Text

Radwaste & Environ Monitoring Annual Rept for 1983
	ML20087P233
Person / Time
Site:	LaSalle
Issue date:	03/31/1984
From:	; TELEDYNE ISOTOPES
To:	;
Shared Package
ML20087P231	List: ML20087P230; ML20087P233;
References
	NUDOCS 8404060186
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4 LAcALLE COUNTY STATION RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING 1

ANNUAL REPORT.1983 i

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e TELEDYNE IS0 TOPES MIDWEST LABORATORY.

Northbrook, Illinois

-MARCH 1984 b

' 8404060186 840328 DR ADOCK 05000

. . . - - - . - .~ . -. . . . ..-_ _ . .= . . . - _ . = . . . . . . .

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i LASALLE COUNTY NUCLEAR POWER STATION 4

4 RADI0 ACTIVE WASTE AND ENVIRONMENTAL MONITORING i

-ANNUAL REPORT 1983

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i TELEDYNE IS0 TOPES MIDWEST LABORATORY Northbrook, Illinois MARCH 1984 -

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TABLE OF CONTENTS Page INTRODUCTION 1

SUMMARY

2 1.0 EFFLUENTS 1.1 Gaseous -

3 1.2 Liquid 3 2.0 SOLID RADI0 ACTIVE WASTE 3 i 3.0 DOSE TO MAN 3.1 Gaseous Effluent Pathways 3 3.2 Liquid Effluent Pathways 5 4.0 SITE METEOROLOGY 5 5.0 ENVIRONMENTAL MONITORING 5 5.1 Gamma Radiation 5 5.2 Airborne I-131 and Particulate Radioactivity 6 5.3 Terrestrial Radioactivity 6 5.4 Aquatic Radioactivity 7 5.5 Milk 7 5.6 Special Collections 7 5.7 Program Modifications 8 6.0 ANALYTIC;L PROCEDURES 9 7.0- MILCH ANIMAL CENSUS 9 8.0 NEAREST RESIDENT CENSUS 9 APPENDIX I - DATA TABLES AND FIGURES 10 Station Releases Table 1.1-1 Gaseous Effluents 11 Table 1.2-1 Liquid Effluents 17 Table 2.0-1 Solid Waste Shipments 22 Figure 3.1 3.1-4 Isodose and Concentration Contours 27 Table 3.1-1 Maximum Doses Resulting from Airborne Releases 31 Table 3.2-1 Maximum Doses Resulting from Liquid Discharges 32 Environmental Monitoring Figure 5.0-1 Locations of Fixed Environmental Radiological Stations 33 Table 5.0-1 Radiological Monitoring Program 35 Table-5.0 5.0-5 Environmental Summary Tables 38 Table 5.1.1 Gamma Radiation Measurements (TLD) 49 APPENDIX II - METEOROLOGICAL DATA 52 APPENDIX III - ANALYTICAL PROCEDURES 81 iii

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t INTRODUCTION LaSalle Station, a two-unit BWR plant is located near Marseilles, Illinois, in Lasalle County, next to the Illinois River. Each reactor is designed to have a capacity of 1078 MW net. Unit No. 1 loaded fuel in March 1982. Unit No. 2 loaded fuel in late December 1983. The plant has been designed to keep releases to the env.ironment at levels below those specified in the regulations.

Liquid effluents from LaSalle County Station are released to the Illinois River in controlled batches after radioassay of each batch. Gaseous effluents

are released to the atmosphere after delay to permit decay of short half-life gases. Releases to the atmosphere are calculated on the basis of analyses of daily grab samples of noble gases and continuously collected composite samples of iodine and particulate matter. The results of eff?uent analyses are summarized on a monthly basis and reported to the Nuclear Regulatory Commission as required per Technical Specifications. Airborne concentrations of noble gases, I-131 and particulate radioactivity in off-site areas are calculated using effluent and meteorological data on isotopic composition of effluents.

Environmental monitoring is conducted by sampling at indicator and reference

-(background) locations in the vicinity of the LaSalle County Station to measure changes in radiation or radioactivity levels that may be attributable to plant operations. If significant changes attributable to LaSalle County Station are measured, these changes are correlated with 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 effluent, Illinois River flow, and meteorological data for the period indicate that consumption by the public of radionuclides attributable to the plant are unlikely.to exceed the regulatory limits. Gamma radiation exposure from noble gases released to the atmosphere represented the critical pathway for the period with a maximum individual dose estimated to be 1.29E-05 mrem for the year, when a shielding and occupancy f actor of 0.7 is assumed.

Environmental monitoring results confirm that dose via other pathways was not significant.

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1.0' EFFLUENTS 1.1 Gaseous Effluents to the Atmosphere

^

Measured concentrations and isotopic composition of noble gases, radiciodine, and particulate radioactivity released to the atmos-phere.during the year, are listed in Table 1.1-1. A total of 1.98 curies of fission and activation gases was released with a maximum release rate of 5.0E+03 pCi/sec.

A total of 2.44E-04 curies of I-131 was released during the year, with an average release rate of 2.07E-04 pCi/sec for all iodines.

A total of 17.80 curies of beta-gamma emitters and less than 1.0E-08 curies of alpha emitters was released as airborne particulate matter, with an average release rate of 5.64E-04 pCi/sec.

A total of 5.25E-05 curies of tritium was released, with an average release rate of 3.30E-06 pCi/sec.

'1.2 Liquids Released to the Illinois River A total of 1.26E+06 liters of radioactive liquid waste (prior to dilution) containing 10.54 curies (excluding tritium, gases, and alpha) were discharged after dilution with a total of 2.56E+10 liters of water. These wastes were released at a monthly average

. concentration of 3.5E-07 pCi/ml, discharged on an unidentified nuclide basis, which is 87.5% of the Technical' Specification release limits for unidentified radioactivity. A total of <7.8E-06 curies of alpha radioactivity and <2.08 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; i Beatty, Nevada; and Barnwell Nuclear Center, South Carolina. The p record of waste shipments is summarized in Table 2.0-1.

I 3.0 DOSE'TO MAN-3.1 Gaseous Effluent Pathways Gamma Dose Rates

' Gamma air and whole body dose rates off-site were calculated based on measured release rates, isotopic composition of the noble gases, and meterological data for the period (Table 3.1-1). Isodose contours of whole body dose. are shown in Figure 3.1-1 for the year.

Based on measured effluents 'and ' meteorological data, the maximum dose to an individual would be 1.29E-05 mrem for the year, with an occupancy or shielding factor of 0.7 included.

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The maximum gamma air dose was 4.26E-05 mrad.

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b Beta Air and Skin Rates-The range of beta particles in air is relatively small (on the order

- of.a few meters or less); consequently, plumes of gaseous effluents may be considered " infinite" for. purpose of calculating the dose from beta radiation incident on the skin. However, the actual dose

.to sensitive skin tissues is difficult to calculate because this depends on the beta particle energies, thickness of inert skin, and

._c ol thing covering sensitive - tissues. For purposes of this report the skin is taken to have a-thickness of 7 mg/cm2 and an occupancy factor of 1.0 is used. -The skin dose from beta and gamma radiation for the year was 1.66E-05 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 5.16E-06 mrad.

Radioactive Iodine The human thyroid exhibits a significant . capacity to concentrate ingested or inhaled iodine, and .the radioiodine, I-131, released during routine operation of the plant, may be made available to man

thus' resulting in ia dose to the thyroid. The principal pathway of interest for this radionuclide is ingestion of radioiodine in milk by L 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. q 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 phe_nomenon of elemental c

iodine deposition on the ground. The maximum off-site average concentration is ' estimated to be 3.83E-06 ' pC1/m3 for the year.

Do'se to-Infant's Thyroid The hypothetical thyroid dose to an infant living near the plant via ingestion Tof : 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 Lthyroid - dose was '4.56E-06 mrem during the year. (Table 3.1.1).

Concentrations of'Particulates in Air Concentration contoursJof radioactive. airborne particulates are

- _ shown in Figure 3.1~-4. The maximum off-site average level is estimated to be 4 53E-05 pCi/m3, Summary of Doses

. Table' 3.1-1-summarizes the doses resulting from releases of airborne -

radioactivity via the different exposure pathways.

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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 2.43E-03 mrem and no organ dose exceeded 9.44E-03 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 pres-ented as cumulative joint frequency distributions of 375' level wind direction and wind speed class by atmospheric stability class determined from the temperature difference between the 375' and 33' levels. Data recovery for these measurements was about 98.4%.

5.0 ENVIRONMENTAL MONITORING Table 5.0-1 provides an outline of the radiological environmental 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.

5.1 Gamma Radiation -

External radiation dose from on-site sources and noble gases re-leased to the atmosphere was measured at ten indicator and four reference (background) locations using solid lithium fluoride thermoluminescent dosimeters (TLD). A comparison of the TLD results for reference stations with on-site and off-site indicator stations is included in Table 5.1-1. Additional TLDs, a total of 48 were installed on June 1, 1980 such that each sector was covered at both five miles and the site boundary.

Nuclear Regulatory Commission, Regulatory Guide 1.109 (Rev. 1).

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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 pC1/m3 throughout the year.

Gross beta concentrations ranged from 0.010 to 0.053 pCi/m3 at indicator locations and 0.010 to 0.075 pCi/m3 at control locations with an average concentration of 0.021 and 0.022 pCi/m3 for the year at indicator and control locations, repectively. No radio-activity 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 gross beta, tritium, strontium-89 and

-90, and gamma-emitting isotopes. Except for gross beta, all other radioactivity was below the limits of detection indicating that there was no measurable amount of radioactivity attributable to the station releases.

Annual mean gross beta concentration measured 23.6 pCi/1, which is

- the level expected in precipitation samples.

Vegetables were collected in July and 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 1.5 to 5.0 pCi/g wet weight and averaged 2.5 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.

i 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.

Well water from on-site well (L-27) was collected monthly and analyzed for gross beta activity. The annual mean gross beta concentration was 20.6 pCi/1. Monthly samples were also composited quarterly and analyzed for strontium-89 and -90, tritium, and gamma scanned. All results were below the lower limits of detection.

Well water was also collected quarterly from five off-site wells and analyzed for the same parameters as in well water from on-site. The results were similar to those obtained for the on-site well, in-dicating that there was no measurable amount of radioactivity due to the station releases.

6 L-

5.4 Aquatic Radioactivity Surface water samples were collected weekly from eight locations and analyzed for gross beta content. Weekly samples from the Illinois River near the intake and discharge pipes were composited monthly and ianalyzed 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.

None of the composite samples indicated the presence of other than naturally occurring gamma emitters at a sensitivity of 10 pCi/1.

None of the samples contained Sr-89 or Sr-90 above respective detection sensitivities of 10 pCi/l and 2 pCi/1. Tritium concen-trations were below the LLD level of 200 pCi/l in all samples.

Gross beta concentrations were similar to those obtained during the preoperational program indicating that there was no measurable amount of radioactivity due to station operation present.

Sediment samples were collected three times, from one indicator and two control locations, and analyzed for gross beta and gamma-emitters. Gamma emitters were below the detection limits. Mean gross beta activity in indicator samples measured 29.0 pCi/g and 27.3 pC1/g at control locations indicating the presence of no radioactivity 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 cases to be below the lower limits of detection for the program.

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Gross beta concentration averaged 3.2 pCi/g wet weight and was at the level expected in fish.

5.5 Milk l Milk samples were collected monthly from November through April and l

weekly from May through October and analyzed for iodine-131, radio-strontium, and gamma emitters. Radioiodine was below the limits of detection, 0.5 pCi/1 during the grazing period (May to October) and i 5.0 ~ pCi/l during the first part of the non-grazing period (January to April). Sr-90 concentrations were variable within the usual 4

range for milk and Sr-89 and gamma emitters were below the limits of detection. ,

- 5.6 Special Collection No special collections were made during the period.

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5.7. Program Modifications Following' modifications were made to the program during 1983: ,

.a. In November .1983, the LLD for I-131 in milk for non-grazing i season was changed from 5.0 pCi/1 to 0.5 pCi/1.

b. The frequency of collection of charcoal was changed.from every :

two weeks to once a week beginning October 29, 1983.

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r 6.0 ANALYTICAL PROCEDURES A description of the procedures used for analyzing radioactivity in environmental samples is given in Appendix III.

7.0 MILCH ANIMAL CENSUS A census of milch animals was conducted within five miles of the Station. The survey was conducted by " door-to door" canvas and by information from Illinois Agricultural Agents. The census was conducted by A. Lewis on August 27, 1983.

There are no dairy farms within a five mile radius of the LaSalle Nuclear Power Station.

8.0 NEAREST RESIDENT CENSUS The census was conducted by A Lewis on August 27, 1983. There were no changes from the previous census.

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APPENDIX I DATA TABLES AND FIGURES l

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1. Caseous (Illuents llN i i S __ JANHARY QghJ lE RR(if g gl1 MAy JtN8E 6MO. TOTAL TECH.5PIC. R[

1. Cross Radioactivity Releases a) Noble Cas Release.- NONE NONE NONE HONE Main Stack

Curles 4.60C.$ REl.f.A5ED RitEASED REttA5Et; RitEA5(0 3.0E-Of 9.0E-05 6.6.A.4.b.

b. Maximum Release Rate }.18.3.1 ,

(grab sample) uCl/sec 4.6D(*l _

N/A N/A N/A is/A $.0(40) 5,0fe0)

c. Isotopes Released 1.11.2.2 y Kr 8$m Curles ---

Kr-87 Curies ... - - -

Kr=88 Curles ... ---

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9.OkQL, _3 QL-QL

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Ne-Il5m curies ---

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Kr-83 . Cwrin_ j.60k)_

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d. Percent of Stach timlt % 4,Zj{-10 N/A N/A N/A 0.77I-6 0.77I-6 J /A

c. Average Release Rate uCl/ set 3llg -6 N/A N/A N/A N/A } ,4 7[-I $,76F.2 3.ll.2.1.a

2. Main Stack fodine Relea e None None None

Mone NON[ 6.6.A.4.b

a. Isntryes Released ag [ggg,j _ Release.1 Released Released RittA5fD 3.18.2.)

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... f.18E-4 1}9r.4

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e Table 1.1-1 (continued)

REPORT OF RA010ACTivt (FFLUENTS I

,I I I ATTACMMENT A 8'*'Ch70*IIO3 7

FACILITY: LASALLE C0lINTV NPS ONIT I DOCRET 8105.3 50-373.50-374 vran. 1981

1. Caseous Eftleents (coni ) UNITS JULT AUGU$f StritMSER SCT00tR II0ttMett SEttneta 6 NO. TOTRItitu. SPEC.Rtf 3 Main Stock Perticulate melease milli- *

a. GrossRedlooctlelty(p-l leverles Detected Detected 9.46E0 3.46EO r.66E0 i 2.94E-3 4.14t-2 6.6.A.4.b

h. Cross Alphe Radioectivity dl <1E-8+ C4E-9+ <9E-9 4

6 41E-8 + 3.18.2 3

c. Isotopes seleased 3.II.2.3 g-u gg ------ ------ ------- ------ ----- ---- -----

Mn-54 aCl 3.48E-2 1.49f-l 2.35E-1 9.96E-3 <2.It-13* C2.lE-13 3.94E-t Co-58 aCl <n.7r-li* <4.7E-13' e6 yr ,i. (4.7E-13* <4.7E-33' <4.7E-13 (4.7E-l} +

Fe-59 aCl (4.9 Ell' <4.9E-13' <4_ gr - t u 4 4.9E-13+ (4.9E-13* (4.9E-13 (4.9t-13 ,

Co-60 =CI 5.96E-3 1.121-1 r, qir-, 3.14E-2 <3.3E-13* <3.3E-13 2.0BE-3

- 2n-65 acl 2.55E-2 2.93t-2 <7 gr-t u <7.9E-13* (7.9E-13 (7.9E-33 5.48E-2 w

St-89 di s.e s -t 4't e ir-q * <3E-9 4 * *

5.ot-9 S r-90 aCl * * (9.0E-9 e

<s c er-9* 41og-q+ (6t-9 , e Zr-95 =C I ------

Nb-95 =CI ------

Re-10) aCl ------

n..-ita aCl 2.87t-i ------- ,,,,,, - --- ------- ----

2.17E-l As-7A MI -"*"

7.40E-? .---.-

7.40E-2 Na-74 eCl 8.23E-I 3.86E0 -.-----

4.68ED Cs-in oCl 03.4E-83* <3.4E-I3' ci tr In <3.4E-13* <3.4E-13' <3.4E-13

<3.4E-13 *

----- ---/

Cs-136 ,c - ------ ------- ------- ----

Cs-13F .Cl :5.8t-93* <5.8E-13' <s.8E-t u <5.8E-33 <5.8E-13" <5.8E-13 <5.8t-83 +

Tc-99m -Ci ------

1. 2 7E -I ------ ---- ------- 4.27E-s Mn-56 aCl 2.36E-0 3.3tED ------ --- --

3.62E0 Re-88 .Cl 5.34t-6 ------- ------ ------ ------- ----

5.36E-6

Data to be presente :1 in an eri ata to thl s report.

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3

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= * #

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2 2 T ee .us ed . = -

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=,

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14

m. .

---._a-__-._L.______

p Table 1.1-1 (continued)

REPORT OF RAD 10AC1BVE EFFLUENTS g, ; 'f March 24,1:

FACILITY: LASALLE COUNTY NP5 UNIT I DOCKET N05: 50-373 YE A'R :*59 3

1. Gaseous iffluents (cont) ungyg JANUARY FEBRUARY MARCH APRIL MAY JUNE blem TOTAL 1ECH SPEC REF

l. Main Stack Particulate Release "

1. Percent Maln Stack' limit 4.59E-8 N/A 6.6.A.4.b*

t' s.69E.9 2.25E-10 5.21E-5 5.33E-5

c. Average Release Rate uCI/sec 2.34E-6 N/A 1.69E-1 5.67E-06 u/A t.47E-3 5.33E-4 3.11.2.t.b

4. Sum of Iodine and SONE r#0NE 6.6.A.4.b.

Particulate Curles 6.28[-6 REMED 4.52E-3 1.47E-05 RELEASED 4. u t-1 9.06r-1 3.tt.2.3

a. Percent Main Stack Limit t 4.59E-8 1.69E.9 2.25E-10 N/A 9.20E-5 9.27E-5 w/A 5 5. Caseaus Tritium None NONE NOME None NONE NONE NONE - EKa6k

a. Release Curles Released RELE.ASED RELEASED Released RELEASED RELEASED RELEASED

b. Average Release Rate uCl/sec N/A- N/A N/A N/A N/A N/A N/A c'. Percent Tech Spec Limit t N/A N/A N/A N/A N/A N/A N/A r

-wp

9 h l

l

Table 1.1-1 (continued)

EtPORT OF RA990ACTigt (FFlutWT5

.gg,gggg,3 ATTACIgetWT A ,' gf g FaflLITTr SMAsttEM M Wiff 99CRET se$r 50-171. to-174 : 1983 t, seseoss Effluents (cent'd 95815 JULT AUGUST SEPTEMBER SC70sta nostMBE R SECEMett '$nt. TgTat Tttle.5PEC. Rf F ,

3. seeln Stock Porticulate

. Release -

~

d. Percent Itein Stock 6.6.A.4.b.

Limit 8 1.2t-5 1.51t-5 , c,r t 1.07t-6 N/A N/A 2.31t-5

e. Average Release Rate uC1/sec 1.29t-3 2. I'I t - 3 f.Itr-4 1.54t-5 N/A N/A 5.9$t-4 3.II.2.1.b.

4. Sur of Iodine sad , ,

6.6.A.4.b.

~ Particulate Curles 7.62t-3 6.58t-3 2.95t-4 7.85t-4 1.64t-4 w/A 1. sit-2 3.81.2 3

a. Percent Mein Stock .

Limit t 1.33t 3 1_ntr-i 3.52t-6 2.25t-5 1.98t-7 w/A 6.51t-5 w

5. Ceteous feltlum 6.6.A.4.b.-

a. Release tweles 5.25t-5 (3.8t-9* (3.03t-9* < 2. 84t-9^ (3.04t-9 <l.20t-9 5.25t-5

b. Average Release Rete uti/see 1.96E-5 N/A NA N /A N/A N/A 3 30t-6

c. Percent Tech Spec tialt % 3.51t-8 N/A NA mfa N/A N/A 3.51[-8

Activity of each arab tmnele is t eu th= ttD fuCl/i tl_

9 y s

.mm*ee--

O

m t

Table 1.2-1 --

REPORT OF RADIDACTIVE EFFLUENTS g, March 24,19s FACILITY: L A5ALLE COUNTY NPS UNIT I DOCKET N05.* 50-373 YEAR: 1981 II. Liquid E f fluents UNITS JANUARY FEBRUARY MARCH APRIL MAY JUNE 6 4. TOTAL TECH.5PEC. RFF.

I.GrossRadioactivity(pf

4. Total Release Curies 6.6.A.4.b.

l . 9X-01 028E

, g,e. 2.62E0 5.19E-02 5.01E-03 9.27E0

h. Avg. Conc. Released w'i/mi 3.45E-07 l.sc c-c'1 7.%E-7 f.42E-6 1.84E-03 2.40E-09 5.60E-07 c.' Man. Conc. Released uC3/mi 2.7E-04 l.') E- c4 4.4E-04 1.96E-6 7.10E-08 3.37E-08 4.4E-04

d. Percent of Tech Spec t_tt_t.t (based on Avg. Conc.

Released) % 9 24E-05 4.gc E-or 5.99E-02 2.82E-02 6.59E-04 8.13E-05 8.91E-02

2. Tritium 6.6.A.4.b.

e--*

N a. Total Release Curles 1.82E-01 /.s A E-ci 5.74E-01 * *

8.6BE-01

b. Avo. Conc. Released uti/mg 2.7E-04 /. 7 E-c 4 2.2tE-04 * *

2.21E-04 c, Percent of Tech Spec 1 1.89E-05 /.s& r-es 5.97E-05 * *

9.00E-05

3. Dissolved Noble Cases None None None None ,03E 6.6.A.4.b.

a. Total Release Curles Released Released Released Released RELEASE 0 1.59E-5 1.59E-5

h. Avg. Conc. Released uCl/ml N/A~ N/A N/A N/A N/A 7.60E-12 9.63E-13

c. Percent of Tech Spec % N/A N/A N/A N/A N/A 2 0.0 2 0.0 3.33.g,3,

4. Cross Alpha Radioactivilf 6.6.A.4.b.

a. Total Release Curies (3.37E-06 < /. 31 E-o(. (7.81-06 * * * <7.8E-06

b. Avg. Conc. Released uCI/ml <5.0E-09 < p.c E-c9 (3.0E-09 * * * <5.0E-09

5. Volume of Liquid Waste Liters 6.73E05 6.57Es 2.60E06 1.41E06 1.75E06 1.03Ee06 8.12E06

6. Volume of Oilution Water Liters 5.50E08 s.01Es 8.44E09 1.84E09 2.82E09 2.09E09 1.65E10 i

Table 1.2-1 (continued) --

REPont or RADIDACTIVE (FFLUENTS LRP 1130-3 O

ATTACHNENT A U,',Ip n g Q g3e)

II FAC it_f TT: LASallt C0tarTT IsPS UNIT I DOCRET 110$_.: go.jyt i;o.irg TEAR: 1983 II. Lieutds Effluents UNITS JULT AUGUST SEPTEM8Ep OCT09tR IIOVEMBER 9tCEMetR WIO. TOTAL ftCN.5PEC. Rtr I.CrossRedlooctivitylf-T)

a. Total Release Curles g 6.6.A.4.b.

l.80E-1 1.09t-1 9.77t-1 1.83t-3 4.32f-3 Released 1.27t 0

b. Avg. Conc. Released uCI/ml l'. % E - 7 3.64t-7, 23BE-7 1.05t-9 2.111-9 N/A 1 39E-7

c. Man. Conc. Released uC1/ml 3.35t-4 5.36t-4 4.5'St-4 N/A 5.36t-4 2.16t-9 4.731-9

d. Percent of Tech Spec 3.II.l.1 (based on Avg. Conc.

' Released) %- 4.27E-5 1.94E-5 1.95t-4 s.68E-5 5.57t-5 N/A 1.98t-4

2. Tritium Non. 6.6.A.4.b.

5 a. Total Release Curles 1_75E-1 i_0NE-t 9.28E-t *

Released 1_21ro

b. Ave. Conc. Re f e's,ed uC8/mt 3. 3 *; E -4 5.36E-4 4.55t-4 *

N/A 2.68E-4

c. Percent of Tech Spec t 1.82t-5 1.32t-5 9.60t-5 *

N/A 1.2EE-4

3. Dissolved Noble Cases None Nonle None 6 6.A 4.b.

a. Total Release Curles Detected 3.2t-5 Detected 9.1t-6 3.8t-6 Released 4.49E-5

b. Avg. Conc. Released uCl/ml Nya 1.07t-1E N/A 5.20E-12 1.85E-12 N/A 4.92F-12

c. Percent of Tech Spec % N/A N/A N/A N/A N/A N/A N/A 3.31.3.3.

4. Cross Alpha Redloactivlt y i None 6.6.A.4.b.

a. Total Release Curles (5.23t-7 < 2.0t F-7 4 . 0t> E'- 6 *

Released 4.06t#6

b. Avg. Conc. Released uCl/ml (It-9 cit-9 2. 0E- 9 *

N/A 2.0E-9

5. Volum of Liquid waste titers 5.23t5 2.01t5 '2.01t6 8.08t5 9.59t5 0.b 4.52t6

. . ...... 9.16E8 s corp 9.t2t3

. .--. 1.75t3 2.05t9 _ ,0.0,_

Table 1.2-1 (continued) LRP 1880-3 REPORT OF RA0104CTIVE EFFLUENTS Revision 0 March 24,1:

Page 12 FACILITY: LASALLE COUNTY NP5 UNIT I -DOCKET NOS.- 50-373 YEAR. 1983 II. Liquid df fluents(cont'd) UNITS ~ANUARY J FEBRUARY MARCH april MAY JUNE 6MO. TOTAL TECH.5PEC. REF

7. Isotopes Released milli-curies 7.50E+0 8.0 9 E*C 5. 71E 03 2.62E03 5.19E01 5.0iE00 8.40E03 Cr-51 MCI ---

1.74E-l 1.43E03 6.77E02 9 63E00 1.45E00 2.12E03 Mn-54 MCI 3.5E+0 3.15E+0 2.10E03 1.24E03 1.77E01 1.51 EGO 3.37E03 Co-58 MCI 1 ter.n 7.01E-1 8.19E02 3.26E02 5.24E00 5.08E-01 1.15E03 Fe-59 MCI 2.72-02 2.17E-2 4.79E00 7.95E-01 3.98E00 ---

9.61E00 5.24E-1 4.86E02 1.63E02 9.25E00 6.22E-01 6.60E02 Co-60 mci 7.55E-01 Zn-65 mCl 2 17E-1 5.29E02 39I 5.24E 00 8.53E-01 7.29E02 5.33t-01 8.8E-03 t ER g-ca *

6.60E-01 Sr-89 mC3 % 7tr-at

5 Sr-90 mC; (6.73E-04 <t.3;s-c3 <7.8E-02 * * * ( 8.00E-02 Np-239 mcl ---

-~

7.0E-01 4.lE-01 ---

1.IIE00 co-57 ---. ---

3.57E-os --- ---

3.57E-01 mC Na-24 ,Cg ---

~

8.52E00 4.5E0 --- ---

6.02E00 1-131 MCI --- -- 3.1E*01 5.3E-01 --- --- 8.4E-On Sb- saa MCI --- -

6.6E-Os --- ---

6.6E-01 Sb-ta4 ' mC I --- ' -

3.07E-01 2.74E-01 4.72E-02 6.28E-Ol Ba-140/La-140 MCI --- --

2.7E-02 1.24E0 --- --

1.27E00 Fe-55 mci 1.28t+0 3.aa r.c 2.56E+2

*

2.6tE02 Tc-99m mC4 --- --

8.92E60 3 1E0 --- ---

1.20E01

_ _ Mo-99 mci ---

1.60E00 1.5[0 --- ---

3.10E00 Mn-56 oci. --- ---

8.1E-02 --- --- --- 8.1E-02 As-76 mcl --- - ---

2.8E0

--- 2.8E00

~ -" ***

Sv-ea .CI ---

3.7E-01 _-- 3.7E-01 _

w- Is1 ,C ---

--- 4,3E-Og --- ---

4.3E-01

+ 0at a to be pre >ented in ai errata to this report.

r

. t s

t i

. P 1

8 9 I5 I

1 t 3 i T

8:

9 1m A L

A 3O - ,t T l v O o 4 3 - 1 1 2 1 0 0 0 o - - f- 7 2 i

e 'e t "42 T

(

1 t

s t

2 8 t

2 t

- t 6

t 6

t 7

t 5

2 t

3 t

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2 E

l E

2 t

9 t

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4 t

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f

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. l P

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r sI 6 1 6 5

1 7

7 3

2 2

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l. 9 3 8 4 5 6 6 0 -

4

~ R e3 G i 1 4 1 1 4 2 2 ( 2 - 2 E l 1 l

a d

-- t e s

e a - - - - - - - - -

l i

ee - - - - -

f

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~

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~

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g 0 - 0 - - - - _ - 3 - - - - - E - - - 3 e t t t E t t t - - - - - - - 6 - - - -

4 l t 2 7 8 2 4 9 4 '

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- I I 4 2 2 8 5 8 2 _ - 4 - - - - - C - - - 3 0

5

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(

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- - - - - 1 - - - -

t A C s 4 1 4 -

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F .- - - - - 4 8 2 - 2 1 - - - - - - - - - - - - - -

2 t O T E E t t E t t t F _ - - - - - - -

t - - r 5 3 0 0 7 o o 7 0 - - - - -

t 2 - -

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n. 3 7 _ -

4 - -

4 0 0

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p e

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( - 2 - 1 a E s R i T h t

1 I 2 l i 3 3 1 1 l l 0 o - - - - - - - , - - - 2 2 - - - - 2 - - - o t t t t t t t E t , - - - - - t t E t - - - - t T 2 9 2 7 7 9 9

7 , - - - t t 6 9 7 7 f - - -

5 3 7 3 1 2 4 0 6 , - - - 9 5 L

3 4 3 6 3 - - - a U , - - - - - t I J 4 2 4 3 6 2 2 2 2 , - - - 4 -

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1 1 2 2 1

(

6 - - a r

? ,

l l

i - s e W S i e n T l l S I l r l l I l : l l l l l l I I l l l i l l a

P N i u C C C= C lC t C C c, C C C C Cs C= C C C t C lC C n I

I U m c a a a a a a a a a a a o a a a a a a i f d-f l i d lu 't t

n 9 e C n S c o

s e

L ( .

r L s d p A t e e S n s A e a b L u e*

l l o f e t f t - =

Y O m

- g ) a T s .

r 2 6 4 3 5 t l d e 1 4 8 9 I 5 9 8 6 i 1 1 c s 2 2 4 2 3 3 3 a t l o

p o

5 5 5 5

f 6- 8 M- 9 7

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1 1

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i - - 1 1 I -

r - - .-

C g t r o e o t S - e h e r e e e A o m 2 S S c s s ^

C C A T 1 F t B R 1

i F C S 1 t F L s I

I .

I 1 _

o

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R .

w C

E P

3 5 9 H 9 C 1

E 3 T 8 t:

9 l L 30 1 A A f O

2 0

- E T

, Y O - -

_ O n4 T E E j I o2 Ii .

9 1

9 5

I s D _

v rc M 5 1 .

Weih LRa E

M 2 0

- r

- 9 E

I

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_. 1 0

t .

9 .

Y 3 .

A 5

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) 5 T 3 d N 7 e E 3

- IL u U 0 R n L

{ 5 P i { A t (

n E A .

o W T oe s

c l T N s .

I "

( C t e H -

t p T a E C

R 1 i C K A

- D A C M 2 A T O R T D A Y 1 F R O A U -

l e T R

R 9 -

O t b P F a E R

T Y

R A

U -

N -

A -

I J f

l s

e - s I S i e i T l l S l l r l i P t s i u C C I

I U m c m m .

Y TI

)

d W

O 't C_ n o

E c 9 L (

L s d A t e S n s A e a L u e l l f e

f R Y E T s I d e p 7 5 i i J 3 t u q

o t 1 t t a i o S e r L s C X I

I .

I ?

v _

Table 2.0-1 ---- - -

REPORT OF RADIDAC".IVE EFFtUENTS

.LRP 1880-3 Revisie O Narch 24,11 FAClllTY: LASALLE COUNTY NPS UNIT I DOCKET N05.- 50-373 YE AR 1983 lin. Solid Waste Shipped Offsite for Burial or Disposal '

UNITS JAN!MRY Ff RRttARY M AR f M ' APRif MAY .fUNE 6MO. TOTAL (({ M P[ W L1

1. Spent Resins, Filter Studges, Evaoora' tor .

Bottoms, etc. NONE NONE 6.6.A.4.h.

SHIPPED SHIPPED

a. Quantity Shipped Cu. meter 1 N/A N/A 3.38E+3 6.77C+l 7.93E+i 3,39E+01 2.tSE+02 "

b. Troe of Weste Evaporatorfvaporator Evaporato' [vaporate-N/A N/A Bottoms Bottoms h , , n,,,, angen ...

c. Radioactivity - Total curles N/A N/A 1.37E-1 2. 8 7E -01 7.0&E-t 6.60E-t 1.79E+0 -

Measured or Estimated? N/A N/A Measured Measured Measured Measured ---

cr-Mt=-/ rr.u

l. Pr inciple Radirmyclides N/A N/A gn.54,(o $! n.6 Jrm.tB rn. W gr-silMn-sso-58 Co-6ll[o-53,ho.chGr-51,Mn-no ---

Natured or Estimated? N/A N/A Measured Mea s ured Measured Nessured ---

e. Type of Container fliA_

het AJype m _ I n, n.m ese y)

N/A N/A LSA L5A LSA LSA ---

. set-a or Container tolume Cu. meter 5 N/A N/A 2.12E-1 2 12E-l * .

lJ OE-1 - ---

f. Solidification Aent N/A N/A Cement Ceaent (e.,e n t (e.gnt ...

e

2. Dry Compressible

6.6.A.4.h.

Waste, Contaminated None None Equ i pme n t . e t c . Shipped S hi pped J. Quantity Shioped Cu. maters 1_76E+01 1.53E+0i N/A t.56E+0! N/A 3.70E+01 8.55t+1 .

u. Radioactivity - fatal turies 1. 71[-Q2_,_ 4.19E-02 N/A 3.9BE-02 N/A 7,37E-02 1,73E-3 1easured or Estimate? Measured Measured N/A

Measured i4/A Measu red ...

i Princiele Radionuclid,s o o- N/A .h[

~

, N/A 'h [,*hl ,,,

'icasured or Estimatei

Measured Measured N/A Measured N/A Mea su red ---

f. Type of Container (LSA, T,pe A. Type B,Lge. Quantity) L5A LSA N/A LSA N/A LSA ---

Container Volune Cu. meters 2.12E-1 2.12E-1 ufa 2.12E-01 N/A 3

~

rf ' ---

_. Type of y aste DAW DAW N/A DAW N/A DAs ---

l Table 2.0-1 (continued) - -

LRP11tO-3 85L - D..s e..a l a . 5..ui h Caroli na SOLID RAD 10AC11VE WASTC Sut' MARY Revision 0 CN - Clem 83ut lear Co. . .

UNITS 1/2 March 24,19 H:4 -. Hi t t=an fluc lear t, Deve lopment Co. LASALLE Cot >'iTY NUCLEAR POWER STATION Page 16 DISPOSITION OF MATERIAL Type- Type Solidifi-Pri nc iple Shipment Ship m .t Volume Activity of of cation Vglume Activit= ner Mont* Pe r flune l 0

TRANS C0. BURfAL 5tTF Waste Container Agent Muclides (ftJ) (mci) (ft3) (mci) _

21 January 83 Tri-State M.T. RWA DAW L5A N/A Cr ypy.g 622.5 17.29 622.5 17.29 RWA DAW L5A N/A h p 540.0 41.86 540.0 41.86 1,8 , February 83 Tri-State M.T. _

16 March 83 Tri-State M.T. RWA N![5ms LSA Lement d r.si,sli-sq 397.5 " 47.8 397.5 47.8 ,

23 March 83 Tri-State M.T. RWA N Ebi tSA Cement fria-sM i 397.5 41.8 795.0 89.6 25 March 83 Tri-state M.T. RWA sNIEi;is L5A Cement C.-sa 397.5 47.8 1192.5 137.4 01 April 83 Tri-State M.T. RWA soffbs LSA Cement Cr-51 390. 34.7 390. ,3.4.L 11 April 83 Tri-state M.T. RVA BoYibs LSA Cement FE-59 397.5 18.6 787.5 53.3 14 April 83, Tri-State M.T. RWA bfff6ms L5A Cement Mn-54 390 19.4 1177.5 72.7 U 15 Apr'il S3 Tri-State M.T. RWA DAW L5A N/A Co-58 My. 39.8 1729.5 112.5 _

20 April 83 Tri-State M.T. RWA [ opp 6es 397.5 61.2 tsA F - ar Co-60 2127 173.7 22 April 83 Tri-State M.T. PWA b Elwn LSA Cement In-63 M7A 88 9 2524 A M2.6 29 April 83 Tri+5 tate M.T. RWA N![6ms L5A r - nr I 416 4 64 3 _ 2941.6 tM e 04 May 83 Tri-State M.T. RWA b5ffoms L5A Cement Cr-51 393.9 84.8 393.9 84.8 06 May 83 Tri-State M.T. RWA g[IfPoAs LSA r ~ ar Fa-59 390.0 102.0 78 1_186.8 11 May 83 Tri-State M.T. RWA NNoms L5A Cement 'in-54 397.5 27.0 1181.4 213.8 13 May 83 Tri-State M.T. NWA N*fs,,,, L5A Cement Co-58 l409.8 25.9 1591.2 239.7

._19 M8Y 83 Tri-State M.T. RWA N' 6 L5A Cement Co-60 !397.5 6.36 1989.7 246.8 25 May 83 Tri-state M.T. RWA N*fy L5A Cement 2n-65 423.0 6.72 2408.7 252.8 27 May 83 Tri-State M.T. RWA LSA Cement { 390.0 450.7 2798.7 703.5 03 June 83 Tri-State M.T. RWA fj{6ms L5A Cement Cr-51 418.0 ' 327.7 418.0 327.7 10 June 83 Tri-State M.T. RWA DAW LSA N/A Co-58 706.5 36.66 1124.5 364.4 16 June 83 Tri-State M.T. RWA DAW L5A N/A Co-60 i 600.0 37.0 1724.5 401.4

~

21 June 83 Tri-State M.T. RWA M*f5ms L5A Cewn: Mn-54 390.0 197.6 2114.5 599.0

~

Tri-State M.T. RWA Iaif6ms L5A Cement 2n-65 390.0 135.0 2504.5 24 June 63 734.0 ]

- b

Table 2.0-1 (continued) ._..

tPORT OF llAtleACTIM IffLW eit lap 1930-3 ATTACIsetNT A Revision 9 narch 24, ISS)

FACILITY: LASALLE COURTT 1r1 Iluli l SOCRET n95.8 to-17t_ sn 171, 15 ftAm. test 111. Solid Waste Shipped Offsite for Durial or Olsposal UNITS JULT AUGUST SEPitMOta OCitetR NovtMstR stCtsigtR GMS. TOTAL TECM.5PEC. Afd I. Spent Resins, Filter Studges, Evaporator ,

Gotteses, etc. 6.6.A.4.b.

a. Quantity 5hiesed Cu. meters t_04t2 1.08[1 at t7t s 5.lott 3.33tl 4.81tl~ 3.2tC2 Lwap. Lwap PI Evftoms Bo twan Evas.

Bot tosas

[vap

b. Type f Waste annen anten- m, , _ ,,,, _ ufa e, Radioactivity . Total cesries a nts 2_stn 3.845 3.420 5.399 9.522 2.671tt se.. ,.a - .a n n- . t Me sured Me asures m - .. .. A MPasured NeOIUIOd Measure i N/A Ea:tiJin-1 4o:k6.M: 1Eo:1&S W:-t& l ;-it sa .

d. Principle Radionuclides - same N/A Measured or estimate? Measured sen Nasu red Measured Measured N/A Measured ..,.a y a Type of Container (LSA.

A type A. Type e,tge Quantity) . L5A - LSA ata tu LSA dIA N/A Container volume Ou. meters $!3DI' 2.12t-1 }Nik!! 3.12t-1 kNI-l C Sam N/A .

j f. Solidification Agent traent Cement Cement Cement r., Cemerft N/A I

2. Dry Cumpressible *

6.6.A.4.b.

Weste, Contaminated 180ne m Egulpment -etc. a e s i mo .. 3h:

a. Quantity $ hipped Co. meters ufa 2.09tl m/A 1 99tl 1.87tt 1.60E0 6.11El .

b. Radioactivttv - Total turfem u/A 0.079 N/A 9.17t-2 2.55E-t 1.04td 1.465 Measured ne antimarm? M/A Measured m/A ' Measured sa..=ured Measured N/A I -

Lt->l.Pe-> p I r53,Fe-53

- c. Prlaciple Radlonuclides N//. in-C R send i N/A I n;B.Mn.%4 Same se,e N/A I

Measured or estimate? N/A Neasured N/A measu red Measured Measured N/A it. Type of Container (LSA.

l Type A. Type 5.Lge. Quantity) N/A tsA N/A L$A LSA LSA N/A io 2.jl}2t0or

-4 4.14 t -s ,J 4Jt-a m '.

Container Volunie N/A g* o- - N/A m/A -

tu. meter. a,t 79tn .-t_29E-1

. Type of Was.te P. N/A DAW ura DAW DAW . _pr.J N/A l

Table 2.0-1 (continued) nw - n.s..........y.

OSC - Barnwell, South Carolina SOLIO RAOl0AtilVE WA5TE SurMARY W lilo-3 CN - Chem Nuclear Co. IfMITS 1/2 8',',

n y9gy H!I - Mittman Nuclear & Developent Co. LA5ALLE C0ultTY NUCLEAR POWER STATIOli 16 ATTACMMENT A DISPOSITION OF MATERIAL Type Type Solidift-s rinciple 5hioment l shi pne..t Volume 4(83v3tv of of cation Vqlisme Activity ner Monti per Mnnel WucI ld ts (ftJ)

DATE TRI.45 CO. _SURIAl_ SITF Weste Containes Agent (mCl) (ft)) (mCl) 01 JULY 83 Trl-State M.T. RWA NN$m itA r,=aa' Cc-51 ti, 142. 442 I42.0 05 JULY 83 Trl-state M.T. RWA CL, LSA Cement Fe-59. 413 34.2 855 . 76.2 08JULYB3 Tri-State M.T. RWA ',- ea r____, Co-58 405 46.6 1260 222.8 13 JULY 83 Trl-State M.T. RWA b5fE6ms LSA Cement Co-60 417.5 16_7 1677_t mL 15 JULY 83 Tri-State M.T. RWA b5fEks tSA Cement Mn-54 390.0 44.6 2062A 101.6 sa msva, Tri-5 tate M.T.* RWA b5fE6ms L5A Cement 2n-65 405.0 SM 0 2467.5 .8 8 8 . 6 __

y 22 JULY 83 Tri-State H.T. RWA b5ffams LSA Cem-nt 197.5 191.0 2865 1279.6 27 JULY 83 Tri-State M.T. RWA b5ffams tsA Cement 3?7.5 312.0- 37M s p s.&

To ttei vRt Tri-State M.T. RWA Mams L5A Cement ,r 403.0 284.0 3670A 1875.6 tvap. Cr-Si 03 AUG 83 Tri State M.T. RWA Bottoms 154 .tement , 405.0 716.0 405.0 736.0 -

12 AUG 83 Tri-State M.T. RWA Evap. LSA Cement Co- 8 450.0 721.0 ,855.0 1657.0

-24 AUG 83 Tri-State H.T. RWA troms tgg ' Cement Co-6gi N"~5 450.0 656.0 1305.0 2113.0 and 2n-65 23 AUG 83 Tri-state M.T. RWA DAW LSA Cement 520.5 616.0 1825.5 2729.0 09trPRt T e l .u .e . uv mua BbIf8ms LSA Cement Cr-51 375.1 717.0 375.1 717.0 145EP83 Tri-State M.T. RWA b5fEams L54' Cement 'Fe-59 319.8 706.0 694.9 1423.0 intrPRt ven tem,. uT mun b5ffoms LSA Cement Co-58 300.0 541.0 994.9 1964,,0 _

235EP83 Tri-State M.T. RWA b5ffoms LSA Cement Co-60 300.0 656.0 1794.9 2620 A 285EPB) Tri-State M.T. RWA MEtoms LSA Cement Mn-54 300.0 '623.0 1594.9 3243.0 30sEPB) Tri-State M.T. RWA BbIfbs LS A - Cement 2n-65 300.0 602.0 1894.9 3845.0 050 CTS 3 Tri-State M.T. RVA DAW LSA N/A Cr-51 702.0 91.2 702.0 98.2 re .$o o*f 0CTb3 Tel-State M.T. RWA skTfRm tSA f e-ien t 300^0 3 0 'UU 0 7' Cc-50 I40CTo) Tri-State M.T. pWA sk{(b, LSA Cement Co.60 300.0 499.6 1302.0 975.8 190CTh3 Tel-State M.T. RWA dtbs 154 Cement **$% 300.0 366.0 1602.0 1341.6 210CTei) Tri-state M.T'. RWA skIfbs tSA C ee'en t 2n-65 iD0_0 6tR n son, n into n

r Table 2.0-1 (continued)

RWA - Alatilan.1, Wnshington l

$0LIO RAtt0ACTIVC waste StrMARY LAP III'*3 95C - Barnwell. South Carolina Cte - Cnee neoclear Co. 1101175 1/2 (','{',93 stil - Mittman eleclear & Development Co. LA5ALLE Coullif 11UCLEAR POWER STAT 10ll 16 ATTACM'MttlT A Dl5Postil001 0F MAftRIAL Type Type Solidifl-'rinciple shipment Shi pme..t volume Activity of of cation Vglume Activity err Penti Per Mnnel DATE TRANS CO. BURfAt siff Weste Containes Agent 1ocileles (f t d (MCI) (f tll ImCl3 same 300.0 768.2 2202.0 2728.0 260CT83 Trl-State M.T. RWA NE.es tta rament es 200CT83 Tri-State M.T. RWA ;;5f[. nmg LSA Cesen t Awye 300.0 783.0 2502.0 35tl.0 I

OltNOv83 Tri-State M.T. RWA $*[,,,,. tsA C==ent tr-SI 117 0 9to_o it? n 910 0 t v.) p 10NOV83 Trl-State M.T. RWA no t t enis ita ram n, Co-58 100.0 1910_7 it? o $Q llNOV8] Tri-State M.T. RWA NI[r s eta r-,n e ca.60 ynn a 1773.0 937.0 4213.7 18N0v83 1rl-State M.T.* RWA DAV LSA N/A Mn-54 659.7 255.0 1596.7 4468.7

,ro 30N0V83 CN kWA N'[ oms tsA r-ment 7n-fA 2Ln_n stRt n tatA 7 ras:1_7

DAW EB 386.0 128.0 02DEC83 Tri-State M.T. RWA L5A w _ Cement

_Ir-5L_ 328.0 396.0 2 0.0 1479.7 568.0 1865.7 02D[C83 CN . RWA nf n,,, tsA C, ment re-C4 ___

RWA kiE6ms L5A Cement Co-56 244.0 2336.0 808.0 L201.7 090tC83 CN Gap I 13DEC83 Trl-State M.T. RWA L5A fement Co-60 300.0 962.0 t108.0 'E141.7 go,,

13DEC83 CN RWA !B L5A Cement Mn-5% 105.0 1909.0 1213 0

7052.7 15D1083 CN RWA h., [,, LSA Cement in-65 240.0 1968.8 1453 0- 9021.5 ISDECB) Tri-State M.T. RWA kQP, LSA Cement 5b-12% 300.0 1 %0. 2 I753.0 10561.7 e

e

Figure 3.1-1 Estimated Cumulative Gamma Dose (mrem) from the LaSalle Station for the period January-December 1983. [j r 7 Isopleth Labels %'

Small figure - multiply by 10-j ,,

f'25, large figure - multiply by 10-

~

us -

8 10 t

i s_..... . s.

'10 A _ __ '

s 9 ! f-

/

10 8 m --

OttoIe Morris warmeelles Senece inoes Rt"' {

f

/ a

'.[___N . -

n'"' * * y 10 N \/ '

oveme

,, ,,. pr

,, Streeter

~

rs 10

/

55 oden

,s -

o,,,,S to t5 20 mi 27

Figure 3.1-2 Estimated Total Concentration (pCi/m3 ) #

of Noble Gases from the LaSalle Station f y for the period January-December 1983.

Isopleth Labels ; Ik d Small figure - multiply by 10-j q' 9,,, \ ~

Large figure - multiply by 10~ ,g, 1

!* I'*^

k g- M 5 k -

l]

"^ S m

. , . . . . ..... ae y'

t 25 ( IG g ( ,

x\ 1 5 o I ta u_-

l

/ 10 w.

\ l 'N io oito.o k ] 15 u.cris

/ a _

w.r n I

I

/ /

s.n.caf f uu,;. e .c 1 -

s Q

wLM --

10

[r-~ p \J

(' ,_

15

/ /; m..

r ..

10 f gstreew om 10 - ~ ~

25 -

, . . .. ,o .. n, 28

Figure 3.1-3 Estimated Total Concentration (pCi/m3) ['

of Iodine from the LaSalle Station for the period January-December 1983.

[ y g i r

g# 25-Isopleth Labels '

7 sj I G---

Small figure - mutliply by 10 7 Large figure - multiply by 10- g){j Md.

,merwowwwo s

1 2

)

, e:::=: ..... ..

l ,

m i

- 5-e l

s a^

(

l [

N \

5 l

5

.., iso otto [ro

\ ..

' M orris i

I sea.ce

! lilinois l

10 Orw AN V s, . .. . 8 is 4r iro

/

i s

( , ; ...

4 str ter 10 3 i

l '

A6 Dwigtet

5 /

- 5s l

Odett o

E8 -

10 t5 2o mi 0 , ,, ,S ,

i 29 l

I Figure 3.1-4 Estimated Total Concentration (pci/m3) of Particulate Matter from the LaSalle Station for the period January-December 1983.

[ Fg r

10

[

Isopleth Labels Small figure - multiply by 10 6 Large figure - multiply by 10-6

-l -

) (- }s7 ,

s dwiwwwi; wwwwwws s

9 ! F 10 W.eren O 80 Otto e a L oresilles fsi meer 's

. Se.f ece lilinese AW 2s l 10 1 917 m 3 5

p.ndmies.' ,

is W * * " '

i f ( 10 I 2s 5 .

N ,

b/ er g

d*

ss

~ 10

/ / '

9 f od fen es -

o 5 10 15 20mi 30

Table 3.1-1 LAS alt.E STATION - UNIT 1 MAXINUP DOSES PF. STILTING FPON AIRBORNE RELEASES PFRitip UF RELF ASF D6 CFMMER 1, 1993 - DECEMBER 31, 1983 DATE OF CALCULATION 03/16/04' '

TYPE CURPENT PFRIOD CURRENT OtfARTER THIRD UUhPTFH SECOND QUARTER FIRST GUARTER ANNUAL b4NNA AIR (MRAD) 0.0007 00( N ) 0.000F 00( h ) 0.420E=04( SW) 0.122E-05(WSW) 0.962E-12(ESE) 0.426E-04( SW)

BETA AIM (NHADI 0.000E 00( N ) 0.000E 00( N ) 0.4N0E-05(NNE) 0.419E-06(NNE) 0.154E-10(ESE) 0.516E-05(NNE)

WHOLE BODY (MREN) 0.000E 00( R 1 0.000E 00( N ) 0.126E-04( SW) 0.440E=06(WSW) 0.196E-22(ESE) 0.329E-04( SW)

SK1W (MPEM) 0.0006, 00( N ) 0.000E 00( N ) 0.th3E-04( SW) 0.596E-06(WSW) 0.522E-St( N ) 0.166E-04( SW)

ORGAN (NREM) 0.n00E osti N .) 0.345F-07tWSW) 0.444F-06( SW) 0.422E-05(NNE) 0.509E-01(SSE) 0.456E-05(NNE)

BN-AD LN- A[i LN-AD LN-AD Cl-IN LN-AD CRITICAL ORG-PERS b.

C0"PLIANCE STATUS 10 CFR 50 APP. I 10 CFR 50 APP.!

TYPD OUARTEHLT 08JFCTIVE % OF APP. 1 TEARLY ORJECTlWE % OF APP. I GANWA AIR trunpt 5.0 0.00 10.0 0.00 BETA AIR (MRAD) 10.0 0.00 20.0 0.00 WHOLE BODY (NRE4) 7.5 0.00 5.0 0.00 SKIN (MRE4) 1.5 n.00 15.0 0.00 GRGAN (MMEM) 7.% 0.00 15.0 0.00 CRITICAL ORGAN-PF.RSON (LN=AD) (I.N

A D )

CRITICAL ORGANS: BNzHONE. LVsLIVEP, 1H=YHT AL Pt'DT 1Hz1NYPulp, KDzFIDNEt, LN a t.U m G, CisCl-LLI CRITICAL PERSilN: AusADULT.,INalNFANT

Table 3.2-1 LA$ALLE UNIT ONE MAXIMUM DOSES (MREM) RESULTIhG FROM Lf GUID EFFLUENTS PERIOD OF RELEA3i - 1/ 1/83 TO 12/31/83 CALCULATED 01/17/84 e 1ST 2ND 3RD 4TH ANNUAL DOSE TYPE QUARTER GUARTER QUARTER GUARTER

_, _ 1/E3- 3/83 4/83- 6/83 7/83- 9/83 10/83:12/83 TOTAL 1.44E-03 7.78E-04 a.24E-06 0.0 2.43E-03 BODY ~ ~ ~

INTE RN AL' ' 4.33E-03 3.05E-03 1.d4E-05 "O.5 9.44E-03 ORGAh

.61-LLI G I.-L LI GI-LLI BONE GI-LLI.

THIS IS A REPORT FOR THE CALENDAR YEAR 1983 COPPLIANCE STATUS - 10 CFR 50 APP. I

......... .. 1 0F APP I. --------------

eTALY IST STR 2hD GTR 3RD STR 4TM GTR YALT I 0F OBJ 1/83- 4/83- 7/83- 10/83- OBJ APP. I 3/83 e/83 9/83 12/83

~T O'T'A' L' 00 D Y (MREM) ~1.5 0.11 0. 0'5 0.00 0.0 3.0 0.08 CRIT. ORGAN (MREM) 5.6 C.13 0.06 0.00 0.0 10.0 0.09 GI-LLI GI-LLI GI-LLI BONE GI-LLI PROJECTED 3Jht Al NEaaEST C0=* UNITY . ATE 4 $TSTEM +

PEkICD uf RELEASE - 11/22/43 70 11/22/43 CALCULATED 12/09/d3 Cus3ENT CunFENT 1sT'PRiv 7ND PREV 3RD PREV ANNUAL 003E TYP! ?:aIOD JUA&TER CutRTEA QU44TER GUARTER 10/13-11/*1 7/J3- 9/13 4/o3- 4/S3 1/83 ,3/83 TOTAL 3.E71-Gd !.57E-07 5.73E-Oo 1.e2E-Oe 2.09E-C4 4.37E-04 A0DY TKTEEWAL 'T.41E-07 2~1!E-'Of 9.23E-Oi 1.14E-04 2.03E-C3 3.07!-C3 ORGAh GI-LLI GI-LLI CI-LLI GI-LLI GI-LLI GI-LLI e LAST PE410C CF RELEASE - 11/14/13 TO 11/14/!! CA.CULATED 12/09/!

THIS AEPC47 AS 385ED CN CUAREAT CLa*TC< RELEas;C COPFLIAhCC STATUS - 44 CF8 1+1 TYPE A N h w a '. . L a M a T T CF LIMIT TOTAL 4.0 (4AEM) C.011 E00T INTERNAL * '4.0 (*1E') 0.077 CREAN

.1-LLI e T>In CALCLLATIC?l ;F fit. Is 345L- CN 1.f=NI.U;5 Oc5CRIVED IN THE COMMChetATLTP s D I S u ?. Crr!!Te CCs! C4LtutAT!35

4 :. ; A L . Th!!! T EC 4*.11UE ! DIFF f e FROM TH0$E DEstaafit I*. 4C CF3 141. A Ps0JECTED DOCE OF 2 mREP uSING CICO TECNh!dUE$ IS APPRLAIFATILY 4 *R1' u'!NG . FPa 'ETWC1!.

32

~

. LASALLE COUNTY tlUCLEAR POWER STATION LOCATIONS OF FIXED. ENVIRONMENTAL RADIOLOGICAL MONITORING S Figure 5.0-1 Y

2 *$

U$

. Ollawa 'di5E

4,/, Marseilles 5 a IIW neca- -

7 ,

s -

Additional .

TLDs -

.I .2 8

, Pl. HT

. 6 LaSalle County )*

- 6 rand Ridg station / Verona

. Kinsman it.Ronsom ,

Str'sofor .

IO GRUN0Y COUNTY LA SALLE COUNTY LIVINGSTON COUNTY

' ' ' ' 'P""

SCALE: .

i Air Samplers 1 - Hearsite 1 8 - Marseilles 2 - Onsite 2 9 - Grand Ridge 3 - Onsite 3 10 - Streator 4 - Nearsite 4 11 - Ransom 5 - Onsite 5 12 - Kernan 6 - Nearsite 6 13 - Route 6 at Gonnam Road *

~

- 7 - Seneca 14 .0ttawa

~

TLD

, Same as air samplers plus a. sufficient number of additional L i 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. -

33

LASALLE COUNTY NUCLEAR POWER STATION Standard Radiological Sampling Program Media is 5* 8 .

E % o L $ e

3 '

5 *

}. 8 4 3 =

E . i Loc. 5 ? 5 '

f 5 Code Type a Location Description 2 # 5 $ C E 8 E E u}.$

L-01 Nearsite No. 1 X X L-02 Onsite No. 2 X X

.L-03 Onsite No. 3 X X L-04 Nearsite No. 4 - X X L-05 Onsite No.-5 X X L-06 Nearsite No. 6 X X L-07 Seneca X X L-08 Marseilles X X L-09 .C Grand Ridge X X L-10 C Streator X X L-11 Ransom X X L C Kernan X X

'L-13 Route 6 at Gonnam Road X X L-14 C Ottawa X X L-15 Johnson Dairy X X X L-16 Lowery Dairy X X X L-17 C Norsen Dairy X X X L-18' C Sunnyisle Dairy .

X X X

'L-19 -Illinois River at Marseilles X L-20 Illinois River at Ottawa X L-21 C Illinois River at Seneca X~

L-22 South Kickapoo Creek X L Illinois Nitrogen Corp.. X L LSCS Cooling Lake near' recreation area X X X X L-25 C LSCS intake pipe / river X La26 .LSCS discharge pipe / river X

., L-27. LSCS onsite well . X-L-28 ' . Marseilles Well Water. X L-29 C Seneca Well Water X L-30. Ransom Well Water X L-31 Ottawa Well. Water. X L-32 . Illinois State Park X L-33 -C Just upstream of cooling lake inlet structure X X L-34'- Just downstream of cooling lake.

. discharge structure .

X X L-35 Marseilles Pool of Illinois River X L-36 Farm A - vegetables X-L-37 Farm B - vegetables X_

"Contrdi(background) locations are indicated by a "C" in this column. All other locations are indicator.

34~

Table 5.0-1 .

1.aSalle County Radiological !!onitoring Program, Sample Coll'ection and Analyse 5.

location Lollection Type of f requency of Sample Analysis Analysis Remarks Media Code Site Frequency Weekly Gross beta weekly On all samples.

1., Airborne L-1 Nearsite No'.1 Quarterly On quarterly composites fram each location.

Onsite No. 2 Gamma Isot Particulates t-2 Sr-89,90 Quarterly , On quarterly temposites f rom each location.

L-3 Dnsite No. 3 L-4 Nearsite No. 4 L.5 Onsite No. 5 L-6 Nearsite No. 6 L-7 Seneca L-8 Marsellie L-9 Grand Ridge L-10 Streator L-11 Ranson L-12 Kernan . .

L-13 Route 6 at Gonnam Rd.

L-14 Dttawa Bi-weekly 1-131 Bi-weekly Bi-weekly = every Z weeks, on _all samples.

2. Airborne Same.as 1.

(weekly)*

lodine .

taa

Quarterly Gamma Quarterly Two sets at all AP locations. One set

3. TLD Same as 1. read quarterly. Second set read if L-101-07 Inner Ring required by (dison. At other locations, L-201-16 Outer Ring all sets read quarterly. -

Johnson Dairy Weekly: Apr to Sep 1-131 Weekly May thru October only. LLD: D.5 pti/l

4. Milk 1-15 Monthly L-16 Sunnylsle Farm Monthly: Oct to Mar Gamma Isot Norsen Dairy $r-89,90 Monthly L-17 L-18 Rinker Dairy Illinois River at Weekly Gross beta Weekly On all samples. .*

5. Surface L-19 Monthly On monthly composites from each location.

Marseilles Gamma Isot Water Quarterly On quarterly composites from each location.

L-20 111. River at Dttawa Tritium -

111. River at Seneca Sr-89,90 Quarterly On aparterly composites from each location.

-L-21 L-22 South Kickapoo Creek-L-23 111. River at Ir.take to Nitrogen Cairp.

L-24 LSCS Cooling Lale near ,

Rec. area LSCS intake pipe / Week ly Gross beta Weekly On all samples.

6. Cooling L-25 Monthly On monthly composites f rom each location.

Water river Gamma 1 sot LSCS discharge' pipe / 1ritium Monthly On monthly composites from each location.

L-26 river Sr-89,90 Monthly _ On monthly camposites from each location.

Beginning October 29, 1983, bi-weekly collections were changed.to weekly. .

Table 5.0-1 (continued)

LaSalle County Radiological Monitoring Program, Sample Collection and Analyses.

Collection lype of Frequency of Sample Location Analysis Analysis Remarks Code Site Frequency Media Gross beta Monthly On all samples. .

7. Precipitation Same as 4. Monthly On quarterly composites from each location.

Gamma Isot Quarterly Tritium Quarterly' On quarterly composites from each location.

Sr-89,90 Quarterly On quarterly composites from each location.

Quarterly Gross beta Quarterly On all samples.

8. Well Water, L-28 Marsellies Well Seneca Well Gamma Isot Offsite L-29 Tritium L-30 Ranson Well L-31 Ottawa ve11 Sr-89,90 L-32 Illinois State Park Well Monthly Gross beta Monthly

9. Well Water, L-27 LSCS Onsite Well Quarterly On quarterly composite.

Gamma Isot Onsite Tritium Quarterly On qaarterly composite.

Sr-89,90 Quarterly On quarterly composite.

Annually at Gross beta Annually Four varieties from each location.

10. Vegetables L-36 Farm A Annually L-37 Farm B harvest Gamma Isot Sr-89,90 Annually Annually at 1-131 Annually

11. Green Leafy Same as 10.

Vegetables harvest Quarterly Gross beta Quarterly Cattle Feed: winter

12. Cattle Feed Same as 4. Quarterly Grass: summer Gamma Isot and Grass Sr-89,90 Quarterly Gross beta Three times On edible portions only.

13. Fish L-24 LSCS Cooling Lake Three times

. a year a year Gamma Isot 'Three times On edible portions only.

L-35 Marsellies Pool a year Sr-89,90 Three times On edible portions only.

a, year 9

G S

't Table 5.0-l'(continued) ,

LaSalle Cotinty Radiological Monitoring Program, Sample Collection and Analyses

~

5 ample Location Collectton. Iype of Frequency of Media - Code site Frequency Analysis Analysis Remarks 14.' Aquatic Plants L-24 LSCS cooling Lake Three times a year, Gross beta Three times if available a year

~

L-33 upstream of Gamma Isot Three times cooling lake a year L-34 Downstream of cooling lake

15. Bottom Same as 14. Three times a year Gross beta Three times Sediments a year Gamma Isot Three times a year

16. Dairy (a) Site boundary to 2 miles Annually During grazing season Census (b) 2 miles to 5 miles d (c) At dalries listed in item 7

17. Nearest In all 16 sectors Annually Restdence Census

(

4

( - ,

tam 2 5.0-2 Environmental Radiological Monitoring Program Quarterly Summary Name of facility LaSalle Nuclear Power Station Docket No. 50-254, 50-265 Location of facility Marsellies, Illinois Reporting Period 1st Quarter 1983 .l (Gounty, State)

Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations husber of Type Number of Meana plean Meana non-routine (Units) Analyses LLD Range Location Range Range Results Air Particulates Gross Beta 182b 0.01 0.018 (120/130) L-09. Grand Ridge 0.020 (12/131 0.018 (45/52) 0 (pC1/m3) (0.010-0.031) 10.4 mi 9 260* (0.010-0.049) (0.011-0.053)

L-14. Ottawa 0.020 (12/13) (LLD 0 12.0 mi 9 315* 10.010-0.053)

Gasma Spec. 14 0.01 <LLD <LLD 0 Sr-89 ' 14 0.01 <LLD - - (LLD 0 Sr-90 14 0.01 (LLD - - <LLD 0 Airborne lodine 1-131 98 0.10 (LLD - - <LLD 0 l

(pCf/m3) l Ganma Background Gamma Dose ' 14 3.0 15.8 (10/10) L-05, On-site # 5 16.9 (1/1) 14.2 (4/4) 0 (TLDs) (mR/Qtr.) (14.5-16.9) 0.3 mi 9 145* -

(13.2-16.3)

Milk 1-131 12 5.0 <LLD - - <LLD 0 (PCi/1) Gamma Spec. 12-Cs-134 10 (LLD - - <LLD 0 CD Cs-137 10 <LLD - - (LLD 0 Other gammas 20 <LLD - - <LLD 0 Sr-89 12 10 <LLD - - <LLD 0 Sr-90 12 2 2.4 (1/6) L-15, Johnson Dairy 2.4 (1/6) (LLD 0

- 7.8 mi 9 258* -

Precipitation Gross Beta 12 13.4 15.1 (2/6) L-18 Sunnytsle 30.3 (1/3) 27.2 (2/6) 0 (14.7-15.4) Farm -

(24.1 30.3) 8.8 ari 9 220*

Ganma Spec. 4 20 <LLD - - <LLD 0 Tritium 4 200 <LLD - - <LLD 0 Sr-89 4 10 <LLD - - <LLD 0 Sr-90 4 2 <LLD - - <LLD 0 Cooling Water Gross Beta 24 2.0 4.0 (12/12) L-26, LSCS Dis- 6.3 (12/12) 6.3 (12/12) 0 (pCf/1) (2.8-6.5) charge Pipe - (4.5-8.0) (4.5-8.0)

River at Station Gasma Spec. 6 Cs-134 10 <tLD - - .<LLD 0 Cs-137 10 <LLD - - <LLD 0 Other gannas 20 <LLD - - <LLD 0 Tritium 6 200 <LLD - - <LLD 0 Sr-89 6 10 (LLD - - <LLD 0 Sr-90 6 2 <LLD - - <tLD 0

7 . --

I !

. 1 l7 p

j' I , /

I 5 1 )$

E Table 5.0-2 (continued) . i Environmental Radiological Monitoribg Program Quarterly Sununary g

.4 kame of Facility LaSalle Nuclear Power Statiion Reporting Period 1st Ouarter 1983

.l Indicator Location with Highest Control.

I Sample Type and Locations Quarterly Mean Locations Number of

) l

. ' (Units) Type humber of Analyses LLD Meana Range Location

.Mean Range Meana Range non-routine' Results surface Water Gross Beta 72 2.0 4.3 (60/60) L-24, Recreational 5.6 (12/12) 5.6 (12/12) 0

. (pCl/1) (2.5-7.3) Area Cooling Lake (3.9-6.2)- - (3.4 8.8)~'

0.3 mi 9 112*

\ ,. .

L-21 Illinois 5.6 (12/12) y, " 9 River at Seneca (3.4-8.8) g *q' 4.0 mi 9 22*

Gamma Spec. 18 m 3

- Cs-134 10 <tLD - - <LLD 0

, Cs-137 10 <LLD - - <LLD 0 Other gansnas 20 (LLD - - <LLD 0 Tritium 6 200 <LLD - - <tLD 0 Sr-89 6 10 <LLD - -

<LLD 0 Sr-90 6 2 <LLD - - <tLD 0

.u '

2 to Well Wat A Gross Eeta 8 5.6 20.6 (7/7) L-27, Onsite Well 24.2 (3/3) 18.1 (1/1) 0 (pC1/1 ) (11.8-27.4) , at Station - -

. Gamma Spec. 6 ?. I 6 1

),

ts-134 <LLD O 10 ((. <LLD- - -

t

, . Cs-137 '10 <LLD - - <tLD 0

.f ' ,' t Other gansnas 20 (LLD - - <LLD ' O 3

/ ? Tritium 6 200 , <LLD - - <tLD 0 l

Sr-89 6 10 - - <tLD 0 3

(<LLD Sr-90 6 2 (LLD - - (LLD 0 Cattlefeed & Grass Gross Beta 11 1.0 9.7 (5/5) L-17 Norsen Dairy 12.2 (3/3) 10.9 (6/6) 0

. (pC1/g wet) (4.4-17.4) 9.0 mi 9 337' (3.1-28.0) (2.5-28.0)

Gamma Spec. 11 Cs-134 0.1 <LLD - - <tLD 0 Cs-137 0.1 (LLD - - <tLD 0 Other genunas 0.2 (LLD - - <LLD 0 Sr-89 11 1.0 <tLD - - <LLD 0 Sr-90 11 1.0 <LLD - - <LLD 0

Mean and range based on detectable measurements only. Fractiott indicated in parenthesis.

One (1) higher LLD value due to a low volume caused by an electrical malfunction was excluded from determination of LLD.

__ q Table 5.0-3 Environmental Radiological Monitoring Program Quarterly Saamary Name of facility' LaSalle Nuclear Power Station Docket No. 50-254, 50-265 '

Location of facility _ tiarseilles, Illinois Reporting Period 2nd Quarter 1983 (County. State)

Indicator Location with Highest Control Sample Type and Locations ' Ouarterly Mean Locations kuuber of Type

Nunter of Meana Mean Meana noa-routine (Units) Analyses LLD Range location Range Range Results Air Particulates Gross Beta 182 0.01- 0.015 (105/1301 L-13. Rt. 6 at 0.017 (12/13) 0.014 (40/521 0 (pC1/m3) (0.010-0.034) Gonnam Rd. (0.010-0.034) (0.010-0.0231 4.3 mi 9 100*

. Gasuna Spec. 14 0.01 <LLD - - <LLD 0-Sr-89 14 0.01 <LLD - - <tLD 0 Sr-90 14 0.01 (LLD - . <LLD 0 ,

Airborne lodine 1 131 84 0.10 <LLD - - <LL9 0.

(pC1/m3)

Gaeuna Background Gamma Dose 14 3.0 12.5 (10/10) L-05, Onsite #5 16.9 (1/1) 12.0 (4/4) 0 (TLDs) (mR/Qtr.) (11.8-13.8) 0.3 at 9 145' - (11.6-12.7)

Milk 1-131 36 5.0/0.5* <LLD - - <LLD 0-(pC1/1) Gama Spec. 12

$ Cs-134 10 <LLD - - <LLD 0 Cs-137 10 <LLD - - <LLD 0 Other gansnas 20 <tLD - - <LLD 0 Sr-89 12 10 <LLD - - <LLD 0 Sr-90 12 2 (LLD <LLD 0 Precipitation Gross Beta 12 12.4 43.6 (2/5) L-16, Lowery Dairy 47.8 (1/3) 12.9 (1/6) 0

.(39.6-47.8) 7.2 mi e 120* - -

Gesuna Spec. 4 20 <LLD - - <tLD 0 Tritium 4 200 (LLD - - (LLD 0 Sr-89 4 10 <LLD - - (LLD 0 Sr-90 4 2 (LLD - - <LLD 0 Cooling Water Gross Beta 26 1.0 3.6 (13/13) L-26 LSCS Dis- 4.2 (13/13) 4.2 (13/13) 0 (pC1/1) (2.2-5.4) charge Pipe - (1.9-7.0) (1.9-7.0)

River at Station Gaauna Spec. 6 Cs-134 10 (LLD - - <tLD 0 Cs-134 10 (LLD - - <tLD 0 Other gasunas 20 (LLD - - <tLD 0 Tritium 6 200 <tLD - - <LLD 0 Sr-29 6 10 (LLD - - <tLD 0 Sr-90 6 2 (LLD - - <LLD 0

" April. LLD = b.U pf.1/1; May-June. LLD a U.5 pf.1/4.

Tabla 5.0-3' (continued) ,

Environmental Radiological Monitoring Program Quarterly Summary Name of Facility LaSalle Nuclear Power Station - Reporting Period 2nd Ouarter 1983 Indicator- Location with Highest Control Sample Type and Locations Quarterly Mean -Locations Number of Type. Number of Meana. Mean Meana non-routine

- lunits)

Analyse 3 'LLD' Range Location' Range Range- Results

Surface Water Gross Beta' 78 2.0 - 4.0 (65/65) L-21. Illinois 4.3 (13/13) 4.3 (13/13) 0 (pC1/1) (2.2-8.9) River at Seneca (2.7-8.3) (2.7-8.3) 4.0 mi 9 22'

' Gaimna Spec. '18 L-22,' South Kick- 4.3 (13/13)

, apoo Creek (2.4-8.7)'

4.7 mi.9 330' Cs-134 10 <LLD - - <LLD 0 Cs-137. 10 <LLD - - <LLD 0 Other gammas 20 (LLD - - . <LLD 0:

Tritium 6 -. -200 (LLD - <LLD 0-Sr 6 10 (LLD - - <tLD 0 Sr-90 6 2 <LLD : - - <LLD 0 Well Water Gross Beta -B' 5.0 19.0 (7/7) L-32. Ill. State - 25.5 (1/1) 18.3 (1/1) 0 (pC1/1) (11.8-25.5) Park Well - -

... 6.5 mi 9 326' -

~

Gaimna Spec. 6 Cs-134 - 10 '<LLD - - (LLD 0

- Cs-137 10 ;<LLD - - <LLD 0 Other gammas 20 <LLD - - <LLD 0 Tritium ' 6' 200 <LLD - - <LLD 0 j ,

s Sr-89 6 10 (LLD - - <LLD' O Sr-90 6 2 <t.LD - - <LLD 0 Fish -~ Gross Beta 10 ' 2.0 3.1-(10/10)' L-24. Recreational 3.5 (5/5) None 0 Area, Cooling 2.5-4.3)

(pC1/g wet) (2.4-4.3)

Lake 0.3 mi 9 112*

' Gausna Spec. 10 Cs-134 0.1 <tLD - - None O Cs-137 0.1 (LLD - - None 0

.Other gammas. 0.2 (LLD - - None 0

. Sr-89 10 0.1 <LLD - - None O Sr-90 10 -- 0.1 <LLD - - None 0

-~

e- - .

Tab 12 5.0-3 (continued)

Environmental Radiological Monitoring Program Quarterly suussary 1Namie of Facility LaSalle Nuclear Power Station Reporting Period 2nd Quarter 1983 Indicator Location with Highest Control i Sample ~ Type and Locations. Quarterly Mean Locations Number of 1

- Type - Number of Meana Mean Meana non-routinel (Units)~ Analyses LLD~ Range Location Range Range Results !

Cattlefeed & Grass Gross Beta 4 2.0 6.2 (2/2) L-17, Norsen Dairy 10.6 (1/1) 8.3 (2/2) -0 (pC1/g wet) (5.6-6.9) 9.0 at 9 337' -

(6.0-10.6)

Gausna Spec. 4' Cs-134 0.1 <LLD - - (LLD 0 Cs-137 0.1 <LLD -- -

<LLD 0 Other gasunas 0.2. <LLD - - <LLD 0 Sr-89 4 1.0 <LLD - - <LLD 0-Sr-90 4 1.0 <LLD - - <LLD 0 ,

{ Aquatic Vegetation Gross Beta 3 1.0 3.8 (2/2) L-24, Cooling Pond 3.9 (1/1) 3.7 (1/1) 0 (pC1/g wet) . (3.7-3.9) 0.3 mi 9 112' - -

r. - Spec. 3 Cs-134 0.1 <LLD - -

<LLD 0 Cs-137 0.1 <LLD - -

(LLD 0 a Other gasunas 0.2 <LLD - - <LLD 0 ro Bottom Sediments Gross Beta. 3 10 27.8 (2/2) L-34, Downstream 30.5 (1/1) 23.1 (1/1) 0 (pC1/g dry) (25.1-30.5) of cooling lake - -

4.8 mi 9 350' Gamuna spec. 3 Cs-134 0.1 <LLD - -

(LLD 0 Cs-137 0.1 (LLD - - <LLD 0 Other gasunas 0.2 (LLD - -

<LLD 0 a

Mean and range based on detectable measurements only. Fractions indicated in parenthesis.

m- -

Table 5.0-4 Environmental Radiological Monitoring Program Quarterly Sumary Name of facility LaSalle Nuclear Power Station Docket No. 50-254, 50-265 Location of facility Marseilles, Illinois Reporting Period 3rd Quarter 1983 Kounty, State) i Indicator Location with Highest Control l Sample Type and ' Locations Quarterly Mean Locations hunter of '

Type Number of Mean8 Mean Means non-routine' (Units) Analyses LLD Range Location Range Range Results Air Partjculates Gross Beta 182 0.01 0.024 (129/130) L-12 Kernan 0.028 (10/131 0.026 (52/52) 0 (pC1/M) (0.010-0.046) 9.0 mi 9 214' (0.015-0.051) (0.010-0.055) ,

s Gama Spec. 14 0.01 <tLD - - , <LLD 0 -

Sr-89 14 0.01 <LLD - - 4LD ;

O Sr-90 14 0.01 <LLD - - (LLD 0 !

I-131 0.10 - <LLD , 0 Airborne lodine 84 <LLD -

(pC1/m3) .

Gama Background Gamma Dose 14 3.0 16.3 (10/10) L-07, Seneca #7 .19.7 (1/1) - 0 l (13.6-19.7) 5.2 mi 918* - 14.3 (4/4) l; j (12.7-16.8)

(TLDs) (mR/Otr.) l 0.5 <LLD 8 - <LLD O Milk I-131 52 -

l (pC1/1)

Gamma Spec. 12 l {

" Cs-134 10 (LLD - - l (LLD 0 0

Cs-137 10 <LLD - - <LLD Other gamas 20 4LD - - <tLD 0 Sr-89 12 10 (LLD - - <LLD 0 Sr-90 12 2 <tLD L-17, Norsen Dairy 2.2 (1/6) 2.2 (3/6) 0 9.0 mi 9 337' - (2.1-2.2)

Gross Beta 11 27.3 (4/6) L-15, Johnson Dairy 29.9 (3/3) 17.6 (3/6) 0 Precipitation 12.6 (pC1/1) (19.6-41.2) 7.8 mi 9 258' (21.0-41.2) -

Gama Spec.. 4 20 (LLD - - <LLD 0 Tritium 4 200 <LLD - - <tLD 0 Sr-89 4 10 (LLD - - 4LD D 4 <LLD - 4LD 0 Sr-90 2 -

1.0' 7.3 (13/13)~ L-26, LCSC Dis- 7.5 (13/13) 3.5 (13/13) 0 Cooling Water Gross Be'ta 26 (pC1/1) (4.4-10,5) charge Pipe -: ,(4.4-10,5) (2.0-5.4)

River at Station Gama Spec 6 10 <LLD - - <LLD 0 i Cs-134

<tLD - - <LLD 0 Cs-137 10

<tLD - 4LD 0 Other games 20 -

- 4LD 0 Tritium 6 200 (LLD -

<LLD - ALD 0 Sr-89 6 10 -

(LLD - <LLD 0

$r-90 6 2 -

i

Table 5.0-4 (continued)

Environmental Radiological Monitoring Program Quarterly Summary Name of Facility LaSalle Nuclear Power Station Reporting Period 3rd Quarter 1983 Indicator Location with Highest Control

. Sample Type and Locations Quarterly Mean Locations Number of Type Number of l Meana Mean Meana non-routine (Units) Analyses 'LLD Range Location Range Range Results Surface Water Gross Beta 78 1.0 4.7 (65/65) L-24. Recreational 5.2 (13/13) 4.9 (13/13) 0 (pC1/1) (2.6-9.7) Area Cooling Lake (4.3-6.2) (3.5-6.4 )

0.3 mi 9 112*

Gamma Spec. 18 Cs-134 10 (LLD - - <tLD 0 Cs-137 10 <LLD - - <LLD 0 Other gammas 20 <LLD - - <LLD 0 Tritium 6 200 (LLD - - <LLD 0 Sr-89 6 10 (LLD - - (LLD 0 Sr-90 6 2 <tLD - - <tLD &

a Well Water Gross Beta 8 1.0 19.4 (7/7) L-30, 111. Ransom 27.3 (1/1) 15.6 (1/1) 0 A (pC1/1) (12.7-27.3) Well - -

6.0 mi 9 191*

Gasma Spec. 6 Cs-134 10 <LLD - -

<LLD 0 Cs-137 10 <tLD - -

<LLD 0 Other gannas 20 <tLD - - <LLD 0 Tritium 6 200 <LLD - -

<tLD 0 Sr-89 6 10 (LLD - - <LLD 0 Sr-90 6 2 <LLD - - <LLD 0 Fish Gross Beta 10 1.0 3.3 (10/10) L-35, Marseilles 3.3 (6/6) None 0 (pCi/g wet) (2.8-3.6) Pool - Illinois (2.8-3.6)

River 6.5 mi 9 326' Gasma Spec. 10 Cs-134 0.1 (LLD - - None O Cs-137 0.1 <LLD - -

None 0 Other gaspas 0.2 (LLD - - None O Sr-89 10 0.1 <LLD - -

None 0 Sr-90 10 0.1 <LLD - - None 0

r-Tabla 5.0-4 (continued)

Environmental Radiological Monitoring Program Quarterly Sumary Name of Facility LaSalle Nuclear Power Station Report 1=tg Period 3rd Quarter 1983 Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Number of Type Number of Meana Mean Means non-routine (Units) Analyses LLD Range Location Range Range Results Cattlefeed & Grass Gross Beta 4 1.0 7.4 (2/2) L-15, Johnson Dairy 7.9 (1/1) 7.4 (2/2) 0 (pC1/g wet) (6.9-7.9) 7.8 mi 9 258' - (7.4-7.5)

Gamma Spec. 4 Cs-134 0.1 (LLD - - (LLD 0 Cs-137 0.1 <LLD - - <LLD 0 Other gamas 0.2 <LLD - - <LLD .O Sr-89 4 1.0 <LLD - - (LLD 0 Sr-90 4 1.0 (LLD - - <LLD 0 Aquatic Vegetation Gross Beta 3 1.0 1.5 (2/2) L-24, Cooling Pond 1.8 (1/1) 1.0 (1/1) 0 (pci/g wet) (1.2-1.8) 0.3 mi 9 112' - -

Gama Spec. 3 Cs-134 0.1 (LLD - - (LLD 0 0.1 -(LLD - - <LLD 0 Cs-137 Other ga m as 0.2 (LLD - - <LLD 0 a

v1 Bottom Sediments Gross Beta 3 1.0 iS.6 (2/2) L-34. Downstream 30.4 (1/1) 27.4 (1/1) 0 (pC1/g dry) (22.8-30.4) of Cooling Lake - -

4.8 mi 9 350' Gama Spec. 3 0.1 <tLD - - (LLD 0 Cs-134 0.1 <LLD - - <LLD 0 Cs-137 Other gam as 0.2 <LLD - - <LLD 0 2.5 (11/11) L-36, Farm A 2.9 (5/5) None 0 Vegetables Gross Beta 11 1.0 (pC1/g wet) (1.5-5.0) (1.6-5.0)

Gasuia Spec. 12 0.1 (LLD - - None O Cs-134 0.1 (LLD - - None 0 Cs-137 0.2 (LLD - None O Other Games -

None O Sr-89 11 1.0 <LLD - -

1.0 <LLD - None 0 Sr-90 11 -

<tLD None 0 I-131 1 0.019 - -

tractions inaicarea in paren6nca 3.

8 Mean and range based on detectable measurements only.

Tabla 5.0-5 Environmental Radiological Monitoring Program Quarterly Sumary Name of facility LaSalle Nuclear Power Station Docket No. 50-254, 50-265 Location of facility Marseilles, Illinois Reporting Period 4th Quarter 1983 (County, 5 tate)

. Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Number cf Type Number of Meant Mean Meana non-routine (Units) Analyses LLD Range Location Range Range Results Air Particulates Gross Beta 176 0.01 0.026 (124/1241 L-09, Grand Ridge 0.030 (13/13) 0.029 (52/52] O (pC1/m3) (0.012-0.053) 10.4 mi 9 260' (0.013-0.058) (0.012-0.0751 Gama Spec. 14 0.01 <LLD - - <LLD 0 Sr-89 14 0.01 <LLD' - - <LLD 0 Sr-90 14 0.01 <LLD - - <tLD 0 Airborne lodine 1-131 162 0.10 <tLD - -

<tLD 0 (pC1/m3)

Gamma Background Gama Dose 14 3.0 16.2 (10/10) L-05, Onsite #5 17.3 (1/1) 15.3 (4/4) 0 (TLDs) (mR/Qtr.) (13.8-17.3) 0.3 mi 9 145* - (13.9-16.2)

Milk I-131 28 0.5 <tLD - - <LLD 0

-(pC1/1) Gama Spec. 12 Cs-134 10 <LLD - - <LLD 0

'$ Cs-137 - 10 (LLD - - <LLD 0 Other gammas 20 <LLD - - <LLD 0 Sr-89 12 10 (LLD - - <tLD 0 Sr-90 12 2 2.9 (1/1) L-15 Johnson 2.9 (1/1) (LLD 0

- Dairy -

7.8 mi 9 258' Precipitation Gross Beta 12 12.1 16.8 (1/6) L-18, Sunnyisle 20.2 (1/3) 18.5 (2/6) 0

- 8.8 mi 9 220' - (16.8-20.2)

Gama Spec. 4 20 <LLD - - <LLD 0 Tritium - 4 200 <LLD - - <LLD 0 Sr-89 4 10 <LLD - - <LLD 0 $

Sr-90 4 2 <LLD - - <LLD 0 Cooling Water Gross Beta 28 1.0 8.9 (14/14) L-26, LSCS Dis- 8.9 (14/14) 6.1 (14/14) 0 (pC1/l) (5.5-19.4) charge Pipe - (5.5-19.4) (2.7-17.0)

River at Station Gamma Spec. 6 Cs-134 10 <LLD - - <LLD 0 Cs-134 10 <LLD - - <tLD 0 Other gammas 20 <LLD - - (LLD 0 Tritium ,6 200 (LLD - - <tLD 0 I (LLD 0 Sr-89 6 10 (LLD- -

Sr-90 6 2 (LLD - - <LLD 0

Table 5.0-5'(continued) l Environmental Radiological Monitoring Program Quarterly Summary Name of Facility ' LaSalle Nuclear Power Station Reporting Period 4th Quarter 1983 Indicator Location with Highest Control Sample Type and Locations Quarterly Mean Locations Numeer of Type Nuater of Meana Mean Meana non-routine; (Units) Analyses LLD _ ' Range Location Range Range- Results Surface Water Gross Beta ' 84 1.0 4.7 (70/70)' L-19 Illinois 4.3 (13/13) 5.1 (14/14) 0

-(pC1/1) -(2.1-8.1) River at Mar- (2.7-8.3) (4.0-6.6) seilles 6.5 mi 9 326*

Gamma Spec. 18 '

.Cs-134 '10 <LLD - -

<LLD 0

-Cs-137 10 <LLO - - <LLD 0 Other games 20 <LLD - - (LLD :0 Tritium. 6 200 <LLD - -

<LLD 0 Sr-89 6 10 ' <LLD - - <LLD 0 Sr-90 6 2 <LLD - - (LLO O Well Water Gross Beta 8 5.0 19.0 (7/7) L-30 Ransom Well 27.9 (1/1) 23.9-(1/1) b (pC1/1) (12.3-27.9) 6.0 mi 9 191* - -

$' . Gamma Spec. 6~

Cs-134 10 <tLD - - <LLD 0 Cs-137 10 <LLD - - <LLD .0 Other gammas. 20 <tLD - - <LLD 0 Tritium 6 200 (LI D - - <LLD 0 Sr-89 6~ '10 (LLD - - <LLD 0 Sr-90 6 2 <tLD - - (LLD 0 Fish Gross Beta 9 2.0 28.3 (10/10) L-24, Recreational 3.0 (5/5) None 0 (pC1/g wet) - (2.0-3.6) Area, Cooling (2.0-3.6)

Lake 0.3 at 9 112' Gasma Spec. '9 Cs-134 0.1 <LLD - - None O Cs-137 0.1 <LLD - - None 0 Other gammes 0.2 <LLD - - None O Sr-89 '10 0.1 <LLD - - None O Sr-90 10 0.1 (LLD g

- - None .0

-. - . . .n

y Table' 5.0-5 (continued)

Environmental Radiological' Monitoring Program Quarterly Susumary .

Name of Facility LaSalle Nuclear Power Station Reporting Period 4th Quarter 1983 Indicator Location with Highest Control Sample Type and Locations- --Quarterly Mean Locations Nua6er of Type ~ Number of- . -Meana Mean Meana . non-routine (Units) . Analyses' LLD Range Location' Range Range- Results Cattlefeed & Grass Gross Beta 4 1.0 8.2 (2/2) L-16 Lowery Dairy 8.3 (1/1) 5.6 (2/2)- 0

.(pC1/g wet) (8.0-8.3) -7.2 mi 9 160* -

.(3.1-8.1)

Gasuna Spec. 4 Cs-134 0.1 (LLD 1- -

<LLD - 0

, Cs-137 - 0.1 <LLD - - <LLD - 0 Other gasunas 0.2 .. <LLD - - <LLD 0 Sr-89 4 1.0 <LLD - -

<LLD 0l Sr-90 4 1.0 <LLD - - <LLD 0 Aquatic Vegetation Gross Beta 3 1.0 3.2 (2/2) L-33, Upstream of 4.9 (1/1) 4.9 (1/1) 0

-(pCi/g wet) (1.9-4.5) Cooling Lake .- --

4.7 mi.9 354' Gansna Spec. 3

-Cs-134 0.1 (LLD - - '<LLD O' Cs-137 0.1 (LLD - - <LLD' 0

- 4 oo Other gammas 0.2 . <LLD - -

<tLD 0 Bottom Sediments Gross Beta- 3' 1.0 32.6-(2/2) L-34, Downstream 35.1 (1/1) 31.3 (1/1) 0

. (pC1/g dry) (30.2-35.1) of cooling lake - -

4.8 mi 9 350*

Gaauna Spec. 3-Cs-134 0.1 (LLD - - (LLD 0 Cs-137 0.1 <LLD - - <LLD 0 Other gansnas - 0.2 <LLD - - <LLD 0 a

Mean and range based on detectable measurements only. Fractions indicated in parenthesis.

4 6

%=%

LASALLE.

Table 5.1-1 Gamma Radiation, as measured by Thermoluminescent Dosimeters (TLDs)

Standard Radiological Monitoring Program 1st Quarter 2nd Ouarter 3rd Quarter 4th Quarter Date Placed: 12-31-82 4-02-83 7-01-83 10-01-83 Date Removed: 4-02-83 7-01-83 10-01-83 12-31-83 Days in the Field: 92 90 91 91 Location Average mR/Qtr.

On-Site and Near-Site Indicator Locations L-01 Near Site'No. 1 16.4il.2 13.210.3 16.410.5 16.610.9 L-02 On-Site No. 2 16.0il.1 11.811.0 16.0i2.5 16.9i0.7 L-03 On-Site No. 3 15.6fl.3 12.710.6 17.0i2.1 15.810.6 L-04 Near-Site No. 4 14.810.9 12.3i0.6 17.3i0.6 16.3tl.1 L-05 On-Site No. 5 16.9tl.2 13.810.8 15.6tl.0 17.3i0.6 L-06 Near-Site No. 6 15.5i0.8 13.li0.7 16.211.8 15.9i2.3 Mean i s.d. 15.910.7 12.8i0.7 16.410.6 16.510.6 Off-Site Indicator Locations L-07 Seneca 16.8i2.6 11.8tl.7 19.711.6 17.0f0.6 L-08 Marseilles 16.410.9 12.4i0.8 16.4i0.8 16.812.3 L-11 Ransom 14.5i0.8 11.7i0.7 13.6i0.7- 13.812.3 L-13 Rt. 6/Gonnam Road 14.911.1 12.610.7 14.6i0.8' 15.6tl.0 <

Mean i s.d. 15.6tl.1 12.li0.4 16.1*2.7 15.8tl.5 b

Background Locations L-09 Grand Ridge 14.011.4 12.010.8 14.0il.0 16.111.4 L-10 Streator 13.2i2.5 11.6i0.9 12.7i0.7 14.910.6 i L-12 Kernan 13.3i0.8 11.7i0.6 13.610.3 13.910.9 L-14 Ottawa 16.3fl.0 12.7f0.5 16.812.2- 16.2il.0 Mean i s.d. 14.211.4 12.010.5 14.311.8 15.311.1 49

LASALLE Table 5.1-1 (continued)

Gama Radiation, as measured by TL0s (continued)

Special Program Inner Ring, Near Site Boundary, Indicator Locations j

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

! 12-31-82 4-02-83 7-01-83 10-01-83 Date Placed:

Date Removed: 4-02-83 7-01-83 10-01-83 12-31-83 Days in the Field: 92 90 92 91 Location Average mR/Qtr.

L-100-1 16.510.6 13.811.0 16.0i0.4 18.110.6 L-100-2 16.3i0.6 13.9tl.2 16.0i0.7 16.012.0 L-101-1 15.5i0.8 14.5 0.7 15.0i0.7 17.910.5 L-101-2 15.6i1.0 -13.7i0.7 15.5tl.6 15.6tl.4 L-102-1 16.0i0.6 13.lil.5 15.2i0.4 19.411.2 L-102-2 17.2i2.5 14.3i0.4 15.4i0.8 16.4i0.7 L-103-1 15.2i0.9 13.7 0.7 14.910.7 17.810.9 L-103-2 15.7i0.8 13.li0.3 16.0i0.7 15.4tl.7 L-104-1 16.8tl.3 14.0 0.8 16.0i0.6 19.110.8 L-104-2 16.0il.1 13.3i0.6 16.0il.2 19.li0.9 L-105-1 17.9i0.8 15.7tl.5 17.2il.7 18.8i2.6 L-105-2 17.4tl.0 13.5tl.3 15.910.5 18.3i0.5 L-106-l' 17.7i0.7 13.910.7 16.1 0.5 18.611.0 L-106-2 17.9i2.6 14.711.3 16.510.6 19.8tl.1 16.8tl.3 14.4tl.0 17.li2.0 19.2i0.5 L-107-1 L-107-2 18.li2.9 14.7*0.5 16.612.3 19.5tl.2 l

Mean i s.d. 16.7tl.0 14.0f0.7 16.0f0.7 18.lil.4 l

i 50

LASALLE Table 5.1-1 (continued)

Gamma Radiation, as measured by TLDs (continued)

Special Program Outer Ring, Near 5 Miles Radius, Indicator Locations i

ist Quarter 2nd Quarter 3rd Quarter 4th Quarter

\

Date Placed: 12-31-82 4-02-83 7-01-83 10-01-83 Date Removed: 4-02-83 7-01-83 10-01-83 12-31-83 Days in the Field: 92 90 92 91 Location Average mR/Qtr.

L-201-1 17.311.6 13.2il.8 16.410.3 17.110.7 L-201-2 15.510.8 13.2i2.0 16.7t2.6 17.410.7 L-202-1 16.110.6 14.0i0.4 16.210.8 17.li0.9 L-202-2 14.6tl.4 13.4i0.5 15.010.6 17.2il.5 L-203-1 15.911.2 12.3i2.0 16.2tl.0 17.511.3 L-203-2 17.0f0.8 14.3tl.0 15.7i0.2 20.7i2.8 L-204-1 16.410.8 13.6i0.7 16.0il.0 17.213.2 L-204-2 15.910.8 14.0il.0 17.4tl.6 18.510.6 L-205-1 17.010.8 16.2il.6 15.810.6 19.811.1 L-205-2 16.9tl.5 13.910.4 16.4fl.8 16.7i2.4 L-206-1 16.611.3 14.310.5 16.510.8 21.8i2.8 L-206-2 16.310.8 13.210.5 14.910.8 18.610.7 L-207-1 18.lil.4 12.7i0.6 15.111.0 16.812.7 L-207-2 15.8tl.7 14.0il.0 15.410.7 18.711.7 L-208-1 16.8i0.8 14.010.5 16.810.6 19.6tl.8 L-208-2 16.110.9 13.6i0.6 17.210.5 16.li2.3 L-209-1 15.910.7 14.310.6 16.4i0.8 18.7tl.6 L-209-2 19.511.9 13.310.7 15.4i0.8 18.810.6 L-210-1 17.3fl.0 12.6tl.8 17.3i2.3 18.811.3 L-210-2 16.411.2 14.610.5 17.710.7 19.6fl.2 L-211-1 15.210.9 -14.110.7 16.410.3 18.5fl.0 L-211-2 15.710.8 14.7i2.4 15.2i0.8 17.0il.0 L-212-1 17.710.9 14.0i0.6 15.410.5 20.lil.1 L-212-2 17.811.1 13.110.5 15.510.9 17.6fl.1 L-213-1 18.412.8 12.112.0 15.4i0.5 18.610.8 L-213-2 16.810.7 14.2f0.6 15.110.8 17.611.0 L-214-1 17.2il.0 15.2i0.7 16.7i0.5 19.711.5 L-214-2 17.310.8 14.710.5 16.911.3 19.310.8 L-215-1 16.810.8 14.210.9 16.2i0.9 19.810.9 L-215-2 17.8tl.7 -15.3i0.8 17.411.0 18.0i0.9 L-216-1 18.8i3.0 13.110.4 17.912.6 17.211.0 L-216-2 15.310.7 15.210.7 15.210.8 18.910.8 Moon 2 1.d, 16.811.1 13.910.9 16.2i0.9 18.411.3 51

a i

APPENDIX II METEOROLOGICAL DATA 1

I i.

L 52 v - .

LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - JANUARY - MARCH 1983 STABILITY CLASS'- EXTREMELY UNSTABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 0 0 0 0 0 0 0 NNE O O O O O 0 0 NE O O O O O O O ENE O O O O O O O E O O O O 2 0 2 ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O

~ TOTAL 0 0 0 0 2 0 2 HOURS OF CALM IN THIS STABILITY CLASS - 0

' HOURS-OF MISSING WIND MEASUHEMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 22 53

L AS ALLE NUCLF. AR POMER STATION PERIOD OF RECORD - JANUARY - MARCH 1983 STABILITY CLASS - MODERATELY UNSTAHLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN HPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O 1 4 0 5 E OL 0 0 0 0 0 0 ESE O O O O O O O SE O O O O O O O SSE O O 1 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O TOTAL 0 0 1 1 4 0 6 HOURS OF' CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 22 54 L

LASALLE NUC1. EAR POWER STATION PERIOD OF PECORD - JANUAHY - MARCH 1983 STABILITY CLASS - SLIGHTLY UNSTABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIPECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 0 0 1 0 0 0 1 NNE O O O O O O O

. NE O O O 3 1 0 4 ENE O O O 4 0 0 4 E O O O 1 1 0 2 ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 1 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 1 3 4 NNW 0 0 0 0 0 2 2 VARIABLE O O O O O O O TOTAL 0 1 1 8 3 5 18 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND-MEASUREMENTS IN THIS STABILITY CLASS - 1 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 22 b

55

i LASALLE NUCLEAR PODER STATI0h PERIOD OF RECORD -

JANUARY - MARCH 1983 STABILITY CLASS - NEUTRAL (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 1 7 37 28 22 2 97 NNE O 19 22 28 2 0 71 NE 3 7 5 22 6 1 44 ENE O 7 14 24 25 37 107 E 2 11 5 19 27 14 78 ESE O 6 5 9 7 1 28 SE O 8 14 14 3 2 41 SSE 1 9 19 23 4 9 65 S 2 10 25 40 14 6 97 SSW 2 14 10 14 2 12 54 SW 0 13 11 6 2 1 33 WSW 3 11 13 12 9 1 49 W' 2 6 10 31 37 15 101-WNW 0 7 to 50 35 27 129 NW 1 6 22 36 26 10 101 NNW 0 6 11 24 73 23 137 VARIABLE O O O O O O O TOTAL 17 147 233 380 294 161 1232 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 86 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 22 56 I

l LASALLE NUCLEAR PODER STATION PERIOD OF RECORD - JANUARY - MARCH 1983 STABILITY' CLASS - SLIGHILY STABLE (DELTA T 375-33 FT)'

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TUTAL N O 1 3 5 3 0 12 NNE 1 5 10 1 0 0 17 NE O 1 9 7 6 0 23 ENE 1 2 3 11 7 14 38 E 1 1 7 6 2 12 29.

ESE O 1 4 14 10 11 40 SE 1 4 7 14 9 17 52 SSE 1 6 16 21 6 10 60 S 2 4 5 8 18 36 73 SSW 0 7 1 7 13 12 40 SW 1 2 4 6 2 10 25 WSW 0 -2 3 4 1 2 12 W D 3 2 8 3 4 20 WNW 0 5 2 11 9 0 27 NW 1 0 5 12 8 3 29 NNW 1 0 2 4 1 0 8 VARIABLE O O O O O O O TOTAL 10 44 83 139 98 131 505 HOURS OF CALM IN THIS STABILITY CLASS - 0

' HOURS OF MISSING WIND MEASIIREMENTS IN THIS STABILITY CLASS - 26 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 22 57

LASALLE NUCLEAR POWER STATION PERIOD'0F HECORD - JANUAbY - MARCH 1983 STABILITY CLASS - MODERATELY STABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND ' WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL

......... .q... ..... ..... ..... ..... ..... .....

N 0 2 0 0 0 0 2 3

NNE 1 1 1 0 0 0 3 NE 'l 0 0 0 0 0 1 ENE O 0 0 0 0 0 0 E O 1 0 2 1 2 6 ESE 2 1 1 2 0 0 6 SE 1 0 2 1 3 5 12 SSE O 4 1 4 4 2 15 S 0 0 1 3 10 11 25 SSW 1 1 1 4' 10 26 43 SW 0 1 1 0 3 4 9 WSW 1 2 3 2 3 1 12 W 1 1 2 1 4 2 11 WNW 2. 1 1 0 4 0 8 NW 4 0 2 6 0 1 13 NNW 0 0 4 2 0 0 6 VARIABLE O O O O O O O TOTAL 14 15 20 27 42 54 172

' HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY-MEASUREMENTS IN ALL STABILITY CLASSES - 22 58

LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - JANUARY - MARCH 1483 STABILITY CLASS - EXTREMELY STABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE O O O O O O O ENE O 1 0 0 0 0 1 E O O 1 0 0 0 1 ESE O O O O O O O SE O O 3 0 0 5 8 SSE O O 4 4 5 5 18 S 0 0 1 2 4 9 16 SSW 0 0 0 1 7 13 21 SW 0 1 0 0 6 3 10 WSW 0 0 0 1 0 0 1 W' O 2 1 0 0 0 3 WNW 0 0 2 2 2 0 6 NW 0 0 3 0 0 0 3 NNW 0 0 1 0 0 0 1 VARIABLE O O O O O O O TOTAL 1 4 16 10 24 35 90 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF. MISSING WIND MEASUREMEhTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 22' 59

LASALLE NUCLEAP POWER STATION PERIOD OF RECORD - APRIL - JUNE 1983 STABILITY CLASS - EXTREMELY UNSTABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 0 O O O O O O NNE O O O 1 1 0 2 NE O O O O O O O ENE O O O O O O 0 E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O 0 0 TOTAL 0 0 0 1 1 0 2

-HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 25 l

l 60

1.ASALLE NUCLEAR POWER STATION PERIOD OF RECORD - APRIL - JUNE 1983 STABILITY CLASS - MODERATELY UNSTABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 0 O O 0 4 0 4 NNE O O 3 6 1 0 10 NE O O 1 2 0 1 4 ENE O O O O O O O E O O O O O O O ESE O O O O O O O

-SE O O O O O O O SSE O O O O O 0 0 S 0 0 0 0 3 2 5 SSW 0 0 0 6 5 2 13 SW 0 0 0 1 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 2 0 2 VARIABLE O O O O O O O TOTAL 0 0 4 15 15 5 39 HOURS OF C ALM - IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 25 61

LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - APRIL - JUNE 1983 STABILITY CLASS - SLIGHTLY UNSTABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET

-WIND WIND SPEED (IN MPH)

. DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N O O 1 3 6 1 11 NNE O O 2 7 2 0 11 NE O O 4 6 1 1 12 ENE O O 5 1 2 0 8 E O O 4 3 0 0 7 ESE O O O O O O O SE O O O 1 0 0 1 SSE O O O O O O O S 0 0 0 5 5 2 12 SSW 0 0 2 4 4 1 11 SW 0 0 3 7 0 0 10 WSW 0 0 0 1 0 0 i W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 4 4 NW 0 0 0 0 0 0 0 NNW 0 0 0 1 2 1 4 VARIABLE. 0 0 0 0 0 0 0 TOTAL 0 0 21 39 22 10 92 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WINO MEASUREMENTS IN THIS STABILITY CLASS - 0

' HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES.- 25 62

LASALLE NUCLEAR POWER STATION PERIOD OF RECURD - APRIL - JullE 1983 STABILITY CLASS - NE11 TRAL (DELTA T 375-33 FT)

WINDS MEASilRED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 R-12 13-18 19-24 GT 24 TOTAL N 2 19 15 15 23 20 94 NNE 2 11 17 8 9 1 40 NE O 21 25 32 16 8 102 ENE 3 25 17 37 23 19 124 E 2 10 22 14 21 24 93 ESE 0. 11 28 17 12 3 71 SE 1 7 22 23 2 9 64 SSE 1 2 8 17 5 10 43 S 2 5 15 14 18 8 62 SSW 0 5 4 14 13 16 52 SW i 4 12 16 8 10 51 WSW 1 3 13 13 12 30 72 W 0 11 9 20 30 12 82 WNW 0 12 20 43 24 12 111 NW 0 1 16 33 8 11 69 l

NNW 1 13 16 24 13 1 68 VARIABLE 0 0 0 0 0 0 0 TOTAL 16 160' 259 340 237 194 1206

HOURS OF CALM IN THIS STABILITY CLASS - 0 H0llRS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 9 l

HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 25 l

l 63

LASALLE NUCLEAR' POWER STATION PERIOD OF RECORD - APRIL - JUNE 1983 STABILITY Cf. ASS - MODERATELY STAHLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N O 1 2 1 0 0 4 NNE 1 1 0 0 0 0 2 NE 2 0 0 1 0 0 3 ENE O O 1 2 0 0 3

.E O O O 1 4 3 8 ESE O 2 1 5 1 3 12 SE O 1 1 9 9 9 29 SSE O O 1 8 10 1 20 S 1 0 2 4 5 9 21 SSW 1 0 1 4 5 16 27 SW 1 1 2 5 2 15 26 WSW 0 2 3 4 9 4 22 W 0 2 6 3 4 8 23 WNW 0 0 3 5 1 1 10 NW 0 0 3 8 6 0 17 NNW 0 0 0 2 0 2 4 VARIABLE O O O O O 0 0 TOTAL 6 10 26 62 56 71 231 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF-MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 25 65

LASALLE NUCLEAR PODER STATION PEPIOD OF HECORD - APRIL - JUNE 1983 STABILITY CLASS - SLIGHTLY STABLE (DELIA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 2 5 4 4 2 0 17 NNE- 1 3 3 4 0 0 11 5 NE 3 4 8 6 0 1 22 ENE 1 3 7 10 4 0 25 E 1 0 0 21 12 11 53 ESE O 4 7 16 13 9 49 SE 1 3 6 13 21 11 55 SSE 1 3 5 12 9 9 39 5 0 3 2 7 10 14 36 SSW 1 2 3 11 13 21 51 SW 0 2 6 6 3 6 23 WSW 2 1 2 5 6 4 20 W 0 3 7 11 12 10 43 WNW 0 3 1 2 10 3 19 NW 5 2 5 5 9 1 27 NNW 0 0 2 4 4 0 10 VARIABLE O O O O O O O TOTAL 18 41 76 137 128 100 500 HOURS OF' CALM IN THIS STABILITY CLASS - 0-HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - lb H0llRS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 25 64

LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - APRIL - JUNE 1983 STABILITY CLASS - EXTREMELY STABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O 1 1 0 0 2 SSE O O 1 2 4 3 10 S 0 0 1 1 2 8 12 SSW 0 0 3 0 5 5 13 SW 0 2 1 2 1 0 6 WSW 0 1 0 2 0 2 5 W 0 0 0 4 2 4 10 WNW 0 0 0 1 0 3 4 NW 0 1 0 0 0 1 2 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O TOTAL 0 4 7 13 14 26 b4 HOURS 1DF CALM ~IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING' STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 25 66

~

r / .

.+

f, ', .

.J f '- *

._LASALLE NUChi.AF pot $EP STATION

~

J' PERIOD OF RECORD dilly - SEPTEMBER 1983

'... STAB'ILITY CLASS - EXTREMELY;ilNSTABLE (DELTA T 375-33 FT)

- ,W.'iNDS MEASUPED AT 375 FEET WIND _ WIND SPEED'(IN MPH)

DIRECTION .7-3 4- 7 8-12r 13- 1 fl 19-24 GT 24 TOTAL

- /

N O O .0 0 0 0 0 NNE O O /1 0 0 0 1 O O O O O O O NE O O O O O O O ENE

'E ,- 0- 0 0 0 0 0 0 ESE / 0 0 0 0- 0 0 0 U

SE j ,e

'a 0 0 0* ,

0 0 0 0 SSE- e 0 0 'o , ,

0 0 0 0 i /

0 s O' O O O S ,0 $< 6

- 0 0 0'. 0 0 0 0 SSW *

! ., 1; SW f, 0 0 0 0 0 0 0

-- ,1 f,

WSW - 0 0 0 'O O O 0 p.

W 0 0 , 0 / 0 0 0 0

,}

r. ,-

} l, ^

[ , ' WNW

,. J ' ' !.

0 0 0 O O O O

,,,p'NW "

, ,, 0 0 0' e i0 0 0 0-NNW i 'I 0 0 0 0 0 0 0 f

VARIABLE o 0 0 0' O O O

, r F g Y_

J

TOTAL 0 O y 1 0 0 0 1

., I f , ' et . !/

o

_i J H0llRS OF C ALM IN THIS STABILITY iCLA'SS -/l 0 HOURS OF HISSING WIND MEASUREMEdfS IN TH3S STABILITY CLASS - 0

,.,.=,

H0llRS OF.MISSINU' STABILITY,,s MEASUREMENTS IN ALL STABILITY CLASSES - 117 4 i Y

~

/ ,j , .;

f f

,./

0 67 4 e

LASALLE NUCLEAR PotER STATION PERIOD OF RECORD - JULY - SEPTEMBER 1983 STABILITY CLASS - MODERATELY UNSTABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12' 13-18 19-24 GT 24 TOTAL N 0 0 0 5 0 0 5 NNE. 0 0 7 2 0 0 9 NE O 1 4 0 0 0 5

~

.ENE O O 3 3 0 0' 6 E 0 0 0 0 0 0 0 ESE O O O O O O O SE O O O O O O O SSE O O O O O O O

-S 0 2 1 1 0 0 4 SSW 0 1 1 6 2 1 11 SW -0 0 2 10 3 0 15 WSW 'O O O 2 0 0 2 W 0 0 0 0 1 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 NARIABLE O O O O O O O TOTAL 0 4 18 29 6 1 58 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 i HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 117 68

LASALLE NUCLEAR PODER STATION PERIOD OF RECORD - JULY - SEPTEMHER 1983 STABILTTY Cl. ASS - SLIGHTLY UNSTAHl.E (DELTA T 375-33 FT)

WINDS MEASURED AT 375-FEET WIND f WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 1 2 6 0 0 0 9 NNE O 4 10 3 0 0 17 W, 0 9 2 1 0 0 12 ENE O 1 4 0 0 0 5 E O O O 2 0 0 2 ESE O O 2 0 0 0 2 SE O 2 4 0 0 0 6 SSE O 3 1 0 0 0 4 5 0 3 6 2 1 0 12 SSW 0 4 4 4 2 0 14 SW 0 1 6 7 0 1 15 WSW 1 0 8 6 5 0 20 W 0 0 1 3 4 0 8 WNW 1 0 0 0 0 0 1

< NW 0 0 0 1 0 0 1 NNW 0 1 2 0 1 0- 4 I O O O O O VARIABLE O O l

i TOTAL 3 30 56 29 13 1 132 I

HOURS OF-CALM IN THIS STABILITY CLASS - 0 4

HOURS OF MISSING WIND MEASUHEMENTS IN THIS STABILITY CLASS -

HOURS OF MISSING STABILITY MEASUaEMENTS IN ALL STABILITY CLASSES - 117 L

69

LASAbi,E NUCLEAR P0hE9 STATION PEHIOD OF RECORD - JULY - SEPTEMBER 1983 STABILITY CLASS - NEUTRAL (DELTA T 375-33 FT)

WINDS MFASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 1 11 10 12 6 1 41 NNE 3 9 16 10 6 0 44 NE 5 21 17 6 0 0 49 ENE 2 16 11 13 3 0 45 E 2 6 10 10 2 1 31 ESE O 2 4 1 1 1 9 SE 1 12 14 5 3 0 35 SSE 2 15 24 8 3 0 52 S 1 11 7 6 10 11 46 SSW 0 7 8 17 15 7 54 SW 3 4 5 15 12 11 50 WSW 1 10 13 13 8 0 45 W 0 21 19 21 12 1 74 WNW 1 9 29 23 15 1 78 Nh 0 6 15 12 8 2 43 NNW 4 8 12 6 11 4 45 l

VARIABLE O O O O O O O TOTAL 26 168 214 178 115 40 741 1

HOURS OF CALM IN NHIS STABILITY CLASS - 0 HOURS OF MISSING WTND MEASUREMENTS IN THIS STABILITY CLASS - 1 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 117 70

LASALLE NUCLEAR PubER STATION PERIOD OF HECORD - JULY - SEPTEMHER 1983 (DELTA T 375-33 FT)

STABILITY Cl, ASS - SLIGHTLY'STARLE WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 1 1 5 8 5 0 20 NNE O 5 4 7 1 0 17 NE 5 8 19 9 1 0 42 ENE O 4 11 11 0 1 27 E O 6 5 11 7 1 30 ESE 1 7 4 8 9 3 32 SE 0 2 7 5 6 2 22 SSE O 1 7 6 4 2 20 S 1 2 4 5 9 20 41 SSW 1 4 5 8 11 35 64 SW 1 2 3 11 10 5 32 WSW 0 1 5 9 5 2 22 W 0 0 4 8 3 2 17 WNW 2 4 3 14 13 6 42 NW 0 5 8 9 10 2 34 NNW 0 3 6 12 4 1 26 VARIABLE O O O O O O O TOTAL 12 55 100 141 98 82 488 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND. MEASUREMENTS IN THIS STABILITY CLASS - 18 HOURS OF MISSING STABILITY MEASUREMENTS IN ALI. STABILITY CLASSES - 117 71

LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - JULY - SEPTEMBER 1983 STABILITY CLASS - MODERATELY STABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 0 0 0 1 1 0 2 NNE 1 3 0 5 0 0 9 NE O l- 2 3 2 0 8 ENE 3 0 3 2 3 0 0 8 E o 3 5 9 5 3 25 ESE 1 1 3 6 6 0 17 SE O 5 6 27 3 1 42 SSE O 4 5 14 2 0 25 S 0 7 5 7 6 17 42 SSW 1 0 11 8 6 17 43 SW 0 3 12 15 14 5 49 WSW 1 1 1 5 5 0 13 W 1 2 11 6 17 8 45 WNW 0 3 8 10 12 2 35 NW 1 2 6 6 16 3 34 NNW 0 3 3 4 3 0 13 VARIABLE O O O O O O O TOTAL 6 41 80 129 98 56 410 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 6 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 117 72

r LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - JULY - SEPTEMBER 1983 STABILITY CLASS - EXTREMELY STABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N O O O O O O O NNE O O O 1 1 0 2 NE O O O O O O O ENE O O O O O O O E O O 0 1 5 0 6 i

}.

ESE O O O 4 0 0 4 SE O 1 1 5 2 1 10 SSE O O 12 6 6 7 31 5 0 1 4 12 24 13 54 SSW 0 1 8 18 4 6 37 SW 0 0 1 4 2 4 11 WSW 0 0 1 7 7 3 18 W 0 0 2 0 10 1 13 WNW 0 1 1 1 5 8 16 NW 0 0 0 1 4 0 5 NNW 0 0 0 1 1 0 2 VARIABLE O O O O O O O TOTAL 0 4 30 61 71 43 209 HOURS OF CALM IN THIS STABILITY CLASS - 0

-HOURS OF MISSING WIND MEASUREMENTS IN-THIS STABILITY CLASS - 9 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 117 73

LASALLE NUCLEAR PODER STATION PERIOD OF RECORD - OCTOBER - DECEMBER 1983 STABILITY CLASS - EXTREMELY UNSTABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 0 0 0 0 0 0 0 NNE O O O O O O O NE O 0 0 0 0 0 0 ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0' O O NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O

~ TOTAL 0 0 0 0 0 0 0 HOURS OF CALM-IN THIS STABILITY CLASS - 0

-HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 28 74 9

o

LAS&Lbg NUCLEAR DOWER SWAT.1P'4 PERIOD OF PECORD - OCTOBER - DECLLSFR 1983 STABILITY CLASS - MODERATELT U!'STABleE (DELTA T 375-33 FT)

WINDS MEASURED AT 315 PZL1 WIND WIND SPEED (IN MPK)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N O O O O O O O NNE O O 0 0 0 0 0 NE O O 1 2 0 0 3 ENE O O O 1 1 0 2 E O

O O O O O O ESE O O O O O O O SE O O O O O O 0 SSE O O O O O O O S 0 0 0 0 0 0 0 SSW- 0 0 0 0 0 1 1 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O TOTAL 0 0 1 3 1 1- 6 HOURS OF CALM IN THIS STABILITY CLASS - 0 0

HOURS OF-MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS -

HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 28 i

l I

75 L . _-.

LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - OCTOBER - DECEMBER 1983 STABILITY CLASS - SLIGHTLY UNSTABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N O O O O O O O NNE O O O 0 0 0 0 NE O O 1 0 0 0 1 ENE O O O 1 4 0 5 E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 2 1 1 3 7 SW 0 1 0 1 0 2 4 WSW 0 0 0 0 3 0 3 W 0 0 0 0 0 0 0 WNW 0 0 0 0 1 0 1 Nd 0 0 1 0 0 0 1 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O TOTAL 0 1 4 3 9 5 22 HOURS OF CALM IN THIS STABILITY CLASS - 0

. HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 28 76

i r a vp-LAS4bbE NUCLEAR PODER STATION PERIOD OF RECORD - OCTOBER - DECEMBER 1983 STABILITY CLASS - NEUTRAL (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 1 1 9 34 5 9 59 8

i NNE 1 2 7 14 1 7 32 NE 2 2 5 31 17 0 57 ENE 1 4 2 5 19 27 58 E O 1 3 8 20 35 67 ESE 2 5 13 6 2 0 28 SE O O 5 5 0 1 11 SSE 1 0 9 3 9 19 41 S 3 1 13 9 8 8 42 SSW 1 3 10 21 15 18 68 SW 0 5 12 8 16 18 59 WSW 1 7 10 18 17 44 9)

W 1 2 14 16 20 20 73 WNW 2 13 21 27 30 39 132 NW _

1 6 21 35 23 25 til NNW 1 2 17 13 16 34 83 VARIABLE O O O O O O O TOTAL 18 54 171 253 218 304 1018 i

I HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 27

. HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 28 I

l i

I, 77

T.

LASALLE NUCLEAR POWER STATION PERIOD OF RECORD - OCTOBER - DECEMBER 1983 i STABILITY CLASS - SLIGHTLY STABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL

......... ..... ..... ,4 ..... ..... ..... ..... .....

N O 1 7 ; Any ' 18 13 2 41 Ail 4 NNE 2 4 15 p 14 7 0 42 NE 2 4 6 13 2 0 27

. ENE O O 6 21 8 9 44 E O M 9 19 18 15 65 ESE O 6 5 15 10 4 40 i

SE 1 7 6 12 13 10 49 SSE O 4 17 13 18 7 59 S 1 1 9 14 23 20 68 SSW 1 4 8 14 14 34 75 SW i 5 10 6 4 26 52 WSW 2- 4 8 12 9 30 65 W 0 3 5 2 17 23 50 WNW 0 2 8 10 12 32 64 NW 0 4 14 '16 12 7 53 NNW 0 1 9 12 4 1 27 VARIABLE O O O O O O O I

i

! TOTAL 10 54 142 211 184 220 821 l

l l . HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF-MISSING WIND MEASUREMENTS IN THIS STABILITY CLASS - 10 f

HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 28 r

[

i 78

t LASALLE NUCLEAR POWER STATION

' PERIOD OF RECORD - OCTOBER - DECEMBER 1983 STABILITY CLASS - MODERATELY STABLE (DELTA T 375-33 FT)-

t WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION .7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL N 0 -0 1 3 0 0 4 NNE 1 0 2 1 0 0 4 NE O O 1 4 1 0 6 ENE O O O 5 3 0 8 E

O O 1 0 0 0 1 ESE O 1 1 0 3 4 9 SE O 2 0 0 1 3 6 SSE O 0- 2 0 1 5 8 S 0 0 9 5 6 17 37 SSW 0 1 2 5 7 23 38 SW 0 2 , 2 1 7 8 20 WSW 0 0 2 7 5 8 22 W 0 1 0 3 8 6 18 WNW '

O O 1 0 4 9 14 NW 0 0 1 0 5 0 6 NNW 0 0 0 0 3 1 4 VARIABLE 'O O O O O O O TOTAL 1 7 25 34 54 84 205 HOURS OF' CALM-IN THIS STABILITY CLASS - 0

-HOURS OF MISSING WIND MEASUREMENTS-IN THIS STABILITY CLASS - 0

-HOURS OF MISSING STABILITY' MEASUREMENTS IN ALL STABILITY CLASSES - 28 79

LASALLE NUCLEAR PODER STATION PERIOD OF RECORD - OCTOBER - DECEMBER 1983 STABILITY CLASS - EXTREMELY STABLE (DELTA T 375-33 FT)

WINDS MEASURED AT 375 FEET WIND WIND SPEED (IN MPH)

DIRECTION 7-3 4- 7 8-12 13-18 19-24 GT 24 TOTAL

!! 0 1 2 0 0 0 3 NNE O 2 0 0 0 0 2 NE O O O O O O O ENE O O O O O O O E O O O O O O O 1

ESE O O 0 0 0 0 0 j

SE O O O 2 0 0 2 SSE O O O 2 2 3 7 S 0 0 6 5 7 13 31 SSW 0 0 0 0 1 5 6 SW 0 0. 0 0 3 1 4 Ik WSW 0 0 0 3 8 2 13 4

W 0 0 0 0 0 0 0 WNW 0 0 0 0 2 0 2 NW 0 0 0 0 0 0 0 NNW 0 0 1 0 0 0 1 O O O O VARIABLE O O O TOTAL 0 3 9 12 23 24 71 HOURS OF CALM IN THIS STABILITY CLASS - 0 HOURS OF MISSING WIhD MEASUREMENTS IN THIS STABILITY CLASS - 0 HOURS OF MISSING STABILITY MEASUREMENTS IN ALL STABILITY CLASSES - 28 80

t f

i i

1 APPENDIX III ANALYTICAL PROCEDURES 4

P i

81

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.

82

1.1~ Fish

1. Wash the fish.

2. Fillet and place the flesh immediately (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 anclyzed, boil remaining fish in water for about I hour. Clean the bones. Air dry, weigh and record as wet weight. Dry at 125' C. Record dry weight. Ash at 800*

C, cool, weigh, and record the ash weight. Grind to a homogeneous sample. The sample is ready for analysis.

3. Gamma scan fillet without delay or store in a freezer.

4. After gama spectroscopic analysis is completed transfer the sample to a drying pan and dry at 125' C.

5. ' Cool, weigh, and record dry weight.

6. Ash by gradually increasing the temperature to 450* C. If cons'ider-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.

83 g

1.2- Bottom Sediments and Soil

1. Air dry the entire sample. Grind or pulverize the sample and ,

sieve through a #20 mesh screen. I

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, s

84 4 i

1.3 Orinking (clear) water (EPA Method 900.0)

A representative sample must be collected from a free-flowing source of drinking water, and should be large enough so that adequate aliquots can be taken to obtain the required sensitivity.

It is recommended that samples be preserved at the time of collec-tion by adding enough IN HNO3 to the sample to bring it to pH 2 ,

(15 ml IN HNO3 per liter of sample is usually sufficient) If samples a7e to be collected without preservation, they should be brought to the laboratory within 5 days, then preserved and held in the original container for a minimum of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months before analysis or transfer of the sample.

The container choice should be plastic over glass to prevent loss due to breakage during transportation and handling.

If the sample was not acidified at the time of collection, use the following procedure:

Procedure

1. Remove 100 ml of sample for tritium analysis, if required.

NOTE: Water should not be acidified for tritium analysis. If samples are acidified in the field, an additional aliquot should be collected.

2. Add 15 ml of IN HNO3 per liter of sample in the original container.

3. Hold the sample in the original container for a minimum of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months before analysis or transfer of the sample.

4. When taking an aliquot for analysis, take acid addition into account. For example:

Sample volume Volume of aliquot to be analyzed required 200 ml 203 ml 400 ml 406 ml

'600 ml 609 ml 800 ml 812 ml 1000 ml 1015 ml 2000 ml 2030 ml 3000 ml 3045 ml 3500 ml 3552 ml For other volumes, adjust aliquots correspondingly, at the rate of 1.5 ml'per 100 ml of sample.

85

2.1 : Airborne Particulates 2.1.1. Gross Alpha and/or Gross Beta Activity Procedure 1., Store the sample for 5 days from the day of collection'to allow for decay of short-lived radon and thoron daughters.

2. Place a 47 mm filter on _a stainless steel planchet and count the sample in a proportional counter.

3. Calculate . the activity in pC1/m3 using computer program AIRPAT.

Calculations Gross alpha (beta) activity:

1 2 2 E E A

+2 sb b (pC1/m 3 ) .

B x C x 2.22 B x C x 2.22 Where:

A = net alpha (beta) count rate (cpm)

B = efficiency for counting alpha (beta) activity (cpm /dpm)

C = volume of sample (m3)

Esb = counting error of sample plus background Eb = counting error of background i

l F

86

2.2.2 Gross Alpha and/or Gross Beta Activity in Dissolved Solids (see note)

Principle of Method Water samples containing suspended matter are filtered through a membrane filter and the filtrate is analyzed. The filtered water sample is evapor-ated 'and the residue is transferred to a tared planchet for counting gross alpha and/or gross beta activity.

Reagents Lucite: 0.5 mg/ml in acetone Nitric acid,.HNO 3: 3N Nitric acid, HNO3 : concentrated Apparatus Filters; Millipore, membrane Type AA, 0.8 p Filtration equipment Planchets (Standard 2" x 1/8" Beckman planchet)

Proportional counter Procedure

1. Filter a volume of sample containing not more than 100 mg of dissolved solids for alpha assay, or not more than 200 mg of dissolved solids for beta assay.

Note: For gross alpha and gross beta assay in the same sample limit amount of solids to 100 mg.

2. .Wash the non-filterable solids on the filter. (Save the filters with suspended matter for separate analyses. See Section 2.2.1).

3. -Evaporate the filtrate to NEAR dryness on a hot plate. Add 25 ml concentrated HNO3 and evaporate to NEAR dryness.

Note: For analysis of total residue (for clear water) proceed as described above but do not fiter the water. Measure out the appropriate amount and proceed with step 3.

L 87 r

Section 2.2.2.(continued)

4. With distilled water and a few drops of 3N HNO3, transfer the residue to a 50 ml beaker. Evaporate lo NfAR dryness.

5. Transfer quantitatively the residue to a TARED PLANCHET, using an eye dropper.

6. Wash the beaker with distilled water and combine the washing and the residue in the planchet. Evsporate to dryness.

7. Bake in muffle furnace at 500* C for 45 min., cool and weigh.

8. Add a few drops (6-7 drops) of lucite solution and dry under the infrared lamp for 10-20 minutes.

9. Store the sample in a desiccator until it is to be counted.

10. Count the gross alpha and/or the gross beta activity in a low background proportional counter.

11. Calculate the activity in pCi/l using computer program OWATAB.

Calculations:

Gross alpha (beta) activity:

A 1

2 Efb -}- E b

(pCi/ liter)=

B x C x 0 x 2.22 B x C x D x 2.22 Where:

A = net alpha (beta) count (cpm)

B = efficiency for counting alpha (beta) activity (cpm /dpm)

C =. volume of sample (liters)

D = correction factor for self-absorption in the sample Esb = counting error of sample plus background Eb = counting error of background

Reference:

Radioassay Procedures for Environmental Samples, U.S. Department of Health, Education and Welfare. Environmental Health Series, January 1967.

88

3.1 Airborne Particulates - Gama Spectroscopic analyses by Ge(Li) Detector 1.- Put the air filter in a filter cup container.

2. Place the filter cup on a Ge(L1) detector.

3. Determine the gama spectrum using 4096 or .8192 channel of gama spectrometer with a setting of 0.5 kev or 0.25 kev per channel.

4. Identify gama emitters (if present) by their respective energy peaks .

Calculations

1. ~ Calculate the- gama activities using the computer program GAMMA 1 or GAMMA 2.

89

3.2 Airborne Iodine 3.2.1 Spectroscopic Analyses by Automatic Gama Counter Transfer charcoal to a plastic scintillation vial. Place the vial in the Automatic Gamma Counter (Packard Instrument Co. Model 5975) and count.

Record the time.

Calculations B

A=

2.22 x C x D x e- At Where:

A = activity of I-131 at the time of collection (pC1/m3)

B = net count rate of I-131 in the 0.36 MeV peak C = efficiency for counting I-131 activity in 0.36 MeV peak (cpm /dpm)-

D = volume of sample (m3) e = the base of the natural logarithm = 2.7183 0.693 0.693 A = decay constant t 8.08 1/2 t= time (days) between the midpoint of collection and counting.

3.2.2 Spectroscopic Analysis by Ge(Li) Detector

1. Transfer charcoal to a small plastic bag.

2. Label the plastic bag with the corresponding project,. location and date of collection and seal it.

3. Place packed charcoal in a 500 cc. Marine 111 beaker (all locations) and seal with tape. .

i.

4. Place it on the Ge(Li) detector and count. Record time.

Calculations Calculation is done by ' the computer by running the Program GAMMA 2.

90

3.3 Water - Gamma Spectroscopic Analyses by Ge (Li) Detector Procedure

1. Measure 3.5 liters of water into a Marinelli beaker.

2. Place the beaker inside the shield on a Ge(Li) detector.

3. Count long enough to meet LLD requirements.

4. After counting, identify gamma emitters (if present) by their respective energy peaks.

5. Store the spectrum on a disc using computer by executing "RUN STORE."

6. After storing, calculate gamma activities, using computer program GAMMA 1 or GAMMA 2.

7. Transfer the sample back to the original container for further analyses.

91

3.4 Soils and Bottom Sediments - Gamma Spectroscopic Analyses by Ge(Li) Detector Procedure

1. Transfer the portion of the ground sample set aside for gamma scan-ning into a 500 ml Marinelli container.

2. Record the dry weight.

3. Place the container inside the shield on a Ge(Li) detector.

(

4. Count the gamma activity long enough to meet the minimum sensitivity requirements. '

5. After counting, identify gamma emitters (if present) by their respec-tive energy peaks.

6. Store the spectrum on a disc using the computer by executing "RUN STORE."

7. After storing, calculate gamma activities using computer Program GAMMA 1 or GAMMA 2.

8. Transfer the sample back to the original container for further analyses.

L i

92 El ,

3.5 Fish and Wildlife - Gamma Spectroscopic Analyses by Ge(Li) Detector Procedure

1. Transfer a portion of the clean wet flesh of fish or animal into a 500 ml Marinelli container.

2. Record wet weight.

3. Add a few cc of formaldehyde and seal the container.

4. Place the container inside the shield on a Ge(Li) detector.

5. Count long enough to meet the minimum ' sensitivity requirements.

6. After counting, identify gamma emitters (if present) by their respec-tive energy peaks.

7. Store the spectrum on a disc using computer by executing "RUN STORE."

8. After storing, calculate gamma activities using computer program GAMMA 1 or GAMMA 2.

9. Transfer the sample back.to the original container for further analyses.

t 93 L

3.6 Ambient Gamma Radiation A. Thermoluminescent Dosimeters (TLD) - Licht Response (Efficiency)

Harshaw Lithium Fluoride TLD-100 chips,1/8" x 1/8" x 0.035".

Procedure .

1. Rinse the chips with warm trichloroethylene followed by the methanol rinse. Dry.

2. Place the chips in a platinum crucible.

3. Anneal for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 400*C.

4. Cool quickly by placing the crucible on a metal plate.

5. Anneal for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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").

14. Calculate mean + one sigma deviation of five chips.

15. - Calculate light response of TLD's (correction factor) by the following equation:

94

, , t.

r . ;- ,

,. ~a .':, .

.r.

'f)

-t, f I '

Section 3.6 (continued) ,

fI Calculations

/" A

-/ C.F. (nanocoulombs/ mrem) =

B i !

', 7, Where:

,/ C.F = correction f actor to be applied in calculating Ji. exposure of field TLD's s .A = Net reading in nanocoulombs

'O = known exposure to TLD's i The, exposure to the TLD's (B) is calculated as follows:

mrdm/hr=8400xmgRa-226

, '. r2 t'c,*

_ s 7ur setup'use the following parameters:

~'

/,Ra-226 = 0.0922 + 1.5% -

/

s . <

, r 19.6 cm Thus:

mrem /hrr '. 8400 x 0.0933 = 2.040

/ 384.16 ,

~

', The total expos'ure (B) is equal to:

?

J B (mrem) = 2.040 x hours r-f i

_f^^ e , ;-- .+

'f ;

<* ~

', y ,

3' 1 ,,

l^ '

'l i u, ~

i -

/ .!

i , ,] .

t'

,- , , s gy .r '< ,-

\

^ \* ^

s' r f_ , /'

_S) '

1; , t- ',:* i

,3b - *li

'A, f " +" -

r.

J .e l

,s? r. []

.s

/'

j t 'i

\ ,'i '

/ - , ,

q 'l

. .c - ,= "95 y

. , ,' ; (,-

?.

i -

x (cJ .

,] .

-_ - rr

}

3.7 Procedure for Preparation and Readout of TLD Chips Materials Harshaw Lithium Fluoride TLD-100 chips, 1/8" x 1/8" x 0.035".

Black plastic bags or boxes Plastic sealer Vacuum needle (for handling the chips)

TLD reader Note: Never handle the chips with bare hands. Use plastic-covered forceps or vacumn needle. Handle them gently, e.g. do not drop them into. the vial or on the table. They chip off easily, resul-ting in efficiency change. .

Procedure

1. Rinse the chips with warm trichloroethylene followed by the methanol ;

rinse. Dry.

2. Place the chips in a platinum crucible.

3. Anneal for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 400*C.

4. Cool quickly by placing the crucible on,a metal plate.

5. Anneal for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at 100*C.

6. Seal 3 to 5 chips (depending on the specifications) in black plastic or plastic boxes.

7. Label and send out by U.S. Mail.

8. Upon arrival at the lab, store TLDs in the big shield until readout day. Do not store longer than a few days.

9. Connect chips reader one day prior to readout.

10. Turn on gas for a few minutes before readout. Adjust to the mark.

'11. Set parameter on the 2000P as follows:

HV - 470 V (It is 970 V, internal volts = 500).

Readout time: 20" T1 - 140' C (Preset)

T 2 - time:

Rise 250'-12*/sec C (Preset)(Preset)

Preheat'- 100* C (Preset.)

Start reading - 90* C 96

i Se.cion 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 alass 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.

i 12.3 ' Place the ' vials in the furnace. Preanneal for 10 min. at ,

100*C. l l

13. Open the drawer and read the standard. It should read 5.70+0.04. i Adjust HV,.if needed. Take 3 readings after final adjustment. 1 Record. l

-14. Close the drawer.

15. - Check bkg. It should read about 0.7-0.8 in 20". If it is higher, l adjust the knob in the back of 2000 P (on left side when facing the )

instrument). )

-Note: Adjust bka as ' low as possible but do not let the needle hit zero. The instrument will not record below zero.

16. Make 10 bkg readings (no chip in). Record. Read (do not record) at least 2 dummies to stabilize the temperature.

Place the chip in, wait until t6npe'rature goes down to 90* C and

~

c 17.

press . " read" button. Make sure. the chip is in the cavity of the heating plate. >

-18. After readout is completed, record the reading, open the drawer, and place next chip.

~

y.

19. Repeat Steps 17-and 18 until all chips are read out.

~

Note: If - reading will last longer than 1.5-2.0 hrs., check the standard and bkg about every 2.0 hrs.

20. 'After readout is completed, turn off the gas.

21. For calculations, use computer program OGTLD. PUB.

, x l

? > 97 L ::

L3.8 Tritium in Water (Direct Method)

Princip'le of. Method

- The water sample is purified by distillation, and portion of the distil-late.is transferred to a counting via1' containing a scintillation fluid.

1The contents of the vial are then mixed and counted in a liquid scintilla-tion counter.

. Reagents Scintillation medium, insta-gel scintillator Tritium standard solution

. Apparatus Condenser.

Distillation flask, 250-m1 capacity Liquid scintillation counter-Liquid scintillation counting vials

. Procedure

1. Distill a.30 ml aliquot of. the sample in a 250-ml. distillation flask. Add a boiling2 chipito the" flask. Connect' a side arm

~

l 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:forLtritium analysis.

2. : Dispense 13.~ml of the. distillate to a-low potassium glass vial.

L

3. - Prepare background and standard tritium-water solutions for countins. using the.same. amount as the sample. Use low tritium background' distilled! water for these preparations (distillate u of most deep well water sources is~' acceptable, but each source should be checked.for. tritium activity beforefusing).

4. Dark-adapt all samples, backgrounds, 'and . standards. Add 10 ml of. insta-gel scintillator. Count the samples, backgrounds'and standards. -Count samples ~ containing . less than 200 pCi/1 for

- 300 minutes and l samples containing more than 200 pC1/1 for_ 200

. minutes.

6 98

' Section 3.8 (continued)

5. Counting efficiency:

Eff = cpm of Standard-cpm of b'ackground dpm Standard 4

6. Sample Activity: -

^

pCi/ml =

2.22 x E x V Where:

A = net count rate (cpm)

E = efficiency (cpm /dpm)

V = volume (ml)

7. Calculate tritium. activity using computer program H3.

^l'_

J i

99

3.9 Iodine-131 Milk by Ion Exchange on Anion ~xchange 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 extracted into CCl4 , back-extracted into water then finally precipitated as palladium iodide, l

Chemical re' c overy of the added carrier is determined gravimetrically from the PdI2 precipitate. I-131 is determined by beta counting the PdI2-l Reagents i Anion exchange resin, Dowex 1-X8 (50-100 mesh) chloride form.

Carbon! tetrachloride,CCl4 - reagent grade.

Hydrochloric acid, HC1, IN.

Hydrochloric acid, HC1, 3N_.

H2O - HNO 3 - HN20H HCL wash solution: 50 ml H20; 10 m1 1M,- NH2 0H-hcl; 10_ ml conc.-HNO3 -

Hydroxylamine hydrochloride, NH2 0H hcl - 1 M.

Nitric acid, HNO3 - concentrated.

~

Palladium chloride, PdI 2, 20 mg Pd++/ml. 1.2 g pdc 12/100 ml 6N hcl).

Sodium bisulfite, NaHS03 - 1 M_

Sodium chloride, Nacl - 2M_

Sodium hypochlorite, Na0C1 - 5% (Clorox).

100

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 sil.ica 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 ug, 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 2". Radiological Science Laboratory. Division of Laboratoriesand Research, New York State Department of Health, March 1975, Revised-February 1977.

101 L _ _ _ . , _ _ _ .- - _ _ _ _ _ . _ _ _ _ . _ , _ , ._ _

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. Add 50 ml of CC14 and 10 ml of 1 M hydroxylamine hydrochloride (freshly prepared). Extract iodiniiinto organic phase (about 2 minutes equilibration). Draw off the organic phase (lower phase) into another separatory funnel.

3. Add 25 ml of CC14 and 5 ml of 1 M hydroxylamine hydrochloride to the first seperatory funnel iind 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 20-HNO 3-NH 20H hcl wash solution to the separa-tory funnel containing the CC1. 4 Equilibrate 2 minutes.

Allow phases to separate and transfer CC14 (lower phase) to a clean separatory funnel. Discard the wash solution.

5. Add 25 ml H2 O and -10 drops of 1 M sodium bisulfite (freshly prepared) to the separatory funiiel containing the CC1. 4 Equilibrate for 2 minutes. Discard the organic phase (lower phase). Drain aqueous phase (upper phase) into a 100-m1 beaker.

Proceed to the Precipitation of PdI2-C. Precipitation of Palladium Iodide CAUTION: AMMONIUM HYDR 0XIDE INTERFERES WITH THIS PROCEDURE

1. Add l10 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++/m1 palladium chloride per liter of milk used dropwise, to the solution.

102

c Section 3.9 (continued)

Special Apparatus Chromatographic column, 20 m x 150 m (Reliarice Glass Cat.#R2725T).

Vacuum filter holder, 2.5 cm2 filter area Filter paper, Whatman #42, 21 m Mylar Polyester gumed 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 culumn 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 3 . and transfer to 250 m1 separatory funnel. (Add.the acid slowly with stirring until the vigorous reacticc subsides.) Volume of concetrated HNO3 required will depend on eluate volume as follows):

103

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

t 4

Section 8.1-

' 8.1 Strontium-89 and Strontium-90 in Milk by Ion Exchanae i ,

-Principle'of Method ;

A citrate complex of yttrium, strontium, and barium carriers at the nH.

of milk-is added to the milk sample. The mixture is then passed s u s-sively through cation- and anion-exchange resin columns. - Strontium,

-barium, and -calcium ' are absorbed - on the . cation-exchange resin, and the b . 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 4 precipitated as. the oxalate. Lanthanum 140, which may be a contaminant, e 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 Rdilute nitric acid and precipitated as the oxalate. The precipitate 'is weighed to determine recovery of : yttrium carrier, then

~

counted for yttrium 90 activity.

. Strontium, barium. and calcium are eluted from the' cation-exchange resin with sodium chloride : solution. Following dilution of the eluate, the 7 -

alkaline earths are precipitated. as carbonates. The carbonates are then converted to nitrates,J and strontium and: barium nitrate _are- precipi-tated. .The-nitrate precipitate is dissolved, and barium is precipitated r 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-i' strontium". ,

The concentration' of strontium-89 is - calculated as the difference-p' between the activity' for " total radiostrontium" and the activity due to r

~s trontium-90.

Reagentsi

~ Ammonium acetate' buffer: pH 5.0 Ammonium hydroxide,-NH .4 0H: concentrated (15N)~

Ammonium oxalate, (NH4)2C0 2 4.H 20: _ IN_

Anion-exchange resin: Dowex 1-X8.(CI- form, 50-100 mesh)

Carrier solutions:-

- Ba+2:as barium nitrate, Ba(NO3 )2: 20 mg Ba+2'per.ml Sr+2'as strontium nitrate, Sr(NO 3)2:- 20 mg Sr+2 per ml Y+3 as yttrium nitrate, Y(NO3.): 10 mg Y+3 per ml Cation-exchange resin: Dowex 50W-X8 (Na+ form, 50-100 mesh) t

Citrate solution: 3N_(pH6.5) i 104 .

Section 8.1 (Continueo)

Diethyl ether, (C H25 )2: anhydrous E_thyl alcohol, C 25 H 0H: absolute (100%), 95%

Hydrochloric acid, HC1: concentrated (12N, 6N*, 2N*)

Hydrochloric acid-diethyl ether, hcl-(C25 0 :5.1 v/v H )2 Nitric acid, HNO 3: fuming (90%), concentrated (16N)*, 14N, 6N, 0.1 N*

0xalic acid, H C224 0 .2H 0:2N_*

2 Sodium carbonate, Na2 3 :3N, 0.1 N 00 Sodium chloride, NaC1:4N Sodium chromate, Na2Cr04:3N, Tri-n-butyl phosphate (TBP), (C Hg)3 4 P04 : pre-equilibrated with 14N_ HNO3

I

Starred reagents are used only in processing the anion column effluent to determine strontium-90 concentration (Part A).

Apparatus Ion-exchang'e system: The apparatus for this system is illustrated in Figure 8.1-1. It consists of three glass components connected one above the other for gravity flow. At the top is a graduated, 1-liter glass .separatory -funnel which serves as the reservoir.

Below it is connected a 250 ml glass column, 5 cm in diameter and 25 cm long, which services as the cation column. Below this is connected the anion column, a 30-ml ' glass column, 1.9 cm in dia-meter --and 10.5 cm long. Both columns have extra coarse, fritted glass disks at the bottom.

Five milliliters of distilled water are placed in the 30-m1 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.

M1111 pore filtering apparatus (Pyrex 'Hydrosol Microanalysis Filter Holder)

Miilipore type OH membrane filter,1.5-p pore size, 2.5-cm diameter low-background beta counter.

105

~

L

V w

I r

a

.RESERV0lR .. < . / .ufEA OLASS)

/ ,\ SEPAR ATOAY Fusenf t !

1 m

L

. . . . . . .s ll w

0

- aso.ea, eLass cotuun s m .;pj.;;, witw Fairveo e us oissg

.gp:;.j.3;;

, , ,,i; CATION RESIN - . *M Et,?L..:

cJ'.;i,. -

1

-- . . =

-l l G-

'n

. /- 30.ast eLAss c0Luuhl

/ ,\ stTM FestTED eL ASS DISKI--

%!:4 .

ANION RESIN .9,,,4.6I:

P

..=

i.

L ,

^ .

J Figure _a g- Ion-exchange system -

106 c

S ction 8.1 - Part A Part A. Strontium-90 Procedure,

1. Place 1 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/iiiin. 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,NSOHusingapHmeter.

7. Stir and heat to near boiling in a water bath (apprcx. 20 min).

8. Cool in an ice bath and centrifuge. Decant and discard the supernatant. Proceed as in (a) or (b) depending on whether Ba-La-140 is absent or present from the gamma analysis of the sample.

(a) If fresh fission products are known to be absent:

Dissolve the ppt in 10 ml of HNO 3 , filter solution through Whatman No. 541 paper into a 40 ml centrifuge tube. Wash paper, collecting the washing in tube and continue as in Step A-9.

107

Section 8.1 - Part A.(Continued)

J (b) If fresh fission products are present:

Dissolve the ppt in '10 ml of HNO3 , transfer the solution to -a 60 ml separatory funnel, washing the tube with addi-

~

tional'10 ml of.HNO3 . Add 10 ml of equilibrated T8P, 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 2O 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 3 , adding it to the centrifuge tube. ;

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,' 4 using a pH i

-meter.

10. Digest the solution in a hot 'H O 2 bath 'for 10 min. with occa-s'ional stirring. - Cool in~an ice bath (20 min).

~

11.- Filter lon'a weighed Whatman No. 42 (2.1 cm) filter paper. Wash h with H 20, ethyl - alcohol, and ether and dry at room tempera-a ture and: weigh.

12. Mount and count in a proportional counter.

L 13. If analysis for Sr-89.is not required, disregard Section o -8.1-Part 8. Use the computer- program SR8990 to calculate (Sr-90) activity.

lr l _

L i -- -_.

l .

I L

l -

108 f

2 se , o-+%- +,,i.- .--- c, y . ., , 4 -r ,w .>c.- + ,--+--w,., re ,,*-. ,. t '-&-p ^ --

-Section 8.1 - Part B Part B Total Radiostrontium (Sr-89 separation)

Procedure Continue following columns separation (Step A-4).

5. Connect 1 1 separator funnel containing 1 1 of 4N Nacl to the cation column. Allow the solution to flow at 10 ml/ min to elute the alkali metal and alkaline earth ions and to recharge the column. Collect 11 of eluate into a 21 beaker, but leave the resin covered with 2-3 ml of solution.

6. Wash the column with 500 ml of H2O or more to remove excess NaC1. Discard the wash.

7. Remove 20 ml of the Nacl eluate into a small bottle for the determination of stable calcium. (See section 6.1).

8. Dilute the eluate to 1500 m1 with distilled water.

9. Heat the solution to 85*-90* C (near boiling on a hot plate)

,. and add, with constant stirring, 100 ml of 3N Na2003. Stir gently while on hot plate to prevent bumping. Let stand overnight.

10. Decant most of the supernate. Transfer the precipitate to a 250 ml centrifuge bottle.

11. Wash the precipitate twice with 50 ml portions of H 20. Dry-it in an oven at 110' C for 1-2 hours.

-12. Dissolve the ppt slowly with vigorous stirring in 10 ml of 6N HNO3 (with magnetic stirrer). Filter through Whatman No. 54T paper . into a 40 ml centrifuge' tube. Rinse the bottle with little - 6N HNO3 and pour the washings through the paper. To the ~ filtrate, add slowly 30 ml of 21N HNO3 (fuming). Stir well and cool in an ice bath. CentriTuge and discard super-natant.

13. Carefully add 30- ml . of conc. HNO3 to the precipitate. Heat in a H 2O bath with stirring for about 30 minutes. Cool the solution in an ice water bath for about 5 minutes. Centrifuge

~

and discard supernatant.

i;. Repeat step No. 13.

109 L.5

Section 8.1 - Part B (Continued)

15. Dissolve the ppt. in 10 ml. of H O 2 and 5 ml. of NH 4AC buffer and heat in a water bath: Adjust pH to 5.5 using a pH meter and add immediately 1 m1. of 3N Na2C r04 and mix well. _ Digest in a water' bath for 5 min., centrifuge and decant the super- l natant into another 40 ml. centrifuge tube.

16. Heat- the supernate in a water bath. Adjust the pH to 8-8.5 with NH4 0H. With continuous stirring, cautiously add 5 ~ ml l of 3N Na2CO3 solution. Heat gently for 10 minutes. Centri-

-- i fuge and decant the supernate. Wash the strontium carbonate l precipitate with 0.1 N_ Na2003 . Centrifuge again, and decant the supernate. l

17. Dissolve the carbonate precipitate in 5 ml of 6N HNO . 3 With continuous stirring, cautiously add 30 ml, of fiiming 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 2O and 5 ml of 6N HNO3 . Add cautiously, with continuous stirring, 20 ml of Tuming HNO3 . Cool f n an ice bath, centrifuge and discard supernatant. RECORD TIME AS BEGINNING OF Y-90 INGROWTH.

l

19. Dissolve - the precipitate in 10 ml of H 20. Heat in a water I bath. Adjust the pH to 8-8.5. With continuous stirring, add 5 ml of 3 N Na2003 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.

I

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.

i l

1 i

i 110

~

Section 8.1 (Continued)

Calculations-Part A.

Strontium 90 activity (pCi/ liter) = A 2.22 x B x C x D x E x F Where:'

.'A = net beta count rate of yttrium 90 (cpm)

B = recovery of yttrium carrier -

C = counter efficiency for counting yttrium-90 or-yttrium oxalate mounted on a 2.1-cm diameter membrane filter (cpm /pCi)

D = sample. volume (liters)

E = Correction factor e -xt for yttrium-90 decay, where t is the time from midpoint of the_elution time of milk (Step

'A-2) to the time of counting.

~..

F = Correction factor 1-e-2 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 activi_ty (pCi/ liter) = 1' A - F (GxH + IxJ)

~

2.22xBxC [FxE

( j 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 /pC1)

.C = correction factor e-4 for strontium-89 decay, where t is the time for. sample collection to the time of counting D = recovery'of strontium carrier 1 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 r- .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 = counter efficiency.for counting yttrium-90 as yttrium

- oxalate mounted on a 2.1-cm diameter membrane filter

. (cpm /pCi)-

~

111 c .,

fi

Section 8.1 (Continued)

J=corrhetion 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).

e

Reference:

Radioassay Procedures for Environmental Samples U.S. Depart-ment of Health, Education and Welfare. Environmental Health Series, January 1967.

I k

6 e-1 b

- 112 '

j

t Section 8.4 8.4 Strontium 89 and Strontium 90 in Water Samples A. Principle of Method The acidified sample of clear water with stable strontium, barium and calcium carriers is treated with oxalic acid at 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 s'econd strontium nitrate precipitation from 70% nitric acid, the nitrates are dissolved in water and with added yttrium carrier, are stored- for ingrowth of yttrium-90. The strontium is again precipitated and_ separated from 70% nitric acid with the yttrium nitrate being in the supernate. Each fraction is precipitated separately as an oxalate and collected on No. 42 (2.1 cm) Whatman filter or planchet for counting either total radiostrontium or yttrium-90 or both.

Reagents Acetic acid, CH C00H:

3 1.5N Ammonium acetate, NH4232 C H 0 : 3N, Ammonium acetate buffer: pH 5.0 Ammonium hydroxide, NH40H: concentrated (15 N), 6 N, 1 N Ammonium oxalate, (NH 4 C0

)2 2 4.H 2 0: 0.5% w/v Carrier solutions:

Ba+2 as baritna nitrate, Ba(NO3 )2: 20 mg Ba+2 per ml Ca+2 as calcium nitrate, Ca(NO3 )24H2 0: 40 mg Ca+2 per ml Sr+2 as strontium nitrate, Sr(N02 ): 20 mg Sr+3 per ml Y+3 as yttrium nitrate, Y(NO3)3: 10 mg Y+3 per ml Hydrochloric acid, hcl: concentrated (12 N_), 0.5 N Hydrogen peroxide, H22 0 : 30% solution Nitric acid, HNO 3: fuming (90%), concentrated (16 N), 6 N, 3N C 0 . 2H 20: Saturated at room temperature 0xalic acid, H 222 Scavenger solutions: 20 mg Fe+3 per m1, 10 mg each Ce+3 and Zr+4 per ml

- Fe+ as ferric chloride, FeCl 3.6H20 Ce+3 as cerous nitrate, Ce(NO3 )3 6H20 Zr+4 as zirconyl chloride, Zr0C1 2.8H 2O Sodium Carbonate, Na2 CO3 :3N, 0.1N Sodium Chromate, Na2Cr04:3N Appsratus Analytral balance Low background beta counter Medium - pcrosity filter stick pH meter 113

Section 8.4 A Part A. Strontium 89 Procedure

1. Filter 1 -litei of an acidified water sample using millipore filter paper.

2. Digest the filter paper with the residue with concentrated nitric acid (HNO 3 ) until all the organic matter is removed.

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 necessary, 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 40H, and allow 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-n ate.

Dissolve the precipitate _ with 10 ml of 6 N-HNO3 and transfer to a 8.

250 ml beaker. Then'use-20 ml of 16 N HNO3 to rinse the centri-fuge tube and . combin'e it '. to - the solutlon in the 250 ml beaker.

l ?9. Evaporate the solution to dryness. Cool; then add 50 ml 16 N_ HNO3 and repeat the acid addition and ' evaporation until the residue is

~

colorless.

10. Transfer the residue to a 40-ml centrifuge tube, rinsing with" a minimum volume of 16 N HNO3 . Cool in a refrigerator overnight.

Centrifuge at 1500-1800 rpm for 10 minutes, and discard the super-n at e.-

t

11. ' Dissolve the' precipitate in 5 ml of 6N HNO3 and then add 30 ml of fuming nitric acid. Centrifuge, and dficard the supernate.

m. ~12. . Dissolve the nitrate precipitate-in about 1_0 ml of distilled water.

Add 1 ml of~ scavenger solution. Adjust the pH of the mixture to 7

. with '6 N HN 40H. Heat, stir, and filter through a Whatman No. 541

-filter. Discard the mixed hydroxide precipitate.

f 1

114 0

Section 8.4 A (continued)

Part A. Strontium 89 Procedure (con inued)

13. To the filtrate, add 5 ml of ammonium acetate buffer. Adjust the pH with 3N HNO 3 or NH4 0H to pH 5.5. (Note: the pH of the solution at this point is critical.) Add dropwise with stirring 1 ml of 3N'-

Na2 r04 solution. Heat in a water bath.

C

14. Cool and centrifuge. Decant the supernate into another centrifuge tube. Save the precipitate for 8a analysis if needed.

15. Heat the supernate in a water bath. Adjust the pH to 8-8,5 with NH4 0H. With continuous stirring, cautiously add 5 ml of 3N Na2CO3 solution. Heat gently for 10 minutes. Cool, centrifuge, and decant the supernate. Wash the precipitate with 0.1N, Na2CO 3 . Centri-fuge again and decant the supernate.

16. Dissolve the precipitate in no more than 4 ml of 3N HNO3 . Then add 20-30 ml of fuming HNO 3 , cool in a water bath, aiid centrifuge.

Decant and discard the supernate.

17. Repeat step 16. Then, RECORD THE TIME AND DATE AS THE BEGINNING OF YTTRIUM 90 INGROWTH. If no immediate count of total radiostrontium is desired add to the precipitate 1 ml of yttrium carrier solution and 4 ml of 6N, HNO3 and store 7-14 days to allow the yttrium 90 to grow in.

18. To determine total 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.

21. Mount and count without delay its beta activity as " total radio-strontium" in a proportional counter, i

115

Secticn 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 t6tal 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 4 0H, stirring 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 40H, stirring continuously.

-6. Cool to room temperature in a cold water bath and centrifuge for 5 minutes.

7. Repeat steps 5 and 6.

8. Add 3 drops of hcl to dissolve the precipitate, then add 20 ml of water. Filter using No. 541 filter paper. Heat in a water bath at approximately 90* C. Add 1 ml of saturated oxalic acid solution dropwise with vigorous stirring. Adjust to a pH of 2-3 with NH 0H. 4 Allow the precipitate to digest for about an hour.

9. Cool to room temperature in a cold water bath. Centrifuge for 10 minutes and decant most of the supernate. Filter by. suction on a weighed filter paper. Wash the precipitate with water and alcohol.

10. Dry the precipitate under the lamp for 30 minutes. Cool and weigh.

Mount and count without delay in a proportional counter.

11. Calculate- Sr-89 and Sr-90 activity in pCi/l using the computer program for Sr-89,90.

116 p

f- Secticn 8.4 (continued)

Part B. Strontium 90 Calculations ;

i For formulas used refer to Section 8.1.

Reference:

Radioassay Procedures for Environmental Samples U.S.

Department of Health, Eduction .and Welfare. ~ Environ-mental Health Series, January 1967.

m 117

^

Section 8;6-8.6 Strontium-89 and Strontium-90 in Milk (Ash), Vegetation, Fish, Wildlife, 1

Soil and Bottom Sediment Samples - Sodium Carbonate Fusion.

n 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 interfering 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 oxalatesfor 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.

4 Reagents-f Ammonium acetate-buffer, (NH4 )2 Ac:pH = 5.0, 6M -

Ammonium hydroxide, NH 40H:6N, Carrier. Solutions-Ba+2,.Ba(No3 2:20 mg/ml of Ba+2 -

Fe+3 3 3, scavenger:5 m Iml of Fe+3

~Sr+2,.Fe(NO Sr(NO

-Y+3,,Y(NO

3 3: 10)3mg/mi 2:2G of mg/ml Y+3 of'Sr 3

. Ethyl alcohol, C H 250H: absolute Hydrochloric acid, hcl:12N (conc.)

Nitric acid, HNO3:16N (conc.), 6N, 3N, fuming Oxalic acid, H C 2240 : saturated Potassium nitrate, KNO :3powdered ,

-Sodium carbonate,-Na2C03: powdered, 3N, 0.1N Sodium chromate, Na2Cr04:3N

_ Sodium hydroxide, Na0H:pe1Tets !

. Apparatus I Teflon filter . holder, or filter. funnel L and . sample mount rings and discs

, Magnetic stirrers with Teflon-Coated magnet bars

[- Mylar film Glass fiber filters

' Fisher filtrator

.Brinkman dispenser - pipettor h>

1 n .

i

i 118

F1 Section 8.6 A Part A. Sample Preparation - Sodium Carbonate Fusion Procedure

1. Weigh out-3 g of ashed sample or silted soil and s'et 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 KN03 -

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 Na2CO3 over the ash so it is completely covered.

6. Place in a muffle furnace at 600*C for 20 to 30 minutes to melt and fuse the mixture.

NOTE: If carbon materials remain floating on the surface 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 KNO3-

-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 solidifieo 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 m1 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.

l 119 m

S ct' ion 8.6 A (continued)

Part A. Sample Preparation - Sodium Carbonate Fusion Procedure (continued)

11. To the residue add 50 ml 3N Na2CO3 as a wash, swirl and disperse the residue, heat for 10 mTnutes in a hot water bath, centrifuge and discard the supernatant.

12. Repea1! step (11) three cimes to put the precipitate in a suitable form for further analysis.

13. Dissolve the precipitate in 50 ml of concentrated HNO3 , transfer to a 250 ml beaker, and take to dryness on a hot plate.

NOTE: Evaporation may be done rapidly at first, and then very slowly to prevent spattering.

A jelly-like substance may form at this point, due to hydrated silicic acid formed from the soluble silicates and will be removed in the following steps.

14. Bake the remaining residue for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 120* to 130* C, cool, moisten the salts with 5 ml of HNO3 and allow to stand at room temperature for 10 minutes. Then place on a hot plate, bring to a boil and add 45 ml of boiling water. DISPERSE ANY REMAINING RESIDUE WITH A GLASS STIRRING R00 AND FILTER IMMEDIATELY into a 250 mi beaker. Use Whatman No. 541 hardened filter paper.

NOTE: To separate the silicic acid the hydrated acid must be changed to a less hydrated and less soluble acid by baking at 100* to 130*C.

It is important at this point that- evaporation be to com-plete dryness. (There should no longer be a smell of acid). ,

Addition of 5 ml of HNO3 converts any metal oxides which may have.been formed back to nitrates so they will be dissolved and not removed with the silicates.

'I 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.

120

S ction 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 if 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.

l 121

Scction 8.6 B Part B. Det'ermination f

I. Strontium - 89 Procedure

1. Transfer the solution to a 40 ml conical, heavy-duty centrifuge tube using a minimum of conc. HNO 3 . Cool the centrifuge tube in 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 phosphate content.

2. Add 30 ml of conc. HNO3 to the precipitate. Heat in a hot water bath with stirring for about 10 minutes. Cool the solution in an ice bath with stirring for about 5 minutes. Centrifuge and discard the supernatant.

. NOTE: Additional calcium is removed from the sample. Nitrate precipitations with 70% HNO3 will afford a partial decontamination from soluble calcium while strcntium, barium, and radium are completely precipitated.

The separation of calcium is best at 60% HNO ,3however at 60% the precipitation of strontium is not complete.

Therefore, it is common practice to precipitate Sr(NO3)2 with 70% HNO3 which is the concentration of commercially available 16 _N HNO3 -

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 NHt0H. Heat, stir, and filter through a Whatman No. -

3 541 filter- D1scard the mixed hydroxide precipitate.

122 L ,

) s Q

Section B.6 . ,

Part B Determination I. Str'$ntium-89 l

Pr

--.ocedure

. (continued)

- 5'. To the filtrate add 5 ml of ammonium notate buffer (pH 5.0).

Adjust the pH to 5.5 with '34 HNO3 or 6N NH40H. (Note: The e pH of the solution at this point is critical. Barium chromate will' not prec'ipitate completely in more acidic solution and str'ontium will partially precipitate in more basic solutions.)

Add dropwise with stirring 1 ml of 3N Na2Cr04 solution. Heat 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 NH4 0H. With,co#:inuous stirring, cautiously add 5 ml of 3H Na2003,solutfen!' Heat gently for 10 minutes. Centrifuge, and when completeness of precipitation has been verified by adding a few drops of Na2C03 , centrifuge and decant the supernate.

Wash the strontium carbonate precipitate with 0.lN Na2003- -

Centrifuge again, and decant the supernate.

Dis' solve the carbonate precipitate in 5 ml 6N HNO . 3 With 7.

entinuous stirring, cautiously add 20 m1 fuming HNO3 to the solution. (Stirrir,g the solution longer helps in the precipita-tion of strontium nitrate). Cool in an ice bath, centrifuge and decant the supernate.

8. Dissolve the . strontium nitrate precipitate .in 3 ml H O 2 and 5 ml 6N HNO'. 3 Add cautiously, with continuous stirring, 20 ml f7Jming HNO3 . Cool in ice bath, centrifuge and discard super-natant. RECORD TIME AS BEGINNING OF Y-90 INGROWTH.

~

9. Dissolve the precipitate in 10 ml of H 20. Heat in a water 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 iNo. 42 (2.1 cm) Whatman filter paper. Wash thoroughly with water and alcohol.

11. Dry the precipitate under the$ 13mp for 30 einutes. Cool and weigh. \

12. Mount and count without delay in,a proportional counter as total radiostrontium.

\

l i

) ,

123

f Section 8.6 Part B Determination II. Strontium-90_

Procedure

1. After counting total radiostrontium, dissolve the strontium carbonate precipitate on the filter in 6N HNO3 and transfer the solution to a 40 ml centrifuge tube. 'The total volume of dissolution and rinsing should be about 4 ml.

2. Add 1 ml of yttrium carrier solution and store until 7 to 14 days have elapsed since Step B-I-8 was completed. .

3. Heat the equilibrated strontium-yttrium sample in a water bath at approximately 90* C. Adjust the pH to 8 with NH 0H, 4 stirring continuously.

4. Cool to room temperature in a cold water bath and centrifuge for 5 minutes. Discard the supernate, record the time and date of the_ decantation as the end of the yttrium-90 ingrowth and the beginning of its decay in the yttrium fraction.

5. Dissolve' precipitate by adding about 4 drops of hcl with stirring. Add 15-20 ml of water. Heat in a water bath and adjust the pH to 8 with NH4 0H, stirring continuously.

6. Cool to room temperature in a cold water bath and centrifuge for 5 minutes. Discard supernate.

7. Repeat steps 5 and 6.

8. Add 3 drops of hcl to dissolve the precipitate, then add 20 ml of water. Filter the solution using No. 541 Whatman hardened filter paper. Heat in a water bath ht 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 absolute ethyl' alcohol.

10. Dry. the precipitate under the lamp for 30 minutes. Cool and

~

weigh. Mount and count without delay in a proportional counter as-Y-90(Sr-90).

-11. Calculate Sr-89 and Sr-90 activity using the computer program for Sr-89,-90. ,

124

Section 8.6 B (continued)

Part B Determination II. Strontium-90 Calculations

a. Strontium-90 activity (pCi/g) = 2.22 x B x xDxExF Where:

A = net beta count rate of yttrium-90 (cpm)

B = recovery of strontium carrier C = efficiency for counting yttrium-90 as yttrium oxalate (cpm /dpm)

D E= = correction sample size (in gramp factor e- for yttrium-90 decay, where t is the time from decantation of the strontium supernate (Step B-II-4) to the time of counting (S,tep B-II-10)

F = correction factor 1 - e-^t for the degree of equilibrium attained during the yttrium-90 ingrowth period, where t is the time from strontium separation (Step B-I-8) to the time of strontium removal (Step B-II-4).

b. Strontium-89 activity (pCi/g) = 2.2 xBxc - 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 /pC1)

C = correction factor e-4 for strontium-89 decay, where t is the time from sample collection to the time of counting 0 = recovery of strontium carrier E = sample size (in grams)

F = strontium-90 concentration .(pCi/g)

G = self-absorption factor for strontium-90 as strontium oxalate mounted on a 2.1 cm diameter membrane filter H = counter efficiency for counting strontium-90 as strontium oxalate mounted on a 2.1 cm diameter membrane filter (cpm /dpm)

I = counter efficiency for counting yttrium-90 as yttrium oxalate mounted on a 2.1 cm diam ter membrane J = correction factor 1 - e- t for yttrium-90 ingrowth, where t is the time from the last decantation of the nitric acid supernate from the strontium nitrate precipitate to the time of counting (Step B-I-8).

References:

Radioassay Procedures for Environmental Samples.

U.S. Department of Health, Education and Welf are Environmental Health Series, ' January 1967. HASL Procedure Manual edited by John H. Harley, 1972.

125 L

ML20087P233

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g g** g =

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