ML18038A462
| ML18038A462 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/31/1988 |
| From: | Joseph Willis NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NMP-49487, NUDOCS 8905030157 | |
| Download: ML18038A462 (165) | |
Text
V NIAGA A U MOHAWK NMP49487 NINE MILE POINT NUCLEAR STATION/P.O. BOX 32 LYCOMING,NEW YORK 13093/TELEPHONE (315) 343-2110
- April27, 1989 United States Nuclear Regulatory Commission
,-- Document Control Desk Washington, DC 20555 RE:
Nine Mile Point Nuclear Station Unit 1 Facility Operating License DPR-63 Docket No. 50-220 Nine Mile Point Nuclear Station Unit 2 Facility Operating License NPF-69 Docket No. 50-410 Gentlemen:
'Ln accordance with the Technical Specifications for Nine Mile Point Nuclear Station Unit 1
and Unit 2,
we are enclosing the v'
t for the period January, 1988 through
- December, 1988.
Any questions concerning the enclosed report should be directed to Hugh J.
Flanagan at Nine Mile Point (315/349-2428).
Very truly yours, ames L. Willis General Superintendent Nuclear Generation JLW:HJF:cb Enclosure (18 copies) xc:
USNRC Region I Resident Inspector (Unit 1/Unit 2)
(2179X)
NIAGARA MOHAWK POWER CORPORATION January 1,
1988
. December 31, 1988 for NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket Number 50-220 and NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69
. Docket No. 50-410 QQQ 3Qa5 Q~()QQ 2Q $
. osaka pDR ADOCK Q pt4V l
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List of Tables List of Figures I. Introduction II'escription 1)
Sample Collection Methodology and Analysis 2)
Analyses Performed 3)
Changes to the 1988 Sample Program 4)
Exceptions to the 1988 Sample Program vi III.
Evaluation of Environmental Data A)
Aquatic Program
- 1) Shoreline Sediment
- 2) Fish 12 13
- 3) Surface Water B)
Terrestrial Program
- 1) Air Particulates Gross Beta
- 2) Monthly Air Parti.culate Composites
- 3) Airborne Radioiodine
- 4) TLD (Environmental Dosimetry)
- 5) Milk
- 6) Land Use Census
- 7) Food Products
- 8) Interlaboratory Comparison Program
- 9) Environmental Sample Locations
- 10) Radiological Environmental Monitoring Program Annual Summary
- 11) Historical Environmental Sample Data 16 20 20 22 24 26 32 36 37 39 40 40 40
(Continued)
C)
Conclusion D)
General Reference Material E)
Data Tables 1988 40 42 44
(
Qg~tg t Table 1
Sample Collection and Analysis, Site Radiological Environmental Monitoring Program A. Aquatic Program 45 Table 2
Sample Collection and Analysis, Site Radiological Environmental Monitoring Program B. Terrestrial Program 46 Table 3A Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/g-dry) 47 Table 3B Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/kg-dry) 48 Table 4A Concentration of Gamma Emitters in Fish Samples (pCi/g-wet) 49 Table 4B Concentration of Gamma Emitters in Fish Samples (pCi/kg-wet),
51 Table 5
Concentration of Gamma Emitters in Surface Water Samples 53 Table 6
Concentration of Tritium in Surface Water Samples 57 Table 7
Table 8
Environmental Airborne Particulate Samples-Off-Site Stations, Gross Beta Activity Environmental Airborne Particulate Samples-On-Site Stations, Gross Beta Activity 60 Table 9
Table 10 Concentration of Gamma Emitters in Monthly Composites of'NMP.Air Particulate Samples I
Environmental Charcoal Cartridge Samples-Off-Site Stations, Z-131 Activity 62 77 Table 11 Environmental Charcoal Cartridge Samples On-Site Stations, I-131 Activity 79 Table 12A Direct Radiation Measurement Results (mrem per standard month) 81 Table 12B Direct Radiation Measurement Results (mrem per quarterly period)
-iii 85
l~g~
(Continued)
~nt gt Table 13 Concentration of Gamma Emitters in Milk 89 Table 14 Table 15 Table 16 Table 17A Concentration of Iodine-131 in Milk Milk Animal Census 1988 Residence Census Concentration of Gamma Emitters in Food Products (pCi/g-wet) 95 97 99 100 Table 17B Concentration of Gamma Emitters in Food Products (pCi/kg-wet)'02 Table 18 Table 19 Table 20 Interlaboratory Comparison Program Results Environmental Sample Locations Radiological Environmental Monitoring Program Annual Summary 104 112 121 Table 21
'istorical Environmental Sample Data Shoreline Sediment (Control) 126 Table 22 Historical Environmental Sample Data Shoreline Sediment (Indicator) 127 Table 23 Historical Environmental Sample Data Fish (Control)
'128 Table 24 Historical Environmental Sample Data Fish (Indicator) 129 Table 25 Historical Environmental Sample Data Surface Water (Control) 130 Table 26 Historical Environmental Sample Data Surface Water (Indicator) 131 Table 27 Historical Environmental Sample Data Surface Water Tritium (Control) 132 Table 28 Historical Environmental Sample Data Surface Water Tritium (Indicator) 133
LI T ABL (Continued)
XahhMu.
ggg ttgt Table 29 Historical Environmental Sample Data Air Particulate Gross Beta (Control) 134 Table 30 Historical Environmental Sample Data Air Particulate Gross Beta (Indicator) 135 Table 31 Historical Environmental Sample Data Air Particulates (Control) 136 Table 32 Historical Environmental Sample Data Air Particulates (Indicator) 137 Table 33 Table 34 Historical Environmental Sample Data Air Radioiodine (Control)
Historical Environmental Sample Data Air Radioiodine (Indicator) 138 139 Table 35 Historical Environmental Sample Data Environmental TLD (Control) 140 Table 36 (A - E)
Table 37
. Historical Environmental Sample Data Environmental TLD (Indicator)
Hi'storical Environmental Sample Data Milk (Control) 141 146 Table 38 Historical Environmental Sample Data Milk (Indicator) 147 Table 39 Historical Environmental Sample Data Food Products (Control) 148 Table 40 Historical Environmental Sample Data Food Products (Indicator) 149.
LI T F FIG RE Z~m~u
~tg t Figure 1A Off-Site Environmental Station and TLD Locations 150 Figure 1B Off-Site Environmental Station and TLD Locations (Southern) 151 Figure 2
On-Site Environmental Station and TLD Locations 152 Figure 3
Figure 4
Nearest Residence and Food Product Locations Milk Animal,Census and Milk Sample Locations I
153 154 Figure 5
New Xork State Map 155
This report is submitted in accordance with Appendix A
(Technical Specifications),
Section 6.9.1.d to License DPR-63, Docket No.
50-220 for the Nine Mile Point Nuclear'tation Unit 1 and Section 6.9.1.7 to License NPF 69, Docket No.
50-410 for the Nine Mile Point Nuclear Station Unit 2 for the calendar year 1988.
The present sample collection and analysis schedule required by the Technical Specifications for the Nine Mile Point Nuclear Station Unit 1
and 2
(NMPNS) is listed in Table 1 and 2.
The sample collections for the radiological program are performed by two groups.
EA Science and Technology Inc.
(EA) performs much of the environmental sampling.
EA is presently performing the Nine Mile Point Biological Monitoring Program required by the Station's SPDES Permit.
The staff required.,by EA to perform this program is used to perform the terrestrial sampling required for the site Radiological Environmental Monitoring Program (REMP).
In-plant canal
- sampling, air sample collection and environmental TLD,collections are-performed jointly by
~ the NMPNS and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) staffs.
A. Shoreline Sediment Shoreline sediment samples are collected twice per year from one area of existing or potential recreational value and from one area beyond the influence of the site.
The area of potential recreational value is the only area from which samples are required by the Technical Specifications.
Approximately one kilogram of shoreline sediment is obtained from areas washed by the lakeshore surf at the two locations twice per year.
All samples are shipped and analyzed for gamma emitters.
Optional samples may be collected from other shoreline locations at or near the site.
Shoreline sediment locations are shown on Figure 1A (refer to Table 19 for location designations and descriptions).
B. Fish Samples Available fish species are obtained from collections during the spring and fall.,
Samples are collected from two of four possible on-site sample transects located in the vicinity of the
(Cont'd) t th (Cont'd)
Fish Samples (Cont'd) site discharge points and one off-site sample transect.
Available species are selected under the following guidelines:
1.
Samples of 0.5 to 1
kilogram of edible portions for a
minimum of two species per location.
2.
When two independent species are not available at all sample locations, a species may be divided into two samples for each location.
This procedure may be accomplished provided that a sufficient sample size is available for the species in question at all three locations.
Selected fish samples are segregated by species and location and are processed immediately after collection.
Samples are shipped frozen in insulated containers.
Edible portions of samples are analyzed for gamma emitting radionuclides.
Fish sample transects are shown on Figure lA (refer to Table 19
'for location designations and descriptions).
C. Surface Water Surface water samples are taken from the respective inlet canals of the J.A.
FitzPatrick facility and Niagara",Mohawk's Oswego Steam Station.
The FitzPatrick facility removes water from Lake Ontario on a
continuous basis and generally represents a
"down-current" sampling point from the Nine Mile Point Unit 1
and Unit 2 facilities.
The Oswego Steam Station inlet canal 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 because of the distance from the site as well as the result of the lake current patterns and current patterns from the Oswego River located nearby (see Figure 1A).
Samples from the FitzPatrick facility are composited from automatic sampling equipment which discharges into a compositing tank.
Samples are obtained from the tank monthly and analyzed for gamma emitters.
Samples from the Oswego Steam Station are also composited from automatic sampling equipment which discharge to a compositing tank.
Samples from this location are obtained weekly and are composited to form monthly composite samples.
Monthly samples are analyzed for gamma emitters.
A portion of the samples from each of the locations is saved and composited to form quarterly composite samples for each calendar quarter.
Quarterly composite samples are analyzed for tritium.
(Cont'd)
(Cont'd)
C. Surface Water (Cont'd)
In addition to the FitzPatrick and Oswego Steam Station facilities, data are presented for the Nine Mile Point Unit 1
and Unit 2 facility inlet canals and city water from the City of Oswego.
The latter three locations are not required by the Technical Specifications, but are optional samples.
Monthly composite samples from these three locations are analyzed for gamma emitters and quarterly composite samples are analyzed for tritium ~
l Sampling for ground water and drinking water, 's found in Section 3.12.1 of the Nine Mile Point Unit 2
Technical Specifications, was not required during 1988 because these
'pathways were not applicable to the Site during the year.
Applicable sampling requirements
.and conditions are presented in the Unit 2 Off-Site Dose Calculation Manual.
Surface water sample locations are shown on Figure lA (refer to Table 19 for location designations and descriptions).
D. Air Particulate/Iodine The air sampling stations required by the Technical Specifications are located in the general area'f the site boundary (within 0.7 miles) in sectors of highest calculated meteorological deposition factors (D/Q) based on historical meteorological data.
These stations (R-l, R-2, and R-3) are located in the
- east, east-southeast, and southeast sectors as measured from the center of the Nine Mile Point Nuclear Station Unit 2
reactor building.
The Technical Specifications also require that a fourth air sampling station be located in the vicinity of a year round community having the highest calculated deposition factor (D/Q)
~ based on historical meteorological data.
This station is located in the southeast sector (R-4).
A fifth station required by the Technical Specifications is located at a site 16.4 miles from the site in a least prevalent wind direction of northeast (R-5).
This location is considered a control location.
I In addition to the Technical Specification required locations, there are six other sampling stations located within the site boundary (Dl, G,
H, I, J, and K).
These locations generally surround the area occupied by the three generating facilities, but are well within the site boundary.
One other air sampling station is located off-site in the southwest sector and is in the vicinity of the City of Oswego.
Three remaining air sampling stations (D2, E
and F) are located in the east-southeast, south-southeast and south sectors and range in distance from 7.2 to 9.0 miles.
h,
~
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~ 4, ~, ~
",a*.I, 4, ~
'g,w,,l,
'),8! 0 '
1.!
(Cont'd) 1 t'
(Cont'd)
D.
Air Particulate/Iodine (Cont'd)
At each station, airborne particulates are collected by glass fiber filters and radioiodine by charcoal filters.
Air particulate glass fiber filters are approximately two inches (47 millimeters) in diameter and are placed in sample holders in the intake line of a vacuum sampler.
Directly down stream from the particulate filter is a
2 x
1 inch charcoal cartridge used to absorb airborne radioiodine.
The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis, or as required by dust loading.
Gross beta analysis is performed for the individual particulate filters on a weekly basis.
Charcoal cartridges are analyzed weekly for radioiodine by GeLi detector.
The particulate filters are composited
'by location for gamma analyses on a monthly basis after all weekly particulate filters have been counted for gross beta-activity.
Air sampling stations are shown in Figures 1 and 2 (refer to Table 19 for location designations and descriptions).
E.
TLD (direct radiation)
Thermoluminescent dosimeters (TLD's) are used to measure direct radiation (gamma dose) in the environment.
TLD's are obtained from Teledyne Isotopes on a quarterly basis and are read at Teledyne Isotopes'acility in Westwood, New Jersey.
Shipment control TLD's (at least two) accompany each shipment to and from the vendor's laboratory.
Shipment control TLD's also accompany the TLD's when they are being placed or collected and are shielded by lead when they are not being used.
TLD data results are corrected for a
transit dose by use of the data from the shipment control TLD's.
Five different types of areas are evaluated by environmental TLD's.
These areas'nclude on-site areas (areas within the site boundary not required by the Technical Specifications),
the site boundary area in each of the sixteen meteorological
- sectors, an outer ring of TLD's located four to five miles from the site in eight available land based meteorological
- sectors, special interest TLD's located at sites of high population density and control TLD's located at sites beyond significant influence of the site.
Special interest TLD's are located at or near large industrial
- sites, schools, proximal towns or communities or other special activity areas.
Control TLD's are located to the southwest,
- south, south-southeast and northeast of the site at distances of 12.6 to 26.4 miles.
TLD's used during 1988 were composed of rectangular teflon wafers impregnated with 25K CaS04.'y Phosphor.
These were placed in
(Cont'd)
(Cont'd)
E.
TLD (direct radiation) (Cont'd) polyethylene packages to ensure dosimeter integrity.
TLD packages were placed in open webbed plastic holders and were attached to supporting structures',
usually trees or utility poles.
Environmental TLD locations are shown on Figures 1A, 1B, and 2
(refer to Table 19 for location designations and descriptions).
F. Milk 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 from three to five minutes to assure a
homogenous mixture of milk and butterfat.
Two gallons are collected during the first half and second half of each month from each of the selected locations within ten miles of the site and from a control location.
The samples are chilled and shipped fresh to the analytical laboratory within thirty-six hours of collection in insulated shipping containers.
The selection of milk sample locations is based on maximum deposition factors (D/Q).
Deposition factors are generated from average historical meteorological data based on all licensed reactors.
The Technical Specifications require three sample locations within 5.0 miles of the site with the highest calculated deposition factors.
During 1988, there were no milk sample locations within 5.0 miles that could be sampled.
- However, there were several optional locations beyond five miles that were sampled.
A fourth sample location required by the Technical Specifications is located in a least prevalent wind direction from the site.
This location is in the southwest sector and serves as a control location.
Milk samples are collected twice per month (April December) and analyzed for gamma emitters and I-131.
Samples are collected and analyzed in January March in the event I-131 is detected in November and December of the preceding year.
The milk sample locations are found on Figure 4.
(refer to Table 19 for location designations and descriptions).
G. Land Use Census A land use census is-conducted to determine the utilization of land in the vicinity of the site.
The land use census actually consists of two types of census.
A milk animal census is
(Cont'd)
(Cont'd)
G. Land Use Census (Cont'd) 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 distance required by the Technical Specifications.
This census
'is conducted during the beginning of the grazing season using road
- surveys, contacting local agricultural authorities, post
- cards, and investigating references
'from other owners.
A second type of census is a residence census.
This census is conducted in order to identify the closest residence in each of the 22.5 degree meteorological sectors.
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.
For the residence
- census, several of the meteorological sectors are over Lake Ontario because the site is located at the shoreline.
Therefore, there are only eight sectors over land where residences are located within 3 miles.
The results of the two land use census are shown on Tables 15 and 16 and on Figures 3 and 4.
H. Food Products Food products are collected once per year during the late summer at the approximate height of the harvest season.
Approximately one kilogram of a
broadleaf vegetable or other broadleaf vegetation is collected from garden locations'ith the highest deposition factors (D/Q) based on average historical meteorological data.
Six samples are collected from at least two sectors.
Additional samples may also be obtained.
Control samples are also collected from available off-site locations 9
to 20 miles distant in a
least prevalent wind direction.
Control samples are of the same or of a
similar type of vegetation.
All samples are shipped fresh as soon as possible after collection.
Food product samples are analyzed for gamma emitters (gamma isotopic analysis).
The gamma isotopic analysis also includes I-131.
Food product locations are shown on Figure 3 (refer to Table 19 for location designations and descriptions).
The Radiological Environmental Monitoring Program (REMP) samples were analyzed by Teledyne Isotopes and by the Site Environmental
(Cont'd) 2 ~
n (Cont'd)
Laboratory during 1988.
The following samples were analyzed by the Site Environmental Laboratory:
Shoreline sediment (gamma spectral analysis)
Fish (gamma spectral analysis)
Lake water (monthly gamma spectral analysis only)
I Air particulate filter (weekly gross beta analysis)
Air particulate filter (monthly gamma spectral analysis)
Airborne radioiodine cartridge (weekly gamma spectral analysis)
Milk (gamma spectral analysis only)
Food products (gamma spectral analysis)
The remainder of the sample analyses, as outlined in Table 1 and 2, were analyzed by Teledyne Isotopes.
3.
h A. Program TLD N108 was added to the monitoring program on March 30, 1988.
TLD 8108 is located in the vicinity of the critical off-site residence and is used to evaluate any potential direct radiation dose from the site and gaseous effluent plumes.
This TLD is not a Technical Specification required TLD.
B. Program TLD 8109 was added to the monitoring program on March 30, 1988.
TLD 8109 is also located in the vicinity of the critical off-site residence and is used to supplement and verify any direct radiation doses measured by TLD 8108.
TLD 8109 is not a Technical Specification required TLD.
C. Program TLD 8110 was added to the monitoring program on March 31, 1988.
TLD Nll0 is located 26.4 miles from the site in the south-southeast sector and is used to measure background gamma radiation doses.
The data from TLD 8110 is considered control data and is used to supplement control data from TLDs 8, 14 and 49.
D. Program TLD 8111 was added to the monitoring program on March 31, 1988.
TLD f/111 is located 21.8 miles from the site in the southwest sector and is used to measure background gamma radiation doses.
The data from TLD Nlll is supplemental control data and is used to determine an average control dose rate in conjunction with TLD 88, 14, 49 and 110.
(Cont'd) 3.
(Cont'd)
E. Food product location Z was added to the sample program during 1988.
Location Z is in 'close proximity to location T which was sampled during both 1988. as well as 1987.
The new location is approximately 1000 feet closer to the site than location T is and is in the same sector (east) as location T.
Also during 1988, food product locations N, V and S were deleted from the sampling program because of either sample unavailability or because the location had a
low deposition potential as a result of the addition of location Z.
4 ~
Exceptions to the 1988 sample p'rogram concerns those samples or monitoring requirements which are required by the Technical Specifications.
This section implements section 3.6.20 of the Nine Mile Point Nuclear Station Unit 1
Technical Specifications and Section 3.12.1 of the Nine Mile Point Nuclear Station.Unit 2
Technical Specifications.
Air radioiodine and air particulate monitoring as the only sample media for which exceptions to the overall monitoring program
.required by the Technical Specifications were noted.
None of the other. monitoring programs required by the Technical Specifications contained exceptions.
A. Air Radioiodine and Particulate Sampling Required by the Technical Specifications Environmental air sample equipment at R-3 off-site air sampling station was inoperable from 1/29/88 (1036 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.94198e-4 months <br />) to 2/2/88 (0833.
hours).
The vacuum pump was found defective and was replaced.
2.
Environmental air sample equipment at R-4 off-site air sampling station was inoperable from 5/8/88 (2324 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.84282e-4 months <br />) to 5/10/88 (0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />).
The vacuum pump was found defective and was replaced.
Other occurrences of downtime for optional air sampling stations were documented for 1988.
- However, these occurrences are not presented here because optional air sampling stations are not required by the Technical Specifications.
Documentation includes downtime for air sampling equipment as well as env'ironmental radiation monitoring equipment.
(Cont'd) 4 ~
t t (Cont'd)
B. Lower Limit of Detection for Environmental Samples The Technical Specifications require that environmental samples analyzed for the Radiological Environmental Monitoring Program meet the lower limits of detection (LLD) found on Table 4.6.20-1 of the Nine Mile Point Unit 1 Technical Specifications and Table 4.12.1-1 of the Nine Mile Point Unit 2
Technical Specifications.
All of the 1988 environmental samples required by the Technical Specifications which showed no net activity were less than the required 'values found on Table 4.6.20-1 and Table 4.12.1-1.
C. Deviations from the Interlaboratory Comparison Program Section 3.6.21 of the Nine Mile Point Unit 1
Technical Specifications and Section 3.12.3 of the Nine Mile Point Unit 2
Technical Specifications require the site to conduct an Interlaboratory Comparison Program utilizing QC samples from the Environmental Protection Agency (EPA).
This section also requires that deviations from the sample schedules be reported in the Annual Radiological Environmental Operating Report.
The sample schedule is set by the EPA and includes media for which environmental samples are routinely collected and for which interlaboratory comparison samples are available from the EPA.
During
- 1988, sample media offered by the EPA for the Interlaboratory Comparison
- Program, and for which environmental samples are routinely coll'ected and analyzed, were obtained and analyzed.
There were no deviations from the program.
The amount of samples obtained from the EPA program was based on the maximum amount available per participant or on a ten percent or better level (percent of the ratio of EPA samples to the total required sample volume).
There were four separate groups of radionuclides that were detected in the environment during 1988.
Several radionuclides could possibly fall into two of the four groups.
The first of these groups is naturally occurring radionuclides.
It must be realized that the environment contains a
broad inventory of naturally occurring radioactive elements.
Background
radiation, as a
function of primordial radioactive elements and cosmic radiation of solar origin, offers
'a constant exposure to the.environment, and man.
These.
radionuclides, such as Ra-226, Be-7 and especially K-40, account for a majority of the annual per capita background dose.
A second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earth's upper atmosphere.
AL D (Cont'd)
The detonation frequency during the early 1950's produced a significant inventory of radionuclides found in the lower atmosphere as well as in ecological systems.
A ban was placed on atmospheric weapons testing in 1963 which greatly reduced the inventory through the decay of short lived radionuclides, deposition, and the removal (by natural processes) of radionuclides from the food chain.
Since
- 1963, several atmospheric weapons tests have been conducted by the People's Republic of China.
In each
- case, the usual radionuclides associated with nuclear detonations were detected several months afterwards, and after a
peak detection
- period, diminished to a
point where most could not be detected.
The last such weapons test was conducted in October of 1980.
The resulting fallout or deposition from this test had influenced the background radiation in the vicinity of the site and was very evident in many of the sample media analyzed during 1981.
Calculations from 1981 of the resulting doses to man from fallout related radionuclides in, the environment show that the contribution from such nuclides (such as Sr-90 or Cs-137) is significant and second in intensity only to natural background radiation.
Quant'ities of Nb-95, Zr-95, Ce-141, Ce-144, Ru-106, Ru-103, La-140, Cs-137, Mn-54 and Co-60 were typical in air. particulate samples during 1981 and have a
weapons test origin.
During
- 1988, Cs-137 was the only radionuclide detected in environmental samples that has a weapons testing origin.
The third group of radionuclides includes those detected at the site that were a result of the Chernobyl Nuclear Plant accident.
These radionuclides were first detected in May of 1986 and were found in.
samples of air particulates, air radioiodine and milk.
Applicable radionuclides include I-131; Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, and La-140.
During 1988, Cs-137 was detected in one milk sample collected prior to the grazing season and was a result of the Chernobyl accident.
The fourth group of radionuclides are those that could be related to operations at the site.
Many of these radionuclides are a by-product of both nuclear detonations and the operation of light water reactors, and therefore, make a distinction between the two. sources difficult, if not impossible.
The radionuclides falling into this category (as applicable to the 1988 Nine Mile Point Radiological Environmental Monitoring Program) includes I-131 and tritium.
The dose to man as a
result of these radionuclides is small and significantly less than the radiation exposure from naturally occurring sources of radiation and fxom fallout.
Thus g the evaluation and interpretation of environmental data must be made at several levels including trend analysis, dose to man, etc.
An attempt has been made not only to report the data collected during 1988, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources.
It is important to note that detected concentrations of radionuclides that are possibly related to operations at the site are very small and are not an indication of environmental significance.
In regards to these very small quantities, it will be further noted that at such minute
. concentrations the
- assessment of the significance of detected
-10
(Cont'd) radionuclides is very difficult.
Therefore, concentrations in one sample that are two times the concentration of another, for example, are not significant overall.
- Moreover, concentrations at such low levels may show a particular radionuclide in one sample and yet not in
'nother because of counting statistics.
The 1970 per capita dose rate (Eisenbud) was determined to be 209 mrem per year from all sources.
This average dose includes such exposure sources as natural, occupational, weapons
- testing, consumer
- products, medical, etc.
The 1970 per capi.ta dose rate due to natural sources was 130 mrem per year.
Of this
- dose, approximately 20 mrem per year is received by the gonads and other soft issues and an additional 15 mrem per year is received by the bone tissue for a
70 kg (155 lb) man.
These doses (ie.
20 mrem and 15 mrem) are the result of just K-40
- alone, a naturally occurring relatively high energy beta emitter (1.3 Mev).,
The 1970 per capita dose rate due to the nuclear fuel cycle was 0.028 mrem per year.
More recently, the nuclear fuel cycle dose was estimated by a USEPA study to be less than 0.6 mrem per year by the year 2000.(Glasstone).
Background
gamma radiation around the Nine Mile Point'ite, as a result of radionuclides in the atmosphere and the
- ground, accounts for approximately 66 mrem per year during 1988.
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 66 mrem per year, as a
background
- dose, is significantly greater than any possible doses as a
result of operations at the site during 1988.
A.
Tables 3
through 6
show the analytical results for the aquatic media collected during the 1988 sampling program.
Aquatic samples were collected at four possible indicator locations.
The locations (on-site transect designations) used for on-site sampling were
- NMPW, NMPP (02),
JAF (03),'nd NMPE.
Because of the unavailability of various sample
- media, on-site samples may be collected from combinations of the above listed locations, when required.
NMPW and NMPP may be combined into location.NMPP.
NMPE and JAF may be
'ombined into location JAF.
Off-site samples were collected at the
'swego Harbor area or in the general vicinity of the harbor and therefore served as control samples.
Refer to Figure 1A for the location of sample transects.
Data are evaluated only from locations required by the Technical Specifications.
Data from optional sample locations are not evaluated unless indicated otherwise.
A. l.
t Table 3
Shoreline sediment samples were collected twice during 1988.
Samples were obtained in April and October at one off-site or control location (near, Oswego Harbor) and at one indicator
-11
(Cont'd) t Table 3 (Cont'd) location (shoreline area just east of the site with recreational value).
The results of the shoreline sediment samples collected during 1988 at the indicator and control locations are shown on Table 3.
Table 3A shows results in units of pCi/g (dry) for purposes of data evaluation.
Table 3B shows results in units of pCi/kg (dry),
as required by the Technical Specifications.'nly the Sunset Bay location was required by the Technical Specifications during 1988.
Several radionuclides were detected in sediment samples using gamma spectral analysis.
These radionuclides were naturally occurring primordial radionuclides.
K-40 was detected at both the control location and indicator locations for both collection periods during 1988.
K-40 ranged in concentration from 10.7 pCi/g (dry) to 12.2 pCi/g (dry) at the control location and 10.4 pCi/g (dry) to 14.7 pCi/g (dry) at the indicator locations.
Ra-226 and AcTh-228, in addition to K-40, were also detected and are also naturally occurring radionuclides.
Ra-226 was detected at concentrations that were representative of normal background level fluctuations.
Ra-226 was found at concentrations of 1.69 pCi/g (dry) to 1.86 pCi/g. (dry) at the indicator locations and 0.98 pCi/g (dry) to 1.17 pCi/g (dry) at the control location.
AcTh-228 was found at the indicator location and ranged from 0.59 pCi/g (dry) to 0.84 pCi/g (dry) and 0.34 pCi/g (dry) to 0.52 pCi/g (dry) at the control location.
Be-7 was not detected in any of the indicator or control samples.
Be-7 is a naturally occurring radionuclide and has been detected intermittently during the past.
No other radionuclides were detected in shoreline sediment samples using gamma spectral analysis.
Evaluation of average historical data (1979-1987) shows that Cs-137 has ranged from 0.05 pCi/g (dry) in 1982 to 0.22 pCi/g (dry) in 1979 at the control location.
Cs-137 at the Nine Mile Point indicator location has ranged from 0.11 pCi/g (dry) in 1981 to 1.58 pCi/g (dry) in 1984.
For the years, 1985 1988, Cs-137 was not detected.
The station's Technical Specifications required shoreline sediment samples to be collected from the closest recreational area where the shoreline was utilized.
The indicator sampling location was relocated, therefore, to an area just east of the site boundary.
This change was initiated in 1985.
As noted
- above, Cs-137 was not detected during 1985 1988 at the new location.
The evaluation of past Co-60 data indicates that Co-60 has not been detected during the period of 1979 1981 at the Nine Mile
-12
(Cont'd)
A. 1.
t Table 3 (Cont'd)
Point indicator location.
During 1982, Co-60 was detected at an average concentration of 0.16 pCi/g (dry) at the Nine Mile Point location.
Co-60 increased to an average concentration of 0.25 pCi/g (dry) during 1983 and decreased to 0.24 pCi/g (dry) during 1984.
As noted
- above, the indicator location was relocated during 1985 as a
result of the Technical Specifications.
During the years 1985 1988, Co-60 was not detected at this new location.
Co-60 has not been detected at the control location since 1979 which was the beginning of the review period.
Tables 21 and 22 show historical environmental data for shoreline sediment samples.
Shoreline sediment samples were not collected prior to 1979.
The impact, as expressed by a dose to man, cannot be evaluated because no plant related gamma emitting radionuclides were detected in the control or required indicator shoreline sediment samples.
A. 2. ~ Table 4A, 4B A total of twenty-seven fish samples were analyzed as a result of collections in the spring season (May 1988) and in the fall season
.(September-October 1988).
Collections were made utilizing 'gill nets 'at one location greater than 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 Nl (02),
and the James A. FitzPatrick (03) generating facilities.
The Oswego Harbor samples served as control samples while the NMP (02) and JAF (03) samples served as indicator samples.
Samples were analyzed for gamma emitters.
Table 4A shows results in units of pCi/g (wet) for purposes of data evaluation.
Table 4B shows, results in units of pCi/kg (wet),
as required by the Technical Specifications.
Spring fish collections were comprised of six separate species.
The six species represented three feeding type.
Lake
- trout, brown
- trout, Chinook
- salmon, and white perch are highly predacious and feed on significant quantities of smaller fish such as
- smelt, alewife, and other smaller predacious species.
Rainbow smelt represent the second feeding type and are characterized by the consumption of small fish species and zooplankton.
The third feeding type is represented by white sucker which are bottom feeders that consume bottom dwelling organisms and decaying organic matter.
Cs-137 was detected in six of the ten indicator samples and in four of the five control samples collected during the spring.
Indicator samples showed Cs-137 concentrations to be slightly
-13
(Cont'd)
A. 2. ~ - Table 4A, 4B (Cont'd) greater than control results for some samples and slightiy less than or equal to control results for other samples.
The average indicator Cs-137 concentration was slightly less than the average control concentration.
The indicator results,
- however, are not significantly different from the control results and are therefore considered to be representative of background concentrations.
The detected Cs-137 concentration in lake trout samples was 0.027 pCi/g (wet) for the indicator samples.
The detected Cs-137 concentration in control samples was 0.023 pCi/g (wet) for lake trout.
Cs-137 in brown trout samples ranged from 0.022 to 0.023 pCi/g (wet) at the indicator locations.
Cs-137 in the control sample was 0.030 pCi,/g (wet)
(one sample collected).
Chinook salmon.
showed Cs-137 detected at 0.030 and 0.031 pCi/g (wet) for the indicator samples and 0.053 pCi/g (wet) for the control sample.
White perch samples showed Cs-137 detected only once at 0.030 pCi/g (wet) at the indicator locations and once in the control sample at a concentration of 0.028 pCi/g (wet).
Cs-137 was not detected in rainbow smelt at the indicator or control locations.
In addition, Cs-137 was not detected in the one white sucker sample collected from the Fitzpatrick location.
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.
Detectable concentrations of K-40 in the indicator samples ranged from 2.64 to 4.92 pCi/g (wet) and 2.75 to 5.31 pCi/g (wet) for the control samples.
Ra-226, also naturally occurring, was found at levels that ranged from 0.17 to 1.03 pCi/g (wet) at the indicator locations and 0.42 to 0.61 pCi/g (wet) at the control location.
No other radionuclides were detected in the spring fish samples.
Fall fish sample collections were comprised of four separate species and twelve individual samples.
Three samples each of
- walleye, lake
- trout, smallmouth bass and white sucker were collected at a
combination of two indicator sample locations (NMP and JAF) and one control sample location (Oswego Harbor area).
Samples were collected by gill net in September October.
Cs-137 was detected in five of the twelve samples which included the control samples.
Indicator samples showed an average Cs-137 concentration that was approximately equal to the control sample mean from the off-site location.
The detected concentrations were not significantly different from one another because of the extremely small quantities detected.
Cs-137 in walleye samples at the indicator locations was detected once at 0.020 pCi/g (wet) and was not detected at the control location.
Lake trout samples showed a
Cs-137 concentration of 0.031 pCi/g (wet) for
-14
N F
EN L DA (Cont'd)
A. 2.
Table '4A, 4B (Cont'd) the control sample and ranged from 0.050 to 0.074 pCi/g (wet) for the indicator samples.
's-137 in smallmouth bass samples was detected only once at a
concentration of 0.030 pCi/g (wet) at the indicator locations and was not detected at the control location. 'hite sucker samples were available at both indicator and control locations.
Cs-137 was not detected in these samples.
The one species of bottom feeder collected during the fall season (white sucker) showed no detectable Cs-137 because of different feeding habits and because this species is not in the same position on the food chain as the other predacious species.
K-40 was detected in all of the fall samples collected.
Detectable concentrations of K-40 in the indicator samples ranged from 3.79 to 4.51 pCi/g (wet) and 4.00 to 4.80 pCi/g (wet) for the control samples.
K-40 is naturally occurring.
Ra-226 was also detected and is naturally occurring.
Ra-226 ranged from 0.38 to 0.67 pCi/g (wet) for the indicator samples and from 0.42 to 0.76 pCi/g (wet) for the control samples.
No other radionuclides were detected in the fall fish samples.
Review of-past environmental data indicates that the mean annual Cs-137 concentration has decreased significantly from the 1976 through 1979 results for indicator samples.
Average concentrations for these samples decreased from a level of 1.4 pCi/g (wet) in 1976 to a level of 0.028 pCi/g (wet) in 1986.
Control sample results have also decreased from a level of 1.2 pCi/g (wet) in 1976 to a level of 0.025 pCi/g (wet) in 1986.
Results from 1980 to 1986
- have, shown a fairly consistent decreasing trend for control and indicator samples.
During 1987 and 1988, control and indicator mean results increased slightly when compared to 1986.
The general decreasing trend for Cs-137 is most probably a
result of ecological'ycling.
The concentrations of Cs-137 detected since 1976 in fish are a result of weapons testing
- fallout, and the general down'ward trend in concentrations will continue as a function of ecological cycling and nuclear decay.
There was no apparent effect from the 1986 Chernobyl Nuclear Plant acci'dent during 1986 relative to Cs-137 results in fish samples although an effect may have been detected during 1987 and 1988 since both indicator and control location mean results increased slightly.
Tables 23 and 24 show historical environmental sample data for fish.
Lake Ontario fish are considered an important food source by many.
Therefore, fish are an integral part of the human food chain.
-15
(Cont'd)
A. 2. ~ Table 4A, 4B (Cont'd)
Based on the importance of fish in the local diet, a reasonable conservative estimate of 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 0.034 pCi/g (wet)
(annual mean result of indicator'amples for 1988),
the whole body'ose received would be 0.051 mrem per year.
The critical organ in this case is the liver which would receive a
calculated dose of 0.078 mrem per year.
The Cs-137 whole body and critical organ doses are conservative calculated doses associated with consuming fish from the Nine Mile Point area (indicator samples).
No radiological decay is assumed for the calculation of doses.
Conservative whole body and critical organ doses can be calculated for the 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
)
but the average annual Cs-137 concentration for the control samples is 0.033 pCi/g (wet).
The 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.
In summary, the whole body and critical organ doses observed as a result of consumption of fish is small.
.Doses received from the consumption of indicator and control sample fish are approximately the same.
The doses from indicator sample fish are slightly greater, although well within natural variability.
For
- example, the whole body and organ doses from the control samples were greater during 1985.
Doses from both sample groups are considered background doses.
A. 3.
Tables 5 and 6
Surface water samples were analyzed monthly for gamma emitters (using gamma spectral analysis) during 1988.
Tritium analyses were performed quarterly.
Quarterly samples (i.e., analysis for tritium) were composite samples.
The analytical results for the 1988 surface water samples showed no evidence of plant related radionuclide buildup in the surface water in the vicinity of the site.
Indicator samples were collected from the inlet canal at-the James A. FitzPatrick facility.
The control location samples were collected at the inlet canal of Niagara Mohawk's Oswego Steam Station.
These two locations are required to be sampled by the Technical Specifications.
Tables 5
and 6
show the results of surface water samples analyzed during 1988.
-16
III.
E L DA (Cont'd)
A. 3.
Gamma spectral analysis was performed on twenty four monthly composite samples (two locations) required by the Technical Specifications.
In addition, three optional sample locations were evaluated.
These included the Nine Mile Point Nuclear Station Unit 1
and Unit 2 inlet canals and the City of Oswego drinking water supply.
The drinking water supply composite samples consisted of twice per week grab samples.
Only two radionuclides were detected in samples from the five locations over the course of 1988.
These radionuclides were naturally occurring.
K-40 was detected intermittently in both Technical Specification required intake canal samples.
The James A. FitzPatrick inlet canal samples showed K-40 detected in ten of the twelve monthly samples and ranged from 60 to 248 pCi/liter.
K-40 in the Oswego Steam Station inlet canal was detected in ten of the twe'lve samples and ranged from 46 to 232 pCi/liter.
The Nine Mile Point Unit 1 inlet canal, Unit 2 inlet canal and the city water samples showed K-40 detected in
- twelve, twelve and eleven respectively, of the twelve monthly samples for each location.
For these
- samples, K-40 concentrations ranged from 50 to 244 pCi/liter, from 70 to 265 pCi/liter and from 68 to 267 pCi/liter respectively.
Ra-226 was detected intermittently in samples from all five locations.
Ra-226 was detected in twelve of the twelve monthly
" samples from the Nine Mile Point Unit 81 inlet. canal and ranged from 59 to 144 pCi/liter.
The Nine Mile Point Unit 2 inlet canal showed Ra-226 detected in ten of the twelve samples and ranged from 73 to 143 pCi/liter.
Samples from the FitzPatrick location showed Ra-226 in ten of the twelve monthly samples and ranged from 73 to 124 pCi/liter.
The control sample location (Oswego Steam Station) showed Ra-226 in nine of the twelve monthly samples and ranged in conce'ntrations from 63 to 130 pCi/liter.
The city water samples results showed Ra-226 detected in ten of the twelve monthly'samples and ranged from 80 to 118 pCi/liter.
Tritium samples are quarterly samples that are a
composite of the appropriate calendar months.
Tritium was detected in samples taken at all five locations.
Two of the sample results showed that tritium was not detected within the analytical sensitivity of the analysis.
The City of Oswego drinking water showed tritium concentrations ranging from 180 to 370 pCi/liter with a mean of 292 pCi/liter.
Tritium concentrations for the James A.
FitzPatrick inlet canal ranged from 430 to 480 pCi/liter and showed a
mean concentration of 460 pCi/liter.
Inlet'anal samples taken at Nine Mile Point Unit 1
'and Unit 2
showed tritium concentrations ranging from 280 to 750 pCi/liter
-17
D (Cont'd) t r Tables 5 and 6 (Cont'd) and 210 to 420 pCi/liter respectively.
The annual mean concentration was 462 pCi/liter and 320 pCi/liter respectively.
The Technical Specification control location (Oswego Steam Station inlet canal) showed tritium results which ranged from 240 to 460 pCi/liter with a mean of 320 pCi/liter.
As noted
- above, annual tritium results for the Nine Mile Point Unit 1 inlet canal ranged from 280 to 750 pCi/liter.
The maximum result (750 pCi/liter) was greater than the control location results (Oswego Steam Station) which ranged from 240 to 460 pCi/liter or the drinking water samples which ranged from 180 to 370 pCi/liter.
The maximum result of 750p120 pCi/liter occurred during the second quarter.
The third quarter showed a
result of 530p100 pCi/liter and the fourth quarter was 290~70.
The second and third quarter results were above background levels.
The fourth quarter result'ppeared to be in general agreement with the control sample fourth quarter. result.
During 1988, the Unit 1 facility was not operational and there were no liquid discharges from the facility.
There are no known operational events during the second and third quarters of the year which would have contributed to the increase in tritium levels over normal background levels other than the recirculation of the 'irculating water.
During this time
- period, the main circulating water pumps were not operational.
A major portion of the discharge flow resulting from the service water system.
was recirculated from the.discharge canal to the inlet canal in order to prevent ice from forming in the inlet canal during January through March.
The recirculation was
'aintained during the second quarter and part of the 'third quarter of the year.
Any small sources of tritium that may have entered the discharge canal via the service water system would have a
tendency to increase in the water being recirculated.
Samples obtained at the NMP-1 inlet sample location would be representative of recirculated water.
Although tritium was detected in the NMP-1 inlet canal samples for the second and third calendar
Samples of the NMP-1 service water system effluent will be taken in order to determine whether any minor leakage is occurring.
Review of past environmental data for Cs-137 from 1979 through 1987 shows that this radionuclide was detected only once at the control location during 1979 at a
concentration of 2.5 pCi/liter.
Cs-137 at the indicator location (JAF inlet canal) was detected only once during 1982 at a concentration of 0.43 pCi/liter.
The 1979 control sample result is. suspect and may have been a
result of contamination during handling or instrument background since Cs-137 was not detected in the indicator inlet canal.
The one result from the indicator
-18
(Cont'd)
A. 3.
location (JAF inlet canal) during 1982 was detected in a January composite sample and may have been a result of inlet canal tempering (the addition of discharge water to the inlet canal) or instrument background.
Cs-137 was not detected during 1988 in surface water samples.
Other plant'elated radionuclides detected during a
review period of 1979 1987 include only Co-60.
The control sample location results showed that Co-60 was detected
'once in 1981 (the May composite sample).
This result is suspect
- and, as noted above, may be a result of contamination during handling or may be instrument background.
This result was 1.4 pCi/liter.
Results from the indicator location showed that Co-60 was detected three times during 1982 and averaged 1 ~ 9 pCi/liter.
These positive results were attributed to inlet canal tempering
'and instrument background.
Co-60 was not detected during 1988 in surface water samples.
Tables 25 and 26 show historical environmental sample data for surface water.
Previous annual mean results for tritium at the indicator sample location (FitzPatrick inlet canal) has decreased since 1976.
Mean sample results reviewed from 1976 through 1987 showed a
peak average value of 627 pCi/liter (1976) and a minimum value of'27 pCi/liter (1980).
The annual mean tritium result at the indicator location for 1988 was 460 pCi/liter.
Mean tritium results for the control location (Oswego Steam Station) can not be evaluated with regard to long term historical data since sampling was only initiated at this location in 1985.
Some idea of the variability of control sample data can be obtained,
- however, by review of previous data from the City of Oswego drinking water samples.
The drinking water samples are not likely to be affected by the station because of the effects of the distance, lake currents, and the discharge of the Oswego River.
Therefore, this previous sample data represents acceptable control sample data for evaluation purposes.
Historical mean annual tritium results from previous city water samples (1976-1984) and Oswego Steam Station samples (1985-1987) show that the tritium concentrations have decreased.
The maximum annual average was found in 1976 (652 pCi/liter) and the minimum in 1982 (165 pCi/liter).
Mean annual results from 1979 to 1987 have remained relatively consistent.
The annual mean result for 1988 was 320 pCi/liter.
Tables 27 and 28 show historical environmental sample data for surface water tritium.
-19
ENTAL DATA (Cont'd)
A.
3 ~
The impact, as expressed as a dose to man, can not be evaluated because plant related gamma emitting radionuclides were not detected in monthly surface water samples.
Plant related radionuclides were not found in the optional drinking water samples either.
Although tritium was found at slightly elevated levels during the second and third quarters of the year at the NMP-1 inlet
- canal, the levels noted in the drinking water samples were normal and representative of background levels.
For the purposes of illustration, the
- impact, expressed as a
dose to man, can be determined by assuming the inlet water for the two calendar quarters flows from the site to the nearest drinking water inlet and is subsequently ingested.
Several assumptions must be made for this determination.
These include:
the nearest drinking water source is at the City of
- Oswego, the dilution of the'ater that flows to the source is 7.7 (NNP-1 Appendix I
submittal),
the average tritium concentration during the two calendar quarters minus the associated average background concentration is 265 pCilliter, the maximum exposed individual is an infant and the consumption rate is 330 liters per year or 82.5 liters per calendar quarter (Regulatory
,Guide 1.109).
The theoretical dose as a result of ingesting water originating from the inlet canal is 0.0017 mrem to the whole body and any organ.
This dose can be compared to the whole body dose received from naturally occurring cosmic radiation originating from outer space when one'ncreases in altitude.
A whole body dose of 0.0017 mrem is equal to residing at a location 328 feet higher in altitude for approximately 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
B.
Tables 7 through 14 and 17 represent the analytical results for the terrestrial samples collected for the 1988 repor'ting period.
Data are evaluated only from locations required by the Technical Specifications.
Data from optional sample locations are not evaluated unless indicated otherwise.
B. l.
t G
t Tables 7 and 8
" Tables 7
and 8
contain the results for the weekly air particulate gross beta analysis for a total of nine off-site and six on-site sample locations.
Five of the nine off-site locations are required by the Technical Specifications.
These sample locations are R 1, R 2, R 3, R 4 (all located near the site boundary) and R-5 (located at a control location beyond any significant influence from.the site).
Data contained on Tables 7 and 8 also shows the results from other air sampling locations
-20
(Cont'd)
B. l. A
t Tables 7 and 8 (Cont'd) not required by the Technical Specifications.
These locations are designated as Dl on-site, G on-site, H on-site, I on-site, J
on-site, K on-site, D2 off-site, E off-site, F off-site and G
off-site locations.
A total of 52 control samples from location R-5 and 208 indicator samples from locations R-l, R-2, R-3, and R-4 were collected and analyzed during 1988.
The minimum,
- maximum, and average gross beta results for sample locations required by the Technical Specifications are presented below.
Location **
Minimum*
Maximum*
Average*
R-1 R-2 R-3 R-4 R-5 (control) 0.008 0.008 0.007 0.007 0.008 0.038 0.037 0.039 0.040 0.039 0.019 0.018 0.018 0.018 0.018
. Concentration in pCi/m3
- Locations required by the Technical Specifications The observed small increases and decreases in general gross beta activity can be attributed to changes in 'he environment, especially seasonal changes.
The concentration of naturally
..occurring radionuclides in the lower limits of the atmosphere directly above land areas are affected by processes such as wind direction, snow
- cover, soil temperature and soil moisture content.
Little change wa's noted in gross beta activity which corresponded with weapons testing as has been observed in past years.
Review of air particulate gross beta concentrations shows that no significant increases in concentration occurred during 1988.
In general, the trend in air particulate gross beta activity has been one of decreasing activity since 1977 (extent of the review period).
The mean gross beta concentration at control'ocations has decreased from a level of 0.165 pCi/m3 in 1981 to 0.021 in 1987.
Results from indicator air sampling locations ranged from 0.151 pCi/m3 in 1981 'o 0.021 pCi/m3 in 1987.
For both indicator locations and control locations, the gross beta concentration during 1977 to 1987 fluctuated with the detonation of thermonuclear weapons.
The Technical Specification control and indicator results during 1988 were 0.018 pCi/m3 and 0.018 pCi/m3 respectively which represented the lowest level recorded to date.
Tables 29 and 30 show historical environmental sample data for air particulate gross beta levels.
-21 P gv tA4 e\\ et (p Opal ~,
0 L'I P vh l P11 p
(> l '
Qd ~ 'l't 8 ff'Pw
(Cont'd)
B. 2.
't Table 9
Weekly air particulate samples were composited by location to form monthly composite samples.
The monthly composite samples required by the Technical Specifications include R-l, R-2, R-3, R-4, and R-5.
Other sample locations not required by the Technical Specifications include Dl on-site, G
on-site, H
on-site, I
on-site, J
on-site, K on-site, D2 off-site, E
off-site, F off-site and G off-site locations.
The results of all monthly composite samples are included on Table 9.
The results for the monthly composite samples showed positive results for Be-7, K-40, and Ra-226.
All three of these radionuclides are naturally occurring.
Be-7 was found in all of the monthly composite samples from all locations required by the Technical Specifications.
Be-7 ranged from 0.055 to 0.153 pCi/m3 for the Technical Specification indicator locations (R-l, R-2, R-3, and R-4).
The Technical Specification control location (R-5) results showed Be-7 ranging from 0.065 to 0.122 pCi/m3.
K-40 was found intermittently in the monthly composite samples required by the -Technical Specifications.
K-40 ranged from 0.016 to 0.049 pCi/m3 at the control location (R-5) and 0.010 to 0.045 pCi/m~ at the indicator locations.
Ra-226 ranged from 0.013 to 0.025 pCi/m3 at the indicator locations required by the Technical Specifications.
The Technical Specification cbntrol location results showed no detectable Ra-226.
As a result of the Chernobyl Nuclear Plant accident in April
- 1986, several radionuclides attributable to the fission process were
- detected, in air particulate samples during 1986.
Detectable radionuclides included Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, La-140 and I-131.
These radionuclides were not detected during 1988.
No other radionuclides were detected using gamma spectral analysis during 1988.
The
- location, concentration range and
- mean, and frequency of occurrence of each radionuclide detected during 1988 ~t~~
are included below.
'Be-7 imaxim Indicator Control Indicator Control Indicator Control ggggpA 0.013 0.025 ND 0.010 0.045 0.016 0.049 0.055 0.153 0.065 0.122 th I
0.017 6/48 ND ND 0.026 34/48 0.031 4/12 0.093 48/48 0.094 12/12 Results in units of pCi/m3.
- Frequency is the number of times detected over the number of samples.
ND - Not detected
-22
N (Cont'd)
B. 2.
t t
t t
Table 9 (Cont'd)
Historically, the naturally occurring radionuclides Ra-226, K-40 and Be-7 have shown fluctuations that are representative of natural changin'g conditions.
No significant trends were noted during 1988.
In the past, Co-60 has fluctuated in air particulate samples as a
result of previous weapons testing.
Co-60 average concentrations at the indicator ~ control locations from, 1977
'o 1978 decreased from approximately 0.0176 to 0.0022 pCi/m3.
Average concentrations decreased significantly during 1979 and 1980 when compared to 1977.
These results where 0.007 to 0.0016 pCi/m3 respectively.
1981 and 1982 average Co-60 concentrations decreased to 0.0007 and 0.0006 pCi/m3.
Average indicator 'and control concentrations were approximately equal during 1979 to 1982.
The 1983 indicator mean Co-60 concentration was 0.0007 pCi/m3. or slightly greater than the 1982 concentration.
The 1983 control mean Co-60 concentration was also 0.0007 pCi/m3 which was slightly greater than 1982 control results.
As noted in, previous annual
- reports, however, a portion of the Co-60 detected during 1983 was attributed to contamination during handling of the unused filters prior to installation.
Co-60 was detected during the first quarter of 1984 and averaged 0.0008 pCi/m3 at the control stations and 0.0012 pCi/m3 at the indicator stations.
- However, the 1984 Co-60 positive results were a result of contamination during handling
~ and not a
result of operations at the site.
The general reduction in previous indicator and control Co-60 concentrations (1981 1983) was a result of nuclear decay and ecological cycling of Co-60 initially produced by the 1980 Chinese weapons test.
Co-60 was not detected during 1985 1986 in air particulate samples from either indicator or control locations.
During
- 1987, Co-60 was detected once at a
concentration of 0.0017 pCi/m3 at an optional air monitoring
- station.
- However, "the Co-60 detected during 1987 was a result of contamination from improper handling of the
- sample, and not as a result of effluents from the site.
This evaluation is contained in the 1987 annual report.
Results from 1988 showed that Co-60 was not detected from either control or indicator sample locations.
Historically, Cs-137 has been variable during the past and has been present in air particulate samples since 1977.
During
- 1977, both indicator and control Cs-137 average concentrations were approximately equal and averaged 0.0038 pCi/m3.
Cs-137 average concentrations at indicator and control locations decreased during 1978 and 1979 to 0.0017 and 0.0013 pCi/m3 respectively.
Average concentrations during 1980 and 1981 were approximately equal at control and indicator locations.
Cs-137 during 1980 was approximately equal to 1979 and increased slightly in 1981 from 1979.
The 1980 and 1981 average
-23
I II.
gap (Cont'd)
B. 2.
't Table 9 (Cont'd) concentrations were 0.0014 and 0.0016 pCi/m3 respectively. The mean 1982 concentration for Cs-137 decreased to 0.0004 pCi/m3.
The 1983 mean Cs-137 concentration for the indicator and control composite samples were 0.0002 and 0.0002 pCi/m3 which was a
reduction from 1982 results.
Cs-137 was not detected during 1984 in any of the indicator or control air particulate composite samples.
As noted above for the average annual "Co-60 results, the reduction in Cs-137 results since 1981 is attributed to nuclear decay and ecological cycling of Cs-137 initially produced by the 1980 Chinese weapons test.
Cs-137 was not detected during 1985 in air particulate samples.
Cs-137 was detected during 1986 as a result of the Chernobyl Nuclear Plant accident in April 1986.
Mean Cs-137 concentrations for vindicator and control sample locations were 0.0183 and 0.0193 pCi/m3 respectively.
During 1987 and
- 1988, Cs-137 was not detected.
Prior to
- 1984, several radionuclides were detected that were associated with the 1980 Chinese weapons test and other weapons tests prior to 1980.
These radionuclides were not detected during 1984 or 1985 as a result of nuclear decay and ecological cycling.
These include Zr-95, Ce-141, Nb-95, Ce-144, Mn-54, Ru-103, Ru-106 and Ba-140.
In addition, La-140 was detected once during 1983 and 'infrequently during 1978 and 1981.
La-140 was not detected during 1984 or 1985.
During
- 1986, however, several fission product radionuclides were detected that were a
result of the Chernobyl Nuclear Plant accident.
These included Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, La-140 and I-131.
All of
- these, with the exception of Cs-134 and particulate I-131, were detected subsequent to the 1980 Chinese weapons test (1981 1983).
These radionuclides were not detected during 1984 1985.
The concentrations detected during 1986 as a result of the Chernobyl accident were generally greater than the concentrations detected as a result of the 1980 Chinese weapons test.
The presence of the radionuclides from the Chernobyl
- facility, however, extended over a
very brief period (two months) while many of the radionuclides from the 1980 Chinese weapons test were present for approximately two years.
During 1987 and
- 1988, none of the radionuclides associated with the 1986 Chernobyl accident were detected in air particulate samples.
Tables 31 and 32 show historical environmental sample data for air particulate composites.
B.
3.
Tables 10 and 11 During the 1988 sampling
- program, airborne radioiodine was not found in any of the fifty-two weekly samples from the control location required by the Technical Specifications.
LLD values at the control location ranged from 0.005 0.012 pCi/m3.
-24
(Cont'd)
B. 3.
Tables 10 and 11 (Cont'd)
I-131 has been detected in the past at control locations.
During
- 1976, the mean off-site I-131 concentration was 0.60 pCi/m~.
The,.1977 mean I-131 concentration decreased to 0.32 pCi/m3 and for 1978 the concentration decreased by a factor of ten to 0.03 pCi/m3.
During 1979 1981 and 1983 1985, I-131 was not detected.
I-131 was detected once during 1982 at a
concentration of 0.039 pCi/m3.
Results from 1986 showed that I-131 was detected at the control location.
This was a result of the 1986 Chernobyl Nuclear Plant accident.
The I-131 mean result was 0.151 pCi/m3.
I-131 was not detected, at the control location during 1987 or 1988.
During 1988, the indicator locations required by the Technical Specifications (approximate site "boundary locations) showed no detectable levels of I-131.
, LLD values for I-131 ranged from 0.005 0.019 pCi/m3.
During 1988, I-131 was detected at one of the optional on-site monitoring locations that was not required by the Technical Specifications.
The H on-site location is in close proximity to the generating facilities and is located in the northeastern area of the site.
A detectable quantity of 0.012~0.007 pCi/m3 was found at the H on-site monitoring location during the week of June 6-13, 1988.
I-131 was not detected at any of the other optional air monitoring locations during the aweek of June 6-13 nor was it detected at any other time dpring 1988.
I-131 at indicator locations has been detected in the past and was detected at a
mean concentration of 0.33 and 0.31 pCi/m3 during 1976 and 1977.
The average concentration decreased to 0.04 pCi/m3 during 1978 and was not detected during 1979.
The 1980-1982 average concentrations were 0.013,
'0.029, and O.OL6'Ci/m3 which were reductions in view of previous I-131 concentrations.
During
- 1983, the mean I-,131 concentration was 0.028 pCi/m3 which represented a slight increase compared to 1982.
For the most part, I-131 in indicator and control samples was a result of I-131 from weapons testing.
A small portion of the concentrations detected may have been a result of operations at the site.
The concentrations detected during 1983 at the on-site sample stations were a
result of operations at the site.
I-131 was not detected in any of the 1984 or 1985 samples.
During
- 1986, I-131 was detected at the indicator locations at a
mean concentration of 0.119 pCi/m3 as a result of the Chernobyl Nuclear Plant accident.
I-131 was found at a
mean concentration of 0.014 pCi/m3 during 1987 and was a
result of operations at the site.
As noted previously,
'I-131 was not found at the Technical Specification required indicator locations during 1988.
Tables 33 and 34 show the historical environmental sample data for'irborne radioiodine.
-25
DA (Cont 'd)
B.3.
~
~
n The impact of the measurable concentration of I-131 at the optional indicator location can be assessed by projecting a dose to the maximum exposed organ (thyroid) and the whole body as a
result of inhalation.
The maximum exposed age group is the child.
Using Standard Regulatory Guide 1.109 methodology, an inhalation rate of 3700 m~ per year and the indicator location I-131 concentration, conservative doses can be calculated.
In order to be conservative and to simplify the computations, no radiological decay is assumed and the maximum exposed individual is assumed to remain at the location for one week.
Maximum child thyroid and whole body doses are presented below.
Samplet'ean Weeks v
Thyroid Whole Body use (2)
Indicator Control 0.012
<LLD 0.004 0.000006 (1) Concentration in pCi/m3 (2) Dose in mrem for 1988 The calculated total dose for the critical individual (child) would be 0.004 mrem to the thyroid and 0.000006 mrem to the whole body.
These doses are very small and are of no significance especially when one considers the fac't that the monitoring location is not an area occupied by members of the public.
B. 4.
Table 12 TLD's were collected and read once pe'r quarter during the 1988 sample year.
The TLD results are, for the most part, an average of eight independent readings at each location and are reported in mrem per standard month (Table 12A) and in mrem per quarterly period (Table 12B).
TLD's required by the Technical Specifications include two TLD's at each location with four independent readings per TLD.
TLD results included on Tables 12A and 12B are comprised of TLD's required by the Technical Specifications and special interest TLD's not required by the Technical Specifications.
During
- 1988, TLD's were collected on approximately March 30,
- 1988, June 29, 1988, September 29, 1988 and December 29, 1988.
Overall TLD results are evaluated by organizing environmental TLD's into five different groups.
These groups include:
(1) on-site TLD's (TLD's within the site boundary not required by the Technical Specifications),
(2) site boundary TLD's (one in each of the sixteen 22 1/2 degree meteorological sectors),
(3) a
-26
(Cont'd)
B. 4.
D E v'm t
m t Table 12 (Cont'd) ring of TLD's four to five miles from the site in each of the land, based 22 1/2 degree meteorological
- sectors, (4) special interest TLD's in areas of high population
- density, and (5) control TLD's in areas beyond any significant influence of the generating facilities.
Special interest TLD's are located at or near large. industrial
- sites, schools, or proximal towns or communities.
Control TLD's are located to the southwest,
- south, south-southeast, and northeast of the site at distances of 12.6 to 26.4 miles from the site.
Most of the TLDs required by the Technical Specifications during 1988 were initiated in 1985 as a result of the issue of new Technical Specifications by the NRC.
Therefore, these TLDs can only be compared to 1985 1987 results.
Other
- TLDs, which
-include a
few TLDs required by the Technical Specifications (i.e.,
numbers 7,
14, 15, 18, 23, 49, 56, and 58) and other optional
On-site TLD's are TLD's at special interest areas and, with the exception of TLD numbers 7
and 23, are not required by the Technical Specifications.
These are located near the generating facilities and at previous or existing on-site air sapling stations.
TLD's located at the air sampling stations
- include, numbers 3, 4, 5, 6, 7,
23, 24, 25 and 26.
The results for these TLD's are generally consistent with, previous years results although
- a. slight increase was. noted when compared to 1987.
These results ranged from 4.4 to 11.9 mrem per standard month.
TLD 83 is located in the vicinity of Nine Mile Point Unit 2 and is between the Unit 1 facility and the FitzPatrick facility.
The results for TLD N3 were approximately double the results of the other TLD's during the first three quarters of 1988 because
- of the effects from the Unit 2
and the FitzPatrick facility.
Overall, slight increases were noted during the third quarter of 1988 for these TLD's, as well as other groups of TLD's, including the control group.
Other on-site TLD's include special interest TLD's located near the north shoreline of the Unit 1,
Unit 2
and FitzPatrick facilities, but in close proximity to radwaste facilities and the Unit 1 reactor building.
These TLD's include numbers 27, 28, 29, 30, 31, 39, and 47.
Results for these TLD's during 1988 were variable and ranged from 6.8 to 40.4 mrem per standard month as a result of activities at the radwaste facilities and the operating modes of the generating facilities.
Results for 1988 are consistent with the ranges of variability noted in 1987 for TLD's at or near these locations.
TLD's in this group ranged up to approximately seven times control TLD results.
Additional on-site TLD's are located near the on-site Energy
-27
A (Cont 'd)
B. 4.
LD Env'm nt D
'm t Table 12 (Cont'd)
Center and the associated northeast shoreline.
These TLD's include numbers 18,
- 103, 106 and 107.
TLD's numbered
- 103, 106 and 107 are located to the east of the Energy Center and to the west of the Unit 1 facility.
TLD number 18 is located on the west side of the Energy Center.
Results during 1988 showed these TLD's ranged from 4.6 7.2 mrem per standard month and were slightly greater than the 1987 results.
- Again, slight increases were noted in the third quarter results as was noted for all TLD's, including control TLD's.
Site boundary TLD's are required by the Technical Specifications and are located in the approximate area of the site boundary with one in each of the sixteen 22 1/2 degree meteorological sectors.
These TLD's include numbers 75, 76, 77, 23, 78, 79, 80, 81, 82, 83, 84, 7,
18, 85, 86 and 87.
TLD numbers 78, 79, 80, 81, 82, 83, 84, 7 and 18 showed results that were consistent with control TLD results and ranged from 3.4 to 7.0 mrem per standard month.
Site boundary TLD's during 1988 were consistent with 1985-1987 results..
TLD numbers 75, 76, 77, 23, 85, 86, and 87 showed results that ranged up to three times the results of control TLD's.
These results ranged from 5.2 to 17.9 mrem per standard month.
This latter group of TLD's are located near the lake shoreline (approximately 100 feet from the shoreline),
but are also located in close proximity of the reactor building and radwaste facilities of Unit 1
and Unit 2
and the radwaste facilities of the FitzPatrick facility.
A net site boundary dose can be estimated from available TLD results and control TLD results.
TLD results from TLD's located near the site boundary in sectors facing the land occupied by members of the public (excluding TLD's near the generating facilities and facing Lake Ontario) are compared to control TLD results.
The site boundary TLD's include numbers 78, 79, 80, 81, 82, 83, 84, 7 and 18.
Control TLD's include numbers 8,
14, 49, 110 and ill. Net'ite boundary doses for each quarter in GKm ggx ~Ldgzsi moat are as follows:
t 't
-0. 2
-0.4
+0.1
-0.2
- Dose in mrem per standard month Site boundary TLD numbers 75, 76, 77, 23, 85, 86, and 87 were excluded from the net site boundary dose calculation since these TLD's are not representative of doses at areas where a member of
-28
(Cont'd)
B. 4.
D t
D t
Table 12 (Cont.'d) the public may be located.
These areas are near the north shoreline which are in close proximity to the generating facilities and are not accessible to members of the public.
The third group of environmental TLD's are those TLD's located four to five miles from the site in each of the land based 22.5 degree meteorological sectors.
These TLDs are required by the Technical Specifications.
At this
- distance, TLD's are not present in eight of the sixteen meteorological sectors that are located over Lake Ontario.
Results for this group of TLD's during 1988 fluctuated slightly as a result of changing naturally occurring conditions and the different concentrations of naturally occurring radionuclides in the ground at each of the locations.
These TLD's were established in 1985 and include numbers 88, 89, 90, 91, 92, 93,,
94 and 95.
Results fluctuated from 3.8 to 7.0 mrem per,standard month.
These results are generally consistent with control TLD results during '1988.
Results 'or this group of TLDs were consistent with the 1985 1987 results.
Results were also consistent with other 'ff-site TLD results
'during 1988 and previous to 1988.
- Again, third quarter TLD results were slightly elevated along with all other groups of TLD's, including control groups.
The fourth group of envir'onmental TLD's are those TLD's located near the site boundary and at special interest areas such as industrial sites,
- schools, nearby communities, towns, off-site air sampling stations, the closest residence to the site, and the off-site environmental laboratory.
Many of these TLDs are required by the Technical Specifications.
Others are optional.
This group of TLD's include numbers 9,
10, ll, 12, 13, 15, 19, 51, 52, 53, 54, 55, 56, 58, 96, 97, 98, 99
- 100, 101,
- 102, 108
, and 109.
TLD numbers 108 and 109 are new TLD locations that were established during 1988 and were added to assist in the evaluation of the critical residence.
Results ranged from 3.9
'o 7.2 mrem per standard month.
All the TLD results from this group were within the general variation noted for the control TLD's.
Results during 1988 for TLD's established during previous years were consistent with results noted for those years.
Overall, third quarter TLD results for this group were slightly elevated as were other TLD
- groups, including the control group.
The fifth group of TLD's include those TLD's considered as control TLD's.
These TLD's are required by the Technical Specifications and include numbers 14 and 49.
Optional control locations are TLD numbers 8,
- 110, and 111.
TLD numbers 110 and 111 were added to the program during 1988 to expand the data
-29
(Cont'd)
B. 4.
v t
Table 12 (Cont'd) base for control TLD's.
Results for 1988 ranged from 4.4 to 6.8 mrem per standard month.
Results from 1988 were consistent with previous years results.
- However, an annual average increase was noted in 1986.
This increase may have been a result of the Chernobyl Nuclear Plant accident and was not noted during 1987 or 1988.
Control TLD's results in 1988 (third quarter) were slightly elevated as were other TLD groups.
Review of past TLD results zgquj.
4~n groups.
These groups include site boundary TLDs in each meteorological sector (16 TLDs total),
TLDs located off-site in each land based sector at a distance of 4 to 5 miles (8
TLDs total),
TLDs located at special interest areas (6
TLDs total) and TLDs located at control locations (2 TLDs total).
As noted previously, since the present Technical Specifications became effective in 1985, these TLDs, for the most part, can only be evaluated for 1985 1988.
TLDs located at the site boundary averaged 6.2 mrem per standard month during 1985.
During 1986 and
- 1987, site boundary TLDs averaged 7.0 and 6.1 mrem per standard month.
As noted previously, this group of TLDs can fluctuate because several of these TLDs are located in close proximity to the generating facilities; An increase was noted during 1986 although such an increase was noted for all TLDs including control TLDs.
During 1988, site boundary TLDs averaged 6.4 mrem per standard month.
This result is slightly greater than 1987 results, and is due to the increased results noted in the third quarter.
TLDs located off-site at a distance of 4 to 5 miles from the site in each of the land based meteorological sectors averaged 5.0 mrem during 1985.
During 1986 1987 off-site sector TLDs averaged 6.0 mrem and 5.2 mrem per standard month.
The 1986 results demonstrated an increase for this group of TLDs.
Results for 1988 for the group averaged 5.3 mrem per standard month.
This is fairly consistent with previous years results.
Again, 1988 third quarter TLD's, showed a slight increases.
Special interest TLDs are located at areas of high population
- density, such as major work sites, communities,
- schools, etc.
and at residences near the site (critical receptor areas).
This group of TLDs averaged 5.3 mrem per standard month during 1985.
During
- 1986, this same group of TLDs averaged 6.1 mrem.
The 1987 results showed a
decrease when compared to the 1985 and 1986 results and averaged 5.1 mrem per standard month.
1988 results averaged 5.3 mrem per standard month.
This result is consistent with previous years results.
Third quarter 1988 TLD's showed an increase.
-30
L A N
(Cont'd)
B. 4.
v t
Table 12 (Cont'd)
The final group of TLDs required by the Technical Specifications is the control'roup.
This group utilizes two TLD locations positioned well beyond the site.
Results from 1985 for the control group averaged 5.4 mrem per standard month.
During
- 1986, this same group of TLDs averaged 6.3 mrem per standard month.
A marked increase was noted in the second quarter of 1986.
The increase may have been a result of the Chernobyl Nuclear Plant accident.
Results for 1987 averaged 5.2 mrem" per standard month.
Results for 1988 averaged 5.4 mrem per standard month and showed levels typical of 1985 and 1987.
Slight increases were noted in third quarter results.
During
- 1988, all environmental TLD groups required by the Technical Specifications were'onsistent with results observed in 1987.
However, all Technical Specification TLD's showed a
slight increase during the third quarter of 1988.
This increase was noted for other non-technical specification TLD's, as well as all control TLD's.
The only TLD's in which the third quarter increase was not noted were the TLD's located along the north fence near the generating facilities.
These TLD's reflect the activities conducted at the radwaste facilities and the operating modes of the generating facilities.
Due to the variability of the activities conducted during
- 1988, the third quarter increases noted for other groups of TLD's were masked by already increased TLD results.
Third quarter 1988 increases in all groups of TLD's ranged'rom 22-40K when
'ompared to the second quarter.
No other environmental parameter or pathway measured revealed any increase or abnormalities during the period.
Additionally, control TLD's located beyond the influence of the plant were similarly affected.
These two facts exclude the possibility of an undetected radiological occurrence from the, facilities.
Subsequent investigation into the methodology employed by the contractor reading the TLD's revealed that the methodology used in subtracting the TLD transit dose from the gross readings resulted in data that was slightly biased in a
conservative manner.
Action was initiated to.preclude such an occurrence in the future.
Tables 35 and 36 show the historical environmental sample data for environmental TLD's.
- Overall, environmental TLD results for 1988 showed no significant impact from
~ direct radiation measured outside the site boundary.
-31
(Cont'd)
B.
5 Kiik-Tables 13 and 14 Milk samples were collected from a
total of six indicator locations (within 10 miles of the site) and one control location (beyond 10 miles from the site) during
. 1988.
The Technical Specifications require that three locations be sampled for milk within 5.0 miles of the site.
During 1988, there were no milk sample locations within 5.0 miles'f the site.
The locations that were sampled during 1988 are located from 5.5 to 9.5 miles from the site.
The only sample location required by the Technical Specifications during 1988 was the control location which was located 17.0 miles to the southwest of the site (location 865).
Sample location descriptions for all milk sample locations utilized during 1988 are listed below.
t' m 't D'
m t
m' 16 50 55 60 4
65 (Control)
ESE S
E E
E ESE SW (107')
(190 )
( 93')
( 95')
( 90
)
(113')
(220
)
5.5 5.9 8.2 9.0 9.5 7.8 17.0 During
- 1988, milk samples were collected at each of the six indicator locations and the control location in the first half
" and the.second half of each month.
Samples were collected during the months of April through December 1988.
Since I-131 was not detected during November and December of
- 1987, no additional samples were collected in January through March of 1988.
For each
- sample, analyses were performed for gamma emitters (analysis by GeLi detector) and for I-131 using a resin extraction.
Sample analysis results for gamma emitters are found on Table 13 and for I-131 on Table 14.
Gamma spectral analyses of the bimonthly samples showed K-40, Ra-226 and AcTh-228 to be the only naturally occurring radionuclides detected in the milk samples collected during 1988.
K-40 was detected in every sample analyzed and ranged in concentration from 513 pCi/liter to 1,730 pCi/liter at the indicator locations and 1,360 pCi/liter to 1,710 pCi/liter at the control location.
Ra-226 ranged from 71 to 258 pCi/liter at the indicator locations and 144 to 231 pCi/liter at the control location.
Ra-226 occurred intermittently in milk samples.
AcTh-228 was found on three occasions for milk samples collected from the indicator locations.
Detectable levels ranged from 6.7 to 26.7 pCi/liter.
AcTh-228 was not detected in the control samples.
K-40, Ra-226 and AcTh-228 are naturally occurring radionuclides and are found in many of the environmental media sampled.
-32
L (Cont'd)
B.
5 QJk-Tables 13 and 14 (Cont'd)
Cs-137 was detected once in the 1988 milk samples.
The concentration detected was 10.0 pCi/liter and was obtained from location N16 on April 18, 1988.
Cs-137 was not detected in any of the other bimonthly samples from this location, nor was it detected in any of the other milk samples from other sample locations.
Location 816 is 5.9 miles from the site in a
southerly (190') direction.
A concentration of 10.0 pCi/liter is not significant and is slightly above the detectable range of the analytical instrumentation.
The source of the detected Cs-137 is thought to be from silage harvested from 1987 or possibly 1986.
Questionnaires, relative to monthly pasturing and supplementary diets of commercial grain and local silage, showed that milk animals had a diet of approximately 90K silage and 10K grain during the month of April 1988 at location 816.
Pasture grass was not part of the milk animal diet at location 816 during April 1988.
Monthly questionnaires showed that this was the case at the other sample locations except for location 855 where pasture grass accounted for approximately 5X of
, the milk animal's diet.
The monthly questionnaire also noted that a
portion of the silage given to milk animals during April 1988 may have been harvested during 1986.
Silage harvested locally during 1986 contained traces of Cs-137 from the April 1986 Chernobyl Nuclear Plant accident.
It is thought that the detected quantity of Cs-137 resulted from stored silage because milk animals were not on pasture during April 1988 and because the monthly questionnaire showed that silage originating from 1986 may have been fed to milk animals during April 1988.
A similar occurrence was noted in 1987.
Cs-137 was detected on May 4, 1987 at levels of 5.5 pCi/liter and 8.1 pCi/liter.
Monthly questionnaires from April 22 and May 4,
1987 showed that milk animals were not on pasture during April through May 4 and that silage constituted a major portion of the milk animal diet.
It was also noted during
- 1987, that Cs'-137 was detected in milk samples at other nuclear sites on the East Coast during the first half of 1987.
Cs-137 in these instances was attributable to silage containing trace amounts of Cs-137 from the 1986 Chernobyl Nuclear Plant accident.
No other radionuclides were detected in milk samples using gamma spectral analysis.
Milk samples were collected and analyzed twice per month for I-131.
I-131 was not detected during 1988 in any of the indicator or control samples.
All 1988 I-131 milk sample results are reported as the lower limit of detection (LLD).
The LLD results for 1988 milk samples ranged from <0.1 pCi/liter to
<0.5 pCi/liter.
-33
E L
TA (Cont'd)
B.
5 HAJJ(-Tables 13 and 14 (Cont'd)
Evaluation of site historical milk data shows that Cs-137 has been detected in environmental milk samples at both indicator (within 10 miles) and control locations (beyond 10 miles).
Mean Cs-137 concentrations for 1976 1981 remained fairly consistent and ranged from 8.1 (1980) to 17.1 pCi/liter (1977) at the indicator locations.
The 1982 indicator mean was 5.7 pCi/liter which showed a decrease when compared to 1976 1981.
Cs-137 in milk during 1983 yielded a
mean of 7.2 pCi/liter which was slightly greater than the 1982 mean but was less than the 1976 1981 mean range.
During 1983,
- however, Cs-137 was detected in only 3 of the 66 samples, while in 1982, Cs-137 was detected in 10 of the 54 samples analyzed.
Cs-137 was not detected during 1984 or 1985 in indicator milk samples.
Results from 1986 showed a
mean Cs-137 concentration of 8.6 pCi/liter at the indicator locations.
Cs-137 in 1986 milk samples was a result of the 1986 Chernobyl Nuclear Plant accident.
During
- 1987, Cs-137 was found in two indicator samples only at a
mean concentration of 6.8 pCi/liter and was also a result of the Chernobyl accident.
The 1988 results showed Cs-137 was detected only once at a concentration of 10.0 pCi/liter.
At the control location, Cs-137 has remained fairly consistent for all years from 1978 1982 except for 1979 and 1982.
For these
- years, this radionuclide was not detected.
Control samples were not obtained prior to 1978.
Cs-137 ranged from 3.9 5.8 pCi/liter during 1978 1981.
Cs-137 was not detected at the control location during
- 1982, 1983,
- 1984, or 1985.
The absence of Cs-137 during 1982 through 1985 may be a result of a two to five year time interval since the last weapons test.
Results from 1986 showed a
mean Cs-137 c'oncentration of 8.4 pCi/liter at the control location.
The positive Cs-137 results during 1986 were a
result of the Chernobyl Nuclear Plant accident.
Cs-137 was not detected during 1987 or 1988 at the control location.
Cs-137 in milk samples is, for the most
- part, a
result of previous weapons testing and more
- recently, the Chernobyl accident.
The continuing reduction of Cs-137 levels is a result of nuclear decay and ecological cycling.
An evaluation of historical data for I-131 in milk samples shows that annual mean results ranged from 0.19 pCi/liter to 6.88 pCi/liter at the indicator locations during 1976 1978.
I-131 during these years is a result of intermittent weapons testing.
During 1979 1985, I-131 in milk samples at the indicator locations was not detected except during 1980.
The mean result during 1980 was 3.8 pCi/liter and was a result of the 1980 Chinese Weapons Test.
Results from 1986 showed that I-131 was detected at a mean concentration of 5.2 pCi/liter as a result of the Chernobyl accident.
I-131 was not detected during 1987 or 1988 in milk samples.
-34
(Cont'd)
B.
5 k-Tables 13 and 14 (Cont'd)
Historical data for I-131 from the control location showed that I-131 was detected during 1980 at a.mean concentration of 1.4 pCi/liter.
There was no detectable I-131 during the period of 1978 1985 with the exception of 1980.
During 1986, I-131 from the control location showed a
mean concentration of 13.6 pCi/liter as a result of the Chernobyl accident.
I-131 was not detected during 1987 or 1988 at the control location.
Tables 37 and 38 show the historical environmental sample data for milk.
h The impact as a result of Cs-137 in 1988 milk samples can be assessed by calculating conservative doses to man from the consumption of milk with detectable quantities of Cs-137.
In order to calculate
- doses, several assumptions are made.
These include:
a Cs-137 concentration of 10.0 pCi/liter'or the indicator sample
- result, a
consumption rate of 330 liters (87 gallons) per year for an infant (the maximum exposed individual),an applicable time period of 1
month of the year (Cs-137 was not detected consistently throughout the year) and no radiological decay.
Dose factors are taken from Table E-14 of Regulatory Guide 1.109.
The infant whole body dose is calculated as 0.012 mrem.
The infant critical organ is the, liver.
The dose to the liver is 0.168 mrem.
These doses are from consuming milk from the indicator location.
The maximum organ dose is the liver of an infant.
The maximum whole body
- dose, however, is to an adult.
Using the same criteria as
- above, except for a
new consumption rate of 310 liters (80 gallons) per year for an adult, th'e maximum exposed organ (liver) dose to an adult is 0.028 mrem for indicator samples.
The adult whole body dose is 0.018 mrem.
The adult liver dose is less than the infant dose.
The adult whole body dose is greater than the infant whole body dose.
For the purpose of illustration, the significance of the above doses can be brought into perspective by comparison to background doses due to the cosmic radiation with changes in altitdde.
The whole body dose to an adult is 0.018 mrem as a
result of consuming milk from the indicator sample location with detectable Cs-137 during 1988.
A,dose of 0.018 mrem is equal to the increase in dose as a result of residing at a location that is 100 meter (328 feet) higher in altitude for 3.3 days.
The increase in dose is for a sea level elevation.
Because the dose due to cosmic radiation is greater at higher altitudes, a whole body dose from milk consumption of 0.018 mrem is equal to residing in the city of
- Denver, Colorado for only 3.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (NCRP Report No. 45).
-35
(Cont'd)
B. 5.
~-Tables 13 and 14 (Cont'd)
An additional comparison can be made to naturally occurring K-40.
K-40 has been noted in almost all environmental samples at significant levels.
A 70 kilogram adult has an equivalent weight of approximately 154 pounds and contains approximately 0.1 microcuries'f K-40 as a result of normal life functions (inhalation, consumption, etc.).
The dose to the bone tissue is about 20 mrem per year as a result of internally deposited K-40 (Eisenbud).
For comparison
- purposes, an adult bone dose can be calculated that results from the consumption of milk with the 1988 concentration of Cs-137.
Using the same criteria used for calculating
,the preceding
- doses, the adult bone dose is 0.020 mrem per year.
This calculated dose is small and is only 0.001 of the annual bone dose received from naturally occurring K-40.
The whole body doses calculated from the indicator samples are small.
The concentration of Cs-137 in milk detected during 1988 is well below criteria utilized by the Federal Public Health 5ervice and Food and Drug Administration to protect the health and safety of the general population (U. S.
Department of Health and Services).
The guide used by these federal health agencies for Cs-137 in milk is 240,000 pCi/liter.
The maximum Cs-137 concentration observed during the 1988 sampling program was 10.0 pCi/liter.
The observed Cs-1'37 concentration is well below the protective action criteria.
Iodine-1'31 was not detected in the bi-monthly milk samples analyzed for 1988.
Therefore, no doses to man have been calculated because of the lack of detectable I-131.
B.
6 Tables 15 and 16 In accordance with the Technical Specifications, a
land use census was conducted during 1988 to identify within a distance of five miles the location of all milk animals (cows and goats) and the location of the nearest residence in each of the sixteen 22.5 degree meteorological sectors.
The milk animal census was actually conducted out to a distance of ten miles in order to provide a more comprehensive census.
The milk animal census is an estimation of the number of cows and goats within an approximate ten mile radius of the Nine Mile Point Site.
A census is initiated once per year in the spring.
The census is conducted by sending questionnaires to previous milk
. animal owners and also by road surveys to locate any possible new owners.
In the event questionnaires are not
- answered, then the owners are contacted by telephone or in person.
The local agricultural agency is also contacted.
-36
L A I N (Cont'd) 6 n
Tables 15 and 16 (Cont'd)
The number of milk animals located
~w't a the ten mile radius of the site was estimated to be 1193 cows and 15 goats for the '1988 census.
The number of cows decreased by 52 and the number of goats decreased by 15 with respect to the 1987 census.
No new milk animal locations were noted as a result of the census.
Therefore, there was no change in the milk sampling locations during 1988.
Most of the goats found on the census were milking goats.
- However, any milk produced was utilized by the owners and was not available for the sampling program.
'The results of the milk animal cen'sus are found on Table 15.
Milk animal locations are shown on Figure 4.
A residence census was conducted during 1988 to identify the nearest residence in each of the sixteen 22.5 degree meteorological sectors within a distance of fiv'e miles from the site.
At this distance, some of the meteorological sectors are over water.
These sectors include:
N; NNE, NE,
- ENE, W,
- WNW, NW, and NNW.
There are no residences in these sectors.
.The results of'he 1988 residence census showing the applicable sectors and degrees and distance of each of the nearest residences are found on Table 16.
The nearest residences are shown in Figure 3.
B.
7 Food product 'amples.collected during 1988 were comprised of garden vegetables, fruit and other types of vegetation.
Samples were collected from five indicator locations and one control location.
The indicator locations were represented by nearby gardens in areas of highest D/Q (deposition factor) 'values based on historical meteorology and all site release points at operating facilities.
The control location was represented by a garden location 9-20 miles distant in a least prevalent wind direction.
Garden vegetables were comprised of
- cabbage, beet
- greens, squash
- leaves, lettuce, collard greens and swiss chard which are all considered broadleaf vegetables.
Other broadleaf vegetation consisted of pumpkin
- leaves, bean
- leaves, pepper leaves and cucumber leaves.
In addition, non broadleaf fruits or vegetables were collected.
Non broadleaf fruits or vegetables collected in 1988 consisted of tomatoes.
At the control location, one sample of each of the same or of a similar type of fruit, vegetable or vegetation was collected.
- Fruits, vegetables and vegetation were collected in the late summer harvest season.
K-40 was detected in all broadleaf and non-broadleaf vegetables/vegetation.
Broadleaf vegetables/vegetation (Swiss
- chard, beet
- greens, cabbage,
- lettuce, pumpkin
- leaves, bean
- leaves, cucumber
- leaves, squash
- leaves, pepper leaves and
-37
(Cont'd)
B.
7 collard, greens) showed concentrations of K-40 ranging from 1.39 pCi/g to 7.37 pCi/g (wet).
Non-broadleaf fruits (tomatoes) showed concentrations of K-40 ranging from 2.03 pCi/g to 2.76
" pCi/g (wet).
Be-7 was also found in broadleaf vegetation samples'his radionuclide ranged from 0.09 pCi/g to 3'4 pCi/g (wet).
Non-broadleaf vegetation (tomatoes) showed no detectable.
Be-7.
Ra-226 was detected at concentrations that ranged from 0.15 to 0.47 pCi/g (wet) for all sample types at the indicator and control locations.
AcTh-228 was
- also, detected intermittently for all sample types at concentrations that ranged from 0.012 to 0.064 pCi/g'wet) for both indicator and control locations.
K-40, Be-7, Ra-226 and AcTh-228 are naturally occurring radionuclides.
Cs-137 was detected in one broadleaf sample (squash leaves) from the indicator locations.
The 'detected quantity was at the limit of detection and was 0.008 pCi/g (wet).
LLD values for all broadleaf samples ranged from 0.008 pCi/g to 0.017 pCi/g (wet)..
The presence of Cs-137 was not detected in any of the other broadleaf or non-broadleaf samples.
It is likely that the quantity of Cs-137 found is a result of uptake by the squash plant or from deposition.
The ultimate source of Cs-137 is from weapons testing,. operations at the site or both.
Cs-137.has been detected in soil'amples from areas at the site and at areas well beyond the site as a resul't of past weapons testing.
Cs-137 was not detected at the control location nor was it detected at other indicator locations near the site.
No other radionuclides were detected in the 1988, samples of fruits, vegetables, or other vegetation.
Review of past environmental data indicates that Cs-137 has been detected intermittently during the years of 1976 1987 at the indicator locations and during the years of 1980 1987 at the control locations (control samples were not obtained prior to 1980).
Review of indicator sample results from 1976 1987 showed that Cs-137 was not detected during 1976 1978 and 1981 1984 or 1986 1987.
During 1979 and
- 1980, Cs-137 in fruits and/or vegetables showed annual mean concentrations of 0.004 and 0.036 pCi/g (wet) respectively.
Cs-137 was found at an indicator location during 1985 at a concentration of 0.047 pCi/g (wet).
The detectable concentration was 0.016 pCi/g (wet).
During 1988, Cs-137 was found at a concentration of 0.008 pCi/g (wet).
Control sample results during 1980-1987 showed Cs-137 detected only during 1980 at a
concentration of 0.02 pCi/g (wet).
Cs-137 was not detected at the control location during 1988.
Tables 39 and 40 show historical environmental sample data for food products.,
-38
AL AT L D (Cont'd)
B.
7
-Table 17 (Cont'd)
The impact of detectable Cs-137 in food product 'samples can be evaluated by calculating a
dose to the maximum exposed individual as a
result of consumption.
Using standard methodology from NRC Regulatory Guide 1.109, the maximum exposed organ is the bone of a'hild.
The maximum whole body dose would be to an adult.
The Cs-.137 concentration is 0.008 pCi/g (wet) and is conservatively assumed to be a result of operations at the site and is assumed to remain consistent throughout the year.
The consumption rate is assumed to be a
maximum consumption rate of 26 kg per year for a child.
The calculated doses are 0.07 mrem per year to a child's bone tissue (maximum organ dose) and 0.01 mrem per year to the whole body.
The maximum whole body dose,
- however, occurs to the adult..
Assuming a Regulatory Guide 1.109 maximum consumption rate of 64 kg per year for an adult, the maximum organ dose is 0.06 mrem to the liver and 0.04 mrem to the whole body.
A maximum child organ dose of 0.07 mrem per year and adult whole body dose of 0.04 mrem per year are small when compared to doses from non man-made sources.
A maximum organ dose of 0.07 mrem is small when compared to a dose of 20 mrem per year to the gonads and other soft tissues of an adult from, naturally occurring K-40.
A maximum whole body dose of 0.04 mrem pe'r year can be compared to the increase in dose from increasing altitude.. As one proceeds from one location to another location higher in
- altitude, the dose rate will increase slightly as a result of solar radiation.
A whole body dose of 0.04 'mrem per year is equivalent to proceeding from one area to another of 100 meters (328 feet) higher in altitude and remaining at that altitude for
= 7.3 days.
An occasion, such as moving to a location 100 meters (328 feet) higher in'ltitude, is a
common occurrence.
Any dose that may be received as a result of such an occurrence is considered small and insignificant.
B. 8
-Table 18 Section 3.6.21 and Section 3.12.3 of the Technical Specifications for the Nine Mile Point Nuclear Station Unit 1
and Unit 2, respectively, require that a
summary of the results obtained as part of an Interlaboratory Comparison Program be included in the Annual Radiological Environmental Operating Report.
Presently, the only NRC approved Interlaboratory Comparison Program is the USEPA Cross Check Program.
Table 18 shows the results of the EPA's reference results and the licensee's results.
Some of the EPA reference samples have been analyzed by the site.
Other EPA reference samples have been analyzed by a vendor who normally analyzes those types of sample
-39
(Cont'd)
B.
8 t
t
-Table 18 (Cont'd) media for the site.
Participation in the EPA Cross Check Program includes sample media for which environmental samples are routinely collected, as required by Table 3.6.20 1
and Table 3.12.1 1 of the Technical Specifications and for which intercomparison samples are available from the EPA.
Where many samples are available from the
- EPA, a
QC sample to program sample ratio of, ten percent is utilized, where applicable.
B.
9 v
t Table 19 Table 19 contains the locations of the environmental samples presented in the data tables (Section E).
The locations are given in degrees and distance from the Nine Mile Point Nuclear Station Unit 2
reactor centerline.
Table 19 also gives the figure (map) number as well as the map designation for each sample location by sample medium type.
The requirement for Table 19 is found in section 6.9.1.d of the Technical Specifications for the Nine Mile Point Nuclear Station Unit 1
and Section 6.9.1.7 of the Technical Specifications for the Nine Mile Point Nuclear Station Unit 2.
B.
10 v'gmg}gzy-Table 20 t
t Table 20 contains'-
a
. summary of basic statistics for environmentalsample media as required by the Technical Specifications.
Table 20 is in the format presented on Table 3
of the NRC Branch Technical Position (Revision 1 dated November 1979) to.
NRC Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants".
The table is presented to meet the requirements of section 6.9.l.d and section 6.9.1.7 of the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit 2 respectively.
B.
11
~ t
~
t Tables 21 40 Tables 21 40 show historical environmental sample data for critical radionuclides or radionuclides
~ routinely detected in environmental sample media.
Data show the minimum, maximum, and mean for each year evaluated.
The data only consider detectable quantities and do not consider lower limit of detection quantities.
Data on Tables 21 40 were obtained from previous Annual Radiological Environmental Operating Report tables.
C.
Qaacluaian The Radiological Environmental Monitoring Program (REMP) was
. established to detect and evaluate any possible impact to the environment surrounding the Nine Mile Point area resulting from operations at the site.
-40
(Cont'd)
Samples representing food sources consumed at higher trophic
- levels, such as fish and milk, were reviewed closely to evaluate any impact,to the general environment or to man.
In addition, the data was reviewed for any possible historical trophic level bioaccumulation trends.
Little or no impact could be determined resulting from radionuclide deposition considering all sources (natural, weapons
- testing, etc..).
In regards to doses as a
result of man-made radionuclides',
a significant portion of the small doses received by a member of the public was from past nuclear weapons testing.
Doses as a
result of naturally occurring radionuclides, such as K-40, contributed a
major portion of the total annual dose to members of the public.
Any possible impact as a result of site operations is extremely minimal when compared to the impact from natural background levels or weapons testing.
It has been demonstrated that almost all environmental samples contain traces of
~ radionuclides which are a result of weapons testing or naturally occurring sources (primordial and/or cosmic related).
Whole body doses to man as a result of natural sources (naturally occurring radionucli:des in the soil and lower atmosphere) in Oswego County account for approximately 66 mrem per year as demonstrated by control environmental TLD's.
Possible doses due to site operations are a minute fraction of this particular natural exposure.
During
- 1988, the presence of several fission product radionuclides was noted in several environmental sample media.
These media included air, fish, milk, and food product (garden vegetables).
The source of the fission product radionuclides is, for 'the most part, past weapons testing and the Chernobyl Nuclear Plant accident.
One sample medium, air radioiodine (one weekly sample) showed activity that was most likely a result of operations at the site.
The impact, expressed as a dose to man, is minimal and is insignificant when compared to the natural background dose.
In actuality, the impact from this sample medium is not measurable because samples were obtained from an on-site location and no activity was measured at
- nearby, critical off-site locations.
Therefore, as determined by review of the data presented
- herein, no impact due to operations at the Nine Mile Point Nuclear Station was detected that would effect the health and safety of the public.
-41
D.
1.
U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", March 1976 (Revision 0).
2.
U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I", October 1977 (Revision 1).
3.
U.S.
Nuclear Regulatory Commission Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",
- December, 1975.
4.
U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program",
Revision 1, November 1979.
5.
National Council on Radiation Protection and Measurements (NCRP),
NCRP Report No. 50, 1976.
6.
National Council on Radiation Protection and Measurements (NCRP),
g;~t t
t
't t t NCRP Report No. 45, 1975.
7.. National Councilt No. 52, 1977.
on Radiation v
t t Protection and Measurements (NCRP),
t NCRP Report 8.
National Council on g
Report No. 56,. 1977.
Radiation Protection and Measurements (NCRP),
9 NCRP t
ICRP Publication 29, 1979.
- 10. Eichholz, G.
EaXiXao w
, First Edition, Ann Arbor Science Publishers, Inc., Ann Arbor, Michigan, 1976.
- 11. Eisenbud,
- Merrill, Press, New York, NY 1973.
Second
- Edition, Academic 12.
- Thomas, C.W.
etc al.> Ea~agJ'j~
September 26, 1976.
(BNWL-2164)
- Battelle, Pacific Laboratories, U.S.
ERDA, 1979.
QQQQ Northwest
- 13. Pochin, Edward E.,
~ngLt t
t Nuclear Energy Organization for Economic Co-Operation and Development, 1976.
- Agency,
-42
D.
G (Cont'd) 14 Glasstone, Samuel and
- Jordan, Walter H.,
w n
t
- EUZi,
, First Edition, American Nuclear Society, La Grange Park, Ill., 1980.
ilhU~
HIM~.
Bureau of Radiological
- Health, Rockville, Maryland 20852.
'anuary 1970.
- 16. U.S.
Department of Health and Human Services.
Zzgyazgsiagg~gsMMagggaa
~t National Center for Devices and Radiological Health, Rockville, Maryland 20857.
August 1983.
-43
'l l 0't V
~
p 0 'W VPYV $
0 h
~ I $
~
t
~ I 'g f 4 "I
('Wt W
~
\\
E.
-44
L L
A.
1.
Shoreline Sediment 2.
Fish GSA GSA 2/year 2/year 1 Indicator (2) 2 Indicator (3),
1 Control 3.
Surface Mater GSA H-3 M. Comp.
Qtr.
Comp.
1 Indicator (4),
1 Control 1 Indicator (4),
1 Control NOTES:
(2)
(3)
(4)
Sampling and analysis program as required by the Technical Specifications.
Indicator samples collected in the vicinity of the site; control samples collected at a
distance of at least five miles from the site.
Indicator sample from an area of potential recreational value.
Indicator samples from an area near the vicinity of a site discharge point.. Control samples of the same species or of species of similar feeding habits.
Indicator sample from the J.A. FitzPatrick inlet canal.
-45
XhlUM G
G B.
l.
Air Particulates GB GSA Weekly M. Composite 4 Indicator, 1 Control 2.
Airborne - I-131 3.
TLD 4.
Milk GSA Gamma Dose I-131 GSA Weekly Quarterly 2/Month 2/Month 4 Indicator, 1 Control (1) 30 Indicator, 2 Control (2) 3 Indicator, 1 Control (3) 5.
Human Food Crops GSA% I-131 (5)
Annually (4)
NOTES:
(2)
(3)
(4)
(5)
Sampling and analysis program as required by the Technical Specifications.
Three indicator samples from near the site boundary in'hree of the highest D/Q meteorological
- sectors, one indicator sample from near a year round community, and one control sample from an area of least prevalent wind direction.
Indicator samples from the site
- boundary, four-five miles from the site, special interest
- areas, and control areas (greater than ten miles from the site).
Three indicator samples from areas within 5.0 miles of the site.
Control sample from an area of least prevalent wind direction.
Six samples total utilizing at least two meteorological sectors in areas of highest D/Q.
One sample of each of the same or similar food product in a least prevalent wind direction.
Gamma spectral analysis to include I-131.
TABLE 3A CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/g (dry) g 2 sigma Sample L t'ollection D t 2
t Langs Beach (Control)*
4-25-88 10-26-88
<0.26 12.2 0.9
<0.040
<0.031
<0.24 10.7 0.7
<0.029
<0.025
<0.037
- 1. 17~0.36 0.52~0. 10
<LLD
<0.030 0.98~0.32
. 0.34~0.08
<LLD Sunset Beach (Off-Site) 4-25-88 10-26-88
<0.51 14.7 1.3
<0.058
<0.050
<0.33 10.4 0.9
<0.036
<0.036
<0.063
<0.050 1.69 0.66 0.84 0.18
<LLD 1.86 0.62 0.59 0.14
<LLD
- Sample ~t required by the Technical Specifications (Optional sample location)
Results in units of activity ~~am dry weight
-47
TABLE 3B CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/kg (dry) p 2 sigma Sample Langs Beach (Control)*
Sunset Beach (Off-Site)
Collection 4-25-88 10-26-88 4-25-88 10-26-88 B
<260 12200<<911
<241 10700 722
<507 14700~1330
<331 10400 936
<40
<29
<58
<36
-1 4
<31
<25
<50
<36
<37
<30
<63
<50 1170M355 981~322 1690~658 1860~622 t r 524 105
<LLD 340+79
<LLD 837~184
<LLD 587~137
<LLD
- Sample not required by the Technical Specifications
TABLE 4A CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/g (wet) + 2 sigma GAMMA EMITTERS 4
5/03/88 5/03/88 5/04/88 5/05/88 5/04/88 Lake Trout Brown Trout Chinook Salmon White Perch Rainbow Smelt
<0.050
<0.045
<0.059
<0.072
<0.176
~<0.023
<0. 024
<0. 025
<0.038
.<0.077
- 2. 75+0. 37 3.70g0.45 5.3120.47 5.15~0.60 4.43+1.13
<0.023
<0.022
<0.020
<0.030
<0.088
<0.020
<0.022
<0.026
<0.035
<0.102
<0.020
<0.023
<0.023
<0.030
<0.078 0.023.015 0.030Z0.014 0.053Z0.018 0.028~0.016
<0.104
<0.044
<0.058
<0.047
<0.063
<0.153 0.43Z0.17
<LLD 0.45g0.20
<LLD 0.42Z018
<LLD 0.61'.25
<LLD
<l.50-
<I,LD 10/07/88 10/07/88 10/07/88 10/07/88 Walleye
<0.056 Lake Trout
<0.038 Smallmouth Bass
<0.055 White Sucker
<0.114
<0. 024
<0.021
<0.031
<0.038 4.60~0.51 4.5020.42 4.0020.52 4.80~0.67
<0.023
<0.022
<0.027
<0.033
<0.024
<0.018
<0.033
<0.034
<0.028
<0.022
<0.027
<0.040
<0.028 0.031+0.015
<0.031
<0.037
<0.049
<0.046
<0.065
<0.075
- 0. 72+0. 24
<ILD 0.42+0.18
<LLD
<0.56
<LLD 0.76g0.37
<LLD 5/03/88 5/05/88 5/04/88 5/03/88 Lake Trout Brown Trout Chinook Salmon White Perch
<0.074
<0.054
<0.051
<0.101
<0.028
<0.021
<0.026
<0.038 3.74~0.50 2.64~.40 4.09Z0.44 3.31.65
<0.023
<0.021
<0.021
<0.042
<0.022
<0.025
<0.024
,<0.022
<0.020
<0.021
<0.039
<0.036 0.027+0.014 0.023+0.014-0.030g0.013
<0-048
<0.048
<0.046
<0.041
<0.091
<0.50
<LLD 0.17'.14
<LLD 0.43g0.24
<LLD 0.43g0.26
<LLD 9/30/88 Walleye
<0.041 10/07/88 Lake Trout
<0.043 9/30/88 Smallmouth Bass
<0.058 9/30/88 White Sucker
<0.074
<0.023
<0.024
<0.026
<0.032 4.30+0.38 4.51+0.43 4.24+0.49 4.0820.53
<0.019
<0.019
<0.030
<0.027
<0.015
<0.021
<0.023
<0.034
<0.019
<0.023
<0.026
<0.027
- 0. 020'. 009
- 0. 050~. 021
<0.033
<0.032
<0.041
<0.053
<0.052
<0.071 0.38~0.19
<LLD 0.43Z0.21
<LLD 0.43~0.25 (1)
<0.59
<LLD (1) AcTh-.228 found at a concentration of 0.086+0.044 pCi/g (wet).
All other radionuclides were
<LLD.
-49
TABLE 4A (Continued)
CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/g (wet) g 2 sigma GAMMA EMITTERS 4
5/03/88 5/03/88 5/05/88 5/03/88 5/03/88 5/03/88 Lake Trout Brown Trout Chinook Salmon White Perch Rainbow Smelt White Sucker
<0.059
<0.082
<0.046
<0.090
<0.106
<0.075
<0.024
<0.026
<0.021
<0.039
<0.040
<0.034
- 2. 73.40
- 2. 78.48 4.54+0.41 4.30~.65 4.21.69 4.92~.58
<0.023.
<0.029
<0.021
<0.042
<0.046
<0.030
<0.029
<0.027
<0.020
<0.045
<0.039
<0.026
<0.019
<0.027
<0.021
<0.035
<0.046
<0.031
<0.026 0.022+0.012 0.031+0.012 0.030g0.019
<0.048
<0.028
<0.044
<0.058
<0.049
<0.073
<0.084
<0.076 0.40+0.18
<0.042 0.3420.20 1.02+0.40 0.68+0.36 1.03Z0.51
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 10/07/88 Walleye
<0.046 10/07/88 Lake Trout
<0.043 10/07/88 Smallmouth Bass
<0.057 9/27/88 White Sucker
<0.058
<0.022
<0.021
<0.026
<0.024 3.7920.45 4.27.40 4.45g0.47 4.22.46
<0.024
<0.022
<0.026
<0.022
<0.027
<0.022
<0.026
<0.024
<0.023
<0.022
<0.019
<0.024
<0.028
<0.061 0.07420.026
<0.049 0.030~.017 '0.051
<0.027
<0.047
<0. 46
<LLD 0.45+0.21
<LLD 0.45+0.19
<LLD 0.67+0.22
<LLD
TABLE 4B D t CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/kg (wet) + 2 sigma GAMMA EMITTERS 4
4 t
r 5/03/88 5/03/88 5/04/88 5/05/88 5/04/88 Lake Trout Brown Trout Chinook Salmon White Perch Rainbow Smelt
<50
<23
<45
<24
<59
<25
<72
<38
<176
<77 2750+373 3700g453 5310Z468 5150~601 4430+1130
<23
<22
<20
<30
<88
<20
<22
<26
<35
<102
<20
<23
<23
<30
<78 23+15 30+14 53+18 28+16
<104
<44
<58
<47
<63
<153 429p167 4502203 420~182 610Z254
<1500
<LLD
<LLD
<LLD
<LLD
<LLD 10/07/88 10/07/88 10/07/88 10/07/88 Walleye
<56
<24 Lake Trout
<38
<21 Smallmouth Bass
<55
<31 White Sucker
<114
<38 4600+506
<23
<24
<28 4500+420
<22
<18
<22 40002525
<27
<33
<27 48002671
<33
<34
<40
<28 31+15
<31
<37
<49
<46
<65
<75 724p244 421Z184
<563 755Z370
<LLD
<LLD
<LLD
<LLD 5/03/88 Lake Trout
<74
<28 5/05/88 Brown Trout
<54
<21 5/04/88 Chinook Salmon
<51
<26 5/03/88 White Perch
<101
<38 3740~503 2640+401 4090~35 3310g646
<23
<22
<21
<24
<21
<20
<42
<39
<25
<22
<21
<36 27+14 23+14 30+13
<48
<48
<46
<41
<91
<500
<LLD 168p140
<LLD 429Z244
<LLD 434~261
<LLD 9/30/88 Walleye
<41
<23 10/07/88 Lake Trout
<43
<24 9/30/88 Smallmouth Bass
<58
<26 9/30/88 White Sucker
<74
<32 4300+380 4510+427 4240+491 4080+532
<19
<15
<19
<21
<30
<23
<27
<34
<19
<23
<26
<27 20+9 50+21
<33
<32
<41
<53
<52
<71 377+190 433p213 4332248
<592
<LLD
<LLD
. (1)
<LLD (1) AcTh-228 found at a concentration of 86+44 pCi/kg (wet).
All other radionuclides were
<LLD.
TABLE 4B (Continued)
CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCi/kg (wet) + 2 sigma GAMMA EMITTERS 4
4
-22 5/03/88 5/03/88 5/05/88 5/03/88 5/03/88 5/03/88 Lake Trout Brown Trout
,Chinook Salmon White Perch Rainbow Smelt White Sucker
<59
<24
<82
<26
<46
<21
<90
<39
<106
<40
<75
<34 27302395 2780+484 4540~11 43002653 4210Z694 49202579
<23
<29
<21
<42
<46
<30
<29
<27
<20
<45
<39
<26
<19
<27
<21
<35
<46
<31
<26 22+12 31+12 30+19
<48
<28
<44
<58
<49
<73
<84
<76 397+180
<419 3442198 1020+400 680+3tj4 1030+506 1
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 10/07/88 Walleye
<46
<22 10/07/88 Lake Trout
<43
<21 10/07/88 Smallmouth Bass
<57
<26 9/27/88 White Sucker
<58
<24 3790+449 4270+396 44502472 42202455
<24
<27
<22
<22
<26
<26
<22
~ <24
<23
<22
<19
<24
<28 74+26 30217
<27
<61
<49
<51
<47
<461
<LLD 449Z208
<LLD 452~192
<LLD 671g223
<LLD
TABLE 5 CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter + 2 sigma Location Nuclide January February March April May June OSWEGO CITY K-40 WATER Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 NINE MILE K-40 POINT UNIT I Ra-226 (INLET)
Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 202i51 98256
<4.16
<4.34
<9.7
<5.28
<4.62
<4.66
<9.8
<4.65
<9.7
<12.5
<9.9 224+41 115+54
<2.73
<3.16
<8.5
<4.13
<3.57
<2.84
<7 '
<3.16
<6.53
<9.1
<5 '
78+30
<84
<3.06
<3.15
<8 '
<4.07
<3.16
<2.61
<8.3
<3.06
<6.1
<8.9
<6.8 220+40 65+40
<3.25
<3.50
<8.1
<3.67
<3.09
<3.51
<6.8
<3'7
<6.60
<9.3
<5.8 178235 96+45
<2.94
<2.76
<7.5
<3.93
<3.36
<3.11
<7.2
<2.71
<6 '
<10.1
<7.0 142g42 91g47
<3.95
<4.34
<11.6
<5.65
<5.15
<4.05
<10.6
<4.37
<6.77
<12.5
<9.7
<44
<118
<5.75
<4.61
<13.4
<6.02
<6.22
<4.79
<12.2
<5.78
<10.4
<13.1
<12.8 225+65 114+46
<3.85
<4.06
<8 '
<4.87
<4.18
<4.34
<9.2
<3'2
~ <8 ~ 66
'12.2
<7 '
241240 116Z47
<3'3
<3.29
<7 '
<4.06
<4.27
<3.25
<8.1
<3'3
<6.3
<12. 2
<7.2 129230 95+40
<2.62
<2.79
<8.3
<4.77
<3.51
<3.26
<7 '
<3.11
<6.49
<11.6
<7.6 123g26 94+36
<2 ~ 52
<2.51
<7 3
<3.94
<3.07
<2.64
<7 '
<2.62
<5.6
<12.3
<8.9 138+38 74g35
<3'2
<3.09
<8.0
<4.27
<4.20
<3.05
<8.4
<2.92
<5.97
<14.5
<9.1
>>>> Optional sample location.
Sample ggt required by the Technical Specifications.
-53
TABLE 5 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter Z 2 sigma Location Nuclide January February March April May June K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 FITZPATRICK (INLET)
K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 NINE MILE POINT UNIT 2 (INLET) 70+26 80g35
<3.20
<2.60
<8.4
<3.62
<3.09
<3.37
<8.1
<2.80
<5.76
<10.9
<7.6 83+32 73+33
<2.85
<3.08
<7.6
<3.37
<3.33
<3.03
<6.6
<3.23
<5.44
<0.46
<7.3 75Z39
<105
<4.41
<3.82
<11.2
<5.27
<3+77
<4.47
<10.0
<4.89
<9.97
<9.5
<9.8 207238 102+47
<3.00
<2.82
<7.7
<4.03
<3.17
<3.04
<7 '
<3.34
<5.85
<0.28
<5.6 265g41 84239
<3.32
<3.19
<8.2
<4.53
<3.70
<3.13
<8.2
<3.29
<6.51
<13.5
<6-3
<41
<84
<3'3
<3.56
<9.1
<4.92
<4.22
<3.12
<9.2
<3.24
<6'2
<0.38
<9.6 234+42 76Z39
<3.37
<3.50
<10.0
<4.44
<3.89
<3.33
<7.9
<2.98
<6.48
<12.6
<9.2
<74 87Z48
<4.72
<5.13
<12.8
<5.17
<5'2
<4.79
<11.3
<5.21;.
<8.34
.'<0.33:
<11.7 191g47 92+58
<3.99
<3.71
<9.3
<5.86
<4.45
<4.35
<9.2
<4.47
<8.66
<14.6
<8.8 170+42 86248
<4.19
<4.59
<11.0
<6.12
<4.18
<4.30
<10.5
<4.17
<9.00
<0.32
<9.8 246+38 143+44
<2.55
<2.90
<7.0
<3.46
<2.81
<2.78
<6.8
<2.74
<5.42
<14.5
<7.2 246+54 115+54
<4.21
<4.79
<12.3
<5.99
<4.32
<4.18
<11.1
<4.73
<9.64
<0.50
<9.5 OSWEGO STEAM STATION (CONTROL)
K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 210g40 122g47
<3.08
<3.45
<7.1
<3.19
<3.05
<2.62
<7 '
<3'2
<6 '
<0.30
<7.0
<71 129272
<4.77
<4.19
<11.0
<6.07
<5.31
<4.37
<11.9
<4.79
<11.8
<0.43
<12.1 46g24
<83,
<2. 91
<3.28
<7.8
<4.13
<3.49
<3.24
<8.2
<3.23
<6.3
<0.30
<7.2
<55
<105
<4.09
<3.96
<9.5
<4.76
<4.73
<4.25
<8.3
<5.04
<7.2
<0.35
<8 '
185+35 85g46
<3.42
<3.63
<9.1
<3.81
<3.44
<3.18
<8.1
<2.98
<6.6
<0.30
<7.1 212+40 74g45
<3.37
<3.61
<9.4
<3.95
<3.63
<3.30
<7.8
<3.37
<7.1
<0.48
<5.1
<<<<-Optional sample location.
Sample ggt required by
<<-Sample required by the Technical Specifications.
-54
TABLE 5 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter ~ 2 sigma Location Nuclide July August September October November December K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 OSWEGO CITY WATER NINE MILE K-40 POINT UNIT I Ra-226 (INLET)
Cs-134
<2.68
<2.79
<8.4
<3.95
<3.72
<3'6
<6.5
<2.46
<5.66
<11.7
<6.4 112+35 90g43
<3.85
<3;68
<9.8
<5.16
<4.33
<3.64
<9.4
<4.08
<6.87
<14.1
<9.00 120i36 80249
<3.76
<4.15
<10.5
<5 33
<4.69
<4.75
<10.0
<3.71
<8.17
<14.2
<10.1 233240 144g54
<3.88
<3.76
<9.3
<4.62
<3.80
<3.82
,<8.4
<3.61
<7.48
<14.1
<8.43 267~43 88Z57
<3.24
<3.02
<8.2 4.50
<3.59
<3.58
<6 '
<3.26
<7.18
<12.5
<7 '
244g53 139~57
<4.43
<4.02
<10.0
<5.80
<4.21
<4.18
<9.6
<3.52
<9.09
<13.1
<8.14 198%30 86~45
<2.91
<2.89
<7.7
<3.98
<3.48
<2.91
<6.3
<2.65
<6.12
<11.4
<7.4 50p21 59+28
<2. 64
<2 ~ 75
<6.9
<3.39
<3.41
<2.83
<6.4
<3.04
<5;09
<9.2
<8.53 68~31 89230
<2.45
<2..99
<7.4
<3.42
<2.57
<2'2
<7.2
<3.09
<5.33
<8.8
<6.4 205234 104+45
<2.25
<2.61
<6.6
<3.82
<2.74
<2.52
<5.7
<2. 14
<5.13
<8.9
<6.60 245+30 118+30
<2.28
<2.43
<6.5
<3.38
<2.50
<2.38
<5.8
<2.40
<4.98
<10.1
<6.8 232+29 100230
<2.23
<2.22
<5.9
<3.20
<2.61
<2.20
<5.8
<2.17
<4'9
<10.7
<5.74
>><< Optional sample location.
Sample ggt required by the Technical" Specifications.
-55
TABLE 5 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN SURFACE WATER SAMPLES Results in units of pCi/liter ~ 2 sigma Location Nuclide July August September October November December K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 K-40 Ra-226 Cs-134 Cs'-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 FITZPATRICK (INLET)
Ba/La-140 NINE MILE POINT UNIT 2 (INLET) 218237 73i35
<2.86
<2.90
<6 '
<3+52
<3.19
<2.76
<6.0
<.2. 85
<5.86
<11.6
<6.5 60+25 82g44
<2.84
<2.91
<8.1
<3.63
<3.01
<3.06
<6 '
<3.60
<5'7
<0.35
<6.8 199+35 105p57
<3.28
<3.50
<9.1
<4.07
<3.40
<3.08
<7.4
<3.15
<6.78
<12.1
<7.0 130g47 78+47
<4.67
<5.21
<10.6
<6.73
<4.86
<4.50
<10.1
<3.74
<9.45
<0.28
<10.7 155+54 102257
<4.66
<4.77
<12.9
<6.50
<5.19
<4.45
<12.7
<5.83
<8.90
<14.1
<14.3 146~52 95+64
<5.36
<5.31
<12.2
<5.80
<5.10
<4.99
<9.7
<5.83
<9;35
<0.34
<10.0 189%38 102Z41
<3.70
<3.95
<9.3
<4.60
<4.76
<3.40
<10.8
<4.15
<8.23
<13.8
<9.2 213+47 124+41
<3.73
<3.69
<9.4
<4.60
<3.84
<4.01
<9.6
<3.41
<8.01
<0.27
<7.9 210+66
<105
<4.00
<3.98
<10.6
<4.39
<4.14
<4.12
<7.4
<4.37
<8.12
<13.3
<9.5 186Z46
<110
<3.92
<4.38
<10.3
<5.64
<4.50
<4'4
<9.9
<3.81
<9.05
<0.34
<10.4 189+30 75+31
<2. 67
<2.86
<7.2
<3.61
<3+22
<2.89
<7 '
<2.71
<5.71
<12.2
<7.7 248+37 108Z48
<2.66
<2.66
<6.7
<3.20
<2.88
<2.89
<5 5
<2.45
<5 ~ 22
<0.37
<4.8 OSWEGO STEAM STATION (CONTROL)
K-40 Ra-226 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 Zn-65 I-131 Ba/La-140 232247 125+70
<4.18
<4.21
<10.3
'<5. 24
<4.47
<3.62
<9.5
<4.07
<8.22
<0.40
<9.06 74226 77233
<2.62
<2.87
<7 '
<3 73
<3.23
<2.76
<7.8
<3.16
<6.18
<0.34
<8.42 59+32
<82
<2.81
<3.30
<6.8
<3.42
<3.07
<2.92
<7 '
<2.82
<4.85
<0.29
<7.20 98+36 63+37
<3.70
<4.24
<10.1
<4.91
<4.18
<3.23
<9.1
<3.96
<7.50
.<0.35
<8.72 232+38 130g44
<2. 70
<2.99
<7.4
<3.13
<3.15
<2'58
<6.5
<2. 90
<5.30
<0.23
<6.33 225+24 84+21
<1.63
<1.57
<4;4
<2.35
<1.82
<1.70
<3.9
<1.68
<3.06
<0.37
- <4.36
- Sample required by the Technical Specifications
<<<< Optional sample location.
Sample ggt required by the Technical Specifications.
-56
TABLE 6 CONCENTRATION OF TRITIUM IN SURFACE'ATER SAMPLES (QUARTERLY COMPOSITE SAMPLES)
Results in units of pCi/liter Z 2 sigma Location Period Date Tritium JAF INLET
- NMP-1 INLET **
NMP-2 INLET **
OSWEGO CITY WATER **
OSWEGO STEAM STATION *
(CONTROL)
First Quarter Second Quarter Third Quarter Fourth Quarter First Quarter Second Quarter Third Quarter Fourth Quarter First Quarter Second Quarter Third Quarter Fourth Quarter First Quarter Second Quarter Third Quarter Fourth Quarter First Quarter Second Quarter Third Quarter Fourth Quarter 12/30/87 03/31/88 03/31/88 06/30/88 06/30/88 09/30/88 09/30/88 12/29/88 01/04/88 03/31/88 03/31/88 06/30/88 06/30/88 09/30/88 09/30/88 12/29/88 01/04/88 03/31/88 03/31/88 06/30/88 06/30/88 09/30/88 09/30/88 12/29/88 01/04/88 03/31/88 03/31/88 06/30/88 06/30/88 09/30/88 09/30/88 12/30/88 01/04/88 03/31/88 03/31/88 06/30/88 06/30/88 09/30/88 09/30/88 12/30/88 430 2 80.
480 i 80 470 Z 90
<100 280 g 110 750 2 120 530 2 100 290 2 70 420 +
80 330 p 100
.210 g 110
<100 300 2 110 370 z 90 320 +
90 180 2 90 290 g 100 460 +
8Q 290 2 70 240 z 110 Samples required by the Technical Specifications.
- Optional samples.
Oswego City Water samples are composites of twice per week grab samples.
-57
TAHLE 7 NMP/JAF SITE ENVIRONMERZALAIRBORNE PARTICULATE SAMPLES - OIT SITE STATIONS GROSS BETA ACTIVITYpCi/m"3 + 2 sigma LOCATION WEEK END DATE R-1" R-4 D-2 88/01/12 88/01/19 88/01/26 88/02/02 88/02/09 88/02/16 88/02/23 88/03/01 88/03/08 88/03/15 88/03/22 88/03/29 88/04/05 88/04/12 88/04/19.
88/04/26 88/05/03 88/05/10 88/05/17 88/05/24 88/05/31 88/06/07 88/06/14 88/06/21 88/06/28 0.02&0.003 0.020%.002 0.020%.002 0.0)9&.002 0.02~.003 0.023%.003 0.0)%0.002 0.0)8%.002 0.0)7%.002 0.0)5%.002 0.0)3%.002 0.0)6%.002 0.0)8%.002 0.0)6%.002 0.0)3+0.002 0.0)4%.002 0.008%.002 0.02~.003 0.0)5%.002 0.0)~.002 0.024%.003 0.0)8%.002 0.030%.003 0.02&%.003 0.0)8+0.002 0.023+0.002 0.02~.003 0.0)8%.002 0.0)9%.002 0.02%0.002 0.0)9&.002 0.0)9&.002 0.0)4%.002 0.0)4%.002 0.0)4%.002 0.0)3+0.002 0.0)5%.002 0.02%0.002 0.0)5%.002 0.0)4&.002 0.0)~.002 0.008%.002 0.02~.003 0.0)5%.002 0.0)(84.002 0.023&.003 0.0)5&.002 0.030&.003 0.023&.003 0.0)8%.002 0.02&0.002 0.02~.003 0.020+0.002 0.023&.004 0.02)&.002 0.02(84.002 0.02%4.002 0.0)7&.002 0.0)6%.002 0.0)4%.002 0.0)~.002 0.0)7%.002 0.020+0.002 0.0)~.002 0.0)4%.002 0.0)6%.002 0.007&.002 0.02)+0.002 0.0)6%.002 0.0)~.002 0.02)+0.002 0.0)6%.002 0.028&.003 0.025&.003 0.020%.002 0.02&0.003 0.023%.003 0.02)&.003 0.0)8%.002 0.02%0.002 0.023%.002 0.0)8%.002 0.0)5&.002 0.01&&0.002 0.0)5&.002 0.0)3+0.002 0.0)7&.002 0.02(B:0.003 0.0)6&.002 0.0)3%.002 0.0)6&.002 0.0))+0.002.
0.0)~.003 0.0)7&.002 0.0))+0.002 0.023+0.003 0.0)8%.002 0.025+0.003 0.025%.003 0.0)9+0.003 0.02~.003 0.02)%.002 0.02)+0.002 0.02&0.002 0.02&0.002 0.02)&.002 0.0)9%.002 0.0)6%;002 0.0)7%.002 0.0)3%.002 0.0)~.002 0.0)6%.002 0.020%.002 0.0)4%.002 0.0)~.002 0.0)4%.002 0.008+0.002 0.023%.003 0.0)4%.002.
0.0)~.002 0.024%.003 0.0)6%.002 0.027+0.003 0.023+0.003 0.0)8%.002 0.02~.002 0.0)7&.002 0.0)9+0.002 0.023&.002 0.0)5%.002 0.0)3%.002 0.0)5%.002 0.0)3+0.002 0.0)2+0.002 0.0)7&.002 0.0)8%.002 0.0)3%.002 0.0)4&.002 0.0)5%.002 0.009+0.002 0.02(84.002 0.0)6%.002 0.0)3+0.002 0.023+0.003 0.0)9%.002 0.028+0.003 0.028+0.003
. 0.026%.003 0.0)8+0.002 0.0)9+0.002 0.023&.003 0.020%.002 0.020+0.002 0.0)8%.002 0.02&%.003 0.02&0.002 0.0)9&.002 0.0)7%.002 0.0)8%.002 0.0)4+0.002 0.0)&0.002 0.0)7%.002 0.0)8%.002 0.0)3%.002 0.0)~.002 0.0)5%.002 0.009+0.002 0.0)~.002 0.0)6&.002 0.0)(84.002 0.020&.002 0.0)7+0.002 0.032+0.003 0.025%.003 0.0)%0.002 0.02&0.002 0.0)9%.002 0.02010.002 0.02(84.002 0.023%.003 0.02(84.002 0.0)7&.002 0.0)5%.002 0.0)4%.002 0.0)~.002 0.0)&0.002 0.0)~.002 0.0)9%0.002 0.0)~.002 0.0))+0.002 0.0)7%.002 0.007%.002 0.02)&;002 0.0)5%.002 0.0))%.002 0.024+0.003 0.0)5+0.002 0.033&.003 0.025%.003 0.0)7&.002 0.020%.002 0.0)8%.002 0.0)7&.002 0.020&.002 0.02)&.002 0.0)~.002 0.0)6%.002 0.0)5&.002 0.0)4%.002 0.0)4%.002 0.0)4%.002 0.0)4%.002 0.0)8+0.002'.0)~.002 0.0)3%.002 0.0)5%.002 0.0)(89.002 0.02)&.002 0.0)2&.002 0.00~.002 0.0)5%.002 0.0)7%.002 0.023+0.003 0.0)8%.002 0.0)7+0.002 Technical Specification Location
TAELE 7 (Continued)
NMP/JAF SITE ENVIRONMENZALAIRBORNE PARTICULATE SAMPLES - OFF SITE STATIONS GROSS BETA ACTIVITY.pCi/m"3 + 2 signa IOCATION MEEK END DATE R-1 R-2 R-3 R-4 R-5 D-2 88/07/05 88/07/12 88/07/19 88/08/26 88/08/02 88/08/09 88/08/16 88/08/23 88/08/30 88/09/06 88/09/13 88/09/20 88/09/27 88/10/04 88/10/11 88/10/18 88/10/25 88/11/01 88/11/08 88/11/15 88/11/22 88/11/29 88/12/05 88/12/12 88/12/19 88/12/27 89/01/03 0.025%.003 0.038%.003 0.021&.003 0.024&.003 0.03KB.003 0.029+0.003 0.019%.002 0.016%.002 0.014%.002 0.014%.002 0.01KB.002 0.02%0.002 0.01~.002 0.017%.002 0.013%.002 0.016%.002 0.00'.002 0.011%.002 0.014%.002 0.009&.002 0.014+0.002 0.021%.002 0.019+0.002 0.021%.002 0.02(B:0.002 0.01&@.002 0.02~.002 0.023+0.003 0.034%.003 0.02&0.002 0.021%.002 0.037%.003 0.024%.003 0.02~.002'.016%.002 0.013%.002 0.015%.002 0.018%.002'.017&.002 0.014%.002 0.017%.002 0.013%.002 0.017%.002 0.008%.001 0.014%.002 0.015%.002 0.01~.002 0.015%.002 0.021&.002 0.017%.002 0.023%.002 0.019%.002 0.014%.002 0.024%.002
- 0. 02~. 003
- 0. 038%. 003 0.021&.002 0.02~.003 0.039+0.003 0.025%.003 0.021&.002 0.016&.002 0.015%.002 0.015%.002 0.021&.002 0.01~.002 0.013+0.002 0.016%.002 0.013%.002 0.015&.002 0.008%.001 0.015&.002 0.015&.002 0.00~.002 0.013%.002 0.02~.002 0.018&.002 0.021&.002 0.018%.002 0.015&.002 0.02&0.002 0.019+0.003 0.035%.003 0.019i0.002 0.025%.003 0.040+0.003 0.027&.003 0.025%.003 0.015%.002 0.014%.002 0.016%.002 0.01%0.002 0.016%.002 0.015%.002 0.017%.002 0.014%.002 0.016%.002 0.007%.001 0.014%.002 0.014%.002 0.008%.002 0.013%.002 0.02~.002 0.017%.002 0.02~.002 0.02&0.002 0.016&.002 0.02&0.002 0.017&.002 0.039%.003 0.021+0.002 0.024+0.003 0.039&.003 0.029%.003 0.024%.002 0.015%.002 0.01~.002 0.014%.002 0.017&.002 0.017%.002 0.013+0.002 0.015%.002 0.011&.002 0.017&.002 0.008+0.001 0.011&.002 0.016%.002 0.009&.002 0.014+0.002 0.019&.002 0.017&.002 0.028&.003 0.021+0.002 0.016%.002 0.023+0.002 0.021+0.003 0.045%.004 0.018%.002 0.024&.003 0.039+0.003 0.027&.003 0.023+0.002 0.018%.002 0.013+0.002 0.016%.002 0.018+0.002 0.017&.002 0.016&.002 0.018%.002 0.01&0.002 0.016%.002 0.007&.001 0.011&.002 0.01398.002 0.008%.001 0.01~.002 0.018+0.002 0.024%.003 0.011+0.002 0.016&.002 0.017&.002 0.021%0.002 0.02&0.003 0.043&.003 0.019+0.002 0.024&.003 0.036&.003 0.03~.003 0.02&0.002 0.014%.002 0.013+0.002 0.015&.002 0.01%0.002 0.017&.002 0.013+0.002 0.015%.002 0.011&.002 0.01&@.002 0.008%.001 0.01~.002 0.014&.002 0.009&.002 0.013M.002 0.018+0.002 0.01&%.002 0.02~.002 0.017&.002 0.015&.002 0.020+0.002 0.024+0.003 0.041&.003.
0.02&0.002 0.023%.003 0.040&.003 0.029&.003 0.024&.003 0.018%.002 0.016%.002 0.016%.002 0.01%0.002 0.01%0.002 0.014&.002 0.021&.009 0.01~.002 0.017&.002 0.007&.001 0.013&.002 0.014%.002 0.01(84.002 0.014&.002 0.019&.002 0.019+0.002 0.02~.002 0.019+0.002 0.014&.002 0.021&.002 0.016%.002 0.035%.003 0.018%.002 0.025&.003 0.034&.003 0.025&.003 0.020&.002 0.014%.002 0.013&.002 0.015%.002 0.017&.002 0.01&%.002 0.01&0.002 0.014&.002 0.011+0.002 0.014+0.002 0.007+0.001 0.011&.002 0.013&.002 0.009&.002 0.01&0.002 0.017&.002 0.01&%.002 0.018&.002 0.017&.002 0.016+0.002 0.021+0.002 Technical Specification Location
-59
TAHLE 8 NMP/JAF SITE ENVIROMM'ALAIRBORNE PARTICULATE SAMPLES - ON SITE SI'ATIONS GROSS BETA ACTIVITYpCi/m"3 + 2 signa IOCATION WEEK END DATE Dl-ON H
ON I
ON J
ON K--ON 88/01/11 88/01/18 88/01/25 88/02/01 88/02/08 88/02/16 88/02/22 88/02/29 88/03/07 88/03/14 88/03/21 88/03/28 88/04/04 88/04/11 88/04/18 88/04/25 88/05/02 88/05/09 88/05/16 88/05/23 88/05/31 88/06/06 88/06/13 88/06/20 88/06/27 0.018%.002 0.026%.003 0.01~.002 0.021&.002 0.02340.002 0.018%.002 0.01%0.002 0.013%.002 0.017%.002 0.015%.002 0.011+0.002 0.014%.002 0.018%.002 0.014%.002 0.014%.002 0.015%.002 0.009%0.002 0.015%.002 0.017%.002 0.010&.002 0..01'.002 0.011%.002 0.010%.002 0.023&.003 0.017&.002 0.01&%.002 0.024&.003 0.01%0.002 0.02~.002 0.02~.002 0.021%.002 0.018%.002 0.015%.002 0.018%.002 0.016%.002 0.014%.002 0.01&%.002 0.021+0.003 0.015%.002 0.015%.002 0;014%.002 0.007%.002 0.019&.002 0.01%0.002 0.01~.002 0.021&.002 0.01&%.003 0.02&0.003 0.027&.003 0.021&.003 0.02(B4.003 0.03'.003 0.023&.003 0.023%.003 0.024&.003 0.02~.002 0.020+0.003 0.018%.002 0.018+0.003 0.017&.002 0.013+0.002 0.017&.002 0.02&0.003 0.017&.002 0.015%.002 0.016%.002 0.009+0.002 0.020%.003 0.017+0.002 0.013%.002 0.024%.003 0.017&.003 0.00&@.002 0.027&.003 0.020i0.003 0.02~.002 0.023&.002 0.019+0.002 0.026%.003 0.027&.003 0.023%.003 0.021+0.003 0.018%.002 0.019&.003 0.016%.002 0.01~.002 0.017%.002 0.021+0.003 0.016%.002 0.013+0.002 0.01'.002 0.00%0.002 0.01&%.002 0.016+0.002 0.015&.002 0.02&0.002 0.018%.003 0.02~.003 0.024%.003 0.020+0.003 0.020+0.003 0.021%.002 0.018&.002 0.02~.003 0.024%.003 0.017&.002 0.01&K.002 0.013%.002 0.010%.002 0.015%.002 0.01~.002 0.014%.002 0.01~.002 0.016%.002 0.013&.002 0.0017+0.002 0.00'.002 0.01%0.002 0.019%.002 0.014%.002 0.023+0.002 0.017&.003 0.02~.003 0.02~.003 0.017%.002 0.020+0.002 0.021&.002 0.017&.002 0.021&.002 0.025%.003 0.02~.002 0.03~.006 0.015%.003 0.017%.002 0.01&%.002 0.014%.002 0.01&%.002 0.02&0.003 0.014+0.002 0.015+0.002 0.018%.002 0.006%.002 0.021&.003 0.018%.002 0.013%.002 0.023%.003 0.01KB.003 0.023+0.003 0.026&.003 0.018+0.002
t TABLE 8 (Continued)
NMP/JAF SITE ENVIRORIEFZAL AIRBORNE PARTICULATE SAMPLES ON SITE STATIONS GROSS BETA ACTIVITYpCi/m"3 + 2 sigma IQCATION MEEK END DATE Dl-ON G--ON I
ON J
ON K--ON 88/07/05 88/07/11 88/07/18 88/07/25 88/08/01 88/08/08 88/08/15 88/08/22 88/08/29 88/09/06 88/09/12 88/09/19 88/09/26 88/10/03 88/10/10 88/10/17 88/10/24 88/10/31 88/11/07 88/11/14 88/11/21 88/11/28 88/12/06 88/12/13 88/12/20 88/12/27 89/01/03 0.01%4.002 0.039%.004 0.02(B:0.002 0.025%.003 0;028%.003 0.02~.002 0.023%.002 0.013%.002 0.013+0.002 0.017&.002 0.02~.003 0.018%.002 0.013+0.002 0.016%.002 0.011&.002 0.017&.002 0.013+0.003 0.015%.004 0.016%.002 0.008%.002 0.014%.002 0.02~.002 0.015%.002 0.02(84.002 0.02~.002 0.018&.002 0.02&0.002 0.023+0.002 0.03~.003 0.003+0.001 0.01~.002 0.032+0.003 0.024%.003 0.024%.002 0.014%.002 0.01&0.002 0.014%.002 0.01'.002 0.018%.002 0.015&.002 0.017&.002 0.013+0.002 0.018%.002 0.009&.002 0.01~.002 0.015%.002 0.008+0.002 0.015%.002 0.021&.002 0.017&.002 0.023+0.002 0;01%0.002 0.018+0.002 0.023+0.002 0.021&.002 0.036%.004 0.02(84.002 0.023%.003 0.034&.003 0.026.003 0.02&@.002 0.015%.002 0.017%.002 0.017&.002 0.02%0.003 0.01~.002 0.014%.002 0.016&.002 0.01~.002 0.01&%.002 0.00%0.002 0.011+0.002 0.015%.002 0.007&.001 0.017%.002 0.021+0.002 0.01&%.002 0.019+0.002 0.015&.002 0.015+0.002 0.023i0.002 0.027&.003 0.043%.004 0.02~.003 0.02&0.003 0.037%.003 0.024%.003 0.025%.002 0.01~.002 0.013+0.002 0.023%.005 0.02(B:0.004 0.02~.003 0.01~.002 0.016%.002 0.011+0.002 0.016&.002 0.008%.001 0.01(88.001 0.016%.005 0;007%.002 0.015%.002 0.019&.002 0.015%.002 0.02~.002 0.017%.002 0.018+0.002 0.023+0.003 0.019%0.002 0.034%.004 0.021+0.002 0.019%.002 0.035%.003 0.020%.002 0.021+0.003 0.014%.002 0.017%.006 0.018%.002 0.019+0.002
- 0. 017&. 002 0.015&.002 0.01234.002 0.011&.002 0.015&.002
- 0. 01(E4. 002 0.01~.002 0.013&.002 0.007&.001 0.016%.002 0.020&.002 0.013+0.002 0.018+0.002 0.019+0.002 0.015&.002 0.021+0.002 A
0.020&.002 0.040&.004 0.019+0.002 0.01~.003 0.03~.003 0.023&.003 0.024&.002 0.013%.002 0.013+0.002 0.017&.002 0.021&.003 0.01&0.002 0.013&.002 0.016&.002 0.011&.002 0.015&.002 0.010%.002 0.010&.002 0.015%.002 0.007&.002 0.015%.002 0.018+0.002 0.015+0.002 0.02~.002 0.019+0.002 0.015+0.002 0.024&.002
-61
. TABLE 9 CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-1 OFF-SITE STATIONA'esults in units of M 3~@3 g 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.9
<0.3
<1 ~ 2
<0.9
<1.0
<1.6
<1 ~ 2
<3 '
<9.9
<1.6 8lw14 10+7
<2'
<19
<2.8
<0.9
<1.3
<1.0
<1.2
<1.2
<3+3
<2.1
<6.1
<11.5
<1.4
'108+16 44pl7
<1.8
<26
<3.4
<1.1
<1.0
<0.9
<1.1
<1.4
<2 '
<1 ~ 9
<5.1
<12.0
<0.9 111Z16 28213
<1.7
<22
<4.1
<lel
<1.0
<1.0
<1.1
<0.8
<2.6
<1.8
<5.0
<12.0
<1.3 64p14 38g16
<2.5 17~11
<3.8
<0.9
<1.5
<1.4'1.3
<1.3
<3.0
<1.8
<6.0
<12.7
<1.4 127p18 22+12
<F 1
<27
<4.0
<1.2
<1.3
<1.3
<1.4
<1.3
<2.9
<1.9
<5.3
<10.5
<1.6 139+18 22gll
<3.5
<21
<5 5
~Nuclide s July August September Oc tober November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.8
<0.5
<0.7
<0.8
<0.9
<1.8
<1.2
<3.9
<6.1
<1.0 115~13 28Z10
<1.9
<15
<2.8
<1.0
<1.2
<1.3
<1 ~ 2
<1.4
<2.5
<1.9
<5.1
<11.0
<1.4 89216
<33
<2.0
<24
<3.5
<0.6
<0.5'0.8
<0.7
<1 ~ 2
<1.8
<1.3
<3.9
<7.0
<0.9 69+10 36p12
<2 ~ 2
<15
<2+7
<1.2
<1.6
<1.1
<1.1
<1.6
<3.9
<1.8
<6.2
<10.9
<1.4 66pl4
<34
<2.0
<22
<4.0
<1.4
<1.4
<0.9
<0.9
<2 '
<2.9
<2.0
<5.3
<11.1
<1.4 80214
<25
<4.4
<22
<4.1.
<0.9
<0.8
<0.8
<0.7
<1.1
<2.4
<1.4
<4.1
<7.2
<1.0 86~12 34~11
<2'
<16
<4.1
<< Location required by the Technical Specifications.
-62
e TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLX COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-2 OFF-SITE STATION*
Results in units of M 3~@3
+ 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RQ-106 RQ-103 Be-7 K-40 La-140 Ra-226 I-131
<0.6
<1.0
<0.8
<0.7
<1.2
<2 '
<1.4
<3.4
<6.6
<1.2
101+16
<15
<3.0
<14
<3 '
<1.4
<1 ~ 2
<1.2
<1.0
<1.3
<1.9
<1.8
<5.6
<12.3
<1.1 88215 23~13
<2 '
<24
<3.6
<1.0
<1.0
<0.9
<0.8
<0.9
<2. 6
<1.3
<3.6
<5.4
<0.9 92~14
<14
<3.4
<13
<3 '
<1.0
<0.9
<1.3
<1.0
<1.7
<3.0
<1.8
<5.4
<8.5
<1 ~ 2 59g12 30Z13
<1.3 18~9
<3 '
<1.0
<0.9
<1.1
<0.9
<1.2
<2.6
<1.7
<5.2
<8.7
<1.2 122+16 45gl7
<1.8
<22
<3.1
<1.5
<0.9
<0.9
<0.9
<1.4
<3.2
<1.9
<4.9
<11.3
<1.4 15'3p20 2lg12
<2.3
<22
<4.8 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.9
<0.5
<0.7
<0.8
<0.8
<2.3
<1.2
<3 '
<6 '
<0.7 103212 18'2.8
<15
<2.5
<1.1
<1.2
<1.3
<1.1
<1.9
<2.9
<1.7
<5 '
<8.8
<1.2 102gl6
<24
<1 ~ 9
<21
<3.4
<0.8
<0.8
<0.8
<0.6
<1 ~ 2
<2.0
<1.3
<3.6
<7.0
<0.9 83Zll 29+10
<2.1
<15
<3.0
<0.8
<1.0
<1.1
<1.0
<1.1
<2.3
<1.2
<4.3
<10.9
<1.2 64p12 14g10
<2.6
<19
<2.9
<2.0
'1.1
<1.0
<1.0
<1.4
<3.6
<1.7
<5.1
<9.9
<1.6 75z14 36Z15
<2.7
<20
<3.6
<0.5
<0.8
<1.0
<0.8
<1.4
<2 '
<1.6
<4.8
<8.6
<1.1 81i13
<23
<4.3
<19
<3+2
- Location required by the Technical Specifications.
-63
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-3 OFF-SITE STATION*
Results in units of 19 3~@3 ~ 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0 '
<1.3
<1.1
<0.8
<1.3
<2.2
<1.7
<4.8
<9.1
<1.2 90~16 13+9
<3.2
<19
'3.5
<1.2
<0.9
<0.7
<0.8
<1.7
<2.9
<1.6
<4.3
<8.8
<1.4 99Z16 18~10
<1.6
<19
<3.6
<0.7
<1.9
<0.7
<0.6
<1.2
<2e3
<1.6
<4.3
<7.6
<1.0 92g14
<12
.<1.5
<17
<3 '
<1.4
<1 ~ 1
<1.2
<1.2
<1.9
<2.7
<1.9
<5 '
<10.8
~
<1.5 67214 33gl4
,<2. 9
<23
<3 '
<1.0
<1.2
<1.4
<0.9
<1.6
<3.1
<1.6
<4.6
<9.5
<1.2 139g19'20
<4.4
~
16Z10
<4.6
<0.9
,<1.0
<0.8
<1.0
<1.0
<2.0
<1.7
<4.9
<9.3
<1.1 123p15 35Z13
<3.1
<18
<4.1 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.8
<0.7
<0.6
<0.6
<0.7
<1.7
<1.2
<3.4
<5.0
<0.8 122+13 34+11
<1.5
<15
<2.9
<1.0
<1.3
<1.2
<0,. 5
<1.4
<3.0
<1.5
<4.7
<5.8
<1.5 87g18
<29
<3.0
<21
<3.8
<1.0
<0.9
<0.9
<0.7
<1.1
<1.4
<1.4
<4.1
<8.4
<1.0 77+12 16i9
<2.0
<16
<3 '
<1.0
<0.7
<0.9
<1.1
<1.4
<2.4
<1.5
<4.7
<9.2
<1.2 55g12 20+12
<2.1
<19
<2.8
<0.7
<1 ~ 1
<0.8
<1.0
<0.9
<2.1
<1.2
<4.1
<8.3
<1.3 59Z12 12~8
<1.7
<17
<3.5
<1.3
<0.7
<0.7
<0.8
<1.1
<2 '
<1.2
<3.4
<7 '
<1.0 72Zll
<14
<1.3
<15
<3.4
- Location required by the Technical Specifications.
-64
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-4 OFF-SITE STATION*
Results in units of lQ 3~@3 g 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-'103 Be-7 K-40 La-140 Ra-226 I-131
<0.7
<1.1
<0.8
<0.9
<1.4
<2.4
<1.6
<3.5
<7.1
<1.1
'05+17
<17
<2 '
<17
<4.4
<1.5
<1.4
<1.3
<1.1
<1.4
<3o7
<1.8
<6 '
<13.1
<1.5 103217 26g15
<3.0 14+9
<2. 9
<1.2
<1.2
<1.1
<0.9
<2.1
<0.8
<0.9
<0.9
<0.8
<1.0
<8.4
<1.4 122g15 41gl4
<1.8
<18
<3.5
<8.9
<1.8 61~16
<21
<3.0
<22
<3.8
<2. 2
<3..8
<1.5
<1.9
<4.1
<4.9
<1.5
<1.4
<1.3
<1.4
<1.8
<3.6
<1.7
<5.6
<14.3
<1.0 137+20 15g12
<4.5
<26
<5.8
<1.5
<0.8
<1.3
<1.1
<1.5
<3.0
<1.8
<5.6
<11.0
<1.4 122gl7 40g15
<2.9 25+12
<5.3 Nuclide s July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
, <0.8
<1.0
<0.8
<0.8
<1.2
<3.0
<1.5
<4.8
<F 1
<1.1 111~14 23~10
<1.5
<18
<3.4
<1.0
<1.2
<1+i
<0.9
<0.9
<3.0
<1.6
<4.2
<12.1
<1.0 112gl7
<15
<2.9
<20
<3.6
<0.8
<0.9
<0.7
<0.7
<0'. 9
<1.9
<1.2
<4.1
<5.3
<1.0 80pll 28Zll
<2 '
<15
<2. 9
<0.7
<1.8
<1.4
<1.4
<2.1
<3.6
<1.8
<5.5
<14.4
<1.6 66p14 17Z12
<2.9
<23
<4.2
<1.3
<1.2
<0.9
<1.1
'1.4
<2.4
<1.7
<5.4
<8.6
<1.3 74g13 31+14
<3.1 13gll
<3 '
<1.4
<1.2
<1.2
<0.9
<1 ~ 2
<2 '
<1.5
<5.2
<9.6
<1.2 88%14 17gll
<4.1
<19
<3 '
- Location required by the Technical Specifications.
-65
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-5 OFF-SITE STATION (CONTROL)*
Results in units of lQ 3y~m3 ~ 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.7
<0.8
<1.0
<1.0
<1 ~ 3
<2.5
<1.5
<4.5
<9.3
<1.4 100+14 18plO
'.< 2 ~ 2
<18
<3.8
<0.8
<1.0
<1.2
<1.2
<1.5
<3 '
<1.4
~<3.9
<9 ~ 2
<1.5 108Z18
<18
<2.4
<20
<3.9
<1.5
<1.2
<1.0
<0.8
<1.4
<2.0
<1.6
<3.6
<6.8
<1.0 120Z18
<14
<3'
<18
<4.2
<1.4
<1.2
<1.3
<1.4
<1.3
<3.1
<1.9
<5.4
<12.8
<1.3 68214 16i10
<3.5
<25
<5.1,.
<1.0
<1.1
<1.0
<0.9
<1.3
<2. 9
<2. 1
<6.7
<8.2
<1.5 121gl8 49i18
<2.8
<25
<4.7
<1.0
<1.0
<1.1
<0.7
<1:2
<2+5
<1.7
<4.9
<10.8
.<1. 2 122+17
<15
<2.0
<20
<4.5 Nuclides July Augus t September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.5
<1.0
<1.0
<1.0
<1.8
<2.7
<1.6
<4.2
<8.9
<1.1 115g16
<18
<2.5
<18
<3.4
<2.1
<1.2
<0.9
<1 ~ 2
<1.5
<3.6
<1 ~ 6
<4.2
<12.9
<1.7 73~17
<34
<6 '
<22
<3.8
<1.1
<0.9
<0.8
<0.9
<0.6
<2.3
<1.2
<3 '
<6.0
<1 ~ 2 83g13
<14
<1.4
<14
<2.6
<0.9
<1.0
<0.9
<1.0
<1 ~ 2
<2.5
<1 ~ 3
<4.7
<9.4
<1.0 66g12
<18
<1.5
<17
<2.8
<0.9
<0.9
<0.9
<1.0
<1.3
<3.2
<1.7
<4.5
<8.5
<1.3 65~12 40pl5
<1.5
<21
<3.0
<0.9
<0.7
<0.7
<0.9
<0.9
<2 '
<1.2
<3.4
<8.5
<0.8 87+12
<12
<2.4
<16
<2.6
- Location required by the Technical Specifications.
-66
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES Dl ON-SITE STATION
- Results in units of M 3~3 Z 2 'sigma Nuclides January February March April 'ay June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-.141 Ce-144 Ru-106 Ru-103, Be-7 K-40 La-140 Ra-226 t
I-131 Nuclides
<0.9
<1.1
<0.9
<0.6
<1.3
<2.9
<1.2
<3.6
<9;8
<0.8 77+14 13Z9
<2.9
<15
<3 '
July
<0.4
<1.0
<0.9
<0.8
<1.2
<2 '
<1.4
<5.0
<6.2
<1.4 87gl3 60gl7
<2~7
<20
<3.2 August
<1.1
<0.9
<0.8
<0.9
<1.0
<2.1
<1.1
<3 '
<7.0
<0.9 106+15
<14
<2.8
<14
<3.0 September
<1.1
<1.2
<1.1
<1.2
<1.2
<3.0
<1.3
<4.3
<8.0
<1.4 62~13 26pl5
<3.4
<19
<3 3
<1.0
<2 ~ 2
<0.9
<1.5
<1.2
<1.4
<1.2
<1.1
<1.4
<1.1
<3.1
<3.2
<2.0
<1.8
<5.6
<6.1
<11.9
<11.9
<1.2
<1.5 102+16 81+15 28213 23214
<2.4
<3.0
<22
<22
<4.0
<3.9 October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RLI-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.8
<1.0
<1.0
<1.0
<1.0
<2 '
<1.6
<4.2
<8.0
<1.0 lllgl5 45g15
<3.0
<18
<3 '
<1.1
<1.4
<0.9
<0.9
<2.
2'2.4
<1.6
<5+2
<13.2
<1.6 98g19
<33
<3.4
<23
<4. 2.
<1 ~ 2
<0.8
<0.7
<0.7
<1.3
<2.4
<1.7
<4.5
<9.6
<0.7 63~13 14~10
<3 '
<19
<3.5
<1.6
<i+3
<1.1
<1'8
<1.8
<4.3
<2.1
<6.4
<14.5
<1.9 76~17
<27
<3 '
19Z13
<4.3
<1.5
<1 ~ 5
<0.9
<1.1
<2.1
<3.1
<1.7
<5 '
<12.0
<1.3 62p14 30pl6
<3.0
<24
<3 '
<0.4
<0.9
<0.7
<1.0
<1.2
<1.9
<1.5
<4.8
<7.0
<1.0 75Z12 24gll
<2.4
<17
<2.9
>>-Optional sample location
-67
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES G ON-SITE STATION
- Results in units of 1Q 3pGilm3 a 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RG-106 Ru-103'e-7 K-40 La-140, Ra-226 I-131
<1.1
<1.2
<1.0
<0.9
'<1.4
<2. 2
<1.8
<4.6
<7.9
<1.4 83%13 32~12
<2.2
<18
<3.58
<1.5
<1.1
<1.1
<1.0
<1.6
<3.6
<1.9
<6.0
<13.1
<1.4 99+16 35i16
<1.6
<24
<3.0
<0.8
<1.0
<1.0
<0.7
<1.3
<1.7
<1.3
<3.6
<7.6
<1.1 114g16
<13
<3 '
<19
<3.9
<1.2
<1.0
<1.0
<0.8
<1.4
<2.6
<1.6
<5.0
<9.1
<1.4 64g14
<22
<2.5
<18
<3.8
<1 ~ 2
<1.0
<1.1
<0.9
<1.5
<3 '
<1.7
<4.4
<8.4
<1.4 115Z17 13pll
<2.9
<22
<3 3
<0.9
<1.1
<1.1
<1.0
<1.0
<2.5
<1.6
<5 '
<10.7
<1.2 123g15 31i12
<2.1
<21
<3.8 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<1.4
<1.1
<1.0
<0.9
<1.4
<1.9
<1.4
<3.6
<8.2
<1.3 72+14
<22
<2.8
<17
<3.6
<2.1
<1.3
<0.9
<0.8
<1.0
<1.9
<1.6
<4.0
<11.1
<1.6 83i17
<33
<3 '
<20
<3.0
<0.5
<0.7
<1.0
<0.8
<1.0
<2.3
<1.4
<3.8
<9.7
<0.9 83213 22pll
<1.8
<16
<3 '
<0.7
<1 ~ 2
<1.1
<1.1
<1.5
<3 '
<1.9
<5.8
<7 '
<1.3 62g13
<30
<3.8
<22
<3.8
<1.0
<1.0
<0.9
<1 ~ 1
<1.2
<2.6
<1.6
<4.6
<7 '
<1.1 74~12 14g10
<3.0
<20
<3 '
<0.6
'<0.6
<0.6
<0.9
<1.2
<2.'1
<1.2
<3.5
<7.4
<0.9 87212 10+8
<1.3 9'2.5
- Optional sample location
-68
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES H ON-SITE STATION
- Results in units of ~ 3ggjgg3 z 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<1.1
<1.2
<1.2
<0.9
<2.0
<2 '
<1.5
<4.6
<10.4
<1.3 95+16
<16
<3.6
<19
<4.2
<0.9
<1 ~ 2
<0.8
<1.9
<1.6
<3 '
<1.6
<4.5
<11.3
<0.8 83g17
<25
<3.8
<25
<4.2
<0.8
<1.0
<1.0
<0.6
<1 ~ 3
<2.9
<1.5
<5.4
<7.4
<1.4 108p16 15+12
<2.6
<18
<4.0
<1..5
<1 ~ 3
<1.1
<1.4
<2.6
<4.7
<2. 7,
<5.5
<11.5
<1.6 80~18 26gl4
<7.0
<25
<12.4
<1 ~ 2
<1.2
<1.0
<1.1
<1.3
<3.2
<1.9
<5.4
<9.8
<1.4 99p15 46gl7
<3.2
<22
<3 '
.<1.5
<0.9
<1.6
<1.1
<1.7
<4.5
<2.1
<4.7
<11.8
<1.6 86Z16
<23
<3.2
<24
<6 '
Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<1.0
<0.6
<0.8
<1.0
<1 ~ 2
<2.4
<1.5
<4.3
<7.4
<1.0 103~14 35pl3
<2.6 9+7
<3+3
<1.1
<1.1
<1.1
<1.3
<1.1
<2.9
<1.6
<4.9
<13.5
<2.0 90p19
<34
<6.0
<22
<4.4
<1.0
<0.7
<0.9
<0.8
<1.4
<2.4
<1.4
<3 '
<8.8
<1.0 62g12 12'3.0
<14
<3 '
<2.4
<1.4
<1.1
<1.3
<1.5
<3 '
<1.6
<4.9
<13.6
<1.7 51pll
<29
~
<2.9
<20
<4.5
<0.7
<1.3
<1.0
<0.7
<1.3
<2 ~ 7
<1.3
<3.5
<9.0
<1.1 50Z10 17Zll
<3.1
<16
<3.0
<1.3
<0.9
<0.8
<0.7
<1.0
<2.1
<1.1
<3.7
<7 '
<0.7 66~11 7+5
<2.8
<14
<2.6
- Optional sample location
-69
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES I ON-SITE STATION
- Results in units of M 3~m3 g 2 sigma Nuclides January February March'pril May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<1.0
<1.0
<0.7
<1.1
<1.2
<2.5
<1.2
<3.7
<7 '
<1 ~ 2 89Z15 10+9
<2 '
<20
<3 '
<1.2
<1.1
<1.7
<1 ~ 6
<1.9
<3+2
<1.9
<6.1
<15.3
<1.7 103t18 19+12
<2.1
<24
<3.9
<1.1
<1.0
<0.9
<0.8
<1.8
<2+5
<1.9,
<4.7
<10.2
<1.5 107gl6 19+11
<4.1
<22
<4.5
<0.9
<1.5
<1.1
<1.3
<1.5
<3.4
<1.8
<4.8
<10.7
<1.3 66g16
<30
<3.8
<20
<4.5
<1.3
<1.0
<1.1
<1.2
<1.6
<3.8
.<1.9
<6.4
<11.5
<1.3 132+18 31zl5
<2' 32+17
<3.4
<1.4
<1.6
<1.2
<1.3
<2 '
<3 '
<2.3
<6.5
<12.8
<1.8 107219
<25
<5.1
<24
<4.7 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 RIL-103 Be-7 K-40 La-140 Ra-226 I-131
<0.8
<0.9
<0.9
<1.0
<0.8
<2.4
<1.4
<4.1
<7.6
<1.2 116+15 26g12
<3.1
<17
<4.2
<1-1
<2.0
<1.4
<0.7
<1 ~ 3
<3 '
<1.5
<4.8
<15.2
<2.0 105219
<31
<5.8
<19
<4.7
<1.1
<1 ~ 2
<1.2
<1.2
<1.4
<3.4
<2.2
<6.1
<10.7
<1.3 84+17 53g18
<3 3
<22
<4.3
<0.9
<1.1
<1.1
<1.0
<1.2
<3.2
<1.4
<4.4
<8.0
<1.5 62i12 38gl4
<1.9 12i7
<3 '
<1.5
<1.4
<1.1
<1.5
<1.7
<2.4
<2.0
<5.8
<10.4
<1.4 59+14 26g16
<3.1 19gll
<3 '
<0.6
<1.1
<0.6
'0.7
<1.1
<2-6
<1.3
<3.5
<8.0
<0.9 62+11 8+7
<1.5
<15
<3.2
>>-Optional sample location.
-70
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE. SAMPLES J ON-SITE STATION Ic Results in units of ~ 3~m3
+ 2 sigma
- Nuclides, January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<1.2
<0.8
<1.1
<1.2
<1.4
<2.4
<1.3
<3.9
<13.5
<1.1 78Z15
<15
<2.4
<16
<3.6
<0.9
<1.1
<1.0
<0.9
<1.4
<2.8
<1.8
<5 '
<10.2
<1.1 88+14 35+14
<2.6
<21
<2.9
<1.1
<0.8
<1.0
<0.7
<0.9
<2 '
<1.4
<4.0
<8 '
.<1.0 73+13 10+7
<2.4
<18
<3 '
<1.4
<1.4
<1.1
<1.4,
<1.4
<2.0
<1.4
<5.. 3
<12.3
<1.6 69+15
<19
<2 '
<25
<4.1
<0. 6
<0.9
<1.1
<1.0
<1 3
<3.7
<1.5
<5 5
<9.5
<1.2 119+17
<9
<3.0
<20
<3.5
<0.8
<0.9
<0.9
<1.0
<1.1
<2.7
<1.7
<4.5
<9.6
<1.3 109+14 35i12
<3.4
<18
<4. 2.
Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<1'.0
<0.8
<0.9
<0.9
<1.3
<1 ~ 9
<1 ~ 2
<4.5
<7.4
<1.1 106+15 2lglO
<2.5
<16
<3.1
<1.4
<1.4
<1
~ 2
<1.5
<2.6
<3+7
<2 '
<6.4
<16.4
<1.6 82~21
<49
<4.5
<21
<4.7
<0.8
<0.7
<0.8
<0.9
<0.9
<2.0
<0.9
<3.6
<7.0
<0.8 49t9 16+9
<1.9
<14
<1.9
<0.7
<0.9
<1.0
<0.8
<1.4
<2 '
<1.6
<5.1
<10.8
<1.0 52210 42p14
<2.9
<20
<3.1
<0.9
<1.2
<1.0
<1.1
<1.5
<2~7
<1.8
<5.6
<10.4
<1.3 60~12 29+14
<3.0
<22
<2.7
<1.1
<1.0
<0.9
<0.8
<1.4
<2 '
<1.5
<4.3
<10.6
<1.3 56+12 20plO
<2.4
<17
<3 '
- -Optional sample location
-71
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES K ON-SITE STATION
- Results in units of ~ 3~iq3 g 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 RU-103 Be-7 K-40 La-140 Ra-226 I-131
<1.2
<0.9
<0.9
<1.2
<1.2
<2.4
<1.5
<4.1
<9.7
<1.3 69~13 15~9
<1.6
<18
<3 '
<1.1
<1.9
<1.3
<1.6
<2.2
<4.1
<2.2
<7.1
<14.9
<1.4 108~20
<26
<3.2
<25
<3 '
<1.5
<1.1
<0.7
<1.2
<1.4.
<3 '
<1.6
<3.6.
<9.9
<1.2 103216
<18
<3 '
<16
<4.2
<1 ~ 9
<1-2
<1.2
<1.4
<1.2
<2.8
<1.9
<4.8
<13.5
<1.4 56gl5
<24
<2.8
<21
<4.8
<1.6
<1.3
<1.2
<0.4
<1.5
<3 '
<2.0
<5.6
<12.1
<1.2 135+19 16+11
<3 '
18+12
<3.7
<0.8
<0.8
<1.2
<1 ~ 2
<1.7
<3.0
<2.1
<5.9.
<12.8
<1.5 117+17 4lpl5
<4.8 14Z9
<5.7 Nuclides July August September Oc tober November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.9
<0.5
<0.9
<1.3
<1.7
<2.1
<1.6
<4.1
<9.6
<1.5 95gl7
<30
<3.0
<18
<3.4
<1.4
<1.4
<1 ~ 1
<0.9
<1 ~ 9
<3.8
<1.7
<5 '
<11.6
<1.5 79p16
<25
<3.8
<21
<4.1
<1.1
<0.9
<0.9
<0.8
<1.0
<2.2
<1.6
<4.8
<7.4
<0.9 54+11 18+13
<4.7
<18
<2.8
<1.4
<1.3
<1 ~ 1
<1.1
<1.4
<3.1
<1.8
<5.4
<11.2
<1.3 62Z13 28Z13
<1.6
<21
<3.0
<0.9
<0.9
<1.0
<1.0
<1 ~ 3
<2 '
<1.5
<4.8
<7.8
<1.5 63Z12 47pl4
<1.2
<18
<3.0
<1.7
<1.1
<0.9
<1.1
<0.9
<3.0
<1.5
<4.6
<8.0
<1.2 73i13 16gl0
<4.6
<17
<4.2
<<-Optional sample location
-72
TABLE 9, (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES D2.0FF-SITE STATION
- Results in units of ~ 3~m3 g 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-.95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.9
<0.8
<0.8
<1.0
<1.1
<1.8
<1.2
<4.3
<7.8
<1.1 94+14
<17
<4.0
<18
<3.0
<1.4
<1.0
<1.0
<0.9
<1.1
<2.4
<1.8
<5 '
<8.8
<1.3 8lg14 30214
<2'
<22
<3 '
<0.8
<1.0
<1.1
<0.9
<1.2
<2.5
<1.5
<4.2
<10.0
<1.3 105Z16
<17
<2 '
<15
<3.8
<1.4
<1.4
<0.9
<1.0
<1.1
<2 '
<1.5
<4.7
<8.9
'<1.2 80p16
<19
<2. 7
<20
<3.6--
<0.7
<1.2
<1.0
<1.0
<1.7
<3.5
<2.0
<4.9
<8.1
<1.3 130216 43+15
<2.6 11+9
<4.0
<1.3
<1.2
<1.0
<1.0
<1.6
<2.8
<1.8
<4.9
<8.3
<1.3 117Z17
<22
<5 '
16ZS
<4.6 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0 '
<0.7
<0 '
<0.7
<0.9
<1.9
<1.2
<3 '
<6.7
<1.0 106~12 24+9
<2.1
<13
<2.6
<1.1
<0.9
<0.9
<1.0
<1.1
<2 '
<1.4
<4.4
<6.0
<1.2 91+14 14p8
<2. 2
<18
<2.6
<0.3
<0.7
<0.5
<0.7
<1.0
<1.8
<1.1
<3.5
<7.4
<1.0 78pll 22g10
<2 ~ 3
<13
<2.2
<1.5
<1.2
<0.9
<0.8
<1.1
<2 '
<1.5
<4.3
<10.6
<1.3 57gll 23g12
<2.5 12g10
<2.7
<1.4
<1.5
<0-8
<0.9
<0.9
<2.4
<1.7
<5.6
<12.1
<1.1 57~12
<24
<2.6
<20
<2.6
<1.3
<1 ~ 2
<0.9
<1.1
<1.4
<2.9
<1.8
<5.7
<7.4
<1.4 84p14 26~14
<2 '
<18
<5 '
<<-Optional sample location
-73
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES E OFF-SITE STATION
- Results in units of ~ 3~3 g 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95
-Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<1.1
<0.9
<1.0
<1.0
<0.8
<1.9
<1.4.
<4.1
<9.0
<1.4 88+14 17g10
<2.8
<17
<3.4
<0 '
<0.9
<1.2
<1.2
<1 ~ 1
<2 '
<1.6
<4.6
<10.8
<0.9 109+17 26g14
<3.0
<20
<3+2
<1.0
<1.0
<0.7
<1.0
<1.3
<2.9
,<1.4
<4.4
<9.9
<1.3 125+18
<22
<3.8
<17
<4.8
<1.2
<1.4
<1.4
<1.0
<1.8
<3.7
<1.8
<5.9
<10.9
<1.9 60p14 10+9
<2.9
<24
<4.3
<1 ~ 2
<1.3
<1.2
<1.5
<1.5
<3.6
<1.9
<5.9
<9.9
<1.4 125+19 38~15
<2.0
<23
'4.7
<0.9
<1.1
,<1 ~ 2
<0.9
<1.3
<1.5
<1.8
<5.3
<8.9
<1.2 110+14 45+14
<3.9
<20
<4.4 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RU-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.9
<1 ~ 2
<0.9
<0.7
<1.0
<2 '
<1.4
<3.9
<6.5
<1.1 113p14 30~12
<2.8 10'3.0
<1.1
<1.3
<1.1
<0.9
<1.2
<3 '
<1.4
<4.9
<9.3
<1.1 77g13
<18
<1.6
<18
<3.1
<1.0
<0.8
<0.8
<0 '
<1.2
<1.8
<1.3
<4.2
<6.1
<0.9 69gll 18Z9
<2.4
<17
<2.9
<0.6
<1.0
<1.0
<1.0
<1.3
<2.4
<1.6
<5.4
<8.6
<1.4 65+13 16gll
<3 7
<22
<3.1
<0.9
<1.2
<0.8
<0.9
<1.3
<2.6
<1.5
<4.8
<9.?
<1-0 53~12 30+13
<2.4
<18
<4.3
<1.1
<0.8
<0.8
<0.9
<0.9
<1.7
<1.3
<3.8
<7.0
<1.1 86p12 32+11
<2 ~ 2
<16
<3.0
>>-Optional sample location
-74
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP
~ AIR PARTICULATE SAMPLES F OFF-SITE STATION
- Results in units of M 3~m3 ~ 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RU-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.7
<1.0
<0.8
<0.8
<1.0
<2.6
<1.7
<4.2
<6.3
<1.4 96+14 36Z13
<1 ~ 5
<20
<3 '
<0.8
<1.3
<1.1
<1.0
<1.2
<2.6
<1.7
<5.0
<12 '
<0.9 105+17
<21
<4.1
<21
<3 '
<1.0
<1.0
<0.9
<0.8
<1.5
<1.8
<1.2
<4.2
<7 '
<1.3 108+16
<17
<3 '
<17
<4.4
<0.8
<1.0
<1.1
<1.1
<1.4
<3.4
<1.6
<4.0
<11.1
<1.5 65g15
<21
<4.8
<20
<4'.5
<0.6
<1 2
<1.4
<0.8
<2.1
<3+3
<1.9
<5.2
<9.7
<1.5 116+18 18gll
<2.8
<23
<4.8
<0.9
<0.9
<0.6
<1.0
<0.9
<3.4
<1.6
<4.9
<10.8
<1.1 109g16 34pl4
<2.8
<20
<4.5 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 RQ-103 Be-7 K-40 La-140 Ra-226 I-131
<0.5
<1.0
<1.2
<1.0
<1.2
<3.0
<1.6
<4.4
<10.6
<1.3 101~15 14210
<4.0
<20
<4.0
<0.7
<1.5
<1.3
<1.7
<1.5
<3.4
<2.0
<6.7
<15.1
<1.5 95Z16
<31
<4.4
<24
<4.1
<1.0
<0.6
<1.0
<1.0
<1.6
<3.0
'<1. 7
<5.0
<11.8
<1.4 76~13 42p14
<3.1
<20
<4.3
<0.8
<0.9
<0.9
<0.8
<1.3
<2.6
<1.4
<3 '
<10.2
<1.2 56~12
<18
<2 '
<18
<2.6
<0.7
<1.5
<1.2
<1.2
<1.7
<3.0
<1 ~ 9
<5 7
<13.2
<1.2 60p14
<28
<4.6
<22
<4.3
<0.9
<1.0
<0.7
<0.7
<1.0
<2.1
<1.2
<3.4
<7.4
<1.1 70p12
<14
<3 3
<14
<4.0
>>-Optional sample location
-75
TABLE 9 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES G OFF-SITE STATION
- Results in units of M 3~m3 ~ 2 sigma Nuclides January February March April May June Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.7
<0.4
<0.8
<0.8
<1.4
<2 '
<1.3
<3.8
<5 7
<1.2 87~13
<20
<2.6
<17
<2.9
<1.1
<1.2
<1.2
<1 ~ 2
<1.3
<3.4
<1.8
<5.3
<9.4
<1.3 94+15 36~15
<2.8
<24
<3.1
<1.4
<0.8
<0.8
<0.8
<1.7
<2.1
<1.4
<3.9
<8.3
<0.9 102+16
<14
<F 1
<18
<3.8
<1.4
<1.1
<0.9
<1.1
<2.2
<2+7.
<1.5
<5.0
<10.5
<1.3 62+14
<12
<2.8
<21
<4.0
<1.1
<1.1
<1.0
<1.2
<1.5
<3.2
<1.7
<4.8
<8.4
<1.1 100+15 37g14
<2 '
<22
<4.8
<1.2
<1.0
<1.0
<0.9
<1.4
<2. 1
<1.9
<4.9
<8.9
<1.2 118+15 42gl3
<2.6 ll+7
<4.9 Nuclides July August September October November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 I-131
<0.9
<0.7
<0.9
<0.7
<1.0
<2.0
<1.3
<3 '
<7.4
<1.0 104+15 13~8
<1.4
<15
<3.0
<1.0
<1.5
<1.1
<0.8
<1.0
<4.1
<1.5
<4.1
<12.0
<1.4 87gl8 33~19
<3.2
<21
<3+5
<0.5
<0.7
<0.8
<0'8
<1 '
<2.1
<1.4
<4.3
<9.8
<1 '
76i13 17g10
<3.1
<18
<3.5
<1.0
<1.0
<0.9
<1.1
<1.2
<2+7
<1.4
<4.9
<8 '
<1.2 51Zll 20~11
<3.0 14~10
<3.1
<1.3
<1 ~ 2
<1.1
<1.4
<1.7
<2.7
<1.8
<5.2
<9.0
<1.6 68g14
<27
<4.4
<19
<3.6
<0.8
<1.1
<0.9
<1.0
<1 ~ 3
<2.6
<1.5
<4.6
<8.5
<1.1 71gl2 12i10
<6.2
<16
<4.3
<<-Optional sample location
-76
TAHLE l0 NMP/JAF SITE
~ ENVIRORIENZAL CHARCOAL CARTRIDGE SAMPLES - OFF SITE STATIONS I-131 ACZIVITYpCi/m"3 + 2 sigma MEEK END DATE R-1+
R-2+
R-3+
R-4'-5>>
D-2 88/01/12 88/01/19 88/01/26 88/02/02 88/02/09 88/02/16 88/02/23 88/03/01 88/03/08 88/03/15 88/03/22 88/03/29 88/04/05 88/04/12 88/04/19 88/04/26 88/05/03 88/05/10 88/05/17 88/05/24 88/05/31 88/06/07 88/06/14 88/06/21 88/06/28
<0.008
<0.009
<0.007
<0.006
<0.006
. <0.009
<0.007
<0.006
<0.005
<0.007
<0.006
<0.010
<0.009
<0.008
<0.009
<0.006
,<0.008
<0.006
<0.008
<0.008
<0.011
<0.009
<0.008
<0.007
<0.008
<0.009
<0;007
<0.008
<0.009
<0.008
. <0.007
<0.008
<0.007
<0.007
<0.006
<0.006
<0.005
<0.008
<0.006
<0.009
<0.011
<0.008
<0.007
<0.009
<0.009
<0.009
<0.007
<0.008
<0.007
<0.008
<0.010
<0.005
<0.010
<0.019
<0.005
<0.007
<0.008
<0.008
<0.006
<0.006
<0.009
<0.008
<0.007
<0.006
<0.007
<0.008
<0.006
<0.007
<0.009
<0.007
<0.008
<0.008
<0.007
<0.010
<0.006
<0.011
<0.008
<0.008
<0.006
<0.008
<0.006
<0.008
<0.009
<0.008
<0.010
<0.009
<0.010
<0.011
<0.008
<0.008
<0.006
<0.011
<0.012
<0.009
<0.010
<0.007
<0.012
<0.007
<0.009
<0.010
<0.009
<0.006
<0.006
<0.007
<0.008
<0.008
<0.006
<0.005
<0.006
<0.007
<0.005
<0.010
<0.009
<0.008
<0.008
<0.008
<0.009
<0'08
<0.008
<0.008
<0.008
<0.005
<0.009
<0.007
<0.006
<0.007
<0.009
<0.006
<0.006
<0.008
<0.006
<0.005
<0.008
<0.008
<0.008
<0.008
<0.009
<0.007
<0.008
<0.009
<0.008
<0.007
<0;008
<0.007
<0.007
<0.007
<0.010
<0.006
<0.009
<0.008
<0.008
<0.009
<0.008
<0.009
<0.009
<0.009
<0.006
<0.009
<0.009
<0.011
<0.009
<0.007
<0.010
<0.007
<0.008
<0.008
<0.007
<0.009
<0.006
<0.008
<0.008
<0.011
<0.006
<0.009
<0.008
<0.009
<0.009
<0.008
<0.007
<0.007
<0.008
<0.005
<0.008
<0.007
<0.009
<0.007
<0.007
<0.007
<0.008
<0.008
<0;007
<0.008
<0.007
<0.008
<0.006
<0.008
<0.007
<0.009
<0.011
<0.009
<0.009
<0.006
<0.008'0.009
<0.009
<0.009
<0.007
<0.007
<0.007
<0.010
<0.008
<0.004
<0.008
<0.009
<0.007
<0.008
<0.008
<0.009
<0.008
<0.010
<0.009
<0.007
<0;007
<0.008
<0.008 Technical Specification Location
-77
TABLE 10 (Continued)
NMP/JAF SITE ENVIRONMENTAL CHARCOAL GQG'RIDGE SAMPLES - OFF SITE STATIONS I-131 ACTIVITYpCi/m"3 + 2 signa IOCATION WEEK END DATE R-l.+
R-2 R-3 R-.4 R-5 D-2 F
G 88/07/05 88/07/12 88/07/19 88/07/26 88/08/02 88/08/09 88/08/16 88/08/23 88/08/30 88/09/06 88/09/13 88/09/20 88/09/27 88/10/04 88/10/11 88/10/18 88/10/25 88/ll/Ol 88/11/08 88/11/15 88/11/22 88/11/29 88/12/05 88/12/12 88/12/19 88/12/27 89/Ol/03
<0.008
<0.010
<0.008
<0.011
<0.007
<0.006
<0.007
<0.008
<0.012
<0.007
<0.010
<0.007
<0.011
<0.012
<0.010
<0.009
<0.008
<0.008
<0.008
<0.009
<0.011
<0.006
<0.009
<0.009
<0.008
<0.010
<0.010
<0.008
<0.010
<0.008
<0.008
<0.009
<0.006
<0.008
<0.010
<0.009
<0.007
<0.008
<0.010
<0.009
<0.007
<0.009
<0.008
<0.009
<0.008
<0.007
<0.008
<0.009
<0.006
<0.008
<0.008
<0.006
<0.008
<0.006
<0.007
<0.008
<0.010
<0.008
<0.009
<0.007
<0.011
<0.010
<0.006
<0.007
<0.008
<0.006
<0.011
<0.008
<0.008
<0.008
<0.011
<0.012
<0.007
<0.006
<0.006
<0.012
<0.006
<O.oil
<0.007
<0.006
<0.006
<0. 008
<0.009
<0.011
<0.009
<0.009
<0.008
<0.008
<0.008
<0.010
<0.011
<0.006
<0.009
<0.'008
<0.008
<0.009
<0.006
<0.006
<0.009
<0.009
<0.008
<0.011
<0.008
<0.007
<0.008
<0.009
<0.011
<0.007
'0.008
<0.011
<0.010
<0.009
<0.007
<0.008
<0.009
<0.009
<0.012
<0.009
<0.007
<0.010
<0.012
<0.011
<0.008
<0.008
<0.009
<0.009
<0.009
<0.005
<0.010
<0.008
<0.008
<0.006
<0.010
<0.010
<0.008.
<0.007
<0.008
<0.009
<0.011
'<0.006
<0.008
<0.010
<0.009
<0.009
<0.009
<0.009
<0.009
<0.005
<0.006
<0.007
<0.009
<0.007
<0.007
<0.007
<0.006
<0.009
<0;009
<0.010
<0.009
<0.008
<0..009
<0.016
<0.007
<0.007
<0.007
<0.010
'<0.009
<0.009
<0.007
<0.008
<0.006
<0.010
<0.010
<0.009
<0.008
<0.008
<0.009
<0.007
<0. 010
<0.007
<0.009
<0.008
<0.009
<0.006
<0.007
<0.008
<0.009
<0.010
<0.010
<0.008
<0.011
<0.011
<0.005
<0.008
<0.009
<0.008
<0.007
<0.010
<0.012
<0;005
<0.010
-<0.012
<0.059
<0.010
<0.010
<0.010
<0.009
<0.008
<0.009
<0.010
<0.007
<0.007
<0.010
<0.011
<0.009
<0.009
<0.008
<0.012
<0.007
<0.007.
<0.007
<0.007
<0.011
<0.010
<0.010
<0.008
<0.008
<0.009
<0.007
<0.010
<0.008
<0.010
<0.010
<0.008
<0.011
<0.007
<0.009
<0.009
<0.008
<0.008
<0.005
<0.008
<0.008 Technical Specification Location
TAELE 11 RP/JAF SITE ENVIRONMEZZAL CHARCOAL CARTfHDGE SAMPLES - ON SITE STATIONS I-131 ACTIVITYpCi/m"3 + 2 signa LOCATION WEEK END DATE Dl-ON G--ON H--ON I
ON K--ON 88/Ol/ll 88/01/18 88/01/25 88/02/01 88/02/08 88/02/16 88/02/22 88/02/29 88/03/07 88/03/14 88/03/21 88/03/28 88/04/04 88/04/11 88/04/18 88/04/25 88/05/02 88/05/09 88/05/16 88/05/23 88/05/31 88/06/06 88/06/13 88/06/20 88/06/27
<0.009
<0.008
<0.006
<0.010
<0.006
<0.008
<0.008
<0.008
<0.009
<0.007
<0.008
<0.008
<0.005
<0.005
<0.009
<0.006
<0.008
<0.006
<0.010
<0.012
<0.008
<0.013
<0.009
<0.007
<0.008
<0.,008
<0.008
<0.008
<0.008
<0.009
<0.006
<0.008
<0.007
<0.007
<0.006
<0.007
<0.007
<0.009
<0.008
<0.012
<0.008
<0.006
<0.009
<0.010
<0.007
<0.008
<0.008
<0.008
<0.008
<0.009
<0.009
<0.007
<0.011
<0.009
<0.011
<0.008
<0.012
<0.009
<0.009
<0.008
<0.009
<0.008
<0.008
<0.009
<0.009
<0.008
<0.010
<0.009
<0.012
<0.006
<0.007
<0.009 0.01&0.007
<0.009
<0.010
<0.011
<0.006
<0.008
<0.011
<0.007
<0.008
<0.012
<0.007
<0.008
<0.013
<0.010
<0.010
<0.008
<0.008
<0.006
<0.009
<0.011.
<0.008
<0.007
<0;007
<0.005
<0.011
<0.010
<0.012
<0.011
<0.007
<0.008
<0.010
<0.008
<0.010
<0.005
<0.007
<0.006
<0.006
<0.007
<0.008
<0.011
<0.011
<0.006
<0.013
<0.009
<0.007
<0.008
<0.004
<0.007
.<0.009
<0.012
<0.012
<0.008
<0.006
<0.009
<0.007
<0.011
<0.010
<0.012
<0.008
<0.024
<0.009
<0.007
<0.010
<0.012
<0.010
<4.008
<0.010
<0.010
<0.008
<0.011
<0.010
<0.008
<0.009
<0.008
<0.011
<0.010
<0.009
<0.010 79
TAB E 11 (Continued)
NMP/JAF SITE ENVIRONMEMZALCHARCOAL CARTRIDGE SAMPLES - ON SITE STATIONS I-131 ACTIVITYpCi/in"3 + 2 signa LOCATION Dl-ON G
ON H--ON I--ON J--ON K--ON 88/07/05 88/07/11 88/07/18 88/07/25 88/08/01 88/08/08 88/08/15 88/08/22 88/08/29 88/09/06 88/09/12 88/09/19 88/09/26 88/10/03 88/10/10 88/10/17 88/10/24 88/10/31 88/11/07 88/11/14 88/11/21 88/11/28 88/12/06 88/12/13 88/12/20 88/12/27 89/01/03
<0.009
<0.009
<0.008
<0.016
<0.007
<0.006
<0.008
<0.009
<0.012
<0.008
<0.006
<0.011
<0.011
<0.010
<0.010
<0.014
<0.014
<0.023
<0.009
<0.009
<0.009
<0.008
<0.007
<0.008
<0.010
<0.010
<0.007
<0.007
<0.009
<0.011
<0.010
<0.007
<0.009
<0.007
<0.008
<0.008
<0.008
<0.012
<0.007
<0.008
<0.007
<0.008
<0.008
<0.008
<0.008
<0.007
<0.008
<0.008
<0.010
<0.007
<0.008
<0.010
<0.008
<0.009
<0.009
<0.010
<0.010
<0.010
<0.009
<0.009
<0.010
<0.007
<0.006
<0.009
<0.008
<0.008
<0.004
<0.011
<0.007
<0.011
<0.012
<0.008
<0.008
<0.010
<0.009
<0.006
<0.008
<0.011
<0.006
<0.007
<0.006
<0.011
<0.011
<0.011
<0.006
<0.010
<0.009
<0.009
<0.008
<0.012
<0.027
<0.020.
<0.013
<0.005
<0.008
<0.008'0.007
<0.009
<0.004
<0.003
<0.012
<0.007
<0.006
<0.005
<0.009
<0.007.
<0.009
<0.009
<0.010
<0.011
<0.008
<0.007
<0.006
<0.011
<0.011
<0.007
<0.041
<0.008
<0.009
<0.010
<0.011
<0.010
<0.010
<0.014
<0.013
<0.009
<0.008
<0.007
<0.010
<0.008
<0.007
<0.006
<0.007
<0.011
<0.004
<0.012
<0.013
<0.007
<0.011
<0.009
<0.008
<0.008
~ <0; 008
<0.008
<0.008
<0.008
<0.007
<0.008
<0.006
<0.009
<0.008
<0.010
<0.007
<0.008
<0.009
<0.011
<0.007
<0.006
<0.008
<0.008
<0.009
<0.010
TABLE 12A DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month g 2 sigma Location Number Location 1988 January Through March April Through June July October Location Through Through (Direction and September December (Distance)(3) 3 4
5 6
7*
8 9
10 11 12 13 14*
15*
18*
19 23*
24 25 26 27 28 29 Dl On Site D2 On Site E On Site F On Site G On Site R-5 Off Site-Control Dl Off Site D2 Off Site E Off Site F Off Site G Off Site DeMass Rd.,
SW Oswego-Control Pole 66, W. Boundary-Bible Camp Energy Info. Center Lamp Post, SW.
East Boundary-JAF, Pole 9
H On Site I On Site J On Site K On Site N. Fence, N. of Switchyard, JAF N. Light Pole, N. of Screenhouse, JAF N. Fence, N. of W. Side Screenhouse, JAF 11.3Z0.9 5.8Z0.3 5.3~0.5 4.9Z0.3 4.620.2 5.8+0.3 5.2.3 5.0g0.1 4.8~.1 4.8~.1 5;OH.1 5.0~. 2 4.820.1 5.1.
2 5.7~0.2 6.2'.4 4.620.4 5.3+0.3 5.0+0.3 16.2~2.4-21.725.0 29.826.3 11.9gl.l 5.5+0.5 4.620.5 5.4'.3 4.4+0.2 6.120.4 4;520.2 4.3'.3 4.220.2 4.4'.5 5.0H.3 4.8+0.3 3.920.2 4.620.3 5.020.2 6.220.4 5.lg0.5 4.7+0.4 4.820.3 20.2i3.8 28.327.5 40.4~9.0 10.3+1.4 7.1+0.7 6.8+0.5 6.2+0.3 5.8+0.3
- 6. 6+0. 3 5.7Z0.4 6.0Z0.2 6.2.3 6.0~.2
- 6. 2+0. 2
- 6. 2+0. 3 5.020.2 6.0Z0.6 7.2+0.7
- 7. 2.4 6.6+0.5 5.2+0.6 6.420.4 15.9g2.1 19.624.0 31.6'.5 5.4Z0.5 5.820.5 6.3+0.6 4.7+0.4 4.920.2
- 6. 2.
6 5.4+0.4 5.6+0.4 6.0Z0.4 5.6+0.5 5.8+0.4 5.8+0.4 4.6~.2
- 6. 2H.4 5.6H.4 6.0~. 3 6.0.5
- 5. 3+0.5 5.4+0.3 8.0+1.0 29.2'.4 11.7g2.6 0.2 miles 0.4 miles 0.4 miles 0.5 miles 0.7 miles 16.4 miles 11.4 miles 9.0 miles 7.2 miles 7.7 miles 5.3 miles 12.6 miles 0.9 miles 0.4 miles 1.3 miles 0.8 miles 0.8 miles 0.9 miles 0.5 miles 0.4 miles 0.5 miles 0.5 miles 8
69' 140' 175' 210' 250' 42' 80' 117' 160' 190' 225' 226' 237' 265' 81' 70' 98' 110'-132' 60' 68' 65'81
TABLE 12A (Continued)
DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month g 2 sigma Location Number Location January 1988 Through March April Through June July October Through Through September December Location (Direction and (Distance)(3) 30 31 39 47 49*
51 52 53 54 55 56*
58*
75*
76*
77*
78*
79*
80*
81*
82*
83*
N. Fence (NW) JAF N. Fence (NW) NMP-1 N. Fence, Rad Waste, NMP-1 N. Fence, NE, JAF Phoenix, NY-Control Liberty & Bronson Sts.,
E of OSS East 12th
& Cayuga Sts.,
Osw. School Broadwell
& Chestnut Sts.,
Fulton H.S.
Liberty St.,
& Co. Rte.
16, Mexico H.S.
Gas Substation
& Co. Rt.
5 Pulaski Rt.
104 New Haven Sch.
(SE Corner)
Co. Rt.
1A Alcan (E. of E. Entrance Rd.)
Unit 2, N. Fence,'.
of Reactor Bldg.
Unit 2, N. Fence, N. of Change House Unit 2, N. Fence, N. of Pipe Bldg.
JAF, E. of E. Old Lay Down Area Co. Rt. 29, Pole 863, 0.2 mi. S. of Lake Rd.
Co. Rt. 29, Pole 054, 0.7 mi. S. of Lake Rd.
Miner Rd., Pole f316, 0.5 mi.
W. of Rt.
29 Miner Rd., Pole 81 1/2, 1.1 mi. W. of Rt.
29 Lakeview Rd., Tree, 0.45 mi. N. of Miner Rd.
- 13. 5+1. 2 8.4+0.9 11.6+1.6 9.821.1 4.820.2 5.2'. 2 5.4+0.4 5.3+0.3 4.5+0.2 5.020.2 4.820.1 5.6+0.2 5.5Z0.4 6.020.4 6.8+0.3 5.5+0.2 5.0g0.1 5.020.2 5.020.2 5.0Z0.1 4.820.1 16.2+2.3 8.1+0.8 12.8+1.4 11.0pl.8 5.0Z0.2 4.620.2 5.0+0.1 5.2+0.1 4.,2+0.2 4.4'.2 4.9'.3 4.8+0.2 5.220.5 5.620.3 6.4+0.4 5.820.4 4.620.2 3.4Z0.1 4.9+0.2 4.420.2 4.2+0.3
- 12. 2gl. 2 8.8+0.7 13.4+1.5 11.4+1.7 6.8+0.3 5.620.3 6.4+0.5 6.5+0.4 6.120.4 5.920.2 5.820.2 6.020.3 6.620.6 6.7+0.2 7.5+0.4 7.0Z0.3 6.0+0.5 6.5+0.2 6.420.3 5.9+0.5 6.7+0.3 6.9+0.6 7.8+0.8 12.021.3 6.8+0.6 5.0~0.3 5.3'.3 5.6+0.4 5.2+0.3 5.2'.2 5.620.4 5.4~0.3 5.420.2 5.220.2 5.620.3 6.2%0.4 6.020.3 5.820.2 5.020.2 5.020.2 5.620.3 5.0+0.3 0.4 miles 0.2 miles 0.2 miles 0.6,miles 19.8 miles 7.4 miles 5.8 miles 13.7 miles 9.3 miles 13.0 miles 5.3 miles 3.1 miles 0.1 miles 0.1 miles 0.2 miles 1.0 miles 1.1 miles 1.4 miles 1.6 miles 1.6 miles 1.2 miles 9
57' 276' 292' 69' 170' 233' 227' 183' 115' 75'.
9 123' 220' 5o 9
25' 454 8
90' 115' 133' 159' 181' 200'
TABLE 12A (Continued)
DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month g.2 sigma Location Number Location January 1988 Through March April Through June July Through September October Through December Location (Direction and (Distance)(3) 84*
Lakeview Rd. N., Pole 86117, 200 Ft.
N. of Lake Rd.
85*
Unit 1, N. Fence, N. of W. Side of Screen House 86*
Unit 2, N. Fence, N. of W. Side of Screen
.House 87*
Unit 2, N. Fence, N. of E. Side of Screen House 88*
Hickory Grove Rd., Pole 82, 0.6 mi.
N. of Rt.
1 Leavitt Rd., Pole 816, 0.4 mi. S. of Rt.
1 Rt. 104, Pole 8300, 150 Ft. E. of Keefe Rd.
Rt. 51A, Pole 859, 0.8 mi.
W. of Rt.
51 Maiden Lane Rd.,
Power Pole, 0.6 mi.,
S. of Rt.
104 93*
Rt. 53, Pole 1-1, 120 Ft. S. of 104 94*
Rt. 1, Pole 882, 250 ft. E'. of Kocher Rd.
95*
Lakeshore Camp Site, From Alcan W.
Access Rd., Pole 821, 1.2 mi. N. of Rt.
1 96*
Creamery Rd., 0.3 mi.
S of Middle Rd.,
Pole 1 1/2 97*
Rt. 29, Env. Station R4, 200 Ft. N.
of Miner Rd.
98*
Lake Rd., Pole 8145, 0.15 mi. E. of Rt.
29 5.220.2 15.621.7 7.0~.6 6.3+0.8 5.420. 2 5.620.3 5.0Z0.2 5.0+0.2 5.4+0.2 5.620.3 5.4'.1 4.820.1 5.2+0.2 5.420.2 5.6+0.2 5.0+0.8 15.8+1.6 6.4+0.5 6.0'.5 4.820.2 4.8+0.3 4.4+0.3 4.120.1 4.820.2 4.320.2 4.220.2 3.8+O.l I
4.420.2 4.420. 2 5.0+0. 3 6.8+0.4 17.9+1.5 8.4+0.7 7.620.8 6.6+0.2 6.8+0.2 6.2+0.5 6.220.2 7.0'.5 5.9Z0.3 6.0+0.4 5.6+0.2 6.2~0.2 6.2+0.2 6.6+0.4 5.6+0.3 15.4+1.5 6.4+0.7 5.820.5
- 5. 2+0. 3 6.0+0.4 5.6+1.0 5.0+0.4 6.3~.3 5.3+0. 2 5.0+0. 2 5.0+0.2 5.920.2
- 5. 7+0.3 5.8+0.2 1.1.miles 9
225'.2 miles 9 294'.1 miles 9 315'.l miles 8 341'.8 miles 4.1 miles 4.2 miles 4.8 miles 8
97 9 ill' 135' 156 1.8 miles 9 143'.2 miles 9 101'.4 miles 9 183'.4 miles 9 205'.7 miles 9 223'.1 miles 9 237'.6 miles 8 199'83
TABLE 12A (Continued)
DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/standard month p 2 sigma Location Number Location January
-1988 Through March April Through June July October Through Through September December Location (Direction and (Distance)(3) 99 100 101 102 103 104 105 106 107 108 109 110ill NMP Rd., 0.4 miles N. of Lake Rd., Env.
Station Rl Off-Site Rt.
29 and Lake Rd., Env. Station R2 Off-Site Rt. 29, 0.7 mi. S. of Lake Rd., Env.
Station R3 Off-Site EOF/Env. Lab, Oswego Co. Airport (Fulton Airport), Rt. 176, E. Driveway Lamp Post EIC, East Garage Rd.,
Lamp Post.'arkhurst
- Road, Pole 148 1/2-A, 0.1 mi.
S. of Lake Rd.
Lakeview Road, Pole 6125, 0.6 mi. S. of Lake Rd.
Shoreline
- Cove, E. of NMP-1, Tree on W.
Edge Shoreline
- Cove, E. of NMP-l, Tree 30 ft. South of TLD 8106 Lake Rd. Pole 8142 300'ast of County Route 29 (S)
Lake Rd. Tree 300'ast of County Route 29(N)
Baldwinsville, NY Control Volza Residence
- Sterling, NY - Control Blasiak Residence 5.620.2 5.4+0.1
- 4. 9~. 2 5.6+0.3 5.6+0.1 5.4+0. 2 5.0.1 6.6+0.4 6.2+0.4 (2)
(2)
(2)
(2) 4.620.2 4.2.2
- 4. 2H. 2 4.6'.2
- 5. 3~. 3 5.0+0.2 4.8H.2 5.220.3 5.220.3 4.8+0.2 5.0Z0.3 4.4+0.2 4.7'.2 6.2+0.5 6.4+0.4
- 6. 7.4 5.8+0.5 6.0H.4 6.5~. 2
- 6. 3.
2
- 7. 2+0. 3 6.620.4 6.620.5 5.8+0.4 5.6~.2 5.8+0.3 5.4.2 5.2~.2 5.020.2 6.0Z0.2 5.5+0.3 5.8+0.3 5.2~0.6 6.420.3 5.620.4 6.020.4 5.6~.4 5.320.2 6.0H. 3 1.8 miles 8 88'.1 miles 1.5 miles 8 104' 132'1.9 miles 8 175'.4 miles 8 267'.4 miles 8 102'.4 miles 9 198'.3 miles 8 274'.3 miles 8 272'.1 miles 9 104'.1 miles 9 103'6.4 miles 9 166'1.8 miles 9 214'1)
(2)
(3)
(4)
TLD lost in field.
TLD not established during the quarterly period.
Direction and distance based on NMP-2 reactor centerline and sixteen 22.5'ector grid.
TLD deleted.
Technical Specification location.
TABLE 12B DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period + 2 sigma Location Number Location 1988 January Through March April Through June July October Through Through September December Location (Direction and (Distance)(3) 3 Dl On Site 4
D2 On Site 5
E On Site 6
F On Site 7*
G On Site 8
R-5 Off Site-Control 9
Dl Off Site 10 D2 Off Site 11 E Off Site 12 F Off Site 13 G Off Site 14*
DeMass Rd, SW Oswego-Control 15*
Pole 66, W. Boundary-Bible Camp 18*
Energy Info. Center-Lamp Post, SW 19 East Boundary-JAF, Pole 9
23*
H On Site 24 I On Site 25 J On Site 26 K On Site 27 N. Fence, N. of Switchyard, JAF 28 N. Light Pole, N. of Screenhouse,JAF 34.4+1.4 17.820.5 16.1Z0.8 14.7H.5 14.1Z0.2 17.220.4 15.3+0.5 14.920.2 14.420.2 14.5H.2 15.0H.2 14.9Z0.3 14.3Z0.1 15.4~0.4 17.220.2 19.220.5 14.020.6 16.2+0.5 15.3+0.4 48.3i3.6 65.027.5 34.9~1.6 16.2~0.7 13.520.8 16.2'.4 13.1+0.4 18.2~0.6 13.7'.4
'2.920.4 12.420.4 13.3Z0.7 15.0+0.5 14.520.5 11.6Z0.4 14.0g0.5 15.220.3 18.6Z0.6 15.3+0.7 14.120.5 14.120.5 60.8+5.7 84.9+11.2 31.6Z2.1 21.7Z1.0 20.920.7 18.820.5 17.6+0.4 20.4+0.4 17.2~0.5 18.220.3 19.120.6 18.3+0.3 18.920.4 18.820.5 15.0+0.3 18.0Z0.8 21.5Zl.l 21.6~0.7 19.7%0.8 15.620.8 19.7+0.7 48.123.3 59.226.0 16.1.8 17.420.8 19.0+0.9 14.1.6 14.7+0.3 18.4.8 16.4Z0.6 16.520.6 17.520.6.
16.420.7 17.420.6 17.420.6 13.6.3 18.320.7 16.6~0.5 18.120.4
'7.820.7 15.8%0.8 16.1+0.5'5.8+1.6 93.2~5.4 0.2 miles 9 0.4 miles 9 0.4 miles 8 0.5 miles 9 0.7 miles 9 16.4 miles 8 11.4 miles 9 9.0 miles 8 7.2 miles 8 7.7 miles 8 5.3 miles 8 12.6 miles 8 0.9 miles 8 0.4 miles 9 1.3 miles 9 0.8 miles 9 0.8 miles 8 0.9 miles 9 0.5 miles 9 0.4 miles 9 0.5 miles 9 69'40'75'10'50'2'0'17'60'90 225'26'37'65'1'0'8'10'32'0'8'85
TABLE 12B (Continued)
DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period + 2 sigma Location Number Location January 1988 Through March April Through June July October Through Through September December Location (Direction and-(Distance)(3) 29 N. Fence, N. of W. Side Screenhouse, JAF 30 N Fence (NW) JAF 31 N. Fence (NW) NMP-1 39 N. Fence, Rad.
- Waste, NMP-1 47 N. Fence, NE, JAF 49*
Phoenix, NY-Control 51 Liberty 6 Bronson Sts.,
E. of OSS 52 East 12th 6 Cayuga Sts.,
Osw. School 53 Broadwell
& Chestnut Sts.,
Fulton H.S.
54 Liberty St.
G Co. Rt. 16, Mexico H.S.
55 Gas Substation, Co. Rt. 5, Pulaski 56*
Rt. 104 New Haven Sch.
(SE Corner) 58*
Co. Rt.
1A Alcan (E. of Entrance Rd.)
75*
Unit 2, N. Fence, N. of Reactor Bldg.
76*
Unit 2, N. Fence, N. of Change House 77*
Unit 2, N. Fence, N. of Pipe Bldg.
78*
JAF, E. of E. Old Laydown Area 79*
Co. Rt. 29, Pole 863, 0.2 mi. S. of Lake Rd.
80*
Co. Rt. 29, Pole 854, 0.7 mi. S. of Lake Rd.
81*
Miner Rd., Pole 816, 0.5 mi. W. of Rt.
29 82*
Miner Rd., Pole 8 1 1/2, 1.1 mi.
W. of Rt.
29 89.129.4 40.4Z1.9 25.0+1.3 34.8g2.4 29.1~1.8 14.220.4 15.8+0.2 16.2+0.6 15.9+0.4 13.6.4 14.720.2 14.1+0.2 16.6+0.3 16.3+0.6 17.6+0.6 20.420.5 16.6Z0.3 15.0+0.2 15.020.3 15.2'.2 15.2Z0.2 121.3Z13.6 48.723.4 23.8+1.1 37.6+2.0 33.022.8 15.320.2 13.820.2 14.8+0.2 15.5+0.2 12.8+0.2 13.2+0.3 14.9'.4 14.4+0.3 15.2~.6 16.6'.5 18.6+0.6 17.6+0.5 13.6+0.4 14.0+0.3 14.8+0.4 13.220.3 95.9Z6.7 37.021.8 27.4+1.1 41.8+2.3 34.0+2.5 20.2~0.4 17.020.5 19.420.8 19.720.5 18.6~.6 17.9+0.3 17.6+0.3 18.4~.5 20.6~0.9 20.8'.3 23.520.5 21.2~0.5 18.3~.7 19.6+0.4 19.2+0.5 17.8~0.8 37.2Z4.1 22.0Z1.0 23.1gl.2 35.621.9 21.9~.9 14.8H.5 15.8~.5 16.4~.6 15.8.4 15.4.4 16.4+0.6 16.2.5 16.1~.4 15.5~.4 16.720.4 18.3.6 17.820.4 17.3Z0.3 14.8+0.3 15.0+0.3 16.9+0.5 0.5 miles 0.4 miles 0.2 miles 0.2 miles 0.6 miles 19.8 miles 7.4 miles 5.8 miles 13.7 miles 9.3 miles 13.0 miles 5.3 miles 3.1 miles 0.1 miles 0.1 miles 0.2 miles 1.0 miles 1.1 miles 1.4 miles 1.6 miles 1.6 miles 9
65' 57' 276' 292' 69' 170' 233' 227' 183' 115' 75' 123' 220' 50 8
25' 45' 90' 9 115' 133' 159' 181'
TABLE 12B (Continued)
DIRECT RADIATION-MEASUREMENT RESULTS Results in units of mrem/quarterly period
+ 2 sigma Location Number Location January 1988 Through March April Through June July October Through Through September December Location (Direction and (Distance)(3) 83*
84*
85*
86*
87*
88*
89*
90%
9]*
92*
93*
94*
95*
96*
Lakeview Rd., Tree, 0.45 mi. N. of Miner Rd.
Lakeview Rd., N., Pole 8 6117, 200 Ft.
N. of Lake Rd.
Unit 1, N. Fence, N. of W. Side of Screen House Unit 2, N. Fence, N. of W. Side of Screen House Unit 2, N. Fence, N. Of E. Side of Screen House Hickory Grove Rd., Pole 82, 0.6 mi. N.
of Rt.
1 Leavitt Rd., Pole 816, 0.4 mi. S. of Rt.
1 Rt. 104, Pole 8300, 150 Ft. E. of Keefe Rd.
Rt. 51A, Pole 859, 0.8 mi. W. of Rt. 51 Maiden Lane Rd.,
Power Pole, 0.6 mi. S.
of Rt.
104 Rt. 53, Pole 1-1, 120 Ft. S. of Rt.
104 Rt. 1, Pole 882, 250 Ft. E. of Kocher Rd.
Lakeshore Camp Site, From Alcan W. Access Rd., Pole 821, 1.2 mi. N. of Rt.
1 Creamery Rd., 0.3mi.
S. of Middle Rd.,
Pole 1 1/2 14.5+0.2 15.8+0.3 46.8+2.6 12.8+0.4 15.0+1.1 46.5+2.3 18.8+1.1 17.6Z0.8 16.0Z0.4 16.820.4 15.0+0.2 15.0Z0.3 14.6+0.4 14.2+0.4 13.4+0.4 12.4i0.2 16.3Z0.2 16.8+0.4 16.2+0.2 14.620.4 12.8Z0.2 12.6+0.3 14.420.2 15.6+0.3 11.6Z0.2 13.3~.4 20.9+0.8 18.7Z0.8 20.0+0.4 20.4.6 55.8+2.3 26.2+1.1 23.7~1.2 19.820.3 20.6+0.4 18.920.7 18,.6Z0.3 21.4Z0.8 17.820.4 18.2~0.6 17.2+0.3 18.8+0.3 14.8~.4 16.8'.4 45.4g2. 1 19.1~1.1 17.3+0.7 15.620.4 17.820.5 16.6Z1.5 15.020.6 18.920.5 16.0~0.4 14.820.4 14.820.4 17.820.3 1.2 miles 8 200'.1 miles 8 225'.2 miles 9 294'.1 miles 9 315'.1 miles 8 341'.8 miles.9 97'.1 miles 9 111'.2 miles 8 135'.8 miles 9 156'.4 miles 8 183'.4 miles 9 205'.7 miles 9 223'.1 miles 9 237'.6 miles 9 199'87
TABLE 12B (Continued)
DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem/quarterly period + 2 sigma Location Number Location January 1988 Through March April Through June July October Through Through September December Location (Direction and
'Distance)(3) 97*
98*
99 100 101 102 103 104 105 106 107 108 109 110 111 Rt. 29, Env. Station R4, 200 Ft. N, of Miner Rd.
Lake Rd., Pole 8145, 0.15 mi. E. of Rt.
29 NMP Rd., 0.4 miles N. of Lake Rd., Env.
Station Rl Off-Site Rt.
29 and Lake Rd., Env. Station R2 Off-Site Rt. 29, 07 mi. S. of Lake Rd.,
Env. Station R3 Off-Site EOF/Env. Lab, Oswego Co. Airport (Fulton Airport), Rt. 176, E. Driveway Lamp Post EIC, East Garage.Rd.,
Lamp Post Parkhurst
- Road, Pole 148 1/2-A, 0.1 mi.
S. of Lake Rd.
Lakeview Road, Pole 6125, 0.6 mi. S. of Lake Rd.
Shoreline
- Cove, E. of'NMP-1, Tree on West Edge Shoreline
- Cove, E. of NMP-l, Tree 30 ft. South of TLD 8106 Lake Rd. Pole 8142 300'ast of County Route 29 (S)
Lake Rd. Tree 300'ast of County Route 29(N)
Baldwinsville, NY Control Volza Residence
- Sterling, NY Control Blasiak Residence 16.2'.2 16.8~0.3 16.8~0.3 16.4+0.2 14.8+0.3 17.0+0.4 17.2+0.2 16.0+0.2 15.0H.3 20.0+0.6 19.1+0.7 (2)
(2)
(.2)
(2) 13.0~0.3 14.820.4 13.6+0.4 14.9+0.4 12.6.2 13.6+0.2 15.8+0.4
- 15. 0.
3 14.6H.3
'5.4+0.5 15.4+0.5 14.220.4 15.0Z0.5 13.020.2 14.1~.3 18.6+0.3 20.0~0.6 18.6~0.7 19.4+0.6 17.2Z0.4 17.4+0.3 16.2.3 15.4Z0.4 17.6ZO.S 18.4+0.5 19.5+0.3 18.920.3 21.6Z0.5 19.8+0.5 19.620.7 17.420.6 16.8'.3 17.4Z0.4 18.0~0.4 16.4.4 17.4~0.5 15.620.9 19.320.5 16.8Z0.5 17.8+0.5 16.8Z0.6 15.620.4 17.620.4 20.2~0.6 14.8~0.3 1.8 miles 8 143'.2 miles 8 101'.8 miles 8 88'.1 miles 8 104'.5 miles.g 132'1.9 miles 9 175'.4 miles 9 267'.4 miles 9 102'.4 miles 8 198'.3 miles 9 274'.3 miles 8 272'.1 miles 9 104'.1 miles 8 103'6.4 miles 9 166'1.8 miles 8 214'1)
(2)
(3)
(4)*
TLD lost in the field.
TLD not established during the quarterly period.
Direction and distance based on NMP-2 reactor centerline TLD deleted.
Technical Specification location and sixteen 22.5'ector grid.
TABLE 13 CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter Z 2 sigma Location Nuclides 4-4-88 4-18-88 5-2-88 5-16-88 6-6-88 6-20-88 60 55 50 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1490Z162
<6.5
<6.7
<4.6 152~75
<LLD 1500+187
<5.4
<7.1
<5.8
<160
<LLD 1450+136
<5.1
<5.2
<4.0
<130
<LLD 1680+141
<5.3
<5.2
<3.7
<149
<LLD 1710pl40
<5.4
<5.7
<5.8
<160
<LLD 1500Zl'41
<5.2
<5.8
<4.7
<127
<LLD 1450+162
<6.3.
<8.3
<7.9
<189
<LLD 1370+176
<6.4
<7.6
<6.9
<153
<LLD 1360p191
<6:0
<7.4
<6.5
<186
<LLD 1160Z167
<7.5
<7.8
<6.2
<184
<LLD 1480Z136
<5.0
<5 '
<5.0
<135
<LLQ 1550Z133
<5.3
<6.1
<5 ~ 7
<151
<LLD 1640p169
<6.4
<6.3
<3.2'32+138
<LLD 1500+139
<4.2
<6.0
<5.6
<139 (1) 1360+187
<6.5
<8.9
<9.5
<192.
<LLD 1540+180
<7.2
<9.4
<6.8 231+116
<LLD 14402158
<6.6
<7.8
<6.1
<181
<LLD 1420Z136
<4.8'5.6
<4.7 f3Z64
<LLD 1360p150
<6.1
<7.5
<8.5 150+73
<LLD 928p227
<6.8
<8.0
<4.8 183t97
<LLD 1570+131
<5.2
<6.4
<3.6
<146
<LLD 1440+136
<4.5
<5.2
<6.0 93+54
<LLD 1500Z177
<7.9
<8.8
<8.1
<198
<LLD 1510+136
<5.6
<6.0
<3.4
<141
<LLD (1) AcTh-228 found at a concentration of 14.0~9.9 pCi/liter.
were less than LLD for this sample.
-89 All other radionuclides
TABLE 13 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter g 2 sigma Location Nuclides 4-4-88 4-18-88 5-2-88 5-16-88 6-6-88 6-20-88 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1360pl33
<5 '
<6.4
<5.8
<126
<LLD 1530+135
<5.6
<6.5
<4.8
<165
<LLD 1370+172
<7.4
<8.5
<8.3
<164
<LLD 513~116
<8.6
<8.4
<10.6
<181
<LLD 1560Z134
<4.9
<6.0
<4.7 132270
<LLD 1530+137
'5
<5.4
<4.8
<136
<LLD 16 65*
(Control)
K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1720p141
<5+5
<6.9
<4.6
<149
<LLD 1520+186
<6.2
<6.4
<6.8
<187
<LLD 1380Z192
<8.5 10.025.9
<3.6 258+176
<LLD 1390Z181
<6.2
<8.0
<5.1
<165
<LLD 1560+204
<8.1
<9.4
<8.0 140+84
<LLD 1710gl39
<5.0
<6.0
<6.0
<160
<LLD 1510+141
<5.2
<7.6
<4.9
<129
<LLD 1530+180
<6.8
<7.9
<5.8
<191
<LLD 1530i141
<4.5
<5.7
<4.7
<134
<LLD 1700Z140
<4.3
<5 ~ 2
<3.7 144g68
<LLD 1360+173
<6.1
<8.9
<5.2
<197
<LLD 1490g161
<6.8
<7.2
<4.5
<199
<LLD
- -Technical Specification location
TABLE 13 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma Location Nuclides 7-5-88 7-18-88 8-8-88 8-22-88 9-6-88 9-19-88 60 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1520+139
<4.9
<5.3
<1.9 162Z87
<LLD 1490Z130
<4.4
<5 '
<4.3
<134
<LLD 1570Z141
<4.9
<5.1
<4.9
<122
<LLD 1320~167
<7 '
<7.6
<6.5
<196
<LLD 1710Z136
<5.2
<5.8
<4.8
<154
<LLD 1660+168
<6.9
<7.4
<7.4
<179
<LLD 55 50 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226
'Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-,140 Ra-226 Others 15302159
<5.8
<6.9
<2.4 151+75
<LLD 1730Z137
<5.4
<5.4
<4.3
<156
<LLD 1440pl34
<4.6
<4.8
<1.8
<135
<LLD 1650+169
-<6.1
<6.2
<4.4
<178
<LLD 1490+159
<5.8
<7.2
<6.3
<168
<LLD 17002137
<5.4
<5.9
<4.1 104i79
<LLD 1700+286
<11.3
<12.7
<13.4
<285
<LLD 1500Z139
<4.5
<5.6
<6.0
<126
<LLD 1450Z125
<4.7
<5.4
<4.0 l37+78
<LLD 1460+137
<4.0
<5.6
<4.2
<124
<LLD 1320Z171
<6.4
<7.8
<7.8
<200
<LLD 1650~250
<9.5
<14.2
<14.0
<237
<LLD 1580254
<2.1
<2.3
<3 '
71g28 (2) 1560+131
<4.5
<5.1
<3'
<150
<LLD 1200+250
<11.8
<14.9
<14.9
<255
<LLD 1620+133
<5.0
<5.4
<4.3
<137
<LLD 1480+127
<4.8
<5.5
<5.0
<144
<LLD 1580il30
<4.7
<5.6
<3.7 90+78
<LLD (2)
AcTh-228 found at a concentration of 6.7~3.4 pCi/liter.
All other radionuclides were less than LLD for this sample.
-91
TABLE 13 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma, Location Nuclides 7-5-88 7-18-88 8-8-88 8-22-88 9-6-88 9-19-88 16 65*
(Control)
K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 C's-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 14702157
<6.4
<6.7
<4.9
<182
<LLD 1550Z181
<6.2
<9.4
<4.3
<213
<LLD 1570pl62
<6.2
<7.4
<6.6
<182
<LLD 1550+128
<5.6
<5.0
<4.8
<141
<LLD 1540Z180
<6.1
<10.3
<5+7
<198
<LLD 1360pl72
<7.9
<8.0
<7.6
<193
<LLD 1330+222
<8.9
<10.7
<14.7
<227
<LLD 1420g201
<7.8
<9.8
<10.8
<210
<LLD 1470+137
<4.9
<5.2
<1.8
<126
<LLD 1380+131
<4.8
<5.2
<5.1
<121
<LLD 1700+135
<6.3
<5.1
<6.4 128+60
<LLD 1600Z163
<5.9
<8.6
<5.9 2312144
<LLD 1520+186
<7.7
<8.8
<6.4
<195
<LLD 15302138
<4.9
<6.5
<4.5
<133
<LLD 1530~160
<6.2
<6.9
<6.3
<179
<LLD 1510Z158
<6.4
<6.8
<7.0
<189
<LLD 1650+166
<7.4
<7.0
<4.5 155Z86
<LLD 1490+178
<7.0
<6.0
<6.0
<185
<LLD
- -Technical Specification location.
TABLE 13 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/liter + 2 sigma Location Nuclides 10-3-88 10-17-88 11-7-88 11-21-88 12-5-88 12-19-88 60 55 50 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1630+131
<5.2
<5.7
<5.0
<149
<LLD 1560pl31
<5.0
<5.7
<5.0
<158
<LLD 1500+137
<5.4
<5.4
<4.6
<126
<LLD 1440+132
<5.0
<4.8
<5.2
<134
<LLD 1520Z140
<4.9
<5.1
<6.0 135~77
<LLD 1520p178
<6.8
<7.8
<7 '
<187
<LLD 1480Z175
<6.7
<7 '
<5.2
<195
<LLD 1520g128
<5.1
<6.1
<4.8
<152
<LLD 1580gl32
<5.4
<5.8
<5.0 150267
<LLD 1480Z156
<6.7
<7.6
<4.5
<194
<LLD 1600g180
<7 '
<7+7
<7.6
<201
<LLD 15502138
<4.7
<4.4
<6.0
<133
<LLD 15002160
<6.8
.<7.8
<3.9
'<185
<LLD 1520~181
<7.8
<8.5
<7.1
<199
<LLD 15302136
<5.3
<5.5
<5.4 105Z69
<LLD 1640+134
<5.0
<6.6
<5 '
<146
<LLD 1320Z128
<5.3
<4.8
<5.5
<126
<LLD 1680~166
<6.9
<7.2
<6.3 152284
<LLD 1720Z138
<4.9
<5.5
<4.3
<142
<LLD 1300+168
<7.5
<9.0
<8.1
<195
<LLD 1410g133
<4.6
<5.0
<4.6
<126
<LLD 1520+131
<5.3
<5.1
<4.1
<151
<LLD 1430+125
<5 ~ 2
<5.8
<4.4
<151
<LLD 1640+186
<7.4
<9.5
<8.1
<204
<LLD
-93
TABLE 13 (Continued)
CONCENTRATION OF GAMMA.EMITTERS IN MILK Results in units of pCi/liter ~ 2 sigma Location Nuclides 10-3-88 10-17-88 11-7-88
'11-21-88 12-5-88 12-19-88 K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1540+163
<6.4
<8.5
<4.4
<199
<LLD 1460Z136
<4.7
<5.5
<4.6
<124
<LLD 1700Z189
<7.. 9
<7 '
<7.0
<203
<LLD 1570~132
<4.9
<6.3
<2.5
<153
<LLD 1720Z136
<4.6
<5.0
<3.6
<142
<LLD 1710p135
<4.9
<6.2
<5.2 162t81
<LLD 16 65*
(Control)
K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others K-40 Cs-134 Cs-137 Ba/La-140 Ra-226 Others 1730+169
<6.4
<8;4
<6.7
<191 (3) 1540pl31
<5.6
<5 ~ 2
<6.3 149289
<LLD 1560~162
<5.9
<7.0
<6.7 194284
<LLD 1560pl81
<7 '
<6.7
<6.6
<185
<LLD 1620Z186
<7.7
<9.2
<5.7
<192
<LLD 15602144
<3.6
<5.6
<4.5
<121
<LLD 1600+132
<5.3
<6.6
<3.8
<162
<LLD 1370+185
<6.4
<8.0
<3.8
<190
<LLD 1570+178
<7.4
<9.1
<8.6 178Z130
<LLD 1610+167
<6.8
<7.0
<7.1
<183
<LLD 1650Z165
<6.2
<8.0
<7.1 86Z71
<LLD 1550+160
<6.7
<6.5
<5.4 180284
<LLD
- -Technical Specification location.
(3) AcTh-228 found at a concentration of 26.7gl4.4 pCi/liter. All other radionuclides were less than LLD for this sample.
TABLE 14 CONCENTRATION OF IODINE 131 IN MILK (1)
Results in units. of pCi/liter ~.2 sigma Location 4-4-88 4-18-88 5-2-88 5-16-88 6-6-88 6-20-88 60 55 50 7
4 16 65*
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
.<0.3
<0.3
<0.3
<0.2
<0.3
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.3
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.4
<0.2
<0.2
<0.3-
<0.2
<0.2 Location 7-5-88 7-18-88 8-8-88 8-22-88 9-6-88 9-19-88 60 55 50 7
16 65*
<0.2
<0.4
<0.2
<0.2
<0.2
<0.2
<0.2
<0.3
<0.2
<0.2
<0.2
<0.3
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.1
<0.2
<0.2
<0.2
<0.3
<0.2
<0.2
<0.2
<0. 2
<0. 2
<0.2
<0.2
<0.2
<0.2
<0.3
<0. 2
<0.2 Control result.
Technical Specification location.
(1) Iodine 131 results are corrected for decay to the sample stop date.
-95
TABLE 14 (Continued)
CONCENTRATION OF IODINE 131 IN MILK (1)
Results in units of pCi/liter g 2 sigma Location 10-3-88 10-17-88 11-7-88 11-21-88 12-5-88 12-19-88 60 55 50 7
4 16 65*
<0.2
<0.2
<0.2
<0.2
<0.3.
<0.2
<0.2
<0.3
<0.2
<0.2
<0.2
<0.3
<0.4
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.3
<0.3
<0.5
<0.2
<0.5
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2 Control result.
Technical Specification location.
(1)
Iodine 131 results are corrected for decay to the sample stop date.
TABLE 15 MILK ANIMAL CENSUS 1988 Scriba New Haven Mexico Richland Pulaski Oswego Hannibal Sterling Volney Number on eau.ms uz(')
1(b) 16*
2 3 (b) 6 (b) 26 (b) 61 (b) 62 8
9 4v'c 45 10(b) 5 11 7*
12 13 14 15 17 18 19 20 60*
50*
55*
21 4
22 24 25 70 66
~g~(3) 220'90'95'90'62'14'40'83' 130'5'13'25'130'46'30'07' 107'14'20'00'15'10'32'23'0'30 95'12' 22 0
182'47'56'
~Dt gg.:(3) 3.0 miles 5.9 8.0 4.5 2.2 1.5 3.0 6.7 9.2 5 '
7.8 8.0 2.6 7.2 8.5 5.5 11.5 11.2 9.8 10.8 10.2 10.0 10.5 11.2 9.5 8.2 9.0 10.5 9.5 9,4 7.8 Number of None 40C ND None 1C ND 1C, 1G(2) 8G(2) 4 30C 40C 90C None 29C 49C 17C 75C 4
21C None 62C 4C 3C'one 42C None 40C 200C 57C 80C G
None
- 20C, 1G(2) 70C 0 MILKING ANIMAL TOTALS:
(including control locations) 1,238 Cows 1,193 Cows (c) 15 Goats (c)
-97
TABLE 15 (Continued)
MILK ANIMAL CENSUS 1988 NOTES:
C =
G =
Yc
- )'C ND =
(1) =
(2) =
(3) =
None=
Cows Goats Milk sample location Milk sample g~t zQ, location Did not wish to participate in the survey References Figure 4
Goat is Ggt currently producing milk or any milk produced is utilized by the owner Degrees and distance are based on NMP-2 Reactor Building centerline.
No cows or goats at that location.
Jocation was a previous location with cows and/or goats.
Census performed out to a distance of approximately ten miles.
Location within five miles (Technical Specification requirement).
Totals excluding control location results.
-98
TABLE 16 1988 RESIDENCE CENSUS Map( )
Meteorological t
t (2)~~t~(2)
Lake Road Lake Road County Route 29 Miner Road Miner Road Lakeview Road Bible Camp Retreat Bible Camp Retreat Vc 1C 1C A
B C
D E
F G
H N
NNE NE ENE E
WNW NW NNW 99'02'30'63'70'07o 234'38'.3 miles 1.1 miles 1.4 miles 1.6 miles 1.6 miles 1.2 miles 0.9 miles 0.9 miles' This meteorological sector is over Lake Ontario.
There is no residence within five miles.
(1) Corresponds to Figure 3.
(2) Based on NMP-2 reactor centerline.
-99
TABLE 17A CONCENTRATION OF GAMMA EMITTERS IN FOOD PRODUCTS Results in units of pCi/g (wet) g 2 sigma Location Sample Date Sample Type Be-7 K-40 I-131 Cs-134 Cs-137 Ra>>226 AcTh-228 Others T
T T
p p
p R
R R
Q>>
J J
J X
X X
8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29>>88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 Cucumber Leaves Beet Greens Pepper Leaves Cabbage Swiss Chard Collard Greens Cucumber Leaves Squash Leaves Bean Leaves Pumpkin Leaves Beet Greens Bean Leaves Swiss Chard Squash Leaves Lettuce Cabbage Bean Leaves Pepper Leaves 0.98'.12 0.10~.04 0.27.07 0.16'.06 0.20+.06 0.27~.06 1.14.09 0.61~.06 0.38.07 3.04H.I3 0.33.06 1.03&.13 0.28+.07 0.98.12 0.17'.05 0.09~.04 0.66.06 0.40.07 2.27.29 5.21'.27 7.37~.31 2.52.22 3.56H.25 2.80+0.20 2.13.18 3.33.19 3.02+.24 3.98d0.23 5.84.30 2.25.31 5.18'.30 2.95+0.33 3.31'.21 1.92+.17 1.39~.14 4.86.32
<0.015
<0.012
<0.013
<0.012
<0.012
<0.011
<0.015
<0.009
<0.011
<0.011
<0.011
<0.016
<0.014
<0.017
<0.012.
<0.011
<0.009
<0.014
<0.012
<0.009
<0.009
<0.011
<0.010
<0.010
<0.010
<0.008
<0.010
<0.010
<0.010
<0.013
<0.011
<0.014
<0.009
<0.008
<0.006
<0.012
<0.017
<0.010
<0.010
<0.012
<0.012
<0.011
<0.010 0.008.004
<0.012
<0.011
<0.012
<0.016
<0.013
<0.016
<0.010
<0.009
<0.008
<0.012
<0.27 0.32H.ll 0.26H.ll 0.25.10 0.47.13 0.29+.11 0.32+.12 0.34H.12'.31.10 0.27'.10 0.35.11
<0.31 0.34+.10
<0.31 0.30H.09 0.18'.10 0.19'.OS 0.28'.10 0.038'.030 0.030.023
<0.042
<0.049
<0.043
<0.039 0.064&.033 0.050.022
<0.048 0.037'.022
<0.048
<0.063
<0.052
<0.066
<0.034
<0.030
<0.034
<0.054
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
- - Control result.
Results in units of activity Ra~zzg wet weight.
-100
TABLE 17A (Continued)
CONCENTRATION OF CANNA EMITTERS IN FOOD PRODUCTS Results in units of pCi/g (wet) g 2 sigma Location Sample Date Sample Type Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 AcTh-228 Others Ts*
p**
RA*
Qe **
Jee Xe*
8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 Tomatoes Tomatoes
'omatoes Tomatoes Tomatoes Tomatoes
<0.05
<0.03
<0.06
<0.04
<0.04
<0.07 2.63.15 2.26+.09 2.12i0.17 2.76.11 2.03i0.12 2 38i0.18
<0.008
<0.006
<0.010
<0 007
<0.006
<0.011
<0.005
<0.004
<0.007
<0.004
<0.005
<0.007
<0.006
<0.004
<0.007
<0.004
<0.005
<0.009
<0.11 0.15i0.04 0.24i0.10
<0.08 0.17.06 0.16.07
<0.021 0.01~.006
<0.029 0.016i0.008 0.017~.010
<0.030
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
- Control result.
ee - Optional sample (non-broadleaf vegetation).
Results in units of activity D~znm wet weight.
-101
TABLE 17B CONCENTRATION OF GAMMA EHITTERS IN FOOD PRODUCTS Results in units of pCi/kg (wet) ~ 2 sigma Location Sample Date Sample Type Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 AcTh-228 Others T
T T
P P
P R
R R
Qk J
J J
X X
X 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29%8 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88.
8-29-88 8-29-88 8-29-88 8-29-88 8-29%8 8-29-88 Cucumber Leaves Beet Greens Pepper Leaves Cabbage Swiss Chard Collard Greens Cucumber Leaves Squash Leaves Bean Leaves Pumpkin Leaves Beet Greens Bean Leaves Swiss Chard Squash Leaves Lettuce Cabbage Bean Leaves Pepper Leaves 978p125 100+0 272~6 158Z61 201259 271L61 1140L91 609260 381g68 3042131 334g62 1030~126 285&6 983Z118 174~6 91~0 66%64 404~75 2270t285 5210~266 7370~310 2520t216 3560x252 2800j201 2130t183 3330i186 3020z239 3980p226 5840p298 2250i314 5180i299 29502331 3310i212 1920z171 1390~138 4860i325
<15
<12
<13
<12
<12
<ll
<15
<9
<11
<ll
<11
<16
<14
<17
<12
<ll
<9
<14
<12
<9
<9
<11
<10
<10
<10
<8
<10
<10
<10
<13
<ll
<14
<9
<8
<6
<12
<17
<10
<10
<12
<12
<ll
<10 8~
<12
<11
<12
<16
<13
<16
<10
<9
<8
<12
<273 32lil06 258~110 2472101 473~130 293tl12 325gl16 337~115 310~105 273tl02 353z109
<310 336i100
<268 299z92 176tl00 193H3 279~104 38z30 30z23
<42
<49
<43
<39 64p33 50t22
<48 37Z22
<48
<63
<52
<66
<34
<30
<34
<54
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
- Control result All results in units of activity D~~gz@g wet weight
-102
TABLE 17B (Continued)
CONCENTRhTION OF GAHHA EHITIERS IN FOOD PRODUCTS Results in units of pCi/kg (wet) ~ 2 sigma Location Sample Date Sample Type Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 hcTh-228 Others Te*
p**
Ree QA JAR 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 8-29-88 Tomatoes Tomatoes Tomatoes Tomatoes Tomatoes Tomatoes
<47
<33
<60
<36
<45
<66 2630gl52 2260t90 2120t166 2760plll 20302120 2380~185
<8
<6
<10
<7
<6<ll
<5
<4
<7
<4
<5
<7
<6
<4
<7
<4
<5
<9
<113 153~1 243zl01
<83 172a59 163L66
<21 12~6
<29 16~8 17plO
<30
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
- Control result ee Optional sample (non-broadleaf vegetation).
hll results in units of activity Iu~~gzam wet weight
-103
TABLE 18 INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Medium Site Reference No.
EPA Result (1)
Site Result (2)
Beta Beta Tritium Tritium Tritum I-131 3/88 8/88 2/88 6/88 10/88 2/88 Air Filter (pCi/filter)
Air Filter (pCi/filter)
Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter) 0 Milk (pCi/liter)
QA 88-31 QA 88-101 QA 88-013 QA 88-070'A 88-129 QA 88-018 50Z5 29+5 33272362 55652557
'2316Z350 4.0+0.4 62Z4 (3) 62g4 63~3 2823 (3) 28Z3 29Z3 33002100 (4) 3300Z200 3500Z100 63002300 (4) 5800%300 57002400 24792130 (4) 2592~131 2524p131 4.0+0.5 (4) 3.0Z0.5 4.0g0.4
TABLE 18 (Continued)
INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Medium Site Reference No.
EPA Result (1)
Site Result (2)
I-131 I-131 I-131 Gamma (I-131)
Gamma (Cs-137)
Gamma (I-131) 4/88 8/88 12/88 1/88 1/88 7/88 Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
Food (pcuvg)
Food (pcu~g)
Food (pci/vg) gA 88-037 0A 88-90 QA 88-162 gA 88-,006 QA 88-006 gA 88-89 7.520.05 76~8 115~12 102~10 91~5 107gll 8.0H.8 (3) 8.020.7
- 8. 0~. 8 77>3 (3) 79+3 79+3 118+6 (3) 117g7 118'5+10(3) 96+7 98Z6 8328 (3) 81'2g2 107+10(3) llOg10 10425
-105
TABLE 18 (Continued)
INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Medium Site Reference No.
EPA Result (1)
Site Result (2)
Gamma (Cs-137)
Gamma (Co-60)
Gamma (Zn-65)
'Gamma (Ru-106)
Gamma (Cs-134)
Gamma (Cs-137) 7/88 2/88 2/88 2/88 2/88 2/88 Food (pci/kg)
Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
QA 88-89 QA 88-007 QA 88-007 QA 88-007 QA 88-007 QA 88-007 49Z5 69+5 94~9 105glO 64~5 94+5 45Z4 (3) 49+6 45~7 6626 (3) 69Z4 70~7 95~11 (3) 10026 100Z6 100~30 (3) 104p14 110Zll 63%6 (3) 60~3 60Z2 93g7 (3) 91~3 91'
TABLE 18.'(Continued)
INTERLABORATORY COMPARISON PROGRAM RESULTS
'Analysis Date Medium Site Reference No.
EPA Result (1)
Site Result (2)
Gamma (Cr-51)
Gamma (Co-60)
Gamma (Zn-65)
Gamma (Ru-106)
Gamma (Cs-134)
Gamma (Cs-137)
Gamma (Cr-51) 6/88 6/88 6/88 6/88 6/88 6/88 10/88 Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)..
Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
QA 88-068 QA 88-068 QA 88-068 QA 88-068 QA 88-068 QA 88-068 QA 88-128 302230 15'01Z10 195220 20~5 25+5 25lg25 278252 (3) 294250 359Z49 14+4 (3) 13+4 13+3 81Z12 (3) 106~16 95Zll 184+40 (3) 206247 192g32 2527 (3) 21+5 17+3 2425 (3) 26~6 25~5 286+35 (3) 284241 272g47
-107
TABLE 18 (Continued)
INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Med'ium
'Site Reference No.
EPA Result (1)
Site Result (2)
Gamma (Co-60)
Gamma (Zn-65)
Gamma (Ru-106) 10/88 10/88 10/88 Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
QA 88-128 QA 88-128 QA 88-128 25i5 15lgl5 152~15 29~4 (3) 27Z5 29g6 143pl3 (3) 152+16 148+17 127230 (3) 123Z34 129Z36 Gamma (Cs-134)
Gamma (Cs-137)
Gamma (Co-60) 10/88 10/88 4/88 Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
QA 88-128 QA 88-128 QA 88-041 25~5 15~5 50+5 28~6 (3) 28g4 27g6 16~3 (3) 18'5'2+6 (3) 49Z6 52g6
TABLE 18 (Continued)
INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Medium Site Reference No.
EPA Result (1)
Site Result (2)
Gamma (Cs-134)
Gamma (Cs-137)
Gamma (Cs-134)
Gamma (Cs-137)
Gamma (Cs-137) 4/88 4/88 10/88 10/88 3/88 Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
Water (pCi/liter)
Air Filter (pCi/filter)
QA 88-041 QA 88-041 QA 88-134 QA 88-134 QA 88-31 7'~5 15~5 15'6+5 5+2 (3) 6+2 7+4 Si3 (3) 6g2-6g2 13+5 (3) 12+5 12~5 15'3) 13+5 16+5 19'3) 20~3 20~3
-109
TABLE 18 (Continued)
INTERLABORATORY COMPARISON PROGRAM RESULTS Analysis Date Medium Site Reference No.
EPA Result (1)
Site Result (2)
Gamma (Cs-137)
Gamma (I-131)
Gamma (Cs-137)
Gamma (I-131)
Gamma (Cs-137) 8/88 6/88 6/88 10/88 10/88 Air Filter (pCi/filter)
Milk (pCi/liter)
Milk (pCi/liter)
Milk (pCi/liter)
Milk (pCi/liter)
QA 88-101 QA 88-71 QA 88-71 QA 88-135 QA 88-135 12'4Z9 51+5 91~9 50+5 19+6 (3) 18+6 20Z6 94+2 (3) 94g2 95+2 48+5 (3) 54Z7 48+5 9022 (3) 89+2 89+2 47+7 (3) 44~8 47z7
TABLE 18 (Continued)
INTKKABORATORYCOMPARISON PROGRAM RESULTS (1)-Results reported aq activity g the standard deviation of the error.
(2)-Results reported. as activity p the error (2 sigma).
(3)-Analyzed at the site environmental laboratory.'4)-Analyzed at a vendor laboratory.
TABLE 19 ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location Description Degrees and Distance (1)
Shoreline Sediment 05*
06 Figure lA Sunset Bay Figure 1A Langs Beach, Control 80't 1.5 miles 230't 5.8 miles Fish 02*
03*
00*
Figure 1A Nine Mile Point Transect Figure 1A FitzPatrick Transect Figure lA Oswego Transect 315't 0.3 miles 55't 0.6 miles 235't 6.2 miles Surface Water 03~
08*
09 10 Figure 1A FitzPatrick Inlet Figure lA Oswego Steam Station Inlet Figure 1A NMP Unit 1 Inlet Figure lA Oswego City Water Figure 1A NMP Unit 2 Inlet 70't 0.5 miles 235't 7.6 miles 305't 0.3 miles 240't 7.8 miles 304't O.l miles'
TABLE 19 (Continued)
ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location Description Degrees and Distance (1)
Air Radioiodine and Particulates R-1*
R-2*
R-3*
R-4*
R-5*
Dl Figure 2
Figure 2
R-2 Station, Lake Road R-3 Station, Co. Rt.
29-Figure 2
R-4 Station, Co. Rt.
29 Figure 1A R-5 Station, Montario Point Road Figure 2
Figure 2
Figure 2
Figure 2 Figure 2
Figure 2
Figure lA Dl On-Site Station G On-Site Station H On-Site Station I On-Site Station J On-Site Station K On-Site Station-G Off-Site Station, Saint Paul Street Figure 1A R-1 Station, Nine Mile Point Road 88't 1.8 miles 104't 1.1 miles 132't 1.5 miles 143't 1.8 miles 42't 16.4 miles 69't 0.2 miles 250't 0.7 miles 70't 0.8 miles 98't 0.8 miles 110't 0.9 miles 132't 0.5 miles 225't 5.3 miles
-113
TABLE 19 (Continued)
ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location Description Degrees and Distance (1)
Air Radioiodine And Particulates Continued D2 Figure lA D2 Off-Site Station, Rt.
64 Figure lA E Off-Site Station, Rt.
4 Figure 1A F Off-Site Station, Dutch Ridge Rd.
117't 9.0 miles 160't 7.2 miles 190't 7.7 miles Thermo-luminescent Dosimeters (TLD) 6 Figure 2 Figure 2
Figure 2
Figure 2
Figure 2
Dl On-Site Station D2 On-Site Location E On-Site Location F
On-Site Location G On-Site Station 69't 0.2 miles 140't 0.4 miles 175't 0.4 miles 210't 0.5 miles 250't 0.7 miles Figure lA R-5 Off-Site Station Figure 1A Dl Off-Site Location 42't 16.4 miles 80't 11.4 miles 10 Figure 1A D2 Off-Site Station 117't 9.0 miles
-114
TABLE 19 (Continued)
ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location Description Degrees and Distance (1)
Thermo-luminescent Dosimeters (TLD)
Continued 12 13 14*
15*
]8*
19 23*
24 25 26 27 28 Figure 1A F Off-Site Station Figure lA G Off-Site Station Figure lA Figure 1A Figure 2
Figure 1A Figure 2
Figure 2
Figure 2
Figure 2
Figure 2
Figure 2
Southwest Oswego Control
-West Site Boundary Energy Information Center East Site Boundary H On-Site Station I On-Site Station J On-Site Station K On-Site Station North Fence, JAFNPP North Fence, JAFNPP Figure 1A E Off-Site Station 160't 7.2 miles 190't 7.7 miles 225't 5.3 miles 226't 12.6 miles 237't 0.9 miles 265't 0.4 miles 81't 1.3 miles 70't 0.8 miles 98't 0.8 miles 110't 0.9 miles 132't 0.5 miles 60't 0.4 miles 68't 0.5 miles
-115
TABLE 19 (Continued)
ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location Description Degrees and Distance (1)
Thermo-luminescent Dosimeters (TLD)
Continued 29 30 31 39 47 49*
51 52 53 55 56*
58*
Figure 2
Figure 2
Figure 2
North Fence, JAFNPP North Fence, JAFNPP North Fence, NMP-1 Figure 2
North Fence, NMP-1 Figure 2
Figure 1B North Fence, JAFNPP
- Phoenix, NY Control Figure lA Oswego Steam Station, East Figure 1A Oswego Elementary School, East Figure 1B Fulton High School Figure lA Mexico High School Figure lA Pulaski Gas Substation, Rt.
5 Figure 1A New Haven Elementary School Figure 1A'o. Rt.
1 and Alcan 65't 0.5 miles 57 at 0.4 miles 276't 0.2 miles 292't 0.2 miles 69't 0.6 miles 170't 19.8 miles 233't 7.4 miles 227't 5.8 miles 183't 13.7 miles 115't 9.3 miles 75't 13.0 miles 123't 5.3 miles 220't 3.1 miles
TABLE 19 (Continued)
ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location Description Degrees and Distance (1)
Thermo-luminescent Dosimeters (TLD)
Continued 75*
76*
77*
78*
. 79*
80*
81*
82*
83*
84*
85*
86*
Figure 2
Figure 2
North Fence, NMP-2 North Fence, NMP-2 Figure 2
East Boundary, JAFNPP Figure 2
County Route 29 Figure 2
County Route 29 Figure 2-Miner Road Figure 2
Figure 2
Miner Road Lakeview Road Figure lA Lakeview Road Figure 2
North Fence, NMP-1 Figure 2
North Fence, NMP-1 Figure 2
North Fence, NMP-2 5't 0.1 miles 25't 0.1 miles 45't 0.2 miles 90't 1.0 miles 115't 1.1 miles 133't 1.4 miles 159't 1.6 miles 181't 1.6 miles 200't 1.2 miles 225't 1.1 miles 294't 0.2 miles 315't O.l miles
-117
r TABLE 19 (Continued)
ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location Description Degrees and Distance (1)
Thermo-luminescent Dosimeters (TLD)
Continued 87*
88*
89*
90*
9]*
92*
93*
94*
95*
96*
97*
98*
99 Figure 2
North Fence, NMP-2 Figure 1A Hickory Grove Road Figure 1A Leavitt Road Figure lA Route 104 and Keefe Road Figure lA Figure lA County Route 51A Maiden Lane Road Figure 2
County Route 29 Figure lA Lake Road Figure 1A Nine Mile Point Road Figure 1A County Route 53 Figure 1A County Route 1 and Kocher Road Figure 1A 'akeshore Camp Site Figure 1A Creamery Road 341't 0.1 miles 97't 4.5 miles 111't 4.1 miles 135't 4.2 miles 156't 4.8 miles 183't 4.4 miles 205't 4.4 miles 223't 4.7 miles 237't 4.1 miles 199't 3.6 miles 143't 1.8 miles 101't 1.2 miles 88't 1.8 miles
-118
TABLE 19 (Continued)
ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location
'Description Degrees and Distance (1)
Thermo-luminescent Dosimeters (TLD)
Continued 100 101 102 103 104 105 106 107 108 109 110 Figure 2
County Route 29 and Lake Road Figure 2
County Route 29 Figure 1B Oswego County Airport Figure 2
Energy Information Center, East Figure lA Parkhurst Road Figure 2
Lakeview Road Figure 2
Shoreline
- Cove, West of NMP-1 Figure 2
Shoreline
- Cove, West of NMP-1 Figure lA Lake Road Figure lA Lake Road Figure 1B Baldwinsville, New York Control Figure 1A
- Sterling, New York Control 104't 1.1 miles 132't 1.5 miles 175't 11.9 miles 267't 0.4 miles 102't 1.4 miles 198't 1.4 miles 274't 0.3 miles 272't.0.3 miles 104't 1.1 miles 103't 1.1 miles 166't 26.4 miles 214't 21.8 miles Cows Milk 16 Figure 4 Indicator Location Figure 4 Indicator Location 107't 5.5 miles 190't 5.9 miles
-119
TABLE 19 (Continued)
ENVIRONMENTAL SAMPLE LOCATIONS Sample Medium Map Designation Figure Number Location Description Degrees and Distance (1)
Cows Milk Continued 50 55 60 65*
Figure 4 Figure 4 Figure 4
Figure 4 Figure 4
Indicator Location Indicator Location Indicator Location Indicator Location Control Location 95't 8.2 miles 95't 9.0 miles 90't 9.5 miles 113't 7.8 miles 220't 17.0 miles Food Products R+
Figure 3
Figure 3
Figure 3
Figure 3
Figure 3
Figure 3
Indicator Location Indicator Location Indicator Location Control Location Indicator Location Indicator Location 84't 1.6 miles 101't 1.9 miles 114't 1.5 miles 225't 12.6 miles 103't 1.9 miles 84't 1.4 miles
- -Technical Specification location.
(1) Degrees and distance based on Nine Mile Point Unit 2 reactor centerline.
~
-1.20
TABLE 20 Medium Qf~t Shoreline Sediment *
(pCi/kg-dry)
Fish *
(pCi/kg-wet)
RADIOLOGICAL ENVIRONMENTAL.MONITORING PROGRAM ANNUAL
SUMMARY
NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1988*
Location (b) of Highest Annual Mean'.
Location
& BC'~
Indicator Locations:
He@~
Control Location:
Haa~
Type and Number of baal'~
LLKal
~G~4 Cs-134 Cs-137 150
<LLD 180
<LLD QSh~7P,(h)
Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 130
<LLD 260
<LLD
<LLD
<LLD 130
<LLD
<LLD
<LLD 130
<LLD
<LLD 260
<LLD
<LLD
<LLD 130
<LLD
<LLD
<LLD 150 JAF:
0.6 at 55'2-74 23-53 20-74
-121 Number of Nonroutine g~~o<<~
0 0.
TABLE 20 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1988*
Medium
~night Type and Number of
~~c~*
Location (b) of Indicator Locations:
Highest Annual Mean:
Hca~
Location 6 gm~3.
Control Location:
Hca~d Number of Nonroutine Re~tg Surface Water *
(pCi/liter)
H-3 3000(c) 430-480 JAF:
~4~4
~2i~L~
0.6 at 55'30-480 240-460 m Gal:
Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 15 30 15 30 15 15 15 (c)
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
TABLE 20 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1988*
Medium Surface Water *
(pCi/liter)
(Continued)
Type and Number of Q~i~k Cs-134 Cs-137 Ba/La-140 18 15 Indicator Locations:
Hca~d Location (b) of Highest Annual Mean:
Location E M~~
<LLD
<LLD Control Location:
H~~
<LLD
<LLD Number of Nonroutine
~e)~rt.~
Air Gross Beta:
0.01 Particulates*
(pCi/m3)
~QQ~
0 07 0.007-0.040
<LLD 1.1 at 88' 0.008-0.038
<LLD 0.008-0.039
~GA (QQ's-134 0.05
<LLD Cs-137 0.06
<LLD
<LLD
<LLD
-123
TABLE 20 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1988*
Medium
~'~t Type and Number of haalgma" Location (b) of Indicator Locations:
Highest Annual Mean:
Has~
Location E 5ea~Q Control Location:.
He@~
Number of Nonroutine
~~tg TLD*
(mrem per quarterly period)
GammaD~~'d) 2 2
11.6-55.8 TMI 85
~i~4 (g) ~(~
0.2 at 294'5.4-55.8 14.2-20.2 Milk*
(pCi/liter)
~G~12tg: (e) (h)
Cs-134 Cs-137 15 18 10.0
<LLD Loca. t16
~~@
<LLD 5.9 at 190'0.0
'0 Ba/La-140 15
<LLD
<LLD 2
<LLD Food Products*
~G A ~1 (pCi/kg-wet)
(broadleaf
-I-131 vegetation)
Cs-134 Cs-137 60 60 80
<LLD
<LLD
<LLD
'oca. R 1.5 at 114'
~
-124 '
TABLE 20 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY DECEMBER 1988*
Data for Table 20 is based on Technical Specification required samples unless otherwise indicated.
LLD values as required by the Radiological Technical Specifications.
LLD units are specified in the medium column.
Location is distance in miles and direction in compass degrees based on NMP-2 reactor centerline.
Units for this column are specified in medium column.
The Technical Specifications specify an I-131 and tritium LLD value for surface water analysis (non-drinking water) of 15 pCi/liter and 3000 pCi/liter respectively.
The Technical Specifications do not specify a particular LLD value for environmental TLDs.
The NMP-1 and NMP-2 Off-Site Dose Calculation Manuals contains specifications for environmental TLD sensitivities.
The Technical Specification 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, the only sample location required by the Technical Specifications is the control location.
Fraction of number of detectable measurements to total number of measurements.
Mean and range results are based on detectable measurements only.
The results for TLD 885 must be evaluated with the knowledge that this TLD is in close proximity (300-500 feet) of the Nine Mile Point Unit 1 reactor building and the radwaste buildings.
This
- TLD, as well as other TLDs in this area, are adjacent to the lake shoreline which's a restricted area to members of the public.
There are no residences or private property near this area.
Data includes results from optional samples in addition to samples required by the Technical Specifications.
For food products, only broadleaf vegetation was evaluated.
Cs-137 is probably an indirect result of the 1986 Chernobyl Nuclear Plant accident.
-125
TABLE 21 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Cs-134 Cs-137 Co-60 1979 (2) 1980 1981 1982 1983 1984 1985 1986 1987 1988 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.22 0.07 LLD 0.05 LLD LLD LLD LLD LLD LLD 0.22 0.22 0.09 0.08 LLD LLD 0.05 0.05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD'LD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Results in pCi/g (dry)
(1)
Control location was at an area beyond the influence of the site (westerly direction).
(2)
Sampling was initiated in 1979.
Sampling was not required prior to 1979.
-126
TABLE 22 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Cs-134 Cs-137 Co-60 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.09 0.09 0.09 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.15 0.20 0.11 0.07 0.16 1.54 1.00 1.07 0.14 0.21
)(1) (3) 0.15 0.15 0.20 0.20 0.11'.11 0.80 0.43 1.81 0.94 1.61 1.58 1.81 1.40 1.07 1.07 0.59 0.36 0.52 0.36 LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.16 0.16 0.16 0.14 0.36 0.25 0.21 0.26 0.24 0.11 0.18 0.15 0.10 0.10 0.10 0.06 0.06 0.06 0.04 0.05 0.04 1979 1980 1981-1982 1983 1984 1985 1986 1987 1988 (4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
LLD LLD LLD LLD LLD LLD LLD LLD (4)
(4)
(4)
~
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
LLD LLD LLD LLD LLD LLD LLD LLD (4)
(4)
(4)
(4)
(4)
(4)
)(2)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
(4)
LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Results in pCi/g -dry (1)
Location was shoreline area near NMP-1.
(2)
Location was off-site at Sunset Bay (closest location with recreational value).
(3)
Sampling was initiated in 1979.
Sampling was not required prior to 1979.
(4)
Sampling initiated in 1985 as required by the new Technical Specifications.
-127
TABLE 23 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Cs-137 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1.2 0.13 0.04 0.03 0.03 0.028 0.027 0.041 0.015 0.026 0.021 0.017 0.023 1.2 0.13
- 0. 20 0.06 0.11 0.062.
0.055 0.057 0.038 0.047 0.032 0.040 0.053 1.2 0.13 0.09 0.04 0.06 0.043 0.046 0.049 0.032 0.034 0.025 0.031 0.033.
'esults in pCi/g (wet)
(1)
Control location was at an area beyond the influence of the site (westerly direction).
-128
TABLE 24 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Cs-137 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 0.5 0.13 0.03 0.02 0.03 0.03 0.034 0.033 0.033 0.018 0.009
- 0. 024, 0.020 3.9 0.79 0.10 0.55 0.10 0.10 0.064 0.056 0.061 0.044 0;051 0.063 0.074 1.4 0.29 0.08 0.10 0.06 0.06 0.048 0.045 0.043 0.'030 0.028 0.033 0.034 Results in pCi/g (wet)
Indicator locations are in the general area of the NMP-1 and J. A.
FitzPatrick cooling water discharge structures.
-129
TABLE 25 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Cs-137 Co-60 1976 (3) 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 (1)
(1)
(2)
(2)
LLD LLD 2.5 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD
.LLD LLD LLD LLD LLD LLD LLD LLD LLD
.(1)
(2)
LLD 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)
(1)
(2)
(2)
(2)
(2)
LLD LLD LLD LLD 1.4 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)
(2)
(2)
LLD LLD 1.4 LLD LLD LLD LLD LLD LLD LLD Results in pCi/liter (1)
No gamma analyses performed (not required)
(2)
Data showed instrument background results (3)
Location was the City of Oswego Water Supply for 1976 1984 and the Oswego Steam Station inlet canal for 1985 1988
-130
TABLE 26 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER C9-137 Co-60 (3) 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 (1)
(1)
(1)
(2)
(2)
(2)
LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD
. 0.43 0.43 0.43 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)
(1)
(2)
.(2)
(2)
(2)
LLD LLD LLD LLD LLD LLD 1.6 2.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)
(2)
(2)
LLD LLD LLD 1.9 LLD LLD LLD LLD LLD LLD Results in pCi/liter (1)
No gamma analyses performed (not required)
(2)
Data showed instrument background results (3)
Location was J. A. FitzPatrick inlet canal
-131
TABLE 27 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Tritium 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 440 300 215 174 211 211 112 230 190 230 250 140 240 929 530 490 308 290 328 307 280 220
- 370 550 270 460 652 408 304 259 257 276 165 250 205 278 373 210 320 Results in pCi/liter (1)
Control location is the City of Oswego drinking water for 1976 1984 and the Oswego Steam Station inlet canal for 1985 1988
-132
TABLE 28 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Tritium
~
~
1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 365 380 377 176 150 212 194 249 110 250 260 160 430 889 530 560 276 306 388 311 560 370
. 1200(2) 500 410 480 627 455 476 228 227 285 266 347 280 530 380 322 460 Results in pCi/liter (1)
Indicator location is the FitzPatrick inlet canal.
(2)
Suspect sample contamination.
Recollected samples showed normal levels of tritium.
-133
TABLE 29 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Gross Beta 1977 1978 1979 1980 1981 1982 1983 1984 1985 1'986 1987 1988 0.001 0.01 0.010 0.009 0.016 0.011 0.007 0.013 0.013 0.008 0.009 0.008 0.484 0.66 0.703 0.291 0.549 0.078 0.085 0.051 0.043 0.272 0.037 0.039
~
- 0. 125 0.16 0.077 0.056 0.165 0.033 0.024 0.026 0.024 0.039 0.021 0.018 Results in pCi/m3 (1)
Locations used for 1977 1984 were C off-site, Dl off-site, D2 off-site, E off-site, F off-site and G off-site.
Control location R-5 off-site was used for 1985 1988 (formerly C off-site location)
-134
TABLE 30 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Gross Beta L
t 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 0.002 0.01 0.001 0.002 0.004 0.001 0.002 0.002 0.010 0.007 0.009 0.007 0.326 0.34 0.271 0.207 0.528 0.113 0.062 0.058 0.044 0.289 0.040 0.040 0.106
'.11 0.058 0.044 0.151 0.031 0.023 0.025 0.023 0.039 0.021 0.018
.0 Results in pCi/m3 (1)
Locations used for 1977 1984 were Dl 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 1988 locations were R-1 off-site, R-2 off-site,
, R-3 off-site, and R-4 off-site.
-135
TABLE 31 HISTORICAL ENVIRONNENTAL SANPLE DATA AIR PARTICULATES C9-137 Co-60 Preop.
1970 1971 1972 1973 1974 1975
=1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0002 0.0008 0.0008 0.0015 0.0003 0.0002 0.0002 LLD
~
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0112 0.0042 0.0047 0.0018 0.0042 0.0009 0.0002 LLD LLD 0.0311 LLD LLD (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0034 0.0018 0.0016 0.0016 0.0017 0.0004 0.0002 LLD LLD 0.0193 LLD LLD (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0034 0.0003 0.0005 LLD 0.0003 0.0004 0.0007 0 0004 LLD LLD LLD LLD (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0347 0.0056 0.0014 LLD 0.0012 0.0007 0.0007 0.0012 LLD LLD LLD LLD (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0172 0.0020 0.0009 LLD 0.0008 0.0006 0.0007 0.0008 LLD LLD
'LD LLD Results in pCi/m3 (1)
No data available (not required prior to 1977)
(2)
Locations included composites of off-site air monitoring locations for 1977 1984.
Sample Location included only R-5 air monitoring location for 1985 1988
-136
TABLE 32 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Cs-137 Co-60 (2)
Preop.
1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 19,85 1986 1987 1988 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0001 0.0003 0.0003 0.0005 0.0002 0.0001 0.0002 LLD LLD 0.0069 LLD
. LLD (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0105 0.0026 0.0020 0.0019 0.0045 0.0006 0.0003 LLD LLD 0.0364 LLD LLD (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0043 0.0016 0.0010 0.0011 0.0014 0.0004 0.0002 LLD LLD 0.0183 LLD LLD (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0003 0.0003 0.0003 0.0016 0.0002 0.0003 0.0003 0.0007 LLD
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0711 0.0153 0.0007 0.0016 0.0017 0.0010 0.0017 0.0017 LLD LLD LLD LLD (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 0.0179 0.0023 0.0005 0;0016 0.0006 0.0005 0.0007 0.0012 LLD LLD LLD LLD Results in pCi/m3 (1)
No data available (not required prior to 1977)
(2)
Locations included composites of on-site air monitoring locations for 1977 1984.
Locations included R-1 through R-4 air monitoring locations for 1985 1988.
-137
TABLE 33 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Iodine-131 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 0.01 0.02 0.03 LLD LLD LLD 0.039 LLD LLD LLD 0.041 LLD LLD 5.88
'.82 0.04 LLD LLD LLD 0.039 LLD LLD LLD 0.332 LLD LLD 0.60 0.32 0.03 LLD LLD LLD 0.039 LLD LLD LLD
'.151 LLD LLD Results in pCi/m3 (1)
Locations Dl 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 1988.
-138
TABLE 34 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Iodine 131 t
~
~
~
t (1) 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985
- 1986, 1987 1988'.01 0.02 0.02 LLD 0.013 0.016 0.002 0.022 LLD LLD 0.023 0.011 LLD 2.09 0.73 0.07 LLD 0.013 0.042 0.042 0.035 LLD LLD 0.360 0.018 LLD 0.33 0.31 0.04 LLD 0.013 0.029 0.016 0.028 LLD LLD 0.119 0.014 LLD Results in pCi/m3 (1)
Locations used for 1976 1984 were Dl 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.
Locations used for 1985 1988 were Rl off-site, R-2 off-site, R-3 off-site and R-4 off-site.
-139
TABLE 35
- HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)
(2)
Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 (1) 6.0 2.0 2.2 2.2 2.7 4.8 3.2 4.0 3.3 3.3 3.8 3.5 3.8 4.9 4.7 4.5 '(4.4)A 5:3 (5.5)*
4.6 (4.6)*
4.4 (4.8)*
(1) 7.3 6.7 6.2 6.9 8.9 6.0
'.2 8.0 F 7 5.7 5.8 5.9 6.1 7.2 8.2 7.6 (6.8)+
7.5 (7.2)~
6.6 (5.8)*
6.8 (6.8)*
(1) 6.7 4,3 4,4 4.7 5.6 5.5 5.4 5.3 4.3 4.7 4.9 4.8 5.1 5.8 6.2 5.6 (5.4)~
6.3 (6.3)<<
5.4 (5.2)*
5.6 (5.4)*
Results in mrem per standard month (1)
Data not available (2)
TLD N8, 14, 49, 110 and 111, where applicable
( )<< TLD result based on the Technical Specification required locations (TLD 814 and 49).
-140
TABLE 36A HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)
Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 4.1 4.4 4.4 3.4 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 12.6 18.7 14.3 17.9 (2)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 6.2 7.0 6.1 6.4 Results in mrem per standard month lf (1)
No data available (not required prior to 1985)
(2)
TLD locations initiated in 1985 as required by the new Technical Specifications.
Includes TLD numbers 75, 76, 77, 23, 78, 79, 80, 81, 82, 83, 84, 7, 18, 85, 86 and 87
-141
TABLE 36B HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)
(2)
Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982'983 1984 1985 1986 1987 1988 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 4.0 4.6 4.3 3.8 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1.)
(1)
(1)
(1)
(1)
(1) 7.1 8.6 6.0 7.0 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1).
5.0 6.0 5.2 5.3 Results in mrem per standard month (1)
No data available (not required prior to 1985)
(2)
TLD locations initiated in 1985 as required by the new Technical Specifications.
Includes TLD numbers 88, 89, 90, 91, 92, 93, 94 and 95.
-142
~>>,4>'as)>> ~w 'l
- '> l,
'l
~
> v'>> >~ >>>
~
"t >.l>>ix>>'>>>.
> I...'>>
>r
> ~ ~,
~
TABLE 36C HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)
(2)(3)
Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1986 1987 1988 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 3.9 4.8 3.5 3.9 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 6.8 8.2 6.0 6..6 (1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1) 5.3 6.1 5.1 5.3 Results in mrem per standard month (1)
No data available (not required prior to 1985).
(2)
TLD locations initiated in 1985 as required by the new Techni;cal Specifications.
TLD's included are numbers 96, 58, 97, 56, 15 and 98.
(3)
TLD locations include critical residences and populated areas near the site.
-143
TABLE 36D HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)
(2)
Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 (1) 4.7 1.5 2.3 3.0 3.1 4.6 3.7 3.0 3.0 2.7 3.9 4.1 3.9 5.0 4.6 4.7 4.7 4.0 4 '
(1) 9.0 7.7 8.2 24.4 10.6 16.0 18.8 15.3 9.0 8.3 12.0 11.8 13.0 16.5 13.2 15.9 16.1 11.4 11.9 (1) 6.0 4.7 4.9 6.6 5.7 7.3 6.9 5.7 4.3 4.3 5.3 5.8 6.3 6.9 7.0 6.3 7.0 5.8 6.0 Results in mrem per standard month (1)
No data available.
(2)
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 1988).
Locations are existing or previous on-site environmental air monitoring locations.
-144
~
TABLE 36E HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Dose (mrem)
(2)
Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1986 1987 1988 (1) 5.0
" 1.1 1.8 2.2 2.4
'.5 3.4 3.7.
2.7 3.0 3.1 3.6 4.0 4.6 4.6 4.6 5.0 4.4 4.2 (1) 8.0 7.7 6.6 6.9 8.9 7.1 7.2 8.0
'.7 5.7 5.8 5.9 6.2 7.2 8.2 7.7 7.6 6.6 6.6 (1) 6.7 4.5 4'
4.1 5.3 5.5 5.2 5.3 3.7 4.0 4.6 4.7 5.2 5.6 6.1 5.5 6.1 5.2 5.4 Results in mrem per standard month (1)
No data available.
(2)
Includes TLD numbers 8, 9, 10, ll, 12 and 13 (off-site environmental air monitoring locations.
-145
TABLE 37 HISTORICAL ENVIRONNENTAL SANPLE DATA NILK Cs-137 I-131 (2) 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985
,1986 1987 1988 (1)
(1)
(1)
(1)
(1)
(1) 2.4 7.8 5.8 LLD LLD LLD 3.6 5.6 4.5 3.9 3.9 3.9 LLD LLD LLD LLD LLD LLD
. LLD LLD LLD LLD LLD LLD 5.3 12.4 8.4 LLD LLD LLD LLD LLD LLD (1)
(1)
(1)
(1)
LLD LLD LLD LLD 1.4 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.8 29.0 LLD LLD LLD LLD (1)
(1)
LLD LLD 1.4 LLD LLD LLD LLD LLD 13.6 LLD LLD I
Results in pCi/liter (1)
No data available (samples not required)
(2)
Location used was an available milk sample location in a least prevalent wind direction greater than ten miles from the site
-146
0 TABLE 38 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Cs-137 I-131
~
t (1) 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 4.0 11.0 3,4 3.2 3.2 3.5 3.5 3.3 LLD LLD 6.1 5.5 10.0 15.0 9.3 22.0 17.1 33.0 9.9 53.0 9.4 21.0 8.1 29.0 8.6 14.0 5.7 10.9 7.2 LLD LLD LLD LLD 11.1 8.6 8.1 6.8 10.0 10.0 0.02 45.00 3.20 0.01 49.00 6.88 0.19 0.19 0.19 LLD LLD LLD 0.3 8.8 3.8 LLD LLD LLD LLD,'LD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.3 30.0 5.2 LLD LLD LLD LLD LLD LLD Results in pCi/liter (1)
Locations sampled were available downwind locations within ten miles with high deposition potential.
-147
TABLE 39 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS C6-137 1976(3) 1977 1978 1979 1980 1981 1982 1983 1984 1985(4) 1986 1987 1988 (1)
(1)
(1)
(1) 0.02 LLD LLD LLD LLD LLD LLD LLD LLD (1)
(1)
(1)
(1) 0.02 LLD LLD LLD LLD LLD LLD LLD LLD (1)
(1)
(1)
(1) 0.02 LLD LLD LLD LLD LLD LLD LLD.
LLD Results in pCi/g (wet)
(1)
No data available (control samples not required)
(2)
Location was an available food product sample location in a least prevalent wind direction greater than ten miles from the site (3)
Data comprised of broadleaf and non-broadleaf vegetation (1980-1984).
(4)
Data comprised of broadleaf vegetation only (1985-1988).
-148
TABLE 40 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Cs-137 1976(>>
1977 1978 1979 1980 1981 1982 1983 1984 1985(3) 1986 1987 1988 LLD LLD LLD 0.004 0.004 LLD LLD LLD LLD 0.047 LLD LLD 0.008 LLD LLD LLD 0.004 0.060 LLD LLD LLD LLD 0.047 LLD LLD 0.008 LLD LLD LLD 0.004 0.036 LLD LLD LLD LLD 0.047 LLD LLD 0.008 Results in pCi/g (wet)
(1)
Indicator locations were available downwind locations within ten miles of the site and with high deposition potential.
(2)
Data comprised of broadleaf and non-broadleaf vegetation (1976-1984).
(3)
Data comprised of broadleaf vegetation only (1985-1988).
-149
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-152
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-155
0