Text

1996 Annual Radiological Environ Operating Rept
	ML20138D712
Person / Time
Site:	North Anna
Issue date:	12/31/1996
From:	Breedon J, Sarver S, Stafford A; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	97-241, NUDOCS 9705010219
	Download: ML20138D712 (111)
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VinciNir El.ECTRIC AND POWER Cmil'ANY RicustoNin, Vuuas A 232<,i April 21, 1997 United States Nuclear Regulatory Commission Serial No.97-241 Attention: Document Control Desk NAPS /JCL Washington, D. C. 20555 Docket Nos.

50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Pursuant to Technical Specification 6.9.1.8, enclosed is the Annual Radiological Environmental Operating Report for North Anna Power Station Unit Nos.1 and 2 for 1996.

No new commitments are intended as a result of this letter. If you have any questions or require additional information, please contact us.

Very truly yours, i

S. P.

arver, Acting Manager Nuclear Licensing and Operations Support 4

cc:

U. S. Nuclear Regulatory Commission

, %[ f Region 11 f

101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 NRC Senior Resident inspector North Anna Power Station 9905010319 961231

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PDR ADOCK 05000338 l.l I.I I.I I.lil.lil.lll. I.I R

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VIRGINIA ELECTRIC AND POWER COMPANY 1

NORTH ANNA POWER STATION l'

Radiological Environmental Monitoring Program f

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January 1,1996 to December 31, 1996 i

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VIRGINIA ELECTRIC AND POWER COMPANY 1

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TELEDYNE ISOTOPES

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O Annual Radiological Environmental Operating Report l

North Anna Power Station January 1,1996 to December 31, 1996 Prepared by:

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James B. Breeden, j

j Supervisor Radiological Analysis and Material Control Reviewed by:

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Erih Dreyer Supentisor Health Physics Technical Services l

S bYS Approved by:

Alan H. dafford Superintendent Radiological Protection O

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Table Of Contents V

Section Title Page Pmface.........................................................................................6 Executive S u mmary......................................................................... 7 I.

In trod u c ti o n......................................................................

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S am plin g A n d A n aly sis Prog ra m.......................................................... 12 III.

Program Exceptions.........................................................................23

'IV.

Summary And Discussion Of 1996 Analytical Results................................. 24 A.

Airborne Ex posure Pathway........................................................ 24 1.

Air Iodine /Particulates.........................................................

2.

Pmcip itati o n.................................................................... 2 6 3.

Soil..............................................................................27 B.

Waterborne Exposu re Pathway..................................................... 27 m

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G rou n d/Well Water............................................................

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Ri v e r Wat e r................................................................

3.

S u rface Water.................................................................

C.

Aq uatic Exposure Pathway.......................................................... 28 1.

S edi men t/S ilt.................................................................

2.

S horeli n e S oil.................................................................

D.

Ingestion Exposure Pathway........................................................ 3 3 I.

Mi1k..............................................................................33 2.

Fish..............................................................................33 3.

Fo o d /V e g e t a t i o n................................................................ 3 5 l

E.

Direct Radiation Exposure Pathway................................................ 3 5

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TLD Dosimeters................................................................35 V.

Co n c l u s i o n............................................................................

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Table Of Contents (Continued) r 6

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Section Title P_ age VI.

R e fe r e n c e s.........................................................................

VII.

A ppe nd ic e s.................................................................................. 4 1 Appendix A - Radiological Environmental Monitoring................................ 41 Program Annual Summary Tables - 1996 l

i Appendix B - Data Tables................................................................ 47 Appendix C - Land Use Census - 199 6................................................. 69 Appendix D - Synopsis of Analytical Procedures...................................... 72 i

Appendix E - Interlaboratory Comparison Program................................... 83 List of Trendine Graohs

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Gross B eta in Air Particulat es............................................................. 25 1

2.

Tri t i u m i n Ri ver Water...................................................................... 2 3.

Tritium i n S u r fa c e W a t e r................................................................... 2 4.

Coba1t-58 in Sediment Silt..................................................................29 5.

Coba1t-60 in Sediment Silt................................................................30 6.

Cesiu m-134 in Sedime nt S ilt............................................................... 3 0 7.

Cesiu m-137 in Sediment S ilt............................................................... 31 8.

Cesi u m-134 i n Fis h........................................................................ 3 1 1

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Ce s i u m-13 7 i n Fi sh......................................................................... 34 10.

Environmental Radiation - TLDs......................................................... 34 i

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List of Tables Table Page l

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Radiological Sampling Station Distance and Direction from Unit 1..................................................................................13 2

2.

North Anna Power Station Sample Analysis Program................................ 20 1

3.

REMP Exceptions for Scheduled Sampling and Ana1ysis During 1996...................................................................23 J

Appendix B Tables 1

i B-1 lodine-131 Concentration in Filtered Air............................................... 47 B-2 Concentrations of Gross Beta in Air Particulates....................................... 49 i

B-3 Gamma Emitter, Strontium 89, and Strontium 90 Concentrations in Air Particulates....................................................... 53 B-4 Gamma Emitter and Tritium Concentration in River Water......................... 56 B-5 Gamma Emitter Co nce n t ration in S oil................................................. 56 j

B6 Gamma Emitter, Strontium, and Tritium Concentrations n

in G round and Well Water.............................................................. 5 7 b

B7 Gamma Emitter, Strontium, and Tritium Concentrations in Ri v e r Wa t e r............................................................................

i B-8 Gamma Emitter, Strontium, and Tritium Concentrations i n S u rface Wa te r.........................................................................

B.9 Gamma Emitter, Strontium, and Tritium Concentrations in Surface Water State-Split Samples.................................................... 59 4

i B 10 Gamma Emitter Concentrations in Sediment Silt...................................... 60 1

B-1I Gamma Emitter Concentrations in Shoreline Soil...................................... 60 B 12 Gamma Emitter Concentrations in Milk............................................... 61 d

B-13 G amma Emitter Concent rations in Fish................................................. 63 B-14 Gamma Emitter Concentrations in Food / Vegetation................................... 64 B-15 Direct Radiation Measurements Quarterly Annua 1 TLD Resu1ts.

......................................................66 B-16 Direct Radiation Measurements S e c t o r Q u a rt e rly T L D R e s u I t s............................................................ 67 O

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s Preface i

This report is submitted as required by Technical Specification 6.9.1.8, Annual 1

Radiological Environmental Operating Report for Nonh Anna Power Stations, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-338 and 50-339.

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Executive Summary

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This document is a detailed report on the 1996 North Anna Nuclear Power Station j

Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1

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. through December 31,1996 in water, silt, shoreline sediment, milk, aquatic biota, food products, i

vegetation, and direct exposure pathways have been analyzed, evaluated, and sununarized. The 1

j REMP is designed to ensure that radiological effluent releases are As Low As is Reasonably

-Achievable (ALARA), no undue environmental effects occur, and the health and safety of the j

public is protected. The program also detects any unexpected environmental processes which could allow radiation accumulations in the environment or food pathway chains.

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l Radiation and radioactivity in the environment is constantly monitored within a' 25 mile j

radius of the station. Virginia Power also collects samples within this area. A number of sampling locations for each medium were selected using available meteorological, land use, and water use 3

data.' Two types of samples are obtained. The first type, control samples, are collected from areas

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j that are beyond the measurable influence of North Anna Nuclear Power Station or any other

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nuclear facility. These samples are used as reference data.' Normal background radiation' levels, or radiation present due to causes other than North Anna Power Station, can thus be compared to the

O cevireement serreundies the neciear Pewer stetien. rediceter samgies are the seceed samgie irge

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obtained. These samples show how much radiation is contributed to the environment by the plant.

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Indicator samples are taken from areas close to the station where any plant contribution will be'at the highest concentration.

Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a " pre-operational baseline."

Analysis results from the indicator samples are compared to both current control sample values and

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the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, other causes such as the Chernobyl accident, or natural variation.

1 Teledyne Brown Engineering provides sample analyses for various radioisotopes as

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-appropriate for each sample media. Panicipation in the Environmental Protection Agency's (EPA)

Interlaboratory Comparison Program provides an independent check of sample measurement L

precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-an measurement methods.

Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for i

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radiological environmental monitoring must be able to detect specified minimum Lower Limits of f,)

Detection (LLD). This ensures that analyses are as accurate as possible. Samples with extremely i

v low levels of radiation which cannot be detected are therefore reponed as being below the LLD.

The NRC also mandates a "reponing level." Licensed nuclear facilities must report any releases equal to or greater than this reporting level. Environmental radiation levels are sometiines referred to as a percent of the reporting lnel.

i Analytical results are divided into five categories based on exposure pathways: Airborne, waterbome, aquatic, ingestion, and direct radiation. Each of these pathways is described below:

The airborne exposure pathway includes airborne iodine, airborne particulate, precipitation, and soil samples. The overall 1996 airbome results were very similar to previous years and to preoperational levels. No increase was noted and there were no detections of fission products or other man-made isotopes in the airborne particulate media during 1996.

The waterbome exposure pathw2y includes ground /well water, river water, and surface water samples. No man-made or natural isotopes were detected in Lake Anna surface water except for tritium. The averap tritium activity in 1996 was 16% of the NRC reporting level. This has essentially remained unchanged from 1995 levels.

The aquatic exposure pathway includes sediment / silt and shoreline samples. North p

Anna sediment contained some cesium-137. During the preoperational penod, cesium-h 137 was detected. Sediment contamination, however, does not provide a direct dose pathway to man. In shoreline soil, which may provide a direct dose pathway, only cesium-137 was detected. Cesium-137 levels were 510 pCi/kg in 1996.

The ingestion exposure pathway includes milk, fish, and food / vegetation samples.

lodine-131 was not detected in any 1996 milk samples. Although cesium-137 has been detected in the past, it was not detected in 1996 milk samples. Strontium-90 was detected at levels comparable to 1989, and lower than preoperational years. Both strontium 90 and cesium-137 are attributable to atmosphenc nuclear weapons testing in the past. Naturally occurring potassium-40 was detected at normal cnvironmental levels.

Fish samples during 1996 contained cesium-137 at a slightly higher activity than preoperational levels. Steam generator repairs anri better liquid waste processing, however, have reduced these activity levels from previous years. Vegetation samples were statistically similar to both control and preoperational levels.

The direct radiation exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially the same since the preoperational period in 1977.

During 1996, as in previous years, operation of the North Anna Nuclear Power Station created no adverse environmental affects or health hazards. The maximum radiation dose A

calculated for a hypothetical individual at the North Anna Power Station site boundary due to liquid V

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l and gaseous effluents released from the site during 1996 was 0.34 millirem. For reference, this O_

aese may he cemP=ea te tae 360 miiiirem averase a##eal exPoSere to every Person the united States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes less than 0.1%.

These results demonstrate not.only compliance with federal and state regulations, but also

demonstrate the adequacy of radioactive effluent control at the North Anna Nuclear Power Station.

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INTRODUCTION i

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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION.

RADIOLOGICAL ENVIRONMENTAL OPERATING PROGRAM i

1.

INTRODUCTION y

The operational radiological environmental monitoring prog-m conducted for 1996 for the North Anna Power Station is provided in this report. The results of measurements and analyses of data obtained from samples collected from January 1,1996 through December 31,1996 are summarized.

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l A.

The North Anna Power Station of Virginia Electric and Power Company is located on Lake 4-Anna in Mineral, Virginia, approximately 35 miles south west of Fredericksburg, Virginia.

j The site consists of two units, each with pressurized water reactor (PWR) nuclear steam

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supply systems and turbine generator fumished by Westinghouse Electric Corporation.

l Each unit is designed with a gross electrical output of 970 megawatts electric (MWe). Unit 1

1 achieved commercial operation on June 6,1978, and Unit 2 on December 14,1980.

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The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) l require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in efnuents to unrestricted areas as low as reasonably achievable

( ALARA). To ensure these criteria are met, the operating license for North Anna Power Station includes Technical Specifications which address the release of radioactive effluents.

l Inplant monitoring is used to ensure release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in North Anna Power Station Offsite Dose Calculation Manual (ODCM).

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Virginia Electric and Power Company is responsible for collecting the various indicator and j

control environmental samples. Teledyne Brown Engineering is responsible for sample analysis and submitting reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with control levels, which vary with time due to such external events as i

cosmic ray bombardment, weapons test fallout, and seasonal vaiiations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This preoperational data is compared with data collected 1

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during the operational phase to assist in evaluating the radiological impact of the plant h

operation.

Occasional' samples of environmental media show the presence of man-made isotopes. As l

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a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence t: man, the data is compared to the reporting level concentrations listed 1

in the USNRC Regulatory Guide 4.8 and Nonh Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of"As Low As Is Reasonably Achievable".

E.

This report documents the results of the Radiological Environmental Monitoring Program for 1996 and satisfies the following objectives of the program:

1.

Provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation.

2.

Supplements the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.

3.

Identifies radioactivity changes in the environment.

4.

Verifies that the plant operations have no detrimental effect on the health and safety of the public.

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i II. SAMPLING AND ANALYSIS PROGRAM

II.

SAMPLING AND ANALYSIS PROGRAM V

A.

Sampling Program 1.

Table I summarizes the sampling program for North Anna Power Station during 1996. Figure 1 indicates the locations of the environmental monitoring stations.

2.

For routine TLD measurements, two dosimeters made of CaSO4:Dy in a teflon card are deployed at each sampling location. Several TLDs are co-located with NRC and i

Commonwealth of Virginia direct radiation recording devices. These are indicated as "co-location" samples.

3.

In addition to the Radiological Environmental Monitoring Program required by North Anna Technical Specifications, Virginia Electric and Power Company (VEPCO) splits i

samples with the Commonwealth of Virginia. All samples listed in Table 1 are

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collected by VEPCO personnel except for those labeled state split. All samples are shipped to Teledyne Brown Engineering located in Westwood, New Jersey.

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All samples listed in Table 1 are taken at indicator locations except those labeled O

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North Anna Power Station - 1996 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Canipass Collection Sansple Media

- Leestion Station Miles Direction Degrees Frequency Researks

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Eavironmental NAPS Sewage 01 0.20 NE 42*

Quarterly On-site. State Split j

TInersneluniinescent Treatrnent Plant

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Fredericks Hall 02 5.30 SSW 225' Quarterly State Split i

& Annually Mineral. Va 03 7.10 WSW 243' Quarterly

& Annually Wares Crossroads M

5.10 WNW 287*

Quanerly State Split

& Annually Route 752 05 4.20 NNE 2P Quanerly

& Annually Sturgeon's Creek 05A 3.20 N

11' Quarterly

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Manna

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Levy.V A 06 4.70 ESE 115' Quanerly State Split.Co-Imcation

& Annually l

Bumpass, VA 07 7.30 SSE 167*

Quanerly State Split

& Annually l

C End of Route 685 2I I.00 WNW 30l*

Quarterly Exclusion Boundary

& Annually State Split.Co-lecation i

Route 700 22 1.00 WSW 242*

Quanerly Exclusion Boundary

& Annually State Split

" Aspen Hills" 23 0.93 SSE 158*

Quanerly Exclusion Boundary i

& Annually State Split.Co-Location i

Orange. VA 24 22.00 NW 325' Quanerly Controt

& Annually Bearing Cooling Tower N-1/33 0.06 N

tr Quanerly On-Site

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Sturgeon's Creek N-204 3.20 N

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Marina r

Parking Lot "C" NNE-3/35 0.25 NNE 32*

Quanerly On-Site (on-site)

Good Hope Church NNE-4/36 4.96 NNE 25' Quanerly State Split Parking Lot "B" NE-5/37 0.20 NE 42*

Quanerly On-Site IAe Anna Marina NE-6/38 1.49 NE 34*

Quanerly i

WeatherTower Fence ENE-7/39 0.36 ENE 74*

Quanerly On-Site Route 689 ENE-8/40 2.43 ENE 65*

Quanerly Near Training E-9/41 0.30 E

91*

Quanerly -

On-Site Facility I

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N.wth Anna Power Statism - 1996 R ADIOl AXilCAI.5AMPLING STATIONS i

DISTANCli AND DIRE (~IlON IROM UNIT NO. I Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Emironmental Morning Glory lidt-E-lu/42 2.E5 E

93*

Quanctly Thermoluminescent Island Dike ESE-1I/43 0.12 ESE 103*

Quarterly On-Site Desimetry (TI.D)

Route 622 ESE-12/44 4.70 ESE 115' Quarterly VEPCO Biology Lah SE-l 3/45 0.75 SE 138' Quarterly On-Site Route 701 IDam Entrance)

SE-14/46 5.88 SE 137*

Quarterly

" Aspen Ilills" SSE-15/47 0.93 SSE 158' Quarterly Exclusion Boundary Elk Creek SSE-16/48 2.33 SSE 165*

Quarterly Warehouse Compound S-17/49 0.22 S

173*

Quarterly On-Site

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Elk Creek Church S-18/50 1.55 S

178*

Quarterly 500 Kv Tower SSW-19/51 0.36 SSW 177*

Quarterly On-Site f

Route 618 SSW-20/52 5.30 SSW 205*

Quarterly t

NAPS Access Road SW-21/53 0.30 SW 218' Quarterly On-Site e-a Route 700 SW-22/54 4.36 SW 232*

Quarterly a

NAPS Radio Tower WSW-23/55 0.31 WSW 237*

Quarterly On-Site i

Route 700 WSW-24/56 1.00 WSW 242*

Quanerly Exclusion Boundary (Exclusion Boundary)

South Gate Construction Switchyard W-25/57 0.25 W

279" Quarerly On-Site Route 685 W-26/58 1.55 W

274*

Quanerly End of Route 685 WNW-27/59 I.00 WNW 30l*

Quarterly Excludon Boundary II. Purceirs Private Rd.

WNW-28/60 1.52 WNW 303*

Quanerly Co-location North Gate Construction Side NW-29/61 0.44 NW 32t*

Quarterly On-Site 1.aydown Area I

Lake Anna Campground NW-30/62 2.54 NW 319' Quarterly

1/#2 Intake NNW-31/63 0.07 NNW 349" Quarterly On-Site Route 208 NNW-32/64 3 43 NNW 184*

Quarterly Bumpass Post Office C-l/2 7.30 SSE 1.67*

Quanerly Control Orange VA C-3/4 22.00 NW 325*

Quarterly Control Mineral.VA C-5/6 7.10 WSW 243*

Quanerly Control Louisa. VA C-7/8 11.54 WSW 257' Quanctly Control

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O TAllt.F. I tPage 3 of 51 North Anna ther Station - 1996 R ADIGI.OGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Compass Collecaion Sample Media 1.oestion Station Miles Direction Degrees Frecuency Remarks e

r Airhorne Particulate NAPS Sewage 01 0.20 NE 42' Weekly On-Site. State Split ced Radiolodine Treatment Plant Fredericks Ifall 02 5.30 SSW 205*

Weekly Mineral. VA 03 7.10 WSW 243' Weekly Wares Crossroads 04 5.10 WNW 287*

Weekly Route 752 05 4.20 NNE 2tr Weekly L

Sturgeon's Creek Marina 05A 3.20 N

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Weekly Ixvy VA 06 4.70 ESE II5*

Weekly Bumpass, VA 07 7.30 SSE 167*

Weekly End of Route 685 21 1.00 WNW 30l*

Weekly Exclusion Boundary Route 700 22 1.00 WSW 242' Weekly Exclusion Boundary State Split

" Aspen Ilills" 23 0.93 SSE 158' Weekly Exclusion Boundary Orange. VA 24 22.00 NW 325' Weekly Contrul Sxrface Water Waste IIcat 08 1.10 SSE 148' Monthly State Split

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Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream) 09 2.20 NW 32(P Monthly Control. State Split (Route 208 Bridge) u"i

Lake Anna (upstream) 09A 12.90 WNW 295*

Monthly Control (Route 669 Bridge) t River Water North Anna River 11 5.80 SE 128*

Monthly (downstream)

Ground Water Biology Lab OIA 0.75 SE 138*

Quarterly State Split (Well Water) i Preelpitation Biology lab 01A 0.75 SE 138' Monthly Aquatic Sediment Waste flcat 08 1.10 SSE 148*

Semi-Annually State Split Treatment Facility (Second Cooling Lagoon)

Lake Anna (upstream) 09 2.20 NW 32tf Semi-Annually Control State Split North Anna River 1I 5.80 SSE 128*

Semi-Annually (Downstream)

In October 1991 the Surface Water Sample location at station 09 was moved to 09A.

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1Alti.E I IP.PFe 4 "I 58 N wih Anna Ibmer Statum - 1996 R ADIOl OGICAI. S AMPl.ING STAllONS DISTANCE AND DIRECTION I ROM UNIT NO. I Distance Compass Collection Sample hiedia 1.ocation Station Alifes Direction Degrees Frequency Remarks ShoreIIne Soll Waste IIcat Ost

1.10 SSE 148' Monthly State Split Treatment Facihty (Second Cooling Lagoon)

Lake Anna (upstream) 09 2.20 NW 320*

Semi-Annually State Spht (Route 208 Bridge)

Ssil NAPS Sewage 01 0.20 NE 42' Once/3 years On-Site Treatment Plant Fredericks iIall 02 5.30 SSW 205*

Once/3 years Mineral. V A 03 7.10 WSW 243*

Once/3 years Wares Crossroads 04 5.10 WNW 287*

Once/3 years Route 752 05 4.20 NNE 27 Once/3 years Sturgeon's Creek Marina 05A 3.20 N

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Once/3 years Levy, V A 06 4.70 ESE il5*

Once/3 years Bumpass. VA 07 7.30 SSE 167*

Once/3 years End of Route 685 21 1.00 WNW 30l*

Once/3 years Exclusion Boundary Route 700 22 I.00 WSW 242' Once/3 years Exclusion Boundary (Exclusion Boundary)

" Aspen flills" 23 0.93 SSE 158' Once/3 years Exclusion Boundary Orange. VA 24 22.00 NW 325' Once/3 years Control Milk llolladay Dairy 12 8.30 NW 310" Monthly State Split (R.C. Goodwin)

Terretrs Dairy 13 5.60 SSW Monthly State Split (l'redericks Ifall)

Fish Waste fleat 08 I.10 SSE I48' Semi-Annually State Split Treatment Facility (Second Cooling Lagoon)

IAe Orange 25 16.5 NW 312' Semi-Annually Control Food Products Route 713 14 I.20 NE 43*

Monthly if available (Broadleaf or at harvest Vegetation)

Route 614 15 1.70(1.37)

SE 133*

Monthly if available or at harvest Shoreline soil was changed from station 09 to 08 effective with the August % sample.

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N ADIOlJX;ICAl. SAMitr-G STAllONS DISTANCE AND DIRI'.CTIO ? ROM UNII NO. I Distance

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Compass Collection Sample hfedia I,ocation Station Stiles Direction Degrees Frequency Remarks Food Prodwets Raute 629/522 16 12.N)

NW 314*

Afonthly if available (Broadleaf or at harvest Vegetallon)

End of Rexpe 6R5 21 1.00 WNW

.MI' Monthly if available or at harvest Aspen fliik 23 0.93 SSE 158*

Monthly if available or at harvest t

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Legend For The North Anna Power Station Environmental Monitoring Stations Overview Maps 4

Map Environmental Sta Map Environmental Sta Designation Identification Designation Identification 1

(a) 01,NE-5/37 7/8 C-7&8 1A 01 A,SE-13/45 1/33 N-1/33 2

(a) 02,SSW-20/52 31/63 NNW-31/63 3

(a) 03 C-5/16 29/61 NW-29/61 4

(a) 04 3/35 NNE-3/35 5

(a) 5 7/39 ENE-7/39 5A (a) 05A,N-2/34 9/41 E-9/41 6

(a) 6,ESE-12/44 11/93 ESE-11/43 7

(a) 07,C-l &2 17/49 S-17/49 8

8-Water, Fish Sediment 19/51 SSW-19/51 Shoreline Soil (d) 9 09-Shoreline Soil Stations 21/53 SW-21/53 NW-30/62 9A 09A-Water sample, sediment 23/55 WSW-23/55 OA 11 I l-River Water, Sediment 25/57 W-25/57 12 12-Milk 16/48 SSE-16/48 13 13 Milk 18/50 S-18/50 14 14-Vegetation, NE-6/38 14/46 SE-14/46 15 Vegetation 22/54 SW-22/54 16 Vegetation 26/58 W-26/58 2I cai 21,WNN 27/59 28/60 WNW-28/60 22 ca) 22,WSW-24/56 32/64 NNW-32/64 23 ta) 23-SSE-15/47 8/40 ENE-8/40 24 (axM 24,C-3&4 4/36 NNE-40/36 25 (c) 25-Fish 10/42 E-10/42 (a) Indicates air sample station, annual and quanerly TI.D. Triennial soil (b) In Orange d

(c) In Lake Orange (d) Station 09 changed to 08 effective with the August 96 sample.

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B.

Analysis Program d

1.

Table 2 summarizes the analysis program conducted by Teledyne Brown Engineering for North Anna Power Station during 1996.

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TABLE 2 i

(Page 1 of 3) l NORTH ANNAPOWERSTATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY A N A LYSIS LLD*

REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2mR 2mR mR/std. month Dosimetry (TLD)

(84 Routine Station TLD's) 12 Station TLD's Annually Gamma Dose 2mRi2mR mR/std. month 3

Airborne Weeldy I-131 0.07 pCi/m Radiolodine 3

Airborne Weekly Gross Beta 0.01 pCi/m Particulate 3

Quanerly(a)

Gamma Isotopic pCi/m Cs-134 0.05 Cs-137 0.06 Annually Sr-89 (c) pCi/m3 (2nd Quaner Sr-90 (c)

Composite) 3(d Surface Water Monthly I-131 1(b) pCi/l Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a)

Tritium (H 3) 2000 pCi/l 2nd Quarterly Sr-89 (c) pCi/l Composite Sr-90 (c) 1 i

l LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed.

O (a)

Quarterly Composites of each location's samples are used for the required analysis.

(b)

LLD for non-drinking water is 10 pCi/ liter.

(c)

There are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

20

1 TABLE 2 (Page 2 of 3)

NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM i

SAMPLE MEDIA FREOUENCY A N A LYSIS LLD*

REPORT UNITS River Water Monthly I-131 1(b) pCi/l Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a)

Tritium (H-3) 2000 pCi/l 2nd Quarter Sr-89 (c) pCi/l Sample Sr-90 (c)

Ground Water Quanerly(a)

Gamma Isotopic pCi/l (Well Water) 2nd Quarter Mn-54 15 Composite Fe-59 30 Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 1(b) i Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quanerly(a)

Tritium (H-3) 2000 pCi/l 2nd Quaner Sr-89 (c)

Composite Sr-90 (c) j i

A o m tic Semi-Annually Gamma Isotopic pCi/kg (dry) i Sediment Cs-134 150 Cs-137 180 Annually Sr-89 (c) pCi/kg (dry)

Sr-90 (c) 1 l

Precipitation Monthly Gross Beta pCi/l Semi-Annual Gamma Isotopic pCi/l Composite LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may

/'

be lower than those listed.

(a)

Quarterly Composites of each location's samples are used for the required analysis.

(b)

LLD for non-drinking water is 10 pCi/ liter.

(c)

There are no required LLD's for strontium 89/90. LLD's are those achieved by Teledyne Brown Engineering.

21 l

TABLE 2 (Page 3 of 3)

U NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM j

SAMPLE MEDIA FREQUENCY A N A LYSIS LLD*

REPORT UNITS Shoreline Soil Semi-Annual Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Annually Sr-89 (a)

Sr-90 (a)

Soil Once per 3 yrs.

Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Once per 3 yrs.

Sr-89 (a) pCi/kg (dry)

Sr-90 (a)

Milk Monthly 1-131 1

pCi/l Monthly Gamma Isotopic pCi/l Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 (a) pCi/l Sr-90 (a)

Fish Semi-Annual Gamma Isotopic pCi/kg (wet)

Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 i

Cs-137 150 Food Products Monthly if Gamma Isotopic pCi/kg (wet)

(Ilroadleaf available or Vegetation) at harvest Cs 134 60 Cs-137 80 1-131 60 pCi/kg (wet)

Note:

This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

LLD's indicate those levels that the ensironmental samples should be analyzed to,in accordance with the North b

Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those hsted.

(a)

There are no required LLD's for strontium 89/90. LLD's are those achieved by Teledyne Brown Engineering.

22

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i III. PROGRAM EXCEPTIONS J

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i Appendix B REMP Exceptions For Scheduled Sampling And Analysis During 1996 - North Anna Location Description Date of Sampling Reason (s) for Loss / Exception W-27 Surface Water 07/31/96 Tritium analyses not requested by NAPS.

W-33 State Splits 09/30/96 LLD's for I-131 and Ba-140 not met due to long lapse of time (30 days) from collection to receipt at laboratory.

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IV.

SUMMARY

AND DISCUSSION OF 1996 ANALYTICAL RESULTS I

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Summary And Discussion of 1996 Analytical Results pV Data from the radiological analyses of environmental media collected during 1996 are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Quality Assurance Manual and J

are explained in the Teledyne Brown Engineering Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Appendix D. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Appendix E.

Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The "less than" values in the data tables were calculated for each specific analysis and are dependent on sample size, detector efficiency. length of counting time, chemical yield, when appropriate, and the radioactive decay factor from time of counting to time of collection. Teledyne Brown Engineering's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, Radiological Monitoring Exceptable Program (November 1979, Revision 1) and the ODCM.

The following is a discussion and summary of the results of the environmental measurements taken during the 1996 reporting period.

A.

Airborne Exposure Pathway 1.

Air lodine /Particulates Charcoal cartridges used to collect airbome iodine were collected weekly and analyzed by gamma spectrometry for iodine-131. The results are presented in Table B-1. ' All results were below the required lower limit of detection. For air particulates, gross beta activity was observed in all fifty-two control samples with an average concentration of 0.021 pCi/m3 and a range of 0.013 to 0.032 pCi/m3. The average measurement for the indicator locations was 0.020 pCi/m3 with a range of 0.009 to 0.071 pCi/m3. The results of the gross beta activities are presented in Table B-2. The gross beta activities for 1996 were comparable to levels measured in the 1982-1995 period. Prior to that period the gross beta O

activities were hisher dee te atmesgaeric neciear weagens testine gerfermed in e18er 24

l q

TRENDING GR APH-1: GROSS BETA IN AIR PARTICULATES 1

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1986 1987 1987 1988 1989 1989 1990 1991 1991 1992 1993 1993 1994 1995 1995 1996

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-+- Required LLD's O

TRENDING GRAPH 2: TRITIUM IN RIVER W ATER-STATION 11 10000=

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1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Tritium Required LLD's 0

I During the preoperatonal period, tritum was not detected in the carnples analyzed.

i 25 l

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countries. During the preoperational period of July 1,1974 through March 31,1978 gross 3

beta activities ranged from a low of 0.005 pCi/m to a high of 0.75 pCi/m3,

Air particulate filters were composited by locations on a quarterly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table B-3. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in all 48 composite samples. The average measurement for the control location was 0.087 pCi/m3 with a range'of 0.070 to 0.109 pCi/m3. The indicator locations had an average concentration of 0.080 pCi/m3 and a range of 0.058 to 0.114 pCi/m3. During the preoperational period, beryllium-7 was measured at comparable levels, as would be expected. Naturally occurring potassium-40 was detected in two control samples with an average concentration of 0.005 pCi/m3 and a range of 0.004 to 0.006 pCi/m3 Potassium-40 was detected in thirteen indicator samples with an average concentration of 0.004 pCi/m3 and a range of 0.002 to 0.010 pCi/m3. All other gamma emitters were below the detection limits. During the preoperational period gamma ray spectroscopy measured several fission products in numerous air particulate filters. All isotopes were attributed to atmospheric nuclear weapons testing conducted before the preoperational period. Among the isotopes measured were zirconium-95, ruthenium-103, ruthenium-106, cesium-137, cerium-141 and cerium-144.

The second quarter composites of air particulate filters from all twelve stations were j

analyzed for strontium-89 and 90. There was no detection of these fission products at any of the elevan indicator stations nor at the control station.

1 2.

Precipitation 3

A sample of rain water was collected monthly at station Ol A, on site,0.75 miles,138 degrees SE and analyzed for gross beta activity. The results are presented in Table B-4.

The average gross beta activity for 1996 in the twelve samples was 3.24 pCi/ liter with a range from 1.4 to 7.1 pCi/ liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritium. Beryllium-7 was not detected during 1996. All other gamma emitters were below their detection limits. Tritium was not detected in the semi-annual composite samples. These results were comparable to or lower than those measured in 1986 thm 1995. During the preoperational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface, thus a direct comparison can not be made to the 1996 period. During the preoperational period, tritium was measured in O

26

over half of the few quarterly composites made. The tritium activity ranged from 100 to 330 pCiAiter.

3.

Soil

)

Soil samples are collected every three years from twelve stations. Since they were collected in 1995 they were not collected in 1996.

B.

n'aterborne Exposure Pathway 1.

Ground /Well Water Water was sampled quarterly from the on site well at the metrology laboratory. These samples were analyzed for gamma radiation and for tritium. The results are presented in Table B-6. No gamma emitting isotopes or tritium were detected during 1996. The second quarter sample was analyzed for strontium-89 and strontium-90. There were no detections of these isotopes above the detection level. No gamma emitting isotopes were detected during the preoperational period. Tritium was measured in most of the samples during that periou with concentrations between 80 and 370 pCiMiter.

O 2.

River Water A sample of water from the North Anna River was collected monthly at station 11,5.8 miles downstream from the discharge lagoon,128 degrees SSE. The results are presented in Table B 7. The samples were analyzed by gamma spectroscopy monthly. The samples were analyzed for tritium quarterly on a composite sample. The second quarter samples were analyzed in addition for strontium-89 and strontium-90.

Potassium-40 was not detected during 1996 and all other gamma emitters were below the detection level. No detections of strontium-89 or strontium-90 occurred. Tritium was measured in all four samples with an average level of 2950 pCiMiter and a range of 2500 to 3800 pCi/ liter. This is slightly higher than the average level measured in 1995 of 2825 pCiMiter and a range of 2l00 to 3600 pCiniter. No river water samples were collected during the preoperational period.

O 27

3.

Surface Water O

LJ Samples of surface water were collected monthly from two stations. Station 08 is at the discharge lagoon,1.1 miles,148 degrees SSE on Lake Anna. Station 09A is located 12.9 miles WNW. The samples were analyzed for iodine-131 by radiochemical separation. No iodine was detected in the 24 samples analyzed. The results are presented in Table B-8.

The samples were also analyzed by gamma ray spectrometry. No gamma emitters were above their detection level at either sampling station.

A quarterly composite from each station was prepared and analyzed for tritium. The tritium activity at station 08 for the quarterly composites was at an average level of 3150 pCi/ liter with a range of 2l00 to 4200 pCiniter. The tritium level had been increasing since the middle of 1978 when the average level was below 300 pCi/ liter. However, during 1996 the results were within the same range as those measured in 1986 thru 1995. During the preoperational period tritium was measured in several samples with concentrations between 90 and 250 pCiMiter. Tritium was not detected at station 09A.

Samples of surface water were collected by the Comrnonwealth of Virginia from two stations. Station W-33 is located at the discharge lagoon while station W-27 is located on O

18e ser8 ^

aiveratthe ar.208 8<i8 e. whic8is#9streem er18eeite. Tweetv-reer 8

samples were collected and analyzed by gamma ray spectroscopy. The results are presented in Table B-9. All gamma emitters were below their detection levels.

Four samples from each station were analyzed for tritium during 1996. The average activity at station W-33 in all samples was 2985 pCiniter with a range of 2240 to 4100 pCiniter. This is slightly lower than the 3500 pCi/ liter measured during 1995 at this station. Tritium was measured in two samples at station W-27 with an average activity of 800 pCi/ liter and a range of 600 to 1000 pCiMiter. This is lower than the average of 1033 pCiniter measured at station W-27 during 1995.

1 C.

Aquatic Exposure Pathway 1.

Sediment / Silt Sediment samples were callected during February and August from each of three locations and were analyzed by gamma spectromeuy. The results are presented in Table B-10. One man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in four samples with an average activity of 104 pCi/kg 28

i TRENDING GRAPH - 3: TRITIUM IN CURFACE W ATER -CTA 08 l

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--+- Station-11 During the preoperational period, cobalt-60 was not detected in the samples analyzed.

TRENDING GR APH - 6: CESIUM-134 IN SEDIMENT SILT 1000.

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During the preoperational period, cesium-134 was not detected in the samples analyzed.

30

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- _/_ _

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Staton 25 replaced station 09.

--m-Station-08

-*- Staton-09 Control-Sta-25

-+

Required LLD's 31

(dry weight) and a range from 42.1 to 255 pCi&g (dry weight). The highest reading for cesium-137 was obtained fr..m station 11 located 5.80 miles SSE.

Naturally occurring potass ium-49 was observed in all six samples with an average activity of 11588 pCi&g (dry weight) t.nd a range from 2170 to 22200 pCi/kg (dry weight).

Radium-226 was measured in all six samples with an average concentration of 1443 pCi&g (dry weight) and a range of 1040 to 1990 pCi/kg (dry weight). Also naturally occurring, thorium-228 was observea in all six samples with an average concentration of 827 pCi/kg

.{ dry weight) and a range of 501 to 1140 pCi/kg (dry weight). Cesium-137 was measured in four samples with an average concentration of 104 pCi/kg (dry weight) and a range of 42.1 to 255 pCi/kg (dry weight). The August samples were analyzed for strontium-89 and strontium 90. There were no detections of strontium-89 or strontium-90 in aquatic sediment / silt.

During the preoperational period sedim.:nt samples were analyzed by gamma ray spectroscopy, Cesium-137 was mearared in most of the samples with concentrations between 33 and 1210 pCi/kg (dry weight). Strontium-90 was measured in most of the samples with concentrations between 60 and 540 pCi/kg (dry weight).' Strontium-89 was not measured. Potassium-40, radium-226, and thorium-228, all naturally occurring, were O

m easured at eacx8ree d ieveis.

2.

Shoreline Soil A sample of shoreline sediment was collected in February and August from station 09,2.2 miles upstream of the North Anna Power Station. The samples were analyzed by gamma ray spectrometry. The results are presented in Table B-ll. The naturally occurring nuclide potassium-40 was measured in both samples with an average activity of 6320 pCi/kg (dry weight) and a range of 1340 to 11300 pCi/kg (dry weight). Cosmogenic beryllium-7 was not measured during 1996. Thorium-228 was measured in both samples at an average of -

1172 pCi/kg (dry weight) and a range of 233 to 2110 pCi/kg (dry weight). Radium-226 was measured in both samples with an average activity of 2287 pCi/kg (dry weight) and a range of 833 to 3740 pCi/kg (dry weight). Cesium-137, a fission product, was monitored in both samples with an average level of 510 pCi/kg (dry weight) and a range of 421 to 598 pCi/kg (dry weight).

The August sample was analyzed for strontium and there were no detections of strontium-89 or strontium-90.

32

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D.

Ingestion Exposure Pathway l

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1.

Milk The results of the iodine-131 analysis of milk samples are presented in Table B-12. A l

sample was collected monthly from two stations. A total of 24 samples were analyzed l

during 1996. There were no measurements ofiodine-131 above the detection limits.

a

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The milk samples were also analyzed by gamma ray spectroscopy and the re'ults are also s

presented in Table B-12. A total of 24 samples were analyzed. Naturally occurring potassium-40 was measured in all samples with an average of 1328 pCiMiter and a range of i

1170 to 1450 pCiditer. The fission product cesium-137 has been detected sporadically in recent years and the activity has been attributed to global fallout from past atmospheric weapons testing. However, cesium-137 was not detected at levels above LLD in any milk i

samples during 1996. All other gamma emitters were below their detection levels. A quarterly composite was prepared from each of the two collection stations and analyzed for strontium-89 and strontium-90. Strontium-89 was not detected at levels above LLD in any 1

of the samples monitored. Strontium-90 was detected in the eight samples monitored with j

an average level of 1.07 pCi/ liter and a range of 0.81 to 1.4 pCiniter. This is similar to p

activities determined in previous years and lower than the preoperational levels of 2.2 to V

5.4 pCiniter.

2.

Fish Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate cenain chemical elements which have radioactive isotopes. The results are presented in Table B-13. Eight samples of fish were collected during 1996. These samples were analyzed by gamma ray spectroscopy and the naturally occurring isotope potassium-40 was found in all samples at an average of 2006 pCi/kg (wet weight) with a range of 1400 to 2620 pCi/kg (wet weight). The Gssion product cesium-137 was measured in three samples at an average of 53.2 pCi/kg (wet weight) and a range of 51.1 to 54.8 pCi/kg (wet weight). During the preoperational period cesium-137 was measured in one-founh of the fish samples collected with concentrations between 31 and 66 pCi/kg (wet weight). All other gamma emitters were below their detection levels.

i O

33

1 TRENDING GR APH - 9: CESIUM-137 IN FISH 10000_

1000.

Ec g

+-

a 100 z

h

/\\l1 l

i.../

i

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./

V 10 1

5/80 5/83 4/85 8/88 7/87 4/88 12/88 10/89 10/90 10S1 4/93 8/94 03/96

--e--

Staton-08

--*-- Staton-09 Staton-25

-A Average Pre-op

-+

Required LLD Station 25 replaced station 09.

TRENDING GR APH - 10: ENVIRONMENT AL R ADI ATON - TLD's 5

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6

~

d.

~

G 82 E

4 E

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1 iiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiie iiiiiiiiii 1/86 10/86 7/87 4/88 1/89 10/89 7/90 4S1 1/9210S27S3 4S4 165 10S5 07S6 Environmentai TLD's

--*-- Sector TLD's

--A Average Pre-op O

34

3.

Food / Vegetation U

Thirty-five food samples were collected from five locations and analyzed by gamma spectrometry. The results are presented in Table B-14. Naturally occurring potassium-40 was monitored in all 35 samples with an average activity level of 16253 pCi/kg (wet weight) and a range of 6690 to 26500 pCi/kg (wet weight). Cosmogenic beryllium-7 was detected in all 35 samples with an average concentration of 4136 pCi/kg (wet weight) and a range of 502 to 14700 pCi/kg (wet weight). Radium was measured in one sample with an activity of 230 (wet weight). The terrestrial nuclide thorium-228 was detected in two samples at an average activity of 104 pCi/kg (wet weight) and a range of 93.1 to 115 pCi/kg (wet weight).

The fission product cesium-134 was not detected at levels above LLD during 1996.

Cesium-137 was detected in three samples w!th an average concentration of 137 pCi/kg (wet weight) and a range of 71.3 to 238 pCi/kg (wet weight). These results are consistent with those measured in previous years. Ce aum-137 was measured in broadleaf garden vegetation during the preoperational perid.uith concentrations between 53 and 98 pCi/kg (wet weight).

i (V

E.

Direct Radiation Exposure Pathway I.

TLD Dosimeters Thermoluminescent dosimeters (TLDs) determine environmental radiation doses and the i

results are presented in Table B-14. Individual measurements of external radiation levels in the environs of the North Anna site had an average dose of 5.9 mR/ standard month with a range of 4.0 to 10.1 mR/ standard month. This is comparable to the preoperational range.

The control station, No. 24, had an average reading of 5.6 mR/ standard month with a range of 4.9 to 6.8 mR/ standard month.

Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. The results are presented in Table B-

15. The average level of the 32 locations (two badges at each location) was 6.6 mR/ standard month with a range of 3.9 to 10.5 mR/ standard month. The eight control TLDs, collected quarterly from four locations, showed an average reading of 5.5 mR/ standard month with a range of 3.8 to 7.9 mR/ standard month. During the A

preoperational period (starting in 1977), when the calculation of the TLD dose included a U

j 35

1 i

correction for the in-transit dose, the doses were measured between 4.3 and 8.8 mR/ standard month.

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CONCLUSIONS 1

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V.

Conclusions The results of the 1996 Radiological Environmental Monitoring Program for the North Anna Nuclear Power Station have been presented. The following sections discuss each pathway individually followed by a program summary.

Airborne Exposure Pathway Air paniculate gross beta concentrations of all the indicator locations for 1996 followed the gross beta concentrations at the control location. The gross beta concentrations were comparable to levels observed since 1982 except for a five week period in 1986 which was influenced by the Chernobyl accident. Gross beta concentrations in the preoperational period were highly variable, ranging from 0.0043 to 0.75 pCi/ cum, due to occasional atmospheric nuclear weapons tests.

Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). There were no detections above the LLD for fission products nor other man-made isotopes in the particulate media during 1996. Iodine-131 was not detected in the charcoal filters analyzed during 1996.

A precipitation sample was collected monthly during 1996 and analyzed for gross beta activity. All the gross beta activities were comparable to those measured in previous years. During the preoperational period the average gross beta activity was 0.92 pCi/liier. Semi-annual composites were analyzed for gamma emitting isotopes and tritium. All gamma emitters were below their detection limits. Tritium was not observed above the LLD during this reporting period in 1996. During the preoperational period the average tritium activity was 165 pCi/ liter.

Waterborne Exposure Pathway No man-made or natural isotopes were monitored in the surface water of Lake Anna except tritium. The average tritium activity during 1996 at the waste heat treatment facility was 3150 pCi/ liter which is 16.0% of the reporting level for a water sample. In 1995 the tritium level was 2775 pCi/ liter. The preoperational level was 150 pCi/ liter and has been rising since 1977. Tritium was not measured upstream of the site, at station 09A.

The samples of surface water collected by the Commonwealth of Virginia at the waste heat treatment facility had similar tritium results with a measurement of 2985 pCi/ liter as compared to 3075 pCi/ liter foc 1995. The upstream location had three measurements at an average activity of 800 pCi/ liter as compared to 1033 pCi/ liter for 1995. No gamma emitting isotopes were detected.

I 37

i i

t Q

1 l

Q River water collected from the North Anna River,5.8 miles downstream of the site had an average tritium level of 2950 pCi/ liter. The average tritium in 1995 had been 2825 pCi/ liter. No gamma emitters were detected.

l Ground water from the environmental well on site contained no gamma emitters. There were also no detections of tritium in ground /well water during 1996.

Aquatic Pathway Sediment / silt samples provide a sensitive indicator of discharges from nuclear power stations. The sediment from North Anna environmental samples indicated that one man-made isotope was present. Cesium-137 was detected in three samples at three locations. During the preoperational period, cesium-137 was measured in samples of aquatic sediment. Sediment contamination does not provide a direct dose pathway to man.

The samples of shoreline soil monitored downstream of the site contained no measurement of cesium-134. Cesium-137 was measured in both samples at an average level of 510 pCi/kg which was higher than the average of 341 pCi/kg detected in 1995.

A i;

ingestion Pathway lodine-131 was not detected in any of the twenty-four milk samples using the radiochemical separation method. Although cesium-137 has been detected occasionally in previous years and attributed to past atmospheric nuclear weapons testing there were no detections during 1996. Strontium 90 was measured in all eight milk samples. Strontium-90 is attributed to past atmospheric nuclear weapons testing. No strontium-89 was detected in any of the milk samples.

Naturally occurring potassium-40 was measured in all the milk samples at normal environmental levels.

Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples during 1996 showed the presence of one man-made isotope, cesium-137.

This isotope was at an activity level somewhat higher than preoperational levels but statistically similar to levels in 1987 through 1995. Only cesium-137 was measured in preoperational l

environmental fish samples. Due to primary and secondary steam generator problems experienced at North Anna during 1984/1985, a build up in activity levels both in effluents and fish did occur.

[T Repairs to the steam generators and better liquid waste processing have reduced these activity v

l 38

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

I levels in effluents and thus decreased activity levels are now being observed in the fish. The O

averase ievei ef activier derin 1996 ef cesiem->37 was 2.7.* ef the rePerties ievei.

Three vegetation samples contained the man-made isotope cesium-137 during 1996.

Cesium-137 was measured during 1993 and in preoperational samples.

Direct Exposure ' Pathway The direct exposure pathway as measured in the environment of the North Anna site by thermoluminescent dosimetry has remained essentially the same since the preoperational period in 1977 at 6 milliroentgens per month or 0.2 milliroentgens per day. The average dose levels monitored have shown a normal fluctuation about these levels which are less than the estimated whole body dose due to natural terrestrial and cosmic radiation and the intemal dose from natural radionuclides.

Program Conclusions The results were as expected for normal environmental samples Naturally occurring activity was observed in sample media in the expected activity ranges. Occasional samples of nearly all media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant

' dose consequence.

As a method of referencing the measured radionuclide concentrations in sample media to the dose consequence, the data may be compared to the Reporting Level Concentrations listed in the Offsite Dose Calculation Manual. These concentrations are based upon 25% of the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion "As Low as is Reasonably Achievable." Based upon the evidence of the environmental monitoring program the station is operating within regulatory limits. Thus, no unusual radiological characteristics were observed in the environs of the Nonh Anna Nuclear Power Station during 1996.

O 39

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aj i.

VI. REFERENCES j

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't 4

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I i

s

VI.

References 1.

Virginia Electric and Power Company, North Anna Power Station Technical l

Specifications, Units 1 and 2.

2.

Virginia Electric and Power Company, Station Administrative Procedure, VPAP-2103, "Offsite Dose Calculation Manual.

3.

Title 10 Code of Federal Regulation, Part 50 (10CFR50), " Domestic Licensing of Production and Utilization Facilities."

4.

United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," October,1977.

5.

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

6.

USNRC Branch Technical Position, " Acceptable Radiological Environmental Monitoring Program," Rev.1, November 1979.

7.

NUREG 0472, " Radiological EfDuent Technical Specifications for PWRs," Rev. 3, March 1982.

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APPENDIX A i

i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM f

ANNUAL

SUMMARY

TABLES - 1996 1

4 i

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li 2

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4

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1996 Docket No. 50-338/339 Page 1 of 6 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range m ents Air lodine 1131 624 0.04 -(0/572)

N/A N/A

-(0/52) 0 3

(pCi/m )

Airborne Gross 624 5

20.2(572-572) 01 22.1(52/52) 21.0(52/52) 0 Particulates Beta (8.5-71)

(13-33)

(13-32) 3 (1E 03 pCi/m )

Gamma 48 Be-7 48 10 79.5(44/44) 04 91.1(4/4) 86.8(4/4) 0 (58.4 114)

(69.2-114)

(70.0-109)

K-40 48 10 4.39(13/44) 07 5.60(3/4) 4.91(2/4) 0 (2.43-10.3)

(2.43 10.3)

(3.96-5.86)

Q St-89 12 3

-(0/11)

N/A N/A

-(0/1)

O LJ Sr 90 12 0.4

-(0/11)

N/A N/A

-(0/1) 0 Ground Gamma 4

Well Water K-40 4

60

-(0/4)

N/A N/A

-(0/0) 0 (pct /l ter)

Tntium 4 2000 -(0/4)

N/A N/A

-(0/0) 0 I

Sr89 1

3

-(0/1)

N/A N/A

-(0/0) 0 Sr 90 1

0.4

-(0/1)

N/A N/A

-(0/0) 0 O

1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an

[

Acceptable Radiological Environmental Monitoring Program, P.evision 1, November 1979.

l l

l 41 1

L RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1996 l ~

Docket No. 50-338/339 Page 2 of 6

(

l l

AllIndicator Control Non-l Medium or Analysis Locations Location with Highest Mean Location routine j

Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Measure.

l (Unit)

Type No.

Range Direction Range Range ments River Gamma 12 Water (pCl/ liter)

K 40 12 200

-(0/12)

N/A N/A

-(0/0) 0 Tritium 4 2000 2950(4/4) 11 5.8 mi.SSE 2950(4/4)

-(0/0) 0 (2500-3800)

(2500-3800)

Sr-89 1

3

-(0/1)

N/A N/A

-(0/0) 0 l

Sr90 1

0.4

-(0/1)

N/A N/A

-(0/0) 0 Precipitation Monthly (pCi/ liter)

Gross 12 4

3.24(12/12) 01 A 0.2 mi.

3.24(12/12)

-(0/0) 0 l

Beta (1.4-7.1)

NE (1.4-7.1)

Gamma 2

(Semi Annually)

Tntium 2 2000 -(0/2)

N/A N/A

-(0/0) 0 Surface 1131 24 0.5

-(0/12)

N/A N/A

-(0/12) 0 Water l

(pCi/ liter) l Regular Gamma 24 Monthlies K-40 24 200

-(0/12)

N/A N/A

-(0/12) 0 l

l l

Tritium 8 2000 31504/4) 08 1.10 mi 3150(4/4) 320(1/4) 0 l

(2100-4200)

SSE (2100-4200) 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

42

l p

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

V North Anna Nuclear Power Station, Louisa County, Virginia - 1996 Docket No. 50 338/339 Page 3 of 6 l

Allindicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported 1

Sampled Total Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range ments i

l Surface Sr 89 1

-(0/1)

N/A N/A

-(0/1) 0

)

Water l

(pCi/ liter)

Regular Sr 90 1

-(0/1)

N/A N/A

-(0/1)

O Monthlies Surface Gamma 24 Water (pCi/ liter)

K-40 24 200

-(0/24)

N/A N/A

-(0/0) 0 State Splits Tritium 8 2000 2200(7/8)

W33 3075(4/4)

-(0/0) 0 (300-4200)

(2200-4200)

Sediment Gamma 6

Silt (pC /kg K-40 6

200 11333(4/4) 11 5.8 mi 18350(2/2) 12100(2/2) 0 (dry))

(2170-22200)

SSE (14500-22200)

(11800-12400)

Cs 137 6

194 149(2/4) 11 5.8 mi 255(1/2) 59.4(2/2) 0 (42.1 255)

SSE (49.5-69.4)

Ra 226 6

100 1425(4/4) 11 5.8 mi 1810(2/2) 1480(2/2) 0 (1040-1990)

SSE (1630 1990)

(1470 1490)

Th-228 6

30 848(4/4) 11 5.8 mi.

1080(2/2) 785(2/2) 0 (501-1140)

SSE (1020-1140)

(631-939)

Sr89 3

4.0

-(0/2)

N/A N/A

-(0/1) 0 (Annually)

Sr90 3

0.8

-(0/2)

N/A N/A

-(0/1) 0 (Annually) p i

1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

43

.. ~ - _ - -.

r RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

V' North Anna Nuclear Power Station, Louisa County, Virginia - 1996 Docket No. 50-338/339 Page 4 of 6 Allindicator Controf Non-Medium or AN/Alpsis Locations Location with Highest Mean Location routine Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range ments Shoreline Gamma 2

Soil (pCi/kg Be-7 2

-(0/2)

-(0/0) 0 (dry))

K-40 2

200 6320(2/2) 9 2.2 mi. NW 11300(1/2)

-(0/0) 0 (1340-11300)

Cs 137 2

40 510(2/2) 9 2.2 mi. NW 598(212)

-(0/0) 0 (421 598)

Ra 226 2

100 2287(2/2) 9 2.2 mi. NW 3740(1/2)

-(0/0) 0 (833-3740)

O Th 228 2

30 1172(2/2) 9 2.2 ml. NW 2110(1/2)

-(0/0) 0 (233-2110)

Sr89 1

4.0

-(0/1)

N/A N/A

-(0/0) 0 (Annually)

St90 1

0.8

-(0/1) 08 0.064(1/1)

-(0/0) 0 (Annually)

Milk 1131 24 0.5

-(0/24)

N/A N/A

-(0/0) 0 (pCi14ter)

Gamma 24 K-40 24 100 1328(24/24) 12 8.3 mi. NW 1363(12/12)

-(0/0) 0 (1170-1450 (1260 1440) l Sr 89 8

5

-(0/8)

N/A N/A

-(0/0) 0 (Ouarterly) l Sr90 8

0.8 1.07(8/8) 13 5.60 mi. SSW 1.19(4/4)

-(0/0) 0 l

(Ouarterly)

(0.81 1.4)

(0.95-1.4) l l

l

\\

l 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

44

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1996 Docket No. 50-338/339 Page 5 of 6 All indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD' Reported Sampled Total Mean Name Distance Mean Mean NIeasure-(Unit)

Type No.

Range Direction Range Range ments Fish Gamma 8

pCi/kg (wet)

K-40 8

?00 1823(4/4) 25 16.5 mi. NW 2190(4/4) 2190(4/4) 0 (1600-1990)

(1400-2620)

Cs 137 8

40 53.2(3/4) 08 1.10 mi. SSE 53.2(3/4)

-(0/4) 0 (51.1 54.8)

(51.1 53.6 Food Gamma 35 Vegetation Dose (pCi/kg Be 7 35 4136(35/35) 14 1.20 mi 4803(7/7)

-(0/0) 0 (wet))

(502 14700)

NE (1530-9320)

K-40 35 16253(35/35) 15 1.37 mi.

17529(7/7)

-(0/0) 0 (6690 26500)

SE (10600-22600)

Cs 137 35 80 137(3/35) 15 1.37 mi.

238(1/7)

-(0/0) 0 (71.3-238)

SE Ra 226 35 230(1/35) 21 1.00 mi.

230(1/7)

-(0/0) 0 WNW Th-228 35 104(2/35) 16 104(2/7)

-(0/0) 0 (93.1 115)

WNW (93.1 115) 0 1

LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitonng Program, Revision 1, November 1979.

45

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

bq North Anna Nuclear Power Station, Louisa County, Virginia - 1996 Docket No. 50-338/339 Page 6 of 6 AllIndicalor Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range m ents Direct Gamma 48 0.2 5.92(44/44) 01 0.2 mi. NE 8.55(4/4) 5.58(4/4) 0 Radiation Dose (4.0-10.1)

(7.7 10.1)

(4.9-6.8)

(mR/std. month)

(Regular TLDs) i

+

4 Direct Gamma 12 0.2 5.82(11/11) 01 0.2 mi. NE 8.7(1/1) 6.5(1/1) 0 Radiation Dose (4.3-7.7)

(mR/std. Month)

(Annual TLDs)

Direct Gamma 286 0.2 6.72(254/254) 21/53 0.30 mi.

8.59(8/8) 5.53(32/32) 0 Radiation Dose (3.9-10.5)

SW (8.1 9.4)

(3.8-7.9)

(mR/std. Month)

O (Sector TLDs) v 1

LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

46

4 J

L i

k t

I 1

ii i

1 1

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4 1

i i

4 t

i i.

APPENDIX B 4

DATA TABLES

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t TABLE B-1: IODINE-131 CONCENTRATIONS IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 1996 pCi/m3 12 Sigma Page 1 of 1 l

Collection STATIONS l

Date 01 02 03 04 05 05A 06 07 21 22 23 24 JANUARY 01/03-01/11

<.008

<.00A

<.008

<.005

<.01

<.009

<.007

<.009 01/11 01/17

<.01

<.008

<.02

<.01

<.02

<.02 01/17 01/24

<.01

<.009

<.01

<.009

<.02

<.02 01/24 01/31

<.02

<.007

<.01

<.009

<.008

<.008 EEllHUARY 01/31 02/08

<.01

<.008

<.01

<.008

<.006 02/08-02/14

<.02

<.009

<.01

<.007

<.01

<.009 02/14 02/21

<.01

<.007

<.008

<.006

<.009

<.007 02/21 02/28

<.02

<.007

<.01

<.02

<.01

<.01 MABGB 02/28 03/06

<.02

<.007

<.01

<.009

<.009 03'06 03/14

<.01

<.008

<.01

<.009

<.006

<.006 03/14 03/20

<.02

<.008

<.02

<.01

<.02

<.02 03'20-03/27

<.01

<.007

<.01

<.008

<.02

<.02 03'27 04/03

<.02

<.01

<.02

<.01

<.02 AERIL 04V3 04/10

<.02

<.01

<.01 04110-04/17

<.02

<.007

<.01

<.009

<.01

< 01 04'17 04'24

<.01

<.02

<.02.

<.007

<.01

<.009

<.006 04 24 05'02

<.006

<.004

<.01

<.006

<.007

<.008

\\

1 MAY 05V2 0508

<.02

<.C2

<.008

<.02

<.01

<.02

<.01 05D8 05/15

<.01

<.009

<.008

<.009

<.007

<.009 05/15 05'22

<.02

<.007

<.01

<.009

<.008 0S'22 0579

<.01

<.006

<.008

<.005

<.006

<.008 JUNE I

05'29 06/05

<.01

<.006

<.008

<.005

<.01

<.01 06/05-06/12

<.01

<.007

<.01

<.009

<.006

<.006 06/12 06/20

<.01

<.006

<.008

<.005

<.01

<.007 06/20-06/26

<.02

<.01

<.02

<.01

<.01 06/26-07/03

<.008

<.006

<.01

<.007

<.008 O

47

l l

l TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 1996 3

pCi/m i2 Sigma Page 2 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JNLY 1

i 07/03-07/10

<.01

<.02

<.008 <.008

<.008

<.005

<.01

<.01 07/10-07/17

<.02

<.008

<.01

<.C1

<.006

<.02

<.02 07/17 07/24

<.01

<.02

<.01

<.007

<.009

<.006

<.01

<.01 07/24 07/31

<.007

<.005

<.008

<.007

<.008

<.008 AUGUST 07/31-08/07

<.01

<.008

<.009

<.01

<.007

<.006

)

08/07-08/14

<.009

<.009 <.007

<.008

<.006

<.01

<.009 08/14 08/21

<.01

<.007

<.01

<.009

<.008

<.008 08/21-08/28

<.02

<.007

<.009

<.006

<.01

<.01 SEPTEMBER 08/28 09/05

<.01

<.007

<.008

<.006

<.007 j

09/05 09/11

<.02

<.01

<.02

<.009

<.008 09/11 09/18

<.007

<.005

<.006

<.005

<.01

<.01 09/18-09/25

<.01

<.007

<.01

<.008

<.009

<.009 09/25-10/02

<.02

<.008

<.009

<.006

<.01

<.01 QCTOBER 10/02 10/09

<.01

<.02

<.01

<.02

<.007

<.009

<.007

<.01

<.01 10/09 10/16

<.02

<.01

<.007

<.01

<.009

<.02

<.01 10/16 10/23

<.01

<.007

<.01

<.009

<.008

<.008 10/23 10/31

<.01

<.006

<.01

<.007

<.01

<.01 NOVEMBER 10/31 11/06

<.02

<.009

<.02

<.01

<.02

<.01 11/06 11/13

<.008

<.009

<.006

<.008

<.006

<.01

<.01 11/13 11/20

<.007

<.005

<.01

<.008

<.006

<.008 11/20-11/27

<.02

<.008

<.02

<.01

<.009

<.01 l

11/27 12/04

<.01

<.007

<.01

<.009

<.01

<.01 DECEMBEB 12/04 12/11

<.007

<.008

<.006

<.01

<.008

<.01

<.01 12/11 12/18

<.01

<.006

<.01

<.007

<.008

<.004 12/18-12/26

<.007

<.005

<.01

<.007

<.008

<.008 12/26-01/02

<.01

<.007

<.008

<.005

<.01

<.01 1

l

\\

48

O O

O 1 AIII.E II 2

.bre s d a NORIII ANNA - 19%

(UNCI NIR AIIONS OI: GROSS IIIITA IN AIR PARTICULATES I.0E.03 pCl/m3 12 Sigma COI.LECTION AVERAGE t

DATE 01 02 03 04 05 05A 06 07 21 22 23 24 i 2 s.d.

JANUARY 01m34I/11 271 2 2412 201 2 2412 201 2 23i 2 231 2 20 i 2 2512 2112 231 2 231 2 23 1 4 01/11-01/17 2913 291 3 291 3 281 3 281 3 321 3 251 2 251 2 33 3 331 3 3113 291 3 291 5 01/17-01/24 221 2 181 2 201 2 221 2 2112 181 2 181 2 181 2 191 2 201 2 231 2 21 i 2 201 4 01/24 41/31 221 2 241 2 2412 2412 2112 241 2 191 2 201 2 231 2 2112 231 2 2512 231 4 FEBRUARY 01/31-02/08 3112 271 2 301 2 281 2 2512 291 2 281 2 2412 291 2 291 2 3112 32i 2 291 5 a

02/0842/I4 181 2 171 2 1612 161 2 1612 171 2 161 2 151 2 1712 14.1 2 181 2 181 2 171 3 02/14-02/21 18i 2 191 2 151 2 191 2 17 i 2 191 2 1712 141 2 171 2 1612 161 2 161 2 171 3 02/21-02/28 171 2 131 2 1512 1412 1712 1412 1412 121 2 1412 14 i 2 151 2 191 2 151 4 MARCH 02/28-03/06 231 2 241 2 221 2 221 2 2112 2412 231 2 181 2 23 i 2 221 2 23 2 2512 23 1 4 03/06-03/14 17 i 2 1412 171 2 151 2 161 2 151 2 I412 I412 151 2 161 2 1712 171 2 161 2 03/I4-03/20 201 2 181 2 161 2 201 2 171 2 18i 2 181 2 1612 181 2 181 2 181 2 16i 2 181 3 03/20-03/27 171 2 1512 151 2 17i 2 1312 151 2 151 2 1412 1512 14 2 1712 181 2 15i 3 03/27-04/03 171 2 131 2 141 2 1512 151 2 1412 141 2 12i 2 171 2 141 2 151 2 151 2 15 1 3 Querfer Avg. 21 i le 20 i 11 20111 20 i 10 19 i 8 20 i12 19 i 9 17 i 8 29 i12 19 i 12 21 i 11 21 i 1 1 20 i 1 0 i 2 s.d.

t'

O O

O TAltl.E Il-2 erste 2 Cl NOR~Ill ANNA - 1996 CONCI-N'IRAllONS OFGROSS IIETA IN AIR PARTICULATES 1.0E-03 pCi/m3 i 2 Sigma COI,I,ECTION AVERAGE DATE 01 02 03 04 05 OSA 06 07 21 22 23 24 i 2 s.d.

AERlL t

04!D34M/10 2112 191 2 181 2 201 2 181 2 201 2 1912 171 2 191 2 201 2 191 2 201 2 19 1 2 08/104M/17 181 2 161 2 151 2 151 2 1412 181 2 1412 1412 1612 161 2 1512 181 2 16 1. 3 38/17-n8/24 221 2 181 2 201 2 181 2 Id i 2 201 2 191 2 191 2 171 2 181 2 201 2 1712-19 i 3 nt/244)3A)2 1412 151 2 1312 1412 151 2 181 2 1211 121 1 13 2 1412 1412 151 2 14 1 3 hlAY 05/02-05/08 1512 181 2 171 2 171 2 1512 141 2 151 2 1612 181 2 1612 191 2 161 2 161 3 05/08-05/15 1612 1312 1412 151 2 1612 161 2 121 2 131 2' 1212 1011 1312 171 2 141 4 05/15-05/22 241 2 2112 191 2 241 2 231 2 231 2 221 2 201 2 201 2 221 2 2112 231 2 22 1 3 05/22-05/29 2112 181 2 161 2 1912 1612 201 2 171 2 151 2 1812 171 2 1612 191 2 18 1 4 JUNE 05/29-06/05 1312 1412 131 2 1412 121 2 1412 Ili2 1312 1412 131 2 Il i 2 1312 131 2 06/05-06/12 1812 1512 1412 1412 1412 141 2 1512 131 2 1412 14 i 2 151 2 151 2 15 1 2 06/12-06/20 221 2 1512 1612 2112 181 2 201 2 1712 191 2 1712 181 2 191 2 20 i 2 191 4 06/204)6/26 23i 2 201 2 231 2 2112 20i 2 221 2 201 2 241 2 201 2 2112 221 2 201 2 211 3 06/26-07A)3 2412 201 2 221 2 241 2 201 2 181 2 2112 191 2 191 2 201 2 231 2 241 2 211 4 Quarter Avg. 19 i 8 17 1 5 17 i 7 18 1 7 17 i 6 1816 16 i 7 1617 1716 1717

-1817 1816 17 s 7 i 2 s.d.

m.

m_

O O

O TAltl.E R-2 (Parc 3cf 43 NORTil ANNA - 1996 CONCENTR ATIONS OF GROSS IETA IN AIR PARTICULATIES 1.0E.03 pC1/m3 12 Sigma COLLECTION AVERAGE DATE 01 02 03 04 05 OSA 06 07 21 22 23 24 i 2 od.

JULY 0703-07/10 2412 2112 2112 201 2 71 17 (a) 231 2 10 i 2 201 2 2112 2112 221 2 221 2 25 1 29 07/10-07/17 191 2 171 2 181 2 191 2 181 2 201 2 151 2 161 2 151 2 161 2 1712 191 2 171 3 07/17-07/24 201 2 161 2 161 2 161 2 15 i 2 181 2 131 2 1412 1412 1612 171 2 181 2 161 4 07/24-07/31 181 2 I4t2 1412 201 2 1612 201 2 171 2 1712 171 2 1712 181 2 1712 171 4 AUGUST 07/31-0807 191 2 1812 181 2 191 2 151 2 191 2 161 2 181 2 151 2 1412 171 2 191 2 171 4 0827-08/I4 2112 151 2 201 2 201 2 171 2 201 2 181 2 191 2 1512 1712 1812 1812 181 4 08/14-08/21 301 2 241 2 281 2 2912 231 2 261 2 241 2 241 2 2112 241 2 261 2 261 2 25.1 5 08/21-08/28 2812 241 2 231 2 301 2 261 2 2512 241 2 231 2 271 2 291 2 3112 3112 271 6 SEPTEMBER u,

w 08/28-09M5 331 2 301 2 271 2 3112 28 2 27 i 2 281 2 28i 2 261 2 2912 301 2 28 i 2 Di4 09/05-09/11 2112 181 2 201 2 231 3 181 2 221 2 1712 201 2 221 3 231 2 181 2 1912 20 1 4 09/11-09/18 241 2 201 2 1712 2112 201 2 221 2 2112 201 2 191 2 2412 2112 2112 211 4 09/184)9/25 31 i 2 241 2 271 2 281 2 251 2 281 2 271 2 271 2 2912 321 2 261 2 2912 28 1 5 09/25-10/02 281 2 271 2 271 2 281 2 261 2 301 2 2512 281 2 261 2 301 2 27 i 2 261 2 27 1 3 Quarter Avg. 24 i 10 21 i 10 21 i le 23 i 10 25129 23 1 8 20 i le 2119 21 i 10 23 i 12 22 i le 23 i 1 0 22 1 3 1 2 s.d.

Y l

(a) Im sample volume.

s.

.._m..

fK V

f s

o "LE H-2 (Page 4 of Al NORTil ANNA - 1996 CONCTNTR ATIONS OF GROSS 13 ETA IN AIR PARTICULATES 1.0E-03 pC1/m3 12 Sigma COLLECTION AVERAGE DATE 01 02 03 04 05 OSA 06 07 21 22 23 24 i 2 s d.

OCTOBER 10A)2-10/09 151 2 131 2 1512 161 2 1412 131 2 1412 1212 151 2 17i2 1512 151 2 15 i 3 10/09-10/16 2512 231 2 231 2 241 2 2112 241 2 201 2 251 2 241 2 221 2 2312 231 2 231 3 10/16-10/23 221 2 251 2 251 2 261 2 2112 231 2 241 2 2912 231 2 301 3 261 2 251 2 251 5 10/23-10/31 281 2 251 2 271 2 241 2 231 2 24i 2 261 2 271 2 25 2 261 2 24i 2 2512 25i 3 NOVEMBER 10/31-II A)6 27i 2 251 2 261 2 1912 281 2 261 2 24i 2 281 2 251 2 241 2 251 2 24i 2 25 i 5 II A)6-II/13 151 2 131 2 1412 151 2 131 2 1312 151 2 121 2 14 i 2 1412 151 2 16 i 2 141 2

{

11/I3-11/20 2512 181 2 1912 231 2 191 2 8.5 i 1.4 231 2 201 2 2112 201 2 221 2 211 2 20 1 8 c.n 11/20-11/27 191 2 191 2 1912 211 2 201 2 191 2 231 2 191 2 191 2 2112 2112 211 2 20 1 3 N

11/27-12,04 231 2 221 2 201 2 241 2 221 2 231 2 231 2 181 2 22i 2 221 2 24i 2 221 2 22 1 3 DECEMBER 12/04-12/11 26i 2 191 2 231 2 241 2 231 2 221 2 241 2 20i 2 221 2 2112 2512 241 2 23 1 4 12/11-12/18 1712 141 2 1612 171 2 171 2 141 2 161 2 1312 1612 161 2 161 2 151 2 16 i 3 12/18-12/26 28i 2 231 2 261 2 241 2 231 2 261 2 251 2 201 2 231 2 231 2 271 2 2512 24 1 4 12/26-0I Al2 321 2 261 2 301 2 3412 281 2 3; i 2 29 i 2 241 2 281 2 3112 281 2 3112 29 1 6 l

Quarter Avg. 23 i ll 20ile 22 i le 22 i 10 2119 21113 2219 21 i l2 21 i s 22 i le 2219 22 i 9 22 i 5 1 2 s.d.

Annual Avg. 22 i le 19 i 9 20 i 10 20110 20 i 17 20 i 10 19 i 10 20 i 10 20 i 11 21120 21110 21 i 9 29i 11 1 2 s.d.

L 1

5 6

m

TABLE B-3: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES O

sorin ^mme eo er stetica. touise couary. vireiaie - 1998 1.0 E-03 pC1/m3 2 Sigma Page 1 of 3 First Second Third Fourth l

Quarter Quarter Quarter Quarter Average Station Nuclide 12/27-03/27 03/27-07/03 07/03-10/02 10/02-01/02 2 s.d.

4 STA-01 Sr-89 (a)

< 0.4 (a)

(a)

Sr 90 (a)

< 0.07 (a)

(a)

De-7 84.6 8.5 101i 10 100 10 65.8 6.6 87.9 33.0 i

K-40

< 10

<5

<7 Co-60

< 0.3

< 0.2

< 0.3 Ru 103

< 0.4

< 0.3

< 0.2

< 0.3 Cs-134

< 0.3

< 0.2

< 0.2 Cs-137

< 0.3

< 0.2 Th-228

< 0.5

< 0.4

< 0.3 STA-02 Sr-89 (a)

< 0.5 (a)

(a)

Sr 90 (a)

< 0.1 (a)

(a)

Be-7 75.4 7.5 79.4 7.9 77.5 7.7 61.1 6.1 73.4 16.7 K 40

<5 3.95 1.75

<5 3 99 1.47 3.9710.06 Co-60

< 0.3

< 0.3 Ru 103

< 0.2

< 0.3

< 0.3 Cs 134

< 0.3

< 0.2

< 0.3

< 0.2 Cs-137

< 0.3

< 0.2

< 0.3 Th-228

< 0.4

< 0.3

<03

< 0.4 STA-03 Sr89 (a)

< 0.4 (a)

(a)

St 90 (a)

< 0.07 (a)

(a) 4 Be-7 69.5 6.9 81.6 8.2 89.1 8.9 63.7 6.4 76.0 23.0 4

K 40 4.14 2.20

<9 3.05 i 1.49

<5 3.60 i 1.5 Co-60

< 0.3

< 0.2

< 0.3

< 0.2 Ru 103

< 0.3

< 0.2

< 0.3 Cs-134

< 0.2

< 0.3

< 0.2

< 0.2 Cs 157

< 0.2

< 0.3

< 0.2 Th 228

< 0.3

< 0.4

< 0.3

< 0.3 l

STA 04 Sr-89 (a)

< 0.4 (a)

(a)

Sr-90 (a)

< 0.08 (a)

(a)

Be 7 91.6 9.2 1141 11 89.7 i 9.0 69.2 6.9 91.1136.6 K-40

<5 3.54 1.78

< 10

<4 3.54 i 1.78 Co-60

< 0.2

< 0.3

< 0.2 Ru 103

< 0.3

< 0.4

< 0.2 Cs 134

< 0.3

< 0.2

< 0.3

< 0.2 Cs 137

< 0.2

< 0.3

< 0.3 Th-228

< 0.4

< 0.5

< 0.3 4

O All gamma emitters other than those hsted we'e <LLD.

(a) Strontium-89/90 analyses performed ordy or: second quar 1er samples.

l 53

TABLE B-3: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES OV North Anna Power Station, Louisa County, Virginia - 1996 1.0 E-03 pCl/m3 2 Sigma Page 2 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/27-03/27 03/27-07/03 07/03 10/02 10/02-01/02 2 s.d.

1 J

STA-05 Sr-89 (a)

< 0.5 (a)

(a)

Sr-90 (a)

< 0.1 (a)

(a)

Be-7 65.9 i 6.6 81.8 i 8.2 98.7 i 9.9 59.8 6.0 76.6 i 34.9 K 40

<4

<7

<5

<7 Co 60

< 0.3

< 0.2

< 0.3

< 0.3 Ru-103

< 0.3

< 0.2

< 0.3

< 0.3 Cs-134

< 0.2

< 0.3

)

Cs-137

< 0.3

< 0.2

< 0.3

< 0.2 Th-228

< 0.4

< 0.3

< 0.4

< 0.3 STA-05A Sr 89 (a)

< 0.5 (a)

(a) l Sr 90 (a)

< 0.1 (a)

(a)

Be-7 75.9 7.6 94.1 i 9.4 88.1 8.8 64.6 i 6.5 80.7 26.2 K-40 4.33 1.60

<5 5.66 2.25

<5 Co-60

< 0.2

< 0.3

< 0.2 Ru 103

< 0.2

< 0.3

< 0.3 Cs-134

< 0.2

< 0.3

< 0.2 Cs-137

< 0.2

< 0.3

< 0.3 Th-228

< 0.3

< 0.4

< 0.5 7

STA-06 Sr 89 (a)

< 0.4 (a)

(a)

Sr-90 (a)

< 0.1 (a)

(a)

)

Be 7 71.5 i 7.1 78.9 i 7.9 93.3 9.3 58.4 i 5.8 75.5 i 29.1 K-40

<9

<6

<4

<6 i

Co-60

< 0.3

< 0.2

< 0.2 Ru-103

< 0.3

< 0.3 Cs 134

< 0.3

< 0.2

< 0.2 Cs 137

< 0.3

< 0.2

< 0.2 Th-228

< 0.4

< 0.3

< 0.4

< 0.3 STA-07 Sr 89 (a)

< 0.4 (a)

(a)

Sr-90 (a)

< 0.07 (a)

(a)

Be 7 72.0 7.2 93.7 i 9.4 87.5 i 8.7 73.1 i 7.3 81.6 21.5 K 40

<5 2.43 1.16 10.3 2.6 4.06 i 2.15 5.60 i 8.31 Co-60

< 0.3

< 0.2

< 0.3

< 0.2 Ru 103

< 0.3

< 0.2

< 0.3

< 0.3 Cs-134

< 0.2

< 0.3

< 0.2 Cs 137

< 0.3

< 0.2

< 0.3

< 0.3 Th-228

< 0.4

< 0.5 O.

All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed only on second quarter samples.

54

TABLE B-3: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES

\\

North Anna Power Station, Louisa County, Virginia - 1996 1.0 E-03 pCi/m3 2 Sigma Page 3 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/27-03/27 03/27-07/03 07/03-10/02 10/02-01/02 2 s.d.

STA-21 St89 (a)

< 0.6 (a)

(a)

Sr90 (a)

< 0.1 (a)

(a)

Be-7 86.4 8.6 68.4 6.8 88.7 8.9 60.9 6.1 76.1 27.2

)

K-40

<5

<3

<4

<9

)

Co-60

< 0.4

< 0.2

< 0.3 Ru 103

< 0.3

< 0.2

< 0.3

< 0.4 Cs 134

< 0.3

< 0.2

< 0.3 Cs-137

< 0.2

< 0.3 Th-228

< 0.6

< 0.3

< 0.4 STA 22 Sr-89 (a)

< 0.8 (a)

(a)

Sr 90 (a)

< 0.3 (a)

(a)

Be-7 67.5 6.7 81.8 8.2 92.2 9.2 63.6 6.4 76.3 26.4 K 40

<8

<4 4.77 1.61

<4 4.77 1.61 Co-60

< 0.3

< 0.2

< 0.2 Ru-103

< 0.3

< 0.2

< 0.3 Cs 134

< 0.3

< 0.2

'Cs 137

< 0.3

< 0.2

< 0.3 f)

Th-228

< 0.4

< 0.3

< 0.3 v

STA 23 Sr 89 (a)

< 0.6 (a)

(a)

Sr 90 (a)

< 0.2 (a)

(a)

Be 7 82.5 8.3 90.4 9.0 80.8 8.1 64.8 6.5 79.6 i 21.5 K 40 3.69 1.67 3.13 1.30

<8

< 10 3.41 0.8 Co-60

< 0.3

< 0.2

< 0.3

< 0.3 Ru 103

< 0.2

< 0.3

< 0.4 Cs 134

< 0.2

< 0.3

< 0.3 Cs 137

< 0.3

< 0.2

< 0.3

< 0.3 Th 228

< 0.4

< 0.3

< 0.4

< 0.5 STA 24 St-89 (a)

< 0.5 (a)

(a)

Sr90 (a)

< 0.1 (a)

(a)

Be 7 81.1 8.1 87.1 8.7 109i11 70.017.0 86.81 32.8 K-40 3.961 1.81 5.861 2.09

<5

<4 4.91 i 2.69 Co-60

< 0.2

< 0.3

< 0.2 Ru 103

< 0.2

< 0.3

< 0.3 Cs 134

< 0.2

< 0.3

< 0.2 1

1 Cs 137

< 0.3

< 0.2

< 0.3

< 0.3 l

Th-228

< 0.3

< 0.5

< 0.4 1

O All gamma emitters other than those listed were <LLD.

(a) Strontium-89/90 analyses performed only on second quarter samples.

55

N TABLE B-4: GROSS BETA, TRITIUM AND GAMMA EMITTER *

(}

CONCENTRATIONS IN PRECIPITATION Station 01A -(On Site)

North Anna Power Station, Louisa County, Virginia - 1996 pCl/li 2 Sigma Page 1 of 1 4

l l

Collection Dates Gross Beta Rainfall (inches) i 12/27/95-01/31/96 3.2 0.7 3.32 02/01/96-02/28/96 7.1 i 1.0 1.40 1

{

02/28/96-03/27/96 4.3 i 0.8 1.45 l

03/27/96-04/24/96 3.0 0.7 3.80 04/24/96-05/29/96 3.1 0.7 4.46 05/29/96-06/26/96 63i 0.9 2.82 06/26/96-07/31/96 2.4 0.7 10.75 07/31/96-08/28/96 3.1 0.7 3.02 l

08/28/96-09/25/96 1.7 0.6 6.49 09/25/96-10/31/96 1.5 0.6 4.99 l

10/31/96 11/27/96 1.4 i 0.6 2.97 11/27/96 12/26/96 1.8 0.6 4.35 Average i 2 s.d.

3.2 i 3.7 e

SEMI-ANNUAL PRECIPITATION COMPOSITES 12/27/95-06/26/96 06/26/96-12/26/96 Be-7 = < 30 Be-7 = < 40 1

H-3 = < 200 H-3

< 200

=

TABLE B-5 SOIL i

Soil samples are collected every three years from twelve stations. Since the samples i

A were collected in 1995, Table B-5 will not be included in the 1996 report.

V All gamma emitters other than those listed were <LLD.

)

56

TABLE B-6: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS IN GROUND AND WELL WATER

\\

North Anna Power Station, Louisa County, Virginia - 1996 pCl/li 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr 90 H-3 Be-7 K-40 1-131 Ba-140 Th-228 STATIONRIA 03/27/96 (a)

(a)

< 200

< 40

< 100

< 0.5

<9

<7 06/26/96

< 0.7

< 0.5

< S00

< 30

< 70

< 0.2

<7

<6 1

09/25/96 (a)

(a)

< 200

< 40

< 100

< 0.3

<6

<8 12/26/96 (a)

(a)

< 200

< 30

< 80

< 0.2

<5

<8 j

All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed only on second quarter sample.

l TABLE B-7: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 1996 pCl/li 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr 90 H-3 Be-7 K-40 1-131 Cs-137 Ba 140 Ra-226 Th-228 STATION - 11 i

01/17/96 (a)

(a) 3800 i 200

< 30

< 50

< 0.2

<3

<4

< 60

<6 i

02/22/96 (a)

(a)

(b)

< 30

< 90

< 0.3

<3

<4

< 60

<5 i

03/20/96 (a)

(a)

(b)

< 30

< 80

< 0.6

<3

<9

< 60

<5 04/15/96 < 1

< 0.3 2500i 200

< 40

< 100

< 0.3

<4

<6

< 70

<6 05/13/96 (a)

(a)

(b) c 30

< 50

< 0.4

<4

<5

< 60

<5 06/19/96 (a)

(a)

(b)

< 40

< 60

< 0.4

<4

<8

< 100

<8 07/17/96 (a)

(a) 3100 200

< 30

< 50

< 0.3

<3

<6

< 80

<7 08/21/96 (a)

(a)

(b)

< 30

< 70

< 0.2

<3

<5

< 60

<6 09/18/96 (a)

(a)

(b)

< 30

< 100

< 0.3

<4

<5

< 70

<6 10/17/96 (a)

(a) 24001200

< 30

< 60

< 0.3

<4

<7

< 80

<7 11/15/96 (a)

(a)

(b)

< 40

< 90

< 0.3

<4

<7

< 70

<6 12/18/96 (a)

(a)

(b)

< 30

< 40

< 0.5

<3

<4

< 60

<6

,q Average i 2 s.d.

2950 i 1291 O

All gamma emitters other than those listed were <LLD.

(a)

Sr 89/90 analyses performed only on second quarter samples.

(b)

Tritium analysis performed on quarterly composite.

57

i i

TABLE B-8: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS IN O

SURFACE WATER O

North Anna Power Station, Louisa County, Virginia - 1996 pCl/li 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131 "

Cs 137 Da-140 Ra-226 Th-228 STATION - 08 01/17 (a)

(a) 3700 200

< 30

< 50

< 0.2

<4

< 60

<5 02/22 (a)

(a)

(b)

< 30

< 70

< 0.2

<3

<4

< 60

<5 03/20 (a)

(a)

(b)

< 30

< 50

< 0.8

<3

<8

< 70

<6 04/15

<2

< 0.4 21001200

< 40

< 60

< 0.2

<5

<8

< 100

<9 05/13 (a)

(a)

(b)

< 30

< 60

< 0.6

<4

<6

< 100

<8 06/19 (a)

(a)

(b)

< 30

< 50

< 0.4

<4

<8

< 90

<7 07/17 (a)

(a) 42001300

< 30

< 50

< 0.2

<4

< 70

<6 08/21 (a)

(a)

(b)

< 30

< 60

< 0.2

<3

<6

< 60

<5 09/18 (a)

(a)

(b)

< 30

< 90

< 0.2

<4

<5

< 70

<6 10/17

<2

< 0.6 2600 i 200

< 30

< 50

< 0.3

<4

<6

< 70

<6 11/15 (a)

(a)

(b)

< 30

< 80

< 0.3

<3

<4

< 60

<5 i

12/18 (a)

(a)

(b)

< 20

< 50

< 0.3

<3

<4

< 50

<4 O

Avg.

3150 1936 i 2. s.d.

STATION - 09A 01/17 (a)

(a)

< 200

< 30

< 90

< 0.2

<4

<5

< 70

<6 4

02/22 (a)

(a)

(b)

< 30

< 100

< 0.3

<4

<6

.< 70

<6 03/20 (a)

(a)

(b)

< 30

< 50

< 0.9

<3

<8

< 80

<7 l

04/15

<2

< 0.4

< 300

< 30

< 50

< 0.4

<3

<4

< 70

<6 05/13 (a)

(a)

(b)

< 30

< 60

< 0.3

<4

<5

< 70

<6 06/19 (a)

(a)

(b)

< 30

< 60

< 0.4

<4

<8

< 90

<7 07/17 (a)

(a) 3201150

< 30

< 70

< 0.3

<3

<4 e 60

<5 08/21 (a)

(a)

(b)

< 30

< 50

< 0.3

<4

<7

< 70

<7 09/18 (a)

(a)

(b)

< 30

< 70

< 0.2

<3

<5

< 60

<5 10/17

<1

< 0.2

< 200

< 30

< 50

< 0.4

<3

<5

< 70

<6 11/15 (a)

(a)

(b)

< 20

< 50

< 0.3

<3

<4

< 40

<4 12/18 (a)

(a)

(b)

< 20

< 60

< 0.4

<3

<4

< 50

<5 Avg.

320 150

2. s.d.

O-All gamma emitters other than those listed were <LLD.

l-131 by radiochemistry (a) Analysis performed only with second quarter.

(b) Analysis performed quarterly.

58

_~

l TABLE B-9: GAMMA EMITTER

AND TRITIUM CONCENTRATIONS 0,

IN SURFACE WATER State-Split Samples North Anna Power Station, Louisa County, Virginia - 1996 pCi/l 2 Sigma Page 1 of 1 li Collection Dates H-3 Be-7 K-40 1-131 Cs-137 Ba-140 Ra-22G Th-228 STATION - W 27 i

01/31

< 200

< 40

< 90

< 0.6

<4

< 10

< 70

<6 02/29 (a)

< 30

< 50

<1

<4

< 10

< 60

<5 03/31 (a)

< 30

< 50

< 0.5

<4

<9

< 70

<6 04/30

< 200

< 40

< 90

< 0.4

<4

<8

< 70

<6 05G1 (a)

< 30

< 50

< 0.3

<4

<6

< 70

<6

)

06/30 (a)

< 50

< 100

< 0.6

<5

< 10

< 90

<8 l

07/31 600 40 (b) < 30

< 50

< 0.4

<4

<6

< 70

<6 1

08/31 (a)

< 40

< 50

< 0.5

<4

< 10

< 90

<7 09/30 (a)

< 50

< 2 (c)

<4

< 30

< 70

<6 10/31 1000 200

< 30

< 50

< 0.3

<4

<7

< 70

<6 11/15 (a)

< 40

< 50

< 2 (c)

<3

< 20

< 90

<7 12/31 (a)

< 50

< 100

< 0.5

<5

< 10

< 80

<7 O

Avg.

800 566

2 s.d.

STATION W-33 I

0101 4100 ! 200

< 50

< 100

< 0.6

<5

< 10

< 80

<7 02/29 (a)

< 30

< 80

<1

<3

<2

< 60

<5 OM1 (a)

< 40

< 100

< 0.4

<4

< 10

< 70

<6 0400 29001200

< 40

< 60

< 0.4

<5

<9

< 100

<9 05/31 (a)

< 40

< 100

< 0.4

<4

<7

< 70

<6 06/30 (a)

< 30

< 70

< 0.5

<3

<8

< 60

<6 07/31 22401330 (b) < 30

< 60

< 0.3

<3

<6

< 60

<5 08/31 (a)

< 40

< 70

< 0.4

<4

< 10

< 90

<8 09/30 (a)

< 50

< 100

< 2 (c)

<4

< 30

< 70

<7 10/31 27001200

< 40

< 80

< 0.6

<4

<8

< 70

<6 11/15 (a)

< 50

< 70

<1

<4

< 20

< 90

<8 12/31 (a)

< 30

< 70

< 0.5

<3

<8

< 60

<6 Avg.

2985 1586 2 s.d.

All gamma emitters other than those listed were <LLD.

(a) Tntium analysis performed on the first monthly composite of each quarter.

t (b) Tritium analysis not requestsed from contract laboratory. Results obtained from Virginia State laboratory.

(c) LLD not met due to the long delay from collection date to receipt at laboratory (30 days).

59 r

TABLE B-10: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN SEDIMENT SILT North Anna Power Station, Louisa County, Virginia - 1996 pCi/kg 12 Sigma Page 1 of 1 STA-08 STA-09A STA-11 STA-08 STA-09A STA-11 Average Nuclide 02/22 02/22 02/22 08/12 08/12 08/12 2 Sigma Sr 89 (a)

(a)

< 0.5

< 0.4

< 0.3 Sr 90 (a)

(a)

< 0.06

<0.04

< 0.04 Be-7

< 200

< 300

< 200

< 300

< 400 K 40 6460 650 12400 1200 22200 2200 21701270 11800 1 1200 14500 1 1500 115881 13764 Mn 54

< 20

< 30

< 20

< 30

< 40 Co-58

< 20

< 30

< 20

< 30

< 30 Co-60

< 20

< 30

< 40

< 20

< 30

< 40 Cs-134

< 30

< 40

< 50

< 20

< 30

< 50 Cs 137 42.1 20.9 69.41 27.4 255 38

< 30 49.5 20.0

< 40 104 203 Ra 226 1040 380 1470 470 1630 470 1040 1 370 1490 430 1990 1 600 1443 728 Th-228 732 73 939 ! 94 1140 110 501 50 631 2 63 1020 100 827 491 l

1 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed annually.

(

TABLE B-11: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN j

SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 1996 pCi/kg 2 Sigma Page 1 of 1 Station-09 Station-08(b)

Average Nuclide 02/13 08/12 i 2 Sigma St89 (a)

< 0.1 Sr 90 (a) 0.064 0.02 0.064 i 0.02 Be-7

< 600

< 200 j

K-40 11300 1100 1340 1 220 6320 i 14086 Mn 54

< 60

< 20 Co-58

< 50

< 20 Co-60

< 60

< 20 Cs-134

< 70

< 30 Cs-137 598 74 421 42 510 i 250 Ra-226 3740 910 833 358 2287 1 4111 Th-228 2110 1 210 233 28 1172 i 2654 1

All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed annually.

(b) Shoreline soil location moved to station 08.

60

a TABLE B-12: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN MILK North Anna Power Station, Louisa County, Virginia - 1996 pCi/li 2 Sigma Page 1 of 1 MONTH NUCLIDE STATION-12 STATION-13 JANUARY Sr-89

<1

<1 Sr-90 0.81 i 0.20 1.2 i 0.2 K-40 1270 1 130 1410 140 Cs-137

<4

<4 l-131

< 0.3

< 0.3 FEBRUARY Sr 89 (a)

(a)

Sr-90 (a)

(a)

K 40 1350i 140 13301 130 Cs-137

<4

<4 1131

< 0.2

< 0.3 MARCH Sr 89 (a)

(a)

Sr 90 (a)

(a)

K-40 1430 140 1450 140 Cs 137

<5

<5 l131

< 0.3

< 0.3 e

APRIL Sr-89

<1

<3 t

Sr-90 0.86 0.14 1.41 0.2 K-40 1390 140 1300i 130 Cs 137

<4

<4 l131

< 0.3

< 0.3 MAY Sr 89 (a)

(a)

Sr 90 (a)

(a)

K-40 1420 140 1180 120 Cs-137

<4

<4 1-131

< 0.3

< 0.2 JUNE Sr-89 (a)

(a)

Sr-90 (a)

(a)

K-40 1350 140 1340 130 Cs 137

<3

<7 l-131

< 0.4

< 0.5

/'%

V All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter.

61

l TABLE B-12: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONSIN MILK O

norin rome eowersteiioo.touise coumiv.vireioie-,eee pCi/li 2 Sigma Page 2 of 2 l

MONTH NUCLIDE STATION 12 STATION-13 JULY Sr 89

<1

<2 Sr 90 1.010.2 1.7 0.2 K-40 1260 130 1170 120 Cs 137

<4

<4 l131

< 0.2

< 0.2 AUGUST Sr-89 (a)

(a)

Sr-90 (a)

(a)

K-40 1310 130 1400 i 140 Cs 137

<4

<4 l131

< 0.2

< 0.3 SEPTEMBER Sr-89 (a)

(a)

Sr-90 (a)

(a)

K-40 1430 i 140 1220 120 Cs-137

<4

<4 l131

< 0.2

< 0.2 OCTOBER Sr 89

<2

<2 (O

Sr-90 1.0 i 0.2 0.951 0.18 K-40 1440 140 1230 120 Cs-137

<3

<4 l-131

< 0.4

< 0.2 NOVEMBER Sr-89 (a)

(a)

St-90 (a)

(a)

K-40 1310 130 1230 120 Cs 137

<4

<4 l131

< 0.2

< 0.2 DECEMBER Sr-89 (a)

(a)

Sr-90 (a)

(a)

K 40 1390 140 1260 i 130 Cs 137

<3

<4 l-131

< 0.5

< 0.5 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter.

62 l

N TABLE B-13: GAMMA EMITTER

CONCENTRATIONSIN FISH O

~o,1n ^ooe ee er sietioo. Louise couaix. viroioie -,eee pCl/kg 2 Sigma Page 1 of 1 Collection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 l

02/13 08 Fish (a) 1990 220

< 20

< 20 54.8 i 15.1 03/06 08 Catfish (b) 1940 i 190

< 20

< 20 51.1 i 15.0 i

03/06 25 Catfish (b) 23201 230

< 10

< 20 i

j 03/14 25 Fish (a) 1400 210

< 20

< 20 08/13 08 Fish (a) 1760 240

< 20

< 20 i

08/13 25 Fish (a) 2620 290

< 20

< 20 08/16 08 Catfish (b) 1600 i 220

< 20

< 20 53.6 16.4 i

08/14 25 Catfish (b) 2420 240

< 20

! O l

Avg.

2006 843 53.2 i 3.8

2 s.d.

i i

All gamma emitters other than those listed were <LLD.

(a) Non-bottom dwelling species of gamefish.

(b) Bottom dwelling species of fish.

63

TABLE B-14: GAMMA EMITTER

CONCENTRATIONS IN FOODNEGETATION O

~or1n Amoe eower steiioo. Louise couaiv, viroioie -,eee a

pCi/kg i 2 Sigma Page 1 of 2 Collection Date Be-7 K-40 1-131 Ru 103 Cs 134 Cs 137 Ra-226 Th-228 There were no food / vegetation samples for all stations during the first quarter,1996 due to seasonal unavailability.

STATION 14 1

04/17 2020 200 20400 i 2000

<9

< 20

< 300

< 30 05/15 2720 280 22500 2200

< 30

< 40

< 40 71.3 33.4

< 600

< 60 06/20 1530 450 159001 1600

< 10

< 60

< 50

< 1000

< 100 07/17 2470 260 13900t 1400

< 20

< 30

< 500

< 40 08/21 7920 790 234001 2300

<9

< 50

< 40

< 50

< 700

< 70 09/18 9320 930 97801 980

< 20

< 60

< 50

< 900

< 80 4

10/16 7640 760 16000 1600

< 10

< 60

< 50

<800

< 70 STATION 15 04/17 3530 350 18400 1800

< 10

< 30

< 20

< 500

< 40 05/15 2800 300 22600 2300

< 30

< 50

< 40

< 700

< 60 06/20 2330 230 18900 1900

< 20

< 200

< 20 07/17 3150 560 18500 1900

< 20

< 70

< 60 238 56

< 1000

< 100 4

08'21 4820 480 20600 2100

< 10

< 50

< 800

< 70 09'18 2530 r 340 13100 1300

< 10

< 40

< 30

< 40

< 600

< 50 10/16 5560: 560 10600 1100

< 10

< 50

< 800

< 70 I

SIAIl0ft16 04!17 2060 1 210 10300 1000

< 10

< 200

< 20 05/15 2830 280 24200 2400

< 20

< 30

< 500 115 i 37 06/20 4410 440 6690 i 670

< 20

< 30

< 20

< 400 93.1 i 19.8 07/17 615 112 188001 1900

< 10

< 200

< 20 08/21 9330 930 164001 1600

<9

< 50

< 40

< 50

< 700

< 70 09/18 4280 430 8090 810

< 10

< 30

< 500

< 50 i-10/16 5680 570 18300 1800

< 10

< 30

< 500

< 50 All gamma emitters other than those listed were <LLD.

64

n TABLE B-14: GAMMA EMITTEW CONCENTRATION IN FOODNEGETATION V

North Anna Power Station, Louisa County, Virginia - 1996 pCl/kg i 2 Sigma Page 2 of 2 Collection Date Be-7 K-40 1131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 STATION 21 04/17 4290 430 23200 2300

< 10

< 30

< 20

< 400

< 30 05/15 502 106 12100 1200

< 20

< 10

< 200

< 20 06/20 980 98 18200 1800

< 20

< 10

< 10 230 131

< 20 07/17 1330 140 24800i 2500

< 20

< 300

< 30 08421 15801 180 10900 1100

<7

< 20

< 20 4400

< 40 09/18 14700 1500 17500 1700

<9

< 50

< 40

< 900

< 80 10/16 6220 620 15800 1600

< 10

< 40

< 30

< 40

< 700

< 60 STATION 23 04/17 2140 210 9690 970

< 10

< 200

< 20 05/15 3620 360 13800 1400

< 20

< 30

< 30 103 24

< 500

< 50 O

06/20 612 118 8430 840

< 20

< 300

< 30 07/17 2680 270 26500 2600

< 20

< 40

< 30

< 500

< 50 08G1 2250 300 17000 1700

<8

< 40

< 600

< 60 09/18 10300 1000 9470 950

< 10

< 60

< 50

< 60

< 800

< 80 10/16 6020 600 14100 1400

< 10

< 60

< 900

< 80 Average 4136 6383 16253 10734 137 i 177 2301131 104131

! 2 s.d.

1 OV All gamma emitters other than those listed were <LLD.

65

1 I

I TABLE B-15: DIRECT RADIATION MEASUREMENTS - QUARTERLY AND ANNUAL 0

TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1996 mR/Std. Month (30.4 days)i 2 Sigma Page 1 of 1 Station First Otr Second Otr Third Qtr Fourth Otr Quarterly Annual TLD Number 12/28/95 04/01/96 06/27/96 09/26/96 Average 06/28/95-04/01/96 06/27/96 09/26/96 12/27/96 07/03/96 01 7.7 0.3 10.1 1.3 7.8 1 0.2 8.6 i 0.1 8.6 2.2 8.7 0.2 02 4.1 0.3 5.9 0.1 4.0 i 1.2 4.6 i 0.3 4.7 1.7 4.5 i 0.1 03 4.0 0.3 5.8 t 0.2 4.4 0.2 4.3 i 0.3 4.6 i 1.6 4.3 1 0.3 04 4.1 0.3 5.9 0.2 4.5 i 0.2 4.4 1 0.5 4.7 1.6 4.9 0.1 05 4.9 0.6 7.0 0.2 5.5 i 0.1 4.9 i 1.7 5.8 2.0 5.7 0.1 05A 4.5 0.5 6.5 0.3 5.3 0.1 5.1 0.6 5.4 1.7 5.2 1 0.1 06 5.9 0.5 7.9 0.2 6.3 0.6 6.8 0.2 6.7 1.7 6.8 1 0.2 07 4.7 0.2 6.5 0.1 5.2 0.4 5.7 0.5 5.5 1.5 5.3 i 0.2 21 4.7 0.3 6.6 0.3 4.9 1.1 5.7 i 0.6 5.5 1.7 5.2 0.1 V

22 5.5 0.2 7.9 1 0.5 6.4 0.9 7.0 0.2 6.7 i 2.0 6.4 i 0.2 23 6.3 : 0.3 8.3 0.2 6.7 0.9 7.5 1 0.3 7.2 1.8 7.0 0.1 24 4.9 0.3 6.8 i 0.2 5.2 0.1 5.4 i 0.3 5.6 i 1.7 6.5 0.3 Average 5.1 2.2 7.1 2.5 5.5 2.2 5.8 2.7 5.9 2.8 5.9 2.5

2 s.d.

D 66

TABLE B-16: DIRECT RADIATION MEASUREMENTS-0 SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1996 mR/Std. Month (30.4 days) 2 Sigma Page 1 of 2 Station First Qtr.

Second Qtr.

Third Qtr.

Foruth Qtr.

Average Number 12/28 04/01 04/01-06/27 06/27-09/26 09/26-12/27 i 2 s.d.

N1 6.1 0.4 8.1 i 0.4 6.6 0.1 6.9 i 0.3 6.9 i 1.7 N-2 4.7 0.2 6.61 0.4 5.4 i 0.2 5.1 1 0.2 5.5 i 1.6 NNE-3 8.5 0.6 10.51 0.1 8.7 0.2 8.4 i 1.1 9.0 1 2.0 NNE-4 5.3 i 0.8 6.9 i 0.1 5.9 0.1 6.2 i 0.9 6.1 i 1.3 NE-5 7.7 i 0.2 9.9 0.4 8.1 0.2 8.1 04 8.5 i 2.0 NE-6 5.2 0.4 7.1 i 0.7 5.4 1 0.2 5.7 i 0.1 5.9 1 1.7 ENE 7 6.3 i 0.1 8.2 0.4 6.9 i 0.2

~7.9 i 1.5 7.3 i 1.8 ENE-8 4.3 0.3 6.3 0.3 5.0 i 0.2 4.8 i 0.4 5.1 1.7 E9 6.5 0.3 8.41 0.4 7.0 0.1 7.2 0.2 7.3 1.6 i

E 10 5.8 1.1 7.5 0.2 6.1 i 0.2 6.6 0.6 6.5 i 1.5 ESE 11 5.9 0.5 7.5 i 0.2 6.5 0.2 6.3 0.1 6.6 1.4 ESE-12 6.2 0.3 8.110.5 5.9 1 2.3 6.9 0.2 6.8 i 2.0 SE-13 6.1 0.3 7.9 0.3 5.3 1.1 7.0 0.2 6.6 2.2 SE-14 8.2 0.2 10.1 0.2 8.0 1 0.9 8.7 0.4 8.8 i 1.9 I

SSE-15 7.1 0.2 8.1 0.2 6.1 0.6 6.7 1.1 7.0 1.7 i

SSE 16 4.9 0.2 6.5 i 0.3 4.9 0.1 5.7 0.3 5.5 i 1.5 S 17 8.2 0.1 10.0 0.1 8.1 0.1 9.0 i 0.1 8.8 i 1.8 S 18 4.2 0.1 5.7 0.1 4.1 0.0 4.7 0.1 4.7 1.5 O

SSW 19 7.1 0.5 9.2 0.6 7.3 0.3 8.2 0.5 8.0 1.9 d

SSW 20 3.9 0.2 5.5 0.2 4.2 i 0.1 4.4 0.4 4.5 1.4 SW 21 5.2 i 0.1 7.3 1.1 5.1 0.3 5.7 0.1 5.8 i 2.0 SW 22 6.0 0.1 7.8 i 0.2 6.2 0.3 7.0 0.1 6.8 i 1.6 WSW 23 7.51 0.1 9.3 t 0.4 7.7 1 0.8 8.0 0.4 8.1 i 1.6 WSW 24 6.410.5 8.2 i 0.4 6.1 0.3 6.6 0.5 6.8 i 1.9 W 25 7.8 0.3 9.6 i 0.3 7.6 0.7 8.9 1 0.5 8.5 i 1.9 W 26 4.7 0.2 6.5 0.3 5.5 0.2 5.4 0.2 5.5 1.5 WNW 27 4.7 0.7 6.31 0.2 5.3 0.1 6.0 i 0.8 5.6 i 1.4 WNW 28 4.6 0.3 6.31 0.2 5.3 0.5 5.5 1 0.4 5.4 i 1.4 NW 29 7.4 i 0.2 9.61 0.2 7.9 i 0.5 8.3 0.6 8.3 i 1.9 NW-30 4.2 0.1 6.0 1 0.2 5.0 0.1 5.2 i 0.1 5.1 i 1.5 NNW 31 5.2 0.3 6.8 i 0.1 5.9 0.3 6.3 i 0.4 6.1 i 1.4 NNW 32 5.3 i 0.3 7.11 0.3 6.5 0.8 6.2 1.0 6.311.5 N 33 6.1 1 0.1 7.8 i 0.3 6.6 i 0.2 7.0 0.2 6.9 i 1.4 N 34 4.7 0.1 6.4 0.2 5.3 0.1 5.7 i 0.2 5.5 i 1.4 NNE 35 8.51 0.6 10.2 i 0.1 9.0 0.3 9.3 i 0.5 9.3 1 1.4 NNE 36 5.0 0.1 6.9 0.3 5.9 0.5 6.0 0.4 6.0 i 1.6 NE 37 7.8 i 0.2 9.410.1 8.2 i 0.2 8.7 i 0.4 8.5 i 1.4 NE 38 5.110.2 6.9 i 0.2 5.9 i 0.1 5.9 i 0.2 6.0 1.5 ENE 39 6.31 0.2 8.4 0.5 7.0 0.3 7.4 t 0.2 7.3 i 1.8 ENE-40 4.410.1 6.110.0 5.0 0.5 5.2 i 0.2 5.2 i 1.4 E-41 6.7 0.1 8.5 0.5 7.4 i 0.1 7.3 i 0.5 7.5 i 1.5 E-42 5.8 i 0.3 8.2 1.4 6.2 0.3 6.5 i 0.2 6.7 2.1 ESE-43 5.9 0.2 7.6 i 0.8 5.9 i 1.5 6.5 i 0.5 6.5 i 1.6 ESE-44 6.3 0.2 8.4 i 0.6 7.1 0.1 7.0 1 0.1 7.2 i 1.8 SE-45 6.2 0.4 8.4 i 0.3 6.7 i 0.2 7.1 t 1.2 7.1 i 1.9 k

67

1 TABLE B-16: DIRECT RADIATION MEASUREMENTS SECTOR QUARTERLY TLD RESULTS a

North Anna Power Station, Louisa County, Virginia - 1996 1

mR/Std. Month (30.4 days)i 2 Sigma Page 2 of 2 Station First Qtr Second Qtr Third Otr Fourth Qtr Average Number 12/28-04/01 04/01-06/27 06/27-09/26 09/26-12/27 i 2 S.d.

s SE-46 8.1 0.2 10.1 i 0.3 8.9 1 0.3 9.2 0.5 9.1 1.7 SSE 47 6.5 0.2 8.5 i 0.2 6.8 0.3 7.4 1 0.1 7.3 i 1.8 SSE-48 5.1 1 0.3 7.0 i 0.3 5.6 i 0.4 5.6 i 0.3 5.8 1 1.6 S 49 8.2 i 0.7 10.31 0.9 8.6 1 0.3 9.2 0.5 9.1 i 1.8 S-50 4.01 0.1 5.9 i 0.3 4.5 0.9 4.8 i 0.2 4.8 i 1.6 SSW-51 7.4 0.3 9.6 i 0.5 8.3 0.6 8.3 i 0.2 8.4 i 1.8 SSW-52 4.01 0.4 6.0 i 0.9 3.9 1 1.9 4.6 i 0.1 4.6 i 1.9 SW 53 5.1 1 0.1 7.2 i 0.2 6.0 i 0.1 5.7 i 0.2 6.0 i 1.8 SW-54 6.0.

0.2 8.2 i 0.3 6.9 i 0.1 6.7 i 0.4 7.0 t 1.8 WSW 55 7.410.4 9.1 1 0.4 7.8 i 0.2 8.2 i 0.6 8.1 i 1.5 WSW 56 6.1 0.5 8.3 1.0 6.7 1 0.1 6.6 0.2 0.9 i 1.9 W-57 7.8 i 0.3 10.4 0.9 8.3 i 0.2 8.2 t 0.9 a.7 1 2.3 W 58 4.7 0.3 6.4 0.3 5.1 0.2 5.1 0.3 3.3 i 1.5 WNW 59 5.0 0.5 6.6 0.1 5.3 0.2 5.4 i 0.6 5.6 i 1.4 WNW-60 4.6 0.2 6.8 i 0.8 4.9 0.1 5.3 i 0.2 5.4 & 2.0 NW-61 7.5 1.5 9.310.2 7.7 1 0.3 8.3 i 0.5 8.2 1 1.6 NW 62 4.3 0.3 6.4 i 0.2 4.8 1 0.6 4.9 0.3 S.1 n 1.8 NNW-63 5.7 0.2 7.110.3 5.7 0.3 6.0 i 0.2 S.11: 1.3 O

NNW-64 5.3 0.4 7.21 0.3 5.8 0.4 6.1 i 0.3 S.1 1 1.6 V

C1 4.7 i 0.3 6.410.3 5.3 0.5 5.5 1 0.1 G.S t 1.4 I

C2 4.81 0.2 6.5 0.2 5.2 i 0.2 5.3 0.4 53 i1.5 I

C3 5.4 i 0.3 6.710.9 5.0 i 0.1 5.4 i 0.3 c.b i 1.5 C4 5.1 i 1.0 6.6 0.9 5.0 1 0.3 5.4 i 0.1 5.5 i 1.5 C5 4.5 0.4 6.0 1 1.6 4.1 0.2 4.5 i 0.4 4.8 i 1.7 C6 4.0 0.2 5.7 0.2 3.8 0.7 4.2 i 0.6 4.4 i 1.7 C7 6.0 0.3 7.4 t 0.4 6.4 1 0.1 5.5 i 3.1 6.3 1.6 C8 5.8 0.2 7.9 0.4 6.1 0.3 6.7 1 0.3 6.6 i 1.9 Average 5.9 i 2.6 7.7 i 2.7 6.2 i 2.6 6.6 i 2.7 6.6 i 3.0 0

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APPENDIX C Um LAND USE CENSUS - 1996 1

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VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 1996 July (I-31)

Nearest Nearest Site Milch

Meat Milch

Veg. Garden Sector Resident Boundary Cow Animal Goat 500 Sq Ft.

KM KM KM KM KM KM N

2.14 1.40 3.23 2.98 NNE

!.51 1.36 4.22 1.87 NE 1.57 1.32 2.51 1.80 ENE 3.17 1.31 4.12 3.17 E

1.95 1.33 1.95 l

ESE 2.53 1.37 7.74 5.63 SE 2.20 1.41 2.20 2.20 j

SSE I.47 1.47 3.83 2.30 oV S

1.67 1.52 2.32 1.96 SSW 2.30 1.62 6.61 2.20 SW 4.83 1.70 4.83 WSW 2.86 1.75 2.86 2.86 W

2.48 1.71 3.20 WNW l.6 l 1.64 6.13 4.28 NW l.57 1.56 1.77 NNW l.72 1.45 3.57 1.80 AV

Note:

No milch cow or goats within a five mile radius of North Anna Power Station KM = Kilometer 69

VIRGINIA POWER NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 1996 July (1-31)

Nearest Nearest Site Milch

Meat Milch

Veg. Garden Sector Resident Boundary Cow Animal Goat 500 Sq Ft.

M M

N 1.33 0.87 2.01 1.85 NNE 0.94 0.85 2.62 1.16 NE 0.98 0.82 1.56 1.12 ENE 1.97 0.81 2.56 1.97 E

1.21 0.83 1.21 ESE 1.57 0.85 4.81 3.50 SE 1.37 0.88 1.37 1.37 SSE 0.91 0.91, 2.38 1.43 S

1.04 0.94 1.44 1.22 SSW l.43 1.01 4.11 1.37 SW 3.00 1.06 3.00 WSW l.78 1.09 1.78 1.78 W

l.54 1.06 1.99 WNW l.00 1.02 3.83 2.66 i

NW 0.98 0.97 1.10 i

NNW 1.07 0.90 2.22 1.12 O

Note:

No milch cow or goats within a five mile radius of North Anna Power Station M = Mile 70

VIRGINIA POWER NORTH ANNA POWER STATION COMPARISON OF THE 1996 TO 1995 LAND USE CENSUS I.

Changes in the nearest resident status as compared te previous year are as follows:

a.

W Sector:

2.60 Km (1995) to 2.48 Km (1996)

II.

No changes were observed in the nearest site boundary distances.

111.

No changes were observed in the nearest milch cow / goat status.

IV.

Changes in nearest vegetable garden as compared to previous year are as follows.

a.

SSE Sector:

1.55 Km (1995) to 2.30 Km (1996) b.

S Sector:

1.67 Km (1995) to 1.96 Km (1996) i V.

No changes were observed in the nearest meat animal status.

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APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES

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i ANALYTICAL PROCEDURES SYNOPSIS

- Appendix D is a synopsis of the analytical procedures performed on samples collected for the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Brown Engineering and include those i

recommended by the USNRC Branch Technical Position, Rev.1, November 1979.

1 l

l ANALYSIS TITLE PAGE G ros s B eta An alysis of S amples...................................................................... 73 1

i Airborne Panic ul ates............................................................................ 7 3 l

Water.............................................................................................74 Analysis of Samples for Tritium (Liquid Scintillation).......................

................75 Analysis of Samples for Strontium-89 and -90.....................

...................76 To ta l Wa t e r................................................................................ 7 6 Milk....................................................................

......................76 S oil and S ed ime n t.............................................

.............................76 Org anic S ol i d s.............................................................................. 7 7 O

Air PartieuIates...............................................................................77 A nalysis of Samples for lodine-131................................................................. 79 M i l k o r Wa t e r................................................................................ 7 9 G a mma S pect rome try o f S amples................................................................... 80 M i l k an d Wa t e r............................................................................ 8 0 Dried Solids other than Soils and Sediment................................................ 80 i

Fish..............................................................................................80 Soils and Sediments............................................................................80 Charcoal Cartrid ge s ( Air Iodine)............................................................ 80 Ai rborn e Panic u l ate s..................................................................... 8 0 E n vi ro n me n t al Dosi met ry............................................................................ 8 2 bV 72

GROSS BETA ANALYSIS OF SAMPLES AV Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by the customer,is counted as the blank.

Calculations of the results, the two sigma error and the lower limit of detection (LLD):

RESULT (pCi/m3)

((S/T)-(B/t))/(2.22 V E)

=

TWO SIGMA ERROR (pCi/m3) 2 2

/

2((S/T ) + (B/t ))l/2 (2.22 V E)

=

LLD (pCi/m3) 4.66 (BM)/(2.22 V E t)

=

where:

S

=

Gross counts of sample including blank B

=

Counts of blank E

Counting efficiency

=

Number of minutes sample was counted T

=

O

"#m8er r =i=#te 81 x *=> c ##ied

=

V

=

Sample aliquot size (cubic meters) 73

1 DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES 1

Introduction The procedures described in this section are used to measure the overall radioactivity of water samples withota identifying the radioactive species present. No chemical separation techniques are involved.

One liter of the sample !s evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size.

j After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter j

stainless steel planchette which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps.

Residue mass is determined by weighing the planchette before and after mounting the sample. The planchette is counted for beta activity on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting efficiency caused by the residue mass.

3(d Detection Capability Detection capability depends upon the sample volume actually represented on the planchette, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time.

The minimum detectable level (MDL) for water samples is nominally 1.6 picoCuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/l at the 2.83 sigma level), assuming that I liter of I

sample is used and that y gram of sample residue is mounted on the planchette. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively.

The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per liter. These values reflect a beta cou.v.ing efficiency of 0.38.

O 74

ANALYSIS OF SAMPLES FOR TRITIUM Water Approximately 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column heated to 400* C. The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure.

The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic rays.

Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/l:

l RESULT 2(3.234) Tu V (C - B)/(C V )

=

s o g s 2(3.234)T V (E)l/2 (C V )

TWO SIGMA ERROR

/

=

u u u s 3.3 (3.234)T V (E)l/2 (C V )

LLD

/

=

u u y s tritium units of the standard where; T

=

u conversion factor changing tritium units to pCi/l 3.234

=

~

Vu volume of the standard used to calibrate the efficiency of the detector in

=

psia 3

volume of the sample loaded into the detector in psia V

=

Cu the net epm of the standard of volume VN

=

Ca the gross epm of the sample of volume V3

=

the background of the detector in cpm B

=

counting time for the sample At

=

S/T + B/t2 2

E

=

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ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Water Stable strontium carrier is added ta 1 liter of sample and the volume is reduced by i

evaporation. Strontium is precipitated as Sr(NO )2 using nitric acid. A barium scavenge and an 3

iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a i-

, minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter t<> infer Sr-90 activity. Strontium 89 activity is determined by precipitating SrCO from the sample after yttrium separation. This precipitate is mounted on a 3

nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

Milk Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrN0 using fuming (90%) nitric acid. A barium chromate scavenge 3

and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC0 from the sample after yttrium separation. This precipitate 3

is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low lesel beta counting.

i Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO )2 using 3

fuming (90% nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrC0 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet'te 3

and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

76

.._= _ _._. _ _.. _ _ _ _._.._ _ _ _ _ _ _

h Organic Solids A wet portion of the sample is dried and then ashed.in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontitim is precipitated as Sr(NO ) using

]

3 fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then pre-cipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on i

a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity.

Strontium-89 activity is determined by precipitating SrC03 rom the sample after yttrium f

2 separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm aluminum absorber for low level beta counting.

Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(NO )2 using fuming (90%) nitric acid. A barium 3

scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is p

performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium V

ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is detemlined by precipitating SrC0 from the sample 3

after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with 80 2

mg/cm aluminum absorber for low level beta counting.

Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/ volume or pCi/ mass:

RESULT Sr-89

= (N/Dt B -B )/(2.22 V Y DFSR-89 ESR-89)

C A 3

TWO SIGMA ERROR Sr-89

= 2((N/Dt+B +B )/At)l/2 (2.22 V Y DF E

C A

/

3 SR 89 SR-89)

= 4.66((B +B )/At)l/2 (2.22 V YS DFSR.g9 E3R-89)

LLD Sr-89 C

A

/

RESULT Sr 90

= (N/At - B)/(2.22 V Y Y DF IF E) i 2

= 2((N/At+B)/At)l/2 (2.22 V Yj Y DF E IF))

TWO SIGMA ERROR Sr-90

/

2

= 4.66(B/At)I/2 (2.22 V Y Y IF DF E)

(_

LLD Sr-90

/

t 2 77

l total counts from sample (counts)

WHERE:

N 1

=

counting time for sample (min)

At

=

background rate of cou ster (cpm) using absorber configuration B

=

C dpm/pCi 2.22

=

volume or weight of sample analyzed V

=

background addition from Sr-90 and ingrowth of Y-90 B

=

4 0.016 (K) + (K) EY/ abs)(IG -90)

B

=

Y A

chemical yield of strontium Y

=

3 SR-89 decay factor from the mid collection date to the counting DF

=

date for SR-89 efficiency of the counter for SR-89 with the 80 mg/cm.sq.

E

=

SR-89 aluminum absorber Y Y (NAt - D )Y 90 (Ey.90IFy.90 DF -90 g)

C

/

K

=

the decay factor for Y-90 from the " milk" time to the mid DF,99)

=

y count time cfGeiency of the counter for Y-90 E) 90

=

ingrowth factor for Y-90 from scavenge time to milking time IF

=

Y 90 the ingrowth factor for Y-90 into the strontium mount from IG,99

=

y A

the " milk" time to the mid count time the efGciency of measuring SR-90 through a No. 6 absorber 0016

=

the efGciency of counting Y-90 through a No. 6 absorber EY

=

g background rate of counter (cpm)

B

=

chemical yield of yttrium Y

=

g chemical yield of strontium Y

=

y decay factor of yttrium from the radiochemical milking time to DF

=

the mid count time cfGeiency of the counter for Y-90 E

=

ingrowth factor for Y-90 from scavenge time to the radio-IF

=

chemical milking time t%

N.]

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ANALYSIS OF SAMPLES FOR 10 DINE-131

{

O Milk or Water ~

Two liters of sample are first equilibrated with stable iodide carrier A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from t

the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is i

extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a f

I nylon planchette for low level beta countir g. The chemical yield is corrected by measuring the I

j stable iodide content of the milk or the water with a specific ion electrode.

L Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/l:

RESULT (N/At !!)/(2.22 E V Y DF)

=

2((N/A>+B)/At)l/2 (2.22 E V Y DF)

TWO SIGMA ERROR

=

/

= 4.66(B/At)l/2 (2.22 E V Y DF)

LLD

/

=

w here.

N

=

total coants from sample (counts) countinJ time for sample (min)

At

=

backgroand rate of counter (epm)

B

=

2.22 dpm/pCi

=

V

=

volume or weight of sample analyzed Y

chemical yield of the mount or sample counted

=

decay f;ctor Imm the collection to the counting date i

DF

=

cfficiency of the counter for 1 131, corrected for self E

=

absorption effects by the formula E

E,(exp-0.0061M)/(exp-0.006iM,)

=

efficiency of the counter determined from an I-131 E

=

s standard mount mass of Pdl on the standard mount, mg Ms

=

2 mass of PDI on the sample mount. mg M

=

2 I

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D l

C 1

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GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature,less than 100 C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Soils and Sediments Soils and sediments are dried at a low temperature,less than 100 C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height and analysis.

Charcoal Cartridges (Air Iodine)

Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for I-131 of each charcoal cartridge can be determined l

(assuming no positive I-131) uniquely from the volume of air which passed through it. In the event I-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector.

Air Particulate i

The thineen airborne paniculate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) l l

80 l

l

,_.m F

l I

detector coupled to a mini-computer-based data acquisition system which performs pulse height O

anaixsis.

A mini-computer software program defines peaks by certain changes in the slope of the 1

spectmm. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma

]

ray abundance, half life, detector efficiency, and net counts in the peak region The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass:

RESULT (S-B)/(2.221 E V F DF)

=

2(S+B)I/2 (2.22 t E V F DF)

TWO SIGMA ERROR

/

=

4.66(B)1/2 (2.22 t E V F DF)

LLD

/

=

Area, in counts, of sample peak and background where:

S

=

(region of spectrum ofinterest)

Background area, in counts, under sample peak, B

=

determinea by a linear interpolation of the representative backgrounds on either side of the peak length of time in minutes the sample was counted i

=

2.22 dpm/pCi

=

detector efficiency for energy of interest E

=

and geometry of sample V

=

sample aliquot size (liters, cubic meters, kilograms, or grams)

F fractional gamma abundance (specific for each j

=

cmitted amma)

F i

l DF decay factor from the mid-collection date to the

=

counting date 1

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l ENVIRONMENTAL DOSIMETRY' Teledyne Brown Engineering uses a CaSO :Dy thermoluminescent dosimeter (TLD) which 4

1 the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other 2

features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.

i Following the field exposure period the TLDs are placed in a Teledyne Brown Engineering l

Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission j

(luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area'of each TLD after every field use.

1 The transit controls are read in the same manner.

t i

Calculations of results and the two sigma error in net milliroentgen (mR):

l D = (D +D +D +D )/4 j

RESULT

=

g 3 3 4 l

2((D -D)2449 9)2+(p).9)2+(9 9)2)f3)l/2 TWO SIGM A ERROR

=

g 7

4 i

![

WilERE:

D i the net mR of area 1 of the TLD. and similarly for D. D. and D4

=

2 3 I K/R - A Di l

g g

the instrument reading of the field dose in area 1

]

1

=

{

K the known exposure by the Cs-137 source

=

g the instrument reading due to the Cs 137 dose on area 1 R

=

2 A

=

average dose in mR, calculated in similar manner as above.

of the transit control TLDs f

the average net mR of all 4 areas of the TLD.

2

=

I l

O l

r 2

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APPENDIX E INTERLABORATORY COMPARISON PROGRAM i

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Interlaboratory Comparison Program O.

Teledyne Brown Engineering participates in the EPA Interlaboratory Comparison

. Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. Beginning with 1996 the EPA I

discontinued providing milk and air particulate filter samples. For replacements, we have purchased comparable spiked samples from Analytics,Inc.

j In this section the second quarter 1996 data summary tables are presented for isotopes in the various sample media applicable to the North Anna Power Station's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence.

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VEPCO - NORTH ANNA EPA INTEltl.AllOIMTOIW COMPARISON PROGRAM 1996 (Page 1 of 2)

EPA Date TI Malled Date EPA EPA TI Norm Dev.

" Warning Preparation Re suits Issued Results Media Nucilde Results(a)

Results(b)

(Known)(c)

*

Action 01/23/96 02/23/96 05/09/96 Water Sr-89 73.0 i

' 5.0 73.67 i 3.21 0.23 Water Sr-90 5.0 i 5.0 5.00 1 0.00 0.00 01/26/96 02/14/96 03/28/96 Water Gr-Alpha 12.1 1 5.0 19.00 i 1.00 2.39

- (ds Gr-Beta 7.0 1 5.0 7.13 1 0.21 0.05 02/02/96 02/23/96 04/19/96 Water I-131 67.0 i 7.0 71.67 1 3.06 1.15 l

03/08/96 03/25/96 04/20/96 Water 11-3 22002.0 1 2200.0 22000.00 1 0.00 0.00 04/16/96 06/28/96 08/13/96 Water Gr-Beta 166.9 1 25.0 160.00 1 0.00

-0.48 Sr-89 43.0 1 5.0 41.33 1 2.31

-0.58 i

Sr-90 16.0 1 5.0 15.33 1 0.58

-0.23 Co-60 31.0 1 5.0 31.67 i 1.15 0.23 Cs-134 46.0 1 5.0 42.33 i 1.53

-1.27 Cs-137 50.0 1 5.0 52.33 i 1.53 0.81 (n

Gr-Alpha 74.8 i 18.7 63.67 1 2.89

-1.03 Ra-226 3.0 1 0.5 3.40 1 0.00 1.39 Ra-228 5.0 i 1.3 3.63 i 0.61

-1.82 06/07/96 07/16/96 08/19/96 Water Co-60 99.0 1 5.0 99.00 i 1.73 0.00 Zn-65 300.0 1 30.0 309.33 1 2.08 0.54 Cs-134 79.0 1 5.0 69.67 i 1.53

-3.23

" (e)

Cs-137 197.0 i 10.0 202.00 1 2.65 0.87 Ba-133 745.0 i 75.0 711.00 1 71.42

-0.79 06/21/96 08/16/96 10/04/96 Water Ra-226 4.9 1 0.7 5.50 0.26 1.48

[

Ra-228 9.0 1 2.3 9.73 1 0.46 0.55 07/12/96 09/06/96 07/12/96 Water Sr-89 25.9 i 5.0 22.67 i 1.53

-0.81 l

Sr-90 12.0 1 5.0 12.33 i 1.15 0.12 07/19/96 08/16/96 10/07/96 Water Gr-Alpha 24.4 i 6.1 22.67 1 0.58

-0.49 Gr-Beta 44.8 i 5.0 45.33 i 2.08 0.18 t

08/09/96 09/06/96 I1/15/96 Water 11-3 1087.90 i I088.0 9800.00 1346.4I

-I.72 f

i

(

O

/m VEPCO - NORTH ANNA EPA INTERI.AllOltNIORY COMPARISON PROGRAM 1996 IPage 2 of 2)

EPA Date TI Malled Date EPA EPA TI Norm Dev.

- Warning Preparation Re suits Issued Results Media Nuclide Results(a)

Results(b)

(Known)(c)

"' Action 09/27/96 10/21/96 01/09/97 Water Ra-226 14.0 1 2.1 14.00 i 1.00 0.00 Ra-228 4.7 i 1.2 6.20 1 0.50 2.17 (O

10/02/96 11/I5/96 12/16/96 Water 1-131 27.0 1 6.0 26.33 1 2.31

-0.19 10/25/96 1I/15/96 01/07/97 Water Gr-Alpha 10.3 i 5.0 9.03 1 0.72

-0.44 Gr-Beta 34.6 i 5.0 39.67 1 0.58 1.76 11/08/96 12/20/96 02/13/97 Water Co-60 44.0 5.0 44.67 i 0.58 0.23 Zn-65 35.0 1 5.0 38.67 i 0.58 1.27 Cs-134 11.0 1 5.0 12.00 1 0.00 0.35 Cs-137 19.0 1 5.0 20.67 i 1.15 0.58 Da-133 64.0 i 6.0 56.67 i 3.21

-2.12 (g) 12/06/96 01/31/97 03/17/97 Water Ra-226 20.1 1 3.0 20.33 1 0.58 0.13 CD Ra-228 10.2 1 2.6 10.33 1 0.58 0.09 i

Footnotes:

(a) Average i experimental sigma.

(b) Expected laboratory precision (I sigma. I detennination)

(c) Normalized devtation from the known (d) The vartation was due to self-absorption properties of the EPA sample matrix. On future EPA water samples of this type we will determine the overall alpha counting efficiency by spIktng the matrix with Th-230 in accordance with their recent advisory.

(el To vertfy the causse for the deviation. a Cs-137 standard has been purchased. If the Cs-134 efDelerxy is lower than the efflctency at 604 KrV and 795 kev. then rather than change those efDctencies (which may be needed for other Isotopes of comparable energtes). the Cs-134 branching intensity shall be adjusted.

(f) Erroneously low cerium ytelds were obtained in back-extraction from IIDEHP. Greater care to be taken during back-extraction. If this operation is incomplete. the certum carrter yteld becomes kmr than the Ac-228 yield. The procedure had been revtsed to require additional back-extractions for longer periods of time to ensure that proper certum carrier ytelds are obtained. The procedure is under review to determine if additional back-extractions are required.

(g) An investigation is being conducted, results will be available shortly.

I

d ANALYTICS CROSS CHECK COMPARISON PROGRAM 1996 D

d Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a)

Result Ratio (b)

E0633-396 Water I-131 39 i 5

36 2

1.08 TI#11912 Ce-141 89 1 9

88 1 4

1.01 03/12/96 Cr-51 330 i 30 322i 16 1.02 Cs-134 53 i 5

58 i 3

0.91 Cs-137 G5 7

64 i 3

1.02 Co-58 49 i 5

48 2

1.02 Mn-54 37 i 4

31 i 2

1.19 Fe-59 93 1 9

83 i 4

1.12 Zn-65 100 i 10 97 5

1.03 a

CO-60 81 i 8

76 i 4

1.07 E0635-396 Milk I-131 16 i 6

13 1

1.23 Tl#11914 Ce-141 240 20 234 12 1.03 03/12/96 Cr-51 880 90 858 i 43 1.03 Cs-134 1501 20 154i 8

0.97 Cs-137 180 1 20 170 9

1.06 Co 58 140 10 128i 6

1.09 Mn 54 93 i 9

84 4

1.11 Fe-59 250 30 223 11 1.12 Zn-65 2601 30 260 13 1.00 Co-60 220 20 204 10 1.08 EOG32 396 Water Sr-89 30 1 4

24 1

1.25 Tla11911 Sr-90 23 2

21 1

1.10 03/12/9G COG 34 39G Milk Sr-89 30 4

31 2

0.97 Tls11914 Sr 90 17 1 1

16 1

1.0G 03/12/9G EOG3G 39G Water 11 3 2800i 200 2982i149 0.94 T1s11913 03/12/9G E074G 396 Air Filter Gross Alpha 37 3

35 2

1.06 Tls19220 Gross Beta 1501 10 144i 7

1.04 OG/10/9G E0747 39G Air Filter Ce-141 500 1 50 400 i 20 1.25 T1#19221 Cr-51 1200i 100 1048i 52 1.15 06/19/96 Cs 134 3101 30 310 16 1.00 Cs 137 9101 90 764 i 38 1.19 Co 58 2101 20 173 9

1.21 Mn 54 6901 70 559 28 1.23 Fe-59 1901 20 1441 7

1.32 Zn-65 1401 10 108i 5

1.30 Co-60 180 1 20 156i 8

1.15 (h

L) 86

ANALYTICS CROSS CHECK COMPARISON PROGRAM 1996 Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a)

Result Ratio (b) e E0748-396 Air Filter Sr-90 71 i 3

74 4

0.96 Ti#19222 06/19/96 E0749 396 Air Filter Sr-90 46 i 3

49 2

0.94 TI#19223 06/19/96 t

E0750-396 Air Filter Sr-90 66 i 4

63 3

1.05 TI#19224 06/19/96 i

i Footnotes:

l (a)

Teledyne Results - counting error is two standard deviations. Units are pCi/ liter for water i

and milk. For gamma results,if two standard deviations are less than 10% then a 10% eror is reported. Units are total pCi for air particulate filters.

l

[b)

Ratio of Teledyne Brown Engineering to Analytics results.

t i

I 4

J i

i I

87

O O

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EPA CROSS CHECK PROGRAM GROSS ALPHA IN AIR PARTICULATES (pg.1 of 1) 80 l

60 -

40 -

g

]

p.

e e

y

{

t to 4

o F-20 -

,L g 'h<l f

o D

o e

I i

<f 3,

g, f., i, o

0-i n

4 5

5 5

3 5

i 5

5 B

s 3

g g

1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 O Tli 3 Sigma o EPA i 3 Sigma t

The US EPA discontinued air particulate filter samples in 1996.

}

4 O

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l 1

?

EPA CROSS CHECK PROGRAM t

GROSS BETA IN AIR PARTICULATES (pg.1 of 1) i 160 140 -

[

's,

120 -

100 -

O o

S 80 -

m 3,

]

[

(

[

't 60 -

,E'l

'b b

[

e, h

tt

'.h.'.'

t

{'

f g"

l i

e 40 -

eg vii.

i I'

go 20 -

J l

0 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 i

a Tli 3 Sigma o EPA i 3 Sigma i

The US EPA discontinued air particulate filter samples in 1996.

I h

L

~

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O r

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN AIR PARTICULATES (pg.1 of 1) 80 i

70 -

60 -

50 -

40 -

o k

30 -

o o

g 10 -

II 0-,

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 O TIi 3 Sigma o EPA i 3 Sigma The US EPA discontinued air particulate filter samaples in 1996.

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EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES (pg.1 of 1) 80 60 -

ll 40 -

o I) a r

10 ft I

~

e 20 -l>

i I.

f.3.{g,.,.-

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1 i

0-1 -

1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 O TIi 3 Sigma o EPA i 3 Sigma The US EPA discontinued air particulate filter samples in 1996.

i

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

.__m.

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m._

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o EPA CROSS CHECK PROGRAM STRONTIUM-89 IN MILK (pg.1 of 1) 100 80 -

I T

IT l

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lo t

1 u

3 40 -

i r o

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u o

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i ct

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gg f

20 -

'8 i

j; y

o 6

i, i

0-0 o

I

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 I

a Tli 3 Sigma o EPA i 3 Sigma I

i The US EPA discontinued mik samples in 1996.

e

O O

O EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK (pg.1 of 1) 80 t

60 -

il, r,

I ij 40 -

i Fi

'1, o

9.

n 20 -' >

o

-1 1

er u p l'

ik I

0-i t

I f

981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 i

l O Tli 3 Sigma o EPA i 3 Sigma i

The US EPA discontinued milk samples in 1996.

l

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O EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK (pg.1 of 1) 2600 2400 -

2200 -

2000 -

1 1800 -

..t>

o

l, I '

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{'

Il>

n.

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't t y

s >

e s fL l' i j

i l ' '

=

l >'

i i >

l ii e

=

n.

1400 -

1200 -

1000 -

800 -

600 1981 1982 1983 1984 1985 1986 1997 1988 1989 1990 1991 1992 1993 1994 1995 1996 O Tli 3 Sigma o EPA i 3 Sigma The US EPA discontinued milk samples in 1996.

O O

O EPA CROSS CHECK PROGRAM IODINE-131 IN MILK (pg.1 of 1) 160 140 -

Ii 120 -

o II

()

-o it'

'!i 100 -

o

+

80 -

II g

=

3 60 -

o u

1k l

fI E

q I

I I#

!'o 40 -

II ' '

t r

\\

E1 o

fa r u

20 -

g I

EE

=

q c

o m

0-o

+

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 D Tli 3 Sigma o EPA i 3 Sigma The US EPA discontinued milk samples in 1996.

O O

O EPA CROSS CHECK PROGRAM i

CESIUM-137 IN MILK (pg.1 of 1) 100 f

i 80 -

[

is j

j al 60 -'

[

'5 b

i II si i

Il l'

(i

(,

g E

5 1

a 40 -

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l'

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t It lI I

1[

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l 20 -

f si,

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1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996

?

i D Tii 3 Sigma o EPA 13 Sigma f

The US EPA discontinued mik samples in 1996

= -

o o

o 1

EPA CROSS CHECK PROGRAM l

GROSS ALPHA IN WATER (pg.1 of 1) 180 l

l 160 i

140

[

120 100 o

l 0

11 o

3 80

[

E g.

.o o.

60 o

i 6

i

~

g o

-Il o'

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y' sl o 5

40 g

o

",i-il g.i i y

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f I

i-i Io 1 ij 20

~

B Il i jf}

14 7

,,A.d>>P" t

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g-o y

p 4~"

i

-20 I

1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 i

o EPA 13 Sigma

- TIi 3 Sigma l

I

-.a

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

i O

O O

EPA CROSS CHECK PROGRAM r

GROSS BETA IN WATER (pg. 2 of 2) 260 220 f

I 180 16 O

O 140 to o

e o

o o

[

e 5

100 p

cn or O

t 5

~

g f

o g

4 f

[E.

U 9

e G

4, o

e

-20 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 t

o EPA i 3 Sigma j

e Tli 3 Sigma f

[

O O

O EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg.1 of 2) 220 200 180 is 160 8

<i 140 120 n

2 L

T 100

=

t 80 I I 60 40

'E 20 0

y i

-20 f

i 1981 1982 1983 1984 1985 1986 o Ti t 3 sigma EPA 13 sigma o

i i

O O

O EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2) 30000 25000 os 20000 u*

15000 U

v5 o

10000 og n-

'E e

og g)p h f

b

~

I[

]fp h 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 o EPA i 3 Sigma e Tli 3 Sigma f

O O O EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg.1 of 2) 5000 l 4000 i ll 11 o 1 3000 <is <a 'li e <p o .T 11 II l e 'f 2000 T <ti eg ,h a g 1000 h i i 0 i -1000 1981 1982 1983 1984 1985 l D TIi 3 sigma o EPA 13 sigma i

[ __. ~.. _.... _- O O O EPA CROSS CHECK PROGRAM IODINE-131 IN WATER (pg.1 of 1) 2 180 4, 140 ) i' t, l'1 (, ll 'l, 100 g e, g 4_ o I si ~ O si r si u o-p" f, i o 60 g 2 E o o i fI I ( f,,., 'l 1a y, I 20 o go [ D E Q D" E E UE i -20 f 1981 1983 1985 1987 1989 1991 1993 1995 1997 o EPA i 3 Sigma a Tli 3 Sigma I

. _ -... - - _. _ -. _.... ~. o-o o i i EPA CROSS CHECK PROGRAM COBALT-60 IN WATER (pg 1 of 2) f 100 t i ? I 80 I t i ll 60 r b e i, E i 40 I C s* O \\ - of 5 / 4 4 i li >g i ~ fn i 20 n, li E' j l i 4 ,1 ,o i t 0 o' o e -20 ~ 1981 1982 1983 1984 1985 1986 1987 1988 t i a Tli 3 sigma o EPA 13 sigma i i i ?

O O O I EPA CROSS CHECK PROGRAM t COBALT-60 IN WATER (pg. 2 of 2) 120 T 100 ,, g-i 80 i o o 60 o o l o o 3 o o -n o" C T u O [ 5 40 ou o o g o. i' a O o f n o 20 of >5 o5 T o of ,{ f. g o t o on o i 0 [ [ f -20 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 e Tli 3 Sigma o EPA i 3 Sigma 9 !-i

O O O l EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 2 of 2) 100 80 o o 60 o l u o b f. 40 o" i o 5 h n o n ] is u o a. o f o o o o n 20 - "o in oli o g f ,f ti o o Jo .ii G ol o o o o 0 -20 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 l o EPA i 3 Sigma e Tli 3 Sigma

._.___m O O O EPA CROSS CHECK PROGRAM CESIUM-134 iN WATER (pg.1 of 2) 100 i M L l' f 60 m. T ' l U ~ ' 'e, 4 C e-- 40 i o O v i f ( r i e [ ils j f' g 20 " - i e u l i ' i l l A t i [ f 0 s a e s a I 1981 1982 1983 1984 1985 1986 1987 1988 i f a Tii 3 sigma o EPA 13 sigma [ I i i P

.. ~. - = O O O EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 2 of 2) 120 i t 1% i o il l 80 I i 60 o 6 o II Il ti te et .it = o [ g h iP ll e3 ,i o o" n is a. O O j o n 20 c 'lle i I " v? g 'v i of I o o8 o I .,,f ,g og "l E o o 0 i i -20 1966 1989 1990 1991 1992 1993 1994 1995 1996 1997 l i o EPA i 3 Sigma e Tli 3 Sigma I ? i I.

. -. - - - -..... - -. _ - ~ - i i O O-O { i EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg.1 of 2) [ 80 1 60 i ei '( g 40 1 C ja i 2 I t i 5 o ei 18 ,i co n, a i, ll ti < 1 alt F 20 g a 8- "; i ti ei 18 I f 11 l i i t t 0 i -20 1981 1982 1983 1984 1985 1906 1987 O Tli 3 sigma o EPA 13 sigma l l t [

=- O O O-EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 2 of 2) 100 i 4 80 Hg 60 o o g b () 5 2 40 I ' J' u E o g U f o a g o n 20 p o o o ,1 .y T ,l he ll> i> lf ,h, 9 fo g< 1, i [, jo d 0 { -20 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 t i e Tli 3 Sigma o EPA i 3 Sigma i l

t O O O l 4 EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg.1 of 2) 100 i 80 r 60 o w i e on is E 2 AG ~ ~ o O

l i

o 20 J [ lj i t 0 { r -20 l 1981 1982 1983 1984 1985 l t n Tli 3 sigma o EPA 13 sigma i t

_._.._...___._..._..__..._._.m.. O O O EPA CROSS CHECK PROGRAM r STRONTIUM-90 IN WATER (pg.1 of 1) f 80 i 60 40 e tt c, p ,g. ..g' J4 T i 5 h H p. a 20 - f

l i

o d M I,lQ gj f k;4( i+f jM.y n 1 -20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 l e Tl t 3 Sigma o EP A i 3 Sigma 6}}

ML20138D712

Text

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