ML17056C297

NMPNS - Unit 2 Odcm.

ML17056C297
Person / Time
Site:	Nine Mile Point
Issue date:	06/30/1992
From:	Terry C NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17056C296	List: ML17056C295 ML17056C297 ML18038A737
References
PROC-920630, NUDOCS 9303110045
Download: ML17056C297 (122)

Text

~+~IN 7 V.P. Nuclear Engineering C. D. Terry v 'v 6 30 2 iii,12-14,17,18,28-31,34, 37-53,55-58,60-82,87-89,92 May 1986 15 May 1987 54 May 1987 (TCN-I) 19 June 1987 g CN-2) 90-91,93-103 February 1988 20-27,83-86 April 1988 I-ll November 1988 1-11,16,32-33,35-36,59 February 1990 100-102,106 June 1992 .

THIS PROCEDURE NOT TO BE USED AFTER JllNF. 1qq4 SUBJECI'TO PEMODIC REVIEW.

93031i0045 930301 PDR ADOCK 05000410 R PDR

.~ ~

TABLE OF CONTENTS SECTION SUB JECT TS SECTION APPLICABLE PAGE or TABLE or TABLE PROCEDURE

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS N/A 2 2.1 Liquid Effluent Monitor Alarm Setpoints '/A 2

2.1.1 Basis 3.11.1.1 N/A 2 2.1.2 Setpoint Determination Methodology 3.3.7.9 N/h 2 2.1.2.1 Liquid Radwaste Effluent Radiation N2-CSP-4V 2<<3 Alarm Setpoint 2.1.2.2 Contaminated Dilution Water Radwaste N/A Effluent Monitor Alarm Setpoint Calculations 2.1.2.3 Service Water and Cooling Tower Blowdown N2-CSP-13 hpp. D Effluent Radiation Alarm Setpoint 2.1.3 Discussion N/h 5 2.1.3.1 Liquid Radwaste Effluent N/A 6-9 2.1.3.2 Service Water and Cooling Tower Blowdown 10-12 2.2 Liquid Effluent Concentration 3. 11.1. 1 N2-CSP-4V 12 Calculation 4.11.1.1.2 2.3 Liquid Effluent Dose Calculation 3.11.1.2 N2-CSPWV 13-14 3.11.1.3 4.11.1.2 4.11.1.3.1 Liquid Effluent Dose Factor 14-15 Derivation - hit 2.5 Liquid Effluent Sampling 4.11.1-1 N2-CSP-4V 15-16 Representativeness note b 2,6 Liquid Radwaste System Operation 3.11.1.3 16-17  !

Table 2-1 Liquid Effluent Detector Response 18 Table 2-2 hit Liquid Effluent Dose Factor 19 Figure 2-1 Liquid Radwaste Treatment System 3.11.1.3 20-27 {

thru 2-8 Flow 3.11.3 2-9 Liquid Radiation Monitoring Diagrams'igure 28 ~

Figure 2-10 Off-line Liquid Monitor 29, 3.0 GASEOUS EFFLUENTS 30 3.1 Gaseous Effluent Monitor Alarm Setpoints 30 3.1.1 Basis 3.11.2.1 30 3.1.2 Setpoint Determination Methodology 3.3.7.10 30 3.1.2.1 Stack Noble Gas Radiation Alarm Setpoint N2-CSP-13 hpp. D 30-31 3.1.2.2 Vent Sgrle Gas Radiation Alarm Setpoint N2-CSP-13 'hpp. D 31-32 3.1.2.3 Offgas Pretreatment Radiation Alarm 32 Setpoint 3.1.3 Discussion 33 3.1.3.1 Stack Effluent 34 3.1.3.2 Vent Effluent 35 3.1.3.3 Offgas Process 36 3~2 Gaseous Effluent Dose Rate Calculation 3.11.2.1 N2-CSP-7V 37

.2.1 Total Body Dose Rate Due to Noble Gases 3.11.2.l.a N2-CSP-7V 37-38 4.11.2.1.1 3.2.2 Skin Dose Rate Due to Noble Gases 3.11.2.1.a N2-CSP-7V 38-39

4. 11.2.1. 1

I TABLE OF CONTENTS SECTION SUBJECT TS SECTION APPLICABLE PAGE '

or TABLE or TABLE PROCEDURE 3.2.3 Organ Dose Rate Due to I-131, I-133, N2-CSP-7V 39-41 Tritium and Particulates <<ith half- 3.11.2.1.b lives greater than 8 days 4.11.2.1.2 Caseous Effluent Dose Calculation 3.11.2.2 (

'1-42 3.3 N2-CSP-7V t, Methodology 3.11.2.3 3.11. 2. 5 3.3.1 Gamma Air Dose Due to Noble Gases 3.11.2.2.a N2-CSP-7V 42 4,11.2.2 3.3.2 Beta hir Dose Due to Noble Cases 3.11.2.2.b N2-CSP-7V 43 <

3.3.3 Organ Dose Due to I-131, I-133, Tritium N2-CSP-7V 43-45 ~

and Particulates <<ith half-lives 3.11.2.3 greater than 8 days. 3.11.2.5 4.11.2.3 4.11.2.5.1 3.4 Gaseous Effluent Dose Factor Definition 45 and Derivation 3.4.1 Bi- Plume Shine Gamma hir Dose Factor 45<<47 Vi- Plume Shine Total Body Dose Factor 3.4.2 Ki, Li, Mi and Ni- Immersion Dose Factors 47 3.4.3 Pi- Iodine, Particulate and Tritium 47-51 Organ Dose Rate Factors 4.4 Ri- Iodine, Particulate and Tritium 51-57 Organ Dose Factors 3 '.5 X/Q and Nr- Dispersion Factors for Dose Rate 3.4.6 Ms and Mv- Dispersion Factors for Dose 3.5 Gaseous Effluent I-133 Estimation N2~P-78Q 59 I 3.6 Vse of Concurrent Meteorological Data vs. 59

(

Historical Data I 3.7 Gaseous Rad<<aste Treatment System 3.11.2.4 59 I Operation 1 I

3.8 Ventilation Exhaust Treatment System 3.11.2.5 60, Operations Table 3-1 Offgas Noble Cas Detector Response 61 Table 3-2 Bi and Vi- Plume Shine Dose Factors 62

(

Table 3-3 Ki. Li, Mi and Ni- Zsssersion Dose Factors 63 Table 34 Pi- Cround Plane Dose Rate Factors 64 Table 3-5 Pi- Inhalation Dose Rate Factors 65 Table 3-6 Pi- Food (Co<< Milk) Dose Rate Factors 66 Table 3-7 Ri- Inhalation Dose Factors for Infant 67-70 to 3-10 Child, Teen and hdult Table 3-11 Ri- Ground Plane Dose Factors 71 Table 3-12 Ri- Co<<milk Ingestion Dose Factors for 72-75 to 3-15 Infant, Child, Teen and Adult Table 3-16 Ri- Co<<meat Ingestion Dose Factors for 76-78 to 3-18 Child, Teen and Adult Table 3-19 Ri- Vegetation Ingestion Dose Factors for 79-81 3-21 Child, Teen and Adult

SECTION TS SBCIION QijjG X/Q, Wv and Ws-Dispersion Factors for Receptor Locations Figure 3-1 thru Gaseous Radwastc Treatment System How Diagrams 3.11.2 4 3-3 Figure ~ Ventilation Exhaust Treatment System How Diagrams 3.11.29 Figure 3-5 Gaseous Radiation Monitoring 87 Figure 34 Gaseous Bfllucnt Monitoring System 88 4.0 URANIUMFUEL CYCLE 3.11.4 89 4.1 Evaluation of Doses &am Liquid Efliucnts 4.11.4.1 4.2 Evaluation of Doses hem Gaseous EIIlucnts 4.11.4.1 Evaluation of Doses from Direct Radiation 4.11.4.2 4,4 Doses to Members of the Public Within Site Boundary 6.9.1.8 93 5.0 ENVIRONMENTALMONITORING PROGRAM 3.12 95 4.12 5.1 Sampling Stations 3.12.1 95 4.12.1 5.2 4.129 95 CapabiTitics for Thcrmoluminciccnt Dosimctcrs Used for 97 Environmental Mcasuremcnts Table 5.1 Radiological Environmental Monitoring Program Sampling 3.12.1 Locations 4.12.1 Table 3.12-1 Note (a) 6.0 DISCUSSION OF TECHNICALSPECIFICATION REFEIKNCE 6.1 Table 3.12-1, Note (g) 6.2 Table 3.12-1, Note (h)

Table 3.12-1, Note (i) 6.4 Table 3.12.1, Note (I)

Figure 5.1-1 Nine Mile Point On4itc Map 105 Figure 5.1-2 Nine Mile Point Olf4itc Map Figure 5.ID-I Site Boundaries

~~~

Ot

1 S 1.0 This is the OFFSITE OOSE CALCULATION HANUAL (OOCH), referenced in the Nine Hile Point - Unit 2 Technical Specification. It describes the methodology for liquid and gaseous effluent monitor alarm setpoint calculations, the methodology for computing the offsite dose due to liquid effluents, gaseous effluents, and the uranium fuel cycle as well as the radiological environmental monitoring and interlaboratory comparison programs.

The ODCH will be reviewed and approved by the Site Operations Review Comnittee. Changes shall be provided in the semi annual radioactive effluent release reports submitted to the NRC.

Section 2 establishes methods used to calculate the Liquid Effluent Honitor Alarm setpoints and to demonstrate compliance with TS Section 3.11.1.1 limits on concentration of releases to the environment as required in TS Section 3.3.7.9 and 4.11.1.1.2 respectively.

Additionally, the method used to calculate the cumulative dose contributions from liquid effluents and the methods used to assure thorough mixing and sampling of liquid radioactive waste tanks to be discharged as required in TS Section 4. 11.1.2, 4. 11. 1.3. 1 and Table 4.11.1-1 note b respectively are presented.

Section 3 establishes calculational methods used to calculate the Gaseous Effluent Honitor Alarm setpoints and to demonstrate compliance with TS Section 3. 11.2. 1 limits on dose rates due to gaseous releases to the environment as required in TS Section 3.3.7.10, 4.11.2.1.1 and 4.11.2.1.2 respectively. Additionally, the calculational methods used to calculate cumulative dose contributions from gaseous effluents as required in TS Section 4.11.2.2, 4,11.2.3 and 4.11.2.5 are presented.

Section 4 establishes the method used to determine cumulative dose contributions from the Uranium Fuel Cycle as required by TS Section

4. 11.4.1, 4.11.4.2 and 6.9. 1.8.

Section 5 establishes the environmental monitoring program as required by TS Section 3. 12 and 4.12 including the Interlaboratory Comparison Program required by TS Section 4.12.3.

Section 6 discusses some of the references contained in TS Table 3.12-1, Radiological Environmental Honitoring Program.

2.0 LIQUID EFFLUENTS Serv1ce Hater A and B, Cooling Tower Blowdown and the Haste Discharges comprise the Rad1oact1ve L1quid Liquid'adioactive-Kffluints at Un1t 2. (See figure 2-9) Presently there are no temporary outdoor tanks containing rad1oactive water capable of affecting the nearest known or future water supply in an unrestr1cted area. NVREG 0133 and Regulatory Guide 1.109. Rev. l were followed in the development of this section.

2.1 L1quid Effluent Honitor Alarm Setpoints

2. l. 1 Basis Techn1cal Spec1f 1 cat1on 3. 1. l .

1 1 prov1de the bas1s for the al arm setpoints: The concentration of radioact1ve mater1al released in liquid effluents to UNRESTRICTED AREAS (see F1gure 5.1.3-1) shall be 11mited to the concentrat1ons spec1fied 1n 10 CFR 20, Appendix 8, Table II, Column 2, for radionucl ides other than d1ssol ved or entrained noble gases. For d1ssolved or entrained nobles gases, the concentrat1on shall be 11mited by 2 x l0-4 microcurie/ml total activity.

2.1.2 Setpoint Determinat1on Hethodology 2.1.2.1 Liquid Radwaste D1scharge Honitor Alarm Setpo1nts Th1s monitors setpoint takes 1nto account the dilution of Radwaste Effluents prov1ded by the Service Hater and Cooling Tower Blowdown flows. Detector response for the nucl1des to be discharged (cpm) is multipl1ed by the Actual Dilution Factor (d1lution flow/waste stream flow) and d1v1ded by the Requ1red Dilut1on Factor (RDF, total fraction of HPC 1n the waste stream). A safety factor is used to ensure that the l1m1t is never exceeded. Serv1ce Hater and Cool1ng Tower Slowdown are normally non-rad1oact1ve. If they are found to be contaminated prior to a L1quid Radwaste discharge then an alternative equat1on 1s used to take into account the contaminat1on. If they become contaminated during a Radwaste d1scharge, then the discharge will be iaeedlately terminated and the s1tuat1on fully assessed.

Normal Radwaste Discharge Hon1tor Setpo1nt Calculation:

Alarm Setpoint < [0.$ '(F/f)'Z1(Cl'CF1)7/fZ1(C1/HPC1)7 + Background.

Nore:

Narm Setpoint The Discharge Honitor Alarm Setpoint, cpm 0.8 Safety Factor, unitless F Nonradioact1ve dilution flow rate, gpm. Service

Flow ranges from 30,000 to 58,000 gpm.

Blowdown flow is typically 10,200 gpm.

Ci Concentration of 1sotope 1 in Radwaste tank pr1or to dilut1on, pC1/ml Cji Detector response for 1sotope 1, net cpm/F1/ml See Table 2-1 for a list of nom1nal values f The perm) ssible Radwaste Effluent Flow rate, gpm Symbol to denote multiplication.

HPC1 Concentrat1on limit for 1sotope 1 from 10CFR20 Append1x B, Table II, Column 2, F1/ml Background Detector response when sample chamber 1s fi lied F/f'ater E1(C1*CF1) with nonradioact1ve water, cpm The total detector response when exposed to the concentration of nuclides in the Radwaste tank, cpm Ei(C1/HPC1) The total fract1on of the 10CFR20, Append1x 8, Table II, Column 2 limit that is in the Radwaste tank, unitless. This 1s also known as the Requ1red Dilution Factor (RDF)

CR*E1C1 An approx1mation toE1(C1CF1) determined, at each cal1bration of the effluent mon1tor, by record1ng monitor cpm response to a typical radwaste tank mixture analyzed by multichannel analyzer (traceable to HBS). CR 1s a we1ghted sumaation of CF (a conservatively lower CR may

,be used).

An approximation to (F+f)/f, the Actual Dilution Factor in effect during a d1scharge.

Required Dilution Factor Permiss1ble effluent flow, f, shall be calculated to determine that HPC w111 not be exceeded in the d1scharge canal.

(RDF) 0 1.5 Fraction Tempering A d1version of some fract1on of discharge flow to the 1ntake canal for the purpose of temperature control.

KIES-'. If Actual Dilution Factor 1s set equal to the Requ1red D1lut1on Factor, then the alarm po1nts required by the above equations correspond to a concentrat1on of BOL of the Radwaste Tank concentration. No discharge could occur, since the monitor would be in alarm as soon as the discharge coaeenced. To avoid this s1tuat1on, max1mum allowable radwaste d1scharge flow 1s calculated using a mult1ple (usually 1.5 to 2) of the Required Dilution Factor, result1ng 1n a maximum discharge canal concentrat1on of 2/3 to 1/2 of HPC prior to alarm and term1nat1on of release.

2. To ensure the alarm setpoint 1s not exceeded, an alert alarm 1s prov1ded. The alert alarm will be set in accordance w1th the equat1on above using a safety factor of 0.5 (or lower) 1nstead of 0.8.

2. 1.2.2 Contaminated Dilution Hater Radwaste Effluent Honitor Alarm Setpo1nt Cal cul at1on:

Tba. al.lowable discharge flow rate for a Radwaste tank, when one of neiml'dilution streams (Serv1ce Hater A, Serv1ce Hater B, or Cool1ng Towe BIOvdown) 1s contaminated, will be calculated by an 1terat1ve 'process.

Using Radwaste tank concentrat1ons w1th a nominal radwaste effluent flow rate <200 gpm, for example) the resulting fraction of Npc <Fmpc) in the [a discharge canal will be calculated.

.=HPC s Zi tZs(Fs*Cis)/(HPC1 Zs[Fsl)]

Then the perm1ssible radwaste effluent flow rate 1s g1ven by:

f em FMPC~2 The corresponding Alarm Setpo1nt w111 then be calculated us1ng the f

follow1ng equation, with limited as above.

0.8'Z1(C1*CF1)

Alarm Setpoint + Background Z1 [Zs(Fs~C1 s) /(HPC1 <<Zs kFs l) l Hhere:

Alarm Setpoint The D1scharge Hon1tor Alarm Setpoint, cpm 0.8 Safety Factor, Unitless Fs An Effluent flow rate for stream s, gpm C1'i Concentration of 1sotope 1 in Radwaste tank pr1or to d11ut1on, F1/ml s Concentrat1on of isotope 1 1n Effluent stream s Includ1ng the Radwaste Efi'luent tank und1luted, F1/ml CF1 Detector response for 1sotope 1, net cpm/pC1/ml See Table 2-1 for a list of nominal values HPC1 Concentrat1on limit for isotope 1 from 10CFR20 Appendix B, Table II, Column 2, F1/ml The permissible Radwaste Effluent Flow rate, gpm Background Detector response when sample chamber 1s f1lled with nonradioact1ve water. cpm Zl (C1 *CF1) The total detector response when exposed to the concentration of nucl1des in the Radwaste tank,

~%

cpm CSFs*C1 sl The total activity of nucl1de 1 1n all Effluent streams, pC1-gpm/ml ZstFs3 The total L1quid Effluent Flow rate, gpm (Serv1ce Hater 5 CT Blowdown 5 Radwaste)

2.1.2.3 Service Hater and Cooling Tower Blowdown Effluent Alarm Setpoint These monf tor setpolnts do not take any credi t for df lutfon of 'each:

respec'tl ve'effluent stream. Detector response for the dl stributlon of nuclide's potentially discharged is divided by the total HPC fraction of the radtonuclfdes potentially ln the respective stream. A safety factor fs used to ensure that the limit is never exceeded.

Service Hater and Cooling Tower Blowdown are normally non-radioactive. If they are found to be contaminated by statistically significant increase in detector response then grab samples will be obtained and analysis meeting the LLD requirements of Table 4.11-1 completed so that an estimate of offsite dose can be made and the situation fully assessed.

Service Water and Cooling Tower Blowdown Alarm Setpoint Equation:

Alarm Setpofnt < [0.8'Zl (Cf'CFf)]/[Ef (Cf/HPCf)] + Background.

Hhere:

Alarm Setpolnt The Radiation Detector Alarm Setpofnt, cpm 0.8 Safety Factor, unltless Cl Concentration of isotope 1 as potential contaminant, pCf/ml CF1 Detector response for isotope 1, net cpm/pCf/ml See Table 2-1 for a list of nominal values HPCl Concentration limit for isotope I from 10CFR20 Appendix B, Table II, Column 2, pCf/ml Background Detector response when sample chamber fs filled with nonradloactlve water, cpm El(C1*CFf) The total detector response when exposed to the concentration of nuclides in the potential contaminant, cpm El(C1/HPC1) The total fraction of the 10CFR20, Appendix B, Table II, Column 2 llmlt that ls ln the potential contaminant, unltless.

CR*Z1C1 An approximation to El(C1CF1) determined, at each calibration of the effluent monitor, by recordfng monitor cpm response to a typical contaminant mixture analyzed by multichannel analyzer (traceable to NBS). CR ls a weighted summation of'Fi.

2.1.3 Dfscussfon

2.1.3.1 Liquid Radwaste Effluent Honl tor The 'iquid Radioactive Waste System Tanks are pumped to the =dl scha

~ ..'lNnef. which'n turn flows directly to Lake Ontario. At the end of d~harge tunnel in Lake Ontario, a diffuser structure has been installed.

Iti purpose ls to maintain surf'ace water temperatures low enough to meet thermal pollution limits. However, it also 'ssists *in the near field dilution of any activity released. Service Hater and the Cooling Tower Slowdown are also pumped to the discharge tunnel and will provide dilution. If the Service Hater or the Cooling Tower Blowdown ls found to be contaminated, then its activity will be accounted for when calculating the permissible radwaste effluent flow f'r a Liquid Radwaste discharge.

The Liquid Radwaste System Monitor provides alarm and automatic termination of release if radlatlon levels above its alarm setpoint are detected.

The radlatlon detector ls a sodium iodide crystal. It is a sclntillatlon device. The crystal ls sensitive to gaaea and beta radiation. However, because of the metal walls of the sample chamber and the absorption characteristics of water, the monitor is not particularly sensitive to beta radiation. Actual detector response E1(C1*CF1), cpm, will be evaluated by placing a sample of typical radloactlve waste into the monitor and recording the gross count rate, cpm. A calibration ratio, CR, cpm/F1/ml, will be developed by divldlng the noted detector response, El(C1'CF1) cpm, by total concentration of activity El(Cl), pC1/cc.

The anent>f)cation of the games actSvSty u11l be completed ufth games equipment whose calibration ls traceable to NBS. This [

'pectrometry calibration ratio will be used for subsequent setpolnt calculations in the determination of'etector response:

El(C1<<CF1) CR*E1(C1)

Where the factors are all as defined above.

For the calculation of El(C1/HPC1) the contribution from non ganma emittsng nuclsdes except trst>um mill be estsmated based on the expected [

ratios to quantified nuclides as listed in the FSAR Table 11.2.5. Fe-55, Sr-89 and Sr-90 are 2.5, 0.25 and 0.02 times the concentration of Co-60.

5 Tritium concentration ls assumed to equal the concentration detected ln the latest available monthly Tritium analysis (performed offslte) on 11quid radioactive waste tanks discharged. m

Hominal flow rates of the L1qu1d Radioactive Haste System Tanks discharged is <165 gpm while d1lution flow from the Serv1ce Hater Pumps and Cooling Tower Blowdown cuamulatively is typically over 20,000 .gpi..Because of the large amount of dilution the alarm setpoint coold be substantially greater than that wh1ch would correspond to the concentration actually in the tank. Potentially a discharge could cont1nue even if the d1stribution of'ucl1des in the tank were substantially different from the grab sample obta1ned prior to discharge which was used to establ1sh the detector alarm po1nt. To avoid this poss1bility of "Non representat1ve Sampling" result1ng in erronous assumptions about the d1scharge of a tank, the tank is rec1rculated for a minimum of 2.5 tank volumes prior to sampling.

A sample calculat1on 1s presented below assuming tank concentrat1ons equ1valent to the d11uted concentrat1on presented 1n FSAR Table 11.2.5 wh1ch 1s the expected concentrat1on of effluent waste after d1lut1on th are d1scharged w1th the des1gn 11m1t for fuel fa1lure (the table below thO und11uted concentrat1on correspond1ng to a tank 2040 gal per d discharge w1th only coo11ng tower blowdown d1lut1on of'0,200 gpm)..

ISOTOPE ACTIVITY MPC FRACTION DETECTOR CPH NAHE CONCENTRATION OF HPC RESPONSE TOTAL pC1/ml F1/ml (8/C) cpm/pCI/ml cpm 8 C D E F (C1 ) (HPC1) (C1 /HPC1 ) <CF1) (C1CF1)

K3 8.4E-3 3E-3 2.8 NA24 1.7E-6 3E-5 5.7E-2 P32 6.8E-S 2E-5 3.4E-3 CR51 2.0E-6 2E-3 1.03-3 MN54 2.4E-S lE-4 2.4E-4 8.42E7 1. 98E+0 MN56 3.2E-7 1E-4 3.2E-3 1.2EB 3.9E+0 5 FE55 3.5E-7 BE-4 4.3E-4 i FE59 1.0K-B 5E-5 2. 1E-4 8.63E7 9.0E-1 C058 6.8E-B 9E-5 7.6E-4 1.14EB 7.8E+0 CO60 1.4E-7 3E-5 4.7E-3 1.65EB 2.4E+1 NI63 3.5E-10 3E-5 1.1E-S NI65 1.8E-9 1E-4 1.8E-S CU64 4.3E-6 2E-4 2.1E-2 ZN65 6.8E-S lE-4 6.8E-4 BR83 3.3E-S 3E-6 1.1E-2 BR84 8.9E-14 1.12EB SR89 3.6E-S 3E-6 1.2E-3 7.8E3 SR90 2.4E-9 3E-7 7.8E-3 SR91 4.6E-7 5E-5 9.3E-3 1.22EB 5.7E+1 SR92 7.6E-S 6E-5 1.2E-3 8.17E7 6.1E+0 Y91 1.7E-B 3E-5 5.7E-4 2.47KB 4.2E+0 Y92 4,6E-7 6E-5 7.8E-3 2.05E7 9.5 Y93 5.1E-7 3E-5 1.7E-2 ZR95 2.7E-9 6E-5 4.5E-S 8.35E7 2.3E-l ZR97 1.0E-9 2E-5 5.2E-5 N895 2.7E-9 1E-4 2.7E-5 8.5E7 2.4E-l H099 6.0E-7 4E-5 1.6E-2 2.32E7 1.4E+1 TC99H 1.2E-6 3E-3 4.1E-4 2.32E7 2.BE+1 RU103 6.8E-9 BE-5 8.5E-5 RU105 6.8E-S 1E-4 6.8E-4 RU106 1.0E-13 1E-5 1.0E-B AG110H 3.5E-10 3E-3 1.1E-7 TE129H 1.4E-S 2E-5 7.0E-4 TE131H 2.4E-S 4E-5 6.0E-4 ISOTOPE ACTIVITY MPC FRACTION DETECTOR CPH NAHE CONCENTRATION OF HPC RESPONSE TOTAL F1/ml pC1/ml B/C cpm/12C1/ml cpm A .B'Ci C D E F

) (HPC1) (C1/MPCi) (CF1) (C1CF1)

TE132 2.9E-9 ZE-5 1.5E-4 1.12EB 3.3E-1 I131 1.4E-6 3E-7 4.7 1.01EB 1.4E+2 I132 2.5E-7 BE-6 3.1E-2 2.63EB 6.7E+1 I133 1.2E-5 1E-6 12.3 9.67E7 1.2E+3 I'134 7.2E-10 2E-5 3.6E-5 2.32EB 1.7E>>1 I135 3.8E-6 4E-6 9.4E>>l 1.17EB 4.4E+2 CS134 5.1E-6 9E-6 5.7E-1 1.97EB 1.0E+2 CS136 3.3E-7 6E-5 5.5E-3 2.89EB 9.4E+1 CS137 1.3E-6 ZE-5 6.6E-2 7.32E7 9.5E+1 f 5

CS138 8.4E-12 1.45EB 1.2E>>3 BA140 1.3E-7 2E-5 E.SE-3 4.99E7 6.6E+0 LA142 3.2E-9 3E-6 1.1E-3 CE141 1.0E-S 9E-5 1.1E-4 CE143 7.6E-9 4E-5 1.9E-4 CE144 7.6E-9 1E-5 7.6E-4 1.03E7 7.86-2 PR143 1.4E-B SE-5 2.8E-4 ND147 1.0E-9 6E-5 1.7E-9 H187 6.3E-S 6E-5 1.0E-3 NP239 2.3E-6 1E-4 2.3E-2 TOTALS 2.1E+1 ~

2.3E+3 o For the example tank, permiss1ble discharge flow to ensure a concentrat1on less than MPC 1n the d1scharge canal would be:

S1nce max1mum obtainable Liquid Radwaste discharge flow is 165 gpm, this value would be used for the discharge, and for calculation of the alarm setpo1nt.

The L1qu1d Radwaste Effluent Rad1ation Honitor Alarm Setpoint equation is:

Alarm Setpo1nt [0.8'F/f'Z1(C1'CF1)]/[Z1(C1/HPC1)l + Background.

llheee the Alasss Setpnlnt 1s ln spm, F ls 10,200 ppm, Et(01*CFS> ls 2.3E+3 cpa, f 1s 165 gpm and Z1(C1/MPC1) is 2.1E+1 unitless. These values y1eld I

aa Alarm Setpoint of 5.4E+3 cpm above background, wh1le the expected detector response 1s 2.3E+3 cpm. It should be noted that the lack of detector response data for many of the nuc11des makes this calculation

)

conservative.

2.1.3.2 Service Hater and Cooling Tower Blowdown Effluent Hon1tor Serv'ice Hater A and 8 and the Coo11ng Tower Blowdown are pumped to discharge'unnel wh1ch 1n turn flows d1rectly to Lake Ontario. Normal f rates 'for. each Service Hater Pump 1s l0,000 gpm while that for the Coo11 Teier Blowdown 1s 10,200 gpm. Cred1t is not taken for any d1lut1on of these 1ndividual effluent streams.

The radiation detector is a sodium iod1de crystal. It 1s a scintillation device. The crystal 1s sensit1ve to gambia and beta rad1ation. However, because of the metal walls in 1ts sample chamber and the absorption characteristics of water, the monitor 1s not particularly sens1tive to beta rad1ation.

Detettor response E l(C'1*CF S> vill be evelueted dursng every fuel uyule by a d1luted sample of Reactor Coolant (after a two hour decay) in a I'lacing representat1ve monitor and not1ng 1ts gross count rate. Reactor Coolant 1s chosen because it represents the most 11kely contam1nate of Station Haters.

A two hour decay 1s chosen by )udgement of the staff of Niagara Hohawk Power Corporation: Reactor Coolant with no decay conta1ns a considerable amount of very energetic nucl1des which would blas the detector response term h1gh. However assuming a longer than 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> decay is not realistic as the most likely release mechanism is a leak through the Res1dual Heat Removal Heat Exchangers which would conta1n Reactor Coolant during shutdowns.

The 1nit1al setpo1nt calculat1on is presented as both an example and for the purposes of documenting the calculat1on.

ISOTOPE 2 HR DECAY HPC FRACTION OETECTOR CPH NHE ACTIVITY OF HPC RESPONSE TOTAL CONCENTRATION pC1/ml 8/C cpm/pC1/ml cpm F1/mi A 8 H3 l:OE-2 3E-3 3.3 F18 l '. 9E-3 5E-4 3.8 N24 3.7E-3 3E-5 1.2E-2 P32 7.8E-5 ZE-5 3.9 CR51 2.3E-3 2E-3 1.2 MN54 4.0E-S lE-4 .4.0E-l 8.42E7 3.4E3 MN56 2.9E-Z lE-4 2.9E-2 1.2EB 3.5E6.

FE55 3. 9E-4 8E-4 4.9E-l FE59 8.0E-S SE-5 l.6 &.63E7 6.9E3 C058 5.0E-3 9E-5 5.6E-l C060 " 5.0E-4 3E-5 1.7E-l 1.14EB 1.65EB 5.7E5 8.3E4 NI63 3.9E-7 3E-5 1.3E-2

ISOTOPE 2 HR DECAY MPC FRACTION DETECTOR CPM NAME ACTIVITY OF HPC RESPONSE TOTAL CONCENTRATION pCl/ml 8/C cpm/pCl/ml cpm pC)/ml .

A

' E F F) 1 ))

NI65 3.0E-4 1E-4 3.0 CU64 1. 1E-2 ZE-4 5.5El ZN65 7.8E-S 1E-4 7.8E-1 ZN69H 7.4E-4 6E-5 1.2E1 BR83 1.3E-2 3E-6 4.3E3 BR84 2.1E-3 1.12EB 2.4E5 RB89 1.0E-4 SR89 3.1E-3 3E-6 1.0E3 7.8E3 2.4E1 SR90 2.3E<<4 3E-7 7.7E2 SR91 &.QE-2 SE-5 1.2E3 1.22EB 7. 3E6 SR92 6.6E-2 6E-5 1. 1E3 8.17K7 5.4E6 Y91 1.1E-4 3E-5 3.7 2.47EB 2.7E4 Y92 1.3E-2 6E-5 2.2E2 2.05E7 2.7E5 Y93 1.0E-2 3E-5 3.3E2 ZR95 4.0E-5 6E-5 6.7E-1 8.35E7 3.3E3 ZR97 2.9E-5 2E-5 1.5 NB95 4.1E-S lE-4 4. 1E-1 B.SE7 3.5E3 H099 2.2E-2 4E-5 5.5E2 2.32E7 5.1ES TC99H 2.2E-l 3E-3 7.3E1 2.32E7 5.1E6 RU103 5.4E-S BE-5 6.8E-l RU105 4.5E-3 1E-4 4.5El RU106 8.4E-6 1E-5 8.4E-1 AG110H 6.0E-5 3E-5 2.0 TE129H l. 1E-4 2E-5 5.5 TE1 31M 2.7E-4 4E-5 6.8 TE132 4.8E-2 2E-5 2.4E3 1.12EB 5.4E6 I131 1.3E-2 3E-7 4.3E4 1.01EB 1.3E6 I132 1.2E-1 BE-6 1.5E4 2.63EB 3.2E7 I133 1.5E-1 lE>>6 1.5E5 9.67E7 1.45E7 I134 , B.QK-2 2E-5 4.0E3 2.32EB 1.86E7 I135 1.4E-l 4E-6 3.5E4 1.17EB 1.6E7 CS134 1.6E-4 9E-6 1.8El 1.97EB 3.2E4 CS136 1. 1E-4 6E-5 1.8 2.89EB 3.2E4 CS'l 37 2.4E-4 2E-5 1.2E1 7.32E7 1.8E4 CS138 1.4E-2 1.45EB 2.0E6 BA140 9.0E-3 2E-5 4.5E2 4.99E7 4.5ES LA142 7.1E-3 3E-6 2.4E3 CE141 9E-5 CE143 4E-5 CE144 8.1E-5 1E-5 8.1 1.03E7 8. 3E2 '5 PR143 SE-5 ND147 6E-5 H187 6E-5 NP239 2.3E-l 1E-4 2.3E3

-. TOTALS 2.7E5 1.2EB The Service Water Efflueat Radiation Monitor Alarm Setpoint equation is -'

Alarm Setpoint ~ [0.8<<Zi(Ci*CPi)]/[Zi(Ci/MPCi)l + Backgrouad.

Here the Alarm Sctpoiat is in cpm, Zi(Ci*CPi) is 1.2E8 cpm, and ll(Ci/MPCi) is 2.7E5 unitless ~ These values yield an Alarm Setpoint of 3.55E2 cpm above background. It should be noted that the lack of detector response data for many of the nuclides makes this calculation conservative.

2.2 Liquid Effluent Concentration Calculatioa Thi.s calculation documeats compliance with TS Sectioa 3.11.1.1:

The concentration of radioactive material relcascd ia liquid effluents to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited to the conceatrations specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentratioa shall be limited to 2 x 10E-4 microcurie/ml total activity.

The conccatration of radioactivity from Liquid Radwaste, Service Water A.

and B aad the Cooling Tower Blowdown arc included 1a the calculation. The calculation is performed for a specific period of time. No credit taken f or averagiag or totaling. The limit1ng concentration is calculated as follows:

MPC Fraction ~ Zi [ Zs(Cis<<Fs)/(MPCi<<Zs(Ps))]

Where+ MPC Praction ~ The limiting conceatratioa of 10 CPR Appendix radioauclides B, Table other II, Columa than dissolved 2,

eatrained noble gases For noble gases, the coaccntratioa shall be limited to 2 x 10E-4

<microcurie/ml total activity, unitless Cia The conccntratioa of nuclide 1 in particular effluent stream s, uCi/ml Ps The flow rata of a particular effluent stream s, gpm MPCi ~ ~ The limiting conccatration of a specific auclide 1 from 10CPR20, Appendix b, Table II, Columa 2 (noble gas limit is 2E 4),

uCi/ml Zs(Cis<<Ps) The total activity rate of nuclide 1, in all the effluent streams s> uCi/ml <<gpm Zs(Ps) W The total flow rate of ail efflueat streams ss gpm'alue oi less than one for MPC fractioa is considered acceptable for compliance with TS Section 3.11.1.1-2.3 Liquid Effluent Dose Calculatioa Methodology This: . calcQation documeats compliance with TS Scctioa 4.11.1.2 sad 4.11.1'.3.1 for doses due to liquid releases. It is completed once per month to assure that TS Section 3.11.1-2 sad 3.11.1.3 src not exceeded:

The dose or dose commitment to a MEMBER OP THE PUBLIC from radioactive materials 1a liquid cffluents released, from each unit, to UNRESTRICTED AREAS (see Pigure 5.1.3-1) shall bc limited:

a. Duriag any calendar quarter to lese than or equal to 1.5 mrem to the whole body and to less thsa or equal to 5 mrem to any organ, and

b. Duriag aay calendar year to less thea or equal to 3 mrem to the whole body aad to less than or equal to 10 mrem to any organ.

The liquid radwaste treatment system shall be OPERABLE, and appropriate portions of thc system shall be used to reduce releases of radioactivity when the pro)ected doses due to the liquid affluent, from the un1t, to UNRESTRICTED AREAS (see figure 5 1.3-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ ia a 31&ay per1od.

Doses due to Liquid Efflueats are calculated monthly for the fish ingestion aad drinkiag water pathways from all detected nuclides in liquid effluents released to the unrestricted areas usiag the following expression from NUREG 0133, Sectioa 4.3.

Dt ZL [Aite XL*(dTlecileP1)1 Where:

Dt The cumulative dose commitment to thc total body or any organ, t from the liqu1d effluents for the total t1mc period EL(dZL) >

mrcm dTl The length of the 1 th time period over which Cil aad Fl are averaged for all 11quid releases, hours Cil The average concentration of radionuclide, 1, in undiluted liquid effluents during t1me pet'iod dTl from any liquid release, uC1/ml Ait The site related iagestion dose commitmcnt factor to thc total body or any organ t for each identified principal gamma or beta emitter, mrcm/hr per uCi/mls Table 2-2.

The near field average dilutioa factor for Cil during any liquid effluent release. Dcfincd as the ratio of the maximum uadiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 5.9. (5.9 is the site spccifice applicable factor for the mixing effect of the discharge structure.) Sce the Nine Mile Poiat Unit 2 Environmental Report - Operating License Stage, Table 5.4-2 footnote 1.

Example Calculation - Thyroid f

A'imple b a radwaste tank indicates I-131 and H-3 concentrations 25E-6 and 8.9E-3 uCi/cc respectively. The tank contains 20,000 gallons of waste to be discharged. The tank is discharged at 165 gpm and there is 30,000 gpm of available dilution water:

Dt zi[Ait*zl(dTl*Cil*Pl)].

Where Dt mrem is the dose to organ t, Ait mrem/hr per Xi/ml is the ingestion dose commitment factor, dT hours is the time interval over which the release occurs, Ci uCi/ml is the undiluted concentration of nuclide in the release and Fl unitless is the dilution factor for the release.

i From Table 2-2 Ait is 7.2]E4 and 3.37E-l mrem/hr per uCi/ml respectively for I-131 and H-3 dose to the thyroid. Prom the discharge and dilution flow rate, Pl unitless can be calculated-Pl ~ 165gpm/(30,000gpm *5.9) ~ 9.32E-04.

Prom the tank volume and discharge rate the length of time required for the discharge is:

dT 20,000 gal/165 gpm 121.2 min ~ 2.02 hr These values will yield 2.04E-4 and 5.65E-6 mrem for I-131 and H-3 respectively for the thyroid when inserted into the equation for Dt. Thus the total dose from the tank is 2.06E-4 mrem to the thyroid. The dose limit to the maximum exposed organ is specified by TS Section 3.11.1.2 a 3.11 1.3.

2.4 Liquid Effluent Dose Factor Derivation Ait Ait mrem/hr per uCi/ml takes into account the dose from ingestion of fish and drinking water. It should be noted that the fish ingestion pathway is the most significant pathway for dose from liquid effluents. The water consumption pathway is included for consistancy with NUREG 0133. Drinking water is not routinely sampled as part of the Environmental Monitoring Program because of its insignificance.

The above equation for calculating dose contributions requires the use of dose factor Ait for each nuclide, i, which embodies the dose factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin. The adult total body and organ dose factor for each radionuclide will be used from

%able E-11 of Regulatory Guide 1.109. The dose factor equation for a fresh 4ater site iss Ait ~ Ko*(Uw/Dw + UfeBPi)+DFi Where:

hit; 'nIs the composite dose parameter for the total body or organ of adult for nuclide, i, for all appropriate pathways, mrem/hr per uCi/ml Is the unit conversion factor, 1.14E5 IXlOE6pCi/uCi x 1E3 ml/kg -:- 8760 hr/hr Uw 730 kg/yr, adult water consumption Uf a 21 kg/yr, adult fish consumption BFi a Bioaccumulation factor for nuclide, i, in fish, pCi/kg per pCi/1, from Table A-1 of RC 1.109 DPi Dose conversion factor for nuclide, i, for adults in respective organ, t, in mrem/pCi, from Table E-ll of RC 1.109.

Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption. This is the Metropolitian Mater Board'.

Onondaga County intake structure located west of the City of Oswego. Prom the NMP-2 ER-OLS Table 5.4-2 footnote 3 this value is 463.8. However the near field dilution factor, footnote 1 is 5.9. So as to not take double account of the near fi eld dilution the value used for Dw is 463.8/5.9 or 78.6, unitless.

Inserting the usage factors of RC 1.109 as appropriate into the equation gives the following expression:

hit ~ 1.14E5~(730/Dw + 21"BPi)~DPi.

Example Calculation For I-131 Thyroid Dose Factor for exposure from Liquid Effluents:

DFi s 1.95E-3 mRem/pCi BFi ~ 1.5E1 pCi/Kg per pCi/1 UF ~ 21 Xg/yr Dw ~ 78.6 unitless Ko ~ 1.14E5 These: values will yield an hit Pactor of 7.21E4 mRem-ml per uCi-hr as listed on Table 2-2. It should be noted that only a limited number are listed on Table 2-2. These are the most common nuclides of'uclides encountered in effluents. If a nuclide is detected for which a factor is not listed, than it will be calculated and included in a revision to the ODCM.

2.5 Sampling Representativeness

%is section covers TS Table 4.11.1-1 note b concerning thoroughly mixin 3

~ ach batch of liquid radwaste prior to sampling.

There are four tanks in the radwaste system designed to be discharged to the discharge canal. These tanks are labeled 4i, 4B, 5A, and 5B.

Radwaste Tank 5h and 5B at Nine Mile point Unit 2 contain a sparger 1'iquid spray ring which assist the mixing of the tank contents while it is being recirculated prior to sampling. This sparger effectively mixes the tank four times faster than simple recirculation.

Liquid Radwaste Tank 4A and 48 contain a mixing ring but no sparger.

Ho credit is taken for the m1x1ng effects of the ring. Normal recirculation flow is l50 gpm for tank 5A and 5B, ll0 gpm for tank 4 and 48 while each tank contains up to 25,000 gallons although the entire contents are not discharged. To assure that the tanks are adequately mixed prior to sampling, it 1s a plant requirement that the tank be rec1rculated for the time required to pass 2.5 t1mes the volume of the tank:

Recirculation Time 2.5'T/R*H Hhere:

Recirculat1on Time Is the minimum t1me to recirculate the Tank, min 2.5 Is the plant requirement, unitless Is the tank volume, gal Is the recirculation flow rate, gpm.

Is the factor that takes into account the mixing of the sparger, unitless, four for tank 5A and 8, one for tank 4A and B.

Serv1ce Hater A and 8 and the Cooling Tower Blowdown are sampled from radiat1on mon1tor on each respect1ve stream. These monitors

'he continuously withdraw a sample and pump 1t back to the effluent stream.

2.6 1 w Technical Specification 3. ll.l.3 requires the Liquid Radwast Treatment System to be OPERABLE and used when pro)ected doses due to liquid radwaste would exceed 0 '6 mrem to the whole body or 0.2 mrem to any organ 1n a 31-day period. Cumulat1ve doses will be determined at l'east once per 31 days (as ind1cated in Section 2.3) and doses will also be pro)ected 1f the radwaste treatment systems are not being fully utilized.

Full utf l1zat1on will be determ1ned on the basis of utilization of the indicated components of each process stream to process contents of the respective system collect1on tanks:

1) Low Conductiv1ty (Haste Collector): Radwaste Filter (see Fig.

2-2) and Radwaste Demin. (see Fig. 2-3)

2) High Conductivity (Floor Dra1ns): Floor Drain Filter (see Fig.

2-5) or Haste Evaporator (see Fig. 2-6)

3) Regenerant Waste: Regenerant Evaporator (see Pig. 2-S)

NOTE: Regenerant Evaporator and Waste Evaporator may be used..

interchangeably.

The dose pro)ection indicated above will be performed in accordance with the methodology of Section 2.3 when ever Liquid Waste is being discharged without treatment in order to determine that the above dose limits are not ezceeded.

J TABLE 2-1 LIQUID EPFLUENT DETECTORS RESPONSES *

(CPM/uCi/ml) z 10 Sr 89 0.78E-04 Sr 91 1.22 Sr 92 0. 817 Y 91 2.47 Y 92 0.205 Zr 95 0.835 Nb 95 0. 85 Mo 99 0.232

'Tc 99m 0. 232 Te 132 Ba 140

l. 12 0.499 Ce 144 0 103 Br 84 II 131 l. 12 1.01 132 2. 63 I 133 0.967 I 134 2.32 I 135 1.17 Cs 134 1.97 Cs 136 2.89 Cs 137 0.732 Cs 138 1.45 Mn 54 0. 842 Ma 56 1.2 Pe 59 0. 863 Co 58 1. 14 Co 60 1 65

• Values froa SKC purchase specificatioa NMP2-P28IP.

TABLE 2-2 kiT VALUES - LIQUID+

mrem - ml hr - uCi NUCLIDE T BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3 3.37E-1 3.37E-1 3.37E-1 3.37E-1 3.37E-1 3.37E-1 Cr 51 1.28 3.21E2 2. 81E-1 7. 63E-1 1. 69 CU 64 4.72 8.57E2 1.01E1 2.54El Mn 54 8.36E2 1.34E4 4.38E3 1.30E3 Pe 59 9.40E2 8.18E3 1.04E3 2.45E3 6.85E2 Co 58 2.01E2 1.82E3 9.00E1 Co 60 5.70E2 4.85E3 2.58E2 Zn 65 3.33E4 4.65E4 2.32E4 7.38E4 4.93E4 Sr 89 6.~4E2 3.60E3 2.24E4 Sr 90 1.36ES 1.60E4 5.52ES Zr 95 5.91E-2 2.77E2 2.72E-1 8.74E-2 1.37E-1 Mn 56 1.96E1 3.52E3 1.10E2 1.40E2 Mo 99 2.05El 2.50E2 1.08E2 2.44E2 Na 24 4.09E2 4.09E2 4.09E2 4.09E2 4.09E2 4.09E2 4.09E2 I 131 1.26E2 . 5.80E1 lo54E2 2.20E2 3.77E2 7.21E4 Ni 65 7.53 4+18E2 1.27E2 1.65E1 I 133 2 78El 8.21E1 5 25El 9.13E1 1.59E2 1.34E4 Ce 134 5.79E5 1.24E4 2.98E5 7.09ES 2.29ES 7.61E4 Cs 136 8.86E4 1.40E4 3.12E4 1.23ES 6 '5E4 9.39E3 Cs 137 3e42ES 1.01E4 3.82E5 5.22ES 1.77E5 5.89E4 Ba 140 1.41El 4.45E2 2.16E2 2.71E-l 9 22E-2 lo57E-1 Ce 141 2.48E-3 8.36El 3.23E-2 2.19E-2 1.02E-2 Nb 95 1.34E2 1.51E6 4.47E2 2.49E2 2.46E2 La 140 2.03E-2 5.63E3 1.52E-1 7 67E-2 Ce 144 9.05E-2 5 70E2 3..69 7 04E-1 4.18E-1

• Calculated ia accordaace with NUREG 0133, Section 4.3.1 TYPICAL OF 3 I

SPEHT FUEL I PON. CORIN6 I I

fLONNAN FILTER

~ AOV I AOV 84 I

I I

RADWASTE I I WASTE MtQKRALllfR I I

GlIECTITI I I RfACTN WATER I wx I CLfuaP SYSTftI I AOV 47 I I I Rf Gf NRAHT I fVAPNATN I I

I I

COIefHSATE I I

DftQtCRALllfRS I I

I I Rf ACTOR St%DING E~NT DRAII6 I I

AOV 44 I I

I Pl Tf Cf I PHASE I f RADWASTE ILTERS I

MPARATN I I I WASTE COllfCTN PLOP I WASTE I. flON DRAINFILTER EVAPORATN AOV I

RECOVfRY WASTE COLLECTOR 48'OV SAt5%f TN4'5 SURGE TANK TK 18 277 TINSIHE SLD8 EQJIPt%NT ORANS PISA tf Rf SIDUAl AT AOV 278 PS RftIOVAL SYSTftl WASTE COLLfCTN RfCOVERY SURGE ~S AOV 308 SAtIPLE TOaS Ps tl Cf fLOOR DRAI flLTER RADWASTE FILTERS P I88 RADWASTf FILTfRS 2-1 A .E COLLECTION

.SERVICf AIR I I: l.

SPE HT ~

PCV266 AOV256 AOV26l g, l ~~ TYPICAL OF I

AOV6 AOV l78 I

C TeraeI I

I I fLOOR DRAItl I AOV l66 COLLECTOR TKS AOV7 WASTE DISCH N AOV263 AOV;l3I AOV l64 I

I AOV 8 S~E TKS I

AOV 167 WASTE COLL I

BASTE SURGE Thtà I I I FLHR I I I I I I

I FLT IAP I ADVS I FV87 I I I WASTE COLL I OVSGI I

PINPS I I I I I fLOOR DRN ADVS I RADWASTf I

)

I CCL PW S AOV 9 OftlIN 4AJ I I I I I I WASTE CRLfCTOR I I QSGE PLOP I I I I TO OTHER I OERIIN Pl BKWSH I AOV 264 COteEHSATE TK l6 I TYPICAL OF 2 AOVSS i I COtefHSA TE f

TRANSf R 1 I AOV 293 AOV l06 . I I TRANSFER I

I AOV Sll I Cf AOV 29 I SPENT RESIN I I AOV l04 fLOOR DRAIN TANK L AOV 262 COLL SURGf TK I6 AOV 86 REGMRANT AOV l9I COLLEClOR TAHKS RW flLTER AOV260 WASTE TANKS RECOVERY SACKWASH PRPS AOV 2P7 SAtIPLE TANK l68 SLUDGE HVI IS TAHK WASTE DISCH AOV l92 TAWS rl8. 2-2 HASTE COLLECTOR TP PTIIER Dfttltl TREATMENT SYSTEM

RfGfNfvAP DIST COOLfR

~, I TYPICAl OF 2 WASH EVAP DIST CMER TYPICAl OF 2

~

.,-. C SP- I WASTE I I I FLOOR DRAIN I Shr&E TKS I FILHR I I I

RADWASQ. AOV2I I RADWASTE AOV29 I , I DftON I DftlINERALllER I I I I I I WASTE RECOvfRY WASTE COLL s s LT SAtA.E RADWASTE FILTERS DISCHARGE I SILAGE TANK I TAM( I S~E I I OMR OTHfR P4 TANK I I PE'ECIRC L<

RfCIRC LNE I TKSA,S I

I I

I I

OTKR P4 I 00%RP5 SUCTIONLl% I SUCTICN ll%

Pl Csrs l AOV I IB I P4 I I PS WASTE COLL I TANKS RECOVERY AOV3I4 SAtR.E PRP AOV66 i I AOV 33 AOV 76 WASI

$ $ '-I WASTE AOV27S EVA SAtlPLE TKS Rf6 FV330 AOV279 EVA SERVICf WAHR HIGH RANGE F f 33O DISCHARGE SAY AOV l42 FLOW DRAIN FV33 I COLLECTOR TAWS I'-I ~

RECOYERY SYSTEM and WASTE LCM RANGE I>., Af I: 9 A MFII l: CVCTI.M

WASTEEVAP REGEHfVAP CST8LOG FLOMORAIN RX8LDG SPENT RESIN AUX GOILER RWGLOG WASTE DISCH DIST COOLER DIST CORER DRAINS FILTER DRAINS MK 8LDG N'RAINS f RW II. TfR TAkKS I'

I I WASTEeuT TINeeLOG tee-I fLOORDRAIH I TK ORANS ORAIHS COLLECTOR TANK I

I REGEHEVAP FLOOR OR TYPICAL OF 2 CRL TK2AJ OMR FLOOR ORAIH CKL PINP I AOV 738 AOV72 I WASTE EVAP OTMR P2 I AOV 282 RECIRC Ll% I OTKR fLNN I DRH SUCT LI% I I RW FILTfR I CE TE I I

AOV73A RW DEHIHS FlOOR DRH FILTER FLOOR DRAIN COLL TK eve AOV90A WASTf DISCH SAtA.E TKS FLOOR DRAIN AOV 20I CCLL SINGE TK l7 EVAP 80TTNS TNC OTKR FLOOR DRAIN COLL TK FLOOR DRH FILTER FLOOR DRAIN I'I p. 2-4 COLL SINGE PNIPS FLOOR ORAIN COLLECTION SYSTFM

WASTE COLL FV 122 SURGE TK fLOOR ORH AOV2 CST CQ,L SINGE TK SOV 251 AOV 236 fLONI ORAIH SERVICE AIR QKLEUN TKS BODV FEED TK AOV 253 7 af6) -

CONVOKE PEGEH WASTE TKS AN DRAW Off AOV2?1 FLAT 8EO fllTER WASTE Qll TKS SLUDGE TK AOV 257 AOV 451 8NV FEED Put@

HOPPER FEEDER EDUCTOR CST FILTER FILTER PRECOAT EfflUENT i AOV2)q TQL TAHy. I I REGS 'It/ASTE T1'.

I I AOV 127 WASTE OISCH Sea.E TK g

~ AOV 12~

LV 251 FLOOR DRAIN COLL TK fI ON DRAIN FILTER f FILTER Ef LUEIIT PRECOAT PS% P27 Ply AOV 126 WASTE COLL TK Fig. 2-5

~

)RAIN FILTER SYSTEM

30'f VENT AOV 246 CCNTACT CONEHSER TBCLCW TBCLCW EVAP DIST fVl AOV 247 EVAP BOTT(NS ~S CONDENSATE tRANSFER 01st TRANS Pre ANO STORAGE AOV 228 I

VI TBCLCW I

RO 140 RW RBLP. AUX STEA11 REGEN WASTE TKS TBCLCW fLOCA ORAIH FE RECIRC PINP LV 141 COLL RS CONEHSATE 5'ISLE TI.S 1.V 130 AOV 132 SPV 2gy TRANSFER AN STORAGE P

~AOV218 WASTE COLL 1XS AOV 187 EVAP fLOOR ORH COLL TTt.'S BOTtmS an S WASTE OISCH SANA.E TKS AOV 147 Pip. 2-6 VASTE EYAPORATOR SYSTEM

flOOR ORAN TYPICAL OF 2 fN.TER r

I I I I I I I

RW flONI AIe I AOI/SE I EQIIP tNV IHS I I I

BACK WASH ~

RW fIlTEQ I I

I QEI$ NERAHT I

I I

I I WASTE I

TAN TKS I

AOV69 I I

I I

I I

I WASTE ~

nnnREOEH ~ I I

I I

OTKR REGECRAHT WASTE TANK L

AOV68,'

RERNEVAP I

AOV 92 I

WASTE EVAP RE6EN WASTE TK I PlkP PBAJ flOOR DRAIN fIlTER AOV95~

Fig. 2-7 REGENERANT WASTE SYSTEM

VENT AOV 24 CON'TACT CONENSER TBCLCW TBCLCW EVAP DIST FV 157 AOV 249 EVAP I BOTTQS PROS CONEHSATE I DIST TRANS PttP TRANSFER AN STORAGE TBCLCW RO 154 RW RBLR AUX STEAN REGEN WASTF. TKS TBCLCW FLOOR DRAIN LV 155 COLL TY.S CCFIEHSATE WASTE O'SCH LV 148 TRANSFER AOV 222 SAtIPL! .KS 288 AN STORAGE SOV WASTE COLL TKS AOV 159 AOV 188 EVAP BOTTOtS ~S FLOOR DRN COLL TKS AOV 149 WASTE DISCH I

S AtIPLE KS AOV 2 P 5 Fig. 2-8 REGENERANT EVAPORATOR SYSTEM

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~ NORMALLYOPEN (10) FS FLOW SWITCH (11) DRAIN CONNECTION gf"Tl TEMPERATURE INDICATION ODCM Fig. 2<<10 FIGURE 11.5-3 OFF-LINE UQUID MONITOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

<<29<<

3.0 GASEOUS EPPLUENTS

.'he gaseous effluent release points are the stack and the combined Radiate/Reactor Building vent. (See Figure 3.5) The stack effluent point includes Turbine Building ventilation, main condenser offgas (after charcoal bed holdup), and Standby Gas Treatment System exhaust. NUREG 0133 and Regulatory. Guide 1.109, Rev. 1 were followed in the development of this section.

3.1 Gaseous Effluents Monitor Alarm Setpoints 3.1.1 Basis Technical Specification Section 3. 11.2. 1 and 3. 11.2.7 provide the basis for the gaseous effluent monitor alarm setpoints.

,TS Section 3.11.2.1:

The dose rate from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDRT.(see Pigure 5.1.3-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yi to the whole body and less than or equal to 3000 mrem/yr to the skin, and

b. Por iodine-131, for iodine-133> for tritium, and for all radionuclides with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

TS Section 3.11.2.7:

The radioactivity rate of noble gases measured downstream of the recombiner shall be limited to less than or equal 350,QQQ microcuries/second during offgas system operation.

3.1.2 Setpoint Determination Methodology The alari setpoint for Gaseous Effluent Noble Gas Monitors are based on a dose rate limit of 500 mrem/yr to the Whole Body. These monitors are sensitive to only noble gases. Because of this considered impractical to base their alarm setpoints on organ dose it is rates due to iodines or particulates. Additionally skin dose rate is never significantly greater then the <<hole body dose rate. The alarm satpoint for the Offgas Noble Gas monitor is based on a limit of 350,000 uQi/sec This is the release rate for which a PSAR aacidant analysis <<as completed. At this rate the Offgas System eQteoal beds <<ill not contain enough activity sa that their failure amd subsequent release of activity will present a significant offsite dose assuming accident meterology.

3.1.2-1 Stack Noble Gas Detector Alarm Setpoint Equation-0.8%* a(Ci) liana Satpofat c ~Zi Ci~<V1 Alarm Setpoint Is the alarm setpoint of the Stack Effluent Monitor,

<<CL/sec 0.8 Zs a Safety Factor, unitless Zs a value of 500 mrem/yr or less depending upon the dose rate from other release points within the site such that the total rate corresponds to 600 mrem/yr Zs the concentration of nuclide i, uCi/ml Is the Stack effluent flow rate, ml/sec Vi Is the constant for each identified noble gas nuclide accounting for the whole body dose from the elevated finite plume listed on Table 3-2, mrem/yr per uCi/sec a.(ci) Is the total concentration of noble gas nuclides in the Stack effluent, uCi/ml Zi(CL~VS) Zs the total o f the product o f the each isotop e concentration times its respective whole body plume constant, mrem/yr per ml/sec.

It should be noted that the flow rate of the Stack effluent has been canceled out of the above expression. The equation ratios the basis, R, to the actual dose rate from the effluent, F*Xi (Ci&i), and multiplies the unitless result by the actual effluent release zate, F*EL(Ci) ~ Since the Stack Effluent Monitor actually measures release rate in uCi/sec the detector response does not enter in.

3.1.2.2 Vent Noble Gas Detector A1arm Setpoint Equation:

0.8+R+Xi (Ci)

Alarm Setpoint <

TFaa" Where:

Alarm Setpoint Is the alarm setpoint of the Vent Effluent Monitor, uci/sec 0.8 Zs a Safety Factoz Is a value of 500 mrem/yr or less depending upon the dose rate from other release points within the site such that the total zate corresponds to < 500 mrem/yz Is the concentzation of nuclide i, uCi/ml Is the Vent effluent flow rate, ml/sec (X/q)v Zs the highest annual average atmospheric dispersion coefficient at the site boundry as listed in the Final Environmental Statement, NUREG 1085, Table D-2, 2-OEM sec/m3 Is the constant for each identified noble gas nuclide accounting for the whole body dose from the semi-infinite cloud listed on Table 3-3, mrem/yr per uCi/m3 Ei (ci ) Is the total concentration of noble gas nuclides in the Vent effluent, pC1/ml E1(C1'K1) - Is the total of the product of the each 1sotop concentration t1mes its respective whole body immersion constant, mrem/yr per ml/m3 It should be noted that the flow rate of the Vent effluent has been canceled out of the above expression. The equation rat1os the basis, R, to the actual dose rate from the effluent, F*(X/Q)v'Ei(C1"Ki) and multiplies the unitless result by the actual effluent release rate, F'E1(C1). Since the Vent Effluent Monitor actually measures release rate in F1/sec the detector response does not enter in.

3.1.2.3 Offgas Pretreatment Noble Gas Detector Alarm Setpoint Equation:

• P

• Alarm Setpoint < f'Ei (C1) + Background Hhere:

Alarm Setpoint Is the alarm setpoint for the offgas pretreatment Noble Gas Detector, F1/cc 0.8 Is a Safety Factor, unitless 350,000 Is the Technical Spec1ficat1on L1mit for Offgas Pretreatment, pC1/sec 2.1E-3 Is a unit conversion, 60 sec/m1n / 2B317 ml/CF Is the Offgas System Hi gh Flow rate Al arm Setpoint, CFH Background Is the detector response when its chamber is filled with nonrad1oactive air, pC1/cc E1(ci ) Is the suaeation of the concentration of nuclides in offgas, F1/cc f s.

Is the detector units of readout, pC1/cc and is equal to the detector response, cpm, times the detector ca11bration factor in units of pC1/cc/cpm.

32~

Discussion The Stack at Nine Hlle Point Unit 2 receives the Offgas after cbarcoal bell delay, Turbine building ventilation and the Standby Gas Treatment system exhaust. The Standby Gas Treatment system exhausts

.'the primary containment during normal shutdowns and maintains a negative pressure on the Reactor Building during secondary containment lsolatlon. The Standby Gas Treatment will isolate on high radiation during primary containment purges. The Stack ls considered an elevated release because its height (131m) ls more than 2.5 times the height of any ad)acent buildings. Nominal flow rate for the stack ls '102,000 CFH.

The Offgas system has a radiation detector downstream of the recomblners and before the charcoal decay beds. The offgas, after decay, ls exhausted to the main stack. The system will automatically isolate lf its pretreatment radlatlo'n monitor detects levels of radiation above the alarm setpolnt.

The Vent contains the Reactor Bulldlng ventilation above and below the refuel floor and the Radwaste Building ventllatlon effluents.

The Reactor Building Ventilation will isolate when radiation monitors detect high levels of radlatlon (these are separate monitors, not otherwise discussed in the ODCM). It is considered a combined elevated/ground level release because even though it is higher than any ad)acent buildings it ls not more than 2.5 times the height.

Nominal flow rate for the vent ls 237,310 CFM.

Nine Hile Point Unit 1 and the James A FltzPatrlck nuclear plants occupy the same site as Nine Hlle Point Unit 2. Because of the independence of these plants safety systems, control rooms and operating staffs it ls assumed that simultaneous accidents are not likely to occur at the different units. However, there are two release points at Unit 2. It is assumed that if an accident were to occur at Unit 2 that both release points could be involved. Thus the factor R which is the basis for the alarm setpolnt calculation is nominally taken as equal to 250 mRem/yr. If there are significant releases from any gaseous release point on the site (>25mRem/yr) then the setpoint will be recalculated with an appropriately smaller value for R and NMP-1 and Fitzpatrick stations shall be notlfled.

ti Inl al ly, and ln accordance wl th Speci f1 cation 4.3.7.11, the Geraanium multichannel analysis systems of the Stack and Vent will be calibrated with gas, or with cartridge standards (traceable to NBS)

$ n accordance with Table 4.3.7.11-1, note (c). The quarterly Channel Functional Test will include operability of the 30cc chamber and the dllutlon stages to confirm monitor high range capablllty. (See Figure 3-6).

3.1.3.1 Stack Noble Gas Detector Alarm Setpoint This. detector is made of germanium. It is sensitive to only gamma N

e

~

radiation. However, because it is a computer based multichannel analysis system it is able to acurately quantif y the activity released in terms of ~@i of specific nuclides. Only pure alpha and bets emitters are not detectable, of wh1ch there are no common noble gases. h distribution of Noble Gases corresponding to offgas is chosen for the nominal alarm setpoint calculation.

Offgas is chosen because it contaminate of gaseous activity in the plant.

represents the most significant The following cal'culation will be used for the initial Alarm Setpoint. It will be recalculated if,a significant release is encountered. In that case the actual distribution of noble gases will be used in the calculation. The listed activity concentrations Ci, correspond to offgas concentration expected with the plant design limit for fuel failure ~

ISOTOPE ACTIVITY PLUME PLUME NAME CONCENTRATION PhCTOR FACTOR

,Ci/ml eeeeeee- mrem/

yz- uC1 ml sec B C D (B+C)

(Ci) (Vi) (Ci.*Vi)

KR83 8.74E-2 KR85 3.28E-5 1'.61E-8 4.90'.56E-1 KR85M 3.2IZ-3 5.0IE-3 KR87 5e23E-1 9 '8K-3 5.22E-3 KR88 5.32E-l 2 2IE-2 1.18E-2 KR89 1.63 1 92E-2 3. 13E-2 KR90 1.5IE-2 XE131M 3.82E-4 6 55E-5 2 50E-8 XE133 2e06E-1 5.93E-4 1.22E-4 XE133M 7.35E-3 2 53E-6 3.44'.12E-3 XE135 5.88E-l 3.60E-3 XE135H 5e 9IE-1 6 12E-3 3.62E-3 XE137 2ell 2.88E-3 6.08E-3 XE138 1.93 1 33E-2 2.57E-2 AR41 1.6IE-2

~ 2 2 The alarm satpoint equation is:

hlarm Setpoint ~ 0.8*Red,(CI.)/zi(CisVi).

Where the Alarm Setpoint is in uCi/sec, R is taken as 250mrem/yr, X(Ci) is 8.36 uCi/ml and X(CieVi) is 9.28E-2 mrem/yr per ml/sac. These values yield an alarm setpoint of 1.80E4 Ci/sec.

3.1.3.2 Vent Effluent Noble Gas Detector Alarm Setpoint This detyctor is made of germanium. It ls sensitive to only ganja

.~:-'adiation. However, because lt ls a computer based multichannel

-==- analysis system lt ls able to accurately quantify the activity released in terms of pCi of specific nuclldes. Only pure alpha and beta emitters are not detectable, of which there are no common noble gases. A distribution of Noble Gases corresponding to that expected with the design limit for fuel failure offgas is chosen for the nominal alarm setpolnt calculation. Offgas is chosen because it represents the most significant contaminate of gaseous activity in the plant. The following calculation will be used for the initial Alarm Setpolnt. It will be recalculated lf a significant release is encountered. In that case the actual distrlbutlon of noble gases will be used in the calculation.

ISOTOPE ACTIVITY IHHERSION IHMERS IOK NAHE CONCENTRATION FACTOR FACTOR pC1/ml SMIRKED yr-pCl yr-ml C Da(B'C)

KR83 8.74E-Z 7.56E-2 6.61E-3 KR85 4.90E-4 1.61El 7.90E-3 KR85M 1.56E-1 1.17E3 1.82E2 KR&7 5.23E-1 5.9ZE3 3.10E3 KR&8 5.32E-1 1.47E4 7.8ZE3 KR89 1.63 1.66E4 2.71E4 KR90 W~W 1.56E4 XE131H 3. 82E-4 9.15E1 3.50E-2 XE133 2.06E-1 2.94E2 6.06E1 XE133H 7.35E-3 2.51E2 1.84 XE135 5.BBE-l 1.81E3 1.06E3 XE135M 5.91E-1 3.12E3 1.84E3 XE137 2.11 1.42E3 3.00E3 XE138 1.93 1.&3E3 1.70E4 AR41 8.84E3 TOTALS 8.36 6.12E4 The Vent Effluent Noble Gas Honitor Alarm Setpoint equation is:

Alarm Setpoint 0.8*R'Zl(C1)/t;(X/Q)v'Zl(C1'Ki)].

Hhere the Alarm Setpolnt 1s in pCi/sec, R ls 250mrem/yr, Zl(C1) ls 8.36 pC1/ml, (X/Q) ls 2.0E-6 sec/m3 and Zi(Cl'Kl) is 6.12E4 mrem/yr per ml/m3. This will yield an

. alarm setpoint of 1.41E4 pCl/sec.

3.1.3.3 Offgas Noble Gas Detector Alarm Setpoint The Radi ation Detector 1 s a sodium 1 od1de crystal . It 1 s scintillation device and has a thin mylar window so that it ts sensitive to both gamma and beta radiat1on.

The detector output is routinely ad)usted to match the total activity detected by NBS traceable, gamma spectroscopic analysis of grab samples. DU is set equal to E1C1 (see equation in step 3.1.2.3).

The offgas Noble Gas Monitor Alarm Setpoint equation can then be reduced to the following:

Alarm Setpoint 0.8 '50,000 *2.1E-3/f + Background Since the offgas flow alarm is equal to or less than 110 SCFH, the Noble Gas Alarm Setpoint shall be equal to or less than 5.3 pCi/cc above background. Particulates and Iodines are not included 1n this calculation because this 1s a noble gas monitor.

To provide an alarm in the event of failure of the offgas system flow 1nstrumentation, the low flow alarm setpoint will be set at or above 10 scfm, (well below normal system flow) and the high flow alarm setpo1nt will be set at or below ll0 scfm, wh1ch is well above I' expected steady-state flow rates w1th a tight condenser.

'36-

-3.2 Gaseous Effluents Dose Rate CalcuLation This section covers TS Section 4.11.2.1.1 and 4.11.2.1.2 concerning the calculation of dose rate from gaseous effluents for compliance

- ~th TS.Sec+on 3.11.2.1.

~ ~ ~

Section 3.11.2.1:

~

The dose rate from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDAR'I (see Figure 5.1.3-1) shall be limited to the fol1owing:

a. For noble gases: Less than or, equal to 500 mrem/yr to the whole body and less than or equal to 3000 mrem/yr to the skin, and

b. For iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

3.2.1 Whole Body Dose Rate Due to Noble Gases This calculation covers TS Section 3.11.2.1.a (for whole body) and 4.11.2:1.2; The dose from the plume shine of elevated releases is taken into account with the factor Vi. The dose from Vent releases takes into account the ezposure from immersion in the semi-infinite cloud and the dispersion from the point of release to the receptor which is at the East site boundary. The release rate is averaged over the period of concern. The factors are discussed in greater detail later.

Whole body do'se rate due to noble gases:

mrem/yr ~ Zi [VisQis + Ki (X/Q)vsQiv]

Where:

Is the constant accounting for the gamma radiation from the elevated finite plume of the Stack releases for each identified noble gas nuclide, i. Listed on Table 3-2, mrem/yr per uCL/sec Qis Is the release rate of each noble gas nuclide, i, from the Stack release averaged over the time period o f concern, uCi/se c Is the constant accounting for the whole body dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed on Table 3-3, mrem/yr per uCi/m3

<<37>>

( X/Q)v 's the highest calculated annual average relative concentration at or beyond the site boundry for the Vent.

Pinal Environmental Statement, NUREG 1085, Table D"2, 2.0E-6 se c/m3 Qiv: . Is the release rate of each noble gas nuclide, i,f from the Vent release averaged over the time period o concern, uCi/se c Example Calculation:

Assume an analysis of the Stack and Vent Effluents indicate that 1.81E4 and 1.26E4 uCi/sec of Xe-133 are being released from each point respectively. From Table 3-2, Vi is 5.93'rem/yr per uCL/sec. Prom Table 3-3 Ri is 2.94E2 mrem/yr per uCi/m3. (X/Q)v is 2.0E-6 sec/m3. These values yield a whole body dose rate of 10.7 and 7,41 mrem/yr from the Stack and Vent respectively for a total of 18.1 mrem/yr. This value is added to the whole body dose rates obtained from the Nine Mile Point-Unit 1 and James A.. Fitzpatrick plants to obtain the site dose rate to the whole body from noble gas releases. The whole body dose rate due to noble gases is specified by TS Section 3.11.2.1.a.

3.2.2 Skin Dose Rate Due to Noble Gases This calculation covers TS Section 3.11.2.l.a (for skin) and 4.11.2.1.1. For Stack releases this calculation takes into account the exposure from beta radiation of a semi infinite cloud by use of the factor Li. Additionally the dispersion of the released activity from the stack to the receptor is taken into account by use of the factor (X/Q). Gamma radiation exposure from the overhead plume is taken into account by the factor 1.1Bi.

Por vent releases the calculations also take into account th e exposure from the beta and gamma radiation of the semi infinate cloud by use of the factors Li and 1.1Mi respectively. Dispersion is taken into account by use of the factor (X/Q). The release rate is averaged over the period of concern. The factors are discussed in greater detail later.

Skin dose rate due to noble gases-mrem/yr > Q. [ (Li*(X/Q)s + 1.1*Bi)*Qis + (Li + l.l&)<(X/Q)>Qiv]

Where:

Is the constant to take into account the skin dose due to each noble gas nuclide, i, from immersion in the semi<nfinite cloud, mrem/yr per qCi/m3 Is the constant accounting for the air gamma dose rate from immersion in the semiMinite cloud for each i

identified noble gas nuclide, ~ Listed on Table 3-3, mrad/yr per uCi/m3 1.1 is a unit conversion constant, mrem/rad bi Is the constant accounting for the air gamma dose rate from exposure to the overhead plume of elevated releases o f each identified noble gas nuclide, i.

Listed on Table 3-2, mrad/yr per uCi/sac.

Is the highest calculated annual average r elative concentration at or beyond the site boundary 'for. the Vent. Final Environmental Statement, NUREG 1085, Table D-2, 2.0E-6 sec/m3 (X/Q)s Is the highest calculated annual average relative concentration at or beyond the site boundary for the Stack. Final Enviroayental Statement, NUREG 1085, Table D-2, 4.5E-8 sec/m Qiv Is the release rate of each noble gas nuclide, i, from the Vent release averaged over the time period o f concern, uCi/se c Qis Is the release rate of each noble gas nuclide, i, from the Stack release averaged over the time period of concern, uCi/se c Example Calculation'.

Assume an analysis of the Stack and Vent Effluents indicate that 1.81E4 and 1.26E4 uCi of Xe-133 are released from each point. From Table 3-2, Bi is 6.12'rad/yr per uCi/sec. From Table 3-3, Li and Mi are 3.06E2 and 3.53E2 mrem.mrad/yr per uCi/m3 respectively.

(X/Q) for the Stack and Vent is 4.5E-8 and 2.0E-6 sec/m3 respectively. These values yield a skin dose rate of 12.6 and 17.5 mrem/yr for the Stack and Vent respectively for a total rate of 30.1 mrem/yr. This value is added to the skin dose rates obtained from Nine Mile Point-Unit 1 and the James A. Fitspatrick plants to obtain the site dose rate to the skin from noble gas releases. The skin dose rate limit due to noble gases is specified by TS Section 3.11.2.1.a.

3 2.3 Organ: Dose Rate Due to I-131, I-133, Tritium, and Particulates with Half-lives greater than 8 days.

This calculation covers TS Section 3.11.2.l.b and 4.11.2.1.2. The factor Pi takes into account the dose rate received from the ground plane, inhalation and food (cow milk) pathways. Qs and Wv take into

. account the atmospheric dispersion from the release point to the Eocation of the most conservative receptor for each of the respective ys. The release rate is averaged over the period of concern.

factors are discussed in greater detail later.

Organ dose rates due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days:

arse/yr ~ Ep [ Ei Pip tWsQis + WvQiv] ]

Where:

Pip Is the factor that takes into account the dose to an individual organ from nuclide inhalation pathway, mrem/yr per uCi/m i through pathway p. For

~ For ground an d food pathways, m&rem/yr per uCi/sec ~

Xi Is the summation over all nuclides, i Is the summation over all pathways Ws, Wv Are the dispersion parameters for stack and vent re)ease respectively for each pathway as approriate sec/m or 1/m ~ See Table 3-22.

Qis, Qiv Are the release rates for nuclide vent respectively uCi/sec.

i, from the stack and Example Calculation Assume an analysis of the Stack and Vent Effluents indicate that 1.84E-l and 1.26E-1 uCi/sec of I-131 are released from each point respectively. From Table 3-4 thru 3-6 and 3-22 the following table can be made:

ORGAN Pi GROUND Pi INHALATION Pi FOOD or m2~em/yr mrem/yr m2~em/yr FACTOR uCi/sec uCi/m3 uCi/sec T BODY 2 46E7 1.96E4 1.43E9 SKIN 2.98E7 BONE 3.79E4 2.77E9 LIVER 4.44E4 3.26E9 THYROID 1.48E7 1.07E12 RIDNEY 5. 18E4 3.81E9 LUNG GI-LLI 1.06E3 1.16E8 1.34E-9 8.48E-9 3.64E-10 2+90E-9 lo42E-7 4.73E-10 WsQeRhrQv 6.12$ -10 1.95E-8 1.27E-ao NOTE: The Dispersion Parameters given in Table 3-22 will be revised based on the results of environmental surveys and meteorological data.

From these values the following table of dose rates (mrem/yr) can be calculated:

-40"

GRAN GNODND ZNllkLLZZON POOD ZOThL T bODY 1.51E-2 3.82E-4 1.82E-l 1.97E-1

,SPN 1.&2E-2 1.82E-2 7.39'.66E-4 3 52E-1 3.53E-l 4.14E-l 4.15E-l 2.89E-1 1.36E+2 1.36E+2 1.0IE-3 4.84E-1 4.85E-1 "KUNG GI-LLI 2.07E-5 1.47E-2 1.47E-2 In this case the maximum dose rate to an organ is 136 mrem/yr to the thyroid from I-131. This calculation would be repeated for all nuclides and age groups then summed for each age group to obtain the dose rates to all organs. The dose rate limit to the maximum ezposed organ is specified by TS Section 3.11.2.l.b.

3.3 Gaseous Effluent Dose Calculation Methodology TS Section 3.11.2.2:

The air dose from noble gases released in gaseous effluents, from each unit, to areas at or beyond the SITE SOUNDAKY (see Pigur e 5.1.3-1) shall be limited to the following.

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, 3

and

b. During any calendar yeaz: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 irad for beta radiation.

TS Section 3.11.2.3:

The dose to a MEMBER OF THE PUBLIC from iodiae-131, iodine-133, tritium, aad all radioactive material in particulate form with half-..lives greater than 8 days in gaseous cffluents released, from

~ach:unit ', to areas at or beyond the SITE BOUNDARY (sce Figure 5.1.3-1) shall be limited to the followiag:

a. During any caleadar quarter: Less than or equal to 7.5 mrem to any organ and,

b. During any calendar year: Less than or equal to 15 mrem to aay organ.

TS Section 3.11.2.5:

The VENTILATION EXHAUST TREATl'KHT SYSTEM shall. be OPERABLE end appropriate portions of this system shall be used to reduce releases of radioactivity when the pro)ected doses in 31 days from iodine and particulate releases, from each unit, to areas at or beyond the SITE BOUNDARY (see Figure 5.1.3-1) would ezceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC ~

3.3.1 Gamma Air Dose Due to Noble Gases This calculation covers TS Section 3.11 .2.2 and 4.11 .2.2.

Gamma air dose due to noble gases released is calculated monthly.

The factor Mi takes into account the dose from immerse.on in the semi-infinite cloud of the vent rclcase. Thc factor X/Q takes into account thc dispersion of vent releases to the most conservative location. The factor Bi takes into account the dose from ezposure to the plume of the stack releases. The release activity is totaled over the period of concern. The factors are discussed in greater detail hater.

Gamma air dose due to noble gases:

mrad ~ [Mi(X/Q)v Qiv + Bi Qis~

Where the constants have all been previously defined. Note that since Q is erpressed as uCi/sec, the constant 3.17E-8 sec ->

given in gHLEG<133, sectioa 5.3.1 may be omitted, provided that the annual dose calculated is divided by 4 to yield quarter dose, or 12 to yield monthly dose, as applicable.

Rxaayle Calculation Assume an analysis of the Stack and Vent Effluents iadicate that 1.42EL1 aad 9.9IZLO uCi of Xe-133 are released from each,poia t respectively over the last quarter. This correlates to 1.81E4 and 1.26E4 uCL/sec respectively. Prom Table 3-2, Bi is 6.12E-4 mrad/yr per uCi/sec. Prom Table 3-3 Mi is 3.53E2 mrad/yr per uCi/m3.

(X/Q)v is 2.0E-6 sec/m3. These values yie1d a gamma air dose rate of 11.1 and 8.9 mrad/yr from the Stack and Vent respectively for a total of 20.0 mrad/yr or 5.0 mrad for the quarter. The gamma air dose limit due to aoble gases is specified by TS Section 3.11.2.2.

Beta Air Dose Due to Noble Gases

.This calculatio covers TS Section 3.11.2.2 and 4.11.2.2.

'i beta air dose due to noble gases released is calculated monthly. The factor Ni takes into account the dose from immersion in the cloud of all the releases. The factor X/Q takes into account the dispersion of releases to the most conservative location. The factors are discussed in greater detail later.

Beta air dose due to noble gases:

<iNif(X/Q)v Qiv + (X/Q)s Qisl Where the constants have all been previously defined'xample Calculation As sume an analysis of the Stack and Vent Effluents indicate that 1.42E11 and 9.91E10 uCi of Xe-133 are released from each point respectively over the last month. This correlates to 1.8IE4 and 1.26E4 iCi/sec respectively. From Table 3-3, Ni is 1:05E3 mrad/yr per Ci/m3. (X/Q) for the Stack and Vent is 4.5E-8 and 2.0EW sec/m3 respectively. These values yield a beta air dose of 0.9 and 26.5 mrad/yr for the Stack and Vent respectively for a total of 27.4 mrad/yr or 6.8 mrad over the last quarter. The beta air dose limit due to noble gases is specified by TS Section 3.11.2.2.

Organ Dose Due to I-131, I-133, Tritium and Particulates with half-lives greater than 8 days.

This calculation covers TS Section 3.11 .2.3, 3.11 .2.5, 4.11 .2.3, and

4. 11.2.5. 1. Organ dose due to I-131, I-133, Tritium and Particulates with half-lives greater than 8 days released is calculated monthly.

The factor Ri takes into account the dose received from the ground plane, inhalation, food (cow milk, cow meat and vegetation) pathways. Ws and Wv take into account the atmospheric dispersion from the release point to the location of the most conservative receptor for each of the respective pathways. The release is totaled over the period of concern. The factors are discussed in greater detail later.

Orgy dose due to iodine-131, iodine-133, tritium radionuclides in yaettculate form with half-lives greater than 8 days area 3.17E-8 Xp [ TL Rip fWs Qis + Wv Qiv] ]

Where'

3. 17E-8 Is the inverse of the number of seconds in a year Is the factor that takes into account the dose to an individual organ from nuclide i through pathway p.

Is the summation over all nuclides i.

Is the summation over all pathways p.

Ws, Wv Are the dispersion parameters for the stack and vent respectively fot'ach pathway as appropriate sec/m or 1/m ~ See Table 3-22.

I Qis, Qiv Are the amount of activity of nuclide the stack or vent respectively over the period o f i released from concern, uCi. If activity released is given in terms of release rate, uCi/sec, then the constant 3.17E-8 sec may be omitted, provided that the annual dose calculated is divided by 4 to yield quarter dose, or 12. to yield monthly dose, as applicable.

Example Calculation Assume an analysis of the Stack and Vent Effluents indicate that 1.45E6 and 9.9ES uCi o f I-131 are released from each point respectively over the last quarter. This correlates 1,84E-1 and 1.26E-l uCi/sec respectively. Calculate the dose to a childs organs. Prom Tables 3-8,11,13,16 and 19 the following table can be made:

ORGAN Ri-GROUND Ri-ZNHAIdlTZON Ri-MIIX Ri-MEAT Ri-VEGETATION or a~a2~cal r mrem/ m2-mrem/ r PACTOR uCi m uCi sec T BODY ET E 'X3'25M E .1 E SKIN 2.09E7 BONE 4.&lE4 6.51E& 8.26E6 1.43E&

LIVER 4.81E4 6.55E8 8.32E6 1.44E8 THYROID 1.62E7 2.17ELl 2.75E9 4.75H.O KIDNEY 7.88E4 1.0&E9 1.37E7 2.36E&

LUNG GI-LLI 2.84E3 5.83E7 7.40ES 1.2&E7 Ws 1.34E-9 8.48E-9 3.64E-10 1.15E-9 9.42E-10 Wv 2.90E-9 1.42E-7 4.73E-10 1.86E-9 1.50E-9 WsQs+WvQv 6.12E-10 1.95E-8 1.29E-10 4.46E-10 3.62E-10 Prom these values the followiag table of annual dose (mrem) can be calculated:

ORGAN GROUND INHALATION MILK MEAT VEGE TOTAL

,~BO Y ~)E-2 E 2 E-3 MGK-2 %3% E-2 SKIN 1.2&E-2 1.28E-2 BONE 9.3&EM 8.40E-2 3.69E-3 5. 1&E-2 1.40E-1 LIVER 9.3&EM 8.45E-2 3.71E-3 5.21E-2 A~1 THYROID 3 16E-1 2&.0 1.23 17.2 46.7 KIDNEY 1.54E-3 1.39E-l 6.11E-3 8.54E-2 2.32E-1 LUNG

'GI-LLI 5.54E-S 742E-3 3.30E-4 4.63E-3 1.25E-2

-44"

In this case the maximum quarterly dose to the child organ is 46.7/4 11.7 mrem to the thyroid from I-131. The calculation would be repeated for all nuclides and age groups and summed to find the maxisnsa dose to any organ. The dose limit to the maximum exposed organ Xs specified by TS Section 3,11.2.3 and 3.11.2.5.

3.4 Gaseous Effluent Dose Factor Definition and Derivation 3.4.1 Bi and, Vi- Plume Shine Factor Por Gamma and Beta Doses (Table 3-2)

Bi (mrad/yr per uCi/sec) is calculated by modeling the ef fluent from the Stack as a line source with an elevation above ground equal to the stack height (131m).

Prom "Introduction to Nuclear Engineering" by &marsh, page 410, the flux o at a point a distance of x from an infinite line emitting S gammas/sec per cm is:

o S/4x.

S is proportional to release rate Q (uCi/sec) and inversly to vend speed U (cm/sec):

S R Q/U.

The distance of an individual on the ground from the elevated plume is approximately equal to the height of the stack h (meters) ~ The gamma radiation from the plume is attenuated by the air. This is proportional to the exponential of the negative product of the stack height h (m) and the air attenuation coefficient Uo, 1/m-exp (-Uo*h).

This is a conservative assumption because only the portion of the plume directly overhead is at a distance of h. The bulk is much further amy.

Additionally, there is a dose buildup factor which, from RG 1.109 Appendix F-ll, 12, is equal to.'+[(Uo<<Ua)*Uo*h)/Ua

+here Ua (1/m) is the air energy absorption coefficient .

<<45>>

The dose D at a point is proportional to the fluz o, energy E (Mev) of the radiation, air energy absorption coefficient Ua (m-1) and unit conversion constant K:

D ~ Kso*EsUa.

Substitution in the above formula for flux from an infinite line source yields:

D ~ K*SsE~Ua/[4*z] ~

Substitution for S yields:

D ~ KsQ*E~Ua/[4*x*V].

Substitution for z of Stack height h yields:

D < K<Q<E*Ua/[4*h*U].

Factoring in the air attenuation and corresponding dose buildup factors yields.

D ~ K*Q*E*[Us+(Uo-Ua)+Uo*h]exp(-Uo*h)/[4*h*U]

Bi is the gamma air dose received on the ground for a given release rate Q. Thus!

B > D/Q ~ KsEs[Ua+(Uo-Ua)*Uosh]*exp(-Uo*h)/[4*hsU].

Where:

K ~ 1.447E4 mradMism /MevmCi-yr, U is 5.71 m/sec and the other symbols are as discussed above.

To calculate Vi (mrem/yr per uCi/sec), the factor to account for the Total Body dose rate for a given release rate Q (uCi/sec) a conversion ratio of 1.1 mrem/mrad is assumed between tissue and air doses. If the Total Body tissue density Td (gm/cc) is assumed to be 5gm/cc (like a rock) and Ut (cm2/gm) is the energy absorption for tissue then:

V ~ 1.1*B*ezp(-Td*Ut).

Example Calculation Ua, Ue and Ut all vary vith the energy of the radiation. Figure M-6 and Table 3.5-1 (~scle) of the "CRC Handbook of Radiation Measurement and Protection" list values for the variables. For a Oo25 Mov g4$ Rac Uo ~ 0.0145 m-1 Ua ~ 0.0036 m-1 Ut ~ 0.0306 cm2/gm.

These values will yield a factor of 4.38E-3 and 4.14E-3 mrad, mzem/yr pez uCi/scc respectively for B aad V. Similarily for the primary energies of Xc135 the foLlowing table is obtainable:

EN ERST MEV-YIELD

~// B

/ * ~~ M// V

//

0.25 0.9 4.38E-3 4.14E-3 0.6 0. 03 9.38E-3 8.77E-3 0.7 0.01 1.06E-2 9.97E-3 TOTALS Fh.CTORING IN THE YEILDS: ~ IE- 7E-These values corzespond to those listed on Table 3-2. It should be aoted that only a limited number of auclides are listed oa Table 3-2. These are the most common noble gas nuclides eacountezed in cffluents. If a nuclide is detected for which a factor is aot listed, then ODCM e it will be calculated and included in a revision to the Semi-Iafinite Cloud Immersion Dose Factors (Table 3-3)

Li, Mi and Ni are the factors which take into 'accouat the dose from immersion in thc semi-infinite cloud of gaseous zeleases. These aze taken from RG 1.109, Table B-l, aad multis.ed by iE6 to convert from uaits of mrem,mrad/yr pcz pCi/m3 to mrem,mrad/yr per uCi/m3.

Dose Rate Factor for I-131, I-133, Tritium and Particulates with Half-lives greater than 8 days.

Table 3-4 Ground Plane Pi (m2~rem/yr per uCi/sec) takes into account several factors among these are the dose rate to thc total body from exposure to radiation deposited on the ground. (Prom NUREG 0133, scctioa 5.2.1.2)

INSERT SYMBOLS Where '.

R' constant of unit covezsionp 10 pCi/pCie R" ~ a constant of uait convcrsioa, 8760 hz/year.

the decay constant for the ith radionculide, sec t ~ the exposuze period, 3.15 x 107 sec (1 year) ~

DFQ ~ the gzound pleas dose conversion factor the thc ith radionuclide (mrem/hr pcz pCi/m2) ~

The depositioa rate onto the ground plaae results in a ground plane coacentration that is assumed to persist over a year with radiological decay the only operating removal mechaaism for each radionuclide. The ground plane dose conversioa factozs for the ith tadloautlldeDPGl, ,ate ptoaeatad u Table D-d of aeaulatotp Gudde 1.109, in units of mrcm/hz per pCi/m$

Resolution of the units yields.

PL (crom') 8.76 x 109 DFGi (1-e 'it)/ii Example Calculation For the I-131 total body dose rate factor for exposure from the ground e

~ 9.98E-7 sec-1 DFGi ~ 2.80E-9 mrem/hr per Ci/m2 These values will yield a Pi factor of 2.46E7 m2~em/yr per uCi/sec as listed on Table 3-4. It should be noted that only a limited number of nuclides are listed on Table 3-4. These are the mos t itIf common nuclides encountered in effluents. a nuclide is detected for which a factor is not listed, then will be calculated and included in a revision to the ODCM.

Pi (m2mrem/yr per uCi/sec) also takes into account the dose rate to the skin from exposure to the ground.

Example Calculation For the I-131 skin dose rate factor for exposure from the ground:

1i ~ 9.98E-7 sec-1 DFGi ~ 3.40E-9 mrem/hr per pCi/m2 These values will yield a Pi factor of 2.98E7 m2~emlyr per uCi/sec as listed on Table 3-4. It should be noted that only a limited nubmer of nuclides are listed on Table 3-4. These are the most common nuclides encountered in effluents.

for which a factor is not listed, then If a nuclide is detected included in a revision to the ODCM.

ith will be calculated and Table 3-5 Inhalation Pi (mrem/yr per uCi/m3) also takes into account the dose rate to various organs from inhalation exposure. (From NUREG 0133, section 5.2.1. 1)

Pi ~ X'(SR)

Dpi (mrem/yr per pCi/m )

%Stet X' a constant of unit conversion, 106 pCi/XCi ~

SR ~ thi breathing rate of the infant age group, in a3/yr.

DFQ ~ the organ inhalation dose factor for the infant age group for the ith radionuclide, in area/pCi. The total body is considered as an organ in the selection of Dpi.

The age group considered is the infant group. The infant's breathing rate is taken as 1400 m /yr from Table E-5 of Regulatory Guide

.'.109.:The 'nhalation dose factors for the infant, DFhi are presented in Table E-10 of Regulatory Guide 1.109, in units of mrem/pCi ~

Resolution of the units yeilds:

Pi (inhalation) ~ 1.4 x 10 DFh,i.

Example Calculation:

For the I-131 thyroid dose rate factor for exposure from inhalation:

DFAi ~ 1.06E-2 mrem per pCi This value will yield a Pi factor of 1-48E7 mrem/yr per uCi/m3 as listed on Table 3-5. It should be noted that only a limited number of nuclides are listed on Table 3-5. These are'he most common nuclides encountered in effluents. If a nuclide is detected for which.a factor is not listed, then it will be calculated and included in a revision to the ODCM.

Table 3H, Food (Cow Milk)

Pi (m2mrem/yr per uCi/sec) also takes into account the dose rate to various organs from the ingestion of cow milk. (From NQREG 0133, section 5.2.1.3)

INSERT SYMBOLS HERE Where s K' a constant of unit conversion, 106 pCi/ gL.

Q ~ the'ow's consumption rate, in kg/day (wet weight).

7Jap

~ the infant ' milk consumption rate, in liters/yr.

Yp ~ the agricultural productivity by unit area, in kg/m Fm ~ the stable element transfer coefficients, in days/liter.

~ izaction of deposited activity retained on cow's feed grass.

DFLi ~ the maximum organ ingestion dose factor for the ith radionuclide, in mrem/pCi.

>i ~ the decay constant for the ith radionuclide, in sec the decay constant for removal of activity on leaf and plant sur faces by weathering, 5.73 x 10 7 sec (corresponding to a 14 day half-time).

the transport time from pasture to cow, to mi,lk, to infant, in sece k fraction of the airborne deposition is captured by thc ground plaae vegetation cover. The captured material is removed from thc

vegetatioa (grass) by both radiologicaL decay and <<esther progresses; >>

The'alues of Qp, Qo, and Tc are provided in Regulatory 1.109, Tables E-3, E-S, and E-L'5, as 50 kg/day, 330 liters/day 0.7 kg/m2, respectively. The value tf is provided in Regulator.

Guide 1.109, Table E-15, as 2 days (1.73 x 105 seconds).

fraction, r, has a value of 1.0 for radioiodiaes aad 0.2 Thc for particulates, as prcseated in Regulatory Guide 1.109, Table E-L5.

Table E-1 of ReguLatory Guide 1.109 provides the stable element transfer coefficients, Pm, and Table E-14 provides the ingestion dose factors, DFLi, for thc infant's of the units yields:

organs'csolutioa o< (tooo~ ~ R.4xllpo

~ r Oil.< fe 5 t) (e errea/yr per C1/sec) for all radioauclides, except tritium.

The conceatration of tritium ia miLk is based on its airborne concentration rather than thc deposition rate.

K'X' p<

~

+ap~1 8 75(0 V~G (ereo/P'or xC1/e )

Where:

R'" ~ a constant of unit convcrsioa, 103 gm/kg ~

H ~ absolute humidity of the atmosphere, ia gm/m /

0.75 the fractioa of total feed that is <<ster ~

0.5 the ratioa of thc specific activity of the feed grass <<ater to atmospheric <<ater.

Prm Table E-1 aad E-14 of Regulatory Guide 1.109, the values of P aak NLi for tritium are 1.0 x 10 2 day/liter and 3.08 x 10 ~

aetna'per pCix. respectively. Assuming an average absolute humidity of 8 grams/meter, the resolutioa of units yields:

P j (Eood) ~ 2.4 x 10 mrem/yr per uCi/m for tritium, only Example Calculation:

For I-L3L thyroid does rate factor for exposure from cow milk inges tion!

r ~ 1.0 unitlcss for Iodincs Pa ~ 6E-3 days/lltex'PLi

~ 1.39E-2 mrem/pCi 4 ~:9.98E=7 sec-1

~ 5.73E-7 scc"1 tf ~ 1.73E+5 sec These values will yield a Pi factor of 1.07E12 mrem/yr per uCl/sec as listed on Table 3-6. It should be noted that only a limited aumber of nuclides are listed on Table 3<<6. These are the most common nuclides encountered in effluents. If a nuclide is detected for which a factor is not listed, then lt wi11 be calculated and included ln '

a revision to.the ODCM.

Dose Pactor for I-131, I-133, Tritium and Particulates with half-lives greater than 8 days.

TABLES 3.7 to 3.10, Ri VALUES - INHALATION Ri (mrem/yr pex uCl/m3) takes into account sevexal factors, among these are the dose rate to vax'ious organs from inhalation ezposure.

(Prom NDREG 0133, Section 5.3.1.1).

Ri ~ K'(BR) a (DFAi)a (mrem/yr per uCi/m )

Where:

K' a constant of unit conversion, 106 pCi/gCi ~

(M,)a - th) breathing rate of the xeceptor of agc group (a),ln m /yr.

(DPQ)a ~ the organ iahalatlon dose factor for the receptor of age group (a) for the ith radionuclide, in mrem/pCi.

The total body is considered as an organ in the selection of (Dpi)a.

The breathing rates (BR)a for thc various age groups are tablulated below, as givca ia Table E-5 of the Regulatory Guide 1.109 ~

e Grou (a) Breathin Rate (m ~/ x)

Iafsat 1400 Child 3700 Teen 8000 Adult 8000 Iahalation dose factors (DPh.i)a for the various age gxoups arc given la Tables E-7 thxought E-10 of Regulatory Guide 1.109.

Ezample Calculation:

Pox thc I-131 infant thyroid. dose factor for ezposurc from iahalatlon:

'DFAi ~ 1.06E-2 arem per pCi These values vill yield a Ri factor of 1.48E7 mrem/yr per uCi/m3 as Dated on Table 3-7. It should bc noted that only a limited aumber of aaclidcs are listed oa Table 3-7 thru 3-10. These are thc most c~a auclides eacouatered ia efflueats- If a nuclide is detected for 'which a factor is aot listed, then included in a revision to the ODCM.

it <<ill be calculated ad TABLE 3-11, Ri VALUES - GROUND PLANE Ri (m2mrcm/yr per uCi/sec) also takes iato account the dose from exposure to radiation deposited on the ground (From NUREG 0133, Section 5.3.1.2) ~

~ K'K"(SF)DFQ t(lm"i )/g] (m 'mrcm/yr per ffCi/scc),

Where:

K' a constant of unit conversioa, 10 pCi/tfCi-K" ~ a constant of unit coaversion, 8760 hr/year

'di ~ the decay coastaat for the ith radionuclide, sec 1.

t ~ the exposure time, 4.73 x 10 sec (15 years) ~

Dpdd tha troaad plate ooe ooaveroioa fetter fot the'th raddoaotlid (mrcm/hr per pCi/m $).

SF the shielding factor (dimcasioalcss) ~

h shieldiag factor of 0.7 is suggested ia Table E-15 of Regulatory Guide 1.109. A, tabulatioa of DFGi values is presented in Table E-6 of Regulatory Guide 1.109 Calculation:

'xample For the I-131 total body dose factor for exposure to the ground:

C ~ 9.98E-7 sac-1 DFGi ~ 2.80E-9 mrcm/hr per pCi/m2 These values <<Q.l yield a Ri factor of 1.72E7 m2~rem/yr per uCi/sec as 14+e4 on Table 3-11. It should be noted that oaly a limited number of aaihMes are Bated oa Table 3-11. These are the most common auclidcs encountered in effluents. If a nuclide is detected for <<hich a factor is not listed, then it rill be calculated and iacluded in a revision of the ODCM.

Ri (a2mrcm/yr per uCi/sec) also takes into account the dose to the skia from exposure to the ground.

Example Calculation:

For the I-131 skin dose factor for exposure to the ground:

lf:~ 9.98E-7 DKi < 3.40E-9 sec-1 mrem/hr per pCi/m2.

These values will yield a Ri factor of 2.09E7 m2-mrem/yr per uCi/sec as listed on Table 3-11. It should be noted that only a limited number of nuclides are listed on Table 3-11. These are the most common nuclides encountered in effluents.

for which a factor is not listed, then included in a revision to the ODCM.

itIfwill a nuclide is detected be calculated an TABLES 3-12 to 3-15 Ri VALUES - COW HILR Ri (m2~rem/yr per uCi/sec) also takes into account the dose rate to various organs from the ingestion of milk for all age groups. (From NUREG 0133, Section 5.3.1.3) ~

Op(V~

)

fI 0 tt~)-~ 1+.] -a(c(

5 (s

2

~W per uCf laos)

Where:

R' constant of unit conversion, 108 pCi/uCi ~

Qp the, cow's consumption rate, in kg/day (wet weight) ~

Uap

~ the receptor' milk consumption rate, in 1 iters/yr.

Yp

~ the agricultural productivity by unit area of pasture feed grassy in kg/m a the agricultural productivity by unit area of stored feed, s

in kg/m2.

Pm

~ the stable element transfer coefficients, in days/liter.

r ~ fraction of deposited activity retained on cow's feed grass.

(Dpi)a the organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in are m/pCi

~i ~ the decay constant for the ith radionuclide, in sec the decay constant for removal of activity on leaf. an

~

gant surfaces by weathering, 5.73 z 10 sec (corresponding to a 14 day half-time).

tf S tho traasport time receptor> ia sec.

from pasture to cov, to milk, to tho transport time from pasture, to harvest, to cov, to milk, to receptor, in sec.

fraction of tho year that the cow is on pasture (dimensionless).

fraction of tho cow feed that is pasture grass while the cov is on pasture (dimensionloss).

SPECIAL MOTE: The above equation is applicablo in the case that the milk animal is a goat.

Silk cattle are considered to bo fod from tvo potential sources, pasture grass aad stored feeds. Following the development ia Rogulatory Cuide 1.109, tho value of is will bo considered unity. TCN fp vill be considered to be O.S for a Hay to October grazing seasoa.

1 Tabulated belov are the appropriate parameter values aad their reference to Regulatory Cuide 1.109. In case that the milk animal is a goat, rather than a cov, refer to Regulatory Cuide 1.109 for the appropriate parameter values.

Parameter Value gab1e r (dimensionless) 1.0 for radioiodine B-15 0.2 for particulates B-15 Fm (days/liter) Bach stable element B-1 Uap (liters/yr) - Infant 330 E-5

- Child 330 E-5 Teen 400 E-5 Adult 310 E-5 (DFLi)a (mrem/pCi) Each radioauclide E-ll to E-14 rp (kg/4) 0.7 E-15 r, (kg/m2) 2.0 E-15 tf (socoads)

-,.th (seconds) 1.73 z 105 (2 days) 7.7S z 10'90 days)

E-15 E<<15

'Q (kg/day) 50 E-3 coacentration oi tritium in milk is based oa the airborne coaceatratioa cather than the deposition. Therefore, tho Ri is based on fz/()]:

Ri K'K"FmgpUapDFLi(0-75(O.S/H)) (mremlyr per uCi/m3)

-54

Where'.

K" a constant 'of unit conversion, 10 gm/kg .

H ~ absolute humidity of the atmosphere, in gm/m3 0.75 ~ the fraction of total feed that is water.

0.5 ~ the ratio of the specific activity of the feed grass water to atmospheric water.

and other parameters and values are given above. The value of H is considered as 8 grams/meter , in lieu of site specific information.

Example Calculation.

For I-131 infant thyroid dose factor from milk ingestion:

r 1.0 unitless for Iodines Fm ~ 6 E-3 days/liter for cows and 6E-2 for goats DPLi ~ 1.39E-2 mrem/pCi ii aw

~ 9.98E-7 sec -1

< 5.73E-7 sec -1 tf ~ 1.73E+5 sec.

These values will yield a factor of 5.26E11 and 6.31E11 mrem/yr per uCi/sec respectively for cow and goat ad.lk. However, the actual dose to the infant thyroid is also dependant on the highest relative deposition at respective cow and goat locations- At the Nine Mile Point Nuclear Station these deposition coefficients are 4.73E"10 and 1.33E-10 m-2 respectively for cows and goats. Because the goa t deposition is relatively so much smaller than the slightly larger Ri factor, cow milk is the limiting milk. If the location of the cow and goat milk receptors changes so that this is no longer true then the Ri factor will be revised accordingly. Table 3-12 lis t the infant thyroid dose factor from I-131 as 5.26E11 mrem/yr per uCi/sec. It should be noted that only a limited number of nuclides are listed on Table 3-12 thru 3-15. These are the most common nuclides encountered in effluents.

which a factor is not listed, then in a revision to the ODCM.

it If a nuclide is detected for will be calculated and included TABLES 3-16 18, Ri VALUES - COW MEAT (a2mrem/yr per uCi/sec) also takes into account the dose rate to rations organs from the ingestion of cowmeat for all age groups except infant. (Prom NUREG 0133, Section 5.3.1.4)

(a ~~ net vci/sec) 5

>>55-

Blare o

~

Pf. ~ the stable element txansfer coefficients, in days/kg.

Uap the receptor's meat consumption rate for age (a), in kg/yr.

tf ~ the txansport time from pasture to receptor, in sec.

th ~ the transport time from crop field to receptor, in sec.

Tabulated belm are the appropriate parameter values and their reference to Regulatory Guide 1.109.

parameter Table(RG1.109) r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Ff (days/kg Each stable element E-1 (kg/yr - Infant 0 E-5 Uap

- Child 41 E-5 65 E-5

- Teen h.dult 110 E~5 (DPLi) a (mrem/pCi) Each radar.onuclide E-ll to E-14 Yp (kg/mc) 0 7 E-15 Ys (kg/m2) 2.0 E-15 tf (seconds)

(seconds) 1.73 z 106 (20 days) 7.78 z 106 (90 days)

E-15 E-15 QF (kg/day) 50 E-3 The concentration of'ritium in meat is based on the airborne concentration rather than the deposition. Therefore, the Ri based on [z/Q]:

x'"'>~(~~) to.ls(o.s/N)7 (~/yr pe ci/g) vhere all terms axe defined above in this manual ~

Ezampla Calculation:

For I-131 child thyroid dose factox from co@ meat ingestion.

ff ~ 2.9E-3 days

~ 1.0 unitless for Iodines DPLi ~ 5.72E-3 mrea/pCi.

These values <<Ql yield a Ri factor of 2.75E9 m2~ea/yr per uCi/sec as listed on Table 3-16. It should be noted that only a limited number of nuclides are'listed on Table 3-16 thru 3-18. These ara the most common nuclides encountered in effluents. If a nuclide is detected fox which a factor is not listed, then in a xevision to the ODCM.

it vill be calculated

ThBLES 3-19 to 3-21 Ri VhLUES - VEGETATION Ri (a2~em/yr pcr uCi/sec) also takes into account the dose to various organs from thc iagestioa of vegetation for aU. age groups

<<xcept infant. (Prom NUREG 0133, Section 5.3.1 .5).

The iategrated concentration in vegetation consumed by man follows thc ezpression developed in the derivation of the milk factor. Man is coasidered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:

(0FLI)a 0 f i~ + IISf e

[

2

(+ 'cree/yr per sCI/sec)

@lire;

~ a constant of unit conversion, 10 pCI/uCI.

L the consumption rate of fresh leafy vegetation by the receptor Ua group ( ~ ). in kg/yr. r tnn aage

~ the consueption rata of stored vegatation by the receptor IPa in kg/yr. in age grou()

group a ~

fL ~ the fraction of the annual intake of fresh leafy vegetation gram>locally.

f ~ .the fraction of the annual intake of stored vegetation groan locally.

t ~ the average tine Ixhaen harvest of leafy vegetation and its consuytiuy on, in seconds ~

t~ the average tiae beoetn harvest of stored vegetation and in seconds.

its consusotion,

~ the vegetation areal densi Tv ty, in kg/as.

and al'1 other factors arc defined in this manual ~

Tabulated belo~ are the appropriate parameter values and their reference to Regulatory Guide 1.109.

PI p~tEF Value Table r (diaensi onl ass) 1.0 for radioiodines E 1 0.2 for particulates E 1 (OFLI ) (area/pCi) Each ra4i onuc1 ide E-'ll to E-Ia 0 (kg/yr) Infant 0 E-5 Chi14 24 E-5

- Teen 42 E-5 Adult 44 ES 0 (kg/yr) - Infant 0 E-5 Chi14 520 E-5 Teen 430 E-5

- Adult 520 E-5

.fL (di~si4 less) site specific (default ~ 1.0) f (dinensionless) site specific (default ~ '0.74) (see A6Nkgpage 28) t (seconds) 4.4 X 10 (1 day) E-15 t (seconds) 5.14 I 10 (40 days) E 15 T(ig/ ) 2.0 ~

E 15 The concentration of tritium in vegetation is based on the-airborne concentration rather than the deposition. Therefore f the Ri is

baaed on'.fx/Q].

a 0 (~))a f0.75(0.$ /H)J (arm/yr par uCt/a~).

where all terms have been defined above and in this manual ~

Example Calculation For I-131 child thyroid dose factor to the from vegetation ingestion-z 1.0 unitless for Iodines DFLi ~ 5.72E-3 mrem.pCi.

These values will yie1d a Ri factors of 4.75E10 m2~zem/yr per Ri/sec as listed on Table 3-19. It should be noted that only a limited number of nuclides are listed on Table 3-19 thru 3"21. These are the moat common nuclides encountered in effluents. If a nuclide is detected calculated and for which a factor is not listed, then included in a revision to the ODCM.

it will be 3.4.5 X/Q and Wv - Dispersion Parameters for Dose Rate, Table 3-22 The dispersion parameters for the whole body and skin dose rate calculation correspond to the highest annual average dispersion pazametezs at or beyond the unrestricted area boundary. This is at the East Site boundary. These values were obtained from the Nine Mile Point Usd.t 2 Final Environmental Statement, NUREG 1085 Table D-2 for the Vent and stack. These were calculated using the methodology of Regulatozy Guide 1.111, Rev. 1. The Stack was modeled as an elevated:release point because its height is more than 2.5 times than any ad)scent building. The Vent was modeled as a ground level release because even though it it is highez than any ad]scent building is not moze than 2.5 times the height.

The NRC Final Environmental Statement values for the Site Boundary X/Q and D/Q terms were selected for use in calculating Effluent Monitor k1azm Points and compliance with Site Boundary Dose Rate sy4jCfications because they are conservative when compared with the c NMPC Environmental Report values. In addition, the StShk "intermittent release" X/Q was selected in lieu o f the "continuous" value, since it is slightly larger, and also would allow not making, a distinction between long term and short term releases.

The dispersion parameters for the organ dose calculations were obtained fzom the Environmental Report, Figures 7B-4 (Stack) and 7B-8 (Vent) by locating values corresponding to curzently existing (1985) pathways. It should be noted that the most conservative pathways do not all exist at the same'ocation. It is conservative to assume that a single individual would actually be at each of the receptor locations.

3.4.6 Hv and Ns - Dispersion Parameters for Dose, Table 3-22 The dispersion parameters for dose calculations were obtained chiefly

'ree the: Nine Hile Point Unit 2 Environmental Report Appendix 7B, as noted in Section 3.4.5. These were calculated using the methodology of Regulatory Gu1de l.ill and NUREG 0324. The Stack was modeled as an elevated release point because 1ts he1ght is more than 2.5 t1mes than any ad)acent build1ng. The Vent was modeled as a combined elevated/ground level release because even though 1t 1s h1gher than any ad)acent building it 1s not more than 2.5 t1mes the height.

Average meterology over the appropriate time period was used.

Dispersion parameters not available from the ER were obta1ned from C.T. Hain Data report dated November, 1985, or as described in Sect1on 3.4.5, the FES.

3.5 I-133 Estimation The Stack and Vent Effluent Honitor at Nine H1le Point-Unit 2 are on line isotopic mon1tors. They are designed to automatically collect 1odine samples on charcoal cartr1dges and 1sotopically analyze them with a sens1tiv1ty wh1ch exceeds the LLD requirement on TS Table 4.11-2 of lE-l2 F1/cc. During those time per1ods 1n which the I-133 analysts cannot meet the LLD requirement, the I-l33 concentrat1on will be est1mated as 4 t1mes the I-l31 concentration, or by ratio applied to the I-131 concentrat1on. The ratio will be determined at least quarterly by analys1s of short durat1on samples.

3.6 Use of Concurrent Meteorological Data vs. Historical Data It 1s the intent of NMPC to use dispersion parameters based on historical meteorological data to set alarm points and to determine or predict dose and dose rates in the environment due to gaseous effluents. Hhen the methodology becomes available, it is the intent to use meteorolog1cal conditions concurrent with the t1me of release to determ1ne gaseous pathway doses. Alarm points and dose pred1ctions or est1mates will still be based on histor1cal data. The ODCH wi:ll be revised at that t1me.

3.7 Techn1cal Spec1fication 3.11.2.4 requ1res the Gaseous Radwaste Treatment System to be in operat1on whenever the main condenser air e3ector system is in operat1on. If discharge occurs without treatment for more than 7 days, a Spec1al Report 1s required describing reasons for inoperab111ty, actions taken to restore operability and prevent reoccurrence. These requ1rements help ensure that during most per1ods of operation, the treatment system 1s ut111zed. Hhen if becomes necessary to bypass components of the Offgas System, monitor1ng of stat1on effluents is prov1ded by the stack mon1tor1ng system to ensure compliance w1th 10CFR20 dose rate limits. The components of the system which are used to treat offgas are the Preheater, Recombiner, Condenser, Dryer, Charcoal Adsorbers, HEPA F1lter, and Vacuum Pump. . See F1gures 3-1, 3-2, and 3-3, Offgas System..

3.8 Ventilation Exhaust Treatment S stem 0 aration

.Technical. Specification 3 ~ 31.2.5 requires the Ventilation Exhaust Tza4Caent System to be OPERABLE when pro)ected doses in 31 days due thymine and particulate releases vould exceed 0.3 mrem to any organ of a member of the public. The appropriate components, which affect iodine or particulate release, to be OPERABLE are:

1) HEPA Pilter - Radvaste Decon Area

2) HEPA Pilter - Radvaste Equipment Area

3) HEPA Filter - Radwaste General Area Whenever one of these filters is not OPERABLE, iodine and particulate dose projections vi11 be made for the remainder of the cuzrent calendar month, and for each month (at the time of calculating cumulative monthly dose contributions) that the filter remains inoperable, in accordance vith 4.11.2.5.1. Pzedicted release rate vill be used, with the methodology of Section 3.3 3. See Figure 3-5, Gaseous Radiation Monitoring.

TABLE 3-1 DETECTOR RESPONS E NET CPM/uCi/cc Kr 85 4.30E+3 Kr 85m 4.80K+3 Kr 87 8.00E+3 Kr 88 7.60E+3 Xe 133 1.75K+3 Xe 133m Xe 135 5.10K+3 Xe 135m Xe 137 8.10K+3 Xe 138 7.10K+3 "Values from SWEC purchase speci.fication NMP2-P281F NUCKZM Kr 83m Kr 85 (Wrad/ r w uCi/sec) 3.5.1E-5 3.39E-3 TABLE rLmE Smrz 3-2 PAEAmXERS*

V (mrem/ r o uC1/sec) 3.28E-5 3.21E-3 I

Kr 85m 1.04E-2 9.98E-3 Kr 87 2.34E-2 2i2ZE-2 Kr 88 2.01E-2 1 92E-2 Kr 89 1 e59E-2 1.51E-2 Xe 131m 6.90E-5 6.55E-5 Xe 133 6. 5.93E-4 12'.62E-4 Xe 133m 3.44E-4 Xe 135 4 31E-3 4.09E-3 Xe 135m 6.55E-3 6.12E-3 Xe 137 3.07E-3 2.88E-3 Xe 138 1 38E-2 1.33E-2 Ar 41 1 69E-2 1.61E-2

• Bi and Vi are calculated for critical site boundary location; 1.6km in the Naaterly direction.

TABLE 3-3 DOSE FACTORS*

Nuclide N((r Bcdy)ee )d(d-N)c(u)ee Nd(r iir)*ee ~g(g dir)eee Kr 83m 7.56E-02 2.88K 2 Kr 85m 1.17E3 1.46E3 1.23E3 1.97E3 Kr 85 Kr 87 1.61E1 5.92E3 1.34E3 9.73E3

'.93E1 1.72E1

6. 17E3 1.95K 3 1.03E4 Kr. 88 1 e47E4 2.37E3 1.52E4 2.93E3 Kr 89 1.66E4 1.01E4 1.73E4 1.06E4 Kr 90 1.56E4 7.29E3 1.63E4 7.83E3 Xe 131m 9. 15E1 4.76E2 1.56E2 1.11E3 Xe 133m 2.5IE2 9.94E2 3.27E2 1.48E3 Xe 133 2.94E2 3.06E2 3.53E2 1.05E3 Xe 135m 3e12E3 7.11E2 3.36E3 7.39E2 Xe 135 1 81E3 1.86E3 1. 92E3 2.46E3 Xe 137 1.42E3 1.22E4 1.51E3 1.27E4 Xe 138 8.83E3 4.13E3 9.21E3 4. 75E3 hr 41 8.84E3 2.69E3 9.30E3 3.28E3

<<Prom, Table B-l.Regulatory Guile 1.109 Reve 1 e*mrem/yr per uCf/m3 ~

• e*mradlyr per i(Ci/m3 ~

TABLE 3-4 Pi VALUES - GROUND PLANE**

a~~azem/ r i'/se c TOTAL BODY SKIN H 3 C 14 Cr 51 6.64E6 7.85E6 Mn 54 1.10E9 1.29E9 3.88E8 4.56E8 Co 58 5+ 27E8 6. 18E8 Co 60 4.40E9 5 17E9 Zn 65 6.87E8 7. 90E8 Sr 89 3.06E4 3.56E4 Sr 90 Zr 95 3.44E8 3.99E8

• Nb 95 3.50E8 4. 12E8 Mo 99 5.71E6 6.61E6 I 131 2.46E7 2.98E7 I 133 3.50E6 4.26E6 Cs 134 2.81E9 3.28E9 Cs 137 1.15E9 1.34E9 Ba 140 2 93E7 3.35E7

• La. QQ 2.10E8 2.38E8 Ce 141 1.95E7 2.20E7 5.85E7 6.77E7

'*Daughter Decay Product. Activity level and effective haLf life assumed to equal parent nuclide.

• eCalculated in accordance with NUREG 0133, Section 5.2.1.2.

TABLE 3-5 P

i VALUES - INHALATION**

ruralr 3

uCi/m NUCLIDE BONE LIVEN T. BODT TETEOID KIDNET LUNG GI-LLI H 3 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 C 14 2.6SE4 5.31E3 5.31E3 5.31E3 5.31E3 5.3323 5.31E3 Cr Sl 8.95E1 5.75EL 1.32EL 1.28E4 3.57E2 Mn 54 2 53E4 4.98E3 4.98E3 1.00E6 7-06E3 Pe 59 1.36E4 2.35E4 9.48E3 1.02E6 2.48E4 Co 58 1.22E3 1.82E3 7.77ES 1.11E4 Co 60 8.02E3 1.18E4 4.51E6 3.19E4 Zn 65 1.93E4 6.26E4 3.11E4 3.25E4 6.47E5 5.14E4 Sr 89 3.98E5 1.14E4 2.03E6 6.40K 4 Sr 90 4.09E7 2.59E6 1.12E7 1.31ES I

Zr 95 1.15ES 2 79E4 2.03E4 3.11E4 1.75E6 2.17E4 "Nb 95 1.57E4 6 43E3 3.78E3 4.72E3 4.79ES 1.27E4 Mo 99 1.65E2 3.23E1 2.65E2 1.35E5 4.87K 4 I 131 3 79E4 4.44E4 1.96E4 1.48E7 5.18E4 1.06E3 I 133 1.32E4 1.92E4 5.60E3 3.56E6 2.24E4 2.16E3 Cs 134 3.96E5 7.03ES 7.45E4 1.90E5 7.97E4 1.33E3 Cs 137 ', 5.49ES 6.12E5 4.55E4 1.72E5 7.13E4 1.33E3 Ba 140 5.60E4 5.60KL 2.90E3 1 34EL 1.60E6 3.84E4

• La 140 S.OSE2 2.00E2 5.15EL 1.68ES 8.48E4 Ce 141 2.77E4 1.67E4 1.99E3 5.25E3 5.17E5 2.16E4 Ce 144 3.19E6 1.21E6 1.76ES 5 38ES 9.84E6 1 48ES

• Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

• • Calculated in accordance with NUREG 0133, Section 5.2.1.1.

-65>>

TABLE 3-6 P VALUES -200D (Cow Milk)*<<*

m 2 - mrem/yr 0 uCi/sec NUCLIDE BONE LIVEN T. BODY THYROID KIDNEY LUNG GI-LLI

• H 3 2.40E3 2.40E3 2.40E3 2.40E3 2.40E3 2.40E3

<<C 14 3.23E6 6.89E5 6.89ES 6.89ES 6.89E5 6.89E5 6.89ES Cr 51 1 .64ES 1.07ES 2 34E4 2.08ES 4.78E6 Mn 54 3.97E7 8 99E6 B.BOE6 1.46E7 Fe 59 2.2BEB 3.99ES 1.57EB 1.18KB 1.91EB Co 58 2.47E7 6.16E7 6 15E7 Co 60 8.98E7 2.12ES 2.14EB Zn 65 5.65E9 1.94E10 8.94E9 9.40E9 1.64ELO Sr 89 1.28ELO 3.67ES 2.63E8 Sr 90 1.24EL1 3. 15ELO 1.55E9 Zr 95 6.93E3 1.69E3 1.20E3 1.82E3 8.41ES

<<<<Nb 95 7.07ES 2.91ES 1.68ES 2.09ES 2.46ES Mo 99 2.12E8 4.13E7 3.17ES 6.98E7 I 131 2.77E9 3.26E9 1.43E9 1.07EL2 3.81E9 lo16ES I 133 3.69E7 5.37E7 1.57E7 9.77E9 6.31E7 9.09E6 Cs 134 3.71E10 6.92KLO 6.99E9 1.78E10 7.31E9 1.88KB Cs 137 5.24ELO 6.13ELO 4.35E9 1.65ELO 6.67E9 1.92ES Ba 140-2.45ES 2.45ES 1.26E7 5.83E4 1.51ES 6.03E7

• • La 140"3,79E2 1 49E2 3.84EL 1.75E6 Ca 141 4N41E4 2.69E4 3. 17E3 8.30E3 1.39E7 Ce 144 2.37E6 9.69ES 1 33ES 3.92E5 1.36EB

<<mrem/yr per uCi/m3.

'<<Daughter Decay Product. Activity level and effective haLf life assumed to equal parent nuclide.

• • • Calculated in accordance with NUREG 0133,. )ection 5.2.1.3.

TABLE 3-7 VALUES - INHALATION - INFANT<<<<

a~rem/ r EECi/m NDOLIDE BONE LEONE T BODE TEZEOZD KIDNEY LUNG GZ-LLZ H 3 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 C 14 2.65E4 5.31E3 5.3IE3 5.3IE3 5.31E3 5 ~ 31E3 5.31E3 Cr 51 8.95E1 5.75El 1.32E1 1.28E4 3.57E2 Mn 54 2.53E4 4.98E3 4.98E3 1.00E6 7.06E3 Pe 59 1.36E4 2.35E4 9.48E3 1.02E6 2.48E4 Co 58 1.22E3 1.82E3 7 '7E5 1. 11E4 Co 60 8.02E3 1.18E4 4.51E6 3B19E4 Zn 65 1.93E4 6.26E4 3.11E4 3.25E4 6.47ES 5.14E4 Sr 89 3.98E5 1. 14E4 2.03E6 6.40E4 Sr 90 4.09E7 2.59E6 1.12E7 1 3IES Zr 95 1.15E5 2.79E4 2.03E4 3 llE4 1.75E6 2.17E4

<<Nb 95 1.57E4 6.43E3 3.78E3 4.72E3 4.79E5 1.27E4 Mo 99 1.65E2 3.23El 2.65E2 1.35E5 4.87E4 I-131 3.79E4 4.44E4 1.96E4 1.48E7 5.18E4 1.06E3 I 133 1.32E4 1.92E4 5.60E3 3.56E6 2.24E4 2.16E3 Cs 134 3.96ES 7.03ES 7.45E4 1.90E5 7.97E4 1.33E3 Cs 137 5.49E5 6.12E5 4.55E4 1.72E5 7.13E4 1.33E3 Sa 140 5.60E4 5.60El 2.90E3 1,34E1 1 60E6 3.84E4

<<La 140 5.05E2 2.00E2 5.15E1 1.68ES 8.48E4 Ce 141 2.77E4 1.67E4 1.99E3 5.25E3 5. 17ES 2.16E4 Ce 144 3.19E6 1.21E6 1.76E5 5 38ES 9 84E6 1.48E5

<<Daughter Decay Product. Activity level and effective half 1ife assumed to equal parent nuclide.

<<<<This and followiag Q Tables Calculated in accordance with NUREG 0133, Section 5-3.1, ezcpet C 14 values in accordance vith Regulatory Guide 1.109 Equation C-8.

>>67-

TABLE 3-8 R VALUES - INHALATION - CHILD a~rea/ r 3

wCi/m NUCLIDE BONE LIVER T. BODE TETROID KIDNET IOEG GI-LLI H 3 1.12E3 1.12E3 1.12E3 1.12E3 1.12E3 1.12E3 C 14 3.59E4 6.73E3 6.73E3 6.73E3 6.73E3 6.73E3 6 73E3 Cr 51 1.54E2 8.55EL 2.43EL 1.70E4 1.08E3 Mn 54 4.29E4 9.5IE3 1.00E4 1.58E6 2.29E4 Pe 59 2.07E4 3.34E4 1.67E4 1.27E6 7.07E4 Co 58 1.77E3 3. 16E3 1.11E6 3.44E4 Co 60 1.3IZ4 2.26E4 7.07E6 9.62E4 Zn 65 4.26E4 1.13E5 7.03E4 7.14E4 9.95E5 1.63E4 Sr 89 5.99E5 1.72E4 2 16E6 1 67E5 Sr 90 1.0IZ8 6.44E6 1.48E7 3.43E5 Zr 95 1.90E5 4.18E4 3.70E4 5.96E4 2.23E6 6.1IE4

• Nb 95 2.35E4 9.18E3 6.55E3 8.62Z3 6.14E5 3.70E4 Mo 99 1.72E2 4.26EL 3.92E2 1.35E5 1.27E5 I 131 4.8IZ4 4.8IZ4 2.73E4 1.62Z7 7.88E4 2.84E3 I 133 1.66E4 2.03E4 7 70E3 3.85E6 3.38E4 5.48K 3 Cs 134 6.5IZ5 I.OIE6 2.25E5 3.30E5 1.2IZ5 3.85E3 Cs 137 SA7Z5 8.25E5 1.28E5 2.82E5 1.04E5 3.62K 3 Ba 140'ya40E4 6.48EL 4 33Z3 2. IIZI 1.74E6 1.02E5 eLa 140 6.44E2 2.25E2. 7.55EL 1.83E5 2.26E5 Ce 141 3.92E4 1.95E4 2.90E3 8.55E3 5.44E5 5.66E4

~

. Ce 144 6.77E6 2 12E6 3.61E5 1.17E6 1.20E7 3.89E5

• Daughter Decay Product. Activity level and effective half life assumed to equal Parent nuclide.

TABLE 3-9 R

i VALUES - INHA?dZION - TEEN m~zcml z 3

uCi/m NUCLIDE BONE LIVER Y. BODY YEYROID KIDNEY I BEG G I-LLI H 3 1.27E3 1.27E3 1.27E3 1.27E3 1.27E3 1.27E3 C 14 2.60E4 4.87E3 4.87E3 4.87E3 4.87E3 4.87E3 4.87E3 Cr 51 1.35E2 7.50KL 3.07E1 2.10E4 3.00E3 Mn 54 5. 11E4 8.40E3 1.27E4 1.98E6 6.68E4 Pe 59 1.59E4 3.70E4 1.43E4 1.53E6 1.78ES Co 58 2.07E3 2.78E3 1.34E6 9.52E4 Co 60 1.51E4 1.98E4 8.72E6 2.59E5 Zn 65 3.86E4 1.34E5 6.24E4 8.64E4 1.24E6 4.66E4 Sr 89 4.34E5 1.25E4 2.42E6 3.71ES Sr 90 1.08E8 6.68E6 1.65E7 7.65ES Zr 95 1.46E5 4.58E4 3.15E4 6.74E4 2.69E6 1.49ES

• Nb 95 1.86E4 1.03E4 5.66E3 1 00E4 7.51ES 9.68E4 Mo 99 1.69E2 3.22EL 4.11E2 1.54ES 2 69E5 I 131 3.54E4 4.91E4 2.64E4 1.46E7 8.40E4 6.49E3 I 133 1.22E4 2.05E4 6.22E3 2 92E6 3.59E4 1.03E4 Cs 134 5.02ES 1.13E6 5.49E5 3.75E5 1.46E5 9.76E3 Cs 137 6.70ES 8.48E5 3.11ES 3.04ES 1.21ES 8.48E3 Ba 140 5.47E4 6.70E1 3.52E3 2.28E1 2.03E6 2.29E5

<<Ia 140 4.79E2 2.36E2 6.26 EL 2.14E5 4.87ES Ce 141 2.84E4 1.90E4 2.17E3 8.88E3 6 14ES 1.26E5 Ce 144 4.89E6 2.02E6 2.62E5 1.21E6 1.34E7 8 64ES

<<Daughter Decay 5'roduct.

equal parent nuclide.

Activity level and effective half life assumed to TABLE 3-10 R

i VAIUES - INHA1ATION - ADULT

~eeet/ e 3

uCi/m NUCLIDE BONE T ~ BODT TEIEOZD KIDNEY LUNG GZ-LLZ 8 3 1.26E3 1.26E3 1 26E3 1.26E3 1.26E3 1.26E3 C 14 1.82E4 3.41E3 3.41E3 3e41E3 3.41E3 3.41E3 3.41E3 Cr 51 1.00E2 5.95EL 2.28E1 1.44E4 3.32E3 Mn 54 3.96E4 6.30E3 9. 84E3 1.40E6 . 7. 74E4 Fe 59 1.18E4 2.78E4 1.06E4 1.02E6 1.88E5 1.58E3 2.07E3 9.28E5 1.06E5 Co 60 1.15E4 1.48E4 5.97E6 2.85E5 Zn 65 3.24E4 1.03E5 4.66E4 6.90E4 8.64E5 5.34E4 Sr 89 3.04E5 8.72E3 1,4PE6 3.50E5 Sr 90 9.92E7 6 '0E6 9 '0E6 7.22E5 Zr 95 1.07ES 3.44E4 2.33E4 5 42E4 1.77E6 1.50E5 eNb 95 1.41E4 7.82E3 4.21E3 7.74E3 5.05E5 1.04E5 Mo 99 1.21E2 2.30KL 2.91E2 9.12E4 2.48E5 I 131 2.52E4 3.58E4 2.05E4 1 19E7 6.13E4 6.28E3 I 133 8.64E3 1.48E4 4.52E3 2.15E6 2.58E4 8.88E3 Cs 134 3.73E5 8.48ES 7.28E5 2.87E5 9.76E4, 1.04E4 Cs 13? .4 78E5 6.21E5 4.28E5 2.22E5 7.52E4 8.40E3 Ba 140 '9.90E4 4.90EL 2.57E3 1.67E1 1.27E6 2.18E5 eLa 140 3.44E2 1 74E2 4.58EL 1.36E5 4.58E5 C@ 141 1.99E4, 1.35E4 1.53E3 6.26E3 3.62E5 1.20E5 Ce 144 3e43E6 le43E6 1.84E5 &.48E5 7.78E6 8 16E5 eDaughter Decay product. Activity level and effective half life assumed to equal parent nuc191e.

TABLE 3-11 Ri VALUES GROUND PLANE ALL A.GE GROUPS m

2 - mrem/yr 4 uCi/sec NUCLIDE TOTAL BODY H 3 C 14 Cr 51 4.65E6 5.50E6 Mn 54 1.40E9 1.64E9 Fe 59 2.73E8 3.20E8 Co 5S 3 80ES 4.45ES Co 60 2.15E10 2.53E10 Zn 65 7 46ES 8.57ES Sr 89 2.16E4 2.5IE4 Sr 90 Zr 95 2.4SE8 2.85E8

• Nb 95 2.50E8 2. 94ES Mo 99 3.99E6 4.63E6 I 131 1.72E7 2.09E7 I 133 2 45E6 2.98E6 Ca 134 6 83E9 7. 97E9 CQ 137 1.03E10 .1.20ELO ba 140 2.05E7 2.35E7

• La 140 1.47ES 1.66E8 Ce 141 1.37E7 1.54E7 Ce 144 6.96E7 8.07E7

• Daughter Decay Product- Activity level and effective half life assumed to equal parent nuclide.

TABLE 3-12 Ri VALUES - COP MILK - INFANT 2

m ~em/yr 4 uCi/sec NUOLZDE BONE Y. BODY YNYROZD KZDNEY LUNG GI-LLI

• H 3 2 3SE3 2.38E3 2.3SE3 2.38E3 2.38E3 2.38E3 "C 14 3.23E6 6.89E5 6.89E5 6 89E5 6.89E5 6.89E5 6.89E5 Cr 51 8.35E4 5.45E4 1.19E4 1.06E5 2A3E6 Mn 54 2.51E7 5 ~ 68E6 5.56E6 9 21E6 Fe 59 1.22EB 2.13ES 8.38E7 6.29E7 1.02EB Co 58 1.39E7 3.46E7 3.46E7 Co 60 5.90E7 1.39EB 1.40ES Zn 65 3.53E9 1.21E10 5.58E9 5. 87E9 1.02E10 Sr 89 6.93E9 1.99ES 1.42ES Sr 90 8.19E10 2. 09ELO 1.02E9 Zr 95 3.85E3 9.39E2 6.66E2 1.01E3 4.68E5

<<<<Nb 95 3.93E5 1.62E5 9.35E4 1 16E5 1.3?EB Mo 99 1.04EB 2.03E7 1.55ES 3.43E7 I 131 1.36E9 1.60E9 7.04ES 5.26E11 1.87E9 S. 72E7 I 133 1.81E7 2.64E7 7.72E6 4.79E9 3.10E7 4A6E6 Cs 134 2.41E10 4.49ELO 4.54E9 1.16E10 4.74E9 1.22EB Cs 137 3A7ELO 4.06E10 2.88E9 1.09ELO 4AIE9 1.27EB Ba 140 1.21ES 1.21E5 6.22E6 2.8?E4 7.42E4 2.97E?

<<<<Xa 141 1 86E2 7.35E1 1.89EL 8.63E5 N

Ce 14L<1 28E4 1.39E4 1.64E3 4.28E3 7. 1BE6 Ce 144 1A9E6 6.1QE5 8.34E4 2A6E5 8.54E?

<<mrem/yr per uCi/m3.

'<<<<Daughter Decay Product. hctivfty level and effective half life assumed to equal parent nuclide.

TABLE 3-13 R

i VALUES - CON MILR - CHILD 2

m ~em/yr 4 nCi/sec NUCLIDE BONE 1 ~ BODT TETEOTD KTDNET LUNG GT-LLT

• H 3 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3

• C 14 1.65E6 3.29E5 3-29E5 3.29E5 3.29E5 3.29E5 3.29E5 Cr 51 5.27E4 2.93E4 7.99E3 5.34E4 2.80E6 Mn 54 1.35E7 3.59E6 3.78E6 1.13E7 Pe 59 6.52E7 1.06E8 5.26E7 3.06E7 1.10ES Co 58 6. 94E6 2. 13E7 4.05E7 Co 60 2.89E7 8.52E7 1.60ES Zn 65 2. 63E9 7.00E9 4.35E9 4.41E9 1.23E9, Sr 89 3.64E9 1.04ES 1.41E8 Sr 90 7.53E10 1 91E10 1.01E9 Zr 95 2.17E3 4.77E2 4.25E2 6.83E2 4.98E5

• <<Nb 95 2.10E5 8 19E4 5 85E4 7 '0E4 1.52E8 Mo 99 4.07E7 1.01E7 8.69E7 3.37E7 I 131 6.51ES 6.55ES 3.72E8 2.17EL1 1.08E9 5.83E7 I 133 8.58E6 1.06E7 4.0IE6 1.97E9 1.77E7 4.27E6 Cs 134 1.50E10 2.45E10 5.18E9 7. 61E9 2.73E9 1.32E8 Cs 137 2.17ELO 2.08ELO 3.07E9 6.78E9 2.44E9 1.30ES Ba 140 5.87E7 5.14E4 3.43E6 1.67E4 3.07E4 2.97E7

<<<<La 140 8.92KL 3.12KL 1.05EL 8.69K 5 Ce 141 1.15E4 5.73E3 8.51E2 2.51E3 7.15E6 Ce 144 1.04E6 3.26E5 5.55E4 1.80E5 8.49E7

• mrem/yr per tTCi/m3.

<<<<Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

TABLE 3-14 R

i VhLUES -

2 COP MILK - TEEN m ~em/yr 4 uCi/sec NOOIIDB BONE Y. BODY YHYROID KIDNEY IONG GI-III

<<8 3 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2

<<C 14 6.70E5 1.34E5 1.34E5 1.34E5 1.34E5 1.35E5 1.34E5 Cr 51 2.58E4 1.44E4 5.66E3 3.69E4 4.34E6 Mn 54 9 OIE6 1 79E6 2.69E6 1.85E7 Fe 59 2.81E7 6.57E7 2.54E7. 2.07E7 1.55ES Co 58 4.55E6 1.05E7 6.27E7 Co 60 1.86E7 4.19E7 2.42ES Zn 65 1.34E9 4.65E9 2.17E9 2.97E9 1.97E9 Sr 89 1.47E9 4.21E7 1.75E8 Sr 90 4.45E10 1.10ELO 1.25E9 Zr 95 9.34E2 2.95E2 . 2.03E2 4.33E2 6.80E5

<<<<Nb 95 9 32FA 5.17E4 2.85E4 5.01E4 2 21E8 Mo 99 2.24E7 4.27E6 5.12E7 4.01E7 I 131 2.68E8 3.76ES 2.02E8 1.10EU. 6.47E8 7.44E7 I 133 3.53E6 5.99E6 1.83E6 8.36E8 1.05E7 4.53E6 Cs 134 6.49E9 1.53ELO 7.08E9 4.85E9 1.85E9 1.90ES Cs 137 9.02E9 1 20ELO 4.18E9 4.0SE9 1.59E9 1.71ES Ba 140 2.43E7 2.98FA 1.57E6 1.01E4 2.00FA 3.75E7

<<<<Ia 140 3 73KL 1 83KL 4.87EO 1.05E6 Ce 14L 4o67E3 3.12E3 3.58E2 1 B47E3 8. 91E6 Ce 144 4.22ES 1.74E5 2.27E4 1.04E5 1.06ES

<<mrem/yr per uCi/m3.

<<<<Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

TABLE 3-15 R

i VALUES - COW MILK - ADULT 2

m harem/yr 4 sCi/sec NUCLIDE BONE LIVEN Y. BODY YEIEOZD EZDNEY LUNG GZ-ZLI

<<H 3 7.63E2 7.63E2 7.63E2 7.63E2 7.63E2 7.63E2

• C 14 3.63E5 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 Cr 51 1.48E4 8.85E3 3.26E3 1.96E4 3.72E6 Mn 54 5.41E6 1.03E6 1. 61E6 1.66E7 Fe 59 1.61E7 3.79E7 1.45E7 1.06E7 1.26E8 Co 58 2.70E6 6 05E6 5.47E7 Co 60 1.10E7 2.42E7 2.06ES Zn 65 8.71ES 2.77E9 1.25E9 1.85E9 1.75E9 Sr 89 7.99E8 2.29E7 1.28E8 Sr 90 3.15E10 7.74E9 9 ~ 11ES Zr 95 5.34E2 1.71E2 1.16E2 2.69E2 5.43E5

<<<<Nb 95 5.46E4 3.04E4 1.63E4 3.00E4 1.84E8 Mo 99 1.24E7 2.36E6 2.81E7 2.87E7 I 131 1.48ES 2.12ES 1.21ES 6.94E10 3.63ES 5. 58E7 I 133 1.93E6 3.36E6 1.02E6 4.94ES 5.86E6 3.02E6 Cs 134 3.74E9 8.89E9 7.27E9 2.88E9 9.55E8 1.56ES Cs 137 4.97E9 6.80E9 4.46E9 2.31E9 7.68ES 1.32ES Ba 140 1.35E7 1.69E4 8.83E5 5.75E3 9.69E3 2.77E7

• <<La 140 2.07E1 1.05El 2.76EO 7.67E5 Ce 141 2 54E3 1.72E3 1.95E2 7. 99E2 6. 58E6 Ce 144 2 29E5 9.58E4 1.23E4 5.68E4 7.74E7

• mrem/yr .per uCi/m ~

<<<<Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

TABLE 3-16 Ri VALUES - COW MEA,T - CHILD 2

m ~rem/yr 4 uCi/sec NDGIZDE BONE I. BODY YNYROZD RZDNEY LUNG GZ-IIZ

• H 3 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 2 34E2

<<C 14 5.29E5 1 06E5 1.06E5 1.06E5 1.06E5 1.06E5 1.06E5 Cr 51 4.55E3 2.52E3 6.90E2 4.61E3 2.41E5 Mn 54 5.15E6 1.37E6 1.44E6 4.32E6 Fe 59 2.04E8 3.30E8 1 65ES 9.58E7 3.44E8 Co 58 9.41E6 2. 88E7 5.4 9E7 Co 60 4.64E7 1.37E8 2.57ES Zn 65 2.38ES 6.35ES 3.95ES 4.00E8 1.12E8 Sr 89 2.65ES 7.57E6 1 o03E7 Sr 90 7.01E9 1.78E9 9.44E7 Zr 95 1.51E6 3.32E5 2.95E5 4.75E5 3.46E8

• • Nb 95 2.41E6 9.38E5. 6.71E5 8.82E5 1.74E9 Mo 99 5.42E4 1.34E4 1.16E5 4.48E4 I 131 8.27E6 8.32E6 4.73E6 2.75E9 1.37E7 7.40K5 I 133 2.87E-1 3.55E-1 1.34E-1 6.60E-l 5.92E-l 1.43E-l Cs 134 6.09E8 1.00E9 2.11E8 3. 10ES 1.11ES 5.39E6 Cs 137 8.99ES 8.60E8 1.27ES 2.80ES 1.01ES 5.39E6 Ba 140 2.20E7 1.93E4 1.28E6 6.27E3 1.15E4 1.11E7

• eLa 140 1.67E2 5.84Ei 1.97E1 1.63E6 Ce MX 1.1784 5.82E3 8.64E2 2.55E3 7 26E6 Ce 144 1.48E6 4.65E5 7.91E4 2 57E5 1.21ES

• mrem/yr per uCi/m3.

• • Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

TABLE 3-17 R

i VALUES - COW MEAT - TEEN 2

m ~em/y e uCi/sec NUCLIDE BONE Y. BODY YBYROID RZDNBY LUNG GZ-LLI 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2

• C 14 2.81ES 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 Cr 51 2.93E3 1.62E3 6.39E2 4.16E3 4.90E5 Mn 54 4.50E6 8.93ES 1.34E6 9 '4E6 Pe 59 1.15ES 2.69ES 1 .04ES 8.47E7 6.36ES Co 58 S.OSE6 1.86E7 1.11E8 Co 60 3.90E7 8 80E7 5.09E8 Zn 65 1.59ES 5.52E8 2.57ES 3.53E8 2.34E8 Sr 89 1.40E8 4.0iE6 1.67E7 Sr 90 5.42E9 1.34E9 1.52ES Zr 95 8.50E5 2.68ES 1.84E5 3.94E5 6.19E8 e*Nb 95 1.40E6 7.74E5 4.26E5 7.51ES 3.31E9 Mo 99 3.90E4 7.43E3 8.92E4 6.98E4 I 131 4.46E6 6 24E6 3.35E6 1.82E9 1.07E7 1.23E6 I 133 1.55E-l 2.62E-l 8 OOE-2 3.66E1 4.60E-l 1.99E-1 Cs 134 3.46ES 8.13E8 3.77E8 2.58ES 9.87E7 1.01E7 Cs 137 4.88E8 6.49E8 2.26E8 2.21ES 8.58E7 9.24E6 Ba 140 1.19E7 1.46E4 7-68ES 4.95E3 9.8iE3 1.84E7

• ~La 140 9.12E1 4.48E1 1.19E1 2.57E6 Ce 14K 6.19E3 4.14E3 4.75E2 1.95E3 1N18E7 Ce 144 7 87E5 3 26E5 4 23E4 1.94ES 1.98ES

• mrem/yr per tzCi/m3.

• eDaughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

77~

TABLE 3-18 Ri VALUES - COW MEA,T - ADULT 2

m ~em/yr w uCi/sec t

NUCLIDE BONE T. BODE INTROID KIDNET LUNG GI-LLI

• H 3 3.25E2 3.25E2 3 25E2 3.25E2 3.25E2 3.25E2

<<C 14 3.33E5 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 Cr 51 3.65E3 2.18E3 8.03E2 4.84E3 9.17E5 Hn 54 5.90E6 1.13E6 1.76E6 1. ME7 Fe 59 1.44E8 3.39ES 1.30E8 9 46E7 1.13E9 Co 58 1.04E7 2.34E7 2.12E8 Co 60 5.03E7 l.liES 9.45E8 Za,65 2.26E8 7.19E8 3.25ES 4D81ES 4.53ES Sr 89 1.66ES 4.76E6 2.66E7 Sr 90 8.38E9 2.06E9 2.42ES Zr 95 1.06E6 3.40E5 2.30E5 5.34E5 1.08E9

• <<Nb 95 1.79E6 9.94E5 5.35ES 9.83E5 6.04E9 Mo 99 4.71E4 8.97E3 1.07E5 1.09E5 X 131 5.37E6 7.67E6 4.40E6 2.52E9 1 32E7 2 02E6 I 133 1.85E-1 3.22E 1 9.81E-2 4.73EL 5.6iE-1 2.89E-1 Cs 134 4.35ES 1G03E9 8.45ES 3.35ES 1.11ES 1.81E7 Cs 137 5.88E8 8.04ES 5.26ES 2.73E8 9.07E7 1.56E7 Ba 140 1G44E7 1.81E4 9.44E5 6 15E3 1.04E4 2.97E7

<<*IN 140 1GliE2 5G59KL 1.48EL 4 10E6 Ce XC 7.38E3 4.99E3 5.66E2 2.32E3 1 91E7 Ce 144 9.33E5 3.90E5 5.0iE4 2 3IX5 3.16E&

<<mremlyr per iM/m3.

<<<<Daughter Decay Product. Activity level and effective half life assumed to equal hereat nuclide.

TABLE 3-19 R

i VALUES VEGETATION - CHILD 2

m mremlyr + pCi/sec NUCLIDE BONE T. BODE TETEOID KZDNET LONG GZ-LLI

<<H 3 4.01E3 4.0IE3 4.01E3 4.01E3 4.01E3 4.01E3

<<C 14 3.50E6 7.01E5 7.01E5 7.01E5 7.01E5 7.01E5 7.01E5 Cr 51 1.17E5 6.49E4 1.77E4 1.18E5 6.20E6 Mn 54 6.65EB 1 ~ 77EB 1.86ES 5 '8EB Fe 59 3.97ES 6.42EB 3.20ES 1.86EB 6.69ES Co 58 6.45E7 1.97EB 3.76ES Co 60 3.78KB 1.12E9 2.10E9 Zn 65 8. 12EB 2. 16E9 1.35E9 1.36E9 3.80ES Sr 89 3.59ELO 1.03E9 1.39E9 Sr 90 1.24E12 3. 15E11 1.67E10 Zr 95 3.86E6 8.50E5 7.56E5 1.22E6 8.86EB

• • Nb 95 7.50E5 2.92E5 2 09E5 2.74E5 5.40EB Mo 99 7.70E6 1.91E6 1.65E7 6.37E6 I 131 1.43EB 1.44KB 8. 16E7 4.75ELO 2.36EB 1 ~ 28E7 I 133 3.52E6 4.35E6 1.65E6 B.OBES 7.25E6 1.75E6 Cs 134 1.60ELO 2.63E10 5.55E9 8.15E9 2.93E9 1.42KB Cs 137 2.39ELO 2.29ELO 3.38E9 7.46E9 2.68E9 1.43ES Ba 140 2.77EB 2.43E5 1.62E7 7. 90E4 1.45E5 1.40ES

<<<<Ia 140 3.37E4 1.18E4 3.97E3 3.28ES Ce 14K 6.56E5 3.27E5 4.85E4 1.43E5 4.08KB Ce 144 1.27EB 3.98E7 6.78E6 2.21E7 1.04 E10

<<mremlyr per uCilm ~

<<<<Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

TABLE 3-20 R

i VhLUES - VEGETATION TEEN 2

m ~remlyr 4 uCilsec NUCLIDE BONE I. BODY TETROID KIDNET LUNG GI-III

• H 3 2.59E3 2.59E3 2.59E3 2.59E3 2.59E3 2.59E3

<<C 14 1.45E6 2.9iE5 2.9iE5 2.91E5 2.9iES 2.91E5 2.9lE5 Cr 51 6.16E4 3.42E4 1.35E4 8 79E4 1.03E7 Mn 54 4 54KB 9 OIE7 1.36EB 9.32EB Pe 59 1.79EB 4.18EB 1.61ES 1.32EB 9.89EB Co 58 4.37E7 1.01ES 6.02EB Co 60 2.49EB 5.60KB 3.24E9 Zn 65 4.24EB 1.47E9 6.86KB 9.41EB 6.23EB Sr 89 1.51E10 4.33EB 1.80E9 Sr 90 7.51E11 1.85Ell 2. 11E10 Zr 95 1.72E6 5.44E5 3 74E5 7.99E5 1.26E9

• • Nb 95 3.44E5 1.91E5 1.05E5 1.85E5 8. 16EB Mo 99 5.64E6 1.08E6 1.29E7 1.01E7 I 131 7 68E7 1 07ES 5.78E7 3.14E10 1.85ES 2. 13E7 I 133 1.93E6 3.27E6 9.98E5 4.57EB 5.74E6 2.48E6 Cs 134 7,10E9 1.67ELO 7 75E9 5.31E9 2 03E9 2.0BEB Cs 137 1.01KLO 1.35ELO 4.69E9 4.59E9 1 78E9 1.92EB Ba 140 1.38ES 1.69E5 8.9iE6 5.74E4 1 14E5 2.13KB

• • La QO 1.69E4 8.32E3 2.21E3 4.78E8 T

Ce 34L 2.83E5 1 89E5 2.17E4 8.89E4 5 40KB Ce 144 5.27E7 2 18E7 2.83E6 1.30E7 1.33 E10

<<mrealyr per uCilm3

<<<<Daughter Decay Product. hctivity level and effective half life assumed to equal parent nuclide.

TABLE 3-21 R VALUES - VEGETATION - ADULT m

2

~em/yr i pCi/sec NUCLIDE bONE LIVER T. BODY THYROID KIDNEY LUNG GZ-LLI

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

• C 14 8.97E5 1.79E5 1.79E5 1.79E5 1.79E5 1.79E5 1.79E5 Cr 51 4.64E4 2.77E4 1.02E4 6.15E4 1.17E7 Mn 54 3.13E8 5.97E7 9.31E7 9.58ES Fe 59 1.26ES 2.96ES 1.13ES 8.27E7 1.02E9 Co 58 3.0SE7 6.90E7 6.24ES Co 60 1.67E8 3.69E8 3.14E9 Zn 65 3 17ES 1.01E9 4.56ES 6.75E8 6.36ES Sr 89 9.96E9 2.86E8 1.60E9 Sr 90 6.05KLl 1.48E11 1.75E10 Zr 95 1.18E6 3.77E5 2.55E5 5.92E5 1.20E9

• • Nb 95 2.41E5 1.34E5 7.20E4 1.32E5'o 8.13ES 99 6.14E6 1.17E6 1.39E7 1 ~42E7 I 131 8.07E7 1.15ES 6.61E7 3.78E10 1.98E8 3.05E7 I 133 2.08E6 3.61E6 1.10E6 5.31ES 6.30E6 3.25E6 Cs 134 4.67E9 l.ilE10 9.08E9 3.59E9 1.19E9 1.94E8 Cs 137 6.36E9 8.70E9 5.70E9 2.95E9 9.81ES 1.68ES Ba 140 1 29E8 1 61E5 8.42E6 5.49E4 9.25E4 2.65ES eeLa ~ 1o58E4 7.93E3 2.11E3 5.86ES Ce 1CU 1 97E5 1 33E5 1.51E4 6 19E4 5. 09E8 Ce 144 3.29E7 1 38E7 1.77E6 8.16E6 1.11E10 emrem/yr per uCi/m3

• eDaughter Decay product. A,ctivity level and effective half life assumed to equal parent nuclide.

ThBLE 3-22 DISPERSION PARAMETERS hT CONTROLLING LOChTIONS*

I/I/Sc ccd D Vd(DSS VENT - DIRECTION DISSSSCS (c) S/tt (sec/adD n~/(e 1)

Site Boundary+** 1,600 2c00 E>>6 2. 10E-9 Inhalation and Ground E (104') 1,800 1.42E-7 2. 90E-9 Plane Cow Milk ESE (130') 4,300 4c llE-8 4.73E-10 Goat Milk<+ E (89') 12,500 1.75E-8 1.33E-10 Meat hnimal E (U.4 ) 2,600 1.17E-7 1.86E-9 Vegetation E (96') 2,900 1.04E-7 1.50E-9 S SSCK Sit@

Boundary*** 1) 600 Inhalation 4.50'.48E-9 6.00'.34E-9 and Ground E (109') 1,700 Plane Cow Milk ESE (135 ) 4,200 lc05EW 3.64E-10 Goat Milkee E (94 ) 12,500 1.80E-8 1.84E-10 Meat hnisa1 E (U.4') 2,500 1.13' 1.15E-9 Vegetation (96') 2,800 1 38E-S . 9 42E-10 NOIX: Inhalation and Ground Plane are annual average values. Others ace gracing season only.

ex/Q aug.D/Q values from NMP-2 ER-OLS.

snd D/Q froa C.T. Main Data Report dated Noveaber 1985.

• ++ . D/Q fry NMP-2 FESs NUREG-1085s May 1985.

SOS 5

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~ ~ utile'<<Salts lao>else GASEOUS RADIATION MONITOAINQ NIAGARA MOHAVAS POWER COAPOAAIION NINE MILE POINT-UNIT 2 FN4AL SAFETY ANALYSIS AEPOIIT AMENDMENT23 DECEMBEFI IQI i,

PARTCLLAYE YOOWE NOBLE GAS COLLECT KTH COLLECTIOH MEASUREMENT STATION STATION STAT KW4 FLYER FLYER C

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HOST COMPUTER 8

FIGURE 3-6 BLOCK DIAGRAM TYPICAL GASEOUS EFFLUENT MONITORING SYSTEM NIAGARA MOHAWK POWER CORPORATION NINE MlLE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

4,0 URhNIUM EUEL CYCLE The "Uranium Fuel Cycle" is defined in 40 CER Part 190.02 (b) as

, followe-

"Uranium fuel cycle means the operations of milling of uraaium f

chemical conversion o uranium > isotopic enrichment o f 're, uranium, fabrication of uranium fuel, generation of electricity by a light~atermooled auclear power pleat using uranium fuel aad reprocessing of spent uranium fuel> to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but ezcludes mining operations, operations at vaste disposal sites y transportation of aay radioactive material in support of these operations, and the reuse of recovered non~ranium special nuclear and by-product materials from thc cycle."

Section 3/4.11.4 of the Technical Specifications requires that vhen the calculated doses associated vith the efflueat releases exceed twice the applicablc quarter or annual limits, the licensee shall evaluate the calendar year doses and, if required, submit a Special Rcport to the NRC aad limit subsequent releases such that the dose commitment to a real individual from aU. uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except the thyroid, which is limited to 75 mrem). This report is to demonstrate that radiation ezposures to all real individuals from all uranium fuel cycle sources (includiag all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190. If releases that result in doses exceeding the 40'CER 190 limits have occurred, then a variance from the NRC to permit such releases vill be requested and reduce subsequent releases.

if possible, actioa vill be taken to The report to the NRC shall contain:

Identification of all uranium fuel cycle facilitics or operations vithin 5 miles of the nuclear power reactor units at the site> that contribute to the annual dose of the maximum exposed member of the public.

2) Idcntificatioa of thc mazimum exposed member oi the public aad a determination of thc total annual dose to this person from all existing pathveys and sources of radioactive cffluent s and direct radiation.

The total body ead organ doses resulting from radioactive material in liqutl offlueats from Nine Mile Point Unit 2 will bc summed vith the doeei resulting from the releases of aoble gases, radioiodines, and particulates. The direct dose components vill also be determined by cithcr calculation or actual measuremcnt. h,ctual measurements utilize environmental TLD dosimetry. Calculated measurements will vill utilize engineering calculatioas to determine a pro]ected direct dose component. Ia the event calculations are used, the methodology be detailed es required in Section 6.9.1 8 of the Technical vill Specifications. The doses from Nine Mile Point Unit 2 will be added to the doses to the mazimam.exposed individual that are contributed from other uranium fuel cycle operations vithin 5 miles of the site ~

~9

4.0 (Cont'd)

. 'or the purpose of calculating doses, tho results of tho garjronmental Eonitoring Program may be included to pcovido more eogiaed estimates of doses to a real maximum exposed individual.

Estimated doses, as calculated from statioa offluonts, may be replaced by doses calculated from actual eaviconmental sample results.

4.1 Evaluation of Doses From Liquid Effluents For the evaluation of doses to real members of the public from liquid ef fluents, the fish consumption aad shoreliae sediment ground dose vill be considerod. Since tho doses from other aquatic pathways aro insignificaat, fish consumption and shoreline sediment ac'e the only two pathways that vill be considered. The dose associated with fish consumption may be calculated using effluent data and Regulatory Guide 1.109 methodology oc by calculating a dose to man based on actual fish sample analysis data. The -doso associated with shoreline sediment is based on the assumpt ion that the shorelino would be atilixed as a recreational aroa. This dose may be derived from liquid effluent data and Regulatory Cuide 1.109 methodology oc froa actual shoreline sediment samplo analysis data.

Equations used to evaluate fish and shoreline sediment samples are based on Regulatocy Cuide 1.109 methodology. Because of tho sample medium type and the half-lives of the radionuclides histocically observed, the decay corrected portioas of the equations ac ~ deleted.

This does not reduce the coaservatism of the calculated dosos but increases the simplicity from aa ovaluation point. of view.

The dose from fish sample media is calculated as:

(1) Rwb ~ Xi fCif x u x 1000 x Diwb x f)

%let o:

The total dose to the whole body of an adult in mrem per yeac The coaceatratioa of radionuclido i ia fish samples ia pCi/gram Tho coasumption cato of fish foc an adult (21 kg poc yoar) 1OIO ~ Crams per kilogram The dose factor for c'adioauclide i for the whole body of an

.adult (R.C 1.109, Table E-11)

Tho fractional poctioa of the yeac ovec which tho dose is applicable.

(2) Rl Xi fCif x y x 1000 x Dil x f]

-90

Where:

Cif ~

The total dose to the liver of organ) in mrem per year The concentration pCi/gram of radionuclide an adult i

(mazimum in fish samples exposed in l

y ~ The consumption rate of fish for an adult (21 kg per year) 1000 ~ Grams per kilogram Di1 a The dose factor for radionuclide i for the liver of an adult (R.C. Table E-ll) f ~ The fractional portion of the year over which the dose is applicable.

The dose from shoreline sediment sample media is calculated as:

a Xi [Cis z y x 40,000 z 0.3 x Diwb z f]

and Xi (Cis z y x 40,000 z 0.3 x Disk x f Where:

The total dose to the whole body of a teenager or adult (maximum exposed age group) in mrem per year The total dose to the skin of a teenager or adult (maximum exposed,age group) in mrem per year Cis The concentration oi radionuclide i in shoreline sediment in pCilgrsm The usage factor. This is assumed as 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year by}

a teenager or adult 4 40 F 000~ The product of the assumed density of shoreline sediment (40 kilogram per square meter to a depth of 2.5 cm) times the number of grams per kilogram 0.3 s The shore width factor for a lake The dose factor for radionuclide i for the total body (R.C.

1.109, Table E-6)

Disk The dose factor for radionuclide i for the skin (R.C.

1.109, Table E-6)

The fractional portion of the year over which the dose is applicable MOOR: Because of the nature of the receptor location

- and the extensive fishing in the area, the critical individual may be a teenager or an adult.

-91

4.2 Evaluation of Doses Prom Gaseous Effluents Por the evaluation of doses to real members of the public from gaseous effluenty > the pathways contained in section 3.0 of the ODCM wi11. be considered and include ground deposition, inhalation, cows milk,. goats milk, meat, and food products (vegetation) ~ However, any updated field data may be utilized that concerns locations of real individuals, real time meteorological data, location of critical zeceptors, etc. Data from the most recent census and sample location surveys should be utilized. Doses may also be calculated from actual environmental sample media, as available. Environmental sample media data such as TLD, air sample, milk sample and vegetable (food crop) sample data may be utiU.zed in lieu of effluent calculational data.

Doses to members of the public from the pathways contained in ODCH section 3.0 as a result of gaseous effluents will be calculated using the dose factors of Regulatory Guide 1.109 or the methodology of the ODCH, as applicable. Doses calculated from environmental sample media will utilize the methodologies found in Regulatory Guide 1.109.

4,3 Evaluation of Doses Prom Direct Radiation Section 3.11.4.a of the Technical Specifications requires that the dose contribution as a result of direct radiation be considered when evaluating whether the dose limitations of 40 CFR 190 have been exceeded. Direct radiation doses as a result of the reactor, turbine and radwaste buildings and outside radioactive storage tanks (as applicable) may be evaluated by engineering calculations or by evaluating environmental TLD results at critical receptor locations site boundary or other special interest locations. For the evaluation of direct radiation doses utilizing environmental TLDs, the critical receptor in question, such as the critical residence, etc., will be compared to the control locations- The comparison involves the difference in environmental TLD results between the receptor location and the average control location result.

Doses to Members of the Public Within the Site Boundary.

Section 6.9.1.8 of the Nine Sile Point Unit 2 Technical Specifications requires that the Samiannual Radioactive Effluent Release Report include an assessment of the radiation doses fzom radioactive liquid and gaseous offluents to members of the public due to their activities inside the site boundary as defined by Figure 5.1.3 of the specifications. h member of the public, as defined by the Technical Specifications, would be repz'esented by an individual who visits the sites'nergy Information Center for the purpose of observing the educational displays or for picnicing and associated activities ~

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

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

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

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

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

-93

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

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

r MOTE: The following equation is adapted from equations C-3 and CA of Regulatory Guide 1.109. Since many of the factors are in units of pCi/m , m3/sec., etc., and since the radionuclide decay expressions have been deleted because of the short distance to the receptor location, the equation presented here is not identical to the Regulatory Cuide equations.

~ X i [Cip Z/Q DFL igaRat]

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

Cim The average concentration in the stack or vent release of radionuclide i in pCi/m for the period in question.

p s Unit 2 average stack or vent flowrate in m3/sec.

The plume dispersion parameter for a location approximately 0.50 miles west of QP-2 <The plume dispersion parameters are 9.6E-Ol <stack) and 2.8B-06 <vent> and were obtained from the C.T. Min five year average annual Z/Q tables. Jl Z/Q value based on real time meteorology may also be utilized for the period in question, if desired. The vent VQ <ground level> is ten times the listed 0.50 mile Z/Q because the vent is approximately 0.3 miles from the receptor location. The stack (elevated) Z/Q is conservative when based on 0.50 miles because of the close proximity of the stack and the receptor location.

a the inhalation dose factor for radionuclide i, the lung j, and adult age group a in ma'am per pCi found on Table E-7 of Regulatory Cuide 1.109.

annual air intake for individuals in age group a in 53 per year (this value is 8 000 sL3 per year and was obtained from Table B-5 of Regulatory Guide 1.109).

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

-Sa

(Cont'd)

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

The direct radiation gamma dose pathway includes any gasssa doses from an overhead plume, submersion in the plume, possible radi ati on from the facility and ground plane dose (deposition) . This general pathway will be evaluated by average environmental TLD readings. ht will be utilixed 0,

least two environmental TLDs at one location in the approximate area where fishing occurs. The TLDs will be placed in the field on approximately the beginning of each calendar quarter and removed on approximately the end of each calendar quarter (quarter 2, 3, and 4).

The average TLD readings will be adjusted by the average control TLD readings. This is accomplished by subtracting the average quarterly control TLD value from the average fishing location TLD value. The applicable quarterly control TLD values will be utilixed af ter adjusting for the appropriate time period (as applicable). Zn the

.event of loss or theft of the TLDs, results from a TLD or TLDs in the area may be utilixed.

-95 0

5.0 ROHMENTAL MONITORINC PROCRh8 5.1 Sampling Stations The current sampling locations are specified in Table 5-1 and Figures 5.1-1, 5.1-2. The meteorological tower location is shown on Figure 5.1-1. The location is shown is TLD location Oil. The Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New York Power Authority, the owners and operators of the Nine Mile Point Uni ts 1 and 2 and the James L.Fitxpatrick Nuclear Power Plants, respectively. Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from both units. The environmental sampling location coordinates shown on Table 5-1 are based on the NMP-2 reactor centerline.

The average dispersion and deposition parameters for the three units have been calculated for a 5 year period, 1978 through 1982. The calculated dispersion or deposition parameters will be compared to the results of the annual land use census.

a milk sampling Zf it is determined that location exists at a location that yields a

~

significantly higher (e.g. SO%) calculated D/Q rate, the new milk sampling location will be added to the monitoring program within 30 days. Zf a new location is added, the old location that yields the lowest calculated D/Q may be dropped from the program after October 31 of that year.

5.2 Interlaboratory Comparison Program analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of i approved or sponsored Znterlaboratory Comparison Program, such as the Commission Eph Crosscheck Program. Participation shall be only for those media,

~ .g., air, milk, water, etc., that are included in the Nine Mile Point 'nvironmental Moni toring Program and for which cross check samples are available. ka attempt will be made to obtain a QC sample]

to program sample ratio of 5% or better. The Quality Control sample I shall be reported in the Annual Radiological Environmental (

'esults Operating Report so that the Coseaission staff may evaluate the results.

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

~ gross beta in air particulate filters

~ gassaa emitters in air particulate filters

~ I-131 in milk

~ ganssa <<mitters in milk

~ gasssa emitters in food product

~ gassna emitters in water

~ tritium in water

~ I-131 in water .

-96

5.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measuzements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by the Technical Specifications aze based on ANSI Standard N545, section 4.3. TLDs, are defined as phosphors packaged for field use.

In regard to the detection capabilities for thezmoluminescent dosimeters, only one determination is required to evaluate the above capabilities per type of TLD. Puzthezmoze, the above capabilities may be determined by the vendor who supplies the TLDs. Required detection capabilities aze as follows.

5.3. 1 Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. The responses obtained shall have a relative standard deviation of less than 7.5Z. A total of at least 5 TLDs shall be evaluated.

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

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

5.3.4 Energy dependence shall be evaluated by the response of TLDs to photons for several energies between approximately 30 keV and 3 MeV.

The response shall not diffez from that obtained with the calibration source by more than 25Z for photons with energies greater than 80 keV and shall not be enhanced by more than a factor of two foz photons with energies less than 80 keV. A total of at least 8 TLDs shall be evaluated'.3.5 The directional dependence of the TLD response shall be determined by coayasing the response of the TLD exposed in the routine orientation with respect to the calibration source with the response obtained for different orientations'o accomplish this, the TLD shall be rotated through at least two perpendicular planes. The response averaged over all directions shall not differ from the response obtained in the standard calibration position by more than 10Z. A total of at least 4 TLDs shall be evaluated-

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

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

The TLDs shall be ezposed under two conditions! (1) packaged in a thin, sealed plastic bag, and (2) packaged in a thin, sealed plastic bag with sufficient water to yield observable moisture throughout the field cycle. The TLD or phosphor, as appropriate, shall be dried before readout. The response of the TLD exposed in the plastic bag containing water shall not differ from that ezposed in the regular plastic bag by more than 10X. A total of at least 4 TLDs shall be evaluated for each condition.

Self irradiation shall be determined by placing TLDs for a period equal to the field cycle in an area where the ezposure rate is less than 10 uR/hr and the ezposure during the field cycle is known necessary, corrections shall be applied for the dependence of If exposure interpretation on the length of the field cycle (ANSI N545>

section 4.3.3) ~ The average ezposure inferred from the responses of the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an ezposure rate of 10 uR/hr during the field cycle. A total of at least 3 TLDs shall be evaluated.

OOX234LL NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAMPUNG LOCATIONS TABLE 5.1 Type of *Map t tl v r Radioiodine and Nine Mile Point Road 1.8miI 884 E Particulates (air) North (R-1)

Radioiodine and Co. Rt. 29 & Lake Road (R-2) 1.1 mi 5 1044 ESE Particulates (air)

Radioiodine and Particulates (air)

Co. Rt. 29 (R-3) 1.5 mi I 1324 SE Radioiodine and Village of Lycoming, NY (RA) 1 8 mi O 1434 SE Particulates (air)

Radioiodine and Particulates (air)

Montario Point Road (R-5) 16.4 mi I 424 NE Direct Radiation (TLD) North Shoreline Area (75) 0.1 m) O 54 N Direct Radiation (TLD) North Shoreline Area (76) 0.1 mi O 254 NNE Direct Radiation (TLD) North Shoreline Area (77) 0.2mi @454 NE Direct Radiation (TLD) North Shoreline Area (23) 0.8 mi I 704 ENE Direct Radiation (TLD) 10 JAP East Boundary (78) 1.0 mi O 904 E Direct Radiation (TLD) Rt. 29 (79) 1.1 mi O 1154 ESE Direct Radiation (TLD) 12 Rt. 29 (80) 1,4mi O 1334 SE Direct Radiation (TLD)'irect Miner Road (81) 1.6 mi I 1594 SSE Radiation (TLD) 14 Miner Road (82) 1.6 mi O 1814 S Direct Radiation (TLD) Lakeview Road (83) 1.2 mi O 2004 SSW Direct Radiation (TLD) 16 Lakeview Road (84) 1.1 mi O 2254 SW Direct Radlatieo (TLD) 17 Site Meteorological Tower (7) 0.7 mi O 2504 WSW Direct Radiation (TLD) 18 Energy Information Center (18) 0.4 mi I 2654 W

• Map ~ See Rgures 5.1-1 and 5.1<

99

002234LL NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAMPUNG LOCATIONS TABLE 5.1 (Continued)

Type of I

Direct Radiation (TLD) 19 North Shoreline (85) 0.2 mi I 2944 WNW Direct Radiation (TLD) 20 North Shoreline (86) 0.1 mi @ 315 O NW Direct Radiation (TLD) 21 North Shoreline (87) 0.1 mi I 341 o NNW Direct Radiation (TLD) 22 Hickory Grove (88) 4.5 mi 9 97o E Direct Radiation (TLD) 23 Leavitt Road (89) 4.1 mi I 111'SE Direct Radiation (TLD) 24 Rt, 104 (90) 4.2 mi I 135'E Direct Radiation (TLD) 25 Rt. 51A (91) 4.8 mi 9 1564 SSE Direct Radiation (TLD) 26 Maiden Lane Road (92) 4.4 mi@ 1834 S Direct Radiation (TLD) 27 Co. Rt. 53 (93) 4.4mi I 2054 SSW Direct Radiation (TLD) 28 Co. Rt. 1 (94) 4.7 mi 5 2234 SW Direct Radiation (TLD) 29 Lake Shoreline (95) 4.1 mi I 2374 WSW Direct Radiation (TLD) 30 Phoenix, NY Control (49) 19.8 mi I 1634 S Direct Radiation (TLD) 31 S. W. Oswego, Control (14) 12.6 mi I 2264 SW Direct Radiation (TLD) 32 Scriba, NY (96) 3.6 mi I 199o SSW Direct Radiation (TLD). 33 Alcan Aluminum, Rt. 1A (58) 3.1 mi I 220o SW Direct Radiation (TLD) 34 Lycoming, NY (97) 1.8mi @143o SE Direct Radiation (TLD) 35 New Haven, NY (56) 5.3 mi@ 1234 ESE Direct Radiation (TLD) 36 W. Boundary, Bible Camp (15) 0.9 mi I 2374 WSW Direct Radlatfoit (TLD) 37 Lake Road (98) 1.2mi I 101o E Surface Water 38 OSS Inlet Canal (NA) 7.6 mi I 2354 SW Surface Water 39 JAFNPP Inlet Canal (NA) 0.5 mi I 70O ENE (NA) ~ Not applicable:

• Map ~ See Rgures 5.1-1 and 5.T-2 100

002234U. NINE MlLE POINT NUCLEAR STATION RADIOLOGICALEhWRONMENTAL MONITORING PROGRAM 0

SAMPUNG LOCATIONS TABLE 5.1 (Continued)

Type of I n V Shoreline Sediment 40 Sunset Bay Shoreline (NA) 1.5miI 80o E Fish NMP Site Discharge Area (NA) 0.3 mi@315o NW Fish 42 NMP Site Discharge Area (NA) 0.6 mi I (and/or) 554 NE Fish 43 Oswego Harbor Area (NA) 6.2 mi O 235o SW Milk Location F50 8.2 mi 9 934 E Milk 45 Milk Location iii7 5.5 mi@1074 ESE Milk 46 Milk Location f16 5.9mi O190o S Milk 47 Milk Location f65 17.0 mi I 2204 SW Milk 64 Milk Location 455 9.0mi I 95O E Milk 65 Milk Location if60 9.5 mi I 904 E Milk 66 Milk Location f4 7.8mi I 113~ESE Food Product 48 Produce Location 46 (NA) 'Bergenstock) 1.9 mi I 141'E Food Product 49 Produce Location Pl 1.7mI@ 96o E (Culeton) (NA)

Food Product 50 Produce Location 4'2 (NA) 'Vitullo) 1.9 mi I 101 4 E Food Product Produce Location $ 5~~

(C.S, Parkhurst) (NA) 1.5 mi I 114'SE Food Product 52 Produce Location f3 (C. Narewski) (NA) 1.6 mi I 844 E Food Product " Produce Location 44 (P. Parkhurst) (NA) 2.1 mi I 110o ESE Food Product (CR) 54 Produce Location f7~~

(Mc Millen) (NA) 15.0 mi I 2234 SW

• Map ~ See S.l-l and 5.1-2

~ Food ProductFigures Samples need not necessarily be collected from all Hated Iocathns. Collected samples will be of the:highest calculated site average D/Q.

(NA) ~ Not applicable CR ~ Control Result (location) 101

002234LL NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAMPUNG LOCATIONS TABLE 5.1 (Continued)

Type of

• Map Food Product (CR) Produce Location ¹8 12.6 mi O 2254 SW (Denman) (NA)

Food Product 56 Produce Location ¹9 1.6 mi@ 1714 S (O'onnor) (NA)

Food Product 57 Produce Location ¹10 2.2 mi O 1234 ESE (C. Lawton) (NA)

Food Product 58 Produce Location ¹11 (C, R. Parkhurst) (NA) 2.0mi I 1124 ESE Food Product 59 Produce Location (Barton) (NA)

¹12 1.9 mi I 115'SE Food Product (CR) 60 Produce Location (Flack) (NA)

¹13 15.6 mi I 2254 SW Food Product 61 Produce Location ¹14 1.9 mi O 954 E (Koeneke) (NA)

Food Product 62 Produce Location (Whaley) (NA)

¹15 1.7 mi I 1364 SE Food Product Produce Location ¹1 6 (Murray) (NA) 1.2 mi I 2074 SSW

.+Map a See Rgures 5.1-1 and 5.1-2

++ Food Product Samples need not necessarily be collected from all listed locations. Collected samples wiII be of the highest calculated site average 0/Q.

(NA) ~ Not applicable:

CR ~ Control Result (location)-

102

6.0 DISCUSSION OF TECHNICAL SPECIFICATION REFERENCES Section 3. 12. 1 o f the Techaical Specifications, Table 3. 12-1

~

(Radiological Environmental Moaitoring Pxogram) refercaces several footaotes to discussions in the ODCM. The following ODCM discussions, are aa attempt, oa the part of thc Commission snd the licensee, to furthez clazify several of the zequirements of Table 3.12-1.

6.1 Table 3.12-1, Footnote g Rcpreseatative composite sample aliquots are obtained from sampling equipment that will obtain sample aliquots over short intervals'n ezample of a short interval is once per hour. Iatervals of less than one hour are also acceptable. Ia addition, in order to be represeatative, the aliquot volume must be consistent over the requixed composite period. Su~ntervals may be designed for sample collection as long as each su~nterval's contribution to the final composite volume is pzoportional to thc duration of the su~nterval. For ezample, a- monthly composite may consist of equal coatributions from four veekly suMntezvals, plus a contributioa 3/7 of that volume from a fifth weekly sub-interval, to be representative of the monthly composite period.

6.2 Table 3.12-1, Footnote h Grouad water in the vicinity of thc site is not currently a drinkiag vatez pathway. The hydraulic gradient and rechazge properties in the viciaity of the site currently cause ground vater to flov in a northerly direction to Lake Oatario. The results of such hydraulic gradient and zechargc propezty studies are documeated in the NMP"2 FSAR. Thus, any'xound water utilized for drinking vater or irzigation purposes is aot affected by the site and therefore sampliag of grouad vater is not curzeatly requixcd.

In the event of significant seismic activity, however, thc hydraulic gzadicat and zech'azge properties in the vicinity of the site may change. Ia this case it is possible that gzound water utilized for drinking water or irrigation purposes may have a poteatial to become contaminated. Thus, in the cvcat of a significant seismic occurrence, samples from oae or tvo sources vill be obtained as noted in Table 3.12-1, Section 3.b of the Technical Specifications until hydraulic investigations conclude that the previous hydzauli c gradient and recharge property studies are unchaagcd. Investigations that conclude that thc hydraulic gradient and recharge properties have changed snd that there is a poteatial for coatamiaation of groun4 water used for drinking vater aad/or izrigatioa vill result in contkauiag aay applicable ground water sampling.

6.3 Table 3.12-1, footnote i Currently, there are no drinking water sources (from Lake Ontario) that 'can 'be- significantly affected by the site under normal operating

.conditions. The closest drinking water source is neaz the City of Oswego. This source is located in an "upmurrent" direction foi the ma)ority of the time based on local Lake Ontario currents. In addition, the source is significantly affected by the "plume" from the Oswego River which enters Lake Ontaxio at a point between the site and the source. The source is located appx'oximately eight miles to the west of the site.

Other drinking water sources within 50 miles of the site range from 20 to 50 miles. These sources are beyond any significant influence of the site.

In the event a drinking water source (other than the source near the City of Oswego) is established within 10 miles of the site (current miles in contrast to air miles), then the new source will be evaluated for any significant dose effects based on dilution cx'iteria. Sources found 'to be significantly affected by the site will be added to the Radiological Environmental Monitoring program required by Table 3.12-1, section 3-C of the Technical Specifications.

6.4 Table 3.12-1, footnote 1 Considering the shoreline topography and land development within 10 miles of the site, and the dilution factors beyond 10 miles, only ma)or irrigation prospects where food px'oducts are irrigated with Lake Ontario water need be considered for specification 4.C of Table 3+12-1.

Ma)or irrigation pro5ects are defined as agricultural pzo]ects where food products fox'uman consumption are grown and izrigation water from Lake Ontario is used fzequently. Ma]or irrigation pro5ects are not considered to be small private gardens located on the lake shore at seamer zesidences ox yeax-round residences where occasional use of lake w'ater during times of draught has been observed. Major pro]ects include pumps and piping systems, either permanent or temporary, that supply lake water to agricultural pro]ects on a frequent basis.

In frequent use of lake watex is not considered to have a significant effect on food products. Therefore, such a situation does not constitute a ma]or izrigation pzo)ect.

-Currently, no ma]or irrigation pzo]ects exist within 10 miles of the

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~4ar TECHNIChL SPECIFICJLTIONS FIGURE 5.1.3-1. SITE SOUNDARIES NINE NILE POINT UNIT 2 107

NOTES TO FIQRK 5.1.3-1 (a) RfPl Stack (height is 350')

(b) NMP2 Stack (height is 430')

(c) JAFNPP Stack (height is 385')

(d) NMP1 Radioactive Liquid Discharge (Lake Ontario, bottom)

(e) NMP2 Radioactive Liquid Discharge (Lake Ontario, bottom)

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

(g) Site Boundary (h) Lake Ontario Shoreline (i) Meteorological Tover (j) Training Center (k! Energy Information Canter Additional Information:

- NMP2 Reactor Building Vent is located 187 feet above ground level

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

" JAFNPP Radvaste Building Vent is 112 feet above ground level

- ThE Energy Information Center and adjoining Picnic area ar' USUSTRICTED AREAS vithin the SITE BORSART that are accessible to MIKHKS OF THE PUBLIC

- Lake Road, a private road, is an UNRESPECTED AREA vithin the SITE BOUNIRQVl accessible to NKKRS OF THE PUBLIC NINE MILE POINT UNIT 2 108