ML20029D202
| ML20029D202 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/31/1993 |
| From: | Sortz A LONG ISLAND POWER AUTHORITY |
| To: | |
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| ML20029D200 | List: |
| References | |
| NUDOCS 9405040178 | |
| Download: ML20029D202 (111) | |
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1 SHOREHAM NUCLEAR POWER STATION l RADIOLOGICAL ENVIRONMENTAL 4
MONITORING PROGRAM 1
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i ANNUAL RADIOLOGICAL ENVIRONMENTAL 4
OPERATING REPORT i
4 JANUARY l TO DECEMBER 31,1993 ISSUED BY NUCLEAR ENGINEERING DIVISION - LIPA ENVIRONMENTAL ENGINEERING DEPARTMENT - LILCO 9405040178 931231 PDR ADOCK 05000322 R PDR
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4_h. ,ra2 SHOREHAM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31,1993 ISSUED BY NUCLEAR ENGINEERING DIVISION - LIPA ENVIRONMENTAL ENGINEERING DEPARTMENT - LILCO TELEDYNE ISOTOPES
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l TABLE OF CONTENTS PAGE EXEC UTIVE
SUMMARY
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 I. THE PRO G RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 A Obj e c tive s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 H Sample Collection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
- 1. Aquatic Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
- 2. Atmospheric Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
- 3. Terrestrial Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
- 4. Direct Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 C Q uality Assurance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 D. Data Interpmtation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
- 1. G e n e ral . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
- 2. Gamma lsotopic Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 E. D os e As ses s m e n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 E Pro gram Su mm ary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 II. RESULTS AND DISCUSSION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0 A Aquatic Environm en t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
- 1. Surface Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
- 2. Fi sh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
- 3. Invertebrate s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
- 4. S e d im e n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 l B Atmospheric Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 l
- 1. Airborne Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1
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l TABLE OF CONTENTS (cont.)
C Termstrial Envimnment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .15
- 1. Fo od Prod u cts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 5 D. Direct Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 4
E. Dose Assessment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 r
III. C O N C LU SI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2 IV. RE FE RE N C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4 APPENDIX A - Radiological Environmental Monitoring Program Sununary - 19 93 . . . . . . . . . . . . . . . . . . . . 2 7 APPENDIX B - Sample Designation and Sampling Locations ....33 APPENDIX C - Data Table s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1 APPENDIX D - Analytical Procedures Synopsis . . . . . . . . . . . . . . . . 5 5 APPENDIX E - Summary of EPA Interlaboratory Comparisons ... 64 APPENDIX F - REMP Sampling and Analytical Exceptions . . . . . . 93 '
APPENDIX G - SNPS Land Use Surveys . . . . . . . . . . . . . . . . . . . . . . 9 8 APPENDIX H - Common and Scientific Names of Species Collected in the Radiological Environmental Monitoring Program . . . . . . . . . . . . . . . . . . . . . . . . 104 -
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l LIST OF TABLES Na TITLE PAGE
- 1. Synopsis of the Shoreham Nuclear Power Station's i Radiological Environmental Monitoring Program for the Period January 1 through December 31, 1993 . . . . . . . . . . . . . . . . . . . 1 1 Appendix A - Radiological Environmental Monitoring Program
) Summary 1993 A-1 SNPS REMP Summary Jan. I to Dec. 31, 19 93 . . . . . . . . . . . . . . . . . . . 2 7 Appendix B - Sample Designation and Sampling Locations i B-1 Sample Locations Required by SNPS Offsite Dose Calculation Manu al . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 5 B-2 Airborne Particulate Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . 3 6 B-3 Waterborne Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6 B-4 Ingestion Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6 B-5 Direct Radiation Monitoring Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 Anoendix C - Data Tables Aountic Environment 1
C-1 Concentrations of Tritium and Gamma Emitters in Surface Water Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2 C-2 Concentrations of Gamma Emitters in Fish Samples . . . . . . . . . . . . . . 4 3 I
C-3 Concentrations of Gamma Emitters in Invertebrate Samples . . . . . . . 44 C-4 Concentrations of Gamma Emitters in Sediment Samples . . . . . . . . . 45 111
LIST OF TABLES (cont.)
M TITLE PAGE Annoscheric Environment C-5 Concentrations of Gross Beta Emitters in Weekly Airborne Particulate Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 6 C-6 Concentrations of Gamma Emitters in Quarterly Composites of Airborne Particulate Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 9 Terrestrial Environment C-7 Concentrations of Gamma Emitters in Food Product Samples . . . . . 50 Direct Radiation C-8 Direct Radiation Measurements - Quarterly TLD Results. . . . . . . . . . 51 Lower Limits of Detection C-9 Typical LLDs Achieved for Gamma Spectrometry. . . . . . . . . . . . . . . . . 52 C-10 LLDs and Reporting Action Levels Required by Offsite Dose Calculation Manual and 1993 Contract . . . . . . . . . . . . . . . . . . . . . 53 Anoendir F REMP Sampling and Analytical Exceptions F-1 REMP Exceptions for Scheduled Fish Sampling and Analysis During 19 93 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 4 F-2 REMP Exceptions for Scheduled Invertebrate Sampling and Analysis During 199 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 5 F-3 REMP Exceptions for Scheduled Airborne Particulates Sampling and Analysis During 1993 . . . . . . . . . . . . . . . . . . . . . . . . . 9 6 F-4 REMP Exceptions for Scheduled Food Products Sampling and Analysis During 1993 . . . . . . . . . . . . . . . . . . . . . . . . . 9 7 1
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LIST OF TABLES (cont.)
NO. TITLE PAGE Anoendir G SNPS Land Use Surveys G-1 REMP 1993 Land Use Census Nearest Milk Animal . . . . . . . . . 100 -
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G-2 REMP 1993 Land Use Census Nearest Garden . . . . . . . . . . . . . 101 G-3 REMP 1993 Land Use Census Nearest Residence . . . . . . . . . . 102
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Anoendir H H-1 Common and Scientific Names of Species Collected in th e REM P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105 LIST OF FIGURES TITLE
- 1. Average Weekly Gross Beta Results in Airborne Particulates . . . . . . . 17
- 2. Comparison of Average Monthly Gross Beta Results in Airborne Particulates (February 1977 - December 1993) . . . . . . . . . . . . . . . . . . . I 8
- 3. Comparison of Average TLD Results (February 1977 -
December 1993)...........................................20 APPENDIX B - SAMPLE DESIGNATION AND SAMPLING LOCATIONS LIST OF MAPS B-1 Shoreham Site Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 8 B-2 On Site Sampling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 9 B-3 Off Site Sampling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 0 9
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EXECUTIVE
SUMMARY
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EXECUTIVE
SUMMARY
This report summarizes the Shoreham Nuclear Power Station's (SNPS) Radiological Environmental Monitoring Program (REMP) operations and results for 1993.
The objective of the SNPS REMP is to monitor the radiation level and the radioactivity concentrations in the plant offsite environs, and to identify .
and measure those that are attributable to the operations and activities of j the plant. When such plant-derived radiation level or radioactivity concentrations are found, verify that the projections of amount of releases /
and resultant doses to the surrounding population, as made by models and '
methods contained in the plant's Offsite Dose Calculation Manual (ODCM),
are reasonable.
In the current non-operational, decommissioning phase of the plant, I as well as in the earlier operational phase, REMP uses the preoperational baseline data to identify plant contributed radiation or radioactivities, and evaluates the effects of plant radioactive effluents, when detected, on the environment.
The SNPS REMP is designed to comply with the plant's Technical Specifications, ODCM and NRC Regulatory Guides as described in licensing basis documents.
The REMP data are acquired by sampling various media in the environment which are then analyzed for radiation levels and/or radioactivity concentrations present. Media sampled within the aquatic environment in 1993 included surface water, fish, invertebrates (squid, lobsters, etc.) and sediment. The atmospheric environment was sampled for airborne particulates throughout the year. Starting in June, locally growm food products were sampled monthly during the growing season. Direct radiation in the environment was measured using TLDs.
Radioactivity in environmental media varies from sample to sample as well as geographically; therefore, a number of sampling locations for each medium were selected using available meteorological, land and water usage data. Sampling locations are designated as either indicator or control locations. The indicator locations are placed close enough to Shoreham so that plant contributed radiation and radioactivity will be at their highest levels. The control sample locations are placed so that they will be beyond measurable influence of Shoreham and any other nuclear facilities. An exception to this occurred at the onshore site for REMP location 13G2, at the entrance to Port Jefferson Harbor. During preoperational testing, aquatic samples revealed the presence of low levels of fodine-131. An investigation revealed that the iodine-131 was from area hospitals treating patients for thyroid carcinoma. Thereafter, until 1990 a second onshore aquatic background location was sampled at the entrance to Mt. Sinai Harbor.
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In 1993, as the decommissioning effort at Shoreham continued under the Possession Only License (POL), REMP continued to be implemeuted but at a reduced level from that required under the full power operating license, with decreased scopes in sampling and analyses. Surveillance of soil, milk, game, precipitation, airborne iodine, aquatic plants and ground water remained discontinued, as did radiochemistry analyses for Sr-89, Sr-90 and I-131. Monitoring of direct radiation by TLD continued at a reduced scope, being conducted only at stations near the site boundaries.
A number of radioactivity analyses were performed on each medium sampled. Not all samples underwent all types of radioanalyses, only those analyses appropriate for the particular medium sampled were performed.
l The analyses included gamma spectrometry, tritium concentration, gross beta and direct gamma radiation.
Dose calculations for the SNPS environs were performed using concentrations of radioactivity detected in the samples collected. In all cases the calculated doses were similar to background doses calculated for previous years. Therefore, no environmental radioactivity was identified as having originated from SNPS. l 1
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I. PROGRAM 4
THE PROGRAM The Shoreham Nuclear Power Station's (SNPS) Radiological Environmental Monitoring Program (REMP) is conducted in compliance with NRC Regulatory Guide 4.15 SNPS Technical Specification Section 6.7.4.b, and SNPS Offsite Dose Calculation Manual (ODCM) Section 3/4.12.
The REMP was developed in general accordance with the NRC Radiological Assessment Branch Technical Position (BTP), Rev. 1, Nov. 1979, and findings in the Environmental Report (ER) Section 6.1.5. All samples were collected by personnel of the Long Island Lighting Company (Environmental Engineering Department) or contractors hired for the collection of aquatic samples. A synopsis of the sampling program can be found in Table 1. Maps and a description of sampling locations appear in Appendix B.
During 1993 sample analyses were performed by Teledyne Isotopes of Westwood, New Jersey (referred to throughout the text as either "TI" or "the laboratory"), under contract to LIPA. A summary of analytical results appears in Appendix A and individual analysis results in Appendix C. Aquatic sample collections were performed by LILCO's Environmental Engineering Department and Energy & Environmental Analysts Inc. (EEA Inc.) under contract to LIPA.
A. Objectives The objectives of the radiological environmental monitoring program are:
- 1. Identify and measure plant generated radiation and radioactivity in the plant environs, and calculate associated potential doses to the surrounding population. l
- 2. Verify the effectiveness of in-plant measures used for controlling the release of radioactive materials.
- 3. Provide reasonable assurance that the predicted doses, based on effluent data and ODCM methodologies, have not been substantially underestimated and are consistent with applicable standards.
- 4. Comply with regulatory requirements and allowable limits, SNPS Technical Specifications and ODCM requirements, and provide records to document compliance.
a Sample Collection
- 1. Aquatic Environment The aquatic environment at the SNPS site was examined by i analyzing samples of surface water, fish, invertebrates, and sediment. !
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Surface water samples were taken at three locations, including 13G2 at the entrance to Port Jefferson Harbor, in May and October using a Niskin bottle. The samples were placed in new polyethylene bottles following three rinses with the sample medium prior to collection.
Samples of Bluefish IPomatomus saltatrix), Winter Flounder IPseudopleuronectes americanus), Windowpane (Scophthalmus aquosus), Sea Robin (Prionotus smL.), and Little Skate (Baja erinaceal were taken by trawl, sealed in plastic bags, frozen, and shipped to the laboratory for analysis.
Invertebrate samples of American Lobster (H o m a r u s americanus), Squid (Loligo pealeit) and Channeled Whelk (Busvcon canaliculata) were collected by trawl. Channeled Whelk were also collected using pots. These invertebrate samples were sealed in plastic bags, frozen and shipped to the laboratory for analysis.
Beach sediment samples were also collected, sealed in plastic bags, frozen and shipped to the laboratory.
- 2. Atmospheric Environment The atmospheric environment was examined by analyzing airborne particulates collected on Gelman Type A/E filters using low volume air samplers (approximately 1 cfm). The samplers used were equipped with a vacuum recorder for sample volume correction to ensure sample validity and to indicate any maintenance problems.
Should the sampler lose vacuum due to a leak, the vacuum level reading will drop to zero. Since this may occur without a corresponding loss of electric supply the exact time of the maintenance problem will be evident on the vacuum recorder chart.
Sample volumes were measured using dry gas meters and corrected for differences between the actual pressure seen by the volume meter and the average atmospheric pressure. Sample volumes are corrected to standard pressure using average weekly barometric pressure (measured at LILCO's Environmental Engineering Department, Melville) and air sampler vacuum readings. Time totalizers indicate the duration of time the sample was taken.
- 3. Terrestrial Environment The terrestrial environment was examined by analyzing samples of locally grown food products during the growing season (June to November).
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- 4. Direct Radiation Direct radiation levels in the environs were measured with energy compensated calcium sulfate (CaSO4 :Dy) TLDs, each containing four separate readout areas. The TLDs are annealed by LILCO prior to placement in the field. After the quarterly collection, the TLDs are packaged and shipped to the laboratory for analysis along with a control dosimeter, and new ones are placed for the next quarterly period.
C. Quality Assuranca Teledyne Isotopes has an extensive quality assurance program designed to ensure the precision and accuracy of the data generated.
An Interlaboratory Comparison Program is conducted with the Environmental Protection Agency (EPA). The results of the Program analyses are listed in Appendix E. Participation in this program permits estimation of bias in TI results from the deviation from the "known" value given, or by comparison with means of all participants.
The TI Quality Assurance Program for Radiological Monitoring is described in various TI publications (References 15, 16, 17).
Approximately 10 percent of TI's total analytical effort is spent on quality control including process quality control, instrument quality control, intra- and inter-laboratory cross check, and comprehensive data review. In addition, LIPA specifically requires that two percent of its analyses be duplicated for further quality control cross check.
Additional information on the LIPA Quality Assurance Program is provided in LIPA NED 417004, Quality Assurance Program for Radio-logical Environmental Monitoring Program. Shoreham Nuclear Power Station.
D. Data Interoretation i 1. General The analytical data generated during 1993 were routinely evaluated by the TI project leader who served as liaison with Long Island Lighting Company's Environmental Engineering Department and LIPA's Nuclear Engineering Division. Several factors are important in the interpretation of the data. These factors are discussed here to avoid repetition in sections that follow.
Within the data tables (Appendix C) an approximate 95 percent (i2 sigma) confldence interval is supplied for those data points above the lower limit of detection (LLD). These intervals represent the range of values into which 95 percent of repeated analyses of the same 7
sample would fall. Tables C-9 and C-10 present typical and required LLDs, respectively.
Results for each type of sample were grouped according to the analysis performed. Means and standard deviations of these results are calculated when applicable. The calculated standard deviations of grouped data represent sample rather than ansJytical variability. For these calculations any values below LLD are considered to be at the LLD. As a result, the means are biased high and the standard deviations are biased low. When a group of data is completely composed of LLD values, averages are not calculated.
Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of 4 radionuclides is expected to vary minimally with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium. This method,. however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation of radionuclide concentrations in the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of i averages based upon repetitive grab samples is valid. I
- 2. Gamma Isotopic Analyses SNPS ODCM Table 3.12.1-1 requires that analyses be performed on all media for gamma emitting radionuclides which may be attributable to effluents from the plant. These analyses include specific gamma emitters such as I-131, Cs-134, Cs-137, Ba-140, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95 and Nb-95. Industry experience suggests that these are the most likely radionuclides. to find their way into the environment from a BWR nuclear power plant.
Gamma spectroscopy is expected to identify most other nuclides which may be discharged when the LLDs for specifled gamma emitters are met by this technique.
Tables 3.1 and 3.2 of the Shoreham Final Environmental l Statement list the calculated liquid and gaseous effluents by 1 radionuclide in curies per year. These release rates assume normal l operation of the plant, including anticipated operational occurrences.
Those nuclides listed in Tables 3.1 and 3.2 which are not routinely ]
i observable by gamma spectroscopy and which are not specifically l analyzed in other ways fall into two categories:
- 1. Those radionuclides with half-lives on the order of hours or minutes which cannot accumulate appreciably in the environment (Na-24, Cu-64, Zn-69m, 2n-69, Sr-91, Y-91m, Y-92, Y-93, Tc-99m, Rh-103m, Rh-105, Rh-106, Te-129 Te-I' 8
, 131m, Te-131, I-132, I-135 Ba-137m, Pr-143, Ce-143, Pr-144 and W-187).
- 2. Those radionuclides with no gammas (P-32, Fe-55), those with a trivial percentage of their transitions going by gamma emissions (Y-91), or those with their primary gamma occurring at such a low energy and at such low abundance that it is not routinely observable in the presence of other gamma .-
activity (Nd-147). With only 10 pCi of Nd-147 calculated to be ,
released per year in Shoreham's liquid effluents in the j operational mode, the nuclide cannot be an important contributor to dose.
E. Dose Assessment The methodology for determining doses is similar for all pathways. Laboratory analyses from the REMP for each sample type ,
are compiled. Data from all locations taken on the same date are s
averaged to obtain the most reliable approximation of the radioactivity concentration on that date for that sample type. The averages of all dates are then taken to provide the best approximation of radioactivity concentrations for the year.
When an average value has been obtained which represents a sample medium or an exposure pathway, it can then be used to calculate the dose for the year. Additional information, such as the quantity of fish, vegetables, etc., consumed per year by the maximum exposed individual is also needed to calculate the total dose (Reference 13).
The dose due to direct radiation exposure is monitored by TLDs.
The laboratory results for TLDs are expressed in dose units directly and do not require any additional calculations. '
The dose to the total body or to a specific organ is then calculated by the product of the radionuclide specific dose conversion factor for its applicable exposure pathway, the environmental sample radionuclide concentration, and the ingestion or inhalation rate of the sample or medium of interest. For example, the following general equation expresses this principle:
Dose = Concentration X Quantity ingested X Dose factor (mrem /yr) per sample per year The sample concentration is typically expressed in pCi/L or pCi/kg. For the ingestion pathway, the quantity ingested or consumed per year is expressed in kg/ year or L/ year. Finally, the dose conversion factor is expressed in terms of mrem /pCI ingested or inhaled.
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F. Program Summarv Table 1 summarizes information on the REMP as performed during the period of this report, January 1 through December 31, 1993. During this reporting period 466 separate analyses were performed on 438 environmental samples.
Appendix A summarizes the analytical results obtained from the SNPS REMP. The format used is that recommended in NRC Radiological Assessment Branch Technical Position (BTP), Rev.1, Nov.
1979. Appendix B describes the sample coding system, which
. specifles sample type and relative locations at a glance. In addition, pertinent information on individual sampling locations, and maps which show their geographic location, are included.
Appendix C presents the analytical results of the Shoreham Nuclear Power Station's Radiological Environmental Monitoring Program for the period January 1 through December 31, 1993.
Appendix D contains a synopsis of the analytical procedures used in the REMP.
Results of the EPA interlaboratory comparison program can be found in Appendix E. Appendix F lists the program exceptions for 1993, and Appendix G reports the Land Use Census performed by LILCO's Environmental Engineering Department during 1993 in the vicinity of the SNPS. Common and scientific names of species collected in the program are presented in Appendix H.
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TABLE 1 SYNOPSIS OFTliE SIIOREllAM NUCLEAR POWER STATION'S RADIO!EGICAL ENVIRONMENTAL MONITORING PROGRAM FOR Tile PERIOD JANUARY I T11ROUGli DECEMBER 31,1993 SAMPLE SAMPlJNG NUMilER ANALYSIS NUM11ER TYPE FREQUENCf LOCATIONS COLLECIED ANALYSIS FREQUENCY PERFORMED Aountic Environment Surface Water Semlannual 3 8 H-3 Semlannual 8
. Gamma Semlannual 8 Fish Semiannual 3 3I Gamma Semlannual 31 Invertebrates Semiannual 3 19 Gamma Semlannual 19 Sediment - Beach Semlannual 1 2 Gamma Semlannual 2 Atmospheric Environmejtt Airborne Particulates Weekly 5 276 Gross Beta Weekly 276 Gamma Quarterly 20 Terrestrial Envirt1grie31 Food Products Monthly 4 30 Gamma Monthly 30 Direct Itadiation TLD Quarterly 18 72 Gamma Dose Quarterly 72
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IL RESULTS AND DISCUSSION 12
RESULTS AND DISCUSSION The analytical results for the reporting period of January 1 through December 31, 1993, have been divided into four categories: aquatic, atmosphenc, terrestrial, and direct radiation. The individual samples and analyses within each category display the unique radiological characteristics of that type of environment. Analytical results of the REMP are summarized in Appendix A. The data for individual analyses are presented in Appendix C.
A. Aquatic Environment The aquatic environment in the vicinity of SNPS consists primarily of Long Island Sound. The radiological characteristics were studied by analyzing samples of surface water, winter flounder, windowpane, sea robin, bluefish, little skate, lobster, squid, channeled whelk, and sediment. The samples were collected by LILCO's Environmental Engineering Department and Energy & Environmental Analysts Inc. (EEA Inc.) under contract to LIPA.
- 1. Surface Water (Table C-1)
Semiannual surface water samples were taken at three locations and analyzed for tritium. Gamma spectroscopy was also performed on all samples.
There was no detectable tritium in any surface water sample. This compares consistently with the 1992 tritium results, which were also all below the detection limit.
Naturally occurring potassium-40 was measured in all eight semiannual samples over three locations with an average of 231 pCi/l and a range between 88.9 to 277 pCi/1, as compared with 1992's average of 227 pCi/l and a range between 128 and 310 pCi/1. No other gamma activity above the detectable levels was measured in the six surface water indicator location samples as analyzed by gamma spectroscopy.
- 2. Fish (Table C-2)
Thirty-one fish samples were collected at three locations and the edible portions analyzed for gamma emitters. Gamma spectrometry showed potassium-40 present in all samples with an average concentration of 3250 pCi/kg wet and a range between 1830 to 5390 pCi/kg wet, comparing with 1992's average of 3590 pCi/kg wet and a range between 1630 and 5720 pCi/kg wet. Cesium-137 was not detected in any samples during 1993.
This compares well with 1991 and 1990 when cesium-137 was detected in three fish samples.
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- 3. Invertebrates (Table C-3)
Nineteen invertebrate samples, comprised of lobsters, squid, and whelk, were collected at three locations and analyzed for gamma emitters.
Gamma spectrometry showed detectable levels of potassium-40 in all samples, ranging from 1640 to 3510 pCi/kg wet with an average activity of 2805 pCi/kg wet. These compare well to 1992's average potassium-40 activity of 2905 pCi/kg wet and a range between 595 and 4440 pCi/kg wet.
Thorium-228 was not detected during 1993 and this compares favorably with the one measurement of thorium of 117 pC1/kg wet in a lobster sample in 1991. No cesium-137 activity was detected in 1993 samples, versus an average of 33.8 pCi/kg wet out of two 1990 lobster samples.
- 4. Sediment (Table C-4)
Two beach sediment samples were collected at one location and analyzed for gamma emitters. Both samples had measurable activities of naturally occurring potassium-40 with an average activity of 2580 pCi/kg dry and a range of 2490 to 2670 pCi/kg dry. This is higher than the average concentration of potassium-40 of 1845 pCi/kg dry with a range of 1790 to 1900 pCi/kg dry measured in 1992. Thorium-228 was measured in both samples with an average activity of 95.0 pCi/kg dry and a range of 77.0 to 113 pCi/kg dry. This is slightly lower than the average thorium concentration of 132 pCi/kg dry with a range of 101 to 163 pCi/kg dry measured during 1992. All other gamma emitters were below the lower limits of detection.
B. Atmospheric Environment The atmospheric environment in the vicinity of the SNPS was examined by analyzing samples of airborne particulates at five sampling I locations. Airborne particulate filters were collected weekly and analyzed '
for beta emitters. Quarterly composites from each station were analyzed for gamma emitters. l
- 1. Airborne Particulates (Tables C-5 and C-6)
Beta-emitter concentrations ranged from 0.005 to 0.029 pCi/m3 with an annual average for the five sampling locations of 0.016 pCi/m3 (Table C-5). Of the 276 measurements two were below the gross beta detection limit, nominally 0.008 pC1/m3 Figure 1 shows the average weekly gross beta fluctuations in airborne particulates from all stations for 1993. Figure 2 represents the average monthly gross beta results in airborne particulates from January 1,1977 through December 31,1993.
Results of gamma spectrometry (Table C-6) showed detectable levels of naturally occurring beryllium-7 in all twenty samples. The average beryllium-7 activity in the quarterly analyses was 0.092 pCi/m3 with a range of 0.054 to 0.160 pCi/m3 Naturally occurring potassium-40 was observed 14
in four samples with an average concentration of 0.007 pC1/m3 and a range of 0.004 to 0.011 pCi/m3. Cesium-137 was not measured during 1993. All other gamma emitters were below the lower limit of detection.
C Terrestrial Environment
- 1. Food Products (Table C-7)
Thirty fruit and vegetable food products grown locally were collected and analyzed at both control and indicator locations, including potatoes, cabbage, lettuce, carrots, corn, and strawberries. All samples contained naturally occurring potassium-40 with an average of 2620 pCi/kg wet and a range of 1180 to 4890 pCi/kg wet. Also naturally occurring beryllium-7-was observed in four samples (3 from an indicator location and 1 from a control location) with an average concentration of 143 pCi/kg wet and a range of 75.6 to 202 pCi/kg wet. All other gamma emitters were below the lower limits of detection. The detection limit varied from 4 to 100 pCi/kg wet.
D. Direct Radiation (Table C-8)
I Direct radiation measurements were taken quarterly at 18 locations during 1993, using CaSO4 :Dy thermoluminescent dosimeters (TLDs). TLDs were used to detect radiation levels near ground level in the vicinity of the Shoreham site due to terrestrial and cosmic gamma ray emitters and possible SNPS contributed direct radiation. Figure 3 presents a comparison of average TLD results from 1977 to 1993.
All TLD results presented in this report have been normalized to a standard month (30.4 days) to eliminate the apparent differences caused by the variations in exposure period. The average. of the quarterly exposures of all 18 locations was 3.5 mR/ standard month which is the same as the average quarterly exposure of the 16 indicator locations only. This is less than quarterly values, 4.1 and 4.3 mR/ standard month, respectively, measured during the preoperational years 1983 and 1984.
Annual average results of all quarters at the same locations, as well as of all locations for each quarter, are given in Table C-8 with 95%
confidence limits for the mean value, except for the average of all locations and all quarters. For this last value, the 95% limits about any individual measurement, i.e., 1.2 mR/std. month, is given. The 95% interval for the mean of all 18 locations for any single quarter is 3.5 i 1.0 mR/std. month, versus that for the mean of all four quarters at any location at a value of 3.5 i l 0.73 mR/std. month.
l 15
- _______.___.___.__________-_-_m_________m_-_- __-_m. _____._. _ . _ _ _ _ _
E. Dose Assessment Initially, all positive concentrations of radionuclides in indicator samples, as shown in Appendix A, were considered for inclusion in the dose l calculation. In an attempt to factor out as much of the contribution due to natural and man-made background radiation as possible, indicator and i control sample results were compared. If the control location results were '
greater than those at the indicator location, the indicator sample results were not included in the dose assessment.
Since no radionuclide other than the naturally occurring !
potassium-40 was found in all the waterborne and aquatic samples, surface water from Long Island Sound was therefore, not considered in the dose assessment. The dose due to standing on soll/ sediment was not calculated since this is accounted for in the direct radiation dose.
Beryllium-7, potassium-40, radium-228 and thorium-228 are all naturally occurring isotopes and not likely to be produced as a result of the operation of Shoreham, so they were excluded. Cesium-137 was not detected in any REMP samples during 1993. Therefore, after excluding these four naturally occurring isotopes identified and measured in all the 1993 REMP samples, there was nothing traceable to the Shoreham activities and the resultant doses are zero.
In 1993, during the first, second and the fourth quarters of decommissioning activities at Shoreham, there were minute, below regulatory-limit releases of iron-55, strontium-89 and cobalt-60 activities, respectively, through the liquid discharge pathway. The concentrations and the total activities released were 0.06 pCi/ml, 0.01 pCi/ml, and 0.03 pCi/ml, 0.011 Cl, 24.6 pCl, and 1.33 pC1, respectively, for iron-55, strontium-89 and cobalt-60. The absense of these nuclides in all the REMP samples collected through all the quarters has proved that these below- :
limit releases had no radiological impact on the environment. 1 Comparison of environmental concentrations found in 1993 shows that they are consistent with those of 1983. For 1993, therefore, there is no discernible dose components other than those from natural sources in the environment.
l l
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16
F )
FIGU RE 1'-
AVERAGE WEEKLY GROSS BETA RESULTS IN AIRBORNE PARTICULATES 1000 _ __ _ _ _ _ . _ _ _. _ _ _ . _ _ . _ _ . _ _ . _ . . . . . _ _ . . _ . . . _ _ . _ . . _ . . . . . _ _
. . _ _ . . ._ _--'~~~ ~- J~ ~~~ _ :--- ~ ~ ~ :~' ::::::. _ .. ._ . _ _ . . . . _ . . _ . . . . . . . _ . _ _~~---
.e .e.me.e. e .*.e e . wen *+. m.. .areen..w.sar .m+..+ ..s..h .,.m u.am.a._ 3.,
....,.::::~~'-^~' ' :::~
~~~~
_ _ _ . _ . . : ~T 1 ::"~ ~ ~ ~ ~ ' ~ * - -. -
~ ~ ~ ~ ' ~ ~
. : . _ . . . . .__ _ . . . . . . _ ~ ~ ~ ...__ . ~T. ._. .TZ ~ ~1ZZZ
- Q . _ . . . _ . _ _ _ . _ . _ _ . . - _ .
N g . _.. _
n . . _ . . . . . . . . . . - - - .. -_ -- -
10 - . . , _ _ . _ _ -
__4 :g.f m. y....__.__.._...._.
.1.
~
1 e .. _ .
? _ _ . . . _ _ .
^1' e i i i 6 .i i i. , i 3 Jan, Feb Mar Apr . May - -Jun 'Jul . A'ug - _ Sep Oct . .Nov . D'ec ' Jan' 1993 C~ '
) j
r- 3
- FIGURE 2 COMPARISON OF AVERAGE MONTHLY GROSS BETA RESULTS IN AIRBORNE PARTICULATES 1000 . _ ._ _ _ _.. . -._._ _ _ _ _ _ . _ . . _ . . _ __
~
._ . _ _ . _ _ J~l" - l1. _.. .
~
~~
-. _ . _ . _ . _~.__.._..._ ~~1 ._ .l..l.l.. E ' ~~~ ~~ll l
,. ...,4
- _. _ .a...-e .we..e-
. , , .., , , , , , , m . , _ , _ , , , , _ , , , , , , , , . , ,
5 ..,. ..._~' _2'2... " _.. ~.[.I"
. . . . _ ~.._..._ . - _ . _
- . _ = =
w q -- .. .. . _ . . _ . . . - - . - . . _ _ _ . . . _ . . . . - -
c . . _ . - _ _ . _ _ _ _ . _ . _ . - _ _ . _ . . - __.
W ___ - . . . . . ....- _ ... _ _ . . .. ._ ___ _ _ _ . _ . . . . _ _ ._ _ . . . _
10: ;- :. .. _:_.
_- x:2 - - _=- ._ _
._ .1:Z_. _ ._ . ~ ... T
~ ~ ~~ ~~ ' ~
~-~ Z:~ ~Z:.. ~ _ . ... ... _._.. _ ..:Z:: J. .. _. _ f~_ ._ _._ . . . _ _ . _ . . _ .._..~~
l
~
_ i . _..I
- ~~ ~ ~ ~~
._~~'~TT.E..T ~~ - . . . _ . _ .
+e..... e . - = . * * . . - * *p.+ .=w=.- o.o..ei .e. .. %
4-.,.3,. _-.we +%.e_# . -.... -e.-ee..>w-...w.-. . .q. -,,. . .,, ,,,,.w,. , , , , , , , , _ , , , , , , , , ,
1 1/77 1/78 1/79 1/80 1/81 1/82' 1/83- - 1/84 ~ 1/85 '1/86 k 1 J
9 -
</
A
( 3 FIGURE 2 (Cont.)
COMPARISON OF AVERAGE MONTHLY GROSS BETA RESULTS IN AIRBORNE PARTICULATES 1000 _ _ _ _ _.__ _ _ _ _.. __.. ...._. !
., . ..u.+. .. - m,. %- *. +-, - '
b h, 100: - -
w _ _ _ _ _ _ _ _ _ _..
- -m,-.. ma -. , + . + . - ~ aw+ .--.-e-4 -
--,a.. . ~-. -e.-, --
< -. -. - -+--.. a g a ,,,.,,, ,
10: -
_. ..-.. -_ - ...-. - _ ..--.. ~.._... . _ -
[ -- . m -. .. - .- -- - .-*-.,.p,.. , .--- ,,, .,.,,,
. . - - . . .- , . _ . . . . ~ ~r, - . . . . - .
...-.-e .- + . = - . - e.e.--++..- _~ - 4,--- .<.5 .e+- -- e. . , w. , ,
1 1/86- 1/87 - 1/88 1/89 1SO 1/91 1G2 1S3 1G4-W )
o
l
/ - ,
FIGURE 3' COMPARISON OF AVERAGE TLD RESULTS(1977-1988) 10
'9- -
8- ---
s- 7-p - -
E:
a E g .e. _ _ . _ _ _ . . _._
E.
5- -
'4 __ _ _ __
4 3 -
\
'l 1/77 1/78 1/79 - ,1/80' 1/81' ' 1/82. 1/83' 1/84' 1/85' 1/86.- '.1/88
,1/87 -
\
t I
FIGUHE 3 (Cont.)
COMPARISON OF QUARTERLY AVERAGE TLD RESULTS (1988-1993) 10
- g. _ - . . . . -- - - - -- - - _ . - . - . . -
- ~
8- - - - - - - - -- - -- - - - - - - -
2 E
p 7 - - - - -- - - - - - - -
[
E 6 - -- - - . . . - - . - - . . .- - - - . - --
5- ~ --- - -- --- -
4- - - -- - - - - - - - - -- -- - - - . -- - - - - - - - - .
O =
3 - - - -_ - _. __. -_. .
2 1/88 2/88 3/88 4/88 1/89 2/89 3/89 4/89 1/90 2190 3/90.4/90 1/91 2/91 3/91 4/91 1/92 2/92 3/92 4S2.1S3 2/93 3/93 4/93 Y' )
mmm \
i 1
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\
III. CONCLUSIONS i
l 4
i 1
I I
i 1
1 22
CONCLUSIONS The unit was defueled in August 1989, and has subsequently been in a non-operating condition. On February 29,1992, the Shoreham plant license was transferred from LILCO to LIPA. On June 11,1992, NRC issued LIPA a Decommissioning Order. The REMP operation continued through these plant ownership and license changes in 1993 without interruption.
Analyses of environmental samples show results consistent with those found during the preoperational years of 1983 and 1984. In addition, comparison of results reveals little difference between indicator and control locations. Therefore, no isotopes could be identified as having originated from SNPS.
Effect on the environment from two decades of atmospheric nuclear weapon testing ending in the early 80's and the Chernobyl accident in 1986 has subsided noticeably in the past several years. This trend is evident through the gradual disappearance of one of the leading indicators, cesium-137, in all the SNPS REMP samples from 1990 to 1993, as is also supported by the lowering and leveling of annual TLD readings in recent years.
Aside from these minute and residual radioactivities from past test fallout and the Chernobyl accident in the environment, expected normal background radioactivity has been measured in REMP samples. Aquatic and terrestrial samples were analyzed and reflected the normal background radiation found in the environment. The atmospheric environment was sampled for airborne particulates and Figure 1 shows weekly gross beta results in airborne particulates from January through December 1993.
Figure 2 shows the average monthly gross beta results in airborne particulates from February 1977 to December 1993. Direct radiation levels ;
were relatively low and approximately the same at all locations. Figure 3 shows the average quarterly TLD results in mR/ standard month from ,
January 1977 to December 1993. j l
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l 23 l
a i
W. REFERENCES l
1 l
i l
l J
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i 24
\
1 IV. REFERENCES (1) Long Island Lighting Company, "Shoreham Nuclear Power Station, Environmental Report, Construction Permit Stage", December 1977.
(2) United States Atomic Energy Commission, Directorate of Licensing,
" Final Environmental Statement Related to Operation of Shoreham l Nuclear Power Station", Docket No. 50-322, September 1972.
(3) Long Island Lighting Company, "Shoreham Nuclear Power Station, Updated Safety Analysis Report".
(4) Long Island Lighting Company and Radiation Management Corporation, "Shoreham Nuclear Power Station Radiological Environmental Monitoring Program - 1977 Annual Report", March 1978.
(5) Long Island Lighting Company and Radiation Management Corporation, "Shoreham Nuclear Power Station Radiological Environmental Monitoring Program - 1978 Annual Report", April 1979.
(6) Long Island Lighting Company and Radiation Management Corporation, "Shoreham Nuclear Power Station Radiological Environmental Monitoring Program - 1979 Annual Report", June 1980.
(7) Long Island Lighting Company and Radiation Management Corporation, "Shoreham Nuclear Power Station Preoperational Radiological Monitoring Program - 1980 Annual Report", September 1981.
(8) Long Island Lighting Company and Radiation Management Corporation, "Shoreham Nuclear Power Station Preoperational Radiological Monitoring Program - 1981 Annual Report," October 1982.
(9) Eisenbud, M., Environmental Radioactivity, 2nd Ed.,1973.
(10) National Academy of Sciences, Radioactivity in the Marine Environment, National Research Council, Washington, D.C.,1971.
(11) Long Island Lighting Company, Environmental Engineering Dept.,
Radiological Environmental Monitoring Program Procedures.
(12) EA Science and Technology, Shoreham Project Quality Assurance and Procedures Manual, March 1985.
(13) U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1-1977.
(14) Health Physics Journal, Vol. 38, No.4, April 1980.
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l 25
I IV. REFERENCES (Cont.)
(15) Teledyne Isotopes, " Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual", IWL-0032-361. J (16) Teledyne Isotopes, " Quality Control Internal Controls and Audits, Environmental Analysis Department", IWL-0032-365.
(17) Teledyne Isotopes, " Quality Assurance Manual, Environmental Analysis Department Compliance with 10CFR50 Appendix B and Reg. Guide 4.15", IWL-0032-395.
(18) Long Island Lighting Co. and Teledyne Isotopes,1982 Radiological Environmental Monitoring Program Annual Report.
(19) Long Island Lighting Co. and Teledyne Isotopes,1983 Radiological Environmental Monitoring Program Annual Report.
(20) Long Island Lighting Co. and Teledyne Isotopes,1984 Radiological Environmental Monitoring Program Annual Report.
(21) Long Island Lighting Co. and Teledyne Isotopes,1985 Radiological Environmental Monitoring Program Annual Report.
(22) Long Island Lighting Co. and Teledyne Isotopes,1986 Radiological Environmental Monitoring Program Annual Report.
(23) Long Island Lighting Co. and Teledyne Isotopes,1987 Radiological Environmental Monitoring Program Annual Report.
(24) Long Island Lighting Co.'and Teledyne Isotopes,1988 Radiological Environmental Monitoring Program Annual Report.
(2 5) Long Island Lighting Co. and Teledyne Isotopes,1989 Radiological )
Environmental Monitoring Prograrn Annual Report, t i
(26) Long Island Lighting Co. and Teledyne Isotopes,1990 Radiological I Environmental Monitoring Program Annual Report, j l
(27) Long Island Lighting Co., Long Island Power Authority and Teledyne Isotopes, 1991 Radiological Environmental Monitoring Program Annual Report.
(28) Long Island Lighting Co., IAng Island Power Authority and Teledyne {
Isotopes, 1992 Radiological Environmental Monitoring Program Annual Report. i I
(29) Defueled Safety Analysis Report (DSAR), Rev. 4. July 1992. j (30) Decommissioning Plan Order, June 1992. !
26
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l APPENDIX A
! RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
1993 I
27 l
_. ~. .. . . _ . _ . . . . _ . . ,-__m - . . . _ . . _ - ._. .. . .. _ . _ _ _ . . _ . . _ . _ . _ _ . _ ..-...___._m _
t TABLE A-1 RADIOIDGICAL ENVIRONMENTAL MONITORING PROCJLM
SUMMARY
SHOREllAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUFFOLK COUNTY. NEW YORK JANUARY I to DECEMBER 31,1993 ANALYSIS AND IDWERIJMrr NUMilER OF MEDIUM OR PATifWAY TOTAL NUMBER OF All INDICATDR IDCATIONSf 31 LOCATION Wrrl! IIIGIIESTJE;At! coffrROLIDCA110N(3) NONIK)tfr!NE SAMPLED OF ANALYSES DETECTION MEAN (2) NAME Ml:AN(2) MEAN(2) REPORTED (UNrr OF MEASUREMEffIl PERFORMED (11D) (1) RANGE DISTANCE AND DIRECTION HANGE RANGE MEASUREMENTS Eurface Water H-3 8 100 -(0/6) N/A N/A -(0/2) 0 (pCl/ liter) - -
Gamrna 8 K-40 60 247(6/6) 3Cl 0.1 mi NE 262(2/2) 183(2/2) 0 (193-277) (246-277) (88.9-277)
Cs-137 4 -(0/6) N/A f4/A -(0/2) 0
, y - -
I-131 7 -(0/6) N/A N/A -(0/2) O P1sh Gamma 31 (pCl/kg wet)
K-40 300 3230(24/24) 13G2 13.2 mi W 3320(7/7) 3320(7/7) 0 (1830-5390) (2280-4230) (2280-4230)
Th-228 7 -(0/24) N/A N/A -(0/6) O Cs-137 5 -(0/24) N/A N/A -(0/6) 0 (I) The LLDs quoted are the lowest actual LLDs obtained in the lah for the various media during the reporting period. Typical LLDs were determined for each nuclide as found on Tables C-9 and C-lO.
(2) Means calculated using detectable measurements only. Fractions of detectable measurements in parentheses.
(3) Indicator and control locations are noted in Appendix B. Table B-1.
l TABIE A-1 IContJ RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SHOREllAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUFFOLK COUN'IY NEW YORK JANUARY I to DECEM!!ER 31.1993 ANALYSIS AND IDWER LIMrr NUMBER OF MEDIUM OR PATIIWAY TOTAL NUMBER OF All INDICAMR LOCAT!ONSf31 LOCATION WTTII IIIGilEST VEAN COVIROL IDCA110N(3) NONROtTTINE r i SAMPLED OF ANALYSES DETECT 10N MEAN (2) NAME M E AN(2) MEAN(2) REPOITTED (UNIT OF MEASUREMEKil PERFORMED (tLD) (1) RANGE DISTANCE AND DIRECTION RA4G8 RANGE MEASUREMENTS Aspastic Invertebrates Gamma 19 (pCl/kg wet)
Be-7 200 -(0/14) N/A N/A -(0/5) O K-40 300 2734(14/14) 13G2 13.2 ml W 3006(5/5) 3006(5/5) 0 (1640-3510) (2610-3240) (2610-3240) 0 Cs- 137 4 -(0/14) N/A N/A -(0/5) 0 l
t g Th-228 7 -(0/14) N/A N/A. -(0/5) O e - -
f (1) The LLDs quoted am the lowest actual LLDs obtained in the lab for the various media during the reporting period. Typical LLDs were determined for each nuclide as found on Tables C-9 and C-10.
(2) Means calculated using detectable measurements only. Fractions of detectable measurements in parentheses.
, (3) Indicator and control locations are noted in Appendix fl. Table B-1.
TABIE A-1 (cont.)
RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SHOREHAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUFFOLK COUNTY, NEW YORK JANUARY I to DECEMBER 31.1993 ANALYSIS AND tDWER LIMIT NUMBER OF MEDIUM OR PATIIWAY TOTAL NUMBER OF All INDICAIUR IDCATIONSf 31 IDCATION WTT11 IllGilEST MEAN CONTROL tDCA110N(3) NONROtfrINE SAMPLED OF ANALYSES DETEC110N MEAN (2) NAME MEAN(2) MEAN(2) REPORIED (UNrr OF MEASUREMEN11 PERFORMED (11D) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Sediment (Beach) Gamma -2 (pCl/kg dry)
K-40 900 2580(2/2) 2A4 0.4 mi NNE 2580(2/2) -(0/0) 0
( 2490-2670) 42490-2670) -
Cs-137 8 -(0/2) N/A N/A -(0/0) 0
$ Ra-226 200 500(1/2) 2A4 0.4 mi NNE 500(1/2) -(0/0) 0 Th-228 60 95.0(2/2) 2A4 0.4 mi NNE 95.0(2/2) -(0/0) 0 (77.0-113) (77.0-113) -
(1) The LLDs quoted are the lowest actual 11Ds obtained in the lab for the various media during the reporting period. Typical 11Ds were determined for each nuclide as found on Tables C-9 and C-lo.
(2) Means calculated using detectable measurements only. Fractions of detectable measurements in parentheses.
(3) Indicator and control locations are noted in Appendix B. Table B-1.
TABLE A-1 (Cont.)
RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SHOREHAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUFFOLK COUN'lY. NEW YORK JANUARY I to DECEMBER 31,1993 ANALYSIS AND LOWERIJMrr NUMBER OF MEDIUM OR PATIIWAY 1DTAL NUMBER OF AllINDICA1DR LOCA110NSf31 II) CATION WTrfI IIIG!!EST MEAN CONTROL IDCAT10N(3) NONROtRINE l SAMPLED OF ANALYSES DETECTION MEAN (2) NAME ME AN(2) MEAN(2) REPORIED (tJNTT OF MEAStJREMEffl1 PERFORMED (11D) - (Il RANGE DISTANCE AND DIRECTION RAVGE RANGE MEASUREMEfGS Airborne Particulates Gross Beta 276 4 16.5(220/220) 6S2 0.1 ml ESE 17.4(56/56) 16.0(55/56) 0 (IO 3pC1/m3) (5.4 -29) 15.7-28) (6.5-27)
Gamma 20 Be-7 92.0(16/16) 1IG1 16.6 ml SW 98.7(4/4) 98.7(4/4) 0 (54.3-160) (56.5-134) (56.5-134)
K-40 4 7.22(4/16) 6S2 0.1 ml ESE 10.6(1/4) -(0/4) 0 (4.29-10.6) - -
i Cs-134 0.4 -(0/16) N/A N/A -(0/4) 0
, w Cs- 137 0.4 -(0/16) N/A N/A -(0/4) O c-* . _ r t
(1) The LLDs quoted are the lowest actual LLDs obtained in the lab for the various media during the reporting period. 'lypical 11Ds were determined for each nuclide as found on Tables C-9 and C-10 (2) Means calculated using detectable measurements only. Fractions of detectable measurements in parentheses.
(3) Indicator and control locations are noted in Appendix 13. Table B-1.
TABLE A-1 (Cont.)
RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SHOREHAM NUCLEAR POWER STATION DOCKET NO. 50-322 SUFFOLK COUNIY, NEW YORK JANUARY l to DECEME ER 31.1993 ANALYSIS AND IDWER LIMrr NUMBER OF MEDIUM OR PATilWAY TOTAL NUMBER OF All !NDICAlDR IDCATIONSf 31 LOCATION WrrII IllGIIEST MEAN COffrROL IDCA110N(3) NONROITTINE SAM PLED OF ANALYSES DETECTION MEAN (2) NAME MEAN(2) MEAN(2) IEPORTED (UNir OF MEASUREMEPrr) PERFORMED (ILD) (1) HANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMEffrS Dhect Radiation Gamma 72 (mR/ Standard month) Dose 1.5 3.52(64/64) 9Si 0.2 mi S 4.43(4/4) 3.40(8/8) 0 Quarterly (2.7-6.8) (3.5-6.8) (2.4-5.3)
Food Products Gamma 30 (pCl/kg wet)
K-40 300 2480(24/24) 12H2 32.1 mi WSW 3402(5/5) 3180(6/6) 0 (1180-4120) (2420-4890) (2070-4800)
Be-7 50 127(3/24) 12H2 32.1 mi WSW 202(1/5) 202(1/6) 0 (75.6-158) - -
Cs- 137 6 -(0/24) N/A N/A -(0/6) 0 I-131 7 -(0/24) N/A N/A -(0/6) 0 (11 11 e 11Ds quoted are the lowest actual LLDs obtained in the lab for the various media during the reporting period. Typical 11Ds were determined for each nuclide as found on Tables C-9 and C-lo.
(2) Means calculated using detectable measurements only. Fractions of detectable measurements in parentheses.
(3) Indicator and control locations are noted in Appendix 13. Table 11-1.
-x . _______ _ _ r ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _
APPENDIX B SAMPLE DESIGNATION AND SAMPLING LOCATIONS i
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I APPENDIX B l l
Sample Designation '
LIPA's Radiological Environmental Monitoring Program (REMP) identifies samples by a three part code. The first two letters are the power station identification code, in this case "SN". The next three letters are for the media sampled.
SWA = Surface Water (Long Island Sound) MLK = Cow Milk AQF = Fish (1) GMK = Goat Milk AQI = Invertebrates (1) PWA = Potable Water (ground water)
AQS = Sediment FPV = Food Products (1)
APT = Airborne Particulates FPF = Fruit AIO = Airborne lodine IDM = Immersion Dose (TLD)
The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22 1/2 degrees centered about the reactor site. Sector one is divided evenly by the north axis, and other sectors are numbered in a clockwise direction, i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant:
S = On site location E = 4-5 miles off site A = 0-1 miles off site F = 5-10 miles off site B = 1-2 miles off site G = 10-20 miles off site C = 2-3 miles off site H = >20 miles off site D = 3-4 miles off site i
The last number is the location numerical designation within each sector and l zone, e.g.,1,2,3,.....for example, the designation SN-SWA-3C1 would indicate a l sample in the SNPS program SN, consisting of surface water SWA, which had been collected in the 22-1/2 degree sector centered on the northeast axis (3) between I the site boundary and 2-3 miles off site (C). The number 1 indicates that this is I sampling station No.1 in the designated area.
Sampling Locations All sampling locations and specific information about the individual locations are I given in Table B-1. Tables B-2 through B-5 list the sampling locations and media required by ODCM.
(1) A more specific means of classification will be noted in the comment section of each laboratory report for these samples. For example, AQI will be designated, in the sample description, as aquatic invertebrate. However, the comment section will specify the sample type by the generally accepted common name of the sample involved. In this case, clam, lobster, crab or other aquatic invertebrate would be listed in the comment section.
34
Maps B-1, B-2 and B-3 show the locations of 1993 sampling stations with respect to the site. These maps are tracings of portions of larger maps prepared by LILCO's Survey Division after an extensive land survey of REMP monitoring locations. l Additional information can be obtained by referring to the Site and Vicinity Map of the Shoreham Nuclear Power Station (Map B-2), the map of Long Island and Connecticut Shore (Map B-3) and by contacting either LILCO's Environmental Engineering Department or Survey Division. ;
TABLE B-1 Sampling Locations Required By SNPS Offiste Dose Calculation Manual LOCATION SAMPLE SECTOR CODE LOCATION TYPE N ISI Beach east of intake. 0.3 mi. N IDM NE 3S1 Site Boundary, 0.1 mi. NE APT,lDM ENE 4S1 Site Boundary, 0.1 mi. ENE IDM E SS2 Site Boundary, 0.1 mi. E IDM ESE 6S2 Site Boundary, 0.1 mi. ESE APT,lDM S 9S1 Service Road, 0.2 mi. S IDM W 13S3 Site Boundary 0.2 mi. W IDM WNW 14S2 St. Joseph's Villa, 0.4 mi. WNW IDM NW 15S1 Beach west of intake, 0.3 mi. NW IDM NNW 16S2 Site Boundary, 0.3 mi. NNW IDM NNE 2A2 West end of Creek Road. 0.2 mi. NNE APT,IDM NNE 2A4 Beach, 0.4 mi. NNE AQS SE 7A2 North Country Road, 0.7 mi. SE IDM SSE 8A3 North Country Road. 0.6 mi. SSE IDM SSW 10Al North Country Road 0.3 mi. SSW IDM SW l1A1 Site Boundary,0.3 mi. SW IDM WSW 12A1 Meteorological Tower, 0.9 mi. WSW IDM SE 7B1 Overhill Road, Wading River,1.4 mi. SE APT SSE 8B1 Farm stand 1.2 mi. SSE FPV,FPF ESE 6B21 Farm stand 1.8 mi ESE FPV,FPF NE 3C1 Outfall area, aquatic location B-5 AQF.AQl, 2.9 mi. NE SWA WNW 14C1 Outfall area, aquatic location SWA.AQF, B-4, 2.1 mi. WNW AQI SW C 11G1 MacArthur Substation,16.6 mi. SW APT,lDM WSW C 12G1 Central Islip SubstatJon,19.9 mi. WSW IDM W C 13G2 Background aquatic location,13.2 mi. W SWA AQF,AQI WhW C 12H1 Farm 25.8 mi. WSW FPV,FPF ;
W5W C 12H2 Farm 32.1 mi. WSW FPV,FPF l
C Denotes Control Location 35 l
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REMP LOCATIONS REQUIRED BY SNPS OFFSITE DOSE CALCULATION MANUAL TABLE B-2 Airborne Particulate Monitoring Stations Location - Codes NUREG-0473 SHOREHAM REMP Location Description A1 SS2 Site Boundary,0.1 mi. ESE A2 2A2 West end of Creek Road O.2 mi. NNE A3 3S1 Site Boundary, 0.1 mi., NE A4 7B1 Overhill Road,1.4 mi. SE A5 11G1 MacArthur Substation,16.6 mi. SW TABLE B-3 Waterborne Monitoring Stations Location Codes NUREG-0473 SHOREHAM REMP Location Description WA1 13G2 Surface, background area,13.2 mi. W WA2 14C1 Surface, outfall area,2.1 mi. WNW WA3 3C1 Surface, outfall area, 2.9 mi. NE Wdi 2A4 Sediment, Beach, 0.4 mi. NNE TABLE B-4 Ingestion Monitoring Stations Location Codes NUREG-0473 SHOREHAM REMP Location Description Ib1 3C1 Fish and Invertebrates, outfall area, 2.9 mi. NE Ib2 14C1 Fish and Invertebrates, outfall area, 2.1 mi. WNW Ib3 13G2 Fish and Invertebrates, background, 13.2 mi. W Ic 1 8B1 Local Farm,1.2 mi. SSE Ic2 6B21 Local Farm,1.8 mi. ESE Ic3 12H1 Background Farm,25.8 mi. WSW 36
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I
' REMP LOCATIONS REQUIRED BY SNPS OFFSITE DOSE CALCULATION MANUAL TABLE B-5 i Direct Radiation Monitoring Stations j Location Codes NUREG-0473 SHOREHAM REMP Location Description :
DR1 IS1 Beach east of intake. 0.3 ml. N DR2 2A2 West end of Creek Road, 0.2 mi. NNE DR3 3S1 Site Boundary,0.1 mi, NE -
DR4 4S1 Site Boundary,0.1 mi. ENE DR5 5S2 Site Boundary 0.1 mi. E DR6 6S2 Site Boundary. 0.1 ml. ESE <
DR7 7A2 North Country Road, 0.7 mi. SE '
DR8 8A3 North Country Road, 0.6 mi. SSE DR9 9S1 Service Road SNPS, 0.2 mi. S DR10 10A1 North Country Road,0.3 mi. SSW DR11 11A1 Site Boundary,0.3 mi. SW DR12 12A1 Meteorological Tower, 0.9 ml. WSW DR13 13S3 Site Boundary. 0.2 mi. W DR14 14S2 St. Joseph's Villa, 0.4 mi. WNW DR15 15S1 Beach west ofintake, 0.3 mi. NW DR16 16S2 Site Boundary,0.3 mi. NNW DR30 12G1 Central Islip Substation, 19.9 mi. WSW i DR31 11G1 MacArthur Substation,16.6 mi. SW l
2 37
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APPENDIX C l
l DATA TABLES l
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TABLE C-1 CONCENTRA110NS OF TRITIUM AND GAMMA EMITTERS
- IN SURFACE WATER SAMPLES Results in Units of pCl/l i 2 sigma IDCATION CODE COLLECTION DATE H-3 I-131** K-40 Cs-137 SN-SWA-3Cl 05/18/93 < 200 <8 246 i 40 <4 10/11/93 < 200 <8 277 1 34 <4 i
t SN-SWA-13G2 (ct) 05/18/93 < 200 < 10 88.9 i 35.2 <5 10/11/93 < 200 <9 277 i 36 <3
.N SN-SWA-14C 1 05/18/93 < 200 <8 256 i 34 <4 05/18/93 < 200 <7 193 i 39 <4 10/11/93 < 200 <9 268 i 39 <4 10/11/93 < 200 <8 240 1 33 <3 Average 231 i 127 i 2 s.d.
N1 other gamma emitters rxt listed werr (LLD; typical 11Ds are given in Tables C-9 arx1 C-10.
" l-131 by gamma gmL=ery.
(ct) Denotes Control 11 ration.
TABIE C-2 CONCENTRATIONS OF GAMMA EMITIERS* IN FISil SAMPLES Results in Units of pCl/kg (wet) i 2 sigma IDCATION COIJEC110N DESCRIPTION K-40 Cs-137 Th-228 ,
CODE DATE l
l SN-AQF-3CI 05/10/93 Winter Flounder 3710 1 450 < 30 < 50 ,
05/10/93 Sea Robin 5390 1 860 < 70 < 100 l 05/10/93 Little Skate 2040 1 340 < 30 < 50 ;
05/10/93 Little Skate 2340 1 330 < 30 < 40 I 05/10/93 Windowpane 3660 1 540 < 30 < 70 l 10/04/93 Little Skate 2500 1 250 < 20 < 30 10/04/93 Little Skate 2210 1 220 < 10 < 30 10/04/93 Winter Flounder 3650 i 360 < 20 < 40 10/04/93 Sea Robin 3900 1 1190 < 100 < 200 10/04/93 Bluefish 3700 i 370 < 20 < 40 10/04/93 Windowpane 2500 1 250 < 20 < 30 10/04/93 Little Skate 2400 1 240 < 10 < 20 10/04/93 Winter Flounder 4100 i 410 < 20 < 30 i
' SN-AQF-14C1 05/11/93 Winter Flounder 4270 1 430 < 20 < 30 05/11/93 Sea Robin 4210 i 540 < 60 < 80
, 8 05/11/93 Little Skate Little Skate 23501 240 < 20
< 20
< 30 i 05/11/93 1830 i 180 < 30 t 05/11/93 Windowpane 3620 1 360 < 20 < 30
- 10/06/93 Sea Robin 2310 i 250 < 20 < 30 10/06/93 Little Skate 2080 1 210 < 20 < 20 :
4 10/06/93 Little Skate 2200 1 220 < 20 < 20 l 10/06/93 Winter Flounder 4060 1 410 < 20 < 30
, 10/06/93 Blueilsh 3470 i 350 < 20 < 40 10/06/93 Windowpane 5010 i 500 < 50 < 70 1
SN-AQF-13G2 tet) 05/12/93 Windowpane 3090 1 310 < 20 < 30 05/12/93 Winter Flounder 3790 i 410 < 30 < 40 05/12/93 Little Skate . 2460 1 400 < 30 < 50 10/08/93 Sea Robin 4230 i 420 < 20 < 40 10/08/93 Windowpane 3600 1-360 < 20 < 30 10/08/93 Little Skate 2280 1 230 < 20 < 30 10/08/93 Winter Flounder 3790 1 380 < 20 < 20 Average i 2 s.d. 32501 1898 I
- All other gamma emitters not listed were <LLD: typical LLDs are given in Tables C-9 and C-10.
- (ct) Denotes Control Location.
._ - . _ _ . _ .a- . _ __ _ . . . . . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ -
.. . - . . - . - . . . . - . _ _ - . .- _. -. _- . . . ~ . - . . = _ - . . .. . .. .~ .
TABIE C-3 CONCENTRATIONS OF GAMMA EMilTERS* IN INVERTEBRATE SAMPLES Results in Units of pC1/kg (wet) i 2 sigma '
t IDCATION COU2CTION DESCRIPTION Be-7 K-40 Cs-137 Th-228 CODE DATE SN-AQl-3Cl 05/10/93 Lobster < 200 2930 i 420 < 30 < 50 05/10/93 Lobster < 200 2760 1 390 < 30 < 60 05/12/93 Whelk < 300 2550 1 410 < 20 < 50 10/04/93 Whelk < 300 1640 i 320 < 30 < 40 10/04/93 Squid < 200 2710 i 270 < 20 < 30 10/04/93 Lobster < 100 3240 i 320 < 20 < 20 3
10/04/93 Squid < 200 2590 1 260 < 20 < 30 SN-AQl-14C l 05/11/93 lobster < 200 2760 1 320 < 20 < 40 05/11/93 Io bster < 300 3370 1 430 < 30 < 50 05/12/93 Whelk < 200 2420 i 370 < 20 < 30 10/06/93 Squid < 200 2610 1 260 < 20 < 40 10/06/93 Whelk < 100 2490 i 250 < 10 < 30 10/06/93 Squid < 200 2690 1 270 < 20 < 20 a 10/06/93 Lobster < 100 3510 1 350 < 20 < 20 4
SN-AQI-13G2 (ct! 05/12/93 Whelk < 400 3000 1 570 < 50 < 90 05/12/93 Lobster < 200 3050 1 380 < 20 < 30 10/08/93 Whelk < 100 2610 i 260 < 10 < 20 10/08/93 Lobster < 100 3240 1 320 < 10 < 30 10/08/93 Squid < 100 3130 i 310 < 10 < 20 Average 2805i848 i 2 s.d.
i 4
I All other gamma emitters not listed were <LLD: typical 11Ds are given in Tables C-9 and C-10.
(cl) Denotes Control location.
t
TABLE C-4 CONCENIHA110NS OF CAMMA EMrrIERS* IN SEDIMENT SAMPLES ;
Results in Units of pC1/kg (dry) i 2 sigma IDCAT10N SAMPLE COMECTION K-40 Ra-226 Cs-137 Th-228 CODE LOCA110N DATE SN-AQS-2A4 Beach 06/02/93 2670 1 270 < 300 < 10 113 i 18 SN-AQS-2A4 Beach 10/20/93 2490 i 250 5001246 < 10 77.0 i 17.3
! Average 2580 1 255 500 1246 95.0 1 50.9 i 2 s.d.
l 4
All other gamma emitters not listed were <LLD- typical LLDs are given in Tables C-9 and C-10.
- (cl) Denotes Control location.
2
_. .~ .- - - . . - . . ._. . . . . - . . - . . - _
l TABIE C-5
- CONCENIRATIONS OF GROSS BETA EMITIERS IN WEEKLY AIRBORNE PARTICUlATES l Results in Units of 10-3 pC1/m3 i 2 sigma i
IDCATION CODES COILECTION IMTES SN-APT-2A2 SM-APT-381 SM-APT-6S2 SM-APT-7B1 SM-APT-I IG1 AVERAGE (ct) 12 s.d.
JANUARY 93 12/29/92-01/05/93 (a) 10 1 3 131 3 < 100 (c) 13 i 3 12 i 3 01/05/93-01/12/93 241 4 (b) 26 i 3 25i 3 13i 7 221 3 22 i 11 01/12/93-01/19/93 17 i 3 14 1 3 19 i 3 16 i 3 17 i 3 17 i 4 01/19/93-01/26/93 17 1 3 13 1 3 151 3 151 3 1213 14 1 4 01/26/93-02/02/93 20 i 3 19 i 3 211 3 23 i 3 16 3 201 5 FEBRUARY 02/02/93-02/09/93 221 3 23 i 3 18 i 3 19 i 3 21 i 3 21i 4 02/09/93-02/16/93 14 i 3 14 i 3 121 3 13 i 3 11 i 3 13 1 3 02/16/93-02/23/93 221 3 18 i 3 241 3 18 i 3 19 i 3 20i 5
$; 02/23/93-03/02/93 19 i 3 19 i 3 221 3 20 i 3 18 i 3 20i 3 MAECR 03/02/93-03/09/93 28 i 3 23 1 3 261 3 241 3 23.i 3 251 4 03/09/93-03/16/93 13 i 3 15 i 3 15 i 3 12 i 3 13 i 3 14 i 3 03/16/93-03/23/93 20 i 3 18 i 3 2213 22 i 4 19 i 3 201 4 03/23/93-03/30/93 5.4 1 2.4 5.7 i 2.3 5.7 1 2.4 5.8 i 2.4 6.51 2.4 5.8 1 0.8 APRIL 03/30/93-04/06/93 7.0 1 2.8 9.9 1 3.0 191 3 9.2 1 2.9 8.4 1 2.9 11 i 10 04/06/93-04/13/93 6.6 i 2.5 7.7 1 2.5 7.6 2.5 7.31 2.4 7.5 i 2.4 7.3 i 0.9 04/13/93-04/20/93 13 1 3 101 3 121 3 9.6 i 2.6 111 3 111 3 04/20/93-04/27/93 13 1 4 131 3 12 i 3 15 i 3 14 i 3 13 i 2 04/27/93-05/04/93 13 i 3 12 3 16 i 3 131 3 121 3 131 3 (a) Sample not collected.
(b) Cdlertion dates are 01/07/93 to 01/12/93.
(c) Lost sample.
(ci) Denotes Control location.
L TABLE C-5 (ccat.)
CONCENTRATIONS OF GROSS BETA EMTITERS IN WEEKLY AIRBORNE PARI 1CUIEIT,S Results in Units of 10-3 pCl/m3 i 2 sigma IDCATION CODES COILECTION DATES SN-APT-2A2 SM-APT-381 SN-APT-682 SM-APT-7B1 SM-APT-1101 AVERAGE l
(cI) i 2 s.d.
M&I 05/04/93-05/11/93 12 1 3 10 i 3 16 i 3 151-3 11 i 3 13 i 5 05/11/93-05/18/93 14 1 3 131 3 12 i 3 13 i 3 16 i 3 14 i 3 05/18/93-05/25/93 13 i 3 13 i 3 231 4 14 i 3 14 i 3 15 i 9 05/25/93-05/28/93 15 6 19 i 6 121 6 (a) 8.9 i 5.1 14 i 9 05/28/93-06/02/93 19 i 5 10 1 4 201 5 (b) 16 i 4 16 i 9 JUNE 06/02/93-06/08/93 .11 i 3 10 1 3 9+t 3.2 9.9 i 3.1 9.1 i 3.0 10 i 1 06/08/93-06/15/93 13 1 3 10 1. 3 9.6 1 2.8 (c) 12 i 3 11 i 3 06/15/93-06/22/93 16 i 3 12 i 3 16 i 3 151 3 171 3 15 i 4 l
$ 06/22/93-06/29/93 15 i 3 15 i 3 181 3 15 i 3 131 3 151 4 !
JULT i 06/29/93-07/06/93 11 i 3 12 i 3 111 3 121 3 15 i 3 12 3 07/06/93-07/13/93 24 1 3 201 3 23 i 3 221 3 22 i 3 221 3 07/13/93-07/20/93 15 i 3 14 i 3 14 1 3 12 i 3 9.7 i 2.6 13 i 4 07/20/93-07/27/93 7.1 1 2.8 8.0 i 2.8 8.6 1 2.9 9.4 1 2.9 8.6 i 2.7 8i 2 .
07/27/93-08/03/93 151 3 15 i 3 16 i 3 15 i 3 18 i 3 16 i 3 i AUGUST 08/03/93-08/10/93 19 i 3 23 i 3 22 i 3 19 i 3 20i 3 21 i 4 08/10/93-08/17/93 18 i 3 16 i 3 19 i 3 19 i 3 20 i 3 18 i 3 08/17/93-08/24/93 14 i 3 16 1 3 211 4 151 3 15 i 3 16 i 6 08/24/93-08/31/93 26i 4 231 3 26i 4 '
28 i 4 24 i 4 27 i 4 (al lost sample; not collected.
(b) Sample not collected; replaced valve.
(c) Sample not collected.
(cl) Denotes Control location.
t
TABLE C-6(cmt.)
CONCE!TIRATIONS OF GROSS BETA EMITIERS IN WEEKLY AIRBORNE PAR 11CUIATES Results in Units of 10-3 pCl/m3 12 sigma LOCATION CODES COILECTION DATES SM-APT-2A2 SM-APT-381 SM-APT-6S2 SM-APT-7B1 SN-APT-1101 AVERAGE (cI) i 2 s.d.
SEliEMBER 08/31/93-09/03/93 21 i 6 16 i 6 22 i 6 18 1 6 22 i 6 201 5 09/03/93-09/08/93 17 i 4 15 i 4 15 i 4 14 i 4 13 i 4 151 3 r 09/08/93-09/14/93 18 i 4 12 1 3 16 i 4 15i 4 15 3 15 i 4 121 3 131 3 9.61 2.6 11 i 3 09/14/93-09/21/93 111 3 11 i 3 201 2 09/21/93-09/28/93 19 i 3 19 i 3 211 3 201 3 211 3 OCTOBER 09/28/93-10/05/93 12 i 3 15 1 3 14 1 3 12 i 3 15 i 3 14 i 3 10/05/93-10/12/93 13
- 3 15 i 3 15 i 3 151 3 15 i 3 15 i 2 10/12/93-10/15/93 12 1 5 11 i 5 11 i 6 10 i 5 101 5 111 2 10/15/93-10/20/93 20 i 4 20 1 4 22i 4 21 i 4 211 4 211 2
$ 10/20/93-10/26/93 18 i 4 16 15 i 3 3
151 3 17 1 4 131 3 20 i 4 19 i 3 17 i 4 16 i 5 10/26/93-11/02/93 17 i 3 14 i 3 NOVEMBER 11/02/93-11/09/93 211 3 22 1 3 2113 18 1 3 211 3 211 3 !
11/09/93-11/16/93 28 i 4 271 4 28 i 4 29 i 4 27 3 28 i 2 11/16/93-11/23/93 18 i 3 211 3 23 i 3 211 3 20 3 21 t 4 11/23/93-11/30/93 24 i 4 19 i 3 23 i 4 211 3 231 3 221 4 DECEMBER 11/30/93-12/07/93 18 i 3 211 3 21 i 3 22 3 17 i 3 2014 12/07/93-12/14/93 231 3 251 3 25 i 3 221 3 201 3 23 i 4 12/14/93-12/17/93 11 i 6 12 1 6 12 i 6 <8 <8 12 i 1 12/17/93-12/22/93 18 i 4 201 4 19 i 4 19 i 4 201 4 191 2 12/22/93-12/28/93 16 i 3 201 4 19 i 3 16 i 3 19 i 3 18 i 4 Average 17i 10 16 1 10 17 1 11 16i 10 16i 10 16 i 5 1 2 s.d.
(ct) Denotes Control Imcation.
TABLE C-6 CONCENIRA~I1ONS OF GAMMA EMITIERS* IN QUARTERLY COMPOSITE OF AIRBORNE PARI 1CULKIE SAMPLE.S Results in Units of 10-3 pC1/m3 12 sigma IACATION NUCUDES FIRST QUARTER SECOND QUAITIER TillRD QUARTER FOURTII QUARTER AVERAGE cooEs 01/07/ases/30/es 03/30/s34s/29/93 os/29/oses/2s/es oo/2s/es-12/2s/es i s s.d-
, SN-AIT-2A2 Be-7 54.3 i 5.8 67.516.7 93.319.3 160 i 16 93.8 i 94.I K-40 <6 < 20 ,
< 10 7.09 i 4.16 7.09 i 4.16 Cs-134 < 0.5 < 0.6 < 0.6 < 0.5 -
Cs-137 < 0.4 < 0.6 < 0.7 < 0.5 -
SN-APT-381 Be-7 58.615.9 79.5 i 8.0 79.4 i 7.9 126 i 13 85.9 i 57.0 K-40 <7 < 10 < 10 6.88 i 3.49 6.88 i 3.49 Cs-134 < 0.4 < 0.5 < 0.5 < 0.5 -
Cs-137 < 0.3 < 0.7 < 0.5 < 0.6 -
SN-AIT-882 Be-7 83.4 i 8.3 84.3 i 8.4 83.1 i 8.3 133 1 13 96.0149.4
, K-40 < 10 <9 10.615.0 <6 10.615.0
- Cs-134 < 0.5 < 0.4 < 0.6 < 0.4 -
Cs-137 < 0.7 < 0.6 < 0.6 < 0.3 -
SN-AIT-7B1 Be-7 65.216.5 87.1 i 8.7 101i 10 116 i 12 92.3 43.2 K-40 < 20 < 20 <9 4.29 i 2.51 4.29 i 2.51 Cs-134 < 0.6 < 0.8 < 0.4 < 0.3 -
Cs-137 < 0.6 < 0.8 < 0.3 < 0.3 -
SN-AIT-11G1 Be-7 56.5 5.7 90.3 i 9.0 114 i l1 134 i 13 98.7 i 66.7 (c!) K-40 < 20 < 20 < 10 <8 -
Cs-134 < 0.6 < 0.6 < 0.5 < 0.4 -
Cs-137 < 0.6 < 0.6 < 0.6 < 0.4 -
All other gamma emitters not listed were <LLD: typical LLDs are found in Tables C-9 and C-10.
(ct) Denotes control location.
l
- ._ .=_ _- .-.. _- . . . ._ - -
TABLE C-7 CONCENTRATIONS OF GAMMA EMrlTERS* AND l-131 IN FOOD PRODUCT SAMPLES Results in Units of pC1/kg (wet) i 2 sigma IDCATION CODE SAMPIE TYPE COILECTION DATE Be-7 K-40 I-131 Cs-137 SN-FPF-6B21 Strawberries 06/16/93 < 90 1580 i 160 < 10 < 10 SN-FPV-6B21 Carrots 08/18/93 < 50 3390 1 340 < 10 <7 SN-FPL-6B21 Cabbage 09/15/93 < 90 1790i 180 < 20 < 10 SN-FPF-8B I Strawberries 06/16/93 < 80 1510i 150 < 10 < 10 SN-FPL-8B I Lettuce 07/21/93 < 50 1300 i 130 <8 <6 SN-FPL-881 Cabbage 07/21/93 < 80 2160 i 220 < 10 <8 SN-FPV-8B I Potatoes 07/21/93 < 50 3670 1 370 <8 <6 SN FPV-8BI Carrots 07/21/93 < 40 3210 1 320 <8 <5 SN-FPV-8B I Carrots 08/18/93 < 40 2540 1 250 < 10 <5 SN-FPV-8B 1 Potatoes 08/18/93 < 50 3410 1 340 <8 <6 SN-FPL-8B I Cabbage 08/18/93 < 70 2010 i 200 < 20 <9 SN-FPle8B I Lettuce 08/18/93 < 70 1430 i 140 < 20 <8 SN-FPV-8B 1 Carrots 09/15/93 < 50 2790 1 280 < 10 <6 u, SN-FPV-8B I Potatoes 09/15/93 < 50 4120 i-410 < 10 <6 O SN-FPL-8B I Cabbage 09/15/93 < 80 2180 1 220 < 20 < 10 SN-FPL-8B I Lettuce 09/15/93 < 50 1180 i 120 < 10 <6 SN-FPV-8 B 1 Carrots 10/13/93 < 60 32201 320 < 10 <7 SN-FPV-8B1 Potatoes 10/13/93 < 40 3690 1 370 <9 <5 SN-FPL-8B1 Lettuce 10/13/93 137 i48 1590i 160 < 10 <7 SN-FPL-8BI Cabbage 10/13/93 < 80 2660 1 270 < 20 <9 SN-FPL-8B I Lettuce 10/13/93 75.6125.3 1450 i 150 <7 <4 SN-FPV-8BI Potatoes 11/16/93 < 50 3790 i 380 <8 <6 SN-FPI 8BI Lettuce 11/16/93 158i45 1260 i 130 < 10 <8 SN-FPL-8B 1 Cabbage 11/16/9'l < 70 3590 i 360 < 10 <8 SN-FPF-12HI tet) Strawberries 06/16/93 < 70 2070 1 210 < 10 <9 SN-FPL-12H2 (ct) Lettuce 07/21/93 < 60 3710 i 370 < 10 <8 SN-FPL- 12H2 Lettuce 08/18/93 < 100 2920 1 290 < 20 < 10 SN-FPV- 12H2 Corn 09/15/93 < 30 2420 1 240 <8 <4 SN-FPL- 12H2 Lettuce 09/15/93 202i 67 4890 1 490 < 20 < 10 SN-FPL- 12H2 Lettuce 10/13/93 < 70 3070 1 310 < 20 <7 Average i 1431105 2620 1 2001 2 s.d.
All other gamma emitters not listed were <LLD; typical LLDs are given in Tables C-9 and C-10.
(ct) Denotes Control location.
_ . . .m. ._.m - . - . _ _ . _ _ _ _ _ . _ . . _ . . . . . .
TABLE C-8 DIRECT RADIATION MEASUREMEffrS - QUARTERLY TLD RESUL'IS mR/ standard month
- IDCATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER ANNUAL AVERAGE CODES 01/14/93-04/02/93 04/02/93 07/08/93 07/08/93-10/07/93 10/07/93-01/06/94 (a)
SN-IDM- 1SI 3.0 1 0.2 2.9 i 0.1 3.I i 0.2 4.2 1 0.6 3.3 i 1.2 SN-IDM-3S1 3.3 1 0.2 3.1 1 0.2 3.0 1 0.1 3.9 i 1.0 3.3 1 0.8 SN-IDM-4SI 3.5 i 0.2 3.3 1 0.I 3.4 1 0.6 3.8 i 0.8 3.5 i 0.4 SN-IDM-SS2 3.4 1 0.1 3.3 i O.2 3.5 i 0.1 4.1 1 0.7 3.6 1 0.7 SN-IDM-GS2 3.4 1 0.1 3.3 1 0.2 3.4 1 0.1 5.2 i 1.4 3.8 i 1.8 SN-IDM-9SI 3.9 i 0.7 3.5 1 0.3 3.5 i 0.2 6.8 1 0.9 4.4 1 3.2 SN-IDM- 13S3 3.6 1 0.4 3.3 1 0.6 3.6 i 0.2 3.6 i 0.1 3.5 i 0.3 SN-IDM- 14S2 2.9 i 0.1 2.9 0.3 2.8 i 1.0 3.7 i 1.4 3.1 1 0.8 SN-IDM- 15S 1 3.1 1 0.I 2.8 i 0.2 3.0 0.2 3.5 1 0.9 3.1 i 0.6 SN-IDM-16S2 3.5 i 0.3 3.1 i 0.2 3.4 i 0.3 4.8 i 1.9 3.7 i 1.5 t ui SN-IDM-2A2 3.3 1 0.5 2.7 1 0.2 2.9 1 0.1 3.1 1 0.6 3.0 1 0.5 i SN-IDM-7A2 3.4 i O.4 3.1 i O.4 3.5 i 0.1 3.7 i 1.3 3.4 1 0.5 SN-IDM-8A3 3.6 i 0.5 3.0 1 0.6 3.4 0.1 3.8 1 0.4 3.5 i 0.7 SN-IDM-10A1 3.5 i 0.1 3.4 i 0.2 3.6 i 0.1 4.1 i 1.3 3.7 i 0.6 SN-1DM-1 I A1 3.3 1 0.1 3.2 i 0.1 3.5 1 0.1 4.3 i 1.4 3.6 i 1.0 SN-IDM- 12A1 3.9 i 0.1 3.5 1 0.7 4.2 i 0.2 3.8 i 0.7 3.9 i 0.6 SN-IDM- 1 IG 1 (ci) 3.4 i 0.1 3.2 1 0.3 3.5 i 0.1 2.4 1 0.3 3.1 i 1.0 .
SN-IDM- 12G 1 (cl) 3.3 1 0.4 3.0 1 0.4 3.1 1 0.3 5.3 i 2.5 3.7 1 2.2 Avereg (b) 3.4 1 0.5 3.110.5 3.4 1 0.7 4.111.9 3.5 i 1.2 (c)
'the standud month = 30.4 days. ,
(a) The i limita given in this column define a 95% confidence interval for the mean of the four quarterly results at that location.
(b) The i limits given in this row define a 95% confldence interval for the mean of all locations for that quarter.
(c) The i limits given here define a 95% confidence interval for a measurement at any location during any quarter in 1993.
(ct) Denotes Control Location
TABLE C-3 "IYPICAL LLDs ACHIEVED FOR GAMMA SPECTROMETRY MttE AND FlSII, GAME AND AQllATIC Soll, AND AIR WATER AQUATIC INVERTEllRATES PIANTS AQUATIC SEDIMENT PARTICULATFS NUCLIDES rpci/!) (;ct/kg =ett frCt/kg dryl (IC /kst dry) (10'3r c:/m3 Be-7 60 80 80 200 20 Na-22 7 8 10 30 2 K-40 100 300 300 900 20 Cr-51 50 100 70 200 10 Mn-54 5 7 9 30 2 Co-58 5 8 8 20 2 Fe-59 15 20 15 50 2 Co-60 5 8 9 20 2 Zn-65 10 20 20 60 2 Zr-95 30 10 10 40 2 Nb-95 15 (a) (a) (a) (a)
Mo-99 10 10 10 20 5 Ru-103 7 10 10 30 2 Ru- 106 50 60 80 200 10 m Ag- 1 IOm 7 10 10 40 2 Sb-125 15 20 25 80 4 Te- 129m 6 10 10 30 2 1-131 10 10 10 30 10 Te-132 10 6 6 25 2 1-133 10 10 10 40 15 Cs- 134 6 7 10 30 2 Cs- 136 10 10 10 30 2 Cs- 137 6 7 10 30 2 Ba-140 60 10 10 5 5 La- 140 15 (a) (a) (a) (a)
Ce- 141 10 10 15 30 3 Ce-144 30 40 60 150 7 Ra-226 90 100 150 400 20 Th-228 10 10 25 60 3 (a) No ODCM Requirements
TABM C-ID LLDs AND REPORTING ACTION LEVEIS - 1993 REQUIRED BY ODCM AND COITTRACT SAMPLE TYPE -.. - te Units Grams Beta H-3 Mn-54 Co 58 Fe40 Co40 Zm48 Sreell)
ATMOSPHERIC Air Sample 11D* ODCM pct /m 3 0.01 - - - - - - -
11D Contract 0.01 - - - - - -
0.005 RAL" ODCM - - - - - - - -
RAL Contract 1 - - - - - - 0.1 AQUATIC Fish and 11D ODCM pct /kg - -
130 - - 130 260 -
Invertebrate IID Contract (wet) - -
130 130 260 130 200 5 (21 Aquatic Plants (2) RAL ODCM - -
30.000 - -
10.000 20.000 -
RAL Contract - -
30.000 30.000 10.000 10.000 20.000 20 (2)
. WATER Surface IlD ODCM pC1/1 4 3.000 15 - -
15 30 -
IlD Contract -
3.000 15 15 30 15 30 10 RAL ODCM -
30.000 1.000 - -
300 300 -
RAL Contract -
30.000 1.000 1.000 400 300 300 20 (n TERRESTRIAL to Food LID ODCM pC1/kg - - - - - - - -
Ihxiucts 11D Contract (wet) - - - - - - - -
RAL Contract - - - - - - - -
Game (2)
Soils 11D ODCM pCl/kg - - - - - - - -
IlD Contract (dry) - - - - - - -
RAL Contract - - - - - - - 80 ,
I SEDIMENT Sediments llD ODCM pCl/kg - - - - - - - -
11D Contract (dry) - - - - - - -
RAL Contract - - - - - - -
80 DIRECT RADIATION TLD llD ODCM - - - - - - - -
IID Contract l_5 mR/std. nxmth - - - . - - - -
RAL Contract - - - - - - - -
Note: See footnotes at end <f table.
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TABLE C-10(Cont.)
LLDs AND REPORTING AC110N LEVELS - 1993
! REQUIRED BY ODCM AND CONTRACT SAMPLE TYPE Unite Sr-90l3) Zr-95 Mb-96 I-131(31 Co-134 Co-137 Ba-140 14-140 WATER i
^
Surface llD ODCM pC1/1 - - - -
15 18 - -
11D Contract 2 30 15 15 I53 15 18 - 15 (6)
RAL Contract 20 400(4) - 20 30 50 - 200 (7)
ATMOSPHERIC
) Air Sample LLD ODCM pC1/m 3 - - - - 0.05 0.06 - -
. LLD Contract 0.001 - - 0.07 0.05 0.06 - -
RAL Contract 0.1 - - 0.9 10 20 - -
AQUATIC Fish and LID ODCM pC1/kg - - - -
130 150 - -
Invertebrate LLD Contract (wet) 5 GI - - -
130 150 - -
$ Aquatic Plants (2) RAL ODCM - - - -
1.000 2.000 - -
1.000 2.000 - -
1ERRESTRIAL i Food 11D ODCM pct /kg - - - -
60 80 - -
htx!ucts LID . Contract (wet) - - - 60 '.A, 80 - -
1.000 2.000 - -
RAL Contract - - - 100 1.0CJ 2.000 - -
Solls 11D ODCM pct /kg - - - - - - - -
LLD Contract (dry) 5 - - - 150 180 - -
RAL Contract 80 - - -
1.000 2.000 - -
SEDIMENTS Sediments LID ODCM pct /kg - - - - 150 180 - -
LID Contract (dry) 5 - - -
150 180 - -
4 RAL Contract 80 - - - 1.000 2.000 - - i 4
.* lxwer Lamit of Detection Reporting Action IEvel
, (1) Sr-89 data remained in contract fa special request cases (e.g. Termination Survey) only. !
(2) There are no ODCM requirements fw game or aquatic plants. Fish contract LLDs and RAlm for gamma specrometry apply to game. Except for Sr-89/90. fish contract ilDs and RALs forgamma w u umetry at same numerical value txt in different units (i.e.. pCl/kg dry). apply to aquatic plants. Sr-fB/9011Ds and RAIA for aquatic plants are 30
^
pct /kg (dry) and 45 pct /kg (dry) . respectively.
1 (3) St-90 and 1-131 by radtorhemistry .rmained in contract for special request cases (e.g. Tenntnation Survey) ordy.
- 14) Reporting level for total Zr-95 plus Nb-95. ;
(5) For non-drtnking water pathway. !
(6) BA/lA-140 combined 11D.
(7) Reporting level for total Ba-140 plus la-140.
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l APPENDIX D ANALYTICAL PROCEDURES SYNOPSIS 55
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ANALYTICAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed during 1993 en samples collected for the Shoreham Nuclear Power Station Radiolog; cal Environmental Monitoring Program. All analyses- have been mutually agreed upon by Long Island Power Authority and Teledyne Isotopes and include those recommended by the USNRC Regulatory Guide 4.8. BTP.
Rev.1, November 1979.
ANALYSIS TITLE PAGE i
l Gross Beta Analysis of Air Particulate Samples . . . . . . . . . . . . . . . . . . . . . . . . . 57 i
Gross Beta Analysis of Water Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 Analysis of Samples for Tritium (Liquid Scintillation) . . . . . . . . . . . . . . . . . . . 60 Gamma Spectrometry of Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 Milk an d Wate r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 I l
Dried Solids other than Soils and Sediment . . . . . . . . . . . . . . . . . . . . . 61 l F1sh........................................................61 Soil s an d Se dim e n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 Airborn e Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 Environm en tal Dosim etry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 l
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GROSS BETA ANALYSIS OF SAMPLES Airborne Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by LIPA, is counted as the blank.
Calculations of the results, the two sigma error and the lower limit of detection (LLD):
RESULT (pCi/m3) = ((S/T) - (B/t))/(2.22 V E)
TWO SIGMA ERROR (pCi/m3) = 2((S/T2) + (B/t 2))1/2/(z.22 V E)
LLD (pCi/m3) = 4.66 (B/t/T)l/2/(2.22 V E) where:
S = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) 57
DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES 1
1.0 INTRODUCTION
The procedures described in this section are used to measure the overall radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.
One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size.
After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchet which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps.
Residue mass is determined by weighing the planchet before hnd after mounting the sample. The planchet is counted for beta activity on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting efficiency caused by the residue mass.
58
2.0 DETECTION CAPABILITY Detection capability depends upon the sample volume actually represented on the planchet, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time.
The minimum detectable level (MDL) for water samples is nominally 1.6 picocuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/l at l the 2.83 sigma level), assuming that 1 liter of sample is used and that h l
gram of sample residue is mounted on the planchet. These figures are l based upon a counting time of 50 minutes and upon representative values of counting efTiciency and background of 0.2 and 1.2 cpm, respectively.
The MDL becomes significantly_ lower as the mount weight decreases because of reduced self-absorption. At a zero. mount weight, l . the 4.66 sigma MDL for gross beta is 0.9 picocuries per liter. These values reflect a beta counting efficiency of 0.38.
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l ANALYSIS OF SAMPLES FOR TRITIUM (Liquid Scintillation)
Water Ten milliliters of water are mixed with 10 ml of a liquid scintillation
" cocktail" and then the mixture is counted in an automatic 11guld scintillator.
Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/l:
RESULT = (N-B)/(2.22 V E)
TWO SIGMA ERROR = 2((N + B)/At)1/2/ (2.22 V E)
LLD = 4.66 (B/At)1/2/(2.22 V E )
where: N = the gross cpm of the sample B = the background of the detector in cpm 2.22 = conversion factor changing dpm to pCi V = volume of the sample in ml E = efficiency of the detector At = counting time for the sample 60
GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is fille' ,ith a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Dried Solids Other Than Soils and Sedlinents A large quantity of the sample is dried at a low temperature, less than 100 C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
I As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(L1) detector ,
coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Soils and Sediments Soils at'l sediments are dried at a low temperature, less than 100 C.
The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(L1) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Airborne Particulates The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
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A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then >
performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efl1ciency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass:
RESULT = (S-B)/2.22 t E V F DF)
EVO SIGMA ERROR = 2(S+B)1/2/ (2.22 t E V F DF)
LLD = 4.66(B)1/2/(2.22 t E V F DF) where: S = Area, in counts, of sample peak and background (region of spectrum of interest)
B = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on either side of the peak t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams)
F = fractional gamma abundance (specific for each emitted gamma)
DF = decay factor from the mid-collection date to the counting date l
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ENVIRONMENTAL DOSIMETRY Teledyne Isotopes uses a CaSO 4 :Dy thermoluminescent dosimeter j (TLD) which the company manufactures. This material has a high light i output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.
Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner.
Calculations of results and the two sigma error in net milliroentgen (mR):
RESULT D = (Di +D2 +D3 +D4 )/4 TWO SIGMA ERROR =
2((Di -D)2+(92-D)2+(D3-D)2+(9 4_932)/3)1/2 WHERE: D1 = the net mR of area 1 of the TLD, and similarly for D2, D 3, and D4
=
D1 11 K/R1-A 11
= the instrument reading of the field dose in area 1 K = the known exposure by the Cs-137 source R1 = the instrument reading due to the Cs-137 dose on area 1 A = average dose in mR, calculated in similar manner as above, of the transit control TLDs D = the average net mR of all 4 areas of the TLD.
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- .- a
,Asw-4 a4. J 4u,$ .,, E s_.en_aL4.. _ _ e .o .a -4 erwm. - _a~Jw.__ . - _#+.s.s_ma_ - % ~ ,., ,,
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APPENDIX E
SUMMARY
OF EPA INTERLABORATORY COMPARISONS I
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EPA INTERLABORATORY COMPARISON PROGRAM Teledyne Isotopes participates in the US EPA Interlaboratoly Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of avail?'lity. In this section trending graphs (since 1981) and the 1993 data summary tables are presented for
~
isotopes in the various sample media applicable to the Shoreham's l Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence. )
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- EPA INTERLABORATORY COMPARISON PROGRAM 1993 l Environmental l I
Collection Teledyme ,
7 Date Media Nuclide EPA Result (a) Isotopes Result (b) Deviation (c) 01/15/93 Water Sr-89 15.0 i 5.0 12.67 1 1.15 -0.81 Sr-90 10.0 1 5.0 8.33 i 1.15 -0.58 01/29/93 Water Gr-Alpha 34.0 1 9.0 17.33 1 1.15 -3.21 (d)
Gr-Beta 44.0 i 5.0 52.00 1.00 2.77 (e) 02/05/93 Water 1-131 100.0 i 10.0 106.67 i 5.77 1.15 03/05/93 Water Ra-226 9.8 1.5 7.67 0.12 -2.46 (0 Ra-228 18.5 1 4.6 19.33 2.31 0.31 04/20/93 Water Gr-Alpha 95.0 24.0 94.33 1.15 -0.05 Ra-226 24.9 1 3.7 19.00 i 1.00 -2.76 (0 Ra-228 19.0 1 4.8 18.33 i 0.58 -0.24 Gr-Beta 177.0 27.0 150.0i 0.00 -1.73 Sr-89 41.0 5.0 35.33 1 1.53 -1.96 Sr-90 29.0 5.0 27.33 0.58 -0.58 Co-60 39.0 5.0 40.67 3.51 0.58 Cs- 134 27.0 5.0 23.67 1 1.53 -1.15 l Cs-137 32.0 5.0 34.33 1 2.08 0.81 l 06/04/93 Water H-3 9844.0 984.0 9366.67 152.75 -0.84 I
GS/11/93 Water Co-60 15.0 5.0 16.33 1,53 0.46 l Zn-65 103.0 10.0 121.33 20.09 3. I8 (g) ;
Ru-106 119.0 12.0 106.33 15.89 -1.83 Cs-134 5.0 5.0 5.67 0.58 0.23 Cs- 137 5.0 5.0 6.67 1 0.58 0.58 Ba-133 99.0 10.0 104.33 1 9.29 0.92 07/16/93 Water Sr-89 34.0 5.0 31.67 2.52 -0.81 Sr-90 25.0 i 5.0 24.00 i 0.00 -0.35 07/23/93 Water Gr-Alpha 15.0 5.0 18.67 1 2,08 1.27 Gr-Beta 43.0 1 6.9 42.67 2.52 -0.08 08/27/93 Air Filter Gr-Alpha 19.0 1 5.0 17.00 1 0.00 -0.69 Gr-Beta 47.0 1 5.0 49.00 1.73 0.69 Sr-90 19.0 5.0 17.67 0.58 -0.46 Cs-137 9.0 5.0 9.67 0.58 0.23 I
09/09/93 Water Ra-226 14.9 2.2 15.33 0.58 0.34 '
Ra-228 20.4 5.1 20.67 1.15 0.09 66
i EPA INTERLABORATORY COMPARISON PROGRAM 1993 l Environmental Collecuon Teledyne Date Media Nuclide EPA Result (a) Isotopes Result [b) 09/24/93 Milk Sr-89 30.0 1 5.0 35.67 3.51 1.96 Sr-90 25.0 i 5.0 24.00 i 1.73 -0.35 1-131 120.0 12.0 126.67 i 5.77 0.96 Cs- 137 49.0 1 5.0 50.67 i 1.15 0.58 K 1679.0 1 84.0 1620.00 1 17.32 -1.22 10/08/93 Water I-131 117.0 1 12.0 103.33 i 5.77 -1.97 19/19/93 Water Gr-Beta 58.0 10.0 51.33 3.21 -1.15 Sr-89 15.0 5.0 15.00 1.00 0.00 Sr-90 10.0 1 5.0 10.00 0.00 0.00 Co-60 10.0 5.0 12.00 1.00 0.69 Cs- 134 12.0 5.0 9.00 1.00 -1.04 Cs-137 10.0 1 5.0 12.67 2.52 0.92 Gr-Alpha 40.0 10.0 39.67 0.58 -0.06 Ra-226 9.9 1 1.5 10.10 0.79 0.23 Ra-228 12.5 1 3.1 14.67 i 1.15 1.21 10/29/93 Water Gr-Alpha 20.0 5.0 20.33 1 2.08 0.12 Gr-Beta 15.0 5.0 15.67 i 2.08 0.23 >
11/5/93 Water H-3 7398.0 740.0 6900.00 i 100.00 -1.17 11/12/93 Water Co-60 30.0 5.0 28.67 2.89 -0.46 Zn-65 150.0 i 15.0 152.00 9.17 0.23 Ru-106 201.0 20.0 177.33 5.51 -2.05 (h)
Cs-134 59.0 5.0 53.33 1 4.93 -1.96 Cs-137 40.0i 5.0 41.33 3.06 0.46 Ba-133 79.0 8.0 69.33 1 3.06 -2.09 (t)
Footnotes:
(a) EPA Results-Expected laboratory precision (1 sigma). Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters.
(b) Teledyne Results - Average i one sigma. Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate fllters. ,
(c) Normalized deviation from the known.
(d) The EPA switched from Am-241 to Th-230 alpha spike. We calibrated with Th-230.
using sodium nitrate to generate a self-absorption curve. The EPA water, however has minerals which have greater self-absorption than the sodium nitrate matrix. The ,
EPA has agreed to send us a gallon of their water which we can use to prepare a self- l absorption curve with Th-230.
l 67
i EPA INTERLABORATORY COMPARISON PROGRAM 1993 Environmental l
~
Collection Teledyne Date Media Nuclide EPA Result (a) Isotopes Result [b) 1 I
(e) By oversight, we did not use the special self-absorption curve which we had previously derived using EPA water and Cs-137 standard. We will use the EPA curve in the future. We may also re-derive this curve using a water sample which the EPA has agreed to send us.
(f) The counting data and backgrounds were verified Possibly some efficiencies used were erroneously _high, causing low values. A less . aly cause is an error in dilution. ;
New Ra-226 standards will be prepared. Closer monitoring of out of control l efficiencies will be done and extra care in preparation of the sample will be maintained.
(g) The calculations were checked and found to be correct. The results of six gamma emitting isotopes were reported to the EPA. The results of four were within 1 normalized deviation; a fifth, within 2 normalized deviations. Only the Zn-65 average was outside the control limits. There is no obvious reason why one isotope should be outside the control limits, while five other isotopes were within control limits.
(h) Although the T1 average (177.3) was 2.05 deviations low compared to the EPA value, i the agreement was good with the average (175.2) of 173 participants. The data was reviewed for accuracy including half life and branching intensity used. No problems were found. No corrective action anticipated because of the good agreement with the average of all participants.
(1) No problems were found with the calculations. Three other isotopes were within 1 deviation, so it's unlikely that a general problem exists. if compared to the average of all participants, the Tl results would undoubtedly be within 2 deviations. The Ba-133 results were within +1 deviation for the past two cross checks, thus there is not a trend. No corrective action antJcipated at this time.
April 26.1994 l
68
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O APPENDIX F REMP SAMPLING AND ANALYTICAL EXCEPTIONS W
93
TABLE F-1 REMP Exceptions for Scheduled Fish Sampling and Analysis During 1993 Date of Reason (s) for Location Description Sampling Loss / Exception Various Fish As noted Samples collected did not below. meet specified amount; however all required analyses were performed.
3C1 Sea Robin 05/10/93 Collected: 40g Required: 1,2Kg 14C1 Sea Robin 05/11/93 Collected: 60g Required: 1.2Kg 13G2 Sea Robin 05/12/93 No samples available.
3C1 Windowpane 10/04/93 Collected: 150g Required: 1.2Kg 3C1 Sea Robin 10/04/93 Collected: 30g Required: 1.2Kg 3C1 Winter Flounder 10/04/93 Collected: 470g Required: 1.2Kg 14C1 Windowpane 10/06/93 Collected: 150g Required: 1.2Kg 14C1 Sea Robin 10/06/93 Collected: 60g Required: 1.2Kg 13G2 Sea Robin 10/08/93 Collected 270g Required: 1.2Kg l
94
TABLE F-2 REMP Exceptions for Scheduled Invertebrate Sampling and Analysis During 1993 Date of Reason (s) for Location Description Sampling Loss / Exception .
Various Invertebrates As noted Samples collected did not below. meet specifled amount:
however, all required analyses were performed.
3C1 Lobster 05/17/93 Collected: 800g Required: 1.2Kg 3C1 Whelk 05/17/93 Collected: 400g Required: 1.2Kg 13G2 Whelk 05/17/93 Collected: 200g Required: 1.2Kg
-1 e
<=
f f
-i 95
TABLE F-3 REMP Exceptions for Scheduled Airborne Particulates Sampling and Analysis During 1993 Date of Reason (s) for Location Description Sampling Loss / Exception 2A2 Particulates 12/29/92- Sampler malfunction and no 01/05/93 sample collected.
7B1 Particulates 05/25/93- Lost sample. Sample 05/28/93 not collected.
7B1 Particulates 05/28/93- Sample not collected. Replaced 06/02/93 valve.
7B1 Particulates 06/08/93- Sample not collected.
06/15/93 96
l TABLE F-4 '
REMP Exceptions for Scheduled Food Product Sampling and Analysis During 1993 Date of Reason (s) for Location Description Sampling Loss / Exception 6B21 Vegetables 07/04/93 Farm stand not open.
12H2 Vegetables 07/21/93 Cabbage, potatoes and carrots not grown locally.
12H1 Vegetables 07/21/93 Cabbage, potatoes and carrots not grown locally.
12H2 Vegetables 08/18/93 Cabbage, potatoes and carrots not grown locally.
12H1 Vegetables 08/18/93 Lettuce, cabbage, potatoes and carrots not grown locally.
6B21 Vegetables 08/18/93 Lettuce, cabbage, potatoes and carrots not grown locally.
12H2 Cabbage 09/15/93 Cabbage not grown locally.
12H1 Vegetables 09/15/93 Lettuce and cabbage not grown locally.
6B21 Lettuce 09/15/93 Lettuce not grown locally.
6B21 Vegetables 10/13/93 Farm stand closed for season.
12H2 Vegetables 10/13/93 Cabbage, corn, potatoes and carrots not grown locally.
97
APPENDIX G SNPS LAND USE SURVEYS f
1 98
SNPS LAND USE CENSUS The Land Use Census program complies with Section 3/4.12.2 of SNPS ODCM. This requires a smvey of all milk animals and gardens greater than 50m2 (500 ft 2) producing broad leaf vegetation within a radial distance of 8 km (5 miles). LIPA is also required to identify the nearest milk animal, residence and garden in each of the 16 meteorological sectors.
LILCO's Environmental Engineering Department conducted the 1993 dairy animal census, from April through June, This survey was conducted by Environmental Technicians driving through each neighborhood within the 5 mile radial distance and visually checking for dairy animals. When a dairy animal was observed the technicians requested information from the owner concerning the amount of milk produced, feed, number of animals and grazing methods.
The 1993 census results indicated that there are no milk producing cows within a 5 mile radial distance from the site: however, the survey did locate the following milk producing goats:
Sector 11, 2.40 miles southwest of SNPS Shoreham-Wading River School District Middle School Randall Road Shoreham, New York 11786 REMP Monitoring Location 11C1 Inventory: 2 milking goats 2 non-milking goats Inventory Date: April 5,1993 Table G-1 lists the nearest milk animal in the sixteen meteorological sectors. Additional field survey data are filed in the Shoreham Record Retrieval System.
The Garden Census was also conducted by Environmental Engineering Technicians visually noting each garden of 50m2 (500 ft2 ) or greater. The 1993 census was performed during July, August, and September locating a I total of 190 gardens. Table G-2 lists the nearest garden in the sixteen meteorological sectors. The field survey sheets and maps are filed at l
Environmental Engineering Melville and in the Shoreham Record Retrieval System.
Environmental Engineering identifies nearest residences by utilizing both aerial photography and visual confirmation. This year's census was conducted in December,1993. Table G-3 lists the nearest residence in each meteorological sector.
99
TABLE G-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1993 Land Use Census Nearest Milk Animal ( within 8 km)
Sector Direction Location 1 N Area within sector is Lond Island Sound 2 NNE None 3 NE None 4 ENE None 5 E None 6 ESE None 7 SE None 8 SSE None 9 S None 10 SSW None 11 SW Shoreham-Wading River Middle School Randall Road, Shoreham 12 WSW None 13 W None 14 WNW None 15 NW Area within sector is long Island Sound '
16 NNW Area within sector is Long Island Sound 100
TABLE G-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1993 Land Use Census Nearest Garden (> 50m2 within 8 km)*
Sector Garden Code # Location & Direction 1 -
Area within sector is Long Island Souna 2 -
None 3 -
None 4 4B22G Czebotab, Sunset Blvd., Wading River 5853' ENE of SNPS.
5 5A11G Loggia, Little Bay Road, Wading River 4201' E of SNPS.
6 6A12G Punda, Sound Ave., Wading River 4343' ESE of SNPS.
7 7B14G Waski, Gateway Dr., Wading River 6788' SE of SNPS.
8 8A14G Pierzchanowski, Randall Road, Wading (8B 1) River, 5194' SSE of SNPS.
9 9B14G Smith, Randall Road, Wading River 6028' S of SNPS.
10 10C13G Waligura, Bradley Dr., Shoreham 14,014' SSW of SNPS.
11 11B34G Gallagher, Royal Way, Shoreham 6724' SW of SNPS.
12 12B12G Jennings, Duchess Street, Shoreham approximately 6100' SW of SNPS.
13 13B22G Connoly, Valentine Road, Shoreham 4542' W of SNPS.
14 -
None 15 -
Area within sector is Long Island Sound 16 -
Area within sector is Long Island Sound SNPS ODCM Part I, Section 3/4.12.2 101
TABLE G-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1993 Land Use Census Nearest Residence (within 8 km)*
Sector Direction Location 1 N Area within sector is Long Island Sound 2 NNE Thurber; Creek Road, Wading River, 1503' from SNPS 3 NE Creek Road, Wading River,1916' from SNPS (First house east of Field and Tennis Club).
4 ENE Hughes; Creek Road, Wading River, 3444 from SNPS (fifth house west of Riverhea'J Town Beach) 5 E Peterson; Sound Road, Wading River, 3598' from SNPS 6 ESE Bartow; Sound Road, Wading River, 2917' from SNPS 7 SE Larsen; North Country Road and Thomas i Drive, Wading River, 3304' from SNPS ;
1 8 SSE North Country Road, fifth house west of Pheasant Run, Wading River, 2588' from SNPS 9 S Fugelsang; 20 Long Bow, Wading River, 3839' from SNPS 10 SSW 16 Defense Hill Road, Wading River, l 4877' from SNPS !
f 11 SW 170 North Country Road, Wading River,
, 1632' from SNPS 12 WSW Gildea; Valentine Road, Shoreham, 5557' from SNPS 13 W Brice: 55 Valentine Road, Shoreham, 4620' from SNPS
) SNPS ODCM Part 1. Section 3/4.12.2 102
TABLE G-3 (cont.)
Sector Direction Location 14 WNW St. Joseph's Villa; Wading River, 2178' from SNPS 15 NW Area within sector is Long Island Sound 16 NNW Area within sector is Long Island Sound 0
103
k 4
4 e
1 APPENDIX H COMMON AND SCIENTIFIC NAMES OF
~
SPECIES COLLECTED IN THE REMP 104
TABLE H-1 COMMON AND SCIENTIFIC NAMES OF SPECIES COLLECTED IN THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Common Name ScientiBe Name Ehh Winter Flounder Pseudopleuronectes americanus Windowpane Scophthalmus aquosus Searobin Prionotus spp.
Little Skate Eala erinacea Invertebrates American Lobster Homarus americant1H Squid Lolico pealeil Channeled Whelk Busvcon canaliculata 105
___ _ - - _ - _ _ _ _ - - _ - - _ - - - - . -