ML20203P889
| ML20203P889 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/31/1985 |
| From: | TELEDYNE ISOTOPES MIDWEST LABORATORY |
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| NUDOCS 8605080303 | |
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Text
LA SALLE COUNTY STATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING ANNUAL REPORT 1985 TELEDYNE ISOTOPES MIDWEST LABORATORY NORTHBROOK, ILLIr4OIS MARCH 1986 P' ' & c 88888s7a J
R PDR
LA SALLE COUNTY NUCLEAR POWER STATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING ANNUAL REPORT 1985 TELEDYNE ISOTOPES MIDWEST LABORATORY NORTHBROOK, ILLINOIS MARCH 1986
TABLE OF CONTENTS Page 1
6 INTRODUCTION 1
S UMMAR Y..............................
2
- 1. 0 EFFLUENTS 1.1 Gaseous 3
- 1. 2 Liquid..............
3
3
- 3. 0 DOSE TO MAN 3.1 Gaseous Effluent Pathways 3
- 3. 2 Liquid Effluent Pathways...................
5
- 4. 0 SITE METEOROLOGY 5
- 5. 0 ENVIRONMENTAL MONITORING 5
5.1 Gamma Radiation 6
- 5. 2 Airborne I-131 and Particulate Radioactivity.
6
- 5. 3 Terrestrial Radioactivity 6
- 5. 4 Aquatic Radioactivity 7
- 5. 5 Milk.............................
8 8
- 5. 6 Special Collections
- 6. 0 ANALYTICAL PROCEDURES.......................
8
8
- 8. 0 NEAREST RESIDENT CENSUS......................
10
- 9. 0 INTERLABORATORY COMPARISON PROGR AM RESULTS 10 APPENDI X 1 - DATA TABLES AND F IGURES..................
23 Station Releases Table 1.1-1 Gaseous Ef fluents 24 Table 1.2-1 Li qui d Ef f l uen ts...................
30 ili
)
TABLE OF CONTENTS (continued)
W APPENDIX I - DATA TABLES AND FIGtRES StationReleases-(continued)
Table 2.0-1 Solid Waste Shipments 34 Figure 3.1 Figure 3.1-4 Isodose and Concentration Contours..........
50 Table 3.1-1 Maximum Doses Resulting from Airborne Releases....
54 Table 3.2-1 Maximum Doses Resulting from Liquid Discharges....
55 E.,vironmental Monitoring Figure 5.0 Figure 5.0-3 Locations of Environmental Radiological Stations...
56 Table 5.0-1 Environmental Radiological Monitoring Sampling Sites 59 Table 5.0-2 Environmental Radiological Monitoring Program 60 Table 5.0 Table 5.0-6 Environmental Summary Tables.............
68 Table 5.1-1 Gamma Radiation Measurements (TLD)..........
83 APPENDIX II - METEOROLOGICAL DATA 86 APPENDIX III - ANALYTICAL PROCEDURES..................
115 i
iv
INTRODUCTION LaSalle Station, a two-unit BWR plant is located near Marseilles, Illinois, in Lasalle County, next to the Illinois River.
Each reactor is designed to have a capacity of 1078 MW net.
Unit No. I loaded fuel in March 1982.
Unit No. 2 loaded fuel in late December 1983.
The plant has been designed to keep releases to the environment at levels below those specified in the regulations.
Liquid effluents from LaSalle County Station are released to the Illinois River in controlled batches after radioassay of each batch. Gaseous effluents are released to the atmosphere af ter delay to permit 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 perticulate matter.
The results of effluent analyses are summarized on a monthly 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 LaSalle County Station to measure changes in radiation or radioactivity levels that may be attributable to plant operations. If significant changes attributable to LaSalle County Station are measured, these changes are correlated with ef fluent releases.
Externa' gamma radiation exposure from opble gases and I-131 in milk are the most critical pathways at this site;.awever, an environment al monitoring program is conducted which includes otherj pathways of less importance.
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1
SUMMARY
Gaseous and liquid effluents for the period remained at a fraction of the Technical Specification limits.
Calculations of environmental concentrations based on effluent, Illinois River flow, and meteorological data f or the period indicate that consunption 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 2.89E-03 mrem for the year, when a shielding and occupancy f actor of 0.7 is assumed.
The assessment of radiation doses are performed in accordance with the Off site Dose Calculation Manual (0001).
The results of analysis confirm that the station is operating in compliance with 10CFR50 and 40CFR190.
2
- 1. 0 EFFLUENTS 1.1 Gaseous Effluents to the Atmosphere Measured concentrations and isotopic composition of noble gases, radiciodine, and particulate radioactivity released to the atmos-phere during the year, are listed in Table 1.1-1.
A total of 1.81E+02 curies of fission and activation gases was released with a maximum release rate of 1.4E+02 pCi/sec.
A total of 8.4E-03 curies of I-131 was released during the year.
-with an average release rate of 8.25E-03 pCi/sec for all iodines.
A total of 2.19 curies of beta-gamma emitters and less than 5.0E-09 curies of alpha emitters was released as airborne particulate matter, with an average release rate of 7.05E-02 pCi/sec.
A total of 2.30 curies of tritium was released, with an average release rate of 7.35E-02 pCi/sec.
- 1. 2 Liquids Released to the Illinois Ri w r A total of 8.40E+0S liters of radioactive liquid waste (prior to dilution) containing 3.81 curies (excluding tritium, gases, and alpha) were discharged af ter dilution with a total of 7.70E+09 liters of water.
These wastes were released at a monthly average concentration of 2.95E-07 pCi/ml, discharged on an unidentified nuclide basis, which is 4.6E-03% of the Technical Specification release limits for unidentified radioactivity. A total of 8.05E-05 curies of alpha radioactivity and 0.39 curies of tritium were released.
Monthly release estimates and principal radionuclides in liquid effluents are given in Table 1.2-1.
- 2. 0 SOLIO RADI0 ACTIVE WASTE Solid radioactive wastes were shipped to Richland, Washington; Barnwell Nuclear Center, South Carolina; Chemical Nuclear Company; Hiltman Nuclear and Development Company; and Tri-State Motor Transit.
The record of waste shipments is summarized in Table 2.0-1.
- 3. 0 DOSE TO MAN 3.1 Gaseous Effluent Pathways Gamma Dose Rates Gamma air and whole body dose rates of f-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.
3
Based on measured effluents and meteorological data, the maximum dose to an individual would be 2.89E-03 mrem for the year, with an occupancy or shielding f actor of 0.7 included.
The maximum gamma air dose was 5.05E-03 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 clothirg covering sensitive tissues.
For purposes of this report i
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 4.21E-03 mrem.
The air concentrations of radioactive noble gues at the off-site receptor locations are given in Figure 3.1-2.
The maximum off-site i
beta air dose for the year was 4.21E-04 mrad.
Radioactive Iodine The human thyroid exhibits a significant capacity to concentrate 1
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 contributions 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.
The maximum pff-site average concentration is estimated to be 1.52E-03 pCi/mJ for the year.
Dose to Infant's Thyroid The hypothetical thyroid dose to an inf ant 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 f arm with the cows pastured from May to October.
The maximum inf ant's thyroid dose was 1.99E-02 mrem during the year (Table 3.1-1).
4 4
Concentrations of Particulates in Air Concentration contours of radioactive airborne particulates are shown in Figure 3.1-4.
The maximum off-site average level is estimated to be 8.24E-03 pCi/m3, 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 enviranment 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 GI 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 year was 1.37E-05 mrem and no organ dose exceeded 1.78E-04 mrem.
4.0 SITE METEOROLOGY A summary of the site meteorological measurements taken during eaca quarter of the year is given in Appendix II.
The data are presented as cumulative joint frequency distributions of 375' level wind direction and wind speed class by atmospheric stability class determined from the temperature difference between the 375' and 33' levels.
Data recovery for these measurements was about 98.9%.
5.0 ENVIRONMENTAL MONITORING Table 5.0-1 provides an outline of the radiological environmental moni-toring program as required in the Technical Specifications.
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).
5 m
5.1 Gamma Radiation External radiation dose f rom on-site sources and noble gases re-leased to th: atmosphere was measured at ten indicator and four reference (background) locations using solid lithium fluoride 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.
A total of 48 additional TLDs were installed on June 1,1980 such that each sector was covered at both five miles and the site boundary.
Six (6) TLD locations were added to the monitoring program on July 1,1985.
- 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 shown in Figure 5.0-1.
Airborne I-131 remained below the LLD of 0.1 pCi/m3 throughout the year.
to 0.109 pCi/m3 at 0.00gatcontrol Gross beta concentrations ranged from locations indicator locations and 0.012 to 0.085 pCi/m th an average concentration of 0.025 pCi/m3 at indicator locations and 0.026 pCi/m3 at control locations.
No radioactivity attribut-able to station operation was detected in any sample.
- 5. 3 Terrestrial Radioactivity Precipitation samples were collected monthly from f our milk sampling locations and analyzed for gross beta, tritium, strontium-89 and
-90, and gamma-emitting isotopes.
Except for gross beta and a trace amount of tritium in one sample, all other radioactivity was below the limits of detection indicating that there was no measurable amount of radioactivity attributable to the station releases.
Annual mean gross beta concentration measured 28.1 pCi/1, which is the level expected in precipitation samples.
Vegetables were collected in July and September and analyzed for gross beta, strontium-89 and -90, and gamma-emitting isotopes.
In addition, green leafy vegetables were analyzed for iodine-131.
Gross beta concentration ranged f rom 0.9 to 3.4 pCi/g wet weight and averaged 1.9 pCi/g wet weight.
The range and mean values were those expected in the vegetation samples.
All other isotopes were below the limits of detection indicating that there was no measurable amount of radioactivity attributable to the station releases.
Cattlefeed and grass samples were collected quarterly f rom milk sampling locations and analyzed for gross beta, strontium-89 and -90 and gamma-emitting isotopes.
Except for gross beta, the level of radioactivity was below the detection limits.
Gross beta concen-trations were at the level usually encountered in these samples.
6
-.. =.
f Well water from on-site well (L-27) was collected monthly and analyzed for gross beta activity.
The annual mean gross beta concentration was 21.8 pCi/l and was similar to the concentration measured in 1984 (21.4 pCi/1). Monthly samples were also composited quarterly and analyzed for strontium-89 and -90, tritium, and gamma scanned.
All results were below the lower limits of detection.
Well water was also collected quarterly f rom five off-site wells and analyzed for the same parameters as in well water from on-site. The results were similar to those obtained for the on-site well, in-dicating that there was no measurable amount of radioactivity due to the station releases.
- 5. 4 Aquatic Radioactivity Surf ace water samples were collecte.1 weekly from eight locations and analyzed for gross beta content.
Weekly samples f rom the Illinois River near the intake and discharge pipes were composited monthly and analyzed f or gamma emitters, tritium, and strontium-89 and -90.
Samples from other locations were composited monthly for gamma isotopic analysis and quarterly for tritium, Sr-89 and Sr-90.
None of the composite samples indicated the presence of other than naturally occurring gamma emitters at a sensitivity of 10 pCi/1.
None of the samples contained Sr-89 above detection sensitivity of 10 p Ci /1.
Sr-90 was detected in five samples and ranged from 2.1 to
- 3. 5 p Ci /1.
Tritium concentrations were close to (220 pCi/l in one sample) or below the LLD level of 200 pCi/l in all sanples.
Gross beta concentrations were similar to those obtained during the preoperational program indicating that there was no measurable amount of radioactivity due to station operation present.
l Sediment samples were collected f our times, f rom one control and two indicator locations, and analyzed for gross beta and gamma-emitters. Gamma emitters were below the detection limits.
Mean gross beta activity in indicator samples measured 23.6 pCi/g and 27.4 pCi/g at control location indicating the presence of no radioactivity due to station operation.
Levels of gamma radioactivity in fish were measured and found in all samples but one to be below the lower limits of detection for the program.
The detected concentration for Cs-137 was 0.12 pCi/g wet weight, barely above the LLO level of 0.1 pCi/g wet weight.
Gross beta concentration averaged 3.1 pCi/g wet weight and was at the level expected in fish.
7
- 5. 5 Milk Milk samples were collected monthly f rom November through April and weekly from May through October and analyzed f or iodine-131, radiostrontium, and gamma emitters.
Radioiodine was below the limits of detection, 0.5 pCi/l in all samples.
Sr-90 concentrations were variable within the usual range for milk and Sr-89 and gamma emitters were below the limits of detection.
- 5. 6 Special Collection I
An unmonitored liquid release occurred in May, 1985.
The extent of the environmental impact was investigated and all analyses results were negative.
- 6. 0 ANALYTICAL PROCEDURES A description of the procedures used for analyzing radioactivity in environmental sanples is given in Appendix III of this report.
- 7. 0 MILCH ANIMAL CENSUS A census of milch animals was conducted within five miles of the Station.
The survey was conducted by " door-to door" canvas and by information from Illinois Agricultural Agents.
The census was conducted by A.
Lewis on August 2, 1985.
There are no dairy farms within a five mile radius of the LaSalle County Power Station.
Dairies that are sampled are listed below.
L-15 Granby Dairy Farm tomber of cows -- 160 fumber of f resh cows -- 140 Diet consists of the following:
Ground corn mix
- 15 lbs./ cow / day Silage 25 lbs./ cow / day (approx.)
Green chop Free choice
- Mix consists of:
Corn 2,000 lbs.
Soybean meal 250 lbs.
Minerals 50 lbs.
Salt 25 lbs.
8
L-16 Lowrey Dairy Farm Number of cows -- 125 e
Number of f resh cows -- 91 Diet consists of the f ollowing:
[
t Ground Corn Mix
- 20 lbs./ cow / day Haylage 20 los./ cow / day (approx. )
Silage 40 lbs./ cow / day (approx. )
Hay Free choice
- Mix consists of:
Corn 2,500 lbs.
Soybean meal 600 lbs.
Oats 600 lbs.
Minerals 200 lbs.
Salt 50 lbs.
L-17 Norsen Dairy Farm Number of cows -- 35 Number of fresh cows -- 24 Diet consists of the following:
Ground Corn Mix
- 14 lbs./ cow / day Hay 20 lbs./ cow / day
- Mix consists of :
Corn 1,600 lbs.
Oats 400 los.
Protein 100 lbs.
Minerals 50 lbs.
Salt 20 lbs.
L-18 Sunnyisle Dairy Farm Number of cows -- 60 tomber of f resh cows -- 57 Diet consists of the following:
Ground corn mix
- 14 lbs./ cow / day Hay Free choice Green chop Free choice
- Mix consists of:
Corn 2,000 lbs.
Soybean meal 600 lbs.
Oats 300 lbs.
Miner als 50 lbs.
Salt 50 lbs.
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- 8. 0 NEAREST RESIDENT CENSUS The census was conducted by A. Lewis on August 2,1985.
There were no
{
changes f rom the previous census.
NEAREST RESIDENT OF THE LA SALLE COUNTY STATION WITHIN A FIVE (5) MILE RADIUS 7
Direction Distance e'
N 2.2 miles NNE 1.4 miles l
NE 1.6 miles ENE 3.4 miles E
3.1 miles ESE 1.6 miles L
2.2 miles SSW 2.0 miles 1
SW 0.7 miles WSW 1.3 miles W
0.9 miles WNW l.0 miles NW 2.6 miles
- 9. 0 INTERLABORATORY COMPARISON PROGRAM RESULTS Teledyne. Isotopes Midwest Laboratory has participated in Interlaboratory i
Comparison (Crosscheck) Programs since the formulation of its quality control program in December 1971.
These programs are operated by agen-cies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.
The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.
' Participant laboratories measure the concentrations of specified radio-nuclides and report them to the issuing agency.
Several months later, 3.
the agency reports the known values to the participant laboratories and specifies control limits.
Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in' the environmental sample crosscheck program for milk, water, air filters, and food sartples during the period 1982 through 1985.
This program has been conducted by the U.
S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Moni-toring and Support Laboratory, Las Vegas, Nevada.
10
The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) during the period 1916, 1977, 1979, 1980, and 1981 through participation in the Second, Third, Fourth, and Fif th International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2.
J W
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Table A-1.
U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples,1982 through 1985.8 Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12cc 13c, n=1d STW-270 Water Jan. 1982 Sr-89 24.3 2.0 21.015.0 Sr-90 9.4 0.5 12.011.5 STW-273 Water Jan. 1982 I-131 8.610.6 8.411.5 STW-275 Water Feb. 1982 H-3 15801147 18201342 STW-276 Water Feb. 1982 Cr-51
<61 0
Co-60 26.0 3.7 2015 Zn-65
<13 15 5 Ru-106
<46 2015 Cs-134 26.8 0.7 2215 Cs-137 29.711.4 2315 STW-277 Water Mar. 1982 Ra-226 11.9 1.9 11.611.7 STW-278 Water Mar. 1982 Gross alpha 15.6 1.9 1915 Gross beta 19.210.4 1915 STW-280 Water Apr. 1982 H-3 2690!80 28601360 STW-281 Water Apr. 1982 Gross alpha 7517.9 85121 Gross beta 114.1 5.9 106 5.3 Sr-89 17.411.8 2415 Sr-90 10.5 0.6 1211.5 Ra-226 11.4 2.0 10.911.5 Co-60
<4.6 0
STW-284 Water May 1982 Gross alpha 31.516.5 27.517 Gross beta 25.9 3.4 2915 STW-285 Water June 1982 H-3 1970 1408 18301340 STW-286 Water June 1982 Ra-226 12.6tl.5 13.413.5 Ra-228 11.112.5 8.712.3 STW-287 Water June 1982 1-131 6.5 0.3 4.410.7 STW-290 Water Aug. 1982 H-3 32101140 2890 619 12
Table A-1.
(continued)
Concentration in pCi/jb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis f2cc 130, n=1d STW-291 Water Aug. 1982 1-131 94.612.5 87115 STW-292 Water Sept. 1982 Sr-89 22.713.8 24.518.7 Sr-90 10.910.3 14.5t2.6 STW-296 Water Oct. 1982 Co-60 20.0 1.0 2018.7 Zn-65 32.315.1 24 8.7 Cs-134 15.311.5 19.018.7 Cs-137 21.011.7 20.018.7 STW-297 Water Oct. 1982 H-3 2470120 25601612 STW-298 Water Oct. 1982 Gross alpha 32130 55124 Gross beta 81.716.1 8118.7 Sr-89
<2 0
Sr-90 14.110.9 17.212.6 Cs-134
<2 1.8 8.7 i
?
Cs-137 22.710.6 2018.7 Ra-226 13.6 0.3 12.513.2 Ra-228 3.9 1.0 3.610.9 STW-301 Water Nov. 1982 Gross alpha 12.0 1.0 19.018.7 Gross beta 34.012.7 24.0 8.7 STW-302 Water Dec. 1982 1-131 40.010.0 37.0110 STW-303 Water Dec. 1982 H-3 1940120 19901345 STW-304 Water Dec. 1982 Ra-226 11.7 0.6 11.011.7 Ra-228
<3 0
STW-306 Water Jan. 1983 Sr-89 20.018.7 29.215 Sr-90 21.7 8.4 17.2 1.5 STW-307 Water Jan. 1983 Gross alpha 29.0 4.09 29.0 13 Gross beta 29.310.6 31.0 8.7 STM-309 Milk Feb. 1983 Sr-89 35 2.0 3718.7 Sr-90 13.710.6 18 2.6 I-131 55.713.2 55 10.4 Cs-137 29 1.0 26 8.7 Ba-140
<27 0
K-40 163715.8 1512 131 13
.~
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Table A-1.
(continued)
Concentration in pCi/lb Lab Sanple Date TIML Result EPA Result 130, n=1d Code.
Type Collected Analysis 12ac STW-310 Water Feb. 1983 H-3 2470180 25601612 STW-311 Water-March 1983 Ra-226 11.911.3 12.713.3 Ra-228
<2.7 0
4
+
STW-312 Water March 1983 Gross alpha 31.6 4.59 31113.4 Gross beta 27.012.0 2818.7 STW-313 Water April 1983 H-3 3240180 33301627 i
STW-316 Water May 1983 Gross alpha 9417 64119.9 Gross beta 13315 149112.4 Sr-89 1911 2418.7 i
Sr-90 1211 1312.6 Ra-226 7.910.4 8.512.25 i
.Co-60 30 2 3018.7 Cs-134 27 2 3318.7 f
Cs-137 29!1 2718.7 STW-317 Water May 1983 Sr-89 59.712.1 5718.7 Sr-90 33.711.5 3813.3 J
STW-318f Water May 1983-Gross alpha 12.8 1.5 11t8.7 Gross beta 49.4t3.9 5718.7 STM-320 Milk.
June 1983 Sr-89 2010 2518.7 Sr-90 10 1 1612.6 I-131 30 1 30110.4 Cs-137 5212.
4718.7 K-40 1553157 14861129 STW-321 Water
&ne 1983 H-3 1470 89 15291583 STW-322 Water
&ne 1983 Ra-226 4.3 0.2 4.811.24 Ra-228
<2.5 0
STW-323 Water
&ly 1983 Gross alpha 31 718.7 Gross beta 21 0 2218.7 STW-324 Water August 1983 I-131 13.3 0.6 14110.4 14
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Table A-1.
'(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12cc 130, n=1d STAF-326 Air August 1983 Gross beta 42 2 3618.7 Filter Sr-90 1412 1012.6 Cs-137 19 1 1518.7 t
STW-328 Water Sept. 1983 Gross alpha 2.310.6 5t 8. 7 Gross beta 10.711.2 918.7 STW-329 Water Sept. 1983 Ra-226 3.010.2 3.110.81 Ra-228 3.2 0.7 2.010.52 STW-331 Water Oct. 1983 H-3 1300130 12101570 STW-335 Water Dec. 1983 1-131 19.611.9 20110.4 STW-336 Water Dec. 1983 H-3 2870 100 23891608 STAF-337 Air Nov. 1983 Gross alpha 18.010.2 1918.7 Filter Gross beta 58.611.2 5018.7 Sr-90 10.9 0.1 1512.6 Cs-137 30.112.5 2018.7 STW-339 Water Jan. 1984 Sr-89 47.211.9 3618.7 Sr-90 22.5 4.0 2412.6 STW-343 Water Feb. 1984 H-3 2487 76 23831607 STM-347 Milk March 1984 I-131 5.3 1.1 611.6 STW-349 Water March 1984 Ra-226 4.0i0.2 4.111.06 Ra-228 3.6 0.3 2.010.52 5
STW-350 Water March 1984 Gross alpha 3.8 1.1 518.7 Gross beta 24.2 2.0 2018.7 STW-354 Water April 1984 H-3 3560 50 35081630 STW-355 Water April 1984 Gross alpha 21.014.1 35115.2 Gross beta 127.8 4.1 147112.7 Sr-89 29.3 2.0 2318.7 Sr-90 16.610.7 2612.6 Ra-226 4.0tl.0 4.011.04 Co-60 32.3 1.4 3018.7 Cs-134 33.6!3.1 30 8.7 Cs-137 33.3 2.2 26 8.7 15
E 1
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected-Analysis 12cc 13o, n=1d STW-358 Water May 1984 Gross alpha 3.010.6 318.7 Gross beta 6.711.2 618.7 STM-366 Milk June 1984 Sr-89 2113.1 2518.7 Sr-90 1312.0 1712.6 I-131 46i5.3 43110.4 Cs-137 3814.0 3518.7 K-40 15771172 14961130 STW-368 Water July 1984 Gross alpha 5.111.1 618.7 Gross beta 11.912.4 1318.7 STW-369 Water August 1984 I-131 34.3 5.0 34.0 10.4 STW-370-Water August 1984 H-3 30031253 28171617 i
STF-371 Food July 1984 Sr-89 22.015.3 25.018.7 Sr-90 14.713.1 20.012.6 I-131
<172 39.0110.4 Cs-137 24.015.3 25.018.7 K-40 25031132 26051226.0 STAF-372 Air August 1984 Gross alpha 15.311.2 1718.7 Filter Gross beta 56.010.0 5118.7 Sr-90 14.-311.2 1812.4 Cs-137 21.Ot2.0 1518,7 s
STW-375 Water Sept. 1984 Ra-226 5.110.4 4.9il.27 i
Ra-228 2.210.1 2.3 0.60 STW-377 Water Sept. 1984 (ross alpha 3.311.2 5.018.7 Gross beta 12.712.3 16.0 8.7 l
STW-379 Water Oct. 1984 H-3 28601312 2810 356 STW-380 Water Oct. 1984 Cr-51
<36 4018.7 Co-60 20.311.2 2018.7 r
Zn-65 150 8.1 14718.7 Ru-106
<30 4718.7 Cs-134 31.3t7.0 3118.7 Cs-137 26.711.2 2418.7 16 2
s n - - -
-r
.e,,-m,
---n-
---,c,
,,,r-,,,,,-,e,-,
,.w,
- ~,
,-r-
r i
Table A-1.
(continued)
Concentration in pCi/lb Lab Sanple Date TIML Result EPA Result Code Type Collected Analysis 12 c 13, n= 1d STM-382 Milk Oct. 1984 Sr-89 15.714.2 2218.7 Sr-90 12.711.2 1612.6 I-131 41.7 3.1 42i10.4 Cs-137 31.3 6.1 32 8.7 K-40 1447 66 15171131 T
STW-384 Water Oct. 1984 Gross alpha 9.7 1.2 1418.7 (Blind)
Sa@ le A Ra-226 3.310.2 3.010.8 Ra-228 3.411.6 2.110.5 Uranium nae 5t10.4 Sanple B Gross beta 48.315.0 6418.7 Sr-89 10.714.6 1118.7 Sr-90 7.3 1.2 12 2.6 Co-60 16.311.2 14 8.7 Cs-134
<2 2 8.7 Cs-137 16.7 1.2 1418.7
\\
STAF-387 Air Nov. 1984 Gross alpha 18.711.2 1518.7 Filter Gross beta 59.0 5.3 5218.7 Sr-90 18.311.2 2112.6 Cs-137 10.311.2 1018.7 STW-388 Water Dec. 1984 I-131 28.012.0 36i10.4 STW-389 Water Dec. 1984 H-3 35831110 31821624 STW-391 Water Dec. 1984 Ra-226 8.411.7 8.612.2 Ra-228 3.lt0.2 4.1 1.1 STW-392 Water Jan. 1985 Sr-89
<3.0 3.018.7 Sr-90 27.315.2 30.012.6 STW-393 Water Jan. 1985 Gross alpha 3.311.2 518.7 Gross beta 17.3 3.0 15 8.7 STS-395 Food Jan. 1985 Sr-89 25.3 6.4 34.015.0 Sr-90 27.0 8.8 26.011.5 I-131 38.0 2.0 35.016.0 Cs-137 32.7 2.4 29.015.0 K-40 14101212 13821120 t
17
i Table A-1.
(continued)
I Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12cc 130, n=1d STW-397 Water Feb. 1985 Cr-51
<29 4818.7 Co-60 21.313.0 2018.7 Zn-65 53.715.0 5518.7 Ru-106
<23 2518.7 l
Cs-134 32.311.2 3518.7 Cs-137 25.313.0 2518.7 STW-398 Water Feb. 1985 H-3 38691319 37961634 STM-400 Milk March 1985 1-131 7.312.4 9.0 0.9 STW-402 Water March 1985 Ra-226 4.610.6 5.011.3 Ra-228
<0.8 9.012.3 Reanalysis Ra-228 9.010.4 STW-404 Water March 1985 Gross alpha 4.712.3 618.7 Gross beta 11.311.2 1518.7 STAF-405 Air March 1985 Gross alpha 9.3 1.0 10.018.7 Filter Gross beta 42.0 1.1 36.018.7 Sr-90 13.311.0 15.012.6 Cs-137 6.311.0 6.018.7 STW-407 Water April 1985 I-131 8.010.0 7.511.3 STW-408 Water April 1985 H-3 33991150 35591630 STW-409 Water April 1985 (Blind)
Gross alpha 29.711.8 32.015.0 Sample A Ra-226 4.4 0.2 4.110.6 Ra-228 nae 6.2 0.9 Uranium nae 7.016.0 i
Sample B Gross beta 74.3111.8 72.015.0 Sr-89 12.317.6 10.015.0 Sr-90 14.7 2.4 15.011.5 Co-60 14.712.4 15.0 5.0 Cs-134 12.012.0 15.015.0 Cs-137 14.012.0 12.015.0 4
18
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12 c 13, n = 1d STW-413 Water May 1985 Sr-89 36.0112.4 39.015.0 Sr-90 14.3 4.2 15.011.5 STW-414 Water May 1985 Gross alpha 8.3 4.1 12.0 5.0 Gross beta 8.711.2 11.015.0 STW-416 Water June 1985 Cr-51 44.716.0 44.015.0 Co-60 14.311.2 14.0 5.0 Zn-65 50.317.0 47.0 5.0 Ru-106 55.3 5.8 62.015.0 Cs-134 32.7 1.2 35.015.0 Cs-137 22.712.4 20.015.0 STW-418 Water June 1985 H-3 24461132 24161351 STM-421 Milk June 1985 Sr-89 10.314.6 11.018.7 Sr-90 9.0 2.0 11.0t2.6 I-131 11.711.2 11.0110.4 Cs-137 12.7 1.2 11.0 8.7 K-40 1512162 15251132 STW-423 Water July 1985 Gross alpha 5.010.0 11.018.7 Gross beta 5.012.0 8.0t8.7 STW-425 Water August 1985 1-131 25.713.0 33.0: 10.4 STW-426 Water August 1985 H-3 4363 83 4480t776 STAF-427 Air August 1985 Gross alpha 11.310.6 13.018.7 Filter Gross beta 46.0 1.0 44.018.7 Sr-90 17.710.6 18.0 2.6 Cs-137 10.3 0.6 8.0 8.7 STW-429 Water Sept. 1965 Sr-89 15.710.6 20.0 8.7 Sr-90 7.0 0.0 7.0 2.6 STW-430 Water Sept. 1985 Ra-226 8.2 0.3 8.912.3 Ra-228 4.110.3 4.611.2 STW-431 Water Sept. 1985 Gross alpha 4.7 0.6 8.0 8.7 Gross beta 4.7 1.2 8.018.7 19
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 120c 13o, n=1d i
STW-433 Water Oct. 1985 Cr-51
<13 21.018.7 Co-60 19.30.6 20.018.7 Zn-65 19.710.6 19.018.7 Ru-106
<19 20.018.7 Cs-134 17.011.0 20.028.7 Cs-137 19.311.2 20.018.7 STW-435 Water Oct. 1985 H-3 1957150 19741598 i
a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercom-parison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
Environmental Protection Agency, b (EPA), Las Vegas, Nevada,All results. are in pCi/1, except for elemental potassium (K) data in mg/1; air filter samples, which are in pCi/ filter; and food, which is in pCi/kg.
c Unless otherwise indicatec, the TIML results are given as the mean 12 *tandard deviations for three determinations.
d USEPA results are presented as the known values i control limits of 3a for n = 1.
e NA = Not analyzed.
f Analyzed but not reported to the EPA.
9 Results af ter calculations corrected (error in calculations when reported to l_
EPA).
J f.
I A
I-20 a
I i
m Table A-2.
Crosscheck program results, thermoluminescent dosimeters (TLDs).
mR d
Teledyne Average 12o Lab TLD Result Known (all Code Type Measurement 12ca Value participants) 2nd International Intercomparisonb CaF :Mn Gamma-Field 17.011.9
- 17. lc.
16.417.7 115-2b 2
Bulb Gamma-Lab 20.814.1 21.3c 18.817.6 3rd International Intercomparisone CaF :Mn Gamma-Field 30.713.2 34.914.8f 31.513.0 115-3e 7
Bulb O
Gamma-Lab 89.616.4 91.7114.6f 86.2124.0 4th International Intercomparison9 CaF :Mn Gamma-Field 14.111.1 14.lil.4f 16.019.0 115-49 2
Bulb Gamma-Lab (Low) 9.311.3 12.212.4f 12.017.6 Gamma-Lab (High) 40.411.4 45.819.2f 43.9113.2 5th International Intercomparisonh CaF :Mn Gamma-Field 31.411.8 30.016.01 30.2114.6 115-5Ah 2
Bulb Gamma-Lab 77.415.8 75.217.61 75.8140.4 at beginning Gamma-Lab 96.615.8 88.418.8i 90.7131.2 at the end a.
.c
n -
+
Table A-2.
(Continued) mR d
Average i 20 Teledyne Lab TLD Result Known (all Code Type Measucement 12aa Value participants) 115-5Bh LiF-100 Gamma-Field 30.314.8 30.0161 30.2114.6 Chips Gamma-Lab 81.117.4 75.217.51 75.8140.4 at beginning Gamma-Lab 85.4111.7 88.418.81 90.7131.2 at the end
\\
i standard deviations of three determinations.
a tab result given is the meci 12 Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health g
b and Safety Laboratory (GASL), New-York, New York, and the School of Public Health of the University of Texas, Houston, Texas.
c Value determined by' sponsor of the intercomparison using continuously operated pressurized ion chamber.
d Mean 12 standard deviations of results obtained by all laboratories participating in the program.
e Third International Interconparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.
f Value 12 standard deviations as determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
9 Fourth International Intercomparison of Environmental Dosimeters conducted in sumer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.
h Fif th International Intercomparison of Environmental Dosimeter conducted in f all of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas c..d Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.
i Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
APPENDIX I DATA TABLES AND FIGURES l
23 i
,\\
Table 1.1-1 LRP-!!!O-3 ATTAO' MENT A Revision 2 August 6. 1985 EEPORT Ot' RAD _TOACTIVR EFFLUENTS 4
FACIL77n L.ASALLE COUNTY NPS UNIT 1 t. 2 DOCKET N03.:
50-373. 50-374 YEAR:
1985 I.
Ganeous Ettb ents UNITS JAN fEB F173M IST OTR TOT APR 531 JUN 2ND_OTR TOT 6 MO TOTAL
.l. Cross Radioactivity l
Release l
4.
Noble cas Release
' Main Stack Curles 3 del 1.881 - 4dE0 5.481 7.3E0 N/A 7.98-5 7.3E0 6.131 l
- b. Maximum Release Rate (grab samplel uC1/sec 9.4El (1E1 7_. LEO 9.481 1.081 N/A 9.18-4 9.17-4 9.4E1
- c. Isotopes Released Kr-85m curies
- 1. 5 Q_
1 Rf.0 2.0E0 2 Q80 2
1 Kr-87 Cu r l es<5. 6E-8 + <5. 6 E-8 + <". 6L'-8 + <5. 68-8 +
<5.6E-8+ <5.68-8+ <5.6E-8+ <5.68-8+
<5.68-86 Kr-83 Curles<5.88-8+ <5.88-8+ <518E J+ <5 88-8+
<5.8E-86 <5.8E-8+ <5.88-8+ <5.8E-8+
<5.8E-8+
2 n
n -133 Curles 1.681
<2.lE-8+ !.78-2 1.6S1
<2.lE-8+ <2 1E-8+ <2j B-8+ <2.1E-8+
1,6El 2
Xe-135 Curies <l.2E-8+
5.4E-l
< !_22E-8+
SdE-1 3.6E0
<l.2E-8+
7.9E-2 3.6E0 4.2E0 Xe_-135m Curles<2.8E-8+
- 2. 7 t:-4 5.0E-3 5dp3
<2.88-8+ <2.88-8+ <2.85-8+ <2.88-8+
5.4E-3 Xe-138.
Curles<l.lE-5+ <l.18-5+ <l.1E-5+ <!.18-5+
<l.lE-5+ <l.lE-5+ <l.lE-5+ <l.1E-5+
<l.1E-5+
AR-41 Curles 1.531 _
3.0E0 3.681 3.8E0 3.8E0 4.0E1 1.881
- d. Percent of Stack Limit 6.4E-3 1.58-2 1.45-3 3.lE-2 1.88-3 N/A 1.48-5 3.78-3 1.7E-2
- c. Ayerage Release Rate UC1/sec 1.281 7.6E0 1.850 6.9E0 2.8E0 N/A 3.08-2 9.48-1 4.0E0 2.
Main Stack Iodine Release a.
Iggt_ppes Released I-131 Curles 5.3E-4 4.5E-5 9,88-4 1.6E-3 3 38-4 9.1E-4 6.98-4 1.98-3 3.5E-3 I-132 Curles 8.lE-4 2.0E-4 1.38-3 2.38-3 1.45-3 2.18-3 3.5E-3 5.88-3 I-133 CurJes 3 6E-3 8.6E-3 4 6E-3 1.7E-2 3.28-3 6.08-3 5.4E-3 1 28-2 3.28-2 2
2 I-134 Cu11es<6.4E-9+ <6.48-9+ <6.4E-9+
<6.4E-9+
<6.4E-9+ 1.78-3 7.88-4 2.58-3 2.5E-3 1-135 Curles 2.48-3 5.2E-3 1.3E-3 9.0E-3 4.1E-3 5.3E-3 7.0E-3 1.6E-2 2.5E-2
- b. Percent of Stack L t_m i t 1.78-4 2.5E-4 2.4R-4 6.25-2 1.48-4 1.7E-2 2.7E-2 7.5E-2 7.1E-2
- c. Average Release Rate uCl/sec 2.78-3 5.88-3 3.18-3 3.88-3 3.5E-3 6.IE-3 6.25-3 5.08-3 5.5E-3
' Data to be presented in an errata to this report.
+ Activity of each sample is less than LLD given (uC1/cc).
DOCUMENT ID 0213h/
Table 1.1-1 (continued)
LRP - l l 10 - 3 Revision 2 ATTAcilMRNT A August 6.
1985 5
REPORT OF RADIOACTIVR RFFLtfRMTS YEAR: 1985 FACILITY:
1.ASAll.R COUNTY NPS UNIT l & 2 DOCKRT NOS.:
50-373. 50-374 1.
Gaseous RIfluents UNITS JUL Atx1 SRP 3RD OTR TOT OCT NOV DRC 4Til OTR TOT 6 PD TOTA 1.
Cross Radioactivity Releases NONE NONE Main Stack Curles 3.7R0 3.881 6.0R1 1.0R2 1.6Rl DETECTED DRTECTED 1.681 1.2g2
- a. Noble Gas Release (grab _ sample) uC1/sec 1.1R1 1.4R2 3.5R1 1 482 5.ORI N/A N/A 5.0R1 1.462
- b. Maximum Release Rate Kr-85m Curles 8.68-1 8.68-1 2 4g-I 2.4R-1 1.180
- c. Isotopes Released 1
Kr-81 Curles
<5.68-86 <6.lR-8+ <6.1R-86 5.28-I
<6.18-8+
<6.lE-B+
5.28-1 5.28-1 Kr-88 Curles
<5.88-86 <6.58-8+
5.081 5.0RI
<6.5R-8
<6.5E-86
<6.5E-Bo 5.081 C$
!!_l33 Curles <2.16786 3.]R I
<2 5g-8+
3.161 1.361
<2 5R-86
<2 5R-84 I,3gt 5.0gl l
1 Xe-135 Curles 3.750 4.3R-4 1.0gl 1.4gl 2 ]RD
<l.38-8*
<l.3R-84 2.180 1.7RI 2
t xe;135m Curles
<2.88-86 1.0R-2 6.28-3 I.68-2
<2.8R-8+
<2.88-86 1.68-2 Xe-138 Ctgles
<l.lR-5* <l.lR-Se <l.18-56
<l.lR-56 <l.18-5+
<l.lR-5+
- d. Percent of Stack Ifmit S
6.3R-4 6.4E-2 7.9R-2 8.OR-2 1.0E-3 N/A N/A 1.0E-3 8.lR-2
- e. Average Release Rate uCl/sec 1.4E0 1.4E I 2.3E1 1.381 2.9El N/A N/A 2.0E0 7.5E0 f
2.
Main Stack lodine Release
- a. Trotopes Released 1-131 Curles 1.88-3 1,18-3 1.4R-3 4.38-3 5.98-4
<2.6R-12+ <2.6R-126 5.98-4 4,98-3 I-132 Curles I.98-3 4.18-3 7.55-3 1.4R-2 2.98-3 2.9E-3 1.78-2 l-133 Curles 3.BR-3 8.4R-3 1.0R-2 2.2E-2 4.58-3
<3.6R-12+ <3.6R-12* 4.5R-3 2.78-2 l
I-134 Curles 6 ]E-3 3.28-3 4.lR-3 1.4R;2 1.48-2 l
l-135 Curles 3.98-3 9.2R-3 3.78-2 5.08-2 4.5R-3 7.5E-2 8.08-2 1.38-1 t
- b. Percent of Stack Limit t
6.68-2 4.3R-2 1.2R-3 2.7R-3 4.2H-4 N/A 7.7R-4 2.4R-2 1.98-l
- c. Aver ase Release Rate uC1/sec 7.18-3 9.7R-3 2.3R-2 1.38-2 4.7R-3 N/A 2.EE-2 1.IR-2 1.18-2
- Data to be presented in an errata to this report.
- Activity of each sample is less than Lt.D 9 ven (uct/cc).
1 DoctmRNT ID 0220h/0360A
Table 1.1-1 (continued)
LRP-IIIO-3 ATTACHMENT A Revision 2 August 6. 1985 6
EEPORT OF RADIOACTIVE _ EFFLUENTS FACILITY: LASA1.LE COUNTY WPS UNIT 1 & 2 DOCKET WOS.:
50-373. 50-374 1 REAR:
1985 J.,
Caseous Ef fltsents(Cont)
UNITS JAN FEB MAR IST OTR TOT APE MAY JUN 2ND OTR TOT 6 MO TUTAL 3.
Main Stack Particulate Release
- a. Cross Radioactivity milli-(0-
)
curies 1.482 1.4E2 5.781 3.3E2 6.751 4.981 4.381 1.682 4.9E2
- b. Gross Alpha Radio-activity mci 5.0E-9
<0.25-8+
5.0E-6 5.0s-6
<2.0E-6+
5.08-6
- c. Isotopes Released 2.980 2.980 2.950 Ba-139 mC1 Mn-54 mC1 1.28-1 2.3E-1 2.0E0 2.3E0 7.9E-1 1.38-1
- 2. 8E-1 1.2E0 3.580 Co-58 mC1 <l.38-12+
1.08-2 <l.3E-12+ 1.0s-2 <l.35-12+ <!,3E-12+ <l.35-12+ <!.38-12+
1.08-2 Fe-59 mC1 4.5E-2 <2.48-12+ <2.45-12+ 4.5E-2 <2.4E-12+ <2.48-12+ <2.48-12+ <2.45-12+
4.55-2 Co-60 mC1 5.08-1 3.38-1 3.95-1 1.2E0 6.38-1 2.2E-1 4.45-1 1.380 2,580 3
zad5 mC1 <2.5E-12+ <3. lg,12* <3. IE-12* <3.1E-12+ <3.18-12+ <3.1E-12+ <3.15-12+ <3.1E-12+ <3.15-12+
Sr-89 mC1 2.95-8 4.65-8 4.0E-5 4.08-5 4.0E-5 4.0s-5 8.08-5 sr_-90 mC1 <5.0E-9+
<0.25-8+
<2.0E-6
<2.08-6
<2.0E-6
<2.0s-6
<2.0g-6 F _18 mC1 1.3E2 1.182 5.351 2.952 6.081 4.IEl 3.6El 1.4E2 4.382 4.480 4.4E0 Cl-38 mC1 4.4E0 1.88-1 Mrd6 mC1 7.78-2 9.8E-2 1.8E-1 6.48-2 6.4E-2 6.45-2 St-91 pC1 6.48-2 1.88-2 5.0E-2 3.25-2 1.88-2 2r-97 mC1 3.28-2 Cs-134 mC1 < !. 48-12+ <l. 4E-12+ < l. 45-12+ < !. 48-12+ <l. 48-12+ <l. 48-12+ < l. 48-12+ < l. 48-12+ < !.4E-12+__
1.08-2 1.05-2 1.0E-2 Cs-136 mC1 Cs-137 mC1 1.98-2 4.88-12+ 1.65-2 3.58-2
<1.88-12+ <l.8E-12+ <l.0E-12+
<l.88-12+
3.5E-2 Cs-138 mC1 3.5E0 2.5El 1.580 3.081 5.650 7.150 3.4E0 1.681 4.681 Ce-141 mC1 <2ME-12+ <2. 35-12+ <2. 3E-12+ <2.38-12+ <2. 3E-12+ <2. 3E-12+ <2.38-12+ <2.38-12 + <2."JE-12+
3 Cc-144 mC1 <8.5E-12+ <8_.5E-12+ <8.55-12+ <8.5E-12+ <8.58-12+ <8.58-12+ <8.58-12+ <8.55-12+ <8.58.12+
1 68-1 Na-24 mC1 4.4E-2 1.]E-1 1.65-1 4
- Data to be presented in an errata to this report.
+ Activity of each sample is less than LLD given (uC1/cc).
DOCUMENT ID 0213h/
l Table 1.1-1 (continued)
LRP-Illo-3 ATTACHMENT A Revision 2 August 6, 1985 RRpORT OF RADIOACTIVR RFFt.URNTS 7
l'ACitslTY : 1.ASAIAE COUNTY NPS UNIT I 1. 2 lxx.KET Nos. : 50-373. 50-314 YRAR: 1985 1.
Caseous RIfluents(Cont)
UNITS
- JUI, AUG SRP
~3RD OTH TOT OCT NOV DEC 4Til OTR TOT 6 Mo TOTAL 3.
Main Stack Particulate Release
- a. Gross Radioactivity milli-(0-
)
curles 1.lR3 1.7R2 2.4R2 1.5R3 1.3R2 5.18-1 1.8RI 1.582 1,7R3
- b. Gross Alpha Radio-act)vity mC1 4.08-9 9.OR-9 3.0s-9 1.6H-8
<l.0R-9 c.
Isotopes Released Cr-51 mCl 4.7R-1 4,78-l 4.lR-I Mn-54 mcl
'3.08-1 8.BR-2 1.48-1 5.38-I 1 98-1 1.1R-1 1.lR-l 4.0R-1 9.'38-1 1
co-58 mC1
<l.38-12+ <l.3H-12+ <l.38-12+
<t 3E-12* <1.38-12+ <l.3R-12+
z y
Fe-59 mC1
<2.4K-12+
2.3R-2
<2.68-126 2.3g-2
<2.6R-12+ <2.6R-12+ <2.6R-12+
N Co-60 mC1 7.0R-1 3.2R0 3,7R-1 7.4R1 6.88-1 3.4R-1 7.68-2 1.180 7.5El 2n-65 mcl
<2.58-12+ <3.0g-12+ <3.08-12+
<3.08,-12+ <3.0R-12+ <3.0E-12+
St-89 mC) 3:5R-R 3 18-8
<3 68-8 1.0R-7 1.8R-8 2
3 Sr-90 mC1
<l.08-9
<l,08-9
<2.0R-9 3.OR-9 2,-93 nCl Nb-95 mCl 1.78-2 3.68-2 5.38-2 5.3R-2
__ D r.8 2 mC1 1.78-2 1.7R-2 1.78-2 Er!10m mci so-124 mC1 Cs-134 mC1
<l.48-12+ <l.3R-12+ <l.3R-12+
1.2R-2 1.28-2 1.28-2 Cs_136 mC1 Cs-l U mcl
<l.8R-12+ <l.3R-12+ <l.38-126
<l.3R-12+ <l.38-12+ <l.38-12+
na-140/l.a-140 mC)
~~-
Cc-141 mC1
<2.3R-12+ <2.18-12+ <2.!R-12+
<2.lR-12+ <2.lR-12+ <2.18-12+
Cc-144 mC1
<8.58-12+ <8.58-12+ <8.58-12+
< 8.5R-12 + <8. 5R-12 + <8.
R-12 + ---
J Cs-138 mC1 3.5R1 1.58 I l.381 6.351 2.4E0 9.4gG l.2gl 7. 5 g 1_
Na-24 mC1 1.0g3 4.BR-1 3.8g-l 1.083 2.7E-2 6.88-2 9.58-2 1.0E3 F-18 mC) 5.IRL l.4E 2 2.2g2 4.2g2 1.3R2 8.7R0 1.4R2 5.682 ga-}39 mCl 1.4E0 7.2R 0 9.9E0 1.9gt
- 1. 9 81___
.Tc-99m mCl 8.0E-l 8.08-1 8.OR-1 3.58-2 3.58-2 W 181 mCl 3.5R-2 Se-75 mC1 6.38-2 6. ~3 R - 2 6.38-2
- Data to be presented in an errata to this report.
- Act ivit y of each sample is less than 1.t.0 given (uct/cc).
DoctrM. INT ID 0220h/0360A
. ~.
i I
Table 1.1-1 (continued)
LRP-ll10-3 i '
REPORT OF RADIOACTIVE RFFLUENTS Revision 2 August 6, 1985 ATTAClWEENT A 8
]
l FACTLITY: LASALLE COUNTY NPS (MIT 1 & 2 DOCKET NOS.: 50-373. 50-374 YEAR:
1985 I.
Caseous Effluents (Cont)
UNITS JAN FEB MAR IST OTR TUT APR MAY JUN 2ND OTR 1DT 6 MO TOTAL i
3.
Main Stack Particulate Re_1. case i
- d. Percent Main Stack Limit 3 28-5 1.28-5 2.78-5 1.2E-4 2.68-5 8.0E-6 3.28-5 9.98-5 1.18-4
- e. Average Release Rate uC&/sec 5.18-2 5.18-2 2.lE-2 4.3E-2 2.68-2 1.88-2 1.68-2 2.08-2 3.1E-2 l
_4.
Sum of Iodine and Particulate Curies 1.58-1 1.55-1 6.58-2 3.68-1 7.68-2 6.3E-2 5.98-2 2.0s-1 5.65-1
- a. Percent Main Stack Limit 1.78-4 2.55-4 2.4E-4 6.25-2 1.45-4 1.78-2 2.7E-2 7.58-2 7.1E-2 5.
Gaseous Tritium
- a. Release Curies 6.78-1 2.08-1 1.5E-1 1.050 ld s-3 <3.lE-9+ <3.2E-9+
1 25-_3
_1 PRO
- b. Average Release Rate UC1/see 2.58-1 8.48-2 5.58-2 1.35-1 4.68-4 N/A N/A 1.58 4 5.'.(-J____
- c. Percent Tech Spec I
Limit 4.4E-4 1.38-4 9.78-5 1.48-3 7.9E-7 N/A N/A 1.6E-6 b.8d-4 _
i a
i 4
l
- Data to be presented in an errata'to this report.
+ Activity of each sample is less than LLD given (uC1/cc).
1 DOCUMENT ID 0213h/
Table 1.1-1 (continued)
LRP-Ill0-3 ATTACitMENT A Revision 2 August 6, 1985 REPORT OF RADIOACTIVE RFFLORNTS 9
FACI t.lTY : 1.ASALLE COUNTY NPS UNIT 1 & 2 DOCKRT NOS. :
50-313, 50-374 YRAR:,[185
- 1.. Gaseous Rffluents(Cont)
IfNITS JUL Atn SRP 3RD OTR TUT OCT NOV DEC 4Til OTR TOT 6 MO. TOTAL 3.
Maln Stack Particulate EeledEP
- d. Percent Main Stack t.lmit i
7.48-4 2.lR-4 2.7R-5 4.88-3 5.OR-5 2.3R-5 6.48-6 8.0g-5 5.4R-3
- e. Average Release Rate uCl/sec 4.1R-1 2.0R-2 9.3R-2 1.8R-1 4.98-2 2.08-4 6.7R-3 1,98-2 1.!R-1 4.
Sum of lotline and Particulate Curles 1.1R0 2.08-1 3.0R-1 1.6RO l.48-1 5.lR-1 1.4RO 2, LEO 3.780
- a. Percent Main Stack Limit i
6.7R-2 4,3R-2 1.2R-3 4.8R-3 4.28-4 2.3R-5 7.88-4 2.48-2 1.98-1 5.
Caseous Tritlum
- a. Release Curles Curles 7.1R-7 <l.988-96 <l.6R-96 7 18-7 1.0R-7 1.3R0 1.4R-3 1,3g0 1.3g0 3
n; 43
- b. Average Release Rate uC1/sec 2.lR-7 N/A N/A 8.9R-8 3.7R-8 5.08-1 5.2R-4 5.2R-1 8.2R-2
- c. Percent Tech Spec Limit i
9.5R-10 N/A N/A 9.5R-10 1.3R-10 1.7R-6 I.98-6 1.7R-3 1.7R-3
- Data to be presented in an errata to this report.
- Activity of each sample is less than LLD given (uCl/cc).
DOCUt.ENT ID 0220h/0360A
Table 1,2-1 LRP-!!!O-3 ATTAOMENT A Revision 2 August 6, 1985 REPORT OF RADIOACTIVE EFFLUENTS 10 EACILITY: LASALLE COUNTY NPS UNIT I & 2 DOCRET WOS.: 50-373. 50-374 YEAR:
1985 II. Liquid Effluents UNITS JAN FE8 MAR IST OTR TOT APR MAY JUN 2ND OTR TOT 6 MO WTAL 4
1.
Gross Radioactivity (8-
)
- a. Total Release CuL es Released 6.lE-3 2.8E-3 8.98-3 2.9E-3 Released 6.68-4 3.6E-3 1.25-2 i
- b. Ave. Conc. Released uC1/ml N/A 1.68-8 3.65-8 1.98-8 9.65-9 N/A 2.58-9 6.38-9 1.98-8
- c. M.tx. Conc. Released UC1/ml N/A 2.9E-8 3.78-8 3.7E-8 1.98-8 N/A 2.58-9 1.98-8 3.78-8
- d. Percent of Tech Spec N/A 1.85-3 3.95-5 3.5E-3 3.45-5 N/A 1.75-5 9.38-5 1.85-3 2.
TTlttum None None
- a. Total Release Curles Released 9.7E-2 2.28-2 1.28-1 8.15-2 Released 6.1E-2 1.4E-1 2.65-1 i
?
w
- b. Avg. Conc. Released UC1/ml N/A 4.6E-4 4.5E-4 4.65-4 3.98-4 N/A 8.2E-4 5.0E-4 4.85-4 i
- c. Percent of Tech Spec N/A 1.0E-5 2.3E-6 2.5E-5 8.4E-6 N/A 1.38-5 2.95-5 2.7E-5 3.
Dissolved Noble Gases None None None None None None a._ Total Release Curles Released Released Released Released Released Released
- b. Avg. Conc. Released uC1/ml N/A N/A N/A N/A N/A N/A N/A N/A N/A
- c. Percent of Tech Spec N/A N/A N/A N/A N/A N/A N/A N/A N/A 4.
Gross Alpha Radloactivity None None
- a. Total Release Curles Released 6.6E-6 6.3E-5 7.0E-5 9.4E-67 Released 8.2E-8 9.5E-6 8.0E-5
- b. Av3 Conc. Released uC1/ml N/A 1.7E-!! 8.18-10 1.58-10 3.15-11 N/A 3.08-13 1.7E-11 8.0E-11 5.
Volume of Liguld Waste Liters 0
2.1E5 4.984 2.685 2.185 0
7.4g4 2.8E5 5.485 6.
Volume of Dilution Water Liters 0
3.888 7.887 4.688 3.088 0
2.7E8 5.7E8 1.089
)
i i
- Data to be presented in an errata to this report.
+ Activity of each sample is less than LLD given (uC1/cc).
DOCUMENT ID 0213h/
i
Table 1.2-1 (continued)
LHP-li10-3 Revision 2 ATTACHNENT A August 6, 1985 BEPORT OF RADIOACTIVE EFFLUENTS YEAR:
1985 50-373. 50-374 F A._C_l LITY :
LA_ sal.1E COUNTY NPS UNIT I & 2 DOCKET hog.:
- 11. Liguld Efiluents(Cont)
UNITS JUL AUG SEP 3RD OTR TOT OCT NOV DEC 4Til OTR TOT 6 MO TOTAL 1.
Gross Radioactivity None None None auTotal Release cur _tes 2 6E-2 peleased peleased 2.6E-2 Released 3.8E0 1.1E-3 3.8E0 3.8E8 (G
)
t
- c. Max. Conc. Released uCl/ml 3.2E-7 N/A N/A 3.25-7 N/A 8,88-9 7.7E-9 7.78-9 3.2E-7 2
7.2E-4 N/A N/A 7.2E-4 N/A 1.0E-4 3.0R-5 4.8E-5 7.8E-4
,_ _d _ Percent of Tech Spec None None None z
- a. Total Release Ctyles 4 95-2 Released Released 4.95-2 Released 5,35-2 2.7E-2_
Tritlum 2
- b. Avg. Conc. Released uCl/ml 7.25-4 N/A N/A 7.2E-4 N/A 3.5E-4 3 55-4 3.55-4 4.3E-4 1
2
- c. Percent of Tech Spec 1.85-5 N/A N/A 1.85-5 N/A 1.1E-5 5.6E-6 1.7E-5 2.7E-5 3.
Dissolved Noble Gases None None None None h
None None None Hone
- a. Total Release C_ur_tes Detected Released Weleased Released Released Detected Detected Detected Detected
- b. Avg. Conc. Released uCl/ml N/A N/A N/A N/A N/A N/A N/A N/A N/A
- c. Percent of Tech Spec N/A N/A N/A N/A N/A N/A N/A N/A N/A None None None
Gross Alpha Radioactivity 1
b._Av3. Conc. Re! eased uC1/ml 1,2g-13 N/A N/A 1.2g-13 N/A 1.55-13 1.8-12 6.4E-14 7.8E-14 5.
Volume of Liquid Waste Litns 6 SE4 0
0 6.854 N/A 1,555 7.734 2.355 3.0E5 6.
Volume of Dilution Water Liters 8.287 8
0 8.257 8
6.559 1.4E8 6.659 6.7E9 i
l i
- Data to be presented in an errata to this report.
- Activity of each sample is less than LLD given (uCl/cc).
I twWtWNT ID 0220h/0360A
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Table 1.2-1 (continued)
LRP-Il10-3 ATTACHMENT A Revision 2 August 6, 1985 PEPORT OF EADIOACTIVE EFFLUENTS
'13 FACILITY: LAS_ALLE CVUNTUPS UN_LT I & 2 DOCRET WOS. :
50-373. 50-374 YEAR: 1985 II Liguld Effluents _{ Cont)
UNITS JUL AUG SEP 3RD OTR TOT OCT WOV DEC 4TH OTR TOT 6 MO TOU L 7
Isotopes Released milli-None None None c_urles Released seleased Released Cr-pt gi Mn-54 oc) 1 4g1 1 451 1
3.6E-l 4.6E-l 8.28-1 1.551 2
Co-58 met 1.0E0 1.0g0 1.7E-2 1.0E-1 1.28-1 1.150 Fe-59 mCl
<l.38-7+
<l.38-7+
<l.25-7+ <l.38-7+
Co-60 mCl 1 0g1 1
1.051 2,25-1 4 85-1 7.}g-1 Idgl 2n_-65 mcl 3.58-I 1
3.55-1
<l._lB-7+ <l.18-7+
3.55-1 St-39 oct 1.18-2 I.is-2 6.28-2 6 !E-3 6 88-2 7.9E-2 St-90 aCl 5.58-4 5.55-4 IJE-4 1.65-4 3.38-4 8.85-4 zr-95 oct w
Nb-95 oct itu303
~~
ac[
I-131 oc!
<6 98_!+
<6 gE-g+
1 1
<6 88-8+
<6.88-8+
Cs_-131.
act
<5.33;!+
a
<5JR-8+
<5.35-8+
<5dg-8+
Cs_-137 oci
<5.68-8+
<5.6E;86
<5.68-8+
<5.65-8+
Ba_-jt0/La-140 mCl Ce_-lil mC1
<9.35-86
<9 )g-8+
<9 25-8+
<9,]E-8+
Ce-l!{
act
< 4 } E -7 +
_t
<4 ]E-7+
1
<4 ]E_-7+
<4 lg-7+
xe_-133 me!
<8 sg;g+
1 1
<8dt-8+
<8 55-8+
<8 gg-g+
xe_-l]3m act
<3.75-7+
1
<3 ]E-16 1
<3.75-7+
<3.75-76 xe__135 oc!
<3.88-8+
<3.85-8+
<3 gs-8+
<3.85-8+
Fe-55 met 2.9E-5 1
2.95-5 2 g5-2 2.75-2 5.55-2 5 ;E-2 1
1
- Data to be presented in an errata to this report.
4 Activity of each sample is less than LLD given (uC1/cc).
DOCUMENT ID 0220h/0360A
Table 2.0-1 LRP-Il!0-3 ATTACHMENT A Revision 2 August 6, 1985 REPORT OF RADIOACTIVE EFFLUENTS 14 FACILITY: LASALLE COUNTY NPS UNIT I & 2 DOCKET WOS.:
50-373. 50-374 YEAR:
1985 III. Solid Waste Shipped offsite for Burial I
or Disposal UNITS JAN FEB MAR IST OTR TOT APR MAY JUN 2ND OTR TOT 6 MO TOTAL I
1.
Spent Resins. F11ter Studges. Evaporator Bottoms. etc.
- a. Quantity Shipped Cu. meters 7.681 4.981 9.4E1 2.282 1.2E2 9.181 1.082 3.1E2 5.382 BB.FS EB.SR EB.SR EB.SR
- b. Type of Waste SR Diat Earth Diet Earth Dlat Earth EBESR EB&SR
- c. Activity - Total Measured Curles 4.681 1.881 3.3E1 9.7El 3.981 3.6El 3.281 1.182 2.182
- d. Principle Nuc!! des Measured /%
Mn-54 40 40 40 40 40 40 g
Cr-51 25 25 25 25 25 25 f
co-60 23 23 23 23 23 23
- e. Type of Container (LSA. Type A. Type B.
Lge Quantity) 2.18-1 2.1E-1 2.18-1 2.18-1 2.18-1 2.18-1 l
container volume Cu, meters or 5.2E0
- f. Solidification Agent CEMENT CEMENT CEMENT CEMENT CEMENT CEMENT 2.
Dry Compressible Waste.
Contaminated Equipment, etc.
a._ Quantity Shipped Cu. meters 6.6E0 4.0E0 2.781 7.4E1 2.681 4.781 2.581 9.881 l.782
- b. Activlty - Total Measured Curles 2.6E-1 4.68-1 5.18-1 1.2E0 3.68-1 8.28-1 2.5E-1 1.4E0 2.7E0
- c. Principle Nuc!! des Measured /%
Mn-54 40 40 40 40 40 40 Cr-51 25 25 25 25 25 25 Co-t,0 23 23 23 23 23 23
)
2.1E-1 2.lE-1 2.1E-1 2.18-1 2.18-1 j
Lge Quantity) or or or or or j
Container volume Cu. meters 2.18-1 2.7EO 2.7E0 2.7E0 2.7EO 2.7RO
_ DOCUMENT ID 0213h/
i
+
6 O
Table 2.0-1 (continued) 1.RP-!!!0-3 ATTAClintcNT A Revision 2 August G.
1985 REPORT OF RADIOACTivs EPPLUENTS 15 fACUJIYi I.ASAl.LE_A N Y WPS UNIT I E 2 DOCEET NOS.t 50-313. 50-374 YEAR: 1985 111. Solid Waste Shipped offsite for Ituttal of_Plfpopal UNITS JUL AUG SEP 3RD OTR TOT OCT NOV DEC 4711 OTR TOT 6 PELT-
-1.
Sperit Resins. Filter
l ud ys. Evaporator Bot t ons, e t c.
aduaritity shipped Cu. meters 8.481 4.661 8.lgt 2dE2 2 del 4 8El I.6El 1,6E2 3. I P.
1 E8. SE E8. SR.
- 58. SE E8. SR E8 SR
- 88. SR ED.
EB. SR.
Ett. !;'
b Type _of_ Waste Dlat Earth Dlat Earth Dlat Earth Dlat Earth Dlat Earth Dlat Earth Dlat Earth Dlat Earth Diat___
u
- c. Activity - Total Measured Curles 3.551 3.951 5.151 1."l82 6.381 6.0E1 1.281 1.482 2.7 t!
- d. Principle NucIldes w
Pleasur ed/%
Mn-54 30 30 32 30
~10 30 30
'l0 30 Cr-51 20 20 22 20 20 20 20 20 20 Co-60 20 20 19 20 20 20 20 20 2?
- e. Type el Contattier LSA LSA 1.SA LSA LSA LSA LSA LSA I.S A ILSA. Type A. Type 8 2.1E-1 2.1E-1 2.18-1 2.lE-l 2.IH L9e Quantity) 2.1.5-1 2.15-1 3.3E-1 3.35-1 3.3E-1 3.3E
_fosjt a lncLVoltyne Cu, meters 2.15-1 2.1E-1 3.3.5-1 3.38-1 2.750 2.180 2.1E0 2.75
- f. Sol 141Ileatton_ Age _nt Cement Cement Cement Cement Cement Cement Cement Cement Cere
_2.
Dr y Cmpressible Waste.
Contaminated Equipment.
etp.
=
a._ Quasj t,l t y Shleged Cu, meters 1.151 1.4EI 3.251 5.751 3.081 3.751 1.851 8.581 1.4R
- b. Acttwity - Total Measured Curles 9.38-2 6.0E-1 1.150 1.880 1.150 6.88-1 3.051 2.150 3.9E c reinciple Nuc!! des Ecasured/%
Mn-54 50 50 40 50 50 50 50 50 50 co-60 40 30 23 30 30 30 30 30 30 ge-55 14 14 7
14 14 14 14 14 14
2.1E-1
.2.1E-1 2.ls-1 2.1E-I 2.1E-1 2.1E-1 2.1E-1 2.lt-1 2.18 L9e Quantity) oc 3.38-1 3.38-1 3.3E-1
'I.3E-1 3.38-1 3.3E-1 3.3E Conta,lner volume cu. meters 2.750 2.750 2.750 2.1E0 2.7EO 2.7E0 2.7E0 2.1EO 2.18 e.
Tyre of Waste DAW DAW DAW DAW DAW DAW DAW DAW DAW t*<tNwWT ID 0220h/03604
Table 2.0-1 (continued)
RWA - Richland Washington ATTACllMENT A LRP-ll10-3 BSC - Barnwell, South Carolina F_EPORT OF RADIOACTIVE WASTE SUPetARY Revision 2 CN
- Chem Nuclear Co.
UNITS 1/2 August 6, 1985 ftN
- Ilittman Nuclear & Development Co.
LASALLE COUNTY NUCLEAR POWER STATION 16 TSMT - Tri-State Motor Transit DISPOSITION OF MATERIAL Type Type Solidif1-Principle Shipment Shipment Volume Activity of of cation Volume Activity Per Month Per Mcoth pATE TRANS Co.
BURIAL SITE Waste Container Ajent Nuclides (ft3)
(mCl)
(ft3)
(mCl) 02JAN85 Tri-State M.T.
RWA SR LSA Cement
_ Cr-51 182 5811.0 182 5811.0 Evap.
04JAN85 CN RVA Bottoms LSA Cement Mn-54 105 2034.2 287 7845.2 1
07JAN85 CN RWA EB & DAW LSA Cement co-60 270 2184.7 557 10029.9 07JAN85 CN RWA EB & FS LSA Cement Co-58 105 1640.0 662 11669.9 08JAN85 McCormack's RWA SR LSA Cement Fe-59 182 5408.0 884 17077.9 Evap.
08JAN85 CN RWA Bottoms LSA Cement 2n-65 105 1382.0 949 18459.9 i
09JAN85 CN RWA EB & DAW LSA Cement Sb-124 292.5 2213.1 1241.5 20673.0 llJAN85 CN RWA EB & DAW LSA Cement Nb-95 240 1928.4 1481.5 22601.4 l
EB.FS &
IlJAN85 CN RWA DAW LSA Cement Fe-55 105 1789.2 1586.5 24390.6 l
Evap.
15JAN85 CN RWA Bottoms LSA Cement N1-63 105 1584.2 1691.5 25974.8 Evap.
17JAN85 CN RWA Bottoms LSA Cement 270 2329.4 1961.5 28304.2 Evap.
18JAN85 CN RWA Bottoms LSA Cement 105 1800.7 2066.5 30104.9 Evap.
19J_AN85 CN RWA Bottoms LSA Cement 270 2182.4 2336.5 32287.3 23JAN95 Tri-State M.T.
RWA SR LSA Cement 182 5022.2 2518.5 37309.5 Evap.
23JAN85 CN RWA Bottoms t.9A Cement 105 1225.6 2623.5 38535.1 DoctmENT ID 0213h/
i l
Table 2.0-1 (continued)
RWA - Richland, Washington ATTACHMFNT A LRP-1110-3 BSC - Barnwell, South Carolina REPORT OF RADI0 ACTIVE WASTE SINGULRY Revision 2 UNITS 1/2 August 6, 1985 CN
- Chem Nuclear Co.
HM
- Hittman Nuclear & Development Co.
LASALLE COUNTY NUCLEAR POWER STATION 16 TSMT - Tri-State Motor Transit DISPOSITION OF MATERIAL
- Type Type Solidifi-Principle Shipment Shipment Volume Activity of of cation Volume Activity Per Month Per Month DATE TRANS CO.
BURIAL SITE Waste Container Agent Nuclides (ft3)
(mCl)
(ft3)
(mCl)
~
Evap.
24JANB5 CW RWA Bottoms LSA Cement 105 1373.3 2728.5 39908.4
_2_8JAN85 McCormack's RWA SR LSA Cement 182 6693.4 2910.5 46601.8 0_5FEB85 CN RWA EB & DAW LSA Ca.;...i t Mn-54 556.5 1831.0 556.5 1831.0 06FEB85 CN RWA EB & DAW LSA Cement Cr-51 328.5 2351.7 885.0 4182.7 07FFB85 CW WA EB LSA Cement Co-60 105 1208.4 990.0 5391.1 IIFEB85 CN RWA EB LSA Cement Pe-55 105 1232.3 1095 6623.4 EB & DIAT.
j 12FEB85 Cw RWA EARTH LSA Cement co-58 105 1591.3 1200 8214.7 14FEB85 CN kWA EB & DAW LSA Cement Fe-59 270 1910.1 1470 10124.8,,,_
18FEB85 CN RWA EB.SR. DAW LSA Cement In-65 285 2338.2 1755 I,4r),o 22FEB85 CW RWA EB LSA Cement Mn-54 105 1061.4 1860 13524.4 22FEB85 CW RWA EB.SR. DAW LSA Cement Cr-51 262.5 2401.5 2122.5 15925.9 26FEB85 Tri-State RWA DAW LSA N/A Co-60 712.5 284.3 2035 16210.2
)
28FEB85 CW RWA EB & DAW LSA Cement Fe-55 285 1727.6
'J120 17937.8 I
OlMAR85 CW RWA EB t.SA Cement mi-54 202.5 2563.1 202.5 2563.1 04 MAR 85 CW RWA EB & DAW LSA Cement co-58 300.0 2201.7 502.5 4764.8 I
i 1
DOCtjMENT ID 0213h/
i I
Table 2.0-1 (continued)
RWA - Richland, Washington ATTACHMRWT A LRP-1110-3 BSC - Barnwell. South Carolina REPORT OF RADIOACTIVE WASTE SUMARY Revision 2 CN
- Chee Nuclear Co.
UNITS 1/2 August 6, 1985 HN
- H!ttman Nuclear & Development Co.
LASALLE COUNTY NUCLEAR POWER STATION 16 TSfff - Trl-State Motor Transit DISPOSITION OF MATERIAL Type Type Solidifi-Principle Shipment Shipment.
Volume Activity of of cation Volume Activity Per Month Per Month DATE TRANS CO.
BURIAL SITE Waste Container Agent Nuclides (ft3)
(eCI)
(ft3)
(MCI) 07 MAR 85 CW RWA DAW & E8 LSA Cement Co-60 292.5 2122.2 795.0 6887.0 08 MAR 85 CW RWA DAW & EB LSA Cement Cr-51 292.5 2412.6 1087.5 9299.6 13 MAR 85 CN RWA DAW.EB.SR LSA Cement Fe-55 292.5 2128.3 1380.0 11427.9 13 MAR 85 CW RWA DAW EB.SR LSA Cement Fe-59 300.0 2302.1 1687.0 13730.0 g
15 MAR 85 CN RWA DAW.SR.E8 LSA Cement 2n-65 351.0 2558.4 2031.0 16288.4 19 MAR 85 CW RWA DAWJR EB LSA Cement NI-63 300.0 2268.9 2331.0 18557.3 2
DIAT EARTH 19 MAR 85 CW RWA SR. EB LSA Cement 202.5 2182.8 2533.5 20740.1 20 MAR 85 CN RWA DAW.EB.SR LSA Cement 285.0 1847.1 2818.5 22587.2 22 MAR 85 CN RWA DAW.BB.SR LSA Cement 336.0 2322.3 3154.5 24909.5 25 MAR 85 CN RWA DAW.EB.SR LSA Cement 285.0 2036.4 3439.5 26945.9 26 MAR 85 CN RWA DAW E8 LSA Cement 292.5 2387.6 3732.0 29333.5 29 MAR 85 CN RWA E8 LSA Cement 202.5 2548.7 3934.5 31882.2 J0 MAR 85 CW RWA BB & DAW LSA Cement 336.0 1990.1 4270.5 33812.3 02APR85 CW RWA E8 & DAW LSA Cement Mn-34 292.5 2224.3 292.5 2224.3 03APR85 CW RWA E8 LSA Cement Cr-51 255.0 2401.2 547.5 4625.5 DOCUMENT ID 0213h/
Table 2.0-1 (continued)
R'w A - Richland. Washington ATTACifMENT A LRP-ll10-3 USC - Barnwell, South Carolina REPORT OF RADIOACTIVE WASTE
SUMMARY
Revision 2 CN
- Chem Nuclear Co.
UNITS 1/2 August 6, 1985 IIM
- liittman Nuclear & Development Co.
LASALLE COUNTY NUCLEAR POWER STATION 16 TSMT - Tri-State Motor Transit DISPOSITION OF MATERIAL Type Type Solidifi-Principle Shipment Shipment volune Activity of of cation Volume Activity Per Month Per Month PATE TRANS CO.
BURIAL SITE Waste Container Agent Nuclides (ft3)
(mC1)
(ft3)
(mC1) 04APR85 CN RWA EB & PAW LSA Cement co-60 336.0 2110.9 883.5 6736.4 05APR85 CN RWA EH. DAW,SR LSA Cement Pe-55 292.5 2050.4 1176.0 8786.8 08APR85 CN RWA EB LSA Cement Co-58 202.5 1767.4 1378.5 10554.2____
09APR85 CN RWA EB. DAW,SR LSA Cement Mn-54 351 2312.33 1729.5 12866.5 12APR85 CN RWA ED DAW.SR LSA Cement Cr-51 336 2294.40 2065.5 15160.9___
2 12APR85 Tri-State RWA EB & SR LSA Cement Co-60 345 3289.34 2410.5 18450.2 13APR85 CN RWA ED & SR LSA Cement Fe-55 336 2146.15 2746.5 20596.4 EB &
16APR85 CN RWA DIAT EARTil LSA Cement Co-58 202.5 2227.11 2949.0 22823.5 DAW E_B SR LSA Cement 2n-65 336.0 2121.59 3285.0 24945.1 17APR85 CN RWA 2
g ED, DAW, 18APR85 CN RWA DIAT EARTH LSA Cement Fe-59 292.5 1790.74 3577.5 26735.8 22APR85 Tri-State RWA EB & SR LSA Cement N1-63 330 2869.42 3907.5 29605.3 _
23APR35 Of RWA EB & SR LSA Cement H-3 330 2018.79 4207.5 31624.0 26APR85 Tri-State RWA EB & SR LSA Cement C-14 330 3114.90 4537.5 34738.9 26APRB5 CN RWA EB & SR LSA Cement 292.5 2035.84 4830 36774.7 30APN85 CN RWA EB & SR LSA Cement 306 2474.21 5136 39248.9 l
J DOCUMENT ID 0213h/
Table 2.0-1 (continued)
RWA - Richland, Washington ATTACHMENT A LRP-il10-3 BSC - Bartwell, South Carolina REPORT OF RADIOAgIIVE WAStK SUPMARY Revision 2 CN
- Chem Nuclear Co.
IMITS 1/2 August 6, 1985 g
HN
- Hittman Nuclear & Development Co.
IASALLE COUNTY NUCLEAR POWER STATION 16 TSMT - Tri-State Motor Transit DISPOSITION OF MATERIAL Type Type Solidifi-Principle Shipment Shipment Volume Activity of of cation Volume Activity Per Month Per Month DATE TRANS CO.
BURIAL SITE Waste Container Agent Nuclides (ft3)
(mCl)
(ft3)
(mCl) 08MAY85 HN RWA EB & SR LSA Cement Co-60 255 2775.48 255 2775.40 10MAY85 HN RWA EB. DAW.SR. LSA Cement Cr-51 300 2391.34 555 5166.82 13MAY85 HW RWA EB & DAW LSA Cement re-55 315 2604.39 870 7771.21 8
15MAY85 HN RWA BB. DAW.SR LSA Cement Mn-54 315 2562.24
!!85 10333.45 16ftAY85 Trl-State RWA DAW LSA N/A zn-65 864 580.30 2049 10913.75 16MAY85 HN RWA EB. DAW.SR LSA Cement co-58 315 2473.56 2364 13387.31 i
j7MAY85 HN RWA EB LSA Cement Fe-59 180 2676.31 2544 16063.62 20MAY85 HN RWA EB & DAW LSA Cement N!-63 315 2557.05 2859 18620.67 l
22MAY85 HW RWA EB. DAW.SR LSA Cement H-3 307.5 2823.53 3166.5 21444.2 23MAY85 HN RWA EB. DAW.SR LSA Cement C-14 300 2522.94 3466.5 23967.14 1
24MAY85 HN RWA EB & SR LSA Cement 180 2928,72 3646.5 26895.86 28MAY85 HN RWA E8. DAW.SR LSA Cement 300 2593.46 3946.5 29489.32
]
30 MAYS 5 HN RWA E8 & DAW LSA Cement Co-60 285 2351.59 4231.5 31840.91 Y
31MAY85 Tri-State RWA EB. DAW.SR LSA Cement Cr-51 447 2388.35 4678.5 34229.26 Fe-55 31MAY85 HN RWA g3 LSA c g7,g pm.54 180 2424.81 4858.5 36654.09 DOCUMENT ID 0:Pl3h/
0 4
Table 2.0-1 (continued)
RWA - Richland. Washington ATTACHMENT A LRP-Illo-3 BSC - Barnwell. South Caro!!na F_EPORT OF. RADIOACTIVE WASTE SUPetARY Revision 2 CN
- Chem Nuclear Co.
UNITS 1/2 August 6, 1985 HN
- Hittman Nuclear & Development Co.
LASALLE COUNTY NUCLEAR POWER STATION 16 TSMT - Tri-State Motor Transit DISPOSITION OF MATERIAL Type Type Solidifi-Principle Shipment Shipment Volume Activity of of cation Volume Activity Per Month Per Month DATE TRANS CO.
BURIAL SITE Waste Container Agent Nuc!! des (ft3)
(mCl)
(ft3)
(mC1) 05JUN85 HN RWA EB. DAW,SR LSA Cement pm-54 289.1 1913.45 289.1 1913.45 06JUW85 Tri-State RWA EB. DAW.SR LSA Cement Cr-51 400.1 2121.51 689.2 4034.96_
06JUN85 HN RWA EB. DAW LSA Cement co-60 300 2372.39 989.2 6407.35 07JUN85 HN RWA EB & SR LSA Cement co-58 277.5 2125.48 1266.7 8532.83 12JUW85 HM RWA EB & SR LSA Cement Fe-55 277.5 1847.13 1544.2 10379.96 13JUN85 Tri-State RWA EB. DAW SR LSA Cement 2n-65 396 2523.96 1904.2 12903.92 14JUN85 HN RWA EB DAW.SR LSA Cement Fe-59 300 2279.71 2240.2 15183.63 18JUN85 HN RWA EB. DAW.SR LSA Cement N1-63 300 1919.95 2540.2 17723.83 19JUN85 HN RWA EB. DAW.SR LSA Cement H-3 300 1982.51 2840.2 20564.03 20JUW85 Tri-State RWA EB. DAW.SR LSA Cement C-14 412.4 2190.69 3252.6 22754.72 2XJUW85 I:N RWA EB. DAW.SR LSA Cement Tc-99 300.7 2254.09 3553.3 25008.81 24JUW85 HN RWA EB & SR LSA Cement I-129 336 2251.02 3889.3 27259.83 26JUN85 HN RWA E3 & SR LSA Cement 336 2050.50 4225.3 29310.33 27JUW85 HN RWA EB. DAW.SR LSA Cement 300 2487.74 4525.3 31798.07 l
m
Table 2.0-1 (continued) i LRP il10-3 ATTACHMRNT A RWA - Richland. Washington Revision 2
.HSC - Barnwell. South Carolina Rite 9RT OF PAD]QACyy5_WASTg St#gWu_t1[
UNITS 1/2 August 6 1985 j
- Chem Nuclear Co.
16 ItN
- ll11taan Nuclear & Development Co.
LASALLE COUNTY NUCLRAR POWER STATION a
TSMT - Tri-State Motor Transit
__DIqtM HION OF MATERIAL TYPE Type Solidift-Principle Shipment Shipment volume Activity of of cation Volume Activity Per Month Per Month DATs TRANs co.
_sUnist SITR Weste Conta]Iler Agent wucIldes Ut3)
(acil
([D)
(sc1L,_
l EB.
2_JUI,_85 HN RVA Dla 6 Earth LSA Cement Mn-54 180 1999.5 180 1999.5 Es, SR.
I 9 JUL_85 llW RWA DAW LSA Cement Co-60 321 2069.3 501 4068.8 j
Jo JUtc85 HN RWA ItB & SR LSA Cement Fe-55_
180 2842.9 681 6911.7
-sB. SR.
i llEL 85 HN RWA D3W LSA Cement 2n-65 270 1386.4 951 8298.1 __
1
- 88. SR. DAW.
)$_JUL 85 HN RWA Qlak8a r_((L_j,SA Cemerit Co-58 285 2388.5 1226 10486.6 HB. SR.
16_JUL 65 IN PWA DAW LEA Cement Cr-51 2R9.I 1927.5 1525.1 12{ l_!L 19J t!L 85 IM RWA BB & SR LSA Cement Fe-52,_
180 3814.8 1705.1 16228.9 l
18_JUL 85 IN RWA cn & SR LSA Cement NI-63.
236.6 2057.7 1941.7 18286.6 f
22 JUL 85 IN RWA Rs & SR LSA Cemant H-3 180 2964.9 2121.7 21251.5 1
23 JUL 85 HN RWA RB & SR LSA Cement C-14_
244.1 2768.5 2365.8 24020 1
EB SR.
i 340.1 1938.6 2705.9 25958.6 24 jut. 85 IW RWA DAW LSA Cement 58 SR.
l 26 JUL 85 IW RWA Dlat. Barth LSA Cement 240 2693.4 2945.9 28652 l
29 JUL 85 IN RWA R8 & SR LSA Cement 218.2 4210.8 3194.1 32862.8 4
30 JUL 85 IW WWA E8 LSA Cemerit 180 2176.1 3314.I 35038.9 I
1 I
i l
I IV GfMFNT ID 0220h/03604
- - - ~.. -
Table 2.'0-1 (continued)
LPP-IIIO-3 ATTACllMRWT A RWA - Richland. Washington Revision 2 BSC - Barnwell. South Carolina REPolt? OF RADIOACEVE WASTE St#9tARY tMITS I/2 August 6, 1985 3
- Chem Nuclear Co.
16 j
ITN
- Illt taan Nuclear & Development Co.
LASALLE COUNTY NUCLEAR POWER STATION TSMT - Tri-State Motor Transit DISPOSITION OF MATERIAt.
Type Type Solidifi-Principle Shipment Shipment Volume Activity of of cation Volume Activity Per Month Per Month DATE TRANS CO.
BURIAL SITE waste container Agent Nuclides (ft3)
(mCl)
(ft3)
(mC1L_
l Diat.
l 2 ALU 85 HN RWA Batth LSA Cement
_ Mn-54 105 8614.2 105 8644.2 _
j BB.SR, 5 Atc 85 IIN RWA DAW LSA Cement Co-60__
180 12J8.0 285 10592.2 _
4 t
6 AtC 85 108 RWA Es & DAW LSA Cement Fe-55_
135 2617.2 420 13209.4 j
i EB, SR, 8 Atc 85 tw RWA DAW LSA Cemept
__ Zn-65_
291.2 1910.6 711.2 15120 Diat.
4 g
12_Atc 85 HN RWA Badh. SR LSA Cement Co-58 105 8732.2 816.2 23852.2__
Diat.
5 14 Atc 85 lof RWA EaGhMR I.SA Cement Cr-5 t __
105 5188.6 921.2 29040,8 Dlat Earth 15 AtC 85 HN RWA ER. DAW LSA Cement Fe-59 135 3104.5 1056.2 32145.3 19 AtC 85 IIN RWA E8 LSA Cement N1-63 105 2863.9 1161.2 33306.5 Es. SR, 21 AtC 85 foi RWA Dlat Earth LSA Cement H-3 105 3321.2 1266.2 34572.7 t
I 22 AtC 85 foi RWA EB LSA Cement C-14 180 2787.8 1446.2 36018.9 j
j 23Jt C_R5 IIN RWA EB & DAW LSA Cem_ent 210 1868.9 1716.2 37735.1 _
l 1
30 Atc 85 HN RWA BB & DAW LSA Cement 401.5 2545.2 2117.7 39852.8 _
I i
i i
I DOCUMENT ID 0220h/0360A i
Table 2.0-l'(continued)
IWA - Hlcliland. War.htngton ATTAdinHNT A LNP-Ill0 3 IMIC - Datenwell. South Caroline ERPORT OF_RAILIDARTtYE WASta Suretagy-Revision 2 tMITO I/2 August 6, 1985 CN
- Clice Nuclear Co.
IW
- Illt temate Nuclear & Development Co.
-LASALI.E COUNTY NUCLEAR. POWER STATION 16 1mr - Te l-St.ste tutor Tr ansit JISIMSIILON OF MATERI AL Type Type Solid!!!-
Principle Shipment shipment Volume Activity of of cation Volume Activity Per Month Per #$antti PATE TRANS Co.
BUR]AL SITE Weste Container
- f. gent Nuclides_
(ft3)
(mCl)
(It3)
(mCl ]__
3 SEP 85 IIN RWA E8 LSA Cement Mn-54 180 3226.38 180 3226. 3ff
_1_SFL85 IN RWA R8 & DAW l.SA Cement Cr-51 180 2916.88 360 6203 2f6, 88, Sil
_6_SFP_85 IfM RWA
& DAW 1,SA Cement Co-60 405.6 2203.28 756.6 8406.54
_?_UFILS$
ItN RWA EB & SR LSA Cement Co-58 105 5194.87 870.6 1360}jl_
f:
10__SFP_85 ItN RWA RD & DAW LSA Cement Fe-55 289 1 2141.50 l9.7 15742.91 2 Il_SFP 85 IN FWA EB LSA Cement In_65 180.0 3581.40 1339.7 17082dl_ 12_SHP 85 IN RWA RB & DAW LSA Cement Fe-59 180.0 2532.05 1519.7 19614 16_ } 3_SfiP 85 IN PWA RB & DAW t.SA rement Wl-63 381 2998.37 1900.7 22613,03_ 16 URP 85 IN RWA EB 1.SA Cement H-3 105 4158.34 2005.7 27311.37 ji Sl?P 85 IM RWA Es !.SA Cement C-14 180 3347.45 2185.7 30718.82_ BB, SR CAW, )SJ EP 85 IfN RWA DIAT EARTH LSA Cement Tc-99 270 2395.46 2455.7 33114.28_ 19_,SEP 85 104 PWA E8 & DAW LSA Cement 1-129 180 2433.27 2635.7 35749.98 EB, SR 20 SEP 85 Im RWA DAW LSA Cement 374.2 2235.10 3009.9 38759.88 Es, sa 23 S_l'P 85 let RWA DAW LSA Cement 105 3894.34 3114.9 41874.18 58, SR 24 SRP_85 ftw RWA DAW LSA Cement 180 2991.88 3294.9 4 4812 6ry_ teorMf'NT ID 0220li/0360A
l
- !lI'
{ h yt 8 5 9 2 9 5 t n) l ol vMC 2 7 6 7 m 8 0 8 1 i t r( 4 6 0 9 ce 7 1 4 7 AP 4 5 5 5 h 2 2 2 2 t 5 en 8 mo) 8 3 1 3 9 uM3 8 9 9 0 t 6 7 8 0 1 l 32 orf 3 3 3 4 Ve( 0 n6 P o l l it I ss - iu t y 2 2 5 4 P vg nt 6 7 9 6 R eu6 el) LRA1 mvl 9 4 9 0 piC 0 2 7 3 i t m 6 1 4 6 hc( 2 4 2 3 SA tnr 3 u e m )3 mt 3 5 5 5 pl t 9 0 0 0 i oI 3 1 1 1 hV( S N J O e R I l s A T p e 4 1 0 8 5 5 9 3 4 9 t A i d 5 5 6 5 5 6 5 6 3 1 9 2 T c i ~ i e t S n l n r o o e n e 1 H C n N ) d S i c M C C C F Z F N T 1 e R r u u .E E P N n T W S O i AA P t W n T 2R t o NE/A f n t t t t c EV1 E iot n n n n ( MI L din e e e e HT SC it e m m m m 1 CC TU l ag e e e e AA 1 N ocA C C C C TO m S 0 TI t Y AD T r 2 A N e R U n e O i l F C a A A A A S, S S S b O e t a E Pf n 1 L L L T T L Yoo R L T C H O A T P S R E_ A e R A R F L e t R SRE S Pf s S S Yoe f. T W ,W ,T BA BsA B ED BEI E D .oC E t L T n A I e I S m R p E L A A A A a o T A W W W W [ R P P R T. n l t R i ei -e l vs U no en F B or Da O ~ t a r gC .&T N A-n O 0 ihorr I 63 ht Cao T su et I O 0 a orl o S C / WSacM O h eu P S 0 .l Ne S N N M W N 2 dl c t I A H H H 2 I nl una D R 0 aeNat T w mS D. l I h mt - e cr etl iahir 5 5 5 5 T RpCHT 8 8 8 8 NE-P P P P M E E U E ]E S S C T E S O AC M T 1 0 D WSwMS M5 6 f RBrI T 2 2 2 3 , i:1 : j! a j1 1j1 {iliI 1i! j{1)Ia lI,.; t 1ili1l I4
- ij
Table 2.0-1 (continued) LRP-Ill0-3 ATTAOMENT A RV4 - Richland. Washington Revision 2 BSC - Bartwell. South Carolina REPORT Ol' RADIOA_GURVASTE SMRJ UNITS 1/2 August 6, 1985 CN - Chem Nuclear Co. HM - Hittman Nuclear & Development Co. LASALLE COUNTY NUCLEAR POWi!R STATION 16 TSMT - Tri-State 790 tor Transit DISPOS 1119N Ofr M_ATER181, _, Type Type Solldif!- Principle Shipment Shipment Volume Activity of of cation Volume Activity Per Month Per Month PSTE TRANS_CO. Syd nid llE Vas_le Conialner Agerit Jiuc_Meleg_ (ft)) (mCl) (ft3) (MCI L 1 0g[_85 IN RVA ftB LSA Cement Cr-51 180 3218.14 180 3218 14_ 2 I 2 OCT 85 IN RVA KB &_ PAW LSA Cement re-59 305.! 2352.05 565.1 5570 19 l 20.785 504 RVA gp t.SA Cemen,t Co-58 180 3067.33 745.1 8637.5L RB _3EB5 IN RVA DAW SR LSA Cement Co-60 297.3 2249.74 1042 4 1988 2_6_ 3 1 2 _4 OCT_8} IDi FvA SR LSA Cement Mn.-54 _ 195 6057.32 Ili!14 16944.58 LL%1 85 ffN EVA SR_& EB LSa Ceme.nt 2n-65 105 615 LO8 125J.4 23095 _$__0CT_QS ItN BSC FB LSA Cement H-3 180 3437.1 1432.4 26532.76 _9_0CT 85 HM RVA EB & SR LSA Ce:nent C-14 180 2732.73 1612.4 29265.49 10 OCT 85 HN RVA EB & DAW LSA Cement N1-63 135 2557.67 1747.4 31012.89 I LOCT_05 808 RVA SR LSA Cement re-55 10s 7366.79 1852.4 32865.29 14_0CT_05 IN PSC ES LSA Cement 180 3378.55 2032.4 34897.69 }} D1_QS 104 BSC FB LSA Cement 180 3219.61 2H2.4 37110.09_ ILOG_85 108 RVA EB & SR LSA Ceme_nt 105 ' 5012.82 2317.4 39427.49 10 OcT_85 IfM RV5 FB LSA Cement _ 135 2459.59 2452.4 41379.89 72 Or7 85 IN Run en LSA Ce,ent 105 2132.19 2557.4 44437.29 TWYWFNT 10 n270h/0160A
i I Table 2.0-1 (continued) 4 LRP-ll10-3 ATTACHMENT A I RWA - Richland Washington Revision 2 BSC - Barnwell. South Carolina R500!t? OF RADIOACTIVE _WAVIE SurmARY l IMITS 1/2 August 6. 1985 j CN - Chem Nuclear Co. 16 IM - Ilittaan Nuclear & Development Co. LASALLE (X)UNTY NUCLEAR POWER STATION } TSMT - Tri-State Motor Transit i I DISPOSIIJoW OF MATER _IAl m Type Type Solidiff-Principle Shipment Shipment Volume Activity of of cation Volume Activity Per Month Per Month 4 PATF TR5 NS __ CO. BURIAL SITE Waste Container Agent Nuc_Ildes (ft3) (mCl) (ft3) (mCl) Olly Raas i 22_OLT 85 TS7ff RWA DAW LSA Cement 769.8 823.24 332L2 45260.53 ] l 7)ET 85 IIN RWA EB LSA Cement 180 3590.85 3507.2' 48851.3R 1 24 OCT 85 194 RWA E8 LSA Cement 135 25'l5.83 3642.2 51427.2 L 1 25 OCT 85 IN RWA RB & SR LSA Cement 180 3841.46 3822.2 55268.67 l 3 Olly Rags, l N EB. SR j 29_OCT_85 llN RVA D}at. Earth LSA Cement 410.9 804.43 4233.1 56073.1 RB. 30 oCT 85 IIN RWA Dlat. EaLth LSA Ceme_nt 105 5671.83 4338.1 61744.93 }l OCT 85 led RWA EB LSA Cement 180 2747.64 4518.1 64492.53_ i i l 1 j i
Table 2.0-1 (continued) LRP-Ill0-3 ATTACIIMENT A RVA - Richland, Washington Revision 2 DSC - Barnwell, South Carallna EftPORT OF RADIOACTIVE WASTS strMMARJ UNITS 1/2 August 6, 1985 CN - chem Nuclear Co. IW - Illt tman Nuclear & Development CO. LASALLS COUNTY NUCLEAR POWER STATION 16 TSMT - Tri-State Notor Transit 4%~CdlI1ON OE_fBTERLAL TYPE Type Solldtft-Principle Shipment Chlpment Volume Activity of of cation Volume Activity Per Month Per Month PA_IE TBSNS_CO. BURIAL SIT 3 Vgs_le Cont _alner Mynt Nuclides_. (ft3) (mCl) (ft3) (mCl) 05_Nov_05 TSMT RVA DAV LSA pone Cr-5J_ 672 194.96 672 124 96_ 2 07 NOV 85 IN RVA BB 1.sA Ceraent Fe-59 135 'J 409J6 807 3601.52 EB, Diat 08 NOV B5 JN FV4 Katth LSA Cemer1L _ Co-58 102 4701.61 912 8 3 0 6. l 'i __ 12_NOV 85 IN PVA EB LSA Cement Co-60 100 3444.65 1092 11751.18 g IL Nov B5 IN RWA EB LSA Cement Mn-54 180 326 h08 1272 110}6 86_ 14 *Av 85 IN FWA En &
- R t.SA Cement 2n-65 10.5 521.4d0 1377 202][d6_
SR, EB 11p2L82 im RVA plat a a r t t _t.s A Cement H-3 105 76_01 82 1482 27836.98 t la_NaV_85 TSMT RVn oav tsA wee C-14 61L.5 92.76 2_099.5 21929.14 19_fKv_85 IN BSC EB LSA Cement _ N1-63 180 3663.65 221L 5 31593.39 20_Fev__65 IN BSC EB LSA Cement _ Pe-}5 180_. 3500.44 2459.5 35093.83_ j 2I Ncv 85 IN RVA gn LSA Cement 135 309C.13 259).5 3Rl91.96 SR. es, 2LNov 85 IN RVA Dlo t__ga tth_1.S A Cement 105 16544.10 2699.5 54736.06 Ceme_nt_ _ 180 3970.34 2879.5 58706.40_ 2'2_NO_V 85 IN BSC E3 LSA n 27__NOV_85 BSC EB LSA Cement 105 1922.74 2984.5 60629.14 PoilfMDFT ID 0220h/0360A - ~
.ipJi % 48 i Table 2.0-1 (c antinued) l 1 l RWS - Richland,. Washington ATTACHpmWT A LRP-Ill0-3 j HSC - Barnwell. South Carolina RgPORT OF RADIOAQUVB WASTE SUf91ARY Revision 2 CN - Chen Nuclear Co. UNITS 1/2 August 6, 1985 l liN - Illt tman Nuclear & Development Co. tASALLE COUNTY NUCLEAR POWER STATION 16 i TsMT - Tri-State notor Transit DISPOSITION OF MATERIAL Type Type Solidifi-Principle Shipment shipment volume Activity of of cation Volume Activity Per Month Per Month DATE TRANS CO. BURIAL SITE Waste Container Agent J elldes (ft3) (mCl) (ft3) (mCl) i j 02 DEC 85 l#8 RWA RB LSA Cement m-54 105 1822.10 105 1822.10 1 I
- 9) DEC 85 IIN RWA EB LSA Cement cr-51 180 3314.78 285 5136.88 Ot_Pgc 85 194 BSC Es LSA Cement Co-60 180 3321.60 465 8458.48 l
ss j = ll_QRC 85 198 RWA Dlat. Earth LSA Cement co-58 105 3083.54 570 !!542.02 e 2Leec 85 Tsnt RWA DAW Dor 1711 None Fe-55 634.5 251.24 1204.5 11793.26 Zn-65 Fe-59 i j N1-63 4 C-14 H-3 i l i 1 i A l i l 1 4 fn N 'WT in 0220h/03604
s cigure 3.1-1 Estimated Cumulative Gama Dose (mrem) ^ . ficm the LaSalle Station for the period July-December 19SJ. [/ 3__ / { Isopleth Labels Sma11 figure - multiply by 10-4 I L&ge figure - multiply 'hy 10 _, g / I , 10 pscs m {, nan, { 20 .m.e ] .w.....,.. / i ? 0 l tm 4-lg t / 'o s 25 j ?~ l A 80 / ci.. "~' ....r ' f ~,, y\\ 4 m .s J. w ' M ),. o v... so i / b Cr N..... ~ s o....
- e 5
SS N 4 s Y 50 O i 5 20,ne w__w_ M
Figure 3.1-2 3 Estimated Total Concentration (pCi/m ) of Noble Gases from the I-A Sn'LU Station F for the period January-December 1985. [y/ 25 1 Isopleth Labels / 40 Small figure - multiply by 10-2 25 i 5 Large figure - multiply by 10-2 kjg -) 1g 40 40 qwaver w.' L,..,.., m 15 15 C / 'L/ 9 ?- st -l 15 50 er o. 15 oftowo 73 S nec Riv t' M , 50 n Y q ,75 w C { g { t iro I W e... F Streo f 50 g 15 '~ ir Dwight 15 f Q es - 51 0 5 10 15 20 ms
.~ Figure 3,1-3 3 g/[, Estimated Tota,1 Concentration (pCi/m ) of Iodine from the LaSalle Station for the period January-December 1985. ._ fl g Isop!eth labels p/ U5 Small t igure - multiply by 10-4 Large figure'- multiply by 10-4 f__ * ~.1 5 u*aaw"""4 35 "~ 7.. Y ~ / x J ud e r- / / N u ..e 79. M\\, / / Ottowo - worris Mor,,,tte id}[ \\ s 5 n.-. 3.5 eo er /1^, /...... 2.5 (ff" x s / /h Q 25 g,$ Od e!I as - 52 O s 80 15 2Ow www-e W
Figure 3.1-4 Estimated Total Concentration (pCi/m3) of Particulate Matter from the LaSalle Station / / for the period January-December 1985. / / ,) Isopleth Labels s 3 1 ( 2,5 Small figure - multiply by 10 4 hEl - \\ f Large figure - multiply by 10-m,, w maxwa g3 Y .....,N Q... ...i,., a.,........ 1 )/ L/ O e 2 riu i i j ) in s 25 / 80 50 R,
- f l
M rse,tres siino.. I 50 ( ) L-L
- ,.... v f
j 25 c; ,o to er 'l 10 fare or 1Z5 Dwight 55 a.g Odell as - 53 O S 10 15 20mi ww ^a
Table 3.1-1 LASALLE UNIT ONE/TWO MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 1/ 1/85 TO 12/31/85 CALCULATED 02/21/86 IST 2ND 3RD 4TH ANNUAL TYPE QUARTER QUARTER QUARTER GUARTER 1/85-3/85 4/85-6/85 7/85-9/85 10/85-12/85 OAMMA AIR 1 42E-03 1.78E-04 3.39E-03 5.06E-05 5.05E-03 (MRAD) (ESE ) (ESE ) (ESE ) (ESE ) (ESE ) BETA AIR 1 43E-04 2.19E-05 2.29E-04 2 71E-05 4.21E-04 (MRAD) (E ) (E ) (E ) (E ) (E ) TOT. BODY 7.73E-04 9.34E-05 2 00E-03 2.17E-05 2.89E-03 (MREH) (ESE ) (ESE ) (ESE ) (ESE ) (ESE ) SKIN 1.21E-03 1.55E-04 2.79E-03 5.36E-05 4.21E-03 (MREM) (ESE ) (ESE ) (ESE ) (ESE ) (ESE ) ORGAN 1.99E-04 5.53E-03 1.22E-02 1.90E-03 1.99E-02 (MREM) (E ) (E ) (E ) (E ) (E ) THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 1985 COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
OTRLY iST GTR 2ND OTR 3RD OTR 4TH OTR YRLY % OF OBJ 1/05-4/85-7/85-10/85-DBJ APP.3 3/85 6/85 9/85 12/85 OAMMA AIR (MRAD) 50 0.03 0.00 0.07 0.00 10.0 0.05 DETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 VOT. BODY (MREM) 2.5 0.03 0.00 0.08 0.00 5.0 0.06 . SKIN (MREM) 75 0.02 0.00 0.04 0.00 15 0 0.03 ORGAN (MREM) 7.5 0.00 0.07 0.16 0.03 15 0 0.13 THYRDID THYROID THYROID THYROID THYROI! RESULTS BASED UPON ODCM REVISION 11 UPDATE DM003 FEBRUARY 1986 l' i 54
t Table 3.2-1 L AS ALLE UNIT ONE / 7'd* MAXIMUM DOSES thREM) RESULTING FROM LIQUID EFFLUENTS FERIOD OF RELEAEE - 1/ 1/05 TO 12/31/85 CALCULATED 02/21/86 1ST 2ND 3RD 4TH ANNUAL DOSE TYPE QUARTER QUARTER QUARTER QUARTER 1/85-3/85 4/85-6/85 7/85-9/85 10/85-12/85 TOTAL 8.41E-06 1.21E-06 4 11E-06 0.00E-01 1.37E-05 BODY INTERNAL 1.76E-04 5.07E-06 3.62E-05 0.00E-01 1.78E-04 ORGAN BONE GI-LLI GI-LLI BONE
- THIS IS A REPORT FOR THE CALENDAR YEAR 1985 COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I. --------------
QTRLY iST OTR 2ND OTR 3RD OTR 4TH GTR YRLY Z OF OBJ 1/85-4/85-7/85-10/85-OBJ APP.I 3/85 6/85 9/85 12/85 TOTAL PODY (MREM) 1.5 0.00 0.00 0.00 00.00 3.0 0.00 CRIT. ORGAN (MREM) 50 0.00 0.00 0.00 00 00 10.0 0.00 BONE GI-LLI GI-LLI BONE RESULTS BASED UPON ODCM REVISION 11 UPDATE DM003 FEBRUARY 1984 55 4
Figure 5.0-1 2 > Ottawa 7: *S M.I - o14 " 0 I Marseilles South 's y Ottawa 8, ~ Seneca i 7 2,5., 2,.., 20,., m., . m., 215-2 21.&.2 201 2 202 2 20g2 y i;t2: 1 2 i;11 : 3 e * -2 pi r ,n, 6e e5
- a. m. i 212-2 I
205 2 e13 Site Property j . m -< b' Grand Ridge "$}}'-2 a2*2 Verona
- t i o.,
2io 2 in:; IiM:1
- 2C4-1 20s 2 Kinsman 11eRansom e12 Kernan Streator
~ e Grundy La Selle County County ~ Livingston County i } 3 5 mm., LA S ALLE COUNTY ST ATION t b d 0 2 6 s 10 Kuometere FIXE 0 AIR SAMPLING SITES AND OUTER ,i RING TLD LOCATIONS O'e's'- x, 56
Figure 5.0-2 L ts. L 17 _l-80 Ottaws e Marseilles U S.6 3, Illin ;, o "L 2s Seneca p Ln go L-23 L.3s e e L 29 L 32
- g. g L2
. L-11 L 21 Rt.23 7 . t is eLJ3 L 34l 3 3 * ' LS* J 6 Station Rt.170 e Ransom L 3o. o 1 2 3 s uu LA SALLE COUNTY STATION n 2 s s , o x n.... INGESTION AND WATERBORNE EXP05UR$ PATHWAY SAMPLE LOCATIONS m.3 co-es-we 57
Figure 5.0-3 \\ / ""i fA l \\ N N. 22 " St. ,1012 1st$ fos-1 a i14 3 \\ Weste Stabiltaation Pond v yg = imi \\ II' :' s J I 11 s x
- li':1 as A Grand Ridge Rd. I oI.
1118-1 , [10-1 , Joe 1 \\ 107-115 1 "stis 2 111 A 2 110-2 tos 2 107 1 o o. o.4 o.s as 1.o asu a-e o.4 a.: 1.2 1.s 2.o zu r. I i LA S ALLE COUNTY ST ATION l INNER RING TLD LOCATIONS Us'-as
IAtiLE 5.0-1 LA SALLE STATION ENVIRONMENTAL RADIOLOGICAL MONITORING SAMPLING $1TES U 5 t u t E m ~ = 0 I h X i Location Location E h h 5 3 2 h 5 5 l-a Code -Type Location E d O O 5 C.5 E 2 & 3 3 2 I l L-01 Nearsite No. 1 X X L-02 Onsite No. 2 X X L-03 Onsite No. 3 I I L-04 hearsite No. 4 I X L-05 Onsite No. 5 I X L-06 Nearsite No. 6 I X L-07 Seneca X X L-08 Marseilles X I L-09 C-Grand Ridge X X L-10 C Streator I X L-Il Ranson X I L-12 C Kernan X I L-13 Route 6 at Gonnam Road X I L-14 C Ottawa X X L-15 Granby Fara X X X X X L-16 Lowery Dairy I X X X X L-17 C Norsen Dairy X X X X X L-18 C Sunnylsle Fara X X X X X L-19 Illinois River at Marsellies I L-20 Illinois River at Ottawa I L-21 C Illinois River at Seneca I L-22 South Kickapoo Creek X L-23 Illinois River at Katser Corporation I L-24 LSCS Cooling Lake near Recreation Area X X X i L-25 C L5CS Intake Pipe / River X L-26 LSC5 Olscharge Pipe / River X L-27 L5CS Onsite hell X L-28 Marseilles Well Water I L-29 C Seneca well Water X t L-30 Ranson Well Water X L-31 Ottawa Well Water X L-32 Illinois State Park I L-33 C Ast Upstreas of Cooling Lake inlet X Structure L-34 Just Downstream of Cooling Lake X X l Discharge Structure i l L-35 Marsettles Pool of Illinois River X L-36 Fara A - Vegetables X L-37 Fars 8 - Vegetables I
- Control (backgrouno) locations are indicated by a C in tnis column. All other locations are inoicators.
l l t l l l 59
Table 5.0-2 LA SALLE COUNTY STATION ENVIRONMENTAL RADIOLOGIAL MONITORING PROGRAM, SAMPLING LOCATIONS 1. AIR SAMPLERS Distance Direction Site Code Location (miles) (*) L-01 a. Near-site No. 1 0.5 326 L-02 b. On-site Station No. 2 0.6 11 L-03 c. On-site Station No. 3 0.2 56 L-04 d. Near-site No. 4 1.5 90 L-05 e. On-site Station No. 5 0.3 145 L f. Near-site No. 6 0.4 270 L-07 g. Seneca 5.2 18 L-08 h. Marseilles 7.0 326 L-09 (C) 1. Grand Ridge 10.4 260 L-10 (C)
- j. Streator 13.5 220 L-11~
k. Ransom 6.0 191-L-12(C) 1. Kernan 5.0 214 'L-13 m. Route 6 at Gonnam Road 7.0 100 L-14 (C) n. Ottawa 12.0 315 1 2. TLDs a. Same as No. 1. b. Special TLD Samplers Distance Direction Revised Site Codeb Previous Site Code (miles) (*) L-101 1,2 None 0.5 359 L-102 1,2 None 0.6 17 L-103 1,2 None 0.7 46 L-105 1,2 None 0.7 91 L-106 1,2 None 1.4 110 L-107 1,2 None 0.8 128 L-109 1,2 L-107 1,2 0.6 178 L-110 1,2 L-108 1,2 0.6 205 L-111a 1,2 L-109 1,2 0.7 217 L-111b'1,2 L-110 1,2 0.8 230 L-112 1,2 L-111 1,2 0.9 244 8' Control (reference) locations are denoted by a "C" af ter site code. All other locations are indicators, b Effective July 1, 1985. i 60 l m-
9 Table 5.0-2 (continued) LA SALLE COUNTY STATION ENVIRONMENTAL RADIOLOGIAL MONITORING PROGRAM, SAMPLING LOCATIONS 2. TLDs P b. Special TLD Samplers (continued) Distance Ofrection Revised Site Codeb Previous Site Code (miles) (*) L-113a 1,2 L-ll2 1,2 0.8 262 L-113b 1,2 L-113 1,2 0.8 273 L-114 1,2 Same 0.9 288 L-201 1,2 Same 2.0 15 L-202 1,2 Same 2.3 33 L-203 1,2 Same 4.0 56 L-204 1,2 Same 3.5 78 L-205 1,2-Same 3.5 102 L-206 1,2 Same 4.3 123 L-207 1,2 Same 4.5 146 L-208 1,2 Same 4.5 170 L-209 1,2 Same 4.0 192 L-210 1,2 Same 3.3 216 L-211 1,2 Same 4.5 240 L-212 1,2 Same 4.0 261 L-213 1,2 Same 3.8 2 83 L-214 1,2 Same 2.0 303 L-215 -1,2 Same 2.0 330 L-216 1,2 Same 1.5 350 3. MILK Distance Direction Site Codea Location (miles) (*) L-15 a. Granby Farm 7.0 85 L-16 b. Lowery Dairy 8.2 120 L-17 (C) c. Norsen Dairy 9.0 350 L-18 (C) d. Sunnyisle Farm 13.2 25 Control (reference) locations are denoted by a "C" after site code. All ) a other locations are indicators. b Effective July 1, 1985. 61
Table 5.0-2 (continued) LA SALLE COUNTY STATION ENVIRONMENTAL RADIOLOGIAL MONITORING PROGRAM, SAMPLING LOCATIONS 4. PRECIPITATION Same as No. 3. 5. VEGETABLES Distance Direction Site Codea Location (miles) (*) L-36 a. Farm A L-37 b. Farm 8 6. CATTLE FEED AND GRASS Same as No. 3. 7. WELL WATER Distance Direction Site Codea Location (miles) (*) L-27 a. LSCS On-site Well At station L-28
- b. -Marseilles Well 7.0 326 L-29 (C) c.
Seneca Well 5.1 18 L-30 d. Ranson Well 6.0 191 L-31 e. Ottawa Well 12.8 304 L-32 f. Illinois State Park 6.5 326 8. SURFACE WATER Dist ance Direction Site Codea Location (miles) (*) L-19 a. Illinois River at 6.5 326 Marseilles L-20 b. Illinois River at 6.5 304 Ottawa Control (reference) locations are denoted by a "C" after site code. All a other locations are indicators. 62 i ~.
4 ( Table 5.0-2 (continued) LA SALLE COUNTY STATION r ENVIRONMENTAL RADIOLOGIAL MONITORING PROGRAM, SAMPLING' LOCATIONS
- 8. ' SURFACE WATER (continued)
Distance Direction i Site Codea Location (miles) (*) i L-21 (C) c. Illinois River at 4.0 22 Seneca L-22 d. South Kickapoo Creek
- 4. 7 352 L-23 e.
Kaiser Corporation 5.3 337 L-24 f. LSCS Cooling Lake 0.3 112 near Recreation Area 9. COOLING WATER Distance Direction .) Site Codea Location (miles) (*) l L-25 (C) a. LSCS Intake Pipe / 4.8 3 River L-26 b. LSCS Discharge Pipe /
- 4. 8 1
River
- 10. FISH Distance Direction 4
Site Codea Location (miles) (*) L-24 a. LSCS Cooling Lake
- 0. 3 112 b.
Marseilles Pool or 6.5 326 L-35 Illinois River 11. BOTTOM SEDIMENTS Distance Direction Site Codea Location (miles) (*) L-24 a. LSCS Cooling Lake
- 0. 3 112 L-34 b.
Just downstream of At Station i i cooling lake discharge structure L-35 c. Marseilles Pool 6.5 326 Control (reference) locations are denoted by a "C" af ter site code. All a other locations are indicators. 63 r m.v ,.,.w-- ,m ,,.--.e --7 e. 4 r-n y,.--. -~ p
._= Tabla 5.0-2 (continued) LA SALLE COUNTY STATION ENVIR044 ENTAL RADIOLOGICAL MONiiORING PHOGRM, SAMPLE COLLECil0N AND ANALYSE $ - Location Collection Type of frequency Sag le Meola coded site Frequency Analysis of Analysis Remarks 1. Airborne a. Onsite and Near Field Continuous Gross beta ndeekly th all samles. Particulates operation Gaassa Isot @arterly th quarterly composites f rom each location. L-1 Nearsite No. I for a week Sr-89. -90 @arterly on quarterly cogosites f rom eacn location. L-2 Onsite No. 2 L-3 Onsite NJ. 3 Non-routine Reporting levelsh L-4 Nearsite No. 4 L-5 mstte No. 5 Cs-13410. C5-137 20 pCl/m3 L-6 Nearsite No. 6 b. Far Field Same as la. Same as la. Same as la. Same as la. Same as 14. L-7 Seneca L-8 Marseille L-9 (C) Crand Ridge L-10 (C) Streator cn L-Il Ransom L-12(C) Kernan L-13 Route 6 at Gonnas Rd. L-14 (C) Ottawa 2. At r borne Same as 1. Weekly 1-131 ndeek ly (h all sagles. lodine Nom-routine keporting level 0.9 pCl/m3 3. ILD Same as 1. @arterly Gamma @arterly Two sets at all AP locations. trie set read quarterly. Second set read if required L-101-1.2 through Inner Ririg by Consson=ealth Edison. At otner loca-103-1.2 tions, all sets read quarterly. Minimum 105-1.2 through of two TLDs per set. 110-1,2 tila-l.2 Illb -1. 2 112 113a -1.2 11 1-1,2 114 L-201-1.2 through (bter Ring 216-1.2
- Control (ref erence) locations are denoted by a "C" in this column. All other locations are indicators.
b Average concentration over calendar quarter.
Table 5.0-2 (continued) LA SALLE COUNTY STATION ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM, SAMPLE COLLECTION AND ANALYSE 5 Location Collection Type of Frequency Sam le Media code
- Site Frequency Analysis of An alys t s Remarks 4.
Milk L-15 Granby Farm Weekly: 1-131 Weekly On all samles. LLu: 0.5 pLi/1. L-16 Lowery Dairy May through Gama Isot. Montnly 01 monthly comosttes. L-17 (C) Norsen Dairy October Sr-89 -90 Monthly On monthly comosites. L-18 (C) Sunnyisle Farm Motthly: 1-131 Monthly 01 all samles. LLD.
- 0. 5 p Ci /1.
November Gama Isot Monthly On all samles. tnrough Sr-89,-90 Monthly On all sam les. @rtl Ncn-routine Heporting levelsD I-131 3; Cs-134 bO; Cs-137 /J; Ba-La-140 300 pct /l m 5 Prec tp t t a tion Same as 4. Monthly Gross beta Monthly 01 all samles. Gamma Isot 4arterly. On quarterly composites f rom eacn location. Tritium Wartrer ly On quarterly composites f rom eacn location. Sr-89,90 42arterly On quarterly comosttes f rom eacn location. 6. Vegetables L-36 Farm A Annually at Gross beta Annually Four vartettes (at least one green leaf y L-37 Farm 8 narvest Gama Isot Annually vegetable) f rom eacn location as availaole Sr-89,-90 Annually at harvest. (1-131 on green leaf y vege-tables. 7. Cattle feed Same as 4. @arterly Gross beta 4arterly Cattle f eed: w6nter. Gamma Isot 4arterly Gr ass : summer. and Grass Sr-89 -90 Warterly. b. well Water, L-28 Marseilles Well @arterly Gross beta Warterly On all sa mles. Of f site L-29 (C) Seneca well Gamma Isot 4arterly L-30 Hansom Well Tritium 4arterly Ottawa Well Sr-89, 90 Warterly L-31 L-32 111:nois State Park well
- Lontrol (ref erence) locations are denoted by a "C" in this column. All other locations are indicators.
Average concentration over calendar quarter.
Tabla 5.0 2 (continutd) LA SALLE COUNTY STATION ENv!RONMENTAL RADIOLOGICAL MONITORING PROGRM. SAMPLE COLLECTION AND ANALYSES Location Collection Type of frequency Sam le Media Coded 51te Frequency Analys15 of MalysIs Remarks 9. Well Water. L-27 LSC5 m stte Well-Monthly Gross beta Monthly Onsite Gamma isot Qaarterly On quarterly composite. Tritium 02arterly On quarterly composite. Sr-89.-90 Ojarterly W quarterly composite.
- 10. Surf ace Water L-19 Illinois River at Weekly Gross beta Weekly W all samples.
L-20 Marseilles Gamma Isot Pbothly m monthly compusttes from each location. L-21 (C) 111. River at Ottawa Trittum 0;srterly & quarterly composites f run each location. L-22 South Kickapoo Creek Sr-89.-90 02arterly (m quarterly cogosites f rom each location. L-23 III. River at Intake Non-routine Meporting levelsD to Kaiser Corporation L-24 LSCS Cooling Lake near recreation area (See f ootnote "c.')
- 11. Cooling hater L-25 (C)
LSC5 intake pipe / .ieek ly Gross beta Weekly On all sam les. river Gama 150t Monthly W monthly cowosites f rom eacn location. g L-26 LSCS discharge pipe / Trittum Monthly f.m monthly cowosttes f rom eacn location. river Sr-89.-90 Monthly W monthly composites f rom eacn location. 12. Fish L-44 L5CS Cooling Lake Three times Gross beta Three times & edible porttons only. T.o spectes, a year a year. L-35 Marsettles Pool Gamma Isot Three times tm edible portions only. T.o species. a ye ar. Sr-89.-90 Three times tm ectele portions only. T o species. a year Non-routtne Weporting tevelsb 4 4 4 Mn-54 310 ; Fe-59 la10 ; Co-58 3a10 )- 4 4 Co-60 la10 Zn-% 2s 10 ; Cs-134 la10 ; Cs-137 2x105 plt /k g wet weight. 13. Bottom L-24 LSCS cooling lake inree times Gross beta inree times Sediments L-33 (C) tpstream of cooling a year, if a year late available Ganssa Isot inree times L-34 Downstream of a year cooling take
- Control (ref erence) locations are denoted by a *C" in this column. All other locations are indicators.
Average concentration over calendar quarter. 2 2 2 2 2 2 pe,fi, 10. Co-581:10. Co-60 3:10, In-65 310 Zr-695 4x10,1-1312. Cs-134 30. (s-137 50. da-La-140 2:10 ' H-3 2 10. Mn-54 1:10. Fe-59 4: 4 3
__m.. a a
- )
1 \\ Table 5.0-2 (continued) 4 i LA SALLE COUNTY STATION ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRM,' SMPLE COLLECTION AND ANALYSES Location Coflection Type of. Frequency Sanple Media Code site Frequency Analysts of Analysts Remarks ] a. Enumeration by a door. Annually During grazirig season, i
- 14. Detry Census a.
Site boundary to 2 miles j to-door or equivalent j ~ counting technique, i b. Enumeration by using Annually Ouring grazing season, b. 2 miles to 5 miles referenced inf ormation. i from county agricultural' j agents or other reliable sources. c. Inquire as to feeding Annually Artng grazing season. 5 c. At datries listed in Item 4. l practices: i i (1) Pasture only. i Q (2) Feed and chop only. (3) Pasture and feed; if both, ask farmer to estimate fraction of food from pasture: .<255, 25-505, 50-755, ) or >755. l
- 15. Nearest In all 16 sectors Annually Residence Census l
i-j 2 I w w e c-,w -ms 01m T
_... _ _ ~. - _ _ -. ....e m .w _...,a__ Tabis 5.0-3 ENVIRONMENTAL RADIOLOGICAL MONITG !NG PROGRAM yuARTERLY Sute%RY Name of facility LaSalle Nuclear Power Station Docket ho. 50-254, 50-265 Location of Factitty Marsellies. Illinois Reporting Period 1st Quarter 1985 (County, State) Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Number of i Type Nuater of Mean4 Mean Meana Non-routine (Units) Analyses LLD Range Location
- .ange Range Results Gross Beta 180 0.01 0.025 (127 % O)
L-09 Grand Ridge 0.029 (13/13) 0.028 (52/52) 0 .l AirPartjtulates (pC1/s ) (0.007-0.055) 10.4 at 9 260* (0.015-0.085) (0.012-0.085) Ganma Spec. 14 0.01 <LLD (LLD 0 i (LLD 0 Sr-89 14 0.01 (LLD f (LLO O Sr-90 14 0.01 (LLD ,(LLD 0 Airborne lodtne 1-131 180 0.10 (LLD (pct /m3) cn Ganssa Background Ganssa Dose 14 3.0 13.9 (10/10) L-04, Near-Site v4, 16.7 (1/l) 10.7 (4/4) u CD (TLDs)(mR/Qtr.) (10.5-16.7) 1.5 ml 9 90' (10.2-12.0) <LLO O Milk I-131 12 0.5 <LLD (pC1/1) Ganesa Spec. 12 <LLD 0 Cs-134 5 (LLO (LLD 0 C5-137 5 <tLD <LLD 0 Other Ganssas 10 (LLD (LLD 0 l Sr-89 12 10 <LLD (LLD 0 Sr-90 12 2 (LLD Precipitation Gross Beta 12 15.yb (LLD L-18. Sunnytste 33.2 ((1/3) 33.2 (1/6) 0 Dalry, 13.2 at W 25* <tLD 0 Gansna Spec. 4 20 <LLD (LLO O Tritium 4 200 (LLD (LLD 0 Sr-89 4 10 (LLD <LLU 0 Sr-90 4 2 (LLO
m n... 1 . 1 Table 5.0-3 (continued) j ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM QUAATERLY SUPDMRY Name of Facility LaSalle Nuclear Power Station Docket No. 50-254. 50-265-Location of Facility Marseilles. Illinois Reporting Period 1st Quarter 1985 (County, State). Indicator Location with Highest Control Sample Type and Locations Quarterly Mean . Locations Number of j Type Numoer of Meane Mean Mean8 Non-routine (Units) Analyses LLD Range Location Range Range Results 4 Cooling Water Gross Beta 26 2.0 6.4 (13/13) L-26, LSCS Discharge 6.4 (13/13) 3.6 (13/13) 0 (pCl/l) (3.8-8.2) Pipe - River at (3.8-8.2) (2.8-4.3) Station i Gama Spec. 6 Cs-134 10 <tLD (LLD 0 Cs-131 10 <LLD (LLD 0 g Other Gamas 20 <L LD (LLD 0 1 Tritium 6 200 (LLD (LLu O l Sr-89 6 10 ' LLO <LLD 0 i Sr-90 6 2 (LLD (LLD 0 Surf ace Water Gross Beta 78 2.2 4.9 (64/65) L-24. LSCS Cooling 5.7 (13/13) 5.2 (12/13) 0 (pCi/1) (2.4-7.7) Lake near Recreation ( 4. 4-7. 7) (2. 8-7. 6 ) Area. 0.3 mi y 112* Gama Spec, 18 i Cs-134 10 (LLD (LLD-0 Cs-137 10 <LLD (LLD 0 l Other Gamas 20 (LLD <tLD 0 Tritlum 6 200 (LLD <LLD 0 Sr-89 6 10 (LLD (LLD U Sr-90 6 2 <LLD <tLD 0 ..m
Tabis 5.0-3 (continuId) ,i. ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM QUARTERLY SUMMARf j j Name of Facility ' LaSalle Nuclear Power Station Docket No. 50-254, 50-265 l Location of Facility Marsettles. Illinois Reporting Period 1st Qua ter 1985 .(County, State) Indicator Location with Highest Control l Sample Type and Locations Quarterly Mean Locations Nun 6er of 1 Type Number of Meana Miran Meana Non-rout ine j (Units) Analyses LLD Range Location R ange ' Range Results 1 i Well Water Gross Beta 8 2.0 22.2 (7/7) L-32, Illinois State 31.4 (1/1) 18.1 (1/1) 0 (pci/1) (12.8-31.4) Park, 6.6 al 8 326* Gama Spec. 6 C5-134 10 <tLD (LLD 0 l Cs-137 10 <tLD <LLD 0 <LLD 0 Other Games 20 (LLD 5 Tritium 6 200 (LLD <LLD '0 (LLD 0 Sr-89 6 10 (LLD <LLD 0 l Sr-90 6 2 <LLD t Cattlefeed & Grass Gross Beta 11 1.0 9.7 (6/6) L-18, Sunny Isle Fars 13.2 (2/2) 11.6 (5/5) 0 (pC1/g wet) ( 3. 9-20.0) 13.2 mi 9 25' (6.1-20.2) (3.2-24.2) Gama Spec. ' 11 (LLD 0 i Cs-134 0.1 <tLD <LLO O Cs-131 0.1 (LLD Other Gewas 0.2 (LLD <LLD 0 l Sr-89. 11 1.0 (LLD (LLD 0 (LLO O Sr-90 11 [ 1.0 (LLD j o
- Mean and range based on detectable measurements only. Fraction Indicated in parenthesis.
LLO value dependent on volume of sample available for analysts. 4 i i l 1 1
Vable 5.0-4 ENVIRONMENTAL RADIOLOGICAL MON!TORING PROGRAM QUARTERLY SLMPARY Name of Facility LaSalle Nuclear Power Station Docket No. 50-254. 50-;'65 Location of f acility Marseilles. Illinois Reporting Period 2nd Quarter 1985 (County, State) Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Nuenber of Type Number of Meana Mean Meana hon-routine (Units) Analyses LLD Range Location Range Range Results Air Particulates Gross Beta 182 0.01 0.020 (129/130) L-02, Onstte #2 0.022 (13/13) 0.020 (52/52) 0 (pCl/m3) (0.013-0.031) 0.6 at 9 11* (0.017-0.030) (0.012-0.027) Gama Spec. 14 0.01 (LLD (LLD 0 Sr-89 14 0.01 (LL D <LLD 0 Sr-90 14 0.01 <t LD (LLD 0 Airborne lodine I-131 182 0.10 <tLD <'.I D 0 (pC1/m3) y Gama Background Gama Dose 14 3.0 12.4 (9/10) L-01, Near-Site #1, 13.6 (1/1) 12.8 (4/4) 0 l (11.4-13.6) 0.5 mt 9 326' (12.0-13.2) L-13, Rt. 6/cranna', 13.6 (1/1) Road. 7.0 ml 9 1 0* Pilk 1-131 40 0.5 (LLD (LLD 0 (pct /1) Gamma Spec. 40 Cs-134 5 (LLD <tLD 0 C5-137 5 (LLD <LLD 0 t I Other Gammas 10 (LLD (LLD 0 Sr-89 12 10 (LLO (LLD 0 Sr-90 12 2 2.0 (1/6) L-18, Sunnytsle Dairy 2.4 (1/3) 2.4 (1/6) 0 13.2 mt 9 25* Precipitation cross Beta 10 l12.0b 55.0 (3/6) L-16. Lowery Dairy 69.2 (2/J) 30.6 (5/6) 0 [ (26.8-96.0) 8.2 ml 9 120' (42.3-96.0) (17.5-43.0) Gama Spec. 4 I 20 <LLD (LLD 0 Tritium 4 '200 <tLD (LLD 0 Sr-89 4 10 (LLD <LLD 0 Sr-90 4 2 (LLD <LLD 0
1 Tabla 5.0 4 (continu:d) ENVIRONMENTAL RADIOLOGICAL MON!TORING PROGRAM (JUARTERLY SUMMANY Nane of Facility LaSalle Nuclear Power Station Docket No. 50-254.'50-265 i Location of Facility Marseilles. Illinois Reporting Period 2nd Quarter 1985 (County, State) Indicator Location with Highest ' Control Sample Type and Locations Quarterly Mean Locations Nunter of Type Number of Meana Mean Mean8 hon-routine (Units) Analyses LLD Range Location Range Range Results
- l j
Cooling Water Gross Beta 26 1.0 '6.5 (13/13) L-26 LSC5 Discharge 6.5 (13/11) 3.5 (13/13) 0 J (pCi/1) (1.0-20.0) Pipe - River at - (1.0-20.0) (1.4-7.2) ~, Station 4.8 at 9 l' Gansna Spec. 6 (LLD 0 Cs-134 10 <LLD (LLD 0 i C5-137 10 <LLD 9 (LLD 0 j Other Ganenas 20 <LLD Tritium 6 200 (LLD L-25, LSCS frGae Pipe 220 (1/3) 220 (1/3) 0 4 - River at Station y N 4.8 at 9 3* <LLO O Sr-89 6 10 (LLD Sr-90 6 2 2.2 (1/3) L-26, LSCS Olscharge -2.2 (1/3) (LLD 0 Pipe - River at Sta-tion, 4.8 ml 9 l' Surf ace Water Gross seta 78 2.0 4.7 (64/65) L-19. Illinois River 5.2 (13/13) 4.9 (12/13) 0 } (pct /I) (2.9-6.8) at Marseilles (4.1-6.2) (3.4-7.8) 6.5 at 9 326* L-24, LSCS Cooling 5.2 (13/13) Lake near Recreation (3.4-6.8) Area. 0.3 et 9112' Gansna Spec. 18 4 <LLD 0 Cs-134 10 (LLO i Cs-137 10 <tLD (LLD 0 f Other Gansnas 20 (LLD (LLO O Tritium 6 200 220 (1/5) L-24 LSC5 Cooling 2.0 (1/1) (LLD 0 Lake near Recreation Area, 0.3 at 9 112* Sr-89 6 10 <tLD (LLU U T Sr-90 6 2 (LLD (LLD u
Tabig 5.0-4 (continued) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM QUARTERLY SumARY Name of f acility LaSalle Nuclear Power Station Docket No. 50-254, 50-265 Location of Facility Marseilles. Illinois Reporting Period 2nd Quarter 1985 (County. State) Indicatc-Location with Highest Control Samole Type and Locations Quarterly Mean Locations Neter :f Type Number of Meana Mean f4e en8 Non-r c at t r.e (Units) Analyses LLD Range Location Range Range Results well water Gross Beta 8 2.0 21.4 (7/7) L-32. Illinois State 28.6 (1/l) 15.1 (1/1) 0 (pC1/1) (14.3-28.6) Park Well 6.5 ml 9 326* Gama Spec. 6 Cs-134 10 <LLD <LLD 0 C5-137 10 <tLD <tLD 0 Other Gammas 20 <tLD <LLD 0 ] Tritium 6 200 (LLD <LLD 0 i Sr-89 6 10 <LLD <LLD 0 Sr-90 6 2 (LLD <LLD 0 Fish Gross Beta 5 1.0 2.6 (5/5) L-35. Marsellies Pool 3.6 (2/2) None 0 (pct /g wet) (1.2-3.9) of 111tnots River ( 3.3-3.9 ) 6.5 ml 9 326' Gamma Spec. 5 l Cs-134 0.1 <LLO None 0 l C5 137 0.1 (LLD None 0 Otner Gamas 0.2 -(LLD None 0 $r-89 13 1.0 (LLD None 0 Sr-90 13 1.0 <tLD None 0
.. ~... _ b-Table 5.0-4 (continued) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM QUARTERLY SUMP %RY Name of Facility LaSalle Nuclear Power Station Docket No. 50-254. 50-265 Location of Facility Marsettles, ilitnots Reporting period 2nd Quarter 1985 (County, State) + ) Indicator Location with Highest Control. i Sample Type and Locations Quarterly Mean Locations Number of, Type humber of Meana Mean Meana Non-routine (Units) Analyses LLD Range Loc ation R ange Range-Results Cattlefeed & Grass Gross Beta 4 1.0 13.3 (2/2) L-15, Granby Farm 18.1 (1/l) 9.9 (2/2) 0 (pct /g wet) (8.5-18.1) 1.0 ml 9 85* (8.2-11.6) <LLD 0 Cs-134 0.1 <LLD Cs-137 0.1 (LLD <LLD 0 i (LLD 0 Other Gammas 0.2 <tLD t Sr-89 4 1.0 <tLD (LLD 0 w I (LLD 0 Sr-90 4 1.0 <tLD 80ttom Sediments Gross Beta 6 1.0 23.2 (4/4) L-33. At station 26.6 (2/2) 26.6 (2/2) 0 1 (PCi/g dry) (16.9-26.7) (21.3-31.8) (21.3 31.8) { Ganna Spec. 6 <LLD 0 C5-134 0.1 (LLD <LLD 0 CS-137 0.1 (LLD l (LLD 0 l Other Games 0.2 (LLD 4
- Mean and range based on detectable measurements only. Fractions indicated in parentheses.
LLD value dependent on volume of sample available for analysis. I I d j 4
j Table 5.0-5 1 ENVIRONMENTAL RADIOLOGICAL MONITOR!hG PROGRAM QUARTERLY
SUMMARY
Name of Facility LaSalle Nuclear Power Station Docket No. 50-254. 50-265 Location of Facility Marsellies. Illinois Reporting Period 3rd Quarter 1985 (County, State) Indicator Location with Highest Control Saw le Type and Locations (Juarterly Mean Locations Number of Type Number of Meana Mean Meane Non-routine (Units) Analyses LLO Range Location Range Range Results Air Particulates Gross Beta 181 0.01 0.025 (130/130) L-12. Kernan 0.028 (10/13) 0.026 (51/51) 0 (pCl/m3) (0.006-0.038) 5.0 mi W 214* (0.015-0.036) (0.014-0.040) Gama Spec. 14 0.01 (LLD <LLD 0 Sr-89 14 0.01 <LLD (LLO O <LLO O Sr-90 14 0.01 (LLO (LLO O Airborne lodine I-131 181 0.10 <LLO (pCl.'m3) y Gama Background Gama Dose 14 3.0 15.5 (10/10) L-02, On-site #2 17.5 (1/1) 13.7 (4/4) U (12.2-17.5) 0.6 al p 11* (12.6-15.9) <LLO O Milk 1-131 52 0.5 (LLO (pC1/3) Gama Spec. 52 Cs-134 5 (LLu <LLO O Cs-137 5 <LLO <tLD 0 Other Gamas 10 <LLO <Lto 0 $r-89 12 10 (LLO (LLO v Sr-90 12 2 2.2 (1/6) L-18. Sunnytste Dairy 2.3 (2/3) 2.2 (3/6) 0 13.2 et W 15* (2.3-2.J) (2.0-2.3) Precipitation Gross Beta 11 5.0b 19.7 (5/5) L-15. Granby F arm 22.2 (3/3) 20.1 (6/6) U (8.9-32.6) 7.0 at W 85* (14.7-32.6) (15.6-23.0) i l <tLO O Gama Spec. 4 20 <tLD I Tritium 4 200 240 (1/2) L-16. Lowery Dairy 240 (1/1) (LLu 0 8.2 mi e 120 <ttb u Sr-89 4 10 <LLO Sr-90 4 2 <tLD <LLO O
Table 5.0-5 (continued) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM QUARTERLY SLt94ARY Npe of f acility LaSalle Nuclear Power Station Docket No. 50-254, 50-265 Location of Facility Marseilles. 111tnots Reporting Pertoi 3rd Quarter 1995 (County, State) Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Nuveer of Type Number of Neana Mean Meana Non-routine (Units) Analyses LLO Range Location R ange Range Results Cooling Water Gross Beta 26 1.0 11.2 (13/13) L-26, LSCS Discharge 11.2 (13/13) 3.5 (13/13) 0 (pC1/1) (6.0-23.4) Pipe - River at (6.0 23.4) (2.1-6.9) Station 4.8 mi 9 1* Gama Spec. 6 (LLD 0 Cs-134 10 (LLD Cs-137 10 (LLD <LLO O <LLD 0 Other Gamas 20 <LLD y cn Tritium 6 200 (LLD <LLD 0 Sr-89' 6 10 <LL D <t LD 0 Sr-90 6 2 2.2 (2/3) L-26, LSCS Discharge 2.2 (2/3) <tLD 0 (2.1-2.2) Pipe - River at Sta-(2.1-2.2) tion, 4.8 mi 9 1* Surf ace Water Gross Beta 78 1.0 4.9 (65/65) L-24. Recreational 5.7 (13/13) 5.1 (13/13) 0 (pci/1) (2.2-8.4) Area Cooling Lake (4.6-8.4) (3.8-6.8) 0.3 mt 9 112* Gama Spec. 18 <tLD 0 Cs-134 10 (LLD Cs-137 10 (LLD <LLD ~0 <LLD 0 Other Gammas 20 (LLD Tritium 6 200 <tLD (LLD 0 Sr-89 6 10 <tLD <tLD 0 l 0 Sr-90 6 2 <tLD <LLD i
Table 5.0-5 (continued) 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM QUARTERLY SUW.ARY Name of F acility LaSalle Nuclear Power Station Docket No. 50-254. 50 265 Location of Facility Marseilles. Illinois Reporting Period 3rd Quarter 1985-(County, State) 4 Indicator Location with Highest Control j Sample Type and Locations Quarterly Mean Locations Number of Type Number of Meana Mean Meana Non-routine (Units) Analyses LLD Range Location Range Range Results well Water Gross Beta 8 1.0 17.0 (7/7) L-30 Ranson Well 22.3 (1/1) 16.4 (1/1) 0 (pC1/1) (9.5-22.3) 6.0 mt 9 191 Gama Spec. 6 <LLO O Cs-134 10 <LLD (LLD 0 Cs-137 10 (LLD Other Gamas 20 (LLD <LLD 0 j Tritium 6 200 (LLD (LLD 0 N (LLO O Sr-89 6 10 <LLD (LLD 0 Sr-90 6 2 (LLD Fish Gross Beta 8 1.0 5.2 (8/8) L-24. Cooling
- Pond 5.4 (4/4)
None 0 (pCl/g wet) (1.1-7.1) 0.3 mt 9 112 (1.7-7.1) Gama Spec. 8 None O C5-134 0.1 (LLD None 0 Cs-137 0.1 (LLD None O Other Gamas 0.2 (LLD None O Sr-89 7 1.0 (LLD Sr-90 7 1.0 (LLD None 0 l i
Tchle 5.0-5 (continutd) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM (JUARTERLY Sut9tARY Name of Fact 11ty. LaSalle Nuclear Power Station Docket No. 50-254. 50-265 Location of Facility Marseilles. Illinois Reporting Period 3rd Quarter 1985 - 1 (County, State) Indicator Location with Highest ' Control Sample Type and Locations Quarterly Mean Locations. Number of a Type Number of Mean - Mean Meena hon-routlne (Units) Analyses LLD Range Location Range Range Results Cattlefeed & Grass Gross Beta 4 1.0 10.8 (2/2) L-16. Lowery Dairy 13.2 (1/1) 4.4 (2/2) 0 .(pct /g wet) (8.5-13.2) 8.2 al 9 120' (3.0-5.8) Gamma Spec. 4 Cs-134 0.1 <LLD (LLD 0 s 1 Cs-137 0.1 (LLO (LLD 0 Other Gammas 0.2 (LLD + <LLD 0 w', ' Sr-89 ' 4 1.0 (LLD (LLD 0 Sr-90 4 1.0 i a <tLD <LLD 0 y cu i Bottom Sediments Gross teta 3 1.0 23.4 (2/2) L-33,:At station 28.6,(1/1) 28.6 (1/1) 0 (pct /g dry) (20.6-26.1) i Gans Spec. 3 N. I C5434 0.1 <LLD <LLD 0 Cs-137 ~ 0,1 (LLD CLD 0 Other Gansnas 0.2 (LLD (LLO O veget ables Gross Beta 9 1.0 1.9(9/9) L 36, F are A 2.1 (4/4) None 0 (0.9-3.4) (0.9-3.4) Gauna Spec. 9 (LLO None O Cs-134 '0.1 . LLD) None u I C5-137 0,1 (LLD None 0 i Other Ganesas 0.2 (LLD None 0 i I j Sr-89 9 1.0 (LLD None U Sr-90 9 1.0 (LLO None 0 I-131 2 0.024 <LLD None u 1
- Mean and range based on detectable measurements only. Fractions indicated in parentheses.
b LLD value dependent on volume of sample available for analysts. l l i
o Tablo 5.0-6 ENVIRONMENTAL RADIOLOGl CAL MONITORING PROGRAM QUARTERLY
SUMMARY
Name of Facility LaSalle Nuclear _ Power Station Docket No. 50-254, 50 265 Location of Facility Marseilles. Illinois Reporting Period 4th Quarter 1985 _, (County, State) Indicator Location with Highest Control Sample Type and Locations Quarterly Mean. ~ Loc'ations humber of Type Number of Mean8 Mean Meana Non-routine (Units) Analyses LLO Range Location Range Range Results Air Particulates Gross Beta 196 0.01 0.031 (140/140) L-il, Ransom 0.034 (13/13) 0.030 (56/56) 0 (pCi/m3) (0.012-0.109) 6.0 mi W 191* (0.014-0.109) (0.013-0.014) (LLD 0 Gamna Spec. 14 0.01 (LLO Sr-89 14 0.01 <tLD <LLD 0 <LLO O Sr-90 14 0.01 (LLD Airborne lodine 1-131 196 0.10 <LLD <LLO O (pC1/m3) N Gama Background Gama Dose 14 3.0 15.6 (10/10) L-01, Near Site #1 20.4 (1/1) 13.6 (4/4) 0 (12.7-20.4) 0.5 mi W 326* (11.2-16.4) (LLD 0 Milk 1-131 52 0.5 <LLD (pCi/l) Ganina Spec. 24 Cs-134 5 <LLO <LLO O Cs-137 5 <LLD <LLO O (LLO O Other Gamnas 10 (LLD l Sr-89 12 10 <LLD <LLO O Sr-90 12 2 2.1 (1/6) L-17, Norsen Dairy 2.5 (1/3) 2.4 (1/6) 0 9.0 mi W 350* Precipitation Gross Beta 12 12.9b 22.2 (3/16) L-17, Norsen Dairy 41.5 (1/3) 33.u (2/b) 0 (12.9-28.8) 9.0 at 9 350* (24.5-41.5) 1 < L L') U j Ganna Spec. 4 20 <tLD i Triti um 4 200 (LLD (LLu u (LLu O Sr-89 4 10 <LLD ~' <LLD O Sr-90 4 2 <LLD F
3 l'- Table 5.0-6 (continued) s p
- i. ~
LNVIRONMENTAL AADIDLOGICAL MONIT0p t$G PROGRAM QUARTERLY SumARY + Name of Facility LaSalle Nuclear Power St(tlon_ Docket No. 50-254. 50-265 Location of Facility Marset11es. Illinois Reporting Period 4th Quarter 1985 (County, 5 tate) + Indicator Location with Highest Control Sample Type and ' Locations Quarterly Mean Locations N1mber of. Type . Number of Meana Mean Meana Non-routine (Units) 'Ana yses LLD Range Location Range Range Results CooIIng Water Gross Beta 26 1.0 8.2 (13/13) L-26 LSCS Discharge 8.2 (13/13) 3.9 (13/13) 0 j (pC1/1) (5.0-18.0)> Pipe - River at (5.0-18.0) (1.9-5.9) 4.8 mi 9 l' <T Gamma Spec. 6 s s Cs-134 10 (LLD <LLD 0 C5-137 10 <tLD' <LLD 0 Other Gamas 20 (LLD <LLD 0 cc Tritium 6 200 (LLD (LLD 0 o Sr-89 6 10 (LLD <LLD 0 Sr-90 6 2 228 (2/3) L-26 LSCS Olscharge 2.8 (2/3) ' <LLD 0 (2.2-3.5) Pipe - River (2.2-3.5)' 4.8 al 9 1* Surf ace Water Gross Beta 78 1.0 4.4 (65/65) L-24, LSC5 Cooling 5.9(13/13) 4.4 (13/13) 0 (pCi/1) (1.9-6.6) Lake near Recreation (5.2-6.6) (3.0-5.5) Area, 0.3 at 9 112' Gama Spec. 18 Cs-134 10 <LLD <LLD 0 Cs-137 10 <LLD (LLD 0 Other Gamas 20 <LLD <LLD 0 Tritium 6 200 <LLD <LLD 0 Sr-89 6 10 (LLD <LLD 0 Sr-90 6 2 -(LLD <LLD 0
w Table 5.0-6 (continued) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRxH QUsRTERLY SUMMAdf N41e of Facility LaSalle Nuclear Power Station Docket ho. 50-254, 50-265 Location of Facility Marseilles Illinois Reporting Period 4tn Quarter 1985 (County, State) s Indicator Location with Higtest Control Sample Type and Locations Quarterly Mean Locations Number of Type Number of Me ana Mean Mean8 Non-routine (Units) Analyses LLO Range Location Hange Range Results nell Water Gross Beta 8 1.0 21.1 (7/7) L-32, Illinois State 26.4 (1/1) 17.8 (1/1) 0 (pCi/l) (12.2-32.2) Park Well, 6.5 mt # 326* Ganna Spec. 6 Cs-134 10 <LLD (LLU 0 Cs-137 10 (LLD <tLU U Other Gammas 20 <LLD (LLD 0 <LLD U 03 Tritium 6 200 <LLD Sr-89 6 10 (LLD <LLD 0 Sr-90 6 2 (LLD <LLD 0 l Fish Gross Beta 10 1.0 2.7 (10/10) L-35, Marselles Pool, 3.0 (5/5) mane u (pC1/g wet) (1.4-4.6) of Illinois River (2.5-4.6) 6.5 mi d 326* l Gamma Spec. 10 Cs-134 0.1 (LLD None O Cs-137 0.1 0.12 (1/0) L-35, Marseilles Pool 0.12 (1/5) kone 0 Illinois River 6.5 et 9 326* Other Gammas 0.2 (LLD hone U i l Sr-89 10 1.0 <tLD Mone 0 hone 0 Sr-90 10 1.0 (LLD l
Table 5.0-6 (continutd) ENVIRONMENTAL RADl0 LOGICAL MON!TURING PROGRAM QUARTERLY
SUMMARY
Nsne of Facility LaSalle Nuclear Power Station Docket No. 50-254. 50-265 Location of Facility Marseilles. Illinois Reporting Period 4th Quarter 1985 (County, State) l Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Number of Type Number of Mean8 Mean Mean8 Non-routine (Units) Analyses LLD Range Location R ange Range Results Cattlefeed & Grass Gross Beta 4 1.0 4.4(2/2) L-18, Sunnylste Farm 6.9 (1/1) 6.6 (2/2) 0 (ptt/g wet) (3.6-5.1) 8.2 at 9 25* (6.4-6.9) Gama Spec. 4 Cs-134 0.1 (LLD l (LLD 0 Cs-137 0.1 (LLD <LLD 0 Other Gamas 0.2 (LLD (LLD 0 Sr-89 4 1.0 (LLD <LLU 0 Sr-90 4 1.0 (LLD <LLD 0 Bottom Sediments Gross Beta 3 1.0 24.6 (2/2) L-33 At station 27.9 (1/1) 27.9 (1/1) 0 (pCi/g dry) (22.8-26.4) Gama Spec. 3 Cs-134 0.1 (LLD (LLD 0 Cs-137 0.1 <LLD (LLO O Other Gamas 0.2 (LLD <LLO O
- Mean and range based on detectable measurements only. Fractions indicated in parentheses.
LLO value dependent on volume of sample available for analysis.
Table 5.1-1 GAMMA RADIATION, AS MEASURED BY THERM 0LtNINESCENT DOSIMETERS (TLDs) STANDARD RADIOLOGICAL MONITORING PROGRAM lst Quarter 2nd Quarter 3rd Quarter 4th Quarter Date Placed: 12-28-85 03-29-85 06-28-85 10-04-85 Date Removed: 03-29-85 06-28-85 10-04-85 12-27-85 Days in the Field: 91 91 98 84 Location Average mR/ Quarter On-Site and Near-Site Indicator Locations L-01 Near Site No. I 16.210.9 13.610.6 17.411.0 20.412.5 L-02 On-Site No. 2 13.410.8 11.910.5 17.511.1 18.512.8 L-03 On-Site No. 3 12.510.8 11.610.8 17.310.4 14.212.2 L-04 Near-Site No. 4 16.710.6 11.410.4 16.211.0 17.912.6 L-05 On-Site No. 5 15.510.6 NDa 15.611.0 14.012.3 L-06 Near-Site No. 6 14.410.6 12.911.1 16.210.8 14.912.5 Mean i s.d. 14.8 1.6 12.310.9 16.710.8 16.612.6 Off-Site Indicator Locations L-07 Seneca 10.510.7 12.510.8 15.010.9 12.711.7 L-08 Marseilles 14.210.7 12.210.8 14.810.8 13.813.6 L-11 Ransom 14.610.9 11.610.4 12.210.8 13.511.8 L-13 Rt. 6/Gonnam Road 11.210.7 13.610.5 12.910.9 16.0i2.9 Mean i s.d. 12.6 2.1 12.510.8 13.711.4 14.011.4 Background Locations L-09 Grand Ridge 10.410.7 13.211.0 15.911.0 11.212.3 L-10 Streator 10.210.3
- 12. Di0. 6 13.210.9 13.012.8 L-12 Kernan 10.210.7 12.910.6 12.610.8 16.412.6 L-14 Ottawa 12.010.6 12.911.1 13.210.5 13.812.5 Mean i s.d.
10.710.9 12.810.5 13.711.5 13.612.2
- ND = No data; TLDs lost in the field.
83
i Table 5.1-1 (continued) ~ GAMMA RADIATION, AS MEASURED BY TLDs SPECIAL PROGRAM Inner Ring, Near Site Boundary, Indicator Locations 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter j Date Placed: 12-28-85 03-29-85. 06-28,08-03*85 10-04,11-22*85 Date Removed: 03-29-85 06-28-85 10-04-85 12-27-85 Days in the Field: 91 91 98,76* 84,35* t Previous Revised Location Location Average mR/ Quarter Code Codea 12.410.7* 14.612.3 None 101-1 NDb 16.111.7 None 101-2 12.8t0.7* 17.511.8 None 102-1 NDb 18.112.1 None 102-2 12.310.5* 15.312.4 None 103-1 NDb 18.312.3 None 103-2 13.010.2* 14.312.4 None 105-1 NDb 16.917.1 None 105-2 11.110.5* 14.011.8 None 106-1 NDb 14.612.3 None 106-2 12.410.7* 14.112.5 None 107-1 NDb 16.012.6 None 107-2 L-107-1 109-1 14.5 0.7 13.010.3 12.910.8 15.012.2 L-107-2 109-2 12.110.7 11.810.8 13.210.3 14.312.4 I L-108-1 110-1 17.711.1 12.710.8 12.710.9 15.112.3 L-108-2 110-2 12.910.7 12.610.5 12.610.5 14.712.4 L-109-1 111a-1 12.510.8 12.610.3 12.510.4 25.715.9* L-109-2 111a-2 14.610.8 12.210.4 NDc 16.611.9 L-110-1 111b-1 13.510.6 11.310.3 12.510.8 16.513.9* 4 L-110-2 111b-2 13.3i0.4 12.210.4 13.610.8 d L-111 112-1 15.410.7 12.510.8 12.610.5 10.411.8 L-111-2 112-2 15.110.9 12.010.8 14.210.8 17.712.3 L-112-1 113a-1 13.310.9 13.810.9 12.510.8 18.212.2 L-ll2-2 113a-2
- 14. Si0. 6 14.6tl.1 13.210.7 19.012.4 L-113-1 113b-1 13.110.8 13.510.9 13.510.7 17.512.2
'L-113-2 113b-2 12.611.0 13.210.4 14.110.7 20.012.6 L-114-1 same 13.410.6 11.910.5 13.410.7 16.212.6 L-114-2 same-14.110.6 12.010.8 15.112.5 18.812.4 Mean 1 s.d. 13.911.4 12.610.8 13.010.8 16.512.8 Effective 3rd quarter 1985. b ND = No data; TLDs not placed in the field by mistake. c ND = No data; TLD lost in the field. d Unreliable result; TLDs damaged (white). 84
. Table 5.1-1 (continued) GAMMA RADIATION, AS MEASURED BY TLDs SPECIAL PROGRAM Outer Ring, Near 5 Miles Radius, Indicator Locations . lst Quarter 2nd Quarter 3rd Quarter 4th Quarter Date Placed: 12-28-84 03-29-85 06-28,07-05*85 10-04-85 Date Removed: 03-29-85 06-28-85 10-04-85 12-27-85 Days in the Field: 91 91 98,91* 84 Location Average mR/Qtr. L-201-1 11.810.8 11.610.8 13.810.9 19.211.8 L-201-2 13.510.8 12.910.8 14.010.9 18.212.4 L-202-1 14.010.6 11.510.5 12.610.9 29.0i3.la L-202-2 12.810.8 14.410.9 13.210.6 18.418.4 L-203-1 13.210.3 10.810.3 12.910.6 12.512.0 L-203-2 13.010.7 13.810.4 15.011.2 13.912.2 L-204-1 13.410.8 11.610.9 12.710.9 16.612.1 L-204-2 12.610.5 13.510.5 14.210.4 16.212.1 L-205-1 12.610.9 12.710.5 13.210.2 17.612.5 L-205-2 12.510.4 13.010.8 12.710.9 17.712.5 L-206-1 16.410.8 12.310.9 12.710.3 16.811.8 L-206-2 15.611.0 13.710.4 10.710.7 28.712.0a L-207-1 13.3 1.0 12.110.5 12.710.3 18.411.9 L-207-2 10.410.4 12.7t0.7 13.110.9 20.212.8 L-208-1 14.110.9 12.610.6 12.710.4 15.612.7 L-208-2 12.410.5 13.610.9 13.610.4 5.613.6 L-209-1 15.811.0 12.010.6 13.110.5 15.012.0 L-209-2 15.710.8 13.0 0.4 13.210.7 13.913.9 L-210-1 16.111.1 13.010.8 13.610.5 15.411.7 L-210-2 14.510.9 13.410.5 13.410.8 25.212.7a L-211-1 15.611.0 11.910.7 13.610.9 18.113.0 L-211-2 13.311.1 11.810.5 13.410.9 17.811.7 L-212-1 14.510.8 11.810.4 12.510.5 16.612.0 L-212-2
- 14. 710.8 13.110.7 13.111.2 31.412.4a L-213-1 13.710.9 11.810 8 12.610.5 23.013.04 L-213-2 15.610.7 12.010.5 12.510.5 27.312.7a L-214-1 15.010.8 12.810.6 13.010.5 18.512.4 L-214-2 15.210.4 13.010.5 13.310.8 18.411.7 L-215-1 15.610.6 12.910.4 13.710.7
- 41. 812. 9a L-215-2 13.410.8 13.410.7 15.110.4 28.0tl.7a L-216-1 18.110.9 13.010.4 14.21 0. 8 22.912.38 L-216-2 16.010.8 12.110.6 12.810.8
- 28. 912. 3a Edward -1*
16.310.4 12.610.8 11.210.7 NDb Edward -2* 16.310.7 13.810.5 12.010.4 ND Ransom-1* 14.610.5 13.913.8 10 810.7 ND Ransom-2* 14.210.6 14.410.7 9.210.5 ND Mean i s.d. 14.311.6 12.710.9 12.911.1 16.812.0 $ Unreliable results; chips damanged (white); not included in the mean. No data; monitoring at this location discontinued. 85 .j
E APPENDIX l1 METEOROLOGICAL DATA 86
- p4L 4.m 4
f A-- e- .h- - -J 4, a J i I LASALLE-NUCLEAR POWER STATION PERIOD OF RECORD - JANUARY-MARCH 1985 STABILITY CLASG - EXTREMELY UNSTAE<LE (DIFF TE."P 075- 03 FT ) - WINDS MEASURED AT 075 FEET WIND WIND SPEED (IN MPH) DIRECTION .7-0 4-7 G-12 13-18 19-24 GT 24 TOTAL 1 N O O O O O O O NNE O O O O O O O NE O O .O O O O C r l ENE O O O O O O O E O O O O C O O ESE O O e O O O O + SE O O - O O O O O 4 SSE O O O O O 9 0 + 5 0-0 0 0 0 0 O l t $$W O O O O Q Q Q [ 5W O O O O O O O WCW O O O O O O 9: W O 0-0 1 t) 9 1 ts:lW O O O O O O O t MW C. O O O 1 6 7 tiNW O O O 9 2 1 3 VaRIADLE O O O O O O O TOTAL 0 0 0 1 3 7 11 Hears of calm in this stability class: O 14our s of rniss ing uai nd racas ur urne nt s i ri this stability clar;: ? Hou. 2 o f.T.19 s i ri g stability measuremer.ts in all stability classes: 4G i { 87 i i e- ..----._,m-- .,.--m .-.__,,_-------.m..
~. l t l' i LASALLE NUCLEAR POWER GTATION t i PERIOD OF RECORD - JANUARY-MARCll 1905 OTABILITY CLASO - MODERATELY UNOTABLE (DIFF TEt1P 375-33 FT) ,-I WINDS MEASURED AT 375 FEET WIND WIND-SPEED (IN MPH) j DIRECTION .7-3 4 7 G-12. 10-10 19-24 GT 24 TOTAL l-l 1 N. .O O O O O O. O l NNE O O O-0 0 0 0 l NE O O O O O O O l t ENE O O O O O O O E O O O O O O O { t n EGE O O 1 O O O 1 j 9 SE O O 1 O O O 1 ) I SSE O O O O O O O i-5 0 1 0 1 O O 2 1 }. I CSW O O O O O O O SW O O 1 0 1 0 2 1 i WSW O O 2 0 1 0 3 W O O O O 4 0 4 WNW O O O 1 1 0 5 j r N4 O O 2 4 2 O O f NNW O O O 1 0 .1 2 [ VARIADLE O O O O O O O r l TOTAL 0 1 10 7 9 1 20 lic ur s of calm in this stability class: O Hour; of missing winc measur ements In this stability class! 4 Hourr of missing tability measurements in 111 stability classes: 40 l-88
t LASALLE NUCLEAR POWER CTATION PERIOD OF RECORD - JANUARY-MARCH 1905 G T ABI t.I ' / Cl.f.09 GLIGHTLY UNSTADLE (DIFF TEMP 375 00 FT) WINDS MEASURED AT 075 FEET WIND WIND EPEED (IN MPil) D: 7ECTION .7-3 4 7 O-12 10-19 19-24 GT 24 TOTAL i O O 2 3 O O 5 NNE O O 1 O O O 1 NE O O O O O O O ENE O O 1 2 1 0 4 E O O 1 1 O O 2 ESE o O O O O O O iE O O O O O O O csE O O O O O O o 0 0 0 2 O C O 2 9 ~. '.' 1 O O O ) O r SW O O O O 1 1 2 WIW O O 2 O O O 2 L 0 0 1 'i 3 2 11 W' W O 1 1 1 1 1 5 NtJ O O 2 4 0 3 12 Nr'W O O O 2 0 2 4 WRIADLE O O O O O O O T i1T AL 1 1 10 10 9 9 51 l 1. u. ; vi cu l n. ii. this stubilit< class: 0 fle.: - of ni2:;na wit.d rr e a t u r e m a n t s i re th;r : t a t.1 1 1 t y clo23: 7 f- ' u. _f
- ni L 1: i r. c Ltabt1it, ree a s u r <eme n t t ti.
a'1 9tabi1it, cia 3as: 45 89
I l l l LASALLE NUCLEAR POWER STATION i PERIOD OT RECORD - JANUARY-MARCH 1985 1 STABILITY CLASO NEUTRAL (DIFF TEMP 075-30 FT) WINDS MEAGURED AT 375 FEET WIND WIND SPEED (IN MPH) i i DIRECTION .7-3 4-7 G-12 10-10 19-24 GT 24 TOTAL I N O 1 0 25 10 8 CC NNE O 4 6 14 4 0 20 NE O 4 21 13 15 0 5 /_. ENE O 5 5 7 10 18 50 E O 3 11 11 22 7 54 EGE O O O 11 0 4 2? SE 1 7 1 9 12 0 30 G5E O 4 13 0 1 2 20 S 1 0 12 12 7 8 4C SSW 1 3 11 10 14 14 50 SW i 3 5 1 12 21 40 WSW 1 1 2 12 11 00 57 W 1 1 5 9 12 41 60 WNW O 7 7 12 30 119 175 NU O O 16 24 31 32 106 NNW O 1 20 7 22 5.7 VARI AL'LE O C 0 0 0 0 0 IO"AL c i.0 105 100 .222 032 940 i Har c of calne in this stability class: C liourt of Tiitsino wind measear enien t s in tht: stubil;ty c l.i n :. : 05 i8aul, U l~ fi. l f E. n g stabilit) Weu5ur9m@nts ih al 5thl>ilitV C l s1 2 " 0 5 : 4L a 90
_m. r 4 i i t I LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - JANUARY-MARCH 1935 I 5TABILITY CLAOS - SLIGHTLY STABLE (DIFF TEMP 375-33 fT) WINDS F.EASURED AT 375 FEET i WIND WIND OPEED (IN MPH) e DIRECTION .7-0 4 -- 7 8-12 13-10 19--24 GT 24 TOTAL E N O O 7 5 0 0 21 j NNE O C S 2 O O 13 NE O 1 2 7 2 0 12 t, j ENE O 3 1 5 G 5 '20 j C O 1 7 0 3 15 t i i EGE O 2 0 6 6 10 02 i e 1 ._; r_- 1 .m . n. L, + =.; A i i SOC O 1 3 17 G 10 09 T O O O 14 5 47 69 i SCW 2 0 3 4 21 .7 67 1 1 .. w., ,J 1 .. ~. %s n 4 1 s .s .i UDW O 2 5 10 23 50 3 W 1 2 1 0 7 29 46 U:JW O O 17 15 J1 125 l 1 i l NW 1 0 4 11 17 24 57 4 i MyW O 5 5 'O 12 0 33 d 1 t.' AR I ADL E r? O O O O O O [ l I T r;TAL 5 29 '70 125 147 ^"7 0 067 !!our s of : a i n; in this s t a t, l i t y class: O Hem
- . f aii s s i n.2 m nd mc asur amen ts in thi3 a t at; i ! t t, class:
10 I"o Jr f O f' m;51;Dg Lta'silltV mCaEurum?nti lh all StaDiliti CI4:305: 40 l l I i a 91
._m.._ i + i } j i.' I LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - JANUARY-MARCH 19CS I STAUILITY CLASS - MODERATELY STADLE (DIFF TEMP 075-00 FT) 1 WINDO MEASURED AT 075 FECT l J. i i f { 'J I ND WIND CPEED (IN MPH) i D!PECTION .7-3 4 7 G-12 13-10 19-24 GT 24 TOTAL 1 i 1 N O 1 O O 2 0 2 i Ngt O Q 1 0 1 0 2 e t:E O O O O O O O t I 1 E 'E O O O O O O O I e o o o o o 1 e ECE O O O 1 O O 1 t i d SE O O 1 5 0 2 11 I SSE 1 O O 1 3 3 3 l l C 0 0 1 0 6 21 31 t SSW O 1 1 11 6 17 06. GW O 1 6 0 4 20 04 i u<:.y O 2 4 3 4 9 22 U O 1 2 2 3 16 15 j e f i WN'J O 1 2 5 24 5 27 I NV O O 2 5 22 12 41 l i j i l NN'4 0 0 1 7 3 0 11 i VARIAELE O O O O O O O l TOTAL 1 7 21 40 01 105 260 t H. ut-of cairn in this stability class: O 12):4. r of.r:1 s s t h g w i re d rneaw r erne re t s ir this s t a b i l l t 's class: 12 Hour: c. f misein4 s tabi1 i t v r..ansur en en t s i r. alI stabt1itv classes: 40 92
LASALLE l-lUCLEAR POWER GTATION PERICD OF RECORD - JANUARY-MARCit 1995 STABIt.!TY CLASS - CXTREMELY GTABLE (DIFF TEMP 375-J3 FT) WINDO C45URCD AT 375 FECT wit 4D WIND SPCED (IN MPt!) D!RECTIUN .7-3 4 7 O-12 10-- 1 L l 'i'-2 4 OT 24 TOTAL N O 1 2 1 1 0 5 NNE 1 O O O O O 1 NE O O O O O O O EME 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 C SSE O O O O 1 1 2 0 0 0 1 O O 2 3 SO:J O O 1 4 0 4 12 SW G O O O 1 7 C W50 0 0 0 0 11 2 10 W O O O C O O O W'JW O O O O 1 0 4
- W 1
0 1 5 1 O O lv ;W O O 2 1 3 0 6 VARIACLC O O O O O O O T O TW_. 2 1 7 11 22 10 '2 H ur ; cf calm 2a this statility class: 0 f l."a of niar tr..a wi.id tr.e a s u r e rna n t : in thic stat 111ty clast: O iteur;.;f missinu stacility cic a s u r emie n t ; in all s t a te i lity clairen: 49 93 i
LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - APRIL-JUNE 1985 STADILITV CLASS - EXTREMELY UNSTABLE (DIFF TEMP 375 -20 FT) i WINDS MEAGURED AT 075 FEET WIND WIND SPEED (IN MPH) DIRECTION .7-3 4-7 S-12 13-18 19-24 G1 24 TOTAL 3 N O O O O O O O 1 NNE O O 2 0-0 0 2 NE O O O O 3 0 3 t ENE O O O 2 O 3 E O O O O O O O .i ESE O O O O O O O 4 i i SE O O O O O O O i j-SCE O O O O v 0 0 l 5 0 0 0 0 0 4 4 4 j SSW O O O O 1 0 1 SW O O O O O 2 2 USW O O O O O 2 I i
- l~
W O O O O O 2 z t i WNW O O O O O O O i PW O O O O O O O i w; o O O O O O O W1R If.DLC O O O O O O O re nt o o 2 2 5 in 19 fiour s of calm in this stability c l a s+ r : O 4 j i lourr . f a,i s s i ro) tsi re d m e a s u r e rr.e ri t s in this,tabi;lty c l a s.3 : O-i H;ur s .f missing stability mea c u r erna n t u t r, all stability clarses: J0 ? l i j i 94 1 re n- , w ,,,,e~n .n,w-,-x,--mem--, -s---
.-na.,,-n,--n..,-
..,_e- _n., w
LAOALLE NUCLEAR FOWER.GTATION PERIOD 01-RECORD - APRIL-JUNE 1985 S T AB I L I T'. CLASO t10DERATELY UNST ABLE (DIFF TEMP 375-33 FT) WINDO MEASURED AT 075 FEET 4 WIND WIND CPEED TIN MPH) DIRECTIUN / --3 4-7 G-12 13-18 19-24 OT 24 TOTAL N O O O O O O t. NNE O 2 14 1 2 O l ', 4 NE O O l '. O 5 0 29 E::E O O 2 4 0 0 E O O O O O O EOE O O O O O O O f f.E O O e v 0 C i a i 53E O e 0 0 0 0 i t. O 3 0 0
- /
8 - W D 1 e 1 10 0
- L I.,
4 m C A a. t l t: q n O O O T i, t! O O O O O 1 O O 3 t. Mt l 0 0 i N',; o O v ) O O O 4 /W U O O C c-0 0 4 '.'f7 T,'.Et.E o C O 9 0 0 0 4 '; in 0 2 07 22 17 iv 4 l kb h 4 -h. ' 4 y 8
- f
'dI.f 4 "1 '8 ha
- t. : ; 1 :..a w i r. J ex i t i i e rr,a n t ; in thl:
tabil.t .1.n. 1 ilvur-l M -ur o ,1 i t. u : t a!.111 t s no n.: u r ena n t s i r. ea l l Etabilits .:135,mr: 30 2 i 95 f
LASALLE t:UCLEAR POWER STATION PERIOD OF RECORD - APRIL-JUNE 19 3'~. 7.TAIIty CLASS - ; LIQ;TLY UNSTABLE (DIFF TEMP 375-32 FT) W I NE"8 MEASURED AT 37'5 FEET w I ' ',, WIND :P _ED (IN MPil) D;nECTION . r-0 O-12 13-13 19--24 0T 24 T01AL ~' = g t.:tc O c: 4 2 0 0 . Lr. o. s o I, 2 0 20 i i f
- ,\\
t 0 r? O O 1 E.t 0 i i U O
- c O
1 1 4 0 0 6 n. o n o 1 c. ~ 9' o p y Mh g i c c .. j f) 1 'd m ~~ _\\ _n 0, 3 r-l b-M _ h J 1 2 1 1 i ' j +,.j O 3 g O o 0 1 1 1 1 ~ t.).m ; O O O C 1 1 q w; i.1 t 4NW O ? O 1 1 0 2 ' 'f,T< I A DL E TOrAL -) I r,
- 1 3 <.
- ?
1 ; _- i ! c. ir, tht: ., t a t.1 1 l t, c'a::: f) .us + 4.. ! _ , l' 11 1 ' " A si.1 IJ,.sd th e t IJ ib e fi t : ils !bl' 1 t.i Li ; I i t i;l2L9: ^'
- i
.i er s4 is i e ' i;.1f.' 1 ' I t iD v L Ili 2 f u l'is t t I fi ul' l ' -i I > A-I1I/ I' l #52 O - O 96
LAGALLE NUCLEAR POWER GTATION PERIOD OF RECORD - APRIL-JUNE 19G5 OTABILITY CLASS NEUTRAL (DIFF TEMP 975-30 FT) WINDO MEASURED AT 075 FEET U T *10 WIND SPEED 'IN MPll) 1*:?ECTION . /-0 4-7 O-12 .0-10 19-24 GT 24 TOTAL i N 1 ? 13 12 15 2 52 t 'ME O O 04 40 9 O "4 NE O 3 22 ';O 11 O CNE O 10 12 14 10 0 4 t. r-1 .m .3 n.
- 4. o v
1 ~, 6 .c. r e ~. E 1 ~ 9 6 7 4 N ,1 4 -1 ? ... c. c" 1 s 4 0 5 7 11 15 20 66 C3W 0 6 6 l '. 16 16 60 .W O 4 6 13 17 13 '4 p..:W O 5 19 10 3 ';.,i. r W O 6 11 11 10 20 61 U:fW 0 13 16 00 ~' O 1.. 1: 1. .o s.. c v , p. n 14 0 7 5 41 t.NU V VARIADLC 0 0 0 0 0-O v T U ;.M C LC: 2*t ':' 1ll
- 50 UL2 k i.. r
>f Ta l m I r. this stability class: O l Ilour of ca t e s i r.g vi r.d niaa s u r ere. n t s i r, t t:10 s t a t.11 1 t j clans! 19 H<>. f ne i s t i r.g s ta bil i t y r,iea sur umer t c i ri Gl! . t at. i l t t s classes: 30 97
LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - APRIL-JUNE -1985 GTABILIT'/ CLASS - SLIGHTLY STABLE (DIFF TEMP 375-33 FT) WINDS MEASURED AT 3'75 FEET WIND WIND SPEED (IN MPH) DIRECTION .7-3 4-- 7 8-12 13-10 19-24 GT 24 TOTAL N O 2 1 5 6 1 15 NNE 1 2 6 19 0 0 28 NE O i 6 14 1 0 22 ENE O 3 5 14 11 1 04 E 1 4 2 12 8 5 32 ESE O 2 4 7 4 4 21 SE 1 2 1 3 7 6 20 SSE O O 3 5 13 29 50 S O 1 4 10 10 56 54 SSW O 2 4 5 10 40 67 i SW O 2 2 10 14 15 46 WrW G 2 1 10 0 ? 30 W O 3 0 ? O 24 47 WNW O O 4 7 14 19 44 NW O 4 4 4 12 2 26 NN;! O 2 5 7 2 0 16 VARIADLE O O O O O O O I TOTAL 0 32 55 144 134 214 S02 i Hourt of c a l ir. In this stab'lity clast: O i llour s 4f m i s s i n g w i n d me a s u r e rre,3 n t s in this s t a t. i l i t y class: 36 H o u r :- o f m i :., s i n g stability measurements in all stability ciAsses: 00 98
.. =. LAGALLE NUCLEAR POWER STATION PERIOD OF RECORD - APRIL-JUNE 19G5 STABILITY CLASS - MODERATELY STABLE (DIFF TEMP 075-33 FT) WINDS MEASURED AT 375 FEET - i? I ND WIND SPEED (IN MPH) T:I RECT I ON , "3 4-7 8--12 13-1C I?-24 OT 24 TOTAL N O O O 2 O O 2 NNC' O 1 0 1 1 0 3 NE O 4 4 4 2 0 14 ENE O 1 2 3 4 0 10 E O 3 2 6 4 0 15 ESE O O O 5 1 1 7 3E O 2 2 5 4 6 !? SSE O O O 5 10 11 26 G O O 2 3 80 36 49 'I OW O O 2 3 5 12 22 SW O C 2 5 4 22 UOtf C O 2 2 11 o 94 W O O 4 14 12 o 09 W'?W 1 1 2 7 15 4 .::G NW O 1 1 6 0 1 17 i %MW D o O 2 O O 2 VARIADL2 O O O O O O 0 l TOTAL 1 13 25 73 94 95 301 H. ui 2 of alm i r. that. stability class: O Hoos u af i;1 s s i r v wi re d c.ea t u r ;-me ri t s a re this c, t a te i l i t ', clar:: Ho ># . af :.i n s tr y s t s.t.1 1 1 t asu a ; o r e me ri t t I r. all :, t a b i l i t y ciatres: 00 f 99
_.m LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - APRIL-JUNE 1935 OTADILITY CLASS - EXTREMELY STABLE (DIFF TEMP 375-03 FT) WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH) DIRECTION .7 4-7 O-12 13-18 19-24 GT 24 TOTAL 3 i N O O O O O O O NNE O O O O O O O 4-NE O O O O O O O ENE O O O 1 O O 1 i E O O O O O 1 1 ESE O O 1 0 1 0 2 SE O O O 3 3 0 6 OSE O O O 3 0 0 3 i S O O 1 5 7 1 14 SSW O O O 2 0 10 10 SW O 2 2 1 5 1 11 WSW O 1 1 1 1 0 4 W O O O O 4 2 6 WNW O O O 1 4 2 7 NW G O O 2 2 0 4 NNW O O O O O 0 0 VARIABLE O O O O O O O TOTAL 0 3 5 19 30 20 77 ilours of calm in this stability class: O j Hour s of misstriq wind measururnants in this stability class: O Hvurs vf missing stability measurements in 111 stability classer: 30 100
l. LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - JULY-SEPTEMBER 1985 GTABILITY CLASS - EXTREMELY UNSTABLE (DIFF TEMP 375-33 FT) (JINDS MEASURED AT 375 FEET WIND WIND GPEED (IN MPH) DIRECTION .7-0 4-7 8-12 13-18 19-24 OT 24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O 2 O O 2 E O O O O 3 0 0 EOE O O O O O O O SE O O O O O O O GSE O O O O O O O O O O O O O O O COW O O O O O O O CW O O O O O O O l WCW O 1 O O O O 1 W O O O O O O O W'4W O O O O O O O NW O O O 0 0 0 0 tiNW O O O O O O O VARIADLE O O O O t, O U TOTAL 0 1 0 2 O O 6 H.mr c :. f calm i r. this stability class: O Hour. vf i.i sing wind tr.ea s ur eme n t s i ri thlo Stabilltv clarc: O Hod! ; o f ini s s ing stability ri,s u s u r e rr e ri t s i t. ull,tability classes: 5 101
LASALLE NUCLEAR POWER GTATION PERIOD 017 RECORD - JULY-SEPTEMBER 1935 GTADILITY CLASS - MODERATELY UNSTABLE (DIFF TEMP 375-33 FT) WINDO MEASURED AT 375 FEET WIND WIND SPEED (IN MPIi) ti! RECT ION .7-0 4 7 G'O 13-10 19 -24 GT 24 TOTAL = - - -..... ~.. - N O O O O O O O NNE -0 1 O O O O 4 i NE O O 2 O O O 2 h b ENE' O O O 2 4 0 6 E O O 3 7 1 0 11 ESE O O O O O O O SE O O O 1 O O l' OSE O O O O O O O G O O O O t O 1 i COW O 2 10 6 4 0 a7 j SW O 2 7 4 1 0 14 t WSW O 1 O O O O 1 W O O O O O O O-WNW O O O O O O O tW O O O O O O O NNW O O O O O O O VARIABLE O O O O O O O fOTAL 0 6 25 20 11 0 62 !! aur 3 of'caln. i r, this stability cleans O !!oas of tr. 2 21 1 r o2 sinc measuroments in thle stability c l et s ; : 2 i f m. : of n.2sr,inc stability me a s u r err c r. t r in all s t at.11 i t y c!atsest 5 102
? l LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - JULY-SEPTEMBER 1985 STABILITY CLAOS - SLIGHTLY UNSTABLE (DIFF TEMP 375-33 FT) WINDS MEASURED AT 275 FEET 'j ; NU WIND OPEED (IN MPH) -7 O-12 13-18 19-24 GT 24 TO TAL DI:iECTION .7-3 N O 1 O O O O 1 NNE O 1 2 1 O O 4 NE O 3 i O O O 4 ENE O O 2 2 i O 5 E O O 7 2 O O 9 ESE O 1 6 2 O O 9 SE O O 4 1 O O SOE O O 4 4 O O O S O O O 7 2 0 ? SSLJ O 2 5 9 7 0 24 I SW O 4 6 5 6 0 21 W5t1 0 3 4 G 4 0 19 W O 2 1 1 1 0 S W;4W O 1 O O 1 0 2 NU O O O 2 O O 2 N,NW O O O 9 1 0 1 VARIAOLE O O O O O O O T OAL O 10 C' r4 20 0 122 Mcur< of.:a l n, in this tabt!its class: O !!o u r. :, f ti. l b s i n o wi nd nicas ur ement s in this stablitty clas1: 7 H;ur ;.; f
- c. i s s i n g :tebility mansur en ent s in all stability clacses:
'? 103 l
LASALLE NUCLEAR POWER OTATION PERIOD OF RECORD - JULY-SEPTEMDER 1985 S T AD I L I TY i.~ L ASS - NEUTRAL (DIFF TEMP 375-33 FT) WINDO MEASURED AT 075 FEET WIND WIND SPEED (IN MP1i) DIRECTION .7-3 4 --- 7 8-12 13-18 19-24 GT 24 TOTAL N O 3 10 8 4 0 20 NNE O 6 15 7 2 1 01 NE O 14 25 26 1 0 66 ENE 1 0 24 19 3 0 55 E O 15 23 23 9 1 71 ESE O 17 16 4 2 0 39 SE 1 6 19 4 1 0 31 SSE 1 7 12 12 1 0 33 5 0 1 10 14 12 7 44 SSW O 6 12 43 30 0 99 SW O 5 17 22 14 6 64 WSW O 7 19 11 4 0 41 W O 13 11 12 17 10 63 4 WNW O 9 15 14 3 40 } flW i 10 12 13 6 0 42 NNW 1 0 16 2 0 51 _v VARIABLE O O O O O O O TOTAL 5 105 259 255 116 06 006 tiours of calm in this stability class: O livurs of rni ss i ng wired meas ur emere t r i re this :tability clast: 34 Hours of missing stability rw a s u r e m e n t s in ull stabil2tv classes: 5 i 104 ~ _~.~ _ _ -._ _____.---_. _
LASALLE NUCLEAR POWER STATION PERIOD OF RECORD -- JULY-SEPTEMBER 1935 GTABILITY CLASO -- SLIGHTLY STABLE (DIFF TEMP 075-03 FT) WINDG MEASURED AT 375 FEET WINO WIND SPEED IN MPH) DIRECTION .7-0 4-7 G - 12 13-10 19-24 C1 24 TOTAL N O 6 4 4 O O 14 N"C 1 1 0 4 1 0 10 NE O 3 10 17 0 0 43 ENE O O 3 9 2 0 14 E 1 5 17 12 7 10 52 ESE O 4 15 15 6 9 49 SE O 1 5 10 3 0 19 S3E 1 4 4 9 7 2 27 0 0 4 3 10 22 23 45 00W 2 4 15 15 26 4? 112 CW O 6 11 13 17 23 70 L;OW O 4 0 t. 9 9 Oc. W 1 1 4 11 19 6 42 WJW O 5 0 5 0 2 21 riu O 4 0 10 2 0 20 N'JW 1 7 3 11 0 1 26 'KRI ADLE O O O O 9 0 o r976L 8 6 ') 129 170 125 132 620 Har ,f c s t r.
- rr this stabi'ity class
O ilo v r wl'. :; t t. ; w i r.c r i% ; J r e m e r t s in t ie l t. stub 111ty class: 20 !=.i_ a.; s s i roj ctability ni n s u r e me re t s a re t11 stability classes: N 105
'i / LASALLE~ NUCLEAR POWER STATION PERIOD OF RECORD - JULY-SEPTEMBER 1985 I STAEttLITY CLA90 - MODERATELY STABLE .DIFF TEMP 375-03 FT) ( 7 WINDS MEASURED AT 3751EET WIND WIND SPEED (IN MPH) DIRECTION .7-3 4s 7 3-12 10-18 19-24 GT 24 TOTAL __A. N 1 0 2 0 0 0 3 NNE O 2 0 1 O O 3 NE O 4 0 1 O O 5 ENE O O 2 6 0 0 3 E O O 1 2 i O 4 ESE O O O 13 0 1 OG SC O 1 5 14 5 1 26 Ot.E O 1, 7 7 5 9 29 5 0 7 0 7 0 14 44 0$W O 6 0 .11 6 31 65 CW O 1 2 12 21 23 5? USW O O 4 5 5 7 21 W O 3 2 ? 4 3 21 WNW 1 2 0 7 6 2 21 i NW O O 3 7 1 20 ^ Nro vJ 1 1 6 11 2 0 21 VARIADLC O O O O O O O l .TCTAL 3 28 56 110 7 '" 92 376 !!ours of calm i r. this ctability c l a', s : O H o.i r t of mi; sir.g wind mearurementL in thir stability class: 20 !!our c .f missinc s tabil i ty rneas ur emen t s in all stability classes: 5 i 106 . ~.
i LATALLE NUCLEAR POWER CTATION PERIOD OF RECORD - JULY-SEPTEMDER 1985 OTADILITY CLASS EXTREMELY STADLE (DIFF TEMP 37S-33 FT) (41NDS (1EAGURED AT 375 FEET 'vn F4J WIND SPIED (IN t1PH) LtIRECTION .7-O 4-7 G-12 13-10 19 -24 GT 24 IOTAL y N O O O O O O O . NE O O O O O O O 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 O O O O 4 0 4 SE O O O v 2 2 7 TSE 0 0 5. 7 2 2 16 S O 2 0 1 1 C 10 53W O O O 1 5 6 12 SW O O 1 2 4 12 19 l-GW O O O 1 2 3 0 W O O O 1 4 1 6 WNW O O O O O O O NW G O O O O O O ' : ;W O O O O C 0 0
- *!'RI APLE O
O O O O O O 1 a i JTA1 0 3 6 .9 24 34 06 ( P L: : v! ; 11 ri in this
- , t a ' t ' i t y clars:
0 s
- L uc t
.f .i.: ng wind macuraments in t t. i s t h ti l l i ty cla:s: 12 .u; .f T: i s r. ;. n g stability measurements i r. all stability cic res: S 107
c l ,j } i LASALLE NUCLEAR POWER OTATION l PERIOD'tT RECORD - OCTOBER-DECEMDER 1985 i / g _OTABILITY CLASS - EXTREMELY UNSTABLE (DIFF TEMP 375-33 FT) . WINDS MEASURED AT 375 FEET l WIND WIND SPEED (IN MPH) i DIRECTION .7-3 4-7 G-12 13-18 19-24 GT 24 TOTAL I i i N O O O O O O O i t l NME O O O O O O O i NE O O O O O O O ENE O O O O O O O E O O O O O O O t 1 i ESE O O O O O O O I SE O O O O O O O l SSE O O G O O O O i S O O O O O O O i ~ SSW O 1 O O O O 1 SW O 1 O O O O 1 l t j WSW-0 0 0 0 0 0 0 I W O O O O O O O i WNW O O O O O O O 4 NU O O O O O O O l NNW O O O O O O O l VARIABLE O O O O O O O i I O O O O 2 TOfAL 0 2 i H o u r-r cf calm i r. this stability class: O i Hour s of raiss anc wind measur emen t s in this stabilit/ class: O l Hourt of mtasing stabi?ity m6asurements i r, alI stability classes
- i i
F 108 i ,-.,-..n, ,. -. -. - - - -.. - - _.,, - _ _..... ~, _-
LALTLLt' NUCLEAR PUW::R '~.T f,T I ON PERIOD Of RECORD OCTODER-DECEMDER 190'
- Jti!.lTV CL A 110K R AT El.Y !!NGT A13LE (DIrr TENr-
._ l1) W I N E". MEW _.URED AT J7t; FEET 'A '. N D WIND GPEED 'IN MPH) F. ! RE.C T I ON .?-O 4 / O-12 10--1:3 19 24 GT 24 TOTAL r3 0 0 0 0 0 0 0 NNE O O O O O O O
- E O
O O O C O O ENE O O O O O O O E O O O O O O O ESE O O O O O <) O E.E O O O O O O O u.0; O C 0 0 0 0 0 O O O O O O O CSW O O O O O O O SW O 1 4 1 0 0 6 W3W O O 0 0 0 0 0 W O O O O O O C Wa:W O O O O 4 0 4 MW O O O O O O t-i,NW O O O O
- 3 O
O J ARI AD'_E O O O O O O C ' >TAL 0 1 4 1 7 0 13 r i k k e r :. cf.:a l n, i; this stab 1;1ty class: O <wr r.ni c c inc wind maarurement: In this utability class: 0 ur-f.r. i s c i n a stabiliti r...1s u c cme n t s i t, r.1 1 stability clasuos: 1 109
1 LASALLE NUCLEAR POWER GTATION PERIOD OF RECORD - OCTOBER-DECEMDER 1985 3TABILITY CLASC - SLIGHTLY UNSTABLE (DIFF TEMP 075-03 FT) WINDO MEASURED AT 375 FEET L,I TID WIND SPEED (IN MPH) DIRECTION .7-3 4-7 8-12 10-19 19-24 GT 24 TOTAL N O O O O O O O NNE O O O O O O O NC O -O 1 O O O 1 ENE O O O 4 0 0 4 E O O O O 3 0 3 ESE O O O O O O O SE O O O O O O O l 90E O O O O O O O 5 O O O 1 O O 1 GdW O O 2 3 0 0 5 SW O O 1 2 2 0 5 WiW O O 1 5 1 1 0 ~ W O O O O 9 0 7 WNU O O O O 2 2 4 NU O O O O L. 4 10 NNW O O O O O 1 1 VARIABLE O O O O O O O TUTAL 0 0 5 15 20 8 51 f os u r ; af c a i rn in this ;.tability class: O Hour, c &' niist a na wind mea s u r c.tr.e n t s in this stability class: 10- .tr S of m121.ing stability measurements in all stabi11tv classes: 2 H1 110
m LAOALLC NUCLEAR POWER OTATION PERIOD OF RECORD - OCTODER -DECEMDER 1005 ' T ACI L ~'c
- .L A G O - NEUTRAL (DIFF TEMP 775 "C FT) i;INDG MCAOURCD AT
~J 7 '.i FECT WIND LIIND CPCCD (IN MPl!) DIRECTION 7-3 4-7 C-12 10-18 19-24 GT 24 TOTAL N 2 8 16 38 7 6 77 NNE 1 4 20 22 3 1 51 O r. ec -.c. a v .m is av CNE 2 8 23 49 2? O 111 E 1 13 19 42 8 15 136 ELC 2 4 12 3 11 0 40 EE 1 2 6 10 2 0 21 CSE 2 4 9 11 4 0 20 0 1 O O 16 20 5 50 ..4 y o. q 47
- 4..c.
. ~. e.n. SW 1 4 1 12 8 20 46 WSW O O 6 10 0 26 52 .v 1 j, 3_, ..s. v,. O e a v Uf!W O 6 7 23 52 52-141
- U 1
0 ? 24 46 30 104 MNW 2 3 20 ~7 16 7 6' 7 VnR I AD'_E O O O O O O 'i <.n c, _ 21 ?? lo? 360 007: 2LO 1194 l Mcur et u l c. 1 this stability c? cur: O l ' to ;r ; :. f .1 ; ; i ri g w a r. d me s s u r c.c.e r.t s in thl: stability class: C6 'v...
- . t
.is ing s *. ab i l i t y me asur emer.t c i r. ell ! : t a b i l i t ;. classes: 2 111
LASALLE NUCLEAR POWER STATION PERIOD OF RECORD OCTODER-DECEMBER 1985 STABILI'Y CLASS - SLIGitTLY STABLE (DIFF TEMP 375-03 FT) WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH) DIRECTION .7-3 4-7 9-12 13-18 19-24 GT 24 TOTAL N O 1 1 19 8 0 27 NNE 1 0 3 6 0 0 10 NE 1 5 3 3 1 0 13 ENE 3 5 3 16 5 1 00 E 1 6 4 7 G 20 ESE 1 4 2 7 11 4 29 SE O O O 5 10 1 00 SSE O 1 6 7 9 0 20 0 0 3 10 6 21 47 37 SSW O 3 2 G 21 22 57 SW O 1 1 4 16 13 3G WSW O 1 2 3 14 14 04 .J 1 2 3 8 20 I? 56 WP 'W 1 1 4 14 21 92 74 NW 1 1 1 6 5 0 14 NNW I O 2 5 1 O VARIABLE O O O O O O O TOTAL 11 36 59 12'J 176 171 te6 1 l' uro <f 11 a4 i r, this stal>111ty clais: 0 + u.; .. f m 13 3 t ri g o i rid mec s ur e n.m n t 3 ; r: th1 clabi1ity c!2522 21 !!..o r _ af m u. s a n ; s t.a b i l ; t > me a s u r e n,e ri t a t r. all stability classes: 2 112
a. 4 l~ LM alt.E NUCLEAR I'CWER CT ATION 1-PERIuD OF RECOPD OCTODER-DECEMDER 1985 ' ' 4 D I. I T'i C L ACG - MODERATELY CTABLE (DIFF TEMT 375-33 fi) WINDO MEASURED AT 375 FEET ' 3.D WIND OPEED (IN MPM) DIRECTION .7-3 4 7 O--12 10-10 19-24 GT 24 TOTAL I N O O O O O C I 'E O O O O O O O i '!E O C O 1 O O 1 l ENE O O O O O 9 0 C 0 0 0 0 3 0 11 i ESE O O O O 2 1 3 d 1.E Q Q Q 1 Q 2 3 i ,c a..,- O J O ~ a 4 2 O 1 1 6 0 1 12 4 c c.> 2 1 .eo .a an a 6 1e ,v )
- .t !
O 3 1 4 7 1E WSW O 2 C 4 4 1 11 1 L 0 1 1 1 2 a 11 i. WM O C 1 2 0 2v 29 T'W O 1 0 2 0 4 i t r W I.S
- )
[ [ h 4 L Vt'Wi ^ OLE O O O O O O 4 .*f = l .) 4./ i H:ur,
- f
- 13 m i r,
- t. h i s s t,1L 11 1 t y -;Iass:
0 !m ed il: 5.r..s w "id peardr0ments i rs this.' ability :less: 20 r f" > -) ) ; .t i NA921%9 L t ~. D i l. tf 'Ta s3 6 5 U r eifie n t s.i. al' Etability ClGE5e3 2 i i r 113
.-m_. E i LASALLE MUCLEAR POWER STATION PERIOD OF RO:ORD OCTODER-DECEMDER 1900 1 t'ALILITY ': L AS. 9 EXTREMELY STABLE (DIFF TEMf-.375- 0.; r" ) WIND: MEASURED AT 375 FEET W1'JD WIND' SPEED (IN MPIO DIRECTION 7-3 4-7 O-12 13--10 19-24 G7 24 TOTAL N O O O O O O O i 1 MNE O O O O O O O NE O O O O O O O EN.E O O O O O O O l F. O O O O O O O i ESE O O O O O O O f a SE O O O O O O O f i l SSE O C 0 0 0 3 0 9 0 0 0 0 0 5 5 i SSW O O O O 4 13 17 SW O O O O 5 9 14 s !JSU O O O O 2 5 10 l I W O O O 1 2 1 4 WNU O 1 1 0 1 2 5 i NW O O 1 4 2 0 7 1 t NNW O 1 1 1 O O 2 l i VARIABLE O O O O O O O TOTAL 0 2 3 ? 16 00 60 J l i..ur3 vf calm 2n tnis stabiltty class: O l c f m 12.=. i r. g w i n.1 meas.rrements in this stability class: 23 Hm 6f missici; stability measurements in ali stability classes: 2 Y i i 114 --m --- ..,-,,..__m. m _.. ~.. -.. _. _, _, _...
APPENDIX III ANALYTICAL PROCEDURES 115
ANALYTICAL PROCEDURES MANUAL TELEDYNE ISOTOPES MIDWEST LABORATORY PREPARED FOR COMMONWEALTH EDISON COMPANY Note: These procedures are taken from the complete Procedures Manual. Only procedures applicable to the CECO Radiological Environmental Monitoring Programs are included in this manual. Compiled by: . (M ~ h B. kirob i Lab Supervisor i Approved by: /L.'G.Huebner . General Manager Revision 0, 11 February 1977 Revision 1, 23 May 1978 Revision 2, 22 May 1981 Revision 3, 15 June 1983 Revision 4, 1 June 1984 l i Revision 5, 7 February 1985 (This information, or any portion thereof, shall not be reproduced in any manner or distributed to any third party without the written permission of Teledyne Isotopes Midwest Laboratory). 116
TABLE OF CONTENTS 1 SECTION I SAMPLE PREPARATION 2 1.1 Fish 3 1.2 Bottom Sediments and Soil 4 1.3 Drinking (clear) Water (EPA' Method 900.0) SECTIONS II, III, VIII ANALYSES 2.1 Airborne Particulates (Gross alpha and/or Beta) 5 2.2.2 Gross Alpha and/or Gross Beta Activity in Olssolved Solids 6 3.1 Airborne Particulates - Gamma Spectroscopic Analysis by 8 Germanium Detector 3.2 Airborne Iodine - Gamma Spectroscopic Analysis by Germanium 9 Dectector 3.3 Water - Gamma Spectroscopic Analysis by Germanium Detector 10 3.4 Soil and Bottom Sediments - Gamma Spectroscopic Analysis by 11 Germanium Detector 3.5 Fish and Wilflife - Gamma Spectroscopic Analysis by 12 Germanium Detector 13 3.6 Anbient Radiation (TLD), Efficiency Calibration 3.7 Procedure for Preparation and Readout of TLD chips 15 17 3.8 Tritium in Water 3.9 Iodine-131 in Milk by Ion Exchange on Anton Exchange Column 19 8.1 Strontium-89 and Strontium-90 in Milk by Ion Exchange 23 32 8.4 Strontium-89 and Strontium-90 in Water Samples 8.6 Strontium-89 and Strontium-90 in Milk (Ash), Vegetation, Fish, Wildlife, Soil, and Bottom Sediment Samples - Sodium 37 Carbonate Fusion l f 117
Rev. 4, 6-01-84 4 SECTION 1.0 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. l 2 t t I t' i 118 L L 4 -e-emT a y vw,-e e-ge, ,--,y-,----7 -rmg-,ry, y,g, - - - ~ ~.w,=-- g --m---- yy sm -p tm-- rw--e-
< f.' 4 // / /[/ >af /pi/ Hev. 4, b-UA-64 Approved by: L'.Gv.' Huebner 1.1 Fish 1. Wash the fish. 2. Fillet and place the flesh imediately (to prevent moisture loss) in a 500 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 1 hour. Clean the bones. Air dry, weich and record as wet weicht. Dry at 125* C. Record dry weight. Ash at 800* C, cool, weigh, and record the ash weicht. 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. Cool, 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. The sample is now ready for analysis. NOTE: If there is sufficient quantity, use surplus flesh for drying and ashing, instead of waiting for gamma scanning to te completed. 119
Rev. 4, 6-01-84,',f/ f' Approved by: d./7-///j//pu t.7. Hueoner 1.2 Botton Sediments and Soil 1. Air dry the entire sample. Grind or pulverize the sample and sieve through a #20 mesh screen. 2. For gama-spectroscopic analysis, seal 500 cc of the ground sample in a Marinelli beaker. Record dry weight. 3. Seal the remaining sample (up to I kg) in a plastic container and save for other analyses or for possible future rechecking. s 120
6-01-84 / - }tu d C 4 Rev. 4 0 d Approved by: L.jf. Huebner 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 collec-tion 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 be collected without preservation, they should be brought to the laboratory within 5 days, then preserved and held in the original container for a minimum of 16 hours 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 container. 3. Hold the sample in the original container for a minimum of 16 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 reouired 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 For other volumes, adjust aliquots correspondingly, at the rate of 1.5 ml per 100 ml of sample. 121
l Rev. 4, 6-01-84,Y /;vl u///v/( Approved by: J..QI Hdebner 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 sample in a proportional counter. 3. Calculate the activity in pCi/m3 using computer program AIRPAT. Calculations Gross alpha (beta) concentration: Efb Eb A +2 3 (pCi/m ). B x C x 2.22 B x C x 2.22 Where: A = net alpha (beta) count rate (cpm) B = efficiency for counting alpha (beta) activity (cpm /dpm) C = volume of-sample (m3) Esb = counting error of sample plus background Eb = counting error of background i l 122
Ree. 4, 6-01-84 /)k" / / / // Approved by: M- ~ ~Q/'/f//g,( L.G.' Huebner 2.2.2 Gross Alcha 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, HNO : 3N 3 Nitric acid, HNO : concentrated 3 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 Section 2.2.1). 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. i l 123
Rev. 4, 6-01-84 Sction 2.2.2.(continued) 4. With distilled water and.a few drops of 3N HNO, transfer 3 the residue to a 50 mi beaker. Evaporate lo NEAR dryness. 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 500* 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. 9. Store the sample in a desiccator until it is to be counted. 10. Count the gross alpha and/or the gross beta activity in a low background proportional counter. 11. Calculate the activity in pCi/l using computer program OWATAB. . Calculations: Gross alpha (beta) concentration: 2 2 y sb + E E 2 b A + (pCi/ liter) = 8 x C x 0 x 2.22 - 8 x C x D x 2.22 Where: A = net alpha (beta) count rate (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 l
Reference:
Radioassay Procedures for Environmental Samples, U.S. Department of Health, Education and Welf are. Environmental Health Series, January 1967. 124
Rev. 4, 6-01-84 'f. / Approved by: r / /f//, N/g L.(/. tiuebner 3.1 Airborne Particulates - Gamma Spectroscopic Analyses by Germanium Detector 1. Put the air filter in a filter cup container. 2. Place the filter cup inside the shield on the detector. 3. Count long enough to meet the LLO requirements. 4. Store the spectra on the disc. 5. After storing, calculate gamma activities using computer and corres-ponding calibrated geometry. 6. Return the filters to the original envelopes for storage or further analyses. 5 125
i ov d b L'.q/Huebner Airborne lodine Gamma Soectroscopic Analysis by Germanium Detector 3.2 NOTE: Because of the short half-life of I-131, count the samples as soon as possible after receipt and no later than 48 hours. 1. Loac~ the charcoal cartridges in a specially designed holder or transfer charcoal from each cartridge to individual plastic bags. Seal the bags. Label each bag with corresponding project ID, locations ID, and date 2. of collection. Place the ba,s in a standard geometry container, cap the container 3. and secure the cap with a tare. Place the holder or container on the detector and count for a period 4. of time that will meet the required Lower Limit of Detection (LLO). Calculation: ^ A.= I-131 activity (pCi/ sample)= latcountingtime) (1) 1 2.22 x B Where: A= net count rate of I-131 in the 0.36 MeV peak (cpm) B= efficiency for the I-131 in 0.36 MeV peak (cpm /dpm) Correction for Equilibrium (assuming constant concentration over the sampling period) and Decay: At1 xAt C = F (1-e-Al ) 2 Where: C = equilibrium concentration of I-131 (pCi/m3) A = activity of I-131 at the time of counting (pCi/ sample) l e= the base of the natural logarithm = 2.71828 x= 0.693/ half life (days)=0.693/8.04 = 0.0862/ day t = elapsed time between the end of sampling and mid-counting 1 point-(in days) t = duration of collection (in days) 2 F= m3/ day I l 126
Rev. 4, 6-01-84 e EkI // d// Approved by: g L.4.' Huebner 3.3 Water - Gamma Spectroscopic Analyses by Germanium Detector Procedure 1. Measure 3.5 liters of water into a Marinelli beaker. 2. Place the beaker inside the shield on the detector. s 3. Count long enough to meet LLO requirements. 4. Store the spectrum on a dist 5. After storing, calculate gamma activities, using computer program and corresponding calibrated geometry. 6. Transfer the sample back to the original container for further analyses. i 127
Rev. 4, 6-01-84 %.' / /' Approved by: k//Q//2///d. li.Gj Huebner 3.4 Soil and Bottom Sediments - Gamma Spectroscopic Analyses by Germanium Detector Procedure 1. Transfer the portion of the ground sample set aside for gamma scan-ning into a 500 ml Marinelli container. 2. Record the dry weight. 3. Place the container inside the shield on the detector. 4. Count the gamma activity long enough to meet the LLD requirements. 5. Store the spectrum on a disc. 6. After storing, calculate garrrna activities using computer and corres-ponding calibrated geometry. 7. Transfer the sample back to the original container for further analyses. 128 L
Rev. 4, 6-01-84fg '(////////~ g Approved by: s
- L.G/ Hdebner 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 a 500 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 the detector. 5. Count long enough to meet the LLD requirements. 6. Store the spectrum on a disc. 7. After storing, calculate gamma activities using computer and corres-ponding calibrated geometry. 8. Transfer the sample back to the original container for further analyses. 129
Rev. 4, 6-01-84 M6 e/ / Approved by: M N/(LLM/// L L'.Gt Huebner 3.6 Ambient Gamma Radiation A. Thermoluminescent Dosimeters (TLD) - Licht Response (Efficiency) Harshaw Lithium Fluoride TLD-100 chips,1/8" x 1/8" x 0.035". F Procedure 1. Rinse the chips with warm trichloroethylene followed by the methanol rinse. Dry. 2. Place the chips in a platinum crucible. i 3. Anneal for 1 hour at 400*C. 4 4. Cool quickly by placing the crucible on a metal plate. I
- 5. ' Anneal for 2 hours 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 in the TLD Reader (For test procedure see
" Performance Test Procedure for TLD Reader"). l
- 14. Calculate mean + one sioma deviation of five chips.
i l-
- 15. Calculate light response of TLD's (correction f actor) by the followino equation:
130
Rev. 4 6-01-84 0 Section 3.6 (continued) Calculations A C.F.(nanocoulombs/mR) = B Where:C.F = correction f actor (efficiency) to be applied in calculating exposure of field TLDs = Net reading in nanocculombs A /l' = known exposure to TLDs The exposure to the TLDs (B) is calculated as follows: mR/hr = 8400 x mg Ra-226 r2 For our setup use the following parameters: Ra-226 = 0.0933 + 1.5% r = 19.6 cm Thus: mR/hr = 8400 x 0.0933 = 2,040 384.16 The total exposure (B) is equal to: B (mR) = 2.040 x hours of exposure to the Ra-226 needle. 131
Rev. 4, 6-01-84 / /' ~ / l Approved by: fvf? ' 7'/,//s6fttf_ cL.A. Huebner - 3. 7 Procedure for Preparation and Readout of TLD Chips Materials c 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, resul-ting in efficiency change. 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 hour at 400*C. 4. Cool quickly by placing the crucible on a metal plate.
- 5. ' Anneal for 2 hours 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.
J
- 11. Set parameter on the 2000P as follows:
HV - 470 V (It is 970 V, internal volts = 500). Readout time: 20" T1 - 140' C (Preset) Tg - 250* C (Preset) Rise time: -12*/sec (Preset) Preheat - 100* C (Preset) Start reading - 90* C 132 -,,+,,-,-.,r-, . -. + -.. -. - - - ~ - - - -, - ---u ,--a . - - - - - - - - - ~. , - +, - - - -
Rev. % 6-01-86 Section 3.7 (continued) ~12. Prepare the chips as follows (do-this before proceedino to the next step). 12.1 Turn on small muffler furnace or drying oven and adjust to 100*C. Use class thermometer. Muffler's indicator is. not accurate. Let furnace stabilize. -12.2 Unpack the chips (under reduced incandescent light) and gently i place them in the glass vials marked with appropriate location numbers. 12.3 Place the vials in the furnace. Preanneal for 10 min. at 100*C. i
- 13. Open the drawer and read the standard.
It should read 5.70+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 7 instrument). Note: Adjust bka 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 heatino plate, j.
- 18. After readout is completed, record the reading, open the drawer, and place next chip.
v
- 19. Repeat Steps 17 and 18 until all chips are read out.
Note: If.readinp will 'last longer than 1.5-2.0 hrs., check the standard and bkg about every 2.0 hrs. { l
- 20. After readout-is completed, turn off the gas.
t
- 21. For calculations, use computer program 0GTLD. PUB.
133
s i ~ Rev.4,6-01-84/, i Approved by: g. . // 24( /, t.Q'. Huebner 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. Reacents-Scintillation medium, insta-gel scintillator Tritium standard solution Apparatus Condenser Distillation flaski 250-ml capacity Liquid scintillation coun'ter Liquid scintillation counting vials Procedure i 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 distil-late for tritium analysis. 2. Dispense 13 ml of the distillate to a low potassium glass vial. 3. Prepare backaround and-standard tritium-water solutions for counting, using the same amount as _ the sample. Use low tritium backpround-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). '4. Dark-adapt all samples, backarounds, and standards. Add 10 ml [ of insta-gel scintillator. Count the samples, backgrounds and standards. Count samples containing less than 200 pC1/1 for 300 minutes and samples containino more than 200 pCi/l for 200 -minutes. 134 ~
Rev. 4, 6-01-84 Section 3.8 (continued) 5. Counting efficiency: Eff = cpm of Standard-com of background dpm Standard 6. Sample Concentration: ^ pCi/ml = 2.22 x E x V x e-At Where:A = net count rate (cpm) E = efficiency (cpm / dam) V = volume (ml) A = 0.693 = 0.05652 12.26 t = elapsed time from the time of collection to the counting time (in years) 7. Calculate tritium activity using computer program H3. o 135
p- ,%'k 4 sp Rev. 4, 6-01-84 /';// f, f Approved by: ~1' M Qf 4'R/ L 4..Gf Kueener 1, 3.9 Iodine-131 in Milk by Ion Exchanae on Anion Exchance Column After samples have been treted to convert all iodine in the sample to a coninon oxidation. state, the iodine is isolated by solvent extraction or a combination of ion exchange and solvent extraction steps. Iodine, as the iodide, is concentrated by adsorption on an anion ex-changed column. Following fa Nacl wash, the' iodine is eluted with sodium Iodine in the iodate form is reduced to 12 and the hypochlorite. elemental iodine extracted into CCl,'back-extracted into water then 4 finally precipitated as palladium iodide. m Chemical reco.very of the added carrier is determined gravimetrically from the PdI2 precioitate. 1-131 is determined by beta counting the PdI - 2 Reagents Anion exchange resin, Dowex 1-X8 (50-100 mesh) chloride form. -Carbon tetrachloride, CC14 - reagent grade. Hydrochloric acid, HC1, IN. Hydrochloric acid,' hcl, 3N,. 3 - HN 0H HCL wash solution: 50 ml Hg0; 10 ml IM,- NH 0H-hcl; 2 H O - HNO 2 2 10 ml conc. HNO - 3 Hydroxylamine hydrochloride, NH 0H hcl 1 M. 2 Nitric acid, HNO3 - concentrated. Palladium chloride, PdI, 20 mg Pd++/ml. (1.'2 g pdc 1 /100 ml 2_ 2 6N hcl). Sodit.g bis.ulfite, NaHS03 - 1 M. Sodium chloride, Nacl --2M_ Sodium hypochlorite, Na0C1 - 5% (Clorox). Yb .) 136
Rev. 4, 6-01-84 Section 3.9 (continued) Special Apparatus Chromatographic column, 20 mm x 150 mm (Reliance Glass Cat.#R2725T). Vacuum filter holder, 2.5 cm2 filter area Filter paper, Whatman #42, 21 mm Mylar Polyester gunned tape,1 1/2", Scotch #853 Drying oven A. Ion Exchange Procedure 1. Set up an ion exchange column of 20 mm diameter and 150 mm length. 2. Pour 20 ml of a slurry of Dowex 1-X8, Cl-form (50-100 mesh) into the column and wash down sides with water. Add 2 ml of I carrier to 2 liters milk, stir for 20 minutes. 4 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 ml increments, stirring resin as needed to eliminate gas bubbles and maintain flow rate of 2 ml/ min. Collect eluate in 250-ml beaker and discard the resin. B. Iodine Extraction Procedure 1. Acidify the eluate from step 7 using concentrated HNO3 to make the sample 2-3 N in HNO, and transfer to 250 m1 separatory 3 funnel. (Add the acid slowly with stirring until the vigorous reaction subsides.) Volume of concetrated HNO3 required will depend on eluate volume as follows): 137
Rev. 4, 6-01-84 Section 3.9 (continued) B. Iodine Extraction Procedure (continued) eluate volume concentrated HNO3 (ml) (ml) j 50-60 10 60-70 12 70-80 14 80-90 16 2. Add 50 ml of CCl4 and 10 ml of 1 M hydroxylamine hydrochloride (freshly prepared). Extract iodine into organic phase (about 2 minutes equilibration). Draw off the organic phase (lower phase) into another separatory funnel. 3. Add 25 ml of CCl4 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 no 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 H 0-HNO -NH 0H hcl wash solution to the separa-2 3 2 to ry funnel containing the CCl4 Equilibrate 2 minutes. Allow phases to separate and transfer CCl4 (lower phase) to a clean separatory funnel. Discard the wash solution. 5. Add 25 ml H O and 10 drops of 1 M sodium bisulfite (freshly 2 prepared) to the separatory funhel containing the CC1. 4 Eauilibrate for 2 minutes. Discard the organic phase (lower phase). Drain aqueous phase (upper phase) into a 100-ml beaker. Proceed to the Precipitation of PdI - 2 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 extraction procediire in step 5. 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. 138
Ree. 4, 6-01-84 Section 3.9 (continued) 1 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. . eighLa clean 21 mm Whatman #42 filter which has been stored W 5. over silica gel in a desiccator. 6. Place the weighed filter in the filter holder. Filter the sample and wash the residue with water and then with absolute alcohol.- 7. Remove filter from filter holder and place it on a stainless ' steel ~ planchet. i 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, gumed 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 in place, put it -directly over_ the precipitate and seal.the - edges 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 on the back side of the disc. 12. Count the sample on a proportional beta counter. 4 Calculations j Calculate the sample activity using computer program 1131.
Reference:
" Determination of 1-131 by Beta-Gamma coincidence Counting of PdI ". Radiological. Science Laboratory. Division of 2 Laboratories and Research, New York State Department of Health, March 1975, Revised February 1977. 4 4 ( s I 139
Y[/, /u////R f/ / j Rev. 4, 6-01-88 Approved by: h.G/ Huebner Section 8.1 8.1 Strontium-89 and Strontium-90 in Milk by Ion Exchance Principle of Method A citrate complex of yttrium, strontium, and barium carriers at the pH of milk is added to the milk sample. The mixture is then passed succes-sively through cation-and anion-exchange resin columns. Strontium, barium, and calcium are absorbed on the cation-exchange resin, and the yttrium carrier with the yttrium 90 daughter of strontium 90 is retained on the anion-exchange resin. The yttrium is eluted from the anion resin with hydrochloric acid and precipitated as the oxalate. Lanthanum 140, which may be a contaminant, is removed by dissolving yttrium oxalate in concentrated nitric acid and extracting yttrium from the solution into an equal volume of pre-equili-bated tributyl phosphate. The lanthanum 140 remains in the concentrated nitric acid to be discarded. Yttrium is re-extracted from the organic phase with dilute nitric acid and precipitated as the oxalate. The precipitate is weighed to determine recovery of yttrium carrier, then counted for yttrium 90 activity. Strontium, barium, and calcium are eluted from the cation-exchange resin with sodium chloride solution. Following dilution of the eluate, the alkaline earths are precipitated as carbonates. The carbonates are then converted to nitrates, and strontium and barium nitrate are precipi-t ated. The nitrate precipitate is dissolved, and barium is precipitated as the chromate, purified as the chloride, and then counted to determine the barium 140. From the supernate, strontium is precipitated as the nitrate, dissolved in water, and reprecipitated as strontium nitrate. The nitrate is converted to the carbonate, which is filtered, weighed to determine strontium carrier recovery, and counted for " tot al radio-strontium". The concentration of strontium-89 is calculated as the difference between the activity for " total radiostrontium" and the activity due to strontium-90. Reagents Ammonium acetate buffer: pH 5.0 Anrnonium hydroxide, NH 0H: concentrated (15N,) 4 Ammonium oxalate, (NH )2 2 4.H 0: IN 4 C0 2 Anion-exchange resin: Dowex 1-X8 (CI-form, 50-100 mesh) Carrier solutions: Ba+2 as barium nitrate, Ba(NO )2: 20 mg Ba+2 per ml 3 I Sr+2 as strontium nitrate, Sr(NO )2: 20 mg Sr+2 per ml 3 Y+3 as yttrium nitrate, Y(NO ): 10 mg Y+3 per ml 3 Cation-exchange resin: Dowex 50W-X8 (Na+ form, 50-100 mesh) Citrate solution: 3N (pH 6.5) 140
Rev. 4 6-01-84 0 Section 8.1 (Continued) Diethyl ether, (C H )2: anhydrous 25 Ethyl alcohol, C H 0H: absolute (100%), 95% 25 Hydrochloric acid, hcl: concentrated (12N, 6N*, 2,f4*) Hydrochloric acid-diethyl ether, hcl-(C H )2 :5.1 v/v 25 0 Nitric acid, HNO : fuming (90%), concentrated (16N)*,14N, 6N, 0.1 N* 3 0xalic acid, H C 04 2H 0:2N* 22 2 CO :3N, 0.1 N Sodium carbonate, Na2 3 Sodium chloride, Nacl:4N C 4 Sodium chromate, Na2 r0 :3N PO : pre-equilibrated with 14,N HNO
- Tri-n-butyl phosphate (TBP), (C H )3 4
3 49
- Starred reagents are used only in processing the anion column effluent to determine strontium-90 concentration (Part A).
1 4 Apparatus-Ion-exchange system: The apparatus for this system is illustrated in Figure 8.1-1. It consists of three glass components connected one above the other for gravity flow. At the top is. a graduated,
- 1-liter glass separatory funnel which serves as the reservoir.
Below it is connected a 250 ml glass column, 5 cm in diameter and 25 cm long, which services as the cation column. Below this is connected the anion column, a 30-ml glass column, 1.9 cm in dia-meter and 10.5 cm long. Both columns have extra coarse, fritted glass disks at the bottom. Five milliliters of distilled water are placed in the 30-ml column, and 15 ml Dowex 1 resin are poured into it. The cation column is filled by adding 170 ml Dowex 50W resin in the same way. Millipore filtering apparatus (Pyrex Hydrosol Microanalysis Filter Holder) l l Millipore Type OH membrane filter, 1.5-p pore size, 2.5-cm diameter low-background beta counter. i i 141
Rev. 4, 6-01-84 r [ s-uf tn c ass l RESERVOIR 4 l .\\ froansTC4Y fumm((f i n L -.......s ll l 0 i~. m e, / aso-at etass coturant y)a.,'.;.. \\wivm ameTTro etass cisul i CATION RE31N ... ~. N .p;. 1 1 4 .e.. n I l u 0 / 33* tA GLASS COLhasht ,\\ DiTu pat?TED st agg giggl 1 ':P AMCN RE31N i,,]p;. ? t i s n V I r <.'# 8 Ior.-exchat:ge system a.+ 142
Rev 4 6-01-84 o Section 8.1 - Part A Part A. Strontium-90 Procedure 1. Place 1 liter of milk into the graduated reservoir. Pipette 1.0 mi each of yttrium, strontium and barium carrier solutions into 10 ml of citrate solution: ' swirl to mix and dissolve the - barium citrate which forms. Transfer this mixture quantita-tively to the milk with 5 ml of distilled wa.er, and mix well. 2. Open the stopcocks of the reservior, anion column, and cation column, in that order. NOTE THE TIME. Control the flow rate at 10 milliliters per minute -(ml/ min) with the anion column stop-cock. Check occasionally by collecting effluent for 1 minute in a graduated cylinder. Stop flow when just enough milk remains in the columns to cover resin. NOTE THE TIME. Discard the effluent-milk. RECORD THE MIDPOINT OF THE ELUTION PERIOD AS THE BEGINNING OF YTTRIUM 90 DECAY. 3. Replace the milk reservoir with a separatory funnel containing 300 ml of warm distilled water, and let the water flow through the columns at approximately _10 ml/ min to displace the milk. Stop the flow when just enough water remains in the columns to cover the resin. Discard the effluent water. 4. Separate the columns. In order to collect eluate for " total radio-strontium", barium, and calcium determinations, and to regenerate the cation column for subsequent use, follow Step 5, Part B. 5. Gradually add 75-100 ml of 2N hcl to the anion colum. Control the effluent flow at 2 ml/ min. Collect eluate in a 250-ml centrifuge bottle. 6 '. Add 5 ml of 2N oxalic acid to the eluate and adjust the pH to 1.5with6NNQ0HusingapHmeter. 7. Stir and heat to near boiling in a water bath (approx. 20 min). 8. Cool in an ice bath and centrifuge. Decant and discard the supernatant. Proceed as in (a) or (b) depending on whether Ba-La-140 is absent or present from the gamma analysis of the sample. (a) If fresh fission products are known to be absent: Dissolve the ppt in 10 ml of HNO, filter solution through 3 Whatman No. 541 paper into a 40 ml centrifuge tube. Wash paper, collecting the washing in tube and continue as in Step A-9, 143
i Rev. 4 6-01-84 0 Section 8.1 - Part A (Continued) (b) If fresh fission products are present: in 10 ml of HNO, transfer the solution 3 Dissolve the ppt to a 60 mi separatory funnel, washing the tube with addi-tional 10 ml of HNO. Add 10 ml of equilibrated TBP, 3 shake 2-3 min, and when separated drain and discard the lower acid phase. Add 15 ml of 14N HNO3 to the separa- ~ tory funnel, shake 2-3 min, drain and discard the lower acid phase. Repeat the 14N HNO3 treatment to remove eight lanthanide elements and La-140. Add 15 ml of H O 2 to the separator and shake. Drain the lower phase into a 125-ml centrifuge tube. Repeat the wash, using 15 ml of 0.lN,HNO, adding it to the centrifuge tube. 3 Add 5 ml of 2N oxalic acid to the purified yttrium solution 9. from (a) or (bT. Adjust to a pH of 1.5 with NH 0H, using a pH 4 meter. 10. Digest the solution in a hot H O bath for 10 min. with occa-2 sional stirring. Cool in an ice bath (20 min). Wash 11. Filter on a weighed Whatman No. 42 (2.1 cm) filter paper. with H 0, ethyl alcohol and ether and dry at room tempera-2 ture and weigh. 12. Mount and count in a proportional counter. If analysis for Sr-89 is not required, disregard Section 13. 8.1-Part B. Use the computer program SR8990 to calculate (Sr-90) activity. 1 l 144
Ree. 4, 6-01-84 i Section 8.1 - Part B Part B Total Radiostrontium (Sr-89 separation) Procedure l Continue following columns separation (Step A-4). 5. Connect 1 1 separator funnel containing 1 1 of 4N Nacl to the cation column. Allow the solution to flow at 70 ml/ min to elute the alkali metal and alkaline earth ions and to recharge the column. Collect 11 of' eluate into a 21 beaker, but leave the resin covered with 2-3 ml of solution. 6. Wash the column with 500 ml of H 0 or more to remove excess 2 Nacl. Discard the wash. 7. Remove 20 ml of the Nacl eluate into a small bottle for the determination of stable calcium. (See section 6.1). 8. Dilute the eluate to 1500 ml with distilled water. 9. Heat the solution to 85*-90* C (near boiling on a hot plate) and add, with constant stirring, 100 ml of 3N Na2CO. Stir 3 gently while on hot plate to prevent bumping. Let stand overnight. 10. Decant most of the supernate. Transfer the precipitate to a 250 ml centrifuge bottle. 11. Wash the precipitate twice with 50 ml portions of H 0. Dry 2 it in an oven at 110* C for 1-2 hours. 12. Dissolve the ppt slowly with vigorous stirring in 10 ml of 6N HNO3 (with magnetic stirrer). Filter through Whatman No. 54T paper into a 40 ml centrifuge tube. Rinse the bottle with little 6N HNO3 and pour the washings through the paper. To the filtrate, add slowly 30 ml of 21N HNO3 (fuming). Stir well and cool in an ice bath. CentriTuge and discard super-natant. 13. Carefully add 30 ml of conc. HNO3 to the precipitate. Heat in a H O bath with stirring for about 30 minutes. Cool the 2 solution in an ice water bath for about 5 minutes. Centrifuge and discard supernatant. 14. Repeat step No. 13. 145
?ev a, 6.... ' Section 8.1 - Part B (Continued) 10 ml. of H O and 5 ml. of NH AC buffer 15. Dissolve the ppt. in 2 4 and heat in a water bath: Adjust pH to 5.5 using a pH meter and add immediately 1 ml. of 3N_ Na2 r04 and mix well. Digest C in a water bath for 5 min., centrifuge and decant the super-natant into another 40 ml. centrifuge tube. 16. Heat the supernate in a water bath. Adjust the pH to 8-8.5 NH 0H. With continuous stirring, cautiously add 5 ml with 4 of 3N Na2CO3 solution. Heat gently for 10 minutes. Centri-fuge and decant the supernate. Wash the strontium carbonate precipitate with 0.1 N_ Na200. Centrifuge again, and decant 3 the superitate. 17. Dissolve the carbonate precipitate in 5 ml of 6N HNO. With 3 continuous stirring, cautiously add 30 ml of fiiming HNO3 to the solution. (Stirring tl.e solution longer helps in the precipitation of the strontium nitrate.) Cool in ice bath, centrifuge and decant the supernate. 18. Dissolve the strontium nitrate precipitate in 3 ml of H O and 2 5 ml of 6N HNO. Add cautiously, with continuous stirring, 3 20 ml of Tuming HNO. Cool in an ice bath, centrifuge and 3 discard supernatant. RECORO TIME AS BEGINNING OF Y-90 INGROWTH. 19. Dissolve the precipitate in 10 ml of Hg0. Heat in a water bath. Adjust the pH to 8-8.5. With continuous stirring, add 5 ml of 3 N Na2CO3 solution. Heat gently for 10 minutes. 20. Cool and filter on a weighed No. 42 Whatman (2.1 cm) filter paper. Wash thoroughly with water and alcohol. 21. Dry the precipitate in an oven at 105* C or under the lamp for 30 minutes. Cool and weigh. 22. Mount and count without delay in a proportional counter as total strontium. 23. Calculate Sr-89 and Sr-90 activitylpC1/1)using computer program SR8990. 146 I l
Rev. 4, 6-01-84 -f I Section 8.1 (Continued) ~ Calculations .Part A. Strontium 90 concentration (pCi/ liter) = BxCxD ExF Where:A = net beta count rate of yttrium 90 (cpm) B = recovery of yttrium carrier C = counter efficiency for counting yttrium-90 or yttrium oxalate mounted on a 2.1-cm diameter membrane filter (cpm /pCi) D = sample volume (liters.)t for yttrium-90 decay, where t is E = Correction factor e -^ the time from midpoint of the elution time of milk (Step A-2) to the time of counting. F = Correction factor 1-e-At for the degree of equilibrium i - . attained during the yttrium-90 ingrowth period, where t is the time from collection of the milk sample to the time of passage through the. column (Step A-2) Part B. Strontium 89 concentration (pCi/ liter) = f,g h - F (GxH + IxJ) Where: A = net beta count rate of " Total radiostrontium" (cpm) .l-B = counter efficiency for counting strontium-89 as strontium oxalate mounted on a 2.1-cm diameter membrane filter i (cpm /pCi) t i C = correction f actor e-At for strontium-89 decay, where t is the time from sample collection to the time of counting 0 = recovery of strontium carrier E = volume of milk sample (liters) F = strontium 90 concentration (pCi/ liter) from Part A G = self-absorption factor for strontium-90 as strontium oxalate mounted on a 2.1-cm diameter filter, obtained from i a'self-absorption curve prepared by plotting the fraction of a standard activity absorbed against density thickness 2 of the sample (mg/cm ) H = counter efficiency for counting strontium-90 as strontium oxalate mounted on a 2.1-cm diameter membrane filter j (cpm /pCi) I = counter efficiency for counting yttrium-90 as yttrium oxalate mounted on a 2.1-cm diameter membrane filter (cpm /pCi) i l i j 147
Rev. 4 6-01-84 0 Section 8.1 (Continued) J= correction factor 1-e-A t for yttrium-90 ingrowth, where it is the time from the last decantation of the nitric acid (Step B-18).
Reference:
Radioassay Procedures for Environmental Samples U.S. Depart-ment of Health, Education and Welfare. Environmental Health Series, January 1967. 1 i 148
Approved by: < F t.u d //Q L.G/ Hueoner Section 8.4 8.4 Strontium 89 and Strontium 90 in Water Samples A. Principle of Method The acidified sample of clear water with stable strontium, barium and calcium carriers is treated with oxalic acid at L pH of 3.0 to precipitate insoluble oxalates. The oxalates are dissolved in nitric acid and strontium nitrate is separated from calcium as a precipitate in 70% nitric acid. The residue is purified by adding iron and rare earth carriers and precipitating them as hydroxides. After a second strontium nitrate precipitation from 70% nitric acid, the nitrates are dissolved in water and with added yttrium carrier, are stored for ingrowth of yttrium-90. The strontium is again precipitated and separated from 70% nitric acid with the yttrium nitrate being in the supernate. Each fraction is precipitated separately as an oxalate and collected on No. 42 (2.1 cm) Whatman filter or planchet for counting either total radiostrontium or yttrium-90 or both. Reagents Acetic acid, CH C00H: 1.5N 3 Ammonium acetate, NH C H 0 : 3N 4232 Ammonium acetate buffer: pH 5.0 Ammonium hydroxide, NH 0H: concentrated (15 N), 6 N, 1 N 4 Ammonium oxalate, (NH )2 2 4.H 0: 0.5% w/v 4 C0 2 Carrier solutions: Ba+2 as barium nitrate, Ba(NO )2: 20 mg Ba+2 per ml 3 4H 0: 40 mg Ca+2 per ml Ca+2 as calcium nitrate, Ca(NO )2 2 3 Sr+2 as strontium nitrate, Sr(N0 ): 20 mg Sr+3 per ml 2 Y+3 as yttrium nitrate, Y(NO )3: 10 mg Y+3 per ml 3 Hydrochloric acid, hcl: concentrated (12 fj,), 0.5 N Hydrogen peroxide, H 0 : 30% solution 22 Nitric acid, HNO : fuming (90%), concentrated (16 N), 6 N, 3N 3 0xalic acid, H C 0. 2H 0: Saturated at room temperature 222 2 Scavenger solutions:,20 mg Fe+3 per ml, 10 mg each Ce+3 and Zr+4 per ml Fe+ as ferric chloride, FeCl.6H 0 3 2 Ce+3 as cerous nitrate, Ce(NO )3 6H 0 3 2 Zr+4 as zirconyl chloride, Zr0Cl.8H 0 2 2 CO :3N, 0.lN Sodium Carbonate, Na2 3 Sodium Chromate, Na2 r0 :3fj, C 4 Apparatus Analytical balance I Low background beta counter Medium - porosity filter stick pH meter 14')
Rev. 4, 6-01-84 Section 8.4 A 'Part A. Strontium 89 Procedure 1. Filter 1 liter of-an acidified water sample using millipore filter paper. 2. . Digest the filter paper with the residue with concentrated nitric acid (HNO ) 'until all the organic matter is removed. 3 - 3. Evaporate to dryness and dissolve the residue with hot water and filter using No. 541 Whatman filter paper. 4. Combine the filtrates in a 2 liter beaker. j 5. Add 1 ml of strontium carrier solution, 1 mi barium carrier solu-tion, and if necessary,1 ml of calcium carrier solution. (Improved i l precipitation may be obtained by adding calcium to soft waters.) Stir thoroughly and while stirring add 125 ml of saturated oxalic acid solution. 6. Using a pH meter, adjust the pH to 3.0 with 15 N, NH 0H, and allow 4 the precipitate to settle for 5-6 hours. 7. Decant most of the supernate (liquid) and transfer the precipitate to a 250 ml centrifuge bottle. Wash the precipitate and the beaker wall with 0.5% ammonium oxalate and centrifuge. Discard the super-nate. 8. Dissolve the precipitate with 10 ml of 6 N HNO3 and transfer to a 250 ml beaker. Then use 20 ml of 16 N HNO3 to rinse the centri- ~ fuge tube and combine it to the solutlon in the 250 ml beaker. 9. Evaporate the solution to dryness. Cool; then add 50 ml 16 N_ HNO3 and repeat the acid addition and evaporation until the residue is colorless. 10. Transfer the residue to a 40-ml centrifuge tube, rinsing with a minimum volume of 16 N HNO. Cool in a refrigerator overnight. 3 Centrifuge at 1500-1800 rpm for 10 minutes, and discard the super-nate. 11. Dissolve the precipitate in 5 ml of 6N HNO3 and then add 30 ml of fuming nitric acid. Centrifuge, and dfscard the supernate. 12. Dissolve the nitrate precipitate in about 10 ml of distilled water. Add 1 ml of scavenger solution. Adjust the pH of the mixture to 7 with 6 N HN 0H. Heat, stir, and filter through a Whatman No. 541 4 filter. - Discard the mixed hydroxide precipitate. 150
Rev. 4, 6-01-64 Section 8.4 A (continued) Part A. Strontium 89 Procedure (continued) 13. To the filtrate add 5 ml of ammonium acetate buffer. Adjust the pH t NH 0H to pH 5.5. (Note: the pH of the solution with 3N HNO3 or 4 at this point is critical.) Add dropwise with stirring 1 ml of 3N, Na2 r04 solution. Heat in a water bath. C 14. Cool and centrif uge. Decant the supernate into another centrifuge tube. Save the precipitate for Ba analysis if needed. 15. Heat the supernate in a water bath. Adjust the pH to 8-8.5 with NH 0H. With continuous stirring, cautiously add 5 ml of 3N Na2CO3 4 solution. Heat gently for 10 minutes. Cool, centrifuge, an3 decant the supernate. Wash the precipitate with 0.1N_ Na2C0. Centri-3 fuge again and decant the supernate. 16. Dissolve the precipitate in no more than 4 ml of 3N HNO. Then 3 add 20-30 ml of fuming HNO, cool in a water bath, aiid centrifuge. 3 Decant and discard the supernate. 17. Repeat step 16. Then, RECORD THE TIME AND DATE AS THE BEGINNING OF YTTRIUM 90 INGROWTH. If no immediate count of total radiostrontium is desired add to the precipitate 1 ml of yttrium carrier solution and 4 ml of 6N HNO3 and store 7-14 days to allow the yttrium 90 to grow in. 18. To determine tot al radiostrontium, dissolve the precipitate in 10 ml of water. Heat in water bath. Adjust the pH to 8-8.5. With continuous stirring add 5 ml of 3ti Na2CO3 solution. Heat gently for 10 minutes. 19. Cool and filter on a weighed No. 42 (2.1 cm) Whatman filter paper. Wash thoroughly with water and alcohol. 20. Dry the precipitate under the lamp for 30 min. Cool and weigh. 21. Mount and count without delay its beta activity as " total radio-strontium" in a proportional counter. 151
Rev. % 6-01-84 Section 8.4' Part B. Strontium 90 Procedure 1. After. counting total radiostrontium dissolve the precipitate on the filter in 6 N HNO3 and transfer the solution to a 40 ml centrifuge tube. The total volume of dissolution and rinsing should be about 4 ml. 2. Add 1 ml of yttrium carrier solution and store until 7 to 14 days have elapsed since step 17 was completed. 3. Heat the equilibrated strontium-yttrium sample in a water bath at approximately 90*C. Adjust the pH to 8 with NH 0H, stirring 4 continuously. .4. Cool to room temperature in a cold water bath and centrifuge for 5 minutes. Record the hour and date of decantation as the end of the yttrium-90 ingrowth and the beginning of its decay in the yttrium fraction. 5. Dissolve by adding about 4 drops of hcl with stirring. Add 15-20 ml of water. Heat in a water bath and adjust the pH to 8 with NH 0H, 4 stirring continuously. 6. -Cool to room temperature in a cold water bath and centrifuge for 5 minutes. 7. Repeat steps 5 and 6. 8. Add 3 drops of hcl to dissolve the precipitate, then add 20 ml of water. Filter using No. 541 filter paper. Heat in a water bath at approximately 90* C. Add 1 ml of saturated oxalic acid solution dropwise with vigorous stirring. Adjust to a pH of 2-3 with NH 0H. 4 Allow the precipitate to digest for about an hour. 9. Cool to room temperature in a cold water bath. Centrifuge for 10 minutes and decant most of the supernate. Filter by suction on a weighed filter paper. Wash the precipitate with water and alcohol. 10. Dry the precipitate under the lamp for 30 minutes. Cool and weigh. Mount and count without delay in a proportional counter. 11. Calculate Sr-89 and Sr-90 activity in pCi/l using the computer program for Sr-89,90. 152 l J
Rev. 4, 6-01-66 Section 8.4 (continued) Part B. Strontium 90 Calculations For formulas used refer to Section 8.1.
Reference:
Radioassay Procedures for Environmental Samples U.S. Department of Health, Eduction and Welfare. Environ-mental Health Series, January 1967. 153
r Rev. 4, 6-01-34 / << J / 71 Approved by: />W/u2////L L*.G / Huebner Section 8.6 8.6 Strontium-89 and Strontium-90 in Milk (Ash), Veaetation, Fish, Wildlife, Soil and Bottom Sediment Samples - Sodium Carbonate Fusion. E Principle of Method Strontium is separated from calcium, other fission products and other ~g; natural radioactive elements. Fuming nitric acid separations remove the . calcium and most of the other interfering ions. Radium, lead, and barium ,~ j-are removed with barium chromate. Traces of other fission products are scavenged with yttrium hydroxide. After the Sr-90 and Y-90 equilibrium l has been attained, the Y-90 is precipitated as the hydroxide and con-verted to the oxalate for counting. Strontium is precipitated as the carbonate and counted for total activity. Strontium-89 activity is computed as the difference between the total radiostrontium and the strontium-90 (as yttrium-90) activity. Reagents Anunonium acetate buffer, (NH )2 Ac:pH = 5.0, 6M, 4 Ammonium hydroxide, NH 0H:6N, 4 Carrier Solutions-Ba+2, Ba(No3 2:20 mg/ml of Ba+2 Fe+3,Fe(N0 3, scavenger:5mgm1ofFe+3 Sr+2,Sr(N0
- 20 mg/mi of Sr l
Y+3, Y(NO ) 0 mg/mi of Y+3 3 4 Ethyl alcohol, C H 0H: absolute 25 Hydrochloric acid, hcl:12N (conc. ) Nitric acid, HNO : 16N (coiic.), 6N, 3N, fuming 3 i Oxalic acid, H C 04: saturated 22 Potassium nitrate, KNO : powdered 3 00 : powdered, 3N, 0.1N Sodium carbonate, Na2 3 Sodium chromate, Na2 r0 :3N C 4 4 Sodium hydroxide, Na0H:pelTets ) Apparatus Teflon filter holder, or filter funnel and sample mount rings and discs K Magnetic stirrers with Teflon-Coated magnet bars Mylar film l Glass fiber filters Fisher filtrator Brinkman dispenser - pipettor 154 . ~. - - -
Hev. 4, 0-U1-o Section 8.6 A Part A. Sample Preparation - Sodium Carbonate Fusion Procedure 1. Weich out 3 g of ashed sample c silted soil and set aside. 2. Sift into a 250 ml nickel crucible enough Na2C03 to very lightly cover the bottom. 3. Add 30 g of NaOH pellets and 5 g of KNO - 3 4. Add the weigned ash sample and tap the crucible gently to shake the ash down among the pellets. 5. Sift from 10 to 20 grams of Na2CO3 over the ash so it is completely covered. 6. Place in a muffle furnace at 600*C for 20 to 30 minutes to melt and fuse the mixture. NOTE: If carbon materials remain floating on the surf ace of the melt, cautiously add a few grains of KN03 and heat for another 5 to 10 minutes. Decomposition of organic matter is complete when no further reaction is noticed on addition of KNO - 3 7. Using a long-handled tongs, remove the crucible from the muffle furnace and immediately, but very cautiously, cool in an ice bath until the melt is completely solidified and cool enough to handle without gloves. NOTE: It is very important that no moisture come in contact with the melt at this time. One drop of water in the crucible could render the melt very difficult, if not impossible, to remove. 8. Transfer the melt to a 250 ml centrifuge bottle using distilled water and stir until completely dispersed. NOTE: Rotating the crucible in the palm of one's hand and very gently applying pressure should be sufficient to loosen the melt from the sides of the crucible. 9. Add 2 ml of strontium and 1 ml of barium carriers. 10. Bring to a gentle boil, cool, centrifuge and discard the supernatant. 155
Section 8.6 A (continued) Part A. Sample Preparation - Sodium Carbonate Fusion Procedure (continued) 11. To the residue add 50 ml 3N Na2CO3 as a wash, swirl and disperse the residue, heat for 10 mTnutes in a hot water bath, centrifuge and discard the supernatant. 12. Repeat step (11) three times to put the precipitate in a suitable form for further analysis. 13. Dissolve the precipitate in 50 ml of concentrated HNO, transfer 3 to a 250 mi beaker, and take to dryness on a hot plate. NOTE: Evaporation may be done rapidly at first, and then very slowly to prevent spattering. A jelly-like substance may form at this point, due to hydrated silicic acid formed from the soluble silicates and will be removed in the following steps. 14. Bake the remaining residue for at least I hour at 120* to 130* C, cool, moisten the salts with 5 ml of HNO3 and allow to stand at room temperature for 10 minutes. Then place on a hot plate, bring to a boil and add 45 ml of boiling water. DISPERSE ANY REMAINING RESIDUE WITH A GLASS STIRRING R00 AND FILTER IMMEDIATELY into a 250 mi beaker. Use Whatman No. 541 hardened filter paper. NOTE: To separate the silicic acid the hydrated acid must be changed to a less hydrated and less soluble acid by baking at 100* to 130*C. It is important at this point that evaporation be to com-plete dryness. (There should no longer be a smell of acid). Addition of 5 ml of HNO3 converts any metal oxides which may have been formed back to nitrates so they will be dissolved and not removed with the silicTtes. Filtering must be done immediately as some of the silicates will tend to go back into solution. Also, due to this fact, removal of silicates by dehydration is not 100% efficient and the process must be repeated at least once and more oftt.n if necessary. 15. Evaporate and repeat step (14) at least once, and again as often as necessary. 156
Rev. 4, 6-01-84 Section 8.6 A (c'ortinuedi Part A. Samole Preparation - Sodium Carbonate Fusion Procedure (continued) 16. Evaporate the solution in a beaker to dryness on a hot plate. Cool, then add 40 ml of concentrated HNO3 and evaporate to 20-25 ml. Then add another 40 ml HNO3 and repeat the procedure. NOTE: The liquid portion of the sample at this point will be yellow. Should the color toward the end of the first evaporation be red-brown, or black, add more nitric acid and repeat the above procedure as often as necessary to obtain a clear yellow solution. The dark samples described above have been known to explode if evaporated to cryness without adding additional portions of nitric acid. These samples should be handled in a hood with the window down as far as possible to prevent possible personal injury to the operator. This step is to destroy any remaining organic materials. The darker colored solutions contain large amounts of organic matter. 17. Complete the analyses as described under Determination.
References:
The basis for this procedure was presented by J.J. Bolan in the Public Health Service Manual, titled " Chemical Analysis of Environmental Radionuclides, Determination of radio-strontium in food" (1.ll.3.A(8.65)). Modifications to this procedure were made by the North Dakota State Department of Health. 157
Rev. 4, 6-01-84 Section 8.6 A (c'ontinued) Part A. Samole Preparation - Sodium Carbonate Fusion Procedure (continued) 16. Evaporate the solution in a beaker to dryness on a hot plate. Cool, then add 40 ml of concentrated HNO3 and evaporate to 20-25 ml. Then add another 40 ml HNO3 and repeat the procedure. NOTE: The liquid portion of the sample at this point will be yellow. Should the color toward the end of the first evaporation be red-brown, or black, add more nitric acid and repeat the above procedure as often as necessary to obtain a clear yellow solution. The dark samples described above have been known to explode if evaporated to dryness without addino additional portions of nitric acid. These samples should be handled in a hood with the window down as far as possible to prevent possible personal injury to the operator. This step is to destroy any remaining organic materials. The darker colored solutions contain large amounts of organic matter. 17. Complete the analyses as described under Determination.
References:
The basis for this procedure was presented by J.J. Bolan in the Public Health Service Manual, titled " Chemical Analysis of Environmental Radionuclides, Determination of radio-strontium in food" (1.ll.3.A(8.65)). Modifications to this procedure were made by the North Dakota State Department of Health. 157
Rev. 4J 6-01 Section 8.6 B. Part 8,. Determination I. Strontium - 89 Procedure 1. Transfer the soiution to a 40 ml conical, heavy-duty centrifuge tube using a minimum of conc. HNO. Cool the centrifuge tube in 3 an ice bath for about 10 minutes. Centrifuge and discard the supernatant. NOTE: The precipitate consists of calcium, stror' tium and barium-radium nitrates.. The supernatant contains part of the sample's calcium and phosphate content. 2. Add 30 ml of conc. HNO3 to the precipitate. Heat in a hot water bath with stirring for about 10 minutes. Cool the solution in an ice bath with stirring for about 5 minutes. Centrifuge and discard the supernatant. NOTE: Additional calcium is removed from the sample. Nitrate precipitations with 70% HNO3 will afford a partial decontamination from soluble calcium while strontium, barium, and radium are completely precipitated. The separation of calcium is best at 60% HNO, however 3 at 60% the precipitation of strontium is not complete. Therefore, it is common practice to precipitate Sr(NO )2 3 with 70% HNO3 which is the concentration of comercially available 16 _N HNO - 3 Most of the other fission products, induced activities and actinides are soluble in concentrated HNO3 affording a good " gross" decontamination step from a wide spectrum of radionuclides. The precipitation is usually repeated several times. 3. Repeat step (2) two more times. 4. Dissolve the nitrate precipitate in about 10 ml distilled water. Add 1 ml of scavenger solution. Adjust the pH of the mixture to 7 with 6 N NH 0H. Heat, stir, and filter through a Whatman No. 4 541 filter 7 Discard the mixed hydroxide precipitate. 158
%. ':. 4, 6 M 'Section 8.6 Part B Determination I. Strontium-89 Procedure (continued) 5. To the filtrate add 5 ml of ammonium acetate buffer (pH 5.0). Adjust the pH to 5.5 with 3N HNO3 or 6N NH 0H. (Note: The 4 pH of the solution at this point is critTcal. Barium chromate will not precipitate completely in more acidic solution and strontium will partially precipitate in more basic -solutions.) ~ Add dropwise with stirring 1 ml of 3N Na2 r04 solution. Heat C in a water bath to about 90*C and centrifuge. Decant the super- ) nate into another centrifuge tuDe. Save the precipitate for Ba j analysis if needed. 6. Heat the supernate in a water bath. Adjust the pH to 8-8,5 with NH 0H. With continuous stirring, cautiously add 5 ml-of 3M 4 Na2003 solution. Heat. gently for 10 minutes. Centrifuge, and when completeness of precipitation has been verified by adding a few drops of Na2 CO, centrifuge and decant the supernate. 3 Wash the strontium carbonate precipitate with 0.lN Na200 - Centrifuge again, and decant the supernate. 3 7. Dissolve the carbonate precipitate in 5 ml 6N HNO. With 3 continuous stirring, cautiously add 20 mi fuming HNO3 to the i solution. (Stirring the solution longer helps in the precipita-tion of strontium nitrate). Cool in an ice bath, centrifuge and decant the supernate. 8. Dissolve the strontium nitrate precipitate in 3 ml H O and 5 ml 2 6N HNO. Add cautiously, with continuous stirring, 20 ml-3 fiiming HNO. Cool in ice bath, centrifuge and discard super-3 natant. RECORO TIME AS BEGINNING OF Y-90 INGROWTH. 9. Dissolve the precipitate in 10 ml of H 0. Heat in a water 2 j. bath. Adjust the pH to 8-8.5. With continuous stirring, add 5 ml of 3Ni Na2CO3 solution. Heat gently for 10 minutes. 10. Cool and filter on a weighed No. 42 (2.1 cm) Whatman filter paper. Wash thoroughly with water and alcohol. i 11. Dry the precipitate under the lamp for 30 minutes. Cool and 1 weigh. l 12. Mount and count without delay in a proportional counter as total radiostrontium. 1 i 159 I
r Rev. 4, 6-01-84 Section 8.6 Part B Determination II. Strontium-90 Procedure 1. After counting tot al radiostrontium, dissolve the strontium carbonate precipitate on the filter in 6N HNO3 and transfer the solution to a 40 ml centrifuge tube. ~The total volume of dissolution and rinsing should be about 4 ml. 2. Add 1 ml of yttrium carrier solution and store until 7 to 14 days have elapsed since Step B-I-8 was completed. 3. Heat the equilibrated strontium-yttrium sample in a water bath at approximately 90* C. Adjust the pH to 8 with NH 0H, 4 stirring continuously. 4. Cool to room temperature in a cold water bath and centrifuge for 5 minutes. Discard the supernate, record the time and date of the decantation as the end of the yttrium-90 ingrowth and the beginning of its decay in the yttrium fraction. 5. Dissolve precipitate by adding about 4 drops of hcl with stirrina. Add 15-20 ml of water. Heat in a water bath and adjust the pH to 8 with NH 0H, stirring continuously. 4 6. Cool to room temperature in a cold water bath and centrifuge for 5 minutes. Discard supernate. 7. Reper? steps 5 and 6, 8. Add 3 drops of hcl to dissolve the precipitate, then add 20 ml of water. Filter the solution using No. 541 Whatman hardened filter paper. Heat in a water bath at approximately 90* C. Add 1 ml of saturated oxalic acid solution dropwise with vigorous stirring. Adjust to a pH of 2-3 with NH 0H. Allow 4 the precipitate to digest for about an hour. 9. Cool to room temperature in a cold water bath. Centrifuge for 10 minutes and decant most of the supernate. filter by suction on a weighed filter paper. Wash the precipitate with water and absolute ethyl alcohol. 10. Dry the precipitate under the lamp for 30 minutes. Cool and weigh. Mount and count without delay in a proportional counter as Y-90 (Sr-90). 11. Calculate Sr-89 and Sr-90 activity using the computer program for Sr-89,-90. 160
r I ce.
- 4. 6-01-34 Section 8.6 B (continued)
Part B Determination II. Strontium-90 Calculations Strontium-90 concentration (pCi/g) = BxCxD ExF a. Where: A = net beta count rate of yttrium-90 (cpm) B = recovery of strontium carrier C = efficiency for counting yttrium-90 as yttrium oxalate (cpm /pci) D=samplesize(ingramsgforyttrium-90 decay,wheretisthe E = correction factor e-A time from decantation of the strontium supernate (Step B-II-4) to the time of counting (Step B-11-10) F = correction f actor 1 - e-At for the degree of equilibrium attained during the yttrium-90 ingrowth period, where t is the time from strontium separation (Step B-I-8) to the time of strontium removal (Step B-II-4). - F(GxH + IxJ) b. Strontium-89 concentration (pCi/g) = B C Where: A = net beta count rate of " total radiostrontium": (cpm) B = counter efficiency for counting strontium-89 as strontium oxalate mounted on a 2.1 cm diameter membrane filter (cpm /pCi) C = correction factor e At for strontium-89 decay, where t is the time from sample collection to the time of counting D = recovery of strontium carrier E = sample size (in grams) F = strontium-90 concentration (pCi/g) G = self-absorption factor for strontium-90 as strontium oxalate mounted on a 2.1 cm diameter membrane filter H = counter efficiency for counting strontium-90 as strontium oxalate mounted on a 2.1 cm diameter membrane filter (cpm /pC1) I a counter efficiency for counting yttrium-90 as yttrium oxalate mounted on a 2.1 cm diameter membrane filter (cpm /pCl). J = correction f actor 1 - e-At for yttrium-90 ingrowth, where t is the time from the last decantation of the nitric acid supernate from the strontium nitrate precipitate to the time of counting (Step B-1-8).
References:
Radioassay Procedures for Environmental Samples. U.S. Department of Health, Education and Welf are Environmental Health Series, January 1967. HASL Procedure Manual edited by John H. Harley, 1972. I 161 . __ _ ____________}}