JAFP-94-0240, 1993 Radiological Environ Operating Rept Ja FitzPatrick Nuclear Power Plant
| ML20065R405 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/31/1993 |
| From: | Harry Salmon POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| JAFP-94-0240, JAFP-94-240, NUDOCS 9405110175 | |
| Download: ML20065R405 (199) | |
Text
{{#Wiki_filter:,
*- . Jam s A. FitzP: trick Nuclear PIw:t Plant P.O. Box 41 ,
w Lycoming. New York 13093 e l 4 , 315 342-3840 l ^
#> NewYorkPbwer I 4# Authority ""'L"if"j"; " "
s 1 >. April 26, 1994 JAFP-94-0240 j i - United States Nuclear Regulatory Commission l Region 1 l 457 Allendale Roa.. King of Prussia, PA . 5 Attention: Thomas T. Martin , Regional Administrator
SUBJECT:
JAMES A. FITZPA " NUCLEAR POWER PLANT _ONMENTAL OPERATING REPORT FACILITY RADIOLOGICAL ! OPERATING LICENSE DPR-59. DOCKET NO. 50-333 Gentlemen: Enclosed please find the 1993 Radiolocical Environmental Operatine Report which covers the operating period of January 1,1993 through December 31, 1993. This report is submitted in accordance with the requirements of Amendment 93, Section 7.3.d of the James A. FitzPatrick Nuclear Pc' - Plant Technical Specifications. Distribution for this report is in accordance with the .latory Guide 10.1, Revision 4. Very trul > yours, H RRY P. SALMON, JR. HPS:BG:Is Enclosures
~
T cc: DocuinentlControiCenterL Desk -(USNRC)l(18)? 9
" ' ~ ~
J. W. Blake (NYP /WPOf ~~" " W. J. Cahill (NYPA/WPO) J. J. Kelly (NYPA/WPO) J. Toennies (NMPC) H. Flanagan (NMPC) CAC Members T. Carroll J. Sipp ; A. McKeen / ! RES File l WPO Records Management [ l Reference Center RMS (JAF) 1 lh j CERTIFIED MAIL, RETURN RECEIPT IEQUESTED
)
9405110175 931231 : PDR- ADOCK 05000333 { R PDR
~
[ [ CWS Radiological c g) Environmental g3 Operating [ P Report [ E James A FitzPatrick Nuclear Power Plant c .
. ' , ) .
[ '
.anW#""P ?%%q:gK !
a, . j; : g ng s.v . : , , g'7u;c . . y;j lh?
-,m. _
,, .g..m . -
n, uit p iy
- :lip:gc - , te Ei,
;p . .-
*==*+m
% .' 's La .
t 2 4 app p4g..gapu.j. .-* . r p .:. O N ewYorkPower
~ '
& Authority L
_ a
i l { NEW YORK POWER AUTIIORITY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1,1993 - DECEMHER 31,1993 [ FOR ( JAMES A. FITZPATRICK NUCLEAR POWER PLANT FACILITY OPERATING LICENSE DPR-59 DOCKET NUMBER 50-333 [ [ ' [ [ [ c r
TA'BLN OF CONTENTS Eage 1.0 EXECUTIVE
SUMMARY
l-1
2.0 INTRODUCTION
2-1 2.1 Site Description and Background 2-1 2.2 Program Objectives 2-2 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection Methodology 3-7 3.2 Analyses Performed 3-13 3.3 Sample Location Maps and Sample Location Reference Tables 3-14 3.4 Land Use Census 3-24 3.5 Changes and Exceptions to the Program 3-25 3.6 Deviation From the Program 3-26 3.7 Statistical Methodology 3-27 3.8 Compliance with Required Lower Limits of Detection (LLD) 3-32 4.0 SAMPLE
SUMMARY
TABLES IN BRANCII TECIINICAL, 4-1 POSITION FORMAT I 5.0 RESULTS EVALUATION A~ND DISCUSSION 5-1 5.1 Aquatic Program 5-5 5.2 Terrestrial Program 5-22 5.3 Conclusion 5-50 5.4 References 5-52 I i I
TABLE OF CONTENTS (Continued) Pace 6,0 REPORT PERIOD ANALYTICAL RESULT TABLES 6-1 7.0 IllSTORICAL DATA TABLES 7-1 8.0 GRAPIIICAL PRESENTATIONS 8-1 9.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM 9-1 f 9.1 Program Description 9-1 9.2 Program Results 9-1
\
9.3 Nonconformities 9-1 ( l [ [ [ [ t ( ii f r I . _ - _ _ .
LIST OF TABLES Pace Table 3.0-1 Required Sample Collection and Analysis 3-2 Table 3.3-1 Environmental Sample Locations 3-20 Table 3.8-1 Detection Capabilities For Environmental Sample Analysis, 3-33 Lower Limit of Detection (LLD) Table 6-1 Shoreline Sediment Sampling Results 6-2 Table 6-2 Fish Sampling Results 6-3 Table 6-3 Surface Water Composite Results, Tritium 6-6 Table 6-4 Surface Water Composite Results, Gamma Isotopic 6-8 Table 6-5 Off-site Airborne Particulate Filter Results, Gross Beta 6-14 Table 6-6 On-site Airborne Particulate Filter Results, Gross Beta 6-16 Table 6-7 Off-site Airborne 1-131 Results 6-18
~
Table 6-8 On-site Airborne I-131 Results 6-20 l Table 6-9 Particulate Composite Results, Gamma Isotopic 6-22 l Table 6-10 Thermoluminescent Dosimeter Results 6-38 Table 6-11 Milk Results, I-131 6-42 Table 6-12 Milk Results, Gamma Isotopic 6-45 l Table 6-13 Milk Animal Census Results 6-48 Table 6-14 Food Product Results, Gamma Isotopic 6-50 Table 6-15 1993 Residence Census 6-51 Table 9-1 Gross Beta Analysis Airborne Particulate (pCi/m') 9-3 l and Water (pCi/L) Table 9-2 Tritium Analysis of Water (pCi/L) 9-4 l Table 9-3 Iodine Analysis of Water (pCi/L) and Milk (pCi/L) 9-5 Table 9-4 Gamma Analysis of Milk, Water (pCi/L), Airborne Particulate 9-6 (pCi/m 3) and Food Products (pCi/kg) iii
LIST OF FIGURES Pace Figure 3.3-1 New York State Map 3-15 Figure 3.3-2 Off-site Environmental Station and TLD Location Map 3-16 Figure 3.3-3 On-site Environmental Station and TLD Location Map 3-17 Figure 3.3-4 Milk Animal Census, Milk Sample Location and Surface 3-18 Water Sample Location Map Figure 3.3-5 Nearest Residence, Food Product, Shoreline Sediment, 3-19 Fish Sample, Location Map Figure 8.1 Graph - Fish (Cs-137) 8-2 Figure 8.2 Graph - Surface Water Tritium 8-3 Figure 8.3 Graph - Airborne Particulate Gross Beta, Annual 8-4 Figure 8.4 Graph - Airborne Particulate Gross Beta, Weeks 1-26 (1993) 8-5 Figure 8.5 Graph - Airborne Particulate Gross Beta, Weeks 27-52 (1993) 8-6 Figure 8.6 Graph - Airborne Particulate Composite (Co-60) 8-7
~
Figure 8.7 Graph - Airborne Particulate Composite (Cs-137) 8-8 Figure 8.8 Graph - Airborne Radiodine (I-131) 8-9 [ Figure 8.9 Graph - Milk (Cs-137), Annual 8-10 Figure 8.10 Graph - Milk (I-131) 8-11 Figure 8.11 Graph - TLD Data 8-12 L ~ iv
1.0 EXECUTIVE
SUMMARY
l l The Annual Radiological Environmental Operating Report is published pursuant to l Section 7.3.d of the Radiological Effluent Technical SpeciGcations (RETS). The RETS require that the results from the Annual Radiological Environmental Monitoring Program (REMP) be provided to the Nuclear Regulatory Commission (NRC). This report describes the REMP program and its implementation as required by Technical Specifications. It also contains the analytical results, data evaluation, dose evaluation, and data trends for each environmental sample media. Also included are l results of the land use census and the Environmental Laboratories performance in the g Quality Assurance / Quality Control interlaboratory comparisons program required by technical speci6 cations. The REMP is implemented to measure radioactivity in the aquatic and the terrestrial pathways. The aquatic pathways include Lake Ontario Rsh, water, and lake shore sediment. Measurements of the samples representing these pathways were representative of background concentrations. The 1993 results were consistent with the Sve year historical data. I Terrestrial pathways were also evaluated and included airborne particulates and radioiodine, milk, food products and direct radiation. Analysis of all terrestrial radiation pathways demonstrated that there has been no detectable increased radiation levels as a result of plant operation. Again, the 1993 results are consistent with five year historical results. In summary, the analytical results from the 1993 Environmental Monitoring Program demonstrate that the routine operation of the James A. FitzPatrick Nuclear Power Plant had no significant or measurable radiological impact on the environment. The measured concentrations of radionuclides in the off-site environment surrounding the JAFNPP are not increasing as a result of plant operation, in many cases, particularly Esh and airborne particulate activity, this report documents a significant downward trend in the concentration of radionuclides in the environment from past weapons testing. The results of the program demonstrate that the operation of the plant did not result in a measurable dose of any significance to the general population, above natural background levels. I ! I l-1 ~I i
I
2.0 INTRODUCTION
l 2.1 SITE DESCRIPTION AND BACKGROUND The New York Power Authority (NYPA) is the owner and licensee of the James A. I FitzPatrick Nuclear Power Plant (JAFNPP). JAFNPP is a single unit boiling water reactor (BWR). The plant generates 2436 megawatts (MW) thermal output and 800 megawatts gross electrical output. The plant is located on the eastern portion of the Nine Mile Point promontory approximately one-half mile due east of the Niagara g Mohawk Power Corporation (NMPC) Nine Mile Point Nuclear Power Stations (NMPNPS). Initial fuel loading of the JAFNPP reactor core was completed in I November of 1974. Initial criticality was achieved in late November 1974 and commercial operation began in July 1975. NMPNPS #1, a 620 MWe (net) BWR, has been operating since 1969. NMPNPS #2, a 1,100 Mwe (net) BWR, has been operating since March 1988. l The plant site is on the southeastern shore of Lake Ontario in the Town of Scriba, Oswego County, New York, approximately seven miles northeast of the City of Oswego, New York. The Universal Transverse Mercator System coordinates of JAFNPP are north 4,819,545.012 m, east 386,968.945 m. Syracuse, New York, I located 36 miles south , is the largest metropolitan city in the area. The site consists of approximately 700 acres of partially wooded land and shoreline The land adjacent , to the site is primarily used for recreation and residential purposes. The country side i to the west, east and south is rolling terrain rising gently up from the lake composed i mainly of glacial deposits. Approximately 34 percent of the land area in Oswego i County is devoted to farming. I NYPA and NMPNC share the responsibility for the JAFNPP Radiological Environmental Monitoring Program (REMP). Technical Specifications for radiological monitoring of the environment for all three plants are similar. This allows the majority of the sampling and analysis to be a joint undertaking. Data generated by the program is shared by the three facilities. Review and publication of the data is done l independently by each organization. j 1 This report is submitted in accordance with Section 7.3.d of the Radiological Effluent Technical Specification ~s (IETS) to DPR-59, Docket 50-333. ' I 2-1 I
2.2 PROGRAM OILIECTIVES The objectives of the Radiological Environmental Monitoring Program are to:
- 1. Measure and evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on radioactive material sources.
- 2. Monitor natural radiation levels in the environs of the JAFNPP site.
- 3. Demonstrate compliance with the various environmental conditions and requirements of applicable state and federal regulatory agencies.
- 4. Provide information by which the general public can evaluate the environmental aspects of nuclear power using unbiased data.
i I i l i j i [ 2-2 r i
I l 3.0 PROGRAM DESCRIPTION To achieve the objectives listed in Section 2.2, an extensive sampling and analysis program is conducte,d every year. The JAFNPP Radiological Environmental I Monitoring Program (REMP) consists of sampling and analysis of various media that include: o Shoreline Sediment o Fish l o Surface Waters o Air o Milk o Food Products In addition, direct radiation measurements are performed using thermoluminescent l dosimeters (TLDs). These sampling programs are outlined in Table 3.0-1. The JAFNPP REMP sampling locations are selected and verified by an annual land use census. The accuracy and precision of the program is assured by participation in The United States Environmental Protection Agency (USEPA) Environmental Radioactivity Laboratory Intercomparison Program. In addition to the participation in the EPA Program, quarterly sample splits are routinely provided to the New York State Department of Health for cross checking purposes. Sample collections for the radiological program are accomplished by a dedicated site l environmental staff from both the James A. FitzPatrick Plant and the Nine Mile Point Stations. The site staff is assisted by a contracted environmental engineering company, EA Science and Technology, Inc. (EA). I I 3-1 i
M M M M M M M M M M M M M M M TABLE 3.0-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Pathway Type and Frequency and/or Sample Number of Samples (a) and Locations Col lectior)a) Frequencyt of Analysis AIRBORNE Radiciodine Samples from 5 locations: Continuous sam- Radiciodine Canisters: and ple operation Analyze weekly for I-131. Particulates a. 3 samples from off-site locations in dif- with sample col-ferent sectors of the highest calculated lection weekly Particulate Samoles: site average D/Q (based on all licensed or as required site reactors). by dust loading, Gross beta following radioactivity filter changelb) whichever is composite (by location) w b. 1 sample from the vicinity of a community more frequent. for gamma isotopic i> having the highest calculated site aver- quarterly (as a minimum). age D/Q (based on all licensed site re-actors).
- c. 1 sample from a control location 9 to 20 miles distant 9q winddirectiontagintheleastprevalent Direct Radiation (e) 32 stations with two or more dosimeters Quarterly Gamma dose monthly or placed as follows: An inner ring of stations quarterly.
in the general area of the site boundary and an outer ring in the 4 to 5 mile range from the site with a station in each of the land based sectors of each ring. There are 16 land based sectors in the inner ring, and 8 land based sectors in the outer ring. The balance of the stations (8) are placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.
l TABLE 3.0-1 (ccurinuso) l OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Pathway Type and Frequency and/or Sample Number of Samples (a) and Locations Collectiop Frequencyta
) of Analysis WATERBORNE Surface (f) a. 1 sample upstream. Composite sam- Gamma isotopic analysis ple over one monthly. Composite for
- b. 1 sample from the si month periodC9) coolingwaterintakeg)smostdownstream Tritiganalysisquar-terly .
Sediment from 1 sample from a downstream area with existing Twice per year. Shoreline or potential recreational value. Gamma semiannually isotopic) (c ,analysis w INGESTION Hilk a. Sam)les from milch animals in 3 locations Twice per month, Gamma isotopic and I-131 wit 1in 3.5 miles distant having the high- April through analysis twice per month est calculated site average D/0. If December (sam- when milch animals are there are none, then 1 sample from milch ples will be on pasture (April through animals in each of 3 areas 3.5 to 5.0 collected in December): monthly (Jan-miles distant having the highest calcu- January through uary throuah March) if latedsiteaverageD/Q(ggsedonall March if I-131 required (cy, licensed site reactors)l 1 is detected in November and
- b. 1 sample from milch animals at a control December of the location (9 to 20 miles distant g preceding year).
less prevalent wind direction)(d;nd in a m M M M W W W W W W W W
sus sus amm aus sus sus sua mas sum num aus amm aus sus aus n m m - TABLE 3.0-1 (c:svruuso) OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Pathway Type and Frequency and/or Sample Number of Samples (a) and Locations Collection Frequencyta) of Analysis FISH
- a. 1 sample of each of 2 commerically or Twice per year. Gamma isotopic (c) analysis recreationally important species in the of edible portions.
vicinity of a site discharge point.
- b. 1 sample of each of 2 species (same as in a. above or of a species with similar feeding habits) from an are least 5 m miles distant from the site L
FOOD PRODUCTS
- a. In lieu of the garden cenus as specified Once during Gamma isotopic (c) in 6.2. samples of at least 3 different harvest season. analysis of edible kinds of broad leaf vegetation (such as portions. (Isotopic vegetables) grown nearest each of two to include I-131).
different off-site locations of highest predicted site average D/Q (based or ;11 licensed site Reactors). One (1) sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a le gt prevalent wind direction sectortas,
I NOTES FOR TABLE 3.0-1 (a) It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances suitable attemative media and locations may be chosen for the particular pathway in question. Actual locations (distance and directions) from the site shall be provided I in the Annual Radiological Environmental Operating Report. Calculated site averaged D/Q values and meteorological parameters are based on historical data (specified in the ODCM) for all licensed site reactors. lj l (b) Particulate sample filters should be analyzed for gross beta 24 hours or more after l, sampling to allow for radon and thoron daughter decay. If gross beta activity in air is greater than 10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. (c) ' Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the plant. (d) The purpose of these samples is to obtain background information. If it is not I practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be l substituted. (e) One or more instruments, such as a pressurized ion chamber, for measuring and g recording dose rate continuously may be used in place of, or in addition to, 5 integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a pocket may be considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation. l (f) The " upstream sample" shall be taken at a distance beyond significant influence of g the discharge. The " downstream sample" shall be taken in an area beyond, but near, the mixing zone, if practical. I 3-5
I l NOTES FOR TABLE 3.0-1 (Continuedl I (g) I Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure that a representative sample is obtained. l (h) A milk sampling location, as required in Table 1 is defined as a location having at least 10 milking cows present at a designated milk sample location. It has been found from past experience, and as a result of conferring with local farmers, that a minimum of 10 milking cows is necessary to guarantee an adequate supply of milk I twice per month for analytical purposes. Locations with less than 10 milking cows are usually utilized for breeding purposes which eliminates a stable supply of milk for samples as a result of suckling calves and periods when the adult animals are dry. In the event that 3 milk sample locations cannot meet the requirement for 10 milking cows, then a sample location having less than 10 milking cows can be used l if an adequate supply of milk can reasonably and reliably be obtained based on communications with the farmer. I I I I I I I 3-6
)
E j 3.1 SAMPLE COLLECTION METIIODOLOGY 3.1.1 SURFACE WATER l Surface water samples are taken from the respective inlet canals of the JAFNPP and the Niagara Mohawk Oswego Steam Station (OSS) located in the City of Oswego. The FitzPatrick Facility draws water from Lake l)! l Ontario on a continuous basis. This is used for the "down-current" or indicator sampling point for the Nine Mile Point Site. The OSS inlet canal l removes water from Lake Ontario at a point approximately 7.6 miles west of the site. This "up-current" location is considered a control location E 5 because of the distance from the site as well as its location relative to prevailing lake current directions and flow pattem of the nearby Oswego l River. 1 Samples from the JAFNPP are composited using automatic sampling ; equipment which discharges into a compositing tank or bottles. Samples are gl collected monthly from the compositor and analyzed for gamma emitting 5 radionuclides. Samples from the OSS are also obtained using automatic sampling equipment and collected in a holding tank. Representative samples from this location are obtained weekly and are composited to form a monthly composite sample. The monthly samples are analyzed for gamma emitting radionuclides. l l A portion of the monthly samples from each of the locations is saved and f composited to form quarterly composite samples. Quanerly composite ; samples are analyzed for tritium. I In addition to the sample results for the JAFNPP and Oswego Steam Station { collection sites, data is presented for the Nine Mile Point Unit I and Unit { 2 facility inlet canal samples and for samples from the City of Oswego drinking water supply. The latter three locations are not required by the Technical Specifications. These locations are optional sample points which are collected and analyzed to enhance the surface water sampling program. Monthly composite samples from these three locations are analyzed for l gamma emitters and quarterly composite samples are analyzed for tritium. Surface water sample locations are shown in Section 3.3 on Figure 3.3-4. 3-7 I I
3.1.2 AIR PARTICULATE / IODINE The air sampling stations required by the Radiological EfDuent Technical Specifications (IETS) are located in the general area of the site boundary. The sampling stations are sited within a distance of 0.2 miles of the site boundary in sectors with the highest calculated meteorological deposition factors (D/Q) based on historical meteorological data. These stations (R-1, R-2, and R-3) are located in the east, east-southeast, and southeast sectors as measured from the center of the NMPNS Unit 2 reactor building. The RETS also require that a fourth air sampling station be located in the vicinity of a year round community having the highest calculated dispersion factor (D/Q) based on historical meteorological data. This station is located in the southeast sector and is designated as location R-4. A fifth station required by the RETS is a control location, designated as station R-5. Station R-5 is located 16.4 miles from the site in the east northeast meteorological sector. In addition to the RETS required locations, there are ten additional sampling stations. Six of these sampling stations are located within the site boundary and are designated as on-site stations Dl, G, H, I, J, and K. These locations are within the site boundary of the JAFNPP and NMPNS. One air sampling station is located off-site in the southwest sector in the vicinity of the City of Oswego and is designated as station G off-site. Three remaining air sampling stations are located in the ESE, SSE, and S sectors and range in distance from 7.2 to 9.0 miles. These are designated as off-site stations D2, E and F respectively. Each station collects airbome particulates using glass fiber filters (47 millimeter diameter) and radiciodine using charcoal cartridges (2 x 1 inch). The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis. Sample volume is determined by use of calibrated gas flow meters located at the sample discharge. Gross beta analysis is perfo'med on each particulate filter. Charcoal cartridges are analyzed for radio!odine using gamma spectral analysis. The particulate filters are composited monthly by location and analyzed for gamma emitting radionuclides. 3-8
I Air sampling stations are shown in Section 3.3, Figures 3.3-2 and 3.3-3. l 3.1.3 MILK Milk samples are routinely collected from six farms during the year. These farms included five indicator locations and one control location. Samples are collected twice per month, April through December and each sample is analyzed for gamma emitting radionuclides and I-131. Sampbs are collected in January, February and March in the event that I-131 is detected in November and December of the preceding year. l The selection of milk sample locations is based on maximum deposition calculations (D/Q). Deposition values are generated using average historical l meteorological data for the site. The Technical Specifications require three sample locations within 5.0 miles of the site with the highest calculated deposition value. During 1993 there were no milk sample locations within g 5.0 miles that were suitable for sampling based on production capabilities. 5 There were however, five optional locations beyond five miles that were sampled as the routine milk sampling program. l The Technical Specifications also require that a sample be collected from a location greater than ten miles from the site and in a less prevalent wind l direction. This location is in the southwest sector and serves as the control location. Milk samples are collected in polyethylene bottles from a bulk storage tank at each sampled farm. Before the sample is drawn, the tank contents are agitated to assure a homogenous mixture of milk and butterfat. Two gallons are collected from each indicator and control locations during the first half and second half of each month. The samples are chilled, preserved and shipped fresh to the analytical laboratory within thirty-six hours of collection l in insulated shipping containers. The milk sample locations are found in Section 3.3 in Figure 3.3-4. (Refer g to Table 3.3-1, Section 3.3 for location designations and descriptions). 5 l 3-9 I I
I l 3.1.4 FOOD PRODUCTS (VEGETATION) Food products are collected once per year during the late summer harvest season. A minimum of three different kinds of broad leaf vegetation (edible g or inedible) are collected from two different indicator garden locations. 5 Sample locations are selected from gardens identified in the annual census that have the highest estimated deposition values (D/Q) based on historical l site meteorological data. Control samples are also collected from available f locations greater than 9.3 miles distance from the site in a less prevalent l wind direction. Control samples are of the same or similar type of vegetation when available. I Food product samples are analyzed for gamma emitters using gamma I isotopic analysis. Food product locations are shown in Section 3.3 on Figure 3.3-5. 3.1.5 FISII SAMPLES I Samples of available fish species are selected from the Nine Mile Point Aquatic Ecology Study which monitors lake fish populations. Fish samples are collected twice per year, once in the spring and again in the fall. I Indicator samples are collected from a combination of the four on-site sample transects located off shore from the site. One set of control samples are at an off-site sample transect located off shore 8 - 10 miles west of the site. Available species are selected using the following guidelines: l a) Samples are composed of 0.5 to I kilogram of the edible portion only. A maximum of three species per location are used. b) Samples composed of more than 1 kilogram of single species from the I same location are divided into samples of 1 kilogram each. A maximum of three samples per species per location are used. Weight of samples are the edible portions only. I 1 c) Samples are limited to edible and or sport species when available. I 3-10 I
l I l l I Selected fish samples are frozen immediately after collection and segregated by species and location. Samples are shipped frozen in insulated containers l ! for analysis. Edible portions of each sample are analyzed for gamma emitting radionuclides. Fish collection locations are shown in Section 3.3 l on Figure 3.3-5. l l 3.1.6 SIIORELINE SEDIMENTS 1 l One kilogram of shoreline sed.iment is collected at one area of existing or ! potential recreational value. One sample is also collected from a location ' beyond the influence of the site. Samples are collected as surface scrapings to a depth of approximately 1 inch. The samples are placed in plastic bags, l, l scaled and shipped to the lab for analysis. Sediment samples are analyzed for gamma emitting radionuclides. Shoreline sediment locations are shown in Section 3.3 on Figure 3.3-5. 3.1.7 TLD (DIRECT RADIATION) Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. TLDs are supplied and processed g quarterly by Teledyne Isotopes of Westwood, New Jersey. Transit and control TLDs accompany each shipment between the site and the vendor's laboratory and accompany the TLDs when they are being placed or collected in the field. TLD data results are corrected using transit and control TLDs data. Five different regions around the site are evaluated using environmental TLDs. ' o On-site areas (areas within the site boundary not required by the RETS) I o Site boundary area in each of the sixteen meteorological sectors o An outer ring of TLDs (located four to five miles from the site in the eight land based meteorological sectors) l 3-11 I I
l o Special interest TLDs (located at sites of high population density and use) l 1 o Control TLDs located at sites beyond significant influence of the site Special interest TLDs are located at or near large industrial sites, schools, or nearby towns or communities. Control TLDs are located to the southwest, south and east-northeast of the site at distances of 12.6 to 19.8 miles. { TLDs used for the 1993 program were constructed of rectangular teflon wafers impregnated with 25 percent CaSOgDy phosphor. Badges are sealed in a polyethylene package to ensure dosimeter integrity. TLD packages were placed in open webbed plastic holders and attached to supporting structures, such as utility poles. Environmental TLD locations are shown in Section 3.3 on Figures 3.3-2 and 3.3-3. l 3-12 j
I 3.2 ANALYSIS PERFORMED l The majority of environmental sample analyses are performed by the James A. FitzPatrick Environmental Laboratory (JAFEL). TLD, tritium and surface water l I-131 analysis were performed by Teledyne Isotopes (TI). The following samples are analyzed at the JAFEL: o Air Particulate Filter - gross beta o Air Particulate Filter Composites - gamma spectral analysis o Airbome Radiciodine - gamma spectral analysis l o Surface Water Monthly Composites - gamma spectral analysis g o Fish - gamma spectral analysis I i o Shoreline Sediment - gamrna spectral analysis o Milk - gamma spectral analysis and I-131 I o I' Special Samples (soil, food products, bottom sediment, etc.) - gamma spectral analysis I Quality assurance samples are analyzed in house and by Teledyne Isotopes N.J. and l Teledyne Isotopes Midwest. I I I 3-13 I I
3.3 SAMPLE LOCATION MAPS Section 3.3 includes maps illustrating sample locations. Sample locations referenced as letters and numbers on the report period data tables are consistent with designations plotted on the maps. This section also contains an environmental sample location reference table (Table 3.3-1). This table contains the following information: o Sample Medium i o Location designation, this column contains the key for the sample location and is consistent with designation on the sample location maps j and on the sample results data tables. ; l o Location description l 1 o Degrees and distance of the sample location from the site. 3.3.1 LIST OF FIGURES 8 o Figure 3.3 New York State Map o Figure 3.3 Off-site Environmental Station and TLD Location Map o Figure 3.3 On-site Environmental Station and TLD Location Map o Figure 3.3 Milk Animal Census, Milk Sample Location and Surface Water Sample Location Map o Figure 3.3 Nearest Resident, Food Product, Shoreline Sediment, Fish l Sample Location Map f L P 3-14 1 _ - - - - - - 1
FIGURE 3.3-1 NEW YORK STATE MAP
.ss +~ '$$
. . . ~ , .
jw f,, CANADA J., b _ , , l J. ..+; . . =lL
.r .h ~ 4 ,
- . ; ,. . . . . _ . f .
==,
.u
;- , ..-. :. r }
rNEW: YORK"f
-, , .:O _.
$,=.
~. ..
,,,,. f.. _.
p -- .
. syn 4eusse .
9FTfCA . FRQ$i(}gF -
.j .. Y\Y <
- xsamei f _
l..... - ... l .
^
f) n = ~.vtv,=,A , 3 ca~.cricur Nino Mile Point Nuclear Station Unit 1 1 Nine Mile Point Nuclear Station Unit-2 # o James A. FitzPatrick Nuclear Power Plant 4 Nfw Jfm.EY I
#fW YORK CITY p -
1 ) l i
N ~
.? -
) i
\:
OSWEGO COUNTY New York --
^
{r~. I 0~;
- -~
FIGURE 3.3-2 % OFF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS enj ! : (. ! KET: f, A }{ ][ .
~,
6ENVIRONMENTALSTATION e
~
$TLDLOCATION .:m 0 N 'l, A R 1 0 = ~g/
ma o, ,u. ,
.g _,, gf irs m
, 56 ~~ '?
/f,Q,
- g '
M ggM.yg %
~
\
. ed4 r 3a=nAh y p ;e w"- e. e twm. ? % g> n _
-~
_s ,. , 7,g ,) 'rh, 5
~k _';
k
/. - a E*;
n 5
&(. %
,p h** -
Yh{'pk Li w s$.h Ah? Y;1@$yd Y%- ' $g v, y e. g ~\ 4 A
; q ,'
s1, [r w * ' m i .4)Q,il
.e . ;l4
= '
M n ,. 4 % . c, . s
,,,,,,,,N' p ;,.
.f, b
- L
. . T3 w oe . ig , 3 -. . .
N' ** y
)
/k,q
,; i, '
% ,/ j ..
4h , 27' ~7 %y
~
, j ,.j , - DR
! {_, 1 a!! ,.' g a.a y e,* ; ,-
%. ,. s s, wegy..
- w .f .
-A r ___ .
m o %r w - 'a 4 ns. . r c ',,o e..
'r , 'y7._.
s 4, # 7,*, ..
. ,l NE_~ I
,g i 1
= ?
'l , ,
MA:gm<g%' A j 2yg #c y 1 y f p pg_
?
V6 ML -gr%% (cr. w , '~QR L[W ~
+f a g 'k g E y- Q S '
\
h yk,
- m'. 'm,. y h$ gi[
,u n&"Ta mba, ga g .p.g q -
sg . s
.g,, ; .
=v s ..
s, 4
;n ,- . me d. ,z < .. .n g n_
. .u w.... y..
k in .. .e - m- ._. -.-; 4;.. . . j( S- , g..p -
.e g 5, ' s"% pg3 'Q t
, aw 4._.
Nr Q:/ n t m m 1
k 5
) ( i I
e il I -
] :m I
. i s- '.... -
l g .. - e 3 I r *
*... ... i
@ ?
/ S
]
wmmm1 y xmm msmmsm e. xmx symm yg
/
? - -
. =
\
l
~
.- t b [t_I b 4 ,...-
3 af__ ~= eqi x 9 -
..- l a
e w % e \ e 3
~
!! g c#
4 y
,... (\ f
.....Kgg. . . . . . ' , g s \
kg ' Aw1w m wwusw k
- ms- _ _ __ _ ._
___y__ .___ q$ _. _ . _ g
~
J 7 '4 9 R
# is
% i i ao ... ;s t_
sas
... . .... . ............. ......... . . . . q 9 . . . . . . . . f..........:3....
i 3,.y..q..... ..... ....... .. ............ ........ ...
- g. ...g
# "N f $k'j .g >NL k- j ~=
ES
. o -
6 /d 5; 's g
.e m
" n 4 5
\ h 8 l!/ % # +e C $
\nA
-s g , f*' o m 5
8 g 18 5 m p * [ $ x - i e
- g .. s a i
I cEG w 09 rn I *
$ 5 3
)
h P* m.% y s
\ $
(i l=D w - h5 ' O5WEGO COU NTY - i . New York ki FIGURE 3.3-4 - MILK ANIMAL CENSUS, . MILK SAMPLE, AND SURFACE WATER SAMPLE LOCATIONS Is AKE lg dMILKANIMALCENSUS 10 m. xy 8',
,3
$ MILK SAM!'LC .
$$URFACEWATER ONTARIO = ,( f~~
% 'N
,~ m ., -.
.grggg .
= ~: =s.;u,,m u +
. 4~ , ,r ~ys,.,,, .
~ t, -.
p;~ ~ TC,.Z~14";l%' M, . " 0, "c:" .. -i >
- s. /j- .
y y/ m 4 ; 1 y,w\ ,4 &, 4 , x ggy, . ( 1
*2b wsw. 'dd W _ %h lG %,.
-N" f% h SkL &/%
c ik . , ,
%:f=$L,
#w
&,\ j L% ~{ D %
~i N aG K /g v 4 e p E , % v g% '~ d % %
i kfth i hkhh l
}a:-v.w.n---
u f fw )w% A .. w .. +wfQrn if 7 m Lm w: Hfy e . i u
,t ) ,; y s%e e N. .
s e.m - { N- A @ :1 . h l,i,.&; - : ) { :-@l ~s y)i XW ll! V_.%? [~' ji mR j
;.,/m3 .- x:,s = 1 .
qa ,q,s n-.
-p p .? w;iQ3 j
\
- hg ,_._p) rt (- s..,%,s m .,,.%g m.. - , s 4 .
m
*'Q- ^g
_.U,, 4,, %wp N ,
",i ' .' # 'g,~
, +- 4
; n,w i
.g a 4 t 1Q- , g _g._3
~ --i s
s, pg% .s i
.& \,
a\ % f " O*\ ' f f p/
...,-,Qc y== y *- "w.4,
(.- I"n'3
.i aw
*f.l.y w+\ k N*b.h* g 3 M ,
h(4 , 4 . '. s - h .O.
. l h[ws- n.bI6 '"s. f f' '. \ ,I d - ,,,,, ,bi f j S .' g*,Q s t:.,,
, ., i h,4 ..
i
,f_,; N s. 1
-~~~%m. t ---
1
. ,@s . / ;. mi . gi ,
'~~.
g q,
..2-W .
f ' ., f i e '; %,.. > J'-*,._/ ' v b. g[ 'N_' h-- d5 ' e\n o< sg
\ /, *s I*N 1 \p r 'g3 e
/ )- . m4x
- 4";n.(. x "' N '\a 'v
~~"
r y 3,}a 7, s g.. it r i N u,1.
- v r
& = ,];_ o -
x_-~3. 7,,_.;. . - m _.-4 , b- .
.g- ,a ,
p;;; y (. t,( 3,
,3, mj
~ , . .
ma '- g .. e, c % , . y .. .,--- l x,
, , e ' ~
x ,,7 v, 3& ( ;' % *-X-;Q; ' v- c- tR:g"- :,,.f
'~~ M mor i- 4
.. _ m{Y. k A , ,3
,- .;' ' u e ^b '1[1~
wn-
{ h A4 h ,(- 1 .s,,,,, x, ie . O5WEGO COUNTY 7% -@ New York e 9 m h i m FIGURE 3.3-5 --A b' I s ' NEAREST RESIDENCE, F000 PRODUCT, FISH AND SHORELINE SEDIMENT SAMPLE LOCATIONS
/, jj K E
)Mtt-A)
KEY: ORE 510ENCE-NMP <
) #
1 FISH $ RESIDENCE-JAF ]. ,jy OF000 PRODUCT D
$ SHORELINE
)6 i
SEDIMENT () A T . I R / () '/
.c.a o, .a i p
~,b
/-- . . ty s, v'- ).,9 sg 1'F:1
, 4 m ..._. w _-q 'JT..... W, - Q~~g/
f% N ' 7 y ,'a g.nky %,gdg+k .
, - k t~-{q2WMc.[Jghn
/ / j,7 e w. rw.
jw=mp{' O M~my - 7' 2 q 0 gj l =- t / 4% d'" ,'r,,
~
k, ,' %j:.h{ h * ?~~M V
-7 ~ * =
, ,7 y e seg y ;
wsw j; p=4 p: m yn .a I S) y ,r ...
. _ y(' o,m -Q] - t { -.., u -
4
- n. x I D4 N1 5 e 4
7yg h ; <_ _f,r y g:,, 8 * ;, ,,, x l,i g.4.y g. ,, g , f , J Y 'l k ,b k' M3_ W jgf N;w Ql ? g,wq ~ 4 . CA
' / V44_~e._a.'R.%
y- - w a:." &n j%g g' g' ass wy+m
' , ,/ m':;4'. h
;* wc~. r ,
g/
' ', / - ,
- l ,
- w. q A.. \, I , , h-a,a w })-,,,7, l \ ,
s 'a;T+y/ m x, 1-
- f. 4 .o s. 'Nc + , - . . , . . . .
,f%. ' 'g I
~ g4 ?- red-.j p$ A -
1,o'4, t i i f_y fW. Km;.,
&'. .lg{Q,n@j%j :
.Q.i ,~
_ - ya - 7
%r c
- <g ,
;~7 =_ ;s.
e g q4'j, s f, a ,.T L w) ;g.,;
' <A s p ;vf, ,y g' i f .s
% J .
s
* *^
. ht 79
~
K e- ' . '
,$(.j:b f .W6$n\ h 1Q' ?< h
~v m ^*./m$ ?ly;h);l.J.n-?
pyd 6 h,,LF "1
- J p'. ,' hW,3{0" , je.!.L .,a g
.; w- o(Q_.. 'y]S. X~d;7 f 4:, .,,#_vc **4 y. f . j. w y
- 3 '.h?\"y'v s,
<g <g . %mS m ..
,.w y .
l} o ,. _- c I ,,1, anb_ Ny- , ,a ,
,t L .,;.,.. "h, ) g.
[ e , .. r- A, . i, w h - = 4.u %s%bN y 7"
-r o ..l ,
pm. ;, au *. l.A' Im,n w- . s . ID wdY w . 4 ima -. p ,, 7
. - s C- S l* \,,. * * * * -'
h ) R G i ( g - , .../ ) r M."q.# s\. 4)\ 0i s g- ,e J I- - \\ k
- c. \ 4. ,A .s;-g , ,s,.h.4
., k L-._ hi 'J T. I'~ ,, g $ P,.
=
-- s
- -O_ 1 y..gi,t;a .
W_g -mK. j .- pM y :.. y-t' yy i .. c= A,
-hs p.J 4,.u :
, m. _a- gsg =u,,g, e wu Q=q 3 . y,'> ,g #y3 a, g4 . g .gSy ,
.g..
W $
TABLE 3.3-1 ENVIRONMENTAL SAMPLE LOCATIONS
- SAMPLEi jLOCATION'
'MEDIUMi FDESIGNATION) iLLOCATION; DESCRIPTION: iDEGREES?ANDDISTANCE(lk Shoreline 05* Sunset Bay 80 at 1.5 miles Sediment 06 Langs Beach, Control 230 at 5.8 miles Fish 02* Nine Mile Point Transect 315 at 0.3 miles 03* FitzPatrick Transect 55 at 0.6 miles 00* Oswego Transect 235 at 6.2 miles Surface Water 03* FitzPatrick Inlet 70 at 0.5 miles 08* Oswego Steam Station 235 at 7.6 miles 09 Nine Mile Point Unit 1 Inlet 305 at 0.3 miles 10 Oswego City Water 240 at 7.8 miles 11 Nine Mile Point Unit 2 Inlet 304 at 0.1 miles Air R-1* R-1 Station, Nine Mile Pt. Rd. 88 at 1.8 miles Radiciodine R-2* R-2 Station. Lake Road 104 at 1.1 miles and R-3* R-3 Station Co. Rt. 29 132 at 1.5 miles '
Particulates R-4* R-4 Station Co. Rt. 29 143 at 1.8 miles R-5* R-5 Station, Mo;itario Point Rd. 42 at 16.4 miles D1 D1 On-site Station. On-site 69 at 0.2 miles D2 D2 Off-site Station Co. Rt. 64 117 at 9.0 miles E E Off-site Station, Co. Rt. 4 160 at 7.2 miles F F Off-site Station. Dutch Ridge Rd. 190 at 7.7 miles G G On-site Station, On-site 250 at 0.7 miles H H On-site Station. On-site 71 at 0.8 miles I I On-site Station On-site 98 at 0.8 miles J J On-site Station, On-site 110 at 0.9 miles - K K On-site Station, On-site 132 at 0.5 miles G G Off-site Station, St. Paul St. 225 at 5.3 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Reactor Centerline
TABLE 3.3-1 (courinuso) ENVIRONMENTAL SAMPLE LOCATIONS SAMPLEt .!LOCATIONL . . . . . .. 1 MEDIUM- DESIGNATIONi : LOCATION DESCRIPTION:- ~ DEGREES ANDiDISTANCE(1):. Thermo- 3 D1 On-site Station 69 at 0.2 miles luminescent 4 D2 On-site Station 140 at 0.4 miles Dosimeters 5 E On-site Station 175 at 0.4 miles (TLDs) 6 F On-site Station 210 at 0.5 miles 7* G On-site Station 250 at 0.7 miles 8 R-5 Off-site Statior, 42 at 16.4 miles 9 D1 Off-site Location 80 at 11.4 miles 10 D2 Off-site Location 117 at 9.0 miles 11 E Off-site Location 160 at 7.2 miles 12 F Off-5ite Location 190 at 7.7 miles 13 G Off-site Location 225 at 5.3 miles 14* SW Oswego - Control 226 at 12.6 miles m 15* West Site Boundary 237 at 0.9 miles 6
~
18* Energy Information Center 265 at 0.4 miles 19 East Site Boundary 81 at 1.3 miles 23* H On-site Station, On-site 70 at 0.8 miles 24 I On-site Station On-site 98 at 0.8 miles
. 25 J On-site Station. On-site 110 at 0.9 miles 26 K On-site Station. On-site 132 at 0.5 miles 27 North Fence. JAFNPP 60 at 0.4 miles 28 North Fence, JAFNPP 68 at 0.5 miles 29 North Fence JAFNPP 65 at 0.5 miles 30 North Fence JAFNPP 57 at 0.4 miles 31 North Fence NMP-1 276 at 0.2 miles 39 North Fence, NMP-1 292 at 0.2 miles 47 North Fence, JAFNPP 69 at 0.6 miles 49* Phoenix. NY - Control 170 at 19.8 miles 51 Oswego Steam Station. East 233 at 7.4 miles 52 Oswego Elementary School, East 227 at 5.8 miles
- Technical Specificatior, location (1) Based on Nine Mile Point Unit 2 Centerline M M M M M M M M M M M M M M M M M M M
- - - _ _ - ~ _ ._ _- . .
TABLE 3.3-1 (Conunuso) ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE- LOCATION
-MEDIUM . DESIGNATION'- -LOCATION-DESCRIPTION- DEGREES:AND' DISTANCE (1)
Thermo- 53 Fulton High School 183 at 13.7 miles luminescent 54 Mexico High School 115 at 9.3 miles Dosimeters 55 Pulaski Gas Substation. Route 5 75 at 13.0 miles (TLDs) 56* New Haven Elementary School 123 at 5.3 miles 58* County Route 1 and Alcan 220 at 3.1 miles 75* North Fence. NMP-2 5 at 0.1 miles 76* North Fence. NiiP-2 25 at 0.1 miles 77* North Fence. nmo-2 45 at 0.1 miles 78* East Boundary. JAFNPP 90 at 1.0 miles 79* County Route 29 115 at 1.1 miles 80* County Route 29 133 at 1.4 miles 81* Miner Road 159 at 1.6 miles v 82* Miner Road 181 at 1.6 miles 6 83* Lakeview Road 200 at 1.2 miles 84* Lakeview Road 225 at 1.1 miles i 85* North Fence. NMP-1 294 at 0.2 miles 86* North Fence. NMP-1 315 at 0.1 miles 87* North Fence. NMP-1 341 at 0.1 miles 08* Hickory Grove Road 97 at 4.5 miles 89* Leavitt Road 111 at 4.1 miles 90* Route 104 and Keefe Road 135 at 4.2 miles 91* County Route 51A 156 at 4.8 miles 92* Maiden Lane Road 183 at 4.4 miles 93* County Route 53 205 at 4.4 miles 94* Co. Rt. 1 & Kocher Road (Co. Rt.63) 223 at 4.7 miles 95* Lakeshore Camp Site 237 at 4.1 miles 96* Creamery Road 199 at 3.6 miles 97* County Route 29 143 at 1.8 miles 98* Lake Road 101 at 1.2 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline 4
TABLE 3.3-1 (courinuso) ENVIRONMENTAL SAMPLE LOCATIONS ASAMPLEL .-LOCATIONL . .. . .. . . . . . . . MEDIUMi ~ DESIGNATION LOCATIONiDESCRIPTION! . DEGREES'ANDDI' STANCE (lb. Thermo- 99 Nine Mile Point Road 88 at 1.8 miles luminescent 100 County Route 29 and Lake Road 104 at 1.1 miles Dosimeters 101 County Route 29 132 at 1.5 miles (TLDs) 102 Oswego County Airport 175 at 11.9 miles 103 Energy Information Center. East 267 at 0.4 miles 104 Parkhurst Road 102 at 1.4 miles 105 Lakeview Road 198 at 1.4 miles 106 Shoreline Cove. East of NMP-1 274 at 0.3 miles 107 Shoreline Cove. East of NMP-1 272 at 0.3 miles 108 Lake Road 104 at 1.1 miles 109 Lake Road 103 at 1.1 miles 111 Sterling-Control 214 at 21.8 miles m 113 Baldwinsville-Control 170 at 24.7 miles 6 Cows Milk 7* Indicator Location 107 at 5.5 miles 50* Indicator Location 93 at 8.2 miles 55 Indicator Location 95 at 9.0 miles 60 Indicator Location 90 at 9.5 miles 4 Indicator Location 113 at 7.8 miles 65* Control Location (4/93 - 8/93) 220 at 17.0 miles 73* Control Location (8/93 - 12/93) 234 at 13.9 miles Food Products K Indicator Location 96 at 1.7 miles L Indicator Location 115 at 1.9 miles T Indicator Location 84 at 1.6 miles P Indicator Location 101 at 1.9 miles Z Indicator Location 95 at 1.7 miles M Control Location 225 at 15.6 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline M M M M M M M M M M M M M M M M M M M j
l l l 3.4 LAND USE CENSUS l Technical Specifications require that a milch animal census and a residence census be conducted annually. 1 The milch animal census is an estimation of the number of cows and goats within l an approximate ten mile radius of the Nine Mile Point site. The census is done once per year in the summer. It is conducted by sending questionnaires to previous milk animal owners, and by road surveys to locate any possible new owners. In the event that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Cooperative Extension Service was also contacted to provide any additional information. The residence census is conducted each year to identify the closest residence in each of the 22.5 degree meteorological sectors to a distance out to five miles. .A residence, for the purposes of this census, is a residence that is occupied on a part time basis (such as a summer camp), or on a full time, year round basis. Several of the site meteorological sectors are over Lake Ontario, therefore, there are only eight sectors over land where residences are located within five miles. In addition to the milch animal and residence census a garden census is performed. The census is conducted each year to identify the gardens near the site that are to be used for the collection of food product samples. The results of the garden census are not provided in this report. The results are used only to identify appropriate sample locations. The garden census is not required by the Technical Specifications , if broadleaf vegetation sampling and analysis is performed. j l l l l l 3-24 l I
Il 3.5 CIIANGES AND EXCEPTIONS TO TIIE PROGRAM 3.5.1 The following change was implemented during the 1993 sampling program. l A. The control milk sampling location was changed in August of 1993. The new control location is designated as location No. 73 and is located gl l 13.9 miles from the site in the SW sector at 234 . The original control I l milk location was sold by the owner and ceased milk production. ' 5.3.2 The following exception was taken during the 1993 sampling program. A. The fourth quarter 1993 TLD results (direct radiation) for monitoring stations 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 18, and 19 were determined to be invalid due to an equipment problem experienced by g the analysis vendor. Results for this period for the noted stations is reported using results from a backup TLD monitoring program. The backup program utilizes Panasonic's 814 dosimeters and is implemented by the J.A. FitzPatrick N.P.P. Environmental Laboratory. Results for the remaining stations for the fourth quarter were determined to be E a correct and are reported as submitted by the analysis vendor. I I I Il I: I I 3-25 I I
i 3.6 DEVIATION FROM TIIE PROGRAM l Exceptions to the 1993 sample program concerns those samples or monitoring l requirements which are required by the Technical Specifications. This section i l addresses the reporting requirements of Section 6.1.a of the RETS. l 1 The following are deviations from Ge program specified by the Technical Specifications: l l A. Air Sampling Stations The air sampling pump at the R-5, off-site Environmental Sampling Station was inoperable from July 6,1993 (1030 hours) to July 7,1993 (1400 hours). The inoperability was caused by technician error, failure to reset pump. l l The air sampling pump at the R-4, off-site Environmental Sampling Station was inoperable from October 14, 1993 (1400 hours) to October 14, 1993 (1545 hours). The inoperability was caused by maintenance on electrical lines feeding the station sampling pump. l 1 4 1 3-26 l i
)
I' 3.7 STATISTICAL METIIODOLOGY There are a number of statistical calculation methodologies used in evaluating the data from the environmental monitoring program. These methodologies include determination of standard deviation, the mean and associated error for the mean and l the lower limit of detection (LLD). 3.7.1 ESTIMATION OF TIIE MEAN AND STANDARD DEVIATION g The mean, (X), and standard deviation, (s), were used in the reduction of the I data generated by the sampling and analysis of the various media in the JAFNPP Radiological Environmental Monitoring Program (REMP). The following equations were utilized to compute the mean (X) and the standard EI deviation (s): A. Mean n l, 5=i=1 X'. g N where, 1 _ 1 X = estimate of the mean. i = individual sample, i. ll j N, n = total number of samples with positive indications. I Xi = value fer sample i above the lower limit of detection. B. Standard Deviation i l/2 I I Dx, - x) s= i=1 g (N-1) I 3-27 I I
- . . - - . - - , - .~ .
1 l where, l ! X = mean for the values of X s = standard deviation for the sample population. 3.7.2 ESTIMATION OF THE MEAN AND THE ESTIMATED ERROR FOR THE MEAN In accordance with program policy, two recounts of samples are performed when the initial count indicates the presence of a plant related radionuclide(s). When a radionuclide is positively identified ir avo or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated enor for that mean. In cases where more than one positive sample result is available, the mean of the sample results and the estimated error for the mean are reported in the Annual Report. The following e'quations were utilized to estima'e t the mean (X) and the associated propagated error. A. Mean n X=i=1 X. 2 N I where, X = estimate of the .mean. i = individual sample, i. N,n = total number of samples with positive indications. Xi = value for sample i above the lower limit of detection. 3-28
E B. Error of the Mean (Reference 18) I E n # ERROR MEAN = { (ERROR)2 l i=1 N where, ERROR MEAN = propagated error i = individual sample ERROR N, n
= 1 sigma
- error of the individual analysis
= number of samples with positive indications l
Sigma (a) Sigma is the greek letter used to represent the mathematical term Standard Deviation. Standard Deviation is a measure of dispersion from the arithmetic mean of a set of numbers. I
- I
- I I
E I I 3-29 I I
3.7.3 LOWER LIMIT OF DETECTION (LLD) The LLD is the predetermined concentration or activity level used to establish a detection limit for the analytical procedures. The LLDs are specified by the Technical Specifications for radionuclides in specific media and are determined by taking into account the overall measurement methods. The equation used to calculate the LLD is: 4.66 s s LLD = (E) (V) (2.22) (Y) exp (-AAt) Where: LLD is the a priori lower limit of detection, as defined above (in picoeurie per unit mass or volume); ss is the standard deviation of the background counting rate or of the counting rate of a blank sample, a; appropriate (in counts per minute); E is the counting efficiency (in counts per disintegration); I V is the sample size (in units of mass or volume); 2.22 is the number of disintegrations per minute per picocurie; Y is the fractional radiochemical yield (when applicable); A is the radioactive decay constant for the panicular radionuclide; At is the elapsed time between sample collection (or end of the sample l collection period) and time of counting. ! I 3-30
~
I The RETS LLD formula assumes that: o The counting times for the sample and background are equal. l o The count rate of the background is approximately equal to the count rate of the sample. In the RETS program, LLDs are used to ensure that minimum acceptable detection capabilities are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative). Table ! 3.8-1 lists the RETS program required LLDs for specific media and j radionuclides as specified by the NRC. The LLDs actually achieved are routinely much lower than those specified by the RETS. l I I I I I I I I Il I i Il l 3-31 I
3.8 COMPLIANCE WITII REQUIRED LOWER LIMITS OF DETECTION (LLD) Table 6.1-3 of the Radiological Effluent Technical Specification (RETS) specifies the detection capabilities for environmental sample analysis (see Report Table 3.8-1). Section 7.3.d of the RETS requires that a discussion of all analyses for which the required LLDs specified were not routinely achieved be included in the Annual Radiological Environmental Operating Report. Section 3.8 is provided pursuant to this requirement. 3.8.1 All sample analyses performed in 1993, required by the RETS, achieved the Lower Limit of Detection (LLD) specified by RETS Table 6.1-3. l 1 4 l 3-32
TABLE 3.8-1 REQUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD) Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/1) 3 or Gases (pCi/m ) (pCi/kg, wet) (pCi/1) (pCi/kg. wet) (pCi/kg. dry) gross beta 4 0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 Y d Co-58,60 15 130 Zn-65 30 260 Zr/Nb-95 15 I-131C) 15 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba/La-140 15 15 (a) No drinking water pathway exists at the Nine Mile Point Site under normal operating conditions due to the direction and distance of the nearest drinking water intake. Therefore, an LLD value of 15 pCi/ liter is used. M M M M M M M M M M M M M M M M M M M
4.0 SAMPLE
SUMMARY
TABLES IN BRANCII TECIINICAL POSITION FORMAT All sample data is summarized in table fonn. The tables are titled " Radiological Monitoring Program Annual Summary" and use the following format as specified in the NRC Branch Technical Position: Column 1 Sample medium. 2 Type and number of analyses performed. I 3 Required Lower Limits of Detection (LLD), see Section 3.8, Table 3.8-1. This wording indicates that inclusive data is based on 4.66 s3 (sigma) of background (see Section 3.7). 4 The mean and range of the positive measured values of the indicator l locations. l 5 The mean, range, and location of the highest indicator annual mean. Location designations are keyed to Table 3.3-1 in Section 3.3. I 6 The mean and range of the positive measured values of the control locations. 7 The number of nonroutine reports sent to the Nuclear Regulatory Commission. I I I NOTE: Only positive measured value.s are used in statistical calculations. I - I - 4-1 1 l I t . t
)
RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
I l JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 I OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1993 Location (b) of Control
. Type and Indicator Locations: Highest Annual Mean:
Medium Number of Location: Number of Mean (a) Locations &- Mean (a) Mean (a) Nonroutine (units) Analysis LLD Range Designation Range Range Reports Surface H-3 (8): 3000 242 (4/4) No. 3 242 (4 /4 ) 188 (4 /4 ) 0 (Lake) Water 200 - 280 0.5 @ 70* 200 - 280 (pCi/ liter) GSA (24): 160 - 230 Mn-54 15 <LLD <LLD <LLD 0 Fe-59 30 <LLD <LLD <LLD 0 p Co-58 15 <LLD <LLD <LLD N 0 Co-60 15 <LLD <LT D <LLD 0 Zn-65 30 <LLD <LLD <LLD 0 Zr-95 15 <LLD <LLD <LLD 0 Nb-95 15 <LLD <LLD <LLD 0 I-131 15 <LLD <LLD <LLD 0 Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0
i RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 i OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1993 l Location (b) of Control l Type and Indicator Locations: Highest Annual Mean: Location: Number of Medium Number of Mean (a) Locations & Mean (a) Mean-(a)- Nonroutine (units) Analysis LLD Range Designation Range Range Reports Shoreline ggg (4) , Sediment (PCi/g-dry) Cs-134 0.15 <LLD <LLD <LLD 0 0.32 (2/2) No. 5 0.32 (2/2) 0.027 (1/2) O Cs-137 0.18 0.18 - 0.46 1.5 0 80' O.18 - 0.46 0.027-0.027
^
/g-wet)
Mn-54 0.13 <LLD <LLD <LLD 0 t Fe-59 0.26 <LLD <LLD <LLD 0 Co-58 0.13 <LLD <LLD <LLD 0 Co-60 0.13 <LLD <LLD <LLD 0 Zn-65 0.26 <LLD <LLD <LLD 0 Cs-134 0.13 <LLD <LLD <LLD 0 Cs-137 0.15 0.028 (8/17) No. 03 0.028 (4/8) 0.033(2/10) 0 0.018 - 0.035 0.6 @ 55* 0.025 - 0.035 0.030-0.036 o ucts (PCi/g-wet) I-131 0.06 <LLD <LLD <LLD 0 Cs-134 0.06 <LLD <LLD <LLD 0 Cs-137 0.08 <LLD <LLD 0.008 (1/6) 0 0.008-0.008 M M M M M M M . E E E E
i RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1993 Location (b) of Control Type and Indicator Locations: Highest Annual Mean: Location: Medium Number of Number of Mean (a) Locations & Mean (a) Mean (a) Nonroutine (units) Analysis LLD Range Designation Range Range Reports Milk (f) GSA (108): (pci/ liter) Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 [ Ba/La-140 15 <LLD <LLD <LLD 0 I-131(108): 1 <LLD <LLD <LLD 0 i V nNd
RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1993 Location (b) of Control Type and Indicator Locations: Highest Annual Mean: Location: Number of Medium Number of Mean (a) Locations & Mean (a) Mean (a)- Nonroutine (units) Analysis LLD Range ' Designation Range Range Reports Air G.B. (265): 0.01 0.014 (212/212) R-2 0.015 (53/53) 0.013 (53/53) O Particulate 0.005 - 0.025 1.1 e 104* 0.006 - 0.023 0.007 - 0.022 and Radioiodine I-131(265): 0.07 <LLD <LLD <LLD 0 (d) (pCi/m') GSA (60): Cs-134 0.05 <LLD <LLD <LLD 0 Cs-137 0.06 <LLD <LLD <LLD 0 TLD Gamma (mrem per Dose (128): N/A 4.9 (120/120) (c) No. 85 9.9 (4/4) (e) 4.4 (8/8) 0 standard 3.2 - 11.7 0.2 e 294* 9.0 - 11.7 3.6 - 5.3 l month) l l
u--- u - - . ANNUAL SUPMARY TABLE NOTES
* =
Data for the Annual Summary Tables is based on RETS required samples only. N/A = Not applicable.
=
(a) Fraction of detectable measurement to total measurement.
=
(b) Location is distance in miles, and direction in compass degrees. Location numbers keyed to Table 3.3-1 and results table location designation numbers.
=
(c) Indicator TLD locations are: #7, 23, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93, 6 94,95,96,97,98,15,18,56, and 58. Control TLDs are all TLDs located beyond the influence of the site (#14, 49).
=
(d) Indicator samples from environmental stations R1 off-site, R2 off-site, R3 off-site, and R4 off-site. Control samples are samples from R5 off-site environmental station.
=
(e) This dose is not representative of doses to a member of the public since this area is located near the north shoreline which is in close proximity to the generating facility and is not accessible to members of the public (see Section 5.2.4, TLDs).
=
(f) The RETS criteria for indicator milk sample locations includes locations within 5.0 miles of the site. There are no milk sample locations within 5.0 miles of the site. Therefore, milk samples are collected from locations greater than 5.0 miles from the site based on the location D/Q values.
I 5.0 RESULTS EVALUATION AND DISCUSSION Each year the results of the Annual Radiological Environmental Monitoring Program are evaluated considering natural processes in the environment and the collection of past environmental radiological data. A number of factors are considered in the I course of evaluating and interpreting the Annual Environmental Radiological Data. This interpretation can be made using several methods including trend analysis, population dose, risk estimates to the general population based on environmental concentrations, effectiveness of plant effluent controls and specific research areas. l The report not only presents the data collected during the 1993 sample program but also assesses the significance of radionuclides detected in the environment. Itis important to note that detection of a radionuclide is not, of itself, an indication of environmental significance. Evaluation of the impact of the radionuclide in terms I of potential increased dose to man, in relation to natural background, is necessary to determine the true significance of any detection. There are four separate groups of radionuclides that were measured in the environment in the media analyzed for the 1993 sampling program. The first of l these groups consists of those radionuclides that are naturally occurring. The i environment contains a broad inventory of naturally occurring radioactive elements. ! l Components of natural background include external cosmic and terrestrial radiation, radionuclides deposited in the body, and radon and its decay products. Naturally occurring radionuclides, such as Th-228, Ra-226, Be-7 and K-40 contribute, along with radon, to the annual per capita background dose which is equal to approximately 300 mrem per year (Reference 17). Comparisons ofprogram samples I to natural background radiation are made throughout this section to help put program results into perspective and to aid the reader in determining what, if any, significance is associated with the Radiological Environmental Monitoring Program (REMP) results. I The second group of radionuclides that were detected are a result of the detonation of thermonuclear device,s in the earth's upper atmosphere. Atmospheric nuclear ' testing during the early 1950s produced a significant inventory of radionuclides presently found in the lower atmosphere as well as in ecological systems. In 1963 lI an Atmospheric Test Ban Treaty was signed. Since the treaty, the global inventory l l of man made radioactivity in the environment has been greatly reduced through the I 5-1 l I
m-I decay of short lived radionuclides and the removal of radionuclides from the food l, chain by such natural processes as weathering and sedimentation. This process is referred to in this report as ecological cycling. Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China. In each l case, the usual radionuclides associated with nuclear detonations were detected for several months following the test and then after a peak detection period, diminished to a point where most could not be detected. Although reduced in frequency, g atmospheric testing continued into the 1980's. The resulting fallout or deposition 5 from these most recent tests has influenced the background radiation in the vicinity of the site and was evident in many of the sample medias analyzed over the years with the highest concentration noted in samples for the 1981 Environmental Surveillance Program. Cs-137 was the major byproduct of this testing and is still detected in a number of environmental media. l A third group of radionuclides was detected as a result of the Chernobyl accident which occurred in the Soviet Union in April 1986. The resulting fallout or E deposition from this accident influenced the background radiation in the vicinity of 5 the site and was easily detected in many of the sample media analyzed during 1986. Quantities of Nb-95, Ru-103, Ru-106, I-131, La-140, Cs-134, and Cs-137 were detected in air particulate samples during May and June of 1986. Milk samples collected and analyzed after April,1986 contained measurable concentrations of I-131 and Cs-137. The origin of these radionuclides was a direct result of fallout l from the Chemobyl accident. g The fourth group of radionuclides that may be detected in the environment are those that are related to nuclear power technology. These radionuclides are the byproduct of the operation oflight water reactors. These byproduct radionuclides are the same , as those produced in atmospheric weapons testing and found in the Chernobyl , fallout. This commonality makes an evaluation of the source of these radionuclides that may be detected in environmental samples difficult, if not impossible. During 1993, H-3 and Cs-137 were the only potentially plant-related radionuclides detected l in the RETS samples. A number of factors must be considered in performing radiological sample data I evaluation and interpretation. The evaluation is made at several levels including l trend analysis and dose to man. An attempt has been made not only to report the 5-2 Il I
data collected during 1993, but also to assess the significance of the radionuclides. detected in the environment as compared to natural and other man-made radiation sources. It is important to note that detected concentrations of radionuclides in the environment as a result of mans technology are very small and are of no or little i significance from an environmental or dose to man perspective. l The 1987 per capita dose was determined to be 360 mrem per year from all sources, as noted in the NCRP Report No. 93 (Reference 17). This average dose includes such exposure sources as natural radiation, occupational exposure, weapons testing, i consumer products and nuclear medicine. The 1987 per capita dose rate due to natural sources was 300 mrem per year. The per capita radiation dose from nuclear power production nation wide is less than one mrem per year (Reference 10). The natural background gamma radiation in the environs of the Nine Mile Point Site, resulting from radionuclides in the atmosphere and in the ground, accounts for approximately 60 - 65 mrem per year. This dose is a result of radionuclides of cosmic origin (for example, Be-7), of a primordial origin (Ra-226, K-40, and Th-232) and, to a much smaller extent, of a man-made origin from weapons testing. A dose of 60 mrem per year, as a background dose, is significantly greater than any possible doses as a result of routine operations at the site during 1993. The results for each sample media is discussed in detail in Section 5.0. This includes a summary of the result, the estimated environmental impact, a detailed i review of any relevant detections with a dose to man estimate where appropriate, ' and an analysis of possible long term and short term trends. In the routine implementation of the Radiological Environmental Monitoring Program, additional or optional environmental pathway media are sampled and analyzed. These samples are obtained to monitor the secondary pathways and to maintain the analytical data base established in 1975 when the plant began commercial operation. These additional samples include; aquatic vegetation I (cladophora), bottom sediment, mollusk, milk (Sr-90), meat, poultry and soil samples. In addition to the optional sample media, additional locations are sampled and analyzed for those pathways required by Technical Specifications. These additional sample locations are obtained to ensure that the important environmental pathways are monitored in a comprehensive marmer. Data from additional sample 5-3
I locations common with the required Technical Specification sample media are included in the data presentation and evaluation. When additional locations are included, the use of this data will be specifically noted in Section 5.0. l Section 6.0 contains the analytical results for the sample media addressed in this report. Tables are provided for each required sample media analyzed during the 1993 program. Section 7.0, titled HISTORICAL DATA, contains statistics from previous years environmental sampling. The process of determining the impact of plant operation on the environment includes the evaluation of past analytical data, a tool by which trends are discemed. As state-of-the-art detection capabilities improve, data comparison is difficult in some cases. For example, Lower Limits of Detections l (LLDs) have improved significantly since 1969 due to technological advance in g laboratory procedures and analytical equipment. I I I I I I I! l I' II 5-4 I I
1 5.1 AQUATIC PROGRAM . 1 The aquatic program consists of samples from three environmental pathways. These pathways are: o Shoreline Sediment o Fish o Surface Waters Section 6.0, Tables 6.1 through 6.4 represent the analytical results for the aquatic l samples collected for the 1993 sampling period. i
]
s [ 5-5
I 5.1.1 SIIORELINE SEDIMENT RESULTS l A. Results Summary A total of four sediment samples were collected for the 1993 sample J program. Small concentrations of Cs-137 were detected in three of the l four 1993 samples. Cs-137 was detected in the two samples taken at l Sunset Beach which is the indicator location. The Cs-137 , concentrations ranged from a minimum of 0.18 pCi/g to a maximum of 0.46 pCi/g. The mean concentration was 0.32 pCi/g. Cs-137 was detected in one of the control location samples at a concentration of 0.027 pCi/g. The source of the Cs-137 detected in the indicator shoreline sediment is considered to be the result of fallout from l atmospheric nuclear weapons testing and not from operations at the site, l This is based on the fact that Cs-137 was also detected at the control location. The mean level of Cs-137 measured in 1993 samples shows l an increase in the mean concentration from 0.13 pCi/g (1991 and 1992) to 0.32 pCi/g measured in 1993. The 1993 results are consistent with i results for 1989 and 1990 (0.29 pCi/g). The concentration measured at the control location was 0.027 pCi/g. The calculated potential whole body and skin doses which may result from the measured Cs-137 concentrations are very small and are insignificant when compared to l natural background doses. g; No other plant related radionuclides were detected in the 1993 shoreline gl sediment samples. E ' I' I' I I 5-6 I I
)
B. Data Evaluation and Discussion Shoreline sediment samples are routinely collected twice per year from the shoreline of Lake Ontario. Samples are collected from one indicator location (Sunset Beach), and one control location (Lang's Beach). The first sample collection was made in May at both the indicator and control locations. The second shoreline sample collection was made in October 1993 again, at both the indicator and the control locations. The results of these sample collections are presented in Section 6.0, Table 1. Several radionuclides were detected in sediment samples using gamma spectral analysis. l Three of the detected radionuclides were naturally occurring. K-40 was detected at both the control location and indicator location. The results ranged from 19.6 pCi/g (dry) to 20.5 pCi/g (dry) at the indicator location, and 10.5 pCi/g (dry) to 12.7 pCi/g (dry) at the control location. Concentrations of AcTh-228 and Ra-226, which are naturally occurring, were also detected at both indicator and control locations. Cs-137 was present in the indicator samples collected for the 1993 program. The mean concentration for these two samples was 0.32 pCi/g (dry). The principle source of the Cs-137 present in the environment has been the atmospheric testing of nuclear weapons. Cs-137 and Cs-134 are both produced in fission reactors and were introduced into the environment from the accident at Chernobyl, but only Cs-137 is found in current weapons test debris. Since Cs-134 has a significantly shorter half-life, detected concentrations of Cs-137 attributable to plant operations (e.g., recent releases), should be accompanied by Cs-134. An absence of such corroborating Cs-134 concentrations would indicate that the presence of Cs-137 in these samples is not distinguishable from the existing background and is attributed primarily to weapons testing i L and residual concentrations; i.e., not to recent plant operations. This assessment is further substantiated by the presence of Cs-137 in the control sample. i L I 5-7 l
1 The difference in the concentration of Cs-137 in the control samples may be attributed to the differences in the sediment type at the two l locations. Few shoreline regions west of the site contain fine sediment and/or sand which would be representative of the indicator location. It l is difficult to obtain control samples which are comparable in physical , and chemical characteristics to the indicator samples. Other factors, ! which include changing lake level and shoreline erosion, further complicate any consistency in shoreline sediment sampling. Soil ) samples from locations beyond any influence from the site, have contained levels of Cs-137 equal to or greater than the concentration found in 1993 shoreline sediment. Cs-137 in soil samples is attributed to weapons testing fallout. Therefore, most shoreline sediment sample containing soil would also contain Cs-137. l C. Dose Evaluation
)
The radiological impact of Cs-137 measured in the shoreline rediment
)'
can be evaluated on the basis of dose to man. In the case of shoreline sediments, the critical pathway is direct radiation to the whole body and skin. Using the parameters found in Regulatory Guide 1.109, the potential dose to man in mrem per year can be calculated. The following regulatory guide values were used in calculating the dose to l man: gj o A teenager spends 67 hours per year at the beach area or on the shoreline. 2 o The sediment has a mass of 40 kg/m (dry) to a depth of 2.5 cm. o The shoreline width factor is 0.3. I o The maximum measured concentration of 0.46 pCi/g (dry) remains constant for the year. 5-8 I I
I l Using these conservative parameters, the potential dose to the maximum exposed individual (Leenager) would be 0.0016 mrem / year to the whole I body and 0.0018 mrem / year to the skin. This calculated dose is very small and is insignificant when compared to the natural background I annual exposure of approximately 60 mrem. D. Data Trends The average Cs-137 concentrations in the shoreline sediment indicator j samples for 1993 was 0.32 pCi/g which is approximately equal to the concentration measured in 1989 and 1990. The mean values for 1989 and 1990 were 0.29 pCi/g. The mean concentration for 1993 shows an increase in concentration by a factor of two and one half from the 1991 and 1992 indicator means. The presence of Cs-137 in the control sample was the first positive measurement at the control location since sediment sampling was implemented in 1985.
.I A review of indicator and control sample results for 1985 - 1988 l indicate only naturally occurring radionuclides present in shoreline sediment. The period from 1989 - 1992 show the presence of Cs-137 in the indicator samples. The five year data base shows an emergence of Cs-137 concentrations in 1989 which continues through 1993. The I trend since 1989 shows a reduction in Cs-137 concentrations over the four year period to the concentration of 0.13 pCi/g measured in 1992.
The mean concentration measured in 1993 is an increase from the two prior years. l Shoreline sediment sampling commenced in 1985. Prior to 1985, no data was available for long term trend analysis. I Tables 1 and 2 in Section 7.0 illustrates historical environmental data for shoreline sediment samples. I I 5-9 I
I 5.1.2 FISII SAMPLE RESULTS A. Results Summary A total of 27 fish samples were collected for the 1993 sample program. Analysis of the 1993 fish samples exhibited detectable concentrations of l radionuclides related to past weapons testing and natural origins (naturally occurring). Small concentrations of Cs-137 were detected in approximately 37% of the total fish samples collected from both the on-g' site and off-site locations. This percentage is slightly higher than the previous year which had a positive detection in 30% of the samples. The ratio of positive detection to total samples collected was higher for the indicator samples (47%) than for the control samples (27%). l Detectable concentrations of K-40, a naturally occurring radionuclide, were found in all fish samples collected for the 1993 program. No other radionuclides were detected in the 1993 fish samples. l The detectable levels of Cs-137 in the fish samples are small. The control and indicator mean concentration values were 0.033 and 0.028 pCi/g respectively. These low levels of Cs-137 represent no significant dose to man or impact on the environment. As noted above, the measured concentrations of Cs-137 in the fish samples are the result of fallout from past weapons testing. Comparable concentrations of Cs-137 ll are routinely found in samples of other aquatic media such as shoreline sediment, bottom sediment and aquatic vegetation. The potential whole g' body and critical organ doses calculated as a result of fish consumption by humans is extremely small. The dose that could result from the g a Cs-137 in fish would be considered background exposures because of the sources of the CsJ37. The fish sample results demonstrate that plant operations at the Nine Mile Point Site have no measurable radiological environmental impact on the upper levels of the Lake Ontario food chain. The 1993 results continue to show a long term downward trend in fish Cs-137 concentrations with concentrations stabilizing over the last 9 - 10 years. The mean indicator Cs-137 concentration for 1993 and 1986 were the l second lowest measured value since the beginning of the surveillance program 20 years ago (1974). 5-10 I
H. Data Evaluation and Discussion Fish collections were made utilizing gill nets at one location greater than l five miles from the site (Oswego Harbor area), and at two locations in the vicinity of the lake discharges for the Nine Mile Point Unit #1 (#02), and the James A. FitzPatrick (#03) generating facilities. The Oswego l Harbor samples served as control samples while the NMP (#02) and JAF (#03) samples served as indicator samples. All samples were
- analyzed for gamma emitters. Table 6-2 shows individual results for all 1
the samples in units of pCi/g (wet). The spring fish collection was made up of thirteen individual samples representing five separate species. Lake trout, white sucker, chinook salmon, smallmouth bass, white perch and brown trout were collected from a combination of the lake sample locations. White sucker, brown trout and lake trout where collected at all three sample locations. The total fall fish collection was comprised of fourteen individual samples representing eight individual species. Brown trout, smallmouth bass, walleye and salmon samples were collected at the indicator sampling locations (NMP and JAF). One sample of each of these species was also collected at the control location (Oswego Harbor). Cs-137 was detected in three of the eight indicator samples and in one l of the five control samples collected during the spring. Indicator ! samples showed Cs-137 concentrations which ranged from a minimum of 0.024 pCi/g (wet) to a maximum of 0.035 pCi/g (wet). The single control sample Cs-137 concentration was 0.036 pCi/g (wet). The average indicator Cs-137 concentration of 0.028 pCi/g (wet) was slightly less than the single control concentration of 0.036 pCi/g (wet). The indicator results, though lower, are not significantly different from the ! control results and the measured concentrations ofCs-137 are considered i to be representative of background concentrations. The maximum detected Cs-137 concentration in both the indicator and the control location was measured in samples of walleye. l 5-11 i i _-
I l In the fall collectien, Cs-137 was detected in six of the fourteen samples collected from both the control (1 of 5) and indicator (5 of 9) locations. Indicator samples showed a mean Cs-137 concentration that was slightly lower than the one positive control sample. The measured concentrations are not significantly different from one another with the g indicator mean equal to 0.027 pCi/g (wet) and the single control value 5 equal to 0.030 pCi/g (wet). The Cs-137 concentrations at the indicator locations ranged from 0.018 to 0.035 pCi/g (wet). l The following graph presents the average Cs-137 concentrations for the l' fish species analyzed for 1993. Walleye samples yielded the highest average Cs-137 concentration for the control locations and chinook g salmon yielded the highest Cs-137 concentration for the indicator location. I JAMES A. FITZPATRICK N.P.P. m FISH Cs 137 1993
* < n amensos w twi e on Avoroge of Goemg and fab Comercenas l g m suoicaron a cournot I
I I 5-12 I I
l l l l K-40 was detected in all of the spring samples collected. K-40 is a naturally occurring radionuclide, and is not related to power plant operations. Ra-226, also naturally occurring, was found at varying levels at both the indicator and control locations. No other radionuclides were detected in the spring fish samples. Naturally occurring K-40 was detected in all of the fall samples collected. Ra-226, also naturally occurring, was detected intermittently at varying concentrations at the indicator and control location samples. No other radionuclides were detected in the fall fish samples. C. Dose Evaluation Some Lake Ontario fish species may be considered an important food source due to the local sport fishing industry. Therefore, these fish become an integral part of the human food chain. Based on the importance of fish in the local diet a conservative estimate of potential dose to man can be calculated. Assuming that an adult consumes 21.0 kg of fish per year (Regulatory Guide 1.109 maximum exposed age group) and the fish consumed contains an average Cs-137 concentration of 0.028 pCi/g (wet)(annual mean result ofindicator samples for 1993), the whole body dose received would be 0.042 mrem per year. The organ of interest in this case is the liver which would receive a [ / calculated dose of 0.064 mrem per year. The Cs-137 w' hole body and organ doses are conservative potential doses associated with consuming ) fish species from the Nine Mile Point area which are represented by the indicator samples. Due to the long half life of Cs-137, no radiological decay is assumed for the calculation of doses. Conservative whole body and organ doses can be calculated for the f consumption of fish from the control location as well. In this case the consumption rate is assumed to remain the same (21.0 kg per year) and , the average annual Cs-137 concentration for the control samples is 0.033 pCi/g (wet). The potential calculated Cs-137 whole body dose is 0.049 mrem per year and the associated dose to the liver is 0.076 mrem per year. l 5-13
1 1 In summary, the potential whole body and organ doses observed as a g result of consumption of fish is small. The dose to man received from i l both the indicator and control sample groups are considered to be ' background exposures. The dose to man from operation of the plants at Nine Mile Point via the fish pathway is of no significance. l D. Data Trends Results for the previous five years (1988 through 1992) have shown a i consistently stable trend for Cs-137 levels in control and indicator )' samples. During the period of 1988 through 1992, control and indicator mean results were consistent with a small rise in 1990. The graph , below illustrates the mean Cs-137 concentration for 1993 and the previous six years. JAMES A. FITZPATRICK N.P.P. FISH Cs.137 = 1993 0 04 n : Ql,f 0 036
'+<
I 0 03 j$5 45 E , 4
=
g { ,,",, mg TE 15 ;5 - 15 sf
"" sig Mg 15 '
~R :S C5 Y W
'"' 93 '3 f 13 si E ypg g3 ag 1,3 3 ggg n g :5 Cs ';h5 [T{ 5, i
in.
.TE
..0 S'E 2
. .n M
l E INDICATOR E CONTROL I The long term trend shows that mean concentrations of Cs-137 for I indicator samples has decreased from a maximum concentration of 1.4 pCi/g (wet) in 1976 to a minimum level of 0.024 pCi/g (wet) in 1992. g' Control sample Cs-137 results have also decreased from a maximum level of 1.2 pCi/g (wet) in 1976 to a minimum level of 0.022 pCi/g (wet) in 1992. The 1993 results were slightly higher than 1992 results. 5-14 I I
The general decreasing long term trend for Cs-137, illustrated in the graph below, is most probably a result of the cesium becoming unavailable to the ecosystem due to ion exchange with soils and sediments and radiological decay. The concentrations of Cs-137 detected since 1976 in fish are a result of weapons testing fallout. The general downward trend in concentrations will continue as a function of additional ecological cycling and nuclear decay. There was no apparent effect from the 1986 Chernobyl Nuclear Plant accident during 1986 relative to Cs-137 results in fish samples although an effect may have been detected during the period of 1987 through 1990 since both indicator and control location mean results increased slightly. [ JAMES A. FITZPATRICK N.P.P. FISH Cs-137
~ ~ ~
1 ii ; os -
- q. j f 1
i 1 on h l E b e . ., . _ . __ _ _ _ __ . _ _, _ . _ _ _ _ N 1 EEEEEE!!EE!!!iii!!!! E INDICATOR E CONTROL The 1993 mean Cs-137 indicator concentration of 0.028 pCi/g (wet) shows a decrease in concentration from 1976 by a factor of 50. Control sample results have decreased from a maximum level of 1.2 pCi/g (wet) in 1976 to a level of 0.033 pCi/g (wet) in 1993. Fish results for the 1993 control samples show a decrease in concentration by a factor of approximately 28 when compared to preoperational data (1974) and by a factor of about 36 compared to 1976. H 5-15
Tables 7-3 and 7-4 in Section 7.0 show historical environmental sample ! data for fish. Full size reproductions of the fish result graphs are found in Section 8.0. l l 4 i 4 i I i I I I J I I I 5-16 I I
5.1.3 SURFACE WATER (LAKE) A. Results Summary The Radiological EfDuent Technical Specifications (RETS) required that monthly surface water samples be taken from the respective inlet water supply of the James A. FitzPatrick N.P.P. and Niagara Mohawk's Oswego Steam Station. 'n conjunction with the RETS sample, three additional Lake Ontario surface water locations are sampled and analyzed. These additional locations are the Oswego City Water Intake, the NMP Unit #1 Intake and the NMP Unit #2, Intake. Gamma spectral analysis was performed on 24 monthly composite samples from the RETS locations and on 36 monthly composite samples from the additional sample locations. The results of the gamma spectral analysis show that only two naturally occurring radionuclides were detected in samples from the five locations (60 samples) collected for the 1993 Sampling Program. Both of these radionuclides, K-40 and Ra-226, are naturally occurring, and are not related to operations of the plant. Monthly composite samples show no buildup of gamma emitting isotopes in the waters of Lake Ontario as a result of the operation of the plant. Quarterly composite samples from the same locations are analyzed for tritium. The 1993 annual mean tritium concentration for the Oswego Steam Station Inlet (control location) was 188 pCi/l with a maximum measurec concentration of 230 pCi/l. Annual mean concentration for the JAF inlet, which serves as the indicator location, was 242 pCi/l with a maximurr measured concentration of 280 pCi/1. Results from the last three years show slightly higher concentrations at the indicator locations relative ta the control sample results. Surface water samples demonstrate that there is no measurable radiological impact on the surface waters of Lake Ontario from tritium concentrations. The mean concentration for the indicator and control are within the normal statistical variations for radiological analysis. The levels of tritium are routinely variable within the range of 200 - 500 pCi/l. The tritium results for 1993 are consistent with previously measured lake concentrations and indicate a small decreasing three year trend in tritium levels in the lake in the samples taken at the site. 5-17
I B. Data Evaluation and Discussion Gamma spectral analysis was performed on monthly composite samples from five Lake Ontario sampling locations. K-40 and Ra-226 were l detected in samples from the five locations over the course of the 1993 sampling program. Both of these radionuclides are naturally occurring gi ' and are not plant related. ' K-40 was detected consistently in both of the Technical Specification required intake canals. The James A. FitzPatrick inlet canal samples and Oswego Steam Station samples showed K-40 was detected in all twelve monthly samples. Ra-226 was also detected intermittently in both locations required by Technical Specifications and at the other l optional sample locations. l Tritium samples are quarterly samples that are a composite of the appropriate monthly samples. Tritium was detected in each of the eight samples taken at the two locations required by Technical Specifications. E Tritium concentrations for the James A. FitzPatrick inlet canal ranged 5 from 200 pCi/ liter to 280 pCi/ liter and showed a mean concentration of 242 pCi/ liter. The Technical Specification control location (Oswego Steam Station inlet canal) showed tritium results which ranged from 160 l pCi/ liter to 230 pCi/ liter. g Tritium was also detected in each of the twelve optional samples taken. The tritium results ranged from 160 pCi/ liter to 330 pCi/ liter for the optional samples taken. The maximum tritium concentration of 330 E pCi/l was measured in the third quarter Nine Mile Point Unit 2 inlet 5 sample. Samples collected from the Oswego City water supply exhibit tritium I concentrations in the range of 180 pCi/l to 230 pCi/l with a mean concentration of 212 pCi/l. l I 5-18 I l I 1
l 'I l ,l A summary of tritium results for the 1993 sample program is listed below: 'I Sample Tritium Concentration pCi/ liter Location Minimum Maximum 'I JAF Inlet 200 280 Mean (Annual) 242 Oswego Steam Inlet 160 230 188 NMP #1 Inlet 160 320 212 NMP #2 Inlet 200 330 242 'E 5 City Water Intake 180 230 212 C. Dose Evaluation l The Oswego Steam Station is considered a control location because of its distance from the site and the influence oflake current patterns and current patterns from the Oswego River located nearby. The current patterns distinguish the Oswego Steam Station intake and the near by I Oswego City water intake as an "up-current" sampling point and the JAFNPP inlet canal as a "down-current" sampling point. The Nine Mile Point Site is located such that it does not have a radiological impact on Oswego drinking water supply. The Oswego City water intake is located west of the Oswego Steam Station inlet placing it upstream from l the Nine Mile Point Site. The tritium concentrations measured in these upstream or control locations are representative of background levels present in Lake Ontario. l The impact of background levels of tritium in water to members of the public is minimal. This can be evaluated by calculating a dose to the whole body and maximum organ. Using Regulatory Guide 1.109 methodology, ingestion of water (5101/yr) at the indicator location (242 pCi/1) would result in a dose of 0.025 mrem to the whole body and l 0.025 mrem to the child liver. The doses at the control locations were 0.019 mrem whole body and 0.019 mrem to the child liver. Drinking water sampled in Oswego is drawn from Lake Ontario at a location l more distant than the control location. Doses from tritium at this !I 5-19 I
I location were 0.022 mrem to the whole body and 0.022 mrem to the child liver. Doses received as a result of water ingestion are approximately the same. The theoretical dose received from the indicator location was slightly higher, although well within natural l variability. Doses from all water sampled are considered background g doses and are negligible. D. Data Trends There are no data trends for gamma emitters such as Cs-137 and Co-60 as historically these radionuclides are not detected in lake water samples. Tritium results for the 1993 lake water samples were consistent with l results from the previous five years for both the indicator and control locations. During the five year period the maximum indicator and control concentration were measured in 1988. The mean tritium concentrations for the period of 1988 - 1992 range from 186 pCi/l to 320 pCi/l for the control and 225 pCi/l to 460 pCi/l for the indicator location. The mean 1993 tritium concentrations for the control and indicator locations were 188 pCi/l and 242 pCi/l respectively. The 1993 indicator results are slightly lower than the previous two years and approximately one half of the mean concentration for 1988. The 1993 data is consistent with concentrations measured since 1989. Mean tritium results of the control INation (Oswego Steam Station) cannot be evaluated with reged to long term historical data since l sampling was only initiated at this location in 1985. Some idea of the variability of historical control sample data can be obtained by a review of previous data from the City of Oswego drinking l water samples. These drinking water samples are likely to be g representative of the current control location because of the effects of the distance, predominate lake currents, and the discharge of the Oswego River. The Oswego City water intake is located in the same vicinity as the Oswego Steam Station inlet though offshore. The maximum annual 5-20 I I
mean concentration of city water was found in 1976 (652 pCi/l) and the minimum in 1982 (165 pCi/l). The following graph illustrates the concentrations of tritium measured ' in Lake Ontario over the past 18 years at both an indicator and control . location. l 1 JAMES A. FITZPATRICK N.P.P. SURFACE WATER TRITIUM 1000
,,,.....-0.
.m..-,
10 0 600 l g E EEEEEi!!!E!!!!Ei!!EE m lNDICATOR O CONTROL * * * sn. Annual mean tritium results from previous city water samples from 1976 to 1993 show that the tritium concentrations have fluctuated over the years. The maximum annual mean concentration was found in 1976 (652 pCi/ liter) and the minimum in 1982 (165 pCi/ liter). Results for the period of 1982 through 1989 shows that the indicator samples were higher than the control samples. This trend reversed itself in 1990 and retumed in 1991 through 1993. ( ( 5-21 ) l mm_
1 I 5.2 TERRESTRIAL PROGRAM The terrestrial program consists of samples from four environmental pathways. These pathways are: l o Airborne particulate and radiciodine i E 1 o Direct radiation B o Milk l 1 i o Food Products l! Tables 6-5 through 6-14 represent the analytical results for the terrestrial samples 1 collected for the 1993 reporting period. I I I ! Il I I i 5 I I 5-22 I 4
5.2.1 AIR PARTICULATEGROSS BETA A. Results Summary Weekly, air samples were collected and analyzed for gross beta paniculate activity. A total of 53 samples were collected from the control location R-5 and 212 samples were collected from the indicator locations R-1, R-2, R-3 and R-4 during 1993. These five locations are j required by the Technical Specifications. Additional air sampling locations are maintained and discussed under Section 5.2.1.B below. The mean concentration of the control location, R-5, was 0.013 pCi/m3 for 1993. The mean concentration for the indicator locations was 0.014 3 pCi/m for 1993. The indicator and control results are essentially equal and show that there are no increased airborne radioactivity levels in the general vicinity of the site. These results are the second lowest mean gross beta concentration measure to date since the inception of the site Environmental Monitoring Program in 1969. The consistency of these low concentrations over the past four years may indicate that the natural base line gross beta activity has been reached. It is possible that the manmade radionuclide contribution to the natural background from weapor.s testing can no longer be detected above the background concentrations for naturally occurring beta emitting radionuclides. f B. Data Evaluation and Discussion Ten air sampling locations are maintained in addition to those required by the Technical Specifications. A total of six on-site and nine off-site locations were sampled weekly for gross beta particulate activity. A total of 780 analyses were performed. Five of the nine off-site locations are required by Technical Specifications. These locations are R-1, R-2, R-3, ( R-4 and R-5. R-5 is a control location required by the Technical Specifications and is located beyond any local influence from the site. In addition, optional off-site and on-site air sample locations are maintained from which weekly samples are collected. The optional off-site locations are designated as D-2, E, F, and G. The optional on-site locations are designated as D-1, G, II, I, J and K. r L ( 5-23
I Gross beta analysis requires that the samples are counted no sooner than 24 hours after collection. This allows for the decay of short half-life naturally occurring radionuclides and there by increasing the sensitivity of the analysis for plant related radionuclides. Tables 6-5 and 6-6 in Section 6.0 present the weekly gross beta activity i results for the off-site and on-site stations. , The average yearly gross beta indicator concentration for the indicator stations (R-1, R-2, R-3 and R-4) in 1993 was 0.014 pCi/m 3. The average yearly gross beta control concentration for the off-site station (R-5) was l 0.013 pCi/m 3 Tlle minimum, maximum and average gross beta results for sample locations required by Technical Specifications were: 3 pCi/m Location
- Minimum Maximum Averace R-1 0.007 0.021 0.014 R-2 0.006 0.023 0.015 R-3 0.005 0.025 0.014 R-4 0.007 0.021 0.014 R-5 (control) 0.007 0.022 0.013 l
.< _ ,_,, ,. m e m . m - - _, I l
i l l 5-24 1
The mean weekly gross beta concentrations measured in 1993 are illustrated in the graphs below. JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE FILTER-GROSS BETA 0 04 inehcesor Seatens RL R2. R3 R4 Centres Sunon R6 0 03 0 026 00,6 - g .$ l
..===S . . . . . . _ . .
WEEK # E INDICATOR E CONTROL f. ( f JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE FILTER-GROSS BETA [ .- l 0 0,, __._....R,_R.
, ,3 Conwel Sienon:R6 '
0 026 0 02 00 . i ' ' ' i
, l j
. . . . R . . ......... .......A . .
WEEK # M INDICATOR D CONTROL r E i u r 5-25
l The small fluctuations observed in the gross beta activity over the year can be attributed to changes in the environment, especially seasonal ; changes. The concentration of naturally occurring radionuclides in the lower levels of the atmosphere directly above land are affected by time related processes such as wind direction, precipitation, snow cover, soil l 1 temperature and soil moisture content.
]
1 C. Dose Evaluation l l Dose calculations are not performed based on gross beta concentrations. Dose to man as a result of radioactivity in air is calculated using the specific radionuclide and the associated dose factor. See Section 5.2.2.C for dose calculations from air concentrations. D. Data Trends With the exception of the 1986 sample data, which was effected by the Chemobyl accident, the general trend in air particulate gross beta
, activity has been one of decreasing activity since 1981.
l E' l JAMES A. FITZPATRICK N.P.P. AIR PART!CULATE FILTER-GROSS BETA , ,. ....m..._
$ l. 6 Chemobyl.cessent P;; I .
... ! - a
,, 3 . ,g st u
": hifin( Lird ~ ._ n..,.. _ _
i: : : : : : : : : : : : : : : i rig 1 E INDICATOR 0 CONTROL 5-26
I The trend for the previous five years is a subset of the overall decline g in gross beta concentrations, again with the exception of 1986 when a one year increase was measured as a result of the Chemobyl accident. The 1993 results are second lowest mean concentrations measured when compared to the previous five years for both the indicator and control locations. The change in concentration from the 1991 values is very small. This is illustrated by the following graph. I l I JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE GROSS BETA 0 06 0 045 3 { ..a g kB$$$ EBB E INDICATOR U CONTROL I I I The air particulate gross beta indicator results for 1993 are a factor of 23 less than the concentrations measured in 1969. 1969 concentrations are considered to be preoperational results for the site. For the operational period of 1975 - 1993 the mean annual gross beta concentration at the control station (R-5) has decreased from a l maximum concentration of 0.165 pCi/m3 in 1981 to a minimum of 0.012 pCi/m3 in 1992. The mean annual concentration for the indicator stations for this same time period ranged from a maximum of 0.151 3 pCi/m in 1981 to a minimum of 0.013 pCi/m3 in 1992. For both the I indicator stations and control stations, the gross beta concentration during 1974 to 1982 fluctuated as a result of fallout from the detonation I of thermonuclear weapons. The mean annual results for the years 1983, 5-27
1 1984,1985,1987 and 1988 from both the indicator and control locations have been similar and ranged from 0.018 to 0.026 pCi/m3 . This level ! of activity appears to be at or near baseline range. The 1986 annual mean result was 0.039 pCi/m3 for both the indicator and control stations. This concentration is slightly higher than 1983-1985 and 1987-1992 4 levels, and is attributed to fallout from the Chernobyl accident. Historical data and graphic representations of air particulate gross beta activity are presented in Sections 7.0 and 8.0 respectively. I I I . I
- I I
I I 5-28 I I
5.2.2 MONTHLY PARTICULATE COMPOSITES (GAMMA EMITTERS) A. Resuin Summary No plant related radionuclides were detected in any of the air particulate filter samples collected from the Technical Specifications required sampling locations. These stations are located near the site boundary and off-site. The gamma analysis results for the monthly composite samples routinely showed positive detections of Be-7, K-40, Ra-226, and AcTh-228. Each of these radionuclides is naturally occurring. Be-7 was detected in all the monthly composite samples for the indicator and control locations. K-40, Ru-226 and AcTh were found intermittently in the monthly composite samples from all locations. B. Data Evaluation Discussion Ten additional air sampling locations are maintained in addition to the five required by Technical Specifications. Each of the fifteen weekly air particulate samples were assembled by location to form monthly composite samples. The monthly composite samples required by Technical Specifications are R-1, R-2, R-3, R-4, and R-5. Other sample locations not required by the Technical Specifications for which analytical results have been provided include six on-site locations and four off-site locations. The results of all monthly composite samples are presented in Section 6.0, Table 6-9. Two plant related radionuclides were detected in one of the additional on-site air sample location composite samples. Analytical results of the H on-site air particulate filter for week 24 (06/07/93) showed an elevated gross beta concentration of 0.046 pCi/m3 . Subsequent gamma spectral analysis detected the presence of small concentrations of Co-60 3 (3.75E-2 pCi/m ) and Zn-65 (1.38E-1 pCi/m 3). The measured concentrations are very small (<l.0 pCi/m ) and no procedural or 3 regulatory limits were exceeded. There was no measurable dose to the 5-29
l l general public as these radionuclides were measured at an on-site sample
)
station. Sample results from environmental stations located at the site boundary in the same general direction showed no elevated gross beta g concentration for this same sample period. An assessment of the operational and environmental conditions demonstrate that the presence of the Co-60 and Zn-65 in the air particulate sample was the result of dust loading on the sample filter. The dust contained activity which was previously deposited in the ground. The soil was put into suspension by the winds and site construction activities during the sample period. The measured activity was not the result of plant operation during the sample period. The total maximum dose from the measured concentrations l would be 2.02E-4 mrem to the critical individual whole body and 7.73E-3 mrem to the lung. C. Dose Evaluation The air particulate sampling program showed no off-site dose to man from this pathway as a result of operations of the plant. No plant related radionuclides were detected at any of the sampling locations located at or beyond the site boundary. D. Data Trends No plant related radionuclides were detected during 1993 at the off-site air monitoring locations. As noted above, two plant related radionuclides were detected at one on-site station. Co-60 was detected in each of the years from 1977 through 1984 at both the indicator and control locations with the exception of 1980 when Co-60 was not detected at the control location. The presence of Co-60 in the air samples collected during these years was the result of atmospheric weapons testing. The maximum yearly mean concentration detected during this period was in 1977 when the mean indicator results was 0.0179 pCi/m2 . The mean control value for this same year was 0.0172 pCi/m'. The Co-60 in the air particulate samples trended downward during the 1977 throegh 1984 period to a low mean 5-30 l
l 1 concentration of 0.0008 pCi/m3 at the control location. Co-60 has not been detected in any of the required air particulate samples since 1985. 1 This general downward trend and eventual elimination of Co-60 in the i air samples is illustrated in the following graph. JAMES A. F8TZPATRICK N.P.P. AIR PARTICULATE FILTEP. COMPOSITE Co-60 0 02 1977. 1970 1980-Atmonohere ie.nn, 00:3 0 0,. 0 014 j uo ~.. 0 012 g { 0 01 . 0.008
' ao=
o 0 004 1 0 002
, tEnan , ,. n, . . . . . . . . . . . . . . . . ..
EEE!!EE!!Eii!!!!! E INDICATOR E CONTROL I 1 Historical data shows that Cs-137 is the fission product radionuclide most frequently detected in the air particulate filter composites. Cs-137 was detected in each of the years from 1977 through 1983 at both the control and indicator sampling locations. The maximum concentration for this period were measured in 1977 with a mean indicator concentration of 0.0043 pCi/m 3 and the corresponding control concentration of 0.0034 pCi/m3 . After 1977, the Cs-137 concentration showed a reduction by a factor of approximately two and remained constant through 1981. In 1982, a second reduction in Cs-137 concentration was measured followed by a further reduction in concentration in 1983. Cs-137 was not detected during 1984 and 19'85 in any of the indicator or control air particulate composite samples. 5-31
I l For the period,1986 to 1991, Cs-137 was detected only in 1986 due to the fallout from the Chernobyl accident. The 1986 mean concentration of Cs-137 for the control location was 0.0193 pCi/m 3. The mean concentration of Cs-137 for the indicator location was 0.0183 pCi/m' for the sample period. This overall reduction in Cs-137 results since 1977 E is attributed to nuclear decay and ecological cycling of Cs-137 initially 5 produced as a result of weapons testing. The decrease in air particulate Cs-137 concentrations since 1977 is clearly illustrated on the graph of historical data. I JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE FILTER COMPOSITE Cs437
;:0 ==. -
- LLD Aeooried See Poem.e Desection 0 03 0 026 7 0 02 00s.
00. rg, _ , ..
..H . . . . . . . . . . . . . .
g EEE!!Ei!!!!!!!!!! E INDICATOR E CONTROL I I In 1986, in addition to Cs-137, Zr-95, Ce-141, Nb-95, I-131, Ce-144, Mn-54, Ru-103, Ru-106, Ba-140. These isotopes were detected in air l particulate composite samples as a result of the fallout from the Chernobyl accident. After 1986, no plant related or fallout radionuclides were detected in any of the off-site air particulate composite samples. E A review of the past five years data for air particulate filter composites 5 indicate no plant related radiological impact on the environment. All the historical positive detections of fission product radionuclides were associated with atmospheric weapons testing or the Chemobyl accident. 5-32 I I
Current air particulate filter composite results can not be compared to preoperational data as none exists prior to 1977. Historical data for air particulate results are presented in Section 7.0, Tables 7-11 and 7-12. Full size graphic representation of air particulate composite Co-60 and Cs-137 concentrations are presented in Section 8.0. l I i l l l 5-33
I 5.2.3 AIRBORNE RADIOIODINE (I-131) A. Results Summary ll Iodine I-131 was not detected in any of the 795 samples analyzed for the 1993 program. No radioiodine has been detected off-site since 1986 l
~
l when measurable levels ofI-131 were found as a result of fallout from the Chernobyl accident. B. Data Evaluation and Discussion Airborne radiciodine is monitored at the fifteen air sampling stations used to collect air particulate samples. There are nine off-site locations, l five of which are required by Technical Specifications. The off-site g locations required by Technical Specifications are designated as R-1, R-2, R-3, R-4 and R-5. R-5 is a control station located beyond any E local influence from the plant. Ten air sampling locations are 5 maintained in addition to those required by Technical Specifications. Six of these stations, D-1, G, H, I, J and K, are located on-site. D-2, E, F and G are the optional stations located off-site. Samples are collected using activated charcoal cartridges. They are I analyzed weekly for I-131. The analytical data fcr radiciodine are presented in Section 6.0, Table 6-7 and 6-8. g' i l l C. Dose Evaluation The I-131 airborne sampling program showed no impact due to the I operation of the plant. No radiciodine was detected in any sampling l location. l D. Data Trends No radiciodine has been detected at air sampling locations required by Technical Specifications since 1987. 5-34 I I
The prior five year I-131 data shows no environmental impact or trend I due to plant operations during the period from 1988 through 1992. I-131 was detected twice over the last five year period, in 1986 and 1987. l The 1986 detection was the result of the Chernobyl accident and the 1987 detection was the result of plant operations. 1 Iodine - 131 (I-131) has been detected in the past at control locations. During 1976, the mean off-site I-131 concentration averaged 0.604 3 pCi/m . 1977 showed an I-131 concentration that decreased to 0.323 pCi/m' and for 1978 the concentration decreased by a factor of ten to 0.032 pCi/m'. During 1979 - 1981 and 1983 - 1985, I-131 was not detected at the control locations. I-131 was detected once at the control location during 1982 at a concentration of 0.039 pCi/m2 . I-131 was detected at the on-site locations in 1980 dirough 1983,1986 and 1987. The mean concentrations ranged from 0.013 pCi/m3 in 1980 to 0.119 pCi/m' in 1986. The maximum I-131 concentration of 0.119 pCi/m' was the result of the Chernobyl accident. I-131 was detected in a total of 75 weekly samples collected during the 1986 sample program. The concentrations detected in 1986 ranged from a minimum of 0.011 pCi/m' to a maximum of 0.36 pCi/m'. Each of the positive detections ofI-131 in 1986 were a direct result of the Chernobyl Nuclear accident. 1 Preoperational data for I-131 in air is limited. Results from 1974 ; showed no positive measurement ofI-131. Current data which showed I no measured concentrations of I-131 is co isistent with the 1969 and 1974 preoperational data. A graphic presentation. of airborne radiciodine is presented in Section 8.0. l 5-35
i j 5.2.4 DIRECT RADIATION (TIIERMOLUMINESCENT DOSIMETERS l (TLD)) A. Results Summary I 71 TLD locations are used to measure direct radiation levels in the environment. The dosimeters are collected and read each quarter. The g 1993 results are consistent with those observed in 1992 and previous 5 years. TLD results are evaluated by organizing the locations into five logical groups by geographic location relative to the site. The five logical groups are on-site, site boundary, off-site, special interest and l controls. A summary of the measured exposure in each group are as follows: Dose in mrem per standard month Group Minimum Maximum Mean On-site indicators 3.1 13.6 5.2 Site boundary 3.3 11.7 5.4 Off-site indicators 3.2 5.7 4.3 Special interest Controls 3.2 3.4 5.1 5.7 4.2 4.4 l Location required by Technical Specifications The highest dose was measured at an on-site location. The location is g in the ENE sector between the FitzPatrick plant and the NMP Unit #2 Facility. This TLD is influenced by turbine shine from the two plants. E The site boundary maximum dose was 11.7 mrem per standard month. 5 This TLD is located in the WNW sector along the lake shore and is in close proximity to the NMP Unit #1 plant. The TLD locations along the ! lake shore close to the plants are influenced by the rad waste building and rad waste shipping activities. These environmental dose are not representative of doses measured at the remaining site boundary ll' location. The remaining TLD locations which are located away from the plant are comparable to levels measured at the control locations. l 5-36 I I l
Overall, environmental direct radiation measurement results for 1993 showed no indication ofincreased direct radietion at or beyond the site boundary resulting from operations at the site. B. Data Evaluation and Discussion Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. Badges are obtained from Teledyne Isotopes quarterly and read at the Teledyne Isotopes facility in Westwood, New Jersey. 71 environmental TLDs were collected and read on a quarterly basis during the sample year. The location results are an average of eight independent readings per quarter at each location and are reported in mrem per standard month (See Section 6.0, Table 6-10). During 1993, collections were made during the weeks of March 29, June 28, September 27, and December 27. Most of the locations required by the Technical Specifica. ions during 1993 were initiated in 1985 as a result of the issuance of new Technical Specifications by the NRC. Therefore,1993 results can only be compared to 1985 - 1992 results. Some locations including a number required by the Technical Specifications (i.e., numbers 7,14,15,18, 23, 49, 56, and 58) can be compared to earlier results since these TLDs were established prior to 1985. On-site TLDs are located at special interest areas within the site boundary. With the exception of location numbers 7 and 23, these locations are not required by the Technical Specifications. Locations 7 and 23 are located near the generating facilities at previous or existing on-site air sampling stations and are used to evaluate sectors that do not extend beyond the site boundary. TLDs located at the environmental monitoring stations include numbers 3, 4, 5, 6, 7, 23, 24, 25 and 26. The results for these locations are very consistent with the previous year results. These results ranged from 3.1 to 13.6 mrem per standard month. t 5-37
I Other on-site special interest TLDs are located near the north shoreline of the Nine Mile Point Unit 1, Unit 2 and JAF facilities. They are in l close proximity to radwaste facilities and the Unit I reactor building. These locations include numbers 27, 28, 29, 30, 31, 39 and 47. Results l for these TLDs during 1993 were widely variable and ranged from 5.3 to 33.7 mrem per standard month as a result of activities at the radwaste facilities and the operating modes of the generating facilities. Results g for 1993 are consistent with the ranges of variability noted in 1992 for 5 measurements at or near these locations. Additional on-site TLD locations are located near the on-site Energy I Center and the associated northeast shoreline. These locations include numbers 18,103,106 and 107. TLDs 103,106, and 107 are located l east of the Energy Center and west of the Unit I facility. TLD number g 18 is located on the west side of the Energy Center. Results for this group ranged from 3.9 - 6.0 mrem per standard month for 1993 and were consistent with the 1992 results. The Technical Specification required site boundary TLDs are located in the approximate area of the site boundary, one in each of the sixteen 22 1/2 degree meteorological sectors. .These include numbers 7,18, 23, and 75 - 87. Location numbers 7,18 and 78 - 84 showed results that l were consistent with control TLD results and ranged from 3.3 to 6.0 g mrem per standard month. These site boundary TL.Ds during 1993 were consistent with 1985-1992 results. TLD numbers 23,75,76,77,85,86 , and 87 showed results that ranged up to approximately three times the l control results. These site boundary results ranged from 3.3 to 11.7 l mrem per standard month. This subset of site boundary TLDs are located near the lake shoreline (approximately 100 feet from the shoreline), in close proximity to the reactor building and radwaste facilities of NMPNS Unit 1 and Unit 2 and the radwaste area of the JAF l facility. g An estimate of the net site boundary dose can be made using available TLD results. Measured results from TLDs located near the site boundary in sectors facing the land occupied by members of the public 5-38 I I
i (excluding TLDs near the generating facilities and facing Lake Ontario) can be compared to control location results. The site boundary locations include numbers 7,18, 78, 79, 80, 81, 82, 83 and 84. Site boundary TLD numbers 75,76,77,23,85,86 and 87 were excluded from the net site boundary dose calculation. These areas are near the north shoreline close to the generating facilities and are not representative of dose rates for members of the public. Control locations include numbers 8,14,49, 111 and 113. Net site boundary doses for each quarter in mrem per . standard month are as follows: Quarter Site Boundary
- Control
- Net Site Boundary Dose
- 1 3.8 4.2 -0.4 2 4.0 4.0 +0.0 3 5.3 5.2 +0.2 4 4.2 4.2 +0.0
- Dose in mrem per standard month The third group of environmental TLDs are located four to five miles from the site in each of the eight land based 22.5 degree meteorological sectors. These locations are required by the Technical Specifications. At this distance, badges are not present in eight of the sixteen meteorological sectors which are located over Lake Ontario.
Results for this group of TLDs during 1993 represented a range of 3.4 to 6.3 mrem per s'andard mondi. The range of results is caused by differences in naturally occurring physical conditions and the varying concentrations of naturally occurring radionuclides in the ground at each of the locations. These results are consistent with control TLD results during 1993 and with the 1986 - 1992 results. Results were also congruous with other off-site TLD ~results during 1992 and previous to 1992. These TLDs were established in 1985 and include numbers 88, 89, 90, 91, 92, 93, 94 and 95. l 5-39
I The fourth group of environmental TLDs are located near the site boundary and at special interest areas. Industrial sites, schools, nearby communities, towns, off-site air sampling stations, the closest residence to the site, and the off-site environmental laboratory are included as special interest locations. l Many of these TLDs are required by the Technical Specifications. Others are optional. This group oflocations include numbers 9, 10, 11, 12, 13, 15, 19, 51, 52, 53, 54, 55, 56, 58, 96, 97, 98, 99,100,101,102,108 and 109. TLD g numbers 108 and 109 are new locations that were established during 1988 and 5 were added to assist in the evaluation of the residence TLD locations. In 1993 results ranged from 3.2 to 5.9 mrem per standard month. All of the TLD results from this group were within the general variation of the control TLDs. Results during 1993 were consistent with results noted for previous years. l The fifth category of TLDs are those used to measure the dose rate at the control locations. These TLDs are required by the Technical Specifications and include numbers 14 and 49.- Optional control locations are numbers 8, 111 and 113. Location number 11I was added to the program during 1988 to expand the data base for control measurements. Results for all control locations from 1993 ranged from 3.4 to 5.7 mrem per standard month. Results from 1993 were consistent with previous years results. l C. Dose Evaluation g TLDs located at the site boundary averaged 4.3 mrem per standard month (No. 7,18, 78, 79, 80, 81, 82 83, 84). TLDs placed at the special interest locations averaged 4.3 rnrem per standard month. The control TLD results averaged 4.4 mrem per standard month in 1993 (No. I 8, 14, 49, 111, 113). g The measured mean dose in the proximity of the closed resident was 4.5 mrem per standard month (No.108 and 109) which is consistent with the control measurements. 5-40 I I
The mean dose for each of the geographic location categories demonstrates that there is no statistical difference in the annual dose as a function of distance from the site. The TLD program verifies that operations at the site do not measurably contribute to the levels of direct radiation present in the off-site environment. D. Data Trends A comparison of historical results for TLD results can be made using the different categories of measurement locations. These include site boundary TLDs in each meteorological sector (16 locations), TLDs located off-site in each land based sector at a distance of four to five miles (8 locations), badges located at special interest areas (6 locations) and TLDs located at control locations (4 locations). As noted previously, many of the present TLD locations became effective in 1985 and these results can only be evaluated for 1985 - 1992. TLDs located at the site boundary averaged 6.1 mrem per standard month during 1987. During 1988,1989,1990,1991 1992 and 1993 site boundary dose rates averaged 5.4, 4.8, 4.8, 4.8, 4.2 and 4.3 mrem per standard month respectively. As noted previously, this group of TLDs can fluctuate because several of these TLDs are located in close proximity to the- generating facilities and influenced by operational modes. An increase was noted during f 1986 although such an increase was noted for all TLDs including the control locations. During 1993, site boundary measurements averaged 5.4 mrem per standard month which is lower than the mean for the last five years and consistent with 1992. TLDs located off-site at a distance of four to five miles from the site in each of the land based meteorological sectors (off-site sectors) averaged 5.2 mrem per standard month during 1987. During 1988,1989,1990,1991 and 1992 off-site sector dose rates averaged 5.3,4.9,4.7,4.7 and 4.1 mrem per standard month, respectively. Results for the group averaged 5.0 mrem standard month over the five year period. The 1993 mean dose of 4.4 mrem per standard month is consistent with the previous five year mean and each individual yearly mean. 5-41
I Special interest locations averaged 5.3 mrem per standard month during 1988. During 1987 these same locations averaged 5.1 mrem.1989,1990,1991 and 1992 results averaged 4.9, 4.8, 4.4 and 4.1 mrem per standard month respectively. The 1993 results for these locations averaged 4.5 mrem per l standard month which is consistent with the previous five year average of 4.7 mrem per standard month. g The final group of TLD locations required by the Technical Specifications is the control group. This group (No. 8,14,49,111 and 113) utilizes locations positioned well beyond the site. Results from 1986 for the control group averaged 6.3 mrem per standard month. During 1987, this same group of TLDs averaged 5.4 mrem per standard month. A marked increase was noted in the second quarter of 1986. The increase may have been a result of the l Chemobyl accident. Results for 1988,1989,1990,1991 and 1992 averaged g 5.6,4.7,4.7, 4.7 and 4.4 mrem per standard month respectively. Results for 1993 averaged 4.4 mrem per standard month. The 1993 TLD program results, when compared to the previous five years and preoperational data, shows no significant trends relative to increased dose rates in the environment. , Tables 7-15 and 7-16 show the historical environmental sample data for I environmental TLDs. A graph of historical TLD data is presented in Section 8.0. g I I I I I 5-42 I I
1 5.2.5 M1LK A. Results Summary A total of 72 milk samples were collected and analyzed for the 1993 sample program. Each sample was analyzed for radionuclides using gamma spectroscopy and iodine extraction procedures. There were no plant related radionuclides detected in the indicator or control milk samples collected and analyzed. Naturally occurring K-40 was detected in both indicator and control samples at levels consistent with past years results. B. Data Evaluation and Discussion Milk samples were collected from five indicator and one control location. Technical Specifications require that three sample locations are within five miles of the site. Based on the milk animal census there were no adequate milk sample locations within five miles of the site in 1993. Samples were collected from six farms located beyond the five mile requirement to ensure the monitoring of this important pathway. The five indicator locations ranged from 5.5 to 9.5 miles from the site. The control samples were collected from a farm 17 miles from the site and in a low frequency wind sector (upwind). The control sampling location, No. 65 ceased milking operations in August f 1993. The milk herd was sold and samples were no longer available. A new control location, No. 73 was initiated in the second half of August 1994. The new control location is in the same relative location as the previous control. With the exception of the new control location, the reported locations have been sampled since 1989. The geographical location of each location is Ested below-l Location No. Direction From Site Direction (Miles) I 7 ESE 55 50 E 8.2 55 E 9.0 60 E 9.5 4 ESE 7.8 65 Control SW 17.0 73 Control (8/16/93) SW 13.9 5-43
i I Samples were collected at locations 7, 50, 55, 60, 4 and 65/73 from April , I through December, during the first and second half of each month. Because I-131 was not detected in samples collected during November and December l, l of 1992, no additional samples were required for January through March of l 1993. l Each sample is analyzed for gamma emitters using a gamma spectral analysis. I The I-131 analysis is performed using resin extraction followed by spectral analysis for each sample. I-131 analytical results are provided in Section 6.0, l Table 6-11. Sample analysis results for gamma emitters are provided in l Section 6.0, Table 6-12. Iodine-131 was not detected in any indicator or control samples analyzed during 1993. All I-131 milk results were reported as lower limits of detection i (LLD). The LLD results for all samples ranged from <0.33 to <0.78 pCi/ liter. l l K-40 was the most abundant radionuclide detected in milk samples collected in 1993. K-40 is a naturally occurring radionuclide and is found in many of El 5 I the environmental media sampled. K-40 was detected in every indicator and control sample. The K-40 concentration for all samples ranged from 1190 to 2730 pCi/ liter. Ra-226 was detected intermittently in the milk samples and is a naturally occurring radionuclide. During 1993, Cs-137 was not detected in any indicator or control milk samples. l C. Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant related radionuclides were detected. The dose to man from naturally occurring concentrations of K-40 in milk and other environmental media can be calculated. This calculation illustrates that l the dose received due to exposure from plant effluents is negligible as compared to the dose received from naturally occurring radionuclides. Significant levels of K-40 have been measured in environmental samples. A E 70 kilogram (154 pound) adult contains approximately 0.1 microcuries of K- B 40 as a result of normal life functions (inhalation, consumption, etc.). The dose to bone tissue is about 20 mrem per year (Eisenbud) as a result of internally deposited naturally occurring K-40. 5-44 I I
I l D. Data Trends 1993 results showed no man-made radionuclides detected in milk samples analyzed as part of the environmental surveillance program. In the past six years, Cs-137 was detected in 1986 and 1987. The mean Cs-137 indicator I activity for those years was 8.6 and 7.4 pCi/ liter respectively. I-131 was measured in milk samples in 1986 with a mean concentration of 13.6 pCi/ liter. This activity was a result of the Chemobyl accident. l From 1976 to 1985, Cs-137 and I-131 were intermittently detected. Cs-137 was detected in a 1983 milk sample with a concentration of 5.1 pCi/ liter. In g 1980, I-131 was detected at the indicator and control locations with a mean concentrations of 4.9 and 1.4 pCi/ liter respectively. The Cs-137 and I-131 activity is attributed to Chinese atmospheric thermonuclear weapons testing. The comparison of 1993 data to results over the operating life of the plant and preoperational data (1974) show that Cs-137 and I-131 levels have decreased significantly since 1974. The levels of Cs-137 and I-131 detected prior to the plant going into commercial operation were the result of activities not related to power production at the site. Historical data and a graphic presentation of milk sample results for Cs-137 and 1-131 are presented in Section 7.0, Tables 7-17 and 7-18 and in Section 8.0, respectively. I I I 1 I I l
- I 5-45
'I
5.2.6 FOOD PRODUCTS (VEGETATION) 1 A. Results Summary 1 There were no plant related radionuclides detected in the 20 food product samples collected and analyzed for the 1993 program. Cs-137 was detected ' in one control (off-site) sample at a concentration of 0.008 pCi/g. The i l presence of Cs-137 in the control sample is the result of fallout from atmospheric weapons testing. Detectable levels of naturally occurring K-40 l i were measured in all control and indicator samples collected for the 1993 program. Be-7, a second naturally occurring radionuclide, was detected in 18 l of the 20 samples collected. These results are consistent with the levels ! measured in 1992 and previous years. B. Data Analysis and Discussion Food product samples were collected from five indicator locations and one g control location. The collection of annual food product samples became a requirement as a result of Technical Specification Amendment 127 in 1985. The indicator locations are represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and an annual g garden census. The control location was a garden 15 miles away in a 5 predominately upwind direction. Food product samples collected during 1993, included cabbage and swiss I chard. These sample types are considered broadleaf vegetables. Where broadleaf vegetables were not available, non-edible broadleaf vegetation was l , collected. Non-edible vegetation consisting of bean leaves, squash leaves, i grape leaves, pepper leaves, cucumber leaves and a tomato were collected for l the 1993 program. Samples were collected during the late summer / fall harvest season. I 5 l Each sample was analyzed for gamma emitters on a GeLi/HPGe detector. One fallout radionuclide, Cs-137 was detected in the 1993 samples. Cs-137 was measured in the cucumber leaf sample collected from the control location. The presence of Cs-137 in the control sample is attributed to atmospheric l' weapons testing fallout. 5-46 I I<
Naturally occurring Be-7, K-40, Ra-226 and AcTh-228 were detected in food product samples. The concentration of Be-7 in vegetation samples ranged from 0.09 to 2.48 pCi/g (wet). The concentration of K-40 in indicator and control samples ranged from 1.92 pCi/g (wet) and 6.95 pCi/g (wet). Ra-226 and AcTh-228 were detected intermittently in the samples. The results for naturally occurring radionuclides are consistent with those of prior years. Analytical results for food products are found in Section 6.0, Table 6-14. C. Dose Evaluation The food product sampling results showed no dose to man from this pathway as a result of operation of the pla'nt. No plant related radionuclides were detected in any of the samples taken. D. Data Trends There was one man-made radionuclide (Cs-137) detected in broadleaf edible and non-edible vegetation samples analyzed in 1993. Food product results for the last five years show no trend other than that plant rebted radionuclides are not routinely detected in this sample media. In the previous five years Cs-137 was detected in three of the 107 samples collected. This fact is also accurate for the entire time period of plant operation including preoperational results. Cs-137 has been detected in four separate years since operation began at the FitzPatrick Power Plant. In 1989, Cs-137 was detected in one non-edible broadleaf vegetation sample I collected at an indicator location. The concentration was 0.011 pCi/g (wet) which was close to its LLD. LLD values for all other samples ranged from l
<0.011 to <0.018 pCi/g (wet). Cs-137 was also detected in 1988. Other than naturally occurring levels of Be-7 and K-40, no other radioisotopes were detected from 1986 - 1989.
During the period of 1981 - 1985, Cs-137, Be-7 and K-40 were detected. Cs-137 was found at one indicator location during 1985 at a concentration of 0.047 pCi/g (wet). The levels of Be-7 and K-40 were consistent with natural background levels. There are no discernable trends indicating the presence of plant related radionuclides in food product vegetation samples. l Historical data and graphic presentations of food product results are presented ! in Section 7.0, Tables 7-19 and 7-20, and in Section 8.0. j 5-47
I 5.2.7 LAND USE CENSUS RESULTS A. Results Summary Technical Specifications require that an annual land use census be performed to identify potential new locations for milk sampling and for calculating the I dose to man from plant effluents. In 1993 a milk animal census, a nearest l resident census and a garden survey were performed. No changes were required to milk sampling indicator or control locations in 1993 based on the 1993 mili animal census. The results of the closest residence census conducted in 1993 required no I change to the ODCM closest resident dose calculation reference. l A garden census, not required by Technical Specifications, showed no chang'es g to food product (vegetation) sampling locations for 1993. The garden samples were collected from those locations listed in Table H-1 of the ODCM and E identified in the census as active for 1993. 5 B. Data Evaluation and Discussion A land use census is conducted each year to determine the utilization ofland l in the vicinity of the site. The land use census actually consists of two types of census. A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site. A census covering areas out to a distance of 10 miles exceeds the 5 mile distance required by the Technical Specifications. A resident census is designed to identify the nearest resident in each meteorological sector out to a distance of five miles. The milk animal census is an estimation of the number of cows and goats I within an approximate ten mile radius of the Nine Mile Point Site. The annual census is conducted during the first half of the grazing season by sending questionnaires to previous milk animal owners and also by road li g surveys to locate any possible new locations. In the event the questionnaires are not answered, the owners are contacted by telephone or in person. The 5-48 l
- I
local county agricultural agency is also contacted as a further source of information concerning new milk animal locations in the vicinity of the site. The number of milch animals estimated by the 1993 census was 1036 cows and 10 goats. This is an decrease of 84 cows and a increase of 3 goats from 1992. The locations identified as a result of the milk animal census are illustrated on a map in Section 3.3, Figure 3.3-4. The results of the milk animal census are found in Section 6.0, Table 6-13. The second type of census is a residence census. The census is conducted in order to identify the closest residence within 3 miles in each of the 22.5 degree land based meteorological sectors. There are only eight sectors over land where residences are located within 3 miles. These water sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW. The results of the residence census showing the applicable sectors and degrees and distance of each of the nearest residence are found in Section 6.0, Table 6-15. The nearest resident locations are illustrated on a map in Section 3.3, Figure 3.3-5. l l \ ! 1 I 5-49
l I
5.3 CONCLUSION
The REMP is a continuous program implemented to determine the radiological impact of JAFNPP operations on the local environment. The program is designed and implemented l to be sensitive to small changes in the radiological environment surrounding the site, g The results of the 1993 Radiological Environmental Surveillance Program continues to l clearly demonstrate that there is no significant short term or chronic long term detrimental impact on the environment in the vicinity of the Nine Mile Point site. The environmental ,
- releases from the plant contribute no measurable radiation exposures to the general public as demonstrated by the assessment of environmental media collected and analyzed as part I of the ongoing environmental program. The major radiological impact on the l
environment remains the result of atmospheric weapons testing in the early 1980s and the 1986 accident at the Chemobyl Nuclear Power Plant. Both of these source terms have g contributed to the ubiquitous inventory of Cs-137. The results for the 1993 sample program demonstrate that the concentrations of manmade radionuclides continue to decline since the last major source tenn in 1986. This reduction in environmental concentrations will allow for the site environmental program to become more sensitive to the measurable impact of plant operations on the environment. E' 5 Samples representing food sources consumed at higher trophic levels, such as fish and milk, were reviewed closely to evaluate any impact to the environment or to man. In l addition, the data was reviewed for possible short and long term historical trends. No g measurable environmental impact could be determined as a result from radionuclide deposition considering all possible sources. 1 Doses as a result of naturally occurring radionuclides such as K-40 and Ra-226, contributed the major portion of the total annual dose to members of the general public. El 5 I During 1993, the presence of one fission product radionuclide (Cs-137) was measured in the different sample media. These samples were shoreline sediment, fish and vegetation. The probable source of this radionuclide is past weapons testing. The impact, expressed l as a dose to man, is minimal. The maximum potential dose to man calculated as received from the fish consumption pathway was 0.037 mrem whole body (adult) and 0.054 mrem ll to the critical organ (teen livers). The long term doses to man as a result of anthropogenic sources can mainly be attributed to the Chemobyl accident and atmospheric weapons testing. Most of the radionuclides detected in 1986 as a result of Chemobyl were not 5-50 I 1
detected in subsequent years. Dose received from man-made sources are very small when compared to the dose from naturally occurring sources of radioactivity. The contribution to the whole body dose as a result of plant operations is extremely small when compared to the dose contribution from natural background levels and sources other than the plant. Whole body doses in Oswego County due to all natural sources is approximately 60 mrem per individual per year as demonstrated by control environmental TLDs. The fraction of the annual dose to man attributable to site operation remains insignificant. [ k I 5-51 l l ..
. _ _ . __- _ - _ _ _ _ _ - _ _- __ _ _ ___--- ._ _-_ ----__ __-- -_- A
Il 5.4 REFERENCE l
- 1. Radiological Effluent Technical Specifications, Appendix B to Facility Operating l; License No. DPR-59 For James A. FitzPatrick Nuclear Power Plant, New York Power Authority, Docket No. 50-333, Amendment 127.
- 2. U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1", October,1977.
- 3. Eichholz, G., Environmental Aspects of Nuclear Power. First Edition, Ann Arbor I
Science Publishers, Inc., Ann Arbor, Michigan,1976. l
- 4. National Council on Radiation Protection and Measurements (NCRP),
Environmental Radiation Measurements. NCRP Report No. 50,1976.
- 5. National Council on Radiation Protection and Measurements (NCRP), Natural Backcround Radiation in the United States. NCRP Report No. 45,1975.
- 6. National Council on Radiation Protection and Measurements (NCRP), Cesium-137 from the Environment to Man: Metabolism and Dose. NCRP Report No. 52, 1977.
- 7. National Council on Radiation Protection and Measurements (NCRP), Radiation Exposure from Consumer Products and Miscellaneous Sources. NCRP Report No. '
56,1977. 4
- 8. U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, " Environmental Technical Specifications for Nuclear Power Plants", December 1975.
- 9. U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory I l Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program",
November,1979. l
- 10. Eisenbud, Merril, Environmental Radioactivity. Third Edition, Academic Press, New York, New York,1987.
5-52 I
i l 1. Francis, C. W., Radiostrontium Movement in Soils and Untake in Plants. Environmental Sciences Division, Oak R.idge National Laboratory, U.S. Department of Energy,1978.
- 12. National Council on Radiation Protection and Measurements (NCRP), Radiation Exposure from Consumer Products and Miscellaneous Sources. NCRP Report No.
56,1977.
- 13. Pochin, Edward E., Estimated Ponulation Exposure from Nuclear Power Production and Other Radiation Sources. Organization for Economic Co-operation and Development,1976.
- 14. ICRP Publication Number 29, Radionuclide Releases into the Environment:
Assessment of Dose to Man.1979.
- 15. U.S. Department of Health and Human Services, Prenaredness and Response in Radiation Accidents. National Center of Devices and Radiological Health, Rockville, MD 20857, August,1983,
- 16. Kathren. Ronald E., RADIOACTIVITY IN THE ENVIRONMENT: SOURCES.
DISTRIBUTION. AND SURVEILLANCE. First Edition, Harwood Academic Press, New York, NY,1984. 1
- 17. National Council on Radiation Protection and Measurement (NCRP), Ionizing Radiation Exposure of the Population of the United States, NCRP Report No. 93, 1987
- 18. Knoll, G., Radiation Detection.and Measuremen't. Second Edition, John Wiley &
Sons, New York, New York,1989. 1 l l 5-53 , 1
6.0 REPORT PERIOD ANALYTICAL RESULTS TAllLES
- 6.1 Environmental sample data is summarized in table format. Tables are provided for select sample media and contain data based on actual values obtained over the year. These values are comprised of both positive values
;I and LLD values where applicable.
6.2 The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of l falsely concluding that a blank observation represents a "real" signal (see Section 3.7.3 for detailed explanation). l
;I l
6.3 When the initial count of a sample indicates the presence of radioactivity, I two recounts are normally performed. When a radionuclide is positively identified in two or more counts, the analytical results for that radionuclide is reported as the mean of the positive detections and the associated error for that mean (see Section 3.7.2 for methodology). l l 6.4 Many of the tables are footnoted with the term " Plant Radionuclides". Plant related radionuclides are radionuclies that are produced in the reactor as a result of plant operation either through the activation or fission process. I I I I 6-1 I
, r- u m r, r r r ~ r - - ~ -
TABLE 6-1 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in Units of pCi/g (dry) i 1 Sigma l
!! STATION! COLLECTIDN)
- tCODE*" : DATEv:
gggg - K-40 Co-60 Cs-134 Cs-137 Zn-65 OTHERS** Sunset Beach 05/93 20.Si0.4 <0.08 <0.08 0.46 0.02 <0.24 <LLD e (05) 10/93 19.610.34 <0.06 <0.06 0.1810.01 <0.15 <LLD Lang's Beach 04/93 10.Si0.2 <0.04 <0.04 (06, Control) 0.02710.009 <0.14 <LLD 10/93 12.710.5 <0.05 <0.06 <0.04 <0.15 <LLD Corresponds to sample locations noted on the maps in Section 3.3.
- Plant Related Isotopes
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ A
TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES Results in Units of pCi/g (wet) i 1 Sigma DATEf ?TYPEG (KH40l iMinS41 iCo458)$Fe459)(Co-60;JZni65J (Cs-134L LCs!137% OTHERS*J FITZPATRICK 06/08/93 Lake Trout 3.1510.18 <0.024 <0.024 <0.068 <0.030 <0.063 <0.022 <0.023 <LLD 06/08/93 Brown Trout 4.76i0.21 <0.026 <0.031 <0.071 <0.028 <0.072 <0.024 <0.022 <LLD 06/15/93 Smallmouth Bass 6.46i0.13 <0.031 <0.032 <0.082 <0.030 <0.086 <0.032 0.02610.005 <LLD
$ 06/18/93 White Sucker 9.2310.24 <0.029 <0.032 <0.070 <0.035 <0.084 <0.038 <0.030 <LLD 09/14/93 Brown Trout 3.65i0.21 <0.025 <0.036 <0.078 <0.035 <0.067 <0.025 <0.022 <LLD 09/14/93 Chinook Salmon 5.63i0.13 -<0.027 <0.037 <0.090 <0.029 <0.068 <0.027 0.03510.006 <LLD 09/14/93 Walleye 5.54i0.12 <0.024 <0.029 <0.088 <0.031 <0.064 <0.024 0.02710.005 <LLD 09/14/93 Smallmouth Bass 4.2710.13 <0.032 <0.038 <0.085 <0.025 <0.067 <0.026 0.025i0.005 <LLD
- Plant Related Radionuclides m M M M M M M M M M M M M M M M M M m
_ - _ _ _ _ . _ _ = . _ - -
amm sus uma sus sus aus aus em aus uma mas ses see amm use aus som mum num TABLE 6-2 (Courzuuso) CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES Results in Units of pCi/g (wet) 1 Sigma JDATES / TYPE 1 IK-40j $ 54}l !CoiS8j FFeiS9' llCoE605 sZnf6s! Cs134) (CM137j OTHERS*D NINE MILE POINT 06/08/93 Brown Trout 5.54i0.12 <0.025 <0.035 <0.079 <0.028 <0.071 <0.024 <0.025 <LLD 06/15/93 White Sucker 10.010.2 <0.030 <0.033 <0.076 <0.031 <0.091 <0.040 <0.030 <LLD 06/17/93 Lake Trout 3.50i0.11 <0.024 <0.026 <0.050 <0.029 <0.066 <0.021 0.024i0.004 <LLD 7 06/17/93 Walleye 3.28i0.13 <0.025 <0.025 <0.060 <0.030 <0.057 <0.024 0.03510.006 <LLD 09/14/93 White Sucker 9.1210.25 <0.034 <0.047 <0.107 <0.034 <0.088 <0.034 <0.028 <LLD 09/14/93 Smallmouth - Bass 4.2110.13 <0.029 <0.039 <0.101 <0.031 <0.066 <0.027 <0.025 <LLD i l 09/21/93 Chinook Salmon 4.9810.13 <0.026 <0.029 <0.081 <0.033 <0.075 <0.025 0.01810.005 <LLD 09/21/93 Walleye 4.3510.19 <0.026 <0.033 <0.086 <0.037 <0.068 <0.030 0.030i0.006 <LLD 09/21/93 Brown Trout 5.24i0.22 <0.027 <0.032 <0.069 <0.031 <0.078 <0.025 <0.023 <LLD
- Plant Related Radionuclides
l r l l TABLE 6-2 (Courzwuso) CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES l Results in Units of pCi/g (wet) 1 Sigma
- DATED ETYPE7 :K240 FHn-54L (Co-58; 1Fe'-59j iCoh60- ;Zn-65: JCs1134- -Cs-137c iOTHERS*-
OSWEGO HARBOR (Control) 06/08/93 Brown Trout 3.87i0.26 <0.034 <0.044 <0.112 <0.043 <0.102 <0.035 <0.030 <LLD 06/15/93 White Sucker 3.25i0.17 <0.024 <0.027 <0.059 <0.026 <0.055 <0.021 <0.021 <LLD 06/17/93 Lake Trout 4.0510.25 <0.034 <0.040 <0.083 <0.048 <0.100 <0.030 <0.029 <LLD 06/17/93 Walleye 3.97i0.11 <0.027 <0.028 <0.057 <0.029 <0.071 <0.027 0.036i0.005 <LLD
?
06/17/93 Smallmouth Bass 5.46i0.38 <0.054 <0.054 <0.135 <0.064 <0.129 <0.047 <0.047 <LLD 09/14/93 Brown Trout 3.6010.21 <0.028 <0.039 <0.093 <0.029 <0.067 <0.028 <0.023 <LLD 09/14/93 Chinook Salmon 4.0010.12 <0.027 <0.042 <0.098 <0.033 <0.078 <0.025 0.030f0.007 <LLD 09/17/93 Walleye 4.9710.23 <0.032 <0.035 <0.092 <0.038 <0.080 <0.026 <0.026 <LLD 09/17/93 Smallmouth Bass 3.5510.22 <0.035 <0.036 <0.099 <0.034 <0.064 <0.027 <0.026 <LLD 09/17/93 White Sucker 4.93i0.22 <0.028 <0.034 <0.090 <0.024 <0.087 <0.026 <0.024 <LLD
- Plant Related Radionuclides W W W W W W M M M M M M M M M M. M M M
TABLE 6-3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER (QUARTERLY COMPOSITE SAMPLES) Results in Units of pCi/ liter i 1 Sigma iSTATIONs. CODE! LPERIOD5 $DkT5 'i dTRITIUHi FITZPATRICK* First Quarter 01/04/93 - 03/31/93 2801110 (03, INLET) ' Second Quarter 03/31/93 - 06/30/93 200i100 OSWEGO STEAM
- First Quarter 12/31/92 - 03/31/93 2301110 STATION (08. CONTROL) Second Quarter 03/31/93 - 06/30/93 180i100 NINE MILE First Quarter 12/31/92 - 03/31/93 3201110 POINT UNIT 1**
(09. INLET) Second Quarter 03/31/93 - 06/30/93 200i100 , NINE MILE First Quarter 12/31/92 - 03/31/93 220il10 POINT UNIT 2** (11, INLET) Second Quarter 03/31/93 - 06/30/93 220i100 ! OSWEGO CITY ** First Quarter 12/31/92 - 03/31/93 220il10 WATER (10) Second Quarter 03/31/93 - 06/30/93 220i100
- Samples required by the Technical Specifications
** Optional samples Oswego City Water samples are composites of twice per week grab samples
TABLE 6-3 (Courinuso) CONCENTRATIONS OF TRITIUM IN SURFACE WATER (OUARTERLY COMPOSITE SAMPLES) Results in Units of pCi/ liter i 1 Sigma STATION CODEt- 1 PERIOD 1 :DATE 4 TRITIUM::: FITZPATRICK* Third Quarter 06/30/93 - 09/30/93 2301100 (03. INLET) l Fourth Quarter 09/30/93 - 12/29/93 260i100 OSWEGO STEAM
- Third Quarter 06/30/93 - 09/30/93 180 100 STATION 2 (08. CONTROL) Fourth Quarter 09/30/93 - 12/30/93 160i100 L
NINE MILE Third Quarter 06/30/93 - 09/30/93 1701100 POINT UNIT 1** (09. INLET) Fourth Quarter 09/30/93 - 12/30/93 1601100 NINE MILE Third Quarter 06/30/93 - 09/30/93 330i100 POINT UNIT 2** (11. INLET) Fourth Quarter 09/30/93 - 12/30/93 200190 OSWEGO CITY ** Third Quarter 06/30/93 - 09/30/93 180t100
- WATER (10) l Fourth Quarter 09/30/93 - 12/30/93 230 100 l
l
- Samples required by the Technical Specifications
** Optional samples l
Oswego City Water samples are composites of twice per week grab samples N"""""""""""""""""""-_
_ _ ~ _ _ TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1993 Results in Units of pCi/ liter i 1 Sigma iSTATION CODE *:: TNUCLIDEU " JANUARY) FEBRUARYfi MARCH 1APRILt iHAYL JUNE OSWEGO STEAMt I-131 <0.70 <1.00 <1.00 <0.5 <1.00 <0.40 STATION Cs-134 <2.74 <3.92 <3.21 <3.52 <3.53 <2.90 (08, CONTROL) Cs-137 <3.24 <3.34 <3.38 <2.92 <3.47 <3.56 Zr-95 <6.48 <6.41 <6.10 <6.80 <7.47 <6.44 Nb-95 <4.08 <4.37 <3.99 <4.26 <4.58 <4.09 Co-58 <3.36 <4.10 <3.55 <4.16 <5.16 <3.51 Mn-54 <3.18 <3.75 <3.05 <3.33 <3.86 <3.05 Fe-59 <7.88 <7.94 <8.43 <8.43 <8.90 <8.20 Zn-65 <8.39 <8.52 <8.36 <9.09 <8.23 <8.11 Co-60 <4.02 <4.42 <4.04 <3.25 <4.50 <4.04 K-40 54i12 33114 57il2 185i18 620i16 57 15 $ Ba/La-140 <10.9 <12.6 <9.25 <10.1 <12.2 <10.9 i FITZPATRICKt I-131 <0.80 <1.00 <1.00 <1.0 <1.00 <0.40 (03. INLET) Cs-134 <4.34 <3.09 <3.80 <2.73 <3.45 <5.96 Cs-137 <3.59 <3.30 <3.20 <2.35 <3.29 <4.54 Zr-95 <6.36 <6.91 <7.40 <4.90 <6.89 <8.84 Nb-95 <4.00 <4.32 <4.48 <3.81 <4.49 <5.87 Co-58 <4.02 <3.52 <3.80 <3.23 <3.91- <5.11 Mn-54 <4.12 <3.50 <3.75 <2.76 <3.59 <4.54 Fe-59 <9.20 <8.65 <8.43 <6.80 <8.29 <12.4 Zn-65 <10.0 <8.10 <10.2 <6.61 <8.54 <12.2 Co-60 <4.33 <3.57 <3.75 <3.34 <3.97 <3.97 K-40 1020128 44i13 246120 58i12 220 18 1150i31 Ba/La-140 <7.97 <8.91 <10.2 <11.2 <9.69 <8.63
- Corresponds to sample locations noted on the maps in Section 3.3.
t Samples required by the Technical Specifications.
TABLE 6-4 (Conrznuso) l CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1993 Results in Units of pCi/ liter 1 Sigma ! STATIONLCODE*1 ?NUCLIDE/ JANUARY # FEBRUARYi MARCH ?APRILt TMAY -JUNE l l NINE MILE I-131 <9.78 <10.1 <9.23 <12.1 <9.74 <7.15 POINT Cs-134 <2.97 <2.99 <3.36 <5.68 <3.18 <3.80 UNIT 1** Cs-137 <3.11 <3.13 <3.56 <4.61 <3.25 <3.51
- (09. INLET) Zr-95 <6.62 <5.77 <6.43 <8.29 <6.87 <5.76 Nb-95 <4.31 <3.85 <4.44 <5.59 <4.31 <4.15 Co-58 <3.66 <3.30 <3.68 <5.09 <3.54 <4.34 Mn-54 <3.03 <3.09 <3.54 <4.24 <3.24 <4.03 Fe-59 <7.28 <8.40 <7.99 <10.8 <8.86 <8.90 Zn-65 <6.77 <8.01 <8.82 <13.2 <9.47 <9.03 Co-60 <3.71 <4.41 <3.98 <4.57 <3.72 <5.27 K-40 50il2 46i15 68i13 1040i29 60t12 72i14 g Ba/La-140 <11.0 <11.4 <11.9 <8.70 <12.7 <10.4 NINE MILE I-131 <10.9 <11.9 <8.47 <12.7 <14.4 <12.5 POINT Cs-134 <3.35 <3.49 <3.63 <3.45 <4.95 <5.90 UNIT 2** Cs-137 <3.27 <3.31 <3.45 <3.04 <4.82 <4.54 (11. INLET) Zr-95 <5.93 <7.25 <6.36 <7.37 <11.2 <8.95 Nb-95 <3.82 <4.90 <4.14 <5.15 <7.32 <5.60 Co-58 <3.72 <3.95 <4.18 <4.56 <6.47 <4.91 Mn-54 <3.21 <3.59 <3.85 <3.45 <5.86 <4.52 Fe-59 <9.48 <7.94 <9.41 <7.78 <14.7 <11.5 Zn-65 <7.40 <8.52 <8.41 <9.31 <14.6 <14.1 Co-60 <4.02 <4.42 <3.83 <4.67 <7.63 <5.05 K-40 55112 33i14 58 15 226i18 138 26 1080i30 Ba/La-140 <11.8 <12.6 <10.3 <13.2 <12.9 <9.53
- Corresponds to sample locations noted on the maps in Section 3.3.
** Optional sample location. Samples not required by Technical Specifications.
M M M M M M M M M M M M M M M M M M M
TABLE 6-4 (Courruuso) CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1993 Results in Units of pCi/ liter i 1 Sigma
!STATIONiCODE*l INUdLID5 JANUARI? /FE5RUARW HARCH APRIs iMAY4 JUNE OSWEGO CITY I-131 <10.3 <11.5 <13.4 <7.14 <9.77 <8.59 WATER ** Cs-134 <3.22 <3.50 <5.81 <3.47 <3.17 <4.03 (10) Cs-137 <3.05 <3.12 <4.84 <3.14 <3.55 <3.37 Zr-95 <7.22 <7.46 <9.10 <6.13 <6.56 <5.94 Nb-95 <4.59 <4.97 <5.61 <4.16 <4.43 <4.10 Co-58 <3.93 <3.79 <5.01 <4.14 <3.94 <4.45 Mn-54 <2.93 <3.84 <4.40 <3.71 <3.34 <3.84 Fe-59 <7.32 <8.28 <11.7 <7.47 <9.05 <8.93 es Zn-65 <7.90 <9.74 <13.4 <7.99 <7.78 <9.74 s; Co-60 <4.08 <3.81 <4.50 <4.00 <3.65 <4.79 K-40 62114 19il7 1150131 44i14 78t15 60115 Ba/La-140 <10.7 <11.9 <9.53 <10.6 <9.05 <12.4 o Corresponds to sample locations noted on the maps in Section 3.3. ** Optional sample location. Samples not required by Technical Specifications.
TABLE 6-4 (ConTrnuso) CONCENTRATIONS OF GAAMA EMITTERS IN SURFACE WATER SAMPLES - 1993 Results in Units of pCi/ liter i 155gma 9~ " . . STATION. CODE *i ;NUCLIDEs MULYs 1SEPTEEER :;:OCTOBERJ AUGUST:L: jNOVEMER ;DECEEERs OSWEGO STEAMt I-131 <0.90 <0.30 <0.30 <0.80 <0.30 < STATION Cs-134 <3.44 <2.85 <2.91 <3.23 <4.25 <2.98 (08. CONTROL) Cs-137 <3.47 <2.93 <3.19 <2.80 <3.32 <3.05 Zr-95 <6.55 <7.60 <5.76 <7.24 <7.84 <6.19 Nb-95 <4.12 <4.22 <3.43 <4.95 <5.00 <4.41 Co-58 <4.32 <3.48 <3.33 <4.27 <4.30 <3.70 Mn-54 <3.84 <3.04 <3.39 c3.66 <3.53 <2.90 Fe-59 <8.08 <8.13 <8.44 <8.05 <8.71 <8.55 Zn-65 <8.67 <7.85 <8.05 <7.67 <9.88 <7.63 Co-60 <4.65 <3.85 <3.57 <4.43 <4.84 <3.94 K-40 150il2 55t15 65i13 214i19 197i19 240il7 [ Ba/La-140 <12.4 <12.3 <9.47 <11.1 <8.60 <11.4 , FITZPATRICKt I-131 <0.80 <0.20 <0.40 <0.90 <0.40 <0.40 (03, INLET) Cs-134 <3.26 <3.90 <3.44 <4.52 <3.22 <4.23 Cs-137 <3.08 <3.23 <3.22 <3.93 <2.89 <3.63 Zr-95 <6.43 <6.37 <6.85 <8.07 <6.36 <7.85 Nb-95 <4.70 <4.51 <4.64 <4.90 <3.97 <4.98 Co-58 <3.42 <4.26 <4.06 <4.15 <3.69 <4.25 Mn-54 <3.37 <4.05 <3.89 <3.95 <3.19 <3.97 Fe-59 <9.07 <9.94 <8.00 <9.96 <8.30 <8.18 Zn-65 <8.27 <9.78 <9.09 <9.60 <7.85 <9.56 Co-60 <3.92 <4.18 <4.02 <6.03 <4.17 <4.34 K-40 54i13 86t15 273i21 213i23 57*14 77i24 Ba/La-140 <10.3 <12.9 <10.1 <12.1 <10.3 <7.65 o Corresponds to sample locations noted on the maps in Section 3.3.
? Samples required by the Technical Specifications.
M M M M M M M M M M M M M M M M M M M
l TABLE 6-4 (Courinuso) CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1993 Results in Units of pCi/ liter i 1 Sigma STATIONIC'0DE* INUCLIDEl fJULY AUGUSTE iSEPTEEER 10CTOBER NOVEEER IDECEEER NINE MILE I-131 <8.17 <12.4 <10.1 <11.0 <12.2 <13.1 POINT Cs-134 <3.08 <3.20 <3.30 <3.39 <4.39 <2.91 UNIT 1** Cs-137 <3.28 <3.01 <3.11 <3.19 <3.23 <2.86 (09. INLET) Zr-95 <6.15 <7.60 <5.95 <7.22 <7.66 <5.58 Nb-95 <3.93 <4.86 <4.28 <4.34 <5.06 <4.11 Co-58 <3.38 <4.50 <3.99 <4.04 <4.47 <3.00 Mn-54 <3.39 <3.80 <3.65 <3.95 <4.08 <2.64 Fe-59 <7.98 <8.67 <8.63 <9.19 <8.88 <8.08 Zn-65 <8.05 <10.5 <9.04 <9.99 <10.0 <6.64 Co-60 <4.52 <4.08 <3.92 <3.75 <3.78 <3.54 K-40 35i13 232119 244119 247i19 908126 68112 { Ba/La-140 <10.7 <11.5 <9.56 <10.8 <8.17 <12.3 NINE MILE I-131 <9.48 <14.2 <9.21 <13.1 <9.10 <13.9 POINT Cs-134 <3.52 <5.52 <3.43 <4.10 <3.45 <2.29 UNIT 2** Cs-137 <3.31 <4.26 <3.34 <3.69 <3.34 <2.17 (ll, INLET) Zr-95 <6.80 <8.43 <6.54 <8.05 <5.60 <5.41 Nb-95 <4.79 <5.72 <4.04 <5.07 <3.93 <3.83 Co-58 <4.00 <4.66 <3.64 <4.49 <3.82 <3.04 Mn-54 <3.50 <4.08 <3.19 <3.94 <3.36 <2.65 Fe-59 <8.35 <11.1 <8.83 <9.16 <9.07 <6.79 Zn-65
<8.55 <12.6 <8.75 <9.80 <7.76 <6.67 Co-60 <4.38 <4.36 <3.78 <3.60 <4.29 <2.58 K-40 200i18 1190i28 41i12 873 26 43i14 217 13 Ba/La-140 <9.04 <8.98 <9.79 <7.13 <10.6 <9.75
- Corresponds to sample locations noted on the maps in Section 3.3.
** Optional sample location. Samples n_ot required by Technical Specifications.
TABLE 6-4 (ConTrnuso) CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1993 Results in Units of pCi/ liter i 1 Sigma STdTION! CODE *? ::NUCLIDE9 . 9JULW AUGUST !SEPTEEER? OCTOBER LNOVEEER LDECEEER OSWEGO CITY I-131 <12.3 <11.7 <10.8 <13.6 <13.1 <13.8 WATER ** Cs-134 <3.14 <3.57 <4.23 <4.15 <4.34 <2.89 (10) Cs-137 <3.29 <3.16 <4.10 <3.59 <3.55 <2.85 Zr-95 <6.80 <7.49 <7.92 <8.32 <7.79 <5.64 Nb-95 <4.32 <4.75 <5.00 <5.65 <4.78 <3.79 Co-58 <4.29 <4.01 <4.88 <4.52 <4.55 <3.10 Mn-54 <3.21 <4.06 <3.70 <3.95 <3.86 <2.68 Fe-59 <8.79 <9.42 <9.25 <9.12 <8.41 <8.21 m Zn-65 <7.98 <9.74 <9.41 <10.6 <10.0 <6.70
" Co-60 <3.79 <4.48 <4.22 <3.76 <4.03 <3.55
. K-40 81114 284121 216124 857i25 944 27 208il5 Ba/La-140 <12.5 <11.2 <11.6 <9.29 <7.89 <11.6 o Corresponds to sample locations noted on the maps in Section 3.3.
- Optional sample location. Samples not required by Technical Specifications.
M M M M M M M M M M M M M M M M M M M
.-6
eoeooeoeoeooeoeooogoeoeeoe oooooC t
o - ooeooo.ooCoooo9oo99e o e o e o e o o e o e +1
+1 +1 +1 +1 +1 +1 +1 +t +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +4 oeooeoe
- o. +o 9 o o c. +1o o O +l M +1 M
.gl .I '
o c-r.o.econ.= eN oN o mo m.=
.=
o om.om.o eo 6.=o .=
= = . mo om coooooo o .mo= . .=
.=oog -. coccoo oo meeo.(
o n== ooc ~= a dddddddddddddddddddddddddd
.= - .= - - -
oeeooeeoeoooeee Lw:~.: c o o o o o o o o o o o o o o c. oooooooooC oceococcoocoocoocooeococo.o o e o o e o e o o e oo
+1 +1 +1 +1 +1+1+i+1 +l+1+1+1+1+1+6+1 +1 +1 +1+1+4+t+1+1 +l +1
.. C : N me-mmm
'yw ]
e-mNmb~r.nmN eN ooooooc.Coooo@ @ o@ oooCoo bmowN-eoo-.=- NnN eo-eo-M o e o e o e o e o e o o e o e o e o o o o e. oooeo oo@ z o H - p oeooooeooeoeoooeooeooeooeo
,e :
' y o o oe oooeooooc.oo oc.eo oo o oo o oo oeooooC.e o@.e@oC@ e.
ooo@ oeoeo+1 b .
+1 +1 +1 +1 +1+1+1+1+1+1 +1 +1 +1+1+1+1+1+1+1 +1 +1 +1 + 1 +!
M L' Q t- m @
.N. .= .c.
@ @ b =.
= .to e@ o o == N =.m
.+=1
.g ; .o N .oc. .o. -r. No .LA = - to .N ==cN 00 . .N e= .e=
i= y i Lgj s C.C.o o o o o c.c.o 9 9 9 9 o 9 9 9 9 9 9 o C O 9 9 oeoeooooeoeoeooeoeoeoeooeo H M i .= - == .= == == .= == La 4 Ib ooooooeoeooooeoooooeoooooo ti. nG. n w
- ceo o C.o C.e o o e o o o c o e+1 o+4 o+ o+1+1+1 o o +4+1o e o+1e+1+1 o o+1+1 o. +1eooeo@
o +1o c. oeoeooe o o +(e Ho +(o +1 o +1 o +1o O G -
@ N &1 W o N 4
+i +4 +1
, M W: ..
e o e o e oN .e- o e.@ o e o eoeo----- oN e 00
.=
N
.=
6@ 00 @ M .+.14N o o e o e o o e. beo-o-
.+.1m @
oooeo N mm y , - o} d66dadad66dddddddad666ddd6 wJ +1 .- a, -.1 E,, f*T
- A e
c 8.e coeeooce.c c ooceoC.
.=
c oc oo oo co ec co oc cc o
.=
eo o cc oc co oo oc
.=
I.O w a:e
- p. m :::: E hw- o e o o.ooco
+1 oeooeoeoeoeoeoooooo -
I H U 2 eN M +i H H +iH H H +1 +1 +t +i +t+t +t44+l+1 +1+i+1+1+1+1M N g M [gj a Q (g) : o N .=* - .= m.=e.. N== m. . m.= .m m m.i= . eb e be .o
==.m N. e oeemob e&N.o. N. .
H - s- CCooC g 4 >"' H g o o o o o.o c.o C.o o o o g o o @oooooooooooo.ooooooooo . ooooooooo W ct I ! < J CO mm> 0
%. t ) - -#
4 ash Oa EHO L-l.a Cococoeocooooocee ooooooc -.=eeceococo
.=
b- zg 4 o o o o o o o
+6 +6+t+i +1 +i+1+t +1 +1 y +1
- o. o c. o o ooooooooooooooooooo o o o o o o o o o c. o o o o c.
+1 +1 +1 +4 H +t+1+1+ H +1 +1 +1 8:C a(H ;gr
.E oN o O.C.
. N b 00.. m tA
-. 40N .= .N @ o o e b@ b 4 N.= M 4 . .=.=. 1 00 H
o o.N .o N y w
- g ooc.ooooooooooC.
oooooooooooooooooooooooooo ooc.ooooC.c. ooc. Z a3 x oO f*i co M - 1' _ .= coo e mO l6J o cooc eooooc c c o oceoo o c o o. ooo.o ococooooo,cc.oc.ocooooooooooooo.o o oco c o 8. o c.o. 8. co ec c H g c ;'
+1 S 40 oMHH c N HHm o+1 H +1 +4 H +1 +1 +1 +1
+1 H +1 +1 M
.M. b My +1 +1 +1 w n
- m. -N --- N . - . r. n e .co N e.=eoo . w s m N .n sn --.
m ee mN oN
- o. o
,,j re e o c o c o o c o c o c c o o coccoococoo e gg H
[ g '. dddddddddddddd6ddddddddddd 'o z E W # m o e o o o c o c e o o o c e o c- - .=coecoceeo 3 .= E Z n k .. o C@.Cc e o i LA 1 c :' eoeo.oooCooooocoococcooocoo S
& +1 +i +1 +1 ceoococococcooocoooooo
+1 +1 +1 +f +1 +1 +( +1 +1 +1 +t +1 +1 +1 +1 H +1+1+1+1+1+1 e
.C H >N - - n-------N N e en -r b c N b - sn s - m m -r m -r o m m N N - sn o
- > -1
-N CC@ oooC -o-o------o---- e o o o o c o o. C. ocooocooocecoccocoe C. o o C. C. o o c. C. C. C. o. o C. C. c o. c. F z ~og-' 3 L3J .Q "O
.= .= .= .= = = .=
16: o c o c e e c e e e o o c e e o o oooe
- w. occoooooooooooooooooo8ecce coco s
. C :. dda6666666666666666666666a
+1 +1 + +1 +1 +1 +1 +1 + +1 +t +1 +1 +1 +1 +1 +1 +1 +1 +1 iw e o @1 +1 m@ QC N m W 1 +1 o@+1+1+1+1 oC @ bmN N P.( -
-l' oeooeoeoeoeooeoeooNN
-N ==
6666666666666666d666666666
- == == .= N - e o o == ==
eoeooeoo ob
==c o.N.oo . M C
2-
.. ' glg :
.cs o E
'{'W
. r mmmmemmmmmmmmmmmmmmmmmmmmm ee . e.mh.
mNee N e e e e .e e .e .e e e e e e e e e. eema, mob ,-mm. ene ao wo. kCCU
- - - - h h h"" o U k k C ,. QmQ qQQ -r o qqQCoCOU o c o o o c c o nmmm(m o e c o c o ~r c on o~ro% Dm E g- m m 3 86 c c o cocococo .a o
6 14
i 1 tb.. g' :.
----~~----------~~---------
S. o c o o c e e e E.oCococococococcoo cooooooo ooooooooooooooooooooooooooo eoooooooooeeooooo li \
+1 +1 +1 +1+1+1+1+1+1+1+1+1+1+1+1+1+1+t+4+4+1+1+1+1+1+1 +1
.CD, _ -em-owroenw-meme-onenwornmm
--e------------------------
m; oooooooo@ ococcooooooooooooo cocoooooooooooooooooooooooo
-----~~~~~--------------~~~ \
cooooooooooooocceCCCCoCocoC ] Ld o. C o C C C C C C o. C o o o o o o o o o C o C o c o. o coooooooooooooooooooooooooo
-: +1 +1 +l +1 +1 + +1 +1 +1 +l+1+1+1 +1 +1 +1 + 1+1+1+1+1+1 !
~ .1.+1.+1+1
,+1 nnn-->~o@ n mn-m- ,+1
, nno
- >o----~------------------
t' 2-.. coce9=o=o=oco==co=oco=o==== m ooooooooooooooooooooooooooo I z i o
- - - - -------------~~--__----- {
p oc o-o c o c o c o c o c c o o 8. 8. o ==oco=ococco cocococco i
< ss o=Co=o===o=o=
ooooooooooooooooooooooooooo h '-
+1 +1+1 +1+1 +1 +1 +1 +1 +1 +1+1+1+4+1+1 +1 +1 +1 +1 +1 +1+1+1+1 +1 +1 m ,
nne-moeocem--mmmmmeommzere-
-n-----~~----------~-------
w : w: ococoCococoCCCococcooCC*coC coccooooooooooooooooooooooo H H m I --------------------------- 6 4 ? ocococococogoecogococcococo e3
,M
- =T
.N
- t1 iiiiiiiiiiigiisisisissisisi
--eenna
- n------n------n---n-------
Co@ co@ oCocooooCCococco@ o@ @ C
,~---,~---->>-nm l g g e .g; cococococoooooooooooooooooo W $ J +I 2 a n '*.:
t . M. H H W gW.EcEm rw- o c C o c o 8. coo Coce=o c o o 8. coo c o o 8. coo c 8. 8.c co.occ oo cc oc oo 8 z ~c ooooooooooooooooooooooooooo
+1 M +i M +1 +l + +1 M +i +1 M +1 +4 +1 M +1 +1 +1 +i +1+i+i+1 M +1 +4 N U2 AmM -nW oM-N won omMoobbm@ b@ @ Mm UO MWH 20 .m: --o---n-n------------------
w
- .'l- :
C o C o o e C C o o C o
- C o o o o c o
- C o C C. C C ge p ;gg: ooooooooooooooooooooooooooo M <J_4 mm '*'-
I su>O @ AM -o b y occoogeCooooooooooccocococo EH O L L o. c o. C o .ocooooooooooooooooooo ooooooooooooooooooooooooooo LM zu( O +1 +1 +1 +l+1+1+1+1 +4+1+1+l+1+1+4+1 M +1+4+1+4 +1 +1+1+1 +1 +1 J 4 wg nnso-wwo-nwnn~se-ownwwwamnn a at : ~ ~ c-----n--------~~~~------ m ww H all
; gg r C @ @ oo cocococococoooooooooooooooo coccococcooooooooo 4
- W m oM "*". ---------------------------
mM T Lk e mO e6; o
*. c o c c o E. C e o. ooo ocooooooooooooooooooooooooo E. E. o o@E. cooc. o o E.o o oc E. E. E. E. S C
H g h C 's +1+1+1M +1 +1 +1 +1+1 M +1 M +1+1+1 M M +1 M M M M +1 M M +1 +1 -
< Q yM1.. No-nn@
- N - - - w hhmM -N .---------N
@ NN-Mcno@ e@ @ bMvnn -------
M U J ic 3 4 g eg . : oCocooCCCooCocooocoCoCocooo ooooooooooooooooooooooooooo FG 4 H a > z c : M { W f*c - - ------------------------- - ) E CCCCoccooo ooooooo o oooooo 4 z j
? E i 9999c.9o909gco99e.cogogo9o999 . .
e { occocoooooooooooooooooooooo
. i o 'Q- +1 +1 +1 +1 +1 +1 +l +4 +1 +1 +1 +1 +1 +1 +1+1+1+1+l +1 +1 +1 +1 +1 +1 +1 +4 .C t
E n@ cnN onoMMmvn-bMM-b-mn@ mv-n O l H . N ..1 -----N NN -----------N- - ----- e j g gg e 9 9 e. 9 C. 9 9 9 9 9 9 9 o O O C. C. 9 9 8 9 9 9 o. 9 9 C coooooooooooooooooooooooooo b
)
l 3 W D { 2 N~ ~8
'W- o c oCoCoCCococco.ococcoo CC@ coCocooCoCo C o c o c o c o S. cCoH e q S. E
'Q:-
cococooCocococococooococo o g
+f +l +1 +4 ti +1 +l+1+4 +1+1+4+1+1+1+1 +1+1 +1+1+1+t +1 +1 + +1 e.
. . Pi :.
J AM=AN@ @ bomM nn@ @ MA-@ mnM b@ m
- - - -----N ----e------------
n
- M Ll oooooooooooooooooooooooooG o C
; gg i- ddddddddddddddddddddddddddd M
~.
4 0 O
.. .i AnnnnnnnnnnnnnnnnnnnnnnnnnW ~
~
.. gJ RRERRRRERRRRRRRER*RRRERRR RR *
~K emornorn-rw-=mnmeAmeners =w a MC w c~ R"CU*C""G*CQQ*"
orenxeekmemecocoo- CUR
- RUQ*"b'"*
---An h- E ococco coco -------------o 3p .
6-15
TABLE 6-6 NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ON-SITE STATIONS GROSS BETA ACTIVITY pCi/m 1 SIGMA LOCATION WEEK END: 3DATE [D1---ONE LGUON) LH- -ON j TI--ONj (Jp0N! :: K---DN ' 0I/04/93 0.010i0.001 0.009i0.001 0.00910.001 0.009i0.001 0.008i0.001 0.010 0.001 0I/11/93 0.022t0.001 0.02310.001 0.02310.001 0.019 0.001 0.01810.001 0.019io.001 0I/18/93 0.018io.001 0.017i0.001 0.01410.001 0.016i0.001 0.012io.001 0.014i0.001 0I/25/93 0.013i0.001 0.013io.001 0.0I110.001 0.013io.001 0.010 0.001 0.013i0.001 02/0I/93 0.013io.001 0.012i0.001 0.01210.001 0.014i0.001 0.01210.001 0.012i0.001 02/08/93 0.01810.001 0.01Si0.001 0.018i0.001 0.018io.001 0.015io.001 0.018 0.001 02/16/93 0.017 0.001 0.013 0.001 0.01210.001 0.013io.001 0.011 0.001 0.012f0.001 1 02/22/93 0.016 0.001 0.014i0.001 0.013 0.001 0.014 0.001 0.013 0.001 0.015i0.00I
$ 03/01/93 0.017 0.001 0.015 0.001 0.016i0.001 0.017 0.001 0.01li0.001
- 0.014io.001 03/08/93 0.025i0.001 0.025 0.001 0.024i0.001 0.02510.001 0.022io.001 0.024i0.001 03/15/93 0.012 0.001 0.011 0.001 0.01510.001 0.014 0.001 0.01010.001 0.01410.001 03/22/93 0.01910.001 0.01810.001 0.01810.001 0.017i0.001 0.012 0.001 0.017i0.001 03/29/93 0.009 0.001 0.008 0.001 0.008i0.001 0.00910.001 0.007i0.001 0.008i0.001 04/05/93 0.010io.001 0.010 0.001 0.01110.001 0.009i0.001 0.008i0.001 0.01010.001 04/12/93 0.009 0.001 0.008 0.001 0.01010.001 0.00910.001 0.007i0.001 0.008 0.001 04/19/93 0.012io.001 0.010 0.001 0.013io.001 0.01li0.001 0.009i0.001 0.012i0.001 04/26/93 0.013i0.001 0.013 0.001 0.012io.001 0.012 0.001 0.01li0.001 0.011 0.001 05/03/93 0.014 0.001 0.014 0.001 0.01410.001 0.015 0.001 0.01li0.001 0.01310.001 j 05/10/93 0.014 0.001 0.01310.001 0.01lio.001 0.013i0.001 0.013 0.001 0.01lio.001 05/17/93 0.011 0.001 0.01110.001 0.010i0.001 0.010io.001 0.010io.001 0.01210.001 05/24/93 0.010io.001 0.009i0.001 0.01110.001 0.011 0.001 0.00610.001 0.005 0.001 06/01/93 0.008 0.001 0.008i0.001 0.008i0.001 0.009 0.001 0.004i0.001 0.00610.001 06/07/93 0.009 0.001 0.008f0.001 0.009i0.001 0.009i0.001 0.006i0.001 0.007 0.001 06/14/93 0.016 0.001 0.013i0.001 0.046i0.001 0.010 0.001 0.012i0.001 0.011 0.001 l 06/21/93 0.012 0.001 0.01li0.001 0.014i0.001 0.010 0.001 0.011 0.001 0.010io.001 06/28/93 0.013io.001 0.013i0.001 0.010 0.001 0.013i0.001 0.009 0.001 0.012 0.001 r l R6 l
TABLE 6-6 (courzuuso) NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - GN-SITE STATIONS GROSS BETA ACTIVITY pCi/m 1 SIGt1A LOCATION INEEK ENDi fDATE 3 D1dONi LGi -ONi /H--ONL II-f0N! v J- -ONi 2K--ON-07/06/93 0.01Si0.001 0.01310.001 0.013io.001 0.013i0.001 0.010 0.001 0.013 0.001 07/12/93 0.020i0.001 0.020i0.001 0.02lio.001 0.01810.001 0.01810.001 0.016io.001 07/19/93 0.013i0.001 0.0Ili0.001 0.009fD.001 0.012i0.001 0.013i0.001 0.009 0.001 07/26/93 0.01Ii0.001 0.012io.001 0.012i0.001 0.014i0.001 0.012i0.001 0.011 0.001 08/02/93 0.012 0.001 0.01410.001 0.015 0.001 0.012 0.001 0.013 0.001 0.012i0.001 08/09/93 0.01310.001 0.014 0.001 0.018i0.001 0.020i0.001 0.014i0.001 0.013i0.001 08/16/93 0.02li0.001 0.02310.001 0.024 0.001 0.025 0.001 0.019i.0.001 0.02110.001 08/23/93 0.015 0.001 0.017 0.001 0.014 0.001 0.01510.001 0.014io.001 0.014 0.001 m 08/30/93 0.02410.001. 0.022 0.001 0.023i0.001 0.02lio.001 0.01810.001 0.021 0.00I b 09/07/93 0.013 0.001 0.016io.001 0.017 0.001 0.017i0.001 0.011 0.001 0.013i0.001 09/13/93 0.013 0.001 0.01510.001 0.01210.001 0.013 0.001 0.014io.001 0.012io.001 09/20/93 0.013 0.001 0.01610.001 0.015io.001 0.014i0.001 0.012i0.001 0.015 0.001 09/27/93 0.01lio.001 0.01310.001 0.01410.001 0.01410.001 0.01lio.001 0.013i0.001 10/04/93 0.01li0.001 0.01li0.001 0.0I110.001 0.011 0.001 0.009io.001 0.010 0.001 10/11/93 0.0I8 0.001 0.017i0.001 0.016i0.001 0.015 0.001 0.014io.001 0.015io.001 10/18/93 0.016i0.001 0.01710.001 0.01610.001 0.01510.001 0.014i0.001 0.016 0.001 10/25/93 0.011 0.001 0.01210.001 0.013 0.001 0.015 0.001 0.012io.001 0.012 0.00I i 11/0I/93 0.009i0.001 0.008io.001 0.010i0.001 0.01li0.001 0.010io.001 0.012i0.001 11/08/93 0.015i0.001 0.015 0.001 0.012i0.001 0.01410.001 0.013i0.001 0.01Si0.001 I1/15/93 0.022i0.001 0.023i0.001 0.020 0.001 0.024i0.001 0.02li0.001 ! 0.020 0.001 II/22/93 0.013io.001 0.014i0.001 0.016fD.001 0.014 0.001 0.01310.001 0.014 0.001 1I/29/93 0.014i0.001 0.01010.001 0.016i0.001 0.012i0.001 0.012 0.001 0.014i0.001 12/06/93 0.019 0.001 0.020i0.001 0.023i0.001 0.019 0.001 0.019i0.001 0.020i0.001 12/1I/93 0.019i0.001 0.020i0.001 0.023i0.001 0.019i0.001 0.019 0.001 0.020 0.001 12/20/93 0.017i0.001 0.017 0.001 0.015io.001 0.017 0.001 0.014io.001 0.017 0.001 12/27/93 0.013io.001 0.014 0.001 0.013i0.001 0.013i0.001 0.012i0.001 0.012i0.001 0I/03/94 0.014i0.001 0.016i0.001 0.014 0.001 0.016i0.001 0.009io.001 0.016 0.001 m m m m m M M M M M M M M .M M M M M M
1 TABLE 6-7 NMP/JAF SITE ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - 0FF-SITE STATIONS l-131 ACTIVITY pCi/m 1 SIGMA LOCATION WEEK!ENDL
;DATE:l 4R-1*: R-2*2 :R-4*T 1R43*h SR-5s iD12f aE3 % :Gi c
l 01/05/93 <0.012 <0.014 <0.013 <0.009 <0.010 <0.011 <0.009 <0.009 <0.009 01/12/93 <0.016 <0.017 <0.014 <0.012 <0.014 <0.015 <0.010 <0.013 <0.011 01/19/93 <0.010 <0.012 <0.008 <0.013 <0.010 <0.015 <0.009 <0.008 <0.009 01/26/93 <0.011 <0.016 <0.015 <0.012 <0.011 <0.015 <0.009 <0.010 <0.009 02/02/93 <0.015 <0.017 <0.011 <0.014 <0.010 <0.012 <0.014 <0.014
<0.012 I 02/09/93 <0.014 <0.012 <0.013 <0.012 <0.009 <0.011 <0.014 <0.010 <0.010 02/16/93 <0.012 <0.014 <0.013 <0.010 <0.008 <0.010 <0.012 <0.008 <0.010 02/23/93 <0.015 <0.012 <0.011 <0.012 <0.012 <0.014 <0.012 <0.012 <0.011 , 03/02/93 <0.016 <0.009 <0.014 <0.010 <0.013 <0.011 <0.012 <0.010 <0.015 g 03/09/93 <0.011 <0.013 <0.020 <0.010 <0.009 <0.017 <0.010 <0.012 <0.016 03/16/93 <0.012 <0.014 <0.014 <0.013 <0.010 <0.014 <0.014 <0.013 <0.009 03/23/93 <0.012 <0.015 <0.010 <0.014 <0.013 <0.013 <0.010 <0.010 <0.012 03/30/93 <0.014 <0.020 <0.011 <0.013 <0.017 <0.014 <0.011 <0.018 <0.011 04/06/93 <0.016 <0.019 <0.012 <0.012 <0.017 <0.011 <0.013 <0.018 <0.011 -
04/13/93 <0.011 <0.013 <0.015 <0.011 <0.012 <0.019 <0.012 <0.011 <0.017 l 04/20/93 <0.013 <0.011 <0.010 <0.014 <0.010 <0.016 <0.013 <0.013 <0.009 04/27/93 <0.013 <0.012 <0.013 <0.014 <0.015 <0.019 <0.010 <0.017 <0.012 1 05/04/93 <0.013 <0.012 <0.014 <0.011 <0.012 <0.009 <0.012 <0.009 <0.012 05/11/93 <0.018 <0.011 <0.011 <0.015 <0.011 <0.016 <0.010 <0.018 <0.014 05/18/93 <0.011 <0.020 <0.009 <0.019 <0.010 <0.021 <0.013 <0.0I0 <0.008 05/25/93 <0.014 <0.014 <0.015 <0.012 <0.014 <0.016 <0.013 <0.011 <0.016 06/01/93 <0.011 <0.014 <0.019 <0.012 <0.008 <0.012 <e.017 <0.011 <0.018 06/08/93 <0.014 <0.011 <0.015 <0.017 <0.015 <0.016 .0.019 <0.013 <0.010 06/15/93 <0.020 <0.016 <0.015 <0.009 <0.017 <0.013 <0.012 <0.018 <0.011 06/22/93 <0.011 <0.025 <0.012 <0.019 <0.012 <0.022 <0.011 <0.020 <0.011 06/29/93 <0.015 <0.024 <0.011 <0.021 <0.012 <0.022 <0.013 <0.017 <0.015 i
- Sample locations required by Technical Specifications
- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _. s
TABLE 6-7 (CouT1suso) NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 0FF-SITE STATIONS I-131 ACTIVITY pCi/m 1 SIGMA LOCATION WEEKLEND: 1DATE: ;R-1*H 1R-2*1 1Rs3*7 ! R- 4*l {R-5*" D-21 iEi :F~ 1G 07/06/93 <0.022 <0.018 <0.013 <0.013 <0.021 <0.013 <0.014 <0.011 <0.017 07/13/93 <0.009 <0.012 <0.018 <0.031 <0.015 <0.018 <0.022 <0.012 <0.012 07/20/93 <0.017 <0.017 <0.022 <0.016 <0.018 <0.016 <0.016 <0.008 <0.018 07/27/93 <0.018 <0.015 <0.021 <0.015 <0.012 <0.018 <0.016 <0.014 <0.014 08/03/93 <0.013 <0.015 <0.015 <0.019 <0.017 <0.016 <0.014 <0.017 <0.012 08/10/93 <0.019 <0.022 <0.019 <0.017 <0.013 <0.024 <0.015 <0.013 <0.013 08/17/93 <0.017 <0.019 <0.014 <0.012 <0.015 <0.017 <0.013 <0.011 <0.014
- 08/24/93 <0.017 <0.013 <0.022 <0.015 <0.010 <0.014 <0.012 <0.019 <0.018 l 08/31/93 <0.016 <0.017 <0.015 <0.014 <0.012 <0.014 <0.010 <0.013 <0.012 l p 09/07/93 <0.012 <0.011 <0.010 <0.017 <0.008 <0.014 <0.016 <0.020 <0.012 G 09/14/93 <0.014 <0.012 <0.021 <0.013 <0.014 <0.016 <0.014 <0.019 <0.009 09/21/93 <0.014 <0.012 <0.013 <0.014 <0.012 <0.017 <0.013 <0.012 <0.011 09/28/93 <0.012 <0.013 <0.015 <0.010 <0.014 <0.015 <0.011 <0.011 <0.010 10/05/93 <0.013 <0.016 <0.013 <0.015 <0.013 <0.019 <0.008 <0.012 <0.010 10/12/93 <0.015 <0.014 <0.013 <0.015 <0.012 <0.016 <0.011 <0.011 <0.010 10/19/93 <0.017 <0.011 <0.014 <0.014 <0.015 <0.014 <0.014 <0.012 <0.011 10/26/93 <0.014 <0.013 <0.013 <0.015 <0.014 <0.011 <0.017 <0.014 <0.011 1I/02/93 <0.011 <0.011 <0.014 <0.016 <0.013 <0.013 <0.016 <0.011 <0.010 11/09/93 <0.015 <0.018 <0.017 <0.014 <0.012 <0.014 <0.015 <0.012 <0.012 11/16/93 <0.013 <0.017 <0.011 <0.020 <0.012 <0.012 <0.019 <0.012 <0.012 11/23/93 <0.014 <0.016 <0.013 <0.020 <0.014 <0.017 <0.011 <0.017 <0.012 11/30/93 <0.016 <0.008 <0.013 <0.022 <0.014 <0.013 <0.016 <0.016 <0.009 12/07/93 <0.014 <0.014 <0.015 <0.014 <0.019 <0.012 <0.015 <0.012 <0.012 12/12/93 <0.012 <0.014 <0.015 <0.014 <0.016 <0.014 <0.014 <0.012 <0.011 12/21/93 <0.013 <0.012 <0.015 <0.014 <0.018 <0.013 <0.013 <0.009 <0.018 12/28/93 <0.013 <0.014 <0.011 <0.014 <0.012 <0.015 <0.010 <0.015 <0.014 01/04/94 <0.005 <0.013 <0.014 <0.013 <0.012 <0.016 <0.012 <0.012 <0.017
- Sample locations required by Technical Specifications M M M M M M M M M M M M M M M M M M
- ~~
r-TABLE 6-8 NMP/JAF SITE ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - ON-SITE STATIONS l-131 ACTIVITY pCi/m i 1 SIGMA LOCATION WEEK)ENDI :DiMONl (G -DN? [H---DN ! ?I -ON l TJa--ON : 1KY-.ON? 01/04/93 <0.014 <0.010 <0.017 <0.012 <0.017 <0.013 01/11/93 <0.013 <0.015 <0.009 <0.010 <0.016 <0.007 0I/18/93 <0.015 <0.008 <0.015 <0.014 <0.015 <0.014 01/25/93 <0.010 <0.013 <0.012 <0.015 <0.010 <0.012 02/01/93 <0.012 <0.014 <0.010 <0.014 <0.016 <0.008 02/08/93 <0.012 <0.012 <0.010 <0.0I 1 <0.009 <0.009 02/16/93 <0.012 <0.012 <0.011 <0.012 <0.009 <0.009 02/22/93 <0.017 <0.011 <0.014 <0.012 <0.015 <0.014
, 03/01/93 <0.017 <0.011 <0.010 <0.022 <0.013 <0.012 tb 03/08/93 <0.019 <0.009 <0.014 <0.018 <0.012 <0.010 03/15/93 <0.010 <0.018 <0.021 <0.019 <0.016 <0.015 03/22/93 <0.008 <0.011 <0.013 <0.011 <0.012 <0.009 03/29/93 <0.012 <0.014 <0.011 <0.018 <0.014 <0.009 04/05/93 <0.010 <0.016 <0.014 <0.018 .<0.014 <0.011 04/12/93 <0.014 <0.019 <0.013 <0.012 <0.013 <0.015 04/19/93 <0.018 <0.010 <0.014 <0.013 <0.012 <0.010 04/26/93 <0.018 <0.012 <0.012 <0.018 <0.012 <0.011 05/03/93 <0.010 <0.013 <0.010 <0.018 <0.010 <0.018 05/10/93 <0.010 <0.019 <0.012 <0.015 <0.012 <0.008 05/17/93 <0.014 <0.013 <0.009 <0.019 <0.015 <0.013 05/24/93 <0.012 <0.009 <0.019 <0.013 <0.016 <0.012 06/01/93 <0.011 <0.010 <0.011 <0.014 <0.020 <0.011 06/07/93 <0.016 <0.010 <0.024 <0.015 <0.010 <0.021 06/14/93 <0.022 <0.011 <0.022 <0.014 <0.014 <0.013 5 06/21/93 <0.008 <0.016 <0.015 <0.0i3 <0.018 <0.012 06/28/93 <0.013 <0.020 <0.011 <0.022 <0.010 <0.023 1 l l M i
TABLE 6-8 (Cour1suto) NMP/JAF SITE - ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - ON-SITE STATIONS I-131 ACTIVITY pCi/m 1 SIGMA LOCATION WEEK ENDS 'D1-f0NT iG--40N; ::H--ONL LIMONi- J ---ONi K---ON 07/06/93 <0.022 <0.013 <0.014 <0.013 <0.014 <0.015 07/12/93 <0.016 <0.017 <0.016 <0.016 <0.021 <0.012 07/19/93 <0.014 <0.016 <0.012 <0.014 <0.014 <0.015 07/26/93 <0.010 <0.019 <0.013 <0.016 <0.012 <0.013 08/02/93 <0.013 <0.015 <0.010 <0.015 <0.011 <0.018 08/09/93 <0.008 <0.020 <0.017 <0.019 <0.017 <0.020 08/16/93 <0.011 <0.017 <0.019 <0.016 <0.014 <0.015 08/23/93 <0.009 <0.018 <0.0II <0.022 <0.013
' <0.012 2 08/39/93 <0.012 <0.016 <0.014 <0.023 <0.013 <0.012 ib 09/07/93 <0.012 <0.012 <0.012 <0.019
~ <0.015 <0.015 l 09/13/93 <0.013 <0.013 <0.012 <0.023 <0.017 <0.010 09/20/93 <0.012 <0.013 <0.015 <0.016 <0.020 <0.013 09/27/93 <0.009 <0.013 <0.016 <0.012 <0.011 <0.012 10/04/93 <0.009 <0.013 <0.013 <0.014 <0.011 <0.0I I 10/11/93 <0.013 <0.015 <0.012 <0.016 <0.016 <0.014 10/18/93 <0.013 <0.016 <0.009 <0.010 <0.013 <0.010 10/25/93 <0.007 <0.012 <0.015 <0.016 <0.013 <0.009 11/01/93 <0.010 <0.010 <0.019 <0.012 <0.014 <0.016 11/08/93 <0.011 <0.011 <0.012 <0.018 <0.014 <0.014 11/15/93 <0.011 <0.009 <0.014 <0.019 <0.013 <0.013 1I/22/93 <0.013 <0.017 <0.014 <0.021 <0.014 1
<0.018 l 11/29/93 <0.011 <0.013 <0.010 <0.012 <0.016 <0.010 !
12/06/93 <0.012 <0.016 <0.012 <0.015 <0.015 <0.013 12/11/93 <0.012 <0.016 <0.012 <0.015 <0.015 <0.013 12/20/93 <0.013 <0.015 <0.013 <0.015 <0.016 <0.014 12/27/93 <0.013 <0.015 <0.011 <0.013 <0.019 <0.012 01/03/94 <0.011 <0.013 <0.008 <0.013 <0.018 <0.010 m M M M M M M M M M M M M M M M M
TABLE 6-9 CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE3 SAMPLES - 1993 Results in Units of 10'3pCi/m i 1 Sigma NUCLIDES? JANUARE iFEBRUARY! MARCH /APRIb bMAYl iJUNE; R1 0FF-SITE COMPOSITE
- TlCe-144 <2.98 <6.06 <8.83 <7.07 <5.18 <5.44 Ce-141 <0.94 <1.71 <2.71 <2.58 <1.90 <1.84 Be-7 59.815.6 92.4t7.7 53.5i8.1 10918 69.4 7.6 89.li9.9 Zn-65 <3.12 <4.42 <6.95 <4.76 <4.67 <5.46 Cs-134 <1.39 <1.78 <2.74 <2.11 <1.51 <1.84 Cs-137 <0.76 <1.51 <1.71 <1.69 <1.04 <1.60 Zr-95 <2.17 <3.12 <4.18 <3.72 <3.93 <4.02 Nb-95 <1.77 <2.38 <2.25 <2.48 <2.55 <2.83 Co-58 <1.22 <1.65 <2.42 <2.01 <1.72 <2.69 l 2 Mn-54 <1.12 <1.57 <2.16 <1.73 <1.93 <2.06 (3 Co-60 <1.15 <2.45 <2.44 <1.90 <1.99 <3.23 K-40 <13.7 16.0i7.8 239115 209i12 54.0i7.8 <35.5 Otherst <LLD <LLD < LLC <LLD <LLD <LLD R2 0FF-SITE COMPOSITE
- TlCe-144 <4.62 <4.04 <4.95 <3.50 <9.79 <5.79 Ce-141 <1.81 <1.60 <1.74 <1.43 <3.29 <2.00 Be-7 72.8 7.5 86.618.4 73.117.6 95.9i7.2 82.918.9 106 11 Zn-65 <4.13 <3.92 <4.03 <4.28 <7.40 <7.14 Cs-134 <1.51 <1.90 <1.53 <1.24 <2.77 <1.98 Cs-137 <1.31 <1.43 <1.65 <1.17 <1.97 <1.75 Zr-95 <2.85 <3.08 <2.81 <2.84 <4.65 <3.74 Nb-95 <1.72 <1.59 <1.79 <1.63 <3.09 <3.25 Co-58 <1.87 <1.53 <1.71 <1.22 <2.90 <2.18 Mn-54 <1.92 <1.28 <1.21 <1.03 <2.24 <2.27 Co-60 <1.85 <2.02 <2.25 <1.66 <2.03 <3.66 K-40 <25.6 <26.0 15.716.9 9.46i4.85 267i16.5 Otherst 36.7 9.1
<LLD <LLD <LLD <LLD <LLD <LLD
- Sample Locations Required by Technical Specifications.
t Plant Related Radionuclides. _ _ _ _ _ _ _ - _ _ ---- - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I
TABLE 6-9 (Conrrnuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE3 SAMPLES - 1993 Results in Units of 10'3pCi/m i 1 Sigma LNUCLIDES: LJANUARYf FEBRUARYJ MARCH SAPRILD 2HAYU JUNE R3 0FF-SITE COMPOSITE
- TlCe-144 <3.96 <8.02 <4.32 <4.70 <5.12 <5.30 Ce-141 <1.24 <2.53 <1.48 <1.55 <1.76 <1.86 Be-7 68.916.1 73.218.0 76.7t7.2 85.2 6.9 68.017.6 84.018.7 Zn-65 <2.47 <5.89 <3.80 <4.37 <4.16 <4.63 Cs-134 <0.88 <2.57 <1.57 <1.16 <1.19 <2.17 Cs-137 <1.07 <1.75 <1.62 <1.04 <1.46 <1.93 Zr-95 <2.35 <3.64 <2.85 <2.58 <2.87 <5.02 Nb-95 <1.47 <2.04 <1.91 <1.45 <2.07 <3.15 Co-58 <1.19 <2.45 <1.98 <1.49 <1.35 <2.24
, Mn-54 <1.26 <1.97 <1.98 <1.46 <1.47 <2.27 L
Co-60 <1.55 <2.50 <1.47 <0.98 <1.66 <3.50 K-40 10.7i4.2 210i13 <19.7 30.615.9 <20.8 52.1 10.9 Otherst <LLD <LLD <LLD <LLD <LLD <LLD R4 0FF-SITE COMPOSITE
- TlCe-144 <3.73 <5.55 <4.35 <3.64 <4.27 <8.99 Ce-141 <1.22 <1.51 <1.70 <1.34 <1.50 <3.25 Be-7 53.8 5.7 73.4t7.3 70.7 7.4 83.717.2 58.6i7.3 76.5 8.7 Zn-65 <2.94 <3.92 <3.69 <2.57 <3.01 <6.02 Cs-134 <1.27 <1.36 <1.42 <1.19 <1.36 <2.45 Cs-137 <1.03 <1.48 <1.35 <1.05 <1.42 <2.12 Zr-95 <2.48 <3.10 <2.95 <2.19 <1.75 <3.56 Nb-95 <1.82 <2.01 <1.72 <1.66 <1.62 <2.83 Co-58 <1.87 <1.90 <1.86 <1.45 <1.96 <2.37 Mn-54 <1.08 <2.14 <1.61 <0.88 <1.80 <2.12 Co-60 <2.25 <1.58 <1.84 <1.49 <1.72 <2.10 K-40 <17.7 17.3t7.2 <20.5 <17.9 <3.53 239i14.7 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
- Sample Locations Required by Technical Specifications.
t Plant Related Radionuclides. M M M M M M M M M M M M M M M M M M M
TABLE 6-9 (courzuuto) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE3 SAMPLES - 1993 Results in Units of 10'3pCi/m i 1 Sigma gNUCLIDES? JANUARYd FEBRUARY MARCH DAPRILi :MAY? iJUNE2 R5 0FF-SITE COMPOSITE (CONTROL)* TlCe-144 <3.04 <3.65 <4.31 <6.66 <5.09 <4.72 Ce-141 <1.18 <1.13 <1.43 <2.47 <1.64 <1.78 Be-7 43.9i5.4 65.616.8 85.7i7.2 97.417.5 70.5i6.9 89.7 7.6 Zn-65 <2.92 <3.30 <2.77 <4.64 <4.35 <4.82 Cs-134 <0.99 <1.49 <1.23 <1.97 <1.27 <1.55 Cs-137 <0.79 <1.17 <1.24 <1.41 <1.27 <1.43 Zr-95 <2.21 <2.19 <2.25 <3.59 <3.15 <3.31 Nb-95 <1.86 <1.56 <1.92 <2.21 <2.03 <2.23 Co-58 <1.63 <1.29 <1.44 <1.97 <1.78 <1.38 Mn-54 <1.14 <1.45 <1.14 <1.56 <1.75 <1.98
? Co-60 <1.75 <1.51 <1.59 <1.49 <1.56 <1.61 1
% K-40 27.516.1 <13.2 12.6i5.0 184t11 43.5i7.6 43.718.3 Otherst <LLD <LLD <LLD <LLD <LLD <LLD D2 0FF-SITE COMPOSITE ** {
I TlCe-144 <3.57 <8.02 <4.22 <3.64 <9.64 <4.89 Ce-141 <1.23 <2.46 <1.58 <1.58 <2.93 <1.57 Be-7 50.7i5.3 81.517.4 73.917.3 97.3t7.4 95.518.2 96.0 8.9 Zn-65 <2.14 <5.51 <3.75 <3.14 <7.15 <4.42 Cs-134 <0.97 <2.46 <1.66 <0.98 <2.77 <1.63 Cs-137 <0.93 <1.76 <1.36 <1.24 <2.35 <1.35 Zr-95 <1.76 <3.57 <2.93 <2.76 <4.40 <3.02 Nb-95 <1.23 <2.31 <1.89 <1.79 <2.82 <2.04 Co-58 <1.09 <2.02 <2.10 <1.03 <2.88 <1.81 Mn-54 <1.19 <1.84 <1.71 <1.59 <2.35 <1.57 Co-60 <1.79 <2.27 <1.45 <1.46 <2.70 <2.13 K-40 <7.82 216+14 <11.4 12.9i4.9 251i15.5 24.3i7.1 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
- Sample Locations Required by Technical Specifications.
** Optional Sample Location. Not Required By the Technical Specifications.
t Plant Related Radionuclides.
TABLE 6-9 (Courinuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1993 Results in Units of 10'3pCi/m3 1 Sigma INUCLIDES JANUARY? FEBRUARY / MARCH JAPRIO HAYl JUNE E OFF-SITE COMPOSITE ** TlCe-144 <3.63 <8.02 <9.07 <4.13 <4.60 8.61 Ce-141 <1.35 <2.63 <3.40 <1.76 <1.36 <3.34 Be-7 60.7i5.4 92.6i8.0 87.3i9.4 94.5 7.0 91.0t7.6 102+9.2 Zn-65 <2.93 <6.17 <6.50 <3.54 <4.07 <6.29 Cs-134 <1.13 <2.18 <2.61 <1.06 <1.47 <2.52 Cs-137 <0.84 <2.01 <2.06 <1.02 <1.46 <1.85 Zr-95 <2.20 <3.72 <4.03 <2.33 <3.06 <4.36 Nb-95 <1.30 <2.31 <3.02 <1.68 <1.89 <3.06 Co-58 <0.87 <2.18 <2.56 <1.59 <1.57 <2.42 e Mn 54 <1.18 <2.05 <2.04 <1.39 <1.56 <2.38 12 Co-60 <1.37 <1.61 <2.01 <1.37 <2.00 <2.28 K-40 15.0i4.2 216i14 233t14 36.116.4 <20.3 231 15.1 Otherst <LLD <LLD <LLD <LLD <LLD <LLD F 0FF-SITE COMPOSITE ** TlCe-144 <4.40 <4.40 <3.99 <3.16 <4.84 <7.87 Ce-141 <1.58 <1.26 <1.31 <1.34 <1.61 <2.88 Be-7 61.li6.0 96.317.5 68.8 6.2 110i8.0 72.2i7.2 93.518.8 Zn-65 <3.11 <2.54 <3.53 <2.75 <3.17 <5.89 Cs-134 <1.12 <1.21 <1.22 <0.95 <1.17 <2.31 Cs-137 <0.98 <1.36 <1.38 <0.98 <1.14 <1.96 Zr-95 <2.73 <2.86 <2.76 <1.61 <3.01 <3.71 Nb-95 <2.06 <1.77 <1.65 <1.28 <1.84 <2.75 Co-58 <1.46 <1.31 <0.98 <1.59 <1.22 <2.17 Hn-54 <1.40 <1.42 <1.30 <1.15 <1.53 <1.90 Co-60 <1.46 <1.21 <1.74 <0.82 <1.44 <2.00 K-40 21.515.4 <12.3 <16.0 11.214.1 28.316.6 216i13.7 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
** Optional Sample Location. Not Required by the Technical Specifications.
t Plant Related Radionuclides. M M M M M M M M M M M M M M E E E E E
- w- w_ - n - - - -
TABLE 6-9 (Courruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1993 Results in Units of 10~3pCi/m3 i 1 Sigma
-; NUCLIDES JANUARY:L :LFEBRUARY2 LMARCH~ ::APRILL: fMAY:j (JUNE:
G OFF-SITE COMPOSITE ** TlCe-144 <2.97 <5.18 <7.28 <6.23 <8.06 <8.12 Ce-141 <1.07 <1.62 <2.37 <2.34 <2.69 <2.95 Be-7 58.115.4 73.6i7.1 61.8i6.9 94.1 6.9 60.8t7.7 91.818.7 Zn-65 <3.30 <1.78 <5.82 <4.73 <6.13 <6.61 e Cs-134 <1.02 <1.46 <2.34 <1.90 <2.42 <2.17 is Cs-137 <0.68 <1.28 <1.64 <1.48 <1.91 <1.83 Zr-95 <2.18 <2.82 <3.38 <2.88 <4.52 <4.02 Nb-95 <1.44 <2.41 <2.50 <2.21 <2.85 <2.76 Co-58 <1.22 <1.57 <1.93 <1.76 <2.37 <2.24 Mn-54 <1.14 <1.71 <1.92 <1.46 <1.64 <1.88 Co-60 <1.18 <1.46 <1.97 <1.99 <2.09 <2.11 i K-40 <14.7 30.9i6.2 205i13 166i10 222i14 186i13 l Otherst <LLD <LLD <LLD <LLD <LLD <LLD
** Optional Sample Location. Mt Required by the Technical Specifications.
t Plant Related Radionuclides.
- Nw 6 * *N
,, ausma _e m _ _ _
TABLE 6-9 (Courruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES ' 0F JAF/NMP SITE AIR PARTICULATE SAMPLES - 1993 Results in Units of 10 pCi/m3 i 1 Sigma iNUCLIDESh JANUARY 2 FEBRUARY MARCH IAPRILf lMAYi JUNE t D1 ON-SITE COMPOSITE ** TlCe-144 <3.81 <4.42 <4.96 <4.04 <4.49 <5.70 Ce-141 <1.39 <1.29 <1.80 <1.52 <1.61 <2.02 Be-7 55.li5.7 10218.0 81.517.6 96.li7.2 76.0i7.0 94.9 11.0 Zn-65 <3.46 <3.94 <3.70 <3.30 <2.55 <8.05 Cs-134 <1.20 <1.29 <1.26 <1.12 <1.43 <2.21 Cs-137 <1.13 <1.30 <1.38 <0.98 <1.38 <1.71 Zr-95 <2.44 <3.07 <2.60 <2.39 <2.73 <5.23 Nb-95 <1.70 <1.72 <2.19 <1.52 <1.92 <3.08 Co-58 <1.68 <1.16 <1.71 <1.26 <1.53 <1.75 m Mn-54 <1.52 <1.57 <1.49 <1.51 <1.43 <2.33 L
" Co-60 <1.47 <1.78 <2.00 <1.45 <1.38 <2.89 K-40 23.li6.7 <16.0 46.li7.9 7.50i4.6 <20.3 20.3i8.4 Otherst <LLD <LLD <LLD <LLD <LLD <LLD G ON-SITE COMPOSITE **
TlCe-144 <2.94 <4.13 <3.88 <4.05 <8.58 <5.27 Ce-141 <1.03 <1.28 <1.92 <1.58 <2.56 <1.67 Be-7 73.Si5.8 78.6i7.2 72.8t7.1 96.3i7.2 74.4i7.5 10018.1 . Zn-65 <3.21 <3.73 <3.39 <3.87 <6.17 <3.86 Cs-134 <1.08 <1.52 <1.14 <1.17 <2.41 <1.35 Cs-137 <0.80 <1.15 <1.41 <1.05 <1.97 <1.50 Zr-95 <1.87 <2.77 <2.92 <2.41 <3.83 <2.71 Nb-95 <1.43 <1.66 <2.10 <1.92 <2.61 <2.07 Co-58 <0.90 <1.17 <1.39 <1.59 <2.10 <1.58 Mn-54 <1.05 <1.40 <1.54 <1.30 <1.88 <1.31 Co-60 <1.07 <1.07 <1.97 <1.24 <2.07 <2.45 K-40 <12.8 <16.4 <16.8 35.3i6.5 218i13.8 <18.4 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
** Optional Sample Location. N_ot Required by Technical Sr,ecifications.
t Plant Related Radionuclides. M M M M M M M M M M M M M M M M W M M
i TABLE 6-9 (Cour1xuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE3 SAMPLES - 1993 Results in Units of 10' pCi/m i 1 Sigma 1NUCLIDESL JANUARY 1 FEBRUARYJ MARCH iAPRIO tMAD JUNE H ON-SITE COMPOSITE ** TlCe-144
<3.12 <4.59 <4.29 <7.69 <4.81 <6.06 Ce-141 <1.03 <1.36 <1.76 <2.76 <1.61 <1.89 l
Be-7 49.5i5.9 59.6i6.6 84.7i8.7 111i8.6 67.7 7.2 56.1 6.9 Zn-65 <2.90 <3.85 <3.55 <5.50 <3.98 <2.73 Cs-134 <1.11 <1.33 <1.43 <2.26 <1.45 <1.52 Cs-137 <1.17 <1.38 <1.39 <1.78 <1.42 <1.41 Zr-95 <1.86 <2.75 <3.15 <4.29 <2.63 <3.71 Nb-95 <1.54 <1.72 <2.17 <2.82 <1.44 <2.03 Co-58 <1.50 <1.86 <1.86 <2.04 <1.69 <1.60 m Mn-54 <1.31 <0.98 <1.52 <1.83 <1.61 <1.93 e' > Co-60 <1.20 <1.62 <1.20 <1.91 <1.88
" <1.46 K-40 8.54i4.8 <18.5 13.2i5.9 202il2.3 <19.0 <19.6 0therst <LLD <LLD <LLD <LLD <LLD <LLD I ON-SITE COMPOSITE **
TlCe-144 <4.11 <5.40 <4.60 <7.17 <5.03 Ce-141
<5.93
<1.48 <1.95 <1.88 <2.73 <1.73 <1.94 Be-7 54.7i5.9 67.5i6.8 59.7i7.7 102i8.1 61.li6.1 97.918.0 Zn-65 <2.67 <3.57 <3.95 <4.72 <3.11 <4.17 Cs-134 <1.21 <1.51 <1.61 <1.94 <1.27 <1.50 Cs-137 <0.97 <1.44 <1.50 <1.67 <1.21 Zr-95 <1.14
<1.76 <4.17 <3.21 <3.37 <3.38 <3.13 Nb-95 <1.43 <2.11 <1.52 <2.80 <2.19 Co-58
<2.46
<2.15 <1.70 <1.70 <1.91 <2.08 <2.07
~
Mn-54 <1.74 <1.62 <1.46 <1.78 <1.47 <1.47 Co-60 <2.16 <2.02 <1.82 <1.70 <1.24 <2.27 K-40 19.116.3 37.517.4 17.116.2 198t12.4 50.718.8 Otherst 42.418.2
<LLD <LLD <LLD <LLD <LLD <LLD
- Optional Sample Location. Noi; Required by Technical Specifications.
? Plant Related Radionuclides.
TABLE 6-9 (Courruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1993 Results in Units of 10'3pCi/m3 i 1 Sigma (NUCL.IDEST JANUARYj FEBRUAPM MARCH /APRIOl [ MAD JUNE - J ON-SITE COMPOSITE ** TlCe-144 <2.40 <4.81 <4.67 <4.46 <4.48 <4.53 Ce-141 <0.92 <1.43 <1.50 <1.55 <1.71 <1.41 Be-7 44.0 5.5 68.7i7.2 65.6i7.7 78.0i7.0 49.414.7 72.717.9 Zn-65 <2.88 <3.60 <4.76 <3.44 <3.20 <4.35 Cs-134 <1.10 <1.34 <1.36 <1.33 <1.45 <1.39 Cs-137 <0.89 <1.37 <1.41 <1.06 <1.42 <1.09 Zr-95 <1.85 <3.06 <3.63 <2.89 <2.66 <2.54 Nb-95 <1.53 <1.99 <2.25 <1.67 <2.03 <1.81 Co-58 <1.33 <1.59 <1.97 <1.31 <2.03 <1.58 m Mn-54 <1.01 <0.94 <1.71 <1.31 <1.52 <1.63 L
- Co-60 <1.57 <1.99 <1.51 <1.35 <1.22 <1.99 K-40 <12.2 19.315.9 <25.6 <1.36 <19.2 16.7i6.5 Otherst <LLD <LLD <LLD <LLD <LLD <LLD l K ON-SITE COMPOSITE **
TlCe-144 <3.09 <4.65 <7.69 <3.58 <7.97 <5.28 Ce-141 <1.19 <1.47 <2.67 <1.35 <2.60 <1.91 Be-7 47.0i5.3 63.4i6.5 78.9 7.3 90.316.4 60.5t7.4 72.9i7.8 Zn-65 <3.10 <4.20 <5.44 <3.38 <6.04 <4.94 Cs-134 <1.05 <1.52 <2.26 <0.94 <2.52 <1.50 Cs-137 <1.07 <1.26 <1.85 <1.05 <1.73 <1.47 Zr-95 <2.42 <2.83 <3.76 <1.88 <3.80 <3.66 Nb-95 <1.47 <2.02 <2.70 <1.57 <2.71 <2.13 Co-58 <1.53 <1.66 <1.82 <1.30 <2.20 <1.78 Mn-54 <0.93 <1.56 <1.66 <1.24 <1.73 <1.66 Co-60 <1.11 <2.19 <2.12 <1.26 <1.99 <2.09 K-40 19.3i5.1 10.415.6 189i13 34.715.6 194i13.1 47.6i7.2 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
** Optional Sample Location. _N_ot Required by Technical Specifications.
t Plant Related Radionuclides, m M M M M M M M M M M M M M M M M M M
TABLE 6-9 (Courruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1993 Results in Units of 10'3pCi/m3 i 1 Sigma NUCLIDES. tJULYJ AUGUST 4 SEPTEMBER' OCTOBER fNOVEMBER: DECENBERT l R1 0FF-SITE COMPOSITE
- TlCe-144 <4.29 <4.95 <4.67 <4.17 <4.80 <3.95 Ce-141 <1.62 <1.78 <1.87 <1.29 <1.77 <1.63 Be-7 74.016.6 85.518.3 94.2i8.7 88.116.5 79.5t7.3 59.4 6.7 Zn-65 <3.76 <3.68 <4.15 <2.68 <5.53 <2.94 Cs-134 <1.16 <1.40 <1.52 <1.25 <1.55 <1.20 Cs-137 <1.20 <1.20 <1.36 <1.20 <1.45 <0.89 Zr-95 <2.83 <3.20 <2.83 <2.40 <2.56 <1.53 Nb-95 <1.71 <2.55 <2.32 <1.86 <2.38 <1.89 Co-58 <1.44 <1.53 <1.35 <1.27 <1.57 <1.52
, Mn-54 <1.27 <1.55 <1.33 <1.41 <1.22 <1.34 & Co-60 <1.40 <1.96 <1.72 <2.07 <2.43 <1.55 K-40 27.6 6.3 <26.7 <26.5 <11.8 93.2i5.4 14.1 4.9 Otherst <LLD <LLD <LLD <LLD <LLD <LLD R2 0FF-SITE COMPOSITE
- TlCe-144 <3.99 <5.50 <4.66 <3.80 <4.13 <5.17 Ce-141 <1.37 <2.03 <1.63 <1.45 <1.44 <4.19 Be-7 87.2 7.6 79.6i7.9 85.318.1 74.916.4 73.2i7.2 66.516.0 Zn-65 <3.47 <3.59 <3.65 <3.11 <3.46 <2.60 Cs-134 <1.41 <1.54 <1.50 <1.07 <1.42 <0.98 Cs-137 <1.55 <1.25 <1.32 <1.05 <1.47 <1.18 Zr-95 <1.95 <3.86 <2.73 <2.73 <2.54 <2.73 Nb-95 <1.39 <2.18 <2.24 <1.67 <1.69 <1.99 Co-58 <1.39 <2.30 <2.15 <1.36 <1.80 <1.49 Mn-54 <1.31 <1.95 <1.57 <1.31 <1.63 <1.26 Co-60 <1.94 <1.74 <1.55 <1.60 <2.20 <1.92 K-40 <10.6 36.7 8.2 46.3i7.8 36.116.2 14.7i5.5 47.116.5 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
- Sample Locations Required by Technical Specifications.
t Plant Related Radionuclides.
TABLE 6-9 (Courinuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES ' OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1993 Results in Units of 10 pCi/m i 2 Sigma 3 3 LNUCLIDESl MULY! AUGUST SEPTEEER 10CTOBER lNOVEEER JDECEEER R3 0FF-SITE COMPOSITE
- TlCe-144 <4.36 <9.34 <4.60 <3.58 <5.17 <3.78 Ce-141 <1.50 <3.33 <2.04 <1.28 <1.85 <1.30 Be-7 70.018.2 91.4i9.6 75.115.6 80.117.5 78.2i7.7 75.6i7.2 Zn-65 <4.47 <6.75 <3.90 <3.28 <5.40 <2.62 Cs-134 <1.47 <2.71 <1.51 <1.05 <1.74 <1.38 Cs-137 <1.31 <2.27 <1.68 <1.06 <1.35 <1.01 Zr-95 <3.61 <4.94 <4.11 <2.85 <3.33 <2.96 Nb-95 <2.50 <2.90 <1.83 <1.58 <1.64 <2.35 Co-58 <1.81 <2.69 <1.72 <1.57 <1.60 <1.16 m Mn-54 <1.93 <2.52 <1.72 <1.55 <1.66 <1.67 s Co-60 <1.40 <2.38 <1.93 <1.67 <1.29 <1.48 K-40 <27.0 225i14.8 11.914.6 <10.0 38.3i8.3 <15.0 Otherst <LLD <LLD <LLD <LLD <LLD <LLD R4 0FF-SITE COMPOSITE
- TlCe-144 <4.23 <4.17 <5.13 <4.06 <5.03 <4.02 Ce-141 <1.45 <1.73 <2.06 <1.39 <1.65 <1.65 Be-7 65.816.1 86.7i8.5 92.li8.5 61.2i5.9 74.6i7.2 60.9i6.6 Zn-65 <3.20 <2.44 <5.13 <2.57 <3.09 <2.10 Cs-134 <1.34 <1.43 <1.43 <0.88 <1.39 <1.12 Cs-137 <1.14 <1.54 <1.53 <1.21 <1.17 <0.91 Zr-95 <2.60 <2.28 <3.91 <2.64 <3.19 <2.03 Nb-95 <1.54 <2.13 <2.25 <1.72 <2.27 <1.55 Co-58 <1.51 <2.26 <1.90 <1.67 <1.80 <1.25 Mn-54 <1.29 <1.31 <1.56 <1.06 <1.63 <1.11 Co-60 <1.37 <2.41 <2.42 <1.68 <2.28 <1.35 K-40 36.317.0 <24.5 31.117.3 25.4i6.2 52.118.6 28.6i6.1 Otherst <LLD <LLD <LLD <LLD <LLD <LLD o Sample Locations Required by Technical Specifications.
9 Plant Related Radionuclides. W W M M M M M M M M M M M M M M M M M
TABLE 6-9 (Conrruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE3 SAMPLES - 1993 Results in Units of 10-3pCi/m i 1 Sigma NUCLIDES? TJULY AUGUST >SEPTENER! OCTOBER LNOVEM ERL _DECEEER R5 0FF-SITE COMPOSITE (COMROL)* TlCe-144 <4.21 <3.76 <5.03 <5.74 <4.11 <3.67 Ce-141 <1.43 <1.62 <1.79 <1.96 <1.44 <1.41 Be-7 76.6i6.7 85.118.6 74.4i7.2 77.6 6.4 69.5i7.3 60.716.0 Zn-65 <2.97 <3.48 <3.14 <3.96 <2.32 <2.04 Cs-134 <1.02 <1.49 <1.20 <1.49 <1.33 <1.10 Cs-137 <1.26 <1.11 <1.15 <1.29 <1.63 <0.82 Zr-95 <2.19 <2.61 <2.47 <2.87 <2.73 <2.11 Nb-95 <1.31 <2.29 <1.89 <1.89 <1.99 <1.81 l Co-58 <1.59 <1.73 <1.02 <1.72 <1.30 <1.22 Mn-54 <1.27 <1.75 <1.43 <1.59 <1.74 <1.14
? Co-60 <1.12 <2.03 <1.97 <1.58 <2.60 <1.27 PJ K-40 15.514.3 19.li6.3 <13.7 139 9.7 10.515.2 <17.2 Otherst <LLD <LLD <LLD <LLD <LLD <LLD D2 0FF-SITE COMPOSITE **
TlCe-144 <3.50 <5.31 <5.67 <4.47 <8.06 <4.28 Ce-141 <1.33 <2.06 <2.06 <1.45 <2.64 <1.79 Be-7 86.0i7.3 91.219.0 73.8i8.0 79.5i7.0 65.017.8 69.516.8 Zn-65 <2.38 <3.51 <4.12 <2.91 <2.38 <3.66 Cs-134 <1.46 <1.26 <1.34 <1.02 <1.92 <1.34 Cs-137 <1.18 <1.29 <1.56 <1.21 <1.77 <1.06 Zr-95 <1.73 <2.49 <3.68 <2.42 <3.88 <3.03 Nb-95 <1.44 <1.50 <3.30 <1.87 <2.53 <2.37 Co-58 <1.93 <1.24 <1.79 <1.68 <2.84 <1.61 Mn-54 <1.26 <1.37 <1.59 <1.28 <2.01 <1.28 Co-60 <1.30 <1.56 <2.80 <1.70 <1.90 <1.90 K-40 <17.4 30.5i7.5 42.219.0 9.9014.4 192i13.6 26.2i7.4 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
- Sample Locations Required by Technical Specifications.
** Optional Sample Location. N_qt Required By the Technical Specifications.
t Plant Related Radionuclides. CMMc0M
TABLE 6-9 (Ceurinuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE3 SAMPLES - 1993 Results in Units of 10'3pCi/m 1 Sigma fNUCLIDES0 TJULYs AUGUST SEPTEMER f0CTOBER NOVEEER iDECEEER E OFF-SITE COMPOSITE ** T1Ce-144 <4.40 <5.22 <4.55 <3.95 <4.41 <3.51 Ce-141 <1.38 <1.82 <1.77 <1.38 <1.57 <1.30 Be-7 76.0t7.9 125t10.4 10518.5 79.816.2 68.617.0 68.7i6.8 Zn-65 <4.87 <3.74 <4.41 <3.35 <3.97 <2.71 Cs-134 <1.69 <1.85 <1.63 <1.11 <1.55 <1.32 C3-137 <1.07 <1.48 <1.33 <1.23 <1.29 <1.00 Zr-95 <2.81 <2.55 <2.30 <2.65 <3.20 <1.82 Nb-95 <2.22 <2.49 <1.91 <1.77 <2.14 <1.61 Co-58 <2.04 <2.14 <2.42 <1.45 <1.20 <1.20 m Mn-54 <2.08 <2.10 <1.94 <0.84 <1.21 <1.24 d> " Co-60 <2.33 <1.64 <2.01 <0.99 <1.58 <1.19 K-40 <21.1 <3.93 17.5i6.4 32.7i6.1 <19.8 12.2i4.1 Otherst <LLD <LLD <LLD <LLD <LLD <LLD F 0FF-SITE COMPOSITE ** TlCe-144 <3.50 <4.57 <3.87 <3.27 <4.63 <3.42 Ce-141 <1.33 <1.96 <1.46 <1.03 <1.60 <1.44 Be-7 71.7i6.1 87.4i7.6 96.818.2 69.316.1 68.217.0 60.316.1 Zn-65 <3.63 <3.87 <3.56 <2.77 <1.45 <3.74 Cs-134 <0.89 <1.22 <1.38 <1.08 <1.19 <0.94 Cs-137 <0.96 <1.23 <1.28 <1.03 <1.20 <0.96 Zr-95 <1.84 <3.02 <2.06 <1.80 <2.75 <2.42 Nb-95 <1.28 <2.40 <1.72 <1.27 <1.96 <1.81 Co-58 <1.19 <1.26 <1.82 <1.04 <1.71 <1.58 Mn-54 <1.18 <1.60 <1.41 <1.21 <1.40 <1.18 Co-60 <1.57 <1.79 <1.60 <1.55 <1.82 <1.45 K-40 <7.77 8.9014.8 <13.9 <8.46 40.6i7.2 9.1914.2 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
** Optional Sample Location. ht Required by the Technical Specifications.
t Plant Related Radionuclides. m M M M M M M M M M M M M M M M M M E
)
TABLE 6-9 (Courinuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1993 Results in Units of 10' pCi/m3 1 Sigma i NUCLIDES!: fJULY AUGUST SEPTEMBER:i ;OCTOB$Ri NOVEMBER 4 DECEMBER 1 G OFF-SITE COMPOSITE ** TlCe-144 <3.51 <8.29 <4.99 <3.61 <7.24 <3.42 Ce-141 <1.22 <3.12 <1.80 <1.26 <2.55 <1.54 Be-7 78.3i5.9 79.2i8.3 70.5i66.6 59.9 5.4 56.8i7.3 5.82i5.4 Zn-65 <2.65 <5.70 <3.26 <2.67 <5.47 <2.84 Cs-134 <1.05 <2.15 <1.17 <1.01 <1.67 <1.14 Cs-137 <0.81 <1.84 <1.19 <0.78 <1.68 <0.100
? Zr-95 <1.65 <3.90 <2.58 <2.06 <3.91 <2.05
% Nb-95 <1.30 <3.01 <1.93 <1.24 <2.67 <1.66 Co-58 <1.46 <2.50 <2.08 <1.13 <2.26 <1.46 Hn-54 <1.17 <1.98 <1.48 <0.95 <1.89 <0.86 Co-60 <1.32 <2.24 <1.97 <0.77 <1.88 <1.68 K-40 6.04i3.5 216114.1 47.517.1 34.015.7 168112.3 29.315.8 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
** Optional Sample Location. Not Required by the Technical Specifications.
t Plant Related Radionuclides. i y l' l I
TABLE 6-9 (ConTruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE3 SAMPLES - 1993 Results in Units of 10~ pCi/m 1 Sigma fNUCLIDES} 9JULYi " AUGUST fSEPTEEER !0CTOBER 1NOVEEER : DECEEER D1 ON-SITE COMPOSITE ** TlCe-144 <3.54 <3.40 <4.52 <3.54 <4.42 <3.93 Ce-141 <1.29 <1.46 <1.70 <1.20 <1.38 <1.71 Be-7 86.916.2 99.3i7.9 76.016.8 72.4i5.6 69.016.6 73.2 6.9 Zn-65 <2.83 <3.73 <3.50 <3.21 <2.46 <1.82 Cs-134 <0.75 <1.41 <1.02 <1.03 <0.97 <1.08 Cs-137 <1.23 <1.32 <0.97 <1.21 <1.11 <0.69 Zr-95 <2.29 <1.91 <1.90 <1.96 <2.45 <2.38 Nb-95 <1.41 <1.78 <1.22 <1.45 <1.47 <1.93 Co-58 <1.28 <2.13 <1.31 <1.10 <1.58 <1.08 , Mn-54 <1.12 <1.18 <0.95 <0.83 <1.16 <1.21 6 Co-60 <1.55 <1.52 <1.44 <1.45 <1.21 <1.80 K-40 <18.2 11.lt5.4 34.9i6.9 <12.4 22.617.1 34.616.7 Otherst <LLD <LLD <LLD <LLD <LLD <LLD - G ON-SITE COMPOSITE ** TlCe-144 <4.37 <8.80 <5.00 <3.85 <6.48 <3.89 Ce-141 <1.37 <2.95 <1.61 <1.33 <2.19 <1.35 Be-7 62.Si7.7 104i8.6 72.li7.4 66.7i6.0 60.116.5 65.816.6 Zn-65 <4.70 <6.78 <4.51 <3.36 <3.91 <1.59 Cs-134 <1.33 <2.73 <1.27 <1.21 <1.70 <1.36 Cs-137 <1.46 <2.07 <1.11 <0.87 <1.38 <1.26 Zr-95 <3.51 <4.83 <2.44 <2.60 <2.93 <1.62 Nb-95 <1.69 <3.34 <1.92 <1.82 <2.02 <0.99 Co-58 <1.79 <2.25 <1.42 <1.43 <2.08 <1.66 Hn-54 <1.65 <2.26 <1.34 <1.34 <1.57 <1.57 Co-60 <2.45 <2.19 <1.84 <1.37 <2.01 <1.93 K-40 27.716.8 214i14.2 42.3i9.0 51.3i7.3 180i11.4 <12.9 Otherst <LLD <LLD <LLD <LLD <LLD <LLD o* Optional Sample Location. Noto Required by the Technical Specifications. t Plant Related Radionuclides. M M M M M M M M M M M M M M M M M M M
TABLE 6-9 (Courruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTi!I_Y COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1993 Results in Units of 10 pCi/m i 1 Sigma 3 3 l i iNUCLIDESL iJULYJ AUGUST SEPTEEER 10CTDBER NOVEMER DECEMER l H ON-SITE COMPOSITE ** TlCe-144 <4.07 <5.60 <5.49 <4.51 <4.62 <4.19 ' Ce-141 <1.52 <1.70 <2.08 <1.41 <1.66 <1.47 Be-7 82.616.5 67.4i7.9 82.3i7.9 74.416.3 69.3t7.0 62.516.3 Zn-65 <3.38 <4.77 <3.34 <3.83 <4.86 <2.15 I Cs-134 <1.14 <1.45 <1.51 <1.16 <1.60 <1.20 Cs-137 <1.11 <1.42 <1.49 <0.91 <1.48 <1.24 I Zr-95 <2.63 <3.06 <2.47 <2.21 <2.76 <2.80 Nb-95 <1.70 <1.98 <2.14 <1.53 <1.46 <2.04 Co-58 <1.58 <1.78 <1.53 <1.65 <1.68 <1.44 m Mn-54 <1.14 <1.85 <1.55 <1.00 <1.58 <0.97 d> Co-60 <1.50 <1.47 <2.33 <1.52 <1.64
* <1.33 K-40 23.6i6.37 <21.7 23.318.0 18.2 5.6 19.416.4 <16.7 Otherst <LLD <LLD <LLD <LLD <LLD <LLD I ON-SITE COMPOSITE **
TlCe-144 <7.37 <4.89 <5.09 <3.85 <5.43 <3.97 Ce-141 <2.48 <1.92 <1.98 <1.38 <2.00 <1.44 Be-7 75.4i4.3 69.li6.9 81.6i7.7 72.2i6.5 57.0i7.0 60.2i5.6 Zn-65 <5.34 <5.13 <3.36 <3.35 <3.77 <3.05 Cs-134 <1.90 <1.34 <1.31 <1.31 <1.53 <0.93 Cs-137 <1.67 <1.35 <1.33 <1.21 <1.27 <0.89 Zr-95 <3.66 <3.62 <2.76 <2.60 <3.70 <1.71 Nb-95 <2.88 <2.31 <2.30 <1.67 <2.14 <1.68 Co-58 <2.16 <1.71 <1.95 <1.35 <1.91 <1.51 Mn-54 <1.87 <1.55 <1.25 <1.33 <1.66 <1.19 Co-60 <2.08 <2.29 <1.76 <1.13 <2.02
<1.64 K-40 190i7.1 52.819.0 37.018.5 16.614.4 55.418.8 45.6i6.2 L Otherst <LLD <LLD <LLD <LLD <LLD <LLD ,
** Optional Sample Location. Not Required by the Technical Specifications.
t Plant Related Radionuclides. I
- -]M
TABLE 6-9 (Courruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE3SAMPLES - 1993 Results in Units of 10~ pCi/m + 2 Sigma {NUCLIDES} iJULY/ AUGUST SEPTEEER 70CTOBER LNOVEEER LDECEEER J ON-SITE COMPOSITE ** TlCe-144 <3.88 <4.38 <4.82 <4.53 <5.12 <3.51 Ce-141 <1.31 <1.62 <1.92 <1.59 <1.58 <1.27 Be-7 75.8i6.7 72.8i7.6 74.1 8.3 78.3i6.8 76.5i7.8 65.2i6.2 Zn-65 <3.13 <3.94 <4.82 <4.31 <3.49 <2.78 Cs-134 <1.56 <1.54 <1.74 <1.39 <1.66 <1.06 Cs-137 <1.21 <1.57 <1.44 <1.10 <1.18 <0.99 Zr-95 <2.40 <2.57 <3.06 <3.04 <3.28 <1.56 Nb-95 <1.75 <2.32 <2.01 <2.11 <2.44 <1.19 Co-58 <2.05 <1.58 <2.41 <1.81 <2.10 <1.31 2 Mn-54 <0.98 <1.48 <1.97 <1.61 <1.76 <1.10 6
" Co-60 <1.87 <2.14 <1.95 <1.06 <2.04 <1.18 K-40 <21.9 <25.7 13.9i6.7 36.4i6.4 16.5i6.3 <13.4 Otherst <LLD <LLD <LLD <LLD <LLD <LLD K ON-SITE COMPOSITE **
TlCe-144 <4.02 <7.95 <4.50 <3.50 <4.56 <3.87 Ce-141 <1.20 <2.84 <1.61 <1.25 <1.57 <1.68 Be-7 78.Si7.5 90.li8.5 71.4 7.3 59.4i5.2 49.4 6.1 68.3i6.4 Zn-65 <4.89 <6.56 <3.34 <3.55 <4.11 <3.41 Cs-134 <1.38 <2.38 <1.20 <1.10 <1.13 <1.18 Cs-137 <1.25 <1.84 <1.32 <0.92 <1.32 <0.90 Zr-95 <3.05 <4.08 <2.89 <2.40 <2.59 <2.71 Nb-95 <2.55 <2.78 <2.22 <1.21 <1.75 <1.67 l Co-58 <2.22 <2.20 <1.55 <1.12 <1.97 <1.66 l Hn-54 <1.31 <2.02 <1.19 <1.07 <1.03 <1.49 Co-60 <2.50 <1.88 <1.65 <1.21 <1.55 <1.25 i K-40 21.516.8 232*13.8 7.6614.1 18.0i5.1 39.6i7.2 43.0i6.6 l Otherst <LLD <LLD <LLD <LLD <LLD <LLD i
** Optional Sample Location. Not Required by the Technical Specifications.
t Plant Related Radionuclides. , i M M M M M M M M M M M M M M M M M M M I
o o i m w u rm__r, r ,__r r , 1 < t - m TABLE 6-10 1 DIRECT RADIATION MEASUREMENT RESULTS (1993) Results in Units of mrem /std. Month i 1 Sigma STATION FIRST- :SECOND . THIRD: LFOURTH: LOCATION. .(DI AN AND NUPEER QUARTERi QUARfER . QUARTER. QUARTER DIRECTION)** 3 D1 On-site 7.6il.0 10.9 1.0 13.611.1 12.5tl.6t 0.2 miles @ 69 l 4 D2 On-site 4.6i0.7 4.410.2 7.113.2 5.2i0.5t 0.4 miles @ 140 l 5 E On-site 4.3i0.6 4.610.2 5.910.9 4.0 0.4t 0.4 miles @ 175 l 6 F On-site 3.4i0.1 3.510.3 5.810.6 4.010.6t 0.5 miles @ 210 l 7* G On-site 3.6i0.3 3.3i0.2 4. to.4 3.510.7t 0.7 miles @ 250 8 R-5 Off-site Control 4.4i0.3 4.410.1 5.NO.2 4.910.6t 16.4 miles @ 42 9 D1 Off-Site 3.910.2 3.710.4 5.220.4 4.4i0.4t 11.4 miles @ 80 10 D2 Off-site 3.410.2 3.210.2 5.2i0.4 4.2i0.5t 9.0 miles @ 117 l 11 E Off-site 3.510.2 3.3i0.2 4.7i0.3 4.4i0.8t 7.2 miles @ 160 12 F Off-site 3.8i0.2 3.510.1 6.610.2 4.3i0.6t 7.7 miles @ 190 13 G Off-site 4.410.4 4.210.5 5.4i0.3 4.410.St 5.3 miles @ 225
? 14* DeMass Rd., SW Oswego-Control 4.2i0.5 4.3i0.3 5.310.3 4.711.0t 12.6 miles @ 226 l Ife 15* Pole 66. W. Boundary-Bible Camp 4.210.3 3.210.1 5.3i0.5 3.910.4t 0.9 miles @ 237 l 18* Energy Info. Center-Lamp Post, SW 4.110.4 3.910.2 5.210.3 4.6i0.9t 0.4 miles @ 265 19 East Boundary-JAF, Pole 9 4.4i0.2 3.9 0.4 5.9i0.3 4.7i0.St 1.3 miles @ 81 23* H On-site 3.910.4 4.2i0.2 6.510.8 5.2i0.6 0.8 miles @ 70 24 I On-site 3.810.5 3.8i0.7 5.8i0.6 3.9 0.5 0.8 miles @ 98 25 J On-site 3.li0.5 3.510.2 4.610.3 3.810.4 0.9 miles @ 110 26 K On-site 3.8 0.3 4.0i0.6 5.7i0.9 3.510.5 0.5 miles @ 132 27 N. Fence, N. of Switchyard, JAF 11.lil.2 16.9i2.3 21.112.5 16.312.3 0.4 miles @ 60 28 N. Light Pole N. of Screenhouse, 17.214.0 21.6i4.7 33.717.6 24.1 5.0 0.5 miles @ 68 JAF 29 N. Fence N. of W. Side 14.112.9 19.714.4 27.6 6.0 20.514.1 0.5 miles @ 65 30 N. Fence (NW) JAF 8.910.9 13.5 1.5 17.8i2.0 12.6il.3 0.4 miles @ 57 l 31 N. Fence (NW) NMP-1 7.li0.8 5.810.4 8.210.9 6.610.8 0.2 miles @ 276 39 N. Fence, Rad. Waste-NMP-1 9.211.5 8.6i1.0 9.9tl.0 8.7 1.0 0.2 miles @ 292 47 N. Fence, (NE) JAF 5.3i0.7 5.5i0.9 7.310.8 6.210.8 0.6 miles @ 69 49* Phoenix, NY-Control 4.0i0.4 3.4i0.1 5.310.5 3.610.3 19.8 miles @ 170 51 Liberty & Bronson Sts.. E of OSS 4.510.5 3.910.3 5.li0.5 4.810.3 7.4 miles @ 170 52 East 12th & Cayuga Sts., Oswego 4.3 0.2 3.410.1 5.010.3 3.910.3 5.8 miles @ 227 School
TABLE 6-10 (C@NTINUED) DIRECT RADIATION MEASUREMENT RESULTS (1993) Results in Units of mrem /std. Month 1 Sigma STATION 1FIRST{ :LSECOE >THIRDL LFOURTHi 2
- 10 CATION L NUMERi N(DESTANDIRE QUARTER QUARTER QUARTER QUARTER" 53 Broadwell & Chestnut Sts. - 3.9i0.1 < 4.3i0.3 5.710.4 4.7i0.3 13.7 miles @ 183 Fulton H.S.
54 Liberty St. & Co. Rt. 16 - 4.2i0.6 3.8i0.3 4.810.3 4.510.7 9.3 miles @ 115 Mexico H.S. 55 Gas Substation Ca. Rt. 5-Pulaski 4.3i0.5 3.7i0.2 5.210.4 4.010.4 13.0 miles @ 75 56* Rt. 104-New Haven SCH.(SE Corner) 4.2i0.2 3.9i0.2 5.710.5 4.li0.2 5.3 miles @ 123 58* Co. Rt. lA-Alcan (E. of Entrance 4.3i0.2 4.3i0.2 5.810.3 3.9i0.2 3.1 miles @ 220 Rd.) 75* Unit 2 N. Fence. N. of Reactor 5.610.4 5.510.5 7.5 0.7 7.7i0.6 0.1 miles @ 5 Bldg. 76* Unit 2 N. Fence, N. of Change 4.610.2 5.2i0.4 6.410.2 4.9i0.5 0.1 miles @ 25
? House d 77* Unit 2, N. Fence, N. of Pipe Bldg. 5.610.3 5.6i0.4 7.7i0.6 5.8i0.6 9.2 miles @ 45 JAF, E. of E. Old Lay Down Area 78* Co. Rt. 29, Pole #63, 0.2 mi . S. 4.2i0.5 4.510.3 6.010.4 4.610.5 1.0 miles @ 90 79* of Lake Rd. 3.7i0.2 4.310.5 5.010.2 4.910.3 1.1 miles @ 115 Co. Rt. 29, Pole #54, 0.7 mi. S.
80* of Lake Rd. 4.0i0.3 3.8i0.4 5.5i0.7 4.0i0.5 1.4 miles @ 133 Miner Rd. , Pole #16, 0.5 mi . W 81* of Rt. 29 3.6i0.2 4.li0.3 5.7 0.3 4.4i0.3 1.6 miles @ 159 Miner Rd. , Pole #1 1/2,1.1 mi . 82* W. of Rt. 29 3.8i0.2 3.9 0.2 5.110.4 3.810.3 1.6 miles @ 181 Lakview Rd., Tree 0.45 mi. N. of 83* Miner Rd. 3.610.4 4.2i0.1 5.4i0.3 3.910.3 1.2 miles @ 200 Lakeview Rd. , N. , Pole #6117, 84* 200 ft. N. of Lake Rd. 3.710.2 4.0i0.3 5.2i0.4 4.0i0.2 1.1 miles @ 225 Unit 1. N. Fence, N. of W. Side 85* of Screen House 9.7il.3 9.2il.2 11.7tl.3 9.0i0.9 0.2 miles @ 294 Unit 2. N. Fence N. of W. Side of 86* Screen House 6.5i0.8 6.511.1 7.5il.6 6.4+1.0 0.1 miles @ 315
TABLE 6-10 (CONTINUED) DIRECT RADIATION MEASUREMENT RESULTS (1993) Results in Units of mrem /std. Month i 1 Sigma STATION FIRST) 1SECOND1 UTHIRD LOCATION L FOURTlt AND' l NUMBERh QUARTER 3(DISTAN QUARTERL QUARTER QUARTER: hDIRECTION)** 87* Unit 2, N. Fence, N. of E. Side 5.9i0.8 6.410.7 8.111.3 7.810.8 0.1 miles @ 341 of Screen House 88* Hickory Grove Rd. , Pole #2. 0.6 4.lf0.1 3.7 0.2 5.910.9 4.2i0.6 4.5 miles @ 97 mi. N. of Rt. 1 89* Leavitt Rd., Pole #16, 0.4 mi. S. 3.9i0.1 4.310.3 6.211.1 4.4 0.6 4.1 miles @ 111 of Rt. 1 90* Rt. 104, Pole #300, 150 Ft. E. 3.5i0.2 3.9i0.3 5.0i0.4 5.li0.5 4.2 miles @ 135 of Keefe Rd. 91* Rt. 51A, Pole #59, 0.8 mi . W. 3.810.1 3.810.2 5.410.4 4.310.5 4.8 miles @ 156 of Rt. 51 92* Maiden Lane Rd., Power Pole. 0.6 4.310.3 5.210.5 6.3 0.5 5.110.4 4.4 miles @ 183
? mi. S. of Rt. 104 $ 93* Rt. 53 Pole 1-1, 120 ft. S. 4.7i0.2 5.0i0.4 5.410.9 5.lil.0 4.4 miles @ 205 of Rt. 104 94* Rt.1, Pole #82, 250 ft. E. of 3.410.1 3.7i0.3 4.210.3 4.010.3 4.7 miles @ 233 Kocher Rd. (Co. Rt. #63) 95* Lakeshore Camp Site, from Alcan W. 3.8i0.3 3.8i0.2 5.010.5 3.8i0.3 4.1 miles @ 237 access Rd. Pole #21,1.2 mi .
N. of Rt. 1 96* Creamery Rd. , 0.3 mi. S. of Middle 4.510.3 4.310.1 5.0t0.3 5.li0.8 3.6 miles @ 199 Rd. Pole 1 1/2 97* Rt. 29. Pole #50, 200 ft. N. of 4.610.3 3.7i0.3 5.5f0.5 3.910.4 1.8 miles @ 143 Miner Rd. 98* Lake Rd., Pole #145, 0.15 mi. 4.3i0.2 4.2f0.3 5.6i0.8 4.4 0.4 1.2 miles @ 101 of of Rt. 29 99 NMP Rd. , 0.4 mi . N. of Lake Rd. , 3.510.4 3.610.2 5.010.2 4.5i0.3 1.8 miles @ 88 Env. Station R1 Off-site 100 Rt. 29 and Lake Rd., Env. Station 4.410.4 3.910.3 4.510.3 4.210.2 1.1 miles @ 104 R2 Off-site 101 Rt. 29, 0.7 mi. S. of Lake Rd., 4.510.1 3.810.3 4.8i0.4 3.7i0.3 1.5 miles @ 132 Env. Station R3
TABLE 6-10 (CONTINUED) DIRECT RADIATION MEASUREMENT RESULTS (1993) Results in Units of mrem /std. Month i 1 Sigma FIRSTS ? THIRD) iF00RTH{ STATION f' LOCATION: QUARTER; SSEC0% QUARTER" 3(DkAN AhD Nt#EER QUARTERJ QUARTERJ iDIRECTION)**N 102 EOF /Env. Lab. Oswego Co. Airport 4.li0.2 4.310.5 4.510.2 4.410.3 11.9 miles @ 175 (Fulton airport, Rt.176) 103 EIC East Garage Rd., Lamp Post R3 4.3i0.2 4.310.4 6.0i0.3 4.110.3 0.4 miles @ 267 Off-site 104 Parkhurst Road, Pole #1481/2-A, 4.5i0.2 3.810.3 5.0i0.2 4.410.3 1.4 miles @ 102 0.1 miles South of Lake Rd. 105 Lakeview Rd. , Pole #6125, 0.6 mi . 4.110.2 4.510.1 5.7i0.6 3.7 0.2 1.4 miles @ 198 South of Lake Road 2 106 Shoreline Cove, East of NMP-1, 4.7i0.4 4.6i0.5 6.0i0.3 4.7i0.5 0.3 miles @ 274 A Tree on West Edge
~
107 Shoreline Cove East of NMP-1 5.li0.3 4.6i0.3 5.410.5 4.6i0.3 0.3 miles @ 272 108 Pole #143, South of Lake Road. 4.810.3 4.110.3 5.410.4 4.110.3 1.1 miles @ 104 300 ft. East of Rt. 29 109 Tree North of Lake Road 300 ft. 4.0i0.3 4.010.2 5.5 0.3 3.910.3 1.1 miles @ 103 l East of Route 29 111 Control, Sterling, NY 4.610.2 4.010.3 5.3i0.2 4.210.4 21.8 miles @ 214 113 Control Baldwinsville, NY 3.810.3 3.910.3 4.6i0.2 3.610.3 24.7 miles @ 17B?
- Technical Specification Location
** Direction and distance based on NMP-2 reactor centerline and sixteen 22.5 degree sectors o** TLD lost in field t Results from Panasonic TLD System. See Section 3.5.
l M M M M M M M M M M M M M M m m m m m
TABLE 6-11 CONCENTRATIONS OF IODINE-131 IN MILK Resu'Its in Units of pCi/ liter i 1 Sigma
- ! STATION */ :04/05/53) id4/19/93 : LD5/03/93:5 !85/17/93!. !!d6/07/95$ IO6/21/931 No. 60 <0.499 <0.371 <0.405 <0.451 <0.363 <0.657 No. 55 <0.421 <0.567 <0.595 <0.405 <0.544 <0.377 No. 50 <0.335 <0.337 <0.371 <0.381 <0.494 <0.450 No. 7 <0.463 <0.440 <0.502 <0.597 <0.449 <0.349 No. 4 <0.602 <0.438 <0.778 <0.373 <0.735 <0.471 No. 65 (Control) <0.383 <0.370 <0.652 <0.347 <0.397 <0.612
- Corresponds to sample locations noted on the maps in Section 3.3.
TABLE 6-11 (conrrnuto) CONCENTRATIONS OF IODINE-131 IN MILK Results in Units of pCi/ liter i 1 Sigma i iSTATION*J LO7/06/931 :.07/19/939 708/02/930 208/16/93l !09/07/93? i09/20/931 No. 60 <0.330 <0.608 <0.440 <0.369 <0.333 <0.427 No. 55 <0.365 <0.657 <0.364 <0.494 <0.428 <0.508 No. 50 <0.389 <0.439 <0.464 <0.516 <0.412 <0.535
?
8 No. 7 <0.442 <0.352 <0.360 <0.428 <0.378 <0.452 No. 4 <0.413 <0.387 <0.490 <0.723 <0.658 <0.519 No. 65/73 <0.595 <0.515 <0.638 <0.677** <0.614** <0.465** (Control)
- Corresponds to sample locations noted on the maps in Section 3.3.
** New control location number 73 1
m m m m m m m m m m M M M M M M M m W
sum uma uma ame uma uma uma amm uma amm num aus uma sum uma amo mas amm si TABLE 6-11 (Courruuso) CONCENTRATIONS OF IODINE-131 IN MILK Results in Units of pCi/ liter 1 Sigma iSTATiON*? ?10/04/931 sid/18/93) 511701/93i sli/15/93) ;12/06/93i .:12/20/93i No. 60 <0.487 <0.412 -<0.451 <0.417 <0.577 <0.369 No. 55 <0.403 <0.364 <0.400 <0.507 <0.386 <0.390 No. 50 <0.437 <0.337 <0.450 <0.458 <0.447 <0.340 No. 7 <0.377 <0.437 <0.397 <0.367 <0.367 <0.390 No. 4 <0.370 <0.400 <0.568 <0.375 < 0.373 <0.440 No. 73 <0.338 <0.551 <0.344 <0.586 <0.337 <0.339 (Control)
- Corresponds to sample locations noted on the maps in Section 3.3. :
i I l_ _ - _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ __m_--_ _ __ - _ __ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
I TABLE 6-12 CONCENTRATIONS OF GAMMA EMITTERS IN MILK Results in Units of pCi/ liter i 1 Sigma l STATION
- NUCLIDES _04/05/93 04/19/93 05/04/93 105/17/93 06/07/93 L 06/21/93 No.60 K-40 1640149 1590 69 2680i73 2720i73 1540 75 1770i72 g Cs-134 <6.50 <6.21 <10.6 <10.6 <7.61 <6.00 5 Cs-137 <6.26 <6.49 <8.24 <8.00 <6.75 <5.84 Ba/La-40 <6.56 <8.58 <7.58 <7.10 <l 2.1 <9.01 Otherst <lLD <LLD <LLD <LLD <LLD <LLD No.55 K-40 2620i72 1440168 1450 73 1520 67 1490i75 1620178 Cs-134 <9.90 <5.78 <6.95 <6.32 E
<7.2 7 <7.96 g Cs-137 <8.12 <6.32 <7.23 <6.82 <5.86 <6.55 Ba/La-40 <8.73 <8.71 <11.5 <4.57 <9.86 <7.35 Otherst <LLD <LLD <LLD E
<LLD <LLD <LLD E No.50 K-40 1710 71 2560f72 1550 75 1600 69 2730i75 2680i72 Cs-134 <5.18 <9.44 <6.67 <6.25 <10.1 < 10.3 Cs-137 <6.76 <8.09 <7.23 <6.32 <8.34 <8.69 Ba/La-40 <7.77 <7.33 <8.72 <8.49 <7.81 <6.59 g l Otherst <LLD <LLD <LLD <LLD <LLD <LLD g No.7 K-40 1480 76 1270 71 1540 67 1340i71 1490i68 1410 63 Cs-134 <7.10 <7.10 <6.13 <6.72 <5.62 <5.83 Cs-137 <6.94 <7.01 <6.54 <6.78 <6.82 <6.95 Ba/La-40 <8.89 <7.73 <6.86 <8.89 <7.07 <8.75 Otherst <LLD <LLD <LLD <LLD <LLD <LLD No.4 K-40 1570 67 2610172 1490166 1650 69 1530167 1790172 Cs-134 <5.65 <10.1 <5.61 <6.17 <5.70 <6.59 Cs-137 <6.18 <8.37 <6.82 <6.37 <6.32 <6.3 7 Ba/La-40 <7.43 <7.38 <10.3 <6.85 <10.1 <8.19 Otherst <LLD <LLD <LLD <LLD <LLD <LLD No.65 K-40 1190iS8 1700i71 1590171 2450170 1790f73 1370165 (Control) Cs-134 <5.65 <6.58 <6.47 <10.1 <5.87 <6.52 g Cs-137 <5.87 <6.54 <6.32 <8.03 <6.20 <6.10 5 Ba/L.a-40 <10.1 <6.54 <8.62 <7.34 <6.69 <9.12 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
- Corresponds to sample locations noted on the maps in Section 3.3.
t Plant related radionuclides. I 6-45
TABLE 6-12 (Courruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MILK Results in Units of pCi/ liter i 1 Sigma STATION
- NUCLIDES '07/06/93 07/19/93 198/02/93 08/16/93. '09/07/93- 09/20/93 No.60 K-40 1320 62 1450 74 2650 73 1720 71 1420164 1580183 Cs-134 <7.41 <7.71 <10.4 <8.37 <5.57 <7.60 Cs-137 <6.95 <5.0 <8.00 <6.02 <5.87 <7.21 Ha/La-40 <9.65 <9.51 <9.09 <9.88 <6.15 < 11.6 Otherst <LLD <LLD <LLD <LLD <LLD <LLD No.55 K-40 1600 68 2530 71 1470 74 1410 78 2690 73 1400i64 Cs-134 <6.00 < 10.3 <7.47 <8.43 <10.1 <5.65 Cs-137 <6.47 <7.51 <7.31 <8.08 <8.06 <6.40 Ba/La-40 <9.62 <6.29 <9.33 <13.3 <9.23 < l 1.0 Otherst <LLD <LLD <LLD <LLD <LLD <LLD No.50 K-40 1350171 1400i65 1360i64 1440 65 1630169 1430 75 Cs-134 <7.21 <6.48 <5.33 <5.56 <6.21 <6.06 Cs-137 <6.38 ~63)2 <6.40 <5.79 <6.26 <6.86 i Ha/La-40 <10.9 <6.94 <7.75 <10.1 <7.41 <7.70 f Otherst <LLD <LLD <LLD <LLD <LLD <LLD No.7 K-40 1490 67 1630 70 2700173 1540168 1420 63 1480i66 Cs-134 <5.65 <7.05 <9.90 <6.25 <5.28 <5.60 Cs-137 <6.54 <6.54 <7.77 <6.49 <6.54 <7.15 Ba/La-40 <9.45 <6.98 <7.78 <8.89 <7.88 <! 4.7 Otherst <ILD <LLD <lLD <LLD <LLD <LLD No.4 K-40 2720 73 1440 64 1530 67 1390 63 1640 70 1670 71 Cs-134 <10.0 <6.74 <6.42 <6.40 <6.38 <6.09 Cs-137 <8.06 <7.46 <6.14 <5.94 <6.37 <5.25 Ha/La-40 <8.37 <10.9 <6.86 <5.85 <8.60 <9.29 l
Otherst <LLD <LLD <LLD <LLD <LLD <LLD No.65 K-40 1750 71 2380 68 1570171 l (Control) Cs-134 <6.17 <9.73 <7.12 Cs-137 <6.37 <8.2 7 <7.38 ** ** ** l l Ila/La-40 <6.54 <7.66
<LLD
<12.0 )
Otherst <LLD <LLD No.73 K-40 1490 66 1560i83 1720 71
] (Control) C.-134 <6.85 <8.42 <5.86 Cs-137 *** *** ***
J <6.75 <6.25 <6.49 Ha/La-40 <8.25 <9.86 <8.16 Otherst <LLD <LLD <LLD 5 Corresponds to sample locations noted on the maps in Section 3.3. t Plant related radionuelides Sample location has been discontinued New sample location starting August 16,1993 6-46
TABLE 6-12 (courinuso) I CONCENTRATIONS OF GAMMA EMITTERS IN MILK Results in Units of pCi/ liter i 1 Sigma i
- STATION
- NUCLIDES 10/04/93 10/18/93 11/01/93' 11/16/93 12/06/93' '12/20/93 No.60 K-40 1510i66 2380165 1570 43 1610 70 Cs-134 <5.43 1570 75 1390 72 g
<6.77 <6.78 <6.58 Cs-137 <6.4 0 <6.40
<6.49 <6.60 3
, <6.70 <5.84 <6.94 <7.16 Ha/La-40 <9.23 <6.82 <9.23 <7.00
<LLD
<8.35 <8.90 g Otherst <LLD <LLD <LLD <LLD <LLD E No.55 K-40 1480 75 1460 51 1460174 1520166 2280164 1560 77 Cs-134 <6.78 <5.24 <6.88 <5.61 <7.38 <7.00 Cs-137 <5.58 <5.87 <5.48 <5.79 <6.50 <6.22 '
- Ha/La-40 < l 2.3 <7.81 <9.90 (8.29 <7.00 <9.36 Otherst <LLD <LLD <LLD <LLD g'
1
<LLD <LLD E No.50 K-40 1480 82 1420 65 1690 71 1490166 1550 76 1290175 l Cs-134 <8.48 <5.87 <6.58 <6.59 <7.36 <7.99 1
Cs-137 <7.21 <7.08 <5.71 <6.10 <6.47 <8.64
'. Ha/La-40 <9.35 <8.65 <4.85 <6.3 7 <11.3 <7.35 Otherst <LLD <t,LD <LLD <LLD <LLD <LLD No.7 K-40 1470i65 1630 69 1390 65 1600169 2100 62 1790 72 4
Cs-134 <5.56 <6.12 <5.51 <5.72 <7.13 <6.38 l Cs-137 <6.32 <5.31 <6.18 <6.20 <6.15 <6.32 ' Ha/La-40 <8.70 <8.51 <10.1 <8.15 <6.94 <8.97 i Otherst <LLD <LLD <LLD <LLD <LLD <LLD l No.4 K-40 1640 70 1520i75 2300161 1550181 1590 86 2400167 Cs-134 <6.55 <7.67 <6.53 <7.32
- Cs-137 <6.76 <6.04
<7.17 <6.90 g
<6.07 <7.96 <7.96 <6.07 5
, Ha/La-40 <9.64 <9.91 <6.30 <7.35 <10.4 <6.95 Otherst <LLD <LLD <LLD <LLD <LLD <LLD No. 73 K-40 1470 79 1350171 1380164 2190i63 1730186 2230164 (Control) Cs-134 <7.53 <6.72 <6.00 <7.29 <7.66 <7.54 Cs-137 <7.41 <6.38 <7.40 <6.05 g Ha/La-40
<7.78 <6.45 g i
<8.49 <8.31 <10.1 <6.02 <10.4 <7.20 Otherst <LLD <LLD <LLD <t,LD <LLD <LLD Corresponds to sample locations noted on the maps in Section 3.3.
t Plant related radionuclides Sample location has been sold 1 I 6-47 1
I TABLE 6-13 I MILK ANIMAL CENSUS 1994 NUMBER.0 NUMBER TOWN OR AREA ( ) CENSUS MAP 1) DEGREES (2) DISTANCE (2) 0F HILK ANIMALS I Scriba 16* 190 5.9 miles l 3 6 190 162 4.5 2.2 NONE 3C 1C 26 114 1.5 I 61 62 140 183 3.0 6.7 NONE NONE 2G 63 185 8.0 35C i I New Haven 9 4* 95 113 5.2 7.8 40C 100C i 45 125 8.0 ND I 10 5 130 146 2.6 7.2 30C 51C 11 130 8.5 NONE I 64 7* 107 107 5.5 7.9 63C 53C 71 111 4.2 NONE I Mexico 72t 98 9.9 33C I 12 14 107 120 11.5 9.8 21C 56C 17 115 10.2 2C l 19 60* 132 90 10.5 9.5 40C 40C 50* 93 8.2 140C l 55* 21 95 112 9.2 10.5 50C 75C 68 108 11.6 l 49 88 7.9 NONE 8G l g Richland 22 85 10.2 46C l Pulaski 23 69 92 85 10.5 11.6 NONE 60C I 6-48 I 1
I TABLE 6-13 (courinuso) g MILK ANIMAL CENSUS 1993 NUMBER ON NUMBER I TOWN OR AREA (a) CENSUS MAP (l)- DEGREES (2) DISTANCE (2) 0F HILK ANIMALS Sterling 65** 220 17.0 miles 25C 73t 234 13.8 miles g 46C (b) Volney 25 182 9.5 NONE 70 147 9.4 27C 66 156 7.8 70C l MILKING ANIMAL TOTALS: (including control locations) 8/2/93 1,107 Cows 8/16/93tt 1,082 Cows (b) l 10 Goats 10 Goats MILKING ANIMAL TOTALS: 1,082 Cows 1,036 Cows (b) I (excluding control locations) 10 Goats 10 Goats tt New control location 8/16/93 I C = Cows I G = Goats
* = Milk sample location l
** = Milk sample control location f = New location ND = Did not wish to participate in the survey (1) = References Section 3.3 I
D (2) = Based on Nine Mile Point Unit 2 Reactor Centerline NONE = No cows or goats at that location. Location was a previous location with cows and/or goats. (a) = Census performed out to a distance of approximately ten miles. (b) = As of August 2,1993 Scott Crawford has gone out of the milking business l and a new control location was added to the REMP. I I 6-49
~
l m m m m e e e e e e e m m M M M M M M 1 TABLE 6-14 i CONCENTRATIONS OF GAMMA EMITTERS IN VARIOUS FOOD PRODUCTS Results in Units of pCi/g (wet) 1 Sigma COLLECTION SAMPLE $ .. .: . . . . . ~ . . . .. .. .
;SITEf LDATEL (DESCRIPTION LBe-7f nKf402 ?I:1314 iCs?134s iCss137s Zn-651 1
09/13/93 Cabbage Leaves 0.1610.03 2.99i0.11 <0.013 <0.012 <0.011 <0.031 l T* 09/13/93 Squash Leaves 0.9610.39 2.9010.09 <0.009 <0.009 <0.008 <0.025
- 09/13/93 Bean Leaves 1.3310.04 6.9510.12 <0.015 <0.016 <0.012 <0.038 09/13/93 Squash Leaves 0.6310.03 2.1110.06 <0.012 <0.007 <0.006 <0.020 K* 09/13/93 Tomato <0.051 2.2810.05 <0.019 <0.006 <0.007 <0.021 09/13/93 Bean Leaves 0.8410.03 2.0010.06 <0.008 <0.006 <0.006 <0.017 L 09/13/93 Squash Leaves 0.8510.02 2.0810.05 <0.017 <0.006 <0.006 <0.018 09/13/93 Pepper Leaves 0.4210.03 4.7010.09 <0.022 <0.007 <0.007 <0.022 09/13/93 Collards 0.42 0.04 4.04 0.13 <0.030 <0.012 <0.012 <0.039 P 09/13/93 Cabbage 0.1910.04 1.9210.09 <0.019 <0.013 <0.009 <0.033 09/13/93 Swisschard 0.3110.04 4.0210.12 <0.023 <0.012 <0.009 <0.032 09/13/93 Lettuce Leaves 0.61i0.07 4.8010.20 <0.026 <0.003 <0.025 <0.068 Z 09/13/93 Grape Leaves 1.32 0.05 2.96i0.09 <0.015 <0.010 <0.009 <0.032 09/13/93 Squash Leaves 0.85i0.03 3.5010.08 <0.008 <0.007 <0.007 <0.022 09/13/93 Beet Leaves 0.20i0.03 5.9410.13 <0.018 <0.011 <0.010 <0.035 M* 09/13/93 Cabbage 0.09i0.04 2.23i0.11 <0.016 <0.013 <0.011 <0.040 (Control) 09/13/93 Squash Leaves 1.70i0.04 3.35i0.09 <0.013 <0.008 <0.008 <0.025 09/13/93 Cucumber Leaves 2.48i0.03 3.1210.06 <0.014 <0.010 0.008i.002 <0.029 09/13/93 Grape Leaves 1.2110.05 2.0110.10 <0.013 <0.013 <0.011 <0.029 09/14/93 Tomato <0.042 2.0010.06 <0.011 <0.005 <0.005 <0.017 NOTE
- Other Plant Related Radionuclides <LLD
- Samples required by Technical Specifications
l I 1 TABLE 6-15 g 1993 RESIDENCE CENSUS HAP . METER 0 LOGICAL I LOCATION DESIGNATIONS -SECTOR DEGREES (') DISTANCE (*) g 1 l W N - - w NNE - - Il, w NE - g w ENE - - Sunset Bay A E 82 0.9 miles Lake Road B ESE 119 0.7 miles g Parkhurst Road C SE 127 1.2 miles County Route 29 D SSE 149 1.2 miles Miner Road E S 173 1.6 miles g Lakeview Road F SSW 210 1.7 miles Lakeview Road G SW 233 1.5 miles Bible Camp Retreat H WSW 249 1.3 miles g w W - - w WNW - - w NW - g w NNW - - w This meteorological sector is over Lake Ontario. There are no residences within three miles. I
"' Based on J. A. FitzPatrick Nuclear Power Plant Reactor Centerline.
- See the maps in Section 3.3.
Ii 6-51 Il
l l 1 7.0 IIISTORICAL DATA TABLES l Sample Statistics from Previous Environmental Samnling The mean, minimum value and maximum value were calculated for selected sample mediums and isotopes. I Special Considerations: l 1. Sample data listed as 1969 was taken from the NINE MILE POINT. PREOPER ATION SURVEY. 1969 and E'NVIRONM ENTAL MONITORING REPORT FOR NIAGAR.A MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION. NOVEMBER,1970. g 2. Sample data listed as 1974 and 1978 through 1992 was taken from the 3 respective environmental operating reports for Nine Mile Point Nuclear Station and James A. FitzPatrick Nuclear Power Plant.
- 3. Only measured values were used for statistical calculations.
I 4. The term MDL was used prior to 1979 to represent the concept of Lower Limit of Detection (LLD). MDL = Minimum Detectable Level. I I I : I I I 7-1
TABLE 7-1 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Results in pCi/g (dry) LOCATION:s: CONTROL $*$
- Isotope l: LCs-:134; TCss137; JCo;60;
[ : Min;-
$ Yea 6 Max. fMeanj LMin: 1 Max > 4Heani Mini -.: Maxk 1Hean:
1969 ** ** ** ** ** ** ** ** ** 1974 ** ** ** ** ** ** ** ** ** 1975 ** ** ** ** ** ** ** ** ** 1976 ** ** ** ** ** ** ** ** ** 1977 ** ** ** ** ** ** ** ** ** 1978 ** ** ** ** ** ** ** ** ** lil79 ** ** ** ** ** ** ** ** ** 19E0 ** ** ** ** ** ** ** ** ** 1981 ** ** ** ** ** ** ** ** ** 1982 ** ** ** ** ** ** ** ** ** 1983 ** ** ** ** ** ** ** ** ** 1984 ** ** ** ** ** ** ** ** ** 1985 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1986 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD [ 1991 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD 0.027 0.027 0.027 <LLD <LLD <LLD o Langs Beach - beyond influence of the site in a westerly direction.
*o No data. Sample not required until new technical specifications implemented in 1985.
I 7-2
l TABLE 7-2 l HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Results in pCi/g (dry) E iL0 CATION:.LINDICATOR
- l l
Isotopei .Cs'1341 ~ Cs-137.J LCo-60} l lye'ar Minb .Hax; -Hean H1n.: :Haxi JHean Hin;:- Haxi iMean; i 1969 ** ** ** ** ** ** ** ** ** 1974 ** ** ** ** ** ** ** ** ** l 1975 ** ** ** 1976 1977 l 1978 1979 l 1980 1981 l 1982 1983 l 1984 ** ** ** ** ** ** ** ** ** 1985 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1986 1987
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1988 1989
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0.25
<LLD 0.32
<LLD 0.29
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1990 1991
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0.28 0.12 0.30 0.14 0.29 0.13
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1992 1993
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0.12 0.18 0.14 0.46 0.13 0.32
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
Sunset Beach - closest off-site location with recreational value.
** No data. Sample not required until new technical specifications implemented in 1985.
7-3
~
TABLE 7-3 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Results in pCi/g (wet)
~
LOCATION: CONTROL
- Isotope . Cs-1371
; Year:: Min. iMax. Mean-1969t No Data No Data No Data 1974t 0.94 0.94 0.94 1975 <MDL <MDL <MDL 1976 1.2 1.2 1.2 1977 0.13 0.13 0.13 1978 0.04 0.20 0.09 1979 0.03 0.06 0.04 1980 0.029 0.110 0.059 1981 0.028 0.062 0.043 1982 0.027 0.055 0.047 1983 0.040 0.060 0.050 1984 0.015 0.038 0.032 1985 0.026 0.047 0.034 1986 0.021 0.032 0.025 1987 0.017 0.040 0.031 1988 0.023 0.053 0.034 1989 0.028 0.043 0.034 1990 0.033 0.079 0.045 1991 0.021 0.034 0.029 1992 0.019 0.026 0.022 - 1993 0.030 0.036 0.033 B
Control location was at an area beyond the influence of the site (westerly direction). I t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. L 7-4
TABLE 7-4 ll HISTORICAL ENVIRONMENTAL SAMPLE DATA l 1 FISH Results in pCi/g (wet)
- LOCATION:D INDICATORE* (letPMAF)I l LIsotope; lCs-1371 g
(Year. Min. fMsxt Mean1 1969t 0.01 0.13 0.06 1974t 0.08 4.40 0.57 1975 g 1.10 1.70 1.38 1976 0.50 3.90 1.4 1977 g 0.13 0.79 0.29 1978 0.03 0.10 0.08 1979 g 0.02 0.55 0.10 1980 0.030 0.100 0.061 1981 g 0.027 0.10 0.061 1982 0.034 0.064 0.050 1983 g 0.030 0.060 0.050 1984 0.033 0.061 0.043 1985 g 0.018 0.045 0.030 1986 0.009 0.051 0.028 1987 g 0.024 0.063 0.033 1988 0.022 0.054 0.032 1989 g 0.020 0.044 0.034 ; 1990 0.027 0.093 0.040 1991 g 0.018 0.045 0.029 1992 0.014 0.030 0.024 1993 g 0.018 0.035 0.028 Indicator locations are in the general area of the NMP-1 and J. A. FitzPatrick cooling water discharge structures, t 1969 data is considered to be pre operational for the site. 1974 data is considered to E be pre-operational for the JAFNPP. m 7-5
TABLE 7-5 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Results in pCi/ liter
.LOCATIONi CONTROL i Isotope? Cs-137) LCo260- ' Year Hin. Max; 'Hean. Min. LHaxi .Heani 1969tt * * * * *
- 1974tt * * * * *
- 1975 * * * * *
- 1976 * * * * *
- 1977 ** ** ** ** ** **
1978 <MDL ** ** **
<MDL <MDL 1979 2.5 2.5 2.5 <LLD <LLD <LLD 1980 <LLD <LLD <LLD <LLD <LLD <LLD
{ 1981 <LLD <LLD <LLD 1.4 1.4 1.4 1982 <LLD <LLD <LLD <LLD <LLD <LLD 1983 <LLD <LLD <LLD <LLD <LLD <LLD 1984 <LLD <LLD <LLD <LLD <LLD <LLD 1985 <LLD <LLD <LLD <LLD <LLD <LLD l 1986 <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD o No gamma analysis performed (not required).
- Data showed instrument background results.
{ I t Location was the City of Oswego Water Supply for 1969 - 1984 and the Oswego Steam Station inlet canal for 1985 - 1993. [ tt 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. I 7-6
TABLE 7-6 l HISTORICAL ENVIRONMENTAL SAMPLE DATA ll SURFACE WATER Results in pCi/ liter l LOCATION:: INDICATORet$ g Isotope- Cs-137? eCo;60? Year. -Min. Max. :Hean; LHin. Max. ;HeanL I l 1 1969tt * * * * *
- 1974tt * * * * *
- l 1975 1976 l l l
1977 ** ** ** ** ** ** 1978 <MDL <MDL <MDL ** ** ** 4 1979 1980
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1981 <LLD <LLD <LLD <LLD <LLD <LLD g 1982 0.43 0.43 0.43 1.6 2.4 1.9 1983 <LLD <LLD <LLD <LLD <LLD <LLD 1984 <LLD <LLD <LLD g
<LLD <LLD <LLD j 1985 <LLD <LLD <LLD <LLD <LLD <LLD g 4
1986 <LLD <LLD <LLD <LLD <LLD <LLD E 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD j 1990 1991
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
j l 1992 1993
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
No gamma analysis performed (not required).
** Data showed instrument background results, t Indicator location was the NMP 1 Inlet Canal for the period 1969 - 1973, and the JAF g g
Inlet Canal for 1974 - 1993. tt 1969 data is considered to be pre operational for the site, 1974 data is considered a to be pre operational for the JAFNPP. E 7-7
i TABLE 7-7 I HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Results in pCi/ liter l LOCATIONFICONTR00** { (Isotope vTritium: g
- Year. ' Min.. 'Hax. Hean: l 1969t No Data No Data No Data 1974t I 1975
<MDL 311
<MDL 414
<MDL 362 1976 440 I 1977 300 929 530 652 408 1978 215 I 1979 174 490 308 304 259 1980 211 I 1981 211 290 357 257 293 1982 112 I 1983 230 307 280 165 250 1984 I 1985 190 230 220 430 205 288 1986 250 I 1987 140 550 270 373 210 1988 I 1989 240 143 460 217 320 186 1990 260 I 1991 180 320 200 290 190
)
l 1992 190 310 I 1993 160 230 243 188 Control location is the City of Oswego, drinking water for 1969 - 1984 and the Oswego Steam Station inlet canal for 1985 - 1993. 1969 data is considered to be pre operational for the site. 1974 data is It considered to be pre operational for the JAFNPP. 7-8
TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Results in pCi/ liter
. LOCATION':..LINDICATOR)*' l Isotopej ::TritiumL g ?Yeari: .Hin. Maxn .Hean!
1969t No Data No Data No Data 1974t 380 500 440 1975 124 482 335 1976 297 889 513 1977 380 530 450 1978 253 560 389 1979 1980 176 150 286 457 234 263 l 1981 1982 183 194 388 2780 258 641 l 1983 1984 190 110 560 370 317 282 l 1985 1986 250 260 1200** 500 530 380 g, 1987 160 410 322 1988 430 g 480 460 1989 135 288 225 1990 220 290 250 1991 250 390 310 1992 240 300 273 1993 200 280 242 Indicator location was the NMP-1 Inlet Canal during the period 1969-1973, and the Ii JAF Inlet Canal for 1974-1993. g
- Suspect sample contamination. Recollected samples showed normal levels of tritium. E )
t 1969 data is considered to be pre-operational for the site. 1974 data is considered l to be pre-operational for the JAFNPP. 1 7-9
a e TABLE 7-9 l l HISTORICAL ENVIRONMENTAL SAMPLE DATA l AIR PARTICULATE GROSS BETA Results in pCi/m l IOCATIONE8 CONTROL $*3 l l iIsotopes :GrossLBsta?
&YearJi L Mi.ii;7 LHR iMean; 1969t 0.130 0.540 0.334 l
1974t 0.001 0.808 0.121 1975 0.008 0.294 0.085 ,l 1976 0.004 0.240 0.051 1977 0.001 0.484 0.126 l 1978 1979 0.010 0.010 0.650 0.703 0.144 0.077 1980 0.009 0.291 0.056 l 1981 0.016 0.549 0.165 , 1982 0.011 0.078 0.033 l 1983 0.007 0.085 0.024 g 1984 0.013 0.051 0.026 iE 1985 0.013 0.043 0.024 , 1986 0.008 0.272 0.039 1987 0.009 0.037 0.021 1988 0.008 0.039 0.018 l 1989 1990 0.007 0.003 0.039 0.017 0.027 0.013 l 1991 1992 0.007 0.006 0.028 0.020 0.014 0.012 l 1993 0.007 0.022 0.013 !g o Locations used for 1977 - 1984 were C off site. D1 off-site. 02 off site. E off site. lg F off site, and G off-site. Control location R 5 off site was used for 1985 1993 (formerly C off site location). , t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP.
- 7-10 l__ _.__ __ _ __ ._.
T TABLE 7-10 l HISTORICAL ENVIRONMENTAL SAMPLE DATA l AIR PARTICULATE GROSS BETA Results in pCi/m 3 l l 4 LOCATION: lINDICATORi*- LIsotopet Gross 8 eta:
. Year ' Min. -Maxh L Mean'-
l 1969t 0.130 0.520 0.320 1974t 0.003 0.885 0.058 1975 1976 0.001 0.002 0.456 0.191 0.067 l 0.047 1977 1978 0.016 0.006 0.140 0.340 0.070 0.102 l 1979 1980 0.001 0.002 0.271 0.207 0.058 0.045 l 1981 1982 0.004 0.001 0.528 0.113 0.151 0.031 l 1983 0.003 0.062 0.023 1984 0.001 g 0.058 0.025 1985 0.001 0.044 0.021 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 1990 1991 0.006 0.006 0.023 0.033 0.014 0.015 l 1992 1993 0.005 0.005 0.024 0.023 0.013 0.014 l
- Locations used for 1969 - 1973 were D1 on-site. D2 on-site. E on site. F on site l
and G on-site. Locations used for 1974 - 1984 were D1 on-site. D2 on site. E on-site. F on site. G on site. H on-site, I on-site. J on site and K on-site, as applicable. ' 1985 - 1993 locations were R 1 off-site. R 2 off-site, R 3 off-site, and R-4 off-site, t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. I 7-11
TABLE 7-11 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Results in pCi/m 3 LOCATIONi: CONTROL ** Isotope) --Cs-137f LCo-60: J: Year Min.- l Max. Mean. Mini .- Max. .Mean 1969t * * * * *
- 1974t * * * * *
- l 1975 * * * * *
- 1976 * * * * *
- 1977 0.0002 0.0112 0.0034 0.0034 0.0347 0.0172 1978 0.0008 0.0042 0.0018 0.0003 0.0056 0.0020 1979 0.0008 0.0047 0.0016 0.0005 0.0014 0.0009 1980 0.0015 0.0018 0.0016 <LLD <LLD <LLD 1981 0.0003 0.0042 0.0017 0.0003 0.0012 0.0008 1982 0.0002 0.0009 0.0004 0.0004 0.0007 0.0006 1983 0.0002 0.0002 0.0002 0.0007 0.0007 0.0007 l 1984 <LLD <LLD <LLD 0.0004 0.0012 0.0008 1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 0.0075 0.0311 0.0193 <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD
{ 1991 <LLD <LLD <LLD <LLD <LLD <LLD l 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 0 ( No data available (not required prior to 1977).
** Locations included composites of off-site air monitoring locations for 1977 - 1984. !
Sample location included only R-5 air monitoring location for 1985 - 1993. ( ( t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. J l 7-12 f
TABLE 7-12 8
- HISTORICAL ENVIRONMENTAL SAMPLE DATA
- AIR PARTICULATES Results in pCi/m3
- LOCATIONi LIND'ICATOR)** l
! I Is0topey Cs-137L:: 'C0-601 g
. Year..i . Min.
~ Maxi .Mean:
' LMink. ? Max.
Mean1
- 1969t * * * * *
- 1974t * * * * *
- l 1975 * * * * *
- 1976 * * * * *
- l 1977 0.0001 0.0105 0.0043 0.0003 0.0711 0.0179 1978 0.0003 0.0026 0.0016 0.0003 0.0153 0.0023
] 1979 1980 0.0003 0.0005 0.0020 0.0019 0.0010 0.0011 0.0003 0.0016 0.0007 0.0016 0.0005 0.0016 l f I 1981 1982 0.0002 0.0001 0.0045 0.0006 0.0014 0.0004 0.0002 0.0003 0.0017 0.0010 0.0006 0.0005 l j 1983 1984 0.0002
<LLD 0.0003
<LLD 0.0002
<LLD 0.0003 0.0007 0.0017 0.0017 0.0007 0.0012 l
j 1985 1986
<LLD 0.0069
<LLD 0.0364
<LLD 0.0183
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
j 1987 <LLD <LLD <LLD <LLD <LLD <LLD g , 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD
- 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD I 1993 <LLD <LLD <LLD <LLD <LLD <LLD
- No data available (not required prior to 1977).
I
** Locations included composites of on site air monitoring locations for 1977 - 1984. E Sample locations included R-1 through R-4 air monitoring locations for 1985 - 1993. 5
- t 1969 data is consied to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP.
7-13 4
TABLE 7-13 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADI0 IODINE Results in pCi/m 3 lLOCATIONh CONTROL?*'
.' Isotope; : Iodine-1311 l Years .Hin. :HaxL '.Hean; 1969t ** ** **
1974t ** ** ** 1975 <MDL HDL <MDL 1976 0.01 5.88 0.60 1977 0.02 0.82 0.32 1978 0.03 0.04 0.03 ( 1979 <LLD <LLD <LLD 1980 <LLD <LLD <LLD 1981 <LLD <LLD <LLD 1982 0.039 0.039 0.039 1983 <LLD <LLD <LLD 1984 <LLD <LLD <LLD 1985 <LLD <LLD <LLD 1986 0.041 0.332 0.151 1987 <LLD <LLD <LLD 1988 <LLD <LLD <LLD j 1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD o Locations D1 off site. D2 off site. E off-site. F off-site and G off-site used for 1976 - 1984. Location R-5 off site used for 1985 - 1993. co No results - I 131 analysis not required. t 1969 data is considered to be pre-operational for the site, 1974 data is considered to be pre operational for the JAFNPP. f 7-14 \ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . . _ _
TABLE 7-14 l HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADI0 IODINE l Results in pCi/m 3 l
- LOCATION: ' INDICATOR *'
lIsotopef LIodine-131: I
? Ye'ar. Min. Max. '.Mean 1 1969t 1974t g'
1975 1976 0.25 0.01 0.30 2.09 0.28 0.33 gj> I 1977 0.02 0.73 0.31 1978 0.02 0.07 0.04 l 1979 <LLD <LLD <LLD 1980 0.013 0.013 0.013 1981 0.016 0.042 0.029 ll 1982 0.002 0.042 0.016 I 1983 0.022 0.035 0.028 1984 1985
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1986 1987 0.023 0.011 0.360 0.018 0.119 0.014 l 1988 <LLD <LLD <LLD g 1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD g 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD
- Locations used for 1976 - 1984 were D1 on-site. D2 on site. E on-site.
F on site. G on site. H on-site. I on-site, J on site and K on site. as applicable. Locat1ons used for 1985 - 1993 were R 1 off site. R 2 off-site. R-3 off-site, and R 4 off-site.
** No results I-131 analysis not required.
t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre operational for the JAFNPP.
! 7-15
TABLE 7-15A HISTORICAL ENVIRONMENTAL SAMPLE DATA EN.;.10NMENTAL TLD Results in mrem / standard month LOCATION: CONTROL'** Year Hin. Max. Mean Preopt * *
- 1970 6.0 7.3 6.7 1971 2.0 6.7 4.3 1972 2.2 6.2 4.4 1973 2.2 6.9 4.7 1974t 2.7 8.9 5.6 1975 4.8 6.0 5.5 1976 3.2 7.2 5.4 1977 4.0 8.0 5.3 1978 3.3 4.7 4.3 1979 3.3 5.7 4.7 1980 3.8 5.8 4.9 1981 3.5 5.9 4.8 1982 3.8 6.1 5.1 1983 4.9 7.2 5.8 1984 4.7 8.2 6.2 1985 4.5 7.6 5.6 1986 5.3 7.5 6.3 1987 4.6 6.6 5.4 1988 4.4 6.8 5.6 1989 2.9 6.4 4.7 1990 3.7 6.0 4.7 1991 3.8 5.8 4.7 1992 2.6 5.1 4.1 1993 3.4 5.7 4.4
- Data not available.
** TLD #8,14. 49,111 established 1985. TLD #113 established 1992.
t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre operational for the JAFNPP. 7-16
TABLE 7-15B HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD l Results in mrem per standard month l LLOCATIONS1RETS{CONTROLi** g
- Year: T Hin. . ~ Haxe .- Mean : !
Preopt * *
- 1970 6.0 7.3 6.7 ,
1971 2.0 6.7 4.3 1972 2.2 6.2 4.4 1973 1974t 2.2 2.7 6.9 8.9 4.7 5.6 l 1975 4.8 6.0 5.5 1976 g 3.2 7.2 5.4 1977 4.0 8.0 5.3 1978 3.3 4.7 4.3 1979 3.3 5.7 4.7 1980 1981 3.8 3.5 5.8 5.9 4.9 4.8 l 1982 3.8 6.1 5.1 1983 g 4.9 7.2 5.8 1984 4.7 8.2 6.2 1985 4.4 6.8 5.4 1986 5.5 7.2 6.3 1987 1988 4.6 4.8 5.8 6.8 5.2 5.4 l 1989 1990 1991 2.9 3.7 6.4 6.0 4.1 4.8 l 3.8 5.3 4.6 1992 2.6 4.7 3.9 1993 3.4 5.3 4.4 Data rot available. I
- TLD #14 and 49 (RETS Control Locations).
t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. 7-17
TABLE 7-16A HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: SITE BOUNDARY ** Year Hin. Max. Mean Preopt * *
- 1970 * *
- 1971 * *
- 1972 * *
- 1973 * *
- 1974t * *
- 1975 * *
- 1976 * *
- 1977 * *
- 1978 * *
- 1979 * *
- 1980 * *
- 1981 * *
- 1982 * *
- 1983 * *
- 1984 * *
- 1985 4.9(4.1) 5.9(12.6) 5.3(6.2) 1986 5.4(4.4) 6.8(18.7) 5.9(7.0) 1987 4.7(4.4) 5.9(14.3) 5.3(6.1) 1988 5.0(3.4) 6.1(17.9) 5.4(6.4) 1989 4.5(2.8) 5.2(15.4) 4.8(5.9) 1990
' 4.5(3.6) 5.4(14.9) 4.8(6.4) 1991 4.3(3.2) 5.5(16.7) 4.8(6.0) 1992 3.7(3.2) 4.6(10.4) 4.2(5.1) 1993 3.8(3.3) 4.8(11.7) 4.3(5.4)
Data not available (not required prior to 1985).
** TLD locations initiated in 1985 as required by the New Technical Specifications.
Includes TLD numbers 7. 18. 78 84 (1985-1993). () Several of the site boundary TLDs numbers 23.75.76,77.85.86 and 87 are in close proximity to site operational buildings not generally accessible to the public. the measured doses and are not representative of the site boundary dose. The statistics for all the Site [ Boundary TLDs are noted in the parenthesis. t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. l 7-18 s
TABLE 7-16B l HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD l Results in mrem per standard month l LOCATION: OFF-SITE.. SECTORS ** Year Hin. Max. Mean I Preopt 1970
- l 1971 * *
- g 1972
- 1973 * *
- g 19/4t * *
- 5 1975 * *
- 1976 1977 l
1978 1979
- l 1980 * *
- 1981 * *
- 1982 * *
- 1983 1984 l
1985 1986 4.0 4.6 7.1 8.6 5.0 6.0 l l 1987 4.3 6.0 5.2 1988 3.8 7.0 g 5.3 1989 2.5 6.8 4.9 1990 1991 3.6 3.6 6.3 5.8 4.7 4.7 l 1992 1993 2.9 3.4 5.0 6.3 4.1 4.5 l Data not available (not required prior to 1985).
** TLD locations initiated in 1985 as required by the New Technical Specifications.
Includes TLD numbers 88. 89. 90. 91. 92. 93. 94 and 95. t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. g' g 7-19
TABLE 7-16C HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: SPECIAL INTEREST ** Year Hin. Max. Mean Preopt * *
- 1970 * *
- 1971 * *
- 1972 * *
- j 1973 * *
- 1974t * *
- 1975 * *
- 1976 * *
- 1977 * *
- 1978 * *
- 1979 * *
- 1980 * *
- 1981 * *
- 1982 * *
- 1983 * *
- 1984 *
- 1985 3.9 6.8 5.3 1986 4.8 8.2 6.1 1987 3.5 6.0 5.1 1988 3.9 6.6 5.3 1989 2.1 6.4 4.9 1990 3.2 6.3 4.8 1991 2.9 5.6 4.4 1992 3.0 4.8 4.1 1993 3.2 5.8 4.5 Data not available (not required prior to 1985).
** TLD locations initiated in 1985 as required by the New Technical Specifications.
( Includes TLD numbers 15, 56, 58, 96, 97 and 98, which are located near critical residences and populated areas near the site. t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre operational for the JAFNPP. s 7-20
TABLE 7-16D l HISTORICAL ENVIRONMENTAL SAMPLE DATA g ENVIRONMENTAL TLD Results in mrem per standard month g LOCATION: ON-SITE INDICATOR ** Year Hin. Max. - Hean' l Preopt *
- g 1970 4.7 9.0 6.0 3 19'il 1.5 7.7 4.7 1972 1973 2.3 3.0 8.2 24.4 4.9 6.6 l
1974t 3.1 10.6 5.7 g 1975 4.6 16.0 7.3 1976 3.7 18.8 6.9 g 1977 3.0 15.3 5.7 5 : 1978 3.0 9.0 4.3 : 1979 1980 2.7 3.9 8.3 12.0 4.3 5.3 l ! 1981 1982 4.1 3.9 11.8 13.0 5.8 6.3 gI 1983 5.0 16.5 6.9 E 1984 4.6 13.2 7.0 a 1985 4.7 15.9 6.3 1986 1987 4.7 4.0 16.1 11.4 7.0 5.8 l 1988 1989 4.4 2.7 11.9 13.1 6.0 6.0 l 1990 3.6 12.9 5.5 1991 3.2 11.6 5.4 1992 3.2 5.6 4.3 1993 3.1 13.6 5.2 l
- No data available.
- Includes TLD numbers 3. 4. 5. 6 and 7 (1970 - 1973). Includes TLD numbers 3. 4.
- 5. 6. 7, 23, 24. 25 and 26 (1974 - 1993). Locations are existing or previous on-site environmental air monitoring locations.
t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. I 7-21
TABLE 7-16E HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: OFF-SITE INDICATOR.**
. Year Hin. Max. Mean Preopt * *
- 1970 5.0 8.0 6.7 1971 1.1 7.7 4.5 1972 1.8 6.6 4.4 1973 2.2 6.9 4.1 1974t 2.4 8.9 5.3 1975 4.5 7.1 5.5 1976 3.4 7.2 5.2 1977 3.7 8.0 5.3 1978 2.7 4.7 3.7 1979 3.0 5.7 4.0 1980 3.1 5.8 4.6 1981 3.6 5.9 4.7 1982 4.0 6.2 5.2 1983 4.6 7.2 5.6 1984 4.6 8.2 6.1 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 1988 4.2 6.6 5.4 1989 2.8 6.4 4.6 1990 3.8 6.1 4.8 1991 3.4 5.8 4.5 1992 3.1 5.2 4.1 1993 3.2 5.7 5.0 r
- No data available.
** Includes TLD numbers 8. 9. 10. 11. 12 and 13 (off-site environmental air monitoring locations).
I t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. 7-22
TABLE 7-17 l HISTORICAL ENVIRONMENTAL SAMPLE DATA 1 MILK l Results in pCi/ liter , i LOCATIONiLCONTROL** l
? Isotope- . Cs-137.- - I-131 --
iYear- Mini iMax; 'Hean 1 Hi n. -- lHax. 1Hean 1969t 1974t l j 1975 1976
- l l
1977 1978 2.4 7.8 5.8 <LLD
<LLD
<LLD l
1979 <LLD <LLD <LLD <LLD <LLD <LLD 1980 g
<LLD <LLD <LLD 1.4 1.4 1.4 1981 7.0 7.0 7.0 <LLD <LLD <LLD i
1982 <LLD <LLD <LLD g
<LLD <LLD <LLD
] 1983 <LLD <LLD <LLD <LLD <LLD <LLD g 1984 <LLD <LLD <LLD <LLD <LLD <LLD E 1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 5.3 12.4 8.4 0.8 29.0 13.6 1987 <LLD <LLD <LLD <LLD <LLD <LLD i 1988 1989
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1990 1991
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1992 1993
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
No data available (sample not required).
** Location used was an available milk sample location in a least prevalent wind a direction greater than ten miles from the site.
g t 1969 data is consied to be pre operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. 7-23
HISTORICAL ENVIRONMENTAL SAMPLE MILK Results in pCi/ liter
- LOCATION: INDICATOR **
-Isotope Cs-137L ,
I-131'. Year Hin. Max. Mean ' Min. 'Hax. Mean 1969t ** ** ** ** ** ** 1974t 1.6 39 10.5 0.70 2.00 1.23 1975 6.0 22 16 0.01 2.99 0.37 1976 4.0 15.0 9.3 0.02 45.00 3.20 1977 11.0 22.0 17.1 0.40 0.22 0.02 1978 3.4 33.0 9.9 0.19 0.19 0.19 1979 2.7 40.0 9.4 <LLD <LLD <LLD 1980 4.0 21.0 9.7 0.4 8.8 4.9 1981 4.3 29.0 7.6 <LLD <LLD <LLD 1982 3.1 18.0 6.3 <LLD <LLD <LLD 1983 5.1 5.1 5.1 <LLD <LLD <LLD 1984 <LLD <LLD <LLD <LLD <LLD <LLD 1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 1987 5.5 9.4 7.4 <LLD <LLD <LLD 1988 10.0 10.0 10.0 <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD { 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993tt <LLD <LLD <LLD <LLD <LLD <LLD ee
- Locations sampled were available downwind locations within ten miles with high deposition potential.
** No data available (control samples not required).
r t 1969 data is consied to be pre operational for the site. 1974 data is considered to be pre operational for the JAFNPP. ( tt New control location as of August 16. 1993. Location No. 65 sold - last sample taken August 2. 1993. 7-24
TABLE 7-19 l HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS tt l Results in pCi/g (wet) LOCATION:' CONTROL
- l!l l
Isotope Cs.137' ] ear Hin. Max.- -Mean. l 1969t ** ** ** 1974t ** ** ** g 1975 ** ** ** 1976 ** ** ** 1977 ** ** ** 1978 ** ** ** 1979 ** ** ** 1980 1981
<LLD
<LLD
<LLD
<LLD
<LLD l li
<LLD 1982 <LLD <LLD <LLD 1983 <LLD <LLD <LLD 1984 1985
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1986 <LLD <LLD <LLD 1987 <LLD <LLD <LLD gl 1988 <LLD <LLD <LLD 1989 g
<LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 0.008 0.008 0.008 Locations was an available food product sample location in a least prevalent wind direction greater than ten miles from the site, I ** No data available (control samples not required). l t 1969 data is considered to be pre operational for the site, 1974 data is considered to be pre operational for the JAFNPP.
tt Data comprised of broadleaf and non broadleaf vegetaion (19801984). Data comprised a of broadleaf vegetation only (1985-1991). , g 7-25
TABLE 7-20 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS tt Results in pCi/g (wet) LOCATION: INDICATOR
- Isotope :Cs-137
-Year Hin. . Max. Mean 1969t ** ** **
1974t 0.04 0.34 0.142 1975 <MDL <MDL <MDL 1976 <MDL <MDL <MDL 1977 <MDL <MDL <MDL 1978 0.01 0.01 0.01 1979 <LLD <LLD <LLD
) 1980 0.004 0.060 0.033 1981 <LLD <LLD <LLD 1982 <LLD <LLD ] <LLD 1983 <LLD <LLD <LLD 1984 <LLD <LLD <LLD 1985 0.047 0.047 0.047 1986 <LLD <LLD <LLD ]
J 1987 <LLD <LLD <LLD 1988 0.008 0.008 0.008
] 1989 0.011 0.011 0.011 1990 <LLD <LLD <LLD ] 1991 0.039 0.039 0.039 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD Indicator locations were available downwind locations within ten miles of the site and with high deposition potential. ** No data available (control samples not required).
t 1969 data is considered to be pre operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. l tt Data comprised of broadleaf and non broadleaf vegetaion (19761984). Data comprised h of broadleaf vegetation only (19851991). f 7 26
I l 8.0 GRAPIIICAL PRESENTATIONS
- 1. DATA GRAPHS This section includes graphic representation of selected sample results.
! For graphic representation, results reported as MDL or LLD were considered to be at the "zero" level of activity. MDL and LLD results were indicated where possible.
- I
- 2. SAMPl.E LOCATIONS
- I Sample location results specified as " indicator" and " control" on the graphs 1
can be referenced back to Section 3.3 for specific locations. I 4 i !I lI lI !I 1 !I 4 !I 4 I lI !I 8-1 !I
E-8 pCi/gm (wet) R 9 9 9 9 "
. r "
o w a o w - w a m 1974 NEU lllll!llllllll ll ll1llllllllllllllllllll!IIlII0IIII$llll 1975 1976 E 11111lllllllll llllllll11!Il 11lll111llllll EMMggs llllllll11@ 1977 Il!I
!!!L E
1978 1979 E 1980 g E M o 1981 (/) - 0 > 1982 I > o u 3 m } 2 1983 I JI h 1 c N E 1984 a 3 m hT 3 p O W H 2 1985 3 _3 ) x a 0 1986 I X - r I . 1987 h g a s : 1988 I
% ? .u
, u 1989 I a
1990 ,
~
h 1991
. $ o 1992 l e.
1993 0
l l I mcumn 8 I gl E66L g I i IImmm1mm ,7 l g 266t ) Em IIIIM ge (g 3 l M t66t ;g g ! HEnu!!I!niinimin 5$ EMIM 066L ; 3 Innsin s ,e a 686L ! l lllll1 ]y i E MI mimmimum 886L 8 i!
?6 l i Imsfru 8E lE .I L86t ; j g
' 2! M imiinimi iniiniluu llilli MMM ilm 886L e?
~s 5:2 E CC H I .
iiim n un un a 1E1111E 11111 S86L i ill I Ie . a: 4w lulii! nnullill agy N M IEqlm '86L El H Se lini alunniillli nic ; w za i Ils E86L a u- o Un wi z86L o l dgm E ggi III IIEl um Innt z E MD RIl IIIII L86L o = Lu m e o l E 086t E E
, a a s
mLunnmmuum un m B 8 : EM EE 646t o e a i e M IM M mz muummnli 846L E o l
$ 5 2
E
? 4 e
Iumululitiimilummm ElEl Bs p milmnunin IEminum lin il i Ellll unmm u6i z E l IM EllEMI *L 4 E 1 g 9 5 g m ini ci lulnimllums E
~
g I III SL6L I V
- E
+
g tL6L g 8 8 8 8 8 8 8 o -1 o e e s e m 8, n 8
~
8 I 7/ lod 8-3 I I
1: I 3991 o . s 3 ! 2991
$ k 5 g E E , 1991 e e ru ; ,
rP 0991 ,
? ? 5 $
5 $ 9 E 9891 w L 8 * $ D $ E m $ E 8891 m a m c > - U" % 7891
)u - p 2 )y Elll 6891 O r
X O E % k 8$ m5 h 588' $ O {-- m g' o lE 4891 T O' P 11 N
- E 3891 QMy !E C T 12 E 2891
hcb @@lll!!11lllh111111!llllliH!! 1891 5 EEE O my us 5 l 0891 h E l >
.C
" E"nnila!n 878' D
EE 8791 f 7791 l 2112 ( E 6791 EEMlliJ 5791 EE 5 lBIM!I!lulll4l 4791 kE slE !llE1! llW!1ll lllllllllll lllllllllll llllllll111011llllI111 9691 ' m m a m w m N m - m o 9
$P $P OP SP $
i 3m/lCp j i 8-V
1 I S-8 I pCl/m3 o o o o 6 9 6 9 6 9 6 9 o O $ 8 $ 8 O S l 1 E 2 MNM l0l!llililli ill!imlilli l miel licultmn E I 3 4 NNIRIEIMllti mill!Illm nllmlilill!ililili MME E
!!lIlmmli,Illinig T I 5 Mb mimillm nlltilIllll1 Illllllmith I
6 g g 7 5 MM h 8 N, D L I 9
!Ilullmill Willimni Illlllli NNNE l1111111lllll Illlllil!!ill Illilllimih g
p u
)
10 MMM l 2 m i I Z E o 11 ini:mlIlli mimmm tillmimlil .e
!]lligg NM lililliulm 1l111111 H
b > C CO
> MNWINEIEE E I I a O
M $ 12 13 M4 mimnniunnninm nummni 3 E
> m m d m unlimulus a N g 14 gg {
O 15 U NI A M d O E111!!11141 33 E 2 MMmm C ~ 5 w 2 je umlag E m O O X O 17 M M CD millniciutilum!m 18 NMM - i all!!ilklll m!llullilllimill! yT 19 MMN mnr E H T j I 20 millm!m milillilill ggl n j n g E D - i 21 g l { I 22 ME tilElll!Villli 5 8 n 23
@@ g ,3 24 NME 1111111niill inlmmm Hilil d
I 25 MEllEE milll!lIlll,Illlimillli 26 illlllllllllillll!Illlllllll}ltlll MME d I t
+
9-8 1 j pCi/m3 o o o o ] o 9 ' o 9 ' o 9 o 9 o O 3 5 8 $ 8 8 2 1 s 27 Munununninonnnninnmi 28
!!allinull unnl@g Iggggj, M
29 MMniniillnn linilli 30 innlilulll Illllillilin lli Mp 31 MMN nnnnnnonununu und 32 Mnifilinln! ilnlilllnll alli!!!!IH E 33 MW noilllinn nnllnnn! lll1l1lllll !! Ilinn1ljl!r I 34 M enamn nnan ini nnunnnoi"n"n"nI M "
> C 35 bb ll 5 M iuumennnnoun mnnnum usum u m g 36 MMM unannuunnun\\nnau E >
x m 37 d O innnnuminnnnnn manuni o y
> 38 M,u,a E nnmunmin e C
- o 5 39 ME samaanmu us 21 h -I
*
- N EE 40 MM '@
gI x un"mn" nnnnne - - u
- tt 41 unannnoinnninn M E n onmnnn nnnnm $mhM i O 42 MMU
""""'n" n"an""Hanin*n"unn 2 "Il-2 o O H 43 MM M N
- D O
unmaini ninonnu o X 44 gg g m F alumuswaunu y to 2 45 M I 9: tm . ununwamuuu nunuu 110 o 0 0 m H
.'c 46 M mininon unnninnnuuuum a
5 w > T-47 Mb ntnlliloninnillllnlin!Inln:litn
?
08 E-- 48 ~ unus unnum numoni a - x 2 49 E m e Minnan nninonnu um Lu] 2 50 noinmoi M nonninnunmens umu N 2 51 M P
!lluuminullums ' MJ 3 x * ^
52 ennnm W unmannngg 53 MM. lit onmumunnunmntunnnn
I l I C66L
.{
5 8 g 266t l
.g :
2a a l :l L66L 4 o z i .
. 066L I o e u l 686L
- =
- n. m .
H R g 886L z" g e o a g o . O g n. L86L E
, f T o z l- O 9861 o
0
< m 9 E aw$
N b 986L b
- u. G-m '? 8 '
E, s
. H ll #86L q < 5 3 9
w h _ l C86L h llii $ fk E86L E 44 )
'eg p g L86L 086L g 6L6L in l glll BLGL l illillll.lllllllllillllllillllll lllIIl llll!lillll lillllillll ll!jlll jll llllllllllj jjjjlllllll g gg g LL6L E
E $ 3 3 0 o 8 8 8 E o 6 9 9 9 9 6 9 9 9 9 o o o o o o o o EW/l3d I 8-7 I
E . C66L i 8 3 B . y 5 , 266L O 2 R- y.E . yg , L66L E3u 0 o
- o 4 2 . 066L
+
7* mB o + 6861 1 o So ee g W
.' +
SE o . 886L 2 b u) mm d
. o J
M o
- m L86L H g o. .
2 E O-2" o l!llll!!lllllllERI l]lillIlllllllllllllllll 986L U F O hm ggl
< mm e - B n.
N b aE
- 986L e o
H E
~~~
W * #86L 4
. & o 4b o 2
g
] CB6L E G 0" 286L E
4< a l
> jg
_U_~ 186L
< -l 096t 646L
{II
]g 846L LL6L
$ C q !$ o N E 5 8 o 9 6 9 6 9 6 9 o o o o EW/ lod 8-8
4 s 1 1 C66L 4 4 [8 g
. 266L I
a i 3 M L66L gl - 3 f m
- 066L 6 .
? .
686L I s : g h . 886L e
- g .
g, 2 . L861 : o E or
- - 11 1 986L z
W g o
. 986l O
< 5 "9 .
E CL. O #96t N F 5 B
=
C E
. O g
[ g C86L
. CC O
4N Z961 6 W . g L96L E. l W
- 7 *I 0961 i
E
. 6L6l 3 BL61 l
lllllllllll lllilllIlllilIllll llIM MIIE "6 ' e g (($([![3($l@[!!llI!I ll llll llll llllli Illlllllll! 9L6L tumum n 946L E 9 m N *
- v. O N " O o o o o o o o o o ELL 8/ lod 8-9
. C66L g . 266L w
yy . Q E$ . L66L j .
$I
- 066L =
'@ A a 8 . .
jj . 686L Ei *
, gg -
886L O. S-g {d g 486L ,= i
- 9lIlknIlliinillclil!i o -
bd lM M 986L g H o
- 5 . 986L z
o Z M
- o I- 7 m
( yd 2 * #86L ll Q. C86L f O zs, g 286L g G
< gM g! lg HIlWUlllOli L86L o
2 W + g g - 096L 4 . 7 g 6L6L I lllll41414lllW! - g 846L g 3 LL6L $ 5 - U M 946L g s
. BL6L 4
#46L
( l h_ 7/ lod l 8-10 L __ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
11-8 I pCl/L o n 4 m m 8 8 E 8 8 8 O 1974 I i g 1975 l 0 2 1976 9 a 1977 l E.
$ 1978 l E +
1979 + f--
+ >
l 1980 4 - E E DE m M E 1981 3 l I 5 1982 FP 7 O + :D - B Y d p 1983
- 31 O N
-i
- E oT
* ? b a I b 1984 1985
-O E2 m @
o * -
-' x o
$ @ljll]llillllllllllllllllIllll llllll!lill Illllllllll lllllMlM][I * $ ,2 33 A o 1987
- r- .T F *
, . o T 1988 *
$ $ I
? ? E 1989 9 N k
. m B .
2
- b h o 1990 f f u
+ 2.
" 8 R E:
I 1991
- e.
a E a g o a 1992 + g
+ g.
1993
- I
Zl-8
]
MREM / standard month 1 J o - N w a m e w m e 5 1974 1975 . e 1976 G j 1977 I o $. O o 2 1978 E E E E H 4
- D 9.
O 3979 M - M E g r a c 1980 M M 9 7 1981 imm um m (f) y) 1982 M M I D H H T m M M M 21 r-1983 H
, g g O 5 0 N C E M M M I T 2
1984 .m H 0 > H 2 1985 3
!!u!!icll lillillimilmimm limill!il E
1986 X
@ illlimillimlilllimilimilllimiillillli Illilllilill!!llilllili O 1987 m mimillil!illmlillimulmmilill!!!!mi!Illiiml il T
- 1988 W .T i
H Jml!Ill!lllilllillim!lllilllilllllmimlillmilull iii 1989 1 lIlllllllllllllillllilll!Ill!Illllllllilll!Ilil illilliHI 1990 t lilllllfilillilll!Illi!Illillllllll!!Itilllilil lllllili 1991 1 I!Ilil!illlillliilillllililllillllllIll11111111 1h!Il!! L 1992 i illlil!lli!llllillllillililllii!liffillHillll! I 1993 ME i 1 i11ll11i11111lIl111114ll111lll!!!]lIlilll!!h!!lllli
l 9.0 QA/QC PROGRAM 9.1 PROGRAM DESCRIPTION I The Radiological Effluent Technical Specifications require that a summary of the results for participation in the Interlaboratory Comparison Program be included in the Annual Radiological Environmental Operating Report. . Reference samples obtained from the US Environmental Protection Agency (USEPA) Cross Check Program are analyzed by the JAFNPP Environmental Laboratory. Sample media l analyzed for the intercomparison program includes those which are routinely obtained as part of the site radiological environmental monitoring program. I Sample results are compared to the USEPA reference results for accuracy and I precision. The USEPA reports results in terms of Normalized Deviations from a Known Value (NDKV). Interlaboratory results are acceptable by the USEPA when the laboratory NDKV is between -3 and +3 NDKV. 9.2 PROGRAM RESULTS I The performance of the JAFNPP Environmental Laboratory was acceptable in 1993. The USEPA provided 29 radionuclides, contained in various environmental media for analysis. Of these 29 radionuclides, the Laboratory reported 28 results within I the range of-2 NDKV and +2 NDKV. The one sample result that was >-3 NDKV is addressed in Section 9.3. All six samples analyzed by the program vendor laboratory were acceptable. Specific results for the USEPA Cross Check Program are presented in Tables 9-1 l through 9-4 contained in this section. 9.3 NONCONFORMITIES I 9.3.1 Sample 93-078, Gamma in Water, contained six radionuclides, Co-60, Zn-65, Ru-106, Cs-134, Cs-137 and Ba-133. The NDKV for Ru-106 was -3.13. I 9-1
- l
)
The USEPA known activity for Ru-106 was 119il2 pCi/l. The Environmental Laboratory reported a mean result of 97i9 pCi/1. The Environmental Laboratory staff routinely uses a factor of 1.13 to correct an inconsistency in the published gamma yield factor. The results were not corrected prior to submittal to the EPA for evaluation. The corrected results is 113 pCi/1. The appropriate NDKV for the 113 pCi/l l results is -0.82 which is well within the acceptable range for the EPA evaluation criteria. The other five radionuclides in this sample were within one standard
- deviation from the known (NDKV), indicating no systematic error.
4 i i I I I. I' I 1 l 9-2 ) l
TABLE 9-1 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARIS0NSTUdYPROGRAM GROSS BETA ANALYSIS OF AIR PARTICULATE FILTERS (PCI/ FILTER) GROSS BETA ANALYSIS OF WATER (PCI/ LITER)
- JAF lENVj ~
!JA6 (EPdh
" DATES ID NUMBERc ": MEDIUM : ANALYSIS: 4RESULTH: ; RESULT:? /NDKV1
;(1); 1(2)) l(5)?
01/93 QA 93-005 WATER GB 45il 44*5 -0.46 41il 42 1 07/93 QA 93-099 WATER GB 38il 4316.9 -1.08 40i1 38t1 08/93 QA 93-123 FILTER GB 52i1 47i5 1.50 52i1 50i1 10/93 QA 93 167 WATER GB 51il 58 10 1.15 50i1 5311 11/93 QA 93-187 WATER GB 14i1 1515 0.00 15t1 16t1 I 93 ? _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _
i ) TABLE 9-2 l j USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARIS0N STUDY PROGRAM I i
! TRITIUM ANALYSIS OF WATER (PCI/ LITER) l
. JAFJENVn . _ . ...
{JAFe-
?.EPAi. . . _
I t.DATE? .LIDiNUMBERi JMEDIUM:- :ANALYSISe a lRESULTs ? RESULT? iNDKV/ (1)? -(2)1 t(5)- E , 06/93 QA 93-068 WATER H3 93441137(3) 9844i984 0.69 + j 9525i138 l , 9740i137 i I 9800i300(4) 9844i984 -0.08 j 9800 300 l' l 9800i300 l i I 11/93 QA 93 185 WATER H-3 7157 126(3) 7398i470 -0.74 I 7078 125 g 7016i125 l 69001300(4) 7398i740 -1.16 I 7000i300 l 6800 300 l' i 9-4 l
I
.= TABLE 9-3
- 3 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY I INTERCOMPARIS0N STUDY PROGRAM i
l IODINE ANALYSIS OF WATER (PC1/ LITER) AND MILK (PCI/ LITER) NAFiE$5. . . . . . . . _ . _ _ . . . . . . . . . . [
,_JAk LsPM LDATEj )ID}.NUMBERT $MEDIUMi iANALYSIS1 1Rt!SULTJ l !NDKVA
? RESULT 2 1;(1)! [(2)J ((5);;l
\
) 02/93 QA 93-020 WATER I-131 99i2 110i10 -0.29
- g 98i2 110i10 98i2 100i10
- I l 09/93 QA 93-154 tilLK I-131 117i2 120i'" -0.48 115*2
- I 118i2
- I
{g 10/93 QA 93-066 WATER I-131 120i2 117il2 0.38 lE l i 12012 l 119i2 b 4
- I
- 1 1
95 l r
~-
i TABLE 9-4 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY l1 INTERCOMPARIS0N STUDY PROGRAM GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER) AND AIR PARTICULATE FILTERS (PCI/ FILTER)
- 'JAFL ENV/ _ . . . . . . . . . . . . . .
NAF[ .. / EPAf: LOATEJ ::IDlNUMBER: iMEDIUME cANALYSIS1 :: RESULT:l i:RESULTJ LNDKV--
- l(1): L(2):' ((5); l 1
- 04/93 QA 93-045 WATER Cs-134 23il 27i5 -1.15 E
] 2511 E
- 23i2 Co-60 40i2 39i5 -0.23 '
3812 ] 37i2 l Cs-137 3112 32i5 -0.35 4 3212 30i3 l ] 06/93 QA 93-078 WATER Co-60 1311 14i1 15i5 -0.58 l 13 1 g Zn 65 109i5 103i10 0.23 10615 g
- 98i5 m
- Ru-106 76i14 119il2 -3.13 114il7 g l 102i16
, Cs 134 4*1 Si5 0.23 4i1
- 511 l
l Cs-137 611 Si5 0.12 512 Si2 l Ba-133 99i3 97 3 99i10 -0.64 l 90i3 96 l
TABLE 9-4 (ConTInuEo) USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER) AND AIR PARTICULATE FILTERS (PCI/ FILTER) iJAFTENVl .
. . . . . sJAFR SEPA)
- DATEi:! (IDiNUMBER iMEDIUM? EANALYSISS .: RESULT 4 s RESULL !NDKV!:1 f (1h i(2)1 '(5)?
08/93 QA 93-123 FILTER Cs-137 8i2 9i5 -0.35 7i2 9i2 09/93 QA 93-154 MILK Cs-137 49i4 49i5 -0.73 4814 4414 10/93 QA 93-167 WATER Co-60 91 10i5 0.00 10i1 llil Cs-134 911 1215 -0.92 9il 10i1 Cs 137 11*1 10i5 0.23 11il 10i1 9-7
i TABLE 9-4 (CoNTInuEo) USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY ! 4 j INTERCOMPARIS0N STUDY PROGRAM GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER) l AND AIR PARTICULATE FILTERS (PCI/ FILTER)
~
TJAF?ENVn . . . . . . j:3AFl . ..lEPII_ . . . . E i jDATE:l sIDjNUMBER5 1 MEDIUM < ? ANALYSIS; iRESULTl LRESULTd E iNDKVi if(1)!. ?(2)) i(5.); i 11/93 QA 93-186 WATER Co-60 30i2 3015 -0.12 29i2 30i1 l 2
- Zn-65 154t7 15718 15015 0.73 l i 15816
! Ru 106 172i20 201i20 -1.91 177i22 188i16 l Cs-134 55i2 59i5 -1.39 g
- 54i2 g 5612 Cs-137 39i2 40i5 0.23 l 41i2 42i2 g
l Ba-133 80i3 79i8 0.43 81t3 g
- 82 3 1
(1) Results reported as activity i 1 sigma. (2) Results reported as activity 1 sigma. (3) Analyzed at the site Environmental Laboratory. (4) Analyzed at a vendor laboratory. g $ (5) NDKV is the Normalized Deviation from Known Value as determined by the EPA. j Values within the range of +3 and -3 indicate acceptable results. 98 g}}