SNRC-1569, Shoreham Nuclear Power Station Operational Radiological Environ Monitoring Program Annual Rept Jan-Dec 1988
| ML20245E798 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/31/1988 |
| From: | Leonard J LONG ISLAND LIGHTING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| SNRC-1569, NUDOCS 8905020135 | |
| Download: ML20245E798 (136) | |
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I SHOREHAM NUCLEAR POWER STATION OPERATIONAL I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I l ANNUAL REPORT l I , i n. . .. I 1850.D BY
! NUCLEAR ENGINEERING DEPARTMENT ! ENVIRONMENTAL ENGINEERING DEPARTMENT I
I l Lux? 1, ns <g g;r%2M Siejjp h 1
I SHOREHAM NUCLEAR POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I 1988 ANNUAL REPORT JANUARY 1 to DECEMBER 31, 1988 I I Prepared by LONG ISLAND LIGHTING COMPANY and TELEDYNE ISOTOPES, Inc. April 15, 1989 I I I _
TABLE OF CONTENTS PAGE EXECUTIVE
SUMMARY
................................................... 1
- 1. THE PR0 GRAM......................................................... 3 A. Objectives...................................................... 4 B. Sample Co11ection............................................... 5
- 1. Aquatic Environment......................................... 5
- 2. Atmospheric Environment..................................... 5 l
- 3. Terrestrial Environment..................................... 6 4 Direct Radiation............................................ 6 C. Quality Assurance............................................... 6 D. Data Interpretation............................................. 7
- 1. General................................,.................... 7
- 2. Gamma Isotopic.............................................. 8 E. Dose Assesscent................................................. 9 F. P r o g r am S umm a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 II. RESUI.TS AND DISCUSSION.............................................. 13 A. Aquatic Environment............................................ 14
- 1. Surface Water.............................................. 14
- 2. Fish....................................................... 14
- 3. Invertebrates.............................................. 15
- 4. Aquatic P1 ants............................................. 15
- 5. Sediment................................................... 15 B. Atmospheric Environment........................................ 16
- 1. Airborne Particulate...................................... 16
- 2. Airborne Iodine............................................ 16
- 3. Noble Gas.................................................. 16 i
j __ -- l
TABLE OF CONTENTS (Cont.) PAGE C. Terrestrial Environment........................................ 20
- 1. M11k....................................................... 20
- 2. P o t ab l e W a t e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0 1
- 3. Game....................................................... 20 I
- 4. Fo od Pr od uc t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 i
- 5. P r ec i p i t a t i o n . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 i D. D i r ec t R a d i at i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 q i
E. Do s e As s e s sme n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3 III. CONCLUSIONS........................................................ 25 IV. REFERENCES......................................................... 28 APPENDIX A - Radiological Environmental Monitoring................. 31 Program Summary - 1988 APPENDIX B - Sample Designation and Sampling Locations. . .. . . . . . . . . . 41 APPENDIX C - Data Tab 1es........................................... 50 APPENDIX D - An alytical Procedures Synopsis. . . . . . . . . . . . . . . . . . . . . . . . 89 ; APPENDIX E - Summary of EPA Interlaboratory Comparisons........... 102 APPENDIX F - REMP Sampling and Analytical Exceptions. . . . . .. .. . .. . .109 APPENDIX G - SNPS Land Use Surveys................................ 119 APPENDIX H - Species Collected in the Radiological................ 125 l Environmental Monitoring Program APPENDIX I - 1987 Errata.......................................... 127 l i ii !
LIST OF TABLES i N0. TITLE PAGE I 1. Synops i s of the Shoreham Nuc lear Power St at ion's . . . . . . . . . . . . . . . . . . . . 11 Operational Radiological Environmental Monitoring Program for the period January-1 through December 31, 1988
- 2. Summary of Dose Determination for 1988.............................. 24
- 3. Comparison of 1988 Positive Results With Pre-Operational Data....... 27
,I Appendix B - Sample Designation and Sampling Locations B-1 Sample Locations.................................................... 44 Locations Required by SNPS Techtical Specifications B-2 Airborne Particulate and Airborne lodine Monitoring Stations. . ... . . . 45 B-3 Waterborne Monitoring Stations...................................... 45 B-4 Ingestion Monitoring Stations....................................... 45 B-5 Di rect Radi ation Monitoring St ations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 Appendix C - Data Tat,les Aquatic Environment C-1 Concentrations of Tritium, Strontium-89 and Strontium-90 ........... 51 i and Gamma Emitters in Surface Water Samples 1 C-2 Concentrations of Strontium-89 and Strontium-90 and Gamma........... 52 Emitters in Fish Samples , C-3 Concentrations of Strontium-89 and Strontium-90 and Gamma. . . . . . . . . . . 53 Emitters in Invertebrate Samples C-4 Concentrations of Strontium-89 and Strontium-90 and Gamma. . . . . . . . . . . 54 Emitters in Aquatic P1snt Samples C-5 Concentrations of Strontium-89 and Strontium-90 and Gamma. . . . . . . . . . . 55 Emitters in Sediment Samples Atmospheric Environment
)
I C-6 Concentrations of Gross Beta Emitters in Weekly Ai rborne. . . . . . . . . . . . 56 Particulate Samples I iii i j l (
1 LTST OF TABLES (Cont.) l l NO. TITLE PAGE l Atmospheric Environment (Cont.) C-7 Concentrations of Gamma Emitters in Quarterly Composite............. 62 J of Airborne Particulate Samples j i C-8 Concentrations of Strontium-89 and Strontium-90 in Quarterly. .. . . .. . 66 j Composites of Airborne Particulate Samples i C-9 Concentrations of Iodine-131 in Air Cartridge Samples............... 67 1 f Terrestrial Environment C-10 Concentrations of Tritium, Gross Beta and Gamma Emitters............ 73 in Precipitation C-11 Concentrations of lodine-131 in Milk Samples........................ 74 C-12 Concentrations of Strontium-89 and Strontium-90 and Gamma .......... 75 Emitters in Milk Samples C-13 Concentrations of Tritium, Iodine-131 and Gamma Emitters in......... 78 Potable Water Samples C-14 Concentrations of Gamma Emi tters in Game Samples. . . . . . . . . . . . . . . . . . . . 79 C-15 Concentrations of Gamma Emitters and 1-131 in Food Product Samples.. 80 DIRECT RADIATION C-16 Di rect Radi ation Measurements - Quarterly TLD Result s. . . . . . . . . . . . . . . 81 C-17 Direct Radiation Measurements - Monthly TLD Results................. 83 l l NOBLE GAS C-18 Concentrations of Krypton-85 and Xenon-133. ....................... 85 in Air Samples LOWER LIMIT OF DETECTION (LLD) C-19 Typical LLDs Achieved for Gamma Spectrometry. . . . . . . . . . . . . . . . . . . . . . . 86 C-20 LLDs and Reporting Action Levels Required by Technical . . . . . . . . . . . . . . 87 Specifications and 1988 Contract iv
LIST OF FIGURES TITLE NO. PAGE
- 1. Average Weekly Gross Beta Results in Airborne Particulate..........17 (January 1 through December 31,1988)
- 2. Comparison of' Average Monthly Gross Beta Results in Airborne....... 18 Particulate (February 1977 - December 1988)
- 3. Comparison of Average TLD Results (February 1977 - December 1988)... 22 APPENDIX B - SAMPLE DESIGNATION AND SAMPLING LOCATIONS LIST OF MAPS B-1 Sh o r e h am S i t e L o c a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 7
~B-2 On Site Sampling Locations.......................................... 48 B-3 Off Site Sampling Locations......................................... 49 l
V - _ - _ _ _ _ - _ - _ - _ _ - - _ _ _ _ - _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ =
I .I I I I EXECUTIVE
SUMMARY
I I I I I 1 I . I
EXECUTIVE
SUMMARY
This report summarizes the Shoreham Nuclear Power Station's (SNPS) Radiological Environmental Monitoring Program (REMP) for 1988. SNPS received a license to coerate up to 5% power in 1985. The plant was, however, in a coid shutdown condition during the entire year of 1988. The objective of the operational REMP is to identify and measure plant related radioactivity in the environment and calculate the poter,tial dose to the surrounding population. The operational phase uses the preopera- I tional baseline data to identify plant contributed radiation and evaluates the possible effects of radioactive plant effluents on the environment. The SNPS REMP is designed to comply with the Plant's Technt .at Specifications 1 and NRC Regulatory Guide 4.15. The REMP data is acquired by sampling various media in the environment which are then analyzed for any radiation prese it. Media sempled within the aquatic environment included surface water, algae, fish, invertebrates (clams, lobsters, etc.) and sediment. The atmospheric environment was sampled for airborne particulate, airborne iodine and noble gases. Milk, potable water, precipitation, game and food products were obtained from the te"restrial environment. Direct radiation was measured using thermo-luminescent dosimeters (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 use data. Sampling locations are designated as either indicator or control locations. The indicator locations are placed close enough to Shoreham so that plant contributed radioactivity will be at its highest concentration. The control sample locations are placed so that they will be beyond measurable influence of Shoreham and any other nuclear facility. An exception to this occurred at the on shore site for REMP location 13G2, at the entrance to Port Jefferson Harbor. During preoperational testing in 1982 and 1983, aquatic samples revealed the presence of low levels of iodine-131. An investigation revealed that the iodine-131 was from area hospitals treating patients for thyroid carcinoma. As a result, a second onshore aquatic back-ground location is now being sampled at the entrance to Mt. Sinai Harbor. A number of radioanalyses were performed on each medium sampled. All samples did not undergo all types of radioanalyses; only those analyses appropriate for the particular medium were performed. The analyses included l l gamma spectrometry, strontiurn-89 and -90, iodine-131, tritium, gross beta l radiation, direct radiation and noble gases. 00se calculations for the SNPS environs were performed using positive concentrations of radioactivity detected in the samples collected. In all cases the calculated doses were similar to the background doses calculated for the previous years. Therefore, no environmental radioactivity was identified as having originated from SNPS. 2 1
l l I i I l I l j i I l
- 1. PROGRAM I
I I I I I 3
I THE PROGRAM The Shoreham Nuclear Power Station's (SNPS) Radiological Environment.1 I Monitoring Program (REMP) is conducted in compliance with NRC Regulatory Guide 4.15, licensing commitments, LILC0's Updated Safety Analysis Report (USAR) 11.6, and Technical Specification 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) 6.1.5. All samples were collected by personnel of the Long Island Lighting Company (Environmental Engineering Department) or EA I Engineering, Science and Technology, Inc. A synopsis of the sampling program can be found in Table 1. Maps and a description of sampling loca-tions appear in Appendix B. During 1988 sample analyses were performed by Teledyne Isotopes (TI) of Westwood, New Jersey (referred to throughout the text as "the laborato*y"), under contract to LILCO. A summary of analytical results appears in Appendix A and individual analysis results in Appendix C. A. Objectives The objectives of the operational radiological environmental monitoring program are:
- 1. Identify and measure radiation and radioactivity in the plant environs for the calculation of potential dose to the population.
- 2. Verify the effectiveness of in-plant measures used for controlling ,
the release of radioactive materials. I Provide reasonable assurance that the predicted doses, based on I 3. effluent data, have not been substantially underestimated and are consistent with applicable standards. . j l l 4. Comply with regulatory requirements and SNPS Technical Specifications and provide records to document compliance. I I l l l l 4 l l
B. f p,e Collection
- 1. Aquatic Environment The aquatic environment at the SNPS site was examined by analyzing samples of surf ace water, fish, invertebrates, aquatic plants and sediment. Surf ace water samples were taken at six loca-tions in May and October using a Niskin bottle or by wading into the water and filling a new two gallon polyethylene bottle. The samples were placed in new polyethylene bottles following three rinses with the sample medium prior to collection. Samples of Winter Flounder (pseudopleuronectes americanus), Windowpane (Scophthalmus aquosus), q Sea Robin (Prionotus spp), and Little Skate (Raja erinacea) were '
taken by trawl, sealed in plastic bags, frozen, and shipped to the laboratory for analysis. Invertebrate samples of American Lobster (Homarus americanus), Squid (Loligo pealeii) and Channeled Whelk (Busycon canaliculata) were collected by trawl. Channeled Whelk were also collected using pots. These invertebrate samples were sealed in plastic bags, frozen s ano shipped to the laboratory for analysis. Blue Mussels (Mytilus edulis) were collected by hand along jetties. Sof t-shell clams (Mya arenaria), from Wading River were shelled and sealed in plastic bsgs, frozen and shipped to the laboratory. Aquatic plants (Fucus sp., Ulva lactuca Enteromorpha sp., and Codium sp.), among others were collected f rom along the snoreline, then sealed in plastic bags, refrigerated and shipped. Deep water i sediment was collected using a Smith-MacIntyre bottom sampler, sealed in plastic bags, frozen and shipped. Beach sediment samples were also collected, sealed in plastic bags, frozen and shipped to the j laboratory.
- 2. Atmospheric Environment The atmospheric environment was examined by analyzing airborne l particulate collected on Gelman Type A/E filters using low volume j air samplers (approximately 1 cfm). Airborne iodine was collected by i absorption on triethylenediamine (TEDA) impregnated charcoal car-tridges, manufactured by Scott, which were connected in series behind the airborne particulate filters. The samplers used were equipped l with a vacuum recorder for sample volume correction to ensure sample l validity and to indicate any maintenance problems. Should the ;
sampler lose vacuum due to a leak the vacutsn level reading will drop to zero. Since this m3y occur without a corresponding loss of electric supply the exact time of the maintenance problem will be evident on the vacuum recorder chart. I i l Sample volumes were measured using dry gas meters and corrected i for differences between the actual pressure seen by the volume l meter and the average atmospheric pressure. Sample volumes are ! corrected to standard pressure using average weekly barometric j ] ! 5 J
I pressure (measured at Environmental Engineering Department, Melville) and air sampler vacuum readings. Time totalizers indicate the duration of time the sample was taken. Air samples were collected weekly at St. Joseph's Villa and analyzed for the noble gases krypton-85 and xenon-133. The samples were collected using a modified low pressure air compressor. Outside air is drawn into an interim holding tank evacuated to 20" Hg and then transferred to a sample tank for transport to the laboratory for analysis.
- 3. Terrestrial Environment The terrestrial environment was examined by analyzing samples of milk, precipitation, potable water, game, food products, and soil.
When available, milk samples were collected from four locations monthly, except during the pasture season (May through October) when the sampling was increased to twice a month. Milk samples were shipped on ice with sodium bisulfite (NaHS03) preservative added. Precipitation was collected at two locations weekly. In order to ensure sufficient sample volume, weekly precipitation senples were combined for a monthly sample composite. Potable water was collected quarterly from three well locations. However, samples were unavailable from well 1352 for three of the four quarterly collections, presumably due to a change in the sater table. Game samples (Squirrel, Sciurus carolinensis and Raccoon, Procyon lotor) were obtained semi-annually from on site locations, sealed in plastic bags, frozen and then shipped. Food products consisting of vegetables and fruit were collected from area farm stands and shipped fresh to the laboratory. I
- 4. Direct Radiation .
I Direct radiation levels in the environs were measured with energy compensated calcitan sulf ate (CaSO4:Dy) TLDs, each contain- ! ing four separate readout areas. The TLDs are annealed by LILC0 i prior to placement in the field. Two TLDs were placed at 36 locations and exchanged on a monthly and quarterly cycle. The units were then , packaged and shipped to the laboratory for analysis along with a j control dosimeter. ' C. Quality Assurance
- 1. Teledyne Isotopes l Teledyne Isotopes (TI) has an extensive quality assurance program designed to ensure the precision and accuracy of the data generated. An Interlaboratory Comparison Program is conducted with I 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 6 l l
i 'I from the "known" value given, or by comparison with means of all l participants. The TI Quality Assurance Program for Radiological Monitoring is described in various TI publications (references 15, 16,17). , 1 Approximately 10 percent of TI's total analytical effort is spent on quality control including process quality control, instrument ( quality control, intra and interlaboratory cross-check, and compre- ! a hensive data review. In addition, LILC0 specifically requires that i g ten percent of its analyses be duplicated for further quality control cross check. l Additional information on the LILC0 Quality Assurance Program is provided in NED 4170004, Quality Assurance Program For Radiological l Environmental Monitoring Program, Shoreham Nuclear Power Station. ! 1 I D. Data Interpretation l 1
- 1. General I The analytical data generated during the program are routinely evaluated by the TI project leader who is the liason with Long Island ]
Lighting Company's Environmental and Nuclear Engineering Departments. Several factors are important in the interpretation of the data, j These factors are discussed here to avoid repetition in sections that i follow. l I Within the data tables ( Appendix C) an approximate 95 percent (t2 sigma) confidence interval is supplied for those data points t { above the lower limit of detection (LLD). These intervals represent l the range of values into which 95 percent of repeated analyses of l the same sample would f all. Tables C-19 and C-20 present typical and i required LLD's, respectively. i
)
Results for each type of sample were grouped according to the analysis performed. Means and standard deviations of these results I are calculated when applicable. The calculated standard deviations of grouped data represent sample rather than analytical variability. For these calculations any values below LLD are considered to be at 3 j the LLD. As a result, the means are biased high and the standard I deviations are biased low. When a group of data is composed of mainly LLD values (>50%), averages are not calculated. j l I 7 _ - _ _ _ _ _ _ _ - _ _ _ _ _ . l
Grab sampling is a useful and acceptable procedure for taking environmental. samples of a medium in which the concentration of . radionuclides.is expected to vary minimally with time or where inter- { mittent sampling is deemed sufficient to establish the radiological j characteristics of the medium. This method, however, is only repre- ' sentative of the sampled medium for that specific location and ) instant of time. As a result, variation of radionuclides concentra-tions in the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averagen i based upon repetitive grab samples is valid. l
- 2. Gamma isotopic Analyses l SNPS Technical Specifications 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 are in addition to requirements for specific gamma emitters such as 1-131, 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 wheri the LLD's for specified gamma emitters are met by this technique.
Tables 3.1 and 3.2 of the Shoreham Final Environmental' Statement list the calculated liquid and gaseous effluents by radionuclides in curies per year. These release rates assune normal operation of the plant, including anticipated operational occurrences. Those nuclides liste; in Tables 3.1 and 3.2 which are not routinely observable by gamma spectroscopy and which are not specifically 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,Zn-69,Sr-91,Y-91m,Y-92,Y-93,Tc-99m, Rh-103m, Rh-105, Rh-106, Te-129 Te-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 emission (Y-91), or those with their primary gamma occurring at l
such a low energy and at such low abundance that it is not routinely observable in the presence of other gamn.a activity (Nd-147). With only 10 pCi of Nd-147 calculated to be released per year in Shoreham's liquid effluents, the nuclide cannot be an important contributor to dose. i 8
E. Dose Assessment The methodology for determining doses is similar for all path-ways. Laboratory analyses from the REMP for each sample type are compiled. Data from all locations taken on the same date are averaged to obtain the most reliable approximation of the radioactivity concen-tration 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, milk, water, meat, vegetables, etc., consumed per year by the maximum individual is also needed to calculate the total dose (13).
, The dose due to direct radiation exposure is monitored by TLDs.
The laboratory results for TLD's 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 calcu-lated by the product of the radionuclides specific dose conversion factor for its applicable exposure pathway, the environmental sample radionuclides 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 constrned per year is expressed in kg/ year or // year. Finally, the dose conversion f actor is expressed in terms of mrem /pCi ingested or inhaled. l l 9
i F. Program Summary Table 1 summarizes information on the REMP as performed during the period of this report, January 1 through December 31, 1988. During this reporting period 3121 analyses were performed on 2427 env.ironmental 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 specifies 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 31,1988. Appendix D contains a synopsis of the analytical procedures used in the REMP. Results of the EPA inter-laboratory comparison program can be found in Appendix E. Appendix F lists the program exceptions for 1988, and Appendix G reports the land use surveys performed by LILC0's Environmental Engineering Department during 1988 in the vicinity of the SNPS. Common and scientific names of species collected in the program are presented in Appendix H. Appendix I lists- 1987 Errata. 1 10
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!!. RESULTS AND DISCUSSION
)
)
13
l RESULTS AND DISCUSSION l l The analytical results for the reporting period of January 1 through a December 31, 1988, have been divided into four categories: aquatic, atmospheric, terrestrial, and direct radiation. The individual samples and l 3 analyses within each category display the unique radiological characteristics I g 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. i A. Aquatic Environment E The aquatic environment in the vicinity of SNPS consists primarily of l 5 Long Island Sound. The radiological characteristics wtre studied by analyzing samples of surf ace water, Winter Flounder, W'indowpane, Sea Robin, Little Skate, American Lobster, Squid, Channeled Whelk, Blue Mussels, Sof t I Shell Clams, aquatic plants and sediment. The samples were collected by LILC0's Environmental Engineering Department and EA Engineering Science and Technology, Inc. (under contract to LILCO).
- 1. Surface Water (Table C-1)
Semiannual surf ace water samples were taken at six locations and were analyzed for tritium, gamma emitters, iodine-131, and strontium-89 and strontium-90. Two surf ace water samples analyzed for tritium showed detectable levels between 190 and 460 pCi/l with an average of 325 pCi/t. The other I ten samples were below the lower limit of detection. This is consistent with tritium concentrations observed in surface water during 1983 and 1984, the preoperational period, and in 1985, 1986 and 1987. , Naturally occurring potassium-40 was measured in ten of the samples with an average of 218 pCi/l and a range between 112 and 350 pCi/l. No other gama activity above the detectable levels was measured in l l the twelve surf ace water samples as analyzed by gama $ spectroscopy. Surf ace water samples were also analyzed for iodine-131, strontium-89, l and strontium-90. None of these nuclides were observed within the limits 1 I of detection.
- 2. Fish (Table C-2)
Twenty-five 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 4095 pCi/kg wet and a range between 2280 and 10800 pCi/kg wet. Cesium-137 was detected in six samples with an average activity of 12.1 pCi/kg wet I and a range between 7.1 and 17.5 pCi/kg wet. These activities are less than those reported in 1983 and 1984 during the preoperational period, and l comparable to those reported in 1985,1986 and 1987. l ' 14
- 3. Invertebrates (Table C-3)
Twenty-two invertebrate samples, comprised of sof t shell clams, mussels, lobsters, squid, and whelks, were collected at six locations and analyzed for gamma emitters, strontium-89 and strontium-90. Gamma spec-trometry showed detectable levels of potassium-40 in all samples, ranging from 1250 to 6550 pCi/kg wet with an average activity of 2723 pCi/kg wet. Naturally occurring beryllium-7 was measured in two samples with an average activity of 98.6 pC1/kg (wet) and a range of 61.1 to 136 pCi/kg (wet). Also, naturally occurring thorium-228 was measured in one sample with an activity of 27.1 pC1/kg (wet). Neither strontium-89 nor strontium-90 was detected. 4 Aquatic Plants (Table C-4) Marine algae, collected at five locations (thirteen samples) in Long Island Sound and at one location in Wading River Marsh (two samples), were analyzed for gama emitters and strontium-89 and strontium-90. Gama spectrometry showed detectable potassium-40 in all samples ranging from 4610 to 54000 pC1/kg dry with an average of 21679 pCi/kg dry. Cosmogenically produced beryllium-7 was mee9 ed in eleven of the samples ranging from 137 to 4670 pCi/kg dry with an ave age activity of 1628 pCi/kg dry. Cesium-137 was measured in one sample with an activity of 39.1 pCi/kg dry. Naturally occurring thorium-228 was measured in eight samples with an average activity of 400 pCi/kg dry and a range of 151 to 700 pC1/kg dry. Radium-226 was measured in one sample with an activity of 1100 pCi/kg dry. Strontium-89 and strontium-90 were not observed.
- 5. Sediment (Table C-5)
Ten offshore sediment samples were collected in April, May, October and November at four offshore locations and analyzed for gamma emitters and strontium-89 and strontium-90. For the summation of samples collected, location 4A3 is grouped with the offshore sites. Gama' spectrometry showed detectable levels of potassium-40 in all samples ranging from 1710 to 8410 pCi/kg dry with an average activity of 3316 pCi/kg dry. Naturally occurring radium-226 was observed in four samples with an activity of 558 pCi/kg dry. Thorium-228, also naturally occurring, was measured in eight samples within the range of 156 to 856 pCi/kg dry with an average activity of 425 pCi/kg dry. All other gama emitters were below the lower limit of detection. No stronti m-89 or strontium-90 was detected in these samples. Ten beach sediment samples were collected and analyzed for strontium-89, stronti m-90 and gamma emitters. No strontium was detected. All samples had measurable activities of naturally occurring potassium-40 with an average activity of 2533 pCi/kg dry and a range of 1140 to 5310 pCi/kg dry. Four samples had measurable radim-226 with an average activity of 229 pCi/kg dry and a range of 148 to 273 pCi/kg dry. Ten samples had measurable thori m-228 with an average activity of 198 pCi/kg dry and a range of 63.0 to 152 pCi/kg dry. All other gama emitters were below the lower limit of detection. i 15
)
B. Atmospheric Environment I The atmospheric environment in the vicinity of the SNPS was examined by analyzing samples of airborne particulate and airborne iodine at 16 sampling locations. TEDA-impregnated charcoal cartridges used to collect airborne iodine were collected weekly and analyzed by gamma spectrometry for iodine-131. Airborne particulate filters were collected weekly and analyzed for beta emitters. Quarterly composites from each station were analyzed for gamma emitters and radiostrontium.
- 1. Airborne Particulate (Tables C-6, C-7, C-8 and C-9)
Beta-emitter concentrations ranged from 0.005 to 0.044 pC1/m3 with an annual average for the 16 sampling locations of 0.017 pCi/m3 (Table C-6). Of the 789 measurements three were below the detection limit, nominally 0.004 pCi/m o. Figure 1 shows the average weekly gross beta fluctuations in airborne particulate from all stations for 1988. Figure 2 represents the average monthly gross beta results in airborne particulate from January 1,1977 through December 31, 1988. Results of gama spectrometry (Table C-7) showed detectable levels of naturally occurring bery111um-7 in all sixty-three samples. Due to a electrical malfunction no weekly samples were collecteC t , station 652 during the first quarter. Therefore, there were only 63 composite samples for the year. However, station 351 located apprgmximately 400' ' north of 652 showed a bery111um-7 average of 0.090 pCi/m3 The average bery111um-7 activity in the guarterly analyses was 0.076 pC1/m3 with a range of 0.052 to 0.157 pCi/m3 Naturally occurring potassium-40 was observed four times with an average of 0.007 pCi/m3 and a range of 0.0062 to 0.0086 pCi/m3 All other gamma emitters were below the lower limit of detection. The radiostrontium analyses on the 63 quarterly composites showed no detectable levels of strontium-89 or strontium-90. A
- 2. Airborne Iodine (Table C-9)
Analytical results of airborne iodine-131 were all bel limitofdetectionwhichrangedbetween0.008and0.2pCi/mgwthelower .
- 3. Noble Gas (Table C-18)
Air samples were collected weekly at St. Joseph's Villa and analyzed for Krypton-85 and Xenon-133. Xenon-133 was not found in any sample. All 52 samples had positive concentrations of Krypton-85 ranging from 28 to 44 pCi/m3, with an average concentration of 34 l pCi/m3, similar to the average concentrations found during the l preoperational years. 16
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l C. Terrestrial Environment The terrestrial environment in the vicinity of the SNPS was examined by analyzing samples of game (raccoon and squirrel), milk, food products, rainwater and potable water. Gama spectrometry was performed on all f s amples. In addition, iodine-131, strontium-89 and strontium-90 analyses were performed on the milk samples, while tritium and iodine-131 analyses l were performed on the potable water samples. Rainwater samples were analyzed for gross beta, tritium and gama emitters.
- 1. Milk (Tables C-11 and C-12)
All of the 73 monthly and semimonthly cow and goat milk samples analyzed for iodine-131 were below the LLD wSich ranged between <0.2 and <0.6 pCi/t. Naturally occurring potassium-40 was observed in all the milk s amples. The goat milk samples had an average measurement of 1532 pCi/t and a range of 1190 to 1860 pCi/2. The cow milk samples had an average concen-tration of 1270 pCi/t with a range of 800 to 1880 pCi/t. Cesium-137 was detected in. Seven of the 50 goat milk samples with an average of 8.7 pC1/f and a range of 7.5 to 10.1 pCi/f. Six of the 23 cow milk samples had detectable measurements of cesium-137 with an average of 8.4 pC1/2 and a range of 5.9 to 11.5 pCi/t. All other gama emitters, as well as strontium-89 were below the detection limit. Strontium-90 was observed in all of the cow and goat milk samples. In the 16 cow milk samples, the average strontium-90 concentration was 3.2 pCi/f with a range from 0.76 to 7.6 pCi/t. For the 30 goat milk samples, the average strontium-90 concentration was 2.2 pCi/l and the range was from 0.53 to 6.0 pCi/t. The activities reported for strontium-90 are consistent with those found in cow and goat milk samples from 1983 to the present.
- 2. Potable Water (Table C-13)
Tritium activity was measured in seven of the eleven; potable water l samples collected at three locations. In these four samples, the average tritium concentration was 270 pCi/l with a range of 150 to 410 pCi/t. The other tritium results were below the lower limit of detection (100 pCi/t). This is consistent with the results of the previous four years. No iodine-131 was measured above the lower limit of detection which was between 0.2 and 0.3 pCi/t. Naturally occurring potassium-40 was observed.in one sample with an activity of 48.5 pCi/t. All other gamma emitters were'below the lower limit of detection.
- 3. Game (Table C-14)
Potassium-40 was observed in the four game suples (two raccoons and two squirrels) with an average activity of 2993 pCi/kg wet and a range from l 2650 to 3420 pCi/kg wet. However, cesium-137, the only other observed gama ) emitter, was measured over a greater range of activity due presumably to differences in diets and possibly to seasonal effects. For the two raccoon l samples the average cesium-137 activity was 307 pCi/kg wet and the two J values were 76.7 pCi/kg wet and 538 pCi/kg wet. These results are consistent with results of the previous four years. The average cesium-137 activity in the two squirrel samples was 5620 pCi/kg wet and the range was from 1970 to 9270 pC1/kg wet. 20
- 4. Food Products (Table C-15)
Nineteen human food products from local farms were analyzed, including tomatoes, potatoes, cabbage, lettuce, beets, onions, strawberries, and corn. All samples contained naturally occurring potassium-40 with an guerage of 1660 pCi/kg wet and a range of 1320 to 4760 pCi/kg wet. All other gamma emitters were below the lower limit of detection. The samples were also analyzed for iodine-131 by a radiochemical procedure. No activity was found. The detection limit varied from 4 to 10 pCi/kg wet.
- 5. Precipitation (Table C-10)
Twenty-four precipitation samples were collected at two stations during the twelve months and analyzed for gross beta, tritium and gamma emitters. Gross beta activity was measured in the 24 samples with an average activity of 5.5 and a range of 1.3 to 14 pCi/f. Tritium was measured in eleven of the 24 samples with an average activity of 292 nCi/f and a range of 130 to 490 pCi/f. Naturally occurring beryllium was observed in eight samples. Three samples from station 951 had an average of 44.9 pCi/t and a range of 38.9 to 53.0 pCi/f. Beryllium was also observed in five samples from station 12A1 with an average of 74.3 pCi/t and a range of 50.1 to 105 pCi/l. All other gamma emitters were below detection limits. D. Direct Radiation (Tables C-1,6 and C-17) Direct radiation measurements were taken monthly and quarterly at 36 locations using CaSO4:Dy thermoluminescent dosimeters (TLDs). In $ddition, one new location was added on November 3, ?988. TLDs were used to detect ractation 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 l from 1977 to 1988. 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 was 3.5 mR/ standard month and the average of the monthly exposures was 3.6 mR/ standard month. This is less than quarterly and monthly values, respectively, measured during the preoperational years 1983 and 1984. f I 21
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E. Cose Assessment Table 2 summarizes the results of the dose assessment determinations based e. '988 data. In R1 ally, all positive concentrations of radionuclides in indicator samples, as shown in Appendix A, were considered for inclusion in the dose calculation. In an attempt to factor out as much of the contribution due to natural and man-made background radiation as possible, indicator and control sample results were compared. If the control location results were greater I than those at the indicator location, the indicator' sample results were not included in the dose assessment. Surface water, aquatic plants and precipi-tation were not considered as significant human exposure pathways and, there- , fore, not considered in the dose assessment. The dose due to standing on soil / sediment was not calculated since this is accounted for in the direct radiation dose. Also, potable water was excluded from dose calculations because it is not considered a pathway. (Since ground water drainage is to the north, no water sources for drinking or irrigation can be affected.) Beryllium-7, potassium-40, radium-226, radium-228 and thorium-228 are all I naturally occurring isotopes and not likely to be produced as a result of the operation of Shoreham, so they were excluded. Krypton-85 was also excluded as an individual contributor to dose since it is not absorbed or ingested and is included in the direct radiation component. The remaining positive isotope, cesium-137, could be produced as a result of plant operation so it was in-cluded in the dose calculations. It should be noted that cesium-137 also exists in the environment as a result of atmospheric weapons testing and the Chernobyl accident. Comparison of the results of the dose assessment of 1988 with those of the preoperational years 1983 and 1984, show similar results for all three yecrs. Doses calculated for 1983 were based on ingestion factors for the average individual, whereas the maximum individual ingestion factors were used in 1984 and 1988. This makes exact comparison of the results difficult; how-ever, the dose is directly proportional to the activity in the medium: in all cases conside ed, the concentrations found in 1988 are consistent with those of 1983. It should be noted that cesium-137 found in game samples was considered as a dose contributor by using ingestion factors for meat. This is highly conservative. I I I 23 i
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III. CONCLUSIONS 25
CONCLUSIONS During 1988, the Shoreham Nuclear Power Station was in a cold shutdown condition during the entire year. Analyses of environmental samples show results consistent with those found during the pre-operational years of 1983 and 1984. In addition, I comparison of results reveals little difference between indicator and control locations. Therefore, no isotopes could be identified as having originated from SNPS. I Sensitive indicators revealed minute quantities of radioactive fallout from the October 1980 atmospheric nuclear weapons test by the Peoples Republic of China, in addition to radioactivity remaining from two decades of atmospheric testing. I Aside from these anomalies 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 I the environment. The atmospheric environment was sampled for airborne particulate matter, iodine, and noble gases. Figure 1 represents the average weekly gross beta results in airborne particulate from January through I December 1988. Figure 2 shows the average monthly gross beta results in airborne particulate from February 19 ' to December 1989. 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 I January 1977 to December 1988. I I I I 26 I
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I I I I I I IV. REFERENCES 28 I _
IV. REFERENCES (1) Long Island Lighting Company. "Shoreham Nuclear Power Station, Environmental Report, Construction Permit Stage", December 1977. (2) United States Atomic Energy Comission, Directorate of Licensing " Final Environmental Statement Related to Operation of Shoreham Nuclear Power Station", Docket No. 50-322, September 1972. (3) Long Island Lighting Company. "Shoreham Nuclear Power Station, Updated Safety Analysis Report". (4) Radiation Management Corporation. "Shoreham Nuclear Power Station Radiological Environmental Monitoring Program - 1977 Annual Report", March 1978. (5) Radiation Management Corporation. "Shoreham Nuclear Power Station Radiological Environmental Monitoring Program - 1978 Annual Report", April 1979. (6) Radiation Management Corporation. "Shoreham Nuclear Power Station Radiological Environmental Monitoring Program - 1979 Annual Report", June 1980. (7) Radiation Management Corporation. "Shoreham Nuclear Power Station Preoperational Radiological Monitoring Program - 1980 Annual Report", September 1981. (8) 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, l National Research Council, Washington, D.C., 1971. ) I (11) Long Island Lighting Company, Environmental Engineering Dept., Radiological i Environmental Monitoring Program Procedures. l l 1 29 i
)
IV. REFERENCES (Cont.) i I (12) EA Science and Technology Shoreham Project Quality Assurance and Procedures Manaual 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. (15) Teledyne Isotopes " Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual", IWL-0032-361. (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 Annusi 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 Annut.1 Report. 30
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ;
SUMMARY
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I I ' I ' ig 1 J l APPENDIX B SAMPLE DESIGNATION AND LOCATIONS I I I 4 I I I 1 l l 41
APPENDIX B Sample Designation LILC0'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) GMK = Goat Milk AQF = Fish (1) PWA = Potable Water (ground water) AQI = Invertebrates (1) GAX = Game (1) AQP = Aquatic Plants (1) FPV = Food Products (1) I AQS APT AIO
=
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Fruit Immersion Dose (TLD) Noble Gas
= Milk RWA = Precipitation (Rainwater)
I MLK SOL = Soil The last four synbols 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 clock-I wise direction, i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant: 5 = 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 The last nun,ber is the location numerical designation within each sector I and zone, c.g. ,1,2,3, .. . .For example, the designation SN-SWA-3C1 would indicate a 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 I axis (3) between the site boundary and 2-3 miles off site (C). The number 1 indicates that this is sampling station No.1 in the designated area. Sampling Locations All sampling locations and specific information about the ind%'ml locations I are given in Table B-1. Tables B-2 through B-5 list the sampi c.,9 iocations and media required by Technical Specifications. I (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 I accepted common name of the sample involved. In this case, clam, lobster, crab or other aquatic invertebrate would be listed in the conrnent section. 42
APPENDIX B ,I Sampling Locations Maps B-1, B-2 and B-3 show the locations of 1988 sampling stations with respect to the site. These maps are tracings of portions of larger maps prepared by LILC0's Survey Division after an extensive land survey of REMP I monitoring locations. Additional information can be obtGined 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 I contacting either LILC0's Environmental Engineering Department or Survey Division. LOCATION TABLE B-1 SAMPLE SECTOR CODE LOCATION TYPE I N 151 Beach east of intake 0.3 mi. N IDM(*) NNE 251 Well, on site, 0.1 mi . NNE PWA(*) I NE ENE E 351 4S1 552 Site Boundary, 0.1 mi. NE Site Boundary, 0.1 mi. ENE Site Boundary, 0.1 mi. E APT (*),AIO(*),IDM(*) IDM(*) IDM(*) ESE 652 Site Boundary, 0.1 mi. ESE APT (*),AIO(*),IDM(*) S 951 Service Road. 0.2 mi. S APT.AIO,IDM(*), RWA S 952 East Gate SNPS, 0.3 mi. S IDM(*) W 1352 Well, on site, 0.2 mi. W PWA(*) W 1353 Site Boundary, 0.2 mi. W IDM(*),GAX WNW 1451 St. Joseph's Villa, 0.4 mi WNW GAX WNW 1452 St. Joseph's Villa, 0.4 mi. WNW IDM(*),NBG I NW NNW 1551 1652 Beach west of intake, 0.3 mi. NW Site Boundary, 0.3 mi. NNW IDM(*) IDM(*) NNE 2A2 West end of Creek Road, 0.2 mi. NNE APT (*),AIO(*),IDM(*) NNE 2A3 Residence 0.3 mi, NNE APT (AIO,IDM(*),PWA NNE 2A4 Beach. 0.4 mi. NNE AQS(*) NE 3A2 Riverhead Town Beach 0.7 mi. NE AQS ENE 4A3 Wading River, Eastern Marsh, 0.2 mi. ENE SWA,AQI,AQP,AQS ESE 6Al Sound Road. 0.7 mi, ESE IDM(*) SE 7A2 North Country Road, 0.7 mi. SE APT,AIO,IDM(*) SSE 8A3 North Country Road. 0.6 mi. SSE APT,AIO,IDM(*) SSW 10A1 North Country Road, 0.3 mi. SSW APT,AIO,IDM(*) SW 11A1 Site Boundary, 0.3 mi. SW IDM(*) WSW 12A1 Meteorological Tower, 0.9 mi. WSW APT,AIO,IDM(*), RWA I WNW NNW 14A1 16Al Brookhaven Town Beach, 0.8 mi. WNW Aquatic location, west jetty of intake cshal 0.4 mi. NNW AQS AQI,AQP ! ESE C 6B1 Remsen Road, Wading River,1.6 mi. ESE PWA SE 781 Overhill Road, Wading River,1.4 mi. SE APT (*),AIO(*),IDM(*) E 7B3 Farm stand, 1.7 mi. E FPV SSE 8B1 Farm stand 1.2 mi. SSE FPV(*),FPF W 1381 Briarcliff Road,1.9 mi. W GMK NNW 16B1 Long Island Sound,1.3 mi . NNW AQS,5WA 43
TABLE B-1 LOCATION SAMPLE SECTOR CODE LOCATION TYPE NE 3C1 Outfall area, aquatic location SWA(*),AQF(*),AQI(*) B-5, 2.9 mi. NE AQP,AQS E SC2 Farm, 2.8 mi E FPVFPF(*) g WSW 12C1 Local Store, McCarricks Dairy, 2.7 mi WSW MLK
- WNW 14C1 Outfall area, aquatic location SWA(*),AQF(*),AQI(*)
B-4, 2.1 mi. WNW AQP,AQS E 501 Wildwood State Park, 3.4 mi. E IDM(*) E 503 Wildwood State Park, 3.1 mi . E APT.IDM, AIO WSW 1201 North Shore Beach Substation, APT,AIO,IDM(*) 3.7 mi. WSW E SE2 Calverton, 4.5 mi E IDM(*) ESE 6El LILCO R0W, 4.8 mi. ESE IDM(*) SE 7El Calverton, 4.9 mi. SE IDM(*) SSE 8E1 Calverton, 4.4 mi. SSE IDM(*) S 9El Brookhaven National Laboratory IDM(*) 5.0 mi. S SSW 10E1 Ridge Substation, 4.0 mi. SSW IDM(*) SW 11El LILCO R0W, 4.7'mi. SW IDM(*) W 13E1 Longview Ave. and Rocky Point Landing IDM(*) Rd., 4.5 mi W E C SF2 Farm, 6.1 mi E FPV ; E C 5F3 Farm, 7.8 mi. E APT,AIO,IDM(*) SSE 8F2 Goat Farm, Wading River Rd., 9.5 mi. SSE GMK SSW C 10F1 Goat Farm, 9.2 mi. SSW GMK(*) W C 13F1 Background aquatic location 9.4 mi. W AQI,AQP,5WA,AQS ESE C 6G1 Hampton Bays Substation, 19.0 mi. ESE IDM(*) SSE C BG1 Wading River Rd., 10.1 mi. SSE - APT,AIO,IDM(*) SSE C 8G2 Dairy Farm, Center Moriches, 10.8 mi. SSE MLK SW C 11G1 MacArthur Substation, 16.6 mi. SW APT (*),AIO(*),IDM(*) WSW C 12G1 Central Islip Substation,19.9 mi. WSW IDM(*) WSW C 12G2 Flowerfield Substation, 15.4 mi. WSW APT AIO,IDM(*) W C 13G2 Background aquatic location,13.2 mi. W SWA(*),AQP,AQS AQF(*),AQI(*) WSW C 12H1 Farm, 25.8 mi. WSW FPV(*),FPF(*) WSW C 12H2 Farm, 32.1 mi. WSW FPV, FPF l C Denotes Control Location
- Denotes SNPS Technical Specification, sampling locations and sample type.
** Bottled Milk l
l 44
I I REMP LOCATIONS REQUIRED BY SNPS TECHNICAL SPECIFICATIONS TABLE B-2 Airborne Particulate and Airborne Iodine Monitoring Stationc I Location NUREG-0473 Codes Shoreham REMP Location Description A1 6S2 Site Boundary, 0.1 mi. ESE A2 2A2 West end of Creek Road, 0.2 mi. NNE ; A3 351 Site Boundary, 0.1 mi., NE " A4 781 Overhill Road, 1.4 mi. SE A5 11G1 MacArthur Substation, 16.6 mi. SW y TABLE B-3 l Location WATERBORNE MONITORING STATIONS Codes NUREG-0473 Shoreham REMP Location Description WA1 13G2 Surface, background area, 13.2 mi. W ; Surface, outfall area, 2.1 mi. WNW I WA2 14C1 I WA3 3C1 Surface, outfall area, 2.9 mi. NE Wbl 251 Potable Water, well on site, 0.1 mi NNE Wb2 1352 Potable Water, well on site, 0.2 mi. W , Wdl 2A4 Sediment, Beach, 0.4 mi NNE TABLE B-4 INGESTION MONITORING STATIONS Location Codes NUREG-0473 Shoreham REMP Location Description Ia1 13B1 Goat Farm, 1.9 mi. W la2 Goat Farm, 9.2 mi. SSW I Ib1 10F1 3C1 Fish and Invertebrates, outf all 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 I Ic1 Ic2 Ic3 881 SC2 12H1 Local Farm, 1.2 mi. SSE Local Farm, 2.8 mi. E Background Farm, 25.8 mi. WSW I 45
I REMP LOCATIONS REQUlRED BY SNPS TECHNICAL SPECIFICATIONS l TABLE B-5 l l Direct Radiation Monitoring Stations ; Location Codes NUREG-0473 Shoreham REMP Location Description DR1 151 Beach east of intake, 0.3 mi. N DR2 2A2 West end of Creek Road. 0.2 mi MNE DR3 351 Site Boundary 0.1 mi. NE DR4 451 Site Boundary, 0.1 mi. ENE DR5 552 Site Boundary, 0.1 mi. E DR6 652 Site Boundary 0.1 mi. ESE DR7 7A2 North Country Road, 0.7 mi . SE DR8 8A3 North Country Road, 0.6 mi. SSE Service Road SNPS, 0.2 mi. 5 I- DR9 DR10 951 10A1 North Country Road, 0.3 mi. SSW DR11 11A1 Site Boundary. 0.3 mi. SW I DR12 DR13 DR14 12A1 1353 1452 Meteorological Tower, 0.9 mi. WSW Site Boundary. 0.2 mi. W St. Joseph's Villa, 0.4 mi. WNW DR15 1551 Beach west of intake, 0.3 mi, NW I DR16 DR17 1652 SE2 Site Boundary. 0.3 mi. NNW Calverton, 4.5 mi. E ; DR17 SD3 Wildwood State Park, 3.1 mi. E I DR18 DR19 DR20 6El 7El 8E1 LILCO R0W, 4.8 mi. ESE Calverton, 4.9 mi. SE Calverton, 4.4 mi. SSE l i I DR21 DR22 9El 10E1 Brookhaven National Laboratory, 5.0 mi. S Ridge Substation, 4.0 mi. SSW DR23 11El LILC0 R0W, 4.7 mi. SW DR24 12D1 North Shore Beach Substation, 3.7 mi. WSW DR25 13E1 Longview Ave, and Rocky Point Landing Rd. 4.5 mi. W DR26 501 Wildwood State Park, 3.4 mi. E DR27 SF3 Dairy Farm, 7.8 mi. E DR28 781 Overhill Road, 1.4 mi. SE I DR29 12G2 Flowerfield Substation, 15.4 mi. WSW DR30 12G1 Central Islip Substation, 19.9 mi. WSW DR31 11G1 MacArthur Substation, 16.6 mi. SW DR32 8G1 Wading River Road,10.1 mi. SSE I DR33 DR34 DR35 6G1 6Al 2A3 Hampton Bays Substation, 19.0 mi. ESE Sound Road 0.7 mi. ESE Nearest Residence, 0.3 mi. NNE East Gate SNPS, 0.3 mi. S DR36 952 DR37 503 Wildwood State Park, 3.1 mi. E 46
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I I I . I I l I I I APPENDIX D ANALYTICAL PROCEDURES SYNOPSIS I I I . j 4 I ' ) ' i I I ' 89 4
ANALYT! CAL PROCEDURES SYN 0PSIS Appendix 0 is a snyopsis of the analytical procedures performed on samples collected for the Shoreham Nuclear Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed , I upon by Long Island Lighting Company and Teledyne Isotopes and include those recommended by the USNRC Branch Technical Position, Rev. 1, November 1979. ANALYSIS TITLE PAGE G r o s s B e t a An a l y s i s o f S am p l e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 Precipitation........................................................ 91 Ai rb o r ne P a r t i c u l a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 3 Analysis of Samples for Tritium........................................... 94 Water................................................................ 94 An alysi s of Sampl es for St ront i um-89 and -90. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 95 Total Water.......................................................... 95 Milk................................................................. 95 Soil and Sediment.................................................... 95 Organic Solids........... ........................................... 96 Air Particulate..................................................... 96 Analysis of Samples for Iodine-131........................................ 98 Milk or Water........................................................ 98 G amma Sp ec t r ome t ry o f S am p l e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 9 Milk and Water....................................................... 99 l Oried Solids other than Soils and Sediment. . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Fisn................................................................. 99 Soils and Sediments.................................................. 99 i Ch arcoal Cartridges ( Ai r Iodi ne) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 ( Ai rbo r n e P a r t i c u l a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 9 E n v i ro nme nt a l Do s i me t ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101 90
DETERMINATION OF GROSS BETA ACTIVITY IN WATER. SAMPLES
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 as measured by a conductivity meter. 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 and 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 l l efficiency caused by the residue mass. l l 91
I l 1 l l 2.0 DETECTION CAPABILITY l Detection capability depends upon the sample volume actually represented on the planchet, the background and the efficiency of the counting instrument, j 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. 1 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 the 2.83 sigma level), assuming tnat I liter of sample is used and that 1/2 gram of sample residue is mounted on the planchet. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively. These figures are based upon a 200 minute counting time and upon a representative efficiency of 0.02 and a background of 0.1 cpm. The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorp' ion. At a zero mount weight, the 4.66 sigma j I MDL for gross beta is 0.9 picocuries per liter. These values reflect a beta l l counting efficiency of 0.38 and an alpha counting efficiency of 0.18. I i 1 I l l - - - 92 l
GROSS BETA ANALYSIS OF SAMPLES Air Particulate Af ter a delay of five or more days, allowing for the radon-222 and r# c,i-220 (thoron) daughter products to decay, the filters are counted'in a gas-flow proportional counter. An unused air particulate filter, supplied by LILCO, 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) - (8/t))/(2.22 V E) 3 2 2 TWO SIGMA ERROP (pC1/m )
= 2((S/T ) + (8/t ))1/2 (2.22
/ V E)
LLD (pCi/m3 ) = 4,66 (81/2)/(2.22 vet) where: S = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Number of minutes sample was counted , i I t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) } l 93
ANALYSIS OF SAMPLES FOR TRTTTUM Water l Approximately 2 ml of water are converted to hydrogen by passing the water, heated.to its vapor state, over a granular zinc conversion column heated to 400* C. The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure.
~ The proportional detector is passively shielded by lead e steel and an electronic, anticoincidence system provides additional shielding from cosmic rays.
Calculation of the results, the two sigma error and the lower limit detec-tion 'LLD) in pCi/f: RESULT = 3.234 TNYN(Cg - B)/(CN Y) S TWO SIGMA ERROR =2((Cg + B)at) / 3.234 T g V N /((CNYS)(C g-B)) LLO = 4.66 (3.234)T N NY G(C ) / /(ot C N Y) S where: T N
= tritium units of the standard ,
3.234 = conversion f actor changing tritium units to pCi/l V = volume of the standard used to calibrate the ' N efficiency of the detector in psia V = volume of the sample loaded into the detector in psia S C N
= the cpm activity of the standard of volume VN C
G
= the gross activity in cpm of the sample of volume V3 and the detector volume B = the background of the detector in cpm At = counting time for the sample l
i l 94
ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 I Water Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO nitric acid. A barium scavenge and an iron (ferric hydroxide)3)2 using scavenge are i performed followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrC03 from ] the sample after yttrium separation. Th i planchetandiscoveredwithan80mg/cm}sprecipitateismountedonanylon aluminum absorber for low level beta counting. ,
)
l Milk Stable strontium carrier is added to 1 liter of sample and trichlor-acetic acid (TCA) is added to produce a curd. The curd is separated by filtration and is discarded. An oxalate precipitation is performed on the filtrate and the precipitate is ashed in a muffle furnace. The ash is I dissolved and strontium is precipitated as SrN0 l acid. A barium chromate scavenge and an ferric iron (3 using fming hydroxide) (90%) nitric scavenge i are then performed. Stable yttrium carrier is added and the sample is f allowed to stand for 7 to 10 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipi-tating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Soil and Sediment The sample is first dried under heat lamps and a 10 gram aliquot is l t ak en . Stable strontium carrier is added and the sample is leached in nitric acid. The mixture is filtered and the liquid portion is reduced in l volume by evaporation. Strontium is precipitated as Sr(NO3)2 using feing (90%) nitric acid. A barium chromate scavenge and an iron (ferric l hydroxide) scavenge are then performed. Stable yttrium carrier is added and j the sample is allowed to stand for 7 to 10 days for yttrin ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is ; counted in a low level beta counter to infer Sr-90 activity. Strontium-89 j activity is determined by precipitating SrC03 from the sample af ter i yttrium separation. This precipitate is mounted on a nylon planchet and is I covered with an 80 mg/cm2 aluminum absorber for low level beta counting. 95
l l l Organic Solids l A 200g wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in nitric acid. The sample is filtered and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO3 )2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitate as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. Thig precipitate is mounted on a nylon planchet and is a covered with an 80 mg/cm aluminum absorber for low level beta counting.
)
i Air Particulate ) l Stable strontium carrier is added to the sample and it is leached in l nitric acid to bring deposits into solution. The mixture is then filtered j and the filtrate is reduced in volume by evaporation. Strontium is precipi- ' j tated as Sr(NO3 )2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then l precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontiurn-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 ' mg/cm2 aluminum absorber for level beta counting. ' Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/ volume or pCi/ mass: RESULT Sr-89 = (N/4t-BC~0 A )/(2.22 V Y3 0F SR-89 SR-89) TWO SIGMA ERROR Sr-89 = 2((N/At+B C A +0 )/4t)/ /2 (2.22 V3 Y 0F SR-89 ESR-89) LLD Sr-89 = 4.66((BC+B A )/At)l/2 /(2.22 V Y3DF SR-89 ESR-89) RESULT Sr-90 = (N/At - B)/(2.22 V Y3 Y2 0F IF E) TWO SIGMA ERROR Sr-90 = 2((N/4t+B)/At) / /2 (2.22 V Y i Y2 DF E IF)) LLO Sr-90 = 4.66(0/At)l/2 /(2.22 V Y y Y2 IF DF E) l ! 96
where: N = total counts from sample (counts) At. = counting time for sample (min) B = background rate of counter (cpm) using absorber configuration C 2.22 = dpm/pCi V = volume or weight of sample analyzed Bg = background addition from Sr-90 and ingrowth of Y-90 B A = 0.016 (K) + (K) EY/ abs)(I6Y-90) Y 3
= chemical yield of strontium DF = decay factor from the mid collection date to the counting SR-89 date for SR-89 E = efficiency of the counter for SR-89 with the 80 mg/cm.sq.
SR-89 aluminum absorber 9 K
= (N/At - B )Y-90 C
/
(EY-90 IF Y-90 DFY-90g) Y 0F = the decay factor for Y-90 from the " milk" time to the Y-90 mid count time E = efficiency of the counter for Y-90 l Y-90 IF = ingrowth factor for Y-90 from scavenge time to milking time Y-90 IG = the ingrowth factor for Y-90 into the strontium mount from Y-90 the " milk" time to the mid count time. 0.016 = the efficiency of measuring SR-90 through a No. 6 absorber E = the efficiency of counting Y-90 through a No. 6 absorber Y/ abs B = background rate of counter (cpm) I Y i = chemical yield of yttrium Y 2
= chemical yield of strontium l
J DF = decay factor of yttrium from the radiochemical milking time to i the mid count time E = efficiency of the counter for Y-90 IF = in rowth f actor for Y-90 from scavenge time to the radiochemical' mi king time j 97
)
1 _ ____ _ __ _ ______ _. I
ANALYSIS OF SAMPLES FOR 10 DINE-131 I Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. l A batch treatment with anion exchange resin is used to remove iodine from the
~
sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamines hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into I sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode. I Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/f: RESULT = (N/6t-B)/(2.22 E V Y DF) TWO SIGMA ERROR = 2((N/6t+B)/6t) (2.22 E V Y DF) LLD = 4.66(B/6t)1/2 /(2.22 E V Y DF) where: N = total counts from sample (counts) 6t = counting time for sample (min) B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date E = efficiency of the counter for 1-131, corrected for self absorption effects by the formula E = E (exp-0.0061M)/(exp-0.0061Ms ) s E 3
= efficiency of the counter determined from an 1-131 standard mount M = mass of PdI2 on the standard mount, mg M = mass of PdI2 on the sample mount, mg I
98
s l GAMMA SPECTROMETRY OF SAMPLES Milk and Wster A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a I shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Dried Solids Other Than Soils and Sediments , A large quantity of the sample is dried at a low temperatur e, less than 100*C. As much as possible (up to the total sample) is loaded into a tared I 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. Fish As much as possible (up to the total sample) of the edible portion of I the sample is loaded into a tared 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. Soils and Sediments Soils and 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 I shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. I Charcoal Cartridges ( Air Iodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of j the Ge(Li) The detector. detection Each Ge limit for I-131(Li) detector is calibrated for both positions, of each charcoal cartridge can be determined { (assuming no positive I-131) uniquely from the volume of air which passed I through it. In the event 1-131 is observed in the initial counting of a ) I set, each charcoal cartridge is then counted separately, positioned on the face of the detector. j 1 Air Particulate ! 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- l based data acquisition system which performs pulse height analysis. l 99
I 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 efficiency, and net counts in the peak region. The calculation of results, two = sigma error and the lower limit of detection (LLD) in pCi/ volume or pCi/ mass: RESULT = (S-B)/(2.22 t E V F DF) TWO SIGMA ERROR = 2(S+B) /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 (reti of spectrum of interest) B = Background area, in counts, under sample peak, deter-mined 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 100
I ENVIRONMENTAL 00SIMETRY I Teledyne Isotopes uses a CaSO4:Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light 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. I 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): l RESULT = 0 = ( Dy+D 2 +0 3 4 +D )/4 TWOSIGMAERROR=2((D-D)2+(D-0)2+(0-D)b(D-D)2)/3) y 2 3 4 where D y = the net mR of area 1 of the TLD, and similarly for D ,2 D , 3and D 4 j D y =1 7 K/Ry-A ly = the instrument reading of the field dose in area 1 K = the known exposure by the Cs-137 source J ( R y
= 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 l
l lI 101
lI i I I ' I I I I I APPENDIX E
SUMMARY
OF EPA INTERLABORATORY COMPARISONS I I (! . I lI lI I I 102
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US EPA CROSS-CHECK-PROGRAM 1988 i Collection. . Teledyne Date Media Nuclide EPA P.asul t(a) Isotopes Result (b) 01/08/88 Water Sr-89 .30.00 i 5.00 27.33
- 0.58 Sr 90 15.00
- 1.50 16.00
- 1.00 01/22/88 Water Gross Alpha 4.00
- 5.00 3.67 i 0.58 4 Gross Beta 8.00
- 5.00 8.33 i 0.58 )
i 01/29/88 Food Sr 89 46.00
- 5.00 40.67 i 2.52 -{
(c) Sr-90 55.00 i 2.75 54.33
- 3.79 . j I 131 102.00 i 10.20 85.67
- 5.13 (d)
Cs-137 91.00 t 5.00 '98.67 i 7.64 (e) K 1230.00
- 61.50 1210.00
- 151.00 02/05/88 Water Co-60 69.00
- 5.00 65.00
- 2.65 Zn-65 94.00
- 9.40 91.00 i 4.36 Ru 106 105.00 i 10.50 89.00
- 7.94 (f)
'Cs-134 64.00
- 5.00 55.00 i 5.29 (g)
'Cs-137 94.00 i 5.00 91.00 i 3.61 02/12/88 Water H-3 3327.00
- 362.00 3266.67
- 57.73 02/26/88 Milk 1-131 4.00
- 0.40 4.33
- 0.58 03/18/88 Water Gross Alpha 6.00 i 5.00 4.00 i 0.00 Gross Beta 13.00
- 5.00 15.67 i 0.58 03/25/88 Air Filt. Gross Alpha 20.00
- 5.00 24.00
- 0.00 Gross Beta 50.00 i 5.00 46.33 t 1.15 Sr-90 17.00 i 1.50 17.00
- 0.00 Cs-137 16.00 1 5.00- 16.33 i 0.58 03/31/88 Water Ra 226 7.60
- 1.14 7.30
- 0.17 Ra-228 7.70 i 1.16 12.00
- 0.00' (h) 04/08/88 Water I 131 7.50 i 0.75 8.67 1 0.58 (i) 04/24/88 Lab Performance - Sample A Water Gross Alpha 46.00 1 11.00 70.67
- 0.58 (j)
Ra-226 6.40 i 0.96 6.63 i 0.12 Ra-228 5.60
- 0.84 6.10
- 0.20 04/24/88 Lab Performance - Sample B l Water Gross Beta 57.00
- 5.00 67.67
- 2.08 (k)
Sr-89 5.00 i 5.00 4.67
- 0.58 Sr-90 5.00 i 1.50 5.00
- 0.00 Co-60 50.00 i 5.00 53.00
- 2.00 Cs-134 7.00 i 5.00 8.33 i 1.15 Cs-137 7.00 1 5.00 9.00 i 1.00 i 103
US EPA CROSS-CHECK PROGRAM 1988 (Cont.) I Collection . Teledyne Date Media Nuclide EPA Result (a) Isotopes Result (b) 05/06/88 Water Sr-89 20.00
- 5.00 16.67 i 2.08 Sr-90 20.00 1.50 19.67
- 1.15 1 05/20/88 Water Gross Alpha 11.00
- 5.00 4.67
- 0.58- (1 )
Gross Beta 11.00
- 5.00 13.67
- 0.58 ;
06/03/88 Water Cr 51 302.00
- 30.00 313.67 i- 20.31- '
Co-60 15.00
- 5.00 18.00
- 2.00 Zn 65 . 101.00 i 10.00 109.33
- 10.50 Ru-106 195.00
- 20.00 184.67 i 20.03 Cs-134 20.00
- 5.00 19.33 i 2.C3 Cs-137 25.00
- 5.00 30.33
- 7.55 06/10/88 Water H-3 5565.00 i 557.00 5900.00 i 199.99 06/17/88 Water Ra-226 10.00
- 1.51 10.60 0.40 Ra 228 12.40
- 1.86 9.97
- 0.06 (m) 06/24/88 Milk Sr-89 40.00 i 5.00 36.33 i- 2.52 Sr-90 60.00 i 3.00 61.00
- 2.00 1-131 94.00
- 9.00 101.67
- 7.64 Cs-137 51.00
- 5.00 53.67
- 3.06 K 1600.00
- 80.00 1656.67
- 55.07 07/22/88 Water Gross Alpha 15.00 1 5.00 8.33
- 0.58 (n)
Gross Beta 4.00
- 5.00 6.00
- 0.00 07/29/88 Food I-131 107.00
- 11.00 103.33 1 11.55 Cs-137 49.00
- 5.00 51.33
- 2.52 K 1240.00
- 62.00 1220.00
- 34.64 08/05/88 Water I-131 76.00
- 8.00 86.00 2 2.65 Co) 08/26/88 Air Fil Gross Alpha 8.00 5.00 9.33 i 0.58 Gross Beta 29.00
- 5.00 25.67
- 1.53 Sr-90 8.00
- 1.50 7.67
- 0.58 Cs 137 12.00 i 5.00 11.00 i 1.00 !
09/16/88 Water Ra-226 8.40 i 1.30 8.70 i 0.26 Ra 228 5.40
- 0.80 5.83 i 0.32 09/23/88 Water Gross Alpha 8.00
- 5.00 9.00
- 0.00 Gross Beta 10.00
- 5.00 11.33
- 0.58 104
I US EPA CROSS-CHECX PROGRAM 1988 (Cont.) I Collection Teledyne Date Media Nuclide EPA Result (a) Isotopes Result (b) 10/07/88 Water Cr 51 251.00 t 25.00 236.00
- 29.21 I Co 60 Zn 65 Ru 106 25.00
- 151.00 1 152.00 1 5.00 15.00 15.00 28.00 t 165.67 1 159.67 i 0.00 5.51 12.22 I Cs 134 Cs-137 25.00
- 15.00
- 5.00 5.00 27.67 i 17.33
- 1.53 3.06 10/14/88 Water H-3 2316. 0
- 350.00 2300.00 i 100.00 10/18/88 Lab Performance - Sample A Water Gross Alphd 41.00
- 10.00 38.67 i 1.15 Ra 226 5.00
- C.80 5.67
- 0.15 I" Ra 228 5.20
- 0.80 5.27 1 0.06 10/18/88 Lab Performance - Sample B I Water Gross Beta Sr 89 54.00 i 11.00 1 5.00 5.00 53.33 1 8.67 1 2.52 0.58 Sr 90 10.00 1 1.50 9.00 0.00 I Cs-134 Cs 137 15.00 15.00
- 5.00 5.00 15.67 1 16.33 1.15 3.21 10/28/88 Milk I Sr-89 Sr-90 I-131 40.00
- 60.00 1 91.00 t 5.00 3.00 9.00 28.33 1 52.00 t 87.67 i 0.58 3.46 1.15 (p)
(p) Cs-137 50.00
- 5.00 51.33 t 1.53 g K 1600.00
- 80.00 1578.33 t 23.63 11/25/88 Water Gross Alpha 9.00 t 5.00 .
10.00 1 0.00 Gross Beta 9.00 t 5.00 11.00
- 1.00 12/09/88 Water I 131 115.00
- 12.00 106.67
- 5.77 I 12/11/88 Water Ra-226 Ra-228 4.80
- 5.30
- 0.72 0.80 5.20 i 4.93 t 0.35 0.49 I
I I I I l 105
US EPA CROSS-CHECK PROGRAM 1988 (Cont.) Notes: I. (a) EPA Rc3ults-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) TeleGjne 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 filters. (c) Units for food analysis are pC1/kg (wet) except K 40 which is mg/kg, (d) The average result of E6 pCi/kg was lowered by one analysis of 80 pCi/kg, in which I-131 may have been lost in processing. If this analysis is discarded and the higher results of the other 2 aliquots are taken, the average becomes 94 pCi/kg which is more favorable (-1.1 sigma for 2 determinations). Our investigation revealed no systemic reason for the low I-131 (-2.77 sigma for 3 determinations). Moreover. our previous performance for this analysis shows no systemctic bias. (e) There is no apparent reason for the deviation. Although there is a bias high, the bias does not appear to be changing significantly. Starting with the 01/13/86 data, the ratio of the average TI results to the EPA result is 1.27. 1.10, 1.08 and 1.15. (f) The Ruthenium-106 results (as well as other isotopes in the EPA sample) for the February 5. 1988. EPA sample were based On a new standard ' (Amersham) used in tne December 1987 annual calibrations. A I calculation using the previous NBS standard efficiencies gave an average of 99.0 pCi/ liter having a normalized deviation of second Amersham standard in 1.1E. a Marinelli was prepared and agreed with A the NBS standard. These efficiencies are in use' currently. (g) fhe Cesium-134 results (as well as the other isotopes in the EPA sample) for the February 5, 1988. EPA sample were based on a new I standard (Amersham) used in the December 1987 annual calibrations. calculation using the previous NBS standard efficiencies gave an average of 60.2 pCi/ liter having a normalized deviation of -1.80. A A I second Amersham standard in a Marinelli was prepared and agreed with the NBS standard. These efficiencies are in use currently. (h) The samples were analyzed for R3-228 by PRO-032-67. A new procedure (PRO-032-97) has been formalized and is currently in use for all samples. The results using the new procedure gave 6.2 1.4 pCi/ liter - (i) An investigation was conducted and there is no apparent reason for the deviation. The samples contained an unusually high concentration of stable iodide (3.6 mg/ liter) as determined by electrode readings whicn was verified at that time. The chemical yields were properly calculated taking these readings into account. No corrective action is necessary since these results fall within the EPA 3 sigma control lin,its and no trends on previous I-131 interccmparison results are I evident. 106
y I I l 1 US EPA CROSS-CHECK PROGRAM 1988 (Cont.) Notes: (Cont.) (j) Dr. Frank Novielli of the EPA states that the EPA takes energy correction into account. He mailed us a document which indicates how I this is achieved. Teledyne Isotopes has implemented the EPA method for { cnergy correction, j (k) High concentration of Co-60 in the sample (50 pCi/1) resulted in false beta counts on the Tennelec counters from Co-60 gamma. Dr. Frank j Novielli of the EPA stated that the EPA will discontinue using Co 60 in ; Performance Evaluation samples (effective October 1988) because of this l problem. ' (1) Low alpha caused by presence of chlorides in the sample residue which I increases self-absorption. Samples are now being evaporated with more nitric acid to convert chlorides to nitrates. f all within the EPA 3 sigma control limits. These reported results i l 1 (m) The investigation revealed no apparent reason for the reported low value: the result is within the EPA 3-sigma acceptance region. The new rapid extraction method Or Ra-228 has provided acceptable results for all of the last 7 EPA tests. (n) The deviation noted is due to unusually high self-absorption I characteristics of EPA water spikes. Our results and the midwest laboratory, each independently calibrated with Am-241, obtained low results by the same margin. Corrective actica involves applying the self-absorption curve derived by our analysis of EPA water in 1976 fl Collaborative Study (solid line) instead of the line) when calculating EPA cross-check samples. usual curve (dashed s l *: ' l [ E . ... ... ... .. ..
~
grams residue (o) Faulty stable iodide yield correction, probably caused by a chemical in the sample which interferes with the iodide electrode. The hign electrode reading was verified by repeating several times. Without l yield correction our average result would have been 77 pCi/1. Ihis is in the EPA 3 sigma control limit. l I 107 l L-__-__. >
US EPA CROSS-CHECK PROGRAM 1988 (Cont.) J I (p) Possible loss of radiostrontium in the initial TCA separation step. Another possibility. The presence of calcium on the final Strontium mount, has been ruled out by an experiment in which the strontium mounts were repurified and recounted, giving the same results as I originally found. An experiment with direct ashing (EML method) and with ion exchange (EPA method) as alternatives to the TCA separation i step is being explored. This study includes an experiment in which j spiked milk samples are stored for several weeks before analysis in order to determine whether radiostrontium becomes bound to the protein or fat components of the milk. I , I g I I I I 108 I a
)
1 I I 3 APPENDIX F REMP SAMPLING AND ANALYTICAL EXCEPTIONS I 109
I Program Exceptions I Direct Radiation A direct radiation location was identified which was not in compliance with SNPS Technical Specification Table 3.12.1-1. Location 503 was located only 5 kilometers from the plant when it should have been between 6 and 8 kilometers distant. A new TLD was located at 7.2 kilometers from the plant and all remaining REMP locations were investigated to ensure that the Technical Specification requirements are being met. Airborne Airborne radiciodine and particulate samples were not available from June 30, 1987 to June 21, 1988, at Technical Specification location 652 due to frequent motor f ailure as a result of inadequate power supply. The equipment was out of service for an extended period due to scheduling of the I. modification to power cables. Sampling was restaned on June 21, 1988, following completion of that modification. Lost and unavailable samples are reported in Tables F-1 through F-8. I I I , I 110 _ _ _ _ _ _ _ _ _ _ - _ _ D
TABLE F-1 REMP EXCEPTIONS FOR SCHEDULED FISH SAMPLING AND ANALYSIS DURING 1988 Date of Reason (s) for Loss / Location Description Sampling Exception I Various Fish Samples collected did not meet specified amount; however, all required analyses were performed. Sea Robin 05/24/88 Collected: 0.5 Kg; I 3C1 Required: 1.2 Kg I SC1 Sea Robin 10/27/88 Collected: 0.9 Kg; Required: 1.2 Kg 14C1 Sea Robin 10/26/88 Collected: 0.1 Kg; ! Required: 1.2 Kg I 14C1 Windowpane 10/26/88 Collected: 0.4 Kg; Required: 1.2 Kg l { l l 13G2 Sea Robin 11/04/88 Collected: 0.4 Kg Required: 1.2 Kg I l l 1 11)
l J TABLE F-2 I REMP EXCEPTIONS FOR SCHEDULED INVERTEBRATE SAMPLING AND ANALYSIS DURING 1988 ) I l Date of Reason (s) for Loss / Location Description Sampling Exception J I 3Cl Whelk None available 05/24/88 3 1 Various Invertebrates Samples collected did I not meet specified I amount; however, all required analyses i l were performed. l 13G2 Whelk 06/10/88 Collected: 0.6 Kg { Required: 1.2 Kg 14C1 Lobster 10/26/88 Collected: 0.6 Kg Required: 1.2 Kg 13G2 Whelk 11/10/88 Collected: 0.35 Kg Required: 1.2 Kg I l I I l l l 112 1 _ - _ _ _ _ _ _ _ _ _ _ . l
TABLE F-3 ) REMP EXCEPTIONS FOR SCHEDULED AIRBORNE 4 PARTICULATE SAMPLING AND ANALYSIS DURING 1988 j Date of Reason (s) for Loss / location Description Sampling Exception 1 652 Particulate Filter 01/05/88- Power failure ) 06/21/88-SD3 01/19/88- Vacu m pep failure; however, 01/26/88 filter was collected. Sample volume was lower than normal . ! 8A3 02/23/88- Vacu m p ep failure; however, , 03/01/88 filter was collected. Sample volume was lower than i normal. 351 03/22/88- Power cut-off so that new 06/21/88 cable to 351 and 6S2 could be installed. 7A2 04/12/88- Power feed to air monitor 05/17/88 burned out. 2A3 10/04/88- Power feed to air monitor 10/10/88 disrupted due to ground fault. Particulate filter collected during both weeks; however, sample volume was lower than normal.
)
i 113
TABLE F-4 REMP EXCEPT10NS FOR SCHEDULED AIR 80RNE 10 DINE SAMPLING AND ANALYSIS DURING 1988 Date of Reason (s) for Loss / Location Description Sampling Exception 652 Canister 01/05/88- Power failure. 06/21/88
.503 01/19/88- Vacuum pump f ailure, however, 01/26/88 canister was collected.
Sample volume was lower than normal. 8A3 02/23/88- Vacuum pump f ailure; however, 03/01/88 canister was collected. Sample volume was lower than normal. 3S1 03/22/88- Power cut-off so that new 06/21/88 cable to 3S1 and 652 could be installed. 7A2 04/12/88- Power feed to monitor 05/17/88 burned out. 2A3 10/04/88-
- Power feed to monitor 10/18/88 disrupted due to ground fault. Canister collected during both weeks, however, sample volume was lower than normal.
114
TABLE F-5 REMP EXCEPTIONS FOR SCHEDULED MILK SAMPL1NG AND ANALYSIS DURING 1988 I Date of Reason (s) for Loss / ; Location Description Sampling Exception i 6B1 Goat Milk 01/11/88- Goats dried up until 04/14/88 10/20/88 then removed from residence. I 6B2 Goat Milk 01/11/88-02/11/88 Supplier moved. longer available. Samples no 8F2 Goat Milk 01/11/88- Goats dried up for kidding. 04/14/88 1381 Goat Milk 04/14/88- Goats dried up for kidding. 05/12/88 8F2 Goat Milk 06/23/88 No sample available. I l 4 I l I I 1 I u5 y
TA8LE F-6 REMP EXCEPT:0NS FOR SCHEDULED FOOD PRODUCTS SAMPLING AND ANALYSIS DURING 1988 Date of Reason (s) for Loss / Location Description Sampling Exception 8B1, SC2, Lettuce, Cabbage, 05/24/88 Not available: Too early 12H1 Carrots, Spinach, in the season. Radishes, Beets and Onions SC2 Lettuce, Cabbage, 08/18/88 Not locally grown. Carrots, Spinach, Radishes and Beets 12H1 Lettuce, Cabbage, 08/18/88 Not available: Farm Spinach, Carrots, stand closed. Radishes and Beets 881 Lettuce, Cabbage 08/18/88 Not available. Spinach, Carrots and Radishes 12H2 Spinach, Carrots, 08/18/88 Not locally grown. Radishes and Beets 881 Lettuce 08/25/88 Not locally grown. SC2 Lettuce, Cabbage 08/25/88 Not locally grown. and Onions 12H1 Cabbage and Onions 08/25/88 Not locally grown. l ) 5F2 Onions 08/25/88 Not locally grown. 783 Lettuce. 08/25/88 Not locally grown. Potatoes and Onions 116
TABLE F-7' REMP EXCEPTIONS FOR SCHEDULED POTABLE WATER SAMPLING AND ANALYSIS OURING 1988 Date of Reason (s) for Loss / Location Description Sampling Exception 1352 Ground Water 06/15/88 Well dry'- apparently due to change in water table. 1352 Ground Water 09/15/88 Well dry. 1352- Ground Water 12/08/88 Well dry. 6B1 Ground Water 12/08/88 Supplier not at home. , a f 117
TABLE F-8 REMP EXCEPTIONS FOR SCHEDULED TLD* SAMPLING AND ANALYSIS DURING 1988 Date of Reason (s) for Loss / Location Description Sampling Exception 8G1 Monthly and 07/06/88 Lost in transit. Quarterly 11El Monthly and 07/06/88 Vandalized Quarterly 11El Monthly and 01/05/89** Vandalized Quarterly l I i l l l l l l Thermoluminescent Dosimeter measuring direct radiation.
** Fourth quarter 1988 TLD ,
l l l l l 118 L_--------------
I I-I I 1 1 i APPENDIX G SNPS LAND USE SURVEYS I I : I l 119 l
SNPS LAND USE CENSUS OPERATIONAL I The operational program complies with Section 3/4.12.2 of SNPS Technical Specifications. greater than 50m 2 (500 f tc) producing broad leaf vegetation within aThis reqyires a su radial distance of 8 Km (5 miles). LILC0 is also required to identify the nearest milk animal, residence and garden in each of the 16 meteorological sectors. Environmental Engineering Department conducted the 1988 dairy animal census, during April through July. This survey was done by Environmental I . 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 1988 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:
- 1. Sector 13, 1.9 miles west of SNPS Poole Briarcliff Road Shoreham, New York 11786 REMP Monitoring Location 1381 Inventory: 2 milking goats 1 non-milking goats Inventory Date: June 13, 1988 I 2. Sector 11, 2.40 miles southwest of SNPS Shoreham-Wading River School District i I Middle School Randall Road Shoreham, New York 11786 I
I REMP Mor'itoring Location 11C1 (Milk not being sampled due to 4 owners decision not to participate). I Inventory: 3 milking goats 1 non-milking goats I j Inventory Date: July 1, 1988 1 i 120 1
I Table G-1 lists the nearest milk animal in the sixteen meteorological I 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 1988 census was performed during July, August, September and October locating a total of 332 gardens. Table G-2 lists the nearest garden in the sixteen meteorological sectors. The field survey sheets and maps are filed at Environmental Engineering Melville. and in the Shoreham Record Retrival System. Environmental Engineering identifies nearest residences by utilizing I both aerial photography and visual confirmation. This year's census was conducted in December. Table G-3 lists the nearest residence in each meteorological sector. I i 1 1 l i l J I l I 121
I Table G-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1988 Land use Census Nearest Milk Animal (within 8 km)* Sector Direction Location 1 N Area within sector is Long 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 C. 8. Poole Residence, Briarcliff Road, Shoreham 14 WNW None 15 NW Area within sector is Long Island Sound 16 NNW Area within sector is Long Island Sound I
- SNPS Technical Specification 3/4 12.2 1
l 122 __.---_mm_..__.mm _ . - _ _ . .
I i 1 Table G-2 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1988 Land usg Census Nearest Garden (> 50m4 within 8 km)* I. Sector Direction Location 1 N Area within sector is Long Island Sound 2 NNE None 3 NE None 4 ENE Mueller, Beach Lub Lane, Wading River, 6217' ENE of SNPS. 5 E Loggia, Little Bay Road, Wading River, J 3978' E. of SNPS. 6 ESE Punda, Sound Ave., Wading River, 4343' ESE of SNPS. 7 SE Groffman, North Country Road, Wading River, 4133' SE of SNPS. 8 SSE Pierzchanowski, Sound Ave., Wading River 6300' SSE of SNPS. 9 S Smith, Randall Road, Wading River, 6027' S of SNPS. 10 SSW Follmann, Defense Hill Road, Shoreham, 4907' SSW of SNPS. 11 SW Utley, Royal Way, Shoreham, 6124' SW of SNPS. 12 WSW Menszak, Royal Way, Shoreham, 6124' WSW of SNPS. 13 W Chaimowitz, Mary Pitkin Path,, Shoreham, 7458' W of SNPS. 14 WNW None 15 NW Area within sector is Long Island Sound I 16 NNW Area within sector is Long Island Sound
- SNPS Technical Specification 3/4 12.2 I
123 . l
RADIOLOGICAL ENVIRONMENTAL MON 1TORING PROGRAM (REMP) 1988 Land use Census Nearest Residence (within 8 km)* Sector Direction Location / Distance from SNPS l 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 (fif th house west of Riverhead i 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 Drive, Wading River, 3304' from SNPS 8 SSE North Country Road, fourth house west of Pheasant Run, Wading River, 2588' from SNPS 9 S Fugelsang- 20 Long Bow, Wading River, 3839' from SNPS 10 SSW Fo11mann- 16 Defense Hill Road, Wading River, 4877' from SNPS 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 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
- SNPS Technical Specification 3/4 12.2 124
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APPENDIX H COMMON AND SCIENTIFIC NAMES OF { SPECIES COLLECTED IN THE REMP I I i I t I I I I 125
Table H-1 l COMMON AND SCIENTIFIC NAMES OF SPECIES COLLECTED i fN 1HE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
. Common Name Scientific Name Fish l l
Winter Flounder Pseudopleuronectes americanus ) i Windowpane Scophthalmus aquosus 1 Sea Robin Prionotus spp. Little Skate Raja erinacea Invertebrates A:.2rican Lobster Homarus americanus Squid Loligo pealeii Blue Mussel Mytilus edulis Channeled Whelk Busycon canaliculata i Soft-Shell Clam Mya arenaria _ Algae f l Fucus sp. Ulva lactuca i Enteromorpha sp. l Polysiphonia sp. Chondrus crispus I l Scytosiphon lomentaria Codium sp. ! Ascophyllum sp. I l _G ame Raccoon Procyon lotor ! l Eastern Gray Squirrel Sciurus carolinensis l 126 L , i 1
s I I I APPENDIX I 1987 ERRATA I I I 127 I - _ - - _ _ _ - _ - _ _ _ _ _ _ -
Revised 1987 Data - Rev. 3, April 1989 Table G-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1987 Land us Census Nearest Garden (> 50mg within 8 km)* j Sector Direction Location 1 N Area within sector is Long Island Sound 2 NNE None i 3 NE None 4 ENE Lapham, Central Rd., Wading River, 4150' ENE of SNPS. 5 E Loggia, Little Bay Rd., Wading River, 3978' E. of SNPS. 6 ESE Rhodes, Overlook Dr., Wading River, 6477' ESE pf SNPS. 7 SE Groffman, Randall Rd./No. Country Rd. Wading River, 4133' SE of SNPS. 8 SSE Pierzchanowski, Sound Avenue, Wading River, 6300' SSE of SNPS 9 S Kwasnisky, Randall Rd., Wading River 6324' S of SNPS. 10 SSW Fo11mann - 16 Defense Hill Rd., Shoreham, 4907' SSW of SNPS. 11 SW Schmidt, 25 Jomar Rd. Shoreham, N.Y.-7510' SW of SNPS. 12 WSW Menszak - 9 Royal Way, Shoreham, 6124' WSW of SNPS. 1 13 W Jehle, 2 Fordham Rd. Shoreham, j 6127' W of SNPS. 14 WNW None 15 NW Area within sector is Long Island Sound 16 NNW Area within sector is Long Island Sound
- ShPS Technical Specification 3/412.2 128
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i (Eg'@ j LONG ISLAND LIGHTING COMPANY i g- _ _ .. SHOREHAM NUCLEAR POWER STATION j P.O. DOX 618, NORTH COUNTRY RO AD e WADING RIVER N.Y.11792 l l .) JOHN D. LEONARD, JR. VICE PRESIDENT NUCLEAR OPERATIONS SNRC-1569 APR 2 71989 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Radiological Environmental Monitoring Program Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 s i Gentlemen: Enclosed is a copy of the Shoreham Radiological Environmental ; Monitoring Program (REMP) Annual Report which provides detailed / information for the full 1988 calendar year. Shoreham's Technical Specification 6.9.1.6 requires this report te be submitted prior to May 1. Shoreham was shutdown during all of 1988. If you require additional information, please do not hesitate to contact me. Very truly yours, - i I Ur 0o16 D.'uLeonar , Jr. /
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i ViePresident-NuclgtrOperations GJG/ap En losure l cc: S. Brown W. T. Russell F. Crescenzo [$h
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