ML17056C297
| ML17056C297 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1992 |
| From: | Terry C NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17056C296 | List: |
| References | |
| PROC-920630, NUDOCS 9303110045 | |
| Download: ML17056C297 (122) | |
Text
V.P. Nuclear Engineering C. D. Terry
~+~IN 7 v
'v 6 30 2
iii,12-14,17,18,28-31,34, 37-53,55-58,60-82,87-89,92 15 54 19 90-91,93-103 20-27,83-86 I-ll 1-11,16,32-33,35-36,59 100-102,106 May 1986 May 1987 May 1987 (TCN-I)
June 1987 g CN-2)
February 1988 April 1988 November 1988 February 1990 June 1992 THIS PROCEDURE NOT TO BE USED AFTER JllNF. 1qq4 SUBJECI'TO PEMODIC REVIEW.
93031i0045 930301 PDR ADOCK 05000410 R
.~ ~
TABLE OF CONTENTS SECTION or TABLE 1.0 SUBJECT INTRODUCTION TS SECTION or TABLE APPLICABLE PROCEDURE PAGE 2.0 2.1 2.1.1 2.1.2 2.1.2.1 2.1.2.2 2.1.2.3 2.1.3 2.1.3.1 2.1.3.2 2.2 2.3 3.11.1.1 3.3.7.9
- 3. 11.1. 1 4.11.1.1.2 3.11.1.2 3.11.1.3 4.11.1.2 4.11.1.3.1 LIQUID EFFLUENTS Liquid Effluent Monitor Alarm Setpoints Basis Setpoint Determination Methodology Liquid Radwaste Effluent Radiation Alarm Setpoint Contaminated Dilution Water Radwaste Effluent Monitor Alarm Setpoint Calculations Service Water and Cooling Tower Blowdown Effluent Radiation Alarm Setpoint Discussion Liquid Radwaste Effluent Service Water and Cooling Tower Blowdown Liquid Effluent Concentration Calculation Liquid Effluent Dose Calculation N/A
'/A N/A N/h N2-CSP-4V N/A N2-CSP-13 hpp.
D N/h N/A N2-CSP-4V N2-CSPWV 2
2 2
2 2<<3 5
6-9 10-12 12 13-14 2.5 2,6 Liquid Effluent Dose Factor Derivation - hit Liquid Effluent Sampling Representativeness Liquid Radwaste System Operation 4.11.1-1 note b
3.11.1.3 N2-CSP-4V 14-15 15-16 16-17 Table 2-1 Table 2-2 Liquid Effluent Detector
Response
hit Liquid Effluent Dose Factor Figure 2-1 Liquid Radwaste Treatment System thru 2-8 Flow Diagrams'igure 2-9 Liquid Radiation Monitoring Figure 2-10 Off-line Liquid Monitor 3.11.1.3 3.11.3 18 19 20-27
{
28
~
29, 3.0 3.1 3.1.1 3.1.2 3.1.2.1 3.1.2.2 3.1.2.3 3.1.3 3.1.3.1 3.1.3.2 3.1.3.3 3 ~ 2
.2.1 3.2.2 GASEOUS EFFLUENTS Gaseous Effluent Monitor Alarm Setpoints Basis Setpoint Determination Methodology Stack Noble Gas Radiation Alarm Setpoint Vent Sgrle Gas Radiation Alarm Setpoint Offgas Pretreatment Radiation Alarm Setpoint Discussion Stack Effluent Vent Effluent Offgas Process Gaseous Effluent Dose Rate Calculation Total Body Dose Rate Due to Noble Gases Skin Dose Rate Due to Noble Gases 3.11.2.1 3.3.7.10 3.11.2.1 3.11.2.l.a 4.11.2.1.1 3.11.2.1.a
- 4. 11.2.1. 1 N2-CSP-13 hpp.
D N2-CSP-13 'hpp.
D N2-CSP-7V N2-CSP-7V N2-CSP-7V 30 30 30 30 30-31 31-32 32 33 34 35 36 37 37-38 38-39
I
TABLE OF CONTENTS SECTION or TABLE 3.2.3 3.3 3.3.1 3.3.2 3.3.3 SUBJECT Organ Dose Rate Due to I-131, I-133, Tritium and Particulates <<ith half-lives greater than 8 days Caseous Effluent Dose Calculation Methodology Gamma Air Dose Due to Noble Gases Beta hir Dose Due to Noble Cases Organ Dose Due to I-131, I-133, Tritium and Particulates <<ith half-lives greater than 8 days.
TS SECTION or TABLE 3.11.2.1.b 4.11.2.1.2 3.11.2.2 3.11.2.3 3.11. 2. 5 3.11.2.2.a 4,11.2.2 3.11.2.2.b 3.11.2.3 3.11.2.5 4.11.2.3 4.11.2.5.1 APPLICABLE PROCEDURE N2-CSP-7V N2-CSP-7V N2-CSP-7V N2-CSP-7V N2-CSP-7V PAGE '
39-41
'1-42 t,
(
42 43 43-45
~
3.4 3.4.1 3.4.2 3.4.3 4.4 3'.5 3.4.6 3.5 3.6 3.7 3.8 3.11.2.4 3.11.2.5 Gaseous Effluent Dose Factor Definition and Derivation Bi-Plume Shine Gamma hir Dose Factor Vi-Plume Shine Total Body Dose Factor Ki, Li, Mi and Ni-Immersion Dose Factors Pi-Iodine, Particulate and Tritium Organ Dose Rate Factors Ri-Iodine, Particulate and Tritium Organ Dose Factors X/Q and Nr-Dispersion Factors for Dose Rate Ms and Mv-Dispersion Factors for Dose Gaseous Effluent I-133 Estimation Vse of Concurrent Meteorological Data vs.
Historical Data Gaseous Rad<<aste Treatment System Operation Ventilation Exhaust Treatment System Operations N2~P-78Q 45 45<<47 47 47-51 51-57 59 I
59
(
I 59 I
1 I
60, Table 3-1 Table 3-2 Table 3-3 Table 34 Table 3-5 Table 3-6 Table 3-7 to 3-10 Table 3-11 Table 3-12 to 3-15 Table 3-16 to 3-18 Table 3-19 3-21 Offgas Noble Cas Detector Response Bi and Vi-Plume Shine Dose Factors Ki. Li, Mi and Ni-Zsssersion Dose Factors Pi-Cround Plane Dose Rate Factors Pi-Inhalation Dose Rate Factors Pi-Food (Co<< Milk) Dose Rate Factors Ri-Inhalation Dose Factors for Infant Child, Teen and hdult Ri-Ground Plane Dose Factors Ri-Co<<milk Ingestion Dose Factors for Infant, Child, Teen and Adult Ri-Co<<meat Ingestion Dose Factors for Child, Teen and Adult Ri-Vegetation Ingestion Dose Factors for Child, Teen and Adult 61 62
(
63 64 65 66 67-70 71 72-75 76-78 79-81
SECTION Figure 3-1 thru 3-3 Figure ~
Figure 3-5 Figure 34 4.0 4.1 4.2 4,4 5.0 5.1 5.2 X/Q, Wv and Ws-Dispersion Factors for Receptor Locations Gaseous Radwastc Treatment System How Diagrams Ventilation Exhaust Treatment System How Diagrams Gaseous Radiation Monitoring Gaseous Bfllucnt Monitoring System URANIUMFUEL CYCLE Evaluation ofDoses &am Liquid Efliucnts Evaluation of Doses hem Gaseous EIIlucnts Evaluation of Doses from Direct Radiation Doses to Members of the Public Within Site Boundary ENVIRONMENTALMONITORINGPROGRAM Sampling Stations CapabiTitics for Thcrmoluminciccnt Dosimctcrs Used for Environmental Mcasuremcnts TS SBCIION 3.11.2 4 3.11.29 3.11.4 4.11.4.1 4.11.4.1 4.11.4.2 6.9.1.8 3.12 4.12 3.12.1 4.12.1 4.129 QijjG 87 88 89 93 95 95 95 97 Table 5.1 6.0 6.1 6.2 6.4 Figure 5.1-1 Figure 5.1-2 Figure 5.ID-I Radiological Environmental Monitoring Program Sampling 3.12.1 Locations 4.12.1 Table 3.12-1 Note (a)
DISCUSSION OF TECHNICALSPECIFICATION REFEIKNCE Table 3.12-1, Note (g)
Table 3.12-1, Note (h)
Table 3.12-1, Note (i)
Table 3.12.1, Note (I)
Nine Mile Point On4itc Map Nine Mile Point Olf4itc Map Site Boundaries 105
~ ~ ~
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 2.1
- 2. l. 1 2.1.2 LIQUID EFFLUENTS Serv1ce Hater A
and B,
Cooling Tower Blowdown and the Liquid'adioactive-Haste Discharges comprise the Rad1oact1ve L1quid 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.
L1quid Effluent Honitor Alarm Setpoints Basis Techn1cal Spec1f 1 cat1on 3.
1 1. l. 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.
Setpoint Determinat1on Hethodology 2.1.2.1 Liquid Radwaste D1scharge Honitor Alarm Setpo1nts Normal Radwaste Discharge Hon1tor Setpo1nt Calculation:
Alarm Setpoint < [0.$'(F/f)'Z1(Cl'CF1)7/fZ1(C1/HPC1)7 + Background.
Nore:
Narm Setpoint 0.8 F
The Discharge Honitor Alarm Setpoint, cpm Safety Factor, unitless Nonradioact1ve dilution flow rate, gpm.
Service 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.
Ci Cji f
HPC1
Background
E1(C1*CF1)
Ei(C1/HPC1)
CR*E1C1 F/f'ater Flow ranges from 30,000 to 58,000 gpm.
Blowdown flow is typically 10,200 gpm.
Concentration of 1sotope 1 in Radwaste tank pr1or to dilut1on, pC1/ml Detector response for 1sotope 1, net cpm/F1/ml See Table 2-1 for a list of nom1nal values The perm) ssible Radwaste Effluent Flow rate, gpm Symbol to denote multiplication.
Concentrat1on limit for 1sotope 1 from 10CFR20 Append1x B, Table II, Column 2, F1/ml Detector response when sample chamber 1s filied with nonradioact1ve
- water, cpm The total detector response when exposed to the concentration of nuclides in the Radwaste
- tank, cpm 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)
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 follow1ng equation, with f limited as above.
Alarm Setpoint 0.8'Z1(C1*CF1)
Z 1 [Zs(Fs~C1 s) /(HPC1 <<Zs kFs l)l
+ Background Hhere:
Alarm Setpoint The D1scharge Hon1tor Alarm Setpoint, cpm 0.8 Fs C1'i s
CF1 HPC1
Background
Zl(C1 *CF1)
~ %
CSFs*C1 sl ZstFs3 Safety Factor, Unitless An Effluent flow rate for stream s, gpm Concentration of 1sotope 1 in Radwaste tank pr1or to d11ut1on, F1/ml Concentrat1on of isotope 1
1n Effluent stream s
Includ1ng the Radwaste Efi'luent tank und1luted, F1/ml Detector response for 1sotope 1, net cpm/pC1/ml See Table 2-1 for a list of nominal values Concentrat1on limit for isotope 1 from 10CFR20 Appendix B, Table II, Column 2, F1/ml The permissible Radwaste Effluent Flow rate, gpm Detector response when sample chamber 1s f1lled with nonradioact1ve water.
cpm The total detector response when exposed to the concentration of nucl1des in the Radwaste
- tank, cpm The total activity of nucl1de 1
1n all Effluent
- streams, pC1-gpm/ml 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 0.8 Cl CF1 HPCl
Background
El(C1*CFf)
El(C1/HPC1)
CR*Z1C1 2.1.3 Dfscussfon The Radiation Detector Alarm Setpofnt, cpm Safety Factor, unltless Concentration of isotope 1 as potential contaminant, pCf/ml Detector response for isotope 1, net cpm/pCf/ml See Table 2-1 for a list of nominal values Concentration limit for isotope I from 10CFR20 Appendix B, Table II, Column 2, pCf/ml Detector response when sample chamber fs filled with nonradloactlve
- water, cpm The total detector response when exposed to the concentration of nuclides in the potential contaminant, cpm The total fraction of the
- 10CFR20, Appendix B, Table II, Column 2 llmlt that ls ln the potential contaminant, unltless.
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.
2.1.3.1 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
[
'pectrometry equipment whose calibration ls traceable to NBS.
This 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 NAHE ACTIVITY CONCENTRATION pC1/ml 8
(C1 )
MPC F1/ml C
(HPC1)
FRACTION OF HPC (8/C)
D (C1 /HPC1 )
DETECTOR
RESPONSE
cpm/pCI/ml E
<CF1)
CPH TOTAL cpm F
(C1CF1)
K3 NA24 P32 CR51 MN54 MN56 FE55 FE59 C058 CO60 NI63 NI65 CU64 ZN65 BR83 BR84 SR89 SR90 SR91 SR92 Y91 Y92 Y93 ZR95 ZR97 N895 H099 TC99H RU103 RU105 RU106 AG110H TE129H TE131H 8.4E-3 1.7E-6 6.8E-S 2.0E-6 2.4E-S 3.2E-7 3.5E-7 1.0K-B 6.8E-B 1.4E-7 3.5E-10 1.8E-9 4.3E-6 6.8E-S 3.3E-S 8.9E-14 3.6E-S 2.4E-9 4.6E-7 7.6E-S 1.7E-B 4,6E-7 5.1E-7 2.7E-9 1.0E-9 2.7E-9 6.0E-7 1.2E-6 6.8E-9 6.8E-S 1.0E-13 3.5E-10 1.4E-S 2.4E-S 3E-3 3E-5 2E-5 2E-3 lE-4 1E-4 BE-4 5E-5 9E-5 3E-5 3E-5 1E-4 2E-4 lE-4 3E-6 3E-6 3E-7 5E-5 6E-5 3E-5 6E-5 3E-5 6E-5 2E-5 1E-4 4E-5 3E-3 BE-5 1E-4 1E-5 3E-3 2E-5 4E-5 2.8 5.7E-2 3.4E-3 1.03-3 2.4E-4 3.2E-3 4.3E-4
- 2. 1E-4 7.6E-4 4.7E-3 1.1E-S 1.8E-S 2.1E-2 6.8E-4 1.1E-2 1.2E-3 7.8E-3 9.3E-3 1.2E-3 5.7E-4 7.8E-3 1.7E-2 4.5E-S 5.2E-5 2.7E-5 1.6E-2 4.1E-4 8.5E-5 6.8E-4 1.0E-B 1.1E-7 7.0E-4 6.0E-4 8.42E7 1.2EB 8.63E7 1.14EB 1.65EB 1.12EB 7.8E3 1.22EB 8.17E7 2.47KB 2.05E7 8.35E7 8.5E7 2.32E7 2.32E7
- 1. 98E+0 3.9E+0 9.0E-1 7.8E+0 2.4E+1 5.7E+1 6.1E+0 4.2E+0 9.5 2.3E-l 2.4E-l 1.4E+1 2.BE+1 i
5 ISOTOPE ACTIVITY NAHE CONCENTRATION F1/ml A
.B'Ci )
MPC FRACTION OF HPC pC1/ml B/C C
D (HPC1)
(C1/MPCi)
DETECTOR CPH
RESPONSE
TOTAL cpm/12C1/ml cpm E
F (CF1)
(C1CF1)
TE132 I131 I132 I133 I'134 I135 CS134 CS136 CS137 CS138 BA140 LA142 CE141 CE143 CE144 PR143 ND147 H187 NP239 2.9E-9 1.4E-6 2.5E-7 1.2E-5 7.2E-10 3.8E-6 5.1E-6 3.3E-7 1.3E-6 8.4E-12 1.3E-7 3.2E-9 1.0E-S 7.6E-9 7.6E-9 1.4E-B 1.0E-9 6.3E-S 2.3E-6 ZE-5 3E-7 BE-6 1E-6 2E-5 4E-6 9E-6 6E-5 ZE-5 2E-5 3E-6 9E-5 4E-5 1E-5 SE-5 6E-5 6E-5 1E-4 1.5E-4 4.7 3.1E-2 12.3 3.6E-5 9.4E>>l 5.7E-1 5.5E-3 6.6E-2 E.SE-3 1.1E-3 1.1E-4 1.9E-4 7.6E-4 2.8E-4 1.7E-9 1.0E-3 2.3E-2 1.12EB 1.01EB 2.63EB 9.67E7 2.32EB 1.17EB 1.97EB 2.89EB 7.32E7 1.45EB 4.99E7 1.03E7 3.3E-1 1.4E+2 6.7E+1 1.2E+3 1.7E>>1 4.4E+2 1.0E+2 9.4E+1 9.5E+1 1.2E>>3 6.6E+0 7.86-2 f 5 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 I
cpa, f 1s 165 gpm and Z1(C1/MPC1) is 2.1E+1 unitless.
These values y1eld 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 I'lacing a d1luted sample of Reactor Coolant (after a
two hour decay) in a
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 NHE ACTIVITY CONCENTRATION F1/mi A
8 HPC pC1/ml FRACTION OF HPC 8/C OETECTOR
RESPONSE
cpm/pC1/ml CPH TOTAL cpm H3 l:OE-2 3E-3 F18 l '. 9E-3 5E-4 N24 3.7E-3 3E-5 P32 7.8E-5 ZE-5 CR51 2.3E-3 2E-3 MN54 4.0E-S lE-4 MN56 2.9E-Z lE-4 FE55
- 3. 9E-4 8E-4 FE59 8.0E-S SE-5 C058 5.0E-3 9E-5 C060 5.0E-4 3E-5 NI63 3.9E-7 3E-5 3.3 3.8 1.2E-2 3.9 1.2
.4.0E-l 2.9E-2 4.9E-l l.6 5.6E-l 1.7E-l 1.3E-2 8.42E7 1.2EB
&.63E7 1.14EB 1.65EB 3.4E3 3.5E6.
6.9E3 5.7E5 8.3E4
ISOTOPE 2
HR DECAY NAME ACTIVITY CONCENTRATION pC)/ml.
A MPC pCl/ml FRACTION OF HPC 8/C E
F)
F 1
))
DETECTOR CPM
RESPONSE
TOTAL cpm/pCl/ml cpm NI65 CU64 ZN65 ZN69H BR83 BR84 RB89 SR89 SR90 SR91 SR92 Y91 Y92 Y93 ZR95 ZR97 NB95 H099 TC99H RU103 RU105 RU106 AG110H TE129H TE1 31M TE132 I131 I132 I133 I134 I135 CS134 CS136 CS'l 37 CS138 BA140 LA142 CE141 CE143 CE144 PR143 ND147 H187 NP239
-. TOTALS 3.0E-4
- 1. 1E-2 7.8E-S 7.4E-4 1.3E-2 2.1E-3 1.0E-4 3.1E-3 2.3E<<4
&.QE-2 6.6E-2 1.1E-4 1.3E-2 1.0E-2 4.0E-5 2.9E-5 4.1E-S 2.2E-2 2.2E-l 5.4E-S 4.5E-3 8.4E-6 6.0E-5
- l. 1E-4 2.7E-4 4.8E-2 1.3E-2 1.2E-1 1.5E-1
, B.QK-2 1.4E-l 1.6E-4
- 1. 1E-4 2.4E-4 1.4E-2 9.0E-3 7.1E-3 8.1E-5 2.3E-l 1E-4 ZE-4 1E-4 6E-5 3E-6 3E-6 3E-7 SE-5 6E-5 3E-5 6E-5 3E-5 6E-5 2E-5 lE-4 4E-5 3E-3 BE-5 1E-4 1E-5 3E-5 2E-5 4E-5 2E-5 3E-7 BE-6 lE>>6 2E-5 4E-6 9E-6 6E-5 2E-5 2E-5 3E-6 9E-5 4E-5 1E-5 SE-5 6E-5 6E-5 1E-4 3.0 5.5El 7.8E-1 1.2E1 4.3E3 1.0E3 7.7E2 1.2E3
- 1. 1E3 3.7 2.2E2 3.3E2 6.7E-1 1.5
- 4. 1E-1 5.5E2 7.3E1 6.8E-l 4.5El 8.4E-1 2.0 5.5 6.8 2.4E3 4.3E4 1.5E4 1.5E5 4.0E3 3.5E4 1.8El 1.8 1.2E1 4.5E2 2.4E3 8.1 2.3E3 2.7E5 1.12EB 7.8E3 1.22EB 8.17K7 2.47EB 2.05E7 8.35E7 B.SE7 2.32E7 2.32E7 1.12EB 1.01EB 2.63EB 9.67E7 2.32EB 1.17EB 1.97EB 2.89EB 7.32E7 1.45EB 4.99E7 1.03E7 2.4E5 2.4E1
- 7. 3E6 5.4E6 2.7E4 2.7E5 3.3E3 3.5E3 5.1ES 5.1E6 5.4E6 1.3E6 3.2E7 1.45E7 1.86E7 1.6E7 3.2E4 3.2E4 1.8E4 2.0E6 4.5ES
- 8. 3E2
'5 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 for averagiag or totaling.
The limit1ng concentration is calculated as follows:
MPC Fraction ~ Zi [ Zs(Cis<<Fs)/(MPCi<<Zs(Ps))]
Where+
MPC Praction ~
Cia Ps MPCi ~
Zs(Cis<<Ps)
Zs(Ps)
W The limiting conceatratioa of 10 CPR Appendix B,
Table II, Columa 2,
radioauclides other than dissolved eatrained noble gases For noble gases, the coaccntratioa shall be limited to 2 x 10E-4
<microcurie/ml total activity, unitless The conccntratioa of nuclide 1 in particular effluent stream s, uCi/ml The flow rata of a
particular effluent stream s, gpm
~
The limiting conccatration of a
specific auclide 1 from
- 10CPR20, Appendix b, Table II, Columa 2
(noble gas limit is 2E 4),
uCi/ml The total activity rate of nuclide 1, in all the effluent streams s>
uCi/ml <<gpm 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 [AiteXL*(dTlecileP1)1 Where:
Dt dTl Cil Ait The cumulative dose commitment to thc total body or any organ, t from the liqu1d effluents for the total t1mc period EL(dZL) >
mrcm The length of the 1 th time period over which Cil aad Fl are averaged for all 11quid releases, hours The average concentration of radionuclide, 1,
in undiluted liquid effluents during t1me pet'iod dTl from any liquid release, uC1/ml 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 A'imple bf 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)].
2.4 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 i in the release and Fl unitless is the dilution factor for the release.
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.
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; Uw Uf a
BFi a
DPi Is the composite dose parameter for the total body or organ of
'n 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 730 kg/yr, adult water consumption 21 kg/yr, adult fish consumption Bioaccumulation factor for
- nuclide, i,
in fish, pCi/kg per pCi/1, from Table A-1 of RC 1.109 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 field 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 of'uclides are listed on Table 2-2.
These are the most common nuclides 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.
1'iquid Radwaste Tank 5h and 5B at Nine Mile point Unit 2 contain a sparger spray ring which assist the mixing of the tank contents while it is being recirculated prior to sampling.
This sparger effectively mixes the tank 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.
2.6 Serv1ce Hater A and 8 and the Cooling Tower Blowdown are sampled from
'he radiat1on mon1tor on each respect1ve stream.
These monitors continuously withdraw a sample and pump 1t back to the effluent stream.
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
- Sr 89 Sr 91 Sr 92 Y 91 Y 92 Zr 95 Nb 95 Mo 99
'Tc 99m Te 132 Ba 140 Ce 144 Br 84 I 131 I 132 I 133 I 134 I 135 Cs 134 Cs 136 Cs 137 Cs 138 Mn 54 Ma 56 Pe 59 Co 58 Co 60 (CPM/uCi/ml) z 10 0.78E-04 1.22
- 0. 817 2.47 0.205 0.835
- 0. 85 0.232
- 0. 232 l.12 0.499 0 103 l.12 1.01
- 2. 63 0.967 2.32 1.17 1.97 2.89 0.732 1.45
- 0. 842 1.2
- 0. 863
- 1. 14 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 H 3 3.37E-1 3.37E-1 LIVER KIDNEY THYROID LUNG 3.37E-1 3.37E-1 3.37E-1 3.37E-1 Cr 51 1.28 CU 64 4.72 3.21E2 8.57E2 Mn 54 8.36E2 1.34E4 Pe 59 9.40E2 8.18E3 Co 58 2.01E2 1.82E3 Co 60 5.70E2 4.85E3 Zn 65 3.33E4 Sr 89 6.~4E2 4.65E4 3.60E3 Sr 90 1.36ES 1.60E4 Zr 95 5.91E-2 2.77E2 Mn 56 1.96E1 3.52E3 Mo 99 2.05El 2.50E2 Na 24 4.09E2 4.09E2 I 131 1.26E2
. 5.80E1 Ni 65 7.53 4+18E2 I 133 2 78El 8.21E1
- 2. 81E-1
- 7. 63E-1
- 1. 69 1.01E1 2.54El 4.38E3 1.30E3 1.04E3 2.45E3 9.00E1 2.58E2 2.32E4 7.38E4 4.93E4 2.24E4 5.52ES 2.72E-1 8.74E-2 1.37E-1 1.10E2 1.40E2 1.08E2 2.44E2 6.85E2 4.09E2 4.09E2 4.09E2 4.09E2 4.09E2 lo54E2 2.20E2 3.77E2 7.21E4 1.27E2 1.65E1 5 25El 9.13E1 1.59E2 1.34E4 Ce 134 5.79E5 1.24E4 Cs Cs 136 8.86E4 137 3e42ES 1.40E4 1.01E4 Nb 95 1.34E2 1.51E6 Ba 140 1.41El 4.45E2 Ce 141 2.48E-3 8.36El 3.23E-2 4.47E2 2.19E-2 1.02E-2 2.49E2 2.46E2 2.98E5 7.09ES 2.29ES 3.12E4 1.23ES 6 '5E4 3.82E5 5.22ES 1.77E5 2.16E2 2.71E-l 9 22E-2 7.61E4 9.39E3 5.89E4 lo57E-1 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 SPEHT FUEL PON. CORIN6 fLONNAN~
FILTER RADWASTE MtQKRALllfR RfACTNWATER CLfuaP SYSTftI RfGfNRAHT fVAPNATN COIefHSATE DftQtCRALllfRS RfACTOR St%DING E~NT DRAII6 PHASE MPARATN WASTE EVAPORATN RECOVfRY SAt5%f TN4'5 TINSIHE SLD8 EQJIPt%NT ORANS RfSIDUAltfAT RftIOVALSYSTftl RfCOVERY SAtIPLE TOaS RADWASTE FILTERS I
I I
I I
I I
I I
I I
I I
I I
I I
I I.
AOV 278 TYPICALOF 3 AOV I AOV 84 WASTE GlIECTITI wx AOV 47 Pl Tf Cf WASTE COllfCTNPLOP I
WASTE COLLECTOR SURGE TANK TK 18 PISA PS Ps P I88 2-1 A
.E COLLECTION I
I I
I I
I I
I I
I I
I I
I I
I I
I AOV 44 I I
I I
I I
AOV 48'OV 277 WASTE COLLfCTN SURGE ~S tl Cf RADWASTEfILTERS flONDRAINFILTER AOV 308 fLOOR DRAI flLTER RADWASTf FILTfRS
.SERVICf AIR WASTE COLL PINPS fLOOR DRN CCL PW S WASTE CRLfCTOR QSGE PLOP I
I I
I AOV7 I
I I
I I
I I
I I
I BASTE FLHR FLT IAP
) ADVS AOV9 I
AOV6 C
I AOV8 AOV 167 I
I I
I I
I I
I I
I I
I I
I Pl COteEHSATE TRANSffR AOV293 BKWSH TK l6 I
I AOV l06 AOV29 I I6 RW flLTER SACKWASH PRPS l68 rl8. 2-2 g, l ~~
TYPICALOF I
I I: l.
PCV266 AOV256 AOV l78 ADVSI FV87 RADWASTf OftlIN 4AJ I
I I
I I
OVSGI I
I I
I I
I I
I TYPICALOF 2 AOV262 AOV260 SPENT RESIN TANK REGMRANT WASTE TANKS 1
. I I
I I
I L
I I
I AOVSS i I
I AOVSll Cf I
AOV86 HVIIS SLUDGE TAHK fLOOR DRAItl AOV l66 COLLECTOR TKS WASTE DISCH N
S~E TKS WASTE COLL SURGE Thtà SPE HT
~
AOV26l I
TeraeI AOV263 AOV;l3IAOV l64 TO OTHER AOV264 OERIIN COtefHSA TE TRANSFER AOV l04 fLOOR DRAIN COLL SURGf TK AOV l9I COLLEClOR TAHKS RECOVERY AOV2P7 SAtIPLE TANK WASTE DISCH AOV l92 TAWS HASTE COLLECTOR TREATMENT SYSTEM TP PTIIER Dfttltl
RfGfNfvAP DIST COOLfR SP-I WASTE Shr&E TKS RADWASQ.
DftON
~.,-.
CI AOV2I LT TYPICAl OF 2 RECOvfRY SAtA.E TAM(
I II I
I I
I I
WASTE COLL s SILAGE TANKI I
I WASH EVAP DIST CMER FLOOR DRAIN FILHR RADWASTE DftlINERALllER TYPICAlOF 2 I
, AOV29 I
WASTE DISCHARGE S~E TANK OTHfR P4 RfCIRC LNE I
I RADWASTE FILTERS I
I I
I I
s I
I I
I I
~,
I OMR PE'ECIRCL<
OTKR P4 SUCTIONLl%
Pl P4 RECOVERY SAtR.E PRP AOV66 i I
I I
I I
I I
Csrs AOV I IB I
I I
WASTE COLL I TANKS AOV3I4 I
$$'-I WASTE SAtlPLE TKS FV330 TKSA,S 00%RP5 SUCTICN ll%
l PS AOV33 AOV76 WASI AOV27S EVA Rf6 AOV279 EVA SERVICf WAHR DISCHARGE SAY AOV l42 FLOW DRAIN COLLECTOR TAWS HIGH RANGE Ff 33O FV33 I I'-I LCMRANGE
~
RECOYERY SYSTEM and WASTE I>., Af I: 9 A MFII l: CVCTI.M
WASTEEVAP REGEHfVAP CST8LOG FLOMORAIN RX8LDG SPENT RESIN AUXGOILER RWGLOG WASTE DISCH DIST COOLER DIST CORER DRAINS FILTER DRAINS MK 8LDG N'RAINS RWfII.TfR TAkKS AOV282 I'
I I
FLOOR OR CRL TK2AJ AOV72 OTKRfLNN DRH SUCT LI%
OMR FLOOR ORAIH CKL PINP I
I I
I I
I I
I I
AOV738 OTMR P2 RECIRC Ll%
WASTEeuT TINeeLOG tee-I fLOORDRAIH TK ORANS ORAIHS COLLECTOR TANK I
I TYPICALOF 2 REGEHEVAP WASTE EVAP RW FILTfR RW DEHIHS FLOOR DRAIN COLL TK eve FlOOR DRH FILTER WASTf DISCH SAtA.E TKS EVAP 80TTNS TNC FLOOR DRAIN CCLL SINGE TK l7 AOV20I AOV90A OTKR FLOOR DRAINCOLL TK FLOOR DRH FILTER FLOOR DRAIN COLL SINGE PNIPS I'Ip.
2-4 FLOOR ORAIN COLLECTION SYSTFM
WASTE COLL SURGE TK fLOOR ORH CQ,L SINGE TK fLONIORAIH QKLEUNTKS PEGEH WASTE TKS WASTE QllTKS FV 122 AOV2 AOV253 AOV2?1 FLAT 8EO fllTER AOV236 SERVICE AIR 7 af6)
- CONVOKE ANDRAWOff CST SOV 251 BODV FEED TK HOPPER FEEDER AOV257 SLUDGE TK AOV451 EDUCTOR 8NV FEED Put@
FILTER PRECOAT TQL fION DRAINFILTER PRECOAT PS% P27 CST FILTER EfflUENT TAHy.
g
~
FILTER EffLUEIIT Ply i
I I
I I
LV251 AOV2)q REGS
'It/ASTE T1'.
AOV 127 WASTE OISCH Sea.E TK AOV 12~
FLOOR DRAINCOLL TK AOV 126 WASTE COLL TK
~
Fig. 2-5
)RAIN FILTER SYSTEM
30'f CCNTACT CONEHSER TBCLCW AOV246 TBCLCW VENT EVAP fVl DIST I
VI I
AOV247 EVAP BOTT(NS ~S CONDENSATE tRANSFER ANO STORAGE AOV228 01st TRANS Pre TBCLCW REGEN WASTE TKS fLOCA ORAIH COLL RS FE RO 140 RECIRC PINP RBLP.
RW AUX STEA11 TBCLCW LV 141 5'ISLE TI.S 1.V 130 CONEHSATE TRANSFER SPV 2gy AN STORAGE AOV 132 EVAP BOTtmS an S Pip. 2-6 VASTE EYAPORATOR SYSTEM P AOV218~
WASTE COLL 1XS AOV 187 fLOOR ORH COLL TTt.'S WASTE OISCH AOV 147 SANA.E TKS
flOOR ORAN fN.TER RWflONIAIe EQIIP tNV IHS RW fIlTEQ BACK WASH~
I nnnREOEH ~
WASTE~
r I
I I
I AOI/SE I
I I
I I
I QEI$NERAHT WASTE TAN TKS RE6EN WASTE TK PlkP PBAJ TYPICALOF 2 AOV69 I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
IL OTKR REGECRAHT WASTE TANK AOV68,'
RERNEVAP I
AOV92 I
WASTE EVAP I
flOOR DRAINfIlTER AOV95~
Fig. 2-7 REGENERANT WASTE SYSTEM
CON'TACT CONENSER TBCLCW AOV 24 TBCLCW VENT FV 157 EVAP DIST I
I AOV 249 EVAP BOTTQS PROS CONEHSATE TRANSFER ANSTORAGE DIST TRANS PttP TBCLCW REGEN WASTF. TKS FLOOR DRAIN COLL TY.S RO 154 RBLR RW AUX STEAN TBCLCW LV 155 WASTE O'SCH SAtIPL!.KS LV 148 AOV 149 EVAP BOTTOtS ~S Fig. 2-8 REGENERANT EVAPORATOR SYSTEM CCFIEHSATE TRANSFER AOV 159 SOV 288 AN STORAGE AOV 222 WASTE COLL TKS AOV 188 FLOOR DRN COLL TKS WASTE DISCH AOV 2P 5 S AtIPLE IKS
ae StanCt eall> I>>
aaa staffct salts Iaf last aa caf I aa caf I
$ft 1Wt aa cal I Sat taat ILW Nfsslsfta Illa an sfslta IISI aa cal I aaa alai tfcaaasfa EIh aa Cal I n
aaa waf ffcaaacfa EIB I
I aa caf II I
I I'a Iawl f Lactea SI5fla I
I I~ Cas SISON I
I~ Cas 5'Islla
~.
I I
I ICW ~ Walla. IIL faw cct wafla. Ila,la.lc ea caf
$5 ILKwa wafta, ll~
lail ccs walla. tlL.la.lc Ia Tlat tatcaaltas lla.fa aa cll 0 SERVICE MhTER
'al IfLa L..
~ I5CNLNCI aaf call taa Iafta caat INc Iaata ataaaaaa
~I caf tt
. (I"I)
L
~ ISCNLICI laf I
Lll Lfaala aaaal5II tftLWNI~ ISCNLLCIS Clacatalfas sall ~ tts af 'i acf lafscafaft QalaaMI IOS f aa Cal ll 5I C IILIt alaf NINS 5fc Ntal Ifofacfas ODCH Fjg. 2-9 5IC 5fslla 5tlal IWL
~aaa al cll I
~L Caf tt FIOURE 55.5 8 I.IOUIORAOIATIONMONITORINO SHEET 2 OF 2 NIAGARA MOHAWK POYYER CORPORATI NINE MILE POINT-UNIT 2 FOAL SAFElY ANAI FPORT
FLOW~
INTERCHANGEABLE PURGE OR TEST CONNECTION SAMPLER I
(2)
I Tl I
(2)
I (2) uaUIO SAMPLER CS L
DETECTOR DATA ACO.UISITION UNIT (DAU) ~
I (9)
Fl FS I
Pl I
(11) w PUMP NOTES:
(1)
GLOBE VALVE.ALLOTHER MANUALLY OPERATED VALVESARE BALLVALVES (2)
REOUIAED ONLYIfSAMPLE FLUID TEMPERATURE EXCEEDS SELLEAS DETECTOR TKMPERATUAEREOUIAEMENTS (2) ~ NORMAL!Y CI.OSED
~ NORMALLYOPEN gf"TlTEMPERATURE INDICATION (5)
TS TEMPERATUAE SWITCH m
CS CHECK SOURCE (8)
PI.PRESSUAE INDICATOR (I) FI~OW INDICATOR (10) FS FLOW SWITCH (11) DRAIN CONNECTION 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 3.1 3.1.1
.'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.
Gaseous Effluents Monitor Alarm Setpoints Basis Technical Specification Section
- 3. 11.2. 1 and
- 3. 11.2.7 provide the basis for the gaseous effluent monitor alarm setpoints.
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.
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 it is considered impractical to base their alarm setpoints on organ dose 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 of the product of 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:
Alarm Setpoint Where:
0.8+R+Xi (Ci)
TFaa" Alarm Setpoint Is the alarm setpoint of the Vent Effluent Monitor, uci/sec 0.8 (X/q)v 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 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:
Alarm Setpoint Hhere:
Alarm Setpoint 0.8 350,000 2.1E-3
Background
E1(ci )
P f'Ei(C1)
+ Background Is the alarm setpoint for the offgas pretreatment Noble Gas Detector, F1/cc Is a Safety Factor, unitless Is the Technical Spec1ficat1on L1mit for Offgas Pretreatment, pC1/sec Is a unit conversion, 60 sec/m1n / 2B317 ml/CF Is the Offgas System High Flow rate Alarm
- Setpoint, CFH Is the detector response when its chamber is filled with nonrad1oactive air, pC1/cc 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.
Inltial ly, and ln accordance wlth 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 N
e This. detector is made of germanium.
It is sensitive to only gamma
~ radiation.
- However, because it is a
computer based multichannel analysis system it is able to acurately quantify 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 represents the most significant contaminate of gaseous activity in the plant.
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 NAME ACTIVITY CONCENTRATION
,Ci/ml B
(Ci)
PLUME PhCTOR eeeeeee-yz-uC1 C
(Vi)
PLUME FACTOR mrem/
ml sec D (B+C)
(Ci.*Vi)
KR83 KR85 KR85M KR87 KR88 KR89 KR90 XE131M XE133 XE133M XE135 XE135H XE137 XE138 AR41 8.74E-2 4.90'.56E-1 5e23E-1 5.32E-l 1.63 3.82E-4 2e06E-1 7.35E-3 5.88E-l 5e 9IE-1 2ell 1.93 3.28E-5 3.2IZ-3 9'8K-3 2 2IE-2 1 92E-2 1.5IE-2 6 55E-5 5.93E-4 3.44'.12E-3 6 12E-3 2.88E-3 1 33E-2 1.6IE-2 1'.61E-8 5.0IE-3 5.22E-3 1.18E-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 NAHE CONCENTRATION pC1/ml IHHERSION FACTOR SMIRKED yr-pCl C
IHMERSIOK FACTOR yr-ml Da(B'C)
KR83 KR85 KR85M KR&7 KR&8 KR89 KR90 XE131H XE133 XE133H XE135 XE135M XE137 XE138 AR41 8.74E-Z 4.90E-4 1.56E-1 5.23E-1 5.32E-1 1.63 W~W
- 3. 82E-4 2.06E-1 7.35E-3 5.BBE-l 5.91E-1 2.11 1.93 7.56E-2 1.61El 1.17E3 5.9ZE3 1.47E4 1.66E4 1.56E4 9.15E1 2.94E2 2.51E2 1.81E3 3.12E3 1.42E3 1.&3E3 8.84E3 6.61E-3 7.90E-3 1.82E2 3.10E3 7.8ZE3 2.71E4 3.50E-2 6.06E1 1.84 1.06E3 1.84E3 3.00E3 1.70E4 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:
Qis 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 Is the release rate of each noble gas nuclide, i, from the Stack release averaged over the time period of 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, from the Vent 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/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 identified noble gas nuclide, i~
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 of each identified noble gas nuclide, i.
Listed on Table 3-2, mrad/yr per uCi/sac.
(X/Q)s Qiv Qis Is the highest calculated annual average relative concentration at or beyond the site boundary 'for.the Vent.
Final Environmental Statement, NUREG
- 1085, Table D-2, 2.0E-6 sec/m3 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 Is the release rate of each noble gas nuclide, i, from the Vent release averaged over the time period of
- concern, uCi/se c 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 i through pathway p.
For inhalation
- pathway, mrem/yr per uCi/m
~
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 i, from the stack and vent respectively uCi/sec.
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 or FACTOR Pi GROUND m2~em/yr uCi/sec Pi INHALATION mrem/yr uCi/m3 Pi FOOD m2~em/yr uCi/sec T BODY SKIN BONE LIVER THYROID RIDNEY LUNG GI-LLI 2 46E7 2.98E7 1.96E4 3.79E4 4.44E4 1.48E7
- 5. 18E4 1.06E3 1.43E9 2.77E9 3.26E9 1.07E12 3.81E9 1.16E8 1.34E-9 2+90E-9 8.48E-9 lo42E-7 3.64E-10 4.73E-10 WsQeRhrQv NOTE:
6.12$ -10 1.95E-8 1.27E-ao 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
,SPN 1.51E-2 1.&2E-2 3.82E-4 7.39'.66E-4 2.89E-1 1.0IE-3 1.82E-l 3 52E-1 4.14E-l 1.36E+2 4.84E-1 1.97E-1 1.82E-2 3.53E-l 4.15E-l 1.36E+2 4.85E-1 "KUNG GI-LLI 2.07E-5 1.47E-2 1.47E-2 3.3 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.
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, and 3
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.
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.
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)vQiv + 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)vQiv + (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.
Ws, Wv Qis, Qiv Is the summation over all nuclides i.
Is the summation over all pathways p.
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 Are the amount of activity of nuclide i released from the stack or vent respectively over the period of
- 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 of 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 or PACTOR Ri-GROUND a~a2~cal r Ri-ZNHAIdlTZON Ri-MIIX Ri-MEAT Ri-VEGETATION mrem/
m2-mrem/ r uCi m uCi sec T BODY SKIN BONE LIVER THYROID KIDNEY LUNG GI-LLI ET 2.09E7 E
4.&lE4 4.81E4 1.62E7 7.88E4 2.84E3
'X3'25M 6.51E&
6.55E8 2.17ELl 1.0&E9 5.83E7 E
8.26E6 8.32E6 2.75E9 1.37E7 7.40ES
.1 E
1.43E&
1.44E8 4.75H.O 2.36E&
1.2&E7 Ws Wv 1.34E-9 2.90E-9 8.48E-9 1.42E-7 3.64E-10 1.15E-9 4.73E-10 1.86E-9 9.42E-10 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
,~BO Y
SKIN BONE LIVER THYROID KIDNEY LUNG
'GI-LLI GROUND
~)E-2 1.2&E-2 INHALATION 9.3&EM 9.3&EM 3 16E-1 1.54E-3 5.54E-S
-44" MILK E 2 8.40E-2 8.45E-2 2&.0 1.39E-l MEAT E-3 3.69E-3 3.71E-3 1.23 6.11E-3 VEGE MGK-2
- 5. 1&E-2 5.21E-2 17.2 8.54E-2 TOTAL
%3%E-2 1.28E-2 1.40E-1 A~1 46.7 2.32E-1 742E-3 3.30E-4 4.63E-3 1.25E-2
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 effluent 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.
B V
~//
/
~~M//
//
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:
ENERST YIELD MEV-0.25 0.6 0.7 0.9
- 0. 03 0.01 4.38E-3 9.38E-3 1.06E-2 4.14E-3 8.77E-3 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 it will be calculated and included in a revision to the ODCM e 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 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.
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 DFGi
~ 9.98E-7 sec-1
~ 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. If a nuclide is detected for which a factor is not listed, then ith will be calculated and included in a revision to the ODCM.
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)
%Stet Pi ~ X'(SR) Dpi (mrem/yr per pCi/m )
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 surfaces 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).
Thc
- fraction, r,
has a
value of 1.0 for radioiodiaes aad 0.2 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 organs'csolutioa of the units yields:
o< (tooo~
~
R.4xllpo ~ Oil.< fe 5 t) (e errea/yr per C1/sec) r for all radioauclides, except tritium.
The conceatration of tritium ia miLk is based on its airborne concentration rather than thc deposition rate.
p<
~
K'X'
+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:
Pj (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)
Iafsat Child Teen Adult Breathin Rate (m
~/ x) 1400 3700 8000 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 villyield 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 it <<ill be calculated ad included in a revision to the ODCM.
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
'xample Calculation:
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 itrillbe 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 sec-1 DKi
< 3.40E-9 mrem/hr per pCi/m2.
These values willyield 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. If a nuclide is detected for which a factor is not listed, then it will be calculated an included in a revision to the ODCM.
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)
~
~
)
fI 0 tt~)-~ 1+.]
-a(c(
Op(V 5
(s ~W per uCflaos) 2 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 1iters/yr.
Yp ~
the agricultural productivity by unit area of pasture feed grassy in kg/m a
s the agricultural productivity by unit area of stored feed, 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 from pasture to
- cov, to receptor>
ia sec.
- 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 pasture grass aad stored feeds.
Rogulatory Cuide 1.109, tho value fp vill be considered to be O.S for fod from tvo potential
- sources, Following the development ia of is will bo considered unity. TCN 1
a Hay to October grazing seasoa.
Value Parameter 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.
gab1e r (dimensionless) 1.0 for radioiodine 0.2 for particulates Bach stable element 330 330 400 310 Each radioauclide 0.7 2.0 1.73 z 105 (2 days) 7.7S z 10'90 days) 50 B-15 B-15 B-1 E-5 E-5 E-5 E-5 E-ll to E-14 E-15 E-15 E-15 E<<15 E-3 Ri K'K"FmgpUapDFLi(0-75(O.S/H)) (mremlyr per uCi/m3)
Fm (days/liter)
Uap (liters/yr) - Infant
- Child Teen Adult (DFLi)a (mrem/pCi) rp (kg/4) r, (kg/m2) tf (socoads)
-,.th (seconds)
'Q (kg/day) coacentration oi tritium in milk is based oa the airborne coaceatratioa cather than the deposition.
Therefore, tho Ri is based on fz/()]:
-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
~ 9.98E-7 sec -1 aw
< 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 list 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.
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.
TABLES 3 3-18, 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) 5 (a ~~
net vci/sec)
>>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 r (dimensionless)
Ff (days/kg Uap (kg/yr
- Infant
- Child Teen
- h.dult (DPLi)a (mrem/pCi)
Yp (kg/mc)
Ys (kg/m2) tf (seconds)
(seconds)
QF (kg/day) 1.0 for radioiodine 0.2 for particulates Each stable element 0
41 65 110 Each radar.onuclide 0 7 2.0 1.73 z 106 (20 days) 7.78 z 106 (90 days) 50 Table(RG1.109)
E-15 E-15 E-1 E-5 E-5 E-5 E~5 E-ll to E-14 E-15 E-15 E-15 E-15 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 it villbe calculated in a xevision to the ODCM.
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
[
(+ 'cree/yr per sCI/sec) 2
@lire;
~
a constant of unit conversion, 10 pCI/uCI.
L Ua the consumption rate of fresh leafy vegetation by the receptor tn a group (~). in kg/yr.
r n age IPa
~
the consueption rata of stored vegatation by the receptor in age grou()
in kg/yr.
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 consuyti in seconds
~
uy on, t~
the average tiae beoetn harvest of stored vegetation and its consusotion, in seconds.
Tv
~
the vegetation areal densi 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.
PIp~tEF r (diaensi onlass)
(OFLI )
(area/pCi) 0 (kg/yr)
Infant Chi14
- Teen Adult 0
(kg/yr) - Infant Chi14 Teen
- Adult
.fL (di~si4 less) f (dinensionless) t (seconds) t (seconds)
T(ig/
)
Value 1.0 for radioiodines 0.2 for particulates Each ra4i onuc1 ide 0
24 42 44 0
520 430 520 site specific (default
~ 1.0) site specific (default
~ '0.74) 4.4 X 10 (1 day) 5.14 I 10 (40 days) 2.0 Table E
1 E
1 E-'ll to E-Ia E-5 E-5 E-5 ES E-5 E-5 E-5 E-5 (see A6Nkgpage 28)
E-15 E 15
~
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 DFLi ~
1.0 unitless for Iodines 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 for which a factor is not listed, then it will be calculated and included in a revision to the ODCM.
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 is highez than any ad]scent building it 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 of 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 3.5 3.6 3.7 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.
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.
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.
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 villbe used, with the methodology of Section 3.3 3.
See Figure 3-5, Gaseous Radiation Monitoring.
TABLE 3-1 Kr 85 Kr 85m Kr 87 Kr 88 Xe 133 Xe 133m Xe 135 Xe 135m Xe 137 Xe 138 DETECTOR RESPONS E NET CPM/uCi/cc 4.30E+3 4.80K+3 8.00E+3 7.60E+3 1.75K+3 5.10K+3 8.10K+3 7.10K+3 "Values from SWEC purchase speci.fication NMP2-P281F NUCKZM TABLE 3-2 rLmE Smrz PAEAmXERS*
(Wrad/ r w uCi/sec)
V (mrem/ r o uC1/sec)
I Kr 83m Kr 85 Kr 85m Kr 87 Kr 88 Kr 89 3.5.1E-5 3.39E-3 1.04E-2 2.34E-2 2.01E-2 1 e59E-2 3.28E-5 3.21E-3 9.98E-3 2i2ZE-2 1 92E-2 1.51E-2 Xe 131m Xe 133 Xe 133m Xe 135 Xe 135m Xe 137 Xe 138 6.90E-5 6.
12'.62E-4 4 31E-3 6.55E-3 3.07E-3 1 38E-2 6.55E-5 5.93E-4 3.44E-4 4.09E-3 6.12E-3 2.88E-3 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 Kr 85m Kr 85 Kr 87 Kr. 88 Kr 89 Kr 90 Xe 131m Xe 133m Xe 133 Xe 135m Xe 135 Xe 137 Xe 138 hr 41 7.56E-02 1.17E3 1.61E1 5.92E3 1 e47E4 1.66E4 1.56E4
- 9. 15E1 2.5IE2 2.94E2 3e12E3 1 81E3 1.42E3 8.83E3 8.84E3 1.46E3 1.34E3 9.73E3 2.37E3 1.01E4 7.29E3 4.76E2 9.94E2 3.06E2 7.11E2 1.86E3 1.22E4 4.13E3 2.69E3
'.93E1 1.23E3 1.72E1
- 6. 17E3 1.52E4 1.73E4 1.63E4 1.56E2 3.27E2 3.53E2 3.36E3
- 1. 92E3 1.51E3 9.21E3 9.30E3 2.88K 2 1.97E3 1.95K 3 1.03E4 2.93E3 1.06E4 7.83E3 1.11E3 1.48E3 1.05E3 7.39E2 2.46E3 1.27E4
- 4. 75E3 3.28E3
<<Prom, Table B-l.Regulatory Guile 1.109 Reve 1 e*mrem/yr per uCf/m
~
3
- e*mradlyr per i(Ci/m
~
3 TABLE 3-4 Pi VALUES - GROUND PLANE**
a~~azem/ r i'/se c TOTAL BODY SKIN H 3 C 14 Cr 51 Mn 54 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95
- Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140
- La. QQ Ce 141 6.64E6 1.10E9 3.88E8 5+ 27E8 4.40E9 6.87E8 3.06E4 3.44E8 3.50E8 5.71E6 2.46E7 3.50E6 2.81E9 1.15E9 2 93E7 2.10E8 1.95E7 5.85E7 7.85E6 1.29E9 4.56E8
- 6. 18E8 5 17E9
- 7. 90E8 3.56E4 3.99E8
- 4. 12E8 6.61E6 2.98E7 4.26E6 3.28E9 1.34E9 3.35E7 2.38E8 2.20E7 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
VALUES - INHALATION**
i ruralr uCi/m3 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 Mn 54 2 53E4 4.98E3 4.98E3 1.00E6 7-06E3 8.95E1 5.75EL 1.32EL 1.28E4 3.57E2 Pe 59 1.36E4 2.35E4 9.48E3 Co 58 Co 60 1.22E3 1.82E3 8.02E3 1.18E4 Zn 65 1.93E4 6.26E4 3.11E4 Sr 89 3.98E5 Sr 90 Zr 95 4.09E7 I
1.15ES 1.14E4 2.59E6 2 79E4 2.03E4 Mo 99 1.65E2 3.23E1 "Nb 95 1.57E4 6 43E3 3.78E3 1.02E6 2.48E4 7.77ES 1.11E4 4.51E6 3.19E4 3.25E4 6.47E5 5.14E4 2.03E6 6.40K 4 1.12E7 1.31ES 3.11E4 1.75E6 2.17E4 4.72E3 4.79ES 1.27E4 2.65E2 1.35E5 4.87K 4 I 131 3 79E4 4.44E4 1.96E4 1.48E7 5.18E4 I 133 1.32E4 1.92E4 5.60E3 3.56E6 2.24E4 1.06E3 2.16E3 Cs 134 3.96E5 7.03ES 7.45E4 Cs 137
', 5.49ES 6.12E5 4.55E4 Ba 140 5.60E4 5.60KL 2.90E3
- La 140 S.OSE2 2.00E2 5.15EL Ce 141 2.77E4 1.67E4 1.99E3 Ce 144 3.19E6 1.21E6 1.76ES 1.90E5 7.97E4 1.33E3 1.72E5 7.13E4 1.33E3 1 34EL 1.60E6 3.84E4 1.68ES 8.48E4 5.25E3 5.17E5 2.16E4 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)*<<*
2 m - 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 Co 60 8.98E7 2.12ES Sr 89 1.28ELO Sr 90 1.24EL1 3.67ES
- 3. 15ELO Zn 65 5.65E9 1.94E10 8.94E9 9.40E9 6 15E7 2.14EB 1.64ELO 2.63E8 1.55E9 Zr 95 6.93E3 1.69E3 1.20E3
<<<<Nb 95 7.07ES 2.91ES 1.68ES 1.82E3 2.09ES Mo 99 2.12E8 I 131 2.77E9 3.26E9 4.13E7 3.17ES 1.43E9 1.07EL2 3.81E9 I 133 3.69E7 5.37E7 1.57E7 9.77E9 6.31E7 8.41ES 2.46ES 6.98E7 lo16ES 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
- La 140"3,79E2 1 49E2 Ca 141 4N41E4 2.69E4 Ce 144 2.37E6 9.69ES
<<mrem/yr per uCi/m3.
'<<Daughter Decay Product.
equal parent nuclide.
- Calculated in accordance 1.26E7
5.83E4 1.51ES 6.03E7 3.84EL
- 3. 17E3 8.30E3 1 33ES 3.92E5 1.75E6 1.39E7 1.36EB Activitylevel and effective haLf life assumed to with NUREG 0133,. )ection 5.2.1.3.
TABLE 3-7 VALUES - INHALATION-INFANT<<<<
a~rem/ r EECi/m NDOLIDE BONE H 3 C 14 LEONE 6.47E2 T
BODE TEZEOZD KIDNEY GZ-LLZ LUNG 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 2.65E4 5.31E3 5.3IE3 5.3IE3 5.31E3 5 ~ 31E3 5.31E3 Cr 51 Mn 54 Pe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95
<<Nb 95 Mo 99 I-131 I 133 Cs 134 2.53E4 4.98E3 1.36E4 2.35E4 1.22E3 8.02E3 6.26E4 1.93E4 3.98E5 4.09E7 9.48E3 1.82E3 1.18E4 3.11E4
- 1. 14E4 2.59E6 1.15E5 1.57E4 2.79E4 2.03E4 6.43E3 3.78E3 3.79E4 1.32E4 3.96ES 1.65E2 4.44E4 1.92E4 7.03ES 3.23El 1.96E4 5.60E3 7.45E4 1.48E7 3.56E6 4.98E3 3.25E4 3 llE4 4.72E3 2.65E2 5.18E4 2.24E4 1.90E5 1.00E6 1.02E6 7'7E5 4.51E6 6.47ES 7.06E3 2.48E4
- 1. 11E4 3B19E4 5.14E4 2.03E6 6.40E4 1.12E7 1 3IES 1.75E6 2.17E4 4.79E5 1.35E5 7.97E4 1.27E4 4.87E4 1.06E3 2.16E3 1.33E3 8.95E1 5.75El 1.32E1 1.28E4 3.57E2 Cs 137 5.49E5 6.12E5 Sa 140 5.60E4 5.60El 4.55E4 2.90E3 1.72E5 1,34E1 7.13E4 1 60E6 1.33E3 3.84E4
<<La 140 5.05E2 Ce 141 2.77E4 2.00E2 5.15E1 1.67E4 1.99E3 Ce 144 3.19E6 1.21E6 1.76E5 1.68ES 8.48E4 2.16E4 1.48E5 5.25E3
- 5. 17ES 5 38ES 9 84E6
<<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 wCi/m3 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 Mn 54 4.29E4 9.5IE3 1.00E4 1.58E6 2.29E4 1.54E2 8.55EL 2.43EL 1.70E4 1.08E3 Pe 59 2.07E4 3.34E4 1.67E4 Co 58 Co 60 1.77E3
- 3. 16E3 1.3IZ4 2.26E4 Zn 65 4.26E4 1.13E5 7.03E4 1.27E6 7.07E4 1.11E6 3.44E4 7.07E6 9.62E4 7.14E4 9.95E5 1.63E4 Sr 89 5.99E5 Sr 90 1.0IZ8 1.72E4 6.44E6 1.48E7 3.43E5 2 16E6 1 67E5 Mo 99 1.72E2 4.26EL Zr 95 1.90E5 4.18E4 3.70E4
- Nb 95 2.35E4 9.18E3 6.55E3 5.96E4 2.23E6 6.1IE4 8.62Z3 6.14E5 3.70E4 3.92E2 1.35E5 1.27E5 I 131 4.8IZ4 4.8IZ4 2.73E4 1.62Z7 7.88E4 I 133 1.66E4 2.03E4 7 70E3 3.85E6 3.38E4 2.84E3 5.48K 3 Cs 134 6.5IZ5 I.OIE6 2.25E5 Cs 137 SA7Z5 8.25E5 1.28E5 Ba 140'ya40E4 6.48EL 4 33Z3
~. Ce 144 6.77E6 2 12E6 3.61E5 eLa 140 6.44E2 2.25E2.
7.55EL Ce 141 3.92E4 1.95E4 2.90E3 3.30E5 1.2IZ5 3.85E3 2.82E5 1.04E5 3.62K 3
- 2. IIZI 1.74E6 1.02E5 1.83E5 2.26E5 8.55E3 5.44E5 5.66E4 1.17E6 1.20E7 3.89E5
- Daughter Decay Product.
Activity level and effective half life assumed to equal Parent nuclide.
TABLE 3-9 R
VALUES - INHA?dZION - TEEN i
m~zcml z uCi/m3 NUCLIDE BONE LIVER Y. BODY YEYROID KIDNEY I BEG GI-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 Pe 59 1.59E4 3.70E4 1.43E4 1.27E4 1.98E6 1.53E6 6.68E4 1.78ES Co 58 Co 60 2.07E3 2.78E3 1.51E4 1.98E4 1.34E6 9.52E4 8.72E6 2.59E5 Zn 65 3.86E4 1.34E5 6.24E4 8.64E4 1.24E6 4.66E4 Sr 89 4.34E5 Sr 90 1.08E8 1.25E4 6.68E6 2.42E6 3.71ES 1.65E7 7.65ES Mo 99 1.69E2 3.22EL Zr 95 1.46E5 4.58E4 3.15E4
- Nb 95 1.86E4 1.03E4 5.66E3 6.74E4 2.69E6 1.49ES 1 00E4 7.51ES 9.68E4 4.11E2 1.54ES 2 69E5 I 131 3.54E4 4.91E4 2.64E4 1.46E7 8.40E4 I 133 1.22E4 2.05E4 6.22E3 2 92E6 3.59E4 6.49E3 1.03E4
<<Ia 140 Ce 141 4.79E2 2.84E4 2.36E2 6.26 EL 1.90E4 2.17E3 Ce 144 4.89E6 2.02E6 2.62E5 Cs 134 5.02ES 1.13E6 5.49E5 Cs 137 6.70ES 8.48E5 3.11ES Ba 140 5.47E4 6.70E1 3.52E3 3.75E5 1.46E5 9.76E3 3.04ES 1.21ES 8.48E3 2.28E1 2.03E6 2.29E5 2.14E5 4.87ES 8.88E3 6 14ES 1.26E5 1.21E6 1.34E7 8 64ES
<<Daughter Decay 5'roduct.
Activity level and effective half life assumed to equal parent nuclide.
TABLE 3-10 R
VAIUES - INHA1ATION-ADULT i
~eeet/
e uCi/m3 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 Co 60 1.58E3 2.07E3 1.15E4 1.48E4 Zn 65 3.24E4 1.03E5 4.66E4 Sr 89 3.04E5 Sr 90 9.92E7 8.72E3 6'0E6 Mo 99 1.21E2 2.30KL Zr 95 1.07ES 3.44E4 2.33E4 eNb 95 1.41E4 7.82E3 4.21E3 9'0E6 5 42E4 1.77E6 7.22E5 1.50E5 7.74E3 5.05E5 1.04E5 2.91E2 9.12E4 2.48E5 1.02E6 1.88E5 9.28E5 1.06E5 5.97E6 2.85E5 6.90E4 8.64E5 5.34E4 1,4PE6 3.50E5 I 131 2.52E4 3.58E4 2.05E4 1 19E7 6.13E4 I 133 8.64E3 1.48E4 4.52E3 2.15E6 2.58E4 6.28E3 8.88E3 eLa 140 C@ 141 3.44E2 1.99E4, 1 74E2 4.58EL 1.35E4 1.53E3 Ce 144 3e43E6 le43E6 1.84E5 Cs 134 3.73E5 8.48ES 7.28E5 Cs 13?
.4 78E5 6.21E5 4.28E5 Ba 140 '9.90E4 4.90EL 2.57E3 2.87E5 9.76E4, 1.04E4 2.22E5 7.52E4 8.40E3 1.67E1 1.27E6 2.18E5 1.36E5 4.58E5 6.26E3 3.62E5 1.20E5
&.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 - mrem/yr 4 uCi/sec 2
NUCLIDE TOTAL BODY H 3 C 14 Cr 51 Mn 54 Fe 59 Co 5S Co 60 Zn 65 Sr 89 Sr 90 Zr 95
- Nb 95 Mo 99 I 131 I 133 Ca 134 CQ 137 ba 140
- La 140 Ce 141 Ce 144 4.65E6 1.40E9 2.73E8 3 80ES 2.15E10 7 46ES 2.16E4 2.4SE8 2.50E8 3.99E6 1.72E7 2 45E6 6 83E9 1.03E10 2.05E7 1.47ES 1.37E7 6.96E7 5.50E6 1.64E9 3.20E8 4.45ES 2.53E10 8.57ES 2.5IE4 2.85E8
- 2. 94ES 4.63E6 2.09E7 2.98E6
- 7. 97E9
.1.20ELO 2.35E7 1.66E8 1.54E7 8.07E7
- Daughter Decay Product-Activity level and effective half life assumed to equal parent nuclide.
NUOLZDE BONE
- H 3 TABLE 3-12 Ri VALUES - COP MILK-INFANT 2
m ~em/yr 4 uCi/sec Y. BODY YNYROZD KZDNEY LUNG GI-LLI 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 Mn 54 2.51E7 5 ~ 68E6 5.56E6 9 21E6 8.35E4 5.45E4 1.19E4 1.06E5 2A3E6 Fe 59 1.22EB 2.13ES 8.38E7 Co 58 Co 60 1.39E7 3.46E7 5.90E7 1.39EB Zn 65 3.53E9 1.21E10 5.58E9
- 5. 87E9 Sr 89 6.93E9 Sr 90 8.19E10 1.99ES
- 2. 09ELO Zr 95 3.85E3 9.39E2 6.66E2
<<<<Nb 95 3.93E5 1.62E5 9.35E4 Mo 99 1.04EB 2.03E7 1.01E3 1 16E5 1.55ES I 131 1.36E9 1.60E9 7.04ES 5.26E11 1.87E9 I 133 1.81E7 2.64E7 7.72E6 4.79E9 3.10E7 6.29E7 1.02EB 3.46E7 1.40ES 1.02E10 1.42ES 1.02E9 4.68E5 1.3?EB 3.43E7 S. 72E7 4A6E6 Cs 134 2.41E10 4.49ELO 4.54E9 Cs 137 3A7ELO 4.06E10 2.88E9 Ba 140 1.21ES 1.21E5 6.22E6 1.16E10 4.74E9 1.22EB 1.09ELO 4AIE9 1.27EB 2.8?E4 7.42E4 2.97E?
<<<<Xa 141 1 86E2 N
Ce 14L<1 28E4 7.35E1 1.89EL 1.39E4 1.64E3 Ce 144 1A9E6 6.1QE5 8.34E4 4.28E3 2A6E5 8.63E5
- 7. 1BE6 8.54E?
<<mrem/yr per uCi/m3.
'<<<<Daughter Decay Product.
hctivfty level and effective half life assumed to equal parent nuclide.
NUCLIDE BONE TABLE 3-13 R
VALUES - CON MILR - CHILD i
m ~em/yr 4 nCi/sec 2
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 Co 58 Co 60
- 6. 94E6
- 2. 13E7 2.89E7 8.52E7 Zn 65
- 2. 63E9 7.00E9 4.35E9 4.41E9 Sr 89 3.64E9 Sr 90 7.53E10 1.04ES 1 91E10 Zr 95 2.17E3 4.77E2 4.25E2
- <<Nb 95 2.10E5 8 19E4 5 85E4 Mo 99 4.07E7 1.01E7 6.83E2 7'0E4 8.69E7 I 131 6.51ES 6.55ES 3.72E8 2.17EL1 1.08E9 I 133 8.58E6 1.06E7 4.0IE6 1.97E9 1.77E7 3.06E7 1.10ES 4.05E7 1.60ES 1.23E9, 1.41E8 1.01E9 4.98E5 1.52E8 3.37E7 5.83E7 4.27E6 Cs 134 1.50E10 2.45E10 5.18E9 Cs 137 2.17ELO 2.08ELO 3.07E9 Ba 140 5.87E7 5.14E4 3.43E6
<<<<La 140 8.92KL 3.12KL 1.05EL Ce 141 1.15E4 5.73E3 8.51E2 Ce 144 1.04E6 3.26E5 5.55E4 2.51E3 1.80E5 8.69K 5 7.15E6 8.49E7
- 7. 61E9 2.73E9 1.32E8 6.78E9 2.44E9 1.30ES 1.67E4 3.07E4 2.97E7
- mrem/yr per tTCi/m3.
<<<<Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide.
NOOIIDB BONE TABLE 3-14 R
VhLUES - COP MILK-TEEN i
m ~em/yr 4 uCi/sec 2
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 Mn 54 9 OIE6 1 79E6 2.69E6 1.85E7 2.58E4 1.44E4 5.66E3 3.69E4 4.34E6 Fe 59 2.81E7 6.57E7 2.54E7.
Co 58 Co 60 4.55E6 1.05E7 1.86E7 4.19E7 Zn 65 1.34E9 4.65E9 2.17E9 2.97E9 Sr 89 1.47E9 Sr 90 4.45E10 4.21E7 1.10ELO Zr 95 9.34E2 2.95E2 2.03E2
<<<<Nb 95 9 32FA 5.17E4 2.85E4 Mo 99 2.24E7 4.27E6 4.33E2 5.01E4 5.12E7 I 131 2.68E8 3.76ES 2.02E8 1.10EU.
6.47E8 I 133 3.53E6 5.99E6 1.83E6 8.36E8 1.05E7 2.07E7 1.55ES 6.27E7 2.42ES 1.97E9 1.75E8 1.25E9 6.80E5 2 21E8 4.01E7 7.44E7 4.53E6 Cs 134 6.49E9 1.53ELO 7.08E9 Cs 137 9.02E9 1 20ELO 4.18E9 Ba 140 2.43E7 2.98FA 1.57E6 4.85E9 1.85E9 1.90ES 4.0SE9 1.59E9 1.71ES 1.01E4 2.00FA 3.75E7
<<<<Ia 140 Ce 14L 3 73KL 1 83KL 4.87EO 4o67E3 3.12E3 3.58E2 Ce 144 4.22ES 1.74E5 2.27E4 1 B47E3 1.04E5 1.05E6
- 8. 91E6 1.06ES
<<mrem/yr per uCi/m3.
<<<<Daughter Decay Product.
Activitylevel and effective half life assumed to equal parent nuclide.
NUCLIDE BONE LIVEN TABLE 3-15 R
VALUES - COW MILK-ADULT i
m harem/yr 4 sCi/sec 2
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 Co 58 Co 60 2.70E6 6 05E6 1.10E7 2.42E7 Zn 65 8.71ES 2.77E9 1.25E9 1.85E9 Sr 89 7.99E8 Sr 90 3.15E10 2.29E7 7.74E9 Zr 95 5.34E2 1.71E2 1.16E2
<<<<Nb 95 5.46E4 3.04E4 1.63E4 Mo 99 1.24E7 2.36E6 2.69E2 3.00E4 2.81E7 I 131 1.48ES 2.12ES 1.21ES 6.94E10 3.63ES I 133 1.93E6 3.36E6 1.02E6 4.94ES 5.86E6 1.06E7 1.26E8 5.47E7 2.06ES 1.75E9 1.28E8 9 ~ 11ES 5.43E5 1.84E8 2.87E7
- 5. 58E7 3.02E6 Cs 134 3.74E9 8.89E9 7.27E9 Cs 137 4.97E9 6.80E9 4.46E9 Ba 140 1.35E7 1.69E4 8.83E5
- <<La 140 2.07E1 1.05El 2.76EO Ce 141 2 54E3 1.72E3 1.95E2 Ce 144 2 29E5 9.58E4 1.23E4
- 7. 99E2 5.68E4 7.67E5
- 6. 58E6 7.74E7 2.88E9 9.55E8 1.56ES 2.31E9 7.68ES 1.32ES 5.75E3 9.69E3 2.77E7
- mrem/yr.per uCi/m
~
<<<<Daughter Decay Product.
Activitylevel and effective half life assumed to equal parent nuclide.
NDGIZDE BONE TABLE 3-16 Ri VALUES - COW MEA,T - CHILD 2
m ~rem/yr 4 uCi/sec 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 Co 58 Co 60 9.41E6
- 2. 88E7 4.64E7 1.37E8 Zn 65 2.38ES 6.35ES 3.95ES 4.00E8 Sr 89 2.65ES Sr 90 7.01E9 7.57E6 1.78E9 Zr 95 1.51E6 3.32E5 2.95E5
- Nb 95 2.41E6 9.38E5.
6.71E5 Mo 99 5.42E4 1.34E4 4.75E5 8.82E5 1.16E5 I 131 8.27E6 8.32E6 4.73E6 2.75E9 1.37E7 I 133 2.87E-1 3.55E-1 1.34E-1 6.60E-l 5.92E-l 9.58E7 3.44E8 5.4 9E7 2.57ES 1.12E8 1 o03E7 9.44E7 3.46E8 1.74E9 4.48E4 7.40K5 1.43E-l Cs 134 6.09E8 1.00E9 2.11E8 Cs 137 8.99ES 8.60E8 1.27ES Ba 140 2.20E7 1.93E4 1.28E6
- eLa 140 1.67E2 5.84Ei 1.97E1 Ce MX 1.1784 5.82E3 8.64E2 Ce 144 1.48E6 4.65E5 7.91E4 2.55E3 2 57E5 1.63E6 7 26E6 1.21ES
- 3. 10ES 1.11ES 5.39E6 2.80ES 1.01ES 5.39E6 6.27E3 1.15E4 1.11E7
- mrem/yr per uCi/m3.
- Daughter Decay Product.
Activitylevel and effective half life assumed to equal parent nuclide.
NUCLIDE BONE TABLE 3-17 R
VALUES - COW MEAT - TEEN i
m ~em/y e uCi/sec 2
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 Co 58 Co 60 S.OSE6 1.86E7 3.90E7 8 80E7 Zn 65 1.59ES 5.52E8 2.57ES 3.53E8 Sr 89 1.40E8 Sr 90 5.42E9 4.0iE6 1.34E9 Zr 95 8.50E5 2.68ES 1.84E5 e*Nb 95 1.40E6 7.74E5 4.26E5 Mo 99 3.90E4 7.43E3 3.94E5 7.51ES 8.92E4 I 133 1.55E-l 2.62E-l 8 OOE-2 3.66E1 4.60E-l I 131 4.46E6 6 24E6 3.35E6 1.82E9 1.07E7 8.47E7 6.36ES 1.11E8 5.09E8 2.34E8 1.67E7 1.52ES 6.19E8 3.31E9 6.98E4 1.23E6 1.99E-1 Cs 134 3.46ES 8.13E8 3.77E8 Cs 137 4.88E8 6.49E8 2.26E8 Ba 140 1.19E7 1.46E4 7-68ES
- ~La 140 9.12E1 4.48E1 1.19E1 Ce 14K 6.19E3 4.14E3 4.75E2 Ce 144 7 87E5 3 26E5 4 23E4 1.95E3 1.94ES 2.57E6 1N18E7 1.98ES 2.58ES 9.87E7 1.01E7 2.21ES 8.58E7 9.24E6 4.95E3 9.8iE3 1.84E7
- mrem/yr per tzCi/m3.
- eDaughter Decay Product.
Activitylevel and effective half life assumed to equal parent nuclide.
77~
NUCLIDE BONE TABLE 3-18 Ri VALUES - COW MEA,T - ADULT 2
m ~em/yr w uCi/sec T. BODE INTROID KIDNET LUNG t
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 Hn 54 5.90E6 1.13E6 1.76E6
- 1. ME7 3.65E3 2.18E3 8.03E2 4.84E3 9.17E5 Fe 59 1.44E8 3.39ES 1.30E8 Co 58 Co 60 1.04E7 2.34E7 5.03E7 l.liES Za,65 2.26E8 7.19E8 3.25ES 4D81ES Sr 89 1.66ES Sr 90 8.38E9 4.76E6 2.06E9 Zr 95 1.06E6 3.40E5 2.30E5
- <<Nb 95 1.79E6 9.94E5 5.35ES Mo 99 4.71E4 8.97E3 5.34E5 9.83E5 1.07E5 X 131 5.37E6 7.67E6 4.40E6 2.52E9 1 32E7 I 133 1.85E-1 3.22E 1 9.81E-2 4.73EL 5.6iE-1 9 46E7 1.13E9 2.12E8 9.45E8 4.53ES 2.66E7 2.42ES 1.08E9 6.04E9 1.09E5 2 02E6 2.89E-1 Ce XC 7.38E3 4.99E3 5.66E2 Ce 144 9.33E5 3.90E5 5.0iE4 Cs 134 4.35ES 1G03E9 8.45ES Cs 137 5.88E8 8.04ES 5.26ES Ba 140 1G44E7 1.81E4 9.44E5
<<*IN 140 1GliE2 5G59KL 1.48EL 2.32E3 2 3IX5 4 10E6 1 91E7 3.16E&
3.35ES 1.11ES 1.81E7 2.73E8 9.07E7 1.56E7 6 15E3 1.04E4 2.97E7
<<mremlyr per iM/m3.
<<<<Daughter Decay Product.
Activitylevel and effective half life assumed to equal hereat nuclide.
NUCLIDE BONE TABLE 3-19 R
VALUES VEGETATION - CHILD i
2 m mremlyr
+ pCi/sec 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 Co 60 6.45E7 1.97EB 3.78KB 1.12E9 Zn 65
- 8. 12EB
- 2. 16E9 1.35E9 1.36E9 Sr 89 3.59ELO Sr 90 1.24E12 1.03E9
- 3. 15E11 Zr 95 3.86E6 8.50E5 7.56E5
- Nb 95 7.50E5 2.92E5 2 09E5 Mo 99 7.70E6 1.91E6 1.22E6 2.74E5 1.65E7 I 131 1.43EB 1.44KB
- 8. 16E7 4.75ELO 2.36EB I 133 3.52E6 4.35E6 1.65E6 B.OBES 7.25E6 3.76ES 2.10E9 3.80ES 1.39E9 1.67E10 8.86EB 5.40EB 6.37E6 1 ~ 28E7 1.75E6 Cs 134 1.60ELO 2.63E10 5.55E9 Cs 137 2.39ELO 2.29ELO 3.38E9 Ba 140 2.77EB 2.43E5 1.62E7
<<<<Ia 140 3.37E4 1.18E4 3.97E3 Ce 14K 6.56E5 3.27E5 4.85E4 Ce 144 1.27EB 3.98E7 6.78E6 1.43E5 2.21E7 3.28ES 4.08KB 1.04 E10 8.15E9 2.93E9 1.42KB 7.46E9 2.68E9 1.43ES
- 7. 90E4 1.45E5 1.40ES
<<mremlyr per uCilm
~
<<<<Daughter Decay Product.
Activitylevel and effective half life assumed to equal parent nuclide.
NUCLIDE BONE
- H 3 TABLE 3-20 R
VhLUES - VEGETATION TEEN i
2 m ~remlyr 4 uCilsec I. BODY TETROID KIDNET LUNG GI-III 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 Mn 54 4 54KB 9 OIE7 1.36EB 9.32EB 6.16E4 3.42E4 1.35E4 8 79E4 1.03E7 Pe 59 1.79EB 4.18EB 1.61ES Co 58 Co 60 4.37E7 1.01ES 2.49EB 5.60KB Zn 65 4.24EB 1.47E9 6.86KB 9.41EB Sr 89 1.51E10 Sr 90 7.51E11 4.33EB 1.85Ell Zr 95 1.72E6 5.44E5 3 74E5
- Nb 95 3.44E5 1.91E5 1.05E5 Mo 99 5.64E6 1.08E6 7.99E5 1.85E5 1.29E7 I 133 1.93E6 3.27E6 9.98E5 4.57EB 5.74E6 I 131 7 68E7 1 07ES 5.78E7 3.14E10 1.85ES 1.32EB 9.89EB 6.02EB 3.24E9 6.23EB 1.80E9
- 2. 11E10 1.26E9
- 8. 16EB 1.01E7
- 2. 13E7 2.48E6 Cs 134 7,10E9 1.67ELO 7 75E9 Cs 137 1.01KLO 1.35ELO 4.69E9 Ba 140 1.38ES 1.69E5 8.9iE6 5.31E9 2 03E9 2.0BEB 4.59E9 1 78E9 1.92EB 5.74E4 1 14E5 2.13KB
- LaQO 1.69E4 T
Ce 34L 2.83E5 8.32E3 2.21E3 1 89E5 2.17E4 2.83E6 Ce 144 5.27E7 2 18E7 8.89E4 1.30E7 4.78E8 5 40KB 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 ~em/yr i pCi/sec 2
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 Cr 51 Mn 54 3.13E8 5.97E7 9.31E7 1.79E5 1.79E5 1.79E5 1.79E5 4.64E4 2.77E4 1.02E4 6.15E4 1.79E5 1.17E7 9.58ES Fe 59 1.26ES 2.96ES 1.13ES 8.27E7 1.02E9 Co 58 3.0SE7 6.90E7 Co 60 1.67E8 3.69E8 Zn 65 3 17ES 1.01E9 4.56ES 6.75E8 Sr 89 9.96E9 Sr 90 6.05KLl 2.86E8 1.48E11 Zr 95 1.18E6 3.77E5 2.55E5
5.92E5
- Nb 95 2.41E5 1.34E5 7.20E4 1.32E5'o 99
6.14E6 1.17E6 1.39E7 I 131 8.07E7 1.15ES 6.61E7 3.78E10 1.98E8 I 133 2.08E6 3.61E6 1.10E6 5.31ES 6.30E6 6.24ES 3.14E9 6.36ES 1.60E9 1.75E10 1.20E9 8.13ES 1 ~42E7 3.05E7 3.25E6 Cs 134 4.67E9 l.ilE10 9.08E9 Cs 137 6.36E9 8.70E9 5.70E9 3.59E9 1.19E9 1.94E8 2.95E9 9.81ES 1.68ES 5.49E4 9.25E4 2.65ES Ba 140 1 29E8 eeLa ~ 1o58E4 Ce 1CU 1 97E5 1 61E5 8.42E6 7.93E3 2.11E3 1 33E5 1.51E4 5.86ES
- 5. 09E8 1.11E10 6 19E4 8.16E6 Ce 144 3.29E7 1 38E7 emrem/yr per uCi/m3
- eDaughter Decay product.
equal parent nuclide.
1.77E6 A,ctivitylevel and effective half life assumed to 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+**
Inhalation and Ground Plane Cow Milk Goat Milk<+
Meat hnimal Vegetation 1,600 E (104')
1,800 ESE (130') 4,300 E (89')
12,500 E (U.4 )
2,600 E (96')
2,900 2c00 E>>6 1.42E-7 4c llE-8 1.75E-8 1.17E-7 1.04E-7
- 2. 10E-9
- 2. 90E-9 4.73E-10 1.33E-10 1.86E-9 1.50E-9 S SSCK Sit@
Boundary***
Inhalation and Ground Plane
- 1) 600 E (109')
1,700 4.50'.48E-9 6.00'.34E-9 Cow Milk Goat Milkee Meat hnisa1 Vegetation ESE (135 ) 4,200 E (94 )
12,500 E (U.4')
2,500 lc05EW 1.80E-8 1.13' (96')
2,800 1 38E-S 3.64E-10 1.84E-10 1.15E-9 9 42E-10 NOIX:
Inhalation and Ground Plane ace gracing season only.
ex/Q aug.D/Q values from NMP-2 ER-OLS.
snd D/Q froa C.T. Main Data Report
- ++
D/Q fry NMP-2 FESs NUREG-1085s are annual average values.
Others dated Noveaber 1985.
May 1985.
IAQU AINAIAAI SIIAUSISIIU SOS IIA 5
SOelos r---
e I
~ylIA H
FE 2
tl lS Oft See 11 FI~fIes>>I AOe IA IA cAIAtelcntcowosdn l
OltSss IA Condsnasf..
ttt II IVISA
) leac
,I I'I SICOnO IOIOlP SK Hl IO OnrIAS IOOU COKXNSIO AH ASIANJL SISfIU VCLnt II IO UAH conolnlcn IO UAH COKXNIIn
~Cs I II 5
lAOU SOVIII 5ISIIU IS IS 2
FE OlfSss W
Fret>>e>>I 0t f5os IS Condenser lAOU ALNLIMf IIIAU SfSIIU SOefoo 5
~Oy IW Fef H
~t Cetstylte h os omblnof lll I
I et+
Figure 3-f
Title:
OFFGAS REGOMBINERS
AOvIA AOvIA Oryer IA N.
I icy SA LvfW
~h fO 'A'SIINGIAAIGASll 11 IAIVI OSIGAS Oryer IS TO CHARCOAL AO5ORO5RS Lvffe ICv SS ICv I~
fCv
~S IO 'O'AfrllsGSAAIOASlf IS Orysr IC ASS IC LO I
~C ISCLC>>
10 IIASI CCWQfleff8 Af1 IC AIAI1C SHCNWI fr1SCAL OS 11 ISCI C>>
Figure s-2 OFFGAS DRYER
Inou StlvrCS AIISISItrr I:ilier I
IAOQ
~OIIOAS O itsS IA IC CHARCOALAOSOR15R5 IO IA IrtPA IS Itnt
~VA~ A I
I I
I I
I I
I I
AOV I
~IA I I
PI 8
PIA VACLAAA AOVIIA IO I
I AOv
---i 0
~ rs
[Q AOVre)
F Ilier Pvr rn To Mein SlsclL Figure 3-3 OFFGAS SYSTEM CHARCOAL ASSORBERS
gy +0 VSI T4 ON OIACIOS OUIL4INC Vt NII LOTION AOVIA NOVI~
I SOUSE
~
I 1
NOT%4
~ IANOST CAS SILICA IOAIN ~
~44 NOVSS I~
I N
ACACIAS OUILSINO 1IA TSA KCAT NCAf COOL INO T ISO NALL IIO IOO MIN ~ IACN SIC I
VO~
TSOA TSIAAST CONIAIMCNI WACO WIST SOVIOO NOVI~I StAC ISA OUILOINO 1IASltNSOC I
1 AOVTA I
I NSVaA
~TAROT OAS fILTSA fSAIN 1 I
II I
rVSA AIA TSA KCAT NC1f C40L ISO TISC OASfttfISN NAIIA N4V OOA ll~
T ~
14VSA TAN l1 VO4 VS1 flASKL VOS St
~ fANOST CAS IStAINCNI SUILOINC OUfSIOO AIA Figure 3-I STANDBY GAS TREATMENT SY
>lets>>ll>>C
~>>I Iae elu IN>ll CI~
>>>>a<<l >>Nl>el QNW >VI Ias IIIII<<e Cae Cae
~a>>a>N IIf>>I
~al ~
gel>N Iae I>>>><<e
~II~ INN~
IH ISII
>illCle I>>>t I>>
el>I I II >>I
~a>>>Ill >>>le>el sl ~
aaa ~ >le>>la>>>>
eltl IllIll I
Ial I tea<<CNI II Cas
~ea IIIN>lNIC III~ II~I I>>><<e T
u Cal It Ia>I>5>> >>IIIII sells>ec I>aalu II~ I
~e I>el
>Sliult I'+3 l>>>We> ('I Ste>>8
>>III<<~
ua>>NI ~ >>
INQSI
~<< ~ 51>CI alIC>el WII~Iel IW>l Hlell>>C Ilue
~
I<< INe<<IIII>>
IIVI>>>>a CI$ ~
1 as
> ICRIII
. <<I~
Cae StCIIW g
- (>>> P I
(Wsj Sllclu <<>>elec elle>
~
iaiixa<<a we<<lwae IN>IN>>>>~i>X IIWKI~
SIIWlleC Ill>>
c>5 I ~
lac>I I Q ucw tt l '(iQIas I >IWIll
~IcIKwltl<<swt~ JI~IUI+IJ~
~
II>> >I>> <wtst
~
III
~I I
sa u>t+ u ca> tt L,
sa cll tt u cll I tal>>cwl>>
I fsh I
us lttg/
~ ~ Sect> 5 I>t Iws>el ls>ll>es Sle>>lll>W
>I>>ecl ~ I,I 0
u cll $$~ sa ul I Iau clt tt
'I' u>>
I sac>> tt Sl C>5 ~
$$15
~Iae <>>let teect llN~ Nae 5CIS S>> Cl~
<<les c> ~
L W.l>el g *; I wi >>>>c I~+I t>>>stet Wa1>la u cal 5
ucw ct I>>list Cllkll>W ~
gI>e Qlas 5 Ills SIICIS $1511 ~
5>VIC Iat Is>l>et Qtii IIIF IIII
~ ~. (>>Stet>IS u5 ~
lcl>tlIC>5 ~ IIce>Kt
>SKI>>W>
!Sa ISS
<<>K>>I aloe> l5 Sl CI~
Sastat Wt Salt>i Ilt u Cll $$
ucw CI
<<151st
~Il le>Ill IW CWISW WW I all>I It>$1> Hn ISISCI~
SIIIIC
>SIC> ~
Ie>>at IllSI I
~>cele>cal Iacew
~eet swcuscl I
I I>>I S5 I
IIIIISS n'
u cll tl uta
(
S
~st+ I<<tilt Ill
>I>>Iw>
Iu>
C)-.
'll IIC ut ~
ac>Ill>>$5 ICI>l>1>W>
SIV>t Wt CI5 ~
~g'5 ll> l>twt IC>>II>>WI Ieg uta It>lilt>$$ at> II>I>W>
C>>VIS>II
<>
>NI<<e la Cll 5 t>SICI~ I>>NII >>ae I>NIVI
~Cl ~ IS>>>I>>C CWIIW IWC>>W tae
~ ts$ 1 ICCIII~I e<<II>>
~ ~ tN>>CNIII ~ lcl>et last>lee Cltll>lail cae ~ cww<<>>5 la<<eeet ewllw
~ ~ utile'<<Salts lao>else FIGUIIE 3-5 GASEOUS RADIATION MONITOAINQ NIAGARAMOHAVAS POWER COAPOAAIION NINE MILE POINT-UNIT 2 FN4AL SAFETY ANALYSIS AEPOIIT i,
AMENDMENT23 DECEMBEFI IQI
DUALOLUTNH PARTCLLAYE COLLECT KTH STATION FLYER C
HEW PARTCU.
LATE CARYRO.
OES YOOWE COLLECTIOH STATION FLYER NEW lOOIHE CARTRE&
OES NOBLE GAS MEASUREMENT STATKW4 SlACK t
STACK~
R%SH AIY~FLYOVER P V V>>
FLOW COHYROL QSOk1%TCl AMPLFKR A AOC FLOWSENSORS VALVES.ETC 4 ADC MLLT CHATS.L ANALYZER YMCA)
HOST COMPUTER COMPUTER VIEOTERMNAL
. ~.
PHWTE4 8
NDUSTRIAL PROGRAMMABLE CONTROLLER FIGURE 3-6 BLOCK DIAGRAM TYPICALGASEOUS EFFLUENT MONITORINGSYSTEM 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
're, chemical conversion of uranium isotopic enrichment of 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 if possible, actioa vill be taken to reduce subsequent releases.
The report to the NRC shall contain:
2)
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.
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 vill utilize environmental TLD dosimetry.
Calculated measurements will utilize engineering calculatioas to determine a pro]ected direct dose component.
Ia the event calculations are used, the methodology vill be detailed es required in Section 6.9.1 8 of the Technical 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 4.1 (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.
Evaluation of Doses From Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, 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:
l The total dose to the liver of an adult (mazimum exposed organ) in mrem per year Cif
~
The concentration of radionuclide i in fish samples in pCi/gram 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.
4,3 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 willutilize the methodologies found in Regulatory Guide 1.109.
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.
where'
~
X i [Cip Z/Q DFL igaRat]
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 p
s The average concentration in the stack or vent release of radionuclide i in pCi/m for the period in question.
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 fishing occurs.
The dose will then be calculated using the sample
- results, the time period in question, and the methodology based on Regulatory Guide 1.109 as presented in Section 4.1.
The resultant dose may be adjusted for a
background dose by subtracting the applicable off-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 least two environmental TLDs will be utilixed 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).
0, 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 after adjusting for the appropriate time period (as applicable).
Zn the
.event of loss or theft of the TLDs, results from a TLD or TLDs in the area may be 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 Units 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.
Zf it is determined that a
milk sampling 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 Commission approved or sponsored Znterlaboratory Comparison
- Program, such as the Eph Crosscheck Program.
Participation shall be only for those media,
~.g., air, milk, water, etc.,
that are included in the Nine Mile Point 'nvironmental Monitoring 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
'esults shall be reported in the Annual Radiological Environmental 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.
5.3. 1 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.
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 If necessary, corrections shall be applied for the dependence of exposure interpretation on the length of the field cycle (ANSI N545>
section 4.3.3)
~
The average 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 MILEPOINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM SAMPUNG LOCATIONS TABLE 5.1 Type of t
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)'irect Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radlatieo (TLD)
Direct Radiation (TLD)
- Map 10 12 14 16 17 18 tl v
r Nine Mile Point Road North (R-1)
Co. Rt. 29 & Lake Road (R-2)
Co. Rt. 29 (R-3)
Village of Lycoming, NY (RA)
Montario Point Road (R-5)
North Shoreline Area (75)
North Shoreline Area (76)
North Shoreline Area (77)
North Shoreline Area (23)
JAP East Boundary (78)
Rt. 29 (79)
Rt. 29 (80)
Miner Road (81)
Miner Road (82)
Lakeview Road (83)
Lakeview Road (84)
Site Meteorological Tower (7)
Energy Information Center (18) 1.8miI 884 E 1.1 mi 5 1044 ESE 1.5 miI 1324 SE 1 8 mi O 1434 SE 16.4 miI 424 NE 0.1 m) O 54 N 0.1 mi O 254 NNE 0.2mi @454 NE 0.8 miI 704 ENE 1.0 mi O 904 E 1.1 mi O 1154 ESE 1,4mi O 1334 SE 1.6 miI 1594 SSE 1.6 mi O 1814 S 1.2 mi O 2004 SSW 1.1 mi O 2254 SW 0.7 mi O 2504 WSW 0.4 miI 2654 W
- Map ~
See Rgures 5.1-1 and 5.1<
99
002234LL NINE MILEPOINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM SAMPUNG LOCATIONS TABLE 5.1 (Continued)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD) 20 21 22 Direct Radiation (TLD) 23 Direct Radiation (TLD)
Direct Radiation (TLD) 24 25 Direct Radiation (TLD) 26 Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD).
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD) 27 28 29 30 31 32 33 34 35 36 Direct Radlatfoit (TLD) 37 Surface Water Surface Water 38 39 Type of I
Direct Radiation (TLD) 19 North Shoreline (85)
North Shoreline (86)
North Shoreline (87)
Hickory Grove (88)
Leavitt Road (89)
Rt, 104 (90)
Rt. 51A (91)
Maiden Lane Road (92)
Co. Rt. 53 (93)
Co. Rt. 1 (94)
Lake Shoreline (95)
Phoenix, NY Control (49)
S. W. Oswego, Control (14)
Scriba, NY (96)
Alcan Aluminum, Rt. 1A (58)
Lycoming, NY (97)
New Haven, NY (56)
W. Boundary, Bible Camp (15)
Lake Road (98)
OSS Inlet Canal (NA)
JAFNPP Inlet Canal (NA) 0.2 miI 2944 WNW 0.1 mi @ 315 O NW 0.1 miI 341 o NNW 4.5 mi 9 97o E 4.1 miI 111'SE 4.2 miI 135'E 4.8 mi 9 1564 SSE 4.4 mi@ 1834 S 4.4miI 2054 SSW 4.7 mi 5 2234 SW 4.1 miI 2374 WSW 19.8 miI 1634 S 12.6 miI 2264 SW 3.6 miI 199o SSW 3.1 miI 220o SW 1.8mi @143o SE 5.3 mi@ 1234 ESE 0.9 miI 2374 WSW 1.2miI 101o E 7.6 miI 2354 SW 0.5 miI 70O ENE (NA)
~
Not applicable:
- Map ~
See Rgures 5.1-1 and 5.T-2 100
002234U.
NINE MlLEPOINT NUCLEAR STATION RADIOLOGICALEhWRONMENTALMONITORINGPROGRAM SAMPUNG LOCATIONS TABLE 5.1 (Continued) 0 Type of I
Shoreline Sediment Fish Fish Fish Milk Milk Milk Milk Milk Milk Food Product Food Product Food Product Food Product Food Product Food Product "
40 42 43 45 46 47 64 65 66 48 49 50 52 n
V Sunset Bay Shoreline (NA)
NMP Site Discharge Area (NA)
NMP Site Discharge Area (NA)
Oswego Harbor Area (NA)
MilkLocation F50 MilkLocation iii7 MilkLocation f16 MilkLocation f65 MilkLocation 455 MilkLocation if60 MilkLocation f4 Produce Location 46
'Bergenstock)
(NA)
Produce Location Pl (Culeton) (NA)
Produce Location 4'2
'Vitullo)
(NA)
Produce Location $5~~
(C.S, Parkhurst) (NA)
Produce Location f3 (C. Narewski) (NA)
Produce Location 44 (P. Parkhurst) (NA) 1.5miI 80o E 0.3 mi@315o NW (and/or) 0.6 miI 554 NE 6.2 mi O 235o SW 8.2 mi 9 934 E 5.5 mi@1074 ESE 5.9mi O190o S 17.0 miI 2204 SW 9.0miI 95O E 9.5 miI 904 E 7.8miI 113~ESE 1.9 miI 141'E 1.7mI@ 96o E 1.9 miI 101 4 E 1.5 miI 114'SE 1.6 miI 844 E 2.1 miI 110o ESE Food Product (CR) 54 Produce Location f7~~
(Mc Millen) (NA) 15.0 miI 2234 SW
- Map ~
See Figures S.l-l and 5.1-2
~ Food Product Samples need not necessarily be collected from all Hated Iocathns.
Collected samples willbe of the:highest calculated site average D/Q.
(NA)
~
Not applicable CR
~
Control Result (location) 101
002234LL NINE MILEPOINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM SAMPUNG LOCATIONS TABLE 5.1 (Continued)
Type of
- Map Food Product (CR)
Food Product Food Product Food Product Food Product Food Product (CR)
Food Product Food Product Food Product 56 57 58 59 60 61 62 Produce Location ¹8 (Denman) (NA)
Produce Location ¹9 (O'onnor) (NA)
Produce Location ¹10 (C. Lawton) (NA)
Produce Location ¹11 (C, R. Parkhurst) (NA)
Produce Location ¹12 (Barton) (NA)
Produce Location ¹13 (Flack) (NA)
Produce Location ¹14 (Koeneke) (NA)
Produce Location ¹15 (Whaley) (NA)
Produce Location ¹1 6 (Murray) (NA) 12.6 mi O 2254 SW 1.6 mi@ 1714 S 2.2 mi O 1234 ESE 2.0miI 1124 ESE 1.9 miI 115'SE 15.6 miI 2254 SW 1.9 mi O 954 E 1.7 miI 1364 SE 1.2 miI 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 wiIIbe 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 of 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 villbe 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 villresult 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.
6.4 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.
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
'<<its (May 1986).
=104-
1
~ae 5
~ ~
5 sl I N
I OQ IA) 5 ~
10 5
15 I~
1$
14 lslXE scil 00 0
esp(
EC 5oacA)
I K
~s
'c5 sr m FIGURE 5.I-I Nine hfile Point On.Site Mep,c Cssssr~ee cesssrse g
C SW-cw c ~
(M) -sear~
I\\
lCO ~
CsAse Aria aae Assea sar
~
~a
~era
~
~ ~ SSSS a 0
e5 ~4m C)re rrseaeer 0
~sr S
5 se 50 11 15 IA
~sssse ~
es ela C'l gl
~ ss
'I (l'i 0
0 55 15 105
~
1 OE 4 4 yo FIGURE 5.l-2 NINE MILE POINT PFF-SITE MAP (5/92)
'hv6 SCILE OF. QQtS
~
~
lLOtND
- 04. 4 Coolo OCoaooyo............
Cooolr CooOo...,........,...,.....
7ooo Coooo.
CooeOg Uooo Toao Used.
Cllg4 VSagoUooo.,.......
CaolronacoCcl bayle LCCCIIM LAKE ON T ARIO C
C O
eeo
~
~
~oee eee oee ee w
N E
W V
E N
oko
<<0 eo eo wo s
~ e 0 NO
~
S 1
C I
ee
'qX I
C Iceo IleeOI
~ Iceel oeeeel
IC~
COuWy el all aeae T
0 A
H 0
T C
N C
I R
E 0
I
~ laeee
~ea IIeae
~eeere Caaeaa l
N II I
la alee X
I C
caela
~Illl Caae 4aacaaQCIal A
PI S
0 W
II I/I II
~
/
~
sL
~
0 I~I t>>
~I O>>sey 3
~ e<<se s>>
0 I>>s fl (I
~
S.~s, Page 3 ot 0
peas'I Ceeeen A
(.
Sa
~I N
Oa N
atCI>>essa w
fllLTO
~CI>>essa I
ass I N
N I
R A
N
~ease I Ca>>essa a,s W
s re(Ir ur
~'
e<<O &
Ao
<<a <<<<
(s
~<<
cOol(Y re Ww
~>>leI
~I (a $ysecaee
a+~
P IR I
H
+tm aces s
s'~g
/
C
/
J
~ee g~/"
~ sa t
S
]
M s
e Asskey Casaas s
0 0
Y I'll
~ ts Asses I; ):J
~
~ '
< ee
~e>>es sa
~see O
n Co>>la al O>>wo s'
ssesa g e ~w
~ ~ se
~>>e se
/"'
C 0
H T
A N
I A
asss>>
>>>>ea>>
ss s\\
te CaspCeC,
~
s ee QwN se
~>>s>> ea
~sa Cea
~see NNse ee aee
~ se
~e No
~ ss oo ss>>
MAO8
~ esca se
~s C
C4>>
graa l D I
lee>
Iseses>>
aces CQIs Asses Par
~IC.'Im<<CIIO<<u. CIeVCC, ICry CIsae4a>'snasssesl OCIIC
~040
'ICt<<OOVCCO CT tCC<<ICON COtTCIC<<f OWNCCC
<<CLCACC 1UIICC<< IICCC
E y
/
(a) kC1RL INN Cgllt'ai LWg kiiCN 0
0 ts)t
~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