ML20078M789

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Rev 10 to Offsite Dose Calculation Manual for LaSalle & Quad Cities
ML20078M789
Person / Time
Site: Quad Cities, LaSalle, 05000000
Issue date: 09/30/1983
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20078M778 List:
References
PROC-830930, NUDOCS 8310250298
Download: ML20078M789 (44)
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Text

,

CECO REVISION 10 SEPTEMBER 1983 O INSTRUCTIONS FOR UPDATING YOUR OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM are identified by a vertical line in the right margin of the page. To update your copy, remove and destroy the following pages and figures and insert pages and figures as indicated, and as updated pages are applicable to your volume only. Destroy those pages of this revision which do not apply to your particular volume of the ODCM.

REMOVE INSERT LA SALLE COUNTY STATION Chap ter 2.0 Pages 2.1-17 and 2.1-18 Pages 2.1-17 and 2.1-18 Page 2.2-4 Page 2.2-4 Chapter 4.0 Page 4-1 Page 4-1 Pages 4.1-1 and 4.1-2 Pages 4.1-1 through 4.1-3 Chapter 8.0 Pages 8.l~4 through 8.1-6 Pages 8.1-4 through 8.1-6 Page 8.4 -2 Page 8.4-2 Pages 8.4-5 and 8.4-6 Pages 8.4-5 and 8.4-6  !

QUAD CITIES Chapter 8.0 Pages 8-1 through 8-111 Pages 8-i through 8-111 Pages 0.1-1 through 8.1-9 Pages 8.1-1 through 8.1-10 Pages 8.2-1 through 8.2-6 Pages 8.2-1 through 8.2-6 Page 8.3-1 Page 8.3-1 i Pages 8.4-1 through 8.4-8 Pages 8.4-1 through 8.4-8 Figures 8.4-1 and 8.4-2 Figures 8.4-1 and 8.4-2 0310250298 031021 PDR ADOCK 050002gg P

1 l i

._ __ . _ _ _ _ _ _ . . _ _ - _ - _ - ~ . . _

l l

\

REVISION 5

-() FEBRUARY 19 8 3 )

l l

Pp Meat Fraction (days /kg) l The fraction of the animal's daily intake of radionuclide i which appears in each kilogram of flesh. See Table 7.1-4.

tg Slaughter to Consumption Time (hr)

The time from slaughter consumption, See Table 7.1-2.

1 2.1.2.1.2 Inhalation + Food Pathways Dose, Calendar Year '

(Four Consecutive Quarters) 3.17 x 10-8 x 10 6 p a DFA ija ( x 01 s his + ( XO v A iv + ( X/0) A ig

( i - -

+U <l5 arem 65 DFI ija U f p

C a i+ I V C{+U Cf

~ ~

(2.17) 2.1.2.2 10 CFR 20 Release Rate Limit The maximum dose rate to an organ of an adult from all radio- l nuclides, radioactive materials in particulate form, and radio-nuclides other than noble gases with half-lives greater than

[

8 days shall be limited to the values given by the equations which follow. For purposes of demonstrating compliance with the Technical Specifications, the dose to the adult from the inhalation pathway shall be considered limiting.

A V

2.1-17

REVISION 5

[ FEBRUARY 19 8 3 O. ~

6 +

10 R DFA ija IX OI s 0 13 + ( Vol y O iy + ( VO) g Q ig i .

K DFI ija U Cf < 1500 mrem /yr (2.18)

K Seasonal Adjustment Factor K is a seasonal adjustment factor to account for nongrazing. For purposes of demonstrating technical compliance for the inhalation pathway, l

K = 0 throughout the year.

Milk Concentration (pCi /li ter)

Of The concentration of radionuclide i in milk.

j Cf=FM Cf Wg exp (-Ai t M I*

l Cf Feed Concentration (pCi/kg)

, The concentration of radionuclide i in feed.

C. =d 1

xr 1 - exp (- A Ei tIe-i _

A (2.20)

Yv Ei (Note that this assumes feed to be 100%

_ pasture grass.)

d Deposition Rate (pCi/m x hri i

Q ig (D/0)g (2.21)

O 2.1-18

-REVISION 5 FEBRUARY 1983 Cf' Concentration in the Discharge Tank (pCi/ml)

The' concentration of radionuclide i in the (radwaste discharge or other similar) tank.

F Flow Rate, Radwaste Discharge (ft /sec)

The flow rate of radwaste from the discharge tank to the initial dilution stream.

F Flow Rate, Initial Dilution Stream (ft /sec)

The flow rate of the initial dilution stream j which carries the radionuclides to the un-restricted area boundary (e.g., the blow-down from cooling tower or lake or the circulating cooling water flow).

MPC g Maximum Permissible Concentration (UCi/ml) r The maximum permissible concentration of nuclide 1

}

(or unknown nuclide) in water in the unrestricted

. area (see Table 7.1-10; or 10 CFR 20, Appendix B, Table II, Column 2 including Note 3.c).

2.2.3 10 CFR 20 Maximum Permissible Concentrations at the Nearest Surface Water Supply The quantity of radionuclides, excluding tritium and dissolved or entrained noble gases, in outdoor tanks without overflow pipes connected to other storage tanks shall be limited to ensure that in the case of an overflow, the annual average con-centration of radioactivity in the potable water of the nearest surface water supply is less than the 10 CFR 20, Appendix B,

. Table II, Column 2 limits.

The annual average concentration of each radionuclide in the potable water of the nearest surface water supply is calculated as follows:

(

F

(- A g x t")

exp x C"=.Cf(I (w*Io t

)

Mg 8760 (2.29) 2.2-4 m

i REVISION 5 FEBRUARY 1983 j 4.0 AQUATIC TRANSPORT AND DOSE MODELS TABLE OF CONTENTS PAGE 4.0 AQUATIC TRANSPORT AND DOSE MODELS 4.1-1 4.1 AQiaTIC TRANSPORT 4.1-1 4.1.1 River Model 4.1-1 4.1.2 Lake Michigan Model 4.1-1 4.1.3 Symbols Used in Section 4.1 4.1-3 l 4.2 AQUATIC DOSE MODEL 4.2-1 4.2.1 Symbols Used in Section 4.2 4.2-2 4.3 AQUATIC TRANSPORT DURING TANK OVERFLOh' CONDITIONS 4.3-1 4.3.1 River Model 4.3-1 4.3.2 Lake Michigan Model 4.3-1

, 4.3.3 Symbols Used in Section 4.3 4.3-2 E

i j

O 4-1

- . . _ , _ _ - , - _ _ - _ . _ , . . _ . . - . _ . . . . _ _ _ - - _ . , _ . _ _ _ , _ , _ _ . _ _ _ _ , . . - _ _ . , _ . ~ . _ _ _

REVISION 5 FEBRUARY 1983 A

U 4.0 AQUATIC TRANSPORT AND DOSE MODELS 4.1 AQUATIC TRANSPORT Dose via the aquatic pathway is discussed in Section 2.2.

Two dilution factors are considered; F, the flow of the receiving body of water; and 1/M, an additional dilution factor.

4.1.1 River Model For purposes of calculating the drinking water dose from liquid effluents discharged into a river, it is assumed that total mixing of the discharge in the river flow (F W) occurs prior to consumption. No additional dilution is assumed to occur; thus 1/M" equals 1.0. The river flow is taken as the long-term (generally 10 years) average. The nearest potable water intakes on the receiving bodies of water are described in a footnote to f)')

Table 7.2-1.

l I For the fish consumption pathway, a near-field dilution flow F f is used; 1/Mf = 1.0.

4.1.2 Lake Michigan Model For purposes of calculating dose from liquid effluents dis-charged to Lake Michigan, it is assumed that the concentra-tion of radioactivity is diluted initially in the condenser cooling water of flow (F c) and than by an additional factor 1/M" of 60 prior to consumption as potable water. The dilution factor of 60 is the product of the initial entrainment dilution (factor of 10); the plume dilution (factor of 3 over approximately I

1 mile); and the current direction frequency (annual average factor of 2).

,n.

(y,)

4.1-1

s REVISION 5 FEBRUARY 1983 For the fish ingestion pathway only, it is assumed the radio-

-activity is diluted fully in a hypothetical river of flow F;f 1/M f = 1.0. To determine F I , it was assumed that the near shore lake current (which can vary in width from 2 to 10 miles) constitutes a " river" 5 miles wide, 50 feet deep (the average lake depth from shore to 5 miles near Zion), and flows at the offshore, measured average speed of 0.2 mile per hour. This results in Ff = 4.0 x 105 3 ft 73,c, t'

i l

l l

l l

l 4.1-2

REVISION 5 e- FEBRUARY 1983

, s' 4.1.3 Symbols Used In Section 4.1 SYMBOL NAME UNIT F Flow of the Receiving Body of Water 1/M Additional Dilution Factor F" Average Flow Rate (ft /sec)

(Drinking Water Pathway) 1/M" Additional Dilution Factor (Drinking Water Pathway) f F Near-Field Flow Rate (ft /sec)

( ). (Fish Ingestion Pathway)

I 1/M Additional Dilution Factor (Fish Ingestion Pathway)

F c Average Flow of the (gal / min)

Condenser Cooling Water During the Period of

! Discharge I

l O

4.1-3

p1 i LA SALLE REVISION 10 SEPTEMBER 1983 The mid- and high-range detection systems consists of solid-state CdTe (Cl) detectors, shielded sample chambers, and pre-ampliers. Signals from the three detection systems are processed by a microprocessor which also controls the system pumps and monitors process stream and sample flowrates. The individual detection system outputs and other system parameters are displayed on a digital readout and control module. A three-pen recorder is utilized to record the individual detection system results in pCi/cm 3. The detection system whose output is indicative of the existing release activity is converted by the micropro-cessor to pCi/sec utilizing the existing process stream flowrate and recorded on a single-pen recorder. This pCi/sec value is also compared to an operator-entered alarm point.

The recorders and digital readout and control module are located

(#l

\- in the main control room. The sample conditioning skid, detec-tion skid, and microprocessor are located in the auxiliary building on the 796 ft 6 in, elevation. Power is supplied to this monitor from Division 1 power.

Detector efficiencies are initially determined by calibration ,

with Xe-133 gas. Once operational, efficiency factors will be based on monitor response and isotopic analysis data.

j The alarm setpoint for this monitor will be selected to ensure that the combined release rate of the station vent stack and SGTS stack does not exceed the most conservative release limit determined from Equations 8.1 and 8.3 by setting the alarm point at or below'one-half the release limit.

8.1.4 Standby Gas Treatment Stack Monitor Release of radioactivity from the standby gas treatment system (SGPS) stack is monitored by one of three SGPS monitoring systems.

! 8.1-4 i .- - - . .-, ,. .- - - - ., - - - , , - - - . . .-

LA SALLE REVISION 10

[

ss SEPTEMBER 1983 l

Two of the systems consist of a beta sensitive scintillation detector for particulate; a beta sensitive reintillation detector for low-range noble gas; a beta sensitive scintillation detector for-high-range noble gas; and a gamma sensitive scintillation detector for iodine. Provisions are made for system inlet and outlet ~ grab samples.

The monitoring system uses a microprocessor to analyze the data from the beta and gamma scintillation detectors. This micro-processor performs background subtracticn and compares the radi-ation values against operator entered alarm limits. A four-pen strip chart recorder records the monitoring syster output..

Alarms are located in the main control room.

~

Power is supplied to this monitor subsystem from Division 2

[') power. The equipment for each monitoring channel is skid mounted and located on the 786 ft 6 in. elevation in the auxiliary building.

4 The third SGPS monitor (OPLD23) utilizes an isokinetic probe to sample the effluent stream prior to discharge into the atmosphere.

The offline monitor consists of three detection systems. Gas flow through the system is provided by vacuum pumps; one for the low-range detection system and one for the mid- and high-range detection systems. A sample conditioning skid, upstream of the detection system, filters particulate and iodine and provides for collection of particulate and iodine grab samples.

The low-range detection system consists of a beta scintillation detector, a shielded sampling chamber, and a preamplifier.

The mid- and high-range detection systems consist of solid-state CdTe (C1) detectors, shielded sample chambers, and preamplifiers. Signals from the three detection systems (GT are processed by a microprocessor which also controls the system pumps and monitors process stream and sample flowrates.

8.1-5

E

/^g LA SALLE

- ( ,/ REVISION 10 SEPTEMBER 1983 The individual detection system outputs and other system para-meters arc displayed on a digital readout and control module.

A three-pen recorder is utilized to record the individual detec-tion system results in pCi/cm 3. The detection system whose l output is indicative of the existing release activity is coa-verted by the microprocessor to pCi/sec utilizing the existing process stream flowrate and recorded on a single-pen recorder.

This pCi/sec value is also compared to an operator-entered alarm point.

The recorders and digital readout and control module are located in the main control room. The sample conditioning skid, detec-tion skid, and microprocessor are located in the auxiliary building on the 796 ft 6 in. elevation. Power is supplied to this monitor from Division 2 power.

Detector efficiencies are initially determined by calibration with Xe-133 gas. Once operational, efficiency factors will be based on monitor response and isotopic analysis data.

The alarm setpoint for this monitor will be selected to ensure that the combined release rate of the station vent stack and SGTS stack does not exceed the most conservative release limit i determined from Equations 8.1 atid 8.3 by setting the alarm point at or below one-half the release limit.

8.1.5 SJAE Off-Gas Monitors The steam jet air ejector (SJAE) monitor subsystem continually measures and records the gamma radiation in the off-gas as it i

is drawn from the main condenser by the steam jet air ejectors before it passes through the holdup line and carbon beds enroute p_

( ,) to the ststion vent stack.

8.1-6

.-. . m._, . , _ __ _ - - - - _ - . _ _. - _ - ~ _ _ -

O O O TABLE 8.4-1 RADIOLOGICAL MONITORING PROGRAM (1982 - 1984)

TYPE AND FREQUENCY FREQUENCY NONROUTINE SAMPLE MEDIUM 0F ANALYSIS

  • COLLECTION SITES OF COLLECTING REPORTING LEVELS
1. Airborne
a. Particulate Gross beta - W. Seneca, Marseilles, Continuous Cs-134, 10 pCi/m 3 Filter Sr 89, 90 - Q. comp. Ottawa, Grand Ridge operation of a Cs-137, 20 pCi/m 3 Gama Spec. - Q. comp. Streator, Ransom, sampler for a Route 6 at Gonnam Road, week Kernan, and six stations near the site (see Figure 8.4-1) 5 vi m b. Charcoal I-131 Same as for la Continuous 0.9 pCi/m 3 ,

b Cartridge coeration of a m 4 < gler for weeks

2. TLD Gama Same as for la, plus 24 Quarterly None Radiation other sites distributed near the site boundary and at 5 miles (see Figures 8.4-1 and 8.4-2)

Minimum of 2 TLD's per packet g 35 m u,

3. Surface Water Sr-89, 90 - Q. ccmp. Illinois River at intake Gamma Spec. - M. comp. of Illinois Nitrogen Corp.

Weekly **

h

o Gross beta - W. Illinois River at Marsellies go Tritium - Q. comp. Illinois River at Ottawa ,m Illinois River at Seneca South Kickapoo Creek Cooling lake near recreation area

r] /^g A_

_Y N-]

TABLE 8.4-2 RADIOLOGICAL MONITORING PROGRAM (1985 and later)

NONR00 TINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS **

1. Air a. Onsite and near field
  • a. Filter - a. Continuous Cs-134, 10; 3

Monitoring gross beta *** operation of a Cs-137, 20 pCi/m

1. Nearsite Station 1 sampler for a
2. Onsite Station 2 week
3. Onsite Station 3
4. Nearsite Station 4 b. Charcoal - b. Continuous 0.9 pCi/m 3
5. Onsite Station 5 I-131 operation of a
6. Nearsite Station 6 sampler for r-2 weeks 2"

. c. Sampling c. Weekly Not Applicable p

?

Train - m Test and Maintenance

b. Far Field *
7. Seneca a. Fiiter a. Continuous Cs-134, 10; 3
8. Marseilles Exchange operation of a Cs-137, 20 pCi/m
9. Grand Ridge sampler for a when analyses
10. Streator week are made
11. Ransom M
12. Kernan b. Charcoal b. Continuous 0.9 pCi/m3 35
13. Route 6 at Exchange operation of a when analyses 9!^

Gonnam Road sampler for are made R@

14. Ottawa 2 weeks N G
c. Sampling c. Weekly Not Applicable $

Train -

Test and Maintenance

l O O' O TABLE 8.4-2 (Cont'd)

NONROUTINE SAMPLE MEDIA COLLECTION SITE- TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS **

2. TLD a. Same as Item I, Idr Ganna Quarterly None Monitoring Sites
  • Radiation
b. Plus 24 other sites distributed about the 'I site boundary and at 5 miles * (minimum of 2 TLD's per packet)
3. Fish a. Marseilles Pool of Gamma Semi-annual pCi/kg wet weight Illinois River Isotopic Mn-54 3 x 10 44 r Co-58 3 x 10

+ *m Zn-65 2 x 10 43 $

i

Fe-59 1 x 10 4 Co-60 1 x 10

,3 Cs-138 1 x 10 3 4 Milk a. Three nearby dairies I-131 a. Weekly pCi/l or private animals during including the nearest, grazing' I 131 3 Cs-134' 70 if possible season, May Cs-137 60 to October Ba-La-140, 300

b. Monthly, Same as above gx i November m<

, to April ME w

i

QUAD-CITIES REVISION 10 SEPTEMBER 1983 (J~'}

8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS ,

MODELS FOR SETTING GASEOUS AND LIOUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS ,

AND ENVIRONMENTAL RADIOLOGICAL MONITORING TABLE OF CONTENTS PAGE 8.1 GASEOUS RELEASES 8.1-1 8.1.1 System Design 8.1-1 8.1.1.1 Gaseous Radioactive Waste Treatment System 8.1-1 8.1.2 Alarm and Trip Setpoints 8.1-1 8.1.3 Main Chimney Releases 8.1-3 8.1.3.1 Chimney Noble Gas Monitors 8.1-3 8.1.3.2 SJAE Off-Gas Monitors 8.1-4 jS 8.1.3.3 Allocation of Effluents from Common

(,) Release Points 8.1-5 8.1.4 Reactor Building Ventilation Stack Releases 8.1-5 8.1.4.1 Ventilation Stack Monitors 8.1-5 8.1.4.2 Allocation of Ef fluents from Common Release Points 8.1-7 8.1.5 Symbols Used in Section 8.1 8.1-8 8.1.6 Constants Used in Section 8.1 8.1-10 8.2 LIQUID RELEASES 8.2.1 8.2.1 System Design 8.2-1 8.2.2 Alarm Setpoints 8.2-1 8.2.3 Radwaste Discharge Line Releases 8.2-2 8.2.3.1 Radwaste Discharge Monitor 8.2-2 8.2.3.2 Allocation of Effluents from Common Release Points 8.2-3 8.2.3.3 Administrative and Procedural Controls for Radwaste Discharges 8.2-3 8.2.4 Service Water Header Releases 8.2-4 8.2.4.1 Service Water Effluent Monitors 8.2-4 8.2.5 Determination of Initial Dilution Stream Flow Rates 8.2-5 8.2.6 Symbols Used in Section 8.2 8.2-6

[~

\-

8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 8-i

QUAD-CITIES REVISION 7

) MARCH 1983

) l 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS ,

MODELS FOR SETTING GACEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICQ MOMITORING LIST OF TABLES I

TITLE PAGE NUMBER 8.4-1 Radio!.ogical Monitoring Program 8.4-2 8.4-2 Practical Lower Limits of Detection (LLD) for Environmental Radiological Monitoring Program 8.4-6 8.4 3 Environmental Radiological Monitoring Sampling Codes 8.4-7

.O h

W 8-11

+w "ge-- p yyg-%-,-- m--g-t3g-w7m ww-+m, w, r m y9,pwyng,g---g-%-y---.In--**gMe me- g--tit *= W w^$yev * ~v+ g-- e r e9 g '-a ur mop *-F y wp+m--+

QUAD-CITIES REVISION 7 MARCH 1983 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS,

, i AND ENVIRONMENTAL RADIOLOGICAL MONITORING I

LIST OF FIGURES NUMBER TITLE 1

8.4-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 8.4-2 Inner Ring TLD Locations O

6 l

4 8-iii

}

QUAD-CITIES REVISION 10 SEPTEMBER 1983 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS ,

MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SWPOINTS ,

AND ENVIRONMENTAL RADIOLOGICAL MONITORING 8.1 GASEOUS RELEASES 8.1.1 System Design -

8.1.1.1 Gaseous Radwaste Treatment System A gaseous radwaste treatment system shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the primary system and pro-viding for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

8.1.2 Alarm and Trip Setpoints Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of ventilation exhaust air containing radioactivity are established to ensure that the release limits of 10 CFR 20 are not exceeded. The setpoints are found by solving Equations 2.9 and 2.10 for each class of release.

For this evaluation the radioactivity mixture in the exhaust air is assumed to have the composition of gases listeo in Table 3-3 from " Technical Derivation of BWR 1971 Design Basis Radioactive Material Source Terms", NEDO-10871, March 1973, General Electric Company. This mixture of radioactive gases

'is representative of the activity found at the point of release from the fuel with no radioactive decay accounted for.

Equation 2.9 is rewritten using the fractional composition of each nuclide, f i, and a total release rate, Qt , f r each class:

1.11 Q ts b*f) i i

+O tv b*f) i i

< 500 (8.1) rut,si

QUAD-CITIES REVISION 10 SEPTEMBER 1983 f

i Fractional Radionuclide Composition The release rate of radionuclide i divided by the total release of all radionuclides.

Q ts Total Release Rate, Stack Release (pCi/sec)

The release rate for all radionuclides due to a stack release.

O tv Total Release Rate, (pCi/sec)

Vent Release The release rate for all radionuclides due to a vent release. l r

l Equation 8.1 can be solved for Q for each class of release t

for release limit determinations.

Similarly, Equation 2.10 can be rewritten:

E **P I- Ai R/3600us) + W/Q)y O gy f f exp(- l R/3600uy)

O ts fi i

_ G/0)s i

+ 1.11 SQi ts i + V Qtvf i f

i

<3000 r (8.2) ,

4 Equation 8.2 can be solved for Q f r each class of release and t

a corresponding release limit be determined. The most conservative release limit determined from Equations 8.1 and 8.2 will be used in selecting the appropriate alarm and trip setpoints for each class of release.

l The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded.

Surveillance frequencies for gaseous effluent monitors will be as stated in Table 4.2-4 of the Technical Specifications.

Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.

w

+

QUAD-CITIES REVISION 10

() SEPTEMBER 1983 8.1.3 Main Chimney Releases

,. 8.1.3.1 Chimney Noble Gas Monitors Releases of radioactive noble gases from the main chimney release point are continuously monitored by an of f-line mon-itoring system consisting of two instrument channels, each of which uses a scintillation detector as its sensing element.

Samples of the effluent stream are taken high in the chimney, where good mixing is ensured, and drawn through a constant flow-and-pump network, past the detectors.

Each monitoring channel consists of & 2-inch by 2-inch sodium iodide-thallium activated scintillation detector, shielded sample chamber, pulse preamplifier, and process radiation

() (log count) monitor with integral power supply for providing high voltage to the detector. The channels share a common i recorder and common trip auxiliaries unit whose output initiate high radiation alarm annunciations. The recorder, alarms, and remote control switches for the chimney gas monitoring system are located in the main control room. The sample pumps and detectors, with local controls, are located in the chimney sample house at the base of the chimney.

Power is supplied to the process radiation monitors from the station 48/24-vdc. battery systems. The monitor display has a logarithmic scale with a range of 10 -1 to 10 6 counts per i

second. The detectors equipment part numbers are RE 1/2-1731A and RE 1/2-1731B.

The main chimney noble gas monitor alarm setpoints will be selected to ensure that the combined release rate of

{}

.the main chimney and the reactor building vent stack does not exceed the most conservative release limit determined from Equations 8.1 and 8.2.

. 8.1-3

QUAD-CITIES REVISION 10 SEPTEMBER 1983

.V 8.1.3.2 SJAE Off-Gas Monitors The major source of radioactive noble gases is from each unit's off-gas system. Each unit's off-gas system has.its own radia-tion detection instrumentation capable of isolating the off-gas release pathway.

Off-gas from the main condenser is monitored for gross gamma activity downstream of the steam jet air ejectors (SJAE) and prior to release' to the main chimney. Continuous radiation monitoring is maintained on the off-gas hold-up pipe. The off-gas mon-itoring system for each unit is performed in two channels, each of which includes a gamma sensitive ion-chamber detector, and a logarithmic radiation monitor with integral power supply.

The two channels share a common two-pen recorder and a trip auxiliaries unit whose output feeds an interval timer. System

!/,_)s controls, alarm annunciators, recorder, and displays are located on panels in the main control room. The ion-chamber detectors

, are mounted adjacent to and at the beginning of the off-gas hold-up pipe, a 36-inch diameter header whose function is to contain the off-gas for a period of time dependent on off-gas flow and allow for radioactive decay prior to release tc the chimney.

A h.igh radiation condition in the hold-up pipe will initiate an interval timer with a variable setting of 0 to 15 minutes.

When the preselected time interval has elapsed, an isolation valve at the inlet to the chimney from the off-gas system will automatically close, preventing release of radioactive gases from the affected off-gas system.

Power is supplied to the off-gas process radiation monitors from the station's 48/24-Vdc battery systems. Power to the

[/)

s_ '

interval timer is from the 120-Vac essential service bus, The timer provides the signal to the solenoid-operated valves which control the air supply to the air-operated isolation 8.1-4

Ci.1 I LJ:

? s

. QUAD-CITIES REVISION 10 SEPTEMBER 1983

("$)_

V valve (equipment part number A0 1(2)-5406) . The monitor display 6

is a logarithmic scale and has a range of 1 to 10 units (mR/hr). 1 The detectors equipment part numbers are RE 1(2)-1733A and

/ RE 1(2)-1733B'.

The SJAE monJ tor alarm setpoints will be selected to ensure that the combined release rate of the main chimney and station i vent stack does not~ exceed the most conservative release limit determined from Equations 8.1 and 8.2.

8.1.3.3 Allocatior of Ef fluents f rom Common Release Points Radioactive gaseous effluents released from the main chimney are comprised of contributions from both units. Under normal operating conditions, it is difficult to allocate the radio-activity between units due to fuel performance, in-plant leakage,

(/)

s 0 ', power history, and other variables. Consequently, allocation

,. 't will ,normally be made evenly between the units. During extended unit shutdowns or periods of known differences, the apportionment will be adjusted accordingly. The allocation of the effluents will be made on a monthly basis.

. 8.1.4 Reactor Building Ventilation Stack Releases

- 8.1.4.1 Ventilation Stack Monitors 6-Releases of radioactive noble gases from each reactor building's

-[ ventilation systen are monitored prior to introduction to i the ventilation stack. Two sensor and converter (detector)

' units are located in each unit's reactor building exhaust duct, and provide continuous gamma radiation monitoring.

The sensor is a Geiger-Mueller tube, polarized by high voltage

{~')

The output signal from each sensor from the power supply.

converter is applied to an indicator and trip unit, where 8.1-5

, - ~ . _ _ _ _ _ _ _ . - -

1983

,s QUAD-CITIES REVISION 10

.l%.J) . SEPTEMBER 19 8 3 l

it is amplified and used to drive a meter. This unit also provides trip functions for upscale cnd dcwnscale alarms through auxiliary units. A downscale trip in either channel annunciates a low radiation (malfunction) alarm. An upscale trip in either channel initiates a reactor building ventilation system high-high radiation alarm. Control logic is such that one channel high level trip or two channel low level trips will shut down and isolate the reactor building ventilation system for both units and initiate the standby gas treatnient systam.

The exhaust duct monitors provide a signal to a two-pen recorder which will annunciate a high radiation condition in the exhaust duct. This is an alarm only, and does not initiate corrective action. The recorder, controls, indicator and trip units, alarms, and annunciators are located on p'anels in the main

n}

\_/

control room.

The power supply to each sensor channel is supplied from a different power source. The A channel is fed from the 120-Vac.

A reactor protection system and the B channel are fed from the 120-Vac B reactor protection system.

The indicating meters have a logarithmic scale with a range of 0.01 to 100 mR/hr. The sensor and converter units have equipment part numbers RE 1(2)-1735A and RE 1(2)-1735B.

Each reactor building's ventilation system is isolated by closure of two air-operated butterfly valves (.A 0 1(2) A-5741 and A0 1(2)B-5741) located in series downstream of the reactor building ventilation supply fans, and by closure of two air-operated butterfly valves (A0 1(2) A-5742 and A0 1(2)B-5742)

[w/)- located in series downstream of the radiation sensors and up-stream of the exhaust fans. Air supplies to these valves 8.1-6

~

d

' r~ QUAD-CITIES REVISION 10

(, SEPTEMBER 1983 are controlled by solenoid valves powered from the 125-Vdc station battery systems. The control logic relays which operate these. solenoids-are powered by the 120-Vac essential service bus.

The reactor building ventilation stack monitor alarm setpoint

~

will be 2 mR/hr above background. Using an empirical relationship of mR/hr and p/Ci/sec at design flowrates, the' calculated reactor building ventilation stack release rate will be. employed in Equation 8.1 and 8.2 to select the.most conservative main chimney monitor alarm setpoints.

8.1.4.2 Allocation of Effluents from Common Release Points

- Radioactive gaseous effluents released from the reactor building

() vent stack are comprised of contributions from both units.

of noble gas contributions from each unit will be made by analyzing Estimates grab samples from the individual units. Allocations of radioiodine and radioactive particulate releases will be made by analyzing samples taken-from continuous samples on each unit. The allocation of the effluents will be made on a monthly basis. ,

e

. uj r

8.1-7 .

. - _ - - . _ , . . - __, . _ . _ , _ _ ._ ._. _ _ _ . _ . _ . _ . . . - - _ - _ - _ . , , , , _ . ~ , , _ . - - _ , _ ,_ , _

. - . ~ .- __ - . - . .

4 QUAD-CITIES REVISION 10 SEPTEMBER 1983 l

0

8.1.5 Symbols Used in Section 8.1 SYMBOL NAME UNIT Q ts Total Release Rate, Stack Release (pCi/sec) 5g Gamma Whole Body Dose Constant, Stack -(mrad /yr per Release pCi/sec) f g- Fractional Radionuclide Composition O tv Total Release Rate, Ground Level (pCi/sec)

V Gamma Whole Body Dose Constant, (mrad /yr per Vent Release pCi/sec))

(~N Q is Release Rate of Nuclide i, Stack Release (pCi/sec) i O gy Release Rate of Nuclide i, Vent Release (pCi/sec)

Lg Beta Skin Dose Constant (mrem /yr per 3

UCi/m )

Relative Effluent Concentration, 3 (X/Q) s (sec/m )

Vent Stack Release

.A g Radiological Decay Constant (hr-1)

R Downwind Range (m) u Average Wind Speed, Stack Release (m/sec) s 8.1-8

. I i

QUAD-CITIES REVISION 10 <

^O, '

SEPTEMBER 1983 SYMBOL NAME UNIT (X/Q) y Relative Ef fluent Concentration, Vent (sec/m )

Release uy Average Wind Speed, Vent Release (m/sec)

S i

Gamma Dose Constant, Stack Release (mrad /yr per pCi/sec)

(mrad /yr per V Gamma Dose Constant, Stack Release i

pCi/sec)

O i

4 e

i l

I

.O i

8 ,.1- 9

. - . . - . . _. - - . . - - , - . . . _ ~ . ~ . . - - . - -. . .. ._

i e

QUAD-CITIES REVISION 10 SEPTEMBER 1983

[

i 8.1.6 Constants Used In Section 8.1

. i.

l NUMERICAL VALUE NAME UNIT 1.11 Conversion Constant (mrem / mrad) t i

!- 3600 Conversion Constant (sec/hr) i e

I  ?

I f

f i

1 F

i i .

i B

t i

8.1-10 i

i

,, , em~.-,~~~,n,- ,,,..~-.----e_w....,w. - - - . . , , - , , _ , , - - . . . _ .

QUAD-CIT IES REVISION 10

/'} SEPTEMBER 1983

\~/ .

8.2 LIQUID RELEASES 8.2.1 System Design A liquid radwaste treatment system shall be a system designed and installed to treat radioactive liquid effluents by collecting

, the liquids, providing for retention or holdup, and providing for treatment by demineralization to reduce the total radioactivity prior to the release of liquids to the environment.

8.2.2 Alarm Setpoints Alarm setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area. The concentration limit (Clim) in the discharge line prior to

() dilution in the initial dilution stream is:

V* +

  • Clim = MPC pr max

_ _ - (8.3) l C

lim Limiting Concentration (pCi/ml) in Discharge Line The maximum concentration in the discharge line permitted to be discharged to the initial dilution stream.

MPC Weighted Maximum permissible (pCi/ml)

Concentration n n

[C g [A "I

g "I

MPC = n or n Ag C.

i 1 i i 1 i (8.4)

-s Ns 8.2-1

. _y . . . . 1g .y. ,, ,w_,- 9 ym-3--. e-g+--- y --.v ,, p,- -.,.-w.-%y---# ,y.-

QUAD-CITIES REVISION 10 SEPTEMBER 1983

[] wherei V-C = pCi/ml of nuclide i; i

MPC i = maximum permissible concentration pCi/ml of nuclide i; and A = pCi of nuclide i released in time t.

i Fr max Maximum Flow Rate, Radwaste Discharge (ft /sec)

.The maximum flow rate of radwaste from the discharge tank to the initial dilution stream.

F ve Average Flow Rate, (f t /sec)

Initial Dilution Stream The average flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area

(,,, boundary.

t I

Surveillance frequencies for liquid effluent monitors will be as stated in Table 4.2-3 of the Technical Specifications.

Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.

-8.2.3 Radwaste Discharge Line Releases 8.2.3.1 Radwaste Discharge Monitor The radwaste discharge line is continuously monitored for radioactivity with a gamma sensitive detector.

The monitoring channel consists of a 2-inch by 2-inch sodium iodide-thallium activated scintillation detector, pulse pre-l

- amplifier, and process radiation (log count) monitor. The i '\_) sensing element is positioned on a vertical section of the process liquid piping.

8.2-2 l

i

QUAD-CITIES REVISION 10 c

f .

SEPTEMBER 1983 The radwaste discharge monitor provides a signal to a recorder and trip auxiliary which initiates a high radiation alarm.

The process radiation monitor , alarm, and annunciator are located on the panels in the main control room.

The recorder is located in the radwaste control room.

The process liquid monitor has a logarithmic scale with a range of 10 ~1 to 10 6 counts per second. The monitor is powered from the station's 48/24-Vdc battery system.

The radwaste discharge line detector ('R E 1/2-1721) is mounted adjacent to the discharge piping after the flow control valves and prior to the selection of several alternate discharge routes.

1 The alarm setpoint for the radwaste discharge monitor is established at or below the maximum concentration determined

()'

\~' by Equation 8.3. The concentration is converted to an alarm setpoint using an efficiency curve developed for the monitor through use of a Cs-137/Ba-137m liquid calibration source.

8.2.3.2 Allocation of Effluents from Common Release Points Radioactive liquids effluents released from the radwaste treat-ment system are comprised of contributions from both units.

Under normal operating conditions, it is difficult to allocate the radioactivity between the units. Consequently, allocation will normally be made evenly between the units. During extended unit shutdown or periods of significant plant input differences, the apportionment will be adjusted accordingly. The allocation of the effluents will be made on a monthly basis.

8.2.3.3 Administrative and Procedural Controls for Radwaste

/" Discharges NT)

Administrative and procedural controls have been~ implemented to ensure proper control of radioactive liquid radwaste discharges,

. _ . _ _ _ 8.2.3 _ _ _ . _

QUAD-CITIES REVISION 10 SEPTEMBER 198 3

(T) v to preclude a release in excess of 10 CFR 20 limits. The dis-charge rate for each batch is calculated by a technician and then iinde' pendently verified by two operating staf f personnel.

A single river discharge tank has been designated and modified from which all radwaste discharges will normally be released.

This tank has manual inlet and discharge valves which can be locked.

The inlet valve is locked closed during recirculation of the tank prior to sampling and during the discharge to preclude an accidental addition to the tank which could change its activity.

The discharge valve is locked closed at all times except during the discharge. All other lines, which tie-in with the discharge line, are locked closed. The high and low flow control valves

(~N, are selected by a key-lock switch which allows the use of only

\ d' one of the two flow control valves at any one time. The key to this switch and the locked valves is under the administrative control of the radwaste foreman.

A documented valve checklist is prepared for each batch discharge.

The proper valve lineup is checked by the operator and the radwaste foreman, prior to release. If any sudden significant increase of the radiation monitor occurs during the discharge, the release is terminated. These controls are documented in Station Operating and Administrative Procedures.

l 8.2.4 Service Water Header Releases 8.2.4.1 Service Water Effluent Monitors Each unit's main service water effluent header is continuously fT monitored for radioactivity with a gamma sensitive detector.

N-],

l l

l 8.2-4 l

l l

t

~

q'jrN s

. QUAD-CITIES REVISION 10 SEPTEMBER 1983 Each monitoring channel consists of a 2-inch by 2-inch sodium iodide-thallium activated scintillation detector, pulse pre-amplifier, and process radiation (log count) monitor. The sensing element for each channel is positioned on a vertical section of the process liquid piping.

The service water effluent monitor on each unit provides a signal to a recorder and trip auxiliary, which initiates a high radiation alarm. The process radiation monitor, recorder, alarm, and annunciator are located on the panels in the main control room.

The process liquid monitors have logarithmic scales with a

-1 to 10 6 counts por second. The monitors are range of 10

_ powered from the station's 48/24-Vdc battery system.

\)

The service water system detectors (Iu: 1(2)-1724) are located adjacent to the main service water effluent header on each unit prior to release to the discharge bay.

The alarm setpoints for the service water ef fluent monitor are established at or below the maximum concentration determined by Equation 8.3.

8.2.5 Determination of Initial Dilution Stream Flow Rates For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to determine the flow rate of the initial dilution stream. This instrumenta-tion will be operated and maintained as prescribed by the Tech-nical Specifications. For those release paths which do not have install'ed flow monitoring instrumentation, flow rates will be

(,s) determined by use of appropriate engineering data such as pump curves, differential pressuren, or valve position indication.

8.2-5

QUAD-CITIES REVISION 10 j

~

SEPTEMBER 1983 8.2.6 Symbols Used In.Section 8.2 SYMBOI. NAME UNIT C

lim Liquid Release. Limit (pCi/ml)

MPC Weighted Maximum Permissible (pCi/ml)

Concentration C Nuclide Concentration (pCi/ml) i MPC g Maximum Permissible

~

Concentration (pCi/ml)

! EA f

Nuclide Quantity Released (pCi)

F Maximum Flow Rate, Radwaste (f t /sec)

( max Discharge F

- 'e Average Flow Rate, Initial (ft /sec)

Dilution Stream i l

.O 8.2-6 l

i~, , _ . ._, ,, _ ..,_,_ .... . ___ __,, .. _ ____ ,_,, m .. ,_, , .___.,,_..._,..,_,._,_m , , . - _ . . , - , - - - . ,.

QUAD-CITIES REVISION 7 1-MARCH 1983 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) shall contain the sampling, analysis, and formulation determination by which solidification ,

of radioactive wastes from liquid systems is ensured.

r i

O ,

l

. i O

8.3-1 i

- - - - . . _ . . _ , _ . . _ _ _ . _ _ , , _ *WWT% ,, , ""'**vsy w,.,f ,

QUAD-CITIES REVISION 7

(l

\s-

\

MARCH 1983 S.4 ENVIRONMENTAL RADIOLOGICAL MONITORING The environmental radiological monitoring program to be performed in the environs around Quad-Cities Station is given in Table 8.4-1.

Figure 8.4-1 shows the 16 fixed air sampling sites and TLD locations; also shown are the " outer ring" (approximately 5 miles distant) TLD locations. Figure 8.4-2 shows the

" inner ring" TLD locations. The TLD's are code numbered as follows: XYY-N.

Where:

X=1 m'eans inner ring, X=2 means outer ring, and YY-N is an identification code.

The practical lower limits of detection for this program are given in Table 8.4-2.

1

'L]

8.4-1

.- ~ . . _ . - _ - - _ . _ _ . _ . _. . - _ _ . . _ , _ _ . - - _ _

O O O b d V TABLE 8.4-1 RADIOLOGICAL MONITORING PROGRAM NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS * .

1. Air a. Onsite and near field ** a. Filter a. Continuous Cs-134, 10; operation of a Cs-137, 20 pCi/m 3 Monitoring gross beta ***
1. Onsite No. I sampler for a
2. Onsite No. 2 week
3. Onsite No. 3
4. Nitrin b. Charcoal - b. Continuous 0.9 pCi/m3 operation of a

~

5. Saddle Club Dairy I-131 Farm sampler for
6. Hanson's Boat 2 weeks

? Landing e

? E N c. Sampling c. Weekly Not applicable A Train - M test and  ;;;

maintenance

b. Far Field **
7. Clinton a. Filter a. Continuous Cs-134, 10;
8. Sikkema Farm exchange operation of a Cs-137, 20 pCi/m 3
9. Erie sampler for a when analyses
10. Hillside week are made
11. Port Byron
12. Bettendorf b. Charcoal b. Continuous 0.9 pCi/m 3 xx
13. Princeton exchange operation of a when analyses M samp 4r for are made 9G
14. Utica Ridge Road 2 weeks y
15. Dewitt c. Sampling c. Weekly Not applicable Train -
16. Low Moor test and maintenance

n-v 0- 0~

TABLE 8.4-1 (Cont'd)

NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS *

2. TLD a. Same as Item 1, Air Gamma Quarterly None Monitoring Sites ** radiation

! b. Plus 40 other sites distributed about the a site boundary and at 5 miles ** (minimum of 2 TLD's per packet) i

3. Fish a. P001 14 of Gamma Semi-annual pCi/kg wet weight Mississippi River isotopic 4 c

c-i m (Q-23) Mn-54 3 x 10 4 g i b Co-58 3 x 10 4 l, Zn-65 2 x 10 U j L, Cs-137 2 x 10 43  ;;;

i Fe-59 1 x 10 4 m Co-60 1 x 10 l Cs-134 1 x 10 3 i

j 4. Milk a. Two nearby dairies I-131 a. Weekly pCi/l

] or private animals during

including the.'earest, grazing I-131 3 j if possible season, May Cs-134' 70 (Q-17,Q-18) to October Cs 137 60 Ba La-140, 300 I
b. Monthly, Same as 4a l November J@

to April N;5 I

Im

._. o t

e

-O -O O TABLE 8.4-1 (Cont'o)

NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS- FREQUENCY REPORTING LEVELS *

5. Surface Q-19 East Moline Water Gama Monthly Nuclides pCi/1 Water Works isotopic caolysis of H-3 20,000 Q-20 Davenport Water Works po ites 1,0

_h 0 Co-58 600 Co-60 300 Zn-65 200 Zr-Nb-95 400 I-131 2 Cs-134 30 Cs-137 50 Ba-La-140 100

6. Cooling 8

Q-21 Inlet Gross beta Weekly None @.

. Water A Sample' Q-22 Discharge

1. -]

O  ;

7. Sediment Q-23 Lock and Dam Gama Annual None No. 14 isotopic
8. Dairy a. Site boundary to 2 miles a. Enumeration During grazing Census annually by a season door-to-door or equivalent 2 :o counting technique SEQ QW
b. 2 miles to 5 miles b. Enumeration During grazing ~

annually by using referenced infor-season

{5 mation from county agricultural agents or other reliable sources

TABLE 8.4-1 (Cont'd)

NONROUTINE SAMPLE MEDIA COLLECTION SITE TYPE OF ANALYSIS FREQUENCY REPORTING LEVELS *

  • Average concentration over calendar quarter.
    • See Figure 8.4-1 '
      • A gama isotopic analysis shall be performed whenever the gross beta concentration in a sample exceeds '

by five times (5x) the average concentration of the preceding calendar quarter for the sample location, t See Figure 8.4-2 ttA gama isotopic analysis shall be performed if I-131 from the plant is found above the LLD.

j tttProvided by statio:. personnel.

1 e

4 i =

a A 4

c 6

l i

I h

TTI M'*-

=m j

G8 CO 2

i QUAD-CITIES REVISION 7

-sq MARCH 198 3

)

-(N/ TABLE 8.4-2 PRACTICAL LOWER LIMITS OF DETECTION (LLD)

FOR ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM LLD SAMPLE MEDIA- ANALYSIS (4.66 ) UNITS Airborne Gross Beta

  • 0.01 3

" Particulate" Gamma Isotopic pCi/mgq 0.01 pCi/m Sr-89, 90 0.01 pCi/m 3 Airborne I-131 Iodine-131 0.10 pCi/m 3 Liquids Sr-89 10 pCi/l Sr- 90 2 pCi/l I-131 5** pCi/l Cs-134 10 pCi/l Cs-137' 10*** pCi/1 Tritium 0.2 pCi/ml Gross Beta

  • 5 pCi/1 Gamma Isotopic 20 pCi/1/nuclide Vege,tation Gross Beta
  • 2 pCi/g wet I-131 0.03 pCi/g wet Sr-89, 90 1 pCi/g wet c Gamma Isotopic 0.2 pCi/g wet Soil, Sediment' Gross Beta
  • 2 pCi/g dry Sr-89, 90 1 pCi/g dry Gamma Isotopic 0.2 pCi/g dry Animal Tissue Sr-89, 90 0.1 pCi/g wet I-131 - Thyroid 0.1 pCi/g wet Cs-134, 137 0.1 pCi/g wet Gross Beta
  • 1.0 pCi/g wet Gamma Isotopic 0.2 pCi/g wet *
    • 0.5 pCi/l on milk samples collected during the pasture season.
      • 5.0 pCi/l on milk samples.

O I 8.4-6 L

r

, - e .,y v. ,-,,,m-v,--- --+,,.-ev ,--.,e- , - ,ew-w -w.,-,- - w-- - - . -er-r--,,,e--,-~ -- m,--r--

TABLE 8.4-3 ENVIRONMENTAL RADIOLOGICAL MONITORING SAMPLING CODES SURFACE WELL AQUATIC PLANTS PRECIPITATION, MONITORING SITES AIR TLD WATER WATER FISH AND SEDIMENT MILK FEED, GRASS VEGETABLES Q-01 Onsite No. 1 X X Q-02 Onsite No. 2 X X Q-03 Onsite No. 3 X X Q-04 Nitrin X X Q-05 Saddle Club Dairy Farm X X Q-06 Hanson's Boad Landing X X Q-07 Clinton X X

.", Q-08 Sikkema Farm

{

X X L Q-09 Erie X X g

Q-10 Hillside X X G

Q-11 Port Byron X X Q-12 Bettendcrf X X Q-13 Princeton X X Q-14 Utica Ridge Road X X Q-15 Dewitt X X Q-16 Low' Moor Q-17 Hansen Dairy Farm X X j

s X X 2y Q-18 Musal Dairy Farm X X e

O . O -O-i

~

TABLE 8.4-3 (Cont'd)~

SURFACE WELL PRECIPITATION, AQUATIC PLANTS i MONITORING SITES AIR TLD WATER WATER FISH AND SEDIMENT MILK FEED, GRASS _ VEGETABLES j Q-19 East Moline Water Works X l Q-20 Davenport Water Works X

] Q-21 Inlet Canal X

) Q-22 Discharge Canal X l

Q-23 Lock and Dam #14 X l (Mississippi River)

Q-24 Pool f14 of Mississippi River X i

?

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j l

! 35

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REVISIO', '

MARCH 195

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u.s so D-3 g x U S 30 J 'iN'h 202-1 l6 g 201,1

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{ 215-2 I .

0 -2 l l 10WA 21 9 0 04 204-2 213-23 g E 2C5-1 iLLINOI 5 l

213-15 h g3

/g!4 212-25 212-1 5 "\1,,L ,

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%i 17 s

re. S" g %  %

A 8 OU.l( 'M 1%Qs  ?

YN

,D, , I-80 E

SCALE 9 , , , 9 m is e,o unas QU AD-CITIES STATION Units 1 & 2

(~

FIGURE 8.4-1 1

FIXE 0 AIR SAMPLING SITES AND Ol'TER RING TLD LOCATIONS

.s---- ._

,,- ~ . - - - _

- - . , --e~- .v-- , , n - - , - - , , , -- _ , , - - , , , - - - - - - . . .-

REVISIO!: 7 MARCH 19?:

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Units 1 6. 2

'- FIGURE 8.4-2 INNER RING TLD LOCATIONS

. - - . - .. .

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