Text

Ja FitzPatrick Nuclear Power Plant,Radiological Environ Operating Rept for 1995
	ML20108C791
Person / Time
Site:	FitzPatrick
Issue date:	12/31/1995
From:	Michael Colomb; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Martin T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	JAFP-96-0190, JAFP-96-190, NUDOCS 9605070154
	Download: ML20108C791 (199)
	v • d • e

__

jim 1s A.FitzP: trick Nucint Pow:r Plant PO Box 41 Lycoming. New York 13093 315-342 3840 M NewYorkPower w cnoe u. c o,o m e tv Authonty mani ueae.

April 29, 1996 JAFP-96-0190 United States Nuclear Regulatory Commission Region 1 457 Allendale Road King of Prussia, PA 19406 Attention:

Thomas T. Martin Regional Administrator

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FACILITY OPERATING LICENSE DPR-59. DOCKET NO. 50-333 Gentlemen:

Enclesed please find the 1995 Radiolonical Environmental Oncratina Report which covers the operating period of January 1,1995 through December 31,1995. This report is submitted in accordance with the requirements of Amendment 93, Section 7.3.d of the James A. FitzPatrick Nuclear Power Plant Technical Specifications. Distribution for this report is in accordance with the Regulatory Guide 10.1, Revision 4.

Very truly yours, AL.$

MICII' AEL J. COLOMB MJC:BG:Is 9605070154 951231 eg PDR ADOCK 05000333 R

PDR Enclosures Document Control Center Desk (USNRC) (18) xc:

JAF NRC Resident inspector J. W. Blake (NYPA/WPO)

W. J. Cahill (NYPA/WPO)

J. J. Kelly (NYPA/WPO)

C. Merritt (NMPC)

CAC Committee (Toivn of New Haven)

CAC Committee (Town of Scriba)

W. Berzins g

A. McKeen

.)

RES File WPO Records Management 060185 l

g jk

/

Reference Center RMS (JAF)

CERTIFIED MAIL, RETURN RECEIPT REQUESTED m

x

1 l

a e.

1 James A. FitzPatrick 9 Nuclear Power Plant L9 %+e

f f.g.

(b g... / ; 3., 7.. f p f,, (

y p /, *

'J s -.

.m

.s.-

,,2 n,

2 p-[.k. 5k,.. ',. '..

J, -

r pe

.Iw

. g 71 r;, : ;.. '

g 'ls

[

~

4 -

y slu...

.;.h

'1 t -

._ fd(f;

. 3. a :.;<;.;st.

y.

..w

q q!,

s :,

4A

.wy s, t.

[9 A.

_? '

g w' 3

%: L::;. :

q',; d '

t

- W < ~ ^ ~

-[

4 :-

g/'k]i})WF gig Rg:g V

mg')

en r

QL} V

~

g,,

wp

' ;,'gW L'

'R

p. ce,

(Mf H

3 J..S y c

v.

9 1

., ~

v 2.

.q.

,g f

4

'(

g agg' Ig h

f,,

g n

.u

~

?

'.. i E '

',,'.,c

~,;,., #.4

~

.n 7.

.4 c,

~

)

')

NewYorkPower

~

Ucense

~DPRCSS Authority

~

. DocketNo. 50-333

mmms~m.1:wm NEW YORK POWER AUTIIORITY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1,1995 - DECEMBER 31,1995 FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT FACILITY OPERATING LICENSE DPR-59 DOCKET NUMBER 50-333

r

)

TABLE OF CONTENTS i

Pace 1.0 EXECUTIVE

SUMMARY

l-1

2.0 INTRODUCTION

2-1 2.1 Site Description 2-1 l

l 2.2 Program Overview 2-1 2.3 Program Objectives 2-2 1

3.0 PROGRAM DESCRIPTION 3-1 l

3.1 Sample Collection Methodology 3-7 3.2 Analyses Performed 3-13 l

3.3 Sample Location Maps and Sample Location Reference Tables 3-14 3.4 Land Use Census 3-24 i

3.5 Changes to the REMP Program 3-25 3.6 Deviation and Exceptions to the Program 3-26 l

3.7 Statistical Methodology 3-27 3.8 Compliance with Required Lower Limits of Detection (LLD) 3-32 4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL 4-1 POSITION FORMAT 5.0 DATA EVALUATION AND DISCUSSION 5-1 l

5.1 Aquatic Program 5-7 l

l 5.2 Terrestrial Program 5-24 l

5.3 Conclusion 5-54 5.4 References 5-56 l

l l

l

l l

TABLE OF CONTENTS (Continued)

Page l

6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES 6-1 l

7.0 IIISTORICAL DATA TABLES 7-1 l

l l

8.0 GRAPIIICAL PRESENTATIONS 8-1 9.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM 9-1 1

l l

9.1 Program Description 9-1 l

9.2 Program Results 9-1 l

9.3 Nonconformities 9-2 l

l l

i 1

i l

LIST OF TABLES Pane Table 3.0-1 Required Sample Collection and Analysis 3-2 Table 3.3-1 Environmental Sample Locations 3-20 Table 3.8-1 Detection Capabilities For Environmental Sample Analysis, 3-33 Lower Limit of Detection (LLD)

Table 6-1 Shoresme Sediment Sampling Results 6-2 Table 6-2 Fish Sampling Results 6-3 Table 6-3 Surface Water Composite Results, Tritium 6-6 Table 6-4 Surface Water Composite Results, Gamma Isotopic 6-7 Table 6-5 Off-site Airborne Particulate Filter Results, Gross Beta 6-13 Table 6-6 On-site Airborne Particulate Filter Results, Gross Beta 6-15 Table 6-7 Off-site Airborne 1-131 Results 6-17 Table 6-8 On-site Airborne 1-131 Results 6-19 Table 6-9 Particulate Composite Results, Gamma Isotopic 6-21 Table 6-10 Thermoluminescent Dosimeter Results 6-37 Table 6-11 Milk Results, I-131 & Gamma Isotopic 6-41 Table 6-12 Milk Animal Census Results 6-44 Table 6-13 Food Product Results, Gamma Isotopic 6-46 Table 6-14 1995 Residence Census 6-47 Table 9-1 Gross Beta Analysis Airborne Particulate (pCi/m')

9-3 and Water (pCi/L)

Table 9-2 Tritium Analysis of Water (pCi/L) 9-4 Table 9-3 Iodine Analysis of Water (pCi/L) and Milk (pCi/L) 9-5 Table 9-4 Gamma Analysis of Milk, Water (pCi/L), Airborne Particulate 9-6 3

(pCi/m ) and Food Products (pCi/kg) iii

LIST OF FIGURES T_agg Figure 3.3-1 New York State Map 3-15 Figure 3.3-2 Off-site Environmental Station and TLD Location Map 3-16

)

Figure 3.3-3 On-site Environmental Station and TLD Location Map 3-17 j

Figure 3.3-4 Milk Animal Census, Milk Sample Location and Surface 3-18 Water Sample Location Map Figure 3.3-5 Nearest Residence, Food Product, Shoreline Sediment, 3-19 Fish Sample, Location Map Figure 8.1 Graph - Fish (Cs-137) 8-2 Figure 8.2 Graph - Surface Water Tritium 8-3 Figure 8.3 Graph - Airborne Particulate Gross Beta, Annual 8-4 Figure 8.4 Graph - Airborne Particulate Gross Beta, Weeks 1-26 (1995) 8-5 l

Figure 8.5 Graph - Airborne Particulate Gross Beta, Weeks 27-52 (1995) 8-6 l

Figure 8.6 Graph - Airborne Particulate Composite (Co-60) 8-7 l

Figure 8.7 Graph - Airborne Particulate Composite (Cs-137) 8-8 i

Figure 8.8 Graph - Airborne Radiodine (I-131) 8-9 l

Figure 8.9 Graph - Milk (Cs-137), Annual 8-10 i

Figure 8.10 Graph - Milk (I-131) 8-11 l

Figure 8.11 Graph - TLD Data 8-12 l

iv l

l l

1.0 EXECUTIVE

SUMMARY

The Annual Radiological Environmental Operating Report is published pursuant to Section 7.3.d of the Radiological Effluent Technical Specifications (RETS). The RETS require that the results from the Annual Radiological Environmental Monitoring Program (REMP) be provided to the Nuclear Regulatory Commission.

This report describes the REMP program and its implementation as required by Technical Specifications. It also contains the analytical results, data evaluation, dose evaluation, and data trends for each environmental sample media. Also included are results of the land use census, historical data and the Environmental Laboratories performance in the Quality Assurance Intercomparison Program required by Technical Specifications.

The REMP is implemented to measure radioactivity in the aquatic and the terrestrial pathways. The aquatic pathways include Lake Ontario Gsh, water, and lake shore sediment. Measurement results of the samples representing these pathways contained only natural background radionuclides or low concentrations of Cs-137 which are the result of past atmospheric nuclear 'esting. The 1995 results were consistent with the previous five year historical data.

Terrestrial pathways are also monitored and included airborne particulate and radioiodine, milk, food products and direct radiation. Analysis of all terrestrial radiation pathways demonstrated that there has been no detectable increased radiation levels as a result of plant operation. Again, the 1995 results are consistent with the previous five year historical results and exhibit no adverse trends.

In summary, the analytical results from the 1995 Environmental Monitoring Program demonstrate that the routine operation of the James A. FitzPatrick Nuclear Power Plant had no significant or measurable radiological impact on the environment. No increase in radiation levels were detected in the off-site environment as a result of the increase in hydrogen injection rates implemented at the plant in 1995. The measured concentrations of radionuclides in the off-site environment surrounding the JAFNPP are not increasing as a result of plant operation. In many cases, particularly fish and airborne particulate activity, this report continues to document a significant downward trend in the concentration of radionuclides in the environment created from past weapons testing. The results of the program demonstrate that the operation of the plant did not result in a measurable dose of any significance to the general population, above natural background levels.

1-1

2.0 INTRODUCTION

This report is submitted in accordance with Section 7.3.d of the Radiological Effluent Technical Specifications (RETS) to DPR-59, Docket 50-333.

2.1 SITE DESCRIPTION The New York Power Authority (NYPA) is the owner and licensee of the James A.

j FitzPatrick Nuclear Power Plant (JAFNPP). JAFNPP is a single unit boiling water reactor (BWR). The plant generates 2436 megawatts (MW) thermal output and 801 megawatts gross electrical output. The plant is located on the eastern portion of the Nine Mile Point promontory approximately one-half mile due east of the Niagara Mohawk Power Corporation (NMPC) Nine Mile Point Nuclear Power Stations (NMPNPS).

Initial fuel loading of the JAFNPP reactor core was completed in November of 1974. Initial criticality was achieved in late November 1974 and commercial operation began in July 1975. NMPNPS #1, a 620 MWe (net) BWR, has been operating since 1969. NMPNPS #2, a 1,100 Mwe (net) BWR, has been operating since March 1988.

The plant site is on the southeastern shore of Lake Ontario in the Town of Scriba, Oswego County, New York, approximately seven miles northeast of the City of Oswego, New York. The Universal Transverse Mercate. System coordientes of JAFNPP are north 4,819,545.012 m, east 386,968.945 m.

Syracuse, New York, located 36 miles south, is the largest metropolitan city in the area. The site consists of approximately 700 acres of partially wooded land and shoreline. The land adjacent to the site is primarily used for recreation and residential purposes. The country side to the west, east and south is rolling terrain rising gently up from the lake composed mainly of glacial deposits. Approximately 34 percent of the land area in Oswego County is devoted to farming.

2.2 PROGRAM OVERVIEW NYPA and NMPNC share the responsibility for the JAFNPP Radiological Environmental Monitoring Program (REMP). Technical Specifications for radiological monitoring of the environment for all three plants are similar. This allows the majority of the sampling and analysis to be a joint undertaking. Data generated by the program is shared by the three facilities. Review and publication of the data is done independently by each organization.

2-1 1

2.3 PROGRAM OBJECTIVES The objectives of the Radiological Environmental Monitoring Program are to:

1.

Measure and evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on radioactive material sources.

2.

Monitor natural radiation levels in the environs of the JAFNPP site.

3.

Demonstrate compliance with the various environmental conditions and requirements of applicable state and federal regulatory agencies including Technical Specifications and 40 CFR Part 190.

4.

Provide information by which the general public can evaluate the environmental aspects of nuclear power using unbiased data.

5.

To satisfy the community interest regarding the impact of the power plants on the environment.

2-2

3.0 PROGRAM DESCRIPTION To achieve the objectives listed in Section 2.3, an extensive sampling and analysis program is conducted every year.

The JAFNPP Radiological Environmental Monitoring Program (REMP) consists of sampling and analysis of various media that include:

o Shoreline Sediment o

Fish o

Surface Waters o

Air o

Milk o

Food Products In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TLDs). These sampling programs are outlined in Table 3.0-1.

The JAFNPP REMP sampling locations are selected and verified by an annual land use The accuracy and precision of the program is assured by participation in census.

The United States Environmental Protection Agency (USEPA) Environmental i

Radioactivity Laboratory Intercomparison Program. In addition to the participation in the EPA Program, quarterly sample splits are routinely provided to the New York State Department of Health for cross checking purposes.

Sample collections for the radiological program are accomplished by a dedicated site environmental staff from both the James A. FitzPatrick Plant and the Nine Mile Point Stations. The site staff is assisted by a contracted environmental engineering company, EA Science and Technology, Inc. (EA).

3-1

TABLE 3.0-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Exposure Sampling and Pathway and/or Sample Number of Samples (a) and Locations Collection )

Type and Frequency Frequencyta of Analysis AIRBORNE Radioiodine Samples from 5 locations:

Continuous sam-Radioiodine Canisters:

and ple operation Analyze weekly for I-131.

Particulates a.

3 samples from off-site locations in dif-with sample col-ferent sectors of the highest calculated lection weekly Particulate Samoles:

site average D/Q (based on all licensed or as required Gross beta radioactivity )

site reactors).

by dust loading, following filter changetb y

whichever is composite (by location) w b.

I sample from the vicinity of a community more frequent.

for gamma isotopic having the highest calculated site aver-quarterly (as a minimum).

age D/Q (based on all licensed site re-actors).

c.

1 sample from a control location 9 to 20 miles distant gr1(i in the least prevalent wind directionta),

Direct Radiation (e) 32 stations with two or more dosimeters Quarterly Gamma. dose monthly or placed as follows: An inner ring of stations quarterly.

in the general area of the site boundary and an outer ring in the 4 to 5 mile range from the site with a station in each of the land based sectors of each ring. There are 16 land based sectors in the inner ring, and 8 land based sectors in the outer ring. The balance of the stations (8) are placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

TABLE 3.0-1 (Counnuso)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Exposure Sampling and Pathway Collectior)a)

Type and Frequency aixUor Sample Number of Samples (a) and Locations Frequencyt of Analysis WATERBORNE Surface (f) a.

1 sample upstream.

Composite sam-Gamma isotopic analysis j

ple over one monthly. Composite for I

1 sample from the si month period (9).

Tritium) analysis quar-coolingwaterintakeg)smostdownstream b.

terlytc,

Sediment from 1 sample from a downstream area with existing Twice per year.

Gamma isotopic) analysis Shoreline or potential recreational value.

semiannually (c,

w da INGESTION Milk a.

Samales from milk animals in 3 locations Twice per month.

Gamma isotopic and I-131 witlin 3.5 miles distant having the high-April through analysis twice per month est calculated site average D/Q.

If December (sam-when milk animals are there are none, then 1 sample from milk ples will be on pasture (April through animals in each of 3 areas 3.5 to 5.0 collected in December): monthly (Jan-miles distant having the highest calcu-January through uary throuch March), if latedsiteaverageD/Q(ggsedonall March if I-131 required (cy,

licensed site reactors)l e.

is detected in November and b.

1 sample from milk animals at a control December of the location (9 to 20 miles distant and in a precedinc year).

less prevalent wind direction)(d)

TABLE 3.0-1 (Canrznuso)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Exposure Sampling and Pathway and/or Sample Number of Samples (a) and Locations Co'ilection )

Type and Frequency Frequencyta of Analysis FISH a.

I sample of each of 2 commerically or Twice per year.

Gamma isotopic (c) analysis recreationally important species in the of edible portions.

vicinity of a site discharge point.

b.

1 sample of each of 2 species (same as in a. aboce or of a species with similar feeding hab;ts) from an area at least 5 miles distant from the site (di, 5

F000 PRODUCTS a.

In lieu of the garden cenus as specified Once during Gamma isotopic (c) in 6.2. samples of at least 3 different harvest season, analysis of edible kinds of broad leaf vegetation (such as portions.

(Isotopic vegetables) grown nearest each of two to include I-131).

different off-site locations of highest predicted site average D/Q (based on all licensed site Reactors).

One (1) sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a leasit prevalent wind direction sectorta)

I

)

NOTES FOR TABII 3.0-1

.(a)

It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired locetion or time. In these instances suitable altemative media and locations may be chosen for the particular pathway in question.

Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Calculated site averaged D/Q values and meteorological parameters are based on historical data (specified in the ODCM) for all licensed site reactors.

(b)

Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thorium daughter decay. If gross beta activity in air is greater than 10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(c)

Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the plant.

(d)

The purpose of these samples is to obtain background infonnation.

If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.

(e)

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a pocket may be considered as two or more dosimeters.

Film badges shall not be used for measuring direct radiation.

(f)

The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream sample" shall be taken in an area beyond, but near, the mixing zone, if practical.

3-5

NOTES.FOR TABLE 3.0-1 (Continued)

(g)

Compor.ite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure that a representative san:ple is obtained.

(h)

A milk sampling loedion, as required in Table 1 is defined as a location having at least 10 milking cows present at a designated milk sample location. It has been found from past experience, and as a result of conferring with local farmers, that a minimum of 10 milking cows is necessary to guarantee an adequate supply of milk twice per month for analytical purposes. Locations with less than 10 milking cows are usually utilized for breeding purposes which eliminates a stable supply of milk for samples as a result of suckling calves and periods when the adult animals are dry. In the event that 3 milk sample locations cannot meet the requirement for 10 milking cows, then a sample location having less than 10 milking cows can be used if an adequate supply of milk can reasonably and reliably be obtained based on l

communications with the farmer.

3-6

3.1 SAMPLE COLLECTION METHODOLOGY 3.1.1 SURFACE WATER Surface water samples are taken from the respective inlet canals of the JAFNPP and the Niagara Mohawk Oswego Steam Station (OSS) located in the City of Oswego.

The I~itzPatrick Facility draws water from Lake Ontario on a continuous basis. This is used for the "down-current" or indicator sampling point for the Nine Mile Point Site. The OSS inlet canal 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 its location relative to prevailing lake current directions and flow pattern of the nearby Oswego River.

Samples from the JAFNPP are composited using automatic sampling equipment which discharges into a compositing tank or bottles. Samples are collected monthly from the compositor and analyzed for gamma emitting radionuclides. Samples from use OSS are also obtained using automatic sampling equipment and collected in a holding tank.

Representative samples from this location are obtained weekly and are composited to form a monthly composite sample. The monthly samples are analyzed for gamma emitting radionuclides.

A portion of the monthly samples from each of the locations is saved and composited to form quarterly composite samples.

Quarterly composite samples are analyzed for tritium.

In addition to the sample results for the JAFNPP and Oswego Steam Station collection sites, data is presented for the Nine Mile Point Unit 1 and Unit 2 facility inlet canal samples and for samples from the City of Oswego drinking water supply. The latter three locations are not required by the Technical Specifications. These locations are optional sample points which are collected and analyzed to enhance the surface water sampling program.

Monthly composite samples from these three locations are analyzed for gamma emitters and quarterly composite samples are analyzed for tritium.

Surface water sample locations are shown in Section 3.3 on Figure 3.3-4.

3-7

k b

k 3.1.2 AIR PARTICULATE / IODINE The air sampling stations required by the Radiological Effluent Technical Specifications (RETS) are located in the general area of the site boundary.

The sampling stations are sited within a distance of 0.2 miles of the site boundary in sectors with the highest calculated meteorological deposition factors (D/Q) based on historical meteorological data. These stations (R-1, R-2, and R-3) are located in the east, east-southeast, and southeast sectors as measured from the center of the NMPNS Unit 2 reactor building. The RETS also require that a fourth air sampling station be located in the vicinity of a year round community having the highest calculated dispersion factor (D/Q) based on historical meteorological data. This station is located in the southeast sector and is designated as location R-4. A fifth station required by the IGTS is a control location, designated as station R-5.

Station R-5 is located 16.4 miles from the site in the east northeast meteorological sector.

In addition to the RETS required locations, there are ten additional sampling stations. Six of these sampling stations are located within the site boundary and are designated as on-site stations DI, G, H, I, J, and K. These locations are within the site boundary of the JAFNPP and NMPNS. One air sampling station is located off-site in the southwest sector in the vicinity of the City of Oswego and is designated as station G off-site. Three remaining air sampling stations are located in the ESE, SSE, and S sectors and range in distance from 7.2 to 9.0 miles. These are designated as off-site stations D2, E and F respectively.

Each station collects airbome particulates using glass fiber filters (47 millimeter diameter) and radioiodine using charcoal cartridges (2 x 1 inch).

The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis. Sample volume is determined by use of calibrated gas flow meters located at the sample discharge. Gross beta analysis is performed on each paniculate filter. Charcoal canridges are analyzed for radiciodine using gamma spectral analysis.

The particulate filters are composited monthly by location and analyzed for gamma emitting radionuclides.

3-8

Air sampling stations are shown in Section 3.3, Figures 3.3-2 and 3.3-3.

3.1.3 MILK Milk samples are routinely collected from five farms during the year. These farms included four indicator locations and one control location. Samples are collected twice per month, April through December and each sample is analyzed for gamma emitting radionuclides and I-131.

Samples are collected in January, February and March in the event that I-131 is detected in November and December of the preceding year.

The selection of milk sample locations is based on maximum deposition calculations (D/Q). Deposition values are generated using average historical meteorological data for the site. The Technical Specifications require three samp!c locations within 5.0 miles of the site with the highest calculated l

deposition value. During 1995 there were no milk sample locations within 5.0 miles that were suitable for sampling based on production capabilities.

There were however, five optional locations beyond five miles that were sampled as the routine milk sampling program.

The Technical Specifications also require that a sample be collected from a location greater than ten miles from the site and in a less prevalent wind direction. This location is in the southwest sector and serves as the control location.

Milk samples are collected in polyethylene bottles from a bulk storage tank at each sampled farm. Before the sample is drawn, the tank contents are agitated to assure a homogenous mixture of milk and butterfat. Two gallons are collected from each indicator and control locations during the first half and second half of each month. The samples are chilled, preserved and shipped fresh to the analytica! laboratory within thirty-six hours of collection in insulated shipping containers.

The milk sample locations are found in Section 3.3 in Figure 3.3-4. (Refer to Table 3.3-1, Section 3.3 for location designations and descriptions).

3-9

1 3.1.4 FOOD PRODUCTS (VEGETATION)

Food products are collected once per year during the late summer harvest season. A minimum of three different kinds of broad leaf vegetation (edible or inedible) are collected from two different indicator garden locations.

Sample locations are selected from gardens identified in the annual census that have the highest estimated deposition values (D/Q) based on historical site meteorological data. Control samples are also collected from available locations greater than 9.3 miles distance from the site in a less prevalent wind direction.

Control samples are of the same or similar type of vegetation when available.

Food product samples are analyzed for gamma emitters using gamma isotopic analysis.

Food product locations are shown in Section 3.3 on Figure 3.3-5.

3.1.5 FISII SAMPLES Samples of available fish species are selected from the Nine Mile Point Aquatic Ecology Study which monitors lake fish populations. Fish samples are collected twice per year, once in the spring and again in the fall.

Indicator samples are collected from a combination of the four on-site sample transects located off shore from the site. One set of control samples are at an off-site sample transect located off shore 8 - 10 miles west of the site. Available species are selected using the following guidelines:

a) Samples are composed of 0.5 to I kilogram of the edible portion only.

A maximum of three species per location are used.

b) Samples composed of more than 1 kilogram of single species from the same location are divided into samples of 1 kilogram each. A maximum of three samples per species per location are used. Weight of samples are the edible portions only.

c) Samples are limited to edible and or spon species when available.

3-10

I Selected fish samples are frozen immediately after collection and segregated by species and location. Samples are shipped frozen in insulated containers for analysis.

Edible portions of each sample are analyzed for gamma emitting radionuclides. Fish collection locations are shown in Section 3.3 on Figure 3.3-5.

3.1.6 SIlORELINE SEDIMENTS One kilogram of shoreline sediment is collected at one area of existing or potential recreational value. One sample is also collected from a location beyond the influence of the site. Samples are collected as surface scrapings to a depth of approximately 1 inch. The samples are placed in plastic bags, sealed and shipped to the lab for analysis. Sediment samples are analyzed for gamma emitting radionuclides.

Shoreline sediment locations are shown in Section 3.3 on Figure 3.3-5.

3.1.7 TLD (DIRECT RADIATION)

Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment.

TLDs are supplied and processed quanerly by the J.A. FitzPatrick N.P.P. Environmental Laboratory. The laboratory utilizes a Panasonic based system using UD-814 dosimeters.

Each dosimeter contains three calcium sulfate elements and one lithium borate element. Two dosimeters are placed at each monitoring location.

Five different regions around the site are evaluated using environmental TLDs.

On-site areas (areas within the site boundary not required by the o

RETS)

Site boundary area in each of the sixteen meteorological sectors o

o An outer ring of TLDs (located four to five miles from the site in the eight land based meteorological sectors) 3-11

-?n'eX9EW M.J.22l2.EEl22EFHma Special interest TLDs (located at sites of high population density o

and use) o Control TLDs located at sites beyond significant influence of the site Special interest TLDs are located at or near large industrial sites, schools, or nearby towns or communities.

Control TLDs are located to the southwest, south and east-northeast of the site at distances of 12.6 to 19.8 miles.

TLDs used for the 1995 program were constructed of rectangular teflon wafers impregnated with 25 percent CaSO :Dy phosphor. Badges are sealed 4

in a polyethylene package to ensure dosimeter integrity. TLD packages were placed in open webbed plastic holders and attached to supporting structures, such as utility poles.

Environmental TLD locations are shown in Section 3.3 on Figures 3.3-2 and 3.3-3.

3-12

3.2 ANALYSES PERFORMED The majority of environmental sample analyses are performed by the James A.

FitzPatrick Environmental Laboratory (JAFEL). Tritium and surface water I-131 analysis were performed by Teledyne Brown Engineering Environmental Services.

l The following samples are analyzed at the JAFEL:

Air Particulate Filter - gross beta o

Air Particulate Filter Composites - gamma spectral analysis o

Airbome Radiciodine - gamma spectral analysis o

Surface Water Monthly Composites - gamma spectral analysis o

o Fish - gamma spectral analysis Shoreline Sediment - gamma spectral analysis o

o Milk - gamma spectral analysis and I-131 Direct Radiation - Thermoluminescent Dosimeters (TLDs) o Special Samples (soil, food products, bottom sediment, etc.) - gamma o

spectral analysis Quality assurance samples are analyzed in-house and by Teledyne Brown Engineering N.J. and Teledyne Brown Engineering Midwest.

3-13

J 3.3 SAMPLE LOCATION MAPS i

Section 3.3 includes maps illustrating sample locations. Sample locations referenced a

as letters and numbers on the report period data tables are consistent with designations plotted on the maps.

4 This section also contains an environmental sample location reference table (Table 3.3-1). This table contains the following information:

o Sample Medium Location designation, this column contains the key for the sample o

location and is consistent with designation on the sample location maps and on the sample results data tables.

o Location description o

Degrees and distance of the sample location from the site.

3.3.1 LIST OF FIGURES o

Figure 3.3 New York State Map o

Figure 3.3 Off-site Environmental Station and TLD Location Map o

Figure 3.3 On-site Environmental Station and TLD Location Map o

Figure 3.3 Milk Animal Census, Milk Sample Location and Surface Water Sample Location Map o

Figure 3.3 Nearest Resident, Food Product, Shoreline Sediment, Fish Sample Location Map 3-14

3 %

L

>, sj

>.>a l

FIGURE 3.3-1 NEW YORK STATE MAP

.? -,,

.I VE pudON, 3

NEWYdRK f

,~

g

_.2.,

f a

trao i.;!

L.. _...

4?

. l t'

j Nine Mlle Point Nucisar Station Unit 1 Nine Mlle Point Nuclear Station Unit-2 James A. FitzPatrick Nuclear Power Plant 6

hfW JERSEY NEW YORK CffY W

ow r

N

. yi

\\

4 h

g49

(

i O5WEGO COUNTY

)

New York FIGURE 3.3-2 0FF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS

>L KEY:

1AKE

\\

f OENVIRONMENTALSTATION

]

$TLDLOCATION ONTARIO

= '-D

'S Y

SCALE OF MILES T

g g

se

>>,w

==

s y

$5*. ~,..

R~ E g [ -

.====

-r t"C

/

~

x/4p p #.)b y

.;ga,p y.

yy,

,# a# n v w y # c..

%u myJ W2 =~ g<

L v,--

wsw pg

-(g,,,

3 Q,,,r+g,_ hm;Q;..y),,} g

_.7.- y g e 7s_ g--

,. %p

,3

/..

4

\\

w

- C,,

,,, ), + h.

-a

z :

}. _k. _I h 9 5% g,p' ' J Is u(t

's.\\

- c.x

,\\

2-9

._p

~

4

~ff ' 2

~

Nl-

[j

,\\

u. }i

.r,. u i m

% m% -

.s a

m.

3 -

7

_ _.. -...- - p.-a 5<.

..p

'g.) h".

[m h, h y

' c, ', d

[

"% 4, %!b,

g q \\=u '. & :' g(4 _T s,s. e t.i. t,Ik.

A O;n Lk n.

5. '. 44 *h V}=i i= x p9

.h u

,N s

[

~

Q Qg n

t g g z w ; y ~v) w /

f:n=3 ii n -a u m J~>~ c s$m $y g[rt;

- M v69JJ>

m"5 I%

P M /" Y,

/

T1-_

- - p h+\\

w.

gQ "2 -)' *yGJ. 4 ($ ~

f, g, e-.-.

+

s;x --

a y. >u w

t\\,

.y) - m %,- /kx's,,,,y g.

s w

g Lg..,. 9TM oga n

v.d.

,.x(e 1

,.s

.~i m-N

. '(

/

Ny=),=l--/ )

[ y> Ep% '

r+-

4+qn(_',pyfn4.fQx'4yh'p4 I [;

q m

w ir

.. -~w s

n.:

e. y g

9 s_

--y;q -.- A p_-

q..,

q, A. x,r_- A}%py x..

t 5.y % y -

c.

4 i

_. %m u.m

1ir+

.S FITZPATRICM

~

sI SUNSET BAY N 1EA ENERGY CENTE'R NYPA

"" 2

/

C TRAINING CENTER

/

270*- - - - W--

,o TR INING NI g

mr

---A

,/E- - - - - - - 90*

CENTER po i

TQ

/

t.

IT 2

\\

I l

METEOROLOGICAL i

TOWER hi f

ll

'-. =.

l

/

.CHYAFd.

3 ll I

\\ g C

._ bi

[

_/

1 a

g g/Tiflb1*@,-

i 1

e

\\9 AUTHORITY q

l 7 i!

l cf l5 l

Y

/

ThANSMISION

\\.

MOHAW l 'I?

f )k g

I I

a

(

o

~

/

a

/

p AIN f

\\.

h MCH

/

ARD l

j

',I l,

s

i I

h ii l

y

/

s 3 '..

ii ru k H u us//1///////u///////,,,,,,,A FIGURE 3.3-3

'I

!* 31 1

'\\

3 ON-SITE ENVIR0f00fTAL STATION I

\\

AfD TLD LOCATIONS I,

l!

l g

KEY:

'?.)

ii I

MINER RD

\\

WM""{',

m OENVIR0l#DiTALSTATION

\\

g go.

ys/vns

~.

OTLDLOCATION I

i.

/

$ /HH/

/

Q

9 OSWEGO COUNTY

(

New York 7

1 y

9 fL'-" e FIGURE 3.3-4 MILK ANIMAL CENSUS, MILK SAMPLE, AND

$URFACE WATER SAMPLE LOCATIONS KEY:

LAKE Q MILK ANIMAL CENSUS

"~

l 10mi

$MILKSAMPLE

=- {Ng

=-

OSURFACEWATER ONTARIO

,s

, mr anomas as, eenn+

=== e

s'

~ W (p j

,3P)

.4 g

/

(/p-} YTu,f%[, %nts? h s

p 4 } =A [h k,f.fZri /1 hl;; fo n % 1

' f l $%y = g %,g q'y w

.$N5. ' %c 'd^l

(# V, lh@ k-

~

[1'l ws

~#adj.ag gr M r%g~

m.spgv yy% c._4, m

.. [yg'*C

' e -Q

}%/ 'N f ;i s liggc-m:; ( q ' Tis ( j

q. n T 9x s4 s=w.'..KshN4 M

$l ?NA

M I N, %[3 '

'y~ "

N 3

m T

4 E

1 li$.1 0 A'sw g% ?

.Ecn 3 (!

e=

3 gg o,Ja!%

u ->p.

%,x,'5 7 m,

$$ $ d q %g[4,..

N j %j

% F4t.c

q=

. L [' f$'

s s%.[a.hri 54-[

a % g e\\ w g g % fe[]

g%M I~i"_,1 y hm_u;b_,'.,

~

.vr g+.%.4.y,N3 g, w m_

_a_

-3 41

..h.

g.. g ~

j.~,

ars 3 g.

g L,n e y.

_..Lpla; tty w% =7\\ %e.) M,A 1_ 4L J~g 11 1,.t s

s i

y

,4

'~f i

q "s m~ p.

f DEPARTMENT OF pub!.lC WORKS M AP OF g ';

O5WEGO COUNTY New York FIGURE 3.3-5

[

NEAREST RESIDENCE, FOOD PRODUCT, FISH AND SHORELINE SEDIMENT

,l SAMPLE LOCATIONS 7

KEY:

ORESIDENCE-NMP LAKE QFISH

$ RESIDENCE-JAF li

$ SHORELINE

$FOODPRODUCT l

$EDMENT O N T A R./ O

==-

.\\

ECALE OF MILES teessa a.r W X FRE^

. i5.u-..

=

9, =

?

00 :=*.%

w, m ~ ~ l.

y c

C,.",

x

(

' a:

.s l-44.

rs rq f

1 WSW E6m- -' ky

. A ? Q. P =x s &" \\/7" l&_ &i

=

f~4.i*

~(

1' ui 3

g,

=.. -

osw o

(

}f

.,.- } 7 s : ir;t w

=

jgg!$

. % \\ (C 9_, K (Q

- 1 s c.-

a p g 8 M 3[ h y ;a e.

+;

nA

- y = g,.

qe e

/,Xy 'w-rv.!s h e e

.: )n, - eyQ t.

d o

. m.

u s %

." g

+

<4 S

\\

c

/

s 1 i s

_, _ t_

..f l.p'.

_J" s 0 ]-c },\\ g g%

l 8 oS. gi\\

)

j j g%r.k1 k.g.

u,,

e

. h '.,'m. p4

-t

.. 3'/

_n

..o ~Q a.

c.

7 [i 4

hi r' y

"' i'.~

/

j

- p A.(yr,.g.

+[

FN

^~

EP 8

b, N 'j, % x p

g

[, g -

e-1,-,

3 l M h _k

.m

~b Sk I

p. x

. <._~_

m a

s-

~..

W>

ht

.$g,

1

<g i

.. va,,-

m.

i

~#

I N

j..'

'y A

z.. -

'l w'

\\ -

p-r-[ }n t,=,,3',.._s,,

\\.

q

^* #

Y 5 - g

g j

N M

u

<*--..j

?.

)f",[. y

""z.

-= ^ s 1

,v, A

t_

"c-T y"

. A t.;i.~.%l,u :

4.

. 'L %j p% 1, l

S

_\\*---

.,.,4v:' !

3 J

_k6 g

F -_

>. _. -. _ _,, m

,o-~~

TABLE 3.3-1 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLEi

.Ii.0CATIONL 7 MEDIUM!

0 DESIGNATION?

iL0 CATION DESCRIPTION!

1DEGREESiAND! DISTANCE _......_.

Shoreline 05*

Sunset Bay 80 at 1.5 miles Sediment 06 Langs Beach, Control 230 at 5.8 miles Fish 02*

Nine Mile Point Transect 315 at 0.3 miles 03*

FitzPatrick Transect 55 at 0.6 miles 00*

Oswego Transect 235 at 6.2 miles Surface Water 03*

FitzPatrick Inlet 70 at 0.5 miles 08*

Oswego Steam Station 235 at 7.6 miles 09 Nine Mile Point Unit 1 Inlet 302 at 0.3 miles 10 Oswego City Water 235 at 7.8 miles 11 Nine Mile Point Unit 2 Inlet 341 at 0.1 miles Air R-1*

R-1 Station, Nine Mile Pt. Rd.

88 at 1.8 miles Radiciodine R-2*

R-2 Station Lake Road 104 at 1.1 miles and R-3*

R-3 Station, Co. Rt. 29 132 at 1.5 miles Particulates R-4*

R-4 Station Co. Rt. 29 143 at 1.8 miles R-5*

R-5 Station, Montario Point Rd.

42 at 16.4 miles D1 D1 On-site Station, On-site 69 at 1.5 miles D2 D2 Off-site Station, Co. Rt. 64 117 at 9.0 miles E

E Off-site Station, Co. Rt. 4 160 at 7.2 miles F

F Off-site Station, Dutch Ridge Rd.

190 at 7.7 miles G

G On-site Station, On-site 250* at 0.7 miles H

H On-site Station On-site 70* at 0.8 miles I

I On-site Station, On-site 98 at 0.8 miles J

J On-site Station, On-site 110 at 0.9 miles K

K On-site Station On-site 132 at 0.5 miles G

G Off-site Station St. Paul St.

225 at 5.3 miles Technical Specification location (1) Based on Nine Mile Point Unit 2 Reactor Centerline

TABLE 3.3-1 (Courinuto)

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLER

. ? LOCATION LMEDIlM sDESIGNATION4 LOCATION! DESCRIPTION 1 iDEGREESfANDg: DISTANCE (1).i Thermo-3 D1 On-site Station 69 at 0.2 miles luminescent 4

D2 On-site Station 140 at 0.4 miles Dosimeters 5

E On-site Station 175 at 0.4 miles (TLDs) 6 F On-site Station 210 at 0.5 miles 7*

G On-site Station 250 at 0.7 miles 8

R-5 Off-site Station 42 at 16.4 miles 9

t D1 Off-site Location 80 at 11.4 miles 10 D2 Off-site Location 117 at 9.0 miles 11 E Off-site Location 160 at 7.2 miles 12 F Off site Location 190 at 7.7 miles 13 G Off-site Location 225 at 5.3 miles 14*

SW Oswego - Control 226 at 12.6 miles 15*

West Site Boundary 237 at 0.9 miles y>

S 18*

Energy Information Center 265 at 0.4 miles 19 East Site Boundary 81 at 1.3 miles 23*

H On-site Station. On-site 70 at 0.8 miles 24 I On-site Station, On-site 98 at 0.8 miles 25 J On-site Station. On-site 110 at 0.9 miles 26 K On-site Station. On-site 132 at 0.5 miles 27 North Fence, JAFNPP 60 at 0.4 miles 28 North Fence, JAFNPP 68 at 0.5 miles 29 North Fence, JAFNPP 65 at 0.5 miles 30 North Fence. JAFNPP 57 at 0.4 miles 31 North Fence, NMP-1 276 at 0.2 miles 39 North Fence, NMP-1 292 at 0.2 miles 47 North Fence JAFNPP 69 at 0.6 miles 49*

Phoenix, NY - Control 170 at 19.8 miles 51 Oswego Steam Station. East 233 at 7.4 miles 52 Oswego Elementary School, East 227 at 5.8 miles Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline

TABLE 3.3-1 (ConTrnuso)

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLEl

.fLOCATIONh.

!MEDILM;i lDESIGNATIONL

?LOCATIONi. DESCRIPTION)

[DEGREESLANDLDISTANCEClI Thermo-53 Fulton High School 183 at 13.7 miles luminescent 54 Mexico High School 115 at 9.3 miles Dosimeters 55 Pulaski Gas Substation. Route 5 75 at 13.0 miles (TLDs) 56*

New Haven Elementary School 123 at 5.3 miles 58*

County Route 1 and Alcan 220 at 3.1 miles 75*

North Fence. NMP-2 5

at 0.1 miles 76*

North Fence. NMP-2 25 at 0.1 miles 77*

North Fence. NMP-2 45 at 0.2 miles 78*

East Boundary. JAFNPP 90 at 1.0 miles 79*

County Route 29 115 at 1.1 miles 80*

County Route 29 133 at 1.4 miles 81*

Miner Road 159 at 1.6 miles 82*

Miner Road 181* at 1.6 miles m

t'a 83*

Lakeview Road 200 at 1.2 miles 84*

Lakeview Road 225 at 1.1 miles 85*

North Fence. NMP-1 294 at 0.2 miles 86*

North Fence. NMP-1 315 at 0.1 miles 87*

North Fence. NMP-1 341 at 0.1 miles 88*

Hickory Grove Road 97 at 4.5 miles 89*

Leavitt Road 111 at 4.1 miles 90*

Route 104 and Keefe Road 135 at 4.2 miles 91*

County Route 51A 156 at 4.8 miles 92*

Maiden Lane Road 183 at 4.4 miles 93*

County Route 53 205 at 4.4 miles 94*

Co. Rt. 1 & Kocher Road (Co. Rt.63) 223 at 4.7 miles 95*

Lakeshore Camp Site 237 at 4.1 miles 96*

Creamery Road 199 at 3.6 miles 97*

County Route 29 143 at 1.8 miles 98*

Lake Road 101 at 1.2 miles Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline

TABLE 3.3-1 (couT1suno)

~

ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE?

.! LOCATION?.

2HEDIIML JDESIGNATION:

LOCATION 1DESCRIPTIONi iDEGREESfAND! DISTANCE

==

l Nine Mile Point Road 88 at 1.8 miles Thermo-99 luminescent 100 County Route 29 and Lake Road 104 at 1.1 miles Dosimeters 101 County Route 29 132 at 1.5 miles (TLDs) 102 Oswego County Airport 175 at 11.9 miles 103 Energy Information Center, East 267 at 0.4 miles 104 Parkhurst Road 102 at 1.4 miles 105 Lakeview Road 198 at 1.4 miles 106 Shoreline Cove. East of NMP-1 274 at 0.3 miles 107 Shoreline Cove. East of NMP-1 272 at 0.3 miles 108 Lake Road 104 at 1.1 miles 109 Lake Road 103 at 1.1 miles 111 Sterling-Control 214 at 21.8 miles 112 Emergency Off-site Facility Env. Lab 179 at 11.9 miles m6 113 Baldwinsville-Control 170 at 24.7 miles Cows Milk 50 Indicator Location 93 at 9.1 miles 55 Indicator Location 95 at 9.0 miles 60 Indicator Location 90 at 9.5 miles 4

Indicator Location 113 at 7.8 miles 73*

Control Location 234 at 13.2 miles K

Indicator Location 90 at 1.7 miles Food Products L

Indicator Location 112 at 1.9 miles Q

Indicator Location 101 at 1.8 miles S

Indicator Location 98 at 1.7 miles R

Indicator Location 100 at 1.9 miles M

Control Location 225 at 15.6 miles Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline

3.4 LAND USE CENSUS Technical Specifications require that a milk animal census and a residence census be conducted annually.

t 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. The census is done once per year in the summer. It is conducted by sending questionnaires to previous milk animal owners, and by road surveys to locate any possible new owners. In the event that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Cooperative Extension Service was also contacted to provide any additional information.

The residence census is conducted each year to identify the closest residence in each of the 22.5 degree meteorological sectors to a distance out to five miles. - A residence, for the purposes of this census, is a residence that is occupied on a part time basis (such as a summer camp), or on a full time, year round basis. Several of the site meteorological sectors are over Lake Ontario, therefore, there are only eight sectors over land where residences are located within five miles.

In addition to the milk animal and residence census a garden census is performed.

The census is conducted each year to identify the gardens near the site that are to be used for the collection of food product samples. The results of the garden census are not provided in this report. The results are used only to identify appropriate sample locations. The garden census is not required by the Technical Specifications if broadleaf vegetation sampling and analysis is performed.

l 3-24 I

m~.-

3.5 CIIANGES TO THE REMP PROGRAM 3.5.1 The following change was implemented during the 1995 sampling program.

i A. Food product location S was added to the program during 1995. This is a new location which was added due to its higher D/Q.

It is designated as a Technical Specification location.

i

)

B. Food product location Z was not utilized by the sampling program during 1995 because of the higher disposition (D/Q) potential of other locations.

C. Food product location R was added to the program during 1995.

Location R is an optional location.

D. Food product location P was not utilized during 1995 due to higher deposition potential (D/Q) oflocation R.

l 3-25

P 3.6 DEVIATION AND EXCEPTIONS TO THE PROGRAM Exceptions to the 1995 sample program concerns those samples or monitoring requirements which are required by the Technical Specifications.

This section addresses the reporting requirements of Section 6.1.a of the RETS.

The following are deviations from the program specified by - the Technical i

Specifications:

A.

' Air radiciodine and particulate sampling iequired by the Technical Specifications Environmental air sample equipment at R-3 and R-4 off-site sampling wo stations was found to be inoperable on 4/12/95 from 2100 to 2330

{

hours. There was a power outage in the area during this time.

't o

Environmental air sample equipment at R-5 off-site station was inoperable from 7/15/95 at 0500 to 7/18/95 at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months due to a j

power interruption. The power interruption was due to high winds and severe weather conditions.

l o

No other sample downtime was observed during 1995 for any Technical l

Specification required air radioiodine and partiediate sampling locations.

Other occurrences of downtime for optional air sampling stations were l

documented for 1995. However, these occurrences were minimal and

'i are not presented here because optional air sampling stations are not i

l required by the Technical Specifications.

B.

Direct Radiation Measurements o

The Thermolouminscent Dosimeters (TLD) for location number 78, a Technical Specification location, were lost for the fourth quarter 1995 sample period. The dosimeters were subsequently found and analyzed showing typical results for this location. The results are not included in this report as appropriate control badge results were not available.

3-26

3.7 STATISTICAL METIIODOLOGY There are a number of statistical calculation methodologies used in evaluating the data from the environmental monitoring program. These methodologies include j

detennination of standard deviation, the mean and associated error for the mean and the lower limit of detection (LLD).

3.7.1 ESTIMATION OF TIIE MEAN AND STANDARD DEVIATION i

The mean, (R), and standard deviation, (s), were used in the reduction of the data generated by the sampling and analysis of the various media in the JAFNPP Radiological Environmental Monitoring Program (REMP). The following equations were utilized to compute the mean (X) and the standard deviation (s):

A. Mean n

X=i=1 X'.

N l

where, i

X

= estimate of the mean.

i

= individual sample, i.

N, n = total number of samples with positive indications.

X

= value for sample i above the lower limit of detection.

i B. Standard Deviation 1/2 n

{ (X, - X)2 S_

.1=1 (N-1) 3-27

where, X = mean for the values of X s = standard deviation for the sample population.

3.7.2 ESTIMATION OF TIIE MEAN AND TIIE ESTIMATED ERROR FOR TIIE MEAN In accordance with program policy, two recounts of samples are performed when the initial count indicates the presence of a plant related radionuclide(s). When a radionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that mean.

In cases where more than one positive sample result is available, the mean of the sarnple results and the estimated error for the mean are reponed in the Annual Report.

The following equations were utilized to estimate the mean (5) and the associated propagated error.

A. Mean n

X=i=1 X*.

N

where, X

= estimate of the mean.

i

= individual sample, i.

N,n = total number of samples with positive indications.

X

= value for sample i above the lower limit of detection.

i I

3-28

B. Error of the Mean (Reference 18) n ERROR MEAN = {

(ERROR)2 i =1 N

where, ERROR MEAN = propagated error i

= individual sample ERROR

= 1 sigma

error of the individual analysis N, n

= ntimber of samples with positive indications Sigma (c)

Sigma is the greek letter used to represent the mathematical term Standard Deviation.

Standard Deviation is a measure of dispersion from the arithmetic mean of a set of numbers.

3-29 i

i j

3.7.3 LOWER LIMIT OF DETECTION (LLD)

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

The LLDs are speciGed by the Technical SpeciScations for radionuclides in speciDe media and are determined by taking into account the overall measurement methods. The equation used to calculate the LLD is:

4.66 s, LLD =

(E) (V) (2.22) (Y) exp (-AAt)

Where:

LLD is the a priori lower limit of detection, as denned above (in picocurie per unit mass or volume);

is the standard deviation of the background counting rate or of the Sb counting rate of a blank sample, as appropriate (in counts per minute);

E is the counting efnciency (in counts per disintegration);

V is the sample size (in units of mass or volume);

2.22 is the number of disintegrations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular radionuclide; At is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

3-30

. ~. ~ _

The RETS LLD formula assumes that:

o The counting times for the sample and background are equal.

o The count rate of the background is approximately equal to the count rate of the sample.

In the RETS program, LLDs are used to ensure that minimum acceptable

- detection capabilities are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative). Table 3.8-1 lists the RETS program required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are routinely much lower than those specified by the RETS.

l l

1 I

j 3-31 l

,,e_

i l

3.8 COMPLIANCE WITil REQUIRED LOWER LIMITS OF DETECTION (LLD)

Table 6.1-3 of the Radiological Effluent Technical Specification (RETS) specifies the detection capabilities for environmental sample analysis (see Report Table 3.8-1).

Section 7.3.d of the RETS requires that a discussion of all analyses for which the required LLDs specified were not routinely achieved be included in the Annual j

Radiological Environmental Operating Report. Section 3.8 is provided pursuant to this requirement.

3.8.1 All sample analyses performed in 1995, required by the RETS, achieved the Lower Limit of Detection (LLD) specified by RETS Table 6.1-3.

l l

t a

4 3-32

TABLE 3.8-1 REQUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

Water Airborne Particulate Fish Milk Food Products Sediment 3

Analysis (pCi/l) or Gases (pCi/m )

(pCi/kg wet)

(pCi/l)

(pCi/kg, wet)

(pCi/kg, dry) gross beta 4

0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260

$Co-58,60 15 130 Zn-65 30 260 Zr/Nb-95 15 I-131 15(a) 0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba/La-140 15 15 (a) No drinking water pathway exists at the Nine Mile Point Site under normal operating conditions due to the direction and distance of the nearest drinking water intake. Therefore, an LLD value of 15 pCi/ liter is used.

4.0 SAMPLE

SUMMARY

TABLES IN BRANCII TECIINICAL POSITION FORMAT All sample data is summarized in table form. The tables are titled " Radiological Monitoring Program Annual Summary" and use the following format as specified in the NRC Branch Technical Position

)

Column 4

1 Sample medium.

2 Type and number of analyses performed.

3 Required Lower Limits of Detection (LLD), see Section 3.8, Table 3.8-1.

This wording indicates that inclusive data is based on 4.66 s3 (sigma) of background (see Section 3.7).

4 The mean and range of the positive measured values of the indicator locations.

5 The mean, range, and location of the highest indicator annual mean.

Location designations are keyed to Table 3.3-1 in Section 3.3.

6 The mean and range of the positive measured values of the control locations.

7 The number of nonroutine reports sent to the ' Juclear Regulatory Commission.

NOTE:

Only positive measured values are used in statistical calculations.

4-1

RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1995 Location (b) of Control Type and Indicator Locations:

Highest Annual Mean:

Location:

Number of Medium Number of Mean...(al.

Locations & Mean (a)

.Mean (a)

Nonroutine (units)

Analysis LLD Range Designation Range

-Range' Reports-Surface H-3 (8) :

3000 320 (1/4l No. 3 320 (1/4i 230 (1/4) 0 (Lake) Water 320 - 320 0.5 @ 70*

320 - 320 230 - 230 (pCi/litar)

GSA (24) :

Mn-54 15

<LLD

<LLD 0

Fe-59 30

<LLD

<LLD 0

p Co-58 15

<LLD

<LLD 4

h)

Co-60 15

<LLD

<LLD 0

Zn-65 30

<LLD

<LLD 0

Zr-95 15

<LLD

<LLD 0

Nb-95 15

<LLD

<LLD 0

I-131 15

<LLD

<LLD 0

Cs-134 15

<LLD

<LLD 0

Cs-137 18

<LLD

<LLD 0

Ba/La-140 15

<LLD

<LLD 0

~

l l

RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 l

OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1995 Location (b) of Control Type and Indicator Locations:

Highest Annual Mean:

Location:

Number of l

Mediiua Number of Mean (al Locations & Mean (a)

Mean (a)

Nonroutine l

(units)

Analysis LLD Range Designation Range Range Reports' Shoreline ggg (4 3,

Sediment (Pci/g-dry)

Cs-134 0.15

<LLD

<LLD 0

l 0.15 (2/2)

No. 5 0.15 (2/2)

<LLD 0

Cs-137 0.18 0.14 - 0.15 1.5 @ 80' O.14 - 0.15

^

/g-wet)

Mn-54 0.13

<LLD

<LLD 0

A Fe-59 0.26

<LLD

<LLD 0

Co-58 0.13

<LLD

<LLD 0

Co-60 0.13

<LLD

<LLD 0

Zn-65 0.26

<LLD

<LLD 0

Cs-134 0.13

<LLD

<LLD 0

Cs-137 0.15 0.019 (2/17)

No. 03 0.022 (1/8) 0.019(3/10) 0 0.016 - 0.022 0.6 @ 55*

0.022 - 0.022 0.017-0.023

^

r ucts (pCi/g-wet)

I-131 0.06

<LLD

<LLD 0

Cs-134 0.06

<LLD

<LLD 0

Cs-137 0.08 0.012 (2/17)

No. K 0.012 (1/23)

<LLD 0

f 0.011 - 0.012 1.7 @ 90*

0.012 - 0.012

RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1995 Location (b) of Control Type and Indicator Locations:

Highest Annual Mean:

Location:

Ntaber of Medium Number of Mean M Locations & Mean (a)'

Mean (a)

Nonroutine (units)

Analysis

'LLD Range Designation. Range Range Reports Milk (f)

GSA (90):

(pCi/ liter)

Cs-134 15

<LLD

<LLD 0

Cs-137 18

<LLD

<LLD 0

Ba/La-140 15

<LLD

<LLD 0

I-131(90):

1

<LLD

<LLD 0

1

RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1995 f

Location (b) of Control Type.and Indicator Locations:

Highest Annual Mean:

Location:

Number of ;i Medium Number of Mean (a)

Locations & Mean - (a)

Mean (al.

Nonroutine' (units)

Analysis

.LLD Range.

Designation Range Range Reports f

Air G.B.

(260):

0.01 0.015 (208/208)

R-1 0.014 (52/52) 0.014 (52/52) 0 Particulate G.004 - 0.031 1.8 0 88*

0.006 - 0.031 0.006 - 0.023 i

and Radiciodine I-131(260):

0.07

<LLD

<LLD 0

(d)

(pCi/m')

GSA (60):

s dn Cs-134 0.05

<LLD

<LLD 0

Cs-137 0.06

<LLD

<LLD 0

i TLD Gamma l

(mrem per Dose '(127):

N/A 4.8 (119/119) (c)

No. 85 9.0 (4/4) (e) 4.2 (8/8) 0 l

standard 3.2 - 9.6 0.2 @ 294*

8.3 - 9.6 3.4 - 4. 9 month) l r

i

ANNUAL

SUMMARY

TABLE NOTES Data for the Annual Summary Tables is based on RETS required samples only.

=

N/A = Not applicable.

(a)

Fraction of detectable measurement to total measurement.

=

(b)

Location is distance in miles, and direction in compass degrees. Location numbers keyed to Table 3.3-1

=

and results table location designation numbers.

(c)

Indicator TLD locations are: #7, 23, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93,

=

94,95,96,97,98,15,18,56, and 58. Control TLDs are all TLDs located beyond the influence of the site

(#14, 49).

Indicator sampics from environmental stations R1 off-site, R2 off-site, R3 off-site, and R4 off-site.

(d)

=

Control samples are samples from R5 off-site environmental station.

This dose is not representative of doses to a member of the public since this area is located near the north (c)

=

shoreline which is in close proximity to the generating facility and is not accessible to members of the public (see Section 5.2.4, TLDs).

The RETS criteria for indicator milk sample locations includes locations within 5.0 miles of the site.

(f)

=

There are no milk sample locations within 5.0 miles of the site. Therefore, milk samples are collected from locations greater than 5.0 miles from tSc site based on the location D/Q values.

l 4

l 5.0 DATA EVALUATION AND DISCUSSION A.

Introduction i

l Each year the results of the Annual Radiological Environmental Monitoring Program are evaluated considering natural processes in the environment and the collection of past environmental radiological data. A number of factors are considered in the course of evaluating and interpreting the Annual Environmental Radiological Data.

This interpretation can be made using several methods including trend analysis, population dose, risk estimates to the j

general population based on environmental concentrations, effectiveness of plant effluent controls and specific research areas. The report not only presents the data collected during the 1995 sample program but also assesses the significance of radionuclides detected in the environment. It is important to note that detection of a radionuclide is not, of itself, an indication of

]

environmental significance. Evaluation of the impact of the radionuclide in j

terms of potential increased dose to man, in relation to natural background, is necessary to determine the true significance of any detection.

B.

Units of Measure Some of the units of measure used in this report are explained below.

Radioactivity is the number of atoms in a material that decay per unit of time.

Each time an atom dec,ays, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms are decaying. One curie of activity indicates the decay of 37 million atoms per second.

Smaller units of the curie are used in this report. Two common units are the microcurie ( Ci), one millionth of a curie, and the picocurie (pCi), one trillionth of a curie. Picocurie is the unit of radiation that is used in this report.

The mass, or weight, of radioactive material which would result in one curie of activity depends on the disintegration rate, for example, one gram of radium-226 is one curie of activity, but it would require about 1.5 million grams of natural uranium to equal one curie since radium-226 is more radioactive than natural uranium.

5-1

C.

Dose / Dose to Man The dose or dose equivalent simply put is the amount of ionizing energy deposited or absorbed in living tissue. The amount of energy deposited or ionization caused is dependent on the type of radiation. For example, alpha radiation can cause dense localized ionization that can be up to 20 times the amount of ionization for the same energy imparted as do gamma or x-rays.

Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent which is an estimate of the possible biological damage resulting from exposure to any type ofionizing radiation. The dose equivalent is measured in rem (roentgen equivalent man).

There' ore, a In terms of environmental radiation, the tem is a large unit.

f smaller unit, the millirem (mrem) is oRen used. One millirem is equal to 1/1000 of a rem.

The dose to man refers to the dose or dose equivalent that is received by members of the general public at or beyond the site boundary based on measured concentrations of radioactive material measured on the environment.

The pathways that contribute to the dose to man are the inhalation pathway, the ingestion pathway and direct radiation.

D.

Discussion There are four separate groups of radionuclides that were measured in the environment in the media analyzed for the 1995 sampling program. The first of these groups consists of those radionuclides that are naturally occurring.

The environment contains a significant inventory. of naturally occurring radioactive elements. 'lhe components of natural or background radiation includes the decay of radioactive elements in the earth's crust, a steady stream of high-energy particles from space called cosmic radiation, naturally-occurring radioactive isotopes in the human body like potassium-40, medical procedures, man-made phosphate fertilizers (phosphates and uranium are oRen found together in nature), and even household items like televisions. In the United States, a person's average annual exposure from background radiation is 360 mrem, as illustrated on the Background Radiation Chart.

5-2

l Background Radiation 1

ALL SOURCES MAN-MADE RADIATION EXPOSURE SOURCES 360 rntem/yr i

MEmCAL x RAYS 11%

RADON 65%

INTERNAL EMITTERS 11%

TERRESTIAL 0%

f NUCLEAR MEDCINE 4%

COSMIC 0%

N_

d,,

N

h *8h e=a MADE 18%

tem es.

3.;.

i Many radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing, These radionuclides are expected to be present in many of the environmental samples collected in the vicinity of the Nine Mile Point Site. Some of the radionuclides normally present include:

o tritium, present as a result of the interaction of cosmic radiation in the upper atmosphere.

o beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere.

c potassium-40, radium-226, a naturally occurring radionuclide normally found in humans and throughout the environment, and fallout radionuclides from nuclear weapons testing, including tritium, o

cesium-137, strontium-89, and strontium-90. These radionuclides may also be released in minute amounts from the nuclear facilities.

5-3

i Beryll:um-7 and potassium-40 are especihlly common in IWMP samples.

Since they are naturally occurring and are abundant, positive results for these radionuclides are discussed in some cases in Section 5.0 of this report. The data on primary naturally occurring radionuclides are included in Section 6.0, Results Tables.

Comparisons of program camples to natural background radiation are made throughout this section to help put program results into perspective and to aid the reader in determining what, if any, significant impact is demonstrated by the Radiological Environmental Monitoring Program (REMP) results.

The second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earth's upper atmosphere.

Atmospheric nuclear testing during the early 1950s produced a measurable inventory of radionuclides presently found in the lower atmosphere as well as in ecological systems. In 1963 an Atmospheric Test Ban Treaty was signed.

Since the treaty, the global inventory of man made radioactivity in the environment has been grcitly reduced through the decay of short lived radionuclides and the removal of radionuclides from the food chain by such natural processes as weathering and sedimentation. This process is referred to in this report as ecological cycling. Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China. In each case, the usual radionuclides associated with nuclear detonations were detected for several months following the test and then after a peak detection period, diminished to a point where most could not be detected. Although reduced in frequency, atmospheric testing continued into the 1980's. The resulting fallout or deposition from these most recent tests has influenced the background radiation in the vicinity of the site and was evident in many of the sample medias analyzed over the years with the highest concentration noted in samples for the 1981 Environmental Surveillance Program.

Cs-137 was the major oyproduct of this testing and is still detected in a number of environmental media.

A third group of radionuclides were detected as a result of the Chernobyl accident which occurred in the Soviet Union in April 1986. The resulting fallout or deposition from this accident influenced the background radiation in the vicinity of the site and was easily detected in many of the sample media 5-4

analyzed during 1986. Quantities of Nb-95, Ru-103, Ru-106, I-131, La-140, Cs-134, and Cs-137 were detected in air particulate samples during May and June of 1986. Milk samples collected and analyzed after April,1986 contained measurable concentrations of I-131 and Cs-137.

The origin of these radionuclides was a direct result of fallout from the Chemobyl accident.

The fourth group of radionuclides that may be detected in the environment are those that are related to nuclear power technology.

These radionuclides are the byproduct of the operation of light water reactors.

These byproduct radionuclides are the same as those produced in atmospheric weapons testing and found in the Chernobyl fallout. This commonality makes an evaluation of the source of these radionuclides that may be detected in environmental samples difficult, if not impossible. During 1995, H-3 and Cs-137 were the only potentially plant-related radionuclides detected in the RETS samples.

A number of factors must be considered in performing radiological sample data evaluation and interpretation.

The evaluation is made at several levels including trend analysis and dose to man. An attempt has been made not only to report the data collected during 1995, but also to assess the significance of the radionuclides detected in the environment as compared to natural and other man-made radiation sources.

It is important to note that detected concentrations of radionuclides in the local environment as a result of mans technology are very small and are of no or little significance from an environmental or dose to man perspective.

The 1987 per capita dose was determined to be 360 mrem per year from all sources, as noted in the NCRP Report No. 93 (Reference 17). This average dose includes such exposure sources as natural radiation, occupational exposure, weapons testing, consumer products and nuclear medicine. The 1987 per capita dose rate due to natural sources was 300 mrem per year. The per capita radiation dose from nuclear power production nation wide is less than one mrem per year (Reference 10).

The natural background gamma radiation in the environs of the Nine Mile Point Site, resulting fnim radionuclides in the atmosphere and in the ground, accounts for approximately 60 - 65 mrem per year. This dose is a result of 5-5

l 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 50 mrem per year, as a background dose, is significantly greater than any rossible doses as a result of routine operations at the site during 1995.

The results for each sample media is discussed in detail in Section 5.0. This includes a summary of the result, the estimated environmental impact, a detailed review of any relevant detections with a dose to man estimate where appropriate, and an analysis of possible long term and short term trends.

In the routine implementation of the Radiological Environmental Monitoring Program, additional or optional environmental pathway media are sampled and analyzed. These samples are obtained to monitor the secondary pathways and to maintain the analytical data base established in 1975 when the plant began commercial operation. These additional samples include; aquatic vegetation (cladophora), bottom sediment, mollusk, milk (Sr-90), meat, poultry and soil samples. In addition to the optional sample media, additional locations are sampled and analyzed for those pathways required by Technical Specifications.

These additional sample locations are obtained to ensure that a variety of environmental pathways are monitored in a comprehensive manner. Data from s

I additional sample locations common with the required Technical Specification sample media are included in the data presentation and evaluation.

When additional locations are included, the use of this data will be specifically noted in Section 5.0.

Section 6.0 contains the analytical results for the sample media addressed in this report. Tables are provided for each required sample media analyzed during the 1995 program.

Section 7.0, titled HISTORICAL DATA, contains statistics from previous years environmental sampling. The process of determining the impact of plant operation on the environment includes the evaluation of past analytical data, a tool by which trends are discemed. As state-of-the-art detection capabilities improve, data comparison is difficult in some cases. For example, Lower Limits of Detections (LLDs) have improved significantly since 1969 due to technological advance in laboratory procedures and analytical equipment.

5-6

5.1 AQUATIC PROGRAM The aquatic program consists of samples from three environmental pathways. These pathways are:

o Shoreline Sediment 4

o Fish o Surface Waters Section 6.0, Tables 6.1 through 6.4 represent the analytical results fer the aquatic samples collected for the 1995 sampling period.

4 4

)

i 5-7

l 5.1.1 SIIORELINE SEDIMENT RESULTS A. Results Summary l

A total of four sediment samples were collected for the 1995 sample program. Small concentrations of Cs-137 were detected in two of the four 1995 samples. Cs-137 was detected in the two samples taken at Sunset Beach which is the indicator location. The Cs-137 concentrations I

ranged from a minimum of 0.143 pCi/g to a maximum of 0.153 pCi/g.

The mean concentration for the two samples was 0.15 pCi/g. Cs-137 was not detected in any of the control location samples. The source of the Cs-137 detected in the indicator shoreline sediment is considered to be the result of fallout from atmospheric nuclear weapons testing and not from operations at the site. Cs-137 was detected at the control location in the 1993 samples.

The mean concentration of Cs-137 measured in 1995 samples represents a decrease in the mean concentration from 1993 (0.32 pCi/g) and 1994 (0.22 pCi/g) to 0.15 l

pCi/g measured in 1995. The 1995 results are consistent with the average results for the past five years (1990 through 1994)(0.23 pCi/g).

The results for th' contral location was <LLD. The calculated potential whole body and skin doses which may result from the measured Cs-137 l

concentrations are extremely small and are insignificant when compared to natural background doses.

No other plant related radionuclides were detected in the 1995 shoreline sediment samples.

I 1

5-8

l i

B. Data Evaluation and Discussion Shoreline sediment samples are routinely collected twice per year from the shoreline ofI.ake Ontario. Samples are collected from one indicator location (Sunset Beach), and one control location (Lang's Beach). The first sample collection was made in April 1995 at both the indicator and control locations. The second shoreline sample collection was made in October 1995 again, at both the indicator and the contml locations. The results of these sample collections are presented in Section 6.0, Table 1.

Several radionuclides were detected in sediment samples using gamma spectral analysis.

Three of the detected radionuclides were naturally occurring. K-40 was detected at both the control location and indicator location. The results ranged from 20.3 pCi/g (dry) to 21.2 pCi/g (dry) at the indicator location, and 13.4 pCi/g (dry) to 15.9 pCi/g (dry) at the control location.

Concentrations of AcTh-228 and Ra-226, which are naturally occurring, were also detected at both indicator and control locations.

Cs-137 was present in the indicator samples collected for the 1995 program. The mean concentration for these two samples was 0.15 pCi/g (dry). The principle source of the Cs-137 present in the environment has been the atmospheric testing of r.uclear weapons. Cs-137 and Cs-134 are both produced in fission reactors and were introduced into the environment from the accident at Chemobyl, but only Cs-137 is found in current weapons test debris. Since Cs-134 has a significantly shorter half-life, detected concentrations of Cs-137 attributable to plant operations (e.g., recent releases), should be accompanied by Cs-134. An absence of such corroborating Cs-134 concentrations would indicate that l

the presence of Cs-137 in these samples is not distinguishable from the existing background and is attributed primarily to weapons testing and l

residual concentrations; i.e., not to recent plant operations.

This assessment is further substantiated by the presence of Cs-137 in the 1993 control sample and other environmental media.

5-9

The absence of Cs-137 in the control samples is attributed to the differences in the sediment types between the two sample locations.

Few shoreline regions west of the site contain fine sediment and/or sand which would be representative of the indicator location. It is difficult to obtain control samples which are comparable in physical. and chemical characteristics to the indicator samples. Other factors, which include changing lake level and shoreline erosion, further complicate any consistency in shoreline sediment sampling. Recent soil samples from locations beyond any expected influence from the site, have contained levels of Cs-137 equal to or greater than the concentration found in 1995 shoreline sediment.

The Cs-137 in soil samples is attributed to weapons testing fallout. Therefore, most shoreline sample containing soil or sediment would also contain Cs-137.

C. Dose Evaluation The radiological impact of Cs-137 measured in the shoreline sediment can be evaluated on the basis of dose to man. In the case of shoreline sediments, the critical pathway is direct radiation to the whole body and skin. Using the parameters provided in Regulatory Guide 1.109, the potential dose to man in mrem per year can be calculated.

The following regulatory guide values were used in calculating the dose to man:

o A teenager spends 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year at the beach area or on the shoreline.

2 o

The sediment has a mass of 40 kg/m (dry) to a depth of 2.5 cm.

o The shoreline width factor is 0.3.

o The maximum measured concentration of 0.15 pCi/g (dry) remains constant for the year.

Using these conservative parameters, the potential dose to the maximum exposed individual (teenager) would be 0.0005 mrem / year to the whole body and 0.0006 mrem / year to the skin. This calculated dose is very 5-10

i small and is insignificant when compared to the natural background annual exposure of approximately 60 mrem.

D. Data Trends The average Cs-137 concentrations in the shoreline sediment indicator-samples for 1995 was 0.15 pCi/g which is lower then the concentrations measured in 1989 - 1990 and 1993 - 1994. The mean values for 1989 -

1990 were both 0.29 pCi/g. The mean concentrations measured in 1993 and 1994 were 0.32 pCi/g and 0.22 pCi/g respectively.

I The presence of Cs-137 in the 1993 control sample was the first positive measurement at the control location since sediment sampling was L

implemented in 1985. Cs-137 was not detected in the cont'rol sample in the 1995 samples.

A review of indicator and control sample results for 1985 - 1988 indicate only naturally occurring radionuclides present in shoreline sediment. The period from 1989 - 1995 show the presence of Cs-137-in the indicator samples. The five year data base shows an emergence of Cs-137 concentratiora in 1989 which continues through 1995. The trend since 1989 shows a reduction in Cs-137 concentrations over the four year period to the concentration of.0.13 pCi/g measured in 1992.

The 1993 sample showed an increase in Cs-137 concentration to 0.32 pCi/g followed by a reduction in concentration to 0.22 pCi/g in 1994 and a further reduction in 1995 to 0.15 pCi/g. The overall five year trend for Cs-137 concentrations in shoreline sediment is steady with the small variations in concentrations from year to year attributable to l

statistical and sample variations. The concentrat'ons b Cs-137 in the sediment samples are consistent with other sample locations in New York State sampled and analyzed by the New York State Department of Health (Reference 19).

Shoreline sediment sampling' commenced in 1985. Prior to 1985, no l

data was available for long term trend analysis.

t Tables 1 and 2 in Section 7.0 illustrates historical environmental data for shoreline sediment samples.

5-11

I 5.1.2. - FISII SAMPLE RESULTS A. Results Summary A total of 27 fish samples were collected for the 1995 sample prou.am.

Analysis of the 1995 fish samples exhibited detectable concentrat:ons of radionuclides related to past weapons testing and natural origins (naturally occurring). The 1995 mean results (control and indication

]

combined) are the lowest concentration of Cs-137 measured in fish since operation of the FitzPatrick Plant began in 1976. Small concentrations i

of Cs-137 were detected in approximately 19% of the total fish samples collected from both the on-site and off-site locations. This percentage is down significantly from the previous year which had positive detections in 37% of the samples. The ratio of samples havi~ng positive detections to total samples collected was higher for the control samples (30%) than for the indicator samples (12%). Detectable concentrations of K-40, a naturally occurring radionuclide, were found in all fish samples collected for the 1995 program. No other radionuclides were detected in the 1995 fish samples.

The detectable levels of Cs-137 in the fish samples are small. The i

control and indicator mean concentration values were equal at 0.019 pCi/g. These low levels of Cs-137 represent no significant dose to man or impact on the environment.

As noted above, the measured concentrations of Cs-137 in the fish samples are the result of fallout i

from past weapons testing. Comparable concentrations of Cs-137 are routinely found in samples of other aquatic media such as shoreline sediment, bottom sediment and aquatic vegetation. The potential whole body and critical organ doses calculated as a result of fish consumption by humans is extremely small. The dose that could result from the Cs-137 in fish is considered background exposures because of the sources of the Cs-137.

The fish sample results demonstrate that plant operations at the Nine Mile Point Site have no measurable radiological environmental impact i

on the upper levels of the Lake Ontario food chain. The 1995 results continue to show a long term downward trend in fish Cs-137 concentrations with concentrations stabilizing over the last 9 - 10 years.

5-12

l The mean indicator Cs-137 concentration for 1994 and 1995 were the

.-lowest measured concentrations since the beginning of the surveillance program 20 years ago (1974).-

B. Data Evaluation and Discussion Fish 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 #1 (#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.

All sampus were analyzed for gamma emitters. Table 6-2 shows individual results for all the samples in units of pCi/g (wet).

The spring fish collection was made up of eleven individual samples representing four separate species. Lake trout, white sucker, smallmouth bass and brown trout were collected from a combination of the lake sample locations. Brown trout, smallmouth bass and lake trout where collected at all three sample locations.

The total fall fish collection was comprised of sixteen individual samples representing seven individual species. Brown trout, smallmouth bass, white sucker, walleye and salmon samples were collected at the indicator sampling locations (NMP and JAF). One sample, with the exception of chinook salmon, of each of these species was also collected at the control location (Oswego Harbor).

Cs-137 was not detected in any of the seven indicator samples or the five control samples collected during the spring.

In the fall collection, Cs-137 was detected in five of the sixteen samples collected from both the control (3 of 6 samples) and indicator (2 of 10 samples) locations.

Control samples showed a mean Cs-137

)

concentration that was slightly higher than the indicator sample mean.

The mean annual concentrations for both the indicator and control i

.5-13

]

j I

results were equal at 0.019 pCi/g (wet). The Cs-137 concentrations at the indicator locations ranged from 0.016 to 0.022 pCi/g (wet) and the control samples ranged from 0.014 to 0.017 pCi/g (wet).

The following graph presents the average Cs-137 concentrations for the fish species analyzed for 1995. Walleye samples yielded the highest average Cs-137 concentration for the control locations and lake trout yielded the highest Cs-137 concentration for the indicator location.

JAMES A. FITZPATRICK N.P.P.

1495 0 04 FISH Co 13 7 0 035 -

0 03

_ D 02S g Co 8"

o oss --

0 01

~

.. u.

0 00.

e lEINDICATOR WCONTROLl K-40 was detected in all of the spring and fall samples collected. K-40 is a naturally occurring radionuclide, and is not related to power plant operations.

Ra-226, also naturally occurring, was found at varying levels at both the indicator and control locations. No other radionuclides were detected in the spring fish samples.

5-14

C. Dose Evaluation i

J Some Lake Ontario fish species may be considered an important food source due to the local sport fishing industry. Therefore, these fish become an integral part of the human food chain.

Based on the importance of fish in the local diet a conservative estimate of potential dose to man can be calculated. Assuming that an adult consumes 21.0

)

kg of fish per year and a teen consumes 16 kg of fish per year j

(Regulatory Guide 1.109 maximum exposed age group) and the fish j

consumed contains an average Cs-137 concentration of 0.019 pCi/g 1

(wet) (annual mean result for both indicator and control samples f' r o

1995), the adult whole body dose received would be 0.028 mrem per -

year. The organ of interest for Cs-137 is the teen liver which would receive a calculated dose of 0.044 mrem per year. The Cs-137 whole body and organ doses are conservative potential doses associated with consuming fish species from the Nine Mile Point area which are represented by both the indicator and control samples. Due to the long

)

half life of Cs-137, no radiological decay is assumed for the calculation of doses.

In summary, the potential whole body and organ doses observed as a result of consumption of fish is small. The dose to man received from both the indicator and control sample groups are considered to be background exposures. The dose to man from operation of the plants at Nine Mile Point via the fish pathway is of no significance.

)

5-15

l D. Data Trends Results for the previous five years (1990 through 1994) have shown a consistently stable downward trend for Cs-137 levels in control and indicator samples. During the period of 1988 through 1993, control and indicator mean results were consistent with a small rise in 1990. The 1995 results are the lowest Cs-137 concentrations measured to date (combined mean) over the 20 year existence of the sampling program.

The graph below illustrates the mean Cs-137 concentration for 1995 and the previous five years.

1 JAMES A. FITZPATRICK N.P.P.

ANNUAL MEAN CONCENTRATION Fish Cs-137 0.1 0.09 0.08 -

0.07 -

0.06 -

E 0.05 l

E S 0.04 -

0.03 -

00 1990 1991 1992 1993 1994 1995 year glNDICATOR ECONTROL l The long term trend shows that mean concentrations of Cs-137 for indicator samples has decreased from a maximum concentration of 1.4 pCi/g (wet) in 1976 to a minimum level of 0.019 pCi/g (wet) in 1994 and 1995. Control sample Cs-137 results have also decreased from a i

maximum level of 1.2 pCi/g (wet) in 1976 to a minimum level of 0.019 pCi/g (wet) in 1995.

5-16

The general decreasing long term trend for Cs-137, illustrated in the graph below, is most probably a result of the cesium becoming unavailable to the ecosystem due to ion exchange with soils and sediments and radiological decay.

The concentrations of Cs-137 detected since 1976 in fish are a result of weapons testing fallout. The general downward trend in concentrations will continue as a function of additional ecological cycling and nuclear decay. There was no apparent effect from the 1986 Chemobyl Nuclear Plant accident during 1986 relative to Cs-137 results in fish samples although an effect may have been detected during the period of 1987 through 1990 since both indicator and control location mean results increased slightly.

JAMES A. FITZPATRICK j

nsw c..ia,

_.. ~. -

l I..

=L" s_Lan..

IEiiiiIiii i i i i I i i I i i i I The 1995 mean Cs-137 indicator concentration of 0.019 pCi/g (wet) shows a decrease in concentration from 1976 by a factor of 73. Control sample results have decreased from a maximum level of 1.2 pCi/g (wet) in 1976 to a level of 0.019 pCi/g (wet) in 1995. Fish results for the 1995 control samples show a decrease in concentration by a factor of approximately 49 when compared to preoperational data (1974) and by a factor of about 63 compared to 1976.

5-17

Tables 7-3 and 7-4 in Section 7.0 show historical environmental sample data for fish. Full size reproductions of the fish result graphs are found in Section 8.0.

5-18

5.1.3 SURFACE WATER (LAKE)

A. Results Summary The Radiological Effluent Technical Specifications (RETS) required that monthly surface water samples be taken from the respective inlet water supply of the James A. FitzPatrick N.P.P. and Niagara Mohawk's Oswego Steam Station. In conjunction with the RETS sample, three additional Lake Ontario surface water locations are sampled and' analyzed. These additional locations are the Oswego City Water Intake, the NMP Unit #1 Intake and the NMP Unit #2, Intake. Gamma spectral analysis was performed on 24 monthly composite samples from the RETS locations and on 36 monthly composite samples from the additional sample locations. The results of the gamma spectral analysis show that only naturally occurring radionuclides were detected in samples from the five locations (60 samples) collected for the 1995 Sampling Program.

The two naturally occurring radionuclides are K-40 and Ra-226 and are not related to operations of the plant. Monthly composite samples show no presence or buildup of plant related gamma emitting isotopes in the waters of Lake Ontario as a result of the operation of the plant.

Quarterly composite samples collected from the same locations are analyzed for tritium. The 1995 annual mean tritium concentration for the Oswego Steam Station Inlet (control location) was 230 pCi/l which is the result of one positive detection. Annual mean concentration for the JAF inlet, which serves as the indicator location, was 320 pCi/l waich again is the result of a single positive detection. Tritium results for 1995 show slightly higher mean concentrations (<240 pCi/l) for the three iniicator locations located at the Nine Mile Point Site relative to tne centrol sample results of 230 pCi/1. Results of the twelve Nine Mile Pout samples collected showed only two positive detections of tritjum.

Surface water sample results demonstrate that there is no measurable radiological impact on the surface waters of Lake Ontario from tritium concentrations based on the levels measured. The mean concentration for the indicator and control are within the normal statistical variations for naturally occurring tritium.in surface water. The levels of tritium are routinely variable within the range of 200 - 500 pCi/1. The tritium results for 1995 are consistent with previously measured lake concentrations.

5-19

B. Data Evaluation and Discussion Gamma spectral analysis was performed on monthly composite samples from five Lake Ontario sampling locations. K-40 and Ra-226 were detected in samples from the five locations over the course of the 1995 sampling program. Both of these radionuclides are naturally occurring and are not plant related.

K-40 was detected consistently in both of the Technical Specification required intake canals. The James A. FitzPatrick inlet canal samples and Oswego Steam Station sarnples showed K-40 was detected in all twelve monthly samples. Ra-226 was also detected intermittently in both locations required by Technical Specifications and at the other optional sample locations.

Tritium sam;21es are quarterly samples that' are a composite of the appropriate monthly samples. Tritium was detected in two of the eight samples taken at the two locations required by Technical Specifications.

Tritium concentration for The James A. FitzPatrick inlet canal samples showed a single positive detection with a concentration of 320 pCi/ liter.

The Technical Specification control location (Oswego Steam Station i

inlet canal) showed a single positive tritium result of 250 pCi/ liter.

Tritium was also detected in two of the twelve optional lake samples taken. The tritium results for both of these samples was 200 pCi/ liter.

The positive tritium concentrations were measured in the first quarter Oswego City Water sample and the third quarter Nine Mile Point inlet canal.

Samples collected from the Oswego City water supply exhibit tritium concentrations in the range of <190 pCi/l to 200 pCi/1.

5-20

l A summary of tritium results Ea die 1995 sample program is listed below Sample Tritium Concentration pCi/ liter l

Location Minimum Maximum Mean (Annuan I

JAF Inlet

<l70 320*

320*

Oswego Steam Inlet

<l70 230*

230*

NMP #1 Inlet

<170 200*

200*

NMP #2 Inlet

<170

<230

<200 City Water Intake

<190 200*

200*

Single positive detection C. Dose Evaluation The Oswego Steam Station is considered a control location because of i

its distance from the site and the influence oflake current patterns and current pattems from the Oswego River located nearby. The current pattems distinguish the Oswego Steam Station intake and the near by Oswego City water intake as an "up-current" sampling point and the JAFNPP inlet canal as a "down-current" sampling point. The Nine Mile Point Site is located such that it would not have a radiological impact on Oswego drinking water supply. The Oswego City water intake is located west of the Oswego Steam Station inlet placing it upstream from the Nine Mile Point Site. The tritium concentrations measured in these upstream or control locations are representative of background levels present in Lake Ontario.

The radiological impact of background levels of tritium in water to members of the public is insignificant.

This can be illustrated by calculating a dose to the whole body and maximum organ.

Using Regulatory Guide 1.109 methodology, ingestion of water (5101/yr) at the indicator location (320 pCi/l) would result in a dose of 0.033 mrem to the child whole body and 0.033 mrem to the child liver (critical age group / organ). The calculated doses at the control locations are 0.024 mrem child whole body and 0.024 mrem to the child liver based on 230 5-21

pCi/1. Drinking water sampled in Oswego is drawn from Lake Ontario at a location more distant than the control location. Doses from tritium at this location were 0.021 mrem to the child whole body and 0.021 mrem to the child liver. Doses received as a result of water ingestion are approximately the same regardless of the location. Doses from all water sampled are considered background doses and are negligible.

D. Data Trends l

There are no data trends for gamma emitters such as Cs-137 and Co-60 as historically these radionuclides are not detected in lake water samples.

Tritium results for the 1995 lake water samples were consistent with results from the previous five years for both the indicator and control locations. During the previous five year period the maximum indicator and control concentration were measured in 1990 and 1991 respectively.

The mean tritium concentrations for the period of 1990 - 1994 range from 188 pCi/l to 290 pCi/l for the control and 220 pCi/l to 310 pCi/l for the indicator location. The mean 1995 tritium concentrations for the control was 230 pCi/l and 320 pCi/l for the indicator. The 1995 data is consistent with concentrations measured since 1990 with no distinct trend.

Mean tritium results of the control location (Oswego Steam Station) cannot 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 historical control sample data can be l

obtained by a review of previous data from the City of Oswego drinking I

water samples.

These drinking water samples are likely to be representative of the current control location because of the effects of the distance, predominate lake currents, and the discharge of the Oswego River. The Oswego City water intake is located in the same vicinity as the Oswego Steam Station inlet though offshore. The maximum annual mean concentration of city water was found in 1976 (652 pCi/l) and the minimum in 1982 (165 pCi/l).

l 5-22

The following graph illustrates the concentrations of tritium measured in Lake Ontario over the past 15 years at both an indicator and control location.

JAMES A FITZPATRICK N.P.P.

EURFACE WATER-TRITluP.1 meo

~

~~ * ~ *~~.~ _

i._,

i (t-I l

I ly_illl h lihlhrti

. i i IEiiiI i i i ! Iiiii I !I ii v,

Annual mean tritium results from previous city water samples from 1980 to 1995 show that the tritiurr concentrations have fluctuated over the years with no clear trend. The highest concentrations for the indicator location were detected in the period between 1982 and 1985. The maximum annual mean conceattation was found in 1982 (641 pCi/ liter) and the minimum in 1994 (220 pCi/ liter). Results for the period of 1982 through 1989 shows that the indicator samples were higher than the control samples. This trend reversed itself in 1990 and retumed in 1991 through 1993. In 1995 the indicator location was nigher than the control location which is the opposite of the 1994 results demonstrating the routine fluctuation measured in background tritium concentration.

5-23

5.2 TERRESTRIAL PROGRAM The terrestrial program consists of samples from four environmental pathways.

These pathways are:

o Airborne particulate and radiciodine o

Direct radiation i

o Milk i

o Food Products Tables 6-5 through 6-14 represent the analytical results for the terrestrial samples collected for the 1995 reporting period.

l l

5-24

.~

1 5.2.1 AIR PARTICULATEGROSS BETA A. Results Summary Weekly, air samples were collected and analyzed for gross beta particulate activity. A total of 52 samp!:s were collected from the control location R-5 and 208 samples were collected from the indicator locations R-1, R-2, R-3 and R-4 during 1995. These five locations are required by the Technical Specifications.

Additional air sampling locations are maintained and discussed under Section 5.2.1.B below.

The mean concentration of the control location, R-5, was 0.014 pCi/m' j

for 1995. The mean concentration for the indicator locations was also 2

0.014 pCi/m for 1995. The mean indicator and control results are equal and demonstrate that there are no increased airborne radioactivity levels in the general vicinity of the site. These results are among the lowest mean gross beta concentration measure to date since the inception of the site Environmental Monitoring Program in 1969. The consistency of these low concentrations over the past six years may indicate that the natural base line gross beta activity has been reached. It is possible that the manmade radionuclide contribution to the natural background from weapons testing can no longer be detected above the background concentrations of naturally occurring beta emitting radionuclides.

B. Data Evaluation and Discussion Ten air sampling locations are maintained in addition to those required by the Technical Specifications. A total of six on-site and nine off-site locations were sampled weekly for gross beta particulate activity. A total of 780 analyses were performed. Five of the nine off-site locations are required by Technical Specifications. These locations are R-1, R-2, R-3, R-4 and R-5.

R-5 is a control location required by the Technical Specifications and is located beyond any local influence from the site.

In addition, optional off-site and on-site air sample locations are maintained from which weekly samples are collected. The optional off-site locations are designated as D-2, E, F, and G. The optional on-site locations are designated as D-1, G, H, I, J and K.

5-25

Gross beta analysis requires that the samples are counted no sooner than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after collection. This allows for the decay of short half-life naturally occurring radionuclides and there by increasing the sensitivity of the analysis for plant related radionuclides.

Tables 6-5 and 6-6 in Section 6.0 present the weekly gross beta activity results for the off-site and on-site stations.

The average annual gross beta indicator concentration for the indicator stations (R-1, R-2, R-3 and R-4) and for the off-site station (R-5) were 3

identical at 0.014 pCi/m. The minimum, maximum and average gross beta results for sample locations required by Technical Specifications were:

3 pCi/m Location

Minimum Maximum Averace R-1 0.006 0.031 0.014 R-2 0.005 0.025 0.014 R-3 0.006 0.024 0.014 R-4 0.004 0.022 0.013 R-5 (control) 0.006 0.023 0.014

Locations required by the Technical Specifications 5-26

The mean weekly gross beta concentrati ns measured in 1995 are 9

illustrated in the graphs below.

AIR PARTICULATE FILTER 4ROSS BETA e 03 C 025 i

hkaesrRt.R2.R3,R4 Slatons Centut R5 &lseen s

DU i

f.cis N

j

. 0, 0 005 j

0 t 2 2 R E R R A 2 R k R R S ; ;O 3 ;8 4 7 i R E 2 WEEK No.1HS

-+-INDICATOR -e-CONTROL l I

i AIR PARTICULATE FILTER 4ROSS BETA e 03 0.025 hkatorR1 R2,R3,R4 sessens Concret RS Staten OM i

l A

esis

/

~

1 n oi V

D

_X I

0 005 l

1 O

..........aaanxna WEEK No.1M8

= INDICATOR -e-CONTROL l 5-27 i

l l

The smal: fluctuations observed in the gross beta activity over the year can be attributed to changes in the environment, especially seasonal changes. The concentration of naturally occurring radionuclides in the lower levels of the atmosphere directly above land are affected by time related processes such as wind direction, precipitation, snow cover, soil l

temperature and soil moisture content.

C. Dose Evaluation l

Dose calculations are not performed based on gross beta concentrations.

Dose to man as a result of radioactivity in air is calculated using the specific radionuclide and the associated dose factor. See Section 5.2.2.C for dose calculations from air concentrations.

D. Data Trends

/

With the exception of the 1986 sample data, which was effected by the Chernobyl accident, the general trend in air particulate gross beta activity has been one of decreasing activity since 1981.

l l

l AIR PARTICULATE FILTER-gross BETA 05 I

O45 1969 is site pre operational data 1974 is JAF pre-operational data 0.35 0.3 -

151NDICATOR WCONTROL l_.

m

.E ti R

.25 t

l 0.2 1986 Chernobyl Arxedent I

0.15 2lhbl=hl...a......_.,

0

..a......

3...

E =:,O C

E : 2 : O eee2 0 2 0 S

Year 5-28 l

l

l The trend for the previous five years is a subset of the overall decline in gross beta concentrations, again with the exceptioh of 1986 when a one year increase was measured as a result of the Chemobyl accident.

The 1995 results are representative of the natural background levels of gross beta activity as were the previous five years for both the indicator 1

and control locations. The change in concentration over the period of l

1990 through 1995 is very small. This is illustrated by the followmg graph.

JAMES A. FITZPATRICK N.P.P.

AIR PARTICULATE FILTER-GROSS BETA 0 04 0.035 3

6 EINDICAToR ECoNTRol 0.025 7

I k

C.02 0.015 l

0.01

-=

i -

C.005 1

o 1990 1991 1992 1993 1994 1995 Years I

The air particulate gross beta indicator results for 1995 are a factor of l

22 less than the concentrations measured in 1969. 1969 concentrations are considered to be preoperational results for the site.

For the operational period of 1975 - 1995 the mean annual gross beta j

concentration at the control station (R-5) has decreased from a i

2 maximum concentration of 0.165 pCi/m in 1981 to a minimum of 0.012 2

pCi/m in 1992.

The mean annual concentration for the indicator stations for this same time period ranged from a maximum of 0.151 pCi/m' in 1981 to a minimum of 0.013 pCi/m in 1992. For both the 2

indicator stations and control stations, the gross beta concentration during 1974 to 1982 fluctuated as a result of fallout from the detonation of thermonuclear weapons. The mean annual results for the years 1983, 5-29

i 1984,1985,1987 and 1988 from botli the indicator and control locations have been similar and ranged from 0.018 to 0.026 pCi/m'. This level of activity appears to be near baseline range. The 1986 annual mean 3

result was 0.039 pCi/m for both the indicator and control stations. This concentration is almost two times higher than 1983-1985 and 1987-1992 levels, and is attributed to fallout from the Chernobyl accident.

i Historical data and graphic representations of air particulate gross beta activity are presented in Sections 7.0 and 8.0 respectively.

i l

l i

i 5-30 l

1

)

5.2.2 MONTHLY PARTICULATE COMPOSITES (GAMMA EMITTERS) i A. Results Summary i

No plant related radionuclides were detected in any of the air particulate j

filter samples collected from the Technical Specifications required sampling locations. These stations are located near the site boundary and off-site.

The gamma analysis results for the monthly composite samples routinely showed positive detections of Be-7, K-40, Ra-226, and AcTh-228. Each of these radionuclides is naturally occurring.

Be-7 was detected in all the monthly composite samples for the indicator and control locations.

K-40, Ru-226 and AcTh-228 were found intemiittently in the monthly composite samples from all locations.

B. Data Evaluation Discussion Ten additional air sampling locations are maintained in addition to the five required by Technical Specifications. Composite air filter samples are assembled for each of the fifteen sampling locations. Each of the four weekly air particulate samples for the month are assembled by I

location to form monthly composite samples. The monthly composite i

samples required by Technical Specifications are R-1, R-2, R-3, R-4, and. R-5.

Other sample locations not required by the. Technical Specifications for which anclytical results have been provided include six on-site locations and four off-site locations. The analytical resuhs for all air paniculate filter composites in 1995 showed no detected levels of plant related radionuclides for the inhalation pathway. He results of all monthly composite samples are presented in Section 6.0, Table 6-9.

5-31

C. Dose Evaluation The air particulate sampling program demonstrated no off-site dose to man from this pathway as a result of operations of the plant. No plant related radionuclides were detected at any of the sampling locations located at or beyond the site boundary.

D. Data Trends No plant related radionuclides were detected during 1995 at the off-site air monitoring locations.

The five year data base of air particulate compsite analysis shows hat there is no buildup or presence of plant related radionuclides in particulate form in the atmopshere around the site. Co-60 was detected in each of the years from 1977 through 1984 at both the indicator and control locations with the exception of 1980 when Co-60 was not detected at the control location.

The presence of Co-60 in the air samples collected during these years was the result of atmospheric weapons testing. The maximum yearly mean concentration detected j

during this period was in 1977 when the mean indicator results was 0.0179 pCi/m'. The mean control value for this same year was 0.0172 pCi/m'. The Co-60 in the air particulate samples trended downward during the 1977 through 1984 period to a low mean concentration of 0.0008 pCi/m' at the control location. Co-60 has not been detected in i

any of the required air particulate samples since 1985. This general downward trend and eventual elimination of Co-60 in the air samples is illustrated in the following graph.

5-32

L7A ; &'n a : D.

i. _. _ i i~

.=

._.w

.g

.i__LA !

m ur m b

~

Historical data shows that Cs-137 is the fission product radionuclide most frequently detected in the air paniculate filter composites. Cs-137 was detected in each of the years from 1977 through 1983 at both the i

control and indicator sampling locations. The maximum concentration for this period were measured in 1977 with a mean indicator concentration of 0.0043 pCi/m' and the corresponding control concentration of 0.0934 pCi/m'. After 1977, the Cs-137 concentration showed a reduction by a factor of approximately two and remained constant through 1981.

In 1982, a second reduction in Cs-137 concentration was measured followed by a further reduction in concentration in 1983. Cs-137 was not detected during 1984 and 1985 l

in any of the indicator or control air paniculate composite samples.

For the period,1986 to 1991, Cs-137 was detected only in 1986 due to the fallout from the Chemobyl accident. The 1986 mean concentration of Cs-137 for the control location was 0.0193 pCi/m'.

The mean concentration of Cs-137 for the indicator location was 0.0183 pCi/m' for the sample period. This overall reduction in Cs-137 results since 1977 5-33

is attributed to nuclear decay and ecological cyding of Cs-137 initially produced as a result of weapons testing. The decrease in air particulate Cs-137 concentrations since 1977 is clearly illustrated on the graph of historical data.

1 JAMES A FITZPATRICK N.P.P.

AIR PARTICULATE FILTER COMPOSITE Cs-137 i

alNDICATOR BCONTROL 1966 Chemobyt Acciders 1

8 616 0 005

No Pos4we Detectson ( LLD H R d d d._ _ " "

YEAR In 1986, in addition to Cs-137, Zr-95, Ce-141, N -95, I-131, Cc-144, Mn-54, Ru-103, Ru-106, Ba-140. These isotopes were detected in air paniculate composite samples as a result of the fallout from the Chemobyl accident. After 1986, no plant related or fillout radionuclides were detected in any of the off-site air particulate composite samples.

A review of the past five years data for air particulate filter composites indicate no plant related radiological impact on the environment. All the historical positive detections of fission product radionuclides were associated with atmospheric weapons testing or the Chernobyl accident.

Current air particulate filter composite results can not bc compared to '

preoperational data as none exists prior to 1977.

5-34

_ _... _. _.. _.. _.... _ _ _ _ _. _ _ _ _ _ ~.

t i

IIistorical data for air particulate results are presented in Section 7.0, Tables 7-11 and 7-12. Full page graphic presentation e air particulate r

composite Co-60 and Cs-137 concentrations are presented in Section f

8.0.

f I

l l

l i

6 4

j 5-35

l 5.2.3 AIRBORNE RADIOIODINE (I-131)

A. Results Summary Iodine I-131 was not detected in any of the 780 samples analyzed for the 1995 program. No radiciodine has been detected off-site since 1986 when measurable levels ofI-131 were found as a result of fallout from j

the Chemobyl accident.

B. Data Evaluation and Discussion i

Airbome radiciodine is monitored at the fifteen air sampling stations also used to collect air particulate samples. There are ni'ne off-site locations, five of which are required by Technical Specifications. The off-site locations required by Technical Specifications are designated as R-1, R-2, R-3, R-4 and R-5. R-5 is a control station located beyond any local influence from the plant. Ten air sampling locations are I

maintained in addition to those required by Technical Specifications.

Six of these stations, D-1, G, H, I, J and K, are located on-site. D-2, E, F and G are the optional stations located off-site.

Samples are collected using activated charcoal cartridges. They are analyzed weekly for I-131. The analytical data for radioiodine are presented in Section 6.0, Table 6-7 and 6-8.

C. Dose Evaluation The I-131 airbome sampling program demonstrated no dose to man due to the operation of the plant.

No radiciodine was detected in any sampling location.

I D. Data Trends No radioiodine has been detected at air sampling locations required by Technical Specifications since 1987.

5-36

l The prior five years of data shows no positive detection ofI-131. This demonstrates that there is no-measurable environmental impact or positive trend for iodine buildup due to plant operations during the period from 1990 through 1994. I-131 was detected twice over the last ten year period, in 1986 and 1987. The 1986 detection was the result of toe Chemobyl accident and the 1987 detection was the result of plant operations.

Iodine - 131 (I-131) has been detected in the past at control locations.

During 1976, the mean off-site I-131 concentration averaged 0.604 pCi/rd. 1977 showed an I-131 concentration that decreased to 0.323 pCi/m' and for 1978 the concentration decreased by a factor of ten to 0.032 pCi/m'. During 1979 - 1981 and 1983 - 1985, I-131 was not detected at the control locations.1-131 was detected once at the control location during 1982 at a concentration of 0.039 pCi/m'. I-131 was detected at the on-site locations in 1980 through 1983,1986 and 1987.

The mean concentrations ranged from 0.013 pCi/m' in 1980 to 0.119 pCi/m' in 1986. The maximum I-131 concentration of 0.119 pCi/m3 was the result of the Chemobyl accident. I-131 was detected in a total of 75 weekly samples collected during the 1986 sample program. The concentrations detected in 1986 ranged from a minimum of 0.023 pCi/m' to a maximum of 0.36 pCi/m'. Ea6 of the positive detections ofI-131 in 1986 were a direct result of the Chemobyl Nuclear accident.

Preoperational data for I-131 in air is limited. -Results from 1974 showed no positive measurement ofI-131. Current data which showed l

no measured concentrations of I-131 is consistent with the 1969 and 1974 preoperational data.

1 A graphic presentation of airbome radiciodine is presented in Section i

8.0.

5-37

5.2.4 DIRECT RADIATION TIIERMOLUMINESCENT DOSIMETERS (TLD).

A. Results Summary 71 TLD locations are used to measure direct radiation levels in the environment. The dosimeters are collected and read each gearter. The 1995 results are consistent with those observed in 1994 and previous years. TLD results are evaluated by organizing the locatims into five logical groups by geographic location relative to the ~ site. The: five logical groups are on-site, site boundary, off-site, special interest and controls. A summary of the measured exposure in each group are as follows:

Dose in mrem per standard month Location Groups Minimum Maximum Mean i

l On-site indicators 3.5 28.6 6.2 Site boundary

3.5 9.6 5.4 Off-site indicators

3.9 5.7 4.4 i

Special interest

3.6 4.8 4.2 Controls

3.4 4.9 4.2

Location required by Technical Specifications The highest dose rate was measured at a Technical Specification required location.

The location is in the ENE sector between the FitzPatrick plant and the NMP Unit #2 Facility. This TLD which read 28.6 mrem / standard month is influenced by turbine shine from the two plants. He site boundary. maximum dose was 9.6 mrem per standard month. This TLD is located in the WNW sector along the lake shore and is in close proximity to the NMP Unit #1 plant. The TLD locations along the lake shore close to the plants are influenced by the rad waste building and rad waste shipping activities. These environmental dose are not representative of doses measured at the remaining site boundary location.

De remaining TLD locations which are located away from the plant are comparable to levels measured at the control locations.

l 5-38

Overall, the environmental direct radiation measurement results for 1995 showed no indication ofincreased direct radiation above background at or beyond the site boundary.

This is demonstrated by the net site boundary dose rate. The consistency in the 1995 site boundary dose rate to historical results is important because of a change in a plant operating parameter during the second half of 1995. The 1995 results demonstrate that the increase in the hydrogen injection rate for hydrogen water chemistry, implemented in 1995, has not increased the site boundary dose rate or the dose to the general public.

Quarter Site lloundary*

Control

Net Site Boundary Dose

1 3.9 3.9 0.0 2

4.5 4.5 0.0 3

4.7 4.8

-0.1 4

4.3 4.4

-0.1

' Dose in mrem per standard month B. Data Evaluation and Discussion Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (garr.ma dose) in the environment.

The TLDs used during 1995 were Puasonic UD-814 dosimeters.

l 71 environmental TLDs were collected and read on a quarterly basis during the sample year. The location results are an average of six independent readings per quarter at cach location and are reported in mrem per standard month (See Section 6.0, Table 6-10).

The majority of the locations required by the Technical Specifications for 1995 were initiated in 1985 as a result of the issuance of new Technical Specifications by the NRC. Therefore,1995 results can only be comparei to 1985 - 1993 results. Some locations including a number required by the Technical Specifications (i.e., numbers 7,14,15,18, 23, 49, 56, and 58) can be compared to earlier results as these TLDs were established prior to 1985.

5-39

. - - - ~. - - -.

1 1

i On-site TLDs are located at special interest areas within the site boundary.

With.the exception of location numbers 7 and 23, these locations are not required by the Technical Specifications. Locations 7 and 23 are located near the generating facilities at previous or existing on-site air sampling stations i

and are used to evaluate meteorological sectors that do not extend beyond the f

site boundary. TLDs located at the on-site environmental monitoring stations include numbers 3, 4, 5, 6, 7, 23, 24, 25 and 26. The results for these locations are consistent with the previous year results with the exception of' TLD number 3. This TLD h located in close proximity to the FitzPatrick l

facility and reflects higher dose rates due to the increased hydrogen water chemistry conducted during the 3rd and 4th quarters of 1995. These results ranged from 3.5 to 28.6 mrem per standard month in 1995. Other on-site special interest TLDs are located near the north shoreline of the Nine Mile Point Unit 1, Unit 2 and JAF facilities.

They are in close proximity to radwaste facilities. and the Unit I reactor building. These locations include numbers 27,28,29,30,31,39 and 47. Restilts for these TLDs during 1995-j were widely variable and ranged from 4.0 to 65.0 mrem per standard month as a result of activities at the radwaste facilities and the operating modes of the generating facilities. With the exception oflocation number 3, as noted above, the results for 1995 are consistent with the ranges of variability noted in 1994 for measurements at or near these locations.

Additional on-site TLD locations are located near the on-site Energy Center and the associated northeast shoreline. These locations include numbers 18, 103,106 and 107. TLDs 103,106, and 107 are located east of the Energy Center and west of the Unit I facility. TLD number 18 is located on the west side of the Energy Center. Results fer this group ranged from 3.9 - 6.0 mrem per standard month for 1995 and were consistent with the 1994 results.

Site boundary TLDs are required by the Technical Specifications and are located in the approximate area of the site boundary with one in each of the sixteen 221/2 degree meteorological sectors. These TLDs include numbers 75, 76, 77,23, 78, 79, 80, 81, 82, 83, 84, 7,18, 85, 86 and 87. TLD numbers i

78,79,80,81,82,83,84,7 and 18 showed results that were consistent with control TLD results and ranged from 2.8 to 4.9 mrem per standard month.

Site boundary TLDs during 1995 were consistent with 1985 - 1994 results.

5-40

TLD number 75,76,77,23,85, 86, and 87 showed results that ranged up to three times the results of control TLDs. These results ranged from 3.5 - 9.6 t

mrem per standard month. His latter group of TLDs are located near the lake shoreline (approximately 100 feet from the shoreline), but are also located in close proximity of the reactor building and redwaste facilities of Unit 1 and Unit 2 and the radwaste facilities of the FitzPatrick facility.

l A net site boundary dose can be estimated using site boundary TLD results and control TLD results. Results from TLDs located at the site boundary in land based sectors (excluding TLDs near the generating facilities and facing Lake Ontario) are compared to control TLD results. The site boundary TLDs include numbers 78, 79. 80, 81, 82, 83, 84, 7 and 18. Control TLDs include numbers 8,14,49,111 and 113. Net site boundary doses for each quarter in mrem per standard month are as follows:

Ouarter Net Site Boundary Dose

1

+0.0 2

+0 0 3

-0.1 4

-0.1 j

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 TLDs are not representative of doses at areas where a member of 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 TLDs are located four to five miles from the site in each of the eight land based 22.5 degree meteorological sectors. These locations are required by the Technical Specifications.

At this distance, badges are not present in eight of the sixteen meteorological sectors which are located over Lake Ontario.

5-41

1 Results for this group of TLDs during 1995 showed a range of 3.2 to 5.2

(

i mrem per standard month. The range of results is caused by differences in I

naturally occurring physical conditions and the varying concentrations of naturally occurring radionuclides in the ground at each of the locations. These

)

results are consistent with control TLD results during 1995 and with the 1986 i

3

- 1994 results. These TLDs were established in 1985 and include numbers 88, 89, 90, 91, 92, 93, 94 and 95.

1 The fourth group of environmental TLDs are located near the site boundary l

j.

and at special interest areas. Included in this group are monitoring locations at industrial sites, schools, nearby communities, oiT-site air sampling stations, the closest residence to the site, and the off-site environmental laboratory.

i

}

Many of these TLDs are required by the Technical Specifications.

The i

remaining locations for this group are optional.

This group of locations l

f i

include numbers 9,10,11,12,13,15,19,51,52,53,54,55,56,58,96,97, I

98,99,100,101,102,108 and 109. TLD numbers 108 and 109 are locations i

that were established during 1988 and were added to assist in the evaluation of the nearest residence. In 1995, results ranged from 3.7 to 5.0 mrem per j standard month for locations 108 and 109. The results for the entire group i

range from a minimum dose rate of 3.3 to a maximum of 5.1 mrem per

^

standard month. All of the TLD results from this group were within the general variation of the control TLDs. Results during 1995 were consistent j

with the results for previous years.

The fifth category of TLDs are those used to measure the dose rate at the control locations. These TLDs are required by the Technical Specifications and include numbers 14 and 49. Optional control locations are numbers 8, 111 and 113. Location number 111 was added to the program during 1988 to expand the data base for control measurements. Results for all control locations from 1995 ranged from 3.4 to 4.9. mrem per standard month.

Results from 1995 were consistent with previous years results.

i 5-42 i

a

+,. -. _,

.m

4 i-l.

I C. Dose Evaluation TLDs located at the site boundary averaged 4.0 mrem per standard month i

i (No. 7,18, 78, 79, 80, 81, 82 83, 84).

TLDs placed at the special interest locations averaged 4.1 mrem per standard F

month.

The control TLD results averaged 4.1 mrem per standard month in 1995 (No.

1 8, 14, 49, 111, 113).

l u

The measured mean dose rate in the proximity of the closest resident was 4.1 mrem per standard month (No.108 and 109) which is consistent with the j

control measurements.

l The mean annual dose for each of the geographic location categories-demonstrates that there is no statistical difference in the annual dose as a function of distance from the site. The TLD program verifies that operations at the site do not measurably contribute to the levels of direct radiation present in the off-site environment.

D. Data Trends A comparison of historical results for TLD results can be made using the different categories of measurement locations. These include site boundary TLDs in each meteorological sector (16 locations), TLDs located off-site in each land based sector at a distance of four to five miles (8 locations), badges located at special interest areas (6 locations) and TLDs located at control locations (5 locations).

As noted previously, many of the present TLD locations became effective in 1985 and these results can only be evaluated for 1985 - 1992.

TLDs located at the site boundary averaged 6.1 mrem per standard month during 1987. During 1990,1991,1992,1993,1994 and 1995 site boundary dose rates averaged 4.8, 4.8, 4.2, 4.3, 4.0 and 4.4 mrem per standard month respectively. As noted previously, this group of TLDs can fluctuate because 5-43

m.

1 1

several of these TLDs are located in close proximity to the generating facilities and influenced by operational modes. An increase was noted during 1986 although such an increase was noted for all TLDs including the control

' locations. During 1995, site boundary measurements averaged 4.4 mrem pe_r standard month which is equal to the mean for the previous five years.

l TLDs located off-site at a distance of four to five miles from the site in each of the land based meteorological sectors (off-site sectors) averaged 5.2 mrem l

ou 94, he ann off.i e sector dose rates a e g d 7 4.1 4 and 4.0 mrem per standard month, respectively.

Results for the group j

averaged 4.4 mrem standard month over the five year period. The 1995 mean -

l dose of 4.3 mrem per standard month is consistent with the previous five year _

1 mean and each individual yearly mean.

i b

Special interest locations averaged 4.4 mrem per standard month over the previous five years. The 1995 results for these locations averaged 4.5 mrem per standard month. This is consistent with the previous five year average of 4.4 mrem per standard month.

i The final group of TLD locations required by the Technical Specifications is the control group. This group (No. 8,14,49,111 and 113) utilizes locations positioned well beyond the site. Results from 1986 for the control group

. averaged 6.3 mrem per standard month. During 1987, this same group of TLDs averaged 5.4 mrem per standard month. A marked increase was noted -

in the second quarter of 1986. The increase may have been a result of the Chemobyl accident. Results for 1990,1991,1992,19B and Ird averaged 1

4.7, 4.7, 4.1, 4.4 and 4.1 mrem per standard month respectively with a five year mean of 4.4. Results for 1995 averaged 4.4 mrem per standard month which is identical to the previous five year mean. The five year mean results for the controls (4.4 mrem per standard month) are nearly identical to the 1995 off-site sector TLD results (4.3 mrem per standard month) as would be -

j expected.

l I

5-44 i

The 1995 TLD program results, when compared to the previous five years and preoperational data, shows no significant trends relative to increased dose rates in the environment.

Tables 7-15 and 7-16 show the historical environmental sample data for environmental TLDs. A graph of historical TLD data is presented in Section 8.0.

1 l

l V-5-45 l

_. - - - -.. - = _ ~

d 5.2.5 MILK i.

l A. Results Summary l

1 A total of 90 milk samples were collected and analyzed for the 1995 sample program.

Each sample was analyzed for radionuclides using gamma j

spectroscopy and an iodine extraction procedures. - There were no plant related

]

radionuclides detected in the indicator or control milk samples collected and i

analyzed. Naturally occurring K-40 was detected in both indicator and control samples at levels consistent with past years results. The 1995 results continue to demonstrate that routine operation of the FitzPatrick Plant has no i

contribution to the " dose to the public" from the cow / milk pathway.

B. Data Evaluation and Discussion Milk samples were collected from four indicator and one control location.

Technical Specifications require that three sample locations are within five i

miles of the site. Based on the milk animal census there were no adequate j

milk sample locations within five miles of the site in 1995. Samples were.

collected from five farms located beyond the five mile requirement to ensure j

the monitoring of this important pathway. The four indicator locations ranged

{

from 5.5 to 9.5 miles from the site. The control samples were collected from j

a farm 13.2 miles from the site and in a low frequency wind sector (upwind).

With the exception of the control location, each of the reported locations have been sampled since 1989. The geographical location of each location is listed below:

Location No.

Direction From Site Direction (Miles) 50 E

9.1 55 E

9.0 60 E

9.5 4

ESE 7.8 73 Control SW 13.2 Samples were collected at locations 50,55,60,4 and 73 from April through December, during the first and second half of each month. ' Because I-131 was j

i 5-46

not detected in samples collected during November and December of 1994, no additional samples were required for January through March of 1995 as stipulated in the Technical Specifications.

Each sample is analyzed for gamma emitters using a gamma spectral analysis.

The I-131 analysis is performed using resin extraction followed by spectral analysis for each sample. I-131 analytical results and sample analysis results for gamma emitters are provided in Section 6.0, Table 6-11.

Iodine-131 was not detected in any indicator or control samples analyzed -

during 1995. All I-131 milk results were reported as lower limits of detection (LLD). The LLD results for all samples ranged from <0.25 to.<0.55 pCi/ liter.

K-40 was the most abundant radionuclide detected in milk samples collected in 1995. K-40 is a naturally occurring radionuclide and is found in many of the environmental media sampled. K-40 was detected in every indicator and control sample. The K-40 concentration for all samples ranged from 1320 to 2430 pCi/ liter. Ra-226 was detected intermittently in the milk samples and is a naturally occurring radionuclide. During 1995, Cs-137 was not detected in any indicator or control milk samples.

C. Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant related radionuclides were detected.

The dose to man from naturally occurring concentrations of K-40 in milk and other environmental media can be calculated. This calculation illustrates that the dose received due to exposure from plant effluents is negligible as compared to the dose received from naturally occund 4 radionuclides.

Significant levels of K-40 have been measured in environmental samples. A 70 kilogram (154 pound) adult contains approximately 0.1 microcuries of K-40 as a result of normal life functions (inhalation, consumption, etc.). The dose to bone ti.ssue is about 20 mrem per year (Eisenbud) as a result of intemally deposited naturally occurring K-40.

l 1

5-47 1

D. Data Trends 1995 results showed no man-made radionuclides detected in milk samples analyzed as part of the environmental surveillance program. In the past ten years, Cs-137 was detected in 1986 and 1987. The mean Cs-137 indicator l

activity for those years was 8.6 and 7.4 pCi/ liter respectively. 1-131 was measured in milk samples in 1986 with a mean concentration of 13.6 pCi/ liter.

i This activity was a result of the Chernobyl accident.

From 1976 to 1985, Cs-137 and I-131 were intermittently detected. Cs-137 was detected in a 1983 milk sample with a concentration of 5.1 pCi/ liter. In 1980, I-131 was detected at the indicator and control locations with a mean concentrations of 4.9 and 1.4 pCi/ liter respectively. The Cs-137 and I-131 activity is attributed to Chinese atmospheric thermonuclear weapons testing.

The comparison of 1995 data to historical results over the operating life of the j

4 plant and preoperational data (1974) show that Cs-137 and I-131 levels have j

decreased significantly since 1974. The levels of Cs-137 and 1-131 detected i

i prior to the plant going into commercial operation were the result of activities not related to power production at the site.

"J.

Historical data and a graphic presentation of milk sample results for Cs-137 and I-131 are presented in Section 7.0, Tables 7-17 and 7-18 and in Section 8.0, respectively.

d 5-48

5.2.6 FOOD PRODUCTS (VEGETATION)

A. Results Summary i

There were no plant related radionuclides detected in the 23 food product samples collected and analyzed for the 1995 program. Cs-137 was detected in two of the seventeen indicator samples at concentrations of 0.011 and 0.012 pCi/g. The presence of Cs-137 in the samples is the result of fallout from atmospheric weapons testing. The concentrations of Cs-137 in the indicator samples are consistent with the levels of Cs-137 measured in other environmental media.

Cs-137 was not detected in the control samples collected. Detectable levels of naturally occurring K-40 were measured in all control and indicator samples collected for the 1995 program. B,e-7, a second naturally occurring radionuclide, was detected in 17 of the 23 samples collected. These results are consistent with the levels measured in 1994 and previous years. The results of the 1995 sampling program demonstrate that the dose to man from the garden pathway is insignificant and the contribution i

from the operation of the FitzPatrick plant, if any, is below the limits of detection.

B. Data Analysis and Discussion Food product samples were collected from five indicator locations and one j

control location. The collection of annual food product samples became a requirement as a result of Technical Specification Amendment 127 in 1985.

The indicator locations are represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and an annual garden census.

The control location was a garden 15 miles away in a predominately upwind direction.

Food product samples collected during 1995, included cabbage, swiss chard and collards. These sample types are considered edible broadleaf vegetables.

Where broadleaf vegetables were not available, non-edible broadleaf vegetation was collected. Non-ediole vegetation consisting of squash leaves, grape leaves, pepper leaves, cucumber leaves, pampkins and a tomato were collected for the 1995 program. The leaves of these plants were sampled as representative ofbroadleaf vegetation. Samples were collected during the late summer / fall harvest season.

5-49

i Each sample was analyzed 'for gamma emitters using gamma spectroscopy.

One fallout radionuclide, Cs-137 was detected in the 1995 samples. Cs-137 was measured in samples of cucumber and squash leaves collected from two separate indicator locations. The presence of Cs-137 in these samples is attributed to atmospheric weapons testing fallout. Cs-137 which is present in j

the soil due to weapons testing fallout is taken up from the soil by the plants and is concentrated in' the plant tissue.' The concentration of Cs-137 measured in these two samples is consistent with previous concentrations ' detected in j

vegetation. Cs-137 was detected in a control sample in the 1993 sample collection and in two of the indicator samples from the 1994 sampling program.

Naturally occurring Be-7, K-40, Ra-226 and AcTh-228 were detected in food product samples. The concentration of Be-7 in vegetation samples ranged from 0.07 to 1.70 pCi/g 1.. t). The concentration of K-40 in indicator and control.

samples ranged from 1.13 pCi/g (wet) and 10.6 pCi/g (wet). Ra-226 and AcTh-228 were detected intermittently in the samples. The results for naturally occurring radionuclides are consistent with those of prior years. Analyucal results for food products are found in Section 6.0, Table 6-13.

C. Dose Evaluation The food product sampling results showed no dose to man from this pathway as a result of operation of the plant. No plant related radionuclides were detected in any of the samples taken.

D. Data Trends i

There was one man-made radionuclide (Cs-137) detected in broadleaf edible and non-edible vegetation samples analyzed in 1995. Food product results for the last five years show no trend other than that plant related radionuclides are not detected in this sample media. In the previous five year period, Cs-137 was detected in two of those years. Cs-137 has been detected in five separate years since operation began at the FitzPatrick Power Plant.

5-50

In 1989, Cs-137 was detected in one non-edible broadleaf vegetation sample collected at an indicator location. The concentration was 0.011 pCi/g (wet) which was close to its LLD. LLD values for all other samples ranged from

<0.011 to <0.018 pCi/g (wet). Cs-137 was also detected in 1988. Other than naturally occurring levels of Be-7 and K-40, no other radioisotopes were detected from 1986 - 1989.

During the period of 1981 - 1985, Cs-137, Be-7 and K-40 were detected.

Cs-137 was found at one indicator location during 1985 at a concentration of 0.047 pCi/g (wet). The maximum Cs-137 concentration was detected in 1974 at a concentration of 0.142 pCi/g (wet). This period is considered to be pre-operational for the FitzPatrick facility. The levels of Be-7 and K-40 were consistent with natural background levels. There are no discernable trends indicating the presence ofplant related radionuclides in food product vegetation samples.

Historical data and graphic presentations of food product results are presented in Section 7.0, Tables 7-19 and 7-20, and in Section 8.0.

{

5-51

J 5.2.7 LAND USE CENSUS RESULTS A. Results Summary Technical Specifications require that an annual land use census be performed to identify potential new locations for milk sampling and for calculating the dose to man from plant effluents. In 1995 a milk animal census, a nearest resident census and a garden survey were performed.

No changes were required to milk sampling indicator or control locations in 1995 based on the 1995 milk animal census.

The results of the closest residence census conducted in 1995 required no change to the Off-site Dose Calculation Manual (ODCM) closest resident dose calculation reference location.

A garden census, not required by Technical Specifications, is performed to identify appropriate garden sampling locations and dose calculation receptors.

As a result of the garden census, food product sampling location S was added to 1995 sampling program.

Garden samples were collected from those locations listed in Table H-1 of the ODCM and identified in the census as i

active for 1995. See Table 3.3-1 for 1995 sampling locations.

B. Data Evaluation and Discussion A land use census is conducted each year to determine the utilization ofland in the vicinity of the site. The land use census actually consists of two types

]

of census. A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site. The census, covering areas out to a distance of 10 miles, exceeds the 5 mile distance required by the Technical Specifications. A resident census is designed to identify the nearest resident in each meteorological sector out to a distance of five miles.

The milk animal census is an estimation of the number of cows and goats within an approximate ten mile radius of the Nine Mile Point Site. The annual census is conducted during the first half of the grazing season by 5-52

sending questionnaires to previous milk animal owners and also by road surveys to locate any possible new locations. In the event the questionnaires f

are not answered, the owners are contacted by telephone or in person. The local county agricultural agency is also contacted as a further source of information conceming new milk animal locations in the vicinity of the site.

The number of milk animals estimated by the 1995 census was 964 cows and 7 goats. This is an decrease of 15 cows and an increase of 1 goat from 1994.

i The locations identified as a result of the milk animal census are illustrated on a map in Section 3.3, Figure 3.3-4.

The results of the milk animal census are found in Section 6.0, Table'6-12.

The second type of census is a residence census. The census is conducted in order to identify the closest residence within 5 miles in each of the 22.5 degree land based meteorological sectors. There are only eight sectors over i

land where residences are located within 5 miles.

These water sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW. The results of the residence census showing the applicable sectors and degrees and distance of each of the nearest residence are found in Section 6.0, Table 6-14.

The nearest resident locations are illustrated on a map in Section 3.3, Figure 3.3-5.

5-53

~ _. _ _.. _..

i 1

5.3 CONCLUSION

i The REMP is a continuous program implemented to determine the radiological impact of JAFNPP operations on the local environment. The program is designed to be sensitive' to'small changes in the radiological environment surrounding the site.

I i

l The results of the 1995 Radiological Environmental Surveillance Program continues to clearly demonstrate that there is no significant short term or chronic long term detrimental 1

impact on the environment in the vicinity of the Nine Mile Point site. The environmental releases from the plant contribute no measurable radiation ' exposures to the general public as demonstrated by the assessment of environmental media collected and analyzed as part of the ongoing environmental program. No increase in radiation levels in the environment were detected as a result of the increased hydrogen water chemistry program' implemented i

in 1995.

The major radiological impact on the environment remains the result of atmospheric weapons testing in the early 1980s and the 1986 accident at the Chernobyi Nuclear Power Plant. Both of these source terms have contributed to the ubiquitous inventory of Cs-137. The results for the 1995 sample program demonstrate that the concentrations of manmade radionuclides continue to decline since the last major source term in 1986. This reduction in environmental concentrations will allow for the site environmental program to become more sensitive to the measurable impact of plant operations on the environment.-

Samples representing food sources consumed at higher trophic levels, such as fish and milk, were reviewed closely to evaluate any impact to the environment or to man. In addition, the data was reviewed for possible short and long term historical trends. No measurable environmental impact could be determined as a result from radionuclide deposition considering all possible sources.

Doses as a result of naturally occurring radionuclides such as K-40 and Ra-226, contributed the major portion of the total annual dose to members of the general public.

During 1995, the presence of one fission product radionuclide (Cs-137) was measured in three different sample media. These samples were shoreline sediment, fish and vegetation.

The probable source of this radionuclide is past weapons testing. The impact, expressed as a dose to man, is minimal. The maximum potential dose to man calculated from the results of the 1995 program was from the fish pathway. The calculated dose from fish consumption was estimated to be 0.028 mrem whole body (adult) and 0.044 mrem to the 5-54

i critical organ (livers). The long term doses to man as a result of man-made radiation can mainly be attributed to the Chernobyl accident and atmospheric weapons testing. Dose received from man-made sources are very small when compared to the dose from naturally occurring sources of radioactivity.

The contribution to the whole body dose as a result of plant operations is extremely small when compared to the dose contribution from natural background levels and sources other than the plant.

Whole body doses in Oswego County due to all natural sources is approximately 50-60 mrem per individual per year as demonstrated by control environmental TLDs. The fraction of the annual dose to man attributable to site operation remains insignificant.

i 5-55

5.4 REFERENCES

l i

1.

Radiological Effluent Technical Specifications, Appendix B to Facility Operating License No. DPR-59 For James A. FitzPatrick Nuclear Power Plant, New York l

Power Authority, Docket No. 50-333, Amendment 127.

2.

U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, " Calculation of j

l Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose

)

of Evaluating Compliance with 10 CFR Part 50, Appendix 1", October,1977.

I 3.

Eichholz, G., Environmental Aspects of Nuclear PoweA First Edition, Ann Arbor Science Publishers, Inc., Ann Arbor, Michigan,1976.

4.

National Council on Radiation Protection and Measurements (NCRP),

Environmental Radiation Measurements. NCRP Report No. 50,1976.

5.

National Council on Radiation Protection and Measurements (NCRP), Natural Backcround Radiation in the United States. NCRP Report No. 45,1975.

6.

National Council on Radiation Protection and Measurements (NCRP), Cesium-137 from the Environment to Man: Metabolism and Dose. NCRP Report No. 52, 1977.

7.

National Council on Radiation Protection and Measurements (NCRP), Radiation Exposure from Consumer Products and Miscellaneous Sources. NCRP Report No.

56,1977.

8.

U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, " Environmental Technical Specifications for Nuclear Power Plants", December 1975.

9.

U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program",

November,1979.

1 l

10.

Eisenbud, Merril, Environmental Radioactivity. Third Edition, Academic Press, New York, New York,1987.

5-56 l

l

~. _

f W

I 11.

Francis, C.

W., Radiostrontium Movement in Soils and Untake in Plants.

Environmental Sciences Division, Oak Ridge National Laboratory, U.S.

1 Department of Energy,1978.

{

12.

National Council on Radiation Protection and Measurements (NCRP), Radiation i

Exposure from Consumer Products and Miscellaneous Sources. NCRP Report No.

56,1977.

t

(

)

13.

Pochin, Edward E.,

Estimated Population Exposure from Nuclear Power Production and Other Radiation Sources. Organization for Economic Co-operation and Development,1976.

j 14.

ICRP Publication Number 29, Radionuclide Releases into the Environment:

Assessment of Dose to Man.1979.

15.

U.S. Department of Health and Human Services, Preparedness and Response in Radiation Accidents. National Center of Devices and Radiological Health, i

Rockville, MD 20857, August,1983.

e 16.

Kathren, Ronald E., RADIOACTIVITY IN THE ENVIRONMENT: SOURCES.

DISTRIBUTION. AND SURVEILLANCE. First Edition, Harwood Academic Press, New York, NY,1984.

i i

17.

National Council on Radiation Protection and Measurement (NCRP), Ionizing

}

Radiation Exposure of the Population of the United States, NCRP Report No. 93, 1987 4

l 18.

Knoll, G., Radiation Detection and Measurement. Second Edition, John Wiley &

Sons, New York, New York,1989.

b 5-57

6.0 REPORT PERIOD ANALYTICAL RESUL1'S TABLES 6.1 Environmental sample data is summarized in table format.

Tables are provided for select sample media and contain data based on actual values obtained over the year. These values are comprised of both positive values and LLD values where applicable.

6.2 The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of falsely concluding that a blank observation represents a "real" signal (see Section 3.7.3 for detailed explanation).

6.3 When the initial count of a sample indicates the presence of radioactivity, two recounts are normally performed. When a radionuclide is positively identified in two or more counts, the analytical results for that radionuclide is reported as the mean of the positive detections and the associated error for that mean (see Section 3.7.2 for methodology).

l 6.4 Many of the tables are foctnoted with the term " Plant Radionuclides". Plant related radionuclides are radionuclies that a e produced in the reactor as a result of plant operation either through the activation or fission process.

6-1

a TABLE 6-1 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES - 1995 Results in Units of pCi/g (dry) i 1 Sigma STATION COLLECTION N EMI N CODE

DATE K-40 Co-60 Cs-134 Cs-137 Zn-65 OTliERS**

Surtset Beach 04/95 20.310.4

<0.054

<0.041 0.143i0 014

<0.109

<LLD (05)

,s, 10/95 21.210.4

<0.081

<0.074 0.15310.014

<0.110

<LLD Lang's Beach 04/95 15.910.4

<0.039

<0.031

<0.034

<0.064

<LLD (06 Control) 10/95 13.410.5

<0.038

<0.036

<0.068

<LLD Corresponds to sample locations noted on the maps in Section 3.3.

C*

Plant Related Isotopes

TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 1995 Results in Units of pCi/g (wet)

1 Sigma DATE TYPE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 OTHERS*

+-

FITZPKfRICK 05/26/95 Lake Trout 3.40i0.17 <0.018 <0.025 <0.059 <0.020 <0.048 <0.020

<0.019

<LLD 06/02/95 Brown Trout 4.76i0.21 <0.024 <0.024 <0.055 <0.022 <0.051 <0.020

<0.020

<LLD 06/02/95 White Sucker 4.18 0.21 <0.021 <0.022 <0.067 <0.021 <0.048 <0.024

<0.023

<LLD 06/09/95 Smallmouth Bass 3.9610.21 <0.021 <0.021 <0.057 <0.022 <0.060 <0.024

<0.022

<LLD 09/19/95 White Sucker 2.6410.17 <0.017 <0.022 <0.063 <0.020 <0.055 <0.017

<0.020

<LLD 09/19/95 Brown Trout 3.0610.16 <0.017 <0.021 <0.066 <0.021 <0.044 <0.019

<0.019

<LLD 09/20/95 Smallmouth Bass 2.7410.18 <0.020 <0.023 <0.066 <0.021 <0.049 <0.019

<0.019

<LLD 09/26/95 Lake Trout 3.18i0.11 <0.022 <0.019 <0.053 <0.025 <0.052 <0.021 0.02210.005

<LLD

Plant Related Radionuclides

TABLE 6-2 (CONTINUED)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 1995 Results in Units of pCi/g (wet) i 1 Sigma DATE TYPE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 OWERS*

NINE MILE POINT 06/02/95 Lake Trout 8.2810.22 <0.023 <0.026 <0.062 <0.024 <0.037 <0.022

<0.022

<LLD 06/02/95 Brown Trou?

3.4110.11 <0.022 <0.021 <0.059 <0.019 <0.055 <0.019

<0.021

<LLD 06/02/94 Smallmouth Bass 4.2910.23 <0.022 <0.025 <0.058 <0.024 <0.050 <0.022

<0.022

<LLD ai 09/19/95 White Sucker 7.6910.21 <0.026 <0.031 <0.068 <0.021 <0.039 <0.016

<0.021

<LLD 09/19/95 Walleye 8.7410.23 <0.025 <0.031 <0.075 <0.021 <0.046 <0.018

<0.024

<LLD 09/20/95 Chinook Salmon 6.2610.11 <0.023 <0.027 <0.062 <0.024 <0.054 <0.017 0.01610.005 <LLD 09/20/95 Brown Trout 4.21i0.20 <0.022 <0.027 <0.059 <0.025 <0.054 <0.019

<0.020

<LLD 19/21/95 Lake Trout 7.92i0.22 <0.027 <0.030 <0.064 <0.023 <0.039 <0.019

<0.025

<LLD 09/21/95 Smallmouth Bass 3.92i0.26 <0.030 <0.032 <0.080 <0.037 <0.077 <0.028

<0.029

<LLD

Plant Related Radionuclides

TABLE 6-2 (CONTINUED)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 1995 Results in Units of pCi/g (wet) 1 Sigma DATE TYPE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 OTHERS*

OSWEGO HARBOR (Control) 05/24/95 Lake Trout 7.1410.12 <0.024 <0.031 <0.078 <0.023 <0.042 <0.018

<0.022

<LLD 05/24/95 Brown Trout 4.28i0.22 <0.021 <0.025 <0.072 <0.022 <0.060 <0.022

<0.022

<LLD 06/06/95 White Sucker 8.58i0.22 <0.024 <0.025 <0.062 <0.022 <0.041 <0.016

<0.021

<LLD 06/06/95 Smallmouth Bass 8.7810.22 <0.023 <0.026 <0.057 <0.021 <0.035 <0.022

<0.021

<LLD g

09/19/95 Salmon 4.1810.13 <0.015 <0.025 <0.071 <0.022 <0.050 <0.018 0.01810.006 <LLD 09/20/95 Walleye 5.1810.19 <0.022 <0.024 <0.056 <0.020 <0.052 <0.022 0.023 0.004 <LLD 09/20/95 Brown Trout 3.7610.24 <0.030 <0.040 <0.011 <0.038 <0.084 <0.030

<0.026

<LLO 09/21/95 Smallmouth Bass 7.3710.21 <0.023 <0.026 <0.056 <0.022 <0.035 <0.017

<0.022

<LLD 09/21/95 White Sucker 3.1610.12 <0.021 <0.026 <0.072 <0.023 <0.055 <0.020

<0.020

<LLD 09/26/95 Lake Trout 5.06i0.11 <0.020 <0.021 <0.067 <0.021 <0.051 <0.022 0.017*0.005 <LLD

Plant Related Radionuclides

TABLE 6-3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/ liter i 1 Sigma JSTATIONiCODE

.$ PERIOD?

y ?DATEj e,

~

,JTRIT[UMi g g-s.

FITZPATRICK*

First Quarter 12/29/94 - 03/31/95

<230 (03, INLET)

Second Quarter 03/31/95 - 06/30/95

<180 Third Quarter 06/30/95 - 09/29/95 320i130 Fourth Quarter 09/29/95 - 01/03/96

<170 OSWEGO STEAM

First Quarter 12/30/94 - 03/31/95

<230 STATION Second Quarter 03/31/95 - 06/30/95

<220 (08. CONTROL)

Third Quarter 06/30/95 - 09/29/95 230i120 Fourth Quarter 09/29/95 - 12/29/95

<170 m&

NINE MILE First Quarter 12/30/94 - 03/31/95

<230 POINT UNIT 1**

Second Quarter 03/31/95 - 06/30/95

<230 (09. INLET)

Third Quarter 06/30/95 - 09/29/95 200t120 Fourth Quarter 09/29/95 - 12/29/95

<170 NINE MILE First Quarter 12/30/94 - 03/31/95

<230 POINT UNIT 2**

Second Quarter 03/31/95 - 06/30/95

<220 (11, INLET)

Third Quarter 06/30/95 - 09/29/95

<180 Fourth Quarter 09/29/95 - 12/29/95

<170 OSWEGO CITY **

First Quarter 12/30/94 - 03/31/95

<230 l

WATER (10)

Second Quarter 03/31/95 - 06/30/95

<240 Third Quarter 06/30/95 - 09/29/95

<190 Fourth Quarter 09/29/95 - 12/29/95 200t110 Samples required by the Technical Specifications

- Optional samples Oswego City Water samples are composites of twice per week grab samples

TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1995 Results in Units of pCi/ liter i 1 Sigma STATI9N CODE

NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE I

OSWEGO STEAMt I-131

<0.80

<0.7

<0.3

<0.70

<0.40

<0.40 STATION Cs-134

<4.59

<2.09

<3.07

<3.59

<3.84

<2.52 (08. CONTROL)

Cs-137

<4.15

<2.18

<2.83

<3.64

<3.80

<3.27 Zr-95

<9.53

<4.40

<6.40

<7.23

<7.05

<6.10 Nb-95

<5.99

<2.68

<4.19

<4.22

<5.12

<3.43 Co-58

<5.15

<2.47

<3.52

<3.69

<3.29

<3.06 Mn-54

<4.55

<2.04

<3.06

<3.65

<3.81

<2.67 Fe-59

<10.0

<5.68

<7.43

<8.93

<9.80

<6.47 Zn-65

<11.1

<5.84

<5.48

<8.20

<9.62

<7.58 Co-60

<5.72

<2.83

<3.14

<3.87

<4.01

<3.22 K-40 139i24.1 42.3i10.6 892i25.7 255-22.7 25.5122.3 32.0t11.5 Ba/La-140

<14.5

<8.03

<6.66

<10.9

<10.5

<8.12

~

FITZPATRICKt I-131

<0.20

<0.7

<0.3

<0.90

<0.40

<0.40 (03, INLET)

Cs-134

<2.08

<2.18

<3.92

<4.18

<3.12

<4.10 Cs-137

<2.12

<2.81

<3.72

<3.92

<2.62

<4.26 Zr-95

<4.69

<6.11

<7.18

<7.38

<5.56

<6.98 Nb-95

<3.01

<4.25

<4.65

<4.79

<3.05

<4.02 Co-58

<2.90

<3.56

<3.83

<3.69

<3.09

<3.91 Mn-54

<2.63

<3.00

<3.45

<3.24

<2.75

<3.12 Fe-59

<6.09

<7.03

<8.99

<10.7

<6.84

<8.49 IZn-65

<6.53

<5.01

<9.89

<9.56

<6.41

<7.65 Co-60

<3.20

<2.67

<3.88

<3.58

<2.89

<4.32 K-40 63.4111.5 787123.2 207i20.7 220i20.7 49.4 11.1 220i22 Ba/La-140

<7.9

<6.52

<11.2

<9.63

<11.7

<7.42 0 Corresponds to sample locations noted on the maps in Section 3.3.

t Samples required by the Technical Specifications.

TABLE 6-4 (Courruuto)

I CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1995 Results in Units of pCi/ liter i 1 Sigma l

STATION CODE

NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE NINE MILE I-131

<7.10

<10.5

<8.46

<9.31

<10.4

<9.08 POINT Cs-134

<1.76

<2.95

<2.87

<2.80

<4.35

<3.05 UNIT 1**

Cs-137

<2.00

<2.97

<2.46

<3.88

<3.16 (09 INLET)

Zr-95

<4.70

<6.22

<5.53

<5.64

<7.70

<6.18 Nb-95

<3.33

<4.25

<3.38

<3.40

<4.18

<4.00 Co-58

<2.69

<3.49

<3.07

<3.00

<3.97

<2.88 Hn-54

<2.76

<3.11

<2.83

<2.66

<3.65

<2.68 Fe-59

<6.20

<6.87

<6.66

<6.81

<9.80

<7.30 Zn-65

<6.06

<5.33

<6.98

<5.67

<8.35

<5.18 Co-60

<3.14

<2.61

<3.06

<2.90

<3.57

<3.07 K-40 78.8111.5 906i25.0 44.3112.1 45.3112.1 261123.9 55i13 Ba/La-140

<8.16

<5.74

<7.11

<7.82

<10.0

<8.95 NINE MILE I 131

<7.32

<10.0

<6.32

<7.94

<11.6

<8.70 POINT Cs-134

<1.77

<1.62

<2.75

<2.43

<4.70

<3.35 UNIT 2**

Cs-137

<3.06

<2.03

<2.81

<2.61

<4.35

<2.57 l

(11. INLET)

Zr-95

<5.76

<4.50

<5.01

<6.12

<8.78

<5.27 Nb-95

<3.89

<2.97

<3.37

<3.89

<5.92

<3.01 Co-58

<3.08

<2.42

<3.10

<2.79

<5.26

<2.99 Mn-54

<2.79

<2.26

<2.44

<2.56

<4.95

<2.75 Fe-59

<6.71

<6.17

<7.88

<7.50

<13.4

<6.37 Zn-65

<7.08

<3.59

<6.72

<7.37

<10.8

<6.32 Co-60

<3.18

<2.70

<2.84

<3.12

<5.05

<3.43 K-40 43.7112.5 38.0i7.38 40.9112.8 33.2il2.8 222*24 50.4111.1 Ba/La-140

<9.32

<9.64

<7.32

<8.16

<12.2

<7.82 Corresponds to sample locations noted on the maps in Section 3.3.

- Optional sample location. Samples not required by Technical Specifications.

TABLE 6-4 (conrruuto)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1995 Results in Units of pCi/ liter i 1 Sigma STATION CODE

NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE OSWEGO CITY I-131

<10.8

<9.68

<11.3

<10.5

<10.1

<8.59 WATER **

Cs-134

<2.24

<2.38

<5.11

<4.84

<2.19

<2.87 (10)

Cs-137

<3.87

<2.03

<4.24

<3.00

<2.84 Zr-95

<7.82

<4.97

<9.24

<8.97

<6.40

<6.50 Nb-95

<5.39

<3.23

<5.86

<6.1"

<4.33

<3.52 Co-58

<3.66

<2.71

<5.02

~b.00

<3.44

<3.35 Hn-54

<3.52

<2.58

<4.76

<4.54

<3.34

<3.24 Fe-59

<9.06

<6.76

<12.0

<12.6

<7.72

<7.32 Zn-65

<8.86

<6.31

<10.8

<11.2

<6.05

<7.05 m6 Co-60

<4.50

<2.48

<6.15

<4.66

<3.06

<3.18 K-40 204121.4 39.317.38 186i24.5 200i25.3 888 25.7 221t18 Ba/La-1A0

<8.02

<9.32

<11.3

<14.0

<6.88

<7.96

_=

Corresponds to sample locations noted on the maps in Section 3.3.

0 M Optional sample locatien. k mples not required by Technical Specifications.

TABLE 6-4 (Ceurinuto)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1995 Results in Units of pCi/ liter 1 Sigma l

STATION CODE

NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECE!EER OSWEGO STEAMt I-131

<0.60

<0.98

<0.60

<0.50

<1.4 STATION Cs-134

<2.16

<2.52

<3.04

<2.06

<1.94

<1.50 (08. CONTROL)

Cs-137

<2.77

<3.30

<2.55

<2.68

<2.74

<1.93 Zr-95

<6.22

<4.70

<6.44

<5.69

<5.72

<3.63 Nb-95

<3.94

<3.47

<3.50

<3.55

<3.31

<1.81 Co-58

<3.05

<3.22

<3.23

<3.15

<3.08

<1.79 Mn-54

<2.99

<2.78

<2.61

<2.78

<2.94

<1.79 Fe-59

<7.71

<6.96

<7.56

<10.8

<7.51

<4.87 Zn-65

<7.23

<6.82

<7.22

<5.22

<7.45

<4.40 Co-60

<3.35

<3.23

<3.14

<3.06

<3.02

<1.72 K-40 224f17.9 ' 44.7 12.8 52.4111.1 36.3ill.1 60.4111.1 39.4t7.67

[

Ba/La-140

<9.36

<8.29

<8.09

<6.90

<7.00

<6.52 FITZPATRICKt I-131

<0.60

<0.70

<0.78

<0.50

<0.40

<1.0 (03. INLET)

Cs-134

<2.74

<1.8

<2.02

<2.55

<3.09

<1.19 Cs-137

<3.10

<2.49

<3.14

<2.86

<3.09

<1.89 Zr-95

<5.35

<5.63

<6.03

<5.50

<5.86

<3.41 Nb-95

<3.63

<3.64

<4.23

<3.61

<3.82

<2.14 Co-58

<3.49

<3.29

<4.09

<3.44

<3.15

<1.91 Mn-54

<2.93

<2.8

<3.02

<2.64

<3.11

<1.70 Fe-59

<7.32

<7.04

<6.88

<6.74

<6.84

<4.44 Zn-65

<7.37

<6.82

<7.17

<8.00

<4.73

<4.39 Co-60

<2.65

<3.18

<3.58

<3.04

<3.12

<1.81 K-40 43.Sil2.8 63.5i12.1 279118.9 47.3il2.8 712i22.2 42.7*6.85 Ba/La-140

<8.02

<8.09

<8.88

<8.14

<6.73

<4.65

Corresponds to sample locations noted on the maps in Section 3.3.

t Samples required by the Technical Specifications.

TABLE 6-4 (ConTruuso)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1995 Results in Units of pCi/ liter i 1 Sigma STATION CODE

NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEM ER DECEE ER NINE MILE I-131

<6.98

<8.27

<10.8

<10.2

<8.57

<10.0 POINT Cs-134

<2.76

<1.9

<2.94

<2.12

<2.99

<2.42 UNIT 1**

Cs-137

<3.10

<2.68

<2.72

<3.02

<2.69

<2.72 (09. INLET)

Zr-95

<4.87

<5.79

<6.64

<5.86

<5.15

<6.17 Nb-95

<3.93

<3.33

<4.13

<4.01

<3.55

<3.99 Co-58

<2.84

<3.16

<3.89

<3.37

<3.26

<3.60 Mn-54

<2.84

<2.64

<2.84

<3.28

<3.26

<2.79 Fe-59

<7.44

<7.86

<7.67

<7.05

<6.49

<8.02 Zn-65

<7.26

<7.44

<7.15

<4.69

<7.73

<7.11 Co-60

<2.80

<3.17

<2.97

<2.77

<2.97

<3.76 K-40 48.6i12.8 55t12 214i18 821 23 23.7i18.9 215t16.3 m

Ba/La-140

<9.37

<7.62

<8.90

<7.00

<7.56

<10.4 NINE MILE I-131

<9.53

<10.7

<8.29

<10.7

<7.93

<8.05 POINT Cs-134

<1.90

<4.02

<2.70

<2.06

<2.67

<1.27 UNIT 2**

Cs-137

<2.77

<4.45

<2.98

<2.97

<3.30

<1.86 (11. INLET)

Zr-95

<5.86

<8.03

<5.98

<6.05

<5.83

<3.45 l

Nb-95

<3.21

<5.80

<3.75

<3.67

<3.30

<2.23 l

Co-58

<3.10

<5.23

<2.69

<2.87

<3.13

<1.95 l

Mn-54

<2.91

<5.14

<3.23

<2.64

<2.76

<1.71 l

Fe-59

<7.57

<13.9

<8.04

<7.47

<7.65

<4.97 Zn-65

<6.84

<11.1

<8.31

<7.38

<7.04

<3.92 l

Co-60

<3.25

<6.60

<3.47

<2.94

<3.17

<1.92 J

K-40 78.6 12.1 188i24.5 39.6i11.5 68.5*12.1

<34.4 61.617.25 Ba/La-140

<7.90

<11.8

<10.8

<7.82

<7.78

<5.89 Corresponds to sample locations noted on the maps in Section 3.3.

o 00 Optional sample location. Samples not required by Technical Specifications.

TABLE 6-4 (Cenrznuso)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1995 Results in Units of pCi/ liter i 1 Sigma STATION CODE

NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEEER OSWEGO CITY I-131

<12.3

<8.93

<10.7

<11.6

<12.2

<8.39 WATER **

Cs-134

<4.14

<2.10

<2.14

<4.29

<4.41

<1.74 (10)

Cs-137

<4.23

<3.04

<2.86

<3.96

<3.80

<1.66 Zr-95

<7.27

<5.97

<5.89

<9.25

<8.55

<3.78 Nb-95

<4.98

<4.14

<3.98

<6.26

<5.50

<2.47 Co-58

<3.92

<3.52

<3.43

<4.92

<5.18

<2.32 Mn-54

<3.70

<3.22

<3.42

<4.47

<4.90

<1.98 Fe-59

<11.8

<6.97

<6.47

<10.3

<12.6

<4.89 m

3 Zn-65

<9.33

<4.54

<4.92

<11.4

<11.6

<4.15 Co-60

<4.20

<2.95

<2.79

<4.51

<5.56

<1.99 K-40 205i22.3 779123.4 697i22.2 194i24.5 175i24.5 266ill.8 Ba/La-140

<11.4

<6.9

<7.39

<11.8

<14.8

<6.50

Corresponds to sample locations noted on the maps in Section 3.3.

- Optional sample location. Samples not required by Technical Specifications.

ocococooooooooooooooo----

oooo kSCS$0.9CO99COoC999909909o i

l CocooococoCococcocooCooco

+1 +1 +t +1 +t +1 +1 +t +4 44 44 +l +1 +1 +1 +t +4 +t +4 +i 44 +4 +1 44 +t C

memonmmmmnmNan-sm-@

mmman

~

-co------------oo-o-o-o--

m CococoCocoC9CooCCCoCocooo ococococococcoooooooooooo

~~~~~~~--------~~--------

ocooooooooococooooooooooo C@ oCCCocoCocco A

oooooooooooooo.CCCCocoooco w

ooooooooooo

+1+1+t M +144 +1+i M +i+t M +i+1+4+i44 M +1 M M +i M +4 M C

nmmNwwnamNnswnommNm-mmmvN a

-co------N

-o---co-o-o-w--

L

- - - COOooooooooCooooo ooooooooooooooooooooo.oooo oooo g

Z l

O

\\

H

~~~~~~~~~~~-- ---------

H cococcoooooooooooooooo---

ooo C C C C. C C C C C C C C C C C C C C o o c c o C o

)

ooooooooooooodocodooooooo i

+1 +t +1 +1 41 +1 +1 +1 +1 +1 M +1 +1 +4 +1 44 +4 +1 +l +i +1 +4 +1 +1 +

e - e m m n v N N m m N m N N e e - c o e N m m,1 m

O l

~~oo-----------oo---o----

99C999909C99909990 W

W cooooooooooooooooo.99099o9 ooooooo g

H M

i

~~---~~------~~-----

m4 ococcocococococcooooooooo bh C

@ NDNMnovm-nmC @ mmemM - MmNM@

g g N

-o---N

--N

o--o-o----

l 9 9 0 0 0 9 9 0 0 9 9 9 9 9 9 9 0 0 9 C. 0 0. 9 0. 9 g e g

ooooooooooooooooooooooooo W

J

+l w

i

--~~~~~~~~~~ ~~~-~~~~~~~--

m E

'w

$$$$$$$$$$$$o.$

o c o o o c c o o g o o o o $ $ $ $ 8. $ $ $ $ $ $

w pg D Q

ooooooooooo S

H U Z NN$$$$$$$d$$?$$$$$N$$N$$$

e mw a o m

--o------------oo-o-o-o--

<a b p e

my w

J nm>

0 m

NuH o 6:

ocococococooooooooooooooo 4

AH a

b EHU L

CCCCC9CCCCCCCCCCCCCCCCCCC i

il +1 +1 -H +4 M +4 M +1 +1 +1 +1 +1 +1 M +1 M +1 +1 +1 +4 +1 M M +1 gg4 Q

cococcoooooooooooooooooo 1

<(

(

wow o@ mMvmH@ -nm-ngMM m@ N-@ v g

-o------N-----ow

-coo----

mb e

sa aaaaaaaaaaaaaaaaaaaaa:

zm MoW

~~~~~~~~~~

E d6 66 M M M +4 M M M,M M 4 t +4,H M- - -,M M M M,M M M M

+l

+1

<w n-@

m@ @ ann ann

--m a

m o------N--

o-o-o----

o J

l coo 9COC90999COC.9COC9COOO9 3

4 g

ooooooooooooooooooooooooo g

W a

Z m

W E

k ooooooooooooooooooooooooo

-4 z

W ooCoo*CCCCCCCoo*Coooo****

2 o

C cooooooooooooooooCCococco C

-H +1 +t +1 +1 +4 +t M +1 +1 +4 +t +6 +4 +1 M +1+1+4 +1 44 +1 +1 +4 +1 I

M

@ NDmw4mm-m@

M N commNNmonm o

H N

o------N N@

-~~o------

e g

e aanasaaaaaaaaaaaaaaaaaaaa t

W E

t 8

L ogooooooooooooooogooooooo

$dassaasassssaaaad=

2:32 I

o

+1M M M M M M M M +1+1 M M M +1 M M M M +1 M +1 M MM w

@ N@ N Km@ mv--M@ M mMovnommNnN I

N o--~~--m-----o--o-o----

M l

ooooooooooooooooooooooooo C

g ddddddddddddddddddddddddd

.h i

m O

g mmmmmmmmmmmmmmmmmmmmmmmmm DDkkkkkkkkkkkkkkEkkkkkkkk H

ons-nw-wnn-mn-mmAs@

o@ men a

m m m m,E t,t,0 E E R GECCU E

ECUQ C000

~

m na mmm m@ @

i ooooooooooooooooooooooooo m

6-13

--~~------------ ----- - -- --

ocoogoooooooooooooooooooooo-co99. Coo C99Co ococodoo$oS90$oo99kooC ooooooooooooooooooe

+1+4+1+1*i w +1 +t +t +1 +t di +4 e +t+t+4

+1 +1+1 +1+1 +1

+t +1 +1 +1 O

emMme-mb omm web cmmem

---o-----oH--

m-wN wmec l

O---N

o-qqoqqqooooooooogogocoqqqqqq ooooooooooooooooooooooooooo

m ococoegoqoo,oogooooooooo{coe oooo gooooq,

oq,qocococco g

oooooooooooooooooooooooo,qqq W

ooo

+4+4+1+4+1+1+1

+t +t vt +1 +1 +1 +i 44 +1 +1 +1 +1 +t+t+1+144 +1+1+1 O

emeaaamwNNNmomemm-mmonwwNmb 3

o----o--------oN

~~o-W C o o C o c o C C 9 C C C C o

C o o C C C o o o o. O m

coooooooooooooooooooooooooo ZO H

p ooooooooooooooooooooooooooo C@ CCCCCCCCooCCCCCCCoCCCCCCC q

H ooScooooooooooooooooooooooo

+i e

+1+i+t+1+t+t+i+t w +t+i e +1+i+i+t e +t u +t u w +1+i M

O mmooMcN @ - m-NN - @ oM Nmm-bob @ Mm l

C-NN --- - - -- - -H on---------o-W W

CCCCCCCCCCCCoocooCCCCCCCCCC g

coooooooooooooooooooooooooo H

M I

1 4 L

ocococoooooccoooooooooooooo 1 E 1

CCCocoooCCooCCoooCoCCocoCoo o it+iS c o c c o S o o o o o o o o o o o o o o o o o o

a o

_c w

e +t u +i +t

+i +1 +t +t+1+t+1 w +6+i e +1 +t +t u +i e ebee-wwmH=Nwm-nme-mNobmmN em a g N

o-N N N--

N oN---------o-I coooooooooooooooooooooooooo g e o

ooooooooooooooooooooooooooo O

W W

J M e

~~~-----------------

n A

ooooooooooooooooooooooooooo E E w

o c o o c o o o o o o o o o o o o o c o. c o o o c c o, H

W<

H gmD o

ooco3oooooooooooooooooooooo t

z H

UZ e +1 +1 +4

+i+i+# w +1+1+tu +444 +4+i e w +1+i+i+1+t u e +t mmmww-wmamNmnoeN o-mvN mmb N wb U yW QQ C-N

o----N eH - - -

o-U I

C C C C C C C C C C C C C C C C C C C C C C C C. o C C H

w g4 p

g ooooooooooooooooooooooooooo

<J _<

l W

om>0 t

E

%U

@ AH H O

~

6 ooooooooooooooooooooooooooo EH Og 6

@ CoCCCCooooooooooooooo@ oC@ @

gl zg4 o

o c o o ii w +i+1 w w w +1 w +1oooooooooooooooooooooo

+t+t+i +1 e w +t +t +i +1 +1 +1 +t +1 +t u +i i

<f wmmm6-mm-mvw-wwN w-wnamwb-e6 i

L Q

o-------------ON

o----o-m H

t CCCCCCCCoCCCCCooC909CCCoCoC 4

ww g

coooooooooooooeoooooooooooo H

hO M mM L

eoooooooooooooooooooooooooo E

E O 1

o oo*C oooooo oooo@ c cooC g g o

ooooooooooooooooooooooooooo o

+1 +i e w e 41 +i e +i +t +4 e +1 m +i c w +1 +i e +i e +i +i +i +i +t 4c MmwNmNw@ - mwNoM@ Nw-w--wNMNbe I

M o--N---

N

oM i

g J

l 99C9999CCCC9C9.CCO9CCC.C999C o

I 4

g ooooooooooooooooooooooooooo 5

I W

e Z

o U

k*

W E

ococococooooooooooooooooooo 3

Z W

o o o o o o o o o o o. o o o o o o. o o o o o o o o o o u

o o

ooooooooooooooooooooooooooo E

w w +t e u u w w w w w w w w w w w w w w w +1+1 e +1 w w 5

MwmmeMMMcNN-N bmw@ - MNN @ mN whm E

H N

o--NN- - -- - ---- oN - --

o-0 l

o o g o o o o o o o o o o o o c, o c o o g o o o o o o, J

g g

oooooooooooooooooooooooocco W

c

~~~~~~~-~~~~~~~~~~~~~~~-~~~

e b

ooooooooooooooooooooooooooo

.h k

ooooooooCoooooooooooooooooo 3

O aada6666666doddd6666666666&

c

+t +1 +t +1 +i +1 +t 44 +4 +1 +1 +4 +1 +4 +t 44 +i +1+1+1+1+t+t+t+i+t+t ID b

mWbwo-mMN@ vmNobmme@ Nemmbwbm d

C--N N- -- - - - - -N ON - - -

-o----o-m I

9999099 CCCCCC999CCCC.C9999kk C

g ooooooooooooooooooooooooooo

,o

-O C

o

{W mmmmmmmmmmmmmmmmmmmmmmmmmme 2

tt7tttt*ttttttttttttttttttt a

H m-Bm-mmhemNmemobn-b w-wmN men kEENkkUDUkEEUkEEDDkEDUbE"Nk Wo bb b bemmemememococo----aNAN-E m

coooooooooooo-------------o e

g M

e 6-14

T cococooooooooooooooooC oco I

9 9 9 0 9 C 9 9 9 C O. 9 9 0 9 9 9 9 9 C. 9 0. C. C C C

ooooooooooooococococococo I

41 M +1+1+1+14444+1+1+1+1+1+1 H +1+1+1+1+1+1+1+1+1+1 I

vmvmmom ecebmmmNemm5cmoNvm M

mm om me nm m m m m m m m ocoom om oom ococococooooococooocococo 0$

d$$

$$$b06 06 d

a m M m m m M mM m M m m mmm M m m m mm mm m m coccoOoooOoooOccccoococco g

ocococoooccoooooooooooooo o

666dddddddddddddddddddddd Z

+1+1 +1+1+1+1+1+1+1 e v m m m m m m c o+1 +1 41 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 44 +1 44 O

)

mNmmvemmemmmemb H

mm om m m m mm m m m m m woomocoom m m q

ocococooooooooooccoccocco ddddddddddddddddddddddddd H

M W

H A

m m m mm mmmmm m mm m m m m m mm m m m m m n 4 coooooooooooooooooooooooo z

2 CC C

CCCCCCCCCCCCCCoCocco oE o

cooooooooooooecocooococco

+1+1+1+1+1+1+1+1+1+1+1+1 O

i o m N o b m v e m m c o c+1 +1 +1 +1 +1 +1 +l +t +t +t +t +1 +1 3

e mommobomommm W

g m oom m mnmmm m mmm m oom omom m m m M

9999999999999999999999099 e

w ooooooooooooooooooooooooo 3

+1 aEM E

w<b ID M

g I

H O 2 "W

2 O H

COCC*CO*CO**O**CC***COC**

$- < =$ g H coooooooooooooooooooooooo w

M#Ad*dddddddddddddddddNN

,u>

O mm om m mm mm mm mm m m oooooomm m m pO E

9999999e.99999999999999999 H

a coccooooooooooooooooooooo

= <

wHW z

M g

mm m mmmm m m ~ ~ ~ m mmm~mm m m m ~ ~ m o

ococococcoccoccococcoccoo m

E 999999999999999990.9999999 e n,$,w$ $ $ $ $ $ $ $ $,$ $ $ $ $ $ $ $ $ $ $ $

$o C

< x b-6mmen mmmmn-n=mnew m m om mmNmmm m m m mm oom om om m Nm g

9999????999??$?99?99999 oooooooooooooooooooooocc??

J o

&zw EZO m~m-mmmwm m m m m m mmm mm m mm m m m E

ocococcococococococococco E

9999999999999999999999999 z

o cocoooooooooooooooooooooo w

a

+1+1+1+1+1+1+1+1+1+I+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1 g

bmmNmmb@vmTo@ mmCem bm mNobe mm om m m m m m m m m m m m oom om om m m m g

Q 9999999999999999999999999 coooooooooooooooooooooooo O

mmmmm m mmmmmmmmmmmmmmmmmmm W

DDDDDREDDDDDkDDDDDDDDDDED H

memoe m odemobmobvm mmmommme kUDDkRDDkUDDkUEDkkUDDkUUD WD m m m m n n nnmmmmwnnnmmmmmeeww ecoco c ooooooooooooooooooo 6-15

~ ~ ~---~~---------~~--------

eeeeeeeeeeeeeeeeeeeeeoceeee 2

ocococococococooo@ @ ocooocco o

$ococooooooooooooooooooooooM -H +1 H +1 +1 +1 H H +1 +1 +1 +1 +1 +1 +1 +1 +1 M +1 H +1 i

i emwm e-o-mmwwombmnwMemchecm-u

~~~nn---o--~~-en-~~------en ooooooooooooooo cocoooooooo coececeooooooeooooooooooooo coecoceceeeeeeeeeeeeeeeeece z

ooooooooooooooooooooooooooo m

o ococcoooooooooooooooooooooo z

s

+1 +1 +1 +1 +1 +1 +1 M +1 +1 +1 +1 +1 +1 +1 +1 +i +1 +1 +1 -H +1 +1 +1 +1 +1 +1 O

enomeom-meemmoevn-Nmnnmemem n

o---o-on---------o-U occooooooooooo oooooooooooo ooooooooooooooooooooooooooo W

m w

&H

~~----

M eeeeeeeeeeeeeeeeeecoeococee sq z

cooooooooooooecocococococco Oy o

dddddddddddd6dddddddddddddd Z

+i+1+1+i+1+1+i+1+1+1+1+i+i+i+1e +1+i+1+i+1+i+i+i+i+1+1 0

e enxm-nnmnwwwaenenmnnmmnowam i-M g

n---e---o-en------nn-on cocococococcococococoeococe ddddddddddddddddddddddddddd

]

F w

au m

e z

za i

E w<d w

m F

g z

o z ococoeocoeceeeeeeeeeeeeeece H

o wC o

H 9

z c o o c. o o o o o o o o o o o o o o o o o o o o o o o M

g <I p

o ocooococococooooooooooooooo

~

4 a

+1 +1 +1 +1 -d +!

H +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +l +1 -H +1 +1 +1 m

<m>-

i

-mownoennmxwonn---mnonwwwmn O

O I

%y-g

--N

Ocee-w eN-w o------o-m O

ceCooooooecoccooooooooooooo J

dddddddddddddadddddddddddad

@ Q w z<<

J 14 W

wH W

4 z

m p

u i

Oceceeeeeeeeeeoceeceococe e

oooooooooooooooooooooooooHo Om g

$M o

ddddddddddddddddddddddddd<d o

e

+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1+1A +1 s

onwoxnnwonnwoonmnmwnnmxwm x

x e

<g g

---n----~~~~~nen---------

999o.99999999999 k k k k k k k 9 9 9 *Q -k g

ooooooooooooooooooooooooo go 4>

2Wz ZO

--s E

ocoeocococeeeocecocecococee H

E 999999999999999999999999999 o

cooooooooooooooooooooecocoe Z

s

+1 +1 +1 +1 +1 +1 +1 +1 +1 +1 -H +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 -H +1 +1 w

3 embMmMNNe@ NNmC@ mm@ m@ NWhomeM

w o---enon--o----n-e-go 999999999999999999999999.kk occocococococoooooooooooooo O

mmmmmmmmmmmmmmmmmmmmmmmmmm@

W DDDDDEDDDDDDDDDDDDDDDDDDDDD monw-nn-wm-xmnewmoemonn-men kEUDQkCDDkECDkkUDDkCDDkUUUk o

osoor===mmmmecocoo----anns-Cocooocococee----------~~-o 6-16

TABLE 6-7 NMP/JAF SITE ENVIRONMENTAL. CHARC0AL CARTRIDGE SAMPLES - 0FF-SITE STATIONS l-131 ACTIVITY pCi/m 1 SIGMA LOCATION WEEK END DATE R-1*

R-2*

R-3*

R-4*

R-5*

D-2 E

F G

01/10/95

<0.011

<0.013

<0.012

<0.007

<0.012

<0.013

<0.010

<0.013

<0.014 01/17/95

<0.013

<0.011

<0.010

<0.018

<0.014

<0.010

<0.009 01/24/95

<0.012

<0.008

<0.011

<0.013

<0.014

<0.012

<0.009 01/31/95

<0.012

<0.014

<0.011

<0.014

<0.010

<0.016

<0.012

<0.015

<0.010 02/07/95

<0.012

<0.008

<0.009

<0.012

<0.013

<0.014

<0.010

<0.014 02/14/95

<0.014

<0.011

<0.013

<0.012

<0.017

<0.011

<0.013

<0.008 02/21/95

<0.013

<0.008

<0.010

<0.011

<0.017

<0.012

<0.010 02/28/95

<0.012

<0.010

<0.014

<0.010

<0.012

<0.017

<0.031

<0.008 03/07/95

<0.013

<0.008

<0.013

<0.008

<0.012

<0.011

<0.010

<0.009

<0.016 03/14/95

<0.010

<0.015

<0.009

<0.013

<0.008

<0.013

<0.009

<0.017

<0.008 03/21/95

<0.012

<0.014

<0.010

<0.014

<0.016

<0.018

<0.012

<0.010 03/28/95

<0.014

<0.008

<0.009

<0.012

<0.009

<0012

<0.011

<0.014

<0.016 04/04/95

<0.012

<0.009

<0.010

<0.013

<0.010

<0.012

<0.011 04/11/95

<0.010

<0.012

<0.015

<0.011

<0.010

<0.012 04/18/95

<0.014

<0.011

<0.010

<0.013

<0.012

<0.013

<0.009

<0.014 l

04/25/95

<0.013

<0.009

<0.010

<0.014

<0.010

<0.016

<0.013

<0.008

<0.009 l

05/02/95

<0.013

<0.011

<0.013

<0.012

<0.014

<0.011

<0.010

<0.009

<0.018 05/09/95

<0.012

<0.014

<0.016

<0.011

<o.016

<0.011

<0.006

<0.012 05/16/95

<0.013

<0.008

<0.017

<0.011

<0.012

<0.008

<0.009

<0.014

<0.016 05/23/95

<0.018

<0.013

<0.018

<0.010

<C.008

<0.014

<0.013

<0.012 05/30/95

<0.010

<0.014

<0.011

<0.013

< ).010

<0.016

<0.009

<0.010

<0.010 06/06/95

<0.012

<0.008

<0.012

< 0.009

<0.018

<0.008

<0.010

<0.009 06/13/95

<0.009

<0.014

<0.010

<0.012

<0.013

<0.014

<0.008

<0.007 06/20/95

<0.014

<0.009

<0.016

<0.013

<0.010

<0.014

<0.011

<0.010

<0.015 06/27/95

<0.011

<0.009

<0.014

<0.010

<0.012

<0.013

<0.008

Sample locations required by Technical Specifications

TABLE 6-7 (ConTrnuso)

NMP/JAF SITE ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - 0FF-SITE STATIONS l-131 ACTIVITY pCi/m 1 SIGMA 1.OCATION WEEK END DATE R-1*

R-2*

R-3*

R-4*

R-5*

D-2 E

F G

07/05/95

<0.017

<0.013

<0.016

<0.011

<0.008

<0.014

<0.015

<0.009

<0.013 07/11/95

<0.014

<0.011

<0.014

<0.012

<0.016

<0.012

<0.021 07/18/95

<0.010

<0.013

<0.010

<0.012

<0.022

<0.016

<0.013

<0.008 07/25/95

<0.012

<0.014

<0.016

<0.014

<0.011

<0.014

<0.015

<0.016

<0.015 08/01/95

<0.009

<0.010

<0.009

<0.011

<0.016

<0.008

<0.013

<0.017 08/08/95

<0.016

<0.008

<0.017

<0.006

<0.015

<0.008

<0.016

<0.010

<0.013 08/15/95

<0.012

<0.013

<0.014

<0.010

<0.011

<0.012

<0.014

<0.006

<0.016 08/22/95

<0.012

<0.009

<0.015

<0.010

<0.012

<0.011

<3.011

<0.011

<0.010 08/29/95

<0.008

<0.013

<0.014

<0.010

<0.013

<0.017

<0.014

<0.008

<0.017

?

09/05/95

<0.016

<0.010

<0.013

<0.010

<0.015

<0.014

<0.012

<0.018 E

09/12/95

<0.010

<0.013

<0.007

<0.008

<0.014

<0.010

<0.012

<0.010

<0.018 09/19/95

<0.018

<0.013

<0.008

<0.014

<0.013

<0.014

<0.011

<0.013

<0.013 09/26/95

<0.014

<0.010

<0.013

<0.009

<0.016

<0.014

<0.012

<0.013 10/03/95

<0.012

<0.014

<0.013

<0.008

<0.009

<0.013

<0.010

<0.018 10/10/95

<0.010

<0.009

<0.014

<0.015

<0.011

<0.015

<0.015 10/17/95

<0.014

<0.010

<0.011

<0.012

<0.010

<0.008

<0.012 10/24/95

<0.008

<0.012

<0.011

<0.013

<0.011

<0.012

<0.017

<0.013 10/31/95

<0.013

<0.012

<0.013

<0.010

<0.011

<0.013

<0.014 4.008

<0.012 11/07/95

<0.008

<0.014

<0.009

<0.013

<0.014

<0.012

<0.010

<0.009

<0.016 11/14/95

<0.010

<0.015

<0.009

<0.012

<0.013

<0.009

<0.014

<0.009

<0.013 11/21/95

<0.012

<0.013

<0.007

<0.017

<0.014

<0.008

<0.014

<0.011

<0.012 11/28/95

<0.010

<0.007

<0.008

<0.010

<0.014

<0.011

<0.017

<0.012 12/05/95

<0.013

<0.014

<0.009

<0.013

<0.010

<0.011

<0.007

<0.010 12/12/95

<0.012

<0.011

<0.015

<0.011

<0.013

<0.009

<0.014 12/19/95

<0.010

<0.013

<0.009

<0.012

<0.013

<0.011

<0.014

<0.011

<0.015 12/26/95

<0.015

<0.009

<0.015

<0.016

<0.014

<0.013

<0.010

<0.018

<0.014 01/02/96

<0.011

<0.009

<0.012

<0.008

<0.014

<0.016

<0.014

<0.018

<0.017

Sample locations required by Technical Specifications

TABLE 6-8 NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ON-SITE STATIONS l-131 ACTIVITY pCi/m 1 SIGMA LOCATION WEEK END Dl--ON G--ON

~H--ON I--ON J--ON K--ON 01/09/95

<0.010

<0.012

<0.013

<0.010

<0.010 01/16/95

<0.007

<0.013

<0.012

<0.017

<0.015

<0.010 01/23/95

<0.012

<0.016

<0.012

<0.011

<0.008

<0.015 01/30/95

<0.010

<0.011

<0.013

<0.010

<0.015 02/06/95

<0.009

<0.015

<0.016

<0.011

<0.015

<0.008 02/13/95

<0.010

<0.013

<0.015

<0.012

<0.010

<0.015 02/20/95

<0.009

<0.008

<0.015

<0.014

<0.016

<0.009 02/27/95

<0.011

<0.016

<0.010

<0.008 03/06/95

<0.010

<0.005

<0.018

<0.011

<0.013

<0.014 03/13/95

<0.010

<0.018

<0.011

<0.016

<0.011

<0.011 03/20/95

<0.014

<0.020

<0.016

<0.010

<0.013

<0.013 03/27/95

<0.013

<0.014

<0.017

<0.011

<0.010

<0.018 04/03/95

<0.008

<0.012

<0.009

<0.013

<0.016

<0.012 04/10/95

<0.010

<0.014

<0.012

<0.013

<0.012

<0.012 04/17/95

<0.012

<0.010

<0.014

<0.017

<0.010

<0.009 04/24/95

<0.012

<0.014

<0.010

<0.014

<0.013

<0.015 05/01/95

<0.010

<0.014

<0.013

<0.012

<0.010

<0.012 05/08SS

<0.008

<0.016

<0.014

<0.008

<0.015 05/15/95

<0.012

<0.017

<0.015

<0.012

<0.007

<0.016 05/22/95

<0.010

<0.017

<0.009

<0.008

<0.011 05/30/95

<0.010

<0.012

<0.008

<0.013

<0.009 06/05/95

<0.012

<0.014

<0.018

<0.008

<0.017 06/12/95

<0.010

<0.016

<0.014

<0.011

<0.014

<0.013 06/19/95

<0.012

<0.008

<0.011

<0.015

<0.012 06/26/95

<0.011

<0.012

<0.011

<0.010

<0.015

==-- _ - -

TABLE 6-8 (Conrruuso)

NMP/JAF SITE ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - ON-SITE STATIONS l-131 ACTIVITY pCi/m i1 SIGMA LOCATION WEEK END D--I G--ON H--ON I--ON J--ON K--ON 07/03/95

<0.011

<0.016

<0.011

<0.010

<0.015

<0.012 07/10/95

<0.014

<0.018

<0.016

<0.015

<0.012 07/17/95

<0.011

<0.016

<0.008

<0.016

<0.014

<0.011 07/24/95

<0.011

<0.014

<0.015

<0.013

<0.014

<0.012 07/31/95

<0.011

<0.013

<0.014

<0.018

<0.009

<0.013 08/07/95

<0.014

<0.011

<0.015

<0.017

<0.013

<0.011 08/14/95

<0.014

<0.013

<0.017

<0.014

<0.013 08/21/95

<0.012

<0.015

<0.014

<0.013

<0.014

<0.010 08/28/95

<0.009

<0.010

<0.014

<0.016

<0.012

<0.012 09/05/95

<0.010

<0.014

<0.018

<0.013

<0.012

<0.014 e

Q 09/11/95

<0.015

<0.016

<0.006

<0.015

<0.014

<0.013 09/18/95

<0.008

<0.017

<0.008

<0.014

<0.012

<0.009 09/25/95

<0.014

<0.012

<0.013

<0.014

<0.009

<0.014 10/02/95

<0.013

<0.012

<0.008

<0.013

<0.013 10/09/95

<0.015

<0.014

<0.010

<0.018

<0.015

<0.013 10/16/95

<0.009

<0.016

<0.011

<0.007

<0.015 10/23/95

<0.100

<0.011

<0.010

<0.012

<0.014

<0.012 10/30/95

<0.010

<0.007

<0.013

<0.008

<0.014

<0.008 11/06/95

<0.011

<0.006

<0.015

<0.016

<0.006

<0.008 11/13/95

<0.014

<0.010

<0.008

<0.016

<0.014

<0.008 11/20/95

<0.011

<0.008

<0.013

<0.012

<0.010 11/27/95

<0.015

<0.011

<0.009

<0.014

<0.011

<0.010 12/04/95

<0.012

<0.009

<0.012

<0.015

<0.011 12/11/95

<0.014

<0.011

<0.013

<0.011 12/18/95

<0.012

<0.009

<0.014

<0.015

<0.012 12/26/95

<0.012

<0.008

<0.016

<0.014

<0.012 01/02/96

<0.014

<0.011

<0.008

<0.012

<0.014

<0.012

TABLE 6-9 CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10'3pCi/m i 1 Sigma 3

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE R1 0FF-SITE COMPOSITE

Be-7 56.017.10 77.6i7.19 97.317.84 82.018.20 72.7 6.94 107 7.23 Zn-65

<4.10

<3.36

<3.44

<4.32

<3.23

<2.81 Cs-134

<1.11

<1.42

<0.86

<0.97

<1.21

<1.06 Cs-137

<1.53

<0.97

<1.09

<1.30

<1.02

<1.07 Zr-95

<3.32

<2.33

<2.75

<2.10

<2.75

<2.59 Nb-95

<2.55

<1.37

<1.90

<2.06

<1.58

<1.72 Co-58

<1.89

<1.49

<1.37

<2.00

<0.89

<1.43 Mn-54

<1.64

<1.30

<1.20

<1.85

<1.36

<1.02

?

Co-60

<1.39

<1.83

<1.29

<2.36

<1.28

<1.34 S

K-40 213i14.3

<14.1 138i9.97 25.916.90 12.514.99 176 10.7 Otherst

<LLD

<LLD R2 0FF-SITE COMPOSITE

Be-7 60.915.67 85.614.55 82.615.99 83.916.81 75.3i8.98 97.616.88 Zn-65

<3.26

<2.29

<2.36

<2.84

<4.23

<2.54 Cs-134

<0.71

<0.72

<0.81

<1.22

<1.37

<0.87 Cs-137

<0.82

<0.91

<0.82

<1.13

<1.45

<0.49 Zr-95

<1.50

<1.81

<1.85

<2.36

<1.87

<1.95 Nb-95

<0.88

<0.69

<1.16

<1.69

<1.73

<1.08 Co-58

<1.05

<1.12

<1.05

<1.14

<1.37

<0.95 Mn-54

<0.76

<0.86

<0.75

<1.24

<0.83

<0.87 Co-60

<1.19

<0.74

<1.05

<1.85

<1.86

<0.93 K-40

<11.6

<11.1 24.0 5.54 35.7i6.48 30.218.39 21.714.72 Otherst

<LLD

<LLD j

o Sample Locations Required by Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (Cennuuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10 pCi/m i 1 Sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE R3 0FF-SITE COMPOSITE

Be-7 52.218.08 108i7.88 93.317.20 76.9 7.58 72.317.29 119i7.78 Zn-65

<4.48

<2.14

<3.38

<3.63

<3.33

<2.84 Cs-134

<1.33

<1.22

<1.04

<0.52

<1.35

<0.78 Cs-137

<1.57

<1.20

<1.19

<1.14

<1.37

<0.98 Zr-95

<4.20

<3.01

<2.59

<2.64

<2.70

<1.97 Nb-95

<2.59

<2.02

<1.75

<1.95

<1.59

<1.25 Co-58

<2.22

<1.54

<1.64

<1.61

<1.16

<1.11 Mn-54

<2.22

<1.35

<1.51

<1.42

<1.46

<0.83

?

Co-60

<1.34

<1.28

<1.27

<1.51

<1.81

<1.13 l3 K-40 23.6i7.26 174112.3 140i10.5 37.218.26 24.716.85

<8.24 Otherst

<LLD

<LLD R4 0FF-SITE COMPOSITE

Be-7 52.415.91 94.316.79 93.615.91 84.7i6.05 76.616.30 12417.25 Zn-65

<1.98

<1.66

<1.53

<3.'19

<3.44

<1.92 Cs-134

<0.90

<0.91

<0.64

<1.27

<0.87

<0.70 Cs-137

<0.94

<0.78

<0.79

<0.76

<1.17

<0.62 Zr-95

<2.10

<1.61

<2.00

<2.34

<2.24

<1.55 Nb-95

<1.38

<1.28

<1.10

<1.33

<1.82

<0.94 Co-58

<1.18

<0.93

<0.90

<0.88

<1.53

<0.80 Mn-54

<0.98

<0.76

<0.82

<D.98

<1.29

<].92 Co-60

<1.21

<0.88

<0.89

<1.03

<1.69

<0.96 K-40

<11.5

<10.8

<10.3 13.0i3.48 145t10.7 22.615.28 Otherst

<LLD

Sample Locations Required by Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (CenTrnuto)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES 0F JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10pCi/m i 1 Sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE R5 0FF-SITE COMPOSITE (CONTROL)*

Be-7 63.li6.66 81.218.26 118i7.15 76.216.77 76.616.18 110 6.82 Zn-65

<4.32

<4.24

<2.62

<2.75

<2.36

<1.78 Cs-134

<1.14

<1.50

<0.83

<1.04

<0.83 Cs-137

<1.08

<1.52

<0.90

<1.00

<1.24

<0.95 Zr-95

<2.35

<3.99

<1.84

<2.16

<2.28

<1.60 Nb-95

<1.73

<2.99

<1.56

<1.42

<1.48

<1.16 Co-58

<1.21

<2.04

<1.03

<1.24

<0.89

<0.94 Mn-54

<1.58

<1.12

<0.85

<1.16

<0.88

<0.76 Co-60

<1.07

<1.69

<1.13

<1.49

<1.20

<0.72 K-40 58.7 9.39 33.518.82 42.416.52 35.2i7.05

<15.3 40.815.49 Otherst

<LLD

<LLD D2 0FF-SITE COMPOSITE **

Be-7 53.216.50 97.518.53 90.017.18 84.915.38 86.9t7.95 105 7.35 Zn-65

<3.49

<3.32

<2.39

<3.74

<4.13

<2.72 Cs-134

<1.10

<0.91

<0.77

<1.31

<1.18

<1.06 Cs-137

<1.24

<1.18

<1.04

<0.98

<1.17

<1.20 Zr-95

<2.32

<2.50

<1.64

<2.60

<2.80

<2.30 Nb-95

<1.50

<1.95

<1.04

<1.94

<2.19

<1.22 Co-58

<1.28

<1.42

<1.32

<1.14

<1.06

<0.80 Mn-54

<1.03

<1.37

<1.01

<1.57

<1.56

<0.87 Co-60

<1.73

<1.70

<1.04

<1.60

<1.26

<1.37 K-40 9.3915.36

<12.2

<12.7 38.li5.67 4e. 9i8.49 24.616.43 Otherst

<LLD

Sample Locations Required by Technical Specifications.

- Optional Sample Location. Hot Required By the Technical Specifications.

t Plant Related Radionuclides.

~

TABLE 6-9 (ConTrnuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 2

Results in Units of 10pCi/m 11 Sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE E CFF-SITE COMPOSITE **

Be-7 46.416.53 88.2t7.39 83.718.31 68.4i6.22 59.5i5.90 111i6.94 Zn-65

<3.36

<3.28

<3.24

<2.76

<2.68 Cs-134

<1.40

<1.07

<1.05

<1.28

<1.12

<1.18 Cs-137

<1.54

<0.97

<1.29

<1.16

<0.88

<1.08 Zr-95

<3.60

<1.84

<2.73

<1.76

<1.48

<2.35 Nb-95

<2.66

<1.70

<1.67

<1.38

<1.35

<1.79 Co-58

<2.19

<1.36

<1.38

<1.33

<0.99

<1.36 Mn-54

<1.42

<1.39

<1.21

<0.98

<0.75

<1.23

?'

Co 60

<1.22

<1.48

<1.16

<1.89

<1.04

<1.22 K-40 32.2i8.95 21.615.68

<12.7

<9.96

<11.9 156t10.3 Otherst

<LLD

<LLD F 0FF-SITE COMPOSITE **

Be-7 48.3i6.37 94.918.31 91.Si6.50 71.916.17 73.217.80 86.416.26 Zn-65

<2.70

<3.69

<2.25

<2.17

<3.11

<2.00 Cs-134

<1.10

<0.98

<1.05

<1.46

<0.87 Cs-137

<1.18

<1.07

<1.01

<0.94

<1.28

<0.65 Zr-95

<2.36

<2.26

<1.66

<2.37

<2.63

<1.66 Nb-95

<1.52

<1.45

<1.17

<1.38

<1.62

<1.21 Co-58

<1.07

<1.00

<0.89

<1.09

<1.23

<0.88 Mn-54

<1.11

<1.28

<0.66

<1.03

<1.28

<0.84 Co-60

<1.67

<1.69

<0.88

<1.26

<2.07

<1.29 K-40 32.517.22 11.215.59 23.515.64 47.9i6.84 30.6i7.28

<11.4 Otherst

<LLD

Optional Sample Location. ! Lot Required by the Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (Cont 1suto)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 3

Results in Units of 10 pCi/m i 1 Sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE G OFF-SITE COMPOSITE **

Be-7 35.515.91 76.818.34 94.0i6.63

<6.08 64.917.64 117 10.5 Zn-65

<2.47

<4.28

<3.03

<2.46

<3.15

<4.17 Cs-134

<1.06

<1.49

<0.96

<1.20

<1.16

<1.36 9s Cs-137

<1.04

<1.16

<0.98

<1.22

<1.33

<1.45 0

Zr-95

<2.52

<2.91

<2.06

<2.19

<3.13

<2.28 Nb-95

<1.93

<1.53

<1.68

<1.34

<1.46

<1.51 Co-58

<1.40

<0.86

<1.19

<1.42

<1.13

<1.48 Mn-54

<1.43

<1.49

<1.05

<1.17

<1.14

<1.26 Co-60

<1.34

<1.72

<1.09

<1.22

<1.60

<1.43 K-40 164*11.2 M 9i7.63 14119.18

<7.89 45.317.99

<19.0 Otherst

<LLD

_LD

<LLD

- Optional Sample Location. Not Required by the Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (Ccurznuso) l CONCENTRATIONS OF GAMMA EHITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10' pCi/m 1 Sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE D1 ON-SITE COMPOSITE **

Be-7 49.415.60 86.114.32 98.8 7.60 74.5i5.94 87.4 7.54 99.1 7.52 Zn-65

<2.61

<2.04

<1.88

<2.87

<3.64

<3.06 Cs-134

<0.95

<0.76

<1.18

<1.07

<1.16

<0.97 Cs-137

<0.89

<0.58

<0.82

<1.04

<1.17

<1.16 Zr-95

<1.45

<1.77

<2.48

<1.59

<2.49

<2.30 Nb-95

<1.05

<0.65

<1.93

<1.13

<2.01

<1.97 Co-58

<1.24

<0.98

<1.28

<1.04

<1.68

<1.63 Mn-54

<1.08

<0.83

<0.87

<0.92

<1.55

<1.33

?

Co-60

<1.06

<1.28

<1.30

<1.61

<1.05

<1.64 E

K-40

<13.1

<10.2

<8.48

<10.2 53.819.16 179111.5 Otherst

<LLD

<LLD G ON-SITE COMPOSITE **

Be-7 57.5i7.52 77.2 7.11 11817.65 92.717.60 88.8i7.74 11618.15 Zn-65

<2.36

<3.38

<3.31

<2.17

<2.68

<2.49 Cs-134

<1.39

<1.26

<0.97

<1.13

<1.10

<1.07 Cs-137

<1.56

<1.41

<1.08

<1.13

<1.06

<1.11 Zr-95

<3.22

<2.76

<3.09

<2.41

<2.16

<2.59 Nb-95

<1.80

<2.10

<1.76

<1.57

<1.05

<1.47 Co-58

<1.56

<1.74

<1.39

<1.76

<1.12

<1.06 Mn-54

<1.80

<1.54

<1.31

<1.43

<0.84

<1.05 Co-60

<2.27

<1.57

<1.37

<1.41

<1.39

<1.53 K-40 42.5i10.2 178i12.2 162i10.5 29.8i7.16

<15.7 39.1 6.84 Otherst

<LLD

- Optional Sample Location. NM Required by Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (CenTrnuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10pCi/m n 1 Sigma NUCLIDES JANUARY FEBRUARY HARCH APRIL MAY JUNE H ON-SITE COMPOSI'E**

Be-7 49.416.54 70.116.95 82.217.13 94.419.44 77.4 8.11 119 8.96 Zn-65

<3.45

<2.52

<2.64

<4.89

<4.75

<2.91 Cs-134

<1.21

<1.18

<1.04

<1.79

<1.58

<1.18 Cs-137

<1.56

<1.19

<1.08

<1.44

<1.59

<1.23 Zr-95

<2.46

<2.01

<1.90

<3.86

<2.84

<1.84 Nb-95

<1.36

<1.57

<1.62

<1.74

<2.60

<1.45 Co-58

<0.62

<1.09

<0.88

<1.35

<2.28

<1.29 Mn-54

<1.43

<1.04

<0.94

<1.69

<1.66

<1.11 e

Co-60

<1.55

<1.11

<1.30

<2.03

<1.72

<1.56 ts K-40 31.2i8.14

<9.53 23.915.44

<26.9 17.817.13 27.916.07 Otherst

<LLD

<LLD I ON-SITE COMPOSITE **

Be-7 49.917.43 91.5i7.15 98.016.94 103 7.38 83.017.45 11818.53 Zn-65

<3.46

<2.07

<2.50

<3.04

<2.36

<3.68 Cs-134

<1.50

<1.15

<1.08

<1.09

<1.27

<0.91 Cs-137

<1.55

<1.15

<0.88

<0.93

<1.17

<0.91 Zr-95

<3.13

<2.18

<1.61

<2.24

<2.72

<2.20 Nb-95

<2.45

<1.60

<1.26

<1.48

<1.35

<1.49 Co-58

<1.94

<1.32

<0.97

<1.18

<1.27

<0.84 Mn-54

<1.68

<0.86

<0.89

<0.90

<1.17

<1.17 Co-60

<1.59

<1.26

<1.24

<1.66

<1.09 K-40 214i14.2

<17.2 11.0i4.23 9.4415.25 44.0t7.76

<14.3 Otherst

<LLD

- Optional Sample Location. N_qt Required by Technical Specifications.

l t Plant Related Radionuclides.

TABLE 6-9 (Contruuto)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10' pCi/m i 1 Sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL-MAY JUNE J ON-SITE COMPOSITE **

Be-7 35.2i5.78 102i7.45 97.0i7.15 105i7.73 68.7i7.25 99.616.85 Zn-65

<3.31

<2.70

<3.20

<3.46

<4.40

<2.90 Cs-134

<1.15

<1.22

<1.13

<1.19

<1.32

<0.90 Cs-137

<1.31

<0.86

<0.95

<1.17

<1.28

<0.85 Zr-95

<2.10

<2.42

<2.82

<2.77

<2.91

<2.37 Nb-95

<1.52

<1.45

<2.01

<1.24

<1.98

<1.26 Co-58

<1.51

<1.18

<1.33

<1.37

<1.43

<1.05 Mn-54

<1.18

<1.05

<1.21

<1.43

<1.45

<0.86

?

Co-60

<1.52

<1.61

<1.02

<2.00

<1.43

<1.07 W

K-40 11.6i4.65

<13.8 56.5+7.66 46.118.48 197 13.0 8.40i3.36 Otherst

<LLD

<LLD K ON-SITE COMPOSITE **

Be-7 53.3i6.42 92.116.64 84.6 6.19 83.3 7.31 58.415.59 67.116.41 Zn-65

<3.63

<1.99

<2.37

<2.45

<1.82

<2.46 Cs-134

<1.29

<1.01

<0.91

<1.03

<0.75

<0.81 Cs-137

<1.36

<0.91

<0.97

<1.22

<1.12

<0.97 Zr-95

<2.16

<1.48

<1.55

<2.28

<1.90

<2.18 Nb-95

<1.67

<0.93

<1.18

<1.19

<1.30

<1.52 Co-58

<1.81

<1.21

<0.94

<1.05

<1.35

<1.11 Mn-54

<1.13

<1.05

<0.85

<0.99

<0.96

<1.11 Co-60

<1.84

<1.36

<0.64

<1.45

<1.19 K-40 50.619.00

<8.74 7.2213.61 23.216.12

<9.23 41.5 6.45 Otherst

<LLD

<LLD o* Optional Sample Location. !!ot Required by Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (Courinuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10~ pCi/m' i 1 Sigma i

NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMER DECEMBER R1 0FF-SITE COMPOSITE

Be-7 96.818.22 89.218.38 92.119.46 68.8i7.89 69.3i6.51 52.015.34 Zn-65

<4.46

<3.80

<3.63

<4.55

<2.96

<2.34 l

Cs-134

<1.20

<1.03

<1.02

<1.68

<1.08

<0.89 Cs-137

<1.61

<1.37

<1.32

<1.28

<1.17

<0.84 Zr-95

<3.09

<1.64

<2.73

<2.94

<1.93

<2.53 Nb-95

<1.14

<1.65

<2.12

<1.89

<1.34

<1.07 Co-58

<1.35

<1.04

<1.59

<2.06

<1.38

<0.91 Mn-54

<1.46

<1.10

<1.42

<1.25

<1.40

<0.90

?

Co-60

<1.60

<0.90

<1.77

<1.83

<1.22

<0.68 0

K-40 9.30i5.31

<15.4 14.li5.66 18.7 6.80

<?.4. 3

<13.5 l

Otherst

<LLD

<LLD R2 0FF-SITE COMPOSITE

Be-7 87.519.10 88.819.23 82.316.02 70.516.61 70.7i7.27 54.816.48 Zn-65

<4.42

<3.25

<2.24

<3.50

<3.19

<3.77 Cs-134

<1.52

<1.01

<0.81

<1.22

<1.23 Cs-137

<1.42

<1.31

<1.16

<1.20

<1.14

<1.05 Zr-95

<3.52

<3.68

<2.30

<2.59

<2.19

<3.01 Nb-95

<2.30

<2.17

<1.63

<1.90

<1.44

<2.17 Co-58

<2.15

<1.79

<1.36

<1.59

<1.52

<1.40 Mn-54

<1.45

<1.80

<1.09

<1.57

<1.07

<1.18 Co-60

<1.59

<1.83

<0.88

<1.30

<1.64

<0.95 K-40

<12.1 26.917.90 110 8.16 170*11.4 34.5i6.67 26.416.61 Otherst

<LLD

Sample Locations Required by Technical Specifications.

t Plant Related Radionuclides.

~~

TABLE 6 -9 (ConTzuuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10~3pCi/m 2 Sigma 3

NUCLIDES JULY-AUGUST SEPTEMBER OCTOBER NOVEMER DECEMBER R3 0FF-SITE COMPOSITE

Be-7 95.518.75 79.117.70 74.816.20 55.916.21 80.9i8.29 42.Si5.21 Zn-65

<3.59

<2.15

<3.11

<3.68

<4.92

<1.94 Cs-134

<1.19

<1.00

<0.85

<0.83

<1.48

<0.62 Cs-137

<1.07

<1.43

<1.02

<1.51

<1.46

<1.08 Zr-95

<2.47

<3.77

<1.78

<2.88

<3.36

<1.98 Nb-95

<1.78

<2.39

<0.88

<1.88

<2.24

<1.72 Co-58

<2.05

<1.95

<0.83

<1.76

<1.55

<1.24 Mn-54

<1.82

<1.94

<1.02

<1.43

<1.57

<1.02 P

Co-60

<1.61

<1.75

<0.67

<1.82

<2.30

<1.14 a

K-40 51.6i10.3 17312.09

<8.85 154*11.0 26.9i8.41

<12.7 Otherst

<LLD

<LLD R4 0FF-SITE COMPOSITE

Be-7 87.416.94 73.215.96 97.016.56 56.316.37 70.516.33 46.615.62 Zn-65

<3.14

<2.91

<2.25

<2.71

<3.32

<2.17 Cs-134

<0.87

<0.90

<0.88

<0.91

<0.98

<0.74 Cs-137

<1.03

<0.80

<0.90

<0.99

<0.80

<0.72 Zr-95

<2.85

<2.13

<2.80

<1.74

<2.57

<2.12 Nb-95

<1.00

<1.56

<1.35

<1.09

<1.35

<1.70 Co-58

<1.23

<0.83

<1.04

<0.98

<1.36

<1.14 Mn-54

<0.79

<0.99

<0.70

<0.87

<1.05

<0.60 Co-60

<1.25

<1.12

<0.98

<0.97

<1.33

<1.30 K-40 7.3214.18 14.614.31 33.115.39

<15.4

<10.6 27.2 5.94 Otherst

<LLD

<LLD o Sample locations Required by Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (Courruuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10 'pCi/m i 1 Sigma NUCLI5_S JULY AUGUST SEPTEEER OCTOBER NOVEEER DiCEMBER i

R5 0FF-SITE COMPOSITE (CONTROL)*

1 Be-7 92.2110.1 94.515.96 96.6i8.33 61.lf6.68 61.0i5.51 41.6i4.46 Zn-65

<5.45

<3.56

<3.54

<2.53

<2.86

<1.96 l

Cs-134

<2.11

<1.08

<1.02

<1.05

<1.26

<0.51 Cs-137

<1.37

<1.35

<0.89

<1.15

<1.24

<0.80 Zr-95

<3.39

<2.79

<2.72

<2.61

<2.43

<1.98 Nb-95

<2.15

<1.87

<1.69

<1.73

<1.75

<1.26 i

Co-58

<2.00

<1.46

<1.26

<1.72

<1.40

<1.03 Mn-54

<1.71

<1.38

<1.48

<1.13

<1.47

<0.84 Co-60

<2.91

<1.62

<1.56

<1.80

<1.21

<0.90 K-40 45.6110.9 46.617.26

<17.7 31.6t7.37 149i10.7 12.li3.79 Otherst

<LLD

~

D2 0FF-SITE COMPOSITE **

Be-7 126i5.46 105i8.96 81.516.25 75.8i7.04 72.316.53 56.3 6.02 Zn-65

<3.04

<3.66

<2.67

<3.93

<2.34

<2.21 Cs-134

<1.50

<1.30

<0.93

<1.18

<1.21

<0.96 Cs-137

<1.20

<1.35

<1.09

<1.08

<1.17

<0.93 Zr-95

<3.12

<3.59

<2.57

<2.04

<2.29

<2.35 Nb-95

<2.59

<2.15

<1.63

<0.76

<1.62

<1.40 Co-58

<1.55

<1.44

<1.41

<1.31

<1.37

<1.43 Mn-54

<1.52

<1.36

<1.27

<0.94

<1.23

<1.07 Co-6J

<1.75

<1.54

<1.33

<1.66

<1.22

<1.25 K-40 53.517.28 53.728.74 14519.48

<11.3

<8.44 47.2i7.26

<LLD

<LLD ye; st Sample Locations Required by Technical Specifications.

o m Optional Sample Location. N_ot Required By the Technical Specifications.

? Plant Related Radionuclides.

TABLE 6-9 (cennuuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10 'pCi/m 11 Sigma 3

NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER E OFF-SITE COMPOSITE **

8e-7 11319.22 79.0 10.1 76.916.44 70.5 6.61 72.4*7.14 42.4i5.19 Zn-65

<2.97

<3.87

<2.44

<2.02

<2.95

<3.04 Cs-134

<1.36

<1.39

<1.06

<1.09

<0.92

<0.71 Cs-137

<1.38

<1.82

<0.76

<1.41

<1.09

<0.88 Zr-95

<2.44

<3.88

<2.10

<2.56

<2.46

<2.15 Nb-95

<1.77

<2.75

<1.21

<1.93

<2.07

<0.73 Co-58

<1.25

<2.06

<1.13

<1.59

<1.44

<0.85 Mn-54

<1.66

<1.41

<0.98

<1.42

<1.22

<0.92

?

Co-60

<1.86

<2.06

<1.21

<1.54

<1.44

<1.21 O

K-40 46.618.82 31.018.61 9.8513.28 53.618.75 47.018.74 6.52i3.73 Otherst

<LLD

<LLD F 0FF-SITE COMPOSITE **

Be-7 87.816.91 54.215.95 67.415.38 48.6i7.43 52.2i6.26 49.7i6.83 Zn-65

<2.87

<2.89

<1.99

<3.27

<3.62

<3.78 Cs-134

<0.83

<0.93

<0.84

<1.16

<1.05

<1.51 Cs-137

<1.15

<1.03

<0.92

<1.39

<1.31

<1.29 Zr-95

<1.95

<2.25

<1.82

<3.49

<2.19

<2.69 Nb-95

<1.33

<1.99

<1.31

<2.40

<1.37

<1.88 Co-58

<1.00

<1.44

<1.08

<1.68

<0.97

<1.65 Mn-54

<1.08

<1.27

<0.95

<1.13

<1.23

<1.65 Co-60

<1.32

<1.24

<1.04

<1.80

<0.86

<2.00 K-40 6.60t3.30 14919.95 6.23i3.56 51.919.22

<10.5 27.8 6.95 Otherst

<LLD

Optional Sample Location. NM Required by the Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (ConTrnuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10' pCi/m' i 1 Sigma NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER G 0FF-SITE COMPOSITE **

Be-7 88.919.44 90.118.24 10917.33 56.3i6.37 80.7 7.16 46.615.61 Zn-05

<3.33

<3.37

<2.53

<3.31

<3.14

<2.74 Cs-134

<1.49

<0.99

<0.84

<0.91

<1.13

<0.84 Cs-137

<1.57

<1.11

<0.93

<0.99

<1.28

<0.95 Zr-95

<3.04

<2.79

<2.51

<2.00

<2.89

<2.43

?

Nb-95

<2.73

<1.57

<1.49

<1.59

<1.57

<1.41 O

Co-58

<2.29

<1.74

<1.28

<1.62

<1.55

<1.35 Mn-54

<1.99

<1.12

<1.10

<0.92

<1.41

<1.14 Co-50

<1.76

<1.36

<1.42

<0.78

<1.41

<1.55 K-40 42.0i9.13 44.816.90 44.6*7.28

<14.3 42.6*7.65 33.3i6.31 Otherst

<LLD

<LLD 0* Optional Sample Location. N_ot Required by the Technical Specifications.

t Plant Related Radionuclides.

TABLE 6-9 (Courruuso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10pCi/m i 1 Sigma 3

NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER D1 ON-SITE COMPOSITE **

Be-7 107f8.69 57.4i7.56 10017.59 74.219.00 58.9 6.37 50.715.2 Zn-65

<3.10

<4.17

<2.74

<2.19

<4.13

<2.70 Cs-134

<1.28

<1.67

<1.09

<1.62

<1.60

<0.94 Cs-137

<1.17

<1.38

<0.80

<1.51

<1.41

<1.08 Zr-95

<3.21

<3.64

<2.36

<3.07

<3.11

<1.64 Nb-95

<1.68

<2.63

<1.94

<2.59

<1.84

<1.47 Co-58

<1.52

<2.03

<1.26

<1.99

<1.69

<0.79 Mn-54

<1.53

<1.64

<0.93

<1.91

<1.64

<1.08

?

Co-60

<1.86

<1.89

<1.45

<1.97

<1.26

<1.28 K-40 46.118.27 27.918.71 43.8t7.46 21.118.78 179il2.9 15.014.2 Otherst

<LLD

<LLD G ON-SITE COMPOSITE **

Be-7 97.7i7.95 80.3i7.51 98.9i9.57 70.516.61 66.4i6.17 61.9i6.38 Zn-65

<3.12

<3.11

<3.28

<3.39

<3.27

<2.70 Cs-134

<1.05

<1.11

<1.45

<1.08

<1.25

<1.19 Cs-137

<1.11

<0.89

<1.33

<1.39

<1.26

<0.91 Zr-95

<2.83

<3.17

<3.20

<2.60

<2.85

<2.51 Nb-95

<1.55

<2.27

<1.83

<2.15

<2.21

<1.86 Co-58

<1.14

<1.45

<1.78

<1.57

<1.42

<1.34 Mn-54

<1.04

<0.99

<1.56

<1.48

<1.43

<1.50 Co-60

<1.76

<1.74

<1.60

<1.45

<1.59

<1.61 K-40 8.81i5.04

<18.1 36.8i8.49 165t11.6 140110.4 42.4t7.41 Otherst

<LLD

Optional Sample Location. Eot Required by the Technical Specifications.

t Plant Related Radionuclides.

l TABLE 6-9 (Cent 1suso)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10'3pCi/m i 1 Sigma NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER H ON-SITE COMPOSITE **

l Be-7 84.lt10.6 68.318.99 67.016.09 65.5 6.13 77.316.45 52.7i7.18 l

Zn-65

<4.89

<4.97

<2.24

<2.79

<3.43

<3.23 Cs-134

<1.41

<1.99

<1.13

<1.00

<0.85

<1.07 Cs-137

<1.69

<1.65

<1.01

<1.14

<0.77

<0.93 Zr-95

<4.65

<4.34

<1.70

<2.61

<2.32

<2.70 Nb-95

<2.91

<3.13

<1.55

<1.63

<1.42

<2.20 Co-58

<1.95

<2.41

<1.43

<1.52

<1.26

<1.31 Mn-54

<2.03

<1.95

<1.24

<1.27

<1.08

<1.03

?

Co-60

<2.81

<2.25

<1.05

<1.40

<1.27

<1.55 d

K-40 16.3i8.17 33.2 10.4 46.017.82

<13.6

<12.4

<11.7 Otherst

<LLD

<LLD I ON-SITE COMPOSITE **

Be-7 95.318.44 92.018.10 92.418.65 56.316.37 65.318.46 67.119.05 Zn-65

<4.10

<3.24

<2.35

<3.81

<4.59

<4.52 Cs-134

<1.39

<1.15

<0.91

<1.55

<1.71 Cs-137

<1.26

<0.86

<1.41

<0.99

<1.43

<1.53 Zr-95

<2.70

<2.42

<3.03

<2.36

<3.46

<3.63 Nb-95

<2.41

<1.99

<1.91

<1.51

<2.15

<2.E9 Co-58

<1.62

<1.70

<2.04

<1.73

<1.78

<1.88 Hn-54

<1.34

<1.24

<1.31

<1.38

<1.96

<1.72 Co-60

<1.30

<1.61

<1.65

<1.15

<2.02

<1.66 l

K-40

<15.2

<11.3 16.2i7.36 68.8i9.82

<19.0

<12.4 I

Otherst

<LLD

Optional Sample Location. !Lo_t Required by the Technical Specifications.

t Plant Related Radionuclides.

l

TABLE 6-9 (Contruuto)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1995 Results in Units of 10' pCi/m 2 Sigma NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER J ON-SITE COMPOSITE **

Be-7 94.019.70 79.li7.69 80.516.52 58.913.54 81.4*7.03 48.8i4.88 Zn-65

<1.21

<3.07

<2.83

<3.28

<1.66

<1.89 Cs-134

<1.36

<1.13

<1.08

<1.11

<1.08

<0.78 Cs-137

<1.08

<1.15

<1.21

<0.84

<1.31

<0.69 Zr-95

<2.83

<2.68

<2.49

<2.44

<2.71

<2.00 Nb-95

<1.39

<2.27

<1.93

<1.97

<1.82

<1.18 Co-58

<2.16

<1.48

<1.34

<1.09

<1.17

.0.93 Mn-54

<1.70

<1.06

<1.10

<1.25

<0.76

?

Co-60

<1.21

<1.48

<1.17

<1.44

<1.66

<1.13 K-40 22.li6.80 42.li7.96 13919.32 19.2i5.06 149i10.7 9.9113.05 Otherst

<LLD

<lLD

<LLD

<LLD K ON-SITE COMPOSITE **

Be-7 10718.07 77.716.88 89.416.85 64.616.32 67.216.30 54.915.97 Zn-65

<2.07

<3.60

<2.65

<2.97

<1.51

<2.70 Cs-134

<1.16

<0.86

<0.87

<0.99

<1.42

<1.10 Cs-137

<1.01

<0.95

<0.81

<0.89

<1.30

<0.75 Zr-95

<2.79

<2.77

<1.54

<2.38

<2.53

<2.10 Nb-95

<1.86

<1.91

<1.52

<1.20

<1.68

<1.37 Co-58

<1.12

<1.42

<0.96

<1.37

<1.54

<1.34 Mn-54

<1.18

<1.17

<0.88

<1.08

<1.71

<1.13 Co-60

<1.08

<1.15

<0.92

<0.79

<1.51

<1.22 K-40

<13.6

<17.4 7.29i3.64 14.413.85 150i10.4 37.6i6.69 Otherst

<LLD

<LLD Co Optional Sample Location. Not Required by the Technical Specifications.

t Plant Related RadionucI! des.

TABLE 6-10 DIRECT RADIATION MEASUREMENT RESULTS (1995)

Results in Units of mrem /std. Month

i Sigma STATION FIRST SECOND THIRD FOURTH LOCATION (DI AN AND NUMBER QUARTER QUARTER QUARTER QUARTER DIRECTION)**

3 D1 On-site 4.2i0.2 16.6tl.4 24.9tl.1 28.612.8 0.2 miles @ 69 4

D2 On-site 4.210.3 5.3i0.1 5.510.1 5.1 0.2 0.4 miles @ 140 5

E On-site 4.010.2 5.010.1 5.010.3 4.3i0.2 0.4 miles @ 175 6

F On-site 3.5i0.3 4.610.4 4.610.2 3.710.3 0.5 miles @ 210 7*

G On-site 3.5i0.3 3.910.3 4.410.2 3.8 0.3 0.7 miles @ 250 8

R-5 Off-site Control 4.410.1 5.4i0.3 5.7f0.2 5.010.3 16.4 miles @ 42 9

D1 Off-site 4.0i0.2 4.310.3 4.420.2 3.910.2 11.4 miles @ 80 10 D2 Off-site 4.110.3 4.3i0.4 4.510.4 4.210.2 9.0 miles @ 117 11 E Off-site 3.910.1 4.510.2 4.4 0.3 4.0i0.2 7.2 miles @ 160 12 F Off-site 4.010.2 4.410.3 4.610.3 3.9 0.2 7.7 miles @ 190 13 G Off-site 4.3i0.2 4.7i0.2 4.710.4 4.3i0.0 5.3 miles @ 225

?

14* lDe!' ass Rd., SW Oswego-Control 4.2i0.2 4.910.4 4.9i0.3 4.410.2 12.6 miles @ 226 5

15* iPole 6i, W. Boundary-Bible Camp 3.910.2 3.910.2 4.010.2 3.9i0.2 0.9 miles @ 237' 18*

Energy Info. Center-Lamp Post, SW 4.4i0.2 5.010.3 4.9i0.5 4.5i0.2 0.4 miles @ 265 19 East Bou,':dary-JAF, Pole 9 4.410.2 4.810.2 4.910.3 4.610.3 1.3 miles @ 81 23*

H On-site 4.6i0.2 5.3i0.3 6.010.4 6.1i0.4 0.8 miler @ 70 24 I On-site 4.120.1 4.810.3 5.3i0.3 5.010.2 0.8 miles @ 98 25 J On-site 4.410.1 4.7i0.3 4.9i0.2 4.5i0.1 0.9 miles @ 110 26 K On-site 4.110.2 4.7i0.4 5.010.2 4.410.4 0.5 miles @ 132 27 N. Fence, N. of Switchyard, JAF 4.8i0.2 23.li0.6 44.li2.3 51.3i3.4 0.4 miles @ 60 28 N. Light Pole, N. of Screenhouse, 15.611.0 31.412.0 52.4i3.7 59.914.9 0.5 miles @ 68 JAF 29 N. Fence, N. of W. Side 7.8+0.5 30.0i2.6 49.814.7 65.0i5.1 0.5 miles @ 65 30 N. Fence (NW) JAF 4.0i0.1 19.3tl.1 32.512.7 28.9il.7 0.4 miles @ 57 31 N. Fence (NW) NMP-1 5.910.2 6.1 0.3 6.4i0.2 7.010.4 0.2 miles @ 276 39 N. Fence, Rad. Waste-NMP-1 8.3i0.7 8.0 0.4 8.610.3 9.5i0.4 0.2 miles @ 292 47 N. Fence, (NE) JAF 4.210.2 7.410.6 10.811.0 11.8i0.6 0.6 miles @ 69 49*

Phoenix, NY-Control 3.410.0 4.010.2 4.310.3 3.810.2 19.8 miles @ 170 51 Liberty & Bronson Sts.. E of OSS 4.0i0.2 4.5i0.1 4.610.4 4.510.5 7.4 miles @ 233 52 East 12th & Cayuga Sts., Oswego 3.910.2 4.310.2 4.li0.3 4.410.2 5.8 miles @ 227 School

~

TAKEET-10 TCONTINUED)

DIRECT RADIATION MEASUREMENT'RESULTS (1995)

Results in Units of mrem /std. Month i 1 Sicma STATION FIRST SECOND THIRD FOURTH LOCATION (DI AND NUMBER QUARTER QUARTER QUARTER QUARTER DIRECTION)**

53 Broadwell & Chestnut Sts. -

4.010.3 4.710.3 4.610.3 4.810.1 13.7 miles @ 183 Fulton H.S.

54 Liberty St. & Co. Rt. 16 -

3.810.1 4.510.3 3.910.3 4.010.2 9.3 miles @ 115 Mexico H.S.

55 Gas Substation Co. Rt. 5-Pulaski 3.6i0.1 4.410.2 4.3i0.1 4.210.2 13.0 miles @ 75 56*

Rt. 104-New Haven SCH.(SE Corner) 3.910.2 4.510.1 4.610.4 4.4i0.2 5.3 miles @ 123 58*

Co. Rt. lA-Alcan (E. of E.

3.910.2 4.510.1 4.210.1 4.210.2 3.1 miles @ 220 Entrance Rd.)

75*

Unit 2. N. Fence, N. of Reactor 5.210.5 6.8 0.4 6.7i0.3 6.910.3 0.1 miles @

5 Bldg.

76*

Unit 2 N. Fence, N. of Change 4.510.2 5.3i0.6 6.li0.2 6.310.4 0.1 miles @ 25

?

House M

77*

Unit 2 N. Fence, N. of Pipe Bldg.

5.010.2 6.910.2 8.010.5 8.3i0.3 0.2 miles @ 45 78*

JAF E. of E. Old Lay Down Area 4.110.2 5.010.3 5.0i0.2 1.0 miles @ 90 79*

Co. Rt. 29 Pole #63, 0.2 mi. S.

3.6i0.1 4.5i0.0 4.610.1 4.210.1 1.1 miles @ 115 of Lake Rd.

80*

Co. Rt. 29, Pole #54, 0.7 mi. S.

3.9i0.1 4.410.3 5.li0.3 4.210.2 1.4 miles @ 133 of Lake Rd.

81*

Miner Rd., Pole #16, 0.5 mi. W.

4.010.3 4.410.1 4.510.2 4.310.3 1.6 miles @ 159 of Rt. 29 82*

Miner Rd., Pole #1 1/2,1.1 mi.

3.810.2 4.4 0.1 4.5i0.1 4.1i0.1 1.6 miles @ 181 W. of Rt. 29 83*

Lakeview Rd., Tree 0.45 mi. N. of 4.li0.2 4.5i0.2 5.110.3 4.4i0.3 1.2 miles @ 200 Miner Rd.

84*

Lakeview Rd., N., Pole #6117, 4.110.2 4.7i0.1 4.6i0.3 4.6i0.3 1.1 miles @ 225 200 ft. N. of Lake Rd.

85*

Unit 1. N. Fence N. of W. Side 9.610.5 9.010.6 9.li0.3 8.310.4 0.2 miles @ 294 of Screen House 86*

Unit 2 N. Fence. N. of W. Side 5.910.5 6.310.2 6.9i0.4 7.2i0.3 0.1 miles @ 315 of Screen House

TABLE 6-10 (CONTINUED)

DIRECT RADIATION MEASUREMENT-REFULTS (1995)

Results in Units of mrem /std. Month i 1 Sigma STATION FIRST SECOND THIRD FOURTH LOCATION (DI AND NUMBER WARTER

@ARTER

@ARTER WARTER DIRECTION)**

87*

Unit 2. N. Fence, N. of E. Side 5.5 0.2 6.710.4 7.li0.3 6.9i0.3 0.1 miles @ 341 of Screen House 88*

Hickory Grove Rd., Pole #2. 0.6 4.0i0.3 4.510.3 4.810.4 4.510.1 4.8 miles @ 97 mi. N. of Rt. 1 89*

Leavitt Rd., Pole #16, 0.4 mi. S.

4.0i0.4 4.910.2 5.010.2 4.410.3 4.1 miles @ 111 of Rt. 1 90*

Rt.104 Pole #300,150 Ft. E.

3.610.3 4.2i0.2 4.510.3 4.2i0.2 4.2 miles @ 135 of Keefe Rd.

91*

Rt. 51A, Pole #59, 0.8 mi. W.

3.210.2 4.li0.2 4.li0.4 4.010.1 4.8 miles @ 156 of Rt. 51 92*

Maiden Lane Rd., Power Pole. 0.6 4.010.4 5.210.3 5.0i0.2 4.7i0.2 4.4 miles @ 183

?

mi. S. of Rt. 104 93*

Rt. 53 Pole 1-1, 120 ft. S.

3.710.3 4.3i0.1 4.410.2 4.510.3 4.4 miles @ 205 of Rt.104 94*

Rt. 1. Pole #82, 250 ft. E. of 3.810.4 4.010.2 4.410.2 4.li0.2 4.7 miles @ 223 Kocher Rd. (Co. Rt. #63) 95*

Lakeshore Camp Site, from Alcan 3.410.2 4.010.2 4.410.2 4.2i0.3 4.1 miles @ 237 W. access Rd., Pole #21, 1.2 mi.

N. of Rt. 1 96*

Creamery Rd., 0.3 mi. S. of 3.810.3 4.5i0.3 4.510.3 4.010.2 3.6 miles @ 199 Middle Rd., Pole 1 1/2 97*

Rt. 29. Pole #50, 200 ft. N. of 3.610.1 4.210.1 4.210.4 4.010.3 1.8 miles @ 143 Miner Rd.

98*

Lake Rd., Pole #145, 0.15 mi.

4.110.3 4.6i0.2 4.810.4 4.3i0.5 1.2 miles @ 101 E. of Rt. 29 99*

NMP Rd., 0.4 mi. N. of Lake Rd.,

3.8 0.3 4.610.3 5.110.3 4.410.2 1.8 miles @ 88 Env. Station R1 Off-site 100*

Rt. 29 and Lake Rd., Env. Station 3.810.2 4.710.5 4.6i0.3 4.5i0.2 1.1 miles @ 104 R2 Off-site 101*

Rt. 29, 0.7 mi. S. of Lake Rd.,

3.310.2 4.210.1 4.4 0.3 4.0i0.2 1.5 miles @ 132 f

Env. Station R3 Off-site

__s

\\

TABLE 6-10 (CONTINUED)

DIRECT RADIATICA MEASUREMENT RESULTS (1995)

Results in Units of mrem /std. Month i 1 Sigma SlATION FIRST SECOND THIRD FOURTH LOCATION (DI AN AND NUEER

@ARTER

@ARTER WARTER

@ARTER DIRECTION)**

102 EOF /Env. Lab. Oswego Co. Airport 3.4i0.2 4.410.3 4.6i0.4 4.210.3 11.9 miles @ 175 (Fulton Airport, Rt.176) E.

Driveway, Lamp Post 103 EIC East Garage Rd., Lamp Post R3 3.910.1 4.7i0.2 5.210.4 4.7i0.1 0.4 miles @ 267 Off-site 104 Parkhurst Road, Pole #1481/2-A, 3.Si0.2 4.410.2 4.5i0.3 4.0i0.2 1.4 miles @ 102 0.1 miles South of Lake Rd.

105 Lakeview Rd., Pole #6125, 0.6 mi.

3.610.2 4.720.3 4.6i0.2 1.4 miles @ 198 e

South of Lake Road 8

106 Shoreline Cove, West of NMP-1, 4.310.2 5.410.2 5.710.3 5.310.1 0.3 miles @ 274 Tree on West Edge 107 Shoreline Cove, West of NMP-1 4.5i0.4 5.410.3 6.0i0.3 5.510.2 0.3 miles @ 272

?M Lake Road, Pole #142, 300 ft. East 4.010.3 4.810.3 5.010.4 4.710.2 1.1 miles @ 104 of Rt. 29 S.

109 Tree North of Lake Road, 300 ft.

3.7i0.3 4.3i0.2 4.510.2 4.3i0.3 1.1 miles @ 103 East of Route 29 N.

111 Sterling, NY 3.510.3 4.210.3 4.510.3 4.3i0.2 26.4 miles @ 166 112 EOF /Env. Lab. Oswego Co. Airport 4.110.5 4.2i0.2 4.410.3 4.010.2 11.9 miles @ 175*

113 Control, Baldwinsville, NY 3.810.3 4.2i0.3 4.7i0.2 4.3i0.3 21.8 miles @ 214 Technical Specification Location Sirection and distance based on NMP-2 reactor centerline and sixteen 22.5 degree sector grid.

TLD lost in field

TABLE 6-11 CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK Results in Units of pCi/ liter 1 Sigma SAMPLE LOCATION NO. 60 CO CTION I-131 K 40 Cs-134 Cs-137 Ba/La-40 OT11ERS*

04/02/95

<0.29 1560175

<3.87

<5.41

<7.75 LLD i

04/17/95

<0.28 1640178

<6.89

<4.96

<6.07 LLD 05/01/95

<0.43 1400172

<5.41

<6.44

<8.03 LLD 05/22/95

<0.44 1710173

<4.83

<5.53

<6.98 LLD 06/05/95

<0.39 1580185

<8.04

<8.38

<8.00 LLD 06/19/95

<0.42 1450164

<5.84

<5.73

<5.58 LLD 07/09/95

<0.41 1620175

<4.45

<5.37

<7.16 LLD 07/23/95

<0.30 1620198

<7.10

<9.08

<8.97 LLD 08/06/95

<0.30 1640198

<7.22

<9.63

<]2.0 LLD 08/20/95

<0.55 1543 67

<3.80

<5.46

<5.78 LLD 09/05/95

<0.40 1647142

<5.37

<5.61

<5.07 LLD 09/17/95

<0.41 1470164

<5.71

<4.89

<7.39 LLD 10/01/95

<0.29 2060159

<5.79

<5.54

<5.64 LLD 10/15/95

<0.28 1500i72

<5.34

<6.65

<7.70 LLD 11/06/95

<0.40 2300164

<5.61

<5.54

<5.13 LLD 11/20/95

<0.25 2270 62

<3.51

<5.87

<5.99 LLD 12/04/95

<0.40 1380172

<3.87

<6.19

<6.58 LLD 12/18/95

<0.30 1460164

<5.25

<4.99

<6.21 LLD SAMPLE LOCATION NO. 55 C0 IM I-131 K-40 Cs-134 Cs-137 Ba/La-40 OlliERS*

04/03/95

<0.37 1730170

<5.50

<6.04

<6.27 LLD 04/17/95

<0.38 1650170

<5.15

<4.63

<7.45 LLD 05/01/95

<0.47 2310165

<4.94

<5.68

<6.31 LLD 05/22/95

<0.28 1450t72

<4.80

<6.25

<7.36 LLD 06/05/95

<0.38 1390193

<9.60

<8.70

<11.5 LLD 06/19/95

<0.28 1640170

<5.85

<3.63

<4.75 LLD 07/10/95

<0.37 1390172

<5.03

<6.75

<8.07 LLD 07/24/95

<0.37 1550167

<4.82

<5.72

<6.35 LLD 08/07/95

<0.39 1340172

<5.70

<6.44

<7.60 LLD 08/21/95

<0.43 1590170

<5.53

<5.15

<5.40 LLD 09/05/95

<0.31 1650170

<5.74

<5.88

<6.21 LLD 09/18/95

<0.49 1410172

<5.12

<6.04

<8.20 LLD 10/02/95

<0.39 1400192

<8.41

<7.23

<11.5 LLD 10/16/95

<0.34 1640170

<5.48

<5.78

<7.01 LLD 11/06/95

<0.38 1460i75

<5.11

<5.67

<6.62 LLD 11/20/95

<0.40 1470164

<6.28

<4.97

<6.66 LLD 12/04/95

<0.36 1700170

<5.15

<4.49

<6.48 LLD 12/18/95

<0.40 1620198

<8.74

<8.59

<13.8 LLD 6-41

TABLE 6-11 (ConTrnuso)

CONCENTRATIONS OF 10 DINE-131 AND GAMMA EMITTERS IN MILK Results in Units of pCi/ liter i 1 Sigma SAMPLE LOCATION N0. 50 COL CTION I-131 K-40 Cs 134 Cs-137 Ba/La-40 OTHERS*

04/02/95

<0.38 1500164

<5.71

<5.49

<7.18 LLD 04/17/95

<0.37 1490167

<6.89

<4.96

<6.07 LLD 05/01/95

<0.29 1510164

<3.65

<5.46

<4.75 LLD 05/22/95

<0.31 1560167

<5.59

<4.82

<5.94 LLD 06/05/95

<0.28 1440172

<5.56

<6.12

<6.32 LLD 06/19/95

<0.38 1720189

<5.32

<,.52

<9.23 LLD 07/09/95

<0.36 1520167

<6.02

<4.41

<5.10 LLD 07/23/95

<0.40 1560167

<5.84

<4.89

<?.C3 LLD 08/06/95

<0.38 1590167

<5.75

<5.12

<5.06 LLD 08/20/95

<0.45 1440i72

<4.80

<6.00

<7.65 LLD 09/05/95

<0.44 1580167

<5.32

<5.33

<7.46 LLD 09/17/95

<0.47 1490164

<4.02

<5.33

<7.44 LLD 10/01/95

<0.40 1490167

<5.75

<5.79

<5.62 LLD 10/15/95

<0.36 1530167

<5.26

<5.53

<5.87 LLD 11/06/95

<0.35 1770i73

<5.24

<5.72

<6.11 LLD 11/20/95

<0.34 1680198

<8.55

<8.23

<9.39 LLD 12/04/95

<0.44 1600167

<3.80

<6.46

<6.71 LLD 12/18/95

<0.38 1500175

<4.62

<5.65

<6.26 LLD SAMPLE LOCATION NO. 4 U N I-131 K-40 Cs-134 Cs-137 Ba/La-40 OTHERS*

TE 04/03/95

<0.43 1580198

<8.18

<9.73

<12.7 LLD 04/17/95

<0.41 1460i92

<9.35

<7.93

<11.7 LLD 05/01/95

<0.53 1660185

<8.32

<7.95

<7.66 LLD 05/22/95

<0.38 1420i72

<5.27

<6.75

<8.38 LLD 06/05/95

<0.47 2370165

<4.86

<5.87

<5.56 LLD 06/19/95

<0.52 1420172

<5.34

<5.11

<5.32 LLD 07/10/95

<0.38 1760189

<7.64

<8.23

<7.26 LLD 07/24/95

<0.48 1850189

<7.04

<6.20

<7.31 LLD 08/07/95

<0.44 1700189

<6.44

<7.71

<7.34 LLD 08/21/95

<0.54 1470198

<9.35

<8.30

<12.4 LLD 09/05/95

<0.50 2280162

<5.12

<5.93

<4.52 LLD 09/18/95

<0.29 2280162

<3.80

<6.32

<4.60 LLD 10/02/95

<0.46 1510175

<5.34

<5.97

<8.09 LLD 10/16/95

<0.42 1640192

<10.2

<7.36

<11.9 LLD 11/06/95

<0.29 1670170

<6.37

<5.73

<7.07 LLD 11/20/95

<0.33 1440172

<3.29

<5.77

<8.88 LLD 12/04/95

<0.30 1630198

<7.09

<7.93

<13.5 LLD 12/17/95

<0.49 1760i73

<5.11

<5.15

<6.51 LLD 6-42

TABLE 6-11 (CONTINUED) 1 CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK Results in Units of pCi/ liter i 1 Sigma SAMPLE LOCATION N0. 73 (Control)

COL I-131 K-40 Cs 134 Cs-137 Ba/La-40 OTHERS*'

E 04/03/95

<0.40 1640185

<7.92

<6.84

<8.19 LLD 04/17/95

<0.47 1700189

<6.94

<8.48

<7.65 LLD 05/01/95

<0.40 1540198

<8.83

<8.55

<10.7 LLD 05/22/95

<0.47 1570167

<4.88

<5.60

<6.10 LLD 06/05/95

<0.50 1320162

<5.41

<5.40

<5.16 LLD 06/19/95

<0.37 2380165

<3.96

<5.36

<4.94 LLD 07/10/95

<0.29 2430167

<5.15

<5.38

<4.53 LLD 07/24/95

<0.41 2280165

<5.18

<5.12

<6.10 LLD 08/07/95

<0.39 1690170

<5.37

<6,34

<3.52 LLD 08/21/95

<0.52 1860158

<4.14

<5.20

<4.78 LLD 09/05/95

<0.48 1540193

<8.96

<7.86

<10.6 LLD 09/18/95

<0.38 1510198

<7.35

<6.91

<9.90 LLD 10/02/95

<0.48 1630170

<4.63

<5.27

<5.46 LLD 10/16/95

<0.43 2290162

<3.37

<5.43

<5.21 LLD 11/06/95

<0.45 1460165

<3.41

<5.73

<5.61 LLD 11/20/95

<0.41 1320172

<4.36

<5.53

<7.56 LLD 12/04/95

<0.43 2200161

<4.83

<5.78

<4.71 LLD i

12/17/95

<0.34 2050 59

<3.83

<4.84

<4.77 LLD

\\

l 6-43

1 TABLE 6-12 MILK ANIMAL CENSUS 1995 NVIEER ON )

NUMBER TOWN OR AREA (a)

CENSUS MAPCl DEGREES (2) DISTANCE (2) 0F MILK ANIMALS Scriba 16*

190 5.9 miles NONE 3

190 4.5 3C 6

162 2.2 NONE 26 114 1.5 NONE 61 140 3.0 NONE 62 183 6.7 1G (2) 63 185 8.0 3C 74 194 6.5 5C New Haven 9

95 5.2 40C 4*

113 7.8 100C 45 125 8.0 NONE 10 130 2.6 NONE 5

146 7.2 3C 11 130 8.5 NONE 7*

107 5.5 NONE 64 107 7.9 52C 71 111 4.2 NONE Mexico 72t 98 9.9 30C 12 107 11.5 22C 14 120 9.8 56C 17 115#

10.2 1C 19 132 10.5 40C 60*

90 9.5 40C 50*

93 8.2 165C 55*

95 9.2 56C 21 112 10.5 70C 49 88 7.9 6G Richland 22 85 10.2 47C Pulaski 23 92 10.5 NONE 68 85 11.5 70C 6-44

TABLE 6-12 (courznuso)

MILK ANIMAL CENSUS 1995 NUMBER ON )

NUMBER TOWN OR AREA (a)

CENSUS MAPCl DEGREES (2) DISTANCE (2) 0F HILK ANIMALS Sterling 73**

234 13.2 miles 41C Volney 25 182 9.5 NONE 70 147 9.4 33C 66 156 7.8 60C MILKING ANIMAL TOTALS:

964 Cows (including control locations) 7 Goats MILKING ANIMAL TOTALS:

923 Cows (excluding control locations) 7 Goats C = Cows G = Goats

= Milk sample location

- = Milk sample control location ND = Did not wish to participate in the survey (1) = References Section 3.3 (2) = Based on Nine Mile Point Unit 2 Reactor Centerline NONE = No cows or goats at that location.

Location was a previous location with cows and/or goats.

(a) = Census performed out to a distance of approximately ten miles.

(b) = As of August 2,1993 a new control location was added to the REMP.

6-45

-- 1

IABLL D-J.S CONCENTRATIONS OF GAMMA EMITTERS IN VARIOUS FOOD PRODUCTS Results in Units of pCi/g (wet) i 1 Sigma COLLECTION SAMPLE SITE DATE DESCRIPTION Be-7 K-40 I-131 Cs-134 Cs-137 Zn-65 CABBAGE LEAVES 0.1410.022 2.22i0.088

<0.008

<0.007

<0.009

<0.024 Q*

9/95 SQUASH LEAVES 0.0710.040 3.2910.116

<0.010

<0.009

<0.030 CUCUMBER LEAVES 1.05i0.063 4.35i0.071

<0.010

<0.006 0.01110.002

<0.021 PEPPER LEAVES 0.44i0.029 8.4610.120

<0.010

<0.006

<0.016 K*

9/95 SQUASH LEAVES 1.5910.028 3.6310.056

<0.009

<0.005 0.012i0.002

<0.021 T0 MAT 0E

<0.048 2.92i0.074

<0.007

<0.005

<0.014 GRAPES LEAVES 1.1810.034 1.13i0.052

<0.007

<0.006

<0.013 L

9/95 SQUASH LEAVES 1.70f0.047 3.4510.098

<0.008

<0.005

<0.007

<0.021 CUCUMBER LEAVES 1.9310.066 2.63i0.121

<0.010

<0.011

<0.012

<0.032 SWISS CHARD 0.12i0.024 5.9810.095

<0.010

<0.005

<0.008

<0.014 R

9/95 SQUASH LEAVES 1.23i0.040 3.2110.088

<0.013

<0.005

<0.007

<0.020 COLLARD LEAVES

<0.064 5.9610.100

<0.015

<0.006

<0.008

<0.012 KALE LEAVES

<0.014 5.1710.200

<0.023

<0.016

<0.050 SQUASH LEAVES 1.04i0.042 2.93i0.106

<0.007

<0.008

<0.022 S

9/95 PEPPER LEAVES 0.4310.034 5.93i0.148

<0.009

<0.032 T0MATOE

<0.047 2.53i0.072

<0.005

<0.014 PUMPKIN LEAVES 1.3910.061 2.2810.115

<0.010

<0.012

<0.010

<0.031 GRAPE LEAVES 1.08t0.037 2.21i0.082

<0.006

<0.005

<0.007

<0.020 SQUASH LEAVES 1.3710.068 3.8510.168

<0.010

<0.016

<0.013

<0.042 M*

9/95 CUCUMBER LEAVES 1.4010.047 2.4710.095 en.009

<0.008

<0.024 (CONTROL)

PEPPER LEAVES 0.5210.029 10.610.123

<0.010

<0.006

<0.008

<0.016 T0 MAT 0ES

<0.036 2.76i0.055

<0.006

<0.005

<0.012 PUMPKIN LEAVES 0.8810.031 3.52i0.084

<0.008

<0.004

<0.006

<0.017 NOTE: Other Plant Related Radionuclides <LLD Samples required by Technical Specifications

l TABLE 6-14 i

1995 RESIDENCE CENSUS HAP METER 0 LOGICAL l

l LOCATION DESIGNATION (b)

SECTOR DEGREES (')

DISTANCE (*)

w N

l w

NNE w

NE 1

ENE w

Sunset Bay A

E 82 0.9 miles Lake Road B

ESE 119 0.7 miles Parkhurst Road C

SE 127 1.2 miles l

County Route 29 D

SSE 149 1.2 miles Miner Road E

S 173 1.6 miles Lakeview Road F

SSW 210 1.7 miles Lakeview Road G

SW 233 1.5 miles Bible Camp Retreat H

WSW 249 1.3 miles W

W l

l w

WNW w

NW w

NNW l

l l

w This meteorological sector is over Lake Ontario. There are no residences within three miles.

l

'" Based on J.A. FitzPatrick Nuclear Power Plant Reactor Centerline.

'" See the maps in Section 3.3.

6-47

}

7.0 IIISTORICAL DATA TABLES Sample Statistics from Previous Environmental Samoline The mean, minimum value and maximum value were calculated for selected sample mediums and isotopes.

Special Considerations:

1.

Sample data listed as 1969 was taken from the BIINE MILE POINT.

PREOPERATION SURVEY.

1969 and EHVIRONMENTAL MONITORING REPORT FOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLE AR STATION.

NOVEMBER.1970.

2.

Sample data listed as 1974 and 1978 through 1993 was taken from the respective environmental operating reports for Nine Mile Point Nuclear Station and James A. FitzPatrick Nuclear Power Plant.

3.

Only measured values were used for statistical calculations.

4.

The term MDL was used prior to 1979 to represent the concept of Lower Limit of Detection (LLD). MDL = Minimum Detectable Level.

7-1

TABLE 7-1 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Results in pCi/g (dry)

LOCATION:

CONTROL *

Isotope-Cs-134 Cs-137 Co Y@ar Hin.

Max.

Mean Hin.

Max.

Mean Hin.

Max.

Mean 1969t 1974t 1975t 1980 1981 1982 1983 1984 1985

<LLD

<LLD 1986

<LLD

<LLD 1987

<LLD

<LLD 1988

<LLD

<LLD 1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD 1992

<LLD

<LLD 1993

<LLD

<LLD 0.027 0.027 0.027

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

<LLD 1

o Langs Beach beyond influence of the site in a westerly direction.

Co No data. Sample not required until new technical specifications implemented in 1985.

t 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-2

TABLE 7-2 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Results in pCi/g (dry)

LOCATION:

INDICATOR'*

Isotope Cs-134

'Cs-137 Co-60

-Year Hin.

Max.

Mean Hin.

Max.

Mean Hin.

Max.

Mean 1%9t 1974t 1975t 1980 1981 1982 1983 1984 l

1985

<LLD

<LLD 1986

<LLD

<LLD 1987

<LLD

<LLD 1988

<LLD

<LLD 1989

<LLD

<LLD 0.25 0.32 0.29

<LLD

<LLD 1990

<LLD

<LLD 0.28 0.30 0.29

<LLD

<LLD 1991

<LLD

<LLD 0.12 0.14 0.13

<LLD

<LLD 1992

<LLD

<LLD 0.12 0.14 0.13

<LLD

<LLD 1993

<LLD

<LLD 0.18 0.46 0.32

<LLD

<LLD 1994

<LLD

<LLD 0.06 0.37 0.22

<LLD

<LLD 1995

<LLD

<LLD 0.14 0.15 0.15

<LLD

<LLD Sunset Beach closest off site location with recreational value.

No data. Sample not required until new technical specifications implemented in 1985.

t 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-3

l TABLE 7-3 1

HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Results in pCi/g (wet)

LOCATION: ' CONTROL *

(Isotope Cs-137 Year Hin.

Max.

Mean 1%9t No Data No Data No Data 1974t 0.94 0.94 0.94 1975t

<MDL

<MDL 1980 0.029 0.110 0.059 1981 0.028 0.062 0.043 1982 0.027 0.055 0.047 1983 0.040 0.060 0.050 1984 0.015 0.038 0.032 1985 0.026 0.047 0.034 1986 0.021 0.032 0.025 1987 0.017 0.040 0.031 1988 0.023 0.053 0.034 1989 0.028 0.043 0.034 1990 0.033 0.079 0.045 1991 0.021 0.034 0.029 1992 0.019 0.026 0.022 1993 0.030 0.036 0.033 1994 0.014 0.031 0.022 1995 0.017 0.023 0.019 o

Control location was at an area beyond the influence of the site (westerly direction).

t 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

7-4 l

TABLE 7-4 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Results in pCi/g (wet)

LOCATION:

INDICATOR * (NMP/JAF)

Isotope Cs-137

. Year Hin.

Max.

Mean i

1969t 0.01 0.13 0.06 1974t 0.08 4.40 0.57 1975t 1.10 1.70 1.38 1976 0

3.90 1.4 1980 0.030 0.100 0.061 1981 0.027 0.10 0.061 1982 0.034 0.064 0.050 1983 0.030 0.060 0.050 1984 0.033 0.061 0.043 1985 0.018 0.045 0.030 1986 0.009 0.051 0.028 1987 0.024 0.063 0.033 1988 0.022 0.054 0.032 1989 0.020 0.044 0.034 1990 0.027 0.093 0.040 1991 0.018 0.045 0.029 1992 0.014 0.030 0.024 1993 0.018 0.035 0.028 1994 0.015 0.023 0.019 1995 0.016 0.022 0.019

Indicator locations are in the general area of the NHP 1 and J.A. FitzPatrick cooling water discharge structures, t 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

7-5

TABLE 7-5 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Results in pCi/ liter LOCATION:

CON 1ROL t Isotope Cs-137 Co-60 Year Hin.

Max.

Mean Hin.

Max.

Mean-1969tt 1974tt j

1975tt 1980

<LLD

<LLD 1981

<LLD

<LLD 1.4 1.4 1.4 1982

<LLD

<LLD 1983

<LLD

<LLD 1984

<LLD

<LLD 1985

<LLD

<LLD 1986

<LLD

<LLD 1987

<LLD

<LLD 1988

<LLD

<LLD 1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD 1992

<LLD

<LLD 1993

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

<LLD o No gama analysis performed (not required).

9 Location was the City of Oswego Water Supply for 1969 - 1984 and the Oswego Steam Station inlet canal for 1985 - 1995.

?? 1969 data is considered to be pre-operational for the site.

1974 and 1975 data is l

considered to be pre-operational for the JAFNPP.

7-6

TABLE 7-6 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Results in pCi/ liter LOCATION:

INDICATOR t

' Isotope Cs-137 Co-C0 1

Year Min.

Max.

Mean Hin.

Max.

~Hean 1969tt 1974tt 1975tt 1980

<LLD

<LLD 1981

<LLD

<LLD 1982 0.43 0.43 0.43 1.6 2.4 1.9 l

1983

<LLD

<LLD 1984

<LLD

<LLD 1985

<LLD

<LLD 1986

<LLD

<LLD 1987

<LLD

<LLD 1988

<LLD

<LLD 1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD 1992

<LLD

<LLD 1993

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

<LLD No gama analysis performed (not required).

t Indicator location was the NMP 1 Inlet Canal for the period 1969 1973, and the JAF Inlet Canal for 1974 - 1995.

tt 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

7-7

TABLE 7-7 l

HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Results in pCi/ liter LOCATION:

CONTROL

Isotope Tritium Year Hin.

Max.

Mean 1969t No Data No Data No Data 1974t

<MDL

<MDL 1975t 311 414 362 1980 211 290 257 1981 211 357 293 1982 112 307 165 1983 230 280 250 1984 190 220 205 1985 230 430 288 1986 250 550 373 1987 140 270 210 1988 240 460 320 1989 143 217 186 1990 260 320 290 1991 180 200 190 1992 190 310 243 1993 160 230 188 1994 250 250 250 1995 230 230 230 0 Control location is the City of Oswego. drinking water for 1969 - 1984 and the Oswego Steam Station inlet canal for 1985 - 1995.

t 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-8

l TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA 1

SURFACE WATER TRITIUM Results in pCi/ liter LOCATION:

INDICATOR

Isotope Tritium

-Year Min.

Max.

Mean 1969t No Data No Data No Data 1974t 380 500 440 1975t 124 482 335 1980 150 457 263 1981 183 388 258 1982 194 2780 641 1983 190 560 317 1984 110 370 282 1985 250 1200**

530 1986 260 500 380 1987 160 410 322 1988 430 480 460 1989 135 288 225 1990 220 290 250 1991 250 390 310 1992 240 300 273 1993 200 280 242 1994 180 260 220 1995 320 320 320 Indicator location was the NMP 1 Inlet Canal during the period 1969 1973, and the JAF Inlet Canal for 1974 1995.

- Suspect sample contamination. Recollected samples showed normal levels of tritium.

t 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

7-9

TABLE 7-9 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Results in pCi/m LOCATION:

C0KIROL

Isotope Gross Beta-Year Min.-

Max.

Mean 1969t 0.130 0.540 0.334 1974t 0.001 0.808 0.121 1975t 0.008 0.294 0.085 1980 0.009 0.291 0.056 1981 0.016 0.549 0.165 1982 0.011 0.078 0.033 1983 0.007 0.085 0.024 1984 0.013 0.051 0.026 1985 0.013 0.043 0.024 1986 0.008 0.272 0.039 1987 0.009 0.037 0.021 1988 0.008 0.039 0.018 1989 0.007 0.039 0.017 1990 0.003 0.027 0.013 1991 0.007 0.028 0.014 1992 0.006 0.020 0.012 1993 0.007 0.022 0.013 1994 0.008 0.025 0.015 1995 0.006 0.023 0.014 o Locations used for 1977 1984 were C off site. D1 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 - 1995 (formerly C off site location).

t 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-10

TABLE 7-10 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA 3

Results in pCi/m l

LOCATION:

INDICATOR *-

. Isotope Gross, Beta Year Hin.

Max.'

Hean 1969t 0.130 0.520 0.320 1974t 0.003 0.885 0.058 1975t 0.001 0.456 0.067 1980 0.002 0.207 0.045 i

1981 0.004 0.528 0.151 1982 0.001 0.113 0.031 i

1983 0.003 0.062 0.023 1984 0.001 0.058 0.025 1985 0.001 0.044 0.021 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 1990 0.006 0.023 0.014 1991 0.006 0.033 0.015 1992 0.005 0.024 0.013 1993 0.005 0.023 0.014 1994 0.006 0.024 0.015 1995 0.004 0.031 0.014 v ma m

Locations used for 1%9 - 1973 were D1 on site. D2 on site. E on-site. F on-s..e and G on site. Locations used for 1974 - 1984 were D1 on-site. D2 on-site. E on-site.

F en-site. G on-site. H on site. I on-site. J on-site and K on site, cs app'. :able.

1985 - 1995 locations were R 1 off-site. R-2 off-site. R-3 off-site. and R 4 off-site.

t 1969 dat0 is considered to be pre operational for the site. 1974 and 1975 dita is considered to be pre-operational for the JAFNPP.

7-11

TABLE 7-11 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES 3

Results in pCi/m LOCATION:

CONTROL **

Isotope Cs-137 Co-60 Y:ar Hin.

Max.

Mean Hin.

Max.

Mean 1%9t 1974t 1975t 1980 0.0015 0.0018 0.0016

<LLD

<LLD 1981 0.0003 0.0042 0.0017 0.0003 0.0012 0.0008 1982 0.0002 0.0009 0.0004 0.0004 0.0007 0.0006 1983 0.0002 0.0002 0.0002 0.0007 0.0007 0.0007 1984

<LLD

<LLD 0.0004 0.0012 0.0008 1985

<LLD

<LLD 1986 0.0075 0.0311 0.0193

<LLD

<LLD 1987

<LLD

<LLD 1988

<LLD

<LLD l

1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD l

1992

<LLD

<LLD 1993

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

No data svailable (not required prior to 1977).

l

- Locations included composites of off site air monitoring locations for 1977 - 1984.

Sample location included only R 5 air monitoring location for 1985 1995.

t 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

7-12

TABLE 7-12 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Results in pCi/m LOCATION:

INDICATOR **

i Isotope Cs-137 Co-60 Year Hin.

Max.

Mean Hin.

Max.

Mean 1969t 1974t 1975t 1980 0.0005 0.0019 0.0011 0.0016 0.0016 0.0016 1981 0.0002 0.0045 0.0014 0.0002 0.0017 0.0006 1982 0.0001 0.0006 0.0004 0.0003 0.0010 0.0005 1983 0.0002 0.0003 0.0002 0.0003 0.0017 0.0007 1984

<LLD

<LLD 0.0007 0.0017 0.0012 1985

<LLD

)

1986 0.0069 0.0364 0.0183

<LLD

<LLD 1987

<LLD

<LLD 1988

<LLD

<LLD 1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD 1992

<LLD

<LLD 1993

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

No data available (not required prior to 1977).

- Locations included composites of on-site air monitoring locations for 1977 - 1984.

Sample locations included R 1 through R 4 air monitoring locations for 1985 - 1995.

t 1969 data is consied to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-13

TABLE 7-13 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADI0 IODINE Results in pCi/m LOCATION:

CONTROL

Isotope Iodine-131 Year Hin..

Max.

Mean 1%9t 1974t p,

1975t

<MDL

<MDL 1980

<LLD

<LLD 1981

<LLD

<LLD 1982 0.039 0.039 0.039 l

1983

<LLD

<LLD 1984

<LLD

<LLD 1985

<LLD

<LLD 1986 0.041 0.332 0,151 1987

<LLD

<LLD 1988

<LLD

<LLD 1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD 1992

<LLD

<LLD 1993

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

<LLD o Locations D1 off-site. D2 off-site. E off-site. F off-site and G off-site used for 1976 1984. Location R-5 off-site used for 1985 - 1995.

N No results I 131 analysis not required.

t 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-14

TABLE 7-14 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADI0 IODINE Results in pCi/m LOCATION:

INDICATOR

Isotope Iodine-131 Year Hin.

Max.

Mean 1969t 1974t 1975t 0.25 0.30 0.28 1980 0.013 0.013 0.013 1981 0.016 0.042 0.029 1982 0.002 0.04?.

0.016 1983 0.022 0.035 0.028 1984

<LLD

<LLD 1985

<LLD

<LLD 1986 0.023 0.360 0.119 1987 0.011 0.018 0.014 1988

<LLD

<LLD 1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD 1992

<LLD

<LLD 1993

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

Locations used for 1976 1984 were D1 on site. D2 on site. E on-site.

F on site. G on-site. H on-site. I on-site. J on site and K on-site. as applicable.

Locations used for 1985 1995 were R-1 off-site. R 2 off-site. R-3 off-site. and R 4 off site.

- No results I-131 analysis not required.

t 1969 data is considered to be pre operat1onal for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

7-15

1 TABLE 7-15A HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem / standard month LOCATION:

C0K!ROL **

Year Hin.

Max.

Mean Preopt 1974t 2.7 8.9 5.6 1975t 4.8 6.0 5.5 1980 3.8 5.8 4.9 1981 3.5 5.9 4.8 1982 3.8 6.1 5.1 1983 4.9 7.2 5.8 1984 4.7 8.2 6.2 l

1985 4.5 7.6 5.6 1986 5.3 7.5 6.3 1987 4.6 6.6 5.4 1988 4.4 6.8 5.6 1989 2.9 6.4 4.7 1990 3.7 6.0 4.7 1991 3.8 5.8 4.7 1992 2.6 5.1 4.1 1993 3.4 5.7 4.4 1994 3.1 5.0 4.1 1995 3.4 5.7 4.4 o Data not available.

TLD #8. 14. 49. 111 established 1985. TLD #113 established 1992.

t 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-16

TABLE 7-15B HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION:

RETS CONTROL **

l Year Hin.

Max.

Mean Preopt 1974t 2.7 8.9 5.6 l

1975t 4.8 6.0 5.5

)

1980 3.8 5.8 4.9 1981 3.5 5.9 4.8 1982 3.8 6.1 5.1 1983 4.9 7.2 5.8 1984 4.7 8.2 6.2 1985 4.4 6.8 5.4 1986 5.5 7.2 6.3 1987 4.6 5.8 5.2 1988 4.8 6.8 5.4 1989 2.9 6.4 4.1 1990 3.7 6.0 4.8 1991 3.8 5.3 4.6 1997.

2.6 4.7 3.9 1993 3.4 5.3 4.4 1994 3.1 4.6 3.9 1995 3.4 4.9 4.2

Data not available, j

- TLD #14 and 49 (RETS Control Locations).

t 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

i i

1 I

7-17

TABLE 7-16A HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION:

SITE B0UNDARY **

. Year Min.

Max.

Mean Preopt 1974t 1975t 1980 1981 1982 1983 1984 1985 4.9(4.1) 5.9(12.6) 5.3(6.2) 1986 5.4(4.4) 6.8(18.7) 5.9(7.0) 1987 4.7(4.4) 5.9(14.3) 5.3(6.1) 1988 5.0(3.4) 6.1(17.9) 5.4(6.4) 1989 4.5(2.8) 5.2(15.4) 4.8(5.9) 1990 4.5(3.6) 5.4(14.9) 4.8(6.4) 1991 4.3(3.2) 5.5(16.7) 4.8(6.0) 1992 3.7(3.2) 4.6(10.4) 4.2(5.1) 1993 3.8(3.3) 4.8(11.7) 4.3(5.4) 1994 2.8(2.8) 4.9(12.4) 4.0(5.2) 1995 3.5(3.5) 5.1(9.6) 4.4(5.4)

Data not available (not required prior to 1985).

TLD locations initiated in 1985 as required by the New Technical Specifications.

Includes TLD numbcrs 7, 18, 78 84 (1985 1995). Sevcr?1 of the site boundary TLDs are in close pro (imity to site operational buildings not generally accessible to the public. and are not representative of the site boundary dose. These locations do not include histo ical data statistics, t 1969 data ds comidered to be pre operational for the site. 1974 and 1975 data is considered to b: Tra operational for the JAFNPP.

( ) Several of the siie boundary TLDs numbers 23.75.76.77.85.86 and 87 are is close proximity to site operaticaai cuildings not generally accessible to the public, the measured doses and are not repic:;cotative of the site boundary dose. The statistics for all the Site Boundary TLDs are noted in the parenthesis.

7-18

TABLE 7-16B 1

HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION:

OFF-SITE SECTORS **

Year Min.

Max.

Mean 4

Preopt 1974t 1975t l

1980 1981 i

1982 1983 j

1984 l

1985 4.0 7.1 5.0 1

l 1986 4.6 8.6 6.0 1987 4.3 6.0 5.2 1988 3.8 7.0 5.3 1989 2.5 6.8 4.9 1990 3.6 6.3 4.7 i

1991 3.6 5.8 4.7 l

1992 2.9 5.0 4.1 1993 3.4 6.3 4.5 1994 3.0 5.1 4.0 1995 3.2 5.2 4.3 Data not available (not required prior to 1985).

TLD locations initiated in 1985 as required by the New Technical Specifications.

Includes TLD numbers 88. 89. 90. 91. 92. 93, 94 and 95.

t 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

7-19

TABLE 7-16C HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION:

SPECIAL INTEREST **

Year Hin.

Max.

Mean-Preopt 1974t 1975t 1980 1981 1982 1983 1984 1985 3.9 6.8 5.3 i

1986 4.8 8.2 6.1 1987 3.5 6.0 5.1 1988 3.9 6.6 5.3 1989 2.1 6.4 4.9 1990 3.2 6.3 4.8 1991 2.9 5.6 4.4 1992 3.0 4.8 4.1 1993 3.2 5.8 4.5 1994 2.9 4.8 4.1 1995 3.6 4.8 4.2 o

Data not available (not required prior to 1985).

TLD locations initiated in 1985 as required by the New Technical Specifications.

Includes TLD numbers 15. 56, 58. 96, 97 and 98, which are located near critical residences and populated areas near the site.

t 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-20

TABLE 7-16D l

HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION:

ON-SITE INDICATOR **

m-Year Hin.

Max.

Mean-Preopt 1974t 3.1 10 6 5.7 1975t 4.6 16.0 7.3 1980 3.9 12.0 5.3 1981 4.1 11.8 5.8 1982 3.9 13.0 6.3 1983 5.0 16.5 6.9 1984 4.6 13.2 7.0 1985 4.7 15.9 6.3 1986 4.7 16.1 7.0 1987 4.0 11.4 5.8 1988 4.4 11.9 6.0 1989 2.7 13.1 6.0 1990 3.6 12.9 5.5 1991 3.2 11.6 5.4 1992 3.2 5.6 4.3 1993 3.1 13.6 5.2 1994 2.8 14.3 5.1 1995 3.5 28.6 6.2

No data available.

- Includes TLD numbers 3. 4. 5. 6 and 7 (1970 1973). Includes TLD numbers 3, 4 5, 6. 7. 23. 24. 25 and 26 (1974 1995). Locations are existing or previous on site environmental air monitoring locations.

t 1969 data is considered to be pre-operatior.al for the site. 1974 and 1975 data is considered to be pre operational for the NNPP.

7-21

TABLE 7-16E HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION:

0FF-SITE INDICATOR **

' Year Hin.

Max.

Mean Preopt 1974t 2.4 8.9 5.3 1975t 4.5 7.1 5.5 1980 3.1 5.8 4.6 1981 3.6 5.9 4.7 1982 4.0 6.2 5.2 1983 4.6 7.2 5.6 1984 4.6 8.2 6.1 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 1988 4.2 6.6 5.4 1989 2.8 6.4 4.6 1990 3.8 6.1 4.8 1991 3.4 5.8 4.5 1992 3.1 5.2 4.1 1993 3.2 5.7 5.0 1994 3.0 5.1 4.1 1995 3.9 5.7 4.4 o No data available.

Includes TLD numbers 8. 9.10.11.12 and 13 (off-site environmental air monitoring locations),

t 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-22

l TABLE 7-17 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Results in pCi/ liter LOCATION:

CONTROL **

i

' Isotope Cs-137 I-131 Year Hin.

Max.

Mean Hin.

Max.

Mean 1%9t 1974t i

1975t

]

1980

<LLD

<LLD 1.4 1.4 1.4 1981 7.0 7.0 7.0

<LLD

<LLD l

1982

<LLD

<LLD i

1983

<LLD

<LLD i

1984

<LLD

<LLD 1985

<LLD

<LLD 1986 5.3 12.4 8.4 0.8 29.0 13.6 1987

<LLD

<LLD i

1988

<LLD

<LLD 1989

<LLD

<LLD 1

1990

<LLD

<LLD j

1991

<LLD

{

1992

<LLD

<LLD 1993

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

<LLD o

No data available (sample not required).

o* Location used was an available milk sample location in a least prevalent wind direction greater than ten miles from the site.

t 1969 data is consied to be pre-operational for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

7-23 l

TABLE 7-18 HISTORICAL ENVIRONMENTAL SAMPLE MILK Results in pCi/ liter LOCATION:

INDICATOR **

Isotope Cs-137 I-131 Ycar Hin.

Max.

Mean Hin.

Max.

Mean 1969t 1974t 1.6 39 10.5 0.70 2.00 1.23 1975t 6.0 22 16 0.01 2.99 0.37 1980 4.0 21.0 9.7 0.4 8.8 4.9 1981 4.3 29.0 7.6

<LLD

<LLD 1982 3.1 18.0 6.3

<LLD

<LLD 1983 5.1 5.1 5.1

<LLD

<LLD 1984

<LLD

<LLD 1985

<LLD

<LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 1987 5.5 9.4 7.4

<LLD

<LLD 1988 10.0 10.0 10.0

<LLD

<LLD 1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD 1992

<LLD

<LLD 1993

<LLD

<LLD 1994

<LLD

<LLD 1995

<LLD

<LLD Locations sampled were available downwind locations within ten miles with high deposition potential.

- No data available (control samples not required).

t 1969 data is consied to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7-24

l TABLE 7-19 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS tt Results in pCi/g (wet) i LOCATION:

CONTROL

l Isotope Cs-137 1

Year Hin.

Max.

Mean 1969t 1974t 1975t 1980

<LLD

<LLD 1981

<LLD

<LLD 1982

<LLD

<LLD 1983

<LLD

<LLD 1984

<LLD

<LLD 1985

<LLD

<LLD 1986

<LLD

<LLD 1987

<LLD

<LLD 1988

<LLD

<LLD 1989

<LLD

<LLD 1990

<LLD

<LLD 1991

<LLD

<LLD 1992

<LLD

<LLD 1993 0.008 0.008 0.008 1994

<LLD

<LLD 1995

<LLD

<LLD Locations was an available food product sample location in a least prevalent wind direction greater than ten miles from the site.

- No data available (control samples not required).

t 1969 dn.ta is considered to be pre-operational for the site.

1974 and 1975 data is considered to be pre operational for the JAFNPP.

tt Data comprised of broadleaf and non broadleaf vegetaion (1980-1984). Data comprised of broadleaf vegetation only (19851995).

7-25

TABLE 7-20 HISTORICAL ENVIRONMENTAL SAMPLE DATA l

FOOD PRODUCTS tt Results in pCi/g (wet)

LOCATION:

INDICATOR

Isotope Cs-137 Yecr Hin.

Max.

Mean 1969t 1974t 0.04 0.34 0.142 1975t

<MDL

<MDL 1980 0.004 0.060 0.033 1981

<LLD

<LLD 1982

<LLD

<LLD 1983

<LLD

<LLD 1984

<LLD

<LLD 1985 0.047 0.047 0.047 1986

<LLD

<LLD 1987

<LLD

<LLD 1988 0.008 0.008 0.008 1989 0.011 0.011 0.011 1990

<LLD

<LLD 1991 0.039 0.039 0.039 1992

<LLD

<LLD 1993

<LLD

<LLD 1994 0.006 0.012 0.010 1995 0.011 0.012 0.012 0 Indicator locations were available downwind locations within ten miles of the site and with high deposition potential.

No data available (control samples not required).

9 1969 data is considered to be pre operational for the site. 1974 and 1975 data is considered to be pre operational for the JAFNPP.

9t Data comprised of broadleaf and non-broadleaf vegetaion (1976-1984). Data comprised of broadleaf vegetation only (1985-1995).

7-26

8.0 GRAPIIICAL PRESENTATIONS 1.

DATA GRAPHS This section includes graphic representation of selected sample results.

For graphic representation, results reported as MDL or LLD were considered to be at the "zero" level of activity. MDL and LLD results were indicated where possible.

2.

SAMPLE LOCATIONS Sample location results specified as " indicator" and " control" on the graphs can be referenced back to Section 3.3 for specific locations.

I 8-1 i

i

l JAMES A. FITZPATRICK N.P.P.

FISH Cs-137 Figure 8.1 l

1.6 l

Note :1974 data is pre-operational 1.4 1.2

~

[

0.8 8

0.6 0.4 0.2 MMmm-memm--m--

e e

e t

e s

a

=

s

=

a a

a

=

?

year

i n

JAMES A FITZPATRICK N.P.P.

SURFACE WATER-TRITIUM

[

Figure 8.2 2000 1800 l

1975-1984: Oswego City water Control site 1600 t

t 1400 1200

mar s1

a 800 l

l 600 i

400 200 Year

0 O.

0 0

2 0

3 0

1 p

5

.1 5

2 5

3 5

E-N o

t e7 1

9 1

69

=

97 i sT 4

s sti J

e S=

AF p r

p e

o re p

S=

o e

p r

e a

a oi t

r t

n

=

n l

o a

a l

d a

d t

A a

a t

=

a IRJ P A

=

AM RE TS I

m C

A UL F S=

FAI TT ig EZ u

S=

r F P A

e I

Y L

8 TT EAR

=

3 E R RI C

-G K

=

R ON S.

S=

SP m

BE.P e

S=

c T

A

+

l S=

a m

lN ID S=

CAT S= N OR B

Ss CO NT S= E RO L

S= N S=

S= E l

(ti l

III lIl!t

JAMES A. FITZPATRICK N. P.P.

i AIR PARTICULATE FILTER-GROSS BETA FI GURE 8.4 0.03 Indicator.R1,R2,R3,R4 Stations Control: R5 Station 0.025 l-+-INDICATOR -m--CONTROL 0.02 Y

n 5 0.015 Q

/

0.01 V

W l

0.005 l

l I

O 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 WEEK No.1995 i

JAMES A. FITZPATRICK N. P.P.

AIR PARTICULATE FILTER-GROSS BETA FIGURE 8.5 0.03 Indicator.R1,R2,R3,R4 Stations Control: R5 Station 0.025 1

-+-INDICATOR -e-CONTROL 0.02

".015 oo

$0 N

l l

I 0

0.01 0.005 0

27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 WEEK No.1995

1 l

1 JAMES A. FITZPATRICK N.P.P.

AIR PARTICULATE FILTER Co-60 Figure 8.6 0.018 -

0.016 l

0.014 I

slNDICATOR ECONTROL i

O.012 T

m E

d 0.01 l

Oc.

0.008 -

0.006 --

0.004 --

No Positive Detections. AII < LLD.

0.002 I-:-

ER O

1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995

JAMES A FITZPATRICK N.P.P.

AIR PARTICULATE FILTER COMPOSITE Cs-137 Figure 8.7 0.025 0.02 1986-Chemobyl BINDICATOR ECONTROL Accident 0015

?

E

$a 0.01 l

0005

No Positive Detection < LLD i

g g g g _ _

1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 YEAR

JAMES A FITZPATRICK N.P.P.

AIR-RADIOIODINE I-131 Figure 8.8 0.7 I

i i

0.6 BINDICATOR mCONTROL i

i 0.5 f

i i

0.4 m

3 E

e ao.

0.3 i

i 0.2 1986: Chernobyl Accident

No Positive Detection <LLD l'

0.1 g

. E' J E'

~~

e e

n e

e

=

a a

a s

=

a a

a

=

S S

S YEAR i

JAMES A FITZPATRICK N.P.P.

MILK Cs-137 Figure 8.9 25 20<

EINDICATOR ECONTROL 15 9*

d 1986: Chernobyl Accident 10 l- --l.l.I- - l-I-l.

No Positive Detection < LLD 5

m c)

YEAR

t I

r JAMES A. FITZPATRICK N.P.P.

MILK RADIOIODINE l-131 Figure 8.10 18 16 14 i

1986: chsrnobyl Accident l

BINDICATOR ECONTROL 12 d

U" CC 8

.mme 6

1980: Atmospheric testing No Positive Detection < LLD 4

4 2

O N

m e

m C

6 m

m o

e N

m e

m m

S co e

o b

b b

5 m

W m

m m

W G

m m

a m

m a

m m

a a

m m

a a

m m

a e

e e

w e

e e

e w

e i

YEAR i

l

James A. FitzPatrick N.P.P.

Figure 8.11 9

1974-1984 : Control Data nly fs

_I 3

,,,,,,,,,,1,,,,,,,,,,,

9.0 QA/QC PROGRAM 9.1 PROGRAM DESCRIPTION One facet of the JAFNPP Environmental Laboratory Quality Assura.ce Program is the routine participation in the Intercomparison Program conducted by the U.S.

Euvironmental Protection Agency (USEPA).

Participation in this program is required by the Radiological Effluent Technical Specifications.

Sample media analyzed for the intercomparison program include those which are routinely obtained as part of the site Radiological Environmental Monitoring Program.

The EPA supplies sample media as blind sample spikes which contains known low levels of radioactivity.

These samples are prepared and analyzed using the standard laboratory procedures.

The results are submitted to the EPA which issues a statistical summary report. The EPA calculates a Normalized Deviation from the Known Value (NDKV) for each sample set submitted.

The EPA considers laboratory data between -3 and +3 NDKV to be acceptable.

9.2 PROGRAM RESULTS The following chart summarizes the JAFNPP Environmental Laboratory results reported to the EPA for fifteen samples which required results for 25 individual isotopes.

EPA INTERCOMPAntSoN JAF RESULTS-1995 4

3' ' ui> pef dontiol b6uhds- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

2 1

0 1

2 3.. lowet control bounds _... _ _......... _ _ _ _ _ _ _ _.. _ _ _ _.. _ _ _ _ _ _ _ _ _ _ _ _ _ _,

-4 s =I s;sxn 8 axn4 xee 4 2 a e 6I I 63I I i e e 2 I I

.I 0

34 o o u o m u

o o 9-1

All results reported by the Environmental Laboratory were acceptable and fall within the range of +1.04 NDKV and -1.96 NDKV.

Tritium sample results provided by the vendor laboratory for the h:tercomparison Program were acceptable.

The specific results for each analysis are presented in Table 9-1 through 9-4 contained in this section.

9.3 NONCONFORMITIES There were no nonconformities for the samples received and analyzed as part of the 1995 EPA Intercomparison Program.

Two laboratory QA samples that were received as part of the EPA Intercomparison Program, JAF QA-95-013 and JAF QA-95-015, were both part of a blind performance evaluation study (Sample B) dated October 17, 1995. The samples were analyzed for Gross Beta (QA-95-013) and Gamma Emitter (QA-95-15) and the results were submitted to the E9 4.

Evaluation of the sample results by the JAF Laboratory could not be completed as the EPA did not publish a subsequent statistical summary report for the sample results as was standard procedure. A number of attempts to obtain the statistical report by phone and computer were unsuccessful.

9-2

TABLE 9-1 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARIS0N STUDY PROGRAM GROSS BETA ANALYSIS OF AIR PARTICULATE FILTERS (PCI/ FILTER)

GROSS BETA ANALYSIS OF WATER (PCI/ LITER)

JAF ENV JAF EPA DATE 10 NUMBER MEDIUM ANALYSIS RESULT RESULT NDKV l

(1)

(2)

(3) 01/95 QA 95-001 WATER GB 6.0i0.5 Si5 0.46 6.010.5 l

7.0i0.5 1

04/95 QA 95-005 WATER GB 87+7 87i10 0.18 88i7 88f7 07/95 QA 95-007 WATER GB 22i5 19i5 1.02 22i5 l

23i5 08/95 QA 95-009 FILTER GB 89 10 87t10 0.18 88110 86110 10/95 QA 95-013 WATER GB 121i0.95 126i0.97 10410.88 11/95 QA 95-015 WATER GB 2815 2515 0.88 2815 2615 l(1)

Results reported as activity 1 sigma.

i(2)

Results reported as activity i 1 sigma.

l(3)

NDKV is the Normalized Deviation from Known Value as determined by the EPA. Values within the range of +3 and 3 indicate acceptable results.

Known values and Statistical Summary Report not provided by EPA, See Section 9.3.

I 93

TABLE 9-2 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM TRITIUM ANALYSIS OF WATER (PCI/ LITER)

JAF ENV JAF*

EPA DATE ID NUMBER MEDIUM ANALYSIS RESULT RESULT NDKV (1)

(2)

(3) 03/95 OA 95-003 WATER H-3 6900i300 7435i744

-1.04 6900i300 70001300 08/95 QA 95-008 WATER H-3 4700i300 4872 487

-0.22 5100 300

.;00i300 1

(1)

Results reported as activity i 1 sigma.

(2)

Results reported as activity i i sigma.

(3)

NDKV is the Normalized Deviation from Known Value as determined by the EPA. Values within the range of +3 and -3 indicate acceptable results.

Samples analyzed at vendor laboratory.

94

__.._a

1 TABLE 9-3 t

USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY l

INTERCOMPARIS0N STUDY PROGRAM 10D1HE ANALYSIS OF WATER (PCI/ LITER) AND MILK (PCI/ LITER)

I JAF ENV JAF EPA DATE ID' NUMBER MEDIUM ANALYSIS RESULT RESULT NDKV (1)

(2)

(3) 02/95 QA 95 002 WATER I-131 89il.1 100i10

-1.96 90i0.9 87il.2 09/95 QA 95-011 MILK I-131 103i9 99i10 0.00 100i9 94il2 10/95 QA 95 012 WATER I 131 157i4 148il5 0.73 152i6 152i5 l

i(1)

Results reported as activity i i sigma.

(2)

Results reported as activity 1 i sigma.

(3)

NDKV is the Normalized Deviation from Known Value as determined by the EPA. Values within the range of +3 and -3 indicate acceptable results.

l l

95

TABLE 9-4 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARIS0N STUDY PROGRAM GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER)

AND AIR PARTICULATE FILTERS (PCI/ FILTER)

JAF ENV JAF EPA DATE ID NUMBER MEDIUM ANALYSIS RESULT RESULT NDKV (1)

(2)

(3) 04/95 QA 95-004 WATER Co-60 31il 29i5 0.69 30 1 31 1 Cs-134 17 1 20i5

-0.69 20i1 17il Cs-137 1211 11i5 0.23 12i1 llil 06/95 QA 95-006 WATER Co-60 37i2 4015

-0.35

)

39i2 41i2 Zn 65 7216 7618

-0.58 7416 6716 Cs-134 44 2 5015

-1.62 45i2 45 2 Cs-137 3413 3515 0.69 37i3 33t3 Ba-133 81i4 7918 0.72 76i4 82i4 e

(1)

Results reported as activity i i sigma.

(2)

Results reported as activity i i sigma.

(3)

NDKV is the Normalized Deviation from Known Value as determined by the EPA. Values within the range of +3 and -3 indicate acceptable results.

9-6

TABLE 9-4 (COnTInuEo)

USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARIS0N STUDY PROGRAM GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER)

AND AIR PARTICULATE FILTERS (PCI/ FILTER)

JAF ENV JAF EPA DATE ID NUMBER MEDIUM ANALYSIS RESULT RESULT NDKV (1)

(2)

(3) 08/95 QA 95-010 FILTER Cs-137 2411 25i5

-0.12 25 1 25 1 09/95 QA 95-011 MILK Cs-137 45i3 50i5

-0.58 4713 53i3 11/95 QA 95-014 WATER Co-60 53i2 4915 48i3 f

59 2 f

Cs-134 34i2 4015 35i3 36i2 Cs-137 30i2 30i5 33*3 42i2 1

i (1)

Results reported as activity i 1 sigma.

i (2)

Results reported as activity i 1 sigma.

(3)

NDKV is the Normalized Deviation from Known Value as determined by the EPA. Values eithin the range of +3 and 3 indicate acceptable results.

Statistical Summary Report not received from the EPA, See Section 9.3.

97

TABLE 9-4 (COuTInuEo)

USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY I

INTERCOMPARIS0N STUDY PROGRAM GAMMA ANALYSIS OF HILK, WATER (PCI/ LITER)

AND AIR PARTICULATE FILTERS (PCI/ FILTER) i' JAF ENV JAF EPA DATE ID NUMBER MEDIUM ANALYSIS RESULT.

RESULT NDKV (1)

(2)

(3) 11/95 QA 95-016 WATER Co-60 6313 6015

-0.12 58i2 58i2 Zn-65 134i5 125113 0.67 134i5 12218 Cs-134 35il 4015

-1.50 g

36il 36i2

~

l Cs-137 48i2 49i5 0.81 5112 55i3 Ba-133 97i3 99i10

-0.64 92i3 97 4 (1)

Results reported as activity i 1 sigma.

(2)

Results reported as activity i i sigma.

(3)

NDKV is the Normalized Deviation from Known Value as determined by the EPA. Values within the range of +3 and -3 indicate acceptable results.

La 98

_

JAFP-96-0190, Ja FitzPatrick Nuclear Power Plant,Radiological Environ Operating Rept for 1995

Contents

Text

SUBJECT:

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.3 CONCLUSION

5.4 REFERENCES

mar s1

Navigation menu

JAFP-96-0190, Ja FitzPatrick Nuclear Power Plant,Radiological Environ Operating Rept for 1995

Text

SUBJECT:

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.3 CONCLUSION

5.4 REFERENCES

mar s1

Navigation menu

Search