ML20203P894

Annual Radiological Environ Operating Rept,1985

ML20203P894
Person / Time
Site:	Indian Point
Issue date:	12/31/1985
From:	CONSOLIDATED EDISON CO. OF NEW YORK, INC., POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
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.I Annual lI l Radiological Environmental I Operating Report Ll l

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Indian Point Nuclear Generating Station Units 1,2 and 3

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I fr.nuary 1 - December 31 1985

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I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT i

I CONSOLIDATED EDISON COMPANY OF NEW YORK, IdC.

NEW YORK POWER AUTHORITY l

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I INDIAN POINT NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 l

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I m eARY 1 . OECE.ER 31 1985 I

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TABLE OF CONTENTS SECTION TITLE PAGE LIST OF FIGURES ........................................ iii LIST OF TABLES ......................................... iv

1. EXECUTIVE

SUMMARY

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2. INTRODUCTION ........................................... 2-1 I 2.1 2.2 2.3 SITE DESCRIPTION .................................

SCOPE ............................................

STATISTICAL AND CALCULATIONAL METHODOLOGY ........

2-1 2-1 2-2 2.3.1 ESTIMATION OF THE MEAN VALUE, x . . . . . . . . . 2-2 I 2.3.2 2.3.3 2.3.4 LOWER LIMIT OF DETECTION (LLD) ..........

TREND ANALYSIS ..........................

CHART F0RMATS............................

2-3 2-4 2-5 2.3.5 TABLE STATISTICS......................... 2-6

3. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS 3-1 I

AND DISCUSSION ..........................................

3.1 DIRECT CAMMA RADIATION............................. 3-2 3.2 AIRBORNE PARTICULATES AND RADIOIODINE . . . . . . . . . . . . . 3-2 3.3 HUDSON RIVER WATER ................................ 3-3 I 3.4 3.5 3.6 DRINKING WATER ....................................

HUDSON RIVER SHORELINE SOIL .......................

BROAD LEAF VEGETATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3-3 3-3 3-4 3.7 HUDSON RIVER FISH AND INVERTEBRATES................ 3-4 I 3.8 3.9 FOO D P RODU CT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

AQUATIC VEGETATION.............. ..................

3-4 3-4 )

3.10 HUDSON RIVER BOTTOM SEDIMENT....................... 3-5 I 3.11 PRECIPITATION......................................

3.12 SOIL ..............................................

3-5 3-5  ;

4. DOSIMETRIC EVALUATION .................................. 4-1

5. QUALITY ASGRANCE ...................................... 5-1

6. REFERENCc.S ............................................. 6-1 l I

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I TABLE OF CONTENTS (CONTINUED)

SECTION TITLE PAGE APPENDICES A. ENVIRONMENTAL SAMPLE STATION LOCATIONS ................. A-1 B. ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS ....... B-1 C. ENVIRONMENTAL SAMPLE AND ANALYSIS PROCEDURES ........... C-1 I C.1 C.2 C.3 HUDSON RIVER WATER ...............................

HUDSON RIVER AQUATIC VEGETATION ..................

HUDSON RIVER BOTTOM SEDIMENT (INCLUDING BENTHOS)..

C-1 C-1 C-1 C.4 HUDSON RIVER SHORELINE SOIL ...................... C-2 I C.5 C.7 C.8 HUDSON RIVER FISH AND INVERTEBRATES...............

PRECIPITATION (FALLOUT) ..........................

DRINKING WATER ...................................

C-2 C-2 C-2 I C.9 AIRBORNE PARTICULATES AND RADI0 IODINE ............

C.13 SOIL .............................................

C.14 MILK .............................................

C-2 C-2 C-3 C.15 BROAD LEAF VEGETATION ............................ C-3 I C.17 DIRECT GAMMA (TLD) ................................ C-3 C.18 LAND USE CENSUS ................................... C-3 I D. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS D.1 1985 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING

SUMMARY

.. D-2 D-2 I

PROGRAM

SUMMARY

D.2 LAND USE CENSUS ................................... D-3 D.3 SAMPLING DEVIATIONS ............................... D-3 D.4 ANALYTICAL DEVIATIONS ............................. D-3 I E. HISTORICAL TRENDS ........................................ E-1 F. EPA INTERLABORATORY COMPARISON PROGRAM ................... F-1 G. CONTRACTOR QUALITY ASSURANCE PROGRAMS .................... G-1 I

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I FIGURE TITLE PAGE I A-1 A-2 Environmental Sample Station Locations (Within Two Mile s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-5 Environmental Sample Station Locations (Gre at e r than two mile s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-6 E-1 Direct Radiation, Summary By Year................... E-3 E-2 Direct Radiation, 1978 to 1985, I E-3 E-4 Standard Normal Deviate............................. E-4 Gross Beta Radioactivity in Air, 1975 to 1985....... E-6 Gross Beta Radioactivity in Air, S t andard Normal D eviate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-7 I E-5 E-6 Cs-137 Radioactivity in Air, 1975 to 1985........... E-8 Cs-137 Radioactivity in Air, Standard Normal Deviate............................. E-9 E-7 Tritium in Hudson River Water, 19 7 5 to 19 85. . . . . . . . . E-11 I E-8 Tritium in Hudson River Water, S tandard No rmal Deviat e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-12 E-9 Tritium in Drinking Water, 1975 to 1985............. E-14 I E-10 Tritium in Drinking Water, S tandard No rmal Deviat e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-15 E-11 Cs-134 and Cs-137 in Shoreline Soil, I E-12 1975 to 1985........................................ E-17 Cs-134 and Cs-137 in Shoreline Soil, S t and a r d No rma l D eviat e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-18 I E-13 E-14 Radioactivity in Broad Leaf Vegetation, 1975 or 1985........................................ E-20 Radioactivity in Broad Leaf Vegetation, S t and ar d N o rma l D ev i a t e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-21 I E-15 E-16 Cs-137 in Fish and Invertebratrs, 1975 to 1985...... E-23 Cs-137 in Fish and Invertebrates, S tandard Normal Devia te . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-24 I

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LIST OF TABLES I TABLE TITLE PAGE A-1 Sampling Station Locations ......................... A-1 B-1 Radiological Ef fluent Technical Specifications. . . . . . B-2 B-2 Detection Capabilities for Environmental Sar.ple Analysis............................................ B-9 D-1 Summary of Sampling Deviations, 1985................ D-4 D-2 Direct Radiation, Inner Ring,........................ D-5 I D-3 D-4 Direc t Radiation , Outer Ring . . . . . . . . . . . . . . . . . . . . . . . . D-6 Direct Radiation, Special Interest and Control Location.................................... D-7 D-5 Quarterly Direct Radiation, Annual I D-6 D-7 S umma ry , 19 8 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D - 8 Radionuclide s in Air, Annual Summary , 1985. . . . . . . . . . D-9 Radioactivity in Hudson River Inlet (Wal) and Discharge (Wa2) Water, Annual Summary, 1985......... D-10 D-8 Radioactivity in Campfield (Wb 1) and Roseton Drinking Water , Annual Summary , 1985. . . . . . . . . . . . . . . . D-11 I D-9 D-10 Radioactivity in Shoreline Soils, Annual Summary, 1985....................................... D-12 Radioactivity in Broad Leaf Vegetation, Annual I D-11 Summary, 1985....................................... D-13 Radioactivity in Fish and Invertebrates, Annual Summary, 1985................................ D-14 E-1 Direct Radiation Annual Summary, 1978 to 1985....... E-2 E-2 Radionuclides in Air, 1975 to 1985.................. E-5 E-3 Radionuclides in Hudson River Water,1975 to 1985. .. E-10 I E-4 E-5 Radionuclides in Drinking Water, 1975 to 1985.......

Radionuclides in Hudson River Shoreline Soil, 1975 to 1985........................................ E-16 E-13 E-6 Radionuclides in Broad Leaf Vegetation, I E-7 1975 to 1985........................................ E-19 Radionuclides in Fish an Invertebrates.............. E-22 F-1 US EPA Cross-Check Program 1985..................... F-2 I

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SECTION 1.

EXECUTIVE

SUMMARY

I This Annual Radiological Environmental Operating Report describes the 1985 Radiological Environmental Monitoring Program (REMP) for the Indian I Point Units 1 and 2 owned and operated by the Consolidated Edison Company of N.Y. , and Unit 3, ovned and operated by the New York Power Authority, and the results of that program.

Direct radiation was measured by means of Thermoluminescent Dosimeters (TLDs). Direct radiation pathways include direct radiation from I

buildings and structures of the plant, t irborne materials that might be released from the plant, cosmic radiation, and naturally occurring radioactive materials in soil, air, and water. The resulta of TLD measurements were consistent with historical averages.

The Hudson River media consists of river water, fish and invertebrates.

During 1985, there were no apparent increases in radionuclide concentrations in these media as a result of the operation of the Indian Point plants.

The primary internal exposure pathwsys from radionuclides consist of I airborne radionuclides which might be breathed, airborne radionuclides which are " washed out" of the atmosphere in precipitation, radionuclides present in drinking water and the direct food pathways. No analysis I results indicated increasing trends in any of these media which were attributable to the Indian Point Station.

identified for Indian Point in 1985).

(No milk pathway was I Overall concentrations of nuclides detected in the vicinity of the Indian Point Site were well within the ranges of historical background concentrations for those nuclides. Positive indications of fission I products were at background levels and were from atmospheric weapons testing. This conclusion was supported by the lack of related short lived fission products such as Cs-134. All positive indications were also less than reporting levels specified by the Nuclear Regulatory Commission (NRC).

The report describes established sampling station locations, requirements of the REMP, environmental sampling and analysis procedures. It summarizes and discusses the results of the 1985 program, and the Indian Point Radiological Environmental Monitoring Quality Assurance Program.

The specific sampling locations are described in Appendix A. All pre-1985 Environmental Technical Specification Requirements (ETSR) program stations have been eliminated from Table A-1 unless they are I current Radiological Effluent Technical Specification (RETS) program sample locations.

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I I l The Radiological Ef fluent Technical Specifications (RETS) , instituted in July of 1984, were in effect for all of 1985. The RETS have completely repIsced the former Environmental Technical Specifications (ETSR). As shown in Table in D-1, 99% of the required RETS samples were collected.

I Within the context of the very large numb er of samples which were collected and analyzed, significant.

the few uncollectable samples were not In addition, the sampling frequency for some media was j higher than that required by the RETS, and sampling and analyses were I

j performed at additional sampling locations which were in excess of the RETS requirements. Quality Assurance was practiced at all stages of the j program, and its results were satisfactory as shown in Section 5.

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I UCTION

. 2.1 SITE DESCRIPTION The Indian Point site occupies 739 acres on the east bank of the Hudson River on a point of land at Mile Point 42.6. The site is in the Village I of Buchanan in upper Westchester County of New York State. Three nuclear reactors, Indian Point Unit Nos. 1, 2 and 3, and associated buildings occupy 35 acres near the southern end of the site. Indian Point Unit 1, I owned by Consolidated Edison, has been retired as a generating facility.

Unit 2 is owned and operated by Consolidated Edison; Unit 3 is owned and operated by the New York Power Authority.

I 2.2 SCOPE h

5 An environmental surveillance program has been conducted at the Indian Point Nuclear Generating Station since 1958, four years prior to start-up of Unit No. 3 (initial criticality attained on August 2, 1962). The r purpose of th e pre-operational program was to determine natural background radioactivity and to measure the variations in activities that may be expected from natural sources, fallout f rom nuclear weapons tests, and other sources in the vicinity.

The current operational program is designed to meet two primary objectives. The first objective was to establish a sampling schedule for I the Indian Point site and vicinity, which would enable changes in the radioactivity in the area to be identified. The environmental sampling schedule requires that analyses be conducted for specific environmental media on a regular basis. (See Appendices A, B, and C.) Rou tine I evaluation of analytical results permits the radioactivity profile of the environment to be established and monitored.

I Environmental ample locations are divided into indicator locations and control locations. Indicator locations are established near the site, where the presence of environmental radioactivity of plant origin is most likely be detected. Control locations are established away from the I plant, where the presence of environmental radioactivity most likely reflects naturally occurring radioactivity or radioactive fallout from nuclear weapons testing. Comparison of measured radionuclide concen-I trations from indicator locations to those at control locations is a method of identifying the presence of environmental radioactivity of plant origin above background (naturally occurring or fallout from nuclear weapons testing) environmental radioactivity.

The second objective of the Radiological Environmental Monitoring Program (REMP) was to verify projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radioactive materials from the Indian Point site. Effluent releases from the plant were kept to the lowest level practicable. All releases 2-1 I

I (liquids and gases) from the Indian Point site were monitored, accounted I for, and reported semi-annually as required by the United States Nuclear Regulatory Commission. Based on predictive models for plant releases, environmental concentrations should be undetectable in most cases. The I presence of residual radioactivity from atmospheric bomb tests and naturally occurring radioactivity were the predominant sources of radioactivity in samples. Their presence interferes with the detection of the predicted low level concentrations due to plant operations.

This report contains the results of the REMP conducted at Indian Point for the reporting period of January 1 to December 31, 1985. This was the first full year in which the REMP was operated under the Radiological Effluent Technical Specifications.

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY There were two basic statistical calculations applied to the raw data resulting from the environmental sample analysis program for the Indian I Point site. The first calculations involved the determination of the mean value for the indicator and the control samples for each sample medium.

The second calculation was the Shewhart Control Chart Analysis of data to discern indications of data trends.

I historical methodologies are discussed in the following sections.

These Data for the REMP were found to be normally distributed and wera analyzed accordingly.

2.3.1 ESTIMATION OF THE MEAN VALUE, x I The mean, (x), and standard deviation, (s) are widely used statistical methods for describing characteristics of a sampled population.

These statistical values were used in the reduction of the data generated by the sampling and analysis of the various media in the Indian Point I Radiological Environmental Monitorin,g Program. The following equations were utilized to estimate the mean (X) and the standard deviation (s):

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Ex g (Equation 2-1)

X= i=1 ,x >0 l

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where, X = estimate of the mean i = individual sample, i.

N = total number of samples with positive indications.

K g= Value for sample i above the lower limit. of detection.

I N 1/2

[ I(xg - Ic) \

s=i i=1 ,x g>0 (Equation 2-2)

\ N I where, s = standard deviation for the sample.

These equations were used in the reduction of the 1985 Radiological Environmental Monitoring Data.

Note that the statistic for the mean using only positive values tends to strongly bias the averages high, particularly when few of the data are measureably positive. Most of the data for this report reflect the small I number of positive values. Exceptions to this case are direct radiation measured by TLDs ,snd gross beta radioactivity in air which showed positive indications related to naturally occurring radionuclides.

Also, the standard deviation is calculated for the sample set (using N) rather than as an estimate of the population standard deviation (using N-1).

All statistical deviations reported are one sample standard deviation.

Many samples were reported by the analytical laboratory as "Less than I LLD" with a quoted LLD value for that analysis. These are interpreted in the tables as the ("LT value")/4.66. This value is shown in the tables in the Std. Dev. column and the sample value column is blank or indicates not detected above LLD.

I 2.3.2 LOWER LIMIT OF DETECTION (LLD)

I The LLD is a predetermined concentration or activity level used to establish a detection limit for the analytical procedure.

The LLDs are specified by the Nucle 2r Regulatory Commission for each radionuclide in specific media, and ate determined by taking into account overall measurement methods. Varisales included (but were not limited to):

1) instrument characteristics (e.g. background and efficiency)

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3) counting time

4) media density (self-absorption)

5) radioactive decay

6) chemical yield Ia the RETS program, LLDs are used to ensure that minimum acceptable detection capabilities are met with specified statistical confidence Table B-2 presents the LLDs used in the RETS programs for I

levels.

required media and radionuclides as specified by the NRC.

2.3.3 Trend Analysis In 1985 trend analysis is based on Shewhart Control Charts. Data contained in Shewhart control charts in this report are displayed as

' I points about a historical mean. Data for the historical means for trending were found to be normally distributed and all charts in this report use the normal distribution. The control charts are used to display the deviation of annual mean values from the 10 year historical mean.

I Deviations are normalized to the historical standard deviation for the period. These charts give visual evidence of trending and eliminate bias based on the variability of the data itself.

Historical averages are based on the period 1975 to 1984, a 10 year period. Since zero values are not generated by the analytical techniques used, only positive values are averaged.

Historical standard deviation is the sample standard deviation for the same period, 1975 to 1984. The devisor is N, not N-1. This, the'refore, I determines the standard deviation for the set of data points being averaged and not the estimated deviation of the population of data points.

Trend analysis is based on Shewhart control chart rules. A normal distribution is assumed. Since the charted values are averages, this is a reasonable assumption. Charts are plotted with i four standard deviations of the annual mean values.

When there is no trend, the data will be within plus or minus two standard deviations approximately 95% of the time. Any single point above the +3 standard deviation line indicates a significant increase from the historical mean. Two points in a row above the 2 standard deviation line also indicates an increase. Note that with the averaging used for the immediate prior 10 year period, historic means and historic standard deviation change each year.

Trends are statistically valid when several points in a row are statistically increasing or decreasing.

When an unexpected value or "special cause" is indicated by one of the tests described, the point on the chart is marked with a cross. The presence of the cross on the chart indicates that the data are not statistically "in control" and that a change in the data has occurred that is very unlikely without some special cause. Special causes may 2-4

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include normal radioactive decay, fallout from nuclear weapons testing, I releases to the environment by plant operations, transfer or relocation of radioactive materials by active transport processes, or experimental or analytical error.

The equation for the value of the standard normal deviate is given by s =

(x - ()

s h

where x is the average for the year in question.

• h ir the historical average for the previous ten years, and s is the historical standard deviation for the same 10 year time h

period.

The historical average is 1984

(=5Ix g i = 1975 The historical standard deviation is calculated using (N I x g - (Exg ) ) 1/2 N

wherethesummationoverNistakenoverthesamerangeasgivenfork, 2.3.4 Chart Formats Bar charts are used to plot the concentration data. Charts are generally scaled to a full scale value of ten times the required lower limit of detection for the nuclide in question. This displays all data relative to the detection sensitivity. In all cases except I-131 (which was not detected in 1985) this is also a convenient method of showing relative concentration importance as well.

Like nuclides are plotted on the same chart. For example Co-60 and Co-58 along with controls are shown together. In all cases, these paired nuclide have similar LLDs. For unpaired nuclides, indicator and control sample concentration are shown together where appropriate.

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Line charts are used for Standard Normal Deviate Charts. Lines are used to connect consecutive points but not for points that are not consecutive.

2.3.5 Table Statistics Averages in the tables are average of positive values only. Samples listed with "LT" values or "<LLD" valuer are not included in the averages.

Standard deviations for reported analytical values are shown at one standard deviation in the body of the table. For values reported as less than the stated analytical lower limit of detection, this value shown has been divided by 4.66 to estimate one standard deviation for the analysis.

I In table summaries ani averages, when three or more values appear in the positive result column, the standard deviation is based only on those values (using N) . When fewer than three positive values occur for a sample category the estimated deviation is based on the square root of the sum of the squares of the indicated deviations divided by N. This provides the best estimator of the analytical sensitivity for the sample category.

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SECTION 3.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS AND DISCUSSION I Data in Sections 3.1 - 3.12 support the conclusion that there were no significant plant related radionuclides in the environmental media around the Indian Point Station during 1985. Similarily, there were no significant increases in ambient background radiation levels in the surrounding area I attributable to station operations.

The Radiological Environmental Monitoring Program (REMP) conducted at Indian I Point was in accordance with the Radiological Effluent Technical Specifications (RETS). The RETS contain requirements regarding the number distribution of sampling locations, the types of samples which must be obtained, and and types of analysis which must be performed for measurement of radioactivity. This was the first full year in which the RETS was implemented in place of the former Environmental Technical Specification Requirements (EISR).

The Radiological Environmental Monitoring Program at Indian Point includes measurements of radioactivity levels in the following environmental pathways.

o Hudson River - water, aquatic vegetation (Non-RETS), bottom sediments (Non-RETS), shoreline soils, fish and invertebrates.

o Airborne particulates and radiciodine o Precipitation (Non-RETS) o Drinking water o Milk / Food products o Terrestrial broad leaf vegetation o Soil (Non-RETS) o Direct gamma radiation In addition, a milch animal census is conducted annually, as described in Section D.2. This census provides current information on the location of milk producing animals near the Indian Point Site.

Appendices A, B, and C provide additional information regarding the I environmental sampling locations, sampling and analysis requirements, and a description of the sampling and analysis procedures to implement the pro gram respectively.

I Sections 3.1 - 3.12 present discussions of the results, by medium, and provide an interpretation of them and an estimate of their significance.

appropriate, comparisons were made between indicator and control locations, and As between 1985 and historical measurements of the same medium. Historical trends focused on the last ten years of data f rom Annual Radiological Environmental Operating Reports.

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I The discussion of each medium includes a distillation of the results in Appendix D. It should be noted that omitted from some of these tables were identified naturally-ocurring (i.e., cosmic ray induced or geologically derived) radionuclides: Be-7, K-40, Ra-226, and Th-228. Concentrations of these radionuclides at the indicator sites were comparable to those at the control sites. Since their presence was unrelated to the operation of the Indian Point site, these results were not discussed further. Also omitted from the tables are the lists of undetected gamma emitters for which results are reported as "LT" I values.

During 1985, H-3 and Cs-137 were the only potentially reactor-related radionuclides detected in the required samples. Cs-134 and Cs-137 are products of uranium atom fission. Since Cs-134 has a significantly shorter half-life than Cs-137, any concentrations of Cs-137 attributable to current plant releases should be accompanied by the short-lived isotope Cs-134. The absence of Cs-134 tends to "date" the radionuclide's presence to weapons testing and residual concentrations.

3.1 DIRECT R)DIATION Direct gamma radiation at locations in the vicinity of the Indian Point I Station was measured on a year-round basis using integrating calcium sulfate (CaSO4 ) thermoluminescent dosimeters (TLDs). TLDS comprehensive measurements of background radiation because they are provide continuously posted and thus represent the total integrated exposures for the time period of emplacement (i.e. , mrem per quarter) .

Two TLD holders were posted at each location and each holder normally contained one TLD. The TLDs were changed quarterly. Results of quarterly measurements for 1985 are presented in Tables D-2 through D-4. Means and standard deviations are also presented, both by location and quarter. All results were normalized to a 91.2 day quarter. Previous annual averages were calculated and were compared with the 1985 averages in Table E-1.

From examination of Tables D-2 through D-4, it is clear that there was no ambient radiation level increase from 1984 to 1985. The 1985 average of i 14.7 1 1.0 mrem / quarter for all locations was essentially equal to the 1984 l average of 14.212.3. Furthermore, there was no increase in the measured l I

dose equivalents over the eight years 1977-1985 as supported by the I calculation and plot of the standard normal deviate, shown in Figure E-2.

The 1985 TLD program produced a clear, consistent picture of the ambient I radiation levels in the area around Indian Point. No increase in levels was observed between 1984 and 1985, or over the years 1977-1985 (328 total samples).

3.2 AIRBORNE PARTICULATES AND RADIOIODINE In 1985, 415 weekly indicator and 52 weekly control air particulate samples I

l were collected and analyzed by gamma spectroscopy and for gross beta. '

Samples were composited quarterly for gamma spectroscopy.

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I The results of the 1985 sampling and analysis are summarized in Table D-6.

I Radionuclides detected with gross beta measurements were predominated by naturally occuring isotopes, iesulting in no significant measurements attributable to plant operations. The mean concentration for gross beta measured at indicator locations was no different than the mean concentration measured at the control location. Table E-2 lists mean annual concentration over the past 10 years.

Based on data collected in 1985, there was no detectable air particulate radioactivity due to Indian Point Nuclear Plant operations.

In 1985, 415 weekly charcoal cartridges along with 52 weekly control cartridges were collected and analyzed for I-131. As shown in Tables D-6, I-131 was not detected in the charcoal cartridges, precluding any impact on the environment due to plant operations.

3.3 HUDSON RIVER WATER Twenty four (24) gamma spectra, and eight (8) tritium analyses were performed on Hudson River water during 1985. Tables D-7 and D-8 summarize the radionuclides detected. The only potential reactor related radionuclide positively measured was tritium. Tritium has been detected in all ten years from 1976-1985, in concentrations ranging from 290 (1977) to 870 (1985) pCi/L (Table E-3) . In 1985 tritium was only detected in the discharge canal third qurrter composite of monthly samples. The average concentret'on for the third quarter was 870 pCi/1, which was witnin the historical t . n e;e . The plot of standard normal deviate (Figure E-8) indicates that chis result is potentially above expected levels, although the average appears high because it is based upon only one positive result out of four samples. The other three quarterly samples for this location were less than LLD. Even though one point on the curve does not indicate a trend, and future results from this station will be noted to identify any I trends.

3.4 DRINKING WATER No concentrations of radioactive materials ascribable to plant operations were observed in drinking water in 1985. No radionuclides were detected in 16 gamma spectrum analyses of water from nearby reservoirs. The tritium concentration of the quarterly samples was less than the LLD. In the previous ten years a decreasing trend in drinking water tritium concentration has been apparent, which is consistent with measurements of weapons test residual trituim. Based on the plot of standard normal deviate (Figure E-10), no apparent trend is identifiable from 1984 to 1985.

The average gross beta concentration of 3.3 pCi/t was quite low and, in fact, below the LLD (4 pCi/1) for this media.

3.5 HUDSON RIVER SHORELINE SOIL In 1985, eight indicator samples and two control samples of shoreline soil were obtained and analyzed. Measured radionuclide concentrations which I resulted from the analyses are listed in Table D-9. Of three potential reactor products which have been observed historically, only Cs-137 was observed in 1985.

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, Cs-137 levels in 1985 were generally consistent with, or lower than, previous years wi;h the exception of the September sample from Verplanck.

Although the concentration found was higher than in previous data at this location, Cs-134 was not detected in the sample. One would expect that both Cs-137 and Cs-134 would be detected in radioactivity attributable to recent releases from Indian Point. There fore , this result is due to variability in background Cs-137 concentrations and is not related to plant operations in 1985.

There was no increase in the activity of Hudson River shoreline soils related to plant activities.

3.6 BROAD LEAF VEGETATION Broadleaf vegetation samples were collected near the Indian Point Station as required by the RETS. Results of the analyses from 36 indicators and 18 control locations are summarized in Tables D-10. Cs-13/ was detected in samples from Camp Smith in August and September. There did not appear to be any correlation of these sample results with plant conditions, and the highest value of 217 pCi/kg was well below the reporting level of 2,000 pCi/kg. The most likely explanation for these results is that Cs-137 was incorporated into plant tissues, with the absence of Cs-134 confirming that it is unlikely the radioactivity was released from Indian Point. The plot of standard normal deviate (Fig E-16) does not indicate any increasing or decreasing trend of concentration in vegetation.

3.7 FISH AND INVERTEBRATES I Cs-137 was the only gamma emitting radionuclide detected in fish and invertebrates during 1985. Sixteen indicator samples and 16 control samples were analyzed and these results are summarized in Tables D-11.

Results froa control samples indicate, as in the past, that background levels of Cs-137 persist due to residual radioactivity produced by previous l nuclear weapons testing and residual concentrations, and these levels did '

not vary appreciably in 1985 (see Table E-7). The absence of Cs-134 is an additional indication that 1985 plant discharges did not contribute to Cs-137 levels in fish and invertebrates. l l

3.8 FOOD PRODUCTS Sampling and analysis of food products is presented and discussed in Section 3.6, " Broad Leaf Vegetation". Broad leaf vegetation was also collected in lieu of milk during 1985 because there were no milch animals producing milk for human consumption within eight kilometers of the plant.

3.9 AQUATIC VEGETATION Even though aquatic vegetation was not required to be sampled by the RETS during 1985 four special indicator and three control station rsmples were collected and analyzed. No increase in concentrations due to plant operations in 1985 was discernible from these measurements. Since these samples were not required by RETS, tables and graphs are not presented for I these data.

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3.10 HUDSON RIVER SEDIMENTS Even though sampling and analysis of Hudson River sediments was not required by the RETS, during 1985 six indicator and two control station samples were collected and analyzed. There has been no buildup of radioactivity in Hudson River sediments. Since these samples were not required by RETS, tables and graphs are not presented for these data.

3.11 PRECIPITATION Even though sampling and analysis of precipitation was not required in 1985 by the RETS, although during 1985 quarterly composites from both indicator and control locations were analyzed for gamma emitters and for tritium. No gamma emitters other than naturally occurring radionuclides and no tritium concentration greater than LLD were detected during 1985. Since these samples were not required by FITS, tables and graphs are not presented for these data.

3.12 SOIL Even though sampling and analysis of soil for gamma emitting radionuclides I was not required in 1985 by the RETS, samples were collected from one control and two indicator stations. These results showed no accumulation of radionuclides in soil related to the operation of the Indian Point Statien. Since these samples were not required by RETS, tables and graphs are not presented for these data.

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SECTION 4 DOSIMETRIC EVALUATION I One of the objectives of the Radiological Environmental Monitoring Program was to verify the projected and anticipated radioactivity concentrations in the environment and related exposures from releases of radioactive materials from the Indian Point Unit Nos. 1, 2, and 3. The preceding discussions have detailed the observations of radiation and concentrations of radionuclides in various environmental media around the Indian Point Site. Conclusions which can be drawn from the discussions are

1) The measured concentrations of radionuclides in the environmental media were not increasing; and

2) The concentrations of radionuclides measured were within the background range for these radionuclides.

Any calculated doses which are based on the measured concentrations of radionuclides are primarily attributable to background radiation.

Coneequently, there was no meaningful dose to man as a result of the I plant's operation.

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SECTION 5.

I QUALITY ASSURANCE Sampling and analysis of environmental media at Indian Point were conducted I in accordance with quality assurance requirements specified in Regulatory Guide 4.15 (Reference 12) and in internal procedures (Reference 2). The annual review of the Radiological Environmental Monitoring program con-I sisted of the following:

Audit of all Indian Point and radioanalytical contractor pro-I cedures related to the Radiological Environmental Monitoring Program by Quality Assurance and Reliability (QA&R) personnel and NRC personnel.

Audit of Indian Point sample collections and radionnalytical contractor laboratory techniques by QA&R personnel and NRC per-sonnel.

Submission for analysis of duplicate (split) samples to the radioanalytical contractor to verify reproducibility (precision) of results.

Submission for analysis of environmental samples spiked with known levels of radioactivity to the radioanalytical contrcctor to verify accuracy of results.

Assessment of the radioanalytical contractor's performance in I the Environmental Prctection Agency (EPA) Interlaboratory Com-parison Study (Appendix F).

Audit of the 1985 Radiological Environmental Monitoring Program demon-I strated that sampling and analysis of environmental media were conducted by qualified technicians, in accordance with approved procedures, to ensure reproducibility and consis tency of analytical techniques. Adherence to I internal procedure requirements ensured that the program met or exceeded requirements stated in the Radiological Ef fluent Technical Specifications for Indian Point Station.

Review of the quality assurance program of Teledyne Isotopes demonstrated that all requirements specified in 10CFR Part 50 Appendbc B and Regulatory Guide 4.15 were achieved. In addition, Teledyne Isotopes performance in the EPA Interlaboratory Comparison Study was completely satisfactory; 81 out of 85 measurements were in agreement (see Appendix F). The content of Teledyne Isotopes' internal quality assurance program is discussed in Appendix G.

In summary, the quality assurance program conducted in conjunction with the Indian Point Environmental Monitoring Program included audits and evalua-I tions of in-house and contractor procedures, work functions, and quality assurance programs. Review of the 1985 quality assurance program indicated that the Radiological Environmental Monitoring Program was performed in accordance with the Radiological Effluent Technical Specifications.

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I SECTION 6.

REFERENCES I

I 1. " Radiological Effluent Technical Specifications" for Indian Point Nuclear Generating Stations, 1,2, and 3.

2. Consolidated Edison Company of N.Y. Environmental Health & Safety I Dept.

Station.

Nuclear Environmental Monitoring Procedures, Indian Point

3. Environmental Analytical Procedures, Teledyne Isotopes, Inc., 50 Van Buren Avenue, Westwood, New Jersey, 07675.

I 4.. Nuclear Environmental Monitoring Sample and Analysis Guide, Environ-mental Health and Safety Department, Consolidated Edison, Rev. O, 08/24/84. (EHS 5.101) .

I 5. United States Nuclear Regulatory Commission. Regulatory Guide 4.8,

" Environmental Technical Specifications for Nuclear Power Plants",

December 1975.

6. M. Eisenbud, Environmental Radioactivity. Academic Press, New York (1973).

7. S. Glasstone and W. H. Jordan, Nuclear Power and Its Environmental Effects, American Nuclear Society, La Grange Park, IL (1980).

I 8. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1", U. S. NRC Regulatory Guide 1.109, Revision 1 (1977).

9. Cohen, N. and Eisenbud, M., " Radiological Studies of the Hudson River, Progress Report," Institute of Environmental Medicine, New York University Medical Center (December 1983).

I 10. Consolidated Edison Company of New York, Environmental Health and Safety Procedure, EHS-5.121, July 1,1984, " Quality Control Program",

February 1984.

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11. " Quality Assurance Manual Environmental Analysis Department".

Teledyne Isotopes Westwood, N.J.

12. United States Nuclear Regulatory Commission. Regulatory Guide 4.15, Revision 1 " Quality Assurance for Radiological Monitoring Programs I (Normal Operations) - Ef fluent Streams And The Environment", February 1979.

13. EPA Interlaboratory Comparison Program Performance Results 1985, Teledyne Isotopes, Westwood, New Jersey.

14. J. W. Poston, " Cesium-137 and Other Man-Made Radionuclides in the I Hudson River: A Review of the Available Literature," Applied Physical Technology, Inc.', report to NYPA, September, 1977.

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15. U.S. Environmental Protection Agency Report EPA-520/1 80-012,

" Upgrading Environmental Radiation Data," August 1980.

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16. Andrews, Howard L. and Lapp, Ralph E. Nuclear Radiation Physics, Prentice-Hall, Inc., Englewood Cliffs, New Jersey, 1972.

17. Nelson, Lloyd S., "The Shewhart Control Chart - Tests for Special Catises, " Journal of Quality Control, Vol. 16, No. 4, PP 237-9, (Oct.

I 15d4).

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I APPENDIX A ENVIRONMENTAL SAMPLE STATION LOCATIONS I

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TABLE A-1 INDIAN POINT STATION - SAMPLING STATION LOCATIONS I RETS Sampling Sample Station Location / Distances Designation Sample Types I A-2 2 Standard Brands, Air Particulate 0.6 MI - NNE A-2 Radiciodine Direct Gamma I 3 Service Building, Onsite - SSE DR-08 Direct Gamma 4 Algonquin Gas Line, A-1 Air Particulate 0.25 MI - SW A-1 Radiciodine I 5 NYU Tower, 1 MI - SSW A-4 A-4 DR-10 Air Particulate Radiciodine Direct Gamma

'I Ic-1 Soil Broadleaf Vegetation 6 Camp Smith, 2.5 MI - NNE Soil Ic-2 Broadleaf Vegetation I 7 Camp Field Reservoir, 3.5 MI - NE Wb-1 Drinking Water 9

I HR" Water Inlet pipe into plants, NE Wa-1 10 Discharge Canal, Onsite - SW Wa-2 HR" Water I

Water Meter House, I

14 DR-7 Direct Gamma Onsite - SE 17 Off Verplanck, 1 MI- SSW HR" Aquatic Vegetation HR" Shoreline Soil 20 Montrose Marina, 1.5 M1 S I DR-38 Direct Gamina 22 Lovett, 1.5 MI - WSW Air Particulate Radioiodine I

A-1

I TABLE-A-1 CONTINUED RETS Sampling Sample Station Location / Distances Designation Sample Types I 23 Rosecon, 20 MI - N Precipitation,b b A-5 Air Particulgte, I A-5 DR-40 Radioiodine, Direct Gamma,b Broadleaf Vegetation Id-3 Soil 25 Where available Ib 1&2 Fish / Invertebrates I 27 Croton Point, 6.4 MI - SSE DR-24 Air Particulate Radioiodine Direct Gamma 28 Lent's Cove. 0.5 MI - ENE HR" Shoreline Soil DR-4 Direct Gamma I 29 Grassy Point, 3.3 MI SSW DR-39 Air Particulate Radioiodine Direct Gere I 33 Hamilton St. SS, 3 MI - NE DR-33 Direct Gamma 34 SE Corner Onsite SE DR-9 Direct Gamma 35 Bleakley & Broadway, DR-5 Direct Gamma Onsite - E 38 Furnace Dock, 3.5 MI - SE DR-34 Direct Gamma I 44 Peekskill Gas Holder Bldg., Precipitation I 1.7 MI NE Air Particulate Radioiodine 50 Manitou Inlet, 4.5 MI NNW Wc-2 HR" Shoreline Soil (control) 1 53 White Beach,, 0.9 MI - SW Wc-1 HR Shoreline Soil DR- 11 Direct Gamma I 1 I l l

A-2

I TABLE A-1 (CONTINUED)

Sampling Sample Station Location / Distances Designation Sample Typcs 56 Verplanck 1.3 MI SSW DR-37 Direct Gamma I 57 Cortlandt Sanitation Garage, 2 MI - N A-3 A-3 DF-1 Air Particulate Radioiodine Direct Gamma 58 Rt. 90 Garrison, 5 MI N DR 17 Direct Gamma 59 Old Pemart Avenue Pole DR-2 Direct Gamma 1.8 MI - NNE I 60 Gallows Hill Road CH G&M Pole #6639F, 5 MI - NNE DR-18 Direct Gamma 61 Lower South St. & Bay St DR-36 Direct Gamma NYT Pole #17, 1.3 MI - NE 62 Westbrook Drive Pole #CP2, DR-19 Direct Gamma E 5 MI - NE I 64 Pine Road - Cortlandt, 4.8 MI - ENE DR-20 Direct Gamma 66 Croton Avenue - Cortlandt DR-21 Direct Gamma Pole #NYT-A, 5 MI E 67 Colabaugh Pond Road DR-22 Direct Gamma I Cortlandt Pole #30, 5 MI - ESE l

69 Mt. Airy & Windsor Road DR-23 Direct Gamma Pola #W-66-2-40, 5 MI - SE 71 Warren Ave - Haverstraw, DR-25 Direct Gamma l 4.8 MI - S 72 Railroad Avenue & 9W DR-26 Direct Gamma Haverstraw, 4.6 MI - SSW 73 Willow Grove Rd. & Birch Dr. DR-27 Direct Gamma 5 MI - SW I

74 I DR-12 Direct Gamma Gays Hill Road S, 1.5 MI - WSW A-3 l

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TABLE A-1 CONTINUED RETS Sampling Sample Station Location / Distances Designation Sample Types 75 Sign (hT and NJ) Palisades DR 28 Direct Gamma Parkway Southbound, I 5 Mi - WSW 76 Gays Hill Road N, DR-13 Direct Gamma 1.2 MI W 77 Palisades Parkway, DR-29 Direct Gamma

4. 2 MI - W 78 Rt. 9W Pirates Cove - DR-14 Direct Gamma Pole #0&R 233, 1.2 MI -Whv 79 Anthony Wayne Park, DR-30 Direct Gamna 4.5 MI - WhN 80 Rt. 9W South of Ayers Road DR-15 Direct Gamma Pole ih7T 255,1 MI - hv I 81 Palisades Parkway Lake Welch DR-31 Exit, 4. 7 MI - NW Direct Gamma I 82 Ayers Road Pole 1 MI - Nhv DR-16 Direct Gamma 83 Rt. 9W Fort Montgomery DR-32 Direct Gamma Pole #142, 5 MI - Nhv 84 Cold Spring, 10.8 MI - N H.R. Aquatic Vegetation I 85 Amicus Reservoir" H.R. Shoreline Soil 88 Sector 6 Reuter Stokes Pole, DR-6 Direct Gamma 0.5 M1 ESE I 89 Highland Avenue & Sprout Brook Rd (near rock out) 3 MI - NNE DR 35 Direct Gamma 90 Charles Point, 0.8 M1 _ NE DR 3 Direct Gamma I Footnotes:

(a) H.R. is Hudson River I (b) Control Station RETS.

(c) Quality Assurance Station A-4

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f - 880A0 LE AF VEG FIGURE A-1: Environmental Sample Station Locations (within two miles)

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APPENDIX B I ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS I

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APPENDIX B ENVIRONMENTAL SAMPLING AND ANALYSIS P.EQUIREMENTS I Environmental media which are sampled at the locations specified in Appendix A are analyzed according to criteria established in the Radiological Effluent I Technical Specification (RETS). These requirements stipulate:

1. Methods of Sample Collection

2. Frequency of Sample Collection

3. Types of Sample Analysis

4. Minimum Sample Size Required I 5. Minimum Detectable Concentrations which must be attained for each media, sample, or analysis type.

I Environmental sampling and analysis criteria for the Indian Point Site are summarized in Table B-1 for the RETS.

program are given in Tables B-2.

Detection capabilities for the RETS An additional environmental surveillance requirement is that an annual land use and milch animal census be performed in accordance with RETS Section 4.11.B for Con Ed and 2.8 for NYPA. The number and location of animals producing milk for I human consumption must be determined within eight kilometers of the plang.

addition, the nearest residence and the nearest garden greater than 50 m size producing broad leaf vegetation must be identified. Vegetation sampling at the In site boundary may be performed in lieu of the garden census.

I Only Consolidated Edison Technical Specifications are included for puaoses of illustration. The requirements for the New York Power Authority are the same.

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I B-1

m M M M M M M M M M M M M M TABLE B-1 Radiological Environmental Monitoring Program Sampling and Analysis Criteria Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations, Collection Frequency of Analysis

1. Direct Radiation 40. routine monitoring Quarterly Gamma dose quarterly stations (DR DR-40) either with two or more dosimeters or with one instrument for measuring and recording integrated dose or dose rate placed as follows:

i' An inner ring of stations, one b) each meterological sector in the general area of the site boundary (DRI-DR16) :

An outer cing of stations, one in each meterological sector in the 6- to 8-Km range from the site (DR17-DR32):

The balance of the stations (DR33-DR40) to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.

M M M M M M M M M M M M M M TABLE B-1 (cont.)

Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency a

and/or Sample Sample locations Lollection Frequency Of Analysis

2. AIRBORNE Radioiodine and Samples from 5 locations Continous sampler Radioiodine Cannister:

Particulater. (Al-A5) operation with sample collection weekly, or 1-131 analysis 3 samples (Al-A3) from close more frequently if weekly.

3 site boundary locations, required by dust loading.

in different sectors, of the Particulate Sampler:

highest calculated annual average Gross beta radioactivity as groundlevel D/Q. analysis folloging

'a filter change; I sample (A-4) from the vicinity of a community having the highest calculated annual average groundlevel D/Q.

3. WATERBORNE f

a. Surface 1 sample upstream (Wal) Composite sample over Gamma isotopic analysis 1 sample downstream (Wa2) 1-month period 8 monthly. Composite for tritium analysis quarterly

M M M M M M M M M M M M M B-1 (Cont.)

Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis

b. Drinking I sample (Wb1) of Grab Sample - monthly Gross beta and gamma the nearest surface isotopic analysis

• monthly.

drinking water supply Composite for tritium analysis quarterly.

c. Sediment 2 samples (Wel-Wc2) 2 annually at Gamma isotopic analysis

• from Shoreline I sample (Wel) from least 90 days apart semiannually.

area with existing or potential recreational ao value. I control sample

', (Wc2) from an upstream area.

4. INGESTION

a. Milk Samples from milking Semimonthly when Gamma isotopic" and animals in 3 locations animals are on pasture I-131 analysis semi (Ial-Ia3) within 5 km monthly at other times. monthly when animals are distance having the on pasture; monthly at highest dose potential. other times.

If there are none, then,

m W W W W M M M M B-1 (Cont.)

Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis I sample from milking animals in each of 3 areas (Ial-la3) between 5 to 8 km distance, if available, where doses are calculated to be grgater than 1 mrem per yr

b. Fish and I sample of each of 2 Sample in season, or Gamma isotopic analysis

• Invertebrates commercially and/or semiannually if they on edible portions, as recreationally important are not seasonal

$, species in vicinity of plant discharge area (Ibl).

I sample of same species, if available in areas not influenced by plant discharge (Ib2).

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M M M M M M M B-1 (Cont.)

Number of Representative Samples and Sampling and Type and Frequency Exposure Pathway Sample Locations" Collection Frequency of Analysis

c. Food Samples of 3 different kinds Monthly when availalbe Gamma isotopic

• and of broad leaf vegetation I-131 analysis.

(edible or inedible) grown nearest each of two different offsite locations of highest predicted annual average groundlevel D/Q if milk sampling is not performed (Icl-Ic2).

as I sample of each of the similar Monthly when available Gamma isotopic" and I-131 os broad leaf vegetation grown analysis 15-30 km distant in the least prevalent wind direction if milk sampling is not performed (Ic3).

TABLE NOTATION a The code letters in parenthesis, e.g., DRI, Al define generic sample locations. Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 4.11-1 in a table and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of Radiological Ef ficient Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1 November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal enavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling eq'aipment malfunctions, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual

M M M M M B-1 (Cont.)

TABLE NOTATION Radiological Environmental Operating Report pursuant to Specification 6.9.1.5. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances __ able alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.6, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

b One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is censidered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for m measuring direct radiation.

c The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater that ten times the previous calendar year mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

e Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility, f " Upstream" samples shall be taken near the intake structures as described in the ODCM. " Downstream" samples shall be taken from the mixing zone at the diffuser of the discharge canal.

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B-1 (Cont.)

TABLE NOTATION g A composite sample is one in which the quantity (aliquot) of liquid sample shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample, h The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

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LOWER LIMIT OF DETECTION (LLD) CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (a)(b) (c)

Analysis Water AirbornePartjculate Fish Milk Food Products Sediment (pCi/1) or Cas (pCi/m ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg. dry) gross beta 4 0.01 11 - 3 2000(d)

Mn-54 15 130 Fe-59 30 260 cn E Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 (e) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 60 180 Ba-La-140 15 15

M M M M M M M M M M M M TABLE B-2 (Cont.)

TABLE NOTATION a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report Specification 5.3.3.2.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

c The LLD is defined, for purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observatien represents a "real" signal. Equations used in the calculation of the LLD for a particular measurement system are presented in the ODCM.

d It should be recognized that the LLD is defined as an a priori (before the f act) limit representing the et, capability of a measurement system and not as an a posteriori (after the fact) limit for a particular

' measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under o routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 5.3.3.2.

e LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

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APPENDIX C I

ENVIRONMENTAL SAMPLE AND ANALYSIS PROCEDURES I

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APPENDIX C ENVIRONMENTAL SAMPLING AND ANALYSES PROCEDURES Adherence to procedures for sampling and analysis of all environmental media at Indian Point is required to ensure compliance with the Radiological Effluent Technical Specifications (RETS). Procedures ensure that environ-mental media are sampled and analyzed in compliance with specific schedules (Table B) and at specific locations (Figures A-1 through A-4 as presented in Tables A-1 through A-4). Analytical procedures a employed to ensure that the detection capabilities presented in Tables 3-2 a achieved.

Collection of environmental samples is performed by the Indian Point Radiological Environmental Monitoring group. Environmental sample analyses are performed by commercial analytical laboratories. Laboratory analyses for I 1985 were performed by Teledyne Isotopes, Inc. of Westwood, New Jersey.

Teledyne Isotopes, Inc. was contracted to perform the analyses as specified in Table B-1, and to operate according to internal procedures to ensure compli-ance with the requirements of the RETS.

Sections C.1 - C.13 describe the environmental sampling and analysis proce-I dures by media type. The actual procedures which are applicable to the sampling and analysis of environmental media are found in References 2,3 4, and 5.

I C.1 HUDSON RIVER WATER Hudson River water is collected continuously frcm the onsite inlet pipe and I the onsite discharge canal. A sampling apparatus is employed which ensures that representativa samples of river water are obtained. Samples are obtained weekly from the inlet and outlet sample collection drums and are composited I for a monthly gamma spectroscopy analysis (GSA) and for a quarterly tritium analysis. GSA is also done quarterly.

C.2 HUDSON RIVER AQUATIC VEGETATION ,

Hudson River aquatic vegetation was collected se three locations: near Verplanck, Lent's Cove, and Cold Spring. Samplea, of Potomogeton crispus and Myriophy111um verticillatum were taken from each location depending upon availability during the spring and summer. These samples were in addition to the requirements of the RETS, Gamma spectroscopy analysis, including I-131, was performed on the aquatic vegetation samples.

C3 HUDSON RIVER BOTTOM SEDIMENT (Including Benthos)

I Bottom sediment was sampled at four locations on the Hudson River including the onsite discharge canal, near Verplanck, Lent's Cove, and Cold Spring.

Samples were obtained using a Peterson grab sampler or similar instrument once each in spring and summer. These samples were in addition to the requirements I of the RETS.

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Gamma spectroscopy analysis was performed on samples of bottom sediment.

C.4 HUDSON RIVER SHORELINE SOIL Shoreline soil is sampled at the two RETS locations and 3 special locations in the Hudson River including Off Verplank, Lent's Cov e , Manitou Inlet (Wer).

White Beach (Wer), and Cold Springs. Samples were taken during the spring and I during the summer.

Gamma spectroscopy analysis is performed on samples of shoreline soil.

C.5 HUDSON RIVER FISH and INVERTEBRATES Fish and invertebrates are obtained from the Hudson River in the sunmer and fall depending upon availability. Samples are collected upstream and downstream of the plant discharge, and edible portions are analyzed b3 gamma spectroscopy.

C.6 PRECIPITATION Precipitation samples were collected at Roseton (20 miles N) and at the Peekskill Gas Holder Building (1.7 miles NE). Samples were collected in open pot type polyethylene bottles which are designed to hinder evaporation. The I Quarterly analysis of composited precipitation samples includ=3 spectroscopy analysis and tritium analysis. These samples were in addition to the requirements of the RETS.

gamma I C.7 DRINKING WATER I Samples of drinking water are collected from the the Camp Field Reservoir (3.5 miles NE) and Roseton (20 miles N). Samples are obtained monthly and are analyzed for gamma emitting radionu:lides and I-131. A composite sample is analyzed quarterly for tritium.

C.8 AIR PARTICULATES AND RADI0 IODINE I Air samples are collected at Standard Brands (0.6 mi NNE), Algonquin Gas Line (0.25 mi SW), NYU Tower (1 mi SSW), Roseton (20 mi N (control location)

Special location at Croton Point (6.4 mi SSE), Grassy Point (3.3 mi SSW),

I Peekskill Gas Holder Building (1.7 mi NE). Lovett (1.5 mi WSW) and Cortlandt Sanitation Garage (2 mi N) were also sampled weekly.

are in addition to the requirements of the RETS.

The special locations The air samples are collected continuously by means of fixed air particulate filters followed by in-line charcoal filters (cartridges), both of which are changed on a weekly basis. The samples are analyzed weekly for gross beta and I radiciodine,and gamma spectroscopy are performed on quarterly composites of this particulate filter.

C.9 SOIL Soil samples were collected from the NYU Tower (1 mi SSW), Camp Smith (2.5 mi NNE), and a control sample from Roseton (20 mi N). Samples were C-2 I

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obtained using a two inch depth topsoil cutter. Gamma spectroscopy analyses I were performed on these samples.

requirements of the RETS.

These samples were in addition to the I C.10 MILK Under the RETS program, milk was not required to be sampled in 1985 because no animals producing milk for human consumption were kept within 8 km of the plant. Should future annual milch animal census results indicate a milch animal exists within this radius producing milk for human consumption, milk will be sampled monthly (or twice per month when animals are on pasture) and analyzed for gamma emitting radionuclides and 1-131.

C.11 BROAD LEAF VEGETATION Broad leaf vegetation (edible or inedible) in collected monthly when available and analyzed for gamma emitting radionuclides and 1-131. Samples are collected from NYU Tower (1 mi SSW), Camp Smith (2.5 mi NNE), and from Roseton (20 Mi N).

C.12 DIRECT GAMMA (TLD)

Calcium sulfate thermoluminescent dosimeters (TLDs) are posted at various locations within a 5 mile (8 km) radius of the plant. TLDs is located in each of the 16 compass sectors at two locations. The inner ring of TLDs are I located near the site boundary and the outer ring are located 4 to 6 km from the site. Eight additional locations are located at nearby points of special interest and at Roseton, 20 miles North, as a control. The TLDs are collected I and evaluated on a quarterly basis. Actual locations for TLD measurements are given in Table A-1.

C.13 LAND USE CENSUS A census of animals producing milk for human consumption is conducted annually I in the Indian Point vicinity to determine herd size and location with respect to the plant site. This census is conducted to locate milch animals in the event that additional sampling was either desired or required during 1985.

A visual field survey of milch animals within eight kilometers of the plant was performed during 1985. The census was completed by reviewing information supplied by the New York State Department of Agriculture and Markets within the eight kilometer radius of Indian Point.

The procedure which is applicable to performance of the Milch Animal Census is found in Reference 2.

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'I I APPENDIX D RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

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I SECTION D RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

I The results of the 1985 Radiological Environmental Monitoring Program are presented in Section D.1. The results of the program as outlined in Tables I B-1 and B-2 are surmarized in tabular form in Sections D.1.1 through D.1.17.

The format of the summary tables conforms to the reporting requirements of the RETS and NRC Regulatory Guide 4.8 (Reference 5).

The required Milch Animal and Land Use Census is summarized in Section D.2.

D.1 1985 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Environmental monitoring data were summarized and presented in tabalar form-by media type. Gamma spectroscopy analysis was performed for the following radionuclides:

Be-7 Ru-106 I K-40 Mn-54 Co-58 T-131 Cs-134 Cs-137 I Co-60 Fe-59 Zn-65 Ba-140 Ce-141 Ce-144 <

Zr-95 I Ru-103 Ra-226 Th-228 Radiochemical (I-131) and tritium analyses were performed for specific media I and locations as required in the RETS (Table B-1). Additionally, the appropriate analyses were performed for samples obtained in. excess of the requirements were performed as noted.

LLD values are presented in Tables B-2 for required radionuclides as shown in Table B-3 for RETS.

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5 D.2 LAND USE CENSUS In accordance with Sections 4.11 B of the Con Ed RETS and 2.8. A of the NYPA RETS, a land use census was conducted to identify the nearest milk animal and I the nearest residence In lieu of identifying and sampling the nearest garden 7

of greater than 50 m , at least three kinds of broad leaf vegetation were sampled (results summarized in Table D-15 through D-18).

D.3 SAMPLING DEVIATIONS

,- During 1985, environmental sampling was performed for 12 media types and for

, I direct radiation. A total of 954 samples were collected and analyzed for the RETS program.

Sampling deviations are summarized in Table D-1.

= D.4 ANALYTICAL DEVIATIONS e

I. No analytical deviations occurred in 1985. LLD sensitivities were met for all samples of all media.

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I I TABLE D-1

SUMMARY

OF SAMPLING DEVIATIONS,1985 Total Scheduled Number of Sampling Reason for each I Media Samples Deviations Efficiency Deficiency Particulates in air 468 1 99.8 Sampler malfunction Charcoal Filter (I-131 in Air) 468 1 99.8 Sampler malfunction TLD 328 3 99.1 Vandalism (all 3)

Drinking Water

• 18 0 100 --

Hudson River Water 24 0 100 --

Precipitation 8 0 100 --

Broad Leaf Vegetation 54 3 94.4 Samples not available at Roseton (control location) in Spring 1985 (3 samples)

Aquatic Vegetation 7 0 100 -

Shoreline Soil 10 0 100 --

Sediments 8 0 100 --

Soil 3 0 100 --

I Fish and Invertebrates 12 0 100 --

• Includes Roseton - a temporary sampling location I

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M M M M M M M M M M M M M M M M M M TABLE D-2 DIRECT RADIATION, INNER RItC OF 16 CECTORS NEAR SITE B00f0ARY mitLirem Location RETS Dist. First Otr. Second Otr. Third Otr. Fourth Otr. Annual Totet Designation 10 # Sector Hites Dose Dev. Dose Dev. Dose Dev. Dose Dev. Total Dev.(b)

Cortlandt Sanitation Garage DR-01 N 2.0 15.2 1.4 13.6 0.2 12.2 0.4 15.1 1.1 56.1 1.8 Old Pomert Avenue DR-02 HNE 1.8 19.4 0.7 18.7 0.6 17.0 0.6 (a] 73.5 1.1 Charles Point DR-03 PE 0.8 13.2 0.7 13.1 0.9 10.9 0.6 14.1 1.4 51.3 1.9 Lent's Cove DR-04 ENE 0.5 15.8 0.7 15.6 0.9 (a) 14.5 0.4 61.1 1.2 8teakley & Broadway DR-05 E 0.4 14.7 0.8 14.7 0.5 12.1 0.5 15.4 1.2 56.9 1.6 Sector 6. Reuter-Stokes Pole DR-06 ESE 0.5 14.5 0.3 15.4 0.7 13.7 0.9 16.1 1.6 59.7 2.0 g Water Meter House DR-07 SE 0.3 15.7 0.7 15.4 0.9 12.5 1.1 15.2 1.2 58.8 2.0 g Service Center DR-08 SSE 0.4 12.3 0.5 12.2 0.5 10.4 0.5 12.8 1.0 47.7 1.3 SE Corner Onsite DR-09 SE 0.6 15.1 0.5 16.0 0.6 13.2 0.4 15.9 1.6 60.2 1.8 NYU Tower DR-10 SW 1.0 14.4 0.6 14.1 0.6 12.2 0.9 14.4 1.0 55.1 2.2 White Beach DR-11 W 0.9 12.1 0.6 12.2 1.0 9.6 0.3 13.5 1.9 47.4 2.2 Gays Hill Road S DR-12 WSW 0.2 16.2 0.2 15.6 0.8 14.5 0.6 16.1 0.8 62.4 1.3 Cays Hill Road N DR-13 W 1.2 20.3 1.0 17.0 0.8 17.3 1.0 20.2 2.5 74.8 3.0 Rt. 9W Pirates Cove DR-14 WNW 1.2 14.9 2.7 19.2 0.8 12.8 0.7 14.7 0.8 61.6 3.0 Rt. SW South of Ayers Rd DR-15 NW 1.0 14.0 0.4 14.0 0.6 12.2 0.4 14.3 0.4 54.5 0.9 Ayers Road DR-16 NNW 1.0 15.7 1.3 15.5 0.2 14.3 0.6 15.8 1.1 61.3 1.8 Averages (c) 15.2 1.0 15.1 0.7 13.0 0.7 15.2 1.4 58.9 2.0 (a) Total Dev. is the square root of the sum of the squares of the quarterly deviations. Quarterly deviations are given es 1s.

(b) Sampig lost due to vandalism. Annuet totet is based on the sum of the monitored quartere plus the average quarterly dose rate for the unmonitored quarter.

(c) Deviation shown for quarterly everages is the standard devistion for all TLDs collected for the quarter in this ring,

M M M M M M M M M M M M M M TABLE D-3 DIRECT RADIATION, OUTER RING OF 16 SECTORS 4-5 al FROM SITE BOUNDARY mittirem Location RETS Dist. First Otr. Second Otr. Third Otr. Fourth Otr. Annual Total Designation ID # Sector Miles Dose Dev. Dose Dev. Dooe Dev. Doce Dev. Total Dev.(e)

Rt. 90 Ga*rison DR-17 N 5.0 14.0 0.8 13.7 0.7 11.5 0.5 14.8 1.5 54.0 1.9 Gallows Hill Road DR-18 NNE 5.0 14.5 0.5 13.1 0.6 12.3 1.0 15.4 1.5 55.3 2.0 Westbrook Drive D R-19 NE 5.0 15.6 0.4 14.9 0.7 14.2 1.0 15.9 0.4 60.6 1.3 Pine Road, Cortlandt DR-20 ENE 4.8 15.9 0.3 14.0 0.7 12.3 0.4 14.8 1.2 57.0 1.5 Croton Ave., Corttendt DR-21 E 5.0 14.7 0.8 14.2 0.7 12.6 0.7 14.7 0.6 56.2 1.4 Colebaugh Pond Road DR-22 ESE 5.0 13.6 0.8 11.4 0.5 10.7 0.8 13.0 0.6 48.7 1.4 c3 Mount Airy & Windsor Rd DR-23 SE 5.0 15.5 1.0 14.0 0.6 12.0 0.3 14.0 0.9 56.3 1.5 jn Croton Point DR-24 SSE 6.4 13.2 0.6 13.3 0.6 11.2 0.7 14.7 0.6 52.4 1.3 Warren Aveenue Haverstraw DR-25 S 4.8 14.0 0.5 14.0 0.7 11.3 0.4 13.1 0.8 52.4 1.2 Railroad Avenue & 9W, Haverstraw DR-26 SSW 4.6 14.8 0.5 14.8 0.8 12.4 0.9 15.2 0.9 57.0 1.6 Willow Grove Rd. & Birch Dr. DR-27 SW 5.0 14.5 0.5 14.4 0.6 11.7 0.3 14.3 0.9 54.9 1.2 Sign "NY and NJ" Pelisades Pa rkway South DR-28 NSW 5.0 16.4 0.7 16.1 0.7 14.4 0.8 16.9 0.7 63.0 1.5 Pelisades Parkway DR-29 W 4.2 18.4 0.9 14.6 0.6 17.4 1.0 19.8 3.9 70.2 4.2 Anthony Wayne Park DR-30 WNW 4.5 16.8 0.2 18.7 0.7 14.3 0.6 16.0 0.8 63.8 1.2 Petisades Parkway Lake Watch Exit DR-31 NW 4.7 21.1 1.4 19.1 0.7 17.7 1.3 10.6 0.8 76.5 2.2 Rt. 8W, Fort Montgomery DR-32 NNW 4.0 17.1 0.7 15.3 0.3 16.0 0.5 14.7 0.9 63.1 1.3 AvereDes (b] 15.6 0.7 14.6 0.7 13.3 0.8 15.4 1.4 58.9 1.9 (a) Totet Dev. is the square root of the sum of the squares of the quarterly deviettone. Quarterly deviations are givnn as 1s.

(b) Davtetton shown for quarterly everagee is the standard deviation for ett TLDs collected for the quarter in this ring.

TASLE 0-4 OIRECT RADIATich. SPECIAL INTEREST AND CONTROL LOCATIONS attLirem Speelal Lacetten RETS Otet. First etc. Second str. Thi rd St r. Four th St r. Anneet Totet Destenetten 10 # Seeter Miles Does Dev. Daee Dev. Dese Dev. Deae Dev. Tatet Dev.(al Meallten St. OR-33 NE 3.0 10.1 0.8 18.0 0.8 S.0 0.3 S.S 0.0 37.8 1.2 Furnace Deck DR-34 SE 3.5 15.2 0.0 15.1 0.4 13 0.0 15.0 1.1 80.8 1.5 HighLead Avenue & Sprout greek Rd. OR-35 NNE 3.0 18.7 0.3 15.8 0.0 14.3 0.0 18.S 1.8 82.5 2.2 Leser South St.E Soy St. OR-38 NE 1.3 15.0 0.0 14.3 0.4 12.8 0.0 (bl 58.1 0.8 Verptenck DR-37 S EW 1.3 14.8 0.8 13.5 0.0 11.0 0.4 14.5 0.8 S4.5 1.3 Mentreme Marine DR-28 8 1.8 11.0 0.0 10.0 1.4 0.0 0.4 10.C O.5 40.5 1.7 Seessy Potat DR-SS REW 3.3 15.7 0.8 15.5 1.8 13.8 0.3 14..8 0.8 58.0 1.5 Roseten (Centret Lacetten) OR-40 N 20.0 18.8 0.2 17.5 0.0 14.0 1.3 18 I 1.0 85.2 1.8 g Averages (e) 14.2 0.8 14.1 0.8 12.2 0.7 13.rl 1.1 54.8 1.7 a

N (e] Tatet Dev. le the aquere rent of the sum of the aqueres of the quarterly deutettene. Qua rtert y doe tettone o ro given se t o.

(b] Sample test due te vendelten. Annual tetet is beoed on the sum of the monitored quartere plus the everage quarterly done rete for the 4 unmenitored quarter.

(c) Devletten sheen for quarterly overages to the atenderd devletten for el4 TLos cotLected for the quarter in this ring.

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1 M M M M M M M M M M M M M M M M TABLE D-5 CUARTERLY DIRECT RADIATION IN 16 SECTORS ANNUAL

SUMMARY

, 1985 are Vquarter Location with HI Dhast Annual /.varage Ave rage No. of Totat Name. Averoga No. of Total of all Highest Lowest Positive No. of Distanca, of ett Highest Lowest Positive No. of Readings Reading Reading Readings Readings Direction Readings Reading Reading Readings ReadinOS At t Naar Boundary Locations 15 20 10 62 62 Gaya Hill Road N, 19 20 17 4 4 West,1.2 mi.

? All Locations 4-5 mi from Boundary 15 21 11 64 64 Palisades Parkway, 19 21 18 4 4 03 Lake Watch Exit, North West 4.7 mi.

Att special Interest lacations 13 17 8 27 27 Highland Ava and 16 17 14 4 4 Sprout Brook Road, NNE, 3.0 mi.

Control Location 16 18 15 4 4 Roseton, 16 18 15 4 4 North, 20 mi.

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TnBLE V-1 RADI0faJCLIDES IN DEESON RIVER INLET (Weil APO DIfiCMARIE [Wa2) WATER AwtJAL RJMMARY,1985 pct /s Att Indtrater Lacettene Contret Lacettens Locetton eith Mtghest Annual Average J

Avg. of Highest Lamest No. of Totel Mome. Avg. of N10 hest Lames t No. of Totet Neme, Avg. of Highest Lamest No. of Totet Asetyste Detected LLD Positive Positive Poststus Positive No. of Distence, Posttive Poettive Poettive Posttive No. of Dietence, Positive Pesttive Positive Poststve No. of Type Actido pct /t 8emptos sempte semple Seaptes Sempton Direction sempton Semple semple Semplee Semples Direction Seeptes Sample semple semples semples Gense Spec t rum Ametyste None 15 to 30 - (Lin (LLD < Lt3 0 8 Intet (Ltm (LLD <llD 0 4 hone - - - -- -

Trittum #-3 2000 000 000 000 1 8 Intat (LLD (LLD <l LD 0 4 0ischerge 900 000 000 1 4 CamposIte Conet O

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TABLF D-8 RADIOWCLIDES IN CA40 FIELD (Whij AW ROSETON DRINKING MATER ANWAL SLM4ARY.1985 pCf/t Att Indicator Locettens Contret Lacettons Lacetten with Nighest Annual Average Avg. of Nighest Lewest No. of Tetet Neme. Avg. of M88 h*et Louest No. of Totet Neme. Avg. of Nighest Lesset No. of Total Anotyste Detected LLD Poettive Positive Positive Positive No. of Distence. Positive Poettive Poetttve Positive No. of Distence. Pcattive Positive Posttive Positive No. of Type Nuctide pct /t Semples Sample Sample Semptoe Samples of rection Semples Compta Sample semples Seaptes Of rection Semples Sample Sempte Samples Samples R

Samme Roseten Spectrum 20 attee Anotysts None 15 to 30 (Lla <tLD (LLD 0 18 North (LLD (LLD (LLO 0 6 Sross Sete Sete 4 3 8 1 18 18 Roseton 4 8 2 8 8 Rosaton 4 5 9 8 6

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M e0 miies ,0 .ti.s North North Trttlum N-3 2000 0 0 0 0 10 Roseten (LLD (LLD (Lt.D 0 $

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TA8LE D-9 RADIDMJCLIDES IN SHDELINE SDILS. ANNUAL SIMIARY.1985 pCVkg (dry]

Att Indiceter Lacettene Centret Lacettene Lacetten eith Highest Annwet Average LLD Avg. of Highest Lonest No. of Totet Neme. Avg. of Highest Lamest No. of Tatet Mees. Avg. of Highest Loneet ho. of Total Anotyste Detected pCVke Positive Positive Positive Peettive No. of D$stsace. Positive Posittvo Poettive Positive No. of Dtatence. Poettive Positive Positive Peettive No. of Type bettde (dry] se ptes sempte semple sempton Sempton Direc tion Semples sempte sempte semples Seeptes Direction Semples Seepte semple Samples Samples Gemme Co-134 150 (LLD <LLD (LLD c e Menttau Intet. (LLD (LLD (LLD 0 4 verplanck (LLD (LLD (LLO O 2 Spectru (Upstreme. Wc2]. 1 otte SSW Analysta Co-137 180 188 628 41 8 6 and Cote Spring. 278 283 273 2 4 364 628 199 2 2 10.8 ottee Marth Co-60 -

(s) (e] le] O e (e) (s] (el O 4 le] le] le] O 2

{s] Not detected in 1985.

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1 TABLE D-11 RADIOf4]CLIDFS IN FISH AM) IPNERTEBRATES, ANNUAL SLeetAHY 1985 pC vhg feet) i Att Indicates Lacettone Centrol tecettens Lacetten eith Highest Annual Avere0e LLD Avg. of Highest Lowest No. of Total Nemo. Av0. of M80 hest Lowest No. of Total Moos. Avg. of Highest Lowest No. of Total Analysts Detected pct /k0 Posttive Posettve Poststve Posttive No. of Distence. Posittee Post tive Positive Positive No. of Dtstence. Poststee Positive Positive Positive No. of Type bet tde [ set] Semples Semple Sample semples Semptoe O t rac tlen Semptee Sempte Semple Samples Samples Direction Semples Sempl e Semple Samplee semples Samma Co-137 150 32 62 13 5 S poseton. 25 1s 37 7 4 5 Deenstrees. 32 62 13 $ 6

spectrum astes mostreen, ehere evettebte.

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APPENDIX E HISTORICAL TRENDS i

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

APPENDIX E HISTORICAL TRENDS Historical data for various radionuclides and media are presented both in tabular fonn and in graphical form to facilitate the evaluation of 1985 data with historical values. Comparison to other data from outside sources is  !

I presented as available. Although samples were taken and analyzed, values were only tabulated and plotted where positive indications were present.  !

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1ABLE E-1 DIRELT RADIATION ANNUAL

SUMMARY

, 1978 TD 1985 atttiree Firet Qtr. Second Qtr. Third Qtr. Fourth Qtr. Annual ToteL I Year Does Dev. Does Dev. Dose Dev. Does Dev. Total Dev.(e) 1978 12 1 24 3 13 2 14 2 62 5 1979 16 2 14 2 11 2 14 2 55 4 1980 12 E 14 2 15 3 13 2 54 5 1981 14 2 16 2 15 3 13 2 58 5 1982 14 2 14 2 13 2 14 2 55 4 1983 14 3 14 3 14 3 15 3 58 6 1984 13 2 15 3 14 3 15 2 56 5 15 I

1985 1 15 1 13 1 15 1 59 2 Notes 1985 data es e the eus of the inner ring and outer ring of RETS I sempting L oc e tio n deto.

the annual summary.

Non-RETS Locatione are not inctuded in (a) Total Dev. is the aque re root of the sum of the aqueroe of the deviationa for tha quartere.

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umm um um mum aus num man amm num um em num sum num um um um num ame l

Fig u re E-1 Direct R a d ia tio n , S u m m a ry by Year All Indicator Lo ca tio n s 70 LEGEND l'

4th Q u a rter 3rd Q u a rte r 30 . 2nd Qu a rter 1 st Quarter

,. y y( ,;l ' , V 30-- ,f ,[f 20--

l 10--

o l

1978 1979 1980 1981 1982 1983 1984 1985 Year See Reg. Guide 4.13 for required sensitivity for TLDs.

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== men mim == sus men ama men == sus num sem == == == == ==

Fig u re E 2 Direct Radiation, 19 78 t~o 1985 Sta n d a rd Normal Deviate 4

3 2

m c A. .g 2 b A o

25 I V

2

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to

-2

-3

-4 .

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1978 1979 1980 1981 1982 1983 1984 1985 Year

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l TABLE E-2 RADIONUCLIOES IN AIR. 1975 to 1985 pct /m3 I

Gross Bete Co-137 AlL RETS ALL RETS Indicetor Control Indicetar Control Yeer Locotions Locetion Lacetiona Locetion E 1975 0.08 0.008 1976 0.03 0.019 I 1977 1978 1979 0.03 0.15 0.03 0.14 0.03 (a) 0.006 0.008 0.040 (a) 0.006 0.026 I

1980 0.03 0.04 0.013 0.010 1981 0.19 0.19 0.015 0.015 1982 0.03 0.04 0.068 (b) 1983 0.02 0.02 0.006 (b)

I 1984 1985 0.02 0.02 0.02 0.02 (b)

(b]

(b]

(b]

HietariceL Av e roge 0.06 0.07 0.020 0.015 I HietoriceL Std. Dev. 0.06 0.06 0.019 0.007 (e) No deto eveltabLe. Control Station initiated in 1978.

(b) Not detected at Lower limit of detection.

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man mum amm um uma num man aus man am um um men mm um um uns F ig u re E 3 Gross Beta R a dio a ctivity in Air 1975 to 1985 All Indicator Statio n s vs. Co n trol LEGEND 27-~

Indicotor

,2 __ Control

.11--

2:n

.i a--

5 .is--

C.

.11--

.09 --

.os-- /j nn i MA -El-m-m-w

.os--

a .9 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: The LLD for Gross Beto in Air is O.01 pCi/m 3.

== == == == == == == men == == == mam == men == men == == man Fig u re E 4 Gross Beta Radioactivity in Air Sta n d a rd No rm al Deviate 4

3 2

T

~

o

._g i

A .

k N jo -i

\ / \ /

m

-2

I

-s

_4 . . .  ; . . . . . . .

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year

~

um um man amm num uma amm num mai uma amm ama amm amm uma num um uma sum Fig u re E-5 Cs 137 R a dio a ctivity in Air 1975 to 1985 All Indicator Stations vs. Control LEGEND Indicotor Control Q' 4--

c2 to E

5 .s--

"o.

a.

.1 --

V Z

'/

n n O - n ( Um m /- _

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: The LLD for Cs-137 in air is 0.06 pCi/m 3.

ci - .-

== == == == == sus == sus == sus == men am == - == == - aus Fig u re E 6 Cs 137 Radioactivity in Air Sta n d a rd N o rm al Deviate 4 -

3 __

2 E

T e

e' ~

.g e

4 Q

C o -1 l  %-

m

-2

-3 i . . . .

_4 . . . . . . .

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: Cs-137 not detected above LLD in 1984 and 1985.

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TABLE E-3 I RADIONUCLIDES IN WATER. 1975 TO 1985 HUDSON RIVER INLET AND DISCHARGE pct /L Year Tritium Co-60 Cs 137 1975 615 (e) (a) 1976 513 (a) 3 I 1977 1978 1979 290 630 354 (a)

(a)

(a) 8 5

6 (e)

I 1980 1981 1982 358 300 370 (a)

(e) 15 6

7 1983 540 4 5 1984 541 [e] [e]

1985 870 (a) (a)

Hiataric 1 Av e rage 451 4 7 Historic l Std. Dev. 123 -

3 I (.) ..t ..t..t.. ..... LLO.

• n

~

I 1

l l

E-10 l l

l l

---_.-,_..-._.._.._..-___...-.-.._._-___._-__,-..-,,-_.....-_-..-_.,_-__._1

- - - man am num men an em em um um Fig u re E 7 Tritiu rn in Hudson River Water 1975 TO 1985 Inlet and Discharge Annual Average 20000 LEGEND

'8 --

E//M Tritium icooo--

14000--

12000--

icooo--

ct sooo--

sooo--

. coo--

l 20o0 LLD o E N "" " " " " " N 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: The LLD for tritium in drinking water is 2000 pCi/l.

- - == - sum - == sus == - - == cm - == mes == == -

Fig u re E 8 Tritiu m in Hudson River Water Inlet and Disch a rg e Sta n d a rd N o rrn al Deviate 4

3 /+

2 E s'

's N A -

1

'5 o [

i j- ' \'

^%

.s en y v

-2

-3

_4 . . . . . . .

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: Tritium is above 3s but well below LLD in 1985.

i TABLE E-4 RADIONUCLIOES IN WATER, 1975 TO 1985 I CAMP FIELO AND ROSETON ORINKING WATER pct /L Year Tritium Co-80 Co-137 1975 3 23 (e) (e) 1978 254 (a) 9 1977 193 (a) 7 1978 208 (e) (a) 1979 170 (e) 4 1980 287 (a) (e) 240 (a) (a) 1981 e 1982 190 (a) (a) 1983 122 (e) 8 1984 178 (e) (a) 1985 (a) (e) (a)

Historic Ave rage 218 --

8

. Historic Std. Dev. 57 --

1 i (a) Not detected above LLO.

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' ll E-13

em num == == ums -

Fig u re E 9 - -

Tritiu m in Water 1975 TO 1985 Camp Field and Roseton Drinking Water LEGEND i == --

FM Tritium isooo--

m 14000--

k 12000--

5 3 toooo--

o.

sooo--

sooo--

4o00--

2 coo LLD o . . . . . . .

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: The LLD for tritturn in drinking water is 2000 pCi/l.

mes == - - - ==== - == - - a em == - == ra - -

Fig u re E 10 Tritiu m in Drinking Water Camp Field Sta n d a rd Normal Deviate 4

3 2

• 5 m

E

.j i

?

s

/

m

/

~

-1 x

-a

-s

_4 . . . . .

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year s Note: Cs-137 not detected above LLD in 1984 ond 1985.

,.., c

\

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I TABLE E-5 I RAD I0 ACTIV I TY IN H1'O S O N RIVER SHORELINE SOIL. 1975 to 19 85 pCl/kg ( d r y '.

B Year Co-134 Co-137 Co-80 I nd i .'* ' 4 Control Indicator Control Indicator Control 1975 1976 1977 B 1978 85 (e) 20e (a) (e) (e) 1979 (a) (a) 179 20b (a) (e) 1900 89 (e) 419 (e) 72 (e)

' 410 160 20 (e) 1981 60 70 1982 70 (a) 420 140 (a) (e) 1983 24 (a) 439 197 85 (e) 1984 34 (e) 286 142 38 (e) 1985 (a) (a) 166 270 (a) (a)

Is Historical Average 60 70 337 1 69 54 ERR Historical Std. Dev. 24 0 103 27 26 ERR I Notes Data prior to 1978 use not reported in ennual reporte due to anelyate requiremente, or reporting unite (e.g.

pC1/kg-dry vs. pC1/kg-wet).

i (a) Not detected above LLD.

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. E-16

.- . - - - . . . - . - - - - .- 1

am - uma num - see - su uma sus em e Fig u re E-11 Cs-134 and Cs 137 in S h o relin e Soil 1975 to 1985 Ave ra g e of Indicator Sta tio n s LEGEND 1e00-- -

Cs-137 1400--

E Cs-137 Control I 'lcs-134 1200--

3 1000--

.sP b 800--

c.

600--

400-- p 7 3 3 Y k k k -

200-- LLD Cs-137 O

.U .b ,

1975 1977 1979 1981 1983 1985 1976 1978 1980 1982 1984 Year Note: LLDs in pCi/kg (dry) are: Cs-137 - 180; Cs-134 - 150.

Fig u re E 12 Cs 134- and Cs 137 in S h o relin e Soil Ave ra g e of Indicator Stations Sta nd a rd Normal Deviate LEGEND

, o Cs-134 o Cs-137 2

7 E E g 3 ~, - x ' *\

s /

\

$o m /

/ \

\

t5 / b 2 / \

h S %g' N

-2

-3

-4 . . . . . .  ; . .  ;  ;

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year

I I TABLE E-6 RADIONUCLIDES IN B R O AD LEAF VEGETATION, 1975 TO 1985 (e) pC1/kg, [ wet)

Year Co-60 Co-60 Co-137 Co-137 Indicator Control Indicator Control I 1975 1976 213 925 (b) 90 1191 (b)

(b) 1977 230 (b) 132 (b)

I 1978 1979 (b)

(b)

(b)

(b)

(b)

(b)

(b)

(b) 1980 (b) (b) (b), (b)

I 1981 1982 1983 (b)

(b)

(b)

(b)

(b)

(b)

(b)

(b) 17 (b)

(b)

(b)

(b) (b) (b) (b]

I 1984 1985 (b) (b) 98 (b)

H1stor(cal Average 456 358 I Historical Std. Dev. 332 483 I (e)

(b)

Leary green vegetett on prior to 1984 Not detected above LLD.

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'~"

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mum um amm um num um num sum num amm num num amm num aus aus em uma sus Fig u re E-13 R a dio a ctivity in B ro a d Leaf Ve g eta tio n 1975 to 1985 Ave ra g e of All Indicator Sta tio n s LEGEND 12oo--

Cs-137 sooo--

T U c eco--

1?

eco--

m 4oo--

Soo-- -

I LLD o- - -

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: The LLD for Cs-137 in food products is 80 pCi/kg (wet).

== = = = = = = = = uma men == = uma == == sus == == == =

Fig u re E 14 Radioactivity in B roa d Leaf Vegetation Ave ra g e of Indicator Stations Sta n d a rd N o rrn a l Deviate LEGEND 5 o Co-60 a Cs-137 "1 P

/ \

$, / \

~5 / \ j cs , ,/

\

hc ---~~-~~-_________,_______---a

_3

_3 en

-2

-5 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: Co-60 not detected above LLD f rom 1978 thru 1985.

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I TABLE E-7 RADI0 ACTIVITY IN FISH AND INVERTE8 RATES, 1975 TO 1985 pC1/k9 (wet]

I Year Co-137 Indicator C o n t ro l I 1975 (e) (a)

(a]

I 1976 590 1977 102 (a) 1978 53 (e) 1979 24 (e) I I 1980 1981 1982 106 50 36 (e]

(e)

(a)

I 1983 1984 1985 43 33 32

[a]

(a) 19 Historicot .

Average 115 19 Histor(cal Std. Dev. 170 --

I (e) Not detected above LLD.

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E-22 .

1

aus em uma um uma mas num nas uma sum num num num as aus num sum Fig u re E 15 Cs-137 in Fis h and I n ve rte b ra te s 1975 to 1985 Indicator Stations vs. C o n trol LEGEND 1400--

1aco-- Indicctor 1200-- Control 1100--

N 1000--

w 900--

d soo--

700--

Q eoO--

soo--

4oo-- /

soo--

9 g

200--

LLD 00'~ .-y M U @

o 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: The LLD for Cs-137 in fish is 150 pCi/kg (wet).

man um amm um um um um um um um um um as amm um sus as am see Fig u re E 16 Cs 137 in Fish and I nve rte b rates Ave ra g e of Indicator Stations Sta n d a rd N o rrn a l Deviate 4

3 2

T

% E

.] 1

?

e

=

] -

= c >

-1

-2

-3 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 Year Note: Cs-137 not detected above LLD in 1975.

e - - a w , - - --

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I n ,es x P EPA INTERLABORATORY COMPARISON PROGRAM I l 1

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APPENDIX F EPA INTERLABORATORY COMPARISON PROGRAM I Teledyne Isotopes participates in the EPA Interlaboratory Comparison program.

Samples of various media containing known activities of radionuclides were I sent from the EPA to participating laboratories for analyses.

analyses were compared to the EPA known values.

Results of the I In 1985, samples of environmental media vere provided and appropriate analyses were performed as indicated in Tabic F-1.

Results were considered acceptable if there was agreement within i 3 standard deviations of the EPA known value. If unacceptable results were reported, the contractors were contacted and the deviations were resolved. Teledyne Isotopes monitored the results of this program and adhered to a policy of I investigation, determination of causation, and corrective action in the event of discrepancies. In addition, the contractors' performance in this program was routinely reviewed. In 1985, Teledyne Isotopes performance in this program was satisfactory; agreement was attained for 81 out of 85 analyses.

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I F-1 i

I TABLE F-1 US EPA CROSS-CHECK PROGRAM 1985 I Collection Teledyne Date Media Nuclide EPA-Results Isotopes Results (b) 01/04 Water Sr-89 3.0 1 8.7 L.T. 3.

Sr-90 ,

30. 2.6 29.0 ! 12.

01/11 Water Pu-239 15.7 1 2.8 19. 2 3.

01/18 Water Gross Alpha 5.0 8.7 5. O.

Gross Beta 15.0 8.7 15.0 3.

01/25 Food Sr-89 34.0 8.7 17.0 ! 0. (d)

(c) Sr-90 26.0 ! 2.6 22.0 6.

7 29 0 8. 3 b!10 K 1382.0 207.9 1393.0 96.4 02/02 Water 11 - 3 3796. 1 634. 3933. 174.

02/08 Water Cr-51 48. i 8.7 L.T. 57.

Co-60 19.0 6.

I

20. ! 8.7 Zn-65 55. 8.7 57. 6.

Ru-106 25. t 8.7 L.T. 40.

Cs-134 35. 8.7 37.0 12.

Cs-137 25. i 8.7 31.0 6.

02/22 Water Uranium 12.0 ! 10.4 12.0 1 3.

03/01 Milk I 131 9. ! 1.6 8.0 3.

03/15 Water Ra-226 5.0 1.3 5.9 2.1 Ra-228 9.0 1 2.3 5.1 1.8 (e) 03/29 Air Filter Gross Alpha 10.0 t 8.7 10.33 ! 1.7 I Gross Beta Sr-90 Cs-137 36.0 1 8.7 15.0 ! 2.6 6.0 8.7 36.66 14.66 7.5 1.7 6.0 1 0.0 04/05 Water I-131 7.5 1.4 6.67 1.7 I F-2

I TABLE F-1 Continued I Collection Teledyne Date Media Nuclide EPA-Results(a) Isotopes Results (b) 04/12 Water H-3 3559. 630. 3367. ! 963.

04/19 Water Gross Alpha 32.0 8.7 25.33 ! 1.7 (f)

(Sample A) Ra-226 4.1 1.0 3.66 0.9 I Ra-228 U

6.2 1 1.6 7.0 ! 10.4 6.13 ! 0.7 6.67 ! 1.7 04/19 Water Gross Beta 72.0 8.7 I

92.33 i 9.6 (Sample B) Sr-89 10.0 8.7 10.0 ! 0.0 Sr-90 15.0 2.6 13.33 1 3.5 Co-60 15.0 ! 8.7 20.0 ! 5.2 I Cs-134 Cs-137 15.0 ! 8.7 12.0 ! 8.7 14.66 ! 3.5 16.33 1 9.6 04/26 Urine H-3 3056. ! 622. 2833. 345.

05/10 Water Sr-89 39.0 8.7 35.66 ! 9.2 Sr-90 15.0 2.6 12.66 ! 1.7 (h) 05/24 Water Gross Alpha 12.0 1 8.7 12.00 5.2 Gross Beta 11.0 ! 8.7 12.66 ! 1.7 06/07 Water Cr-31 44.0 8.7 L.T. 53.3 Co-60 14.0 !8.7 15.66 ! 3.3 Zn-65 47.0 8.7 48.33 1 7.5 Re-106 62.0 8.7 53.67 ! 9.6 (i)

Cs-134 35.0 ! 8.7 33.0 ! 13.1 Cs-137 20.0 1 8.7 23.33 ! 6.2 06/14 Water H-3 2416.0 ! 608.0 2366.66 ! 346.4 06/21 Water Ra-226 3.1 0.7 3.86 I

0.18 (j)

Ra-228 4.2 1.0 3.66 ! 2.0 06/21 Milk Sr-89 11.00 8.7 11.66 ! 3.5 I Sr-90 I-13 1 Cs-137 11.00 11.00 2.6 10.4 11.00 i 8.7 10.00 0.0 9.00 1 3.0 11.00 1 7.9 l

l 1540.0 103.9 I

K 1525.0 i 131.6 l

I F-3 I

TABLE F-1 Continued Collection Teledyne Date Media Nuclide EPA-Results(a) Isotopes Results (b) 07/05 Urine H-3 2444.0 ! 610.0 2066.66 ! 624.5 07/13 Water Pu-239 10.6 1 1.9 8.20 2.2 (k) 07/19 Water Gross Alpha 11.0 1 8.7 5.67 1.7 Gross Beta 8.0 1 8.7 4.33 ! 1.7 07/26 Food St-89 33.0 8.7 25.33 6.2 (1)

(c) Sr-90 26.0 1 2.6 28.33 2 4.6 (1)

I-131 35.0 10.4 37.33 1 4.6 Cs-137 29.0 1 8.7 31.00 3.0 K 1514.0 131.6 1633.33 1 154.0 (m) 08/09 Water I-131 33.0 10.4 36.66 4.6 08/16 Water H-3 4480.0 ! 776.0 4433.3 ! 458.3 08/23 Water U 4.0 10.4 4.33 1 1.7 08/30 Air Filter Gross Alpha 13.0 8.7 12.66 2 1.7 Gross Beta 44.0 t 8.7 43.00 ! 9.0 I Sr-90 Cs-137 18.0 2.6 8.0 2 8.7 20.00 i 3.0 10.00 3.0 (n) 09/06 Water Sr-89 20.0 8.7 18.33 ! 4.6 Sr-90 7.0 2.6 6.00 0.00 09/13 Water Ra-226 8.9 2.3 9.23 1 1.5 Ra-228 4.61 1.2 4.03 1 0.6 G e 80!87 4 b0 0b0 l

I g s.4 l

l

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TABLE F-1 Continued I

I Collection Date Media Nuclide EPA-Results(a)

Teledyne Isotopes Results(b) 10/04 Water Cr-51 21.00 8.7 L.T. 63. j Co-60 20.00 8.7 17.66 ! 9.6 Zn-65 19.00 ! 8.7 25.33 ! 7.5 (o)

Ru-106 20.00 8.7 L.T. 37.

C s-13.- 20.00 ! 8.7 18.33 9.2 Cs-137 20.00 8.7 22.33 3.5 10/11 Water H-3 1974.0 598. 2133.33 624.5 I l 1

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I l F-5

l I TABLE F-1 Continued i

I (a) EPA Results-Expected laboratory precision (3 sigma) . Units are pCi/t for water, urine, and milk except K is in mg/1. Units are total pCi for air particulate filters.

(b) Teledyne Results - Average ! three sigma. Units are pCi/t for water, I urine, and milk except K is in mg/t.

particulate filters.

Units are total pCi for air (c) Units for food analysis are pCi/kg.

(d) The results from the EPA were received on August 09, 1985 for the analysis completed in April. The EPA had difficulty determining the correct results for this sample. It was difficult to scavenge and the results were reported as a courtesy although they were considered suspect because of the difficulty of analyzing a synthetic food sample.

(e) A new chemistry was tried but did not give good results.

(f) The proportional counters are calibrated for beta efficiency with Ce-137.

The efficiency correction applied for the low energy beta emitters overcompensated because the amount of the low energy emitters was small compared with the high energy emitters.

(h) The low Sr-90 results were caused by erroneously high Sr-89 yields because of trace calcium and barium in the precipitated mount.

Experiments will be conducted to eliminate this problem.

(i) The three results were 50, 55 and 56 pCi/1. The one low result of 50 caused the average to be below the two sigma normalized deviation from the known.

(j) A new NBS traceable standard was prepared to check the efficiency calibration of the ZS coated alpha counters used to count Ra-226.

(k) A new Pu-239 standard solution was prepared and a new Pu disc was ordered from NBS to check the efficiency calibration of the counters.

(L) The results for these samples showed high variability with some results near the spike value. In the future samples will be counted longer and sooner after milk time to reduce the amount of ingrowth correction of Sr-90 I into Sr-89.

(m) The weight of the sample analyzed will be controlled more carefully since the density may vary from sample to sample.

(n) The reported results were 21, 20 and 19. If the counting error (! 1.0) is I taken into consideration, these results would have been within the two sigma normalized deviation from the known.

(o) The reported results were 23, 25 and 28. The one high result of 28 I caused the average to be above the 2 sigma normalized deviation from the known.

F-5

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I I APPENDIX G i

CONTRACTOR QUALITY ASSURANCE PROGRAM I

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APPENDIX G CONTRACTOR QUALITY ASSURANCE PROGRAM The analysis of environmental samples was performed by Teledyne Isotopes (TI).

TI maintains its own comprehensive quality assurance program and has made a I commitment to quality control. Quality assurance requirements specified in 10CFR50 Appendix B and Regulatory Guide 4.15 were met by the quality assurance program at TI. This program included stability, operational, and accuracy checks throughout the analysis procedures.

Checks were performed on analytical equipment using standards to monitor the stability and reproducibility of counting instruments. Operational checks were performed utilizing blanks, spikes and splits (including internal cross-checks) to monitor the quality of analytical procedures and the quality of analyses performed by laboratory personnel. Accuracy checks were performed by I laboratory participation in the Environmental Protection Agency (EPA) and other laboratory intercomparison programs and by maintaining equipment cali-brations with standards from the National Bureau of Standards (NBS), Amersham, or IAEA.

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_ _ . , _ _ - _ - -