ML20203Q104
| ML20203Q104 | |
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|---|---|
| Site: | Byron  |
| Issue date: | 12/31/1985 |
| From: | TELEDYNE ISOTOPES MIDWEST LABORATORY |
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BYRON STATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING ANNUAL REPORT 1985 TELEDYNE IS0 TOPES MIDWEST LABORATORY NORTHBROOK, ILLIN0IS MARCH 1986
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BYRON STATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING ANNUAL REPORT 1985 9
t TELEDYNE IS0 TOPES MIDWEST LABORATORY
- NORTHBROOK, ILLINOIS MARCH 1986 i
f
l TABLE OF CONTENTS Page___
INTRODUCTION 1
SUMMARY
2 1.0 EFFLUENTS
?
1.1 Gaseous 3
- 1. 2 Li q u i d............................
3
- 2. 0 SOL ID RADI0ACTI VE WASTE......................
3
- 3. 0 DOSE TO MAN 3.1 Gaseous Effluent Pathways 3
- 3. 2 Liquid Ef f l uent Pathways...................
5 4.0 SITE METEOROLOGY 5
- 5. 0 ENVIRONMENTAL MONITORING 5
5.1 Gama 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-
- 5. 6 Special Collections 8
- 6. 0 ANALYTICAL PROCEDURES.......................
8
- 7. 0 MILCH ANIMAL CENSUS........................
8
- 8. 0 NEAREST RESIDENT CENSUS......................
11 9.0 INTERLABORATORY COMPARIS0N PROGRAM RESULTS 11 APPENDIX I - DATA TABLES AND FIGURES. '.............
1 24-1 Station Releases i
Table 1.1-1 Gaseous Effluents 25 l
Table 1.2-1 Li qui d Ef f l uents................... -
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l TABLE OF CONTENTS (continued)
Page APPENDIX I - DATA TABLES AND FIGURES Station Releases (contint ed)
Table 2.0-1 Solid Was',e Shipments 41 Figure 3.1 Figure 3.1-4 Isodose and Concentration Conteurs..........
43 4
i Table 3.1-1 Maximum Doses Resulting from Airborne Releases....
47 Table 3.2-1 Maximum Doses Resulting from Liquid Discharges....
48 j
Environmental Monitoring i
Figure 5.0 Figure 5.0-4 Locations of Environmental Radiological Stations...
49 4
Table 5.0-1 Environmental Radiological Monitoring Sampling Sites...................
53 Table 5.0-2 Environmental Radiological Monitoring Program 54 Table 5.0 Table 5.0-6 Environmental Summary Tables.............
62 Table 5.1-1 Gamma Radiation Measurements (TLD)..........
78 APPENDIX II - METEOROLOGICAL DATA 81 APPENDIX III - ANALYTICAL PROCEDURES..................
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l INTRODUCTION Byron Station, a two-unit PWR plant, is located about two miles east of the i
Rock River and approximately three miles southwest cf Byron in. 0gle County, north central Illinois.
Each reactor is designed to have a capacity of 1120 MW net.
Uni t No. I loaded fuel in November 1984.
Unit No. 2 is under construction.
The plant has been designed to keep releases to the environment at levels below those specified in the regulations.
Liquid effluents from Byron Station are released into the Rock River in controlled batches af ter 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 grad samples of noble gases and continuously collected composite samples of iodine and particulate 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 Byron Station to measure changes in radiation or radioactivity levels that may be attributable to plant opera-tions. If significant changes attributable to Byron Station _ are measured, these changes are correlated with effluent releases.
External gamma radiation exposure from noble gases and I-131 in milk are the most critical pathways at this site; however, an environmental monitoring program is conducted which includes other pathways of less importance.
1
SUMMARY
Gaseous and liquid effluents for the period remained at a fraction of the Technical Specification limits.
Calculations of environmental concentrations based on affluent, Rock River flow, and meteorological data for the period indicate t' hat consumption by the public of radionuclides attributable to the plant are unlikely to exceed the regulatory limits.
Gamma radiation exposure from noble gases released to the atmosphere represented the critical pathway for the period with a maximum individual dose estimated to be 1.47E-03 mrem for the year, when a shielding and occupancy factor of 0.7 is assumed.
The assessment of radiation doses are performed in accordance with the Offsite Dose Calculation Manual (00CM).
The results of analysis confirm that the station is operating in compliance with 10CFR50 and 40CFR190.
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- 1. 0 EFFLUENTS l
l 1.1 Gascous Effluents to the Atmosphere Measured concentrations and isotopic composition of noble gases, radioiodine, and particulate radioactivity released to the atmos-phere during the year, are listed in Table 1.1-1.
A total of 7.83E+02 curies of fission and activation gases was released with a maximum release rate of 3.61+04 pCi/sec.
A total of 3.22E-03 curies of I-131 was released during the year.
A total of 6.94E-05 curies of beta-gamma emitters and 2.04E-04 curies of alpha emitters was released as airborne particulate matter.
A total of 0.93 curies of tritium was released.
- 1. 2 Liquids Released to the Illinois River A total of 4.83E+07 liters of radioactive liquid waste (prior to dilution) containing 16.3 curies (excluding tritium, gases, and alpha) were discharged after dilution with a total of 4.16E+10 liters of water.
These wastes were released at a monthly average concentration of 3.74E-07 pCi/ml, discharged on an unidentified nuclide basis, which is 8.27% of the Technical Specification release limits for unidentified radioactivity. An undetectable amount of alpha radioactivity and 261.0 curies of tritium were released.
Monthly release estimates and principal radionuclides in liquid effluents are given in Table 1.2-1.
- 2. 0 SOLID RADI0 ACTIVE WASTE Solid radioactive wastes were shipped to Richland, Washington; and Barnwell Nuclear Center, South Carolina.
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 rata, off-site were calculated based on measured release rates, isotopic composition of the noble gases, and meterological data for the period (Table 3.1-1).
Isodose contours of whole body dose are shown in Figure 3.1-1 for tha year.
3
Based on measured effluents and meteorological data, the maximum dose to an individual would be 1.47E-03 mrem for the year, with an occupancy or shielding factor of 0.7 included.
The maximum gamma air dose'was 4.16E-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 tne dose from beta radiation incident on the skin.
However, the actual dose to sensitive skin tissues is difficult to calculate because this depends on the beta particle energies, thickness of inert skin, and clothing covering sensitive tissues.
For purposes of this report the skin is taken to have a thickness of 7 mg/cm2 and an occupancy factor of 1.0 is used.
The skin dose from beta and gamma radiatio'1 for the year was 9.04E-03 mrem.
The air concentrations of radioactive noble gases at the off-site receptor locations are given in Figure 3.1-2.
The maximum off-site beta air dose for the year was 1.26E-03 mrad.
Radioactive Iodine The human thyroid exhibits a significant capacity to concentrate ingested or inhaled iodine, and the radiciodine, 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 radioiodine 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 depositiv: on the ground.
The maximum off-site aver' age concentration is estimated to be 3.03E-04 pCi/m3 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 farm with the cows pastured from May to October.
The maximum infant's thyroid dose was 2.22E-02 mrem during the year (Table 3.1-1).
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j Concentrations of Particulates in Air l
Concentration contours of radioactive airborne particulates are shown in Figure 3.1-4.
The maximum off-site average level is estimated to be 6.29E-06 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 environment for potential doses to man from liquid waste are ingestion of potable water, eating aquatic foods, and exposure while walking on the shoreline.
Not all of these pathways are applicable at a given time or station but a reasonable approximation of the dose can be made by adjusting the dose formula for season of the year or type and degree of use of the aquatic environment.
NRC* developed equations were used to calculate the doses to the whole body, lower 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 2.48E-01 mrem and no organ dose exceeded 3.54E-01 mrem.
4.0 SITE METEOROLOGY A summary of the site meteorological measurements taken during each quarter of the year is given in Appendix II.
The data are presented as cumulative. joint frequency distributions of 250' level wind direction and wind speed class by atmospheric stability class determined from the temperature difference between the 250' and 30' levels.
Data recovery for these measurements was about 99.1%.
5.0 ENVIRONMENTAL MONITORING Tables 5.0-1 and 5.0-2 provide an outline of the radiological anviron-mental monitoring 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).
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l 5.1 Gamma Radiation External radiation dose from on-site sources and noble gases re-leased to the atmosphere was measured at nine indicator and three reference (background) locations using solid lithiu.a 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.
Additional TLDs, a total _of 64 were installed on September 28, 1981 such that each sector was covered at both five miles and the site boundary.
5.2 Airborne I-131 and Particulate Radioactivity Concentrations of airborne I-131 and particulate radioactivity at monitoring locations are summarized in Tables 5.0-2 through 5.0-5.
Locations of the samplers are shown in Figure 5.0-1.
Airborne I-131 remained below the LLD of 0.1 pCi/m3 throughout the year.
Gross beta concentrations. ranged from 0.007 to 0.085 pC1/m3 at indicator locations and 0.011 to 0.070 pCi/m3 at control locations with an average concentration of 0.026 both at indicator and control locations.
No radioactivity attributable to station operation was detected in any sample, 5.3 Terrestrial Radioactivity Precipitation samples were collected monthly from four milk sampling locations and analyzed for grocs beta, tritium, strontium-89 and
-90, and gamma-emitting isotopes.
Except for gross beta and one Sr-90 (2.2 pCi/l), all other radioactivity was below the limits of detection indicating that there was no measurable amount of radio-activity attributable to the station releases.
Annual mean gross beta concentration measured 25.6 pCi/1, which is the level expected in precipitation samples.
e Vegetables were collected in August 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 from 1.2 to 5.5 pCi/g-wet weight and averaged 3.2 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 from 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.
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Well water was collected quarterly from two off-site wells and analyzed for gross beta, tritium, strontium-89 and -90, and gamma-emitting isotopes.
The annual mean gross beta concentration was 7.4 pCi/1.
The annual mean tritium concentration was 230 pCi/l and was barely above the LLD level - of 200 pCi/1.
All other results were below the lower limits of detection.
- 5. 4 Aquatic Radioactivity Surf ace water samples were collected weekly from five locations and analyzed for gross beta content.
Weekly samples from the Rock River near the intake and discharge pipes were.composited monthly 1
and analyzed for 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.
In all samples, except from discharge pipe, gross beta concentration averaged 3.2 pCi/1.
Cesium-134 and -137 concentrations were below the LLD level of 10 pCi/1.
Strontium-89 was below the LLO of 10 pCi/1, and strontium-90 concentrations were below the LLD of 2 pCi/i in all samples but two (2.2 and 2.9 pCi/1). Tritium concentration averaged 290 pCi/1.
These levels were similar to those obtained during the preoperational program, indicating that there was no measurable amount of radioactivity due to station operation.
At discharge pipe, gross beta averaged. 48.5 pCi/1, and tritium averaged 3840 pCi/l, ranging from 220 to 8120 pCi/1.
Strontium-89 was detected -in one sample (43.3 pCi.1),. and strontium-90 was below
~
the LLD level of 2 pCi/l in all samples.
Cobalt-58, cobalt-60, and manganese-54 were detected in several samples.
Cobalt-58 averaged 1051 pCi/l (range:
190 - 2060 pCi/1), cobalt-60 averaged 187 pCi/l (range:
155 - 219 pCi/1)), and manganese-54. averaged. 200 pCi/l i
(range:
167-234 pCi/1).
Elevated levels of radioactivity detected j
in samples collected at discharge pipe are attributable to the j
station operation.
Sediment samples were collected three times, from one control and i
one indicator location, and analyzed for gross beta and gamma i
emitters. Gamma emitters were below the. detection limits.
Mean gross beta activity in indicator samples measured 11.2 pCi/g and
~
9.5 pCi/g at control location indicating the presence of no radio-activity due to station operation.
Collection sites, frequency, and analysis of aquatic vegetation were identical to those of sediments.
As expected, the gross beta concentration was lower for aquatic vegetation than for sediments.
All gamma emitters were below the detection levels.
)
Levels of gamma radioactivity in fish were measured and found in all i
cases to be below the lower limits of detection for the program.
I Gross beta concentration averaged 3.1 pCi/g wet weight and was at i
the level expected in fish.
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- 5. 5 Milk Milk samples were collected monthly from November through April and biweekly from May through October and analyzed for iodine-131, radiostrontium, and gamma emitters.
Radiciodine was below the limits of detection, 0.5 pCi/l (1.0 pCi/l during November - April) 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 j.
detection.
- 5. 6 Special Collection No special collections were made during tne period.
- 6. 0 ANALYTICAL PROCEDURES A description of the procedures used for analyzing radioactivity in envi-ronmental sanples is given in Appendix III of this report.
e
- 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 P. Coulter on August 5, 1985.
Dairies that were surveyed are listed below.
Within 2 Miles of Plant Lambs Tail Acres (Hugh McKiski), located 1.9 mi W of station Number of cows -- 19 Within 5 Miles of Plant Reeverts Dairy Farm, located 2.1 mi NE of station Number of cows -- 40 i
8
Within 5 Miles of Plant (continued)
BY-20 Ed Seabold Farm (operated by M. Lookinglong), 2.5 mi NE of station Number of cows -- 85 Diet consists of the following:
Haylage High moisture corn Protein / mineral supplement BY-15 J. A. Reeverts Pine Hill Dairy, located 3.2 mi ESE of station Namber of cows -- 54 Diet consists of the following:
Haylage Corn silage High noisture corn Protein / mineral supplement Warren Danakas Farm, located 3.3 mi ESE of station Number of cows -- 8 I
BY-16 Kenneth Druien Farm, located 3.3 mi SE of statior.
Number of cows -- 40 Diet consists of the following:
Hay Ground corn Corn silage Protein / mineral supplement Oltmann Dairy Farm, located 2.2 mi S of station Number of cows -- 28 9
Within 5 Miles of Plant (continued)
Bill Luepkes Farm, located 3.7 mi S of station -
Number of cows -- 41 Ashelford Dairy Farm, located 2.6 mi W of station Number of cows -- 35 CAM-DEE Farms (Gerald DeVries, owner), located 3.3 mi WNW of station Number of cows -- 32 Allen Camling, Jr. Farm, located 3.34 mi WNW of station Number of cows -- 35 Duane Camling Farm, located 3.2 mi NW of station Number of cows -- 26 More Than 5 Miles from Plant BY-17 Bosecker/Lingel Farm, located 7.0 mi NE of station Number of cows -- 30 Diet consists of the following:
Green chop i
Corn Silage 10 4
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~ 8.0 NEAREST RESIDENT CENSUS '
-The census was conducted by P.' Coulter on August 5, 1985. There is a new house on ;Winterton Farm opposite. BY-23 (0.7. miles south - of station).
Nearest resident of the Byron Station ~ within a five (5) mile radius.
Direction Distance N
1.4 miles NNE 1.8 miles i
NE 1.'6 miles ENE 1.3 miles i
E 1.2 miles ESE 1.6 miles-SE 1.3 miles i
SSE 0.8 miles S
0.7 miles SSW 0.6 miles SW 0.8 miles.
i WSW 1.7 miles W
l.9 miles
{
WNW 2.1 miles i
NW 0.8 miles NNW l.2 miles l
- 9. 0 INTERLABORATORY COMPARISON PROGRAM RESULTS i
Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental l
Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971.
These programs are operated by agencies which supply environ-
. mental-type samples (e.g., milk or water) containing concentrations of i
radionuclides known_to the issuing agency but.not to participant labora-tories. 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, the agency _ reports the known values to the participant laboratories and specifies control limits.
Results consistently higher or: lower than the 4
}
known values or outside the control limits indicate a need to check the instruments or procedures used.
i The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water, air filters, and food samples during the period 1982 through 1985.
This program:ha_s 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.
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The results in Table A-2 were obtained for thermoluminescent dosimeters (TLDs) during the period 1976,1977,1979,1980, and 1981 through participation in the Second, Third, Fourth, and Fif th International Intercomparison of Environ-i mental Dosimeters under the sponsorships listed in Table A-2.
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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.a l
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12cc i3c, n=1d STW-270 Water Jan. 1982 Sr-89 24.3 2.0 21.0 5.0 Sr-90 9.410.5 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 26.013.7 20t5 Zn-65
<13 15 5 Ra-106
<46 20i5 Cs-134 26.8 0.7 2215 Cs-137 29.7tl.4 2315 STW-277 Water Mar. 1982 Ra-226 11.9 1.9 11.6 1.7 STW-278 Water Mar. 1982 Gross alpha 15.6tl.9 1915 Gross beta 19.2 0.4 1915 STW-280 Water Apr. 1982 H-3
.2690180 28601360 STW-281 Water Apr. 1982 Gross alpha 75 7.9 85121 Gross beta 114.115.9 106i5.3 Sr-89 17.411.8 2415 Sr-90 10.510.6 12 1.5 Ra-226
-11.412.0 10.911.5 Co-60
<4.6 0
STW-284 Water May 1982 Gross alpha 31.516.5 27.5t7 Gross beta 25.9 3.4 2915 STW-285 Water June 1982 H-3 1970t1408 18301340 STW-286 Water June 1982 Ra-226 12.611.5 13.413.5 Ra-228 11.112.5 8.712.3 STW-287 Water June 1982 1-131 6.510.3 a.410.7 STW-290 Water Aug. 1982 H-3 32101140 2890i619 13
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis
- 2cc i30, n=1d STW-291 Water Aug. 1982 I-131 94.6i2.5 87115 STW-292 Water Sept. 1982 Sr-89 22.7t3.8 24.518.7 Sr-90 10.9i0.3 14.512.6 STW-296 Water Oct. 1982 Co-60 20.011.0
.20i8.7 Zn-65 32.315.1 2418.7 Cs-134 15.3tl.5 19.018.7 g
Cs-137 21.011.7 20.018.7 STW-297 Water Oct. 1982 H-3 2470i20 25601612 STW-298 Water Oct. 1982 Gross alpha 32i30 55i24 Gross beta 81.716.1 81i8.7 Sr-89
<2 0
Sr-90 14.110.9 17.2i2.6 Cs-134
<2 1.8i8.7-Cs-137 22.710.6 2018.7 Ra-226 13.610.3 12.Si3.2 Ra-228 3.9tl.0 3.610.9 STW-301 Water Nov. 1982 Gross alpha 12.0il.0 19.018.7 l
Gross beta 34.0i2.7 24.018.7 STW-302 Water Dec. 1982 I-131 40.010.0 37.0110 STW-303 Water Dec. 1982 H-3 1940120 1990i345 STW-304 Water Dec. 1982 Ra-226 11.7i0.6 11.0tl.7 Ra-228
<3 0
STW-306 Water Jan. 1983 Sr-89 20.0i8.7 '
29.2i5 Sr-90 21.718.4 17.2tl.5 STW-307 Water Jan. 1983 Gross alpha 29.0i4.09 29.0i13 Gross beta 29.310.6 31.0i8.7 STM-309 Milk Feb. 1983 Sr-89 35i2.0 37f8.7 Sr-90 13.710.6 1812.6 I-131 55.7i3.2 55i10.4 Cs-137 29tl.0 2618.7 8a-140
<27 0
K-40 163715.8 1512i131 1
14
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Table A-1.
(continued) b Concentration in pCi/l Lab Sample Date TIML Result EPA Result Code Type Collected Analysis t2cc 3 ar, n=1d STW-310 Water Feb.'1983 H-3 2470180 25601612 STW-311
-Water March 1983 Ra-226 11.911.3 12.7 3.3 Ra-228
<2.7 0
STW-312 Water March 1983 Gross alpha 31.614.59 31i13.4 Gross beta 27.0t2.0 28 8.7 STW-313 Water April 1983 H-3 3240i80 33301627 STW-316 Water May 1983 Gross alpha 94t7 64i19.9 Gross beta 13315 149112.4 Sr-89 1911 24t8.7 Sr-90 1211 1312.6 Ra-226 7.9 0.4 8.5 2.25 Co-60 30i2 3018.7 Cs-134 27i2 3318.7 Cs-137 29 1 27 8.7 STW-317 Water May 1983 Sr-89 59.712.1 5718.7 Sr-90 33.711.5 38t3.3 STW-318f Water May 1983 Gross alpha 12.8tl.5 11t8.7 Gross beta 49.413.9 5718.7 STM-320 Milk June 1983 Sr-89 20t0 25 8.7 Sr-90 1011 1612.6 I-131 30 1 30t10.4 Cs-137 5212 4718.7 K-40 1553157 14861129.
STW-321 Water June 1983 H-3 1470189 15291583 STW-322 Water June 1983 Ra-226 4.3 0.2 4.8 1.24 Ra-228
<2.5 0
STW-323 Water July 1983 Gross alpha 31 718.7 Gross beta 2110 2218.7 STW-324 Water August 1983 1-131 13.310.6 14t10.4 15
Table A-1.
(continued)
Concentration in pCi/lb j
Lab Sample Date TIML Result EPA Result Code Type Collected Analysis i2cc 13 o, n =1d STAF-326 Air August 1983 Gross beta 4212 3618.7 Filter Sr-90 1412 1012.6 Cs-137 1911 1518.7 STW-328 Water Sept. 1983 Gross alpha 2.3i0.6 5 8.7 Gross beta 10.711.2 918.7 STW-329 Water Sept. 1983 Ra-226 3.0i0.2 3.110.81 Ra-228 3.210.7 2.010.52 STW-331 Water Oct. 1983 H-3 1300130 1210i570 STW-335 Water Dec. 1983 1-131 19.611.9 20i10.4 STW-336 Water Dec. 1983 H-3 28701100 23891608 STAF-337 Air Nov. 1983 Gross alpha 18.0t0.2 19i8.7 Filter Gross beta 58.611.2 5018.7 Sr-90 10.910.1 1512.6 Cs-137 30.112.5 2018.7 STW-339 Water Jan. 1984 Sr-89 47.211.9 3618.7 Sr-90 22.514.0 2412.6 STW-343 Water Feb. 1984 H-3 2487 76 23831607 STM-347 Milk March 1984 I-131 5.311.1 611.6 STW-349 Water March 1984 Ra-226 4.010.2 4.lil.06 Ra-228 3.6t0.3 2.010.52 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 3560150 35081630 STW-355 Water April 1984 Gross alpha 21.014.1 35115.2 Gross beta 127.814.1 147112.7 Sr-89 29.312.0 2318.7 Sr-90 16.610.7 26f2.6 Ra-226 4.0 1.0 4.0il.04 Co-60 32.3tl.4 3018.7 Cs-134 33.6 3.1 3018.7 Cs-137 33.3 2.2 2618.7 16
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12cc 130, 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 21 3.1 2518.7 Sr-90 13t2.0 1712.6 I-131 46 5.3 43 10.4 Cs-137 3814.0 3518.7 K-40 15771172 14961130 STW-368 Water July 1984 Gross alpha 5.111.1 618.7 Gross beta 11.9 2.4 1318.7 STW-369 Water August 1984 I-131 34.3i5.0 34.0110.4 STW-370 Water August 1984 H-3 30031253 28171617 STF-371 Food July 1984 Sr-89 22.015.3 25.018.7 Sr-90 14.713.1 20.0 2.6 I-131
<172 39.0110.4 Cs-137 24.0 5.3 25.018.7 K-40 2503 132 2605t226.0 STAF-372 Air August 1984 Gross alpha 15.311.2 17i8.7 Filter Gross beta 56.010.0 5118.7 Sr-90 14.311.2 18 2.4 Cs-137 21.012.0 15t8.7 STW-375 Water Sept. 1984 Ra-226 5.110.4 4.911.27 Ra-228 2.210.1 2.3 0.60 STW-377 Water Sept. 1984 Gross alpha 3.311.2 5.018.7 Gross beta 12.7i2.3 16.0 8.7 STW-379 Water Oct. 1984 H-3 2860t312 2810 356 STW-380 Water Oct. 1984 Cr -51
<36 4018.7 Co-60 20.311.2 2018.7 Zn-65 15018.1 14718.7 Ru-106
<30 4718.7 Cs-134 31.317.0 3118.7 Cs-137 26.711.2 24i8.7 17 l
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis
- 2 c f3, n=1d STM-382 Milk Oct. 1984 Sr-89 15.714.2 2218.7 Sr-90 12.711.2 1612.6 I-131 41.7i3.1 42i10.4 i
l Cs-137 31.316.1 32i8.7 K-40 1447i66 15171131 STW-384 Water Oct. 1984 Gross alpha 9.711.2 1418.7 (Blind)
Sample A Ra-226 3.310.2 3.010.8 Ra-228 3.411.6 2.110.5 Uranium nae 5110.4 Sample 8 Gross beta 48.3i5.0 6418.7 Sr-89 10.714.6 11i8.7 Sr-90 7.311.2 1212.6 Co-60 16.3tl.2 1418.7 Cs-134
<2 2i8. 7 Cs-137 16.7tl.2 1418.7 STAF-387 Air Nov. 1984 Gross alpha 18.7tl.2 15 8.7 Filter Gross beta 59.015.3 5218.7 Sr-90 18.3tl.2 2112.6 Cs-137 10.311.2 1018.7 STW-388 Water Dec. 1984 I-131 28.012.0 36i1 0.4 STW-389 Water Dec. 1984 H-3 3583t110 31821624 STW-391 Water Dec. 1984 Ra-226 8.411.7 8.612.2 Ra-228 3.li0.2 4.111.1 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 1518.7 STS-395 Food Jan. 1985 Sr-89 25.316.4 34.015.0 Sr-90 27.018.8 26.0fl.5 I-131 38.012.0 35.016.0 Cs-137 32.712.4 29.015.0 K-40 14101212 13821120 18
l
?
I
'l Table A-1.
(continued)
Concentration in pCi/lb i
Lab-Sample Date-
' TIML Result EPA Result Code Type Collected Analysis
- i2cc i3o, n=1d i
l STW-397 Water
'Feb. 1985 Cr-51
<29 4818.7
[
Co-60 21.313.0
~2018.7 Zn-65 53.7i5.0
-5518,7 Ru-106
<23 25 8.7
.Cs-134 32.3t1.2 3518.7 Cs-137 25.3t3.0 25 8.7 l
STW-398 Water Feb. '1985 H-3 38691319 3796i634 j
l STM-400 Milk March 1985 I-131-7.3i2.4 9.010.9 STW-402 Water March 1985 Ra-226 4.6t0.6 5.011.3 Ra-228
<0. 8 9.0i2.3 Reanalysis Ra-228 9.010.4 I
STW-404 Water March 1985 Gross alpha 4.712.3 618.7 i
Gross beta 11.311.2 1518.7 STAF-405 Air March 1985 Gross alpha 9.311.0 10.018.7 Filter Gross beta' 42.0il.1 36.0i8.7 Sr-90 13.3tl.0 15.0i2.6' i
Cs-137 6.311.0 6.018.7 STW-407 Water April 1985 I-131 8.010.0 7.Sil.3 l
STW-408 Water April 1985 H-3 33991150 3559i630.
STW-409 Water April 1985 i.
(Blind)
Gross alpha 29.7tl.8 32.015.0 i
Sample A Ra-226 4.4t0.2 4.110.6 Ra-228 nae 6.2 0.9 Uranium nae 7.016.0 Sample B Gross beta 74.3111.8
'72.015.0~
Sr-89 12.3i7.6 110.015.0 Sr-90 14.712.4 15.0fl.5 Co-60 14.'7 2.4
- 15.0 5.0 Cs-134 12.0i2.0 15.015.0
'Cs-137 14.012.0
.12.0i5.0 i
19 l
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date
'flML Result EPA Result Code Type Collected Analysis f2 c i3, n=1d I
STW-413 Water May 1985 Sr-89
- 36. 0il2. 4 39.0i5.0 Sr-90 14.314.2 15.0il.5 STW-414 Water
.May 1985 Gross alpha 8.314.1 12.015.0 Gross beta 8.7tl.2 11.015.0 STW-416 Water June 1985 Cr-51 44.7i6.0 44.0i5.0 Co-60 14.311.2 14.015.0 Zn-65 50.317.0 47.0i5.0 Ru-106 55.3f5.8 62.015.0 Cs-134 32.7tl.2
- 35. 0t5. 0 Cs-137 22.7i2.~
20.0i5.0 STW-418 Water June 1985 H-3 2446t132 2416i351 STM-421 Milk June 1985 Sr-89 10.314.6 11.0i8.7 i
Sr-90 9.012.0 11.0i2.6 I-131 11.7tl.2 11.0i10.4 Cs-137 12.711.2 11.018.7 K-40 1512i62 15251132 1
STW-423 Water July 1985 Gross alpha 5.010.0 11.0i8.7 Gross beta 5.0i2.0 8.018.7 STW-425 Water August 1985 I-131 25.7i3.0 33.Di10.4 STW-426 Water August 1985 H-3 4363i83 44801776 STAF-427-Air August 1985 Groas alpha 11.3i0.6 13.0i8.7 Filter Gross beta 46.0 1.0 44.0i8.7 Sr-90 17.7f0.6 18.0i2.6 Cs-137 10.3i0.6
- 8. 0i8. 7 STW-429 Water Sept. 1985 Sr-89 15.710.6 20.018.7 Sr-90
- 7. 0i0. 0 7.0f2.6 STW-430 Water Sept. 1985 Ra-226 8.2i0.3 8.912.3 Ra-228 4.110.3 4.6i1.2 STW-431 Water Sept. 1985 Gross alpha
- 4. 7i0. 6
- 8. 0i8. 7 Gross beta 4.7tl.2
- 8. 0i8. 7 20
,u.e n...
y
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12cc 13o, n=1d STW-433 Water Oct. 1985 Cr-51
<13 21.018.7 Co-60 19.30.6 20.0 8.7 Zn-65 19.710.6 19.0 8.7 Ru-106
<19 20.018.7 Cs-134 17.011.0 20.018.7 Cs-137 19.311.2 20.018.7 STW-435 Water Oct. 1985 H-3 1957150 19741598 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, Quali ty 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, which are in mg/1; air filter samples, which are in pCi/ filter; and food, which is in pC\\lkg.
c Unless otherwise indicated, the TIML results are given as the mean 12 standard 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 EPA).
21
Table A-2.
Crosscheck program results, thermoluminescent dosimeters (TLDs).
i mR d
Teledyne Average 12o
~ Lab TLD Result Known (all Code Type Measurement
- 2aa Value participants) 2nd International Intercomparisonb i
115-2b Ct.7 :Mn Gama-Field 17.0il.9 17.lc 16.417.7 2
Bulb l
Gama-Lab 20.814.1 21.3c 18.817.6 3rd International Intercomparisone i
CaF :Mn Gama-Field 30.713.2 34.914.8f 31.513.0 115-3e 2
Bulb R$'
- Gama-Lab 89.616.4 91.7i14 6f 86.2i24.0-4th International Intercomparison9 CaF :Mn Gama-Field 14.lil.1 14.lil.4f 16.0i9.0 l
115-49 2
l Bulb Gamma-Lab (Low) 9.3tl.3 12.212.4f 12.017.6 Gama-Lab (High) 40.411.4 45.819.2f 43.9113.2 l
.Sth International Intercomparisonh 115-5Ah CaF :Mn Gama-Field - _
31.4tl.8 30.016.0i 30.2114.6 2
Gama-Lab
-77.4i5.8 75.217.61 75.8140.4 at beginning Gama-Lab 96.615.8 88.418.81 90.7131.2-i
-at the end t
i-4
-w
Table A-2.
(Continued) mR Teledyne Average i 20 d Lab TLD Result Known (all Code Type Measurement 12aa Value participants) ll5-5Bh LiF-100 Gamma-Field 30.314.8 30.016i 30.2114.6 Chips 75.8140.4 Gamma-Lab 81.li7.4 75.217.61 at beginning Gamma-Lab 85.4111.7 88.418.81 90.7131.2 at the end a Lab result given is the mean i2 standard deviations of three determinations.
O b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health 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 Intercomparison 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 l
pressurized ion chamber.
9 Fourth International Intercomparison of Environmental Dosimeters' conducted in summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.
h Fifth International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.
I Value determined by sponsor of the intercorparison using continuously operated pressurized ion chamber.
L__--__--_-_---_-
APPENDIX I DATA TABLES AND FIGURES 24
4 Table 1.1-1 4
j BYRON NUCLEAR OC'~'R STATION l
EFFLUENT AND WASTE DISPOSAL SMAn?2N Rt'. PORT POR JANUARY TO JUNE, 1985 GASEOUS EFFLLUJTS - S'R% TION OF ALL RELEASES UNITS JAN FEB MAR 1st Quarter APRIL MAY JUNE 2nd Ouarter A. Fission and Activation Gas Releases
- 1. Total Release Activity Ci (LLD
<LLD 1.22E-2 1.22E-2 3.22E-1 3.58El 1.31E2 1.67E2
- 2. Maximwn Release Rate uCi/sec 0
0 1.78E3 1.78E3 1.98E2 1.8SE2
- 7. 8 3'.:2 7.83E2 l
- 3. % of 10CFR20 Limits *
- a. Phole boa _(500 mrem /yearj O_
0
.01
.01
.10 0
.05
.10
- b. Skin (3000 mrem /yearj 0
0
.01
.01
.03 Q
.03
.0L
- 4. 4 of_10gTR50_tdm_iAs a
_Ca"M @a r.terly_(5_ mrad) 0 0
Q 0
_,0
.Q1
.03
.04 b._ Beta _ Quarterly (10 mrad) 0 0
0 0
0
.02
.03
.05 m
- c. Canna Annual _(10 mead) 0 Q
0 0
Q
.006
.015
.021
- d. Beta A~iua: (20 mrad) 0 0
0 0
0
.008
.Z6
.02,4
- 3. Iodine Releases 1.. Total I-131 and I-133 Activity Ci (LLD (LLD (LLD (LLD (LLD (LLD 2.23E-5 2J3E-5__
- 2. % of 10CFR20/10CFR59 Limi_ts_*"
% of 10CFR20 limits is based on the maximum release rate for the period considered.
Iodine, particulate, and tritium limits are expressed as a total limit. See Step E.
('J D = No detectable activity above background.
- 751M)
Table 1.1-1 (continued)
BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SDiIANNUAL REPORT FOR JULY - DECEMBER, 1985 GASEOUS EFFLUDITS - StA9tATION OF ALL RELEASES UNITS JULY AUG SEPT 3rd Quarter OCT NOV DEC 4th Quarter A. Fission and Activation Gas Releases
- 1. Total Release Activity C1 3.8120 2.31El 2.81E2 3.08E2 2.95E2 9.99E0 2.76E0 3.08E2
- 2. Maximum Release Rate uCi/sec 1.00E3 3.95E3 3.61E4 3.61E4 1.79E4 2.28E2 2.10E3 1.79E4
- 3. % of ICCFR20 Limite *
- a. Whole Body (500 mrom/ year) 0.03 0.03 0.26 0.26 0.12 0.00 0.02 0.12
- b. Skin (3000 ares / year) 0.02 0.03 0.28 0.28 0.14 0.00 0.02 0.14
- 4. t of 10CFR50 Limits
- a. Gamma Quarterly (5 scad) 0.00 0.00 0.02 0.02 0.02 0.00 0.00 0.02
- b. Beta Quarterly (10 mead) 0.00 0.00 0.04 0.04 0.04 0.00 0.00 0.04
- c. Ganuna Annual (10 mrad) 0.00 0.00 0.01 0.01 0.01 0.00 0.00 0.01 1
- d. Beta Annual (20 mrad) 0.00 0.00 0.02 0.02 0.02 0.00 0.00 0.02 B. Iodine Kaleases
- 1. Total I-131 and I-133 Activity Ci 3.09E-4 3.57E-4 7.02E-4 1.37E-3 1.06E-3 3.15E-4 4.53E-4 1.83E-3 j
- 2. % of 10CFR20/10CFR50 Limite **
a i
% of 10CFR20 limits is based on the maximum release rate for the period considered.
O 3
(0906M/0085M)
l l
Table 1.1-1 (continued)
BY2ON NUC'"AR POWE7 STATION EFFLUENT AND WASTC DISPOSAL SEMIANNUAL REPORT."OR JANUARY TO JifME, 1985 G.V"?OUS EFFLUEfCS - SUMMATION OF ALL RELEASES I
']NJ_TS JAN FEB MAR l_s_t Qua rt er APRIL MAY J'?JE 2 nd,,Qua_r t,e r C. Particulate (> 8 day half-life) Releases
- 1. Grose Activity gi
<LLD
<LLD (yyD (LLD 2.1E-5 3.31E-6 5.21E-6 235F'[5'i'
- 2. Gross Aloha Activity Ci 1.3E-5 1.66E-5 2.57E-5 5.53E-5 5.6C-5 5.07E-5 4.25E-5 1.492-4
- 3. t of it.yFR20/10CFR50 Limits **
l D. Tritium Releases
- 1. Total Release Activity, Ci (LLD 1.01E-1 3.98E-3 1.05E-1 2.46E-1 4.31E-2 7.11E-2 3.60E-1
- 2. % of 10CFR20/10CFR50 Limits **
E. Sum of Iodine, Particulate () 8 day half-life), and Tritium Releases
- 1. Total Activity Ci (LLD 1.01E-1
- 3. 98 E_-3 1.05E-1 2.46E-1 4._31 E-1 7.11E-2 3. 6 0.E-l_._
- 2. t of 10CFR2D Limit a Any_ Organ (1500 mrem / year) t 0
0 0
0 0
0 Q
0, n
- 3. t of 10g_PR50 Limits
- a. Quarter _1y_A_ny_ Organ _(7.5 mrem)
Q 0
Q Q
Q 0
.004
.Q04
- b. Annual Any Organ (15.0 meem)
E O
O O
O Q
0
.002
.,002 l
See Step E.
j
<LLD = No detectable activity above background.
i
)
!0751M) l
Table 1.1-1 (continued)
BYRON NUCLEAR POWER STATION EFFLUDJT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR JULY - DECDiBER,1985 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNITS JULY AUG SEPT 3rd Ouarter OCT NOV DEC 4th Ouarter C. Particulate () 8 day half-life) Releases
- 3. % of 10CFR20/10CFR50 Limits **
D. Tritium Releases
- 1. Total Release Activity Ci 6.54E-3 1.43E-2 8.45E-2 1.05E-1 1.62E-1 6.97E-2 1.30E-1 3.62E-1
- 2. % of 10CFR20/10CFR50 Limite **
E. Sum of Iodine, Particulate () 8 day half-life), and Tritium Releases
- 1. Total Activity Ci 6.86E-3 1.47E-2 8.52E-2 1.07E-1 1.63E-1 7.00E-2 1.30E-1 3.63E-1
- 2. % of 10CFR20 Limit
- a. Any Organ (1500 mrem / year)
% 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- 3. % of 10CFR50 Limits
- a. Quarterly Any Organ (7.5 mrem)
% 0.04 0.03 0.09 0.16 0.13 0.00 0.00 0.13
- b. Annual Any Organ (15.0 mrem)
% 0.02 0.02 0.04 0.08 0.07 0.00 0.00 0.07
(LLD = No detectable activity above Lower Limit of Detection for Counting Room Instrumentation.
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Table 1.1-1 (continued)
BYRON NUCLEAR POWER STATION EFFLUD4T AND HASTE DISPOSAL SEMIANNUAL REPORT FOR JULY - DECD4BER, 1985 GASEOUS EFFLUDITS - VDJT STACK RELEASES Isotopes Released UNITS JULY AUG SEPT 3rd Quarter OCT NOV DEC 4th Quarter F. Fission and Activation Gas Releases Xe-131m Ci 1.83E-2 6.44E-2 1.31E-1 2.14E-1
<LLD 8.87E-2 9.96E-3 9.87E-2 Xe-133m 2.86E-3 1.93E-2 2.01E-1 2.23E-1 2.98E-1 7.45E-3 (LLD 3.05E-1 Xe-135m.
<LLD (LLD (LLD Xe-133 2.76E0 2.29El 2_. 78 E2 3.04E+2 2.92E2 9.73E0 2.48E0 3.04E2 Xe-135 9.97E-1 7.08E-2 1.41E0 2.48E0 2.75E0 (LLD 7.17E-2 2.82E0 Kr-85m 2.64E-3 (LLD (LLD 2.64E-3 (LLD 5.28E-4 (LLD 5.28E-4 Kr-85 (LLD (LLD
<LLD (LLD 3.50E-2 1.61E-1 6.91E-2 2.65E-1 Kr-87
<LLD
<LLD
<LLD
<LLD
<LLD (LLD
<LLD
<LLD Kr-88 1.88E-2 (LLD (LLD 1.88E-2
<LLD (LLD (LLD (LLD Ar-41 1.06E-2 5.26E-2 1.40E-1 2.03E-1 1.43E-1 (LLD 1.30E-1 2.73E-1 w
Others (specify)
Xe-138 1.27E0 1.27E0 G. Iodine Releases I-131 Ci 2.56E-4 1.90E-4 5.30E-4 9.76E-4 8.06E-4 3.05E-4
<LLD 1.11E-3 I-132 (LLD 2.48E-4 (LLD 2.48E-4 (LLD (LLD (LLD (LLD I-133 I-134 5.34E-5 1.67E-4 1.72E-4 3.92E-4 2.50E-4 1.04E-5 4.53E-4 7.13E-4 (LLD (LLD (LLD (LLD (LLD (LLD (LLD
<LLD I-135 (LLD 3.67E-4 1.12E-4 4.79E-4 1.48E-4 (LLD -
(LLD 1.48E-4 (LLD = No detectable activity above lower limit of detection for countin room instrumentation.
(0906M/008SM)
f e
t 5
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LLLL6
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d 2
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,L L L J
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A LLLLL -
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9
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i
Table 1.1-1 (continued)
BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SDfIANNUAL REPORT FOR JULY - DECEMBER,1985 GASEOUS EFFLUENTS - VENT STACK RELEASES Isotopes Released UNITS JULY AUG SEPT 3rd Ouarter OCT NOV DIC 4th Ouarter G. Iodine Releases dContinued)
Others (Specify)
Ci None M
H. Particulate () 8 Day Half-Life) Releases Mn 54 Ci (LLD (LLD (LLD (LLD (LLD (LLD (LLD (LLD Fe 55 (LLD (LLD (LLD (LLD (LLD (LLD (LLD (LLD Fe 59 (LLD (LLD (LLD (LLD (LLD (LLD (LLD (LLD CO 58 (LLD 5.80E-6 (LLD 5.80E-6 (LLD (LLD
<LLD
<LLD Co 60 4.87E-6 (LLD (LLD 4.87E-6 2.17E-5 (LLD (LLD 2.17E-5 Sr 89
<3.1E-5*
<3.1E-5*
Sr 90
<1.3E-4*
<1.3E-4*
Y 88 (LLD (LLD (LLD (LLD (LLD (LLD (LLD (LLD Ru 103 (LLD (LLD (LLD (LLD (LLD (LLD (LLD (LLD Aq 110m
-(LLD (LLD (LLD (LLD (LLD (LLD (LLD (LLD
<LLD = No detectable activity above Lower Limit of Detection for counting Roose Instrumentation.
= Analysis performed by offsite vendor; value listed is the LLD for the analysis.
1
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1 l
l Table 1.2-1 BYRON NUCLEAR POWER STATION EFFLUNT AND k'ASTE DISPOSAL c"vi A*?'.'JAL REPORT POR.'ANUARY T) JUNE, 1985 LIQUID EFFLUEN'S - SUV%% TION OF ALL RELEASES UNIN JAN FEB MAR ist Quarter APRIL MAY JUNE 2nd_Qecd er l
'. Pission and Activation Products l
1 1
- 1. Total Agtivity, Released Ci (LLD 1.31E-3 1.27E-2 1.40E-2 4.55E-2 1.89E-1 8.89E-1 1.1200 l
- 2. Average Concentration Released uCi/ml (LLD 3.57E-10 3.06E-9 1.55E-9 1.27E-8 5.56E-8 2.36E-7 1.05E-7
- 3. t of 10CFR50 Limits
- a. fugrterly_Whole Body _11.5 mrem _)
0 0
0 0
0
.032
.101 0.133
- b. Quartu ly_Any_ Organ _(5.0_ mrem) t 0
0 9
Q 0
.014
.045 0,059
- c. Annual Whole Body (3.0 mrem) t 0
0 0
0 0
.016
.0$0 0.066 t
- d. Annual Any_ Organ QO.0 mrem _)
t 0
0 0
0 0
.007
.022 0.029 J. Tritium w
l t.n i
- 1. Total Activity _R,eleased Ci
<LLD 7,22E-2 __7J 3E-1 8.25E-1 1.12E0 2.00E1
- 1. 25E2 1.50E2 l
- 2. Average Concentration Released eCi/ml (LLD 1.97E-8 1.81E-7 9.14E-S 3.14E-7 5.88E-6 3.43E-5 1.40E-5 l
- 3. % of Limit L3E-3 uCi/ml)
O 6.50E-4 6.0E-3 3.05E-3 1.00E-2
- 1. 9,:-:-1 1.14v0 4.6PE-1 l
l
. Dissolved Noble Gasses l
- 1. Total Activit R
1 eleased Ci (LLD (LLD 1.45E-4 1.45E-4
-3.68E-4 6.91E-3 4.?""-1 4.450-1
- 2. Average Concentration Released uCi/mi
<LLD (LLD 3.49E-11 3.49E-11 1.03E-10 2.04E-9 1.16E-7 4.16E-8
- 3. %_of Limit (2E-4 uCi/m )
0 0
1.7E-5 1.7E-5 5.15E-5 1.02E-3 5.82E-2 2.08E-2
'.. Gross Alpha
- 1. Total Activity Released Ci
< L',3 (LLD (LLD (LLD (LLD (LLD (LLD
<(LD
_ _2. Aver _ age Concentration Released uCi/ml <LLD
<LLD
< t/.D.
<LLD (LLD M. Volume of Liquid Waste to Discharge liters 4.47E6 5.02E6 2.31E6 1.18E7 1.89E6 2.59E6 8.76E6 1.32E7
". Volume of Dilution Water liters 1.21E9 3.67E9 4.15E9 9.03E9 3.57E9 3.40E9 3.76E9 1.07E10
<'.LD = No detectable activity above background.
t
!0751M) l l
Table 1.2-1 (continued)
BYRON NUCLEAR POWER STATION EETLUENT AND WASTE DISPOSAL SDiIANNUAL REPORT FOR JULY - DECDiBER,1985 LIQUID EFFLUENTS - SUtelATION OF ALL RELEASES UNITS JULY AUG SEPT 3rd Ouarter OCT NOV DEC 4th Quarter I. Fission and Activation Products
- 1. Total Activity Released Ci 3.82E0 4.77E0 9.55E-1 9.54E0 2.75E-1 3.03E0 2.32E0 5.62E0
- 2. Average Cor.contration Released uC1/mi 1.14E-6 1.17E-6 2.77E-7 8.83E-7 7.81E-8 7.74E-7 6.39E-7 5.06E-7
- 3. % of 10CFR50 Limite
- a. Ouarterly Whole Body (1.5 mrem) 0.33 0.58 0.80 1.71 3.91 4.04 5.62 13.67
- b. Quarterly Any Organ (5.n mrom) 0.79 2.00 1.12 3.91 1.68 1.70 2.38 5.76
- c. Annual Whole Body (3.0 mrem) 0.16 0.29 0.40 0.85 1.95 2.02 2.81 6.78
- d. Annual Any Organ (10.0 mrem) 0.40 1.00 0.56 1.96 0.84 0.85 1.19 2.88 J. Tritium
- 1. Total Activity Released Ci 1.06El 2.06El 5.68E1 8.80E1 3.42E-2 1.55El 6.70E0 2.22E1
- 2. Average Concentration Released uCi/ml 3.16E-6 5.07E-6 1.65E-5 8.15E-6 9.72E-9 3.95E-6 1.84E-6 2.00E-6
- 3. % of Limit (3E-3 uCi/ml) 0.11 0.17 0.55 0.27 0.00 0.13 0.06 0.07 K. Dissolved Noble Gasses
- 1. Total Activity Released Ci 6.91E-1 4.06E-2 4.63E-1 1.19EO 1.78E-2 2.58E-2 4.68E-3 4.83E-2
- 2. Average Concentration Released uCi/mi 2.06E-7 1.00E-8 1.34E-7 1.10E-7 5.06E-9 6.58E-9 1.29E-9 4.35E-9
- 3. % of Limit (2E-4 uCi/ml) 0.10 0.01 0.07 0.06 0.00 0.00 0.00 0.00 L. Gross Alpha
- 2. Averaqs Concentration Released uCi/ml (LLD (LLD (LLD (LLD (LLD (LLD (LLD (LLD M. Volume of Liquid Waste to Discharge liters 4.79E6 5.40E6 4.90E6 1.51E7 2.50E6 2.82E6 2.90E6 8.22E6, N. Volume of Dilution Water liters 3.35E9 4.06E9 3.44E9 1.08E10 3.52E9 3.52E9 3.63E9 1.11E10 (LLD = No detectable activity above the lower limit of detection for counting room instrumentation.
(0906M/0085M)
~
yob Table 1.2-1 (continued)
BYRON NUCLEAR !WER STATION EFFLUENT AND WASTE DISPC':.Y. SEMIAM.'UAL RCPORT POR JANUARY TO JUNE. 1985 LIQUID EFFLUE'JTS Isotopes Released UNITS JAN FEB MAR 1st Quarter APRIL MAY JUNE Q..d Qua M
~
O. Liquid Effluents SN89 Ci Sr-90 Co-58 (LLD (LLD 6.86E-3 6.86E-3 1.76E-2 3.24E-2 1.06E-1 1.56E-1 Co-60 (LL?
<LLD 1.69C-3 1.69C-3 4.52E-3 7.16E-3 1.37E-2 2.54E-2 Cs-134 d*Q QLD (LLD
<LLD (LLD_
(LLD
<LLD 1.76E-3 8.76E-3 1.05E-2 Cs-!37 (LLD 1.03C-5 8.44E-5 9.47E-5 2.30E-4 5.69E-3 1.72E-2 2.31E-2 I-131 (LLD (LLD 1.19E-4 1.19E-4 4.06E-4 6.88E-3 5.63E-3 1.29E-2 I
w
- -133 (LLD
<LLD (LLD (LLD_
9.81E-5 9.20E-4 3.46E-3 4.48E-3 Ba/La-140
<W 8.54E-6 1.49E-3 1.50E-3 3.97E-3 5.16E-2
- 09C-2 1.36E-1
':e-123
<LLD
<LLD 1.45E-4 1.45E-4 2.35E-5 6.07E-3 3.7fE-1 3.f4 E '.
Xe-135
<LLD (LLD 5.50E-4
- 4. fu:n-2 4.94U-2 Others (Specify)
Na-24 1.29E-3 1.07E-3 2.36E-3 1.37E-2 5.63E-2 5.39E-1 6.09E-1 va-54 1.31E-3 1.31E-3 4.94E-3 1.99E-2 3.70E-2 6.19E-2 l
re-59 8.21E-5 8.21E-5 1.73E-3 2.91E-3 4.64E-3 l
Xe-131m 3.44E-4 2.60E-3 2.94E-3 "e-7 7.14E-4 7.14E-4 Ar-41 2.8EE-4 5.90E-4 8.7HC-4 l
V.n-5b 1.37E-4 1.32E-4 Zn-69m 1.51E-4 4.13E-4 5.64C-4 I
.?D = No detectable activity above background.
l
- Naiting for analysis results - data to be presented in im errata to this report at a later date.
t0751M)
. _- - - - -... - ~.
t l
1 Table 1.2-1 (continued)
BYRON NUCLEAR POWER STATION EFFLUENT AND HASTE DISPOSAL SEMIAISIUAL REPORT FOR JULY - DECEMBER, 1985 LIQUID EIEUENTS 1
Isotopes Released UNITS JULY AUG SEPT 3rd Quarter CCT NOV DEC 4th Quarter
}
O. Liquid Effluents (6.8E-8 *
(6.8E-8
- Sr-89 C1 (8.22-9 *
(8.2E-9
- Sr-90 Co-58 2.95E0 3.848-0 6.52E-1 7.44E-0 1.02E-1 2.82E0 1.93E0 4.85E0 4
co-60 4.02E-t 3.45E-1 8.88E-2 8.36E-1 2.21E-2 7.37E-2 1.11E-1 2.07E-1
-Co-134 (LLD 7.03E-5 2.30E-3 2.37E-3 1.54E-2 1.69E-2 2.62E-2 5.85E-2 Co-136 1.13E-3 (LLD 2.92E-4 1.42E-3 7.43E-3 7.42E-3 2.09E-3 1.69E-2,,
Cs-137 3.58E-3 8.32E-3 1.22E-2 2.41E-2 5.54E-2 5.37E-2 7.34E-2
- 1. 82E-1,,
]
I-131 7.92E-2 4.72E-2 2.21E-2 1.48E-1 2.26E-2 1.17E-3 6.908-3 3.07E 4 I-133 8.78E-4 8.79E-4 1.73E-3 3.49E-3 6.26E-4 ( LLD 4.96E-3 5.58E-3,
i
)!
Xe-133 6.76E-2 3.20E-2 4.43E-1 5.43E-1 7.23E-3 1.99E-2 8.19E-4 2.79E-2 Ba/La-140 3.84E-2 1.14E-2 6.39E-4 5.04E-2 2.23E-3 3.74E-3 4.385-4 6.41E-3
[
Xe-135 5.47E-3 2.18E-3 1.36E-2 2.125-2 5.13E-5 ( LLD 3.335-4 3.84E-4
'i Others (Specify) j Na-24 4.68E-3 1.20E-2 2.07E-5 1.67E-2 1.69E-4 1.62E-3 1.79E-3
~
Cr-51 7.78E-2 1.48E-1 6.42E-2 2.90E-1 7.77E-3 8.05E-3 9.05E-3 2.49E-2 Mn-54 2.13E-1 2.78E-1 5.45E-2 5.45E-1 9.78E-3 3.05E-2 1.29E-1 1.69E-1
(
Zn-65 7.00E-4 2.39E-3 1.46E-3 4.55E-3 2.97E-4 8.10E-5 3.78E-4 Co-57 1.85E-3 3.07E-3 5.61E-4 5.40E-3 1.72E-3 1.82E-3 3.54E-3 3
Fe-59 1.64E-2 3.30E-2 1.48E-2 6.42E-2 2.09E-3 2.45E-3 5.89E-3 1.04E-2 i
Nb-95 5.825-3 2.40E-2 1.65E-2 4.63E-2' 4.17E-3 2.31E-3 4.34E-3 1.08E-2 2
Zr-95 7.66E-3 2.13E-2 1.49E-2 4.39E-2 2.87E-3 6.27E-4 1.878-3 5.37E-3 I-132 1.16E-4 1.16E-4 1.37E-2 1.52E-3 2.945-3 1.82E-2 S
I' 1
l_
(LDD = No detectable activity above the lower limit of detection for counting room instrtamentation.
= Analysis performed by offsite vendor; value listed is the LIA for the analysis.
)
(0906M/0085M) i
l l
t l
l Table 1.2-1 (continued) l l
BYRO*J NUCLEA9 %'ER STATIOtt EFFLUENT AND WASTC DIS"'OSAL ST_V!AY',"?AL REPORT FOR JANUARY TO JUNE, 1985 l
LIQ',':0 EFFLtlENTS Ij!;oppes k?Ieased tNITS JAN PEP MAR ls t _Qua rt e.r APRI_L MAY JUNC 2nd Quarter 1
- 0. Liquid Effluents (Continued)
Others_(Specify]
G2
%-99 1.84E-3 1.84C-3 l
Ic-99m
- 5. 42 ff-5 7.46E-5 1.29E-4 ~
l "r-82 1.07C-4 1.07C-4
~
Kr-85m 2.29E-5 1.54C-3 1.560-3 i
Sr-91 1.41C-3 3.330-3 4.74C-3 Y-91m "r-88 6.37C-3 6.37E-3
---I
- 4. !!00 t.
4. 8 tJ E-4 9.64E-5 9.64C-5 St-92
~
~
1.9SC-3 1.98C - ~
v.gi~
- 1. 960 e.
1.96E-4
'b-88 i
2 70P-3 2.70R-3
---;s -13 8 3.388-4 3.3SE-4 3.16C-3 3.16R-3
~3 4 7 (r-87
- - - -Xe-133m
- 3. 6 '.0-4 3.61C-.
t 1
1.42C-4 1.42R-4 l
l l
1 i
i
!0751M) 1
re t
4 3 3 3 3 4
3 3 3 4 r
a E E -
E E E - E -
E E E E u
6 0 9 1 5 2
5 3 7 6 O
2 0 4 4 2 5
4 4 0 4 h
5 9 1 4 6 6
9 4 6 7 t
4 4
3 3 3 4 4
3 4
E E
E E E E
E -
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3 1
9 3 6 -
7 3
2 E
8 8
4 2 5 D
3 5
6 1
1 1
1 9 1
3 3
3 3 3 3
4 E
E E E
E V
9 0
6 4
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8 N
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2 9
8 9
2 2
5 5
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3 3
5 4
3 3 E
B T
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E E M
C 3
0 8
9 5
3 7 E
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2 0
6 1
4 0
C 3
4 1
3 5
4 6
ED re 4
3 3
3 3
5 4
1 4
2 3
Y t
r E
E E E E E E E E E E LU a
2 0
1 3
6 4
9 4
0 9
5 J
u 9
2 1
0 3
9 3
3 2
9 8
O NR 6
8 2
3 9
2 1
5 2
8 5
t OO dr IF T
3 AT
)
TR 5
3 4
4 5
4 4
3 d
SO S e
P T T
E E E E E E
E E u
RE N P
4 4
2 9
4 6
2 8
n ER E E
6 2
7 0
9 4
8 6
W U
S OL L 3
7 1
1 2
1 3
5 i
t PAT n
UI 3
3 o
RN E 8
c AN 7
E
(
EA D G
7 3
I U
CM U A
4 LI 1
UE Q 2
6 NS I 2
L NL 4
4 3
3 3
4 1
4 2
4 1
OA RS Y
E E E E E E E E E E e
YO L
6 6
4 3
2 9
4 0
1 3
BP U
5 5
9 0
0 3
3 2
3 7
l b
S J
I 6
9 1
3 7
1 5
2 8
1 a
D T
S E
T I
i TS N
C A
U W
DNA T
TDU L
)
T d
IE eun i
tno C
(
d e
s
)
s t
y a
n f
e e
i l
u c
e l
e R
f p
f S
)
M s
E
(
5 e
m m p
d s 3 3
2 48 5 m
3 1 5 8
0 o
i r 9 9
8 0 2 23 3 1 5 5 8 3 3 2 t
u e 9 9
8 1 1 1 1 1 4 8 8 8 1 1 1 0
o q
h
/
e-b M
s i
t c o b u b b s
r r r r e I
L O T M R R S S C I A K K K X X S 6
0 9
O 0
(
Table 2.0-1 BYRON N'JCLEAR POWER STATION EFFLUENT AND YASTE DISPOSAL SEMIANN'.'AL REPORT SOLID MDIOACTIVE WASTE MON *'t 1/1 to 6/30 YEAR 1985 l
Disposition of Material Volume Per Curies Per 3
Oate (Description, Class
, Type
)
Mode of Transport Destination Shipment (ft )
Shipment (Ci)
No Radwaste shipments duri:x; first six months of 1985.
A I
P f
i
'r Monthly Totals O
ft3 0
Ci b
(0751M)
___m_
l Table 2.0-1 (continued) l, BYRON NUCLEAR POWER STATION r.iTLUDIT AND WASTE DISPOSAL SEMIAMUAL REPORT FOR JULY - DECEMBER,1985 SOLID RADI0 ACTIVE WASTE j
Disposition of Material Volume Per Curles Per j
Date (Description, Class
, Type
)
Mode of Transport Destination Shipment (ft )
Shipment (Ci) 3 08-24-85 Spent Resins Class A 2 Liners Hacke Trucking Richland, WA 340 0.1338 08-26-85 Spent Resins Class A Liner in Cask Hittman - Truck Barnwell, SC 170 0.0660 9
09-09-85 Spent Resins Class A Liner in Cask Hittman - Truck Bernwell, SC 170 0.7513 3
09-16-85 Spent Resins Class A Liner in Cask Hacke Trucking Barnwell, SC 170 0.8400 l
'09-20-85 Spent Resins Class A Liner in Cask Hittman - Truck Barnwell, SC 170 0.7300 1
10-01-85 Spent Resins Class A 2 Liners Hacke Trucking Richland, WA 340 2.2800 10-07-85 Spent Resins Class A 2 Liners Hacke Trucking Richland, WA 340 0.4600 10-15-85 Spent Resins Class A 2 Liners Hacke Trucking Richland, WA 340 0.5780 10-22-85 Spent Resins Class A 2 Liners Hittman - Truck Richland, WA 340 0.1671 i
1.
10-29-85 Spent Resins Class A 2 Liners Hittman - Truck Richland, WA 340 0.4350 11-05-85 DAW Class A 7 boxes /
Hacke Trucking Richland, WA 844.5 0.6226 i'
23 Drtans 11-12-85 Spent Resins Class A 2 Liners Mittman - Truck Richland, WA 340 1.5049 l
1 11-18-85 DAW Class A 67 Drums Hacke Trucking Richland, WA 502.5 1.4304 11-19-85 Spent Resins Class A Liner in Cask Hittaen - Truck Barnwell, SC 170 1.3470 11-26-85 Tank sludge class A 2 Liners Hacke Trucking Richland, WA 340 6.24E-5 l'
12-03-85 -Spent Resins Class A Liner in Cask Hacke Trucking Barnwell, SC 170 1.5390 l
12-04-85 Spent Rosin /
Class A 2 Liners Hacke Trucking Richland, WA 340 0.0208 j
Sludge 12-12-85 Spent Resin /. Class A 2 Liners Hacke Trucking Richland, HA 340 0.0396 '
i Sludge 12-18-85 Spent Resins Class A 2 Liners Hacke Trucking Richland, WA 340 0.2779 12-27-85 Spent Resins Class A-Liner in Cask Hittman - Truck Barnwell, SC 170 0.6834 TOTALS
'6277 ft.3 13.907
.Ci i
t j (0906M/0085M)
-o e
Figure 3.1-1 i
Estimated Cumulative Gamma Dose (mrem) f from the Byron Station for the period i
January-December 1985.
Isopleth Labels 10 #
Small figure - multiply by 10 5 4
(
40 Large figure - multiply by 10-4,.,a
'5
/
\\
10 j y
?
t t =.
I
- Pecotonica ROCKFORD
/
(..
_S, 1
l r
,g.
//.?
N r
150
- (...
y
\\
n
/
2S j....n.
/
3 o....
x 43 e.....
.g
7._.--...-..._.
r i
3, e
i i
i I
/
1, 2'
l 1
d d
i f
h i
a I
L f
4 h
4 a
i s
(
t r
0 p
i f
t i
a o
e i
I i
i n
.m
l Figure 3.1-3 3
Estimated Total Concentration (pCi/m ) of Noble Gases from the Byron Station for the 50 m l
period January-December 1985.
Isopleth Labels 0
4 Small figure - multiply by 10 Large figure - multiply by 10-1 15 l
6
=
syw
~^5 J
__ s k I
15 30
/'b_
15 NvU ROCKFO o
- 25 f
to g
l
/
a l
(
err 10 300
{
l i
r 7:
f p
4 g
- r.ee 2S
)
g/
...n.
5 x
)
9...
'?
'?
8? a'
Figure 3.1-4 Estimated Total Concentration (pCi/m3) of 40 Particulate Matter from the Byron Station 3
for the period January-December 1985
~~,
)
t
_ w I
Isopleth Labels 10 5
I Small figure - multiply by 10-7 Large figure - multiply by 10-8
,l syhd 15 20
{
?
T
~
l G
10 j
\\
15 ^
?
2~
' Pecatonice
- ROCKFORD, ao
/
I-
-20 10 l
i
),reer.et.
200
)
y
'3 Y' y e4 oe.e..
/
25 l
,..... i i.
/
3 o
o.
x_/ J 46 U
s ip 1p 2,o.nl i
wm.
l Table 3.1-1 i
BYRON UNIT ONE MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE -
1/ 1/85 TO 12/31/85 CALCULATED 01/08/86 1ST 2ND 3RD 4TH ANNUAL TYPE QUARTER QUARTER QUARTER QUARTER 1/85-3/85 4/85-6/85 7/85-9/85 10/85-12/85 GAMMA AIR 3.74E-08 2.13E-03 1.04E-03 9.96E-04 4 16E-03 (MRAD)
(SE
)
(SE
)
(SE
)
(SE
)
(SE
)
BETA AIR 1.54E-07 4.66E-03 3.98E-03 3.94E-03 1.26E-02 (MRAD)
(EE
)
(SE
)
'(SE
)
(SE
)
(SE
)
TOT. BODY 9.06E-09 9.39E-04 2.78E-04 2.54E-04 1 47E-03 (MREM)
(SE
)
(SE
)
(SE
)
(SE
)
(SE
)
SKIN 7.39E-08 5.03E-03 2 04E-03 1.97E-03 9.04E-03 (MREM)
(SE
)
(SE
)
(SE
)
(SE
)
(SE
)
ORGAN 4.69E-05 4.30E-04 1 18E-02 9.93E-03 2 22E-02 (MREM)
(EhE )
(ENE )
(ENE )
(ENE )
(ENE )
LIVER THYROID THYROID THYROID THYROID THYROID KIDNEY LUNG GI-LLI THIS IS A REPORT FOR THE CALENDAR YEAR 5985 COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP 1. --------------
OTRLY 1ST OTR 2ND OTR 3RD OTR 4TH OTR YRLY
% OF OBJ 1/85-4/85-7/85-10/85-DBJ kPP.I 3/85 6/85 9/85 12/85 GAMMA AIR (MRAD) 5.0 0.00 0.04 0.02 0.02 10.0 0.04 BETA AIR (MRAD) 10.0 0.00 0.05 0.04 0.04 20.0 0 01 TOT. BODY (MREM) 2.5 0.00 0.04 0.01 0.01 5.0 0.03 SKIN (MREM) 7.5 0.00 0.07 0.03 0.03 15.0 0.06 ORGAN (MREM) 7.5 0.00 0.01 0.16 0.13 15.0 0 15 LIVER THYROID THYROID THYROID THYROID THYROID t
KIDNEY LUNG GI-LLI RESULTS BASED UPON ODCM REVISION 10 UPDATE DM002 OCT OI:ER 1905 47
~.
Table 3.2-1
-BYRON UNIT ONE HAXIMUM DOSES (MREM)'RESULTINO FROM LIQUID EFFLUENTS PERIOD OF RELEASE -
1/;1/85.TO 12/31/85 CALCULATED 01/13/86 *-
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.
7.56E-05 1.87E-02 2.57E-02 2.04E-01 2.48E-01 BODY INTERNAL 1.18E-04 2.83E-02 1.95E-01 2.88E-01 3.54E-01 ORGAN f
LIVER LIVER OI-LLI LIVER LIVER
- THIS IS A REPORT FOR THE CALENDAR YEAR 1985
)
COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
QTRLY 1ST OTR 2ND OTR 3RD OTR 4TH GTR YRLY
% OF OBJ 1/85-4/85--
7/85-10/85-OBJ APP.I
}
3/85 6/85 9/85 12/85 i
{
TOTAL BODY (MPEM) 1.5 0.01 1.24 1.71 13.57 3.0 8.27 j
CRIT. ORGAN (MREM) 5.0 0.00 0.57 3.91 5.76 10.0 3.54 i
LIVER LIVER GI-LLI LIVER LIVER RESULTS BASED UPON ODCH REVISION 10 UPDATE DM002 OCTOBER 1985 t
i k
l i
i i
i 48 L
BYRON STATION Figure 5.0-1 0FFSITE AIR SAMPLING AND TLD LOCATIONS s'
e on
~
s Leaf River i
g
~
Addltional TLDs
[
gggg.
.,,,, /
f.lley 1
m sVRON
- 3 WL UTATION L
7 Warris FA
' e, f
. N$I*
, AA o,.
x osa R e c e_
SCALE
, sana Air Sanolers 1 - Byron 5 - Nearsite Station - S 2 - Stillman Valley 6 - Oregon 3 - Nearsite Station - E 7 - Mt. Morris 4 - Paynes Point 8 - Leaf River TLD Same as air samplers plus a sufficient number of additional dosimeters placed near the site and near 5 miles to assure that one dosimeter is located at each range in each of the 16 meteorological sectors.
49
BYR0ti STATI0tl Figure 5.0-2 ONSITE AIR SAMPLING AND TLD LOCATIONS
' ske n.5 ' %
j BY2l ParY1 I
i, a
BYRON STADON L
r, BY22 x
l BY24 M
j==b, '
i N GRAVEL RD BY2s DEEPPATH RD
--g
/f 3-1 1
,m 1
50
BYRON STATION l
Figure 5.0-3 f
I ENVIRONMENTAL RADIOLOGICAL MONITORING LOCATIONS l
t s'
?
1 - Byron Air Sanpler g'i
. g/
2 - Stillman Valley Air Sanpler i
3 - tiearsite Station - East Air Sanpler syr.,
",EEM i
8 l
4 - Paynes Point Air Sanpler x
'I 5 - FMarsite Station - South Air Station 8'
N,',,
2 a
g 6 - Oregon Air Sanpler g
4 7 - Mt. Morris Air Sanpler O
f',se e
8 - Leaf River Air Sanpler i3 l
9 - Woodland Creek Surf ace Water Sanple j"/
l
$',Yl,7 E
10 - Intake Surf ace Water Sanple i
11 - Discharge Surf ace Water Sanple I-o/n
- I*
12 - Conposite Downstream Surf ace Water Sanple synoN F
- 3 Mt s! pion i
l 13 - Lpstream Surf ace Water Sanple I
14 - Of f site Well Water r e,"'"I',., ceu.
- 8 2
~
15 - J. A. Reeve'rts Pine Hill Dairy
=
g i
j g
16 - Kenneth Durien Farm
{,i s, p,i.a l
17 - Bosecker/Lingel Dairy Farm
- >it 3
4**
I enc P*t
= a 18 - Off site Well Water Sanple s,
5 19 - Vegetable Farm j
,g, 20 - Ed Seabold Farm o,,,,,
i 21 - Onsite 22 - Onsite i
l 23 - Onsite 24 - Onsite
- Q
[
t y aus
BYRON STATION Figure 5.0-4 SPECIAL TLD LOCATIONS 1
i n
i[ 9
~
f}.'-
Fh.... J.F r_h +- :., %
- a r
7,>%t l
i l
i l } }k!,... x&
y * '"hy.(
cf.
bO )!!$
i
[
??*
.",k i h 'r5'g l' l
U.
~
\\
g.-
- d)5 k $.I,))J
- VI.*
.=
, v4 tug __~. _.%.m I
M'.1 i
^'
,s ~,c
,g
.=
v
$$.,*,,,,1ha*
%y gh y'pygPg:,
av b VI Ij fh5. rd b.h dd.,. ' '.[ d[h f,y, Yh L,$'$b
~~
vt=
r If
[/M l' l I i f. '
r a,%
ms
,- \\
.un g w
- L Og
,F,,
,!f-N 4,!a>%y,*o: v ; d..., 1 m m m,
-J
,s L
a.
.p-n.
- gggg' ~.,
- " Ban uriC "J.
j j,.
O
,.w' ****
.:.?..,
'.e$ -
o-n.
) r
- '. p.
.g e v e-q A' jyAw g-
- ~
d p ( n,8 g..
sg
'W V.a w p _; h. - Qr x,:
g p-a'. ank..u.
, m. -
=..,;;,', - - c,,Q ff
@f?'
n 4...
4,\\-/.'
N " %ler
- 1
] ~~+ 1:t.vri ;,"'
cm p p.
. Em
- T.,i r 6,,
1 o
,1,1,i
.;5 j
'4,.,
- 1. _
s t 'u "7~
t M}~
,4 4
j t,it s.[-d )
?yg.") n' s
.I,/. :
util w,
f,~.mt e.a.:
0./
/
.a.,3 x( em 4
.er;k
.t...
v p.. l
.~
a je v=d.
f S %. M., -
- - :.. p[ yu A. %I 1.jJC A N 8 @!
s&%,:
? % %U ? y =~E.,T t. m y ".i g*' o R s,2 t
r. f x,.11, J i
he,4
\\ :~ f@j e/..
m
, c. go.4)5 ;g[. l' b ",....
h
(.A g
r e,;;-
m t
4 A
hTE s
ms%_A su me 52 1
Table 5.0-1 BVRON STATION ENylR0WNTAL RADIOLOGICAL MONII0HING SN1PLING SITES l
b MLDIA 5
+
0 8
t o
t 3
b u
i I
I
' 3 3
a 2
3 4 i
f
(
Location location o T E
Code Type Location w
u u
c2 u.
r a
o a
- =
2 Bf-01 C
Byron Air Sagler X
X BY-02 C
Stillman Valley Air Sam ler X
X BY-03 hearsite - East Air Sagler X
X BY-04 Palnes Point Air Sagler X
X BY-05 Nearsite - South Air Sarnpler X
X BY-01 C
Mt. Morris Air Sag ler X
X BY-08 C
Leaf River Air Sagler X
X BY-09 Woodland Creek Surface Water Sam ler X
BY-10 Intake Surf ace Water Sagler X
BY-ll Discharge Surf ace Water Sagler X
Bf-12 Cogosite Downstrean ~'erf ace Water X
X X
X Sagler BY-13 C
lbstream Surface Water Sa g ler X
X X
X BY-14 Of f site Well Water X
BY-15 Reeverts Pine Hill Dairy X
X X
X X
HY-16 Kenneth Durien Farm X
X X
X X
BY.11 C
Bosecker/Lingel Dairy Farm X
X X
X X
BY-18 Of f-stte Well Water X
BY 19 Vegetable Farm X
BY-20 Seabold Farm X
X X
X X
BY-ll Byron Nearsite N X
X BY-22 Byron Nearsite ESE X
X BY 23 Byron Nearsite S X
X HY-24 Byron hearsite SW X
X
- Centrol (background) locations are indicated by a "C' in this column. All other locations are indicators.
53
N j
i Table 5.0-2 BYRON STATION
{
ENVIR0fMENTAL RADIOLOGIAL MONITORING PROGRAM, SAMPLING LOCATIONS i
j 1.
AIR SAMPLERS Distance Direction l
Site Codea Location (miles)
(*)
i BY-01 a.
Byron
' 3. 5 25
]
BY-02(C) b.
Stillman Valley
- 6. 2 56 i
BY-03 c.
Nearsite - East
- 3. 8 85 l
BY-04 d.
Paynes Point
- 4. 5 14 0 1
BY-05 e.
Nearsite - South
- 3. 6 180 i
BY-06 f.
Oregon ~
- 4. 6 213 i
BY-07(C) g.
Mt. Morris
- 7. 8 240
{
BY-08 (C) h.
Leaf River
- 7. 0 315 i
BY-21 1.
Onsite 0.26 9
l BY-22 j.
Onsite
- 0. 3 101 BY-23 k.
Onsite
- 0. 6 182 j
BY-24 1.
Onsite
'). 6 5 229
]
2.
TLDs a.
Same as No. 1.
i b.
Special TLD Saglers j
Distance Direction Site Codea (miles)
(*)
BY-101 1,2
- 1. 2 13 j
BY-102 1,2
- 1. 0 25 1
BY-103 1,2
- 1. 7 51 1
BY-104 1,2 1.4 64 e
f BY-105 1,2
- 1. 3 '
84 i
BY-106 1,2
- 1. 4 108 i
BY-107 1,2 1.4 141 1
8Y-108 1,2
- 0. 6 158 BY-109 1,2
- 0. 6 183 BY-110 1,2 0.6 201 BY-111 1,2 0.9 235 BY-112 1,2 0.8 247 4
a Control (reference) locations are denoted by a "C" after site code.
All other locations are indicators.
i 54 1
5
. - -, - - ~. -, -., -.. - - -,, _. _ _ _,,.,, _,,. -
,m.,-,---
.._,.__,,__,_-,-,,,.,__.,_,,-,_.-,..--,..,._---,..-.m-,
l Table 5.0-2 (cor.tinued)
BYRON STATION ENVIRONMENTAL RADIOLOGIAL MONITORING PROGRAM, SAMPLING LOCATIONS 2.
TLDs b.
Special TLD Samplers (continued)
Distance Direction Site Codea (miles)
(*)
BY-113 1,2
.0.7 270 BY-114 1,2 1.8 298 BY-115 1,2
- 1. 0 314 BY-116 1,2
- 1. 4 329 BY-201 1,2 4.8 36 0 BY-202 1,2 4.5 13 BY-203 1,2 5.1 42 BY-204 1,2 4.2 66 BY-205 1,2
- 3. 9 89 BY-206 1,2 4.2 112 BY-207 1,2 4.2 140 BY-208 1,2 4.1 159 BY-209 1,2
- 3. 8 189 BY-210 1,2
- 3. 6 218 BY-211 1,2
- 5. 2 238 BY-212 1,2 4.9 257 BY-213 1,2 5.0 280 BY-214 1,2 4.8 298 BY-215 1,2
- 5. 2 32 2 BY-216 1,2 4.8 337 3.
MILK Distance Direction Site Codea Location (miles)
(*)
BY-15 a.
J. A. Reeverts Pine Hill
- 3. 2 108 Dairy BY-16 b.
Kenneth Druien Farm
- 3. 3 134 BY-17(C) c.
Bosecker/Lingel Farm
- 7. 0 53 BY-20 d.
Ed Seabold Farm
- 2. 5 41 a Control (reference) locations are denoted by a "C" af ter site code.
All other locations'are indicators.
55 j
Table 5.0-2 (continued)
BYRON STATION ENVIRONMENTAL RADIOLOGIAL MONITORING PROGRAM, SAMPLING LOCATIONS 4.
PRECIPITATION Same as No. 3.
5.
VEGETABLES Distance Direction Site Code Location (miles)
(*)
~
BY-19-1 Oregon Stand BY-19-2 Oregon Stand 6.
CATTLE FEED AND GRASS Same as No. 3.
7.
WELL WATER Distance Direction Site Code Location (miles)
(*)
BY-14 a.
Of f -si te Wel l
- 0. 3 101 BY-18 o.
McCoy Farmstead
- 1. 0 235 (CECO-owned well) 8.
SURFACE WATER J
Distance Direction Site Code Location (miles)
(*)
l BY-09 a.
Woodland Creek 2.1 32 0 BY-12 b.
Downstream at Oregon Dam 4.5 213 BY-13 (C) c.
Upstream of Intake 2.6 302 4
9.
COOLING WATER Distance Direction Site Code Lootion (miles)
(*)
BY-10 a.
Byron Intake Pipe / River
- 2. 4 283 BY-11 b.
Byron Discharge Pipe /
- 2. 3 283 River 56 i
l l
l-Table 5.0-2 (continued) i BYRON STATION l
ENVIRONMENTAL RADIOLOGIAL MONITORING PROGRAM, SAMPLING LOCATIONS 10.
FISH 4
Distance Direction Site Code Location (miles)
(*)
I BY-12 a.
Downstream at Oregon Dam
- 4. 5 213 BY-13(C) b.
Upstream of Intake 2.6 302
- 11. AQUATIC PLANTS Same as No. 10.
12.
BOTTOM SEDIMENTS Distance Direction Site Code Location-(miles)
(*)
BY-12 a.
Downstream at Oregon Dam
- 4. 5 213 BY-13(C) b.
Upstream of Intake
- 2. 6 302 1
b
.\\
+
~~
S i.y yr-
- s
- s.
_f
, y#
?,
'(
-[,+
,R)
- l' L
Tacle 5.0-2 (continued)
BY<uN STATIJN ENVIRu'.MENTA a-]IOLOGICat M.ON!!uRING PROGRAM, SAMPLE COLLECT 104 ANJ AAA YSES Location Collection Type of Frequency Sample Media codes site Frequency Analysis of Analysts Remarks 1.
Airborne BY-1 Byron Continuous Gross beta Wee <1y un all samples.
Particulates BY-2 (C) 5ttllman valley operation Sr-89.-90 Cuarterly On quarterly composites from each location.
BY-3 Nears ite-E for one Gamma Isot 02arterly un quarterly composites from eacn location.
BY-4 Paynes Point week BY-5 Nearsi te-S Non-routtne Reporting Levelsb BY-6 Oregon BY-7 (C)
Mt. Morris Cs-134 10, Cs-137 20 pC1/m3 BY-8 (C)
Leaf River BY-21 Onsite BY-22 Onsite BY-23 Onsite BY-24 Onsite en 2.
Airborne Sane as 1.
Continuous 1-131 weekly On all saaples, oo lodine operation for one Non-routine Neporting Level week 0.9 pC1/m3 3.
Air Sampling Same as 1.
Test and weekly on all samplers.
Train Maintenance 4.
TLD Same as 1.
Qu arterly Gamma Quarterly Two sets at all AP locations. Une set read quarterly. Second set read if reautred BY-101-1,2 Inner ding by Commonwealth Edison. At otner loca-through tions, all sets read quarterly. Minimum 116-1.2 of two TLDs per set.
8Y-201-1,2 Outer king
- througn, 216-1,2 a Control (ref e ence) locations are denoted by a "C" in this colonn. All otner loca* ions are indicators, r
b Average concentration over calendar quarter.
i fable 5.u-2-(continucd)
BYRON STATION ENVIRONMENTAL RADIOLOGICAL MUNITURING PROGRAM, SAMPLE COLLECTION AND ANALYSES (continued)
Location Collection Type of Frequency Sample Media Code
- Site Frequency Analysis of Arialysis xemarks 5.
Milk 8Y-15 J. A. Reeverts Pine Biweekly:
1-131 8tweekly un all samples. LLu: 0.5 pC1/1.
Hill Dairy May through Gamma 1 sot.
May -
BY-16 Kenneth Drufen Farm Octobar Sr-89,-90 October Non-routine Heporting Levels 0 BY-17 (C)
Bosecker/Lingel Dairy Fara Monthly:
Monthly I-1313; Cs-134 bO; Ls-137 70; BY-20 Ed Seabold Farm hovember November - Ba-La-140 300 pC1/1 through April April 6 Precipitatfor Same as 5.
Monthly Gross beta Monthly On all samples.
Gamma Isot Quarterly.
On quarterly composites from each location.-
Tritium Quartrerly On quarterly composites from eacn location.
Sr-89.90 Quarterly On quarterly composites from each location, bS 7.
Vegetables 8Y-19-1 Oregon Stand Annually at Gross beta Annually Four varieties (at least one green leafy BY-19-2 harvest Gamma Isot Annually vegetable) from eacn location as evallanie Sr-69 -90 Annually at harvest. (I-131 on green leafy vege-1-131 Annually tables.)
8.
Cattle Feed Same as 5.
Quarterly Gross beta Quarterly Grass: Summer (May - October) and Grass Gamma Isot Quarterly Feed: kinter (hovember - April)
Sr-89,-90 Quarterly.
9.
Well Water.1 BY-14 Off-site Well Quarterly Gross beta Quarterly On all samples.
Offsite Gamma Isot Quarterly on all samples.
8f-18 McCoy Farmstead Tritium Quarterly on all samples.
Sr-89, 90 yuarterly on alt s amples.
a Control (reference) locations are denoted by a "C" in this column. All other locations are indicators.
Average concentration over calendar quarter.
(
Table 5.0-2 (continued)
BYRON STAT!UN ENVIRONMENTAL HADIOLOGICAL MON!TORlhG PRUGHAM, SAMPLE COLLECTluN MND ANALYSES (continued) location Collection Type of Frequency Sample Media Codea 5ite Frequency analysis of Analysis xemarks
- 10. Surf ace Water BY-09 Woodland Creek Weekly (if Gross beta weekly Oi all samples.
8Y-12 Downstream at Oregon Woodland Tritium Quarterly un quarterly composites f rom each location.
8Y-13 (C)
Dam Creek is Gamma Isot Moqthly un monthly composites froin eacn location.
Upstream of Intake flowing)
Sr -89. -90 Quarterly On quarterly composites from eacn location.
Non-routine weporting Levelso (See f ootnote 'c.")
- 11. Cooling Waterd gy.10 Intake pipe Weekly Gross beta Weekly On all samples.
BY-ll Discharge pipe Gamma Isot Montnly un montnly composites from eacn location.
Tritium Montnly un monthly composites from eacn location.
Sr-89,-90 Monthly On montnly composttes from eacn location.
Ch o
- 12. Fish BY-12 Downstream at Dregon Three times Gross beta Three times From Oregon pool of deck River, on ediole BY-13 Dam a year.
Gamma Isot a year.
portions only. At least two species.
U stream of Intake Sr-89,-90 Non-routine Reporting Levels 0 4
4 4
Mn-54 3x10 ; Fe-59 lx10 ; Co-58 3x10 )-
4 4
Co-60 lx10 Zn-65 2x10 ; Cs-134 1x10 ;
Cs-137 2x10I pLi/kg wet weigns.
- 13. Aquatic Same as 12.
Three times Gross beta Three times If available.
Plants a year.
Gamma Isot a year 14.
Bottom BY-12 Downstream at Dregon Three times Gross beta Three times un all samples.
Sediments BY-13 Dam a year Gamma Isot a year On all samples.
Upstream of Intake
' Control (ref erence) locations are denoted oy a "C" in this column, all other locations are indicators.
Average concentration over calendar quarter.
c 4
3 2
3 2
2 2
H-3 2x10, an-54 lx10, Fe-59 4x10, Co-581x10, Co-60 3x10, 2n-65 3xlC, 2r-Nb-95 4x10,1-1312. Cs-134 30. Cs-137 50, 8a-La-140 2x lu2 peif t.
d Provided by station personne).
Table 5.0-2 (continued)
BYRON STATION ENVIRONMENTAL N AD10 LOGICAL M0!41TORING Pn0 GRAM, SArlPLE COLLECTION AND ANALYSES (continued)
Location Collection Type of Frequency Sagle Media code M te Frequency Analysis of Analysis Remarks t
a.
Enumeration by a door-Annually inaring grazing season.
- 15. Dairy Census a.
Site boundary to 2 miles to-door or equivalent counting technique.
b.
2 miles to 5 miles
' b.
Enumeration by using Annually During grazing season.
referenced information from county agricultural agents or other reliable sources.
c.
Inquire as to feeding mnually During grazing season.
c.
At dalries listed in item 5.
practices:
(1) Pasture only.
(2) Feed and chop only.
1 (3) Pasture and feed; if both, ask farmer to estimate fraction of food from pasture:
<255,25-50s, 50-755, or >755.
- 16. Nearest in all 16 sectors Annually Residence.
Census L
,v m
w.
,,,s
---ns
Table 5.0-3 ENVIRONMENTAL RADIOLOGICAL MONITORING PRUGRAM QUARTEHLY
SUMMARY
Name of Facility syron Nuclear Power Station Docket No.
50-454. Su-ded Location of Facility Ogle, Illinois Reporting Period 1st Ouarter 1965 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations hur.ber of Type Number of Meana Mean Meana Non-routine (Units)
Analyses LLD Range Location Range Range Results Air Particulates Gross Beta 156 0.01 0.027 (116/117)
By-22, Onsite 0.029 (13/13) 0.026 (38/J9) 0 (pCl/m3)
(0.011-0.062) 0.3 mi e lul" (0.01b-U.002)
(0.012-0.0$2)
Gamma Spec.
12 0.01
<LLD
<LLD 0
Sr-89 12 0.01
<LLD
<tLU 0
Sr-90 12 0.01
<tLO
<LLu o
Airborne lodine I-131 156 0.07
<LLD (LLu O
(pC1/m3)
Gamma Background Gamma Dose 3.0 13.0 (9/9)
By-22, unsite 14.7 (1/1) 12.1 (J/3) 0 (TLDs) (mR/Qtr.)
(11.4-14.7) 0.3 mi W 10l*
(10.9 12.8) cn h3 Milk I-131 12 1.0
<LLO
<L'Lo O
(pC1/1)
Gamma Spec.
12 Cs-134 5.0
<LLD
<ttu o
Cs-137 5.0
<LLD
<LLu 0
Other Gammas 10.0 (LLD
<LLD 0
Sr-89 12 10
<LLD
<ttu o
Sr-90 12 2
2.8 (2/9)
By-17, Bosecker/
3.2 (3/3) 3.2-3/3) o (2.4-3.2)
Lingel Farm (2.8-4.1)
(2.8-4.1) 7.0 mi W S3' Precipitation Gross Beta 10 15.7b (LLD By-17, Bosecker/
22.8 (1/3) 22.5 (1/3) 0 Lingel Farm 7.0 mi e 53*
Gamma Spec.
4 20
<LLD
<LLD 0
Tritium 4
200 (LLD
<LLv u
Sr-89 4
10 (LLD
<LLu o
Sr-90 2
2.2 (1/3)
By-15. Heeverts Pine 2.2 (1/3)
(LLu o
Hill Dairy 3.2 mi W 108*
Table 5.0-3 (continued)
(
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM QUANTERLY StJMHasty Name of Facility Byron Nuclear Power Station Docket No.
50-454, 50-455 Location of facility Ogle, Illinois keporting Period 1st Q>arter 1985 (Lounty, 5 tate)
'.. i, Indicator Location with Highest Control Sample Type and Locations quarterly Mean Locations seumoer of Type Number.of Meana Mean Meana Non-routine-(Units)
Analyses LLO Range Location Range Range Results Cooting water Gross Beta 25 1.0 4.2 (13/13)
By-ll, Discharge 4.2 (13/13) 2.9 (12/12) 0 (pCf/1)
(2.2-6.2) 2.3 mi W 283 (2.2-6.2)
(l;0-5.4) l Gamma Spec.
6 Cs-134 10
<LLD
<LLO O
Cs-137 10
<LLD
<LLu 0
6
<LLO U
I Other Gammas 20
<LLD t
Tritium 6
200
<LLD
[
(LLD U
[
l I
O
.c* * * * * * "
S.-89 6
10
<LLO
<LLO O
k Sr-90 6
2 (LLD
<LLO O
Surf ace Water Gross Beta 39 1.6 3.3 (23/26)
By-12, Downstream at 3.6 (13/13) 3.4 (13/13) 0 i
(pCi/l)
(1.6-6.3)
Oregon Dam (2.2-6.3)
(1.b-6.8)
A.5 at W 213' i
Gamma Spec.
9 l
Cs-134 10
<LLO
<LLU u
Cs-137 10
<LLO
<LLD 0
Other Gammas 20 (LLD (LLu O
Tritium 3
200
<LLD
<Ltu u
Sr-89 3
10
<LLD (LLO u
)
Sr-90 3
'2 (LLD dy-12, Downstream at 2.9 (1/1) 2.9 (1/l) u cregon Dam 4.5 mi W 213*
1
_~..
. - _ ~, - - _ ~
..~
1 ENVIRONMENTAL RADIOLOGICAL MONITORING PRCGRAM QUAkTERLY
SUMMARY
Name of Facility Byron Nuclear Power Stetton Docket ho.
50-64 50-455 Location of Facility Ogle. Illinois Reporting Period 1st Quarter 1985 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations humber of Type Number of Meana Mean Meana leon-roucine (Units)
Analyses LLD Range Location Ranga Range Hesults kell Water Gross Beta 2
2.9 6.1 (1/2) dy-16, McCoy Farmstead 6.1 (1/2)
(LLO U
t (pC1/1) 1.0 mi 9 235" 4
Gama Spec.
2 Cs-134 10
<LLD
<LLU 0
Cs-137 10
<LLD
<LLO 0
i Other Gammas 20
<LLU
<LLO O
cn Tritium 2
200 240(1/2)
By-18, McCoy Farmstead 240(1/2)
<LLU 0
1.0 ml W 235' I
Sr-89 2'
10 (LLO
<LLU 0
i Sr-90 2
2
<tLD
<LLO O
Cattlefeed & Grass
. Gross Beta 8-1.0' 4.4 (b/6) dy-IS, Reeverts Pine 5.1 (2/2)
>3.1 (2/2)'
U' (pC1/g wet)
(1.4-7.1)
Hill Dairy (3.8-6.4)
(1.2-5.0) 3.2 mi W 108*
Gama Spec.
8 Cs-134 0.1
<LLD
. LLD.
O
<LLu 0
I j
.Other Gammas 0.2
<tLD-
<Lto 0
Sr-89
'8 1.0
<LLD
<LLD' o
Sr-90 8
1.0
<LLD (LLD o,
~
- Mean and range based on detectable measurements only. Fraction indicated in parentnesis.
b LLO value dependent on volume of sample available for analysis.
Table 5.U-4 ENVIRONMENTAL RADIOLOGICAL MONITORING PRUGRfN QUARTERLY
SUMMARY
Name of Facility Byron Nuclear Power Station Docket No.
50-454. 50-455 Location of Facility Ogle. Illinois Reporting Period 2nd Quarter 1985 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly dea 9 Locations humber of Type Number of Meana Mean Mean8 hon-routine (Units)
Analyses LLD Range Location Rarge Range desults Air Particulates Gross Beta 156 0.01 0.020 (116/117)
By-03, Nearsite - East 2.1 (13/13) 0.020 (39/J9) 0 (pCl/m3)
(0.007-0.032) 3.8 mi W US*
(0.014-0.028)
(0.011-0.033)
By-05, Nearsite -
2.1 (13/13)
Svet h, 3.6 ml v 180*
(0.012-0.030)
By-06, Oregon 2.1 (13/13) 4.6 mi 9 213*
(0.016-0.030)
Gamma Spec.
12 0.01 (LLD
<LLU 0
Sr-89 12 0.01
<LLD
<LLD 0
cp Sr-90 12 0.01
<LLD (LLO O
Airborne lodine I-131 156 0.07
<LLD
<LLO O
(pC1/m3)
Gamma Background Ganma Dose 3.0 13.0 (9/9) dy-04, Paynes Point 16.7 (1/l) 14.2 (3/3) 0 (TLDs) (mR/Qtr.)
(10.5-16.7) 4.5 ml 9 140' (13.0-15.3)
Milk I-131 20 1.0/0.5b
<LLD
<LLO O
(pCl/1)
Gamma Spec.
20 Cs-134 5.0 (LLD
<LLD 0
Cs-137 5.0
<LLO
<tLD 0
Other Gammas 10.0
<LLO
<LLD u
i Sr-89 20 10
<LLO
<LLu o
j Sr-90 20 2
2.9 (14/15) 3.6 (5/s) o (1.7-3.9)
(J.0-4.3) i i
Table 5.0-4 (continued)
ENVIRONMENTAL RADIOLOGICAL MON!TURING PROGRAM QUARTERLY
SUMMARY
Name of Facility Byron Nuclear Power Station Docket No.
50-454, 50-455 Location of Facility Ogle, Illinois Reporting Period 2nd Quarter 1985 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Number of Type Number of Meana Mean Mean4 Non-routine (Units)
Analyses LLD Range Location Rc2ge Range Hesults Precipitation Gross Beta 12 12.0C 49.5 (5/9)
By-16, Kenneth 79.8 (2/3)
<lLD 0
(13.4-146.2)
Drufen Farm (13.4-146.2) 3.3 ml 9 134' Gamma Spec.
4 20
<LLD
<LLD 0
Tritium 4
200
<tLD
<LLO O
Sr-89 4
10
<LLD
<LLO O
2
<LLD
<LLU U
Cooling Water Gross Beta 26 1.0 6.1 (13/13) dy-ll, Discharge 6.1 (13/13)
J.2 (12/13) 0 (pCf/1)
(3.6-12.8) 2.3 mi 9 283 (3.6-12.8)
(2.0-7.8)
Gamma Spec'.
6 Cs-134 10
<LLD
<LLU 0
Cs-137 10
<LLD
<LLU O
Other Gammas 20
<LLD
<LLD 0
Tritium 6
200 3520 (3/3)
By-ll, Discharge 3520 (3/3)
<LLD 0
(310-8120) 2.3 mi 9 283 (310-8120)
Sr-89 6
10 (LLD
<LLD 0
Sr-90 6
2 (LLD
<LLO O
~
Table 5.0-4 (continued)
ENVIRONMENTAL RADIOLOGICAL MONITUR!hG PROGRAM QUARTERLY
SUMMARY
Name of Facility Byron Nuclear Power Station Docket No.
50-454 50-456 Location of Facility Ogle. Illinois Reporting Period 2nd Quarter 1985 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations numoer of Type Number of Meana Hean Meana Non-routine (Units)
Analyses LLD Range Location Range Range Results Surface Water Gross Beta 39 2.0 2.2 (24/26)
By-12 Downstrean at 2.5 (12/13) 2.4 (13/13) 0 (pCl/1)
(1.1-3.5)
Oregon Dam (1.7-3.5)
(1.7-3.6) 4.6 mi W 213' Gamma Spec.
9 Cs-134 10
<LLD
<LLU U
Cs-137 10
<LLU
<LLD 0
Other Gammas 20
<LLD
<LLU 0
0 Tritium 3
200 305 (2/2)
(LLU 0
(250-360)
Sr-89 3
10
<LLD
<LLU 0
Sr-90 3
2
<LLD (LLU U
Well Water Gross Beta
~3
4 7.9 (1/1)
By-18, McCoy Farmstead 7.9 (1/1)
None 0
(pCf/1) 1.0 ml 9 235' Gamma Spec.
2 Cs-134 10 (LLD O
Cs-137 10
<LLD 0
Other Gammas 20
<LLD 0
Tritium 2
200
<LLD 0
Sr-89 2
10
<LLD U
Sr-90 2
2
<LLD U
Table 5.0-4 (continued)
ENVIRONMENTAL RADIOLOGICAL MONITOR!hG PROGRAM QUARTERLY SUMrtARY Name of Fact 11ty Byron Nuclear Power Station Docket No.
50-454. 50-465 Location of Facility Ogle. Illinois Reporting Perlov 2nd Quarter 1983 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Number of Type Number of Meana Mean Meana Non-routine (Units)
Analyses LLD Range Location Range Range Nesults Fish Gross Beta 6
1.0 2.0 (2/2)
By-13, Upstream of 3.4 (4/4) 3.4 (4/4) 0 (pCl/g wet)
(1.1-3.0)
Intake (2.5-4.5)
(2.5-4.5) 2.6 mi e 302' Gamma Spec.
6 Cs-134 0.1
<LLD
<LLD 0
Cs-137 0.1
<LLO
<LLO O
Other Gammas 0.2
<LLD
<LLU U
co Sr-89 6
1.0
<LLD
<tLU U
Sr-90 6
1.0 (LLD
<LLO '
O Cattlefeed & Grass Gross 8 eta 4
1.0 4.3 (3/3)
By-20, Seabold Farm 4.8 (1/1) 5.0 (1/1) 0 (pC1/g wet)
(3.8-4.8) 2.5 mi 9 41*
bamma Spec.
4 Cs-134 0.1
<LLD
<tLD 0
Cs-137 0.1
<LLD (LLO O
e Other Gammas 0.2 (LLD
<LLU 0
Sr-89 4
1.0
<LLO
<LLD 0
Sr-90 4
1.0
<LLD -
(LLU 0
Table 5.0-4 (continued)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM QUARTEHLY
SUMMARY
4 Name of Facility Byron Nuclear Power Station Docket ho.
50-454. 50-455 Location of Facility Ogle. Illinsis keporting Period 2nd Quarter 1985 (County, State)
Indicator Location with riighest Control Sample Type and Locations Quarterly Mean Locations.
humoer of Type Numoer of Meana-Mean Meana Non-routine 4
(Units)
Analyses LLD Range Location Hange Range Results l l
Aquatic Vegetation Gross beta 2
1.0 0.7 (1/1)
By-13, Upstrece of 4.0 (1/1) 4.0 (1/1) 0
)'
(pCi/g wet)
Int ake 2.6 ml 9 302*
i Gamma Spec.
2 Cs-134 0.1 (LLD
<LLO O
l 1
<LLu O
Cs-137 0.1
<LLD Uther Garunas 0.2 (LLD
<LLD 0
e Bottom Sediments bross Beta 2
1.0 8.6 (1/1)
By-12, Downstream at u.6 (1/1) 8.0 (1/1)
U Oregon Dam (pCi/g dry) 4.5 mi to 213' 4
i Gamma Spec.
2 e
Cs-134 0.1 -
<LLD
<LLU u
Cs-137 0.1 0.12 (1/1)
By-12, Downstream at 0.12 (1/1)
<LLu u
Uregon Dam i
4.5 mi 18 213*
i f
other Gammas 0.2-
<LLD (LLO O
1
+
1 Mean and range based on detectable measurements only. Fractions indicated in parentneses.
b November - April LLD = 1.0; May - October LLD = 0.5 pCl/1.
i L
C LLD value dependent on volume of sample available for analysis.
i L
i 4
j
Tabic 5.0-5 ENVIRONMENTAL RADIOLOGICAL MONITOR!hG PROGRAM QUARTERLY
SUMMARY
Name of Facility Byron Nuclear Power Station Docket No.
50-454, 50-455 Location of Facility Ogle. Illinois Reporting Period 3rd Quarter 19b5 (County, State)
Indicator Location with Highest Crntrol Sample Type and Locations Quarterly Mean Locations Number of Type Number of Meana Mean Mean8 Non-routine (Units)
Analyses LLD Range Location Range Range Hesults Air Particulates Gross Beta 156 0.01 0.025 (117/117)
Hy-02, Stillman Valley 2.7 (13/13) 0.026 (38/39) 0 (pct /m3)
(0.012-0.039) 6.2 ml 9 56*
(0.016-0.039)
(0.015-0.039)
By-08 Leaf River 2.7 (13/13) 7.0 mi 9 315*
(0.017-0.032)
Gama Spec.
12 0.01
<LLD (LLD 0
Sr-89 12 0.01
<LLD
<LLO O
Sr-90 12 0.01
<LLD
<tLD 0
Airborne lodine I-131 156 0.07 (LLD
<LLD 0
(pC1/m3) yo Gama Background Gama Dose 3.0 13.8 (9/9)
By-22, Onsite 16.1 (1/1) 12.ti (3/3) 0 (TLUs) (mR/Qtr.)
(11.4-16.1) 0.3 mi e 10l*
(12.3-12.8)
Milk I-131 24 0.5
<LLD (pCi/1)
<LLD 0
Gama Spec.
24 Cs-134 5.0
<LLD
<LLD 0
Cs-137 5.0
<LLD
<LLD 0
Other Gamas 10.0 (LLO
<Ltu O
Sr-89 24 10 (LLD
<LLO O
Sr-90 24 2
2.8 (17/18) 3.b (5/s) 0 (2.3-3.4)
(2.4-4.1)
Precipitation Gross Beta 12 9.0b 26.2 (6/9) dy-20, Seabola f arm b3.1 (2/3) 19.0 (J/3) 0 (10.1-73.7) 2.5 mt 41*
(32.b-73.7)
(9.3-3J.7)
Gama Spec.
4 20,
<LLD
<LLD 0
Tritium 4
200
<LLD
<Ltu o
Sr-89 4
10
<LLD
<LLu o
Sr-90 4
2
<LLD
<lLD 0
Table 5.0-5 (continued) i ENVIR0re4 ENTAL RADIOLOGICAL MONIVURING PROGRAM QUARTERLY SUPMMY Name of Facility Byron Nuclear Power Station Docket No.
50-454 50-455 location of facility Ogle. Illinois Reporting Period 3rd Quarter 1983 l
(County, State)
Indicator Location with tilgnest Control Sample Type and Locations Quarterly Mean Locations humber of Type Number of Neana Mean Meana Non-routine (Units)
Analyses LLD Range Location Hange Range kesults Cooling Water Gross Beta 1.6 158.5 (13/13) 8 -11, Discharge 158.5 (13/13)
J.3 (12/14) 3 3
(pct /I)
(3.4-1043) 2.3 mi e 283 (3.4-1043)
(2.3-5.0)
Gama Spec.
6 Cs-134 10 (LLD
<LLU 0
Cs-137 10 (LLO
<LLO O
Mn-51 10 200 (2/3)
By-II, Discharge 200 (2/3)
<L LU 2
(167-234) 2.3 mi y 283 (167-454)
Co-58 10 1935 (2/3) sy-ll, Discharge 1935 (2/3)
(LLD 2
(1810-2060) 2.3 mi is 283 (1810-2060)
N Co-60 10 182 (2/3)
By-ll,Olscharge 182 (2/3)
<LLU -
2
~
3 (155-219) 2.3 mi W 283 (155-219)
Other Gammas 20
<LLD
<LLu O
Tritium 6
200 3920 (3/3)
By-ll, Discharge 3920 (3/3)
<LLD 3
(220-5910) 2.3 mi 61 283 (220-5910) i Sr-89 5
10 (LLO
<LLD 0
i Sr-90 6
2 (LLU
<LLO O
i.
Surf ace Water Gross Beta 39 1.4 4.1 (22/26)
By-12. Downstrem at 4.6 (13/13) 3.4 (13/13) 0 (pCf/1)
(2.2-18.0)
Oregon Dam (2.2-18.0)
(1.5-13.2) 4.5 mi W 213*,
i Gamma Spec.
9 Cs-134 10
<LLD (LLu o
<Llu 0
l uther Gammas 20
<LLD
<LLu 0
1 i
Tritium 9
200 (LLU 4
<LLO o
Sr-89 9
10
<LLD
<LLu o
Sr-90 9
2 (LLO
<LLu o
,i -
u
Taoie 5.0-5 (continued)
ENillRONMENTAL RADIOLOGICAL MON!TURING PROGRAM QUARTERLY
SUMMARY
f.xne of Facility dyron Nuclear Power Station Docket No.
50-454 50-455 Location of f acility Ogle, Illinois Reporting Period 3rd Quarter 19o5 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Number of Typ e Number of Meana Mean Meana Non-routine Jnits)
Analyses LLO Range Location Range Range Nesults Well Water Gross Beta 2
2.8 9.0 (1/2)
By-18 McCoy Farmstead 9.0 (1/1)
None 0
(pti/1) 1.0 ml 9 235*
Ganana Spec.
2 Cs-134 10 (LLD None O
Other Gamas 20
<tLD I4one 0
Tritium 2
200 250 (2/2)
By-14. Off-site Well 290 (1/1)
None 0
(210-290) 0.3 mi 0 10l*
1 Sr-89 2
10
<LLD None O
M Sr-90 2
2
<LLD None 0
Fish Gross Beta 4
1.0 3.8 (2/2)
By-12. Oregon Pool 3.8 (2/2) 3.3 (2/2) 0 (pCl/g wet)
(3.6-3.9) 4.5 mi W 213*
(3.o-3.8)
(3.3-3.3)
Gama Spec.
4 Cs-134 0.1
<LLD
<LLO O
Cs-137 0.1
'<LLD
<LLU 0
Other Gamas 0.2
<LLO
<LLD 0
Sr-89 4
1.0 (LLD
<LLU U
Sr-90 4
1.0 -
<LLO
<LLD 0
Cattlefeed & Grass Gross Beta 4
1.0 5.1 (3/3)
By-20, Seabold Farm 9.8 (1/1) 2.2 (1/1) 0 (pC1/g wet)
(1.7-9.8) 2.5 mi W 41*
Gama Spec.
4 Cs-134 0.1 (LLD
<LLu o
Cs-137 0.1
<LLD
<LLO 0
Other Gamas
'O. 2
<LLD
<LLO O
Sr-69 4
1.0
<LLD
<LLO 0
Sr-90 4
1.0
<LLD
<LLU 0
Table 5.0-5 (continued)
ENVIRosetENTAL RADIOLOGICAL MONITORING PROGRAM QUARTEHLY SUNr%HY Name of Facility Byron Nuclear Power Station Docket No.
50-454. 50-4$5 Location of Facility Ogle. Illinois Reporting Period 3ra Quarter 1985 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Number of Type '
Humber of Meana r9ean Meana hon-routine (Units)
Analyses LLD Range Location Range Range Nesults Aquatic Vegetation Gross Beta 2
1.0 4.9 (1/1)
Hy-13 Upstream of 8.3 (1/l' u.3 (1/1) 0 (pC1/g wet)
Intake 2.6 mi y 302*
Gamma Spec.
2 i
<LLu 0
l Cs-134 0.1 (LLD f
Cs-137 0.1
<LLU
<LLu O
Other Gammas 0.2
<LLD
<LLD-U Bottom Sediments Gross Beta 2
1.0 16.5 (1/1)
By-12, Downstream at 16.5 (1/1) 7.6 (1/1) 0 N
(pCi/g dry)
Oregon Dam W
4.5 mi e 213*
Gamma Spec.
2 Cs-134 0.1
<LLD
<LLU 0
Cs-137 0.1 0.14 (1/1)
By-12, Downstream at 0.14 (1/1)
(LLD 0
i Uregon Dam I
4.5 mi 9 213*
Other Gammas 0.2
<LLD
<LLD U
Vegetables Gross Beta
.8 1.0 3.2 (8/8)
By-19-1. Oregon Stand 4.2 (4/4)
None O
l (1.2-5.5) 966 E. Weld dart Rd.
(3.1-5.5)
Gamma Spec.
8 Cs-134 0.1;
<L LD reone U
l Cs-137 0.1
<LLD-None O
j Other Gamaas 0.2
<LLO None 0
Sr-89 8
1.0 (LLO hone u
Sr-90 8
1.0
' LLD None 0
I-131 3
0.03
<LLD none 0
- Nean and range based on detectable measurements only. Fractions indicated in parentheses.
D LLD value dependent on volume of sample available for analysis.
w2 u
--4..l
-. +.
A A..
4%%+-
A.
4m-.
14 E..
- + -.
4+-%J.
.-,E.--11.w A.
e 4-e w.
u 4
4 ENVIRONMENTAL RADIOLOGICAL MONITORING PR0bdAM QUARTERLY SUMMAxy Name of Facility Byron huclear Power Station Docket No.
50-454, 50 45S Location of Facility Ogle, Illinois Reporting Period 4th Quarter 19db (County, State)
Indicator Location witn Highest Control Sample Type and Locations Quarterly Mein Locations Numoer of Type Number of Mean8 l
Mean Meana Non-routine (Units)
Analyses LLD Range Location Range Mange Results Air Particulates Gross Beta 156 0.01 0.032 (117/117) dy-23, Unsite 3.6 (13/13) 0.031 (39/39) 0 (pci 'm3)
(0.009-0.085) 0.6 mi e 182*
(0.014-0.069)
(0.011-0.070)
Gama Spec.
12 0.01
<LLD
<LLu 0
Sr-89 12 0.01 (LLD
<t ' O O
l Sr-90 12 0.01
<tLD
<LLO O
Airborne lodine 1-131 156 0.07
<LLD
<LLD 0
(pct /m3) l Gamma Background Gamma Dose 3.0 19.9 (9/9)
By-22, Onsite 34.3 (1/1) 14.6 (3/3) 0 (TLDs) (mR/Qtr.)
(10.7-34.3) 0.3 ml 9 10l*
(10.8-16.7)
Milk
!-131 16 0.5
<LLD (LLD 0
(pCi/1)
Gamma Spec.
16 Cs-134 5.0 (LLO
<LLD ft Cs-137
- 5. 0
<LLO
<LLu o
Other Gammas 10.0
<LLO
<LLO O
Sr-89 16 10
<tLD
<LLO u
Sr-90 16 2
2.6 (12/12)
By-17, Bosecker/Lingel 3.3 (4/4) 3.3 (4/4) 0 (1.4-3.3)
Farm, 7.0 mi e 53' (3.03.6)
(3.0-3.6)
Precipitation Gross Beta 10 8.40
<LLD (LLu u
Gama Spec.
4 20
<tLD (LLD 0
Tritium 4
200 (LLD (LLU 0
5r-89 4
10
<LLU
<LLU 0
$r-90 4
2
<tLD
<LLU U
Table 5.0-0 (continued)
ENVIRUNMENTAL RADIOLOGICAL MONITORING PROGRAM QUARTERLY SUMMMY hame of Facility Byron Nuclear power Station Docket No.
50-454, 50-455 Location of Fac111 y Ogle. Illinois Reporting Period 4th Vuarter 1985 (County, State)
Indicator location with Highest Control Sample Type and Locations Quarterly Mean Locations number of Type Number of Meana Mean Meana Non-routine (Units)
Anslyses LLD Range Location Range Range Results Cooling Water Gross Beta 26 1.6 158.5 (13/13)
By-II, Discharge 158.5 (13/13) 3.3 (12/13) 2 (pCi/1)
(3.4-1043) 2.3 mi e 283 (3.4-1043)
(2.3-5.0)
Gama Spec.
6 Cs-134 10
<LLD
<LLD 0
Cs-137 10
<LLD
<L' u O
Co-SS 10 168 (2/3)
By-11, Discharge 168 (2/3)
<LLD 2
(147-190) 2.3 ml 9 283 (147-190)
Other Gammas 20
<LLD
<LLU 0
(7 Trit ium 6
200 4087 (3/3)
By-ll, Discharge 4087 (3/3)
(LLO 3
(299-7410) 2.3 mi W 283 (1860-7410)
Sr-89 6
10 43.3 (1/3)
By-11. U15 charge 43.3 (1/3)
<tLU 1
2.3 mi e 283 Sr-90 6
2
<LLD By-10, Intake Pipe 2.2 (1/3) 2.2 (1/3)
O at Station Surface Water Gross Beta 39 1.8 3.1 (25/26)
By-13 Upstream 3.5 (13/13) 3.3 (13/13) 0 (pC f /1)
(1.5-4.4) of Intake (1.7-10.7)
(1.7-10.7) 2.6 ml 9 302*
Gansna Spec.
9 Cs-134 10
<LLD
<LLU 0
Cs-137 10
<LLD
<LLO O
Other bamas 20
<LLD
<tLD 0
Tritium 3
200
<LLD (LLO O
Sr-89 3
10
<LLD
<LLO O
Sr-90 3
2 (LLD
<LLU 0
1
Table 5.0-0 (continued)
Ehv!RONMENTAL RADIOLOGICAL MONITORINd PROGRAM QUARTERLY SUMt4ARY P.ne cf F acility Byron Nuclear Pcwer Station Docket No.
50-454. 50-455 Location of Facility Dole. Illinois keporting Period 4th Quarter l'id5 (County, State]
Indicator Location with Highest Control Sample Type and Locations Guarterly Mean Locations Hum er of Type Number of Mean8 Mean Meand Non-routine (Units)
Analyses LLu Range location Range Range Hesults i
hell Water Gross Beta 2
2.8 6.1 (1/2)
By-18. McCoy Farmstead 6.1 (1/2) tvane 0
(pCi/I) 1.0 mi @ 2 h
- Gamma Spec.
2 None O
Cs-134 10
<LLO Cs-137 10
<LLD tione 0
hone 0
Other Gammas 20
<tLD Tritium 2
200 170 (1/2)
By-14. Off-site Well 170 (1/2) none U
0.3 mt M 101*
Nane U
Sr-89 2
10 (LLD M
Sr-90 2
2
<LLU f.one 0
Fish Gross deta 3
1.0 3.3 (1/1)
By-12. Gregon Pool 3.3 (1/1) 2.8 (2/2) 0 (pCi/g wet) 4.5 mi W 213*
(2.8-2.t0 Gama Spec.
3 Cs-134 0.1 (LLD
<LLO U
T Other Gammas 0.2 (LLO
<LLu o
Sr-89 3
1.0
<LLD
<LLD 0
i i
Sr-90 3
1.0
<tLD (LLD u
Cattlefeed & Grass Gross Beta 4
1.0 7.6 (3/3) 8y-20, Seabold Farm 4.3 (1/1) 4.5 (1/1) 0 (pCi/g wet)
(5.7-9.3) 2.5 mi e 41*
Gammi 5pec.
4 Cs-134 0.1 (LLD g
<LLu u
~
Cs-137 U.1
<tLD (LLO u
i Other Gammas 0.2 (LLD
<LLO u
I
<LLu O
l Sr-89 4
1.0 (LLD
<ttu u
Sr-90 4
1.0 (ILD
l l
ENVIRONMENTAL RADIOLOGICAL MONITORING PRUGRAM QUARTERLY SUPEARY Name of facility Byron Nuclear Power Station Docket No.
50-454, 50-455 Location of Facility Ogle. Illinois Reporting Period 4tn Quarter 1985 (County, State)
Indicator Location with Highest Control Sample Type and Locations Quarterly Hean Locations Number of Type Number of Meana Mean Meana Non-routine (Units)
Analyses LLD Range Location Range Range Results Aquatic Vegetation Gross Beta 2
1.0 3.9 (1/1)
By-12, Downstream at 3.9 (1/1) 1.6 (1/1) 0 (pCl/g wet)
Oregon Dam 4.5 mi 48 213*
Gama Spec.
2 Cs-134 0.1 (LLD
<LLD 0
<LLD 0
Other Gamas 0.2 (LLD
<LLD 0
l D
Bottom Sediments Gross Beta 2
1.0 8.5 (1/1)
By-13 Upstream of 12.8 (1/1) 12.8 (1/1) 0 (pCl/g dry)
Intake j
2.6 mi 9 302*
j Gama Spec.
2 Cs-134 0.1
<LLD
<tLD 0
Cs-137 0.1
<LLD
<LLD 0
Other Gamas 0.2 (LLD
<LLD 0
' Mean and range based on detectable measurements only. Fractions indicated in parentheses.
LLD value dependent on volume of sample available for analysis, i
t l
Table 5.1-1 GAMMA RADIATION, AS MEASUR20 BY THERM 0 LUMINESCENT 00SIMETERS (TLDs) i STANDARD RADIOLOGICAL MONITORING PROGRAM 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Date Placed:
12-31-84 04-01-85 07-01-85 09-30-85 Date Removed:
04-01-85 07-01-85 09-30-85 12-30-85 Days in the Field:
91 91 91 91 I
Location Average mR/Qtr.
i Offsite Indicator Locations i
BY Byron 12.3 0.7 12.212.6 11.410.3 14.6t1.5 BY rearsite East 12.910.6 13.7i0.2 14.211.0 15.6fl.1 4
BY Paynes Point 13.710.7 16.714.5 14.8il.0 14.511.8 BY Nearsite South 13.710.7 14.012.6 14.2il.9
- 15. lilt 5 BY Oregon 11.410.7 12.0il.1 12.0i0.6 10.712.0 l
Mean i s.d.
12.811.0 14.211.9 13.311.5 14.112.0 Onsite Indicator Locations BY Onsite North 11.810.4 10.510.2 12.211.2 20.012.5 BY Onsite ESE 14.710.7 12.510.6 16.112.2 34.311.9 i
BY Onsite South 13.310.4 11.010.7 14.910.3 30.713.9 BY Met. Tower 13.410.4 11.810.6 15.020.7 23.812.0 2nd Qtr mean i s.d.
13.3tl.2 11.410.9 14.Sil.6 27.216.5 Background Locations BY Stillman Valley 12.7 0.7 13.0t0.8 12.310.4 16.411.1 BY Mt. Morris 12.810.7 15.313.1 12.8 0.3 16.711.5 BY Leaf River 10.910.6 14.211.5 12.710.4 10.811.3 Mean i s.d.
12.111.1 14.211.2 12.6i0.3 14.6t3.3 l
l 78
Table 5.1-1 (continued)
I GAMMA RADIATION, AS MEASURED BY TLDs (continued)
SPECIAL PROGRAM-Inner Ring, Near Site Boundary, Indicator Locations 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Date Placed:
01-07-85 04-01-85 07-01-85 09-30-85 Date Removed:
04-01-85 07-01-85 09-30-85 12-30-85 Days in the Field:
84 91 91 91 Location Average mR/Qtr.
BY-101-1 14.810.6 26.911.0a 16.210.1 19.511.2 BY-101-2 14.910.4 15.010.9 17.110.7
'20.713.1 BY-102-1 14.010.5 13.910.6 17.3i0.5 28.Si2.8 BY-102-2 12.510.7 12.710.9 16.210.7 24.2i5.8 BY-103-1 15.010.9 13.610.6 15.910.5 18.111.1 BY-103-2 14.9*0.9 17.310.6 15.511.0 21.6tl.0 BY-104-1 14.210.2 11.810.8 20.710.6 20.414.1 BY-104-2 15.712.8 24.411.4a 16.211.2 18.8i7.0 BY-105-1 16.315.8 13.710.6 16.2i0.8 20.Sil.5 BY-105-2 13.3 0.8 15.lil.0 16.510.8 15.812.2 BY-106-1 23.4t2.6a 13.810.8 16.4i0.7 17.211.2 BY-106-2 13.312.0
- 25. 713. 3a 17.313.4 18.218.0 BY-107-1 21.3tl.2a 14.711.1 16.010.5 19.312.1 BY-107-2 14.410.6 16.110.6a 16.910.9 21.7i7.4 BY-108-1 16.3i0.8 13.110.2 16.1*0.7 22.812.0 BY-108-2 14.0t0.8 13.210.6 14.810.7 20.-315.4 BY-109-1 28.214.Sa 19.810.8 16.110.7 20.315.4' BY-109-2 13.li0.3
- 12. Si0. 2 15.0 0.8 17.811.5 BY-110-1 21.0il.la 28.116.9a 15.~ 910. 9 22.911.6 BY-110-2 13.0 1.6 12.410.7 15.210.5 23.316.8 BY-111-1 2t 8tl.5a 13.010.7 15.910.7 16.611.7 BY-111-2 12.110.4
- 14. 910. 3a 16.410.4 16.811.2 BY-112-1 20.0i5.3 13.010.6 15.910.7 17.311.4 BY-112-2 13.411.4 15.3t1.0 13.910.7 22.312.4 BY-113-1 19.0il.la 13.3 0.8 14.710.5 12.Sil.4 BY-113-2 12.711.2 20.211.3 14.210.3 16.912.0 BY-114-1 14.610.9 13.210.3 12.610.4 15.911.5 BY-114-2 13.210.6 13.810.9 14.512.0 17.634.7 BY-115-1 16.810.2 15.610.6 15.910.6 13.421.6 BY-115-2 12.510.8 15.111.1 14.410.8 15.811.6 BY-116-1 13.711.7 14.4i0.7 12.810.1 18.6t1.2 BY-116-2 12.110.7 11.810.3 14.2i0.1 15.4fl.5 Mean i s.d.
14.311.8 14.312.1 15.711.5 19.113.3 a Chips damaged (white color); excluded from the mean.
79
4
?
Table 5.1-1 (continued)
GAMMA RADI ATION, AS MEASURED BY TLDs (continued) 1 SPECIAL PROGRAM Outer Ring, Near 5 Mlle Radius, Indicator Locations _
lst Quarter 2nd Quarter 3rd Quarter 4th Quarter Date Placed:
12-31-84 04-01-85 07-01-85 09-30-85 Date Removed:
04-01-85 07-01-85 09-30-85 12-30-85 Days in the Field:
91 91 91 91 location Average mR/Qtr.
BY-201-1 18.910.9 13.510.8 15.510.9 15.411.1 BY-201-2 13.910.7 46.413.la 19.811.2 16.511.2 BY-202-1 15.111.6 11.710.6 14.110.9 15.611.0 BY-202-2 13.911.1 27.413.9 15.910.7 16.315.4 BY-203-1 13.613.7 12.511.2 11.810.4 17.911.6 BY-203-2 12.610.2 12.210.8 15.311.2 16.211.2 BY-204-1 14.010.9 25.510.6 27.114.1 16.012.9 BY-204-2 13.910.3 13.410.6 16.010.4 20.012.9 BY-205-1 12.810.4 20.511.4 15.5f0.8 22.712.9 BY-205-2 13.810.9 12.210.7
'16.010.6 21.211.0 BY-206-1 15.810.9 12.610.7 16.811.0 15.511.3 l
BY-206-2 15.210.9 21.411.6 17.910.5 20.0t1.1 BY-207-1 15.110.9 14.010.9 16.310.3 19.811.3 BY-207-2 14.010.6 15.610.6 16.010.3 20.611.9 BY-208-1 16.110.7 15.810.4 17.410.8 19.611.4 BY-208-2 13.910.5 13.410.8 18.010.8 19.311.7 BY-209-1 17.615.6 16.410.1 17.410.8 18.015.5 BY-209-2, 14.912.4 13.910.7 16.110.8 16.111.5 BY-210-1 13.310.2 19.810.5 15.210.5 17.811.5 BY-210-2 14.110.9 14.911.0 15.210.5 26.211.8 BY-211-1 13.913.4 14.110.7 15.711.0 18.110.9 BY-211-2 13.412.0 13.010.5 16.910.3 24.612.3 BY-212-1 13.010.8
- 14. 31 1. 0 NDb 25.010.9 BY-212-2 13.410.9 17.910.9 17.010.7 30.012.5 BY-213-1 15.310.9 18.811.4 17.110.3 15.311.2 BY-213-2 13.910.2 13.110.6 15.610.4
- 24. 714. 5 BY-214-1 14.510.8 11.710.5 15.010.6 19.817.0 BY-214-2 13.410.5 17.910.9 15.710.6 27.813.4 BY-215-1 16.811.8 15.511.1 17.511.2 17.211.4 BY-215-2 12.610.9 16.911.0 17.810.2 27.111.2 BY-216-1 15.210.7 33.111.68 16.610.4 22.411.7 BY-216-2 14.710.9 15.010.1 16.010.2 22.211.9 Mean i s.d.
14.511.4 15.413.3 16.612.4 20.li4.d d Chips damaged (white color); excluded from the mean.
b ND = No data.
TLD lost in field.
80
p i
)
APPENDIX II METEOROLOGICAL DATA i
i l
i i
J i
e N
J I
81
=
_____m2___
IJYRON NU'.'L LA9 POtJCR U f Al ION PERIOD - OF RECORD -~. JANUARY-MARCH
? TADIL _ TY 1905 CLACL EXTREMELY UNSTADLE (DIFF TEMP 250-30 FT)-
L4INDO MEASURED AT 250 FEET
.4TNO WIND SPEED (IN MPH)
DIRECi1CN
. &-0 4
7 O-12 13-18 1? 24 OT 24.
TOTAL N
O O
O O
O O
O NNE O
O O
O 0
0 0
NE O
O O
O O
O
'0-l 1
1
_. 'f E O
O O
O O
l'
- n..
~
'r O
O O
O O
C 0
7 :E O
C 0
0 0
C 0
~'r E O
O O
O CC f
'54 O
'O' i
0 3
0 0
0',
O O
I O
O C
0 0
0 0
r
- ' Yf h
C h
h
- 0 0
0 r
u) it
.\\
O U
C O
s.
C O
r f
e r
i A
f.
e
- k pp
'd (I
f<g b
(%
4
~*\\
(m Q,
f,;
(~r Y
y l
p\\
O l
Q O
Ci
().
.v ut 0
0 e
7c o
6 4
4:
t tt ie T n \\.V) ;s....'
g*)
Iy t'
o e
J' u
~
o 0..'
I.,}
I
'> p y.
I 1..
i. ;c.
a, r.
th:
t '. c. t i ! i t ',.; 1 2. ;' '
O f
/.'
a2 _
,i n a.. s. a ; air o;c. 0 r, t ;
- ta t.11 1 ; >,
h*ui.
1 s.
I Ei"ab,4 ica :
(:
tG3 l$I li. 2 4 : I ' '
.: 4
- r..
.C' 1 [.
si
/ I'
- 3 1.', L -
- S
- l' n.
- - r.
6 i
82 e..
1
BYRON NUCLEAR POWER STATION PERIOD OF' RECORD - JANUARY-MARCH 1985 STADILITY CLASS - MODERATELY UNSTABLE (DIFF TEMP 250-30 FT)
WINDS MEASURED AT 250 FEET WIND WIND SPEED (IN MPH)
DIRECTION
.8-3 4-7 8-12 13-18 19-24 GT 24 TOTAL N
O O
O 1
O O
1 NNE O
O O
O O
O O
NE O
O 1
O O
O 1
ENE O
O 1
O O'
O 1
E O
O O
O
.0-0 0
ESE O
O O
1 O
O 1
SE O
O O
1 O
O 1
SSE O
O O
O O
O' O
S O
O O
1 O
O g
1 SSW O
O O
O O
O O
SW O
O O
O O
O O
WSW O
O O
O O
O O'
W O
O O
O O
O O
WNW O
O O
1 O
O 1
NW O
O O
O O
O O
NNW O
O O
O O
O O
f-VARIABLE O
O O-0 0
0 0
TOTAL 0
0 2
5
.O O
7 Hours of calm in this stability class:
O tlours of missing wind mecsuremants in this stability class:
O Hours of ruissing'rtability moacurements in all stability classes:
'O 83 A
g m,
y j
s w
BYRON NUCLEAR POWFF STA'i(ON PERIOD OF RECORD - JANtJARY-h' ARCH 1985 STADILITY CLASS - SLIGHTLY UNSTADLE (DIFF TEMP 250 30.,FT) 7 WIND 9 MEASURED AT 250 EEET.
WIND WIND SPEED (IN MRII)
IJ I RECT ION O-3 4 -- 7 8-12 13-19 1 9.24 GT 24 TOTAL N
0 0
0 0
2 0
2 NNE O
O O
0 0
0 1.
'NE O
O 2
O O
O 2
~. 1.
ENE qO O
1 3
0 O
/t 1'
E O
O O
O O
O O
ESE O
O
'Q 2
0'-
O 2
SE O
O O
4 0
0
~
4 SSE O
O Oi 2
O O
2 5,
0 0
0 1
'i.
O 2
(,
o O
O c'
O O
~
s SW G
O O J, O
O O
O WSW O
O
~
O 1
O O
?,
W O
O O
O
'O O
a
!#M O
T O
O O
O 0
MW O
O 1
0 '
2
'O 4/
NNtl O
'O O-
.3 1
0 VARIABLE O
e O
O O
O
'o J
4 s
TOTAL O^
O 4.
14 O
29 r
e 1
ilouc s v:
_cim ir thir g.;abit ty h.
Y p.
a33 l'ourr of rr. i s s i ri g u.ri r d / nie aI' u r e m a n & '
e 1 r>
t r. 4 F.
_c t a b i l i t y c-l a s s :
0
'iGut ; Uf rh i t. 517. (1 Stab 1}i (r n,ea5drCmentO ID all stability ClaS5es:
O k
" }
n 4
'k.
84
+
,,e g
,x
,O y,.
BYRON NUCLEAR POWER STATION PERIOD OF RECORD - JANUARY-MARCH 1985 STABILITY CLASS - NELITPAL (DIFF TEMP 250--30 FT)
WINDS MEASURED AT 250 FEET WIND WIND SPEED (IN MPH)
DIRECTION
.0-3 4-7 8--12 13-18 19-24 GT 24 TOTAL N
1 0
11 17 12 8-49 NME O
1 5
18 4
3 01 NE 1
1 11 9
9 4
35 ENE O
6' 18 18 25 7
74 E
2 1
13 18 7
10 51 ESE 1
1 6
9 1
5 23 SE O
1 11 7
23 4
46 SSE O
4 5
21 9
3 42 S
1 c'
O 10 17 7-54 i
SSW O
1 12 35 17 1
66 SW O
1 20 22 21' 16 SO WSU 1
4 12 21 22 17 07 U
1 6
13 23 28 21 92 WNU O
O 18 22 77 10 140.
-NW O
10 21 34 50 20 145 NNW 1
0 6
15 18 21.
64 VARIADLE O
O O
O O
O
-O TOTAL 9
45 191 327 340 175 1007 Hours of c a i r;. In this stability class:
O s
Houss o f it it a ing wind measur'ements in this stability class:
23 H6urs cf missino ntability measurements in all stability classes:
0 85
Di'RON '!UCLEAR POWER '1 T ATION PERIOD OF RECORD -- JANUARY-MARCH 1985
'.Tr.D2LITY CLAOG - SL!GHTLY GTABL.E (DIFF TEMP
50 -- 30 F T
L'INDE MEA *2URED AT 250 FEET WIND 5~iED (IN MPH) i l-
., e t-r..
1: t 4-
'.7 8-12 1 0--l e 19--24 GT 24 T C17.L l
n.
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-. -... - - -. -. -. - - --, --,.---- ~~- l
i.
BYRON NUCLEAR POWER GTATION PERIOD.OF RECORD - JANUARY-MARCH 198S i
GTABILITY CLASS - MODERATELY STABLE
-(DIFF TEMP 250-30 FT)
WINDS MEASURED AT 250 FEET WIND WIND SPEED l(IN MPH)
DIRECTION
-,8-3 4 - 17 G-12 13 19-24 GT 24 TOTAL N
O 5
4 1
O O
10 NME O
2 0
1-0 0
3 i
NE O
2 3
2 O
O 7
ENE
~1 1
1 4
0 0'
7 E
O O
2 2
?
O 13 ESE O
O O
2 1
O O
4 SE O
O O
~4 3
0
-7 SSE O
O O
O 1
1 2
S O
O 1
4 0
0-5 1
SSW O
O 1
10 6
0-17 SW O
1 3
3 6
0 13 WSW O
O 4
4 0
0 3
]
W 1
1 5
6 1
0 14-WNW O
1 7
11 1
0 20 NW O
O 4
17 1
'O 22 NtlW O
O 1
S 1
0 10 VARIABLE O
O O
O O
O O
i TOTAL 2
13 36 79 30 1--
'161 i
. lour s vf c a l tn ui this t.tabi;ity class:
C
' Iv ut : c f rai s s i ri g w i n d t s e a.t. o r-+.:rrie n t s in this.itability class:
0 t
four - of n,i r s i n g s tut.i i i t y n.eas ureme n t s in all stability classes:
O 5
l 87-t
.J.
i.
i
BYRCN SUCL. EAR PO14ER GTATION
'ERIOD GP RECORD ~ JAt4UARY-MARCH 1985
- a. 3.,. T....m.,
.,e.
.y. r.g e r.. o:.u 9 o^ E>.l C;
(.r.,I,'T TE.*..^
.?9. 0 3.L~i,cT )
i L ITOS MEASURED AT-250 FEET
.J. 7 g -
.-....,.'4
- A.T
- 1 T'*g, e".f iL* C, h.
, T N ao1r up e g im m
- A
.r..
va L6I T q,.. _
o-1..
,9"...,
.,J,s 4 't
, I.,s c yt u._
.u m%i5
=
r
/
O~A a-v A;
1 O
C 7
2 O
O O
4 i< ~
1 p.
a a
+
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1 1
r
+
a s
s c
,T r)
.i o.s o-4 s,
s-e o
c.
c s
CC'.
C 3
o n
u a
C 0
0 0
2 i
O O
. ; - r.-
a n.
o o
o 0
0 0
0 0
0 0
e.%f O
O O
5 1
0 1
_v 0
0 5
1 0
0 o
u 3
1 0
0 4
O O
O O
0 0
0 oa o
o o,
c,,
..,s 1
z
- n..
. m u
O, b li L_
O O-0 0
O O
w*
., =
v e.
4
.4
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I Il i
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! c19 2 O
.+!
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i.
5 c
c..,
3 a.:.
i
'J a a c y T s fl.: r. t.U J' l'
. t ri b 1. i t, c '.1 ~ 0 a f.
in
-li.
s 88
DYRON NUCLEAR POWER STATION
. PERIOD OF RECORD - APRIL-JUNE 190'5 ZTADILITY CLASS - EXTREMELY UNSTABLE (DIFF TEMP 250 -3C FT)
UINDO !1EASURED AT 250 FEET WIND WIND' SPEED (IN Mr'H)
DIFECTION
.OO 4-7 O 12 10-10 19-24 GT 24 TOTAL O
O O
O O
O G
tlnC D
0 1
1 O
O 2
N O
O O
1 2
-O 3
ENE O
O O
O O
O O
l E
O O
O O
O O
O i
ESE O
O O
O O
O O
dC 0
0 0
0 0
0 0
- .C 0
0 0
0 1
0 1
O O
O O
O O
O
. ~_. U O
O O
O O
1 1
- W O
O O
O 0
1 s
t,. ;)
O O
O O
C O
u L;
O O
O O
o O
C v't !
O O
O O
O-1 NW O
O O
O 1
0 1
m;u 0
0 0
0 u
O O
'/ARI AP' t O
O O
O O
o O
r JA O
1 L
1 10
- a !.
- :, '. h :. _. t: 6.. ; 1 1 *. y. l.1 s :
i,
..a_
. ; ?..
L' i I. *.}
i h e.:< _ U i e b e ti !.'
ila
'l I, I etGbil1ty : I.L G 2 :
O vi
! l
.t.e i. t l. 2. i
- m e 3 E U r 9 7i c i s t,_. i r, 0.1 l
- 5. t ;s b i l i t;/ c !.a ;. 0 0 0 '
O o l'
_. 5 1 :6 1
1 i
89
BYRON NUCLEAR POWER STATION PERIOD OF RECORD - APRIL-JUNE 1995 GTABILITY CLASS - MODERATELY UNSTABLE (DIFF TEMP 250-30 FT)
WINDS MEASURED AT 250 FEET WIND WIND SPEED (IN MPH)
DIRECTION
.8-3 4-7 8-12 13-18 24 GT 24 TOTAL N
O O
1 1
O O
2 NNE O
O 5
1 1
0 7
{
NE O.
O 6
4 O'
O 10 ENE O
O 5
1 O
O 6
i E
O O
.O O
O O.
O r
ESE O
C 0
4 0
0 4
f SE O
O O
O O
O O
%E O
O O
O O
O O
h l
S O
O O
O 1
2 O
l SE:W O
O O
O 4
6 10 SW O
O O
3 5
1 9
i WSW O
O O
1 4
1 5
I il O
O O
O O
O O
WNW O
O O
O O
O O
l i
NW O
O O
1 O
O 1
NNW O
O O
O O
O O
UARIABLE O
O O
O O
O O
1
\\
l TOTAL 0
0 17 16 15 10 58 i
llours of calm in this stabi1ity class:
O H o u r :.. o f in i s t A n.; wind measurements in this s tabil i ty c l as: s:
O HourL of missing stabi'ity measurements in all stability classes:
0 1
i 90 2
)
5 2
w
i t
I t
BYRON NUCLEAR POWER STATION PERIOD OF RECORD -- APRIL-JUNE 1985 STABILIT CLASS - SLIGHTLY UNSTABLE (DIFF TEMP 250-30 FT)
WINDS MEASURED AT 250 FEET WIND WIND SPEED (IN MPH)
DIRECTION
.8-3 4-7 8-12 13--10 19 -24 GT 24 TOTAL N
O O
5 2
3 0
10 NNE O
3 4
3 0
0 10 NE O
O 7.
4
~1 0
12 ENE O
1 5
3 0
0 9
E O
2 3
5 0
0 10 ESE O
O 3
2 O
O 5
SE O
O O
3 0
0 3
j S5E O
O 4
4 2
1 11 S
O O
O 1
4 1
6 S'5 W O
O 1
9 5
17 SW O
O 3
8 5
3 19 WSW O
2 3
1 2
4 12 z
W G
O 1
3 0
4 0
WNW O
O O
O 2
0 2
NW O
1 0
5 3
0 9
NNW O
1 1
1 2
0 5
i VARIADLE O
O O
O O-0 0
1OTAL 0
10 40 47 33 13 148 Ilvur
- f caln. In this ctability class:
O H v.a r s of.ru t> s i o y wind measurcments in this stability class:
O liour :
'f missinq stability measurements in al1 stability classes:
O 4
91
BYRON NUCLEAR POWER STATION PERIOD OF RECORD - APRIL--JUNE 1983 STABILITY CLASS - NEUTRAL (DIFF TEMP 250-30 FT)
WINDS MEASURED AT 250 FEET
'A I ND WIND SPEED (IN MPH) j LIIPECTUN
.8-3 4~
7 8-12 13-18 19--24 GT 24 FOTAL l
N O
5 14 18 17 O
07 N';E O
6 27 13 0
0
'55 Ne o
o
>7 s-m.
- .,n m
k EN O
5 6
1G 12
/1 13 E
O 1
5 10 4
O LO 4
E'2 E O
')
6 0
0 1.3 TE O
2 5
4 3
0 1,;
1 1
'E W
/:
18 5
S
_c 0
2 14 16 12 l 'J-O SSW O
10 l e,
^a
_m 4 m.
s 8
i I e.t th.
A6, "s na
- 'a *e 9
,a#
- ~
se u
I
}.$,,
' s,1"s
')6
- A f\\
s 4~
v
.s A 1.
1 l) j f[
/0 t-1
< t se m ~,
e, A.
4 i a
4,
n, t4 1
.i i'.M,
a 19 a
o c, 5 a
V "Ji! AI.:LL 0
0 0
G n
o o
y,, i [s L e
L.S
. c., 4
....s.7. s e,, e_.
.. v -
i.4
. r, e
.,4
, ~..,.,
1 i-
.c
_ I.i l' #
'b
![4 U..
e2L
.3 ' (1 1i yg dL',
()
^
J
..:i ~ Of 11 L f.
is J '
d.fac 6 a f c.0 ; r, t :
1,,
(hi3.,. '. a L i } i t j,
- 193*
1
s:
'eu
- +~ u b. l 1 t, ii. 71 a ; i ;' s ta c n ( 2 i c,
., l 1 y t, a._ { i } _ ' y.; } ;. 5 5 t' i-7 O
~
I J
d 92 1
BYRON NUCLEAR POWER STATION PERIOD OF RECORD - APRIL-JUNE 1985 G T AD I L I TY CL AO _'. - SLIGHTLY STAELE (DIFF TEMP 250-30 FT)
WINDS MEASURED AT.250 FEET WIND WIND SPEED '(IN MPIl}
DIRECTION
.8-3 4-7 O-12 13-18 19--24 GT 24 TOTAL
~....
N O
1 11 0
1 0
16 NNE O
O 9
17 3
0 32 NC O
1 5
20 10 0
44 ENE O
1 6
14 7
0 20 E
O 2
4 31 11
-1 49 ESE 1
0 3
9 5
2 20 SE O
1 3
7 1
0 12 SSc 0
0 1
0 16 8
30 5
0 2
2 18 54 21 97 iSW 0
3 0
17-SS 21 9's SW 1
4 12 21 24 12 74 WCW O
5 18 13 6
1 40 W
1 1
13 22 9
0
~46-WNW 1
9 19 21.
15 0
64 NW O
2 16 24
^
O 52 NNW 2
17 10 0
0 3.3 VARIABLE O
C 0
0 0
0 0
TOTAL 6
29 142 255 204 66 742
!! oui
.f calm in this s t a b :. ! : t y c l a:.; -
O a
l l :. u r sc. i r i rig wind meas ur 2nien ts in this stability cis.es:
O mi.rsinc stability measurements i r, al! stability classes:
O Heurr or 93
i l
l f
t r
t i
i SYRON N'rLEAR POWER *0TATION PERIOD OF RECORD - APRIL JUNE i v'S5 l
'3 Tn0 ! L I TY CLASS -- MODERI;TELY STABLE (DIFF TEt1P 250-30 FT)
WINDS MEASURED AT 250 FEET l
WIrID WINLt 'PliED (IN MPH)
O I T:EC T 10N 5-3 4-7 3-12 13-18 19-2ii GT 24 TOTAL
_ = - - _.
m t
O 6
4 1
0 12 iM.1 0
1 10 9
0 0
20 NE O
O 5
2 1
0 C
ENE O
1 4
1 C
0 6
l o.
4 1
1 _.
i o
^o 1
~
~
4 4 @
)f 4.
"h I". "w y
_ _0 L-'
gg 6
w.*
9.~
0 0
0 2
/._
O 11
__c c,
s-C 1
' 's
~'
a
_ u
'A 1-A
~ :.v i
2 O
o o
7 3
k3 m
T
.m
/he V
I e
4
-7 4
5 s
.V 4
A A
A A
e
)
w
} *o?
(*-
4) 49 l
F"?
p - 6.
y a
o 4
- 7 4.
s M
s I
0 0
O 1.
YiRIADLE o
l l
- s'v
- a. ts
..'4
= --
. r
..,r.s-v. r il.
w,-
a 5 44
.I I*
e s'$
'I
=5 h
J
[
4.' 2 B
! *', > J
> f-
- n 1 ? ? 11, i a 1 h J.
ID 4 2%
. r -.; h l' S i ft 1h: E-
.:i. l b. l. t y.
- 7. L !. =
')
i '. I h t_
._ t E. I i ( N
% 4 S u r W,e T,i r ID ll Etabi!ilw ; ? G L.6 d a !
r S t. : -
e c
94
'i
e BYRON NUCLEAR POWER STATION PERIOD OF RECORD -- APRIL-JUNE.
1905
- TABILITY CL AOO - EXTREMELY STABLE-(DIFF TEMP 250-30 FT)
WINDS MEASURED AT 250 FEET WINil WIND '? PEED (IN MPil) 8--12 10-10 19-24 GT 24 TOTAL D I;tEC T I ON
.1-3 4-N O
1 2
2 O
O 5
NNE 1
0 1
1 O
O O
NE 1
0 1
O O
O 2
ENE O
2 O
O O
O 2
E O
5 2
1 1
0 9
ECE o
^
1 1
2 0
6 4
)
SE O
O 1
1 3
O.
5 GSE O
T..
O 2
O O'
5 S
O O
1 1
2 0
'4 i
COW 1
0 1
O O
O 2
SW O
1 1
2 1
0 5
W5W 4
1 2
O O
O 10 W
1 0
1 2
O O
4 WNW O
1 0
1 O
O 2
l NW O'
1 O
O O
O 1
i
~
NNU 1
S O
1 O
O T
VARIADLE O
O O
O O
O O
't OTAL.
9 22 14 1?
t
-O 72 flours o f ' c a i rr. In this stIbi!ity cl.as4:
O livurs of mi:. sir.g vind m e a s u r e rrie n t s in this stability clu.;:
9 4
Hears > F mi s s i rig r t ab i l i t y :rieas ur ciae n t s in al.1 stability classer l.
O 95 p
l l
l 1
i BVRON NUCLEAR POWER STATION PERIOD OF RECORD JULY -SEPTEMBER 1905
- ' ~i:; I t ! T '/ Q.!:i.~.S
- EX TF.EMEL'.' UNCTABLE (DIFF I tiMP 250-30 FT)
W1NDE MEASURED AT 250 FEET W!MU WIND GPL.ED ( IN MP:-l)
D :;tEC1 IGN
. u -O 4-7 G-12 13--10 19-24 GT 24 Tol 'iL N
O O
O O
O NNE O
1 3
0 0
0 4
NE O
O 1
O O
O 1
ENE O
2 3
O O
O U
r O
O O
6 0
0 6
I f_'.~ E O
O 1
3 O
O 4
E O
O 5
0 0
C 5
5:E O
O 1
0 O
i O
O O
2 2
0 4
1
_W O
O O
4 1
0 5
f o!
O O
1 o
o e
zu O
e O
O 2
LJ 0
O O
1 0
1
.tv.
O O
9 O
O O
l'u o
o 0
1 0
'O 1
N '.* k.'
O C
O 2
O
.-(.:iI ADLE C
O O
O O
O O
7,, e,.,.
n
}
,,3 y
J s
l. 'y'
- l ) *s 5.* I O
} 4:e 1.
IIii O 3 ( O b' 1 ~
i
.,t
'm 1. i d fli & a.' Q : 4.7s t. re t $ l i, thi; S tGl. i ! l ty._ l d i S :
O f....">
t:.
.a.
i
.e.. _ _ ~ i i 'l
.- L e ) i l / i< ii. ; d d r G r.ed+ f i t 3 1 's a 5 t ilb i ) 1 'C ' !IC.5LQS 6 f 96
I l l-1 BYRON NUCLEAR POWER STATION PERIOD OF RECORD - JULY-SEPTEMDER 1985 ifADILITY CLASS - t10DERATELY UNSTADLE (DIFF TEMP 250-30 FT) WINDC.f4EASURED AT 250 FEET gjrr'D WINCi GPEED (IN MF'H) DIREC1 ION . 0 --3 4 7 G-12 13-10 19-24 GT 24 TOTAL N O O 5 1 O O 6 NNE O O 2 O O O 2 NE O 1 2 O O O O ENE O O 2 3 0 0 5 E. O O 1 1 1 O O E~CE O 1 0 1 O O 2 SE O O 4 0 0 0 4 SSE O O 5 0 0 0 5 S o 0 1 0 1 O 2 2.SW O O 2 4 0 1 7 SW G O 4 2 1 0 7 M'::W O O 1 O O 1 2 W O O 1 1 O O WNW O O O O O O O NW O O 1 O O O 1 riNW O 2 3 ? n O 7 VARIAOLE O O O O O O O TOTAL 0 4 04 15 4 2 59' Hcore of. 41 n :. n thic stability cia.s:: O livus u
- f nu s :.i r. v w t a d.1.e a s u r u ne n t s in this sta' ility ciasc:
O s ( lina. ai' ai l s o i,2 9 s tab il i ty raeas ur eraen t s in all stability classes: 5 r l-97
l 5 i I DYRON NUCLEAR F'OWER OTATION t ~ PERIOD OF RECORD - JULY-SEPTEMBER 1985 O T A I; T L I T't C ' APG - StIGitTLY UNSTABLE (DIFF TEMP 250-00 FT) WINDC MEASfJRED AT 250 FEET i WIND SPEED (IN MPH) i j DI G TION ,S-3 4-7 C-12 10 -18 19-24 GT 24 TOTAL I f
- 4!ND l
N O 1 3 2 O C c. i Nic o 7; 2 0 0 0 5 i N; O ? O 1 O O v 1 i EN; O 2 1 1 0 0 4 E O O O 1 r, d ESC O 2 2 1 0 0 C CE O 1 O O r. 0 4 I K c_ o 0 5 5 1 O i t i n, 1 n. r p ,J ~ ( O O O O 2 1 3 [ l O 1 t L 0 0 1 0 ~-' i .v! 2 0 0 6 c
- o c
s b*A a l 4 O 7 r-u f .I Ih g Q v o o wV,; 1 a. .T C ( 1, St 0 10 '.7 30 2 a'. 11 r
- 1 - a en this S t (b i t '. y c i a.L s :
? ., u ' . i i.<J us t d cit e.: c i 2.;i.t r. t e I r, ' t. t._ _ tai.i'itv _is:1: ji .ii 7.' A h e) il',d'!Iif.,y nn_ d 5 t J r-c Ta i t:1. T 1 r. ulI $(dbi!;ij C I u r,, ;> e r
- 6 98
( ..,-e_,~.. _,y--,e, ,w-, w y-w tw.
l l BYRON NUCLEAR POWER STATION PERIOD OF RECORD - JULY-SEPTEMBER 1985 ~. l A E' I '_ I T Y CLAOS - NEUTRAL (DIFF TEMP 250- 30 FT) WINDS MEASURED AT 250 TEET WIND WIND SPEED (IN MPif) DIRECTION . 0 -3 4-7 G-12 10-10 19 -24 OT 24 TO TAL f. O 20 10 5 0 0 35 klNE 1 15 13 11 3 0 43 MC 0 0 7 11 ~7 0 05 Et:E 2 O O 11 0 0 24 E O O 1 13 0 0 17 EGE O 9 14 0 0 0 26 CE 1 7 12 9 1 0 30 OSE O 7 00 12 9 1 59 1 0 15 17 16 2 54 SSW O C 21 45 26 1 115 2 12 07 25 6 3 95 WIW 3 10 14 10 ? 2 42 U 1-1,_ 10 16 10 6
- c. b W:U U
10 10 31 3 0 09 MW O 12 21 11 0 0 47
- ; T.~;
2 o 1.? 7 0 0 $/ '. N I A.t.E O O O e.- 0 0 0 EU1..:. 21 153 .37 217 G7 10 7% I
- 41. m c ; l er in *hac s t a t. i l i t y clar :
O i k. i, .n i t : 'r1 wind mea s '. r e cue r. t s .t n this stability clai.s.sr C I I.,,a . :' I m t '. ; 1. i 4.tabi1ity mea urements in alI stabi1ity c l a t s e: c : 6 l 99
BY9OM flOCLEAR POWER STATION PERIOD OF RECORD -~ JULY-SEPTEMBER 1905 0 TnOILI.T / CLASS -- SLIGHTLY STABLE (DIFF TEMP 250-00 FT) WINDS MEASURED AT 250 FEET ? I. JINO WIND SPEED ( IN MPii) l IJIEEC1 ION . 0- 3 4-7 G-12 13-18 19-24 GT 24 TOTAL N O C 7 16 3 0 34 tiNC 1 4 11 29 1 0 16 f i:E 1 3 5 12 O O 21 l l ENE O 3 4 17 o O 24 t n t n . n y
- e. c.,
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BYRON NUCLEAR POWER STATION PERIOD OF RECORD - JULY-SEPTEMBER 1985 STADILITY CLASS - MODERATELY STABLE (DIFF TEMP 250-30.FT) WINDO MEAGURED AT 250 FEET ' WIND WIND SPEED (IN MPli) DIRECTION .O-3 4-7 8-12 13-18 19-24 GT 24 TOTAL _.. _ _ _. _ _ ~.... _. N O 1 6 3 0 0 10. NNE 2 2 13-4 0 0 21 NE 1 4 11 2 O O .12 ENE O 6 4 9 0 0 19 E O 1 3 14 5 0 23 ESE O 3 2 3 17 0 23 SE O 1 3 11 13 0 20 'a'3 E 2 0 5 4 4 0 15 ? O 2 10 11 14 0 97 SSW 1 1 2 33 10 0 "J O 3u O 1 7 10 0 0 1U NU 2 0 11 4 9 0 17 L: 0 1 0 1 0 -O 5
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~. 4 I I 3 I i BYRON t!UCLEAR POWER' STAT 10N PERIOD OF. RECORD - OCTOBER -DECEMDER 1983 ( ~:1 AD I' ' TY ' CLIES - NEUTRAL (DIFF TEMP 2'30 30 FT) WINDC MEACUPED AT 050 FECT i j 6i1NU WIND '3 PEED (IN MMI) DIRECTIUN .J-0 4-7 n-12 13-le 22-24 oT 24 TcTnL 4 1 4 .e... c. u. c o.3., c. l N'iE 3 11 34 33 11 4 96
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BYRON NUCLEAR POWER GTATION PERIOD OF RECORD - OCTODER-DECEMDER 1905 '7TADILITY CLA2~ - CLIGHILY CTADLE (DIFF TEMP 250-30 FT) WINDS MEASURED AT 250 FEET WIND WIND GPEED (IN MPit) DIRECTION .O-3 4-7 0-12 13-18 19-24 GT 24 TOTAL N O 2 6 10 0 0 24 NNE O S 7 4 1 0 17 NE 1 3 6 0 0 0 lb ENE O 7 6 15 0 0 Oe E O 6 0 16 5 1 u i ESE O 2 5 2 O 11 SF 0 3 3 4 11 0 21 ' ':E O 1 2 4 11 9 ./ 0 1 2 10 21 12 47 s_W 0 v 9 17 10 0 4.! SW C 2 '/ C 7 _o 2.; W3W D 0 11 16 0 0 2 ", 'I O 2 10 15 '? O ad ' ttW O 10 12 4 4 '1W G O 9 1 1 0 }i i ';U 0 2 9 1.2 i o '.' Ali i. ',DL E O O O O O O <? IU I,M 1 09 110 1% 15.6 27 427 !m n -f c o l e.i . r. thxt. i A t.. l i t, 1 u r: O
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, m 4 9 4 I s APPENDIX III ANALYTICAL PROCEDURES t f -e f s 9' ,s 110
4 i ANALYTICAL PROCEDURES MANUAL 1 TELEDYNE ISOTOPES MIDWEST LABORATORY PREPARED FOR COMMONWEALTH EDIS0N COMPANY i Note: These procedures are taken from the complete. Procedures Manual. Only procedures applicable to the CECO Radiological Environmental Monitoring I 1 Programs are included in this manual. t [ l Compiled by: . (M fB.brob i Lab Supervisor l W Approved by: i /L.h.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 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). 111 _____----__j
=u n ,3 1 1 ^ v e TABLt 0F CONTENTS SECTION I SAMPLE PREPARATION 2 1.1 Fish 1.2 Bottom Sediments and Soil 3 1.3 Drinking,(clear) Wate- (EPA Method 900.0) 4 SECTIONS II, III, VIII ANALYSES s 'l 2.1 Airborne Particulates (Gross. alpha and/cr. Beta) 5 2.2.2 Gross Alpha and/or Gross Beta Activity in Dissolved Solids 6 3.1 Airborne Particulates - Ga rl Spectroscopic Analysis by Germanium Detector 8 ~ 3.2 Airborne Iodine - Gamma Spectroscopic Analysis by Germanium Dectector ~ g 3.3 Water - Gamma Spectrosccpic / Analysis byiGermanium Detector 10 3.4 Soil and Bottom Sediments.- Gamma Spectroscopic Analysis by Germanium Detector 11 3.5 Fish and Wilflife, Gamma. Spectroscopic. Analysis by c Germanium Detector ~ ~- 12. 3.6 Ambient Radiation'(.TLD), Efficiency Calitiration - 13' 3.7 Procedure for Preparation and Readoutof TLD chips - 15 3.8 Tritium in Water 17 .x 3.9 Iodine-131 in Milk by Ion Exchange 'on Anio~n Exchange Column 19 8.1 Strontium-89 and Strontium-90 in Milk by Ion Exchange-23 8.4 Strontium.-89 and Strontium-90 in Water Sdmples 32 8.6 Strontium-89 and Strontium-9?in Milk (Ash), Vegetation,. Fish, Wildlife, Soil, and Bottom Sediment Samples - Sodium Carbonate Fusion -37 % ~ l ss 4 s 9 f* ' ' 112F s' 'l
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. I 1 113 1 l
Rev. 4, 6-01-84 fo/ / / Approved by: f / E /// / $ a C L.Gi 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 I hour. Clean the bones. Air dry,' weigh 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. i 3. Gamma scan fillet without delay or store in a freezer. s 4 After gamma spectroscopic analysis is completed transfer the sample to a drying pan and dry at 125* C. l 5. Cool, weigh, and record dry weight. l 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 be completed. 114 1
Approved by: d'/"/-/////}p/( t.7. Huebner 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 gamma-spectroscopic analysis, -seal 500 cc.of the ground sample in a Marinelli beaker. Record dry weight. 3. Seal the remaining sample (up to 1 kg) in a plastic container and save for other analyses or for possible future rechecking. e i t 115
Rev. % 6-01-86 /,, // ~ d Approved by: ( NNuIts L.F. Huebner i 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 tSe sample to bring it.to pH 2 (15 ml 1N,HNO3 Per liter of sample is usually sufficient) If samples are to be collected withcJt preservation, they should be brought to the laboratory within 5 days, then preserved and held in the ori.ginal 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. l 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 required 200 ml 203 ml 400 ml 406 ml 600 ml 609 ml 800Ini 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. 116
1 Rev. 4, 6-01-64 i,, i !. /A -l / e. ///// Approved by: r ~L.Qt Huebner 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 f ar - 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: +2hEsb + E' A b 3 (pCi/m ) = B x C x 2.22 8 x C x 2.22 Where: A = net alpha (beta) count rate (cpm) B = efficiency for counting alpha (beta) l activity (cpm /dpm) C = volume of sample (m3) Esb = counting error of sample plus background Eb = counting error of background 117
Rev. 4, 6-01-84 (( ' / Approved by: n, a,- [iM/z/,( t.G' Huebner ~ 2.2.2 Gross Aloha 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. } l Note: For gross alpha and gross beta assay in the same sample. I 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. Evapo. rate 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. e 118- ~
Rev. 4, 6-01-84~ Section 2.2.2.(continued) 4. With distilled water and a few drops of 3N HNO.. transfer 3 the residue to a 50 ml beaker. Evaporate 70 NEAR - dryness. 5. Transfer quantitatively the residue to a TARED PLANCHET, using an eye dropper. l 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 0WATAB. Calculations: Gross alpha (beta) concentration: ~2 sb + b A (pCi/ liter) = t B x C x D x 2.22 B 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) -0 = correction factor for self-absorption in the sample Esb = counting error of sample plus background Eb = counting error of background
Reference:
-Radioassay Procedures for Environmental. Samples, U.S. Department of Health, Education and Welf are.
Environmental Health Series, January 1967. 119
Rev. 4, 6-01-84 / z. / / Approved by: .f 7, /l////N// L.((. H0 ebner 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 LLD 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. 1 I 120
Rev. 4 6-01-84 / 2 0 Approved by: A.,, f[2 L.@' Huebner 3.2 Airborne Iodine Gamma Spectroscopic Analysis by Germanium Detector NOTE: Because of the short half-life of I-131, count the sainples as soon as possible after receipt and no later than 48 hours. 1. Load the charcoal cartridges in a specially designed holder or transfer charcoal from each cartridge to individual plastic bags. Seal the bags. 2. Label each bag with corresponding project ID, locations ID, and date of collection. 3. Place the bags in a standard g.eometry container, cap the container and secure the cap with a tape. 4. Place the holder or container on the detector and count for a period of time that will meet the required Lower Limit of Detection (LLD). Calculation: A A1 = I-131 activity (pCi/ sample)= (at counting time) (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 l_ sampling period) and Decay: I (2) C = F (1-e-At ) 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 121
Rev. 4, 6-01-84 d Approved-by: [I/. [ tid //h L.M 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. 3. Count long enough to meet LLD requirements. 4. Store the spectrum ori a disc, 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. 122
Rev. 4, 6-01-84 'S / / f:1 // /]fE//bl_. / Approved by: li.G/ 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. l l 4. Count the gamma activity 'long enough to meet the LLD requirements. 5. Store the spectrum on a disc. 6. After storing, calculate gamma activities using computer and corres-- ponding calibrated geometry. 7. Transfer'the sample back to the original container for further analyses. 123
Rev.-4, 6-01-84 /? - /) Approved by: ///////// ~ s_
- L.G/ Huebner
~ 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. l 3. Add a few cc of formaldehyde and seal the container. l l 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. 124
Rev. 4, 6-01-64
- 4. f/
o Approved by:
- 2 // / 6f L///// L L.G/ Huebner 3.6 Ambient Gamma Radiation A.
Thermoluminescent Losimeters (TLD) - Licht Response (Efficiency) Harshaw Lithium Fluoride TLD-100 chips,1/8" x 1/8" x 0.035". Procedure 1. Rinse the chips with warm trichloroethylene followed by the methanol rinse. Dry. 2. Place the chips in a platinum crucible. 3. Anneal for 1 hour at 400*C. 4. Cool quickly by placing the crucible on 1 metal plate. 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"). I 14. Calculate mean + one sioma deviation of five chips. 15. Calculate light response of TLD's (correction factor) by the followina equation: 125
Rev. 4,~-6-01-84 L Section 3.6 (continued) l Calculations A C.F. (nanocoulombs/mR) = Where:C.F = correction factor (efficiency) to be applied in calculating. . exposure of field TLDs A = Net reading in nanocoulombs B = known exposure to TLDs The exposure to the TLDs -(B) is calculated as follows: nR/hr = 8400 x mg Ra-226 r2 For our setup' use the following parameters: ) Ra-226 = 0.0933 + 1.5% r = 19.6 cm I 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.'
- 126
Rev. 4, 6-01-84 / // / / ~ Approved by: <T/ f///id/u/_ it.E. Huebner 3.7 Procedure for Preparation and Readout of TLD Chios Materials Harshaw Lithium Fluoride TLD-100 chips,1/8" x 1/8" x 0.035". Black plastic bags or boxes Plastic sealer Vacuum needle (for handling the chips) TLD reader Note: Never handle the chips with bare hands. Use plastic-covered forceps or vacuum needle. Handle them gently, e.g. do not drop them into the vial or on the tab.le. 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 pas for a few minutes before readout.
Adjust to the mark. 11. Set parameter on the 2000P as follows: HV - 470 V (It is 970 V, internal volts = 500). Readout time: 20" T1 - 140' C (Preset) T2 - 250' C (Preset) Rise time: -12*/sec (Preset) Preheat - 100* C (Preset) Start reading - 90* C 127
Rev. 4, 6-01-84 1 Section 3.7 (continued) 12. Prepare the chips as follows (do this before proceeding 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 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.
- 13. Open the drawer and read the standard.
It should read 5.70+0.04.il Adjust HV, if needed. Take 3 readings after final adjustment. Record.
- 14. Close the drawer, 15.
Check bkg. It should read about 0.7-0.8 in 20". If it is higher, adjust the knob in the back of 2000 P (on left side when facing the instrument). Note: Adjust bko 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. 18. After readout is completed, record the reading, open the drawer, and place next chip.
- 19. Repeat Steps 17 and 18 until all chips are read out.
Note: If readino will last longer than 1.5-2.0 hrs., check the standard and bkg about every 2.0 hrs.
- 20. After readout is completed, turn off the gas.
- 21. For calculations, use computer program OGTLD. PUB.
128
4'[7/((LIlML Rev. 4, 6-01-84 / Approved by: Y L.G'. 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. Reaaents Scintillation medium, insta-gel scintillator Tritium standard solution Apparatus Condenser Distillation flask, 250-ml capacity Liquid scintillation counter Liquid scintillation counting vials Procedure 1. Distill a 30 ml aliquot cf the sample in a 250-ml 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 background and standard tritium-water solutions for counting, using the same amount as the sample. Use low tritium background distilled water for these preparations (distillate of most deep well water sources is acceptable, but each source should be checked for tritium activity before using). 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 pCi/l for 300 minutes and samoles containing more than 200 pCi/l for 200 minutes. 129
Rev. 4, 6-01-84 Section 3.8 (continued) 5. Counting efficiency: Eff = com of Standard-cpm of background dpm Standard 6. Sample Concentration: A pCi/ml = 2.22 x E x V x e-At Where:A = net count rate (cpm) E = efficiency (cpm /dpm) 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. 130
Rev. 4, 6-01-84 g/j' f / Approved by: -f N--- O L c'!// c 4..G/ Ruebner 3.9 Iodine-131 in Milk by Ion Exchange on Anion Exchange Column After samples have been treated to convert all iodine in the sample to a common oxidation state, the iodine is isolated by solvent extraction or a combination of ion exchange and solvent extraction steps. Iodine, as the iodide, is concentrated by adsorption on an anion ex-changed column. Following a Nacl wash, the iodine is eluted with sodium hypochlorite. Iodine in the iodate form is reduced to 12 and the elemental iodine erstracted into CCl, back-extracted into water then 4 finally precipitated as palladium iodide. Chemical recovery of the added carrier is determined gravimetrically from the PdI2 precipitate. I-131 is determined by beta counting the PdI. 2 Reagents Anion exchange resin, Dowex 1-X8 (50-100 mesh) chloride form. Carbon tetrachloride, CCl4 - reagent grade. Hydrochloric acid, hcl, IN. Hydrochloric acid, hcl, 3N. 50 ml H 0; 10 ml IM - NH 0H-HC1; 3 - HN 0H HCL wash solution: H O - HNO 10 ml conc. HNO - 2 2 2 2 3 Hydroxylamine hydrochloride, NH 0H hcl - 1 M_. 2 Nitric acid, HNO3 - concentrated. Palladium chloride, PdI, 20 mg Pu++/ml. (1.2 g PdCl /100 ml 2 2 6N hcl). Sodium bisulfite, NaHS03-1M Sodium chloride, Nacl - 2M, Sodium hypochlorite, Na0Cl - 5% (Clorox). 131
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 gummed 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. 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 mi 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): 132
Re/ 4, 6-01-84 Section 3.9 (continued) B. Iodine Extraction Procedure (continued) eluate volume concentrated HNO3 (ml) (ml ) 50-60 10 60-70 12 70-80 14 80-90 16 2. ^dd 50 ml of CCl4 aad 10 m1 of 1 M hydroxylamine hydrochloride (freshly prepared). Extract iodine into organic phase (about 2 minutes equilibration). Draw of f the organic phase (lower phase) into another reparatory funnel. 3. Add 25 ml of CCl4 and 5 ml of 1 M hydroxylamine hydrochloride to the first separatory funnel 3nd 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-HN0 -NH 0H hcl wash solution to the separa-2 3 2 tory funnel containing the CCl 4 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 funTiel containing the CC1. 4 Eouilibrate 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. 133 1
Rev. 4, 6-01-84 l 'Section 3.9 (continued) 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. 5. Weigh a clean 21 mm Whatman #42 filter which has been stored over silica gel in a desiccator. 6. Place the weighed filter in the filter holder. Filter the sample and wash the residue with water and then with absolute alcohol. 7. Remove filter from filter holder and place it on a stainless steel planchet. 8. Dry under the lamp for 20 minutes. 9. Cut a 1 1/2" strip of polyester tape and lay it on. a clean surface, gummed side up. Place the filter, precipitate side up,, in the center of the tape. 10. Cut a 1 1/2" wide piece of mylar.. Using a spatula to press it 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. Calculations 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 Healtn, March 1975, Revised February 1977. 134
Rev. 4, 6-01-84 /7) // /r Approved by: Y /- W!//#//M E.G; Huebner Section 8.1 8.1 Strontium-89 and Strontium-90 in Milk by Ion Exchance Principle of Method A citrate comolex 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-exch arige 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 elated 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 at ed. 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 " total 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 Amnonium hydroxide, NH 0H: concentrated (15N) 4 Ammonium oxalate, (NH )2 2 4.H 0: IN 4 C0 2 Anion-exchance resin: Dowex 1-X8 (CI-form, 50-100 mesh) Carrier solutions: Ba+2 as barium nitrate, Ba(NO )2: 20 mg Ba+2 per m1 3 Sr+2 as strontium nitrate, Sr(NO )2: 20 mg Sr+2 per ml 3 Y+3 as yttrium nitr ate, Y(NO ): 10 mg Y+3 per ml 3 Cation-exchance resin: Dowex 50W-X8 (Na+ form, 50-100 mesh) Citrate solution: 3N (pH 6.5) l 135
Rev. 4, 6-01-84 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*, 2N*) 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 0.2H 0:2N_* 224 2 l Sodium carbonate, Na2C0 :3N, 0.1 N 3 Sodlum chloride, Nacl:4N Sodium chromate, Na2 r0 :3N C 4 Tri-n-butyl phos'phate (TBP), (C Hg)3P0 ; pre-equilibrated with 14N_ HNO
- 4 3
4
- Starred reagents are used only in processing the anion column effluent to determine strontium-90 concentration (Part A).
Apparatus Ion-exchange system: The apparatus for this system is illustrated in F igure 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 mi glass column, 5 cm in diameter and 25 cm long, which services as the catiu column. Below this is connected the anion column, a 30-ml glasa 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) Millipore Type OH membrane filter, 1.5-p pore size, 2.5-cm diameter low-background beta counter. 136
Rev. 4 6-01-84 0 r A RESERVOIR 4 f ,.g,y g g g(,3 y stPasaf047 F uh ee t t ! ~ m ( ........s II 1 I-O sy' i".,, 2SO-ht. GL ASS COLuuhj .tl: wlT M FalTTED e4. Ass casut a OTION RESIN s. . p: O I I u 0 / 30-EL GLASS COLUWhi /L.- _, 4tTM F AITTED GL ASS Otsuj ANICN RESLN [:,;.' r .... I ll...... l_ L n v FiMe e-4 Icn-exchange system 137
Rev. 4, 6-01-84 Section 8.1 - Part A Part A. Strontium-90 Procedure 1. Place ] liter of milk into the ' graduated reservoir. Pipette 1.0 ml 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 water, 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 MIDP0 INT OF THE ELUTION PERIOD AS THE BEGINNING 0F 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 1.5with6N_NHiOHusingapHmeter. 7. Stir and heat to near boiling ir a water bath (approx. 20 min). 8. Cool in an ice bath and centrifuge. Decant and discard the supernatant. Proceed as in (a), 6r (b) depending on whether Ba-La-140 is absent or present from the gamma analysis of the sample. (a) If fresh fi.ssion products are known to be absent: in 10 ml of HNO, filter solution through Dissolve the ppt 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. 132
Rev. 4, 6-01-84 Section 8.1 - Part A (Continued) (b) If fresh fission products are present: 10 ml of HNO, transfer the solution Dissolve the ppt in 3 to a 60 ml 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 0.1N_ HNO, adding it to the centrifuge tube. 3 9. Add 5 ml of 2N oxalic acid to the purified yttrium solution from (a) or (bf. Adjust to a pH of 1.5 with NH 0H, using a pH 4 meter. 10. Digest the solution in a hot H 0 bath for 10 min. with occa-2 sional stirring. Cool in an ice bath (20 min). 11. Filter on a weighed Whatman No. 42 (2.1 cm) filter paper. Wash H 0, ethyl alcohol and ether and dry at room tempera-with 2 ture and weigh. 12. Mount and count in a proportional counter. 13. If analysis for Sr-89 is not required, disregard Section 8.1-Part B. Use the computer program SR8990 to calculate (Sr-90) activity. i 139
7. .x f Ree. 4;'6-01184/ ' m- '~ y w i Section 8.1 - Part B ~ N Part B T ~ Total Radiostrontium (Sr-89 separation) Proceilure - Continue following. columns.siparation (Step A-4). 1 5. Connect 1 l ' separator funnel containing ~ 1 1 of 4N Nacl to the cation column. Allow the solution to flow 'at '10 ml/ mini 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-F ml of solution. / 6. s 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~ b6ttle for the determination of stable calcium. (See section 6.1). 8. Dilute the eluate to 1500 ml with distilled water. 4 l 9. Heat ths < solution to 85*-90*' C~ (near boiling on a hot plate)L and add, with constant stirring,100 ml' of 3N Na C0. Stir-j gently while on' hot plater.to< prevent bumpilig. 2 3 Let stand overni,ght. 10. Decant most ofithe surernate. Transfer the precipitate to a 250 ml centrifuge bottle. 11. Wash the predipitate.'C for 1-2 hours.twice with 50 ml partions of H 0. Dry 2 it in an oven et 110* ~, / %y 12. Dissolve the por slowly with vigorous stirring in 10 m1 of'6N.- HNO3 (with; magnetic stirrer). ' Filter through;Whatman Va.. 54T paper into a" 40lnil centrifdga ; tube. ' Rinse.the bottle with littJe 6N HNO3 and pour the Washings throuah the paper.. To. CentriTuge a[nd' discard super-of 21N HNO (fuming). 1 Stir. - the filtrate, add ' slowly 30. ml well and cool in an ice bath. natant. ,P ~ .x 13. Carefully add 30 ml of conc. HNO -to the? precipitate. ! Heat 3 in a H 0 bath with stirrina-for 'about' 30 minutes ~. Cool-the-2 solution in an ice water baOL for abo'ut~ 5 minutes. Centrifuge.- and. discard supernatant. j -14. Repeat' step No. 13. 4' I 4 A ek
- F
_140 w ~..,. $ w.- L,. tri, e v rs +,-+ --- & e t y s ,2,
Rev. 4, 6-01-84 Section 8.1 - Par t B (Continued) 15. Dissolve the ppt. in '10 ml of H 0 and 5 ml. of NH AC buffer 2 4 and heat in a water bath: Adjust pH to 5.5 using a pH meter and add immediately 1 ml. of 3N NapCr04 and mix well. Digest 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-i fuge and decant the supernate. Wash the strontium carbonate precipitate with 0.1 N Na200. Centrifuge again, and decant 3 the supernate. 17. Dissolve the carbonate precipitate in 5 ml of 6N HNO. With 3 continuous stirring, cautiously add 30 ml of fuming HNO3 to the solution. (Stirring the 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 0 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 activity (pCi/1) using computer program SR8990. 141 I.
I Rev. 4, 6-01-84 Section 8.1 (Continued) Calculations Part A. Strontium 90 concentration (pCi/ liter) = BxCxD ExF Where:A = net beta count rate of ytt sum 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 f actor 1-e-At for the degree of equilibrium 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) = fxC - F (GxH + IxJ) 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-A.t for strontium-89 decay, where t is the time from sample collection to the time of counting D = 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 a self-absorption curve prepared by plotting the fraction of a standard activity absorbed against density thickness of the sample (mg/cm2) H = counter efficiency for counting strontium-90 as strontium oxalate mounted on a 2.1-cm diameter membrane filter (cpm /pCi) I = councer efficiency for counting yttrium-90 as yttrium oxalate mounted on a 2.1-cm diameter membrane filter-(cpm /pCi) 142 l
key. 4, 6-ul-e4 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. s ( l L 143
[ Rev. 4 6-01-84.f / Approved by: < b,, f< El, c'///d 0 U.G/ Hueoner Section 8.4 8.4 Stront'ium 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 a 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 sdpernate. 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 g Acetic acid, CH C00H: 1.5N 3 Ammonium acetate, NH CgH 0 : 3N 4 32 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 3 2 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 N), 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 rocm 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 O 3 2 Ce+3 as cerous nitrate, Ce(NO )3 6H 0 3 2 Zr+4 as zirconyl chloride, Zr0C1.8H 0 2 2 CO :3N, 0.lN Sodium Carbonate, Na2 3 Sodium Chromate, Na2 r0 :3N, C 4 Apparatus Analytical balance low background beta counter Medium - porosity filter stick-EH mGtgr _____ __ m
Kev. 4 0-uA-64 0 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. 5. Add 1 ml of strontium carrier solution, 1 ml barium carrier solu-tion, and if necassary, 1 ml of calcium carrier. solution. (Improved 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- "uge 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 end 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 df card the supernate. s 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, ar.d filter through a Whatman No. 541 4 filter. Discard the mixed hydroxide precipitate. l 145 l
i. Section 8.4 A (continued) Part A. Strontium 89 Procedure (continued) i 13. To the filtrate, add 5 ml of ammonium acetate buffer. Adjust.the pH 3 or NH 0H to pH 5.5. (Note: the pH of the solution with 3N' HNO 4 at this~ point is critical.) Add dropwise with stirring 1 ml of 3N_ Na2 r04 solution. Heat in a water bath, C s' 14. Cool and centrifuge. 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 Na2003 4 solution. Heat gently for 10 minutes. Cool, centrifuge, ard decant the ~ supernate. Wash the precipitate with 0.lN-Na2CO. 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 0F 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 614 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 3N 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. 1 21. Mount and count without delay its beta activity as " total radio-strontium" in a proportional counter. 146
Kev. 4, 0-U1-04 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. I 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. 147 L
Rev. 4, 6-01-84 Section 8.4 (continued) Part B. Strontium 90 Calculations For formulas useo refer to Section 8.1.
Reference:
Radioassay Procedures for. Environmental Samples U.S. Department of nealth, Eduction and Welfare. Environ-mental Health Series, January 1967. p ~ 148
Rev. 4, 6-01-24 / Approved by: y ' [ // / /. ///g [ L.G, Huebner - Section 8.6 ( 8.6 Strontium-89 and Strontium-90 in Milk (Ash), Veoetation, Fish, Wildlife. Soil and Bottom Sediment Samples - Sodium Carbonate Fusion. Principle of Method Strontium is separated from calcium, other fission products,and other natural radioactive elements. Fuming nitric acid separations remove the calcium and most of the other inter fering ions. Radium, lead, and barium are removed with barium chromate. Traces of other fission products are scavenged with yttrium hydroxide. After the Sr-90 and Y-90 equilibrium 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. 1 Reaoents Ammonium acetate buffer, (NH )2 Ac:pH = 5.0, 6M_ 4 Ammonium hydroxide, NH 0H:6,N 4 Carrier Solutions-l Ba+2 Fe+3, Ba(No3 2:20 mg/ml of Ba+2 Sr+2,Fe(NO33, scavenger:5mg/mlofFe+3 i Sr(NO l Y+3,,Y(NO )3 2:20 mg/ml of Sr J 3 3:10 mg/ml of Y+3 Ethyl alcohol, C H 0H: absolute 25 Hydrochloric acid, hcl:12N (conc.) Nitric acid, HNO : 16N (conc.), 6N, 3N, fuming 3 Oxalic acid, H C 0 : saturated 224 Potassium nitrate, KN0 : powdered 3 Sodium carbonate, Na2CO : powdered, 3N, 0.1N 3 Sodium chromate, Na2Cr0 :3N 4 Sodium hydroxide, Na0H:pelTets Apparatus Teflon filter holder, or filter funnel and sample mount rings and discs Magnetic stirrers with Teflon-Coated magnet bars Mylar film Glass fiber filters Fisher filtrator Brinkman dispenser - pipettor 149 l
Rev. 4, 6-01-84 -Section 8.5 A Part A. Sample Preparation - Sodium Carbonate Fusion Procedure 1. Weich out 3 g of ashed sample or silted soil ~ and set aside. 2. Sift into a 250 ml nickel crucible enough Na2CO3 to very lightly-cover the bottom. 3. Add 30 g of Na0H pellets and 5 g of KN0 - 3 4. Add the weighed ash sample and tap the crucible gently to shake the ash down among the pellets. 5. Sift from 10 to 20 grams of Na2C03 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 KNO3 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. 150
-nev. N'0-U M (7" ~ 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 minutes 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 to a 250 ml beaker, and take to dryness on a hot plate. 3, transfer NOTE: Evanoration 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 1 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 ml 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. l 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 1 may have been formed back to nitrates'so they will be dissolv'ed and not removed with the silicates. 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 often if necessary. 15. Evaporate and repeat step (14) at least once, and again as often as necessary. 151
d Rev. '4, 6-01-M Section 8.6 A'(continued) Part A. Sample 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 Tf evaporated to dryness 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" (1.11.3.A(8.65)). Modifications to this procedure were made by the North Dakota State Department of Health. I 152
Rev. 6, 6-01-84 Section 8.6 8 Part B, Determination I. Strontium - 89 Procedure 1. Transfer the solution 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, strontium and barium-radium nitrates. The supernatant contains part of the sample's calcium and pho'sphate 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 commercially 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. 153
Rev. 4, 6-01-84 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 po~ int is critical. Barium chromate will not precipitate completely in more acidic solution and ( strontium will partially precipitate in more basic solutions.) of 3N Na2 r04 solution. Heat Add dropwise with stirring 1 ml C in a water bath to about 90*C and centrifuge. Decant the super-nate into another centrifuge tube. Save the precipitate for Ba 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 m1 of 3R 4 Na2CO3 solution. Heat gently for 10 minutes. Centrifuge, and when completeness of precipitation has been verified by adding a CO, centrifuge and decant the supernate. few drops of Na2 3 Wash the strontium carbonate precipitate with 0.lN Na2C0 - 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 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 0 and 5 ml 2 6N HNO. Add cautiously, with continuous stirring, 20 mi 3 fiiming HNO, Cool in' ice bath, centrifuge and discard super-3 natant. RECORD TIME AS BEGINNING 0F Y-90 INGROWTH. 9. Dissolve the precipitate in 10 ml of H 0. Heat in a water 2 bath. Adjust the pH to 8-8,5. With continuous stirring, add 5 ml of 3N Na2C03 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. 11. Dry the precipitate under the lamp for 30 minutes. Cool and weigh. 12. Mount and count without delay in a proportional counter as total radiostrontium. 154 i}}