ML20050D590
| ML20050D590 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/31/1982 |
| From: | HAZLETON LABORATORIES AMERICA, INC. |
| To: | |
| Shared Package | |
| ML20050D567 | List: |
| References | |
| NUDOCS 8204120345 | |
| Download: ML20050D590 (127) | |
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1 QUAD CITIES STATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL M0!ilTORING ANNUAL REPORT 1981 5
HAZLETON ENVIRONMENTAL SCIENCES Northbrook, Il1inois MARCH 1982 8204120345 820401 PDR R
ADOCK 05000254 PDR
t t
QUAD CITIES NUCLEAR POWER STATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING
/ ANNUAL REPORT 1981 l
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l MARCH 1982 l
TABLE OF CONTENTS Page Introduction.............................................................. 1 Summary................................................................... 2 1.0 Effluents 1.1 Gaseous......................................................... 3 1.2 Liquid.......................................................... 3 2.0 Solid Waste 3.0 Dose to Man 3.1 Ga s eou s E f fl ue nt Pa t hway s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.2 Liquid Effluent Pathways........................................ 5 4.0 Site Meteorology..................................................... 5 5.0 E n v i ro nme n t a l Mon i t o r i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5.1 Gamma Radiation................................................. 6 5.2 Airborne I-131 and Particulate Radioactivity.................... 6 5.3 Aquatic Radioactivity........................................... 6 S.4 Milk............................................................ 7 6.0 Analytical Procedures................................................ 7 7.0 Milch Animal Census.................................................. 7 Appendix I - Figures and Data Tables...................................... 8 Station Releases Table 1.1-1 Ga s eou s E f fl ue nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Table 1.2-1 L i q u i d E f f l u e nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Table 2.0-1 Solid Waste Shipments................................... 25 Figure 3.1 3.1-4 Isodose and Concentration Contours............. 53 Table 3.1-1 Dose Calculations....................................... 57 Environmental Monitoring Locations of Fixed Envi ronmental Radiological Stations. ... . . . . .. .. . . . 58 Table 5.0-1 Standa rd Radi ol ogi cal Moni tori ng Program. . . . . . . . . . . . . . . . 60 Table 5.0 5.0-5 Envi ronmental Summa ry Tabl es . . . . . . . . . . . . . . . . . . . . 62 Table 5.1-1 Gamma Radiation Measurements (TLD)...................... 66 Appendix II - Meteorological Data......................................... 69 Appendix III - Analytical Procedures...................................... 98
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INTRODUCTION Units 1 and 2 of the Quad Cities Station located near Cordova, Illinois next to the Mississippi River, are 800 MWe boiling water reactors, similar in design to Dresden Units 2 and 3. The plant has been designed to keep releases to the environment at levels below those specified in the regulations.
Liquid effluents from Quad Cities are released to the Mississippi River in controlled batches after radioassay of each batch. Gaseous effluents are released to the atmosphere after delay to pennit decay of short half-life gases. Releases to the atmosphere are calculated on the basis of analyses of daily grab samples of noble gases and continuously collected composite samples of iodine and particulate matter. The results of effluent analyses are summarized on a raenthly basis and reported to the Nuclear Regulatory Commission as required per Technical Specifications. Airborne concentrations of noble gases, I-131 and particulate radioactivity in off-site areas are calculated using effluent and meteorological data on isotopic composition of effluents.
Environmental monitoring is conducted by sampling at indicator and reference (background) locations in the vicinity of the Quad Cities plant to measure changes in radiation or radioactivity levels that may be attributable to plant operations. If significant changes attributable to Quad Cities are measured, these changes are correlated with effluent releases. External gamma radiation exposure from noble gases and I-131 in milk are the most critical pathways at this site; however, an environmental monitoring program is conducted which includes other pathways of less importance.
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SUMMARY
Gaseous and liquid effluents for the period remained at a fraction of the Technical Specification limits. Calculations of environmental concentrations based on effluent, Mississippi River flow, and meteorological data for the period indicate that consumption by the public of radionuclides attributable to the plant are unlikely to exceed the regulatory limits. Gamma radiation exposure from noble gases released to the atmosphere represented the critical*
pathway for the period with a maximum individual dose estimated to be mrem for the year, when a shielding and occupancy factor of 0.7 is assumed.
Environmental monitoring results confinn that dose via other pathways was not significant.
- Datum will be provided 2
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l 1.0 EFFLUENTS 1.1 Gaseous Effluents to the Atmosphere Measured concentrations and isotopic composition of noble gases, radioiodine, and particulate radioactivity released to the atmos-phere during the year, are listed in Table 1.1-1. A total of 3.20 E+04 curies of fission and activation gases was released with an average release rate of 1.02E+03 pC1/sec.
A total of 0.46 curies of I-131 was released during the year, with an average release rate of 1.46E-02 pCi/sec.
A total of 0.81 curies of beta-gamma emitters and 9.10E-05 curies of alpha emitters was released as airborne particulate matter, with an average release rate of 2.57E-02 pCi/sec.
A total of 8.58E+01 curies of tritium was released, with an average release rate of 2.72E+00 pCi/sec.
1.2 Liquids Released to the Mississippi A total of 6.11E+06 liters of radioactive liquid waste (prior to dilution) containing 3.27 curies (excluding tritium, gases, and alpha) were discharged after dilution with a total of 3.08E+09 liters of water. These wastes were released at a quarterly average concentration of 3.31E-06 pCi/ml during the first and second quar-ters, dicharged on an identified nuclide basis; and 1.27E-07 pCi/ml during the third and fourth quarters, which is 7.4% of the Technical Specification release limits for identified radioactivity. A total of 4.8E-04 curies of alpha radioactivity and 11.9 curies of tritium were released. Quarterly release estimates and principal radio-nuclides in liquid effluents are given in Table 1.2-1.
2.0 SOLID RADI0 ACTIVE WASTE Solid radioactive wastes were shipped to Richland, Washington; Beatty, Nevada; and Barnwell Nuclear Center, South Carolina. The record of waste shipments is sumarized in Table 2.0-1.
3.0 DOSE TO MAN i
3.1 Gaseous Ef. fluent Pathways Gamma Dose Rates Gamma air and whole body dose rates off-site were calculated based on measured release rates, isotopic composition of the noble gases, and meterological data for the period (Table 3.1-1). Isodose contours of whole body dose are shown in Figure 3.1-1 for the year. Based on measured effluents and meteorological data, the
! 3
maximum dose to an indiv4ual would be
- mrem for the year, with an occupancy or shiv .g factor of 0.7 included. The maximum gamma cir dose was
- mrad.
Beta Air and Skin Rates The range of beta particles in air is relatively small (on the order of a few meters or less): consequently, plumes of gaseous effluents may be considered " infinite" for purpose of calculating the dose from beta radiation incident on the skin. However, the actual dose to sensitive skin tissues is difficult to calculate because this depends on the beta particle energies, thickness of inert skin, and clothing covering sensitive tissues. For purposes of this report the skin is taken to have a thickness of 7 mg/cm2 and an occupancy factor of 1.0 is used. The skin dose from beta and gamma radiation for the year was
- mrem.
The air concentrations of radioactive noble gases at the off-site receptor locations are given in Figure 3.1-2. The maximum off-site beta air dose for the year was
- mrad.
Radioactive Iodine The human thyroid exhibits a significant capacity to concentrate ingested or inhaled iodine, and the radioiodine, I-131, released during routine operation of the plant, may be made available to man thus resulting in a dose to the thyroid. The principal pathway of interest for this radionuclide is ingestion of radiciodine in milk by an infant. Calculation made in previous years indicate that contri-butions to doses from inhalation of I-131 and I-133, and I-133 in milk are negligible.
Iodine-131 Concentrations in Air The calculated concentration contours for I-131 in air are shown in Figure 3.1-3. Included in these calculations is an iodine cloud depletion factor which accounts for the phenomenon of elemental iodine deposition on the ground. Themaxgmumoff-siteaverage concentration is estimated to be + pC1/m for the year.
Dose to Infant's Thyroid l
The hypothetical thyroid dose to an infant living near the plant via ingestion of milk was calculated. The radionuclide considered was I-131 and the source of milk was taken to be the nearest dairy fann with the cows pastured from May to October. The maximum infant's
! thyroid dose was
- mrem during the year (Table 3.1-1).
l
, Concentrations of Particulates in Air l
Concentration contours of radioactive airborne particulates are l shown in Figure 3.1-4. The maximum off-site average level is esti-
! mated to be .
- Data will be provided 4
Summary of Doses Table 3.1-1 summarizes the doses resulting from releases of airborne radioactivity via the different exposure pathways.
3.2 Liquid Effluent Pathways The three principal pathways through the aquatic environment for potential doses to man from liquid waste are ingestion of potable water, eating aquatic foods, and exposure while walking on the shoreline. Not all of these pathways are applicable at a given time or station but a reasonable approximation of the dose can be made by adjusting the dose formula for season of the year or type and degree of use of the aquatic environment. NRC* developed equations were used to calculate the doses to the whole body, lower 6'. tract, thyroid, bone and skin; specific parameters for use in the equations are given in the Commonwealth Edison Off-site Dose Calcu-lation Manual. The maximum whole body dose for the years was **
mrem and no organ dose exceeded ** mrem.
4.0 SITE METEOROLOGY A sununary of the site meteorological measurements taken during each quarter of the year is given in Appendix II. The data are pres-ented as cumulative joint frequency distributions of 296' level wind direction and wind speed class by atmospheric stability class determined from the temperature difference between the 296' and 33' levels. Data recovery for these measurements was about 97.6%.
5.0 ENVIRONMENTAL MONITORING Table 5.0-1 provides an outline of the radiological environmental monitoring program as required in current Technical Specifications.
This program went into effect in November 1977 and differs from previous programs in the number and types of analyses perfonned.
Tables 5.0-2 to 5.0-5 summarize data for the year.
Except for tables of special interest, tables listing all data are no longer included in the annual report. All data tables are available for inspection at the Station or in the Corporate offices.
Specific findings for various environmental media are discussed below.
- Nuclear Regulatory Commission, Regulatory Guide 1.109 (Rev.1).
- Data will be provided.
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5.1 Gamma Radiation External radiation dose from on-site sources and noble gases re-leased to the atmosphere was measured at six indicator and ten reference (background) locations using solid lithium fl(Qjride h thermoluminescent dosimeters (TLD). A comparison of the TLD rEsults for reference stations with on-site and off-site indicator stations is included in Table 5.1-1. Additional TLDs, a total of 61 were installed on June 1,1980 such that each sector was covered at both five miles and the site boundary.
5.2 Airborne I-131 and Particulate Radioactivity Concentrations of airborne I-131 and particulate radioactivity at monitoring locations are summarized in Tables 5.0-2 through 5.0-5.
Locations of the samplers are shows in figure 5.0-1. Airborne I-131 remained below the LLO of 0.1 pC1/m 3 throughout the year.
Gross beta concentrations ranged f rom 0.01 to 0.49 pCi/m 3 at indicator locations with an average concentration of 0.11 pC1/m 3 d
for the year. No radioactivity attributable to station operation was detected in any sa.mple.
5.3 Aquatic Radioactivity Surface water samples were collected daily and composited for
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analysis weekly from the Inlet Canal, blowdown diffuser pipe, East Moline Water Works, and Davenport Water Works. The cooling water samples are analyzed weekly for gross beta concentrations. A composite sample from each quarter from the blowdown diffuser pipe does not indicate measurable radioactivity attributable to station operation. Gross beta concentration in the blowdown water sample ranged from 3 to 1800 pCi/1. Supplementary gamma isotopic analysis indicated quantitatively that this activity was mainly due to Cs-134, l
Cs-137, and Co-60 and is clearly attributable to station releases.
Samples from the two water works are compositied quarterly and analyzed for gamma emmiters. All samples analyzed were below the limits of detection for the program indicating that there was no measurable amount of radioactivity due to station operation present.
Levels of gamma radioactivity in fish collected were measured and
! found in all cases to be below the lower limits of detection for the program.
l A sediment sample was analyzed by gamma spectrometry. Gamma-emitters were either below the limits of detection or at the level usually
! encountered in the environment (Cs-137, 0.60 pCi/g dry weight) indicating the presence of no radioactivity due to station operation.
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5.4 Milk Milk samples were collected monthly from November through April and weekly f rom May through October and analyzed for iodine-131.
Sampled locations were the Hansen Dairy Farm located about 5 miles northeast of the Station, Turner Farm, 2.5 miles southwest of the Station, and Musal Dairy Farm located 5.5 miles softhwest of the Station. Turner Farm went out of dairy business' at the end of April 1981 and was replaced by Musal Dairy Farm in early May 1981.
Radioiodine was below the limits of detection of 0.5 pCi/l during the grazing period (May to October) and 5.0 pCi/l during the non-grazing period (November to April).
5.5 Special Collection No special collections were made during the period.
6.0 ANALYTICAL PROCEDURES A description of the procedures used for analyzing radioactivity in environmental samples is given in Appendix III of the report.
7.0 MILCH ANIMAL CENSUS A census of milch animals was conducted within five miles of the Station and the finding is presented below. The survey was conducted by " door-to-door" canvas and by information from Illinois and Iowa Agricultural Agents.
Name of Farm Distance and Direction or Farmer from Station Milking Animals Saddle Club Dairy 1 mile S 100 cows 7
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1 APPENDIX I DATA TABLES AND FIGURES i
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Table 1.1-1 QUAD CITIES I4UCLEAR POWER STATICN 1981 EFFLUENT AND WASTE DISPOSAL SEMl ANNUAL REPORT CASEQUS EFFLUU4TS-5UMMATl0N OF ALL RELEASES Muarter Quarter Est. Total Unit let 2nd Error, t I
A. Fission & Activation Gases
- 1. Total release Cl 1.24E+04 6.99E+03 uC 1/see 1.59E+03 8.89E+02
- 2. Averaae release rete for eerlod
- 3. a. Percent of Tech. Spec. Ilmit
% 3.51E-01 1.97E-01 Chimney
- b. Percent of Tech. Spec. Ilmit 3 7 !!E-01 5. 26E-01 j B. lodines
- 1. Total lodine-l?I Cl 1.24E-01 1.06E-01
- 2. Averaco release rate for period uCl/see 1.59E-02 1.35E-02
- 3. a. Percent of Tech. Spec. limit statio- % 1.07 .89 l
C. Particulates
- 1. Particulates with half-lives > R days Cl 1.89E-01 3,35Es01
- 2. Averane release rate fer earlod uCl/sec 2.4 3 E-0 2 4.26E-02 l
Cross alpha radioactivity Ci 5.24E-06 9. 76 E-06 3.
l 9
0
Table 1.1-1 (continued)
QUAD CITIES IUCLEAR POWER STATION EFFLUENT AND WASTE Dl5?05AL SEM1 ANNUAL REPORT 3rd & 4th qtr. 1981 GASEQUS EFFLUENTS-$UMATION OF ALL RELEASES quarter quarter Est. bral Unit 3rd 4th Error. % .
A. Fission t Activation Cases
- 1. Total releese Cl 7 5E03 5.lE03
- 2. Averace release rate for eeriod uCl/sec 9.4E02 6.5E02
- 3. a. Percent of Tech. Spec. Ilmit Chimney % 2.7E-01 2.4E-01
- b. P reent of Tech. Spec. Ilmit 2.0E-01
% 5.7E-01 B. lodines
- 1. Total lodine-Ill CI 'I.3E-01 1.0E-01
- 2. Averace release rate for neriod uCl/see 1.6E-02 1.3E-02 3* a. Percent of Tech. Spec. Ilmit statloi
% 6.8E-01 l.1Ec0 C. Particulates
- 1. Particulates with half-Ilves > 8 days Cl 1.8E-01 4.lE-Of
- 2. Averane releere rate fer nerlod uC1/see 2.2E-02 1.3E-02
- 3. Cross alpha radioactivity 6.3E-05 1.3E-05 10 f
Talble 1.1-1 (continued) 1981 EFFLUENT AND WASTE DISPOSAL SEMIAl4NEAL REPORT GA5EDUS EFFLUENTS-SumATION OF ALL RELEASES Quarter Quarter Est. Total Unit let 2s Error, %
0 Tritte Total relee<a C1 4. 55te0 1.39tet 1.
- 2. Aversee release rate for eerfod uCl/sec 5.85E-01 1.76E+oo i
9 11
Table 1.1-1 (continued)
EfFLUCNT AND WASTE Ol5P05AL SEMI ANNUAL REPORT 1491 GASEOUS EFFLUENTS-SUMATION OF ALL RELEASES Quarter Quarter ist. Total Unit 3rd 4th Error, Y, D. Tritlun I. Total relenee Cl 6.0E01 7.4E00
- 2. Averaqa release rate for period ut t /sec 7.5E-01 9.3E-01
(
i l.
l 12 I
l Table 1.1-1 (continued)
QUAD CITIES I.VCLEAA POVER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 GA$EDUS EFFLUENTS- ElevateJ Continuous Mode Batch Mode Nuclides Aeleased Unit is t $
- l. Flssion gases Kr-8s CI < LLD < t.1.D Kr-85m Cl 6.26E+02 4.93E+02 Kr-87 Cl 6.97E+02 1.66E+02 l
K r-88 Cl 1.07E+03 5.70E+02 Ne-lit Cl 8.41E+02 1.01E+02 re-Ils Cl 1.84E+03 6.23E+02 ye-lism Cl 1.68E+03 1.35E+03 t
re-118 CI 4.49E+03 1.86E+03 CI Cl I
i l U ni den t i f l ed CI l
Total for Perled Cl 1.13E+04 5.16E+03 l 2. lodines i
1-111 Cl 1.04E-01 1.03E-01 1-111 CI 4.86E-01 4.85E-01 I-lis CI 9.51E-01 8.95E-01 Total for Parind Cl 1.54E+00 1.48E+00 13 l
l l
-- ~- ~ P v
i I
a 4
i Table 1.1-1 (continued)
QUAD CITIES l;UCLEAR POVER STATION
)
i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT E GA$EDUS EFFLUENTS-Elevated Release Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit 3rd 4th I. Flssion gases Kr-85 C1 <LLD <LLD Kr-85m Cl 7.5E02 7.6E02 K,-87 CI 6.5E02 5.lE02 K r-88 Cl I.6E03 1.5E03 Xe-111 Cl 8.3E02 1.0E03 Xe-135 Cl 3 7E02 2.4E02 i
re-lism Cl 6.4E02 1 3E02 ye-118 C1 2.4E03 3.4E02 CI CI Unident i f ied Cl <LLD <LLD Total for Period Cl 7.2E03 4.4E03 2 lodines 4-111 Cl 1.2E-01 C.0E-02 1-111 CI 3.5E-01 4.IE-01 j 1-115 Cl 6.8E-01 6.4E-01 Total for Period Cl 1.2E00 1.lE00 l
I i
! 14 l
Table 1.1-1 (continued)
EFFLUENT AND VASTE DISPOSAL SEMI ANNUAL REPORT 1981 GASEQUS EFFLUENTS-[/evW Continuous Mode Batch Mode Quarter Quarter quarter Quarter Nuclides Released Unit let 2nd
- 3. Particulates
$r-89 Cl 3.42E-02 2.71E-2 t
$r-go Cl 1.19E-04 9.06E-05 Cs-l% Cl 8.16E-05 3.59E-05 Cs-137 C: 6.24E-04 5.88E-04 Ba-140 Cl 5.64E-02 5.99E-02 La-140 Cl < LLD < LLD Cr51 C < LLD < LLD Mn54 ci < tto < tto CoS8 e < tto < tto Co60 Cl 3.03E-04 3.30E-04 i 1131 C1 1.62E-02 6.35E-03 Ag110m Cl i
- tto
- te l
Ce-141 Cl 4.03E-04 3.25E-04 Cl Cl CI Cl Unidentified Cl l
l f
4 15 l 1
Table 1.1-1 (continued)
EFFLUENT AND WASTE DISPOSAL SEMI ANfiUAL REPORT 1981 GASE0US EFFLUENTS-Elevated Release Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit 3rd 4th
- 3. Particulates Sr-89 Cl I.IE-02 f .4 E-07, Sr-90 Cl 4.lE-05 5.lE-05 Cs-l% CI 1.2E-05 1.3E-05 Cs-In C1 2.2E-04 3.2E-04 Sa-ILO Cl 2.6E-02 1.7E-02 La-140 Cl <LLD <LLD CrSt Cl <LLD <LLD Hn54 Cl <LLD <6LD CoS8 gg <LLD <LLD Co60 Cl 9.9E-05 1.0E-04 3131 CI 5,5E-03 9.5E-01 Agil0m Cl <tLD <LLO Ce 141 C1 2.0E-04 3.0E-03 Ce 144 Cl I 9E*03 Cl CI CI Unidantifled C1 16 l
Table 1.1-1 (continued) 1 QUAD CITIES NUCLEAA PCVER STATION EFFWENT AND WASTE 01070$Al. SEMIANNUAL REPCAT 19a1 GASEQUS EFFWENT5. Ud 6/g Continuous Mode Batch Mode Nuclides Released Quarter Quarter Quarter Quarter I
Unit 1st 2nd r
- l. Fission gases l
Kr-8s CI < LLD < LLD Kr-8sm Cl < LLD < LLD Kr-87 Cl < LLD < LLD K r-88 Cl < LLD < LLD re-111 CI 4.73E+02 2.39E+02 re-lis Cl 4.24E+02 3.26E+02 re-llem CI 2. 89 E+02 1. 86 E+02 re-418 Cl < LLD < LLD 1
Cl Cl Unidentified Cl Total for Period Cl 1.19E+03 7.51E+02
- 2. lodines 1-111 CI 2.01r-02 3.est n1 1-111 Cl 9.41E-02 1.34 E-02 2
1-tis CI 2.03E-01 4.61E-02 l
I Total for Period Cl 3.17E-01 6.52E-02 17 i (
_ _. .- .. . . ~
j Table 1.1-1 (continued) 2 QUtD CITIES IUCLEAR POWER STATION i
EFFLUENT AND VASTE DISPOSAL SEMIANNUAL REPORT 1981 GA$EDU$ EFFLUENTS- Vent Release Continuous Mode Batch Mode Nuclides Released Quarter Quarter Quarter Quarter
-Unit 3rd 4th I. Fission gases Kr-85 C1 <LLD <LLD Kr-85m CI <LLO <LLD Kr-87 CI <LLD <LLD K r-88 Cl <LLD <LLD Ne-lit Cl- 3.5E01 5.5E02 Xe-115 Cl 9.SE01 4.0E01 Xe-115m CI 1.7E02 3.7E01 Xe-t 18 C1 <LLD 3.4E01 CI Cl l
I Uni dent i f Ied Cl <tLO <tLO Total for Period Cl 3 0E02 6.6E02 2 lodines l
l
! l-111 Cl 5.8E-03 2.4E-02 1-111 Cl 2.0E-02 J.8E-01 1-115 CI 3.2E-02 1.9E00 l
l __ Total for Period CI 5.8E-02 2.1E00 l
I l
l i
i 18 l
'm
- v--+ -
-w- , . - - - - - - . , - - - - . - - - +- - - - . _ -
--v - -. ---
\
Table 1.1-1 (continued)
EEFl.UENT AND WASTE DISPOSAL SEMIANNUAL. REPORT 1981 sAsEOUS EFFLUENTS- YM Ma.K.,
Continuous Mode Batch Mode quarter Quarter quarter Quarter Nuclides Released Unit ist 2nd 3 Particulates Cg 2.37E-03 1. 2 5E-04
$r-89 CI 3.75E-05 3,org.og 3r.e0 CI 1.16E-04 1.46E-04 Cs-1% r 4.10E-04 1.47E-02 C s-117 Cl
. . 5 -03 S a-I f*O -Cl CI < LLD < LLD L a-II+0 CrSt CI 2.91E-03 4.7sE-04 Mn54 Cl 1.03E-04 5.09E-05 CoS8 cl 2.23E-04 2.50E-04 Co60 CI 2.92E-03 3.07E-03 1131 Cl 2.46E-03 1.62E-03 Agil0m Cl 1.33E-05 < t.LD Cs-136 C1 2.29E-04
l - - - - --- - _ . _ . _ ____ __ ___ _ _ _ _
=. ._ .
Table 1.1-1 (continued)
EFFLUENT AND WASTE Dl!POSAL SEMI ANhuAL REPORT 1981 j GASEDUS EFFLUENTS- Vent Release Continuous Mode Batch Mode Quarter quarter quarter Quarter Nuclides Released Unit 3rd 4th
- 3. Particulates
$r.89 CI 3.lE-04 1 3I-04 Sr-90 Cl 1.3E-05 I A E-05 Cs-11t, Cl 1.0E-04 1.lE-04 Cl 2.8E-04 9 5E-04 Cs-117 i
La-140 less thaa 8 day ha lf Cl life <LLD <LLO Cr51 C1 2.lE-03 1.6E-02 Hn54 Cl I.0E-04 9.7E-05 CoS8 c; 1 7E-04 1.0E-05 Co60 Cl 1.6E-03 2.8E-03 1131 Cl 1.5E-03 8.3E-03 Agl10m Cl <tLD 1.25-05 Rul03 Cl 4.9E-06 <LLO Csl36 Cl 'LLD 4.8E-04 2n65 Cl *tib 7 7E-04 Sbl24 CI 'LLD 3.4E-05
- Ce l41 C1 d 3.8E-03 Unidantified Cl t
1 5
i 20
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Table 1.2-1 quad CITIES NUCLEAR POWEA STATION EFFLUENT AND WASTE DISPOSAL $EMBANNUAL REPORT 1981 Liquio EFFLUENTS-SUMMATION OF ALL RELEASES quarter quarter Est. Total Unit let 2nd Error, %
A. Fission and Activation Products
- 1. lotal release (not including tri tt w. cases . aloha) Cl 2.17EMO 9.89E-01 2 Average luted concentration uCI/mi 2.82E-06 3.80E-06
% 1.32E+01 1.22E+01
- 1. Percent of anolleable limit 4 Hamimum diluted concentration 6.29E-06 4.58E-06 durinn neriod uCI/s1 B. Tritium I. Total release C1 2.04E+00 1.60EMo 2 Average diluted concentration durina oeriod uCl/mi 2.65E-06 1.8 4-06
- 1. Percent of ecolicable Ilmit g 8.83E-02 6.0 E-02 C. Olssolved and Entrained Gases I. Total release Cl 4.00E-01 1.16E-02 2 Average diluted concentration durina nerlod uC1/ml 5.20E-07 1.33E-08
{
- 1. Percent of soolteable limit % 1.73E-02
- 4.42E-04 0 Gross Alpha Radioactivity I. Tntal ratasse Cl 2.93E-04 7.53E-05
- 2. Averane enneentretten released uC1/mi 3.81E-10 8.61E-Il E. Volurne of waste released (prior to dilution) Liters 1.43E+06 2.68EM5 F. Volume of dilution water used 7.69E+08 j
durino narind Liters 8. 7 5 EM7 l
l l
21
Table 1.2-1 (continued) quad CITIES NUCLEAR F0WER STATiett EFFLUEliT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 LiqulD EFFLUEl4TS-5UitttATION OF ALL RELEASES Quarter Quarter Est. Iota Unit 3rd 4th Error, ?.
A. Fission and Activation Products I. Total release (not including tritim. cases. einh3) CI 4.8E-02 6.7 E-02 2 Averaga diluted concentration durInn eeriod uCl/ml 2.2E-07 3.3E-08
- 3. Parcent of annliceSle limit % 3.89E00 1.4E-01
- 4. Maxiv.um diluted concentration durinn period uCl/ml 5 3E-06 9.2E-05 B. Tritium I. Total release Cl 1.7E-ol 8.lE00 2 Average dilhted concentration durino period uCl /ml 7.7E-07 4.1606
- 3. Percent of anolicable limit' % 2.6E-02 1.4E-01 C. Olssolved and Entrained Casos
- 1. Total retcose Cl 7.6E-01 1.1E00 I
2 Average diluted concentration durino period uCI /ml 3.5E-08 6.5E-07 i 3. Percent of annlicable limit % l.2E-03 2.2E-02 l
l D. Cross Alpha Radioactivity l
- 1. Total rel aec CI 1.lE-04 3.7E-07
- 2. Averaae caneentration relensed uC1/ml 5.0E-10 1.9E-13 j E. Volume of waste released (prior to dilution) LItals 3.lE05 4.lEt06 l
F. Volume of dilution water used dortno narlod Liters 2.2E08 2.0E09 _
22
Table 1.2-1 (continued)
QUAD CITIES NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 LiqulD EFFLUENTS Continuous Mode 8atch Hode Quarter Quarter Quarter Quarter Unit 1st 2nd Sr-8g Cl 9.68E-04 7.44E-04 CI 2.87E-04 -1.85E-04 Sr 00 Tc-99's 2.53E-04 8.00E-04 C1 4.79.n, 2,13E-01 C s-111 I-133 1.78E-04 1.27E-03 Cs-117 Cl 1,49E+00 7.39E.01 1.51E-03 5.09E-04 1-135 1.69E-03 2.82E-03 l-Ill Cl Cr-51 4.81E-04 3.75E-04 Co-58 Cl 2.37E-03 2.03E-03 sr-91 < LLD 6.42E-04 Co-60 Cl 1.94E-01 2.31E-02 sr-92 < LLD 1.83E-05 Fe-qq Cl < tto , tto Mg Cl 2.43E-04 < tto Mn-% Cl 5.79E-03 5.87E-05 Cr-El Cl < LLD < LLD Zr 05 CI < LLD < 1.LD Hb 09 Cl
Cal 36 CI
- LLD < LLD La-140 Cl 4.27E-04 1.01E-03 Ce-let C1 < LLD 3.21E-05 Unidentified CI Total for Period (cbove) Cl 2.17E+00 9.88E-01
(
I re-111 C1 2.73E-01 5.70E-03 l
Cl 1.16E-01 7.92E-03 I
_re-419 Xe-133m 1.22E-02 i i
23 j
- -- _ , . . ~ - - - - - - _ _ _ _ _ _ _ _
Table 1.2-1 (continued)
QUAD CITIES NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 LIQUID EFFLUENTS Continuous Pode Batch Hoda Quarter Quarter Quarter Quarter Unit 3rd 4th Sr-89 Cl 1.7E-03 2.6E-03 S r oo CI 9.2E-05 7 2E-04 Tc-99m 8.4E-04 9 6E-04 C3-134 Cl 1.lE-02 7.8E-04 Eeiki 9 5E-05 8.4E-04 Cs-137 Cl 4.PE-02 1.4E-02 1-133 5 7E-03 4 3E-03 1-131 Cl 4.6E-03 3.lE-03
$r-94 5.dE-0* 6.3E-04 Co-58 Cl 6.3E-04 5.5E-04 6435 2.jE-03 4 3E-03 Co-60 Cl I.lE-02 2.6E-02 Na24 3.*t-u* 4.st-u*
Fe-59 C1 ettb *LLb Csl38 2.6E-03 '@
2n-65 CI c.tr-04 1.1r-01 Hn-$4 Cl 7.4E-04 1.5E-01 Csl36 3.9E-05 Cr-51 Cl I.lE-03 1.9E-03 Sr-92
- 6 6& 2.lE-05 Zr-95 Cl *Lth 'LM Nb-95 Cl ALLD 2.8E-05 Hn-99 Cl 3.8E-04 9.9E-04 An110- Cl <LLO <LLO Ba-140 Cl I.8E-03 2.lE-03 Csl36 Cl 8.6E-05 't t b La-140 less than 8 day hal" lifGI 'LLD 'LLb NO239 Cl 'LiJ) i.iE-04 -
Unidentifled Cl
_ Total for Perlod (rkove) Cl 9.6E-02 6.7E-02 xc ill Cl 3.3E-03 1.2E00 xe-133m 'LLD 5.6E-04 Xe-13g C1 4.4E-01 1.?r-at 24
l i
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30
< Table 2.0-1 (continued)
RWA - Richland Washington SOLID RADI0 ACTIVE WASTE SUtttART USE - U. S. Frology 1/2 BSC - Parnwell South Carolina CN - t,1am Nuclear Co. QUAD-CITIES STATION ItN - Hittman Nuclear & Development Co. March 1981 DISPOSITION OF MATERIAL VOLtME (f t ) WOLtME (f t ) MILLICURIES CURIES 7 DATE Co. TPANS. BURIAL SITE PER SHIPMEalf PER MoffrH PER lsHIPMEVT PER PONTil 1
l HN BSC 105.0 16114.5 t
3_g;_gg 1-02-81 HN BSC 105.0 12436.1 1-03-81 HN BSC '105.0 13618.7 1-03-81 CN BSC 85.0 46300.0 1-04-81 HN BSE 105.0 14805.4 (a
" 11960.2
')-0 5-81 HN BSC 90.0 3-0 5-84 USE BWA 1289.8 60.5
'l-09-81 HN BSC 105.0 12827.4 1-09-81 HN BSC '90.0 11016.9 l-10-81 HN BSC 105.0 14421.2 1-10-81 CN BSC 85.0 46300.0 1-11-81 HN BSC 105.0 14158.3 3-11-81 HN BSC 90.0 12726.3 1-12-81 HN BSC 90.0 5957.8 3-12-81 HN BSC 102.0 211.3 3-13-81 HN BSC 105.0 12585.5
11 T
SN EO I R R
UR CE P
T SN EE 9 9 6 0 7 3 6 6 3 0 3 2 8 6 7 3 I M RP 7 4 6 2 3 1 6 9 3 4 6 9 6 5 2 2 UI 3 0 1 7 6 8 6 6 2 6 3 6 1 5 2 0 CH 9 4 5 4 8 4 4 1 2 0 3 0 7 3 1 0 4 1 1 2 6 7 3 4 5 8 5 2 2 8 1 3 I. s 1 1 1 1 1 7 1 1 1 1 1 1 2 1 7 1 I. R I
I E MF
)
H t T f
f f0
(
M
) T E M R R U FE d A1 L e W O u L V n S N O
i t E I T T n S A1 o A W T 9 c 1 S 9 1
) f
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C T r I a (IP 5 0 5 3 5 5 0 5 0 5 5 0 5 5 5 5 0 A U CM EH 0 9 0 9 C 8 9 0 9 0 0 9 0 0 8 0 D -
M S 1 1 1 1 1 1 1 1 1 I D 2 D A U L R A U O E e R Q V P l
D b I a L T O S
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t E n L T e A I m I S p R C O C C C C C C C C o E L C C C C C C S S S S S S S S S S S S S S S S a l T A B B B B B B B B B B B B B B B B n e A I i v M R l e U n o D F B o r O t a .&
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n or O i hCa I h y t s gu a c r( 1 T
I aoo S WlS le Nu O P .
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H H H H H C H H H H H I H H C I hSnst T I I i
c
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1 1 1 1 1 1 1 1 AECHN 1 1 1 1 1 1 1 I 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 WSSCl l E - - - - - - - - - - - - - - - -
RIB J T 3 3 6 6 7 7 8 8 9 9 0 0 3 4 4 5 A 1 1 1 1 1 1 1 1 l 1 2 2 2 2 2 2 D - - - - - - - - - - - - - - - -
3 3 3 3 3 3 3 3 3 ) 3 3 3 3 3 3
i i
i Table 2.0-1 (continued) i RWA - Richland Washington SOLID RADI0 ACTIVE WASTE S1A9 TART j
USE - U. S. Ecology i BSC - Parnwell South Carolina "O I!
CN - Clme Nuclear Co. QUAlH:ITIES STATION llN - Hittman Nuclear & Development Co.
March 1981 DISPOSITION OF MATERIAL IPOLIME (ft ) VOLUME (ft ) MILLICURIES CURIES j DATF. CD. TRANS. BURIAL SITE PER ENIPMENT PER M00ml PER SMIPMENT FER 210NTil 3 26-8 HN BSC 105.0 15756.3 ,
3-27-8 HN BSC 105.0 18610.2 ,
3-27-8 HN BSC 90.0 9312.2 4
3-30-8 HN BSC 105.0 21191.1 3-31-8 l USE BWA 105.0 20244.2 i W
' " 4836.8 689.4169 1
^
i l
i 9
p, I
l
Table 2.0-1 (continued) kWA - Richlar.d Washington SOLID RADIDACTIVE IJASTE Silt 9 TART USE - U. S. Ecology BSC - Parnwell South Carolina UNITS 1/2 CN - Clion Nuclear Co. QUAD-CITIES STATION HN - Hittman Nuclear & Development Co.
April, 1981 T
DISPOSITION OF MATERIAL VOLIME (ft ) WOLUNE (ft ) MILLICURIES CURIES DATF. CO. TRANS. BURIAL SITE PER SHIPMENT PER MONTH PER SHIPMENT PER tt0NTil L-01-81 USE RWA 105.0 11816.3 6-08-81 CN BSC 85.0 71122.7
.-02-81 HN BSC ~105.0 19172.9 i-02-81 USE RWA 630.0 56.7 L-03-81 HN pSd 105.0 15849.5 w
A i-03-81 USE RWA 105.0 19979.6 i-06-81 USE RWA 105.0 16206.1 i-06-81 USE RWA 105.0 18707.5 i-08-81 HN BSC lb5.0 17196.7 i-08-81 HN BSC- 105.0 17522.9 4-08-81 CN BSC 85.0 71122.7 4-08-81 CN BSC 85.0 71122.7 4-09-81 USE RWA 622.5 105.7
! 4-09-81 USE RWA 105.0 16424.6 4-10-83 USE RWA 105.0 17001.1 4-10-81 USE RWA 105.0 11221.1 l
I Table 2.0-1 (continued)
RWA - Richland Washington SOLID RADIDACTIVE WASTE SID91ARY USE - U. S. Ecology BSC - Barnwell Se th Carolina UNITS 1/2 CH - Clean Nucle.1r Co. QUAD-CITIES STATI0tl itN - Hittman Nuclear 4, Development Co. April 1981 DISPOSITION OF MATERIAL 4
VOLUME (ft ) VOLUME (ft ) MILLICURIES CURIES DATE CD. TRANS. BURIAL SITE PER SHIPMElff PER MONTH PER SHIPMENT PER PCNTH
.-13-81 HN BSC 105.0 13877.3 L-13-81 HN BSC 105.0 15668.6
' 14-81 CN BSC 85.0 63700.7 l'
.-14-81 USE RWA 1289.8 66.6
.-15-81 USE RWI 105.0 15655.1
$ ,-I5-81 CN BSC 85.0 63700.7
> 8 f HN BSC 105.0 16577.4 4-1 6-81 USE RWA 105.0 13658.3 4-20-81 USE RWA 105.0 13403.0 4-20-81 USE RWA- 105.0 14097.3 4-21-81 HN BSC 105.0 17150.2 4-21-81 CN BSC 85.0 63700.7 4-22-81 USE RWA 105.0 11260.7 4-23-81 USE RWA 105.0 14506.8 4-24-81 CN BSC 60.5 14260.3
! 4-24-81 USE RWA 105.0 14694.4
X h
m- ,
85a ;
M
- o
- n * *
- My ; ~
9
& 8 9 8 l-E g
0
- - A. 3
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8 -
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v g a. N.
QJ 3 g 5
sc -
M ::
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U U
u
$*- a
- 2 E ~g 3 e * * * * * * *
- e n n - . , . . . . . .
o f E v <. g g * =
- g a
- m -
4 g o 3 8 =
5m a a
O b
- q #
E E < < < u ~ < u <
. 3 N 4 A E E 2 A R E .E
, < ~
we > E g
= %w 8 a,
=
3 34 da 5 2 d u .5 E n rs g 2=so -
g .
3a $o:j ae a j = = = x = u = m 2an o m es.
we oM
- s s s o s s =
=
m o m U *=. g ieee e
<Wu"Z es op 5 5 5 5 5' 5
- e. - - - - - -
36
Table 2.0-1 (continued)
RWA - Richland Washington SOLID R.AD10 ACTIVE WASTE SIM1ARY USE - U. S. Ecology BSC - P.irnwell South Carolina UNITS 1/2 CN - Chen Nucicar Co. QUAD-CITIES STATION llN - Hittman Nuclear & Development Co. g,,g9gg DISPOSITION OF MATERIAL VOLIME (f t ) VOLIME (f t ) MII.LICURIES CURIES DATE CD. TRANS. BURIAL SITE PER SHIPMENT PER MONTH PER EHIPMENT PER PONTil 5-01 HN BSC 105.0 18607.1 5-01 USE RWA 105.0 15609.5 5-04 USE RWA *105.0 13029.4 5-04 USE RWA 105.0 11403.8 5-05 CN .BSd 85.0 135.4 5-06 CN BSC 85.0 135.4 5-06 USE RWA 105.0 35950.5 5-06 HN BSC 105.0 33059.2 5-07 HN BSC l'05.0 19654.5 5- 08 USE RWA 105.0 21084.3 5-08 USE RWA 105.0 28551.8 5-18 HN BSC 105.0 2858.4 5-1I USE RWA 105.0 17354.1 5-13 CN BSC 85.0 135.4 5-13 CN BSC 85.0 135.4 5-13 CN BSC 60.5 17696.8
H T
SN EO I H R
UR CE P
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2 6
6 5
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3 1 1 5 3 n 9 4 0 Cil 1 1 5 7 9 2 i 7 6 7 I S 8 1
6 2
4 2
9 3
8 2 2 7 0 2
1 5 0 3 n 0 1 4 L 2 2 2 ? 2 2 1 LR I E MF
)
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o V / S 1 8
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V s E 1 t E I y I f M 0 0 0 5 0 0 0 0 0 9 0 0 0 0 0 0
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g C i l
n o r O inC a I i
h yt r e T sgu a lc I ao WlS o ic u S O
ol c N P .
S S dnElc o n I N a e Na D A E E N N N E E N E E N N E E E l . wm R T
S S H H H S S C S S H C S S S N
H hSnmt U U U U U U U U U c
.alrwt i .
iRUBCH o C
A r. C N Nl WSSCl P.
NUB T 3 3 4 4 5 5 8 9 9 0 0 1 1 2 6 7 A 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 D - - -
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
- ' l!f ,i F ' i ! >
~
H T
. SN
- EO 3 5
I ir R 8 UR 1 CE 8 P 3 -
6
- T SN -
EE 0 4 6 3 6
- I M RP 0 5 8 8 4 -
UI 5 3 4 0 2 CN 7 1 0 5 8 I. E 8 8 5 0 I 1 1 1 1 -
LR I E
. MP
)
H t T f N
( O M 0 E R 3
) Y M E 4 R U P 6 d A L 3 e t M O u U V n S N O
i t E I T T _
n S A o A 2 T W / S c 1 ,l )T
( E S 9 N V S E 3 t E 1 I T I f M 0 0 0 0 0 T
(I P I T y
_. - C N I , 5 5 5 5 5 0 A U ;
4, 0 8 0 0 0 D
I D mM 2
S 1 1 1 1 2 D A t R A U L E e R Q OP V
l b D I
a L T O S
- o
._ C
- t E n L T ,
- e A I -
m I S p R A C C A o E L d e S S W W E
- a l T A l B B R I
- n e A I i v M R
- l e U -
n o D F B o r O t a .&
g C N n o r O
.- i hC te I T _
- h yt r s gu a lc I aoo e u S
WlS O c N l
o P . .
S S m d cl u n I N nEl l
a
.ew N am D A R
T E
S N
C N
H E
S E
S -
hSnst c r at U U U i .al i .
RUBCl i D
C AEC! r M NSSCI F.
I I UR T 7 7 8 9 9 ,
- A 2 2 2 2 2 .
D - - - - - -
5 5 5 5 5
- we .
- )i;li!' ll lll)1J) . IdJ11 ,l j;J j j! 114 i 1
!4 i l I: ; 4# a
H T
SN E0 I tt R
UR CE P
T SN EE 7 3 7 3 3 I N 8 4 0 8 5 4 5 7 7 0 4 RP ' 4 9 9 UI 5 3 1 7 7 3 0 0 4 7 8 9 2 4 CM 1 8 4 3 4 7 1 6 6 7 6 9 6 6 1 1 5 7 9 7 6 7 7 6 4 6 7 IE 6 5 7 3 1 0 8 8 5 7 4 L 8 1 6 3 6 9 1 3 3 3 1 2 2 2 LR 1 1 4 3 2 1 I E MP
)
H t T f N
( O M
) T E R d R M U E A L P e t e O u l U V n S N i O t E I n T T o S A A 2 T c W / S )
( 1 , T E S 9 N V S E t E 1 I T I M T T f 0 0 0 0 0 0 0 8 0 0 0 0 5 0 0 0 (IP I
0 C N I 5 5 5 5 5 5 5 9 5 5 5 5 2 5 5 5 A U C E SH 0 0 0 0 0 0 0 8 ~0 0 0 0 5 0 0 0 O - t 1 1 1 1 1 1 1 2 1 1 1 1 2 I D S 1 1 1 1 D A I L R e A U O PE R Q V l
b D I
a L T O S
o C
t E n L T e A I m I S p R o E L C C A A C' C C A C C C C C C C C
_ a l T A S B
S B
W B
W S S S W S S S S S S S S n e A I B B B B B B B B B B B B B i v M R
_ l e U n o D F B o r O t
a .&
g C o r N n O i hCa e I T
h yt r
- sgu a c l I aoo c S ,
WlS i Nu O P
o c d c l u n S S nElN I N a e a D A l . wm R T
N H
N H
E E N N N E N N N N N N N N h5ne s t S S H H H S H H H I I H H H H
_ i c
. u. luti .
U U U RUPCH 3 0
_ A EC N N _
WSSCl l F.
BUB T
_ A D
1 0
1 0
3 0
4 0
5 0
5 0
8 0
1 1
_ 2 5 7 8 9 9 3 H_2 2 1 1 1 1 1 1 1
_ 6 6 6 6 6 6 b b t r t 6 b 5 > >
bO
)
6 H
T SN 2 EO 1 I N 8 R 9 UR CE 2 P 6 4
L T
SN EE 1_
7 5 2 I M RP 1 1 5 2 UI 6 4 7 9 CH 1 6 2 8 I S ? 5 9 5 L ? 1 1 1 LR TE MP
)
H t T f N
( O 3 M
T E R 2
) 3 d R M U E 2 A L P 3 e M O u M U W n S N i O t E I n T T S A o A 2 T c W / S 1 8 1 ) T
( E S 9 N V S E 1 t E 1 I T I f M 0 0 0 0
- T I T e (IP 0 C N I n 5 0
5 0
5 5 A U C -u J 0 E SH 1 1 0
'1 0
1 2 I D
D A
M I
R e A U L E O
R Q V P l
b D I
a L T O S
o C
t E n L T e A I m I S p R C C C C o E L S S S S a l T A B B B B n e A I i v M R l e U n o D F B o r O a
t C .& N g
n or h Cae O
I i
h yt r T sa ges o o a uc l I S
WlS le N O P
o c d c l u n S S nEl N a I N a e D A N N N N l . w m R H H I H
hSnat T I i
c
.al rwt i .
RUBCH o C
AtCN41 WSSC1 E 4 5 6 9 RUB T 2 2 2 2 A - - - -
D 6 6 6 6 k *e-
-. . .. - - - . - -~ - -.
Table 2.0-1 (continued)
RWA - Ricliland Washington SOLID RADIOACTIVE WASTE SID9(ARY USE - U. S. Ecciogy BSc - Harnwell South Carolina UNITS 1/2 CN - Cine NucIcar Co. QUAD-CITIES STATION 114 - Ilittman Nuclear & Development Co.
JULY 1931 DISPOSITION OF MATERIAL VOLUME (ft ) VOLUME (ft ) MILLICURIES CURIES DATE CO. TRANS. BURIAL SITE PER SHIPMENT PER Holmt PER 51tIPNENT PER MONTH 7/l/81 HN BSC 105" MLLt nR 7/1/81 HN SSC 105 17425 31 7/2/81 HN BSC 105 24932.90 7/6/bl HN BSC 103 24559.82 7/8/81 HN 8SC 105 19134 m 7/9/JI Tristate USE 1289.75 93.70 ru 7/9/J1 HN ' BSC 105 9567.57 7/10/8 HR 8SC 105 26004.14 7/10/8 HN USC 106 4331.92 7/13/8 HN SSC 103 . 22863.56 7/l5/8 HIJ 85C 105 15041.92 7/1//8 HN 8SC 105 18I41.52 7/16/8 Hacke 8SC 106 7243.06 7/l7/8 HN BSC 103 15923.90 7/20/8 HH 85C 105 15131.90 7/22/8 Nccormack BSC 103 32733.11
H T
SN E0 t 7 i
I t l.
R UR 8 CE 2
- P 6 2
e 6 8
T SN EE I M 8 3 5 6 9 2 7 6 RP 3 2 3 1 2 9 1 UI 5 CH 7 3 5 8, 9 1 8
~ S 3 0 9 9 0 2 7 17 L 8 7 7 9 2 12 LR 2 11 7 4 9 4 IE 3 2 2 1 1 19 2 MP
)
H T
tr f ro
(
H ^
T E R C.
) R A
ME t P 8 6
d L 6 e M O 3 2 V u t S N n O i E I t T T n S A o A 2 T W / S c 1 S g g
)T
( E N V S E I9 l t E 3 1 I T f M 3 T I T y ( P 5 5 5 5 5 5
- C N I I 5 0 0 0 0 0 5 L 0 0 A U C g- E 0 t SH 1 1 1 1 1 1 8 O g 1 2
I D R D A t. R A U I O EP e R Q V l
D b I a L O
T S o
C t E n L T e A I m I S p R o E L C C C C C' t C C a l T A S 5 5 S S s S S n e A I S 8 6 S B e B B i v M R l e U n o D F B o r O a
t g C o.& N n r O i h Cae I T
h ytir l I a o o ae s g. c S WlS l Nu O P .
o c S S e e dnElc l u n I N k k a e N a D A c c H
l .w m R T
N N H H a H H
N H H a N H H hSnst H i
c .al r iat .
RUBCH O C
- - - - - i I
1 1 1 1 1 1 A EC H N 8 f/ 8 6 8 8 8 8 WSSCl l F.
T
/
1 4 / / / / / /
RUI I 2 4 7 9 9 0 1 A 2 / 2 2 2 2 3 3 D / 7 / / / / /
7 7 7 7 ./7 7 7
=
- W -
Table 2.0-1 (continued)
RWA - Ricliland Washington SOLID RADIOACTIVE WASTE SIMIART USF. - U. S. Ecology BSC - parnwell South Carolina WIM 1/2 CN - Clue Nuclear Co. QUAD-CITIES STATION llN - Hittman Nuclear & Development Co. g DISPOSITION OF MATERIAL VOLUME (ft ) YOLIME (ft ) MII.LICURIES H= CURIES DATT. CO. TRANS. BURIAL SITE PER SHIPMENT PER MONTH PER ElllPMENT PF.R HONTH 8/3/81 HN BSC 105 4336.93 8/3/81 HN BSC 105 4362.03 8/4/88 HN BSC 105 14654.65 8/5/88 HN BSC 103 15437.27 d/7/81 HN BSC 85.08 143.65 4
A 3/10/81 HN BSC 105 20780.34 3/12/81 HN BSC 105 1I067.97 J/12/81 Trista'te USE 1299.75 36.48 0/s3/dl Hacke 8SC 105 23670.36 8/14/81 HN BSC- 105 12510 95 3/14/81 HN BSC 105 18206.32 J/17/81 HN 8SC 105 14407.50 d/19/81 McCormack BSC 135 8324.19 8/20/81 Hit BSC 103 14331 8/20/dl Tristate USE 630 113.64 8/21/81 HN BSC 105 9~,34.32 l
l
H T
SN 3 E0 t 9
_ I t R 9 UR 7 CE 9 6
3 wP 2
M T
SN EE 9 5 0 8 0 5 7 I M 5 4 6 4 5 17 2 6 RP .
UI 4 3 8 0 2 8 1 8 4 CH 6 0
7 4
2 4
0 2
9 7
3 2
1 5 7
1 5
I S L 2 2 1 2 3 10 9 LR 1 1 1 1 IE MP
)
H t T N f
( O M
3 Y E R 3
) R A
ME t P 2 d t L ?
e O 0 u M I
V 5 n S N O
i E I t T T n S A o A 2 T c W / S 1 8 E
1 S 91
)T
( N V S E t E 1
I T I f M 5 T I T T S (I P
0 C A MI CU G 5 S 5 5 5 7 5 0 5 O
( EH 0 O 0 0 0 3 0 9 0 U M S 3 1 I 1 1 1 1 1 2
I D D A A UR A U L E e R Q OP V
l b D I
a L T O S
o C
t E n L T e A I m I S p R
_ o E L C C C C C E C C E a l T A S 5 S S S S S S S n e A I B 8 B B B U S B U i v M R l e U n o D F B o r O t a .&
C N g
n or h Cae O I
i t T sa oguo are c h y l I S
_ WlS ol l
c N u O P
S S k
d c nE l un I h k c
e c a
a eNa D A a e t
a e l .w m R N m N k N t m
r N k l iSnet r T H r H c H s o H c c
.ahi t o a i C a i C H r c H R UbCl i O c T M .
C M A EC N N!
WSSCI F, 1
8 81 1
8 1
8 l
d 1
8 1
8 81 81 -
RUB T / / / / / / / / /
A 1 4 6 6 7 7 8 8 D 2 2 2 2 2 2 2 2 13
/ / / / /
9 / / /
3 J B 3 B J 3 3 u
H T
SN E0 t I t R
UR C F.
P T
SN 5 6 3 3 3 9 0 6 7 ) 6 / 4 EE 9 7 4 5 9 3 0 7 9 2 1 7 3 I M 1 5 1 1 RP 1 7 0 4 0 0 0 ! 4 7 6 1 4 3 3 3 UI 4 3 8 CH 5 2
4 7
4 9 2
6 7
2 5
0 9
7 1
3 0
4 0 - 1 3
9 7 5 0 0 1 3
1 b 2 8 17 1 2 6 3 4 4 0 3 2 L 1 1 1 4 1 1 61 1 I 2 2 2 1 LR I E MP
)
H t T f N
( O M
T E R
) R ME U
d A l L P e e t
O V
u U S N n O i E I y t T T g n S A 2 T A g o d
/ S g
c I 1 , ) T
( E S ( N 8 V S E , t E 3 I T I M 0 0 1 f P
T I T 5 5 5 3 5
- C N I (I 5 3 5 3 5 5 5 0
5 5 6 0
5 0 8 0 0 0 0 A U C , H 0 0 0 0 0 8 6 10 O
I D- g ES N
1 1 1 1 1 10 1 1 1 1 1 3 1 2 D A I R A l L E e t q O l
R V P b D I
a L T O S
o C
t E n L T e A I m I S p R o E L C C C C C C C C a l T A C C C C C C C C S S S S S S S S S S S S n e A I S S B
S B
S B B B B B B B B B B B B B i v M R B l e U n o D F B o r O a .&
t g C N n o r O i ht Cae I T
h ys r l I a ge a ao o le WlS c
u S
O o c N P S S k
dnElcl uN na I N c
a e e a e D A m e e N N k l .w m R r N N N N k N k e t u N H
N H
k c H H c lc Snwt s T o H H H H c H c H H a a r at C a a H H
.al i . c H H i
RUBCH o M C
- - - - - 1 1 1 1 1 1 1 1 1 1 1 A F. C N N 6 & 8 3 8 8 8 8 8 8 E 1 1 8 1 8 J
t SSCl l 1 8 8 8 8 8 / / / / / / / / / /
4
/
_ RUB T / / / / 0 1 1 4 6 7 7 4 3 A /
2 8 8 9 1 1 1 l 1 1 l 81 2 2 2 D 2 / / / / / /
. / / / / / / / / / / 3 3 3 3 J 3 J J 3 3 3 9 J 3 3 3 n
,c
,- )1l ,
H T
SN 5 EO t 1
I t R 17 UR 8 CE 5 uP a 9 2
M T
SN EE 2 8 0 5 8 I M 3 7 5 4 1 9
RP UI 1 3 3 9 5 CH 1 3 4 4 7 I E 8 3 7 0 L 6 3 5 8 LR I E 1 1 1 MF
)
t i
f ftr0
( 19 M
Y E R 0
) R M E 5 A U 3 d L P 3 e M O u U V n S N i O E I t T T 1 n S A 2 T 9 A 8 o W / S 1 c 1 )T
( E S R N V S E E B t E 1 I T I M 5
- T I C N I T M E
f (I
P 7 0 T A U C D P EH 3 5 3 5 5 M S
- E 0 8 2 I D 1 10 2 10 10 S
D A t. R 1 A U 1 0 E l
e R Q V P b D a I L
T O S
o C
t E n L T e A I m I S p R o E L C C C C C a l T A 5 S S S S n e A I 8 B B B B i v M R l e U n or o
D F O
B t a .&
C N g
n or O i h Cae I T
h yt r -
s gu a lc I ao o c WlS i u
S O
ol c N P S S e
d c nEl un I N t a e Na D A a l . w m R t hSnst T N N is N N i
c .al r ut i .
H H r
H H R U B :t H O C
T A EC W SS N C Nl l F.
I J d l l b 81 8 1
R UB T / / / / /
A ) 8 4 8 0 D 2 2 2 2 3
/ / / / /
9 1 3 J 3
l Table 2.0-1 (continued)
RWA - Richland Washington SOLID RADI0 ACTIVE 13ASTE SUM 4ARY USit - U. S. Ecology BSC - Parnwell South Carolina UNITS 1/2 i CN Cln1m Nuclear Co. QUAD-CITIES STAT 1018 IIM - Hittman Nuclear & Development Co.
81 DISPOSITION OF MATERIAL VOLUME (ft ) VOLUME (ft ) MII.I.ICURIES MauCURIES DATF. CO. TRANS. BURIAL SITE PER SHIPMEIIT PER MONTH FER lillIPMENT PER NONTH -
10/l/81 Tristate USE 1225.5 100.86 t
80/5/31 HN BSC 105 3934.48 10/7/S1 HN SSC 105 473.22 10/2/dl HN BSC 135 7793.88 10/7/81 Tristate USE. 1327.25 29.74
$ 10/8/81 HN BSC 105 5232.73 10/9/sl HN '85C 105 12427.07 10/14/81. NN BSC 105 11077.21 10/I3/01 HN BSC 105 8770.44 10/19/81 HN BSC 105 6436.05 10/22/81 Tristate USE 1225.5 130.54 10/23/81 Hacke BSC 105 7794.94 10/2d/8I HN 85C 105 9722.24 10/26/E l HN BSC 105 12349.05 10/29/J i Tristate USE 1283.75 51.00 g,,, 86420.47
m aO we T.
E DM UW Co N o - ra - es ,O es . i N
- - ,== 4.3 .O .O W Be O.
m O
. N.
3 O
.r." c
. N. e.
n m.
a .?.
e.
.A o.
e.
es N.
3 D ** O. r3 ==. $3 U5 O O eS *S r4 O N O N N C3 7 e3 C3 e% N
>* 30 C CO M C fi *A m *i to C% N == C5 49 p3 t ,t 4 N O N O C3 .=3 N 3g 4= N - .-
- $al E Se a
M M
tee w
M M l
e D
G d
{b J
O M
3 >
C M g H H CO C m < O" O 4 N H U 3 )*g "JD
. u da N #
n ng "t; U %,e b M 4% N i >
ene f
. N ~
o <
o E Na w =m ., ; ., ,, , ,, ., m .., ,, ,, ,, .: ., :s o
m
.o -m a .o- .o. o a
-n .a. .o.
N 8'* .o. - .o. m.a .c. - -- - -
I a=
@ M O O I C U 1 8 .
O O
u u C 1 b E ** 44
- 4. E O u saa u u u u u u u u u u ha u u g - - e m e + - - - - - - m e m u.
. O D 4D ED dD (D 4D ED G3 ED dE3 El 3 (D El C3
. m 8 O Q km an t- Q 3 0* E
.E. , d a, -
.lll >= T b8 ) D
=
-a
=:: #*5 3 u 2 .
,"kE . ,
u m "o
m "
=
C . "3 8 H
~ 2 ~ ~ -* 2 ~ 2
" ~ ~
v "u E -
u E I E f u.
i I f I v i 3 ~3 I.
JM6$.2 as23 g ~ 1 = x
. iiii o as I
<WU53 s en CC D E
_ e b
<3 s
N
,o N
N C.
<O N
so s
es s
c3 s s
- O 3 -Q s s 3 c0 s s O
s M
s i
- A
< % .A 4 g4 (9 m .N= .N= .m= .= C.O= .O
= =m N N N C % % N N N N N N N
.=.= N.
. . .N. == N.
. N.- N.- %.-
- - - - - - - - - - M a.m =.=* *** -
t 49
B es s
$5 N
.a 36 E E
D!
mm a e b5 N "b E!5 2 x.
[
M the 5
e n
O 3
m l>
C g p u -
c t; t; ;
8 sO ~
ti 0 a
- u .a M h$ -
M o
i e" ~e $ ~~
W "3 E E 5
g E{E g l5
.O 4
- U >=
W d R .
e q N j, -
. a 5 4 u u g:
~ = =
.a 1 g g O b O O
- O e,
j.4 E
E. ed' C 7- as gu
- pr: **
U
$a M
88 0 c
=2 2 rc T arj ae n o j
. .=3 5 (M(fu 2 2
EiEDE f i ea e i _
IE 5"
- W 'J <= -a
=
- 3 2 R O 50
r---- - _ - - _ - - - - - - _ _ - - _ _ _ _ __ _ _ _ _ -
Table 2.0-1 (continued)
RWA - Ricialand Washington MLID RADIOACTIVE WASTE SUletART USE - U. S. Ecology yygyg gg BSC - Barnwell South Carolina CN - Clum Nuclear Co. QUAD-CITIES STATION llN - Hittman Nuclear & Development Co. DECEMBER 1981 DISPOSITION OF MATERIAL DotUME (ft ) WOLUME (f t ) MTLLICURIES CURIES DATT. Co. TRANS. BURIAL SITE PER SHIPMElff PER MONTH PER ENIPMENT PER HONTH 12/2/81 Hacke BSC 105 10044.92 12/3/81 HN BSC 105 12380.52 12/3/81 Tristate USE 1289.75 47.06 12/4/81 Macke' BSC 105 552.04 12/4/81 Hacke BSC 22.5 48808 us
" 12155.62 12/7/88 Tristate USE 105 12/7/8'l Tristate USE 562.5 45.34 12/19/dI HN BSC 22.5 39340.SI 12/10/6i Hacke BSC 165 16383.72 12/10/bl Tristate USE 1225.5 71.42 12/11/81 Hacke BSC 103 1519.60 12/II/dl HN BSC 106 5330.21 12/14/81 Tristate USE 570 138.28 12/88/81 ' HN BSC 103 10537.97 -
12/14/01 Hacke BSC 22.5 39097.10 12/18/81 Hu BSC 10; 12866.57
n----.--. . _ - . . ---. -
Table 2.0-1 (continued)
RWA - Richland Washington SOLID RADI0 ACTIVE WASTE SUtelARY USE - U. 5. Ecology DSC - Itarnwell South Carolina UNITS 1/2 CN - Clas Nuclear Co. QUAD-CITIES STATION life - Hittmari Nuclear & Development Co* DECEMBER 1981 F
DISPOSITICII OF MATERIAL N (f t ) VOLUME (ft ) MII.LICURIES MuuCURIES DATF. Cd. TRANS. BURIAL SITE PER SHIPMENT PER WATH FER SHIPMENT PER NONTH 12/21/8 Hacke BSC 106 10956.35 12/21/8 Hacke BSC 22.5 45794.97 12/24/9 Hacke BSC 105 7644.61 l2/23/8 Hacke BSC 105 6342.12 12/22/d Tristate USE. 420 50.83
$ 12/28/8 HN 8SC 105 6307.44 12/23/8 Tristate USE 630 -66.25 12/28/8 Hacle BSC 22.5 51004.7) 12/30/8 Tristate USE 1269.73 62.78 12/3J/8 H8J BSC 105 10297.23 I2/31/d HN 8SC 105 8057.07 7677 357654.12
Figure 3.1-1 N as . ,aj
=7 Estimated Cumulative Gamma Dose (mrem) from the Quad Cities Station for the ,
5,C M
period January - December 1981. , a Isopleth Labels REL ASE ,^
Small figure - multiply by 10-1 POINT N ^
Large figure - multiply by 10-2 3 x
.J
)
\ "v l }
SCALE i !
' wites
.- 4, o i e f
~
L T O N C
ji N q Q( , 2.5 , ,
~ ,
- ,. , ,34 _ i
- 7; W380m C "a '*a
- 5.0 '1 us so D' * '" .- i Th i Uf ce== wt x i u s sow i *, j M'**a k
/ g _
s c- , ,
"'.., / ,
s* :" (
1 Oh . A ,. ' '\l L L I N O' i S 'f 25j-
- c. ,,^ / lj :a,
\g WHIT S1 Dk E , , ,
1.
r- ..
I /
L T.
S C O T T ,
- R O C K ds .I"'
N e ll *****
{ [ ,
. .. f..,, ~ -
j
, \ ,,4 iSLA *'
l *b I ILL 92 l $gt
~~hy W'<
p .x A /,, /
/
b H4N M Y
~' ..
. _ f. . . . . .
Green tuna
- A .>u5*
SCALE 9 9 e is to mitts C iS 29 30 u m O _5 to 53
Figure 3.1-2 N
/
a' o ,* / '
Estimated Total Concentration (pCi/m3 ) of 1 4 *
'/
- R Noble Gases from the Quad Cities Statidn '
t' M /
' j for the period January - December 1981. i Isopleth Labels RELEASE h4 h Small figure - multiply by 10 i POINT
's
't Large figure - multiply by 10 1 [ 3 4.0 i
h,..'\ v 2,0 I scu.E p,
'
- u.as tllll' ,
h '
!: t
~
C L I N T O N O *' '
4 i
- ~ ,
oc n 2 % * '
% [, cunh E w," i4,, p usao .mi .tp bd j Uf i
u so D' *j ,,
- c. ,, , w ,
Morrison O ,
Comenck aiw , ,
,,'y s erair e*'*.. G r,,
g ;
- 4.q,3 '
SITE i
W A q L L I N I S f I O >=
k[a ~\ W,H ITESI D- E -
e ., , , -
s_ / ,
l.0 _ T.
o S C 0 T T 'f<, R O C K d s ,. Ene l , 'S g ,\ ,
aug **,/
, , t Do M 91W
?:.
~ --
gg .g l SLA /q
_- o / i ,u ,,
97 3
) wM.b"- . %
s,s d wry" H E N R Y
'C YWf\
f ::
na,e
- k ,
1 00 SCAL.E O $ e0 is 2_0 mitts 0 6 so IS 20 f_S 30 a u l
54
(
Figure 3.1-3 N
"' n h a' . a .
=7 Estimated Total Concentration (pCi/m3) of , 1 M R lodine from the Quad Cities Station fot .
the period January - December 1981. qsg {' 10 '
Isopleth Labels REEEASE g/h Small figure - multiply by 10-3 .ct, mT Large figure - multiply by 10-3 [ POINT / '
25 0 '$
l f ' '
b ,
SCALE
' ! I mists 4 '> ..
z c= 1
.s: .
5 1
IE'
=
~
C L 1 N T O N 1 5
H
,, [ ** ,
- h.',, : - -
ce,nroe /\ n us w D**'"
-w i Y ,.
\ 4 y m . wg -
h, ,
s uwn a s
IO cm m.,i, ,
I oao..,.*'*.. ,,,
25 Ob . W A_ 4
- I L L I N O I S ,f I
ITESI DlE,.'
c.*r. j m *)WH sf K '"g** N A.,
q- QS C O T T j
l R O C K si ds
,* /
E"'
- 3. go 'Pwt en
'2 d'
~ - --
iSLA 0} ""
l wgywry~Krt" j b . ~-> ,
fH E N R Y
'[ f T f g Np g**'"us. ;
I x 6
- 7. ,
SCALE io is to uites
( o 9 to s$ FC 2_S M su S
Ou -
55
1
- ' o -
Figure 3.1-4 */
N Estimated Total Concentration (pCi/m3 ) *t.f/
d of Particulate Matter from the Quad Cities Station for the period ' ,'
. ,[ /.' I January - December 1981. ? ;
RELEAS L
/c-5.0h' e
"' l' Isopleth Labels POINT gp3 )
Small figure - multiply by 10-4 Large figure - multiply by 10-5 5.0 5 j 3 l l \
l se SCALE mitts
\ ' I I Y ,,
Genoa e g' .
i L*** e a g ,
- I m' *
! a ,
m - <
[ C L I N ,, T O N $ '
4
) t', '. ,
+ c *> 15 N wison >
- E
'. Clint g
'II u s so ce== A 3
+ , S S o, , ,t
{ u.,,,s.n % b[
(s C-~ . , , \.,
~. .
\ e I O = W A, '
SITE I I N O ih 'f M - \
c= ,,, 3l WH TESI D: E -
a 5._ - mi, s.
_ ~ ..
v- ,+
S C O T T R O C K d s Ene
,*,,/
N' ' *** er **
)
/
'l T _ s ,9
. I_hy. eo g.,
iStA o-l w .
. , , ,,< ,2 j
) z e.
- , , , , /
i w
jE- 4 k%*
eA ..a x N
l SCALE o s e is to v.tts l
l o s o is to __ rs so = =
56
Table 3.1-1 Doses Resulting from Airborne Releases
(
THIS TABLE WILL BE PROVIDED
(
l 57 L
QUAD CITIES NUCLEAR POWErl STATION April 1981 ,
Revision 1 Figure 5.0-1 LOCATIONS OF FIXED ENVIRONMENTAL RADIOLOGICAL MONITORING STATIONS air u ni.,e 1 -Onsile Station 1 ,
2-Onsite Station 2 ,h ,
3-Onsite Station 3 j3 quad cities station 4 NITRIN 5-Seddle Cleb Delty cw-6 -Henson:* Boot Londing
~
" p- -
..=I 7-Clinton <
8 Sikkemo Form ,[ 'I 8 i O el4 W A I L t. I N O I S
- 3. Erie
~
10 Hillsdele ,
ll-Port Syron ,,,ggi,,,1 2
"* to ...'
3 It Bettendorf _
13 Princeion ". % g g g g ,1, 14 Ullte Ridge Rood ] i' ' ' ] " ' . , '
15 DeWilt 16 Los ifoor NS I,'{f B
TLD @
Same as air samplers plus a sufficient number of additional dosimeters placed near the site and near 5 miles to assure, to the extent practical, that one dosimeter , . T' . = = =
is located at each range in each of the . .. . . . . . . .
16 meteorological setors, 58
I QUAD CITIES NUCLEAR POWER STATION Standard Radiological Sampling Program Media s.
m 5 3 3 % $
- e #
8-a 3 N 8 Ol d New Loc. t $ $ 3 5 3 $ h
- E ' u m ' u Code Code Typea Location Description W-15 W-02 On-site No. 1 On-site No. 2 X
X X
X
-16 -03 On-site No. 3 X X
-01 -04 Nitrin X X
-06 -05 Saddle Club Dairy X X
-12 -06 Hanson's Boat Landing X X
-02 -07 C Clinton X X
-03 -08 C Sikkema Fann X X
-04 -09 C Erie X X
-05 -10 C Hillsdale X X
-07 -11 C Port Byron X X
-08 -12 C Bettendorf X X
-09 -13 C Princeton X X
-10 -14 C Utica Ridge Road X X
-11 -15 C DeWitt X X i -13 -16 C Low Moor X X I -17 -17 Musal Dairy Farm X X L
-34 -18 Turner Farm X X
-20 -19 East Moline Water Wcrks X l -21 -20 Davenport Water Works X i -18 -21 C Inlet Canal X
-19 -22 Discharge Canal X
-27 -23 Lock & Dam No. 14 (Mississippi River) X l -27 -24 Davenport Fish Market (Pool No.14, Mississippi River) X a
Control (background) locations are indicated by a "C" in this column.
! All other locations are indicators.
59 L
_ m v _
TABLE 5.0-1 QUAD CITIES STANDARD RADIOLOGICAL MONITORING PROGRAM Nondoutine Sample Media Collection Site
- Type of Analysis Frequency ,
Reporting Levels b C Cs-134 10,Cs-137 20 pCi/m 3
. 1. Air Monitoring (a) Onsite and near Field 1. Filter - gross beta 1. Weekly (1) Onsite Station #1 2. Charcoal 131 2. Bi-weekly d 0.9 pC1/m3 (2) Onsite Station #2 (3) Onsite Station #3 3. Sampling Train -
(4) Nitrin Test and Maintenance 3. Weekly (5) Saddle Club Dairy Fam (6) Hanson's Boat Landing (b) Far Field 1. Filter Exchange 1. Weekly Same as 1 (a)
(1) Clinton (2) Sikkema Fars 2. Charcoal Exchange 2. Bi-weekly When analyses (3) Erie (4) Hillsdale 3. Sampling Train - 3. Weekly are made cn (5) Port Byron Test and Maintenance O (6) Bettendorf (7) Princeton (8) Utica Ridge Road (9) DeWitt (10) Low Moor
- 2. TLD Same as 1 Gamma Radiation Quarterly
- 3. Fish Pool 14 of Mississippi Gamma isotopic Semi-annually Mn-54 3x10 ,Fe-59 1x10 4 4
Co-58 3x10 .00-60 1x10 Zn-65 2x10 Cs-134 1x103 Cs-137 2x103 pCf /Kg wet weight 4 Milk (a) Hansen Dairy 1-131 1. Weekly - I-131 3 pC1/1 Grazi ng Season - Cs-134 60 pC1/1 May to Oct (b) Musal Dairy Cs-137 70 pC1/1
- 2. Monthly -
Now to Apr Ba-La-140 300 pC1/1
TABLE 5.0-1 (continued)
QUAD CITIES STANDARD RADIOLOGICAL MONITORING PROGRAM Non-Routine b Sample Media Collection Site Type of Analysis Frequency Reporting Levels
- 5. Public Water (a) East Moline Water Works 1. Gamma Isotopic 1. Monthly Analysis (See footnote e)
(b) Davenport Water Works of Weekly Composites 6 Cooling Water f (a) Inlet 1. Gross Beta 1. Weekly (b) Discharge
- 7. Sediment (a) Lock and Das No.14 Gamma Isotopic Annually
- 8. Dairy Census (a) Site Boundary to (a) Enumeration by Annually, during 2 miles a door-to-door or grazing season equivalent counting technique (b) 2 miles to 5 miles (b) Enumeration by using referenced information from county agricultural agents or other reliable
$ sources.
(c) At dafries Itsted in item 4. (c) Inquire as to feeding practices.
(1) pasture only (2) Feed and chop only (3) Pasture and feed; if both, ask farmer to estimate fraction of food from pasture
<25%
25-50%
50-751
>75%
- Additional infonnation giving the distance and direction of individual sampling locations may be b
found in Appendix 111 of the 1978 Annual Report.
c Average concentration over calendar quarter.
A gamma 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 d
sample location.
Bi-weeki
, H-3 gx10g , Mn-54shall 1x10mean
, Fe-59 ghat 2x10 , the Co-58 6x102 , Co-60is freqgency once 2x10 2x102 other every
, Zn-65 pek.
, Ir-Wb-95 2
g 4x10 , I-131 2 Cs-134 30. Cs-137 50, Ba-La-1401x10 pCf/1.
Provided by station personnel.
s
- ~ m m
Table 5.0-2 Environmental Radiological Monitoring Program Quarterly Summary Name of facility Quad Cities Nuclear Power Station Docket No. 50-254. 50-265 Location of facility Rock Island. Illinois Reporting Period 1st Quarter 1981 (County, 5 tate)
Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Meana Mean Meana non-routine (Units) Analyses LLD Range Location Range Range Results Air Particulates Gross Beta 77 1.0 0.14 (77/77) Q-02, Onsite #2 0.16 (13/13) None 0 (pC1/m3) (0.04-0.28) 0.5 mi 9 70* (0.08-0.28)
Airborne Iodine I-131 41 0.10 <tLD - -
None 0 (pci/m3 )
Gaasna Background Gamma Dose 16 3.0 11.3 (6/6) Q-01, Onsite #1 14.3 (1/1) 11.9 (10/10) 0 (TLDs) (mR/Qtr.) (9.1-14.3) 0.5 mi 0 0* -
(10.8-14.3)
Q-11 Port Byron 14.3 (1/1) 8.0 ml 9 170*
m Milk I-131 6 5.0 <LLD - -
None 0 (pCi/1)
Cooling Water Gross Beta 34 5.0 112.1 (21/21) Q-228. Spray Canal 217 (13/13) 6.6 (12/13) 0 (pC1/1) (3.0-1800.0) Blowdown at (3.5-1800) (3.0-15.1)
Station Tritium 1 240 410 (1/1) A-22A, Blowdown 410 (1/1) None 0
- Diffuser Pipe -
Gamma Spec. 3 Cs-134 10 240 (3/3) Q-228, Spray Canal 240 (3/3) None 0 (83-440) Blowdown at (83-440)
Station Cs-137 10 707 (3/3) Q-228 Spray Canal 706.7 (3/3) None 0 (296-1500) at station (296-1500)
Mn-54 10 60 (1/3) Q-228, Spray Canal 60 (1/3) None 0 at station -
Co-60 10 245 (2/3) Q-228, Spray Canal 245 (2/3) None 0 (169-320) at station (169-320)
Pubite Water Gamma Spec. 6 10.0 (LLD - - None 0 (pct /1)
Mean and range based on detectable measurements only. Fractions indicated in parentheses.
Table 5.0-3 Environmental Radiological Monitoring Program Quarterly Sussury Name of facility Quad Cities Nuclear Power Station Docket No. 50-254, 50-265 Location of factitty Rock Island. Illinois Reporting Period 2nd Quarter 1981 Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Meana Mean Meana non-routine (Units) Analyses LLD Range Location Range Range Results Air Particulates Gross Beta 78 1.0 0.24 (76/78) 0-01, Onsite #1 0.35 (11/13) None 0 (pCf/mJ) (0.02-0.49) 0.5 mi 9 0* (0.15-0.49)
Airborne lodine 1-131 36 0.10 (LLD - -
None 0 (pCf/m3)
Gamma Background Gamma Dose 16 3.0 12.9 (6/6) Q-11, Port Byron 15.0 (1/1) 13.1 (10/10) 0 (TLDs) (mR/Qtr.) .(11.4-13.9) 8.0 mi 0 170* -
(11.4-15.0)
Miggjyy I-131 6 5/0.5* <LLD - -
None 0
$ Cooling Water Gross Beta 39 2.0 .14.8 (26/26) Q-22B, spray Canal 23.9 (13/13) 5.6 (13/13) 0 (pCf/1) (3.8-76.4) Blowdown at (4.8-76.4) (3.5-12.4)
Station Tritium 1 240 260 (1/1) Q-22A, Blowdown 260 (1/1) None 0 Diffuser Pipe -
Public Water Gamma Spec. 6 10.0 <tLD - -
None 0 (pC1/1)
Fish Gansna Spec. 17 (pCf/g wet)
Cs-137 0.1 <LLD - -
None 0 Other Gasunas 0.2 <LLD - -
None 0 a
Mean and range based on detectable measurements only. Fractions indicated in parentheses.
" ~
Table 5.0-4 Environmental Radiological Monitoring Program Quarterly Summary Name of facility Quad Cities Nuclear Power Station Docket No. 50-254, 50-265 Location of facility Rock Island, Illinois Reporting Period 3rd Quarter 1981 (County, State)
Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Meana Mean Meana non-routine (Units) Analyses LLD Range Location Range Range Results Gross Beta 73 1.0 0.06 (71/73) Q-01, Onsite #1 0.07 (9/9) None 0 Air(pC1/n Part{culates
) (0.02-0.16) 0.5 mi 9 0' (0.02-0.16)
Airborne Zodine 1-131 40 0.10 (LLD - -
None 0 (pC1/m3)
Gamma Background Gamma Dose 16 3.0 12.4 (6/6) Q-11, Port Byron 13.8 (1/1) 12.2 (10/10) 0 (TLDs) (mR/Qtr.) (11.5-13.6) 8.0 mi 0 170* -
(9.9-13.8)
None 0 (pCi/1)
Cooling Water Gross Beta 39 2.0 5.3 (26/26) Q-22B, Spray Canal 5.8 (13/13) 4.5 (13/13) 0 (pC1/I) (3.0-8.7) Blowdown at (4.3-8.3) (3.6-5.1)
Station Tritium 1 240 330 (1/1) Q-22A, Blowdown 330 (1/1) None 0
- Diffuser Pipe -
Public Water Gamma Spec. 6 10.0 (LLD - -
None 0 (pC1/1)
Botton Sediments Gamma Spec. 1 (pci/g dry)
Cs-137 0.1 0.60 (1/1) Q-23 Lock & Dam 0.60 (1/1) None 0
- 14 Mississippi River 15.0 mi 9 220' Other Gaaunas 0.2 <LLD - -
None 0
- Mean and range based on detectable measurements only. Fractions indicated in parentheses.
Table 5.0-5 Environmental Radiological Monitoring Program Quarterly Sumary Name of facility Quad Cities Nuclear Power Station Docket No. 50-254, 50-265 Location of facility Rock Island, Illinois Reporting Period 4th Quarter 1981 (County, 5 tate)
Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type . Number of Meana Mean Meana non-routine (Units) Analyses LLD Range Location Range Range Results Air Particulates Gross Beta 84 1.0 0.04 (84/84) Q-02, Onsite #2 0.04 (14/14) None' O (pC1/m )
J (0.01-0.06) 0.5 mi 9 70* (0.03-0.06)
Q-03, Onsite #3 0.04 (14/14) 0.6 mi 9 170* (0.02-0.05)
Airborne lodine I-131 42 0.10 <tLD - -
None 0 (pC1/m3 )
Gem Backgrwnd Gamma Dose 16 3.0 11.8 (6/6) Q-11. Port Byron 14.9 (1/1) 12.8 (10/10) 0 (TLDs) (mR/Qtr.) (31.0-13.7) 8.0 mi 9 170* -
(11.3-14.9)
M11k I-131 12 5/0.5* <LLD - - None 0 g (pti/1)
Cooling Water Gross Beta 42 2.0 4.7 (28/28) Q-228, Spray Canal 4.8 (14/14) 3.6 (14/14) 0 (pC1/1) (2.8-10.8) Blowdown at (3.3-8.0) (2.7-6.0)
Station Tritium 1 240 690 (1/1) Q-22A, Blowdown 690 (1/1) None 0
- Diffuser Pipe -
Public Water Gamma Spec. 6 10.0 <LLD - -
None 0 (pti/1)
Fish Gamma Spec. 9 (pCf/g wet) Cs-137 0.1 (LLD - -
None 0 Other Gammas 0.2 <LLD - - None 0
- Mean and range based on detectable measurements only. Fractions indicated in parentheses.
L - _. - -
i QUAD CITIES NUCLEAR POWER STATION Table 5.1-1 1 Gamma Radiation as Measured by Thermoluminescent Dosimeters (TLD)
Standard Radiological Monitoring Program.
1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Date Placed: 03/28/81 06/27/81 10/03/81 Date Removed: 03/28/81 06/27/81 10/03/81 01/01/82 01/02/82*
Location Average mR/ Quarter On-Site Indicator Locations Q-01 On-site No. I 14.3 2.6 11.420.5 13.421.0 11.8 0.7*
Q-02 On-site No. 2 10.822.6 13.710.4 11.5 1.1 11.810.6*
Q-03 On-site No. 3 9.113.9 12.710.5 11.511.2 11.210.6*
Mean t s.d. 11.4 2.6 12.621.2 12.121.1 11.620.4 Off-Site Indicator Locations Q-04 Nitrin 10.822.6 12.021.0 12.7 1.6 11.010.7*
0-05 Saddle Club Dairy 10.822.6 13.910.6 11.7il.1 11.020.9*
Q-06 Hanson's Boat Landing 11.712.6 13.4tl.0 13.6 1.2 13.7 1.0 Mean + s.d. 11.110.5 13.121.0 12.7 1.0 11.9 1.6 Background Locations Q-07 Clinton 13.0 2.6 14.010.7 13.4tl.0 13.3 1.0 Q-08 Sikkema Farm 13.023.9 14.310.6 12.521.2 13.1 0.7*
Q-09 Erie 10.8 1.3 13.6t0.8 11.6 1.5 12.110.8*
Q-10 Hillsdale 10.812.67 13.4tl.0 12.921.3 12.510.7*
Q-11 Port Byron 14.313.9 15.010.4 13.811.1 14.010.8*
Q-12 Bettendorf 11.7tl.3 13.010.5 12.8 1.2 13.521.0 Q-13 Princeton 11.7t2.6 12.6 0.6 12.521.1 13.711.2 Q-14 Utica Ridge Road 10.811.3 11.610.5 11.411.2 12.021.0 Q-15 DeWitt 10.8 2.6 11.410.4 9.9 1.1 11.321.0 Q-16 Low Moor 11.722.6 11.720.7 10.8tl.3 11.320.9 Mean + s.d. 11.921.2 13.1 1.2 12.721.0 12.8 1.1 I
4 66
E QUAD CITIES NUCLEAR POWER STATION Table 5.1-1. (continued) t Gamma Radiation as Measured by Thermoluminescent Dosimeters (TLD).
Special Program.
Inner Ring, Near Site Boundary, Indicator Locations.
1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Date Placed: 03/28/81 06/27/81 10/03/81 Date Removed: 03/28/81 06/27/81 10/03/81 01/01/82 01/02/82*
Location Average mR/ Quarter Q-101-1 10.8 1.3 12.020.8 11.421.2 11.020.6*
Q-101-2 11.7t2.6 10.710.8 9.811.0 11.021.1*
Q-102-1 10.812.6 12.4 1.0 12.011.2 12.320.8*
Q-102-2 11.712.6 11.110.5 10.8 1.1 12.210.6*
Q-103-1 10.821.3 11.410.8 10.621.2 11.310.9*
Q-103-2 10.8tl.3 10.111.6 10.5 1.0 11.010.9*
Q-104-1 . 9.112.6 10.810.4 10.121.5 10.520.5*
Q-104-2 9.121.3 12.2 1.1 11.3tl.0 11.110.8*
Q-105-1 10.4 1.3 11.210.9 11.4 1.1 10.910.6*
Q-105-2 11.7 1.3 11.0i0.6 10.821.1 11.8 0.6*
Q-106-1 10.4 1.3 11.511.1 10.8tl.3 11.510.6*
Q-106-2 10.421.3 11.210.5 11.211.1 11.910.7*
Q-107-1 10.421.3 12.410.5 11.7 1.2 13.311.6*
Q-107-2 10.411.3 10.810.6 11.311.2 13.010.6*
Q-108-1 7.611.3 12.110.7 11.1 1.2 10.420.6*
Q-108-2 13.022.5 11.710.4 10.5 1.0 10.510.6*
Q-109-1 11.711.3 11.310.7 10.6 1.4 10.210.9*
Q-109-2 11.712.6 11.610.8 10.3 1.2 10.310.5*
Q-111-1 14.312.6 12.610.7 11.3 1.1 13.620.9 Q-111-2 11.7 1.3 11.810.4 10.111.1 12.3 0.9 Q-112-1 11.712.6 12.620.6 11.111.1 12.711.0 Q-112-2 13.012.6 13.310.4 12.5 1.0 13.711.3 Q-113-1 13.0 2.6 13.010.8 11.3 1.1 11.821.3 Q-113-2 11.721.3 11.710.5 ND (Missing) 11.211.8 Q-114-1 11.712.6 12.210.7 10.321.3 9.910.9 Q-114-2 9.111.3 11.110.7 9.911.1 10.310.9 Q-115-1 10.411.3 12.210.6 10.8 1.2 13.121.0 Q-115-2 11.722.6 12.6 0.6 11.621.0 13.221.0 Q-116-1 13.012.6 12.2 0.6 11.2 1.1 12.9 1.0 Q-116-2 13.921.3 10.8i0.9 10.4il.3 11.621.0 Mean i s.d. 11.211.4 11.710.8 10.910.6 11.7 1.1 67
QUAD CITIES NUCLEAR POWER STATION i
f Table 5.1-1. (continued)
Gamma Radiation as measured by Thermoluminescent Dosimeters (TLD).
Special Program.
Outer Ring, Near 5 Miles Radius, Indicator Locations.
1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Date Placed: 03/28/81 06/27/81 10/03/81 Date Removed: 03/28/81 06/27/81 10/03/81 01/01/82 01/02/82*
Location Average mR/ Quarter Q-201-1 13.0 2 5 12.8i0.4 11.8tl.0 14.221.0 Q-201-2 13.012.6 12.510.4 12.5 1.0 14.411.2 Q-202-1 11.722.6 11.310.9 10.0 1.0 11.221.0 Q-202-2 10.4 1<3 10.7t0.6 10.7 1.1 10.811.0 Q-203-1 11.722.6 12.610.6 11.421.3 12.3 1.0 Q-203-2 13.021.3 12.Si0.7 13.7 1.1 12.910.6*
Q-204-1 13.021.3 13.6il.0 12.421.1 14.4 1.1*
I Q-204-2 13/0 1.3 13.6 0.5 13.221.2 13.8 0.6*
Q-205-1 11.712.6 13.720.5 13.3 1.1 13.610.7*
Q-205-2 11.712.6 12.510.6 12.0 1.1 12.210.8*
Q-206-1 14.312.6 13.li0.5 11.4tl.2 12.420.7*
Q-206-2 14.321.3 11.8 0.6 12.5 1.3 12.4i0.9*
Q-207-1 13.012.6 12.9 0.6 12.011.0 12.6i0.7*
Q-207-2 11.7 1.3 11.3i0.5 11.1 1.2 11.2 0.8*
Q-208-1 11.711.3 11.8t0.5 11.4 1.0 11.2i0.6*
Q-208-2 11.722.6 13.010.7 12.621.2 13.4 1.0*
Q-209-1 13.0 2.6 13.210.7 11.Sil.3 12.4i0.6*
Q-209-2 13.0 2.6 11.210.5 11.4 1.3 10.6i0.8*
Q-210-1 13.011.3 11.810.5 11.621.0 11.5 1.0 Q-210-2 14.322.6 13.710.7 13.5 1.1 13.911.0 Q-211 14.3 2.6 15.0 0.4 13.421.1 15.0 1.1 Q-212-1 13.0i2.6 14.720.7 13.6 1.0 13.610.8 Q-212-2 11.7 1.3 11.310.5 10.4 1.0 10.711.1 Q-213-1 11.712.6 12.420.4 11.4 1.3 13.921.6 Q-213-2 10.411.3 11.0 0.7 10.311.3 11.5 1.0 Q-214-1 19.513.9 13.3 0.5 11.711.0 13.211.2 Q-214-2 18.223.9 13.320.9 13.311.5 13.410.9 Q-215-1 18.213.9 14.320.5 12.0il.0 13.3 0.9 Q-215-2 16.911.3 15.710.9 13.011.7 13.510.9 Q-216-1 24.726.5 14.6t0.5 11.911.3 13.1 0.9 i
Q-216-2 22.1 3.9 13.310.9 12.811.2 14.4 1.0 Mean i s.d. 14.013.4 12.821.2 12.1 1.0 12.811.2 68
APPENDIX 11 METEOR 0GICAL DATA 69
j i
APPENDIX II METEOR 0GICAL DATA 1
i 1 i i
i f 69
} - -
OU AD-CITIrs MICLF AP PowFF ST A rin ,
PFR!nD nr 9FCr,po - JANUAFY - %WCH 1941 S!ABILTTY CLISS - FXTL FvFI,Y Ot4ST AriLE ( D r.I,T A T 290-33 FT)
WIN 05 W ASilRED /T 24h FEET sfNG Alko SPEED (Ih VPH)
DIPF.CTION .A-3 4- 7 8-12 13-14 10-24 GT 74 roTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O E f. F 0 0 0 0 0 0 0 E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSd 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0
'd 0 0 0 0 0 0 0 dra N O O O O O O O NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABl.E O O O O O 0 0 TOTAL 0 0 0 0 0 0 0 NOURS OF CALM IN THIS STABILITY CI, ASS - 0 HOURS OF 4ISSING WIND PEASilPEuFNTS IN THIS STABILITY Cl, ASS -
u HOURS OF MISSING STABILITY *FASURFHFNTS Iri ALL STA911,ITY CLASSES - O l
i 70 (
l
Ol'AD-CITIES hiiCI F AP Po t.F P STAT 10fi PEPj00 OF PECORD - JAP 40AAY - fiARCH 1441 STAbIf,ITY CLASS - MODE P ATFI,Y O!'ST AnLE ( DFT.T A T 29o-33 FT)
W i tJ DS ME AsilRED AT 296 FFET blND W IP>D SPF FD ( I f, upp)
DIPECTION .R-3 4- 7 H-17 13-1R 19-24 GT 24 Tt'T A L N O O O O O O O PJ N E O O O O 0 0 0 NE O O O O 1 0 1 ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 2 0 0 0 2 WSW 0 0 1 0 0 0 1 d 0 0 0 0 0 0 0 dNa 0 0 0 0 0 0 0 4* O O O O O O O NNW 0 0 0 0 0 3 3 VARIAHLE O O O O O 0 0 TOTAL 0 0 3 0 1 3 7 HOUPS OF CAL" IN THIS STABILITY CIASS - 0 HOURS OF MISSING WTND MEASUPEMENTS IN THIS STAITILITY CLASS - 0 H0 tips OF MISSING STAPILITY MEASUFFMENTS IN AIL STABILITY CT.ASSFS -
0 71 l
l
Oll AD.(* IT T FS NI'CLEAP D0eEF ST AT I41r#
PERIOD OF PECOPD - .1M111 AP Y - M A RCH 1981 STAklLifY CIASS - SLIGH1f,Y lif4 ST A B f 4 (OFI,rA T 296-33 FT)
WINDS PEASUPED AT 296 FF6T WIND w i flD SPEED (TM uPH)
DIRECTIOtt .R-3 4- 7 H-12 13-1A 14-24 GT 24 TOTAL N O O O O 1 1 2 O O O O O- 0 0 NNE NE O O O 1 1 0 2 O O O O O O ENE O O O O O 1 0 1 E
ESE O O O 1 0 0 1 SE O O O O O O O O O O O O SSE O O 0 0 0 1 0 0 1 S
SSW 0 0 1 1 0 0 2 SW 0 0 1 1 0 0 2 WSW D 0 0 2 0 0 2 W 0 0 3 1 0 -
0 4 WNW 0 0 0 2 4 0 6 NW G 0 0 1 1 0 4 NNW 0 0 0 0 0 2 2 VARIABLE O O O O O O O l
l f
TOTAL 0 0 5 11 10 1 29 HOUPS OF CALM IN THIS STABILITY CLASS - 0 H011PS OF MISSING WIND HEASilPEMENTS IN THIS STABILITY CLASS - O 0
f H0tlRS OF MISSING STABII.ITY MEASUPEMENTS IN ALT. STABILITY CLASSES -
I i
t 72 L
OllAD-CITIES NilCLFAP P O'e F F STATION PEpinD OF PECnpD . .1ANilARY . MARCH 1991 STAHTI.ITY CLASS - N FitT R AI, (OFb7A T 296 33 FT)
WINDS MEASilHED AT'2'95 FEET WIhD WIND SDEFD ( I t. '4 P H )
DIRECTION .R-3 4- 7 H-12 13-18 19-24 GT 24 TOTAL N 0 R 24 29 7 1 69 NNE O 1 12 21 5 0 39 NE O 12 13 14 10 0 49 ENE O 9 14 6 8 0 37 E O 6 4 17 16 0 43 ESE O 7 6 21 12 0 46 SE O 3 2 13 10 0 28 SSE O 3 1 3 15 2 24 S 1 3 4 12 11 7 38 SSW 1 3 9 31 15 4 63 SW 1 6 24 25 9 6 71 dSW 0 to 15 20 6 0 51 W 1 17 24 35 30 R 115 aNW 1 21 32 57 80 34 225 Nn 0 5 26 120 84 19 254 NNW 0 5 31 66 4 2 113 VARIABl.E O O O O O O O TOTAL 5 119 241 490 127 83 1295 H0llRS OF CALM IN THIS STABILITY CLASS - 0 HOUPS OF MISSING WIND MEASilREMENTS IN THIS STABILITY CLASS - 0 Hnt!PS OF MISSING STABILITY VFASUPFPENTS IN ALL STARILITY CLASSES - 0 73
r a
Gil4D-CIT IES MICf,E AR POnFH STATION PFPIOD OF PECDPD - ilAN!! Arf - 'dAPCH 19H1 STAFILITY CLASS - SI,1GHTL.Y STARI.E ( DFI,0 4 T 296-33 FT)
W INDS 'dE ASUPED AT 246 FEET alND kih0 SPFFD (Th >PH) 13-18 10-21 GT 24 TO T AI, DIPECTION .8-3 a- 7 9-12 r1 0 2 5 7 0 0 14 NNE 1 3 7 7 0 0 1R NE O 1 8 14 1 0 24 FNE O 3 3 13 4 0 23 E O 4 6 8 4 0 22 ESE 1 1 1 3 5 3 14 SE O O 4 8 7 0 19 SSE o 1 3 11 7 4 26 S 0 0 1 22 1R 5 46 SSW 1 2 8 41 14 3 00 SW 1 0 20 22 20 2 e5 WSW 1 1 8 25 R 4 47 i
- W 0 1 5 36 22' 4 68 d t. a 0 2 12 39 24 5 81 Na 0 2 13 34 8 0 57 NNW 0 6 21 33 3 0 e3 l
i VARIABI.C 0 0 0 0 0 0 0 l
l l
TO T AI, 5 29 125 322 145 30 656 i HOUPS OF CALM IN THIS STARILITY CLASS - O l HOURS OF MISSING alND MEASUREMENTS IN THIS STABII,ITY CLASS - 0 HOURS OF MISSING STABILTTY MEASUPEMENTS I rt ALI. STABILITY CLASSES - 0 i
l
\
74
OtfAD-CITIES NIlCLEAD PnaEP STATinal PEPinD OF RECOkD - 1ANDAPY - MARCH 1 4.11 ST AB II,11 Y CI, A SS - dG0F R ATFI,Y STAHl.E ( O FI,T 4 T 746-41 L' T )
'41N05 uF ASilRED A T 296 FEFT aIND WIND SPFFD (IN .v P H )
DIPECTI0ta 9-3 4- 7 9-12 13-18 19-24 GT 24 TOTAL N O 4 2 0 0 0 6 NNE O 1 1 0 0 0 2
- l E O 1 2 2 0 0 s Et!E 1 0 3 4 0 0 A E O O 1 4 4 0 4 ESE 1 1 0 6 4 0 12 SE O O O 3 1 0 4 SSE O 1 2 9 1 0 13 5 0 0 1 9 1 0 11 SSW 0 1 3 H 0 0 12 SW 0 2 8 11 1 0 22 WSW 1 1 3 6 0 0 11 W 0 3 3 10 2 0 18 d '# W 1 2 3 5 0 0 11 NW 0 2 3 2 0 0 7 NNW 0 to 10 5 1 0 26 VARIABLF 0 0 0 0 0 0 0 TOTAL 4 29 45 94 15 0 177 H0llPS OF CALM IN THIS STABILITY Cl, ASS - 0 H0llRS OF MISSING WIND adEASUPEMEtiTS IN THIS STAB 1f,ITY CLASS - o HollRS OF MISSING ST A R II,I Ti *EASUPEMFNTS TN ALI, ST ABII,ITY Cl, ASSES - O 75
]
1 4tI AD-C IT I ES NilCLEAR P n '* E H STATID's PERIOD OF PEcliPD - .1 A rill i PY - MAPCM 1Q91 51 ABILITY Ct. ASS - EXTkFFEl.( STAPLE ( O F1.T 4 r N6-3 3 FT)
WINDS ME AstJpED AT 296 FEET WIND W!HP SPEFD (Ib MPF)
OIuRCTION 9-3 4- 7 8-12 13-18 19-24 GT 24 rot AI. ;
N O 1 1 0 0 0 2 i
NNE O 1 0 0 0 0 1 NE 1 1 0 0 0 0 2 ENE O O O O O O O E O O C 0 0 0 0 ESE O O O O O O O SE O O O O O O O SSE O O O 1 0 0 1 5 0 0 0 2 0 0 2 SSW 0 0 2 4 0 0 6 S 'a 0 3 3 1 0 0 7 WSW 0 1 1 0 0 0 2 W 0 0 1 0 0 0 1 i d ra w 0 0 0 0 0 0 0 NW 0 2 0 0 0 0 2 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O TOTAL 1 9 R A 0 0 26 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOUPS OF MISSING WIND MEASUPEMENTS IN THIS STARILITY CLASS - 0 HOURS OF MISSING STARII.1TY *EASURFUENTS IN AI.L ST AB11,ITY CL ASSES -
0 76 l
l
GII AD-C IT I ES tellCLE. AF PO*EP STATIOh PERIOD nF' DECODD - APPIL - Jilt E luul STABTLITY Cl. ASS - EXTD E- F LY f16S T AH LF ( D FI.T a T 206-33 FT) d1NDS '% ASilP ED AT 796 FEET a l rJD aIND SPEED ( I t: l4PH)
OIRECTION 8-3 4- 7 6-12 13-18 19-24 GT 24 TOTAL N O o 0 0 0 3 3 N f4 E O O O O O O O tlF 0 0 0 0 0 0 0 Eta E O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O 0 0 SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 1 0 0 1 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0
) W 0 0 0 0 0 0 0 wNW D 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNd 0 0 0 0 0 0 0 VARIABLE O O O n 0 0 0 TOTAL 0 0 0 1 o 3 4 H0tlPS OF CALM IN THIS STABTLITY CLASS - 0 H0tJPS OF MISSING WIND MEASUREMFNTS IN THIS STABILITY CLASS - 0 Hul!PS OF MISS t r!G STAPII,ITY M F A SI:R F M E P'TS IN ALL STABTLITY CLASSFS - 4 f
77
r QUAD-CITIES NUCLEAP POeER~ STATION PFPIOD OF PECORD - ADRI!. - JilNE 1941 1 STABILITY CLASS - MODERATELY ONST4RLE (Dw.LTs T 246-33 FT)
WINDS ME ASilPED AT 296 FEET ,
WIND alND SPEED (IM lAph)
DIRECTION .8-3 4- 7 8-12 13-19 19-24 GT 24 TOTAL N O O O O O 1 1 NNE O O O 1 3 0 4 NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE 0 0 0 0 0 0 0 SE O O O O O O O SSE O O O O O O O
'S 0 0 0 0 0 0 0 SSW 0 0 3 3 0 0 6 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0
(
WNd 0 0 0 0 0 0 0 NW 0 0 0 0 1 0 1 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O TOTAL 0 0 3 4 4 1 12 HOUPS OF CALM IN THIS STABTLITY CI. ASS - 0 HOURS OF MISSING WTND *EASURF4ENTS IN THTS STABILITY CLASS - 0 i
HOURS OF MISSING STABII,ITY MEASUPEMENTS IN ALL STABILITY CLASSES - 4 4
i i
, 78 i
Il I
l OHAD-CITIES NUCLFAF PDhEH STATION PERInD OF PECC'RD - APPII. - JUtlE 1041 STAP,IlIri CI, ASS - SLIGH1T,Y ONSTABLE (DEIT4 T 7 % -33 FT)
WIhDS 'AFASURED AT 796 FEET
- IND WIND SPEED (Th MPH)
OIRFCTION .8-3 4- 7 R-12 13-18 19-24 Gr 74- TOTAL k 0 0 0 0 1 0 1 NNE o 0 0 2 3 0 5 NE O O O 3 3 0 o ENE O O O O O O O E O O O 1 0 0 1 ESE O O O O O O O SE O O O 1 1 0 ?
SSE O O 4 6 3 0 13 S 0 0 1 3 1 0 5 SSW G 0 5 3 s 1 0 9 SW 0 0 1 6 0 0 7 WSW 0 0 1 1 0 0 2 4 0 0 0 1 0 0 1 dNW 0 0 0 2 4 0 o NW 0 0 0 0 6 0 6 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O TOTAL 0 0 12 29 23 0 64 i
HOUPS OF CALM IN THIS STABIt.ITY CLASS - 0
- H0llPS OF MISSING WIND MEASUPEMENTS IN THIS STARifITY CLASS - 0 HOUPS OF MISSING STABII.ITY MEASURFMENTS IN ALL STABIt.ITY CLASSES - 4 l
i i 79 f
OllAD-CITIES NilCLFAP PneER STATIO*-
PEHIOD OF PECOPD - APPIL - JilNE 1991 STAbit, TTY Ct. ASS - NEll1P A T, ( O h !,T A T 296-33 FT)
WTNDS MEASilPED AT 296 FEET nIMD WIND SPEED ( I t. MPH)
DipECTION .A-3 4- 7 8-12 13-19 19-24 GT 21 TOT AI.
N 0 5 16 26 11 7 5%
NNE O 4 11 23 22 11 71 NE 1 12 17 24 18 2 74 ENE O 6 23 30 7 10 76 E O 4 1H 25 13 1 of ESE 1 2 7 17 6 0 33 SE 2 12 23 30 0 0 e7 SSE 2 R 19 35 9 1 74 5 0 19 25 28 30 14 115
, SSW 3 19 25 36 23 to 116 SW 2 8 10 11 2 3 36 WSW 6 6 11 24 4 10 61 W 0 17 11 22 1R 31 99 l WNW 0 6 21 30 2A 7 42 NW 0 11 26 34 28 4 193 NNw 2 4 23 22 12 1 o9 VARIABLE O O O O O O O TOTAL 19 147 2H6 417 231 112 1712 HOUPS OF CALM TN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 2 HOURS OF MISSING STABII,ITY MEASlIRF*ENTS IN AT,1, STABILITY CLASSES - 4 80
QUAD-CITIES Hl'C L E A P PO*EP STATION PEPIOD OF PECDHD - APRII. - JIINF 1981 STAHILITY Cf. ASS - SLIGHTLY STaubF (DELLA T 2'86-3 3 FT)
WINDS MEASURED AT 246 FEET WIND WIND SPEED (IN ldPH)
DIPFCTION .H-3 4- 7 8-12 13-1A 14-24 GT 24 TOTAL N 3 4 9 7 0 0 23 i i
PIN E 1 4 -9 12 4 0 30 i
NE O 4 15 10 2 0 31 ENE 1 3 12 15 1 0 32 E 1 3 10 20 3 1 38 ESE O 4 8 2R 6 0 46 SE O 7 20 29 10 0 66 SSE O 5 12 34 26 3 80 S 0 5 15 30 51 to 120 SSW 1 4 17 29 23 8 82 SW 0 7 8 17 1 1 34 dSW 0 4 11 5 1 0 21 d 1 1 6 4 7 0 19 ANW 1 7 11 11 5 0 35 N 'a 1 7 22 21 0 0 51 NNW 0 0 12 3 0 0 15 ,
VARIABl.E O O O O O O O TOTAL 10 69 197 275 140 32 723 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND ME AstikEMENTS IN THIS STARILITY CLASS - o 1
H0llPS OF MISSING STABII.lTY MEASUPFUENTS IN AI.L STARII. TTY CLASSFS - 4 81 .
i
l l
l OU/ D-CIT IFS NI'CL E AR P n ,, g o STATION PEPIOD OF PErnPn - APHIL - JilNF 1991 51AAILTTY CLASS - MODEPATEL) STA41E (DE LT A T 796-33 FT)
WINDS t'FASilPED AT 746 FFET
- a lND aINC SPEED (IF MPH)
DIPECTION .A-3 4- 7 9-12 13-1H 10-24 GT 74 rt,T AL )
..... ...-- ----- ----- ..... ...-- l l
- 1 1 1 1 1 0 0 4 i
NNE O 0 3 1 0 0 4
'l E o 0 1 2 0 0 3 ENE O O 1 0 0 0 1 2 0 0 4 E 1 1 5 I
FSE O 1 5 7 0 0 13 SE O O 1 5 0 0 6 SSE 1 0 1 7 1 0 10 S 0 1 3 3 2 0 9 SSW 1 5 4 5 0 0 15 SW 0 1 2 2 0 0 5 WSW 1 1 0 3 0 0 5 W 1 2 1 4 1 0 9 4 t. W 4 2 1 4 6 0 17 Na 1 5 2 3 0 0 11 i
N N n' 1 3 1 0 0 0 5 VAPIAHI,F 0 0 0 0 0 0 0 i
l TOTAL 12 23 32 49 to 0 126 l
H0 tips OF CALM IN THIS STABILITY CLASS - 0 H()t!RS OF MISSING *IND MEAStlPFMENTS IN THIS STARILITY Ct. ASS - o HollPS OF "ISSING STABILITY FFASUPEMENTS IN ALL STARILITY CLASSES - 4 l
r i
l 82 l
l
Oll/.0-C I T I ES MilCLEAP POAEP STATTON PEPIOD LF PECOND - APRIL - JUNE 19A1 ST AisILITY CL ASS - EXTPE*EL Y ST APLE (OEl. f A T 796-33 Fr) wlN05 MEASUPFD AT 296 FFET nIND WIND SPEED (IN d PH)
DIPFCTION 9-3 4- 7 R-12 13 19-24 GT 24 TOTAL IJ 0 1 0 0 0 0 1
'J N E 1 0 0 0 0 0 1 NE 2 0 0 0 0 0 2 ENE O O O O O O O E 1 0 0 0 0 0 1 ESE O 2 0 0 0 0 2 SE O 1 2 0 0 0 3 SSE O O O 2 3 0 5 S 1 0 0 1 1 0 3 SSd 0 1 3 1 0 0 5 SW 0 2 0 0 0 0 2 WSW 1 2 0 0 0 0 3 W 1 1 0 0 0 0 2 W N 'n 0 0 0 0 0 0 0 Nw 0 0 0 0 0 0 0 NNW 1 0 0 0 0 0 1 VARIARLF 0 0 0 0 0 0 0 TOTAI, 8 10 5 4 4 0 31 HOUHS OF CALM IN THIS STABILITY Cl, ASS - 0 H0llPS OF MISSING WIND MEASUPEMENTS IN THIS STARIf,ITY CI, ASS - 0 HollPS OF MISSING ST ABILITY ME ASUREMENTS IN ALL STABILITY CI, ASSES - 4 l
i 83
1 i
l t'8 l i
l SdSSV'AD All'lI b VIS T14 P.1 SIN 3WidilSVar All'11 d V AS Ut41 S S i r.
~
0 - 30 S dilun j 1
0 -
SSV'13 A11'llbV1S S141 'l i S1N.s d 1ti llS d 3 a U N i t* DNISSih 30 Sdilled i u -
SSV IJ A11'lltiVib Sini N1 n'lVJ Au SellOH 1
l 4 0 0 4 0 0 o 'lV101 l l
l l
0 0 0 0 0 0 0 31G V i d V A l
O O O O O O O FNb 0 0 o u o o 0 vh 0 0 u u o 0 0 MJ 0 0 0 o o u o I4 E O O E o 0 0 PSM 0 0 0 0 0 O U YS 0 0 0 0 0 0 0 MSS l 0 0 0 u u o S 0
O O O o 0 0 0 3SS O O O O O O O 3S O u o 0 0 0 0 h S.:1 l
0 u o o u u o A 1 0 0 0 u o 0 0 3N3 0 0 o o 0 0 0 :44 !
0 0 0 U U 0 0 Ais ?4 l l
0 0 0 0 0 0 N j 0
l
'Iv at ti v4 13 v6-bl el-tL 41-n L -t t-b* 14'J 1 J D 7 d I O CHda 'l l ) 0330h ofa l h 0111'# j 1333 954 J. V G3eilSvh d u ti l >>
(13 EE-964 1 VI'13 0 ) 3'idV1SNis Fl.rnAdA L1 -
S S v 'IJ All'Il H V LS Ib6L 63hWJid35 -
A % t t' -
O ed3? u .s U U O ! *14 d NOIAVAS 8.svud av ilJap. S31113-d V eld 1
i
1 S8 0 -
S':i S S v '1) A A I'll e Vis 'Fl v N1 SINA..1dilSVak All 11 rtv1S DN I SS A W 30 SHnOn 0 - SS V'lD All'I t a y19 SlH1 f. I Sit; mdHilSV3a UNIM Dt.15 S i r; 30 SellOn u - SS v '1J AJ 1'llHvlS Slnl N1 n'14 3 30 Sdtion 0 0 0 4 t 0 0 '19 LU1 O O O O o 0 0 3'IPV I NV A 0 0 0 0 V O O tW h U O O O O O O V f.
O U O U 0 0 0 IA !W 0 0 0 0 0 0 0 e 0 0 0 0 0 0 0 M S P.
O O O U U 0 0 wS 1 0 0 0 1 o O MSS E O O E & O O b
% 0 0 V L 0 0 3SS 0 0 0 o O O O '45 U O U U U O u 393 0 o O O o o u 3 0 0 0 O V O U d h.s 0 0 0 0 0 0 u 3 t.
0 0 0 0 0 0 0 3 fJ ie 0 0 0 0 v 0 v f.
'1 Villa v /, l') # 7. - o l HI-El 4L-r L - t' t-e* . 011.id n t u (Ho/ rw l ) 039d9 Owle u t. l d T.3713 9 6 4 A V JaHitSV in S d!.1 P-
~
(13 EE-9t,4 .1. V1'140 ) 3 'l n V A9 N ii U131'!ad 10., - sSV IJ A I l 'l A 4 t, J b ie6L d3u".3Ld3S - A I n t' - UnUJ3s .1tl 'Juld9a NUI1V1S dovud c V 913s t'. S.:i l 11 J - U '.' n D
cf!AO-FITIFS *? tir i.F A l- PotFk STATinN D E D [ 01; 0F PEroPD - .itl[.y - SEPTFypMP 1991 S T 4!* T i.T TY Pl. ASS - SLIGhTin ilNST A ALE ( O F.h t' A T 796-33 FT)
W I 'OS NE ASitPED A T 7 4 f, FEET 4 T NI' Wi*!D SPFED (in PDH)
OI9EPTT0" 0-1 4- 7 8-12 13-1R 19-74 GT 24 TOTAL
'J 0 0 0 0 1 0 1 NNF n 0 0 0 0 0 0
- 19 0 0 0 0 0 0 0 D4r 0 0 0 0 0 0 0 E o 0 0 0 0 0 0 FSF 0 0 0 0 0 0 0 ME O O O O O O O SSF 0 0 7 % 0 0 12 S 0 1 5 1 0 0 9 s S'd 0 0 4 1 0 0 5 SW 0 0 6 1 0 0 7 WSW D 0 7 3 0 0 5
'a 0 0 0 1 0 0 t W r. w 0 0 0 1 0 0 1
's , 0 0 0 0 0 0 0
% ssa 0 0 0 0 n 0 0 V AP I ABf,E O O O O O O O TOTAT. 0 1 24 15 1 0 41 nolipS OF cal'A T *3 THIS STaHT!ITY C IJ S S - 0 40flPS OF ?4 f SS i t.G w i ta n uEaStiuruFhTS IN THTS STABILITY CT, ASS - 0 40flPS OF M I S S I 'f G ST3 p II.I TY P1F A S O P Fv EN TS IN A I.I. STAPIblTY CLASSES - 0 86
C'I A n-C IT I FS eHICT.E A R GOWEH S T A T I O'!
DEpinD OF PEFODD - Ji1LY - SF.DTeeREW 1981 ST A t4 T L I T ( Ft. A SS "IEH TpAI. ( O FI.T A T 296-33 FT)
M I O S W3S" PED AT 296 FEET WTMP *IFD SPEED (IH MD4) ningelynn ,g 1 47 p.32 13 18 19-22 GT 24 .TOTAT.
1 1 12 27 37 2 0 74 NNE 1 13 27 19 2 0 of
'J E 2 13 45 24 5 0 80 ENE O 15 42 20 2 0 8R F 3 20 31 13 0 0 67 rSE 2 to 27 15 1 0 64 SK 1 17 15 3 2 0 3R 95E O 23 21 20 1 0 05 S 0 17 21 16 1 0 55 SSN 1 24 19 16 0 0 59 k SW 2 22 24 11 4 0 68
'4SW 4 27 2R 12 0 0 71
'4 1 5 16 17 9 0 48 4N4 0 to 16 21 5 7 59 N id 0 4 24 5 1 4 43 NHd 1 A 2A 25 0 0 62 V A R I A RT.E O O O O O O 0-TOTAI. 10 254 410 2H7 35 11 1011 4 0119 S IIF C A I.* TN THIS STABTLTTY Ct. ASS - 0 HollRS OF MISSING wTiJD uf ASliprvrNTS IN THTS STARII,1TY CT, ASS - 5 90119s nF MTSSING STAPII.ITY *E ASilREMF MTS IN A I.1, ST A R II. I T Y Cf. ASSES - 0 87 Y
[
ull A D-C I i t?S NilC f.F W PnaFP STATIDN PFDInD OF DEC000 - .Jift Y - SED 1FfmED 1981 STAxTLTTY CLASC - SLTCHTbY STA54LE (DELTA T 296-33 FT)
'81 ?'95 UE AsilpFD AT 296 FEET wind 54thD SPEED (TN N Pli )
DIDECTTON 9-3 4- 7 6-17 13-14 19-21 GT 24 TOTAL
- 1 1 0 ?? 1? 1 0 45
?8 h E 1 7 12 4 0 0 29
'1 E 2 12 26 14 2 0 56 FNE O 17 22 16 0 0 50 E 3 11 25 23 1 0 63 FSE 4 14 14 16 5 0 53 SE 7 11 11 10 4 0 40 SSE 2 14 14 23 2 0 55 S 1 11 24 27 2 0 65 ,
59 SSW 3 4 25 to 2 1 Sb 1 6 21 18 1 1 50 WSW 1 4 15 10 2 0 52 N O 4 7 1A 2n 0 49 4
'd N td i 1 7 24 3 1 37
'l a 0 3 10 21 2 0 36 NNW 0 1 17 15 1 0 31 V AR I nsi.E O O o 0 0 0 0 Tf1T AI. ?? 131 267 245 50 1 770 HOIINS OF CAL'4 TN T 53 t S STAhTLTTY CIASS -
0 HOIIRS OF MTSSiffG ,vitJD VFASilNFNFMTS IN THTS STAPIIITY Cf. ASS - 22 540llPS f'F
Gf t An.c l T IF S "flCI F A R Po=F6 ST A T I n ti p r:p i nti pF DEronn - Jtil:Y - S tsp T F'@ E P 1991
< T ?.rt i f, f r Y PfPS9 i
- "D o t p t. T F T.) SrABLF (DF Lra T 796-33 FT)
WiuDS b a bliF rD AT ?46 FFFI etto AIND SPe r0 ( I f' 'd DH)
D19fer10N 9-1 4- 7 H-17 13-1R 19-2% GT 74 Tf1TAL
'A 1 1 1 1 0 0 6
'J N r 0 5 ? O O O 7 NE 4 3 2 0 0 0 9 ENF 1 1 4 2 0 0 10 E O 4 4 4 0 0 11 ESF 9 % Q 1R 1 0 34 SE 1 1 16 15 7 0 39 SSF 2 1 20 21 5 0 53 S 1 0 17 20 3 0 36 SSW 0 2 A 14 0 0 24 SW 0 5 1 0 0 0 8 WSW 1 7 4 0 0 0 7 W 0 ? ? 7 1 0 7 W4 1 7 5 9 2 0 19 N ed 1 0 7 4 0 0 12 al N W 1 1 1 3 0 0 9 VARIAPTE O O O O O O O Tf1T A I, 1A 43 101 114 14 0 790 H0flHS OF CAL 9 IN THIS STARTLTTY CLASS -
0 HullRS OF '4 T S S i ff G
- I N T' UF ASilPEl4FNTS IN ThTS STARllelTY CI, ASS . O ut1 TIPS nF 41SSIMG STAFiflTi "r A S0 Q 5."F H15 T r' A I,f. STARIT.ITY CT, ASSES - 0 89
Gil A D.C I T [ rs *. IICt.E a r, powrF STATION PEpino tir PEFOPD - Jit LY - RFDTFMAE9 1941 STaaT[.ITY CLASS ry1er$ FLY START.E ( ')E L T i T 796-33 FT)
'd!"as " EAST 1PCD AT 796 FFET n f *;0 % I P'O SPEVD ( T t. MDHi 5 1 4- 7 6-12 13-19 19-24 GT 74 TijTAL O I D Fr:I T ON
'J 0 0 0 0 0 0 0 N,iF 1 7 0 0 0 0 3 FI E O O O O O O O CNE 1 0 0 0 0 0 1 7 0 0 0 0 0 0 0 FSC 0 7 1 0 0 0 3 ,
S r. 0 7 0 0 0 0 2 SSE o S 7 7 3 0 17 S 1 1 3 4 0 0 9 SSW 0 0 1 2 0 0 3 SA 0 ? ? 3 0 0 7 WSW 7 1 7 0 0 0 5
'd 1 7 1 0 0 0 4 4Nu 1 1 0 0 0 0 2 Nw 0 0 1 0 0 0 1 MNW D A 0 1 0 0 1 V A P I 5 8 0 *' O O O O O O O TO T Al- 7 1Q 11 17 1 0 SR HOllPS OF CAI.M I 'l 1915 STA6TI, TTY CI, A SS - 0 HullPS OF A T S S I'lG WTND Uk' ASilR F urNTS I f1 TN TS ST ABILITY CT, ASS - 0 40tlRS OF ' ifs 91PH; ST AP T I.I TY "F A Silu EMEP'TS TN ALL ST ARii,T TY CT, A SSFS _ O 90
f Ol' A D-C I T i rS S'f CT,e, A g pnkFR STATInt, P e:0TOD Or pEcopo . ocTngpr .
D rC F . H D 14A1 RTAwil, TTY Cf*SS -
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92
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'l E 1 2 4 7 0 0 9 rra E O 1 0 0 0 0 1 E O 3 0 0 2 0 5 ESF 0 0 0 1 1 0 4 SE 1 2 7 0 1 0 6 SSE O 1 4 7 1 1 11 S 0 4 4 4 4 0 16 SSW 0 3 7 1 2 0 13 Sa n 1 2 4 1 0 8 4SW 1 2 0 1 0 0 4 4 0 0 2 1 1 0 4 WNN 1 0 0 6 0 4 11 Na 1 1 2 4 1 4 21
- ! h d 1 3 5 1 1 1 17 VAp1A41.F 0 0 0 0 0 0 0 TOT A T, 6 11 30 34 20 to 140 HO'tRS OF CALM T 'l THIS S T A I+ 1 t,11 v C l, a S S - o 54ntlas nF u T S S I 'lG wihD VF4511HrMENTS IN TFTS STAATI,ITY CLA95 - O l'0HWS OF M T S51'lG ST Anll. T TY PF ASUDEME'l TS IN A LL. ST A RII,ITY Cl. A SSrS - 10 93
QU AD-F [T I F S r,l'Ci# A i- Prer- e STATInN PFRlOD lir PErn.JD -
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94 l
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HDflR S OF C A L'8 11 T5315 ST A Ril.T TY ctASS - 0 HrlfJks GF M ISS I'!G w i r1D "V t Sit P F"* E N TS ! *l ThTS STA84ILITY CL A9S - 0 H0 lips OF "i f SS I 'J G ST A R I f [ T) e rASUD M F t. T S f t4 AI,L ST A RI t.i T Y Cf.t SSFS -
10 95
OllAO-rITIFS 'll'CI F A P P o h F.e ST Finh P E D i nt, O F upcop0 . ricinkFF -
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- ! O 4 7 1 0 0 7
'm r 0 1 4 0 0 0 5 NF 0 0 1 1 0 0 4 FNE O 1 6 0 0 0 7 E O 1 5 7 0 0 8 ESE O 1 1 9 0 0 13 SE O 9 3 7 7 0 22 95E O 1 2 2R 11 0 42 S 0 1 3 5 1 0 10 SSW 0 0 5 4 0 0 9 SW D 4 0 0 0 0 4 4 S '.4 0 0 0 0 0 0 0 4 0 0 0 0 0 0 0 w% n 1 2 1 0 0 4
N O 1 6 6 1 0 14
%W 0 3 5 0 0 0 A VAPIAHIE O O O O O O , O TO T At. n 26 47 A4 20 0 157 HOf1HS nF C A L,9 TN 1541S S1APil.TrY P!JSS - 0
'intfPS OF MISSirlG %TND ME A Stf R FuF?lTS IN TFTS STARII,ITY Ct. ASS - 0 540t t p S nF U ISS I Nr. ST Ap [i,ITY *W A S U D E P F T S TN AT,1, STARif,lTY CLASSES -
10 96
R uPAD-riiIr5 NHFIESP pn.:FR ST ATin's PEpino W P Ect.pn - oc1nFFP - DrCEMAER 1981 iTf bTi.t TV Ft. ASS - FXTprpcIY STaHl.E ( DE.T,T a T 796-13 FT)
'!i NOS etAsituMD AT ? (, n rEE7 wi4D 4 I f4 D SPtCD (T\ '1 D 'i l O T H EC1 T ola .Q-3 4- 7 6-17 13-la 10-21 GT 24 TOTAL N 1 0 0 0 0 0 1 th4 E O 1 0 0 0 0 1 NF 0 1 0 0 0 0 1 eNE o ? O O O O 2 E O o 0 0 0 0 0 ESE O O 7 0 0 0 2 SF 0 1 1 0 1 0 12 SSE O a 3 R 1 0 17 S 0 1 6 4 0 0 11 SSW 0 0 0 0 0 0 0 SW 0 3 7 0 0 0 5 4S'd 0 5 2 1 0 0 R 4 n n 0 0 0 0 0 44W 0 0 1 n 0 0 1 Plh 1 0 1 0 0 0 2 NNW 0 0 0 0 0 0 0 VADIABI,E o O n o o 0 0 TOTAL 7 14 1R 72 2 0 59 liOf f RS OF C A Lu T ri THIS Sl a P T [, T TY class - 0 40tlRS OF 'ilSSING wind MEAStiRFurNTS IN THTS STAkit,JTY CI, ASS - 0 HOttRS DV MT8SIMG STAR [i1TY "rASilDF"ENTS TN AI.L STARIT.ITY CI, ASSES - 10 97
APPENDIX III ANALYTICAL PROCEDURES 98
SAMPLE PREPARATION Different classes of samples require different preparations. In general, food products are prepared as for home use, while others are dried and ashed as received.
I t
l 99
f, 1.1 Fish
- 1. Wash the fish.
- 2. Fillet and place the flesh immediately (to prevent moisture loss) in a 450 cc plastic container. Add a few cc of formaldehyde. Seal and record wet weight.
NOTE: If bones are to be analyzed, boil remaining fish in water for about I hour. Clean the bones. Air dry, weigh and record as wet weight. Dry at 125* C. Record dry weight. Ash at 800* C, cook, weigh, and record the ash weight. Grind to a homogeneous sample. The sample is ready for analysis.
- 3. Gamma scan fillet without delay or store in a freezer.
- 4. After gamma spectroscopic analysis 'is completed transfer the sample -
to a drying pan and dry at 125* C.
- 5. Cook, weigh, and record dry weight.
- 6. Ash by gradually increasing the temperature to 450* C. If consider-able amounts of carbon remain after overnight ashing, the sample should be brushed and placed back in the muffle furnace until ashing is completed. Record ash weight. Grind to pass 30 mesh. The sample is now ready for analysis.
NOTE: If in sufficient quantity, use surplus flesh for drying and ashing, instead of waiting for gamma scanning to be completed.
i 100
1.2 Bottom Sediments and Soil
- 1. Air dry the entire sample. Grind or pulverize the sample and sieve through a #20 mesh screen.
- 2. For gamma-spectroscopic analysis seal 450 cc of the ground sample in a Marinnelli beaker. Record dry weight.
- 3. Seal the remaining sample (up to I kg0 in a plastic container and save for other analyses or for possible future rechecking.
i 4
101
1.3 Drinking (clear) water (EPA Method 900.0)
A representative sample must be collected from a free-flowing source of drinking water, and should be large enough so that adequate aliquots can be taken to obtain the required sensitivity.
It is recommended that samples be preserved at the time of collection by adding enough IN HNO3 to the sample to bring it to pH 2 (15 ml IN HNO3 per liter of sample is usually sufficient) If samples are to lie collected without preservation, they should be brought to the labora-tory within 5 days, then preserved and held in the original container for a minimum of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> before analysis or transfer of the sample.
The container choice should be plastic over glass to prevent loss due to breakage during transportation and handling.
If the sample was not acidified at the time of collection, use the following procedure:
Procedure
- 1. Remove 100 ml of sample for tritium analysis, if required.
NOTE: Water should not be acidified for tritium analysis. If samples are acidified in the field, an additional aliquot should be collected.
' 2. Add 15 ml of IN HNO3 per liter of sample in the original con-tainer.
l 3. Hold the sample in the original container for a minimum of 16 l
hours before analysis or transfer of the sample.
- 4. When taking an aliquot for analysis, take acid addition into account. For example:
Sample volume Volume of aliquot to be analyzed required 200 ml 203 ml 400 ml 406 ml 600 ml 609 ml 800 ml 812 ml 1000 ml 1015 ml 2000 ml 2030 ml 3000 ml 3045 ml 3500 ml 3552 ml l For other volumes, adjust adliquots correspondingly, at the rate i of 1.5 m1 per 100 ml of sample.
i 102
1 l
PROCEDURES 103 1
l I
2.1 Airborne Particulates 2.1.1. Gross Alpha and/or Gross Beta Activity Procedure
- 1. Store the sample for 5 days from the day of collection to allow for decay of short-lived radon and thoron daughters.
- 2. Place a 47 mm filter on a stainless steel planchet and count the samples on a proportiona'. counter.
- 3. Calculate the activity in pCi/m3 using computer program RADIO.
Calculations Gross alpha (beta) activity:
(pci/m3 ) . A g 2kEfb i b ,
B x C x 2.22 B x C x 2.22 Where:
A B
= net alpha for
= efficiency (beta) countalpha counting rate (cp(m) beta) activity (cpm /dpm) 3 C = volume of sample (m )
Esb = counting error of sample plus background Eb = counting error of background 1
I t
4 104
2.2 Water 2.2.1 Gross Alpha and/or Gross Beta Activity in Suspended Solids Principle of Method The sample is filtered through a tared membrane filter. The filter contain-ing the solids is transferred to a metal planchet, dried and is fixed 'to the planchet. The gross alpha and/or gross beta activities are measured in low background internal proportional counter.
Reagents Acetone Apparatus ,
Filters; Millipore, membrane Type AA 0.8 u Filtration equipment Planchets (Standard 2" X 1/8" Beckman planchet)
Proportional counter Proccdure
- 1. Filter one liter of sample through a TARED membrane filter. Wash the non-filterable solids'en the filter with distilled water.
- 2. Place the-filter in a planchet and air dry.
- 3. Dry in an oven for 30 minutes. Dessicate to constant weight and weigh.
- 4. Fix the filter to the planchet at four peripheral points using acetone (1 drop). Air dry.
- 5. Count for gross alpha and gross beta activity using a proportional counter.
- 6. Calculate the activity in pCi/l using computer program OWATAB.
i 1
105
- 2.2.1 Calculations Gross alpha (beta) activity
- (pCi/ liter) = A + \sb i b B x C x D x 2.22 B x C x D x 2.22 Where
A = net alpha (beta) count (cpm) i B = efficiency for counting alpha (beta) activity (cpm /dpm)
C = volume of sample (liters)
D = correction factor for self-absorption in the sample Esb = counting error of sample plus background Eb = counting error of background
Reference:
Radioassay Procedures for Environmental Samples, U.S. Department of Health, Education and Welfare. Environmental Health Series, January 1967, i
L 106 f .._. _
l 2.2.2 Gross Alpha and/or Gross Beta Activity in Dissolved Solids (see note)
Principle of Method Water samples containing suspended matter are filtered through a membrane filter and the filtrate is analyzed. The filtered water sample is evapor-ated and the residue is transferred to a tared planchet for counting gross alpha and/or gross beta activity.
Reagents Lucite: 0.5 mg/ml in acetone Nitric acid, HNO3 : 3N Nitric acid, HNO3 : concentrated Apparatus .
Filters; Millipore, membrane Type AA, 0.8 p Filtration equipment Planchets =(Standard 2" x 1/8" Beckman planchet)
Proportional counter Procedure
- 1. Filter a volume of sample containing not more than 100 mg of dissolved solids for alpha assay, or not more than 200 mg of dissolved solids for beta assay.
Note: For gross alpha and gross beta assay in the same sample limit amount of solids to 100 mg.
- 2. Wash the non-filterable solids on the filter. (Save the filters with suspended matter for separate analyses. See Section2.2.1).
- 3. Evaporate the filtrate to NEAR dryness on a hot plate. Add 25 ml concentrated HNO3 and evaporate to NEAR dryness.
Note: For analysis of total residue (for clear water) proceed as described above but do not fiter the water. Measure out the appropriate amount and proceed with step 3.
107 L
Section 2.2.2.(continued)
- 4. With distilled water and a few drops of 3N HNO 3 , transfer the residue to a 50 m1 beaker. Evaporate to NEAR dryne:;s.
- 5. Transfer quantitatively the residue to a TARED PLANCHET, using an eye dropper.
- 6. Wash the beaker with distilled water and combine the washing and the residue in the planchet. Evaporate to dryness.
- 7. Bake in muffle furnace at 600* C for 45 min., cool and weigh.
- 8. Add a few drops (6-7 drops) of lucite solution and dry under the infrared lamp for 10-20 minutes.
Store the sample in a desiccator until it is to be counted.
9.
- 10. Count the gross alpha and/or the gross beta activity in a low background proportional counter.
- 11. Calculate the activity in pC1/1 using computer program OWATAB.
Calculations:
Gross alpha (beta) activity:
2 A Efb +
(pCi/ liter) = B x C x D x 2.22 1 B x C x D x 2.22 Where:
A = net alpha (beta) count (cpm)
B = efficiency for counting alpha (beta) activity (cpm /dpm)
C = volume of sample (liters)
D = correction factor for self-absorption in the sample Esb = counting error of sample plus background Eb = counting error of background
Reference:
Radioassay Procedures for Environmental Samples, ll.S. Department of Health, Education and Welfare. Environmental Health Series, January 1967.
108
-. - _ ---J
3.1 Airborne Particulates - Gamma Spectroscopic analyses by Ge(Li) Detector
- 1. Put the air filter in a filter cup container.
- 2. Place the filter cup on a Ge(Li) detector.
- 3. Determine the gamma spectrum using 4096 or 8192 channel of gamma spectrometer with a setting of 0.5 kev or 0.25 kev per channel.
- 4. Identify gamma emitters (if present) by their respective energy peaks.
Calculations
- 1. Calculate the gamma activities using the computer program GAMMA 1 or GAMMA 2.
109
3.2 Airborne Iodine 3.2 Spectroscopic Analyses by Automatic Gamma Counter Transfer charcoal to a plastic scintillation vial. Place the vial in the Automatic Gamma Counter (Packard Instrument Co. Model 5975) and count.
Record the time.
Calculations 1-131 activity (pCi/m3 ) = A B x C x 2.22 Where:
A = net count rate of I-131 in the 0.36 MeV peak B = efficiency for counting I-131 activity in 0.36 MeV peak (cpm /dpm) '
C = volume of sample (mJ )
Correction for decay
~
At2 Ao = Ale
- A l eO when t1 <<1 F (1 - e-At) i F x t1 ,
Where:
A = activity of I-131 at the time of collection (pCi/m3)
A0 = activity of I-131 at the time of counting e = 2.71828
= 0.693/ half life (days) = 0.693/8.08 = 0.09576/ day t = duration of collection (in days)
= elapsed time between collection and counting in days)
F=M{/ day 3.2 Spectroscopic Analysis by Ge(Li) Detector
- 1. Transfer charcoal to a small plastic bag.
- 2. Label the plastic bag with the corresponding project, location and date of collection and seal it.
- 3. Place packed charcoal in a 450 ml. NC (black) container (all locations) and seal with a tape.
- 4. Place it on the Ge(L1) Detector and count. Record time.
Calculations Calculation is done by the computer by running the Program GAMMA 2.
110
3.3 Water - Gamma Spectroscopic Analyses by Ge (Li) Detector Procedure
- 1. Measure 3.5 liters of water into a Marinelli beaker.
- 2. Place the beaker inside the shield on a Ge(L1) detector.
- 3. Count long enough to meet LLD requirements.
- 4. Af ter counting, identify gamma emitters (if present) by their respective energy peaks.
- 5. Store the spectrum on a disc using computer by executing "RUN STORE."
- 6. After storing, calculate gamma activities, using computer program GAMMA 1 or GAMMA 2.
- 7. Transfer the sample back to the original container for further analyses.
J P
O 111
l 1
l 3.4 Soils and Bottom Sediments - Gamma Spectroscopic Analyses by Ge(Li) Detector Procedure
- 1. Transfer the portion of the ground sample set aside for gamma scanning into a 450 ml Marinelli container.
- 2. Record the dry weight.
- 3. Place the container inside the shield on a Ge(L1) detector.
- 4. Count the gamma activity long enough to meet the minimum sensitivity requirements.
- 5. Af ter counting, identify gamma emitters (if present) by their respec-tive energy peaks.
- 6. Store the spectrum on a disc using the computer by executing "RUN STORE."
- 7. Af ter storing, calculate gamma activities using computer Program GAMMA 1 or GAMMA 2.
- 8. Transfer the sample back to the original container for further analyses.
+
112
3.5 Fish and Wildlife - Gamma Spectroscopic Analyses by Ge(Li) Detector Procedure
- 1. Transfer a portion of the clean wet flesh of fish or animal into 450 ml Marinelli container.
- 2. Record wet weight.
- 3. Add a few cc of formaldehyde and seal the container.
- 4. Place the container inside the shield on a Ge(L1) detector.
- 5. Count long enough to meet the minimum sensitivity requirements.
- 6. After counting, identify gamma emitters (if present) by their respec-tive energy peaks. .
- 7. Store the spectrum on a disc using computer by executing "RUN STORE."
- 8. After storing, calculate gamma activities using computer program GAMMA 1 or GAMMA 2.
- 9. Transfer the sample back to the original container for further analyses.
113
3.6 Ambient Gamma Radiation A. Thermoluminescent Dosimeters (TLD) - Light Response (Efficiency)
Harshaw Lithium Fluoride TLD-100 chips,1/8" x 1/8" x 0.035".
Procedure
- 1. Rinse the chips with warm trichloroethylene followed by the methanol rinse. Dry.
- 2. Place the chips in a platinum crucible.
- 3. Anneal for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 400*C.
- 4. Cool quickly by placing the crucible on a metal plate.
- 5. Anneal for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 100'C.
Note: Avoid exposing the chips to the fluorescent light.
- 6. Seal 5 chips each in black plastic.
- 7. Mount the packs on the turntable.
- 8. Position the Ra-226 needle in the middle of the turntable and start rotation (appr. 60 revolutions per minute). Record the time.
- 9. Irradiate the chips for 2-6 hrs.
- 10. Remove the packages from the turntable. Return the Ra-226 needle to the lead container. Record the time.
- 11. Take the chips out of the plastic bag and place them in the vial.
- 12. Postanneal the chips for 10 minutes at 100*C.
- 13. Read each chip twice in the TLD Reader (For test procedure see
" Performance Test Procedure for TLD Reader").
- 14. Subtract second reading from the first to obtain net reading in nanocculombs.
- 15. Calculate mean + one sigma deviation of five chips.
- 16. Calculate light response of TLD's (correction factor) by the following equation:
114
Section 3.6 (continued)
Calculations A
C.F. (nanocoulombs/ mrem) =
B Where:
C.F = correction factor to be applied in calculating exposure of field TLD's A = Net reading in nanocoulombs B = known exposure to TLD's The exposure to the TLD's (B) is calculated as follows:
mrem /hr = 8400 x mg Ra-226 r2 .
For our setup use the following parameters:
Ra-226 = 0.0922 + 1.5%
r = 19.6 cm Thus:
mrem /hr = 8400 x 0.0933 = 2.040 384.16 The total exposure (B) is equal to:
B (mrem) = 2.040 x hours 115
3.7 Procedure for Preparation and Readout of TLD Chips Materials Harshaw Lithium Fluoride TLD-100 chips, 1/8" x 1/8" x 0.035".
Black plastic bags or boxes Plastic sealer Vacuum needle (for handling the chips)
TLD reader Note: Never handle the chips with bare hands. Use plastic-covered forceps or vacuum needle. Handle them gently, e.g. do not drop them into the vial or on the table. They chip off easily, resulting in efficiency change.
Procedure Rinse the chips with warm trichloroethylene followed by the methanol 1.
rinse. Dry.
- 2. Place the chips in a platinum crucible.
- 3. Anneal for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 400*C.
- 4. Cool quickly by placing the crucible on a metal plate.
- 5. Anneal for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 100*C.
- 6. Seal 3 to 5 chips (depending-on the specifications) in black plastic or plastic boxes.
- 7. Label and send out by U.S. Mail.
- 8. Upon arrival at the lab, store TLDs in the big shield until readout day. Do not store longer than a few days.
- 9. Connect chips reader one day prior to readout.
- 10. Turn on gas for a few minutes before readout. Adjust to the mark.
- 11. Set parameter on the 2000P as follows:
HV - 470 V (It is 970 V, internal volts = 5000).
Readout time: 20" T1 - 140' C (Preset)
T2 - 250" C (Preset)
Rise time: -12*/sec (Present)
Preheat - 100* C (Present)
Start reading - 90* C 116
Section 3.7 (continued)
- 12. Prepare the chips as follows (do this before proceding to the next step).
12.1 Turn on small muffler furnace or drying oven and adjust to 80*C. Use glass thermometer. Muffler's indicator is not accurate. Let furnace stabilize.
12.2 Unpack the chips (under reduced incandescent light) and gently place them in the glass vials marked with appropriate location numbers.
12.3 Place the vials in the furnace. Preanneal for 10 min. at 80*C.
- 13. Open the drawer and read the standard. It should read 8.34+0.04.
Adjust HV, if needed. Take 3 readings after final adjustment.
Record.
- 14. Close the drawer.
- 15. Check bkg. It should read about 0.7-0.8 in 20". If it is higher, adjust the knob in the back of 2000 P (on left side when facing the instrument).
Note: Adjust bkg as low as possible but do not let the needle hit zero. The instrument will not record below zero.
- 16. Make 10 bkg readings (no chip in). Record. Read (do not record) at least 2 dummies to stabilize the temperature.
- 17. Place the chip in, wait until temperature goes down to 90* C and press " read" button. Make sure the chip is in the cavity of the heating plate.
- 18. After readout is completed, record the reading, open the drawer, and l place next chip.
l
! 19. Repeat Steps 16 and 17 until all chips are read out.
Note: If reading will last longer than 1.5-2.0 hrs., check the standard and bkg about every 2.0 hrs.
- 20. After t'adout is completed, turn off the gas.
- 21. For calculations, use computer program 0GTLD. PUB.
117 L. . _ _
3.8 Tritium in Water (Direct Method)
Principle of Method The water sample is purified by distillation, and portion of the distil-late is transferred to a counting vial containing a scintillation fluid.
The contents of the vial are then mixed and counted in a liquid scintilla-tion counter.
Reagents Scintillation medium, insta-gel scintillator Tritium standard solution Apparatus Condenser Distillation flask, 250-ml capacity Liquid scintillation counter Liquid scintillation counting vials Procedure
- 1. Distill a 30 ml aliquot of the sample in a 250-m1 distillation flask. Add a boiling chip to the flask. Connect a side arm adapter and a condenser to the outlet of the flask. Place a glass vial at the outlet of the condenser. Heat the sample to 100 - 150* C to distill, just to dryness. Collect the distillate for tritium analysis.
- 2. Dispense 13 ml of the distillate to a low potassium glass vial.
- 3. Prepare background and standard tritium-water solutions for
- counting, using the same amount as the sample. Use low tritium i
background distilled water for these preparations (distillate of most deep well water sources is acceptable, but each source should be checked for tritium activity before using).
i Dark-adapt all samples, backgrounds, and standards. Add 10 ml 4.
( of insta-gel scintillator. Count the samples, backgrounds and standards. Count samples containing less than 200 pCi/ml for
[ 300 minutes and samples containing more than 200 pCf /ml for 200 minutes.
. 118 l
Section 3.8 (continued)
- 5. Counting efficiency:
Eff = cpm of Standard-cpm of background dpm Standard pCi/mi = A 2.22 x E x V Where:
A = net count rate (cpm)
E = efficiency (cpm /dpm)
V = volume
, 6. Calculate tritium activity using computer program OH3.
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3.9 Iodine-131 Milk by Ion Exchange on Anion Exchange Column After samples have been treated to convert all iodine in the sample to a common oxidation state, the iodine is isolated by solvent extraction or a combination of ion exchange and solvent extraction steps.
Iodine, as the iodine, is concentrated by adsorption on an anion exchanged column. Following a Nacl wash, the iodine is eluted with sodium hypochlorite.
Iodine in the todate form is reduced to 12 and the elemental iodine extracted into CCl4, back-extracted into water the finnally precipated as palladium iodide.
Chemical recovery of thgdded carrier is detennined gravimetrically from the PdI2 precipitate. I is determined by beta counting the PdI2 Reagents Anion exchange resin, Dowex 1 x 8 (50-100 mesh) chloride form.
Carbon tetrachloride, CCl4 - reagent grade.
Hydrochloric acid, hcl, IN.
Hydrochloric acid, hcl, 3N_..
H2 O - HNO 3 - HN20H HCL wash solution (50 ml H2 0); 10 ml 1M -
NH2 0H-hcl; (10 ml conc. HNO3 )-
Hydroxylamine hydrochloride, NH2 0H hcl - 1 M_.
Nitric acid, HNO3 - concentrated.
Palladium chloride, PdI2, 20 mg Pd"/ml . 1.2 g Pd C1 2/100 ml j 6N hcl).
l Sodium bisulfite, NaHS03-1M l
l Sodium chloride, Nacl - 2M l
Sodium hypochlorite, Na0Cl - 5% (clorox).
l 120 E-
__________J
l Section 3.9 (continued) ;
I Special Apparatus Chromatographic column, 20 m x 150 m (Fisher & Porter Cat. #274-457).
Vacuum filter holder, 2.5 cm2 filter area Filter paper, Whatman #42, 24 m l
! Mylar i Polyester gumed tape,1 1/2", Scotch #853 Drying oven A. Ion Exchange Procedure
- 1. Set up an ion exchange column of 20 m diameter and 150 m length.
- 2. Pour 20 ml of a slurry of Dowex 1 x 8, Cl fonn (50-100 mesh) l into the column and wash down sides with water. Add 2 ml of I-carrier to 2 liters milk, stir for 20 minutes.
- 3. Pass the sample through the ion exchange column at a flow rate of 20 ml/ min. Save the effluent for other analyses and label it
" iodine effluent".
- 4. Wash column with 500 ml of hot distilled water for milk samples or 200 ml of distilled water for water samples. Discard wash.
- 5. Wash column with 100 ml of 2 M Nacl at a flow rate of 4 ml/ min.
Discard wash.
- 6. Drain the solution from the column.
- 7. Measure 50 ml 5% sodium hypochlorite in a graduated cylinder.
Add sodium hypochlorite to column in 10-20 m1 increments, stirring resin as needed to eliminate gas bubbles and maintain l flow rate of 2 ml/ min. Collect eluate in 250-m1 beaker and discard the resin.
B. Iodine Extraction Procedure
- 1. Acidify the eluate from step ' ssing concentrated HNO3 to make
! the sample 2-3 N in HNO 3 , and transfer to 250 m1 separatory funnel. (Add tTie acid slowly with stirring until the vigorous reaction subsides.) Volume of concttrated HNO3 required will depend on eluate volume as follows):
121 e .
I Section 3.9 (continued)
B. Iodine Extraction Procedure (continued) eluate volume concentrated HNO3
! (ml) (ml) 50-60 10 l 60-70 12 70-80 14 80-90 16 .
- 2. Add 50 ml of CC14 and 10 ml of 1 M hydroxylamine hydrochloride (freshly prepared). Extract iodiiie into organic phase (about 2 minutes equilibration). Draw off the organic phase (lower phase) into another separatory funnel
- 3. Add 25 ml of CC14 and 5 ml of 1 M hydroxylamine hydrochloride to the first separatory funnel and again equilibrate for 2 minutes.
Combine the organic phases. Discard the aqueous phase (Upper phase) if not other analyses are required. If Pu, U or Sr is required on the same sample aliquot, submit the aqueous phase and data sheet to the approprate laboratory section.
- 4. Add 20 ml H2 0-HNO 3 -NH2 0H hcl wash solution to the separatory funnel containing the CC1. 4 Equilibrate 2 minutes. Allow phases to separate and transfer CC14 (lower phase) to a clean separatory funnel. Discard the wash solution.
- 5. Add 25 ml H 2 O and 10 drops of 1 M sodium bisulfite (freshley prepared) to the separatory fLnnel containing the CC1. 4 Equi-librate for 2 minutes. Discard the organic phase (lower phase).
Drain aqueous phase (upper phase) into a 100-m1 beaker. Proceed to the Precipitation of PdI -2 l
C. Precipitation of Palladium Iodide CAUTION: AMMONIUM HYDR 0XIDE INTERFERES WITH THIS PROCEDURE
- 1. Add 10 ml of 3 N hcl to the aqueous phase from the iodine extrac-tion procedure Tn step 5.
t 2. Place the beaker on a stirrer-hot plate. Using the magnetic stirrer, boil and stir the sample until it evaporates to 30 ml or begins to turn yellow.
- 3. Add 1.0 ml of 20 mg Pd++/ml palladium chloride per liter of milk, used dropwise, to the solution.
y 122 1
i
{
Section 3.9 (continued) i C. Precipitation of Palladium Iodide (continued)
- 4. Turn the heat off, but continue to stir the sample until it cools to room temperature. Place the beaker in a stainless steel .
tray and put in the refrigerator overnight.
l S. Weigh a clean 24 nun Whatman #42 filter which has been stored over silica gel in a desiccator.
- 6. Place the weighed filter in the filter holder. Filter the sample and wash the residue with 1 N HIl and then with absolute alcohol.
4 1 7. Remove filter from filter holder and place it on a watch glass.
, 8. Dry under the lamp for 20 minutes.
- 9. Cut a 1 1/2" strip of polyester tape and lay it on a clean surface, gummed side up. Place the filter, precipitate side up, in the center of the tape.
- 10. Cut a 1 1/2" wide piece of mylar. Using a spatula to press it 1 in place, put it directly over the precipitate and seal the edges l to the polyester tape. Trim to about 5 mm from the edge of the filter with scissors.
- 11. Mount the sample on the plastic disc and write the sample number l on the back side of the-disc.
- 12. Count the sample on a proportional beta counter.
I Calculations Calculate the sample activity using computer program 010D131. k
Reference:
" Determination of 1-131 by Beta-Gamma coincidence Counting of PdI2 ". Radiological Science Laboratory. Division of Labor-atories and Research, New York State Department of Health, l
March 1975, Revised February 1977.
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