevated Releases

ELEVATED ELEVATED GROUND'ROUND

LOCATION

Residences

DairyCows'ilk

Goats'eat

Animals

Gardens

Site Boundary

DIR

E (980)

SE (1300)

SE (1300)

ESE (1154)

E (97 )

ENE (670)

MILES

1.4

2.6

2.6

1.8

1.8

0.4

1.8 E-07b

2.2E-08'.2

E-08'.1

E-08'.0

E-07'.4

E-06~

5.2 E-09

7 0 E-10D

7.0E-10'.7

E-09'

5 E-09D

4.4 E-08~

~Xeec mi ~D~m i4.02 E-07

6.00 E-08

6.00 E-08

1.16 E-07

2.53 E-07

6 63 E-06

8.58 E-09

1.64 E-09

1.64 E-09

3.54 E-09

5.55 E-09

6.35 E-08

~X~se~cm~g ~D~m zg

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

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.

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

003856LL 43


TABLE 3-2

Gamma Air and Whole Body Plume Shine Dose Factors*For

Noble Gases

Nuclide

Kr-85

Kr-85m

Kr«87

Kr-88

Kr-89

Kr-83m

Xe»133

Xe-133m

Xe-135

Xe-135m

Xe-137

Xe-138

Xe-131m

Ar-41

Gamma Air B,~mr ad

~Ci. see

2.23E-6

1.75E-3

1.02E-2

2.23E-2

2.50E-2

2.26E-6

2.80E-4

2.27E-4

2.62E-3

5.20E-3

2.30E-3

1.32E-2

1.74E-5

1.64E-2

Gamma WholeBody V,mme mr

~Ci sec

1.68E-3

9 '5E-32.17E-2

1.71E-2

2.41E-4

1.87E-4

2.50E-3

4.89E-3

2.20E-3

1 ~ 26E-2

1.47E-6

1.57E-2

* Calculated in accordance with Regulatory Guide 1.109. (See Appendix B.)

003856LL 44


TABLE 3-3

IMMERSION DOSE FACTORS*

~cclidc KdK-B~cd ** A~Ski.c ** ~N-Aic ~ ** ~N-Air

Kr 83m 7 '6E-02

Kr 85m 1.17E3

Kr 85

,Kr 87

Kr 88

Kr 89

Kr 90

1 ~ 61El

5.92E3

1.47E4

1.66E4

1.56E4

Xe 131m 9.15E1

Xe 133m 2.51E2

Xe 133 2.94E2

Ar 41 8.84E3

Xe 135m 3.12E3

Xe 135 1.81E3

Xe 137 1.42E3

Xe 138 8.83E3

1.46E3

1.34E3

9.73E3

2.37E3

1.01E4

7.29E3

4.76E2

9.94E2

3.06E2

7.11E2

1.86E3

1.22E4

4.13E3

2.69E3

1.93E1

1.23E3

l.72El

6.17E3

1.52E4

1.73E4

1.63E4

1.56E2

3 27E2

3.53E2

3.36E3

'1.92E3

1.51E3

9.21E3

9.30E3

2.88E2

1.97E3

1.95E3

1.03E4

2.93E3

1.06E4

7.83E3

1.11E3

1.48E3

1.05E3

7.39E2

2.46E3

1.27E4

4.75E3

3.28E3

* From, Table B-l.Regulatory Guide 1.109 Rev. 1

** mrem/yr per pCi/m~.

*** mrad/yr per pCi/m'.

003856LL


TABLE 3-4DOSE AND bOSE RATE

VALUES — INHALATION -INFANT'remr

pCi/m

NUCLIDE

H 3*C 14*Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95Nb 95

Mo 99I-131I 133

Cs 134

Cs 137Ba 140La 140Ce 141

Ce 144

Nd 147

BONE

2.65E4

1.97E41.36E4

1.93E43 '8ES4.09E71.15E51.57E4

3.79E41. 32E4

3.96ES5.49E55.60E45.05E22.77E43.19E67.94E3

LIVER

6.47E25.31E3

2.53E41.17E42.35E41.22E38.02E36.26E4

2.79E46.43E31.65E24.44E41.92E47.03ES6.12E55.60E12.00E21.67E41.21E68.13E3

T. BODY

6.47E25.31E38.95E14.98E33.33E39.48E31.82E31.18E43 11E4

1.14E42.59E62.03E43.78E33.23E11.96E45.60E37.45E44.55E42.90E35.15E11.99E31.76E55.00E2

6.47E25 '1E35.75E1

6.47E25.31E31.32E14.98E3

GI-LLILUNG

6.47E25+31E3

1.28E4

6.47E25 '1E33.57E2

1.00E6 7.06E38 '9E4 1.09E31 ~ 02E6 2.48E47.77E5 1.11E4

1.48E73 '6E6

4.51E6 3.19E43 '5E4 5.14E4

6.40E41.31ES

6.47ES2.03E61.12E71.75E64.79E5

2.17E41.27E4

3.11E44.72E32.65E25.18E42.24E41.90E5

1.35ES 4.87E41.06E32.16E31.33E31.33E33.84E48.48E42.16E4

7.97E41.72E5 '.13E41.34E1 . 1.60E6

1.68E55.17ES5.25E3

5.38E53.15E3

9 '4E6 1.48ES3.12E43.22E5

THYROID KIDNEY

* mrem/yr per pCi/mL.

~ ~

~

'his and following g 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.

003856LL 46


0

TABLE 3-5DOSE AND DOSE RATE

g VALUES — INHALATIONmrem rpCi/m

CHILD

NUCLIDE

H 3*C 14*Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133Cs 134Cs 137

Ba 140La 140

Ce 141

Ce 144

Nd 147

BONE

3.59E4

4.74E42.07E4

4.26E45.99E51.01E81.90E52.35E4

4.81E41.66E46.51ES9.07ES7 '0E46.44E23.92E46.77E61.08E4

LIVER

1.12E3~ 6.73E3

4.29E42.52E43.34E41.77E31.31E41.13ES

4.18E49.18E31.72E24.81E42.03E41.01E68.25E56.48E12.25E21.95E42.12E68.73E3

T. BODY

1.12E36.73E31.54E29.51E37.77E31.67E43.16E32.26E47.03E41.72E46.44E63.70E46.55E34.26E12.73E47 70E3

2.25ES1.28ES4.33E37.55E12.90E33.61E56.81E2

1.12E36.73E38.55E1

1.12E36.73E32.43E11.00E4

7.14E4

1.62E73.85E6

5.96E48.62E33.92E27.88E43.38E43.30ES2.82E52.11E1

8.55E31.17E64.81E3

THYROID KIDNEY LUNG

1.12E36.73E31.70E41.58E6

GI-LLI

1.12E36.73E31.08E32.29E4

1 ~ 11E5 2.87E31 ~ 27E6 7 '7E41.11E6 3.44E47.07E6 9.62E49.95E52 ~ 16E6

1.48E7

1.63E41.67ES3.43E5

1.35E5

1 ~ 21ES

1.04E51.74E6

1.27E52.84E35.48E33.85E33.62E31.02E5

1.83E5 2.26E55.44E5 5.66E41.20E7 3.89E53.28E5 8.21E4

2.23E6 6.11E46.14E5 3.70E4

* mrem/yr per pci/m'.

003856LL



Ri VALUES — INHALATION~rem~rpci/m

TEEN

NUCLIDE

H 3*C 14*Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99I 131

I 133

Cs 134

Cs 137

Ba 140

La 140Ce 141

Ce 144Nd 147

BONE

2.60E4

3.34E41.59E4

3.86E44 34ES

1.08E81.46E51 ~ 86E4

3.54E41.22E45.02ES6 70E5

5.47E44.79E22.84E44 '9E67.86E3

LIVER

1.27E3. 4.87E3

5.11E42.38E43.70E42.07E31.51E41.34E5

4.58E41.03E41.69E24.91E42.05E41.13E68.48E56.70E12.36E21.90E42.02E68.56E3

T. BODY

1.27E34.87E31.35E28.40E35.54E31.43E42.78E31.98E46.24E41.25E46.68E63.15E45.66E33.22El2.64E46.22E35.49ES3.11E53.52E36 '6E12.17E32.62ES5.13E2

THYROID

1.27E34.87E37.50El

1.46E72.92E6

KIDNEY

1.27E34.87E33.07E11.27E4

8.64E4

6.74E41.00E44.11E28.40E43.59E43.75E53.04E52.28E1

8.88E31.21E65.02E3

LUNG

1.27E34.87E3

GI-LLI

1.27E34.87E3

2.10E4 3.00E31.98E61.24E51.53E61.34E68.72E6

6.68E46.39E31.78E59.52E42.59E5

1.24E6 4.66E42.42E61.65E72.69E67.51E51.54E5

1.46E5

3.71ES7.65E51.49E59.68E42.69ES6.49E31.03E49.76E3

6. 14E5 1 ~ 26ES

1.34E7 8.64E53.72E5 1.82ES

1.21E5 8.48E32.03E6 2.29E52.14ES 4.87ES

* mrem/yr per pci/m~.

003856LL



Q VALUES - INHALATIONgirem~rpCi/m'DULT

NUCLIDE

H 3*C 14*Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140La 140Ce 141

Ce 144Nd 147

BONE

1.82E4

2.46E41.18E4

3.24E43.04E59.92E71.07ES1.41E4

2.52E48.64E33.73E54.78E53.90E43.44E21. 99E4

3.43E65.27E3

LIVER

1.26E3~ 3.41E3

3.96E41.70E42.78E41.58E31.15E41.03E5

3.44E47.82E31.21E23.58E41.48E48.48E56.21ES4.90E11.74E21.35E41.43E66.10E3

T. BODY

1.26E33.41E31.00E26.30E33.94E31.06E42.07E31.48E44 66E4

8.72E36.10E62.33E44.21E32.30E12.05E44.52E37.28ES4.28ES2.57E34.58El1.53E31.84ES3.65E2

1.26E33.41E35.95E1

1.26E33.41E32.28E19.84E3

6.90E4

LUNG

1.26E33.41E3

GI-LLI

1.26E33.41E3

1.44E4 3 '2E31 ~ 40E6

7.21E41.02E69.28E55.97E68.64ES1.40E6

7 '4E46.03E31.88E51.06E52.85E55.34E43.50ES

9.60E6 7.22ES

1.19E72.15E6

1.77E65.05ES

5.42E47.74E32.91E26.13E42.58E42.87ES

1.50ES1.04ES

9.12E4 2.48ES6.28E38.88E31.04E48.40E3

9. 76E4

2.22E5 7.52E41.67E1 1.27E6 2.18E5

6.26E38.48ES3.56E3

1.36E53.62E57.78E62.21E5

4.58E51.20E58.16E51.73E5

THYROID KIDNEY

* mrem/yr per pci/m~.

003856LL 49


NUCLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144Nd 147


Q VALUES - GROUND PLANEALL AGE GROUPS

mi~mrem rpCi/sec

TOTAL BODY

4.65E61.40E9

2.73E83.80E82 '5E107.46E82.16E4

2.45E81.36E83.99E61.72E72.39E66.83E91.03E102.05E71.92E71.37E76.96E78.46E6

SKIN

5.50E61 '4E9

3.20E84.45E82.53E108.57E82.51E4

2.85E81.61E84.63E62.09E72.91E67.97E91.20E102.35E72.18E71.54E78.07E71.01E7

003856LL 50



VALUES — COW MILK — INFANTm~~mrem r

pCi/sec

~UC ~DE

H 3'

14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co 60Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144Nd 147

BONE LIVE T. BODY

2.38E33.23E6 . 6 89E5

8 '3E71.22ES

2.51E75.44E72.13ES1.39E75.90E7

2.38E36.89ES

8.35E45.68E61.45E78.38E73.46E71.39ES

3.53E96 93E9

8.19E103.85E34.21ES

6.81ES8.52E62.41E10

1.21E10 S.SSE9

9.39E21.64ES1.04EB8.02EB1.24E74.49E10

1.99EB2.09E106.66E21.17ES2.03E73.53ES3.63E64.54E9

1.21ES2 '3E12.28E41.49E64.43E2

1 '1ES7.991.39E46.10ES4.55E2

2.88E96.22E62.061.64E38.34E42.79E1

3 '7E10 4.06E10

GI-LLILUNG

2.38E36.89ES

2.38E36.89E5

2.38E36.89E55.45E4

2.38E36.89E51.19E45 '6E6

1.06E5 2.43E69.21E66.91E62.66E7

6.29E7 1.02EB3.46E71.40EB1.02E101.42ES1.02E94.68ES3.03EB3.43E72.86E72.10E61.22EB1.27EB2.97E79.39E47.18E68.54E72.89ES

5.87E9

1.01E31.54E51.55ES9.37EB1.46E7

2.64E112.26E9

1.16E10 4.74E91.09E10 4.41E92.87E4 7.42E4

4.28E32.46E51.76E2

THYROID KIDNEY

mrem/yr per pci./m~.

003856LL 51


0


Q VALUES - COW MILK — CHILDmi~mrem r

pci/sec

~DDLIDE

H 3

C14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137Ba" 140

La 140Ce 141

Ce 144Nd 147

BONE

1.65E6

LIVER

1 '7E3. 3.29ES

6.97E76.52E7

2.63E93.64E97.53E102.17E31.86E5

3. 26E8

4.04E6

1.35E73.07E71 '6E86.94E62.89E77.00E9

4 '7E21.03E44.07E73.28E84.99E6

5.87E79.701 ~ 15E4

1.04E62.24E2

5.14E43.395.73E33 '6ES1.81E2

1.50E10 2.45E102.17E10 2.08E10

T. BODY

1.57E33.29ES5.27E43.59E61.15E75.26E72.13E78.52E74.35E91.04E81.91E104.25E25.69E41.01E71.86EB1.89E65.18E93.07E93.43E61.148.51E25.55E41.40E1

THYROID

1.57E33.29ES

2.93E4

1.08E119.27EB

KIDNEY

1.57E33.29ES

7.99E33.78E6

4.41E9

6.83E21.00ES8.69E75.39EB8.32E67.61E96.78E91.67E4

2.51E31.80E59.94E1

LUNG

1.57E33.29E55.34E4

2.09E73.06E7

2.73E92.44E93.07E4

GI-LLI

1.57E33.29ES

2.80E61.13E76.85E61.10EB4.05E71.60E81.23E91.41E81.01E94.98E54.42E83.37E72.92E72.01E61.32E81.30EB2.97E79.45E47.15E68.49E72.87E5

mrem/yr per pCi/m'.

003856LL 52


0

NUCLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134Cs 137

Ba 140La 140Ce 141

Ce 144

Nd 147

BONE

6.70E5

2.78E72.81E7

1.34E91.47E94.45E109.34E21.86ES

1.34E81.66E66.49E99.02E92.43E74.054.67E34.22E59.12E1

LIVER

9.94E2.1.34ES

9.01E61.97E76.57E74.55E61.86E74.65E9

2.95E21.03E52.24E71.88E82.82E61.53E101. 20E102.98E41.993.12E31 ~ 74E5

9.91E1

KIDNEY

9.94E21.34ES

5.66E32.69E6

T. BODY THYROID

9.94E21.34E51.44E4

9.94E21.34ES

2 '8E41.79E64.59E62.54E71.05E74.19E72.17E94.21E71.10E102.03E25.69E44.27E61.01E88.59E57.08E94.18E91.57E65.30E-13.58E22.27E45.94EO

2.97E9

4.33E21.00ES5.12E7

5. 49E10 3. 24E8

3.93E8 4.94E64.85E94.08E91.01E4

1.47E31.04E55.82E1


Q VALUES - COW MILK - TEENm~~mrmm r

pCi/sec

LUNG

9.94E21.35E5

GI-LLI

9.94E21.34E5

1.25E72.07E7

1.85E91.59E92.00E4

1.85E78.52E61. 55E8

6.27E72.42E81.97E91.75E81.25E96.80ES4.42E84.01E73.72E72.13E61.90E81.71E83.75E71.14E58.91E61.06E83.58E5

3.69E4 4.34E6

mrem/yr per pci/m'.

003856LL 53


TABLE 3-12,DOSE AND DOSE RATE

Q VALUES — COW MILK - ADULTgP~mr emr

pCi/sec

CLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140La 140Ce 141Ce 144Nd 147

BONE

3.63ES

1.57E71.61E7

8. 71ES

7.99EB3.15E105.34E21.09ES

7.41E79.09E53.74E94.97E91.35E72.262.54E32.29ES4.74E1

LIVER

7.63E2~ 7.26E4

5.41E61.08E7 2.52E63.79E72 '0E61.10E72.77E9

1.71E26.07E41.24E71. 06ES

1.58E68.89E96 'OE91 ~ 69E4

1. 14

1.72E39,58E45.48E1

1.45E76.05E62.42E71.25E92.29E77.74E91.16E23.27E4,2.36E66.08E74.82E57.27E94.46E98.83E53.01E-11.95E21.23E43.28EO

3.47E102.32ES

T. BODY THYROID

7.63E2 7.63E27 '6E4 7.26E41.48E4 8.85E31.03E6

KIDNEY

7.63E27 '6E43.26E31.61E6

1.85E9

2.69E26.00E42.81E71.82ES2.76E62.88E92.31E95.75E3

7.99E25.68E43.20E1

LUNG

7.63E27.26E41.96E4

GI-LLI

7.63E27.26E43.72E61.66E7

6.04E6 6 '1E61.06E7

9.55ES

1.26ES5.47E72.06ES1.75E91.28E89.11ES5.43ES3.69E82.87E72.80E71.42E61.56ES

9.69E3 2.77E78.35E46.58E67.74E72.63E5

7.68ES 1.32E8

mrem/yr per pci/m3.

003856LL


0


VALUES - GOAT MILK - INFANTmd~me emr

pci/sec

NUCLIDE

H 3'

14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144Nd 147

BONE

3.23E6

LIVER

6.33E3~ 6.89ES

1 10E6

1 ~ 59E6

4.24E81.48E101.72Ell4.66E29.42E4

8.17E81 ~ 02E7

7.23E10

3.01E67.08E52.78E61.67E67.08E61.45E9

'.13E23.88E41.27E79.63E81.49E71.35E11

1.45E72.4302.74E31.79ES5 '2E1

1.45E49 59E-11.67E37.32E45.47E1

1.04E11 1.22E11

T. BODY

6.33E36.89ES

1.00E46.82E51.89E51.09E64 '6E61.67E76.70E84.24E84.38E108.04E12.24E42 '7E64.23E84.36E61.36E108.63E97.48E52.47E-11.96E21.00E43.35EO

THYROID KIDNEY

6.33E36.89ES

6.56E3

6.33E36 '9ES1.43E36.67ES

7.04E8

3. 16E11

2.71E9

1.22E22.78E41.89E71.12E91.75E7

LUNG

6.33E36.89E51.28E4

3.46E58.21ES

GI-LLI

6.33E36.89ES

2.93ESl. 11E6

8.98E41.33E64.16E61.68E71.23E93.04E82.15E95.65E43.27E74.17E63.44E72.52E6

3.27E103.44E3

5.14E22.96E42.11E1

1.32E10 3.81E88.91E3 3.56E6

1.13E48.62E51.03E73.46E4

3.47E10 1.42E10 3.66E8

mrem/yr per pci/m'.

003856LL 55


0


VALUES - GOAT MILK — CHILDmi~meem e

pCi/sec

PUCl~DE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140Ce 141

Ce 144Nd 147

BONE

1.65E6

LIVER

4 '7E3. 3.29E5

9.06ES8.52ES

3.15E87.77E91.58E112.62E25.05E4

3.91E84.84E6

1.62E64.81E51.38E68.35E53.47E68.40E8

5.76E11.96E44 '5E63 '4E85 '9E6

6.52E107.05E61 ~ 161.38E31. 25ES

2 '8E1

6.24E106.18E34.07E-16.88E23.91E42.17E1

4.49E10 7.37E10

T. BODY

4.17E33.29E56.34E34.31E51.49ES6 86ES

2.56E61.02E75.23EB2.22E84.01E105.13E11.40E41.22E62 '4E82.27E61 ~ 55E10

9 '1E94 '2ES1.37E-11.02E26.66E31.68EO

THYROID KIDNEY LUNG GI-LLI

4.17E3 4.17E34.17E3

3.29E53.52E3

4.17E33.29E5

9.62E24.54E5

3.29E53.29E56.43E3 3.36E5

1.36E68.91E41.43E64.87E61.92E71.48E83. 01E8

2.13E96.01E43.63E74.09E63.50E72.41E63.97E83.91EB3.57E61.13E48.59E51.02E73.44E4

2.72E53.99E5

5.29E8

8.25E11.85E41 ~ 06E7

1-30E11 6.46EB1.11E9 9.98E6

2.03E10 7.32E93.68E32.01E3

3.02E22.16E41.19E1

2.28E10 8.19E9

mrem/yr per pCi/mi.

003856LL 56


TABLE 3-15DOSE ANl5 DOSE RATE

VALUES - GOAT MILK-m~~mrem r

pCi/sec

TEEN

gUUCL DE

H 3

C 14

Cr 51

Mn 54

Fe 55.

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140La 140Ce 141

Ce 144Nd 147

BO E

6 '0E5

LIVER

2.64E31.34E5

3. 61E5

3 '7ES

1 ~ 61E8

3.14E99.36E101.13E22.23E4

1.61EB1.99E6

1.08E62.56ES8.57ES5 '6ES2.23E65.58E8

3.56E11.24E42.72E62.26E83.38E6

2 '1E102.92E64.86E-15.60E25.06E41.09E1

3 60E10

3 '8E32.39E-13 '4E22.09E41.19E1

1.95E10 4.58E10

T. BODY

2.64E31.34E53.11E32.15ES5.97E43.31ES1.26E65.03E62.60E88.99E72.31E102.45E16.82E35.19E51.21E81.03E62.13E101.25E101.88E56.36E-24.30E12 72E37.13E-1

THYROID KIDNEY

2.64E31.34ES1.73E3

2.64E31.34E56.82E23 '3ES

3.57E8

4.72E8 5.93E61.46E101.23E101.21E3

1 ~ 76E2

1.25E46.99EO

5.23E11.20E46.23E6

6.59E10 3.89E8

LUNG GI-LLI

2.64E3 2.64E31.35ES 1.34E54.44E3

1.62ES2.70E5

5.56E9

5.23E52 '2E61.11E52.03E67.53E62.91E72.36E83.74E82.63E98.22E45.30E74.87E64.47E72.56E65.70E8

4.76E9 5.12E82.41E3 4.50E6

1.37E41.07E61.27E74.29E4

mrem/yr per pCi/m~.

003856LL 57



Q VALUES — GOAT MILK — ADULTmi~meem r

pCi/sec

~NDD IDE

H 3

C14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

LR 140

Ce 141

Ce 144

Nd 147

BONE

3.63E5

2.04E52 '0E5

1.05ES1.70E96.62E106.45E11.31E4

8 '9E71 '9E61. 12E10

1.49E101.62E62.71E-13.06E22.75E45.69EO

LIVER

2.03E3

. 7.26E4

6.50E51.41E54 '5E53.25E51. 32E6

3.33ES

2.07E17.29E31.51E61.27ES1.90E62.67E102.04E102.03E31.36E-12.07E21.15E46.57EO

T. BODY

2.03E37.26E41.78E31.24E53.28E41.90E57.27ES2.91E61.51E84.89E71.63E101.40E13.92E32.87E57.29E75 '9ES2.18E101.34E101.06E53.61E-22.34E11.48E33.93E-1

THYROID KIDNEY

2.03E37.26E41.06E3

2.03E37.26E43.92E21.93E5

2.23E8

2.79E8 3.31E68.63E96.93E96.91E2

9.60E16.82E33 '4EO

3.25E17.21E33.41E6

4.17E10 2.18ES

LUNG

2.03E37.26E42.36E3

GI-LLI

2.03E37.26E44.48E51.99E6

1.38E5

2.86E92.30E91.16E3

1 65E6

6.58E62.48E72.10E82.73E81.91E96.56E44.42E73.49E63.36E71.71E64.67ES3.95E83.33E61.00E47.90E59.30E63.15E4

7.85E4 8.07E4

mrem/yr per pci/m~.

003856LL 58


0


g VALUES - COW MEAT - CHILDmi~meem

pci/sec

~UC',~DF~

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134Cs 137

Ba 140

La 140

Ce 141

Ce 144

Nd 147

BONE

5.29ES

2.89ES2.04EB

2 '8EB2.65EB7.01E91.51E64.10E6

4.15E69.38E-26.09EB8.99EB2.20E72.80E-21.17E41.48E65.93E3

LIVE

2.34E2~ 1. 06E5

5.15E61.53ES3.30ES9.41E64.64E76.35EB

3.32E51.59E65.42E44.18E61.16E-11.00E98.60ES1.93E49.78E-35.82E34.65E54.80E3

T. BODY

2.34E21.06E54.55E31.37E64.74E71.65ES2.88E71 37ES

3.95ES7 57E6

1.78E92.95ES1.14E61.34E42.37E64.39E-22.11ES1.27ES1.28E63.30E-38.64E27.91E43.72E2

2.34E21.06ES

2.52E3

2.34E21.06E56.90E21.44E6

4 ~ OOEB

1.38E92.15El

4.75E51.50E61.16E56 '6E61.93E-13.10EB2.80EB6.27E3

2.55E32.57E52.64E3

THYROID KIDNEY LUNG GI-LLI

2.34E2 2 '4E21.06E54.61E3

8.66E79.58E7

1.06ES

2.41E54.32E62.84E73.44EB5.49E72.57ES1.12ES1.03E79.44E73 '6EB2.95E94.48E43.72ES4.67E-2

1.01ES1.15E4

5.39E61.11E72.73E27.26E61.21ES7.61E6

1.11EB 5.39E6

mrem/yr per pci/m~.

003856LL 59


0


Q VALUES — CON MEAT — TEENme~mmmme

pCi/sec

NUCLIDE

H 3

c 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140Ce 141Ce 144

Nd 147

BONE

2.81ES

1.50ES1.15ES

1 59ES

1 40ES

5.42E98.50ES2.37E6

2.24E65.05E-23.46ES4.88ES1.19E71.53E-26.19E37.87ES3.16E3

LIVER

1.94E2

. 5. 62E4

4.50E61.07ES2.69EB8.05E63 '0E75.52ES

2.68E51.32E63.90E43.13E68.57E-28.13E86.49ES1.46E47 '1E-34.14E33.26E53.44E3

T. BODY

1.94E25.62E42.93E38.93E52.49E71.04E81.86E78.80E72.57E84.01E61.34E91.84E57.24E57.43E31.68E62.61E-23.77ES2.26ES7.68E52.00E-34.75E24.23E42.06E2

THYROID

1.94E25.62E41.62E3

9.15ES1.20E1

1

KIDNEY

1.94E25.62E46.39E21.34E6

3 '3E8

3.94ES1.28E68.92E45.40E61.50E-12.58E82.21ES4.95E3

1.95E31.94E52.02E3

LUNG

1.94E2

GI-LLI

1.94E2

5 '2E4 5.62E4

4.16E3 4.90E5

6.77E78.47E7

9.87E78.58E7

9.24E64.62E76.36ES1.11ES5-09E82.34ES1.67E71.52E86.19ES5.63E96.98E46.20ES6.48E-21.01E79.24E6

9.81E3 1.84E74.31E21.18E71.98E81.24E7

mrem/yr per pCi/m'.

003856LL 60



Q VALUES — COW MEAT - ADULTm'-mr em Irmr

pCi/sec

NUCLIDE

H 3

C14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140Ce 141

Ce 144Nd 147

BONE

3.33E5

1.85ES1.44ES

2.26E81.66E88.38E91.06E63.04E6

2.69E66.04E-24.35E85.88E81.44E71.86E-27 '8E39.33E53.59E3

LIVER

3.25E2. 6.66E4

5.90E61.28E83.39ES1.04E75.03E77 19ES

3.40ES1.69E64.71E43.85E61.05E-11.03E98 '4ES1.81E49 '7E-34.99E33.90E54.15E3

T. BODY

3.25E2

6.66E43.65E31.13E62.98E71.30ES2.34E71.11E83 25ES

4.76E62.06E92.30E59.08ES8.97E32.21E63.20E-28.45E85.26ES9.44ES2.48E-35.66E25.01E42.48E2

3.25E26.66E42.18E3

3.25E26.66E4

8.03E21.76E6

4.81E8

1.26E91.54E1

5.34ES1.67E61 07ES

6.61E61.83E-13.35E82.73E86.15E3

2.32E32.31E52.42E3

THYROID KIDNEY LUNG

3.25E2

GI-LLI

3.25E2

6.66E4 6.66E4

4.84E3 9.17ES

7.14E79.46E7

1.11E89.07E7

1.81E77.34E71.13E92.12ES9.45ES4.53ES2.66E72.42ES1.08E91.03E101.09ES1.02E69.44E-21.81E71.56E7

1.04E4 2.97E76.88E21.91E73.16ES1.99E7

mrem/yr per pci/m'.

003856LL 61



VALUES — VEGETATIONmi~mrem

pci/sec

CHILD

NDCIDIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 5S

Co 60

Zn 65

Sr 89Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140Ce 141

Ce 144Nd 147

BONE

3.50E6

7. 63ES

3.97EB

8 '2EB3 '9E101.24E123.86E61.02E6

7.16E71.69E61.60E102.39E102.77EB3.25E36.56E51 ~ 27ES

7.23E4

LIVER

4.01E3

. 7.01E5

6.65ES4.05ES6.42ES6.45E73.78ES2.16E9

8 '0E53.99E57.70E67.20E72.09E62 '3E102.29E102.43ES1.13E33.27ES3.98E75 '6E4

T. BODY

4.01E37.01E51.17ES1.77ES1.25ES3.20EB1.97ES1.12E91.35E91.03E93.15E117.56E52.85ES1.91E64.09E77 '2E55.55E93.38E91.62E73.83E24.85E46 '8E64.54E3

THYROID

4.01E37.01E5

KIDNEY

4 '1E37.01E5

1.36E9

1.22E63.75E51.65E7

2.38E10 1.18EB3.89ES 3.49E6

8.15E97.46E97 90E4

1.43ES2.21E73.22E4

6.49E4 1.77E41.86ES

LUNG GI-LLI

7.01E51.18E5

7.01E56.20E65.58EB

2.29EB 7.50E71.86EB

2.93E92.68E91 ~ 45E5

6.69ES3.76ES2.10E93.80EBl. 39E9

1 ~ 67E10

8 '6EB7.37ES6.37E66.41E68 '4ES1.42EB1.43EB1. 40EB

3.16E74.08EB1.04E109.28E7

4.01E3 4 '1E3

mrem/yr per pci/m .

003856LL 62



Q VALUES - VEGETATIONm~~meem

pci/sec

TEEN

NUCLIDE

H 3

C 14

Cr 51

Mn 54Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134Cs 137

Ba 140

La 140Ce 141

Ce 144Nd 147

BONE

1.45E6

3.10ES1.79ES

4.24ES1 51E107.51E111 ~ 72E6

4.80E5

3.85E79.29E57.10E91.01E101.38ES1.81E32.83E55.27E73.66E4

LIVER

2.59E3~ 2.91E5

4.54E82.20E84.18ES4.37E72.49E81.47E9

5.44E52 '6ES5.64E65.39E71 ~ 58E6

1 ~ 67E10

1 ~ 35E10

1 ~ 69ES

S.SSE2

1.89E52.18E73.98E4

T. BODY

2.59E32.91ES

6 '6E49.01E75.13E71.61ES1.01E85.60ES6.86E84.33ES1.85E113.74ES1.46E51.08E62.89E74.80E57.75E94.69E98.91E62 '6E22.17E42.83E62.3863

THYROID KIDNEY

2.59E32.91E53.42E4

2.59E32.91ES

1.35E41'. 36ES

9. 41ES

2.20ES 2 '6E65.31E94.59E95.74E4

8.89E41.30E72.34E4

7.99E52.58ES1.29E7

1.57E10 9.28E7

LUNG GI-LLI

2.59E3 2.59E3

2 '1ES 2.91E58.79E4

1.40ES1.32ES

1.03E79.32ES9.53E79.89ES6.02ES3.24E96.23ES1.80E92.11E101.26E91.14E91.01E71.07E71.19E6

1.78E91.14E5

1.92E82.13ES5.10E75 '0ES1.33E101.44E8

2.03E9 2.08ES

mrem/yr per pci/m~

003856LL 63


0


VALUES - VEGETATIONmicr eme

pCi/sec

ADULT

NUCL DE

H 3

C14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133Cs 134

Cs 137

Ba 140

La 140Ce 141

Ce 144

Nd 147

BONE

8.97ES

2.00ES1 ~ 26E8

3 '7ES9.96E96.05Ell1.18E63.55E5

4.04E71.00E64.67E96. 36E91.29E81.98E31.97E53.29E73.36E4

LIVER

2.26E3. 1.79E5

3.13E81.38ES2.96E83.08E71.67ES1.01E9

3.77ES1.98E56 14E6

5.78E71.74E61.11E108.70E91.61E59.97E21.33ES1.38E73.88E4

T. BODY

2 '6E31.79ES

4.64E45.97E73.22E71.13E86.90E73.69ES4.56ES2e86ES

1.48E112.55E51.06ES1.17E63.31E75.30E59.08E95.70E98 '2E62.63E21. 51E4

1.77E62e32E3

THYROID

2.26E31.79ES

2.77E4

KIDNEY

2. 26E3

1.79ES1.02E49.31E7

6.75E8

2.56ES 3.03E63.59E92.95E95.49E4

6.19E48.16E62.27E4

5.92E51.95ES1.39E7

1.90E10 9.91E7

LUNG GI-LLI

1 ~ 79E5

6.15E4

7.69E78.27E7

1.19E99.81E89.25E4

1.79E51.17E79.58ES7.91E71.02E96 '4ES3.14E96.36E81.60E91.75E101.20E91.20E91.42E71.53E71.56E61.94ES1.68ES2.65E87.32E75.09ES1.11E101.86ES

2.26E3 2.26E3

mrem/yr per

pCi/m'03856LL

64


TABLE 3-23PARAMETERS FOR THE EVALUATION OF DOSES TO REAL MEMBERS

OF THE PUBLIC FROM GASEOUS AND LIQUID EFFLUENTS

Fish

Fish

Shoreline

Shoreline

Inhalation

Parameters

U (kg/yr) - adult

D~. (mrem/pCi)

U (hr/yr)— adult- teen

(mrem/hr per pCi/m~)

DFAg,

Value

21

Each Radionuclide

6767

Each Radionuclide

Each Radionuclide

Reference

Reg. Guide 1.109Table E-5

Reg. Guide 1. 109Table E-11

Reg. Guide 1.09Assumed to be same as Adult



003856LL 65


NINE MILE POINT NUCLEAR STATIONRADIOLOGICALENVIRONIVIENTALMONITORING PROGRAM

SAIVIPLINGLOCATIONS

TABLE 5.1

Type ofm I

Radioiodine andParticulates (air)





Direct Radiation (TLD)








Direct Radiation (TLD),





*MapLoca ion

10

12

13

14

15

16

17

18

II i n i Env.Pr ramN

Nine Mite Point RoadNorth (R-1)

Co. Rt. 29 5 Lake Road (R-2)

Co. Rt. 29 (R-3)

Village of Lycoming, NY (R-4)

Montario Point Road (R-5)

North Shoreline Area (75)




JAF East Boundary (78)

Rt. 29 (79)

Rt. 29 (80)

Miner Road (81)

Miner Road (82)

Lakeview Road (83)

Lakeview Road (84)

Site Meteorological Tower (7)

Energy Information Center (18)

Loc I n

1.8 rni I 88o E

1.1 mi I 104o ESE

1.5 mi I 132'E

1.8 mi I 143o SE

1 6.4 mi I 42 o NE

01mi@5o N

0.1 mi@25o NNE

0.2 mi I 45o NE

0.8 ml I 70O ENE

1.0 mi I 90'

1.1 mi @ 115'SE'.4

mi I 133~ SE

1.6 mi I 159~ SSE

1.6 mi I 181o S

1.2 mi I 200 SSW

1.1 mi I 225o SW

0.7 mi I 250o WSW

0.4 mi I 265o W

*Map = See Figures 5.1-1 and 5.1-2

003856LL 66


NINE lVlILEPOINT NUCLEAR STATIONRADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SAMPLING LOCATIONS

TABLE 5.1(Continued)

Type ofm I

*MapLoca ion Collection Site Env. Pro ram No. Location
















Direct Radiation (TLD),




Surface Water

Surface Water

19

20

21

22

23

24

25

26

27

28

29

30

31

32

33

35

36

37

38

39

North Shoreline (85)



Hickory Grove (88)

Leavitt Road (89)

Rt. 104 (90)

Rt. 51A (91)

Maiden Lane Road (92)

Co. Rt. 53 (93)

Co. Rt. 1 (94)

Lake Shoreline (95)

Phoenix, NY Control (49)

S. W. Oswego, Control (14)

Scriba, NY (96)

Alcan Aluminum, Rt. 1A (58)

Lycoming, NY (97)

New Haven, NY (56)

W. Boundary, Bible Camp (15)

Lake Road (98)

OSS Inlet Canal (NA)

JAFNPP Inlet Canal (NA)

0.2 mi I 294'NW

0.1 mi I315'W

0.1 mi e 341'NW

4.5 mi O 97'

4.1 mi I 111 o ESE

4 2mi O 135o SE

4.8 mi O 156 SSE

4.4 mi O 183o S

4.4 mi O 205o SSW

4.7 mi O 223o SW

4.1 mi I 237 WSW

19.8 mi I 163'

126 mi I 226 SW

3.6 mi I 199 SSW

3.1 mi O 220'W

1.8 mi O 143'E

5.3 rni O 123o ESE

0.9 mi I 237o WSW

1.2 mi I 101o E

7.6 mi O 235o SW

0.5 mi I 70o ENE

(NA) = Not applicable*Map = See Figures 5.1-1 and 5.1-2

003856LL 67


NINE MILE POINT. NUCLEAR STATIONRADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SAMPLING LOCATIONS


Type ofm I

*MapLoca ion Coll ction i e Env. Pro ram N Location

Shoreline Sediment

Fish

Fish

Fish

Milk

Milk

Milk

Milk

Milk

Milk

Food Product

Food Product

Food Product

Food Product

Food Product

Food Product

Food Product (CR)

40

42

43

44

45

47

64

65

66

48

49

50

51

52

53

54

Sunset Bay Shoreline (NA)

NMP Site Discharge Area (NA)

NMP Site Discharge Area (NA)

Oswego Harbor Area (NA)

MilkLocation ¹50

MilkLocation ¹7

MilkLocation ¹65

MilkLocation ¹55

MilkLocation ¹60

MilkLocation ¹4

Produce Location ¹6++(Bergenstock) (NA)

Produce Location ¹1++(Culeton) (NA)

Produce Location ¹2**(Vitullo) (NA)

Produce Location ¹5++(C,S. Parkhurst) (NA)

Produce Location ¹3**(C. Narewski) (NA)

Produce Location ¹4++(P. Parkhurst) (NA)

Produce Location ¹7++(Mc Millen) (NA)

1.5 mi I 80'

0.3 mi I315'W(and/or)

0.6 mi I 55~ NE

6.2 mi I235'W

8.2 mi I 93o E

5.5 mi I 107'SE

17.0 mi I 220 SW

9.0 mi I 95o E

9.5 mi I 90'

7.8 mi I 113'SE

1.9 mi I 141o SE

1.7 mi I 96'

1.9 mi I 101'

1.5 mi I 114o ESE

1.6 mi I 84~ E

2.1 mi I 110o ESE

15.0 mi I 223 SW

*Map =

(NA)CR

The Jones milk location has been deleted due to the herd being sold. (Map location ¹46.)See Figures 5.1-1 and 5.1-2Food Product Samples need not necessarily be collected from all listed locations. Collected

samples will be of the highest calculated site average D/Q.Not applicableControl Result (location)

003856LL 68


NINE MILE POINT NUCLEAR STATIONRADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SAMPLING LOCATIONS


Type ofm I

Food Product (CR)

Food Product

*Maploc ion

55

56

pile tion Si Env. Pr ram No.

Produce Location ¹8(Denman) (NA)

Produce Location ¹9(O'onnor) (NA)

Loca I n

12.6 mi I225'W

1.6 mi I 171'

Food Product

Food Product

57

58

Produce Location(C. Lawton) (NA)

Produce Location(C. R. Parkhurst)

¹10'11~~

(NA)

2.2 mi I 123~ ESE

2.0 mi I 112'SE

Food Product

Food Product (CR)

Food Product

Food Product

Food Product

59

60

61

62

63

Produce Location ¹12(Barton) (NA)

Produce Location ¹13(Flack) (NA)

Produce Location ¹14(Koeneke) (NA)

Produce Location ¹15(Whaley) (NA)

Produce Location ¹16(Murray) (NA)

1.9 mi I 115'SE

15.6 mi I225'W

9mio95oE

1 7 m) I 136o SE

1.2 mi I 207~ SSW

(NA)CR

See Figures 5.1-1 and 5.1-2Food Product Samples need not necessarily be collected from all listed locations. Collectedsamples will be of the highest calculated site average D/Q,Not applicableControl Result (location)

003856LL 69


FIGURE 5.1-1

003856LL 70


5 7 ~I~ 9 N.I 10 14 15 16

~N N

1.A II't OIVPARI

~P 0+g IA)

q Iol f-

00

6ttCTOO LOGIC TOOilll)

Io I~ '

4o( oooO

/ ~v

FIGURE 5.I-INine Mile Point On Site

6oooNooNvol SNooloLooolko

5 W - CAIN Col CNICI

IM) - TotNI OIII'Colooo

160o ll6lo 4lll IIIN OMIT

Map;I

'*IOW

OIINO KWIIII I oN IIN

NON ~ iN Nl~ OIN a

0

@I

/0/o >'0

O

O

43'30'ool

oo1

1 2 2

5

l 10

N~ CCI

12 12 14

HIHI~

15

PI

OOlo

016

FIGURE 5.1-2

003856LL 71


Qr>

FIGURE 5,I-2(p > «2)

NINE MILE POINT OFF-SITE MAP (2/93)

~CCCC OC NILCC

LtOKND

44 4 CUOOUUOpoOO„,.„„„,....~Toro 1oooo,Cooroo UrrlClio 4 YUoCO Ibad

LAKE

ONTARIOSIITII44IIICIUCt SCI44t4 4

~ Ii'

r~ ~

o a'll '5 C

IorrC~\iio

I ~

N S r Y 5

P

UooUoh

'gX I

p fQ 5 0

~ op

UPSCo

Ppo \

~ro 0

ioiopo

fULTO< So

Ihrro a I ~ ~

'

Figure 5.1-2

(p. 2 of 2)eaaaraaaa .„„„„...„Eaaalteneaeaatet SecreteLecelletl

a»a a ~a»a

a ~

oswCog"i l,.

%r aaa»»a»aa)

I

~ A

K C V C oHteaalaa

V aaa

/ » r» aaaaa

~ waaa»»a

i~S'I

ar»a a

0fhQ '

~ a1

~ag»

e )I

e l A R M

~»a~aa

Ae

y~I ~ A L

~ l

I

JULTO

*aH ae

karaa a

II~aaa t»rara I a»aara

I r~

I

I

» a

aa ar e ara Cawn

«Oaeate ta e»aaaar1e

~e

Ia~ atr

er aae

FIGURE 5.1.3-1

003856LL 72


0

C

~ Q't ~ ' 0

lp

E~~

a ~ ~ ~

R ~~ 4 1 0 '

NOTES TO FIGURE 5,I.3

(a) HHP1 Stack (height is 350')(b) HHP2 Stack (height is 430')(c) JAFHPP Stack-(height is 385')(d) HHPI Radioactive Liquid Discharge (Lake Ontario, bottom)(e) HHP2 Radioactive Liquid Discharge (Lake Ontario, bottom)(f) JAFNPP Radioactive Liquid Discharge (Lake Ontario, bottom)(g) Site Boundary(h) Lake Ontario Shoreline(i) Heteorological Tower(j) Training Center(k) Energy Information Center

Additional Information:

- NHP2 Reactor Building Vent is located 187 feet above ground level- JAFNPP Reactor and Turbine Building Vents are located 173 feet above ground

level- JAFHPP Radwaste Building Vent is 112 feet above ground level- The Energy Information Center and adjoining picnic area are UNRESTRICTED

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

accessible to HEHBERS OF THE PUBLIC

APPENDIX A

LIQUID DOSE FACTOR DERIVATION

003856LL 73


Appyndix A

Liquid Effluent Dose Factor Derivation, A

~ (mrem/hr per pci/ml) which embodies thetransfer factors (e.g., bioaccumulation fa

dose conversion factors, pathwayctors), pathway usage factors, and

dilution factors for the points of pathway origin takes into account the dosefrom ingestion of fish and drinking water and the sediment. The total bodyand organ dose conversion factors for each radionuclide will be used fromTable E«ll of Regulatory Guide 1.109. To expedite time, the dose iscalculated for a'maximum individual instead of each age group. The maximumindividual dose factor is a composite of the highest dose factor A(„ of eachnuclide i age group a, and organ t, hence A,„. It should be noted that thefish ingestion pathway is the most significant pathway for dose from liquideffluents. The water consumption pathway is included for consistency withNUREG 0133.

The equation for calculating dose contributions given in section 1.3 requiresthe use of the composite dose factor A;, for each nuclide, i. The dose factorequation for a fresh water site is:

Lit -X,t<D

+ 69.3 D e e e (3-e )(DFS)i)Kit -Xitq

(D.) (4)

Where'o

U

Is the dose factor for nuclide 1, age group a,total body or organ t, for all appropriatepathways, (mrem/hr per pCi/ml) .

Is the unit conversion factor, le 14E5=1E6pCi/pCix lE3 ml/kg -: — 8760 hr/yr.

„'I

Water consumption (1/yr)g from Table E-5 of Reg.Guide 1.109.

Uf Fish consumption (Kg/yr); from Table E-5 of Reg.Guide 1.109.

U,

(BF) i

Sediment Shoreline Usage (hr/yr); from Table E-5of Reg. Guide 1.109.

Bioaccumulation factor for nuclide, i, in fish,(pCi/kg per pCi/1), from Table A-1 of Reg. Guide1.109.

(DFL)Li Dose conversion factor for age, nuclide, i,group a, total body or organ t, (mrem/pCi); fromTable E-11 of Reg. Guide 1.109.

(DFS) ) Dose conversion factor for nuclide i and totalbody, from standing on contaminated ground(mern/hr per pCi/m'); from Table E-6 of Reg.Guide 1.109.

D Dilution factor from the near field area withinone-quarter mile of the release point to thepotable water intake for the adult waterconsumption. This is the Metropolitan WaterBoard, Onondaga County intake structure locatedwest of the City of Oswego; (unitless).

003856LL 74


C 'd

Appendix A (Cont'd)

D,

69.3

tb

Dilution factor from the near field areawithin one quarter mile of the release pointto the shoreline deposit (taken at the samepoint where we take environmental samples 1.5miles; unitless).conversion factor .693 x 100, 100 K, (L/kg-hr)*40*24 hr/day/.693 in L/m'-d, and K, = transfercoefficient from water to sediment in L/kg per hour.

Average transit time required for each nuclide toreach the point of exposure for internal dose, it isthe total time elapsed from release of the nuclidesto either ingestion for water (w) and fish (f) orshoreline deposit (s), (hr).Length of time the sediment is exposed to thecontaminated water, nominally 15 yrs (approximatemidpoint of facility operating life), (hrs).

decay constant for nuclide i (hr').Shore width factor (unitless) from Table A-2 of Reg.Guide 1.109.

Example Calculation

For I-131 Thyroid Dose Factor for an Adult from a Radwaste liquideffluents release:

(DFS) )

(DFL)L,BF)UgDD<

U,W

t~

2.80E-91 95E-315214012120.35 '

mrem/hr per pci/m~mrem/pCi t~ ~ 30 hrs. (w ~ water)pCi/Kg per pCi/L t< ~ 24 hrs. (f ~ fish)Kg/yr tb = 1.314ES hrs. (5.48E3 days)unities s U„ = 730 L/yrunitless Ko ~ 1.14E5 Ci Ci ml khr/yr (hr/yr)

3.61E-3hrhrs (s = Shoreline Sediment)

These values will yield an + Factor of 6.79E4 mrem-ml per pCi.-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 forwhich a factor is not listed, then it will be calculated and included in a revision to theODCM.

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

003856LL 75


APPENDIX B

PLUME SHINE DOSE FACTOR DERIVATION

003856LL 76


APPENPIX B

For elevated releases the plume shine dose factors for gamma air (B,) andwhole body (V,), are calculated using the finite plume model with an elevationabove ground equal to the stack height. To calculate the plume shine factorfor gamma whole body doses, the gamma air dose factor is adjusted for theattenuation of tissue, and the ratio of mass absorption coefficients betweentissue and air. The equations are as follows:

gamma AirBi ~ Z, Q~EI

Re V,Where: K'onversion factor (see

below for actual value).

mass absorption coefficient(cm/gi air for B„ tissue for V,)

V<

Energy of gamma ray perdisintegration (Mev)

average wind speed for eachstability class (s),downwind distance (site boundary,m)

sector width (radians)

subscript for stability class

I function = I, + kIi for eachstability class. (unitless, seeRegulatory Guide 1.109)

Fraction of the attenuated energythat is actually absorbed in air(see Regulatory Guide 1.109, seebelow for equation)

Whole Bod

ViPatd

1. 11S|:B,eWhere: t~ tissue depth (g/cm~)

S|: shielding factor from structures(unitless)Ratio of mass absorptioncoefficients between tissue andair.

Where all other parameters are defined above.

'K ~ conversion factor [3.7 E10 ~dis 1.6 E-6 ercr]Ci-sec

[1293 g ]m'ev[100 ~er ]g-rad

a46

~k~~PA Where: p ~ mass attenuation coefficient

(cm /gg air for B„ tissue for V,)

p, . = defined above

003856LL 77


APPENDIX B (Cont'd)

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

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

The average gamma energies were calculated using a weighted average of allgamma energies emitted from the nuclide. These energies were taken from thehandbook "Radioactive Decay Data Tables", David C. Kocher.

The mass absorption (p,) and attenuation (p) coefficients were calculated bymultiplying the mass absorption (p,/p) and mass attenuation (p/p) coefficientsgiven in the Radiation Health Handbook by the air density equal to 1.293 E-3g/cc or the tissue density of 1 g/cc where applicable. The tissue depth is5g/cm~ for the whole body.

The downwind distance is the site boundary.

003856LL 78


Ex. Kr-89

C O

APPENDIX B (Cont'd)

F STABILITY CLASS ONLY - Gamma Air

-DATAEP R

pecS

K ~ .46VF ~ 5 '5 m/sec

k ~ ~ ~ 871Pa

R ~ 644m

2.22MeV2 943 E-3m5 '064E-3m'39

19m.......vertical plume spread taken from "Introduction to NuclearEngineering", John R. LaMarsh

-I FunctionUa,

m

I~a

.06

.33~ 45I~ + kIg ~ 33 + ( ~ 871) ( ~ 45) ~ 72

B> 0. 6dis.

C -sec Mev er s . 4 -3 '.22Mev 7

(g/m ) (erers)(g-rad)

(5.55 m/s) (.39) (644m)

1.55(-6) rad s 3600 s r 24 h d 365 d 1E3m ad radCi/s (~1E6 Ci)

Ci

V)

2.76(-2) pradopCi/sec - (. 0253 cm /g) ( 5g/cm )

1. 11 (. 7) 2. 76 (-2) mr ad r] (e )pci/seel

1. 89 (-2) p~ad~rpCi/sec

~OTE: The above calculation is for the F stability class only. For Table 3-2and procedure values, a weighted fraction of each stability class wasused to determine the B< and V~ values.

003856LL 79


APPENDIX C

DOSE PARAMETERS FOR IODINE 131 and 133,

PARTICULATES AND TRITIUM

003856LL 80


'

APPENDIX C

DOSE PARAMETERS FOR IODINE - 131 AND - 133, PARTICULATES AND TRITIUM

This appendix contains the methodology which was used to calculate the organdose factors for I-131, I-133, particulates, and tritium. The dose factor,

was calculated using the methodology outlined in NUREG-0133. Theradioiodine and particulate Technical Specification (Section 3.6.15) isapplicable to the location in the unrestricted area ~here the combination ofexisting pathways and receptor age groups indicates the maximum potentialexposure occurs, i.e., the critical receptor. Washout was calculated anddetermined to be negligible. R, values have been calculated for the adult,teen, child and infant age groups for all pathways. However, for dosecompliance calculations, a maximum individual is assumed that is a compositeof highest dose factor of each age group for each organ and pathway. Themethodology used to calculate these values follows:

C.l alatio Pathwa

Q(I)where>

K'BR)~ (DFA)g,

$ (I) dose factor for each identified radionuclide iof the organ of interest (units = mrem/yr perpci/m~);

K' constant of unit conversion, 1E6 pCi/pCi

(BR) ~ Breathing rate of the receptor of age group a,(units = m~/yr)i

(DFA)6, The inhalation dose factor for nuclide i, organj and age group a, and organ t (units ~mrem/pCi) .

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

e Grou a Breathin Rate m~ rInfantChild

Teen

1400

3700

8000

Adult

Inhalation dose factors (DFA)>E-7 through E-10 of Regulatory

8000

for the various age groups are given in TablesGuide 1.109 Revision l.

003856LL 81


APPENDZX C (Cont'd)

C.2

Q(G)

Ground Plane Pathwa

K'K'' SF DFG-X,t

1-e

Mhere:

Q(G) Dose factor for the ground plane pathway for eachidentified radionuclide i for the organ of interest(units ~ m~-mrem/yr per pCi/sec)

K''' A constant of unit conversion, 1E6 pCi/pCi

A constant of unit conversion, 8760 hr/year

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

t The exposure time, sec, 4.73E8 sec (15 years)

(DFG)( ~ The ground plane dose conversion factor for radionuclidei~ (units ~ mrem/hr per pCi/m~)

SF The shielding factor (dimensionless)

A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide1.109 Revision 1. A tabulation of DFG,,values is presented in Table E-6of Regulatory Guide 1.109 Revision 1.

003856LL 82


APPENDIX C (Cont'd)

C.3 Grass- Cow or Goat -Milk Pathwa

Q(C) ~ K' F r DFL ~ff + (~1-f f)(e e-l,tr

(1, Yp Y,

Where'(C)

Dose factor for the cow milk or goat milk pathway, for eachidentified radionuclide i for the organ of interest, (units =

m2-mrem/yr per pCi/sec)

K' constant of unit conversion, 1E6 pCi/pCi

The cow's or goat's feed consumption rate, (units ~ Kg/day-wetweight)

The receptor's milk consumption rate for age group a, (units =

liters/yr)Yp

Y,

The agricultural productivity by unit area of pasture feed grass,(units ~ kg/m2)

The agricultural productivity by unit area of stored feed, (units ~

kg/m2)

(DFL)LI

The stable element transfer coefficients, (units ~ pCi/liter perpCi/day)Fraction of deposited activity retained on cow's feed grass

The ingestion dose factor for nuclide i,age group a, and total body or organ t (units ~ mrem/pCi)

The radiological decay constant for radionuclide i, (units=sec -1)

The decay constant for removal of activity on leaf and plantsurfaces by weathering equal to 5.73E-7 sec -1 (corresponding to a14 day half-life)The transport time from pasture to cow or goat, to milk, toreceptor, (units = sec)

The transport time from pasture, to harvest, to cow or goat, tomilk, to receptor (units = sec)

003856LL 83


'PPENDIX C (Cont'd)

Fraction of the year that the cow or goat is on pasture(dimensionless)

Fraction of the cow feed that is pasture grass while the cowis 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 Guide1.109 Revision 1, the value of f, is considered unity in lieu of site specificinformation. The value of f~ is 0.5 based on 6 month grazing period. Thisvalue for f was obtained from the environmental group.

Table C-1 contains the appropriate values and their source in Regulatory Guide1.109 Revision 1.

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

+(C) ~ K'K' '~QP~(DFL) ~ 0. 75 (0. 5/H)

-Where:

Rz (C) Dose factor for the cow or goat milk pathway fortritium for the organ of interest, (units = mrem/yrper pci/m')

Kt

H

0.75

A constant of unit conversion, 1E3 g/kg

Absolute humidity of the atmosphere, (units ~ g/m~)

The fraction of total feed that is water

The ratio of the specific activity of the feed grasswater to the atmospheric water

Other values are given previously. A site specific value of H equal to6.14 g/m~ is used. This value was obtained from the environmental groupusing actual site data.

003856LL 84


APPENDIX C. (Cont,'d)

C.4 Grass-Cow-Meat Pathwa

g(C) ~ ' r DFL [~ff + (~1-f f ) (e "i ~ e "i"r+ 1„) I Y, Y,

W(M)

Fr

Dose factor for the meat ingestion pathway for radionuclide i forany organ of interest, (units ~ m~-mrem/yr per pci/sec)

The stable element transfer coefficients, (units ~ pCi/kg perpCi/day)

The receptor's meat consumption rate for age group a, (unitskg/year)

The transport time from harvest, to cow, to receptor, (units ~sec)

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-2contains the values which were used in calculating g(M).

The concentration of tritium in meat is based on airborne concentration ratherthan deposition. Therefore, the Rz(M) is based on X/Q.

R~(M) ~ K'K' 'FQP~(DFL)~ [0 ~ 75(0.5/H) ]

Where>

R~(M) ~ Dose factor for the meat ingestion pathway for tritium for anyorgan of interest, (units ~ mrem/yr per pci/m')

All other terms are defined above.

C.5 Ve etation Pathwa

The integrated concentration in vegetation consumed by man follows theexpression developed for milk. Man is considered to consume two types ofvegetation (fresh and stored) that differ only in the time period betweenharvest and consumption, thereforei

Q(V) ~ K'„(l,, + 1„)

-l,,t„-l,t,(DFL)~ U",F„e + U',F e

003856LL 85

Unit 1 ODCMRevision 12. une 1993

APPENDIX C (Cont'd)

Where'(V)Dose factor for vegetable pathway for radionuclide i for theorgan of interest, (units ~ m~-mrem/yr per pCi/sec)

K'L

Us

A constant of unit conversion, 1E6 pCi/pCi.

The consumption rate of fresh leafy vegetation by thereceptor in age group a, (units ~ kg/yr)The consumption rate of stored vegetation by the receptor inage group a (units ~ kg/yr)The fraction of the annual intake of fresh leafy vegetationgrown locallyThe fraction of the annual intake of stored vegetation grownlocally

Yy

The average time between harvest of leafy vegetation and itsconsumption, (units sec)

The average time between harvest of stored vegetation andits consumption, (units ~ sec)

The vegetation areal P density, (units ~ kg/m~)

All other factors have been defined previously.

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

In lieu of site-specific data, values for Fz and F, of, 1.0 and 0.76/respectively, were used in the calculation. These values were obtainedfrom Table E-15 of Regulatory Guide 1.109 Revision 1.

The concentration of tritium in vegetation is based on the airborneconcentration rather than the deposition. Therefore, the R>(V) is basedon X/Q:

Rp(V) ~ K K [U sf' U ~ c] (DFL)> 0'5 (0'/H)Where:

+(V) = dose factor for the vegetable pathway for tritium forany organ of interest, (units ~ mrem/yr per pCi/m').

All other terms are defined in preceeding sections.

003856LL 86


TABLE C-l

Parameters for Grass-(Cow or Goat)-Milk Pathways

Parameter

Qr (kg/day)

(DFL)> (mrem/pCi)

F (pCi/liter per pCi/day)

Y, (kg/m~)

Y~ (kg/ma)

t„ (seconds)

t, (seconds)

U~ (liters/yr)

Value

50 (cow)6 (goat)

1.0 (radioiodines)0.2 (particulates)Each radionuclide

Each stable element

2.0

0,7

7.78 x 10'90 days)

1.73 x 10~ (2 days)

330 infant330 child400 teen310 adult

ReferenceRe . Guide 1.109 Rev. 1

Table E-3Table E-3

Table E-15Table E-15

Tables E-11 to E-14

Table E-1 (cow)Table E-2 (goat)

Table E-15

Table E-15

Table E-15

Table E-15

Table E-5Table E-5Table E-5Table E-5

003856LL 87


0

TABLE C-2

Parameters for the Grass-Cow-Meat Pathway

~arameter

F< (pCi/Kg per pCi/day)

(Kg/yr)

(DFL)> (mrem/pCi)

Y, (kg/m~)

Y, (kg/mi)

tb (seconds)

t, (seconds)

Qi (kg/day)

Value

1.0 (radioiodines)0.2 (particulates)Each stable element

0 infant41 child65 teen110 adult

Each radionuclide

0.7

2.0

7.78E6 (90 days)

1.73E6 (20 days)

50

ReferenceRe . Guide 1. 109 Rev. 1

Table E-15Table E-15

Table E-1


Tables E-11 to E-14

Table E-15

Table E-15

Table E-15

Table E-15

Table E-3

003856LL 88


TABLE C-3

Parameters for the Vegetable Pathway

Parameter

r (dimensionless)

(DFL)> (mrem/pCi)

U")~ (kg/yr) - infant« child- teen- adult

U'), (kg/yr) - infant- child- teen- adult

t„ (seconds)

t~ (seconds)

Yv (kg/m')

Value

1.0 (radioiodines)0.2 (particulates)Each radionuclide

0264264

0520630520

8.6E4 (1 day)

5.18E6 (60 days)

2.0

ReferenceRe . Guide 1.109 Rev. 1

Table E-1Table E-1

Tables E-11 to E-14



Table E-15

Table E-15

Table E-15

003856LL 89


APPENDIX D

DIAGRAMS OF LIQUID AND GASEOUS TREATMENT SYSTEMSAND

MONITORING SYSTEMS

003856LL 90


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Documents

Nuclear Regulatory CommissionITEM SUMMARY (Page 2 of 3) 2) A paragraph was added to Section 3.1.3, "Recombiner Discharge (Offgas) Monitor Setpoints" to reflect the Technical Specification