Text

1993 Annual Radiolgical Environ Operating Rept
	ML20065P676
Person / Time
Site:	North Anna
Issue date:	12/31/1993
From:	Bowling M, Breeden J, Dreyer E; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	94-259, NUDOCS 9404290231
	Download: ML20065P676 (132)
	v • d • e

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VIItOTNIA I$LECTitIC AND l'OWIill CMil'ANY R ICal>10ND, YlHOINIA 20261 April 21, 1994 United States Nuclear Regulatory Commission Serial No.94-259 Attention: Document Control Desk NAPS /JHL/GSS 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 UNIT NOS.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 Units 1 and 2 for 1993.

If you have any questions or require additional information, please contact us.

Very truly yours,

)

M. L. Bowling, Manager Nuclear Licensing and Programs Enclosure cc: U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N.

Suite 2900 Atlanta, Georgia - 30323 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station 2 % aa gr2ggg gggge p)f I s R

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VIRGINIA ELECTRIC AND POWER C0hfPANY NORTH ANNA POWER STATION Radiological Environmental hionitoring Program January 1,1993 to December 31, 1993 u

o Prepared by ;

VIRGINIA ELECTRIC AND POWER COAfPANY and }

TELEDYNE ISOTOPES l l

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.O 1 V !

Annual Radiological Environmental Operating Report \

NORTil ANNA POWER STATION l January 1,1993 to December 31, 1993

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Prepared by: _.

/ James B. Breeden, Supervisor Radiological Analysis Reviewed by: E* /%, I Erich W. Dreyer Supervisor Health Physics Technical Services

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Approved by: J WWU AlakH. St fford

- SuperintendentWaj ogical Protection -,

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Table Of Contents ~

(v3 Srction Title Eagc Preface........................................................................................7 Execu ti ve S um m ary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

1. I n tro d u c ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 II. Nuclear Power And The Environment: In Perspec tive . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 1II. S am pli n g A n d A n alysis Progra m . . . . . . . . . . .. .. .. . . .. .. . . . . . .. .. . . . .. .. . . .. . . . . .. .. .. . 25 IV. Program E x c e p t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 V. Summary And Discussion Of 1993 Analytical Results ........ . ...................... 42 A. Airborne Ex posure Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42

1. Air Iodine /Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2

2. Prec i p i ta ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44

3. Soil..............................................................................45 Q B. W ate rbo rne Ex posu re Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45

1. Ground /We ll W ate r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5

2. R i ver W a ter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5

3. S urface Wa te r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5 ;

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l C. Aq uatic Exposu re Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 1 1

1. Sed ime n t/S il t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47

2. S h o reli n e S oil . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 0 d 1

l D. I n ges ti on Ex posu re Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 .

1. Milk.............................................................................50 l

2. Fish..............................................................................51 1

3. Fo o d / V e g e t a t i o n . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 -

E. Direct Radiation Ex posure Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3

1. TLD Dosimeters...............................................................53 VI. C o n c l u si o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4 O

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m Table Of Contents (Continued.1 V

Section Titic Page Vll. R e fe r e n e e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 7 VIII. A p pe n d i ce s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 8 Appendix A - Radiological Environmental Monitoring ................... .. .......... 58 Program Annual Summary Tables - 1993 Appendix B - Data Tables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 Appendix C - Land Use Census - 199 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 7 Appendix D - Synopsis of A nalytical Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 90 Appendix E - EPA Interla'3 oratory Comparison Program ........................... 101 List of Trendine Graphs

1. Gross B eta in Ai r Partic ulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 O 2. Tritiu m in River water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3

3. Tritium in Surfaee Water...... . ......................................................46

4. Coba1t 58 in Sediment Silt...........................................................46

5. Cobalt-60 in Sediment Silt.............................................................48

6. Cesium-134 in Sediment Silt. . . ..... . ................. ............................48

7. Cesium- 137 in Sediment Silt. . ... .. . . .. . . ... . . . . .. . ...................................49

8. Cesi u m - 134 in Fi s h . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49

9. Cesi u m 13 7 i n Fish . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2

10. Environmental R ad iation - TLDs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2 O

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List of Fleures :

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V Fleure Title Pace

1. Ato m ic S truc ture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

2. Al pha Partic l e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

3. Beta Particle . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

4. G am m a R ay . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4

5. The Penetrating Ability of Various Types of Radiation........ ... ................15

6. Unit Comparison .. . .. . . . . .. . .. . ....... .. ... .. ............... ..............15

7. The Curie, a Measurement of Activity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16

8. Average Annual Dose Equivalent to Persons in the U.S.

from Various Radiation Sources... ....... . ......................................17 9 Estimated Average Days of Life Expectancy Lost Due to yg Various Hea1th Risks.............. ... ......................................19

10. Reactor Vessel with Fuel Assemblies, Rods, and Fuel Pellets..... . ..... ......... . 20

11. Fission: a Chain Reaction........ . ..... .................... ....... ... .. .........21

12. PW R S yste m Di a g ra m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22

13. Containment Schematic . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23

14. Nort h Anna Radiological M onitoring Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 5

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List of Tables n

b Table Page

1. U ran i u m Isot o pes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 3

2. Radiological Sampling Station Distance and Direction from Unit 1..................................................................................26

3. North Anna Power Station Sample Analysis Program... ..... .... .................. 38 L 4 REMP Exceptions for Scheduled Sampling and Ana1ysis During 1993.....................................................................41 l Appendix 11 Tables ,

1 B1 Iodine- 131 Concentration in Filtered Air . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 B-2 Concentrations of Gross Beta in Air Particulates.... .......... ... ... ..... .... . ........ 66 l

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B-3 Gamma Emitter, Strontium 89, and Strontium 90 l Concentrations in Air Paniculates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 70 B-4 Gamma Emitter and Tritium Concentration in River Water ............ ......... .... 73 B-5 Gamma Emitter C on ce n t ra ti o n in Soil. . .. . ....... .. . .... . .. ........ ... . ... . .... .. .. .... 7 3 B-6 Gamma Emitter, Strontium, and Tritium Concentrations in Ground and Well Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................................74 i B.7 Gamma Emitter, Strontium, and Tritium Concentrations m i R i ver W ate r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4 B-8 Gamma Emitter, Strontium, and Tritium Concentrations i n S u rface Wa te r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 5 B.9 Gamma Emitter, Strontium, and Tritium Concentrations ]

in S urface Water State-S plit Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76 l 2

B-10 Gamma Emitter Concentrations in Sediment Silt .... .. ... ..................... .... .. .. 77 B-11 Gamm a Emitter Concentrations in S horeline S0i1.. . . . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . .. 78 '

11- 1 2 Gamma Emitter Concentrations in Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79 B-13 Gam ma Emitter Concentrations in Fish.... ............. ............ .................. 81 B-14 Gamma Emitter Concentmtions in Food / Vegetation ................................... 82 B-15 Direct Radiation Measurements Q u arte rly A n n u al TLD R es u 11s... . . .. . . . . . . .. .. . . .. . .. .. . .. . . . . . . . .. .. .. .. .. ... .. .... . . . 84 B-16 Direct Radiation Measurements

]- See t or Q un rterly TLD Re sul ts .. . .. .. . .. .. . ... . .. .. . . .. .. . . .. . . . . .. . . . . . . .. . . . .. .. .. .. . 85 6

Preface This report is submitted as required by Technical Specification 6.9.1.8, Annual Radiological Environmental Operating Report for North Anna Power Stations, Units 1 and 2 Virginia Electric and Power Company Docket Nos. 50-338 and 50-339.

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Executive Sumanmy O

'this document is a detailed report on the 1993 North Anna Nuclear Power Station Radiological Environmental Monitoring Program OtEM19 Radioactivity levels from January 1 through December 31,1993 in water, silt, shoreline sediment, milk, aquatic biota, f(xxi prcxlucts, vegetation, and direct exposure pathways have been analyzed, evaluated, and summarized. 'Ihe REMP is designed to ensure that radiological effluent releases are As inw As is Itcasonably Achievable (ALARA), no undue environmental effects occur, and the health and safety of the public is protected. 'Ihe program also detects any unexpected environmental processes which could allow radiation accumulatiorts in the environment or f(xxl pathway chains.

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Radiadon and mdioactivity in the environment is con- ;

stantly monitored within a 25 mile radius of the station. 7' .% 9 '

Virginia Power also collects samples within this area. A number of sampling locations for each medium were selected 4 using available meteorological, land use, and water use data. .

'l\vo types of samples are obtained. 'lhe first type, control < . ..

samples, are collected from areas that are beyond the measur- ~MM able influence of North Anna Nuclear Power Station or any I Qp"Q@ygf4 hh hkh p tM other nuclear facility. 'Ihese samples are used as reference data. Nornul background radiadon levels, or radiation present gk. ..

.,C1g'[

i due to causes other than North Anna Power Station, can thus j fC TQ My 0 b e c o m n are d to th e e n viro n m e nt ee rro e n din a th e n u cie2 r power station. Indicator samples are the second sample type i a .zW' hg 1.' ..ef.wc.

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l obtained. 'Ihese samples show how much radiation is r contributed to the environment by the plant. Indicator samples b '( ,.

l are taken from areas ck>se to the station where any plant Q7 .L';..n

. ./ l contribution will be at the highest concentration. 3' -

*JP4' Prior to station operation, samples were collected and analyzed to detennine 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 lx>th current control sample values and the pre-operational baseline to detennine if changes in radioactivity levels are attributable to station operations, other causes such as the Chemobyl accident, or natural variation. l Tcledyne isotopes provides sample analyses for various radioisotopes as appropriate for each sample media. Participation in the Environmental Protection Agency's (EPA) Interialx>ratory Comparison Program provides an independent check of sample measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently f;di below the minimum detection limits of state-of-the-art measurement meth(xis.

Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must lx able to detect specified minimum I ower umits of Detection (LLD). 'Ihis ensures that analyses are as accurate as possible. Samples with extremely O io- ievete or reai2 tion which c>nnot be actectea =re thererore reportea ms beina betow the t'o.

'lhe NRC also mandates a " reporting level." Ucensed nuclear facilities must report any releases 8

M equal to or greater than this reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.

bq Analytical results are divided into five categories based on exposure pathways: Airbome, watedx>me, aquatic, ingestion, and direct radiation. Each of these pathways is described below:

'Ihe airbome exposure pathway indudes airbome iodine, airbome particulate, precipita-tion, and soil samples.1he overall 1993 airix>me 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 airbome particulate media during 1993

. 1he waterix>me exposure pathway indudes ground /well water, river water, and surface watersamples. Noman-madeornaturalisotopesweredetectedinI2keAnnasurfacewater except for tritium. 'lhe average tritium activity in 1993 was 14.0% of the NRC reporting level.

1his has increased from preoperational levels but has decreased from 1992 levels. ,

'lhe aquatic exposure pathway indudes sediment / silt and shoreline samples. North Anna sediment contained some cobalt 40, cesium-134 and cesium-137. During the preopera-tional pericxi, cesium-137 was detected. Additional man-nude isotopes appear to have accumulated since that time. 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. Cesiv .-137 levels increased from 534 pCi/kg in 1992 to 662 pCi/

kg in 1993.

- 1he ingestion exposure pathway includes milk, fish, and food / vegetation samples. Iodine-0 131 w s n t detected in any 1993 milk s mples. Although cesium-137 lus been detected in the past, it was not detected in 1993 milk samples. Strontium-90 was detected at levels comparable to 1989, and lower than preoperational years. Ik>th strontium-90 and cesium-137 are attributable to atmospheric nudear weapons testing in the past. Naturally occurring potassium-40 was detected at normal environmental levels.

Fish samples during 1993 contained cesium-137 at a slightly higher activity than preoperational levels. Steam generator repairs and better liquid waste processing, however, have reduced these activity levels from previous years. Vegetation samples were statistically similar to both control and preoperational levels. ,

1he direct radiation exposure pathway measures environmental radiation dosec by use of themioluminescent dosimeters (TLDs). TLD results have remained essentially the same since the preoperational peri (xi in 1977.

During 1993, as in previous years, operation of the Nonh Anna Nudcar Power Station created no adverse environmental affects or health hazards. The maximum radiation dose calculated for a hypothetical individual at the North Anna Power Station boundary due to liquid and gaseous etfluents released fmm the site during 1993 was 0.47 millire n. For n:ference this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82%

of radiation exposure to man while Nudcar Power contributes less than 0.1%.1hese results p demonstrate not only compliance with fedemi and state regulations, but also demonstrate the

.V adequacy of radioactive effluent control at the North Anna Nudear Power Station, 9

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. VIRGINIA ELECTRIC AND POWER COMPANY a

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NORTH ANNA POWER STATION RADIOLOGICAL ENVIRONAfENTAL OPERATING PROGRAAf

1. INIRODUCTION The operational radiological environmental monitoring program conducted for the year

. 1993 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 1,1993 through December 31, 1993 are summarized.

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

The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply systems and turbine generator furnished by Westinghouse Electric Corooration.

Each unit is designed with a gross electrical output of 970 megawatts electric (MWe). Unit I achieved commercial operation on June 6,1978, and Unit 2 on December 14,-1980.

Q B. The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, constructed, and operated to keep levels of -

radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license for Nonh Anna Power Station includes Technical Specifications which address the release of radioactive effluents.

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).

C. Virginia Electric and Power Company is responsible for collecting the various indicator and control environmental samples. Teledyne Isotopes 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 cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally occurring Q isotopes. Data collected prior to the plant operation is used to indicate the degree of natural 10 i

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.. variation to be expected. This preoperational data is campared with data collected during l0.

the overationai ghase to assist in evaiuatins the radieiosicai impaci of the giant egeration.

D. Occasional samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a .

dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM. These concentrations are based upon the annual dose commitment reconunended by 10CFR50, .\ppendix 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 1993 and satisfies the following objectives of the program:

1. Provides measurements of radiation and of radioactive materials in those exposure -

pa.hways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station 3 operation.

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

3. Identifies radioactivity changes in the environnent. .;

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

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II. Nuclear Power And The Environinent:

G,, In Perspective Coal, oil, natural gas, nuclear power, and hydropower have all been used to mn the nation's electric generating stations. Each methcx1, however, has its drawbacks. Coal-fired power can damage the environment during the mining process, or by airbome discharges such as fly-ashand chemicals which contribute to acid rain.. Oil and natural gas are costly because of their limited supply. Few suitable sites for hydropower exist, and building the large dams necessary to produce Hydropower has a significant impact on the environment.

Nuclear energy provides an alternate source of energy which is readily available. The operation of nuclear power stations has a very small impact on the environment. In fact, hundreds of acres adjoining Surry Power Station are a state waterfowl refuge, and Lake Anna, next to Nonh Anna Power Station, is a well-known fishing site with a state park on its shore.

In order to more fully understand this unique energy source, background information alx)ut basic radiation chameteristics, risk assessment, reactor opemtion, effluent control, environmental monitoring, and radioactive waste is provided in this section.

Fundarnentals TheAtom Everything we encounter is made of atoms. Atoms are the smallest pans of an element that still have all the chemical propenies of that element. At the center of an atom is a nucleus. The nucleus consists of neutrons and protons. Electrons move in an orbit around the nucleus and am negatively charged. Protons and neutrons are nearly identical in size and weight, and each is about 2000 times heavier than an electron. The proton, however, has a positive charge, while the neutron has no charge, it is electrically neutml. Figure 1 presents a simple diagram of an atom.

p-

,pPositive Protons Charge g

Electron '

7 p-Negative Charge Nucleus N

' 2' ~ Neutrons

$ Neutral Charge g

Y S"'

Isotopes O The ee m ner orvretee ,in tae ato m ofanv 8vecillc eie m ent1,aiwar the a m e. ror exa m rie, all hydrogen atoms have one proton whereas all oxygen atoms have eight protons. Unlike protons, 12

the nutuber of neutrons in the nucleus of an element may vary. Atoms with the s:une nuinber of

(- protons, but a different number of neutrons, are called isotopes. Table 1 lists the isotopes of

\. 7 .umnium.

Isotopes Symimis Nurnber Number of Protons ofNeutrons Untnium-235 *U 92 143 Uranium-236 #*U 92 144 Umnium-237 "U 92 145 Umnium-238 "U 92 146 Umnium-239 "U 92 147 Uninium-240 "U 92 148 Table 1. Uranlurn Isotopes Radiation andRadioactivity l Radionucikles O m>mmur , the na,1 aan ax>m are in e aaiaeced m , tame , tate. 4 mannercentase aax>m natumily contain excess energy and therefore are not stable atoms. If the nucleus of an atom contains excess energy, it may be called a radioactive atom, a radioisotope, or mdionuclide. The excess energy is usually due to an imbalance in the number of electrons, protons, and/or neutrons which make up the atom.

ludionuclides can be naturally occurring, such as unmium-238, thorium-232 and potassium-40, or man-made, such as iodine-131, cesium-137, and cobalt 40.

Radioactit'e Decay ludioactive atoms attempt to reach a stable (non-radioactive) state through a process known as radioactive decay. Radioactive decay is the release ofenergy from the atom through the emission of particulate and/or electinmagnetic nidiation.' Particulate radiation may be in the form of electrically charged particles such as alpha (2 protons plus 2 neutmnsior beta partides (1 electn>r0, or may be electrically neutml, such as neutrons. Part of the electromagnetic spectrum consists of.

gamma mys and X-niys which are similar to light and microwaves, but have a much higher enesgy. :

HaIf-Lffe A mdioactive half-life is the amount of time required for a mdioactive substance to lose half O a v< ee8e or m aioactive a ecar. c o uait 4 o nae a nait-iire ca s o "t sveare.

orit8 activirv ti e " s tne 13

After 5 years,50% ofits radioactivity is gone, and after 10 years,75% has decayed away. Itadioactive half-lives vary from milliontits of a second to millions of years.

t ltidioactive atoms may det ay directly to a stable state or may undergo a series of decay stages.

During the decay process, ses emi daughter products may be formed which eventually tnmsfomi into stable atoms. Naturally occurring mdium-226, for example, has 10 successive daughter prcxlucts (including mdon) resulting finally with lead-206 as a stable fonn.

Types OfRadiation Two types of radiation are considered in the nuclear industry, paniculate and electromagnetic. Particulatemdiation may come from the nucleus of an atom in the fonn of an ejected alpha particle. 7 y Alpha panicles consists of two protons g, together with two neutrons. N g.,. ,

&+

2 Protrons Alpha particles have a very limited 2 Neutrons e ability to penetrate matter. A piece of s KC566 paper will stop all alpha mdiation. For this ~-

e .-

reason, alpha radiation from sources out- Nw.$-[-b hsh.s p side the lxx!y are not considered to be a

'V radiation hazard. ,

A beta particleis like an electron that y 5 has been ejected from the nucleus of an g atom. Skin or a thin piece of aluminum N g.:. ,

will stop beta radiation. Exposure to beta -

- 1 Neutron transforms to - "

mdiation can be a hazard to the skin or (*i j fro $n"(in nudeugta lens of the eye. Ikcause of their limited >

ability to penetrate the body, beta and alpha mdiation are a health concem prinurily if alpha or beta emitters are h((M N. M[- - -

swallowed or inhaled where they might _

cause intemal mdiation exposure. Gamma mys are like X-mys, except that they come from the nucleus of an atom while X-rays 7 -

come fmm the electron rings. g 4 Electromagnetic Gamma mys cnn penetrate deep into > radiation indistinguishable frorn X-rays the Ixxty and thus give a "whole-lxxty' a radi;uion dose. Setemiinches ofconcrete kcses or lead will stop both gamma and X-rays.

Q"'.:7.Ufl] g1Rayi O

~ -

rixere s eao- tae ever ximete reecimt- 1 ing ability of various types of radiation.

1 14 l 1

-)

H l

1 O a = Alpha p <

O p = Beta , ,

Y = Gamma g'~ t

.N @ ?

go j e@N !

ss*** " p'iCBS g, p Qwe _m .

<m '" 'w.

, e .

rgasa5A p

' %, yd%l@. ;

M

~;

~-

e

,y g 3 $5t W N ",

s -

Radioactive Material Paper Aluminum Concrete As radiation travels, it collides with other atoms and loses energy. Alpha particles can be stopped by a sheet of paper, beta particles by a thin sheet of aluminum, and gamma radiation by severalinches of concrete or lead. ,c,,,

i kbbbbk bb hbkb N Quantilles And Units OfRadioactive Meastusment Several quantities and units are used to describe radioactivity and its effects. In the following i sections two tenns, rem and activity, will be used to describe amounts of radiation.

s Rem measures the potential effect of radiation exposure on human cells. Small doses are counted in millirem. Each millirem is equal to one thousandth of a rem. Federal standards limit exposure for an individual member of the public to 100 millirem annually, compared with the average 300 millirem received from natural sources and approximately 60 millirem from medical applications.

n -

1 inch 1 millirem 1

a =: . 2=.

3 h 6 y e

. .7.

L ?EEEE:"E?EEEEE:'EE."

L? :?:22,?.? : E? .*:

9 10 )N L".-#."#.-# # # # " "# # # # # # # # #

E5$$i$$$$-$-$-$-5$5 s.=

s austas :.- : -

Twelve inches equals one foct 1000 millirem equals 1 rem A KC661

. W L 15

1 Curie f- Activityis the numberof nuclelin a 1 sample that disintegrate (decay) every second. Each time a nucleus disinte- xf ,

gmtes, radiation is emitted. The unit of 2 6::::::::::-? :: : :

activity is the curie. A Curie (Ci) is the :::::!:: : :

amount of radioactive material which :::::::: : :

decays at a mte of 37 billion atoms per :::::::{::: ,

second. Smaller units of the Curie are :::: ::;;

]: 1 Curie often used.Two common units are the [{:{;:'

microcurie (uCl), one millionth of a 10' Curie, and the picocurie (pCi), one

' O 10 Tons of Thorium-232 1 Gram of Radium-226 trill.ionth of a Cun.e. A Cun.e is a mea- (radiation source) (radiation source) surement of nidioactivity, not a quan- One gram of radium-226 and 10 tons of thorium-232 tity of material. The amount of material are both approximately 1 Curie. xeso, necessary to make one Curie varies. For ?[ . gMea'Sureme.ntN ~-.#a Ld example, one gmm of radium-226 is k%@#

p# M *"" .Mik ]lylty ""

~ w 3

~ ' "

~ '

one Curie of radioactivity, but it would take 9,170,000 gmms (about 10 tons) of thorium-232 to obtain one Curie.

Sources OfRadiation O m~,. n-,~,,

Radiation is not a new creation of the nuclear power industry; it is a natumi occunence on the eadh. Mankind has always lived with radiation and always will. Every second of our lives, over 7,000 atoms undergo radioactive decay in the Ixxly of the average adult. Radioactivity exists naturally in the soil, water, air and space. All of these common sources of radiation contribute to the natural background radiation that we are exposed to each day.

The canh is constantly showered by a steady stream of high energy gamma mys. These rays come from space and are known as cosmic radiation. Our atmosphere shields out most of this mdiation, but everyone still receives about 20 to 50 millirem each year from this source. At high altitudes, the air is thinner and provides less protection from cosmic radiation. liecause of this, people living at higher altitudes or even flying in an airplane are exposed to more radiation.

Radioactive atoms commonly found in the at mosphere as a result of cosmic my interactions include beryllium-7, cirbon-lel, tritium, and sodium-22.

Other natumi sources of mdiation include mdionuclides naturally found in soil, water, fo(x1, building materials and even people. People have always been radioactive, in part because the I carbon found in our lxxiles is a mixture of all carbon isotopes, both non-mdioactive and l radioactive. Approximately two-thirds of the whole Ixxty dose from natural sources is contributed i byRadongas Aboutone-thirdofthenaturallyoccuringexternalterrestrialandinternalwholelxxty O mdiatiee dese i, attrinet>aie te a eatemiiv mdioactive i otene of nota iem, eetae i"m-40.

16 )

j

Man-Made In addition to naturally occurring radiation, people are also exposed tc) ntin-made radiation.

The largest sources of the.se exposures are from medical X-mys, fluoroscopic examinations, radioactive drugs, and tobacco. Small doses are received from consumer 3roducts such as television, smoke alanns, and fenilizers. Very small doses result from the prot uction of nuclear

[xnver. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout mdionuclides include strontium-90, cesium-137, carbon-14, and tritium.

Man-Made Sources

-g. 2 3 g3W@ Nuclear Power (0.1%)

M a ry 0.9 ) sceHancous (0.1%)

wmg , , Occupational (1.4%)

> $Q@?

5[Mjf Consumer Goods (15.6%)

W'

-g Other Medical (21.9%)

Man-Made Medical Natural And Man-Made Sources Diagnostic X-Rays 39.00 Other Medical 14.00 Consumer Products 5.00 to 13.00 p , .

()

Occupational 0.90 a ff1 $?N[h79 3 Mig %' @M.g u ' Miscellaneous Environmental 0.06

,}& 'hl4 hQ Ni kN , Nuclear Power 0.05 r

hkhk%hh!kQy(psl j

g

-'rsinhe g[hY g(sif~!

Natural Background

" d.,ij

' ?39 Radon E ( %"' C ' 955.6%} SN

~

Radon and Radon Daughters 200.00 o $MW 4 Cosmic Rays 27.00 M ,^i.f y- gw gbji . an-Made 7.8 Cosmogenic Radiation Terrestnal Radiation 1.00 28.00

, Nd T.mjM Q Internal Radiation 40.00

' QR $;%qiw&

[gg'siM

. ~g < m p , Total 360.00 MREM Per Year LlG>fb , 1 e:4 t 3,# GWM! Interna 1.1 %

gf0T"d M,i - 1 4

Terrestrial 7.8%

smic as .8%)

NCRPReportik 93. 'lonizing Radatron Exposure of the Population of the United States."30 Dec 1987, Bethesda, MD 20614 KC563 '

17

Fffects OfRadialion n

\'f Studies The effects ofionizing radiation on human health have been under study for more tlum eighty years. Scientists have obtained valuable knowledge through the study of laix>ratory animals tlut were exposed to radiation under controlled conditions. It has proven difiitult, however, to relate the biological effects of irnidiated laboratory animals to the potential health effects on humans.

Because of this, human populations irmdiated under various circumstances have been studied in great depth. These groups include:

Survivors of the atomic bomb.

Persons undergoing medical radiation treatment.

Itadium dial painters during World War I who ingested large amounts of radioactivity by " tipping' the paint bmshes with their lips.

ITranium miners, who inhaled large amounts of mdioactive dust while mining pitchblende (umnium ore).

= Early radiologists, who accumulated large doses of ntdiation from early X-ray q equipment while being unaware of the potential hazards.

V Analysis of these groups has increased our knowledge of health effects resulting from large nidiation doses. less is known about the effects oflow doses ofradiation. To be on the conservative side, we assume that health elTects occur proportionally to those observed following a large dose of radiation. That is, if one dose of mdiation causes an effect, then half the dose will cause half the elTect. Itadiation scientists agree that this assumption overestimates the risks associated with low les el mdiation exposure. The effects predicted in this manner have not been actually observed in individuals exposed to low level mdiation.

Ilealth Risks Since t he actual effects of exposure to low level radiation a re dilficult to measure, scientists often refer to the possible risk involved. The problem is one of evaluating attematives, of comparing risks and weighing them against benefits. People make decisions involving risks every day, such as deciding whether to wear seat belts or smoke cigarettes. Itisks are a part of everyday life. The question is to determine how great the risks are.

We accept the inevitability of automobile accidents. Building safer cars or wearing seat belts will reduce the risk ofinjuiy. You could choose to not drive to be even safer, but pedestrians and bicyclists are also injured by cars. Iteducing the risk of injuiy from automobiles to zero requires moving to a place where there are no automobiles.

(O 18

1 1

While accepting the many daily risks of living, some people feel that their demands for energy m should be met on an essentially risk-free basis. Attention is focused on safeguarding the public, d developing a realistic assessment of the risks, and placing them in perspective. l l

Because you cannot see, feel, taste, hear, or smell mdiation, it is often a source of concem. We i have the same lack of sensory perception for things such as mdio waves, carbon monoxide, and l small concentrations of numerous cancer causing substances. Although these risks are just as real l as the risks associated with radiation, they have not genemted the same degree of concem as mdiation.

Most risks are with us tluoughout our lives, and their effects can be added up over a lifetime to obtain a total effect on our life span. The typical life span for an American woman is now 76 years, whereas men average 71 years of age. Figure 9 shows a number of different factors that decreased our avemge life expectancy.

Days Activity 2500 '

1. Smoking 1 Pack of Cigarettes a Day n 2. Being 20% Overweight 2000 - ;

3. Construction f 4. Agriculture 1500 - T 5. Auto Accidents p/'

s ]E 6. Avg Alcohol Consumption per Person

7. Home Accidents 1000 - >

J y 8. AllIndustry Hazards

?_ [ '

9. Radiation Dose of 6.5 Millirem per 500 _ '

Year for 30 Years

}3 }- ' O, M -

- NCRPReport Na 95. " Radiation Exposure of the US.

Population from Consumer Products and Mtscellaneous g ~/ .

l l l l l l l l l Sources.* Natoonal Council on Radiatuan Protection and 1 2 3 4 5 6 7 8 9' Measurernents, Dec 1987, Beusesda, MD 208 M KC562 4 .

The Americui Cancer Society estimates that about 30 percent of all Americms will develop cancer at some time in their lives from all possible causes. So, in a group of 10,000 people it is expected that 3,000 of them will develop cancer. If each person were to receive a radiation exposure of one rem in addition to natu ral background mdiation, then it is expected that three more may develop cancer during their lifetime. This increases the risk from 30 percent to 30.03 percent.

IIence, the risks of radiation exposure are small when compared to the risks of everyday life.

These comparisons should give you some idea of the risk involved in activities that you are familiar with. They give a basis for judging what smoking, eating, or driving a car could mean to your health and safety. Everyone knows that life is full of risks. If you have the basis for judgment, you can decide what to do or what not to do.

u 19

NuclearReactor Operation C)

Electricity in the United States is being produced using fossil fuel, uranium, or fillling water.

A fossil-fueled power station bums coal, oil or natural gas in a boiler to produce energy. Nuclear power stations use uranium fuel and the heat produced from the fission process to make energy.

In lxath cases, they heat and luil water to produce steam. The stemn is used to drive a turbine which turns a genemtor and produces electricity.

Nuclear Fuel Uranium (U) is the basic ingredient in nuclear fuel, consisting of U-235 and U-238 atonts.

Natumt uranium contains less than one percent U-235 when it is mined. Commercial nuclear power plants use fuel with a U-235 content of approximately three percent. The process used to increase the U-235 concentration is known as enrichment.

Reactor Operation After enrichment, the umnium fuel is chemically changed to umnium dioxide, a dry black powder. This powder is compressed into small cemmic pellets. Each fuel pellet is ainut 3/4 inches long and 3/8 inches in diameter. The pellets are placed into 12 foot long metal tubes made of zirconium alloy to make a fuel rod. About five pounds of pellets are used to fill each rod. A total of 204 fuel rods make a single fuel assembly. Virginia Power nuclear reactors contains 157 fuel assemblies (Figure 101 p)

Reactor Vessel 9 Fuel Rod g; y .

Control Rods N

M4$$ h4f a b l H

.gr - Water Level ][ ;

couan'= E: ; - Cuennns

[g

/ l l .

Nozzle D Fuel Rod Assembly I Fuel Pellet Fuol Rod Assemblies I '

q ;

a ul i u> ;

Tno mal Shield --a { I i - -

l l .

, JJ Cote inimid Support \ ,, _ /

MT424 o

HEEIGRMrawMWrsmETI!EEM 20

Fission f,,.s

>?a V Nuclear energy is pnxluced by a {^o process utiled fission. Fission occurs in a g 4 :cf a reactor when uranium is split into %

fmgments producing heat and releas- $ :

ing neutrons. These neutrons strike k g<F #

.M other uranium atoms, ciusing them to split (tlssion) and release more heat MT 427 and neutrons. This is called a chain reaction (Figure 11) and is controlled h Heavy Atom o Free Neutron by the use of reactor control rrxis. .

O Fission Fragment v^- Heat Control axis are ary essential pan of the nuclear reactor. Control rods con-gggggggggfggy tain cadmium, indium, and silver metals which absorb and control the amount of neutrons produced in the reactor. The control rods act to slow down or stop the chain reaction. A chain reaction cannot occur when the control axis are inserted completely into the core. When the control rods are withdmwn, the chain reaction begins and heat is generated.

Design & Operation Surry Power Station and North Anna Power Station use a Pressurized Water Reactor (PWlO system to genemte electricity. There are two complete and independent PWR systems on-site at both Surry and North Anna Power Stations. These are referred to as Unit-1 and Unit-2.

The reactor core is inside a large steel container called the Reactor Pressure Vessel. The reactor core is always surrounded by water. The fissioning of the uranium fuel makes the fuel nxts get hot. The hot fuel rods heat the water, which serves as a coolant that carries away heat.

In a pressurized water reactor, heat is moved from place to place by moving water, the reactor's coolant. The water flows in closed k> ops. As (primary) water moves through the core it gets very hot (605 F), but because it is under such high pressure, 2235 pounds per square inch (pso, it doesn't boil. The hot water then flows to the steam generator. The steam genemtor is a heat exchanger. Reactor coolant passes through it but doesn't mix with the steam genemtor (secondary) water. Instead, heat from the primary wateris transfened through thousands of tubes to the cooler secondary water. The water in the steam generator is under much less pressure, and the heat boils the secondary water to steam. At Virginia Electric and Power stations, each unit has 3 steam generators.

The steam is piped to a steam turbine that tums an electric generator. The exhausted steam from the turbine is cooled and converted back to water in a condenser. The condenser is also a heat exchanger; in it heat passes from the steam to a third loop of water. In Surry's case theJames River provides the third kx)p water. At North Anna Power Station third loop water is from lake 3 Anna. The ste;un tums back to liquid and is pumped back to the steam genemtor. Figure 12 is (V a diagmm of typical nuclear reactor systems.

21

Hgh Pressure Safety injection System (Emergency Core Coolmg)

'/ Low Pressure Safety injecnon System

( (Emergency Core Coolmg)

V Contamment Spray System Man Steam System Reactor Containment Building ======e,

p b -* - Hotwell -ML- 4 % Accumunalor g t,9 ~ Une : g E . a ra 1ake Or River % e frol [k Np Reactor Vessel +- Feed Pump , Safety injectron Pump y V47 - . . _ , ,-- AoWhary Feed Pump Emergency densate Reactor Coolant Pump Contamment Sump p b[dhb b kbbb Nk N Containtnent Nuclear power plants are designed to prevent the escape of large quantities of radiation and radioactive substances. Two principles are used. First, thick, heavy walls are used as shielding to absorb ridiation and prevent its escape. Second, strong. airtight walls called containment, are used to prevent the escape of radioactive materials. The reactor pressure vessel and the containment building that houses it are enormously strong (Figure 13). Strong enough, in fact, to withstand a direct hit fmm a 707 jetliner. The reactor core lies within a sealed pressure vessel, Like all boilers its walls must be very strong because the water inside must be kept under high pressure. The reactor pressure vessel in a nuclear power plant is es en heavier than an ordinary steam boiler because of the need to minimize the chance of rupture 1 and release of any radioactive materials. The reactor pressure vessel is made from a stainless steel l alloy 6 to 8 inches thick. Around the reactor pressure vessel is a thick concrete wall. This wall acts as shielding, protecting workers by absorbing radiation resulting from the nuclear chain reaction. Next an 'N airtight 1/2 inch steel liner surrounds the entire interior of the containment. If the reactor pressure (V vessel or any of the primary piping should break, the escaping steam would be trapped inside the liner. 22 -I cp u # s " [] / 21/2 Feet Thick Concrete v f 1 1/2 inch Steet Liner s h. E-' h 3'8 inch Steel Liner 41 M > I j ; 1 IIWM i

1. (

g y 41/2 Feet Thick Concrete Steam g* g[ D Pressurizer n 185 Feet w :: w:.; 122 Feet 4 5 :k o: :.: b!*!

..L ::

5 . . .. . . . . ._._. 8 ?. :k !!D!b0060: _L 1 ! -- - . _ . _ . 5 . l Yl_ ; l$ **' L__ _ ,: Nif .... /"~% W # ritts W W Q $ - . y .9..- Liner 10 Feet Thick Concrete 4 126 Feet > Finally, the building's reinforced concrete outer wall is 41/2 feet thick tapering to 21/2 feet at the top of the dome. It is designed to act as shielding and is also intended to withstand natural and man made events like emthquakes and even the direct impact from a large commercial jet aircrall. Operating the ReactorSafely Accidents The most serious accident that could happen in a nuclear power plant involves overheating in the nuclear mactor core. Such an accident would result from a loss-of<oolant accident or LOCA. During a LOCA, primary coolant would no longer circulate through the reactor core to remove heat. (j Circulation could be lost if a combination of pipes burst, for example. Conceivably, a dry, overheated mactor core could melt through the pressure vessel. 23 The reactor itself is designed to respond automatically to such an emergency. Opemtors are n also tmined to make corrections for any system failure. The automatic and opemtor responses have () two goals: to prevent d:unage to the reactor, and prevent the release of mdiation. Shutting the reactor down is relatively easy. Control rods drop in and chemical to stop the nuclear reaction are injected into the ax>lant. Losing the coolant itself tends to stop the chain reaction because the ; coolant is needed to keep the nuclear chain reaction going. Within 10 seconds of shutdown, the i amount of heat is less than 5 percent of the amount produced at full power and within 15 minutes, less than 1 percent. To carry heat away during an accident, all reactors have Emergency Core Cooling Systems WCCS). The ECCS consists of primary and back-up pumps and reservoirs of coolant that opemte separately from those that normally circulate through the system. A nuclear reactor has many different luck-up safety systems designed so that if one fails another is ahvays available. Workers There are many different jobs at a nuclear power plant and Ihey are filled by people with diverse backgrounds. All employees are initially tmined and then retmined annually by the company. Virginia Power's Training centers are fully accredited by the National Academy for Nuclear Training and the Institute for Nuclear Power Opemtions. The operators are tested and certified by the United States Nuclear Regulatory Commission (NRCL Safety Statistics O, Job safety is another measure of assumnce that the station is being propedy opemted. Suny Power Station attained 1480,M1 man hours without a lost time accident and is continuing that record into 199i. Nonh Anna Power Station has attained over 2,000,000 man hours without a lost time accident. Stim m m y Nuclear energy provides an alternate source of energy which is readily available. The opemtion of a nuclear power station has a very small impact on the environment. = Radiation is not a new creation of the nuclear Ix>wer industry; it is a natural occunence on the emth. Mankind has always lived with radiation and always will. Radioactivity exists naturally in the soil, water, air and space. All these common sources of mdiation contribute to the natural background radiation to which we are exposed. In addition to naturally occuning radiation and radioactivity, people are also exposed to mananade mdiation. Very small doses result from the production of nuclear power. Nuclear power plants are designed to prevent the escape of radiation and mdioactive substances. O V = A nuclear reactor has many difTerent back-up safety systems designed so that if one fails another is available. 24 Ill. SAMPLING AND ANALYSIS PROGRAM O A. Sampling Program

1. Table 2 summarizes the sampling program for North Anna Power Station during 1993. Figun: 1 indicates the locations of the environmental monitoring stations.

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

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 samples with the Commonwealth of Virginia. All samples listed in Table 1 are collected by VEPCO personnel except for those labeled state split. All samples are shipped to Tcledyne Isotopes in Westwood, New Jersey.

4. All samples listed in Table 2 are taken at indicator locations except those labeled -

" control" O 25 O O. .O ' TABLE 2 (Par < 1 of 5) North An sa Power sr? inn - 1993 RADIOLOGICAL S.BIPL1NG STATIONS DISTANCE AND DIRECITON FROM UNIT NO.1 Distance Compass Collection Sarpple Media Location Station Miles Direction Degrees Freq uency Remarks Environmental NAPS Sewage 01 0.20 NE 42" Quarterly On-site, State Split Thermoluminescent Treatment Plant & Annually Dosimetry (TLD) Fredericks Itall 02 5.30 SSW 225* Quarterly . State Split & Annually Mineral Va 03 7.10 WSW 243* Quarterly & Annually Warcs Crossmads 04 5.10 WNW 287* Quarterly State Split & Annually Route 752 05 4.20 NNE 20 - Quarterly & Annually Sturgeon's Creek 05A 3.20 N 11* Quarterly Manna & Annually levy, VA 06 4.70 ESE 115' Quarterly State Split, Co-locatk>n & Annually Bumpass, VA 07 7.30 SSE 167* Quarterly State Split & Annually End of Route 685 21 1.00 WNW 301* Quarterly Exclusion Boundary N & Annually State Split.Co-location

Route 700 22 .1.00 WSW 242* Quarterly Exclusion Boundary

& Annually State Split " Aspen flills" 23 0.93 SSE 158* Quarterly Exclusion Boundary & Annually State Split,Co-location Orange, VA 24 22.00 NW 325* Quarterly Control & Annually . Bearing Cooling Tower . N-1/33 0.06 N IT Quarterly On-Site Sturgeon's Creek N-2/34 3.20 i 11' Quarterly Marina Parking lot "C" NNE-3/35 0.25 NNE 32* Quarterly - On-Site (on-site) Good llope Church NNE-4/36 4.96' NNE 25* Quarterly State Split Parking lot "B" NE-5/37 0.20 NE 42* Quarterly On-Site Lake Anna Marina NE-6/38 1.49 NE 34* Quarterly WeatherTower Fence ENE-7/39 0.36 -ENE-74* Quarterly On-Site Route 689 ENE-8/40 2.43 ENE 65* Quarterly . NearTraining E-9/41 0.30 .E 91* Quarterly On-Site Facility , y e s. 3 -'w. a w ._. -+ --L--- ---------. O .O - G TABLE 2 . (Page 2 of 5) North Anna Power Station - 1993 RADIOLOGICALSAMPilNG STATIONS DISTANCE AND DIRrfT10N FROM UNrr NO.1 Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental Morning Glory llill' E-10/42 _ 2.85 E 93* Quarterly Thermoluminescen t Island Dike ESE-II/43 0.12 ESE 103* Que.erly On-Site Dosimetry (TLD) ' Route 622 ESE-12/44 4.70 ESE 115* Quarterly VEPCO Biology Lab SE-13/45 0.75 SE 138* Quarterly On-Site Route 701 (Dam 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 Gate S-17/49 0.22 S 173* Quanerly On-Site Elk Carek Church S-18/50 1.55 S 178* Quarterly NAPS Access Road SSW-19/51 0.36 SSW 197* Quarterly On-Site Route 618 SSW-20/52 5.30 SSW 205* Quarterly NAPS Access Road SW-21/53 0.30 SW 218' Quarterly On-Site 'y Route 700 SW-22/54 4.36 SW 232* Quarterly ; 500 kv Tower WSW-23/55 0.40 WSW 237* Quarterly On-Site Route 700 WSW-24/56 1.00 WSW 242* Quarterly Exclusion Boundary (Exclusion Boundary) NAPS RadioTower W-25/57 0.31 W 27 7 Quarterly On-Site Route 685 W-26/58 1.55 W 274* Quarterly End of Route 685 WNW-27/59 1.00 WNW .30l* Quarterly Exclusion Boundary IL Purcelfs Private Rd. WNW-28/60 1.52 WNW 303* Quarterly Co-location End of #1/#2 Intake NW-29/61 0.15 NW 321* Quarterly On-Site Ide Anna Campgrourd 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 344' Quanerly Bumpass Post Office C-1/2 7.30 SSE- 1.67* Quarterly Control Orange, VA C-3/4 22.00 - NW 325* Quarterly Control Mineral.VA . C-5/6 7.10 WSW 243' Quarterly Control Imuisa. VA . C-7/8 11.54 - WSW ~257' Quarterly ' Control E

I . _ _ _ __ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ ________m_.m_._._m _. .__2 m_ - - s - s , , _, m . ._ m. O- O- G . TABLE 2 (Page 3 ef 5) - North Anna Power Station - 1933 RADIOLOGICALSAMPilNG STATIONS DISTANCE AND DIRR"110N FROM UNTT NO.1 Distance Compass Collection . Sample Media Location Station Miles Direction Degrees Frequency Remarks 1 , Airborne Particulate NAPS Sewage 01 0.20 NE 42' Weekly On-Site, State Split and Radioiodine Treat:rrot Plant . Fredericks IIaB 02 5.30 SSW 205* Weekly Mineral.VA _ 03 7_10 WSW 243* Weekly - Wares Crossroads 04 5.10 %WW 287* Weekly Route 752 05 4.20 NNE 2[F Weekly - Sturgem's Creek Marina 05A 3.20 N 11* Weekly levy, VA 06 4.70 ESE 115* Weekly Bumpass, VA - 07 7.30 SSE- 167* Weekly

End of Route 685 21 1.00 WNW 30l* Weekly Exclusion Boundary Reute 700 22 1.00 WSW 242* Weekly Exclusion Bcunaary State Split l

" Aspen Ilills" 23 0.93 SSE 158' Weekly Exclusion Boumiary > Orange, VA 24 22.00 NW 325' Weekly Control s Surface Water Waste lleat 08 1.10 SSE 148' Mont!Jy State Split y Treatment FaciEty (Secmd Coolmg Lagoon)

lake Anna (upstream) 09 2.20 NW 32(P Monthly Control. State Split (Route 20S Bridge) 4

Lake Anna (upstream) 09A 12.90 WNW 295* Monthly Cmtml (Route 669 Bridge)

River Water Ncrth Anna River 11 5.80 SE 128* Monthly (downstream) - Ground Water Biology Lab OIA O.75 SE 138' . Quarterly Stare Split (Well Water) Precipitation Biciegy Lab OIA 0.75 SE 138' Monthly -Aquatic Sediment Waste IIcat 08 1.10 SSE 148' Semi-Annually State Split Treatment Facility

(Second Coolmg Lagoon) >

12ie Anna (upstream)- 09 2.20 NW 32(P Semi-Annually - Control, State Split North Anna River 11 5.80 ' SSE 128* Semi-Annually (Downstream) - ,

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

W _r m._ -. _ - . w-+ -w . O O O TABLE 2 (Page 4 of 5) North Anna lher Station - 1993 RADIOLOGICAL SAMPLING STA IlONS DISTANCE AND DIRECITON FROM UNIT NO. I Dista nce Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Shoreline Soit li Anna (upstream) 09 2.20 NW 320* Semi-Annually State Split (Rouk_208 Bridge) Soll 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 VA 03 7.10 WSW 243' Once/3 years ~ Wares Crossroads 04 5.10 WNW 287* Once/3 years Route 752 05 4.20 NNE 2tr Once/3 years Sturgeon's Creek Marina 05A 3.20 N 11' Once/3 years levy, VA 06 4.70 ESE 115' Once/3 years Bumpass, VA 07 7.30 SSE 167* Once/3 years End of Route 685 21 1.00 WNW 301* Once/3 years Exclusion Boundary Route 700 22 1.00 WSW 242' Once/3 years Exclusion Boundary (Exclusion Boundary) " Aspen Ilills- 23 0.93 SSE 158* Once/3 years Exclusion Boundary Orange. VA 24 22.00 NW 325' Once/3 years Control to Milk llolladay Dairy 12 8.30 NW 31tP Monthly State Split (R.C. Goodwin) Terreirs Dairy 13 5.60 SSW 205* Monthly State Split (Fredericks IIall) Fish * *

Waste IIcat 08 1.10 SSE 148' Semi-Annually State Split Treatment Facility (Second Cocling Lagoon)

Lake Anna (upstream) 09 2.20 NW 320 Semi-Annually State Split (Route 208 Bridge) Lake Orange

25 16.5 NW 312* Semi-Annually Control Food Products Route 713 14 1.20 NE 43' Monthlyif available (Broadleaf or at harvest Vegetation) Route 614 15 " 1.70(1.37) SE 133' Monthlyif available or at harvest 1

Added as result of 1990 Quality Assurance Audit.

- Imation changed as a result of 1991 Land Use Census to garden at 137 miles October 1991. .',

- - Fish sample no longer obtamed at station #09.

~ O O 10 TABLE 2 (Page 5 of 5) Nonh Anna Power Station - IW3 RADIOLOGICAL SAhtPilNG STA110NS DISTANCE AND DIRECITON FROh! UNIT NO. I Distance Compass Collection Sample Media Location Station Miles Direction Deerees Frequenev Remarks Food Products Route 629/522 16 12.60 NW 314* Monthly if available (Broadleaf or at hanrst Vegetation) End of Route 685 21 1.00 WNW 301' Monthly if available or at harvest Aspen Ilills ' 23 0.93 SSE 158' Monthly if available or at banest 'I w o

- Added as result of 1990 Quality Assurance Aixlit.

Legend For The North Anna Power Station (} Environmental Monitoring Stations Overview Maps 1 Map Environmental Sta Map Environmental Sta Designation Identification Designation Identification 1* 01,NE-5/37 7/8 C-7&8 1A 01 A,SE-13/45 1/33 N-1/33 2* O2,SSW-20/52 31/63 NNW-31/63 3* 03 C-5/16 29/61 NW-29/61 4* 04 3/35 NNE-3/35 5* 5 7/39 ENE-7/39 l 5A+ 05A,N-2/34 9/41 E-9/41 6+ 6,ESE-12/44 11/93 ESE-l l/43 7* 07,C- 1 &2 17/49 S-17/49 8 8-Water, Fish Sediment 19/51 SSW-19/51 9 09-Shoreline Soil Stations 21/53 SW-21/53 NW-30/62 9A 09A-Water sample, sediment 23/55 WSW-23/55 O u n-aiver 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 21* 21,WNN-27/59 28/60 WNW-28/60 22* 22,WSW-24/56 32/64 NNW-32/64 23* 23-SSE-15/47 8/40 ENE-8/40 24*I 24,C-3&4 4/36 NNE-40/36 252 25-Fish 10/42 E-10/42

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1. Table 3 summarizes the analysis program conducted by Teledyne Isotopes for North -

Anna Power Station during 1993. O P P C L F O 37 , - - - - - - ~ . ~ s,, , , TABLE 3 (Page 1 of 3) O soRTHissA eownR STArios SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY A N A LYSIS LLD* REPORT UNITS Thermoluminescent Quanerly Gamma Dose 2mRi2mR mR/std. month Dosimetry (TLD) (84 Routine Station TLD's) 12 Station TLD's Annually Gamma Dose 2mRi2mR mR/std. month Airborne Weekly I-131 0.07 pCi/m3 Radioiodine Airborne Weekly Gross Beta 0.01 pCi/m3 Particulate Quarterly (1) Gamma Isotopic pCi/m 3 Cs-134 0.05 Cs-137 0.06 Annually Sr-89 0.005 pCi/m3 r~ (2nd Quaner Sr-90 0.0002 d Composite) Surface Water Monthly I-131 1 pCi/l Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 Co-58, 60 15 Zn-65 30 Zr-Nb-95 15 Cs-134 15 Cs-137 18 4 Ba-La-140 15 Quarterly (1) Tritium (H-3) 2000 pCi/l 2nd Quarterly Sr-89 5 pCi/l Composite Sr-90 1 , d (1) Quarterly Composites of each location's samples will be used for the required analysis. 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 Q' Teledyne Isotopes may be lower than those listed. 1 38 l l 1 I i l l TABLE 3 (Page 2 of 3) O Noaru xNNA POwna SrarioN SAMPLE ANALYSIS PROGRAM l SAMPLE MEDI A FREQUENCY A N A LYSIS LI.D* REPORT UNITS l l River Water Monthly I-131 1 pCi/l .l Gamma Isotopic pCi/l i Mn-54 15 ! Fe-59 30 Co-58,60 15 , Zn-65 30 1 - Zr-Nb-95 13 Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Tritium (H-3) 2000 pCi/l 2nd Quarter Sr-89 5 pCi/l Sample Sr-90 1 Ground Water Quarterly Gamma Isotopic pCi/l (Well Water) 2nd Quarter Mn-54 15 Composite Fe-59 30 0 Co-58.60 Zn-65 15 30 Zr-Nb-95 15 I-131 1 Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Tritium (H-3) 2000 pCi/l 2nd Quarter Sr-89 5 Composite Sr-90 1 Aquatic Semi-Annually Gamma Isotopic - pCi/kg (dry) Sediment Cs-134 150 Cs-137 180 Annually Sr-89 200 pCi/kg (dry) Sr-90 40 Shoreline Soll Semi-Annual Ganuna Isotopic pCi/kg (dry) Cs-134 150 Cs-137 180 Annually Sr-89 200-Sr 40-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 isotopes may be lower than those listed. 39 , TAllLE 3 (Page 3 of 3) } NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Soil Once per 3 yrs. Gamma Isotopic pCi/kg (dry) Cs-134 150 Cs-137 180 Once per 3 yrs. Sr-89 200 pCi/kg (dry) Sr-90 40 Milk Monthly I-131 1 pCill , Monthly Gamma lsotopic pCi/l Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Sr-89 5 pCi/l Sr-90 1 Fish Semi-Annual Gamma Isotopic pCi/kg (wet) O Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Monthly if Gamma Isotopic pCi/kg (wet) (11roadlenf available or Vegetation) at harvest Cs-134 60 Cs-137 80 I-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 I reported. 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 i Teledyne Isotopes may be lower than those listed. l 40 i Table 4 REMP Exceptions For Scheduled & Sampling And Analysis During 1993 - North Anna Location Description Date of Sampling Reasons (s) for Loss / Exception W-27 River Water 12/31/93 LLD for 1-131 not met due to late receipt of W-33 State Split sample from the State of Virginia. O O 41 1 V. Summary And Discussion of 1993 Analytical Results Data from the radiological analyses of environmental media collected during the report period are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Isotopes Quality Assurance Manual and are explained in the Teledyne Isotopes 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 Isotopes analytical methods meet the O uwer umit of Derecu<m uD> <cquirements yiven in Tabie 2 0f the usxRC aranch Technicai Position of Radiological Monitoring (November 1979, Revision 1) and the ODCM. The following is a discussion and summary of the results of the environmental measurements taken during the 1993 reporting period. A. Airborne Exposure Pathway

1. Air lodine /Particulates Charcoal cartridges used to collect airborne iodine were collected weekly and analyzed by a radiochemical separation procedure 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/m 3and a range of 0.010 to 0.036 pCi/m 3 The average measurement for the indicator locations was 0.021 pCi/m3 with a range of 0.006 to 0.056 pCi/m3. The results l of the gross beta activities are presented in Table B-2. The gross beta activities for 1993 were comparable to levels measured in the 1982-1992 period. Prior to that period the gross Q beta activities were higher due to atmospheric nuclear weapons testing by other countries. l I 42 =- 4 TRENDING GRAPH-1: GROSS BETA IN AIR PARTICULATES 1_ o k O.1- d l i- - - -- -~ - - - - - - - - - -- l 0.01 ;>--------------------------- - - - - - - -4 , u. M 0.001 ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, 1986 1987 1988 1989 1990 1991 1992 1993 --R - Control Sta-24 --O-- Indicator - -- Average Pre op -+ Required LLD's O TRENDING GR APH 2: TRITIUM IN RIVER WATER-STATION-11 10000

r -

- +.-----------.-------------------, E '0U & 1 l. 100 - N 8" 10 -- ~ 1 ) l 1 , , , , , , , ,. 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tritium - + - Required LLD's (/ During the preoperational period river water was not measured. I 'l I 43 During the preoperational period of July 1,1974 through March 31,1978 gross beta O activities ranged from a low of 0.005 pCi/m3 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 0.081' pCi/m3 with a range of 0.050 to 0.136 pCi/m3. The indicator locations had an average concentration of 0.083 pCi/m3 and a range of 0.038 to 0.154 pCi/m3. During the i preoperational period, beryllium-7 was measured at comparable levels, as would be expected. Naturally occurring potassium-40 was detected in one control samples with a1 I concentration of 0.049 pCi/m3 - Potassium-40 was detected in eight indicator samples with an average concentration of 0.020 pCi/m3 and a range of 0.010 to 0.035 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 ' i isotopes were attributed to atmospheric nuclear weapons testing conducted before the preoperational period. Among the isotopes measured were zirconium-95, ruthenium-103, l ruthenium-106, cesium-137, cerium-141 and cerium-144. O The second yuarte, comgesites of air particuiate fiiters f,om aii tweive stations were ; analyzed for strontium-89 and 90. There was no detection of these fission products at any j of the eleven indicator stations nor at the control station. l

2. Precipitation > l 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 1993 in the twelve samples was 5.34 pCi/ liter with a range from 2.5 to 16 pCi/ liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritium. All 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 thru 1992. During the pmoperational 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 1993 period. During the . preoperational period, tritium was measured in' aver half of the few quarterly compowes made. The tritium activity ranged from 100 to 330 pCi/ liter.

0 44

I - 3. Soil Soil samples are collected every thme years from twelve stations. Since they were collected in 1992, soil was not sampled during 1993. ) B. Waterborne 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 j Table B-6. No gamma emitting isotopes or tritium were detected during 1993. The second quarter sample was analyzed for strontium-89 and strontium-90. There were no detections I 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 period with concentradons between 80 and 370 pCi/ liter.

1

2. River Water A sample of water from the North Anna River was collected monthly at station 11,5.8 !

O miies downstream nem the di cherse ies-n,128 desrees SSe. The reseits are gresented in Table B-7. The samples were analyzed by gamma spectroscopy monthly. The samples were analyzed for tritium monthly.until July 1993, when the analysis was performed at the minimum required frequency, quarterly on a composite sample. The second quarter samples were analyzed in addition for strontium-89 and strontium-90.- , .l Potassium-40 was measured in one sample with a concentration of 139 pCi/ liter. All other j gamma emitters were below the detection level. No detections of strontium-89 or ! strontium-90 occurred. Tritium was measured in eight samples with an average level of 2750 pCi/ liter and a range of 1700 to 4000 pCi/ liter. This is lower than the the average l level measured in 1992 of 4000 pCi/ liter and a range of 3500 to 4600 pCi/ liter. No river 3 water samples were collected during the preoperational period. I 1

3. Surface Water

) ~ Samples of surface water were collected monthly from two stations. Station 08 is at the discharge lagoon,1,1 miles,148 degmes 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. 45 TRENDING GRAPH-3: TRITIUM IN SURFACE WATER STA 08 . ,ww 9 . n ~ n f - ' W eo i 1000 - B - e I 100 ,,,,,;,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, 1/77 1/78 1/79 1/80 1/81 1/82 1/83 1/84 1/85 1/86 1/87 1/88 1/89 1/90 1/01 1/92 1/93 - Tritiurn Required LLD's Unit 1 critical on 06/06/78. Unit 2 cntical on 12/14/80. O TRENDING GRAPH -4: COBALT-58 IN SEDIMENT SILT 1000 1 I 100 - E- E o . . f . 10- , 1 i - i i i i i i , , , i i i , i , , i 03/85 03/86 04/87 03/88 04/89 03/90 03/91 03/92 03/93 10/93 Station-8 Station-09 :-- Control Sta-09A . -+- Station-11 No cobatt-58 measured during pre-operatioal period. 46 1 ] 1 l I i i The samples wem also analyzed by gamma ray spectrometry. All gamma emitters were O beiow their detectiou ieveis at both station. A quarterly composite from each station was prepared and analyzed for tritium. The tritium a activity at station 08 for the quarterly composites was at an average level of 2400 pCi/ liter { with a range of 1900 to 3300 pCi/ liter. The tritium level had been increasing since the I middle of 1978 when the average level was below 300 pCi/ liter. However, during 1993 7 the msults were within the same range as those measured in 1986 thru 1992. During the preoperational period tritium was measumd in several samples with concentrations between ! 90 and 250 pCi/ liter. Tritium was not detected at station 09A. i Samples of surface water were collected by the Commonwealth of Virginia from two stations. Station W-33 is located at the discharge lagoon while station W-27 is located on the North Anna River at the RT. 208 Bridge, which is upstream of the site. Twenty-four samples were collected and analyzed by gamma ray spectroscopy and for tritium. The results are presented in Table B-9. All other gamma emitters were below their detection levels. Four samples from each station were analyzed for tritium during 1993. The average activity at station W-33 in all samples was 2850 pCi/ liter with a range of 2200 to 3800 pCi/ liter. This is lower than the 3833 pCi/ liter measured during 1992 at this station. Tritium was measured in two samples at station W-27 with an average activity of 1200 pCi/ liter and a range of 1000 to 1400 pCi/ liter. This is lower than the average of 2650 pCi/ liter measured at station W-27 during 1992. C. Aquatic Exposure Pathway

1. Sediment / Silt Sediment samples were collected during Mamb, September and October frorn each of thme locations and were analyzed by gamma spectrometry. The results are presented in Table B-10. A number of man-made and naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in five samples with an average activity of 161 pCi/kg (dry weight) and a range from 45.9 to 313 pCi/kg (dry weight). The highest reading for cesium 137 was obtained from station 08 located 1.10 miles SSE.

Naturally occurring potassium-40 was observed in all nine samples with an average activity of 10428 pCi/kg (dry weight) and a range from 2050 to 17200 pCi/kg (dry weight). 47 l TRENDING GRAPH - 5: COBALT-60 IN SEDIMENT SILT 1 1000. O a <T 100-E A o 4 ~ " /. A\. / ~ " " q_ _ _; . ' S - 7 E l tn 10 M R 1 , i i i , , i i i i i i i i i , , i 03/85 03/86 03/87 03/88 04/89 03/90 03/91 03/92 03/93 1 0/93 --M- Station-8 -*- Station-09 4- Control-Sta-09A -+- Station-11 No cobalt-60 measured during pre-operational period. l l O l TRENDING GRAPH - 6: CESIUM-134 IN SEDIMENT SILT 1000 i 1 I 100-- O 4 { {

. . . .> l z

f - ~ - [ ~ _" q,a l t - 10 -- l w . . < : 1 0" - _~ 1 i i i i i i i i i i . i i i i i i i 03/85 03/86 03/87- 03/88 04/89 03/90 03/91 03/92 03/93 10/93 Station 8 Station-09 ,e- Control-Sta-09A -+- Station-11 l 4 No cesium-134 measured during pre-operational period. l l 1 48 ) TRENDING ORAPH - 7: CESIUM 137 IN SEDIMENT SILT 10000 O '1000:

l 4

g o Z 100 y ,- / 4 f, dr - - E o M g 10 ) l I 1 . i i i i i i i i i i 6 i i i i i i 3/85 9/85 3/86 9/86 3/87 9/87 3/88 9/88 3/89 9/89 3/90 W90 3/91 991 3/92 9/92 3/93 99310/93 l 1 'I --m- Station-8 -.4-- Station-09 + Control-Sta-09A : Station-11 -+ Average Pre-Op i No cobalt-58 measured during pre-operational period. TRENDING GRAPH - 8: CESIUM 134 IN FISH 1000 e 1 c 100 - 1 l 5 . E : / l , j j O 1 \s/-/ PS--a a 10- A-4 : k . I 1 ie i i i i e i i i e i i i i i i i i i i i i i i i i i i i N80 4 82 N84 N85 N86 12/86 8/87 12/87 6/88 12/88 6/89 10/89 10/90 10/91 10/92 10/93 I Staton-08 Station-09 -&- Control-Sta 25 O Du,in a e greenereticeaine,iw eeeiem. m ee ns m eaeured. Station 25 replaced etation 09. 49 Radium-226 was measured in seven samples with an average concentration of 1485-h, pCi/kg (dry weight) and a range of 645 to 2190 pCi/kg (dry weight). Also naturally occurring , thorium-228 was observed in all nine samples with an average concentration of 674 pCi/kg (dry weight) and a range of 345 to 1370 pCi/kg (dry weight). The September 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 panod sediment samples were analyzed by gamma ray spectroscopy. Cesium-137 was measured in most of the samples with concentration between 33 and 1210 pCi/kg (dry weight). Strontium-90 was measured in most of the samples with concentrations between 60 and $40 pCi/kg (dry weight), Strontium-89 was not measured. Potassium-40, radium-226, and thorium-228, all naturally occurring, were measured at background levels.

2. Shoreline Soil A sample of shoreline sediment was collected in March and September 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 r.aturally occurring nuclide potassium-40 was measured in both samples with an average activity of 6315 pCi/kg (dry weight) and a range of 4440 to 8190 pCi/kg (dry weight). Thorium-228 was measured in both samples at an average of 1200 pCi/kg (dry weight) and a range of 1080 to 1320 pCi/kg (dry weight). Radium 226 was measured in both samples with an average activity of 1735 pCi-kg (dry weight) and a range of 1290 to 2180 pCi/kg (dry weight). Cesium 137, fission product, was monitored in both samples with an average level of 662 pCi/kg (dry weight) and a range of 174 to 1150 pCi/kg (dry weight).

The September sample was analyzed for strontium and there were no detections of strontium 89 or strontium-90. D. Ingestion Erposure Pathway

1. Milk G

V 50 1 i The results of the iodine-131 analysis of milk samples are presented in Table B-12. A Q sample was collected monthly from two stations. A total of 24 samples were analyzed during 1993. There wem no measurements ofiodine 131 above the detection limits. i l The milk samples were also analyzed by gamma ray spectroscopy and the results are also 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 1342 pCi/ liter and a range of 1190 to 1500 pCi/ liter. 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 samples during 1993. All other gamma emitters were below their detection levels. A quarterly composite was prepared from each of the two collection stations and analyzed for stmntium-89 and strontium 90. Strontium-89 was not detected at levels above LLD in any of the samples monitored. Stmntium-90 was detected in the eight samples monitored with an average level of 1.75 pCi/ liter und a range of 1.0 to 2.1 pCi/ liter. This is similar to activities determined in previous years and lower than the preoperational levels of 2.2 to 5.4 pCi/ liter.

2. Fish Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. The results are presented in Table B-13. Eight samples of fish were collected during 1993. These samples were analyzed by gamma ray spectroscopy and the naturally occurring isotope potassium-40 was found in all samples at an average of 1806 pCi/kg (wet weight) with a range of 1200 to 2460 pCi/kg (wet weight). The fission product cesium- -

137 was measured in four samples at an average of 69.5 pCi/kg (wet weight) and a range of 39.5 to 90.3 pCi/kg (wet weight). During the preoperational period cesium-137 was measured in one-fourth of the fish samples collected with concentrations between 31 and 66 pCi/kg (wet weight).

3. Food / Vegetation 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 of the samples with an average activity level of 15153 pCi/kg (wet weight) and a range of 5370 to 24000 pCi/kg (wet weight). Cosmogenic beryllium 7 was 51

TRENDING GRAPH - 9: CESIUM-137 IN FISH 10000. O 1000. = 100: s.a. C 4- / E / _4 10: 7 O k R' g 1 5/80 5/82 4/84 4/85 4/86 10/86 7/87 12/87 7/88 12/88 7/89 12/89 10/90 5/91 4/92 4/93 --R-- Station-08 --o- Station-09 -+- Station-25 -+ Average Pre-op , Station 25 replaosd staton 09. O TRENDING GRAPH - 10: ENVIRONMENTAL RADIATON TLD's 10 4__ ____._. ... .... ___ _ .____+ (?: _ y?": . e - t , ?, - b e S

5 H 2 .I

~ E l h 1 , , , , , . . . , , , , , , , , , , . . . . . . . . , , , , . E 1/86 7/86 1/87 7/87 1/88 7/88 1/89 7/89 1/90 7/90 1/91 7/91 1/92 -7/92 1/93 7/93 Environmental TLD's --+ -- Sector TLD's .+ Average Pre-op O ! l l l 52 d detected in all samples with an average concentration of 1607 pCi/kg (wet weight and a range of 169 to 5120 pCi/kg (wet weight). Radium was measured in one sample with a concentration of 246 pCi/kg (wet weight). The terrestrial nuclide thorium 228 was detected in five samples at an average activity of 141 pCi/kg (wet weight) and a range of 48.5 to 266 pCi/kg (wet weight). The fission product cesium-134 was not detected at levels above LLD during 1993. Cesium-137 was detected in ten samples with an average activity of 89.5 pCi/kg (wet weight) and a range of 12.2 to 353 pCi/kg (wet weight). These results are consistent with those measured in previous years. Cesium-137 was measured in broadleaf garden vegetation during the preoperational period with concentrations between 53 and 98 pCi/kg (wet weight). E. Direct Radiation Exposure Pathway

1. TLD Dosimeters Thermoluminescent dosimeters (TLDs) determine environmental radiation doses and the results are presented in Table B-15. Individual measurements of external radiation levels in the environs of the North Anna site had an average does of 5.7 mR/ standard month with a range of 3.4 to 9.7 mR/ standard month. The control station, No. 24, has an average reading of 3.9 mR/ standard month with a range of 3.4 to 4.3 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-

16. The average level of the 32 locations (two badges at each location) was 6.1 mR/ standard month with a range of 3.4 to 10.5 mR/ standard month. The eight control TLDs, collected quarterly from four locations, showed an average reading of 4.9 mR/

standard month with a range of 3.4 to 7.0 mR/ standard month. During the preoperational period (starting in 1977) when the calculation of the TLD dose included a correction for the intransit dose, the doses were measured between 4.3 and 8.8 mR/ standard month. O ~ 53 VI. Conclusions O The results of the 1993 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 particulate gmss beta concentrations of all the indicator locations for 1993 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 Chemobyl 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 potassiurn-40). There were no detections above the LLD for fission products nor other man-made isotopes in the particulate media during 1993. Iodine-131 was not detected in the 624 charcoal filters analyzed during the first three quarters of 1993. A precipitation sample was collected monthly during 1993 and analyzed for gross beta O activity. ^ii the aross beta activities were comparable to those measured in previous years. During the preoperational period the average gross beta activity was 0.92 pCi/ liter. 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 reponing period in 1993. During the preoperational period the average tritium activity was 165 pCi/ liter. Waterborne Exposure Pathway No man-made or natural isotope t wem monitored in the surface water of Lake Anna except tritium. The average tritium activity duing 1993 at the. waste heat treatment facility was 2400 pCiAiter which is 12.0% of the reporting level for a water sample. In 1992 the tritium level was 3950 pCiAiter. The preoperationallevel 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 mearnrement of 2300 pCi/ liter as compared to I 3360 pCi/ liter for 1992. The upstream location had two measurements at an average of 1200 pCi/ liter as compared to 2650 pCi/ liter for 1992. No gamma emitting isotopes were detected. 4 54 l l i River water collected from the North Anna River,5.8 miles downstream of the site had an ] / average tritium level of 2814 pCi/ liter. The average tritium in 1992 had been 4000 pCi/ liter. No gamma emitters wem detected. Ground water from the environmental well on site contained no gamma emitters. There were also no detections of tritium in ground /well water during 1992. Aquatic Pathway Sediment / silt samples provide a sensitive indicator of discharges from nuclear power stations. The sediment from North Anna environmental samples indicated that two man-made isotopes were prese'rit. Cesium-137 was detected in five samples at two locations. During the-preoperational period, cesium-137 was measured in samples of aquatic sediment. In 1993 cobalt-60 was measured in two samples at an average of 56.5 pCi/kg. 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 662 pCi/kg which was slightly higher than the average of 534 pCi/kg detected in 1992. Ingestion Pathway Iodine-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 1993. Strontium-90 was measured in all eight milk samples. Strontium-90 is attributed to past l 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. ] l Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples during 1993 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 1992. Only cesium-137 was measured in preoperational environmental fish samples. Due to primary and secondary steam generator problems experienced at Nonh Anna during 1984/1985, a build up in activity levels both in effluents and fish did occur. Q Repairs to the steam generators and better liquid waste processing have reduced these activity I 55 levels in effluents and thus decreased activity levels are now being observed in the fish. The O evera8e ievei ef activitv ie i993 ef cesium-i>> was 3.0.* ef the revertins ievei. Vegetation samples contained the man-made isotope cesium 137. The cesium-137 activity levels during 1993 and in preoperational samples were statistically similar to the 1992 level.. 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 internal dose from natural radionuclides. Program Conclusions The results were as expected for normal environrnental 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 ar very low concentrations and had no significant dose consequence. As a method of referencing the measure 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 North Anna Nuclear Power Station during 1993. O 56 Vll. References

1. Virginia Electric and Power Company, North Anna Power Station Technical Specifications, Units I and 2.

2. Virginia Electric and Power Company, Station Administrative Procedure, VPAP-2103, "Offsite Dose Calculation Manual," Rev. O, May 31,1990.

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 G472, " Radiological Effluent Technical Specifications for PWRs," Rev. 3, March 1982.

8. National Council on Radiation Protection and Measurements, Report No. 39, " Basic Radiation Protection Criteria," Washington, D.C., January 1971.

9. National Council on Radiation Protection and Measurements, Report No. 45, " Natural Background Radiation in the United States," Washington, D.C., November 1975.

10. National Council on Radiation Protection and Measurements, Report No. 93, " Radiation Exposure of the Population of the United States, Washington, D.C., December,1987.

I1. National Council on Radiation Protection and Messurements, Report No. 95, " Radiation Exposure of the U.S. Population from Consumer Products and Miscellaneous Sources," Washington, D.C., December 1987.

12. DOE /NE-0072, " Nuclear Energy and Electricity, The Harnessed Atom," US Dept. of Energy,1986.

I3. Eichholz, G., " Environmental Aspects of Nuclear Power," Lewis Publishers, Inc.,1985.

14. Eisenbud, M., " Environmental Radioactivity," Academy Press, Inc., Orlando, F1,1987.

15. Fitzgibbon, W., " Energy Skill Builders, Nuclear Reactor," Enterprise for Education, Inc.,

1987.

16. Glasstone, S., and Jordan, W., " Nuclear Power and its Environmental Effects,"'American Nuclear Society,1982.

C' 57 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

-O - North Anna Nuclear Power Station, Louisa County, Virginia - 1993 Docket No. 50-338/339 January 1 to December 31,1993 Page 1 of 6 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD1 R* Ported Sampled Total Mean Name Distance Mean - Mean Weasure- , (Unit) Type No. Range Direction Range Range ments , Air lodine I131 624 0.04 -(0/572) NA NA -(0/52) 0 (pCi/m3 ) . Airborne Gross 624 5 20.8(572-572) 03 7.10 mi. 22.9(52/52) 20.7(52/52) 0 Particulates Beta (5.9-50) WSW (12-56) (9.6-36) (1E-03 pCi/m3) Gamrna 48 Bo-7 48 10 83.4(44/44) 07 3.20 mi. 104(4/4) 81.0(4/4)- 0

i. (37.6-154) N (63.6-138) (50.2 136)

K-40 48 10 19.6(8/44) 05 5.10 mi. 29.6(3/4) 48.7(1/4) 0 (10.4 35.3) WNW (21.1 35.3) - Sr-89 12 3 -(0/11) NA NA -(0/1) 0

                                                                      ~                                                                         ~

O- Sr 90 12 0.4 -(0/11) NA NA -(0/1) 0 Ground Gamma 4 Well Water - K-40 4 60 -(0/4) N/A N/A NONE o (pCi/ liter) - Tritium 4 2000 -(0/4) N/A N/A' NONE o

                                                                      .                                                                                             .l River         Gamma              12                                                                                                                       i Water (pCi/ liter)    K-40             12 200              139(1/12)              11 5.8 mi SSE           139(1/12)                  NONE            O           l
                                                                                                                                                                    }

l Tritium 8 2000 2750(8/8) 11 5.8 mi.SSE 2750(8/8) NONE O j l (1700-4000) (1700-4000) Sr-89 1 3 -(0/1) NA NA NONE o Sr90 1 04 -(0/1) NA NA NONE O

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, Revision 1, November 1979. 58 i l 1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

b North Anna Nuclear Power Station, Louisa County, Virginia - 1993-Docket No. 50-338/339 January 1 to December 31,1993 Page 2 of 6 l All Indicalor Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD1 Reported , Sampled Total Mean Name Distance Mean Mean Measure-(Unit) - Type No. Range- Direction Range Range monts Precipitation Monthly (pCl/ liter) Gross 12 4 5.34(11/12) 01 A 0.2 ml. 5.34(11/12) NONE O Beta (2.5-16) NE (2.5 16) Gamma 2 (Semi-Annually) Be 7 2 70 -(0/2) N/A N/A NONE O Tritium 2 2000 -(0/2) N/A N/A NONE 0 Surface I131 24 0.5 -(0/12) N/A N'A -(0/12) 0 Water - - (pCl/ liter) . Regular Gamma 24 i' Monthlies K-40 24 200 -(0/12) N/A N/A -(0/12) 0 Tritium 8 2000 2400(4/4) 08 1.10 mi 2400(4/4) -(0/4) 0 (1900 3300) SSE (1900 3300) i Surface Sr-89 1 2000 -(0/1) N/A N/A- -(0/1) 0 Water - - - (pCl/ liter)

            - Regular .                  Sr 90       1   2000                      -(0/1)                   N/A.               N/A                 -(0/1)        0 Monthlies                                                                  -                                                                -

Surface Gamma 24 l Water (pCi/ liter) K-40 24 200 -(0/24) N/A N/A NONE: 0

            . State Splits                                                               -

, Tritium 14 2000 2300(6/8) W33 2850(4/4) NONE O (1000-3800) (2200-3800) l i h 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. 59 b 4 & e w- --w-m- m- p=sm-'w 2:---r-- +---*vs - temur u'---ie e- y -w y--g y-

                                                                                                                                                                      * * =

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

O. North Anna Nuclear Power Station, Louisa County, Virginia - 1993 Docket No. 50-338/339 January 1 to December 31,1993 Page 3 of 6 AllIndicalor Contr01 Non-l Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD1 Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments Sediment Gamma 9 Silt (pCl/kg K-40 9 200 9192(6/6) 11 5.8 ml 15250(3/3) 12900(3/3) 0 (dry)) (2050 17200) SSE (14200-16300) (10700-14000) Co-60 9 56.5(2/6) 08 1.10 mi SSE 56.5(2/3) -(0/2) 0 (30.7-82.2) (30.7-82.2) - l Cs 137 9 194 204(3/6) 081.10 mi SSE 204(3/3) 96.5(2/3) 0 ; (138 313) (160 313) (45.9 147) j Ra 226 9 100 1629(5!0) 11 5.8 mi SSE 2137(3/3) 1127(2/3) 0 (645-2190) (2080-2190) (863 1390) Th-228 9 30 786(6/6) 11 5.8 ml. 1154(3/3) 449(3/3) 0 (349 1370) SSE (963-1370) (345-610) O St-89 3 4.0 -(0/2) N/A N/A -(0/1) 0 (Annually) - - St-90 3 0.8 -(0/2) N/A. N/A (0/1) 0 (Annually) - - - 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. 60

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

O North Anna Nuclear Power Station, Louisa County, Virginia - 1993 Docket No. 50-338/339 January 1 to December 31,1993 Page 4 of 6 Allindicalor Control Non-Medium or Analysis Locations Location with Hlahest Mean Location routine Pathway LLD1 Reported Sampled Total Mean Name Distance Mean Mean Measure) (Unit) Type No. Range Direction Range Range ments l Shoreline Gamma 2 Soll (pC1/kg K-40 2 200 6315(2/2) 9 2.2 mi. 6315(2/2) NONE O (dry)) (4440-8190) NW (4440-8190) Cs-137 2 40 662(2/2) 9 2.2 mi. 662(2/2) NONE O (174-1150) NW (1174-1150) Ra-226 2 100 1735(2/2) 9 2.2 mi. 1735(2/2) NONE O (1290-2180) NW (1290-2180) Th-228 2 30 1200(2/2) 9 2.2 mi. 1200(2/2) NONE 0 (1080-1320) NW (1080-1320) Sr-89 1 4.0 -(0/2) NA NA NONE O (Annually) Q Sr-90 (Annually) 1 0.8 -(0/2) NA NA NONE 0 I i I O ' uo is i"e 'o er timit oi oeiection es derined end required in usNRC erancn recnnicai eosition on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. 61

l l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

O North Anna Nuclear Power Station, Louisa County, Virginia - 1993 ! Docket No. 50-338/339 January 1 to December 31,1993 Page 5 of 6 i AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD1 ileported Sampled Total Mean Name Distance Mean . Mean Measure-(Unit) - Type No. Range Direction Range Range ments Milk l-131 24 0.5 -(0/24) N/A N/A -NONE- 0-(pCl/ liter) - Gamma 24 K-40 24 100 1342(24/24) 12 8.3 ml. 1387(12/12) NONE O (1190-1500 NW (1190-1500) Sr-89 8 5 -(0/8) N/A N/A NONE O (Quadedy) - Sr-90 8 0.8 1.75(8/8) 13 5.60 ml 1.95(4/4) NONE O (Ouarterly) (1.0-2.1) SSW (1.5-2.1) Fish Gamma 8 pCi/kg O (wet) K 40 8 200 1800(4/4) 25 16.5 mi. 1813(4/4) 1813(4/4) 0 (1200 2390) NW (1330-2460) (1330-2460) Cs 137 8 40 69.5(4/4) 08 1.10 mi, 69.5(4/4) -(0/4) 0 (39.5-90.3) SSE (39.5-90.3) - Food Gamma 35 Vegetation Dose (pCi/kg Be-7 35 - 1607(35/35) 23 0.93 mi 2284(7/7) NONE O (wet)) (169-5120) SSE (1460-2990) K-40 35 - 15153(35/35) 14 1.20 ml. 17243(7/7) NONE O (5370-24000) NE (12400-21100) Os-137 35 80 89.5(10/35)- 21 1.00 mi. 125(5/7) NONE O (12.2-353)- WNW (34.1-353) Ra-226 35 80 246(1/35) 14 1.20 ml. 246(1/7) NONE O NE - Th-228 35 - 141(5/35) 23 0.93 mi 164(4/7) NONE- 0 (48.5-266) SSE (101 266) O ' ttD is ine tower timii ot Deiection es eerinea ano requiree in uSNRC erancn Tecnnicai eosition on an ! Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. l l I l 62

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

O North Anna Nuclear Power Station, Louisa County, Virginia - 1993 Docket No. 50-338/339 January 1 to December 31,1993 Page 6 of 6 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD1 Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments Direct Gamma 48 0.2 5.85(44/44) 01 0.2 mi. 7.90(4/4) 3.88(4/4) 0 Radiation Dose (3.9-9.7) NE (6.9-9.3 (3.44.3) (mR/std. month) (Regular TLDs) Direct Gamma 12 0.2 5.76(11/11) 01 0.2 mi 8.0(1/1) 3.9(1/1) 0 Radiation Dose (4.3-8.0) NE - - (mR/std. Month) (Annual TLDs) Direct Gamma 288 0.2 6.29(256/256) 21/53 0.30 mi 8.90(8/8) 4.85(32/32) 0 Radiation Dose (3.5-10.5) SW (8.2-10.4) (3.4 7.0) (mR/std. Month) )

 ,] (Sector TLDs)                                                                                                               ;

i 4 l l l l l l O ' uD is the 'o er 'imit ot Detectica as devined and required in uS"ac erenca Tecnnicei eosit'on oa en Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. 63 u

O 1 l ~ APPENDIX B DATA TABLES .O

TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR Q No'rth Anna Power Station, Louisa County, Virginia - 1993 pC1/m3 2 Sigma January 1 to December 31,1993 Page 1 of 2 Collectica STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23' 24

JANUARY 12/30-01/06 <.007 <.008 <.004 < .008 < .01 <.01 <.006 <.008 <.01 <.008 <.007. <.009 01/06-01/13 <.006 <.006 <.006 < .007 < .008 <.008 <.006 <.007 <.007 < .01(a) < .009(a)< .007 01/13-01/20 <.007 <.007 <.006 < .006 < .007 <.006 <.007 <.007 <.007 <.006 <.009 <.008 01/20-01/27 < .008(a)< .005 <.005 < .006 < .007 <.006 <.007 <.006 <.006 <.007 <.007 <.007 01/27-02/03 <.007 <.008 <.007 < .008 < .007 <.01 <.008 <.009 <.009 <.009 < .008 . < .01 FEBRUARY 02/03-02/10 <.01 <.01 <.01 <.02 <.01 <.01 <.009 < .009 . < .01 <.01 <.009 -<.01 02/10-02/17 <.007 <.009 <.007 < .007 < .008 <.007 <.007 < .006 < .007 <.008 <.00s <.007 02/17-02/24 <.006 <.006 <.007 < .006 < .006 <.005 <.007 <.006 <.006 <.007 <.007 <.006 02/24 03/03 <.007 <.008 <.007 < .007 < .007 <.009 <.01 <.006 <.006 <.006 <.008 <.007 MARCH 03/03-03/10 <.008 <.01 <.01 <.01 <.01 <.009 <.01 <.008 <.01 <.01 <.01 <.007 , 03/10-03/17 <.007 <.006 <.009 < .008 < .01 <.009 <.007 <.009 <.007 <.01 <.009 <.007 03/17-03/24 <.003 <.002 <.003 < .003 < .003 <.003 <.003 <.003 <.003 <.003 <.003 <.002 03/24-03/31 <.006 <.005 <.007 < .007 < .007 <.006 <.008 <.007 <.008 <.007 <.007 <.007-APRIL 03/31 04/07 <.006 <.007 <.008 < .007 < .006 <.007 <.007 <.006 <.006 <.007 <.006 <.006 04/07-04/14 <.01 <.01 <.01 < .008 < .008 <.009 <.008 <.007 <.01 <.007 <.008 '<.009 04/14-04/21 <.008 <.008 <.007 < .008 < .007 <.008 <.007 <.008 <.006 <.006 <.009 <.007 04/21-04/28 <.01 <.008 <.009 < .008 < .008 <.007 <.008 <.006 <.008 <.01- <.008 <.008 04/28-05/05 <.008 <.008 <.007 < .009 < .009 <.007 <.009 <.007 <.008 <.01 <.007 <.009 MAY 05/05-05/12 <.007 <.008 <.009 < .008 < .008 <.007 <.009 <.008 <.006 <.009 <.008 < .02(a) 05/12-05/19 <.01 <.008 <.01 <.01 <.008 <.008 <.01 <.01 <.008 <.008 <.008 <.009 05/19-05/26 <.006 <.005 <.008 < .009 < .008 <.008 <.01 <.007 <.008 <.009 <.005 <.01 05/26-06/02 <.006 <.006 <.007 < .008 < .009 <.008 <.009 <.006 <.007 <.01 <.02 <.01 JUNE 06/02-06/09 <.007 <.007 <.007 < .009 < .007 <.005 <.008 <.007 <.007 <.007 <.008 <.007 06/09 06/17 <.005 <.005 <.006 < .005 < .006 <.007 <.006 <.009 <.006 <.008 <.009 <.009 06/17-06/23 < .01 <.01 <.009 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.008 <.009 06/23 06/30 <.01 <.01 <.01 <.01 <.01 <.01 <.02 <.01 <.02 <.01 <.01 .<.01 O (a) Sampler malfunction. l 64

TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR O Norin Anne eower station, touise county, virginie - ,993 ! pD'm3t 2 Sigma January 1 to December 31,1993 Page 2 of 2 ) Collection STATIONS l Date 01 02 03 04 05 05A 06 07 21 22 23 24 i M)LY 06/30-07/07 <.009 <.01 <.01 < .009 < .009 <.009 <.01 <.007 <.008 <.008 <.009 <.009 07/07-07/15 <.009 <.01 <.009 <.004 <.005 <.005 <.004 <.004 <.005 <.004 <.007 <.007 07/15-07/21 <.01 <.008 <.007 <.01 <.009 <.009 <.01 <.007 <.009 <.009 <.008 <.008 07/21 07/28 <.009 <.008 <.008 < .009 < .009 <.009 <.01 <.008 <.008 <.008 <.008 <.008 07/28-08/04 <.009 <.009 <.007 < .009 < .008 <.01 <.009 <.008 <.009 <.008 <.009 <.008 AUGUSI 08/04-08/11 <.007 <.007 <.007 < .007 < .007 <.007 <.007 <.01 <.008 <.009 <.007 <.008 08/11-08/18 <.009 <.007 <.01 < .008 < .01 <.009 <.01 <.009 <.009 <.008 <.01 <.008 08/18-08/25 <.008 <.01 <.007 <.01 <.008 <.009 <.01 <.009 <.008 <.01 <.008 <.008 08/25-09/01 <.01 <.008 <.008 < .009 < .009 <.008 <.008 <.008 <.01 <.01 <.01 <.009 SEPTEMBEB 09/01-09/08 <.008 <.008 <.02 < .007 < .008 <.009 <.008 <.006 <.006 <.008 <.002 <.008 09/08-09/15 <.006 <.006 <.006 < .007 < .008 <.007 <.007 <.005 <.006 <.007 <.002 <.002 m 09/15-09/22 <.006 <.007 <.008 < .006 < .006 <.007 <.008 <.006 <.009 <.01 <.008 <.008 09/22-09/29 <.008 <.009 <.008 < .009 < .008 <.007 <.007 <.007 <.006 <.007 <.009 <.007 QCIDBEB 09/29-10/06 <.008 <.01 <.008 <.01 <.009 <.009 <.009 <.008 <.007 <.008 <.01 <.008 10/06-10/13 <.02 <.003 <.02 < .009 < .02 <.01 <.02 <.02 <.003 <.01 <.02 <.004 10/13 10/20 <.008 <.008 <.006 < .007 < .008 <.008 <.007 <.008 <.006 <.008 <.007 <.007 10/20-10/27 <.007 <.008 <.008 <.01 <.008 <.01 <.008 < 008 <.008 <.01 <.009 <.008 10/27-11/03 <.007 <.008 <.008 <.009 <.007 <.01 <.009 <.009 <.009 <.01 <.008 <.009 NQYEMBEB 11/03 11/10 <.02 <.01 <.01 <.01 <.01 <.01 <.01 <.008 <.01 <.01 <.01 <.01 11/10-11/17 <.02 <.03 <.02 < .02(a)< .03 <.03 <.03 < .03 <.03 <.02 <.02 <.03 1 11/17-11/24 <.01 < .05 <.01 <.02 <.01 <.01 <.01 <.02 <.01 <.02 < .01 <.01 : 11/24 12/01 <.01 <.02 <.01 <.02 <.02 <.01 <.01 <.01 <.01 <.02 <.009 <.009 ) DECEMllEB 12/01-12/08 <.02 <.02 <.02 <.02 <.01 <.02 <.01 <.01 <.01 <.008 <.01 <.003 12/08-12/15 <.01 <.01 <.01 <.01 <.007 <.02 <.02 <.02 <.02 <.01 <.01 <.003 1 12/15-12/22 <.03 <.03 <.03 <.03 <.02 <.01 <.01 <.01 <.01 <.01 <.01 <.009 12/22 12/29 <.01 <.01 <.01 <.01 <.009 <.02 <.02 <.02 <.02 <.01 <.02 <.01 1 l l O (a) Low sample volume. 65

O O O TABLE B-2 (Page 1 of 4) NORT11 ANNA - 1993 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 1.0E-03 pCum3 12 Sigma COLLECTION 1993 AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 1 2 s.d. JANUARY 12/30-01/06 8.712.8 19 i 4 13 i 3 15 i 3 16 i 3 161 3 161 3 13i 3 5.912.7 13. 3 15 i 3 11 i 3 14 1 7 01/0641/13 181 4 19i 4 18 i 4 19 4 21 i 4 211 4 251 4 20 4 201 4 2816 (a) 23 i 5 (a) 15 i 4 21 1 7 01/13-01/20 261 4 371 4 251 4 29i 4 36 i 4 29 i 4 30 i 4 29 4 291 4 211 4 32i 5 261 4 29 1 9 01/20-01/27 14 4 (a) 211 4 19 4 201 4 16i 3 20 4 18 i 3 181 3 20i 4 19 i 4 181 3 19.1 3 19 1 4 01/27-02/03 21 i 4 241 4 161 3 20 4 19 i 4 23i 4 24 4 201 4 22 i 4 191 4 211 4 201 4 21 i 5 FEBRUARY 02/03 4 2/10 14 i 3 21 i 4 161 4 181 4 181 4 211 4 211 4 20 i 4 171 4 17 i 4 22i 4 22i 4 19 1 5 02/10 42/17 15 i 3 191 4 16 3 16i 3 1814 181 4 191 4 1513 201 4 1713 19i 4 18 i 4 181 3 02/17-02/24 171 3 29 4 221 4 21 i 4 231 4 2414 24i 4 251 4 24i 4 231 4 24 i 4 21 4 231 6 cn 02/24 43/03 15 i 3 271 4 23 4 15 3 2514 29 i 4 231 4 231 4 28 .4 201 4 271 4 181 3 23 1 10 m MARCil 03/03-03/10 9.612.7 201 3 17 i 3 19i 3 181 3 161 3 17 i 3 1413 1513 19 3 161 3 161 3 16 i 6 03/10 4 3/17 12 3 191 3 141 3 161 3 22 4 22i 4 181 3 20i 3 171 3 16 i 3 19 3 15i 3 18i 6 03/17-03/24 131 3 19i 3 24i 4 191 3 25 4 22i 4 20 i 4 24i 4 201 4 191 4 191 3 201 3 20i 6 03/24-03/31 101 3 9.8 i 2.8 121 3 11 i 3 9.012.7 8.9 i 2.7 131 3 14 4 1113 8.412.7 10 i 3 9.612.8 11 i 3 Average 15 i 10 22 i 13 18 i 9 18 i 9 '20 i13 21111 21 i 9 20 i10 19 i I 3 18 i 9 20 i 11 18 i 9. 19 i 9 i 2 s.d. (a) Sampler malfunction. _ _ _ _ _ _ --_m _ __ _ r ,

O O OL TABLE B-2 mage 20t 4) NORT11 ANNA - 1973 CONCEN1 RATIONS OF GROSS BETA LN AIR PARTICULAITiS 1.0E43 pCUm3 12 Sigma COLLECTION 1993 AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 i 2 s.d. APRIL 03/31 44!07 8.612.8 11 i 3 22 4 23 4 14 i 3 162.3 171 4 181 4 15 i 3 12 3 12 i 3 1714 15 1 9 01/074t/14 13i 3 13 3 18 4 1513 15 3 14 i 3 1313 161 3 13i 3 1513 1213 15 i 3 14 1 3 04/144t/21 8.6 3.0 201 4 161 4 16 4 21 t 4 12 3 161 4 151 3 161 3 171 4 181 4 131 3 161 7 04/21 48/28 14 i 3 18 i 3 20i 3 221 3 211 3 19 3 24i 4 201 3 201 3 20 3 171 3 19 i 3 20 1 5 04/28-05/05 201 4 211 4 22 i 4 23 i 4 21 i 4 24 i 4 201 4 26 i 4 181 3 24i 4 17 3 231 4 22 1 5 MAY 05/05-05/12 201 4 211 4 221 4 221 4 181 3 21 4 20i 4 261 4 18 3 221 4 181 3 16 i 7 (a) 20 1 5-05/12-05/19 141 3 201 3 19 3 21i 4 17 i 3 171 3 191 3 2514 171 3 18i 3 13 3 1513 18 1 7

m. 05/19-05/26 171 4 1814 15 i 3 15 i 4 191 4 18 i 4 17i 4 181 4 1714 21i 4 151 4 161 4 17 1 4

" 05/26-06/02 11 3 20 9 18 4 14 3 161 3 14 i 3 181 3 19 4 17 3 17 i 3 181 3 1513 16 5

  .l U N E 06/024)6/09       1513      131 3   241 4   18 i 3   171 3      161 3        191 4      20i 4    16 i 3  191 3     191 4  20i 4         181 6 06/094)6/17       1513      1313    22 i 3  19 i 3   18 i 3     161 3        16i 3      19 i 3   15 i 3  19 3      16 3   14i 3         17 i 5 06/17-06/23       17 i 4    16 i 4  33t 5   331 5    34 i 5     281 4        291 4      301 5    211 4   24i 4    22i 4   281 4         26i 12 06/234)6/30       17 3      16 i 3  22 i 4 24 i 4    241 4      22i 4        26i 4      25i 4    17 i 3  13 i 3   231 4   17i 3         21 i'9 Average          15 i 7    17 i 7  21 i 9  20 i 10 20     to   18     9     20 t 9     21 i 9   17 i 4  19 i 8    17 i 7 18 i 8        18 i 4 i 2 s.d.

(a) ~ Sampler malfunction.

O O O TABLE B-2 mage 3 or4)

NORT11 ANNA - 1913 CONCINILVITONS OFGROSS BL:TA IN AIR PARTICULATES 3 1.0E-03 pCUm 12 Sigma COLLECTION 1993 AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 2 s.d. JULY 06/30-07/07 191 3 161 3 28i 4 23 4 28 4 '28i 4 241 4 28 i 4 221 4 20 i 3 24 4 2414 24 1 8 07M7-07/15 16i 3 131 3 2514 171 3 19 3 16 i 3 23 i 3 27t 4 211 3 19t 3 201 3 211 3 20 1 8 , 07/15-07/21- 1414 121 3 15 4 191 4 20t 4 181 4' 16 i 4 201 4 141 4 16 4 161 4 1514 161 5 07/21-07/28 111 3 13i 3 20 4 231 4 22 4 25 i 4 22 i 4 2.2 i 4 16 4 231 4 191 4 20 i 4 20 1 9 07/28-08M4 15 i 3 211 4 21 4 231 4 25 4 26i 4 24 i 4 2414 17i 3 191 3 2414 19 i 3 22 1 7

  . AUGUST 0&0t48/11     14 3      2314     271 4   28 4     281 4       27i 4         241 4       24 i 4   201 3    2514     211 4   22 i 4      24 i 8 08/11 4 8/18 431 6      431 5'    38 5   401 5    351 5       33i 5         401 5       361 5    251 5    39 i 5   331 5   291 5       36 1 11 08/18-08/25   16 3      24 4      33i 4  35 4     301 4       25 i 4        321 4       291 4    231 4    28 4     26i 4   26 i 4      271 .10 cn   08/25-09/01   32 4      331.4    371 5   43 i 5   45 5        411 5         42 5        37 5     26 4     39 5     361 5   29i 4       37 1 12 to SEPTEMBER 09M1-09/08    12 i 3    22i 4    561 10  27 4     26i 4       23 i 4        23i 4       221 4     17 4    24 4     20i 4   161 4       24 i 22 09/08 49/15   14 i 3    20 4     221 4   25 i 4   23 i 4      22 4          261 4       221 4    281 4    24i 4    22 i 4  18i 4       22 i 7 09/15 49/22   211 4     17 i 3    20 4   18 3     251 4       211 4         25 i 4       191 4   20i 4     17 i 3  21 i 4  211 4       20 i 5 09/22-09/29   191 4     32 5      21i 4  29 4     28 i 4      28i 4         24 4        29 i 4    331 5    17 4    271 4   27 i 5      26 1. 10 Average      19    18 22 i 1 8   28 22 27116 27114           26     13 27 i 15         26     11 22111    24115 24 i 1 1  22 i 9      24 i 6 i 2 s.d.

1 TABLE H-2 (Page 4 of 4) NORTil ANNA - 1993 CONCENTRATIONS OF GROSS DETA IN AIR PARTICULAT11S 1.0E03 pcum3 i 2 Sigma COLLECTION- 1993 . AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 2 s.d. OCTOBER 09/29-104 6 1 -i t 3 20 4 17 4 17 4 20 4 201 4 20 4 181 4 24i 4 19 4 21 i 4 20 i ; 19 t 4 10S 6-10/13 1413 221 4 23 4 21 4 19 4 25 4 191 4 221 4 2514 29 4 201 4 30 i 4 22 i 9 10/13-10/20 21 4 28 4 291 4 24 4 321 4 2313 291 4 231 4 25 4 21i 4 271 4 3114 261 8 10/20-10/27 10 i 4 25 i 5 26 5 20 4 1814 28 5 241 5 261 5 25 5 26 5 24 4 28 i 5 23 1 10 NOVES1HER - 10/27-11M3 17 3 221 4 231 4 20 4 17 3 20 i 4 221 4 24 4 24i 4 21 4 12i 3 231 4 201 7. 110 3-11/10 201 4 26 i 4 28 4 22 4 28i 4 20i 4 24 4 231 4 261 4 22 i 4 251 4 27 4 24i 6 11/10-11/17 27 i 4 28i 5 361 5 341 5 33 5 34 5 30 t 5 33i 5 38i 5 3415 331 5 361 5 33i 7 11/17-11/24 261 4 26 i 5 31 4 5019 ta) 26 4 27i 4 231 4 26 4 24i 4 24 3 24 4 22 i 4 '27 i 15 11/24-12M1 ' 29 4 16 2 27 i 4 26 2 20i 2 31 5 201 4 25 i 4 28 i 4 181 2 2514 25 4 24 i 9

 $   DECES1BER
   - 12M1-12/08          24 i 2     22 2                   201 2                        241 2     19 i 2     221 2              20i 2   191 2   17 2      21i 2   24i 2      171 3       21 i 5
   -12/08-12/15          23 i 2     25 i 2                2212                          25 i 2    231 2      23 2               20 2    23 i 2  231 2     231 2   17 2       281 4       23 5 12/15-12/22          13 2      13 2                   151 2                        151 2     13 2       1512               121 2   1512    14 i 2    1112    1412       161 2       14 1 .3 12/22-12/29         2512       221 2                 22 2                          2512      23 2       2512               21 i 2  21.i 2  23 2      201 2   21 2       29i.2       23 1 5 Quarter Aig. 20            12 2319                 25                    12 25118 22112                24110 2219                 2319    24    11  22 i 11 22 i ll 26112          23 i 3 2 s.d.

Annual Avg- 17 i 13 21 i 13 23 15 23 15 22 13 22112 22 1.12 22111 21 11 21112 21 11 21 t 11 21 1 3 2 s.d. (a) - low sample volume.

TABLE B-3: GAMMA EMITTER 1, STRONTIUM-89, AND STRONTIUM-90 CONCENTRATIONS IN AIR PARTICULATES

   'Oi                       North Anna Power Station, Louisa County, Virginia - 1993 1.0 E-03   pCi/rn3 12 Sigma           January 1 to December 31,1993            Page 1 of 3 First         Second          Third       Fourth Quarter         Quarter        Quarter      Quarter        Average Station       Nuclide       12/30-03/31      03/31-06/30    06/30-09/29  09/29-12/29       i 2 s.d.

STA-01 Sr-89 Sr-90 (a) Be-7 40.4 i 8.2 Co-60 < 0.8 Ru-103 <1 Cs-134 < 0.8 Cs-137 < 0.8 Th-228 <1 . STA-02 St-90 (a) Be-7 53.016.9 Co-60 < 0.8 Ru-103 < 0.8 Cs-134 < 0.7 DU Cs-137 < 0.7 Th-228 < 0.9 STA-03 Sr-89 Sr 90 (a) Be-7 52.6 i 8.8 K-40 < 30 Co-60 <1 Cs-134 - < 0.8 Cs 137 < 0.9 Th-228 <1 STA-04 Sr-89 Sr-90 (a) Be-7 53.5 i 7.1 Co-60 . < 0.7 Ru-103 < 0.6 Cs-134 <: 0.5 Cs-137 < 0.7 Th-228 <1 0 1 All gamma (a) Strontium-89/90 70 (a) < 0.9 (a) (a) -- < 0.2 (a) (a) - 57.5 i 7.5 37.6 7.9 124-113 64.9 i 80.8 K-40 < 10 <10 < 10 <9 - < 0.6 < 0.8 < 0.6 - < 0.8 < 0.9 <1 - < 0.6 < 0.7 < 0.4 - < 0.6 < 0.7 < 0.5 - <1 <1 < 0.8 - Sr 89 (a) <1 (a) (a) - < 0.2 (a) (a) - 60.016.9 61.5 7.6 125 i12 74.9 67.2 K-40 < 20 < 20 < 20 <6 - < 0.7 < 0.8 < 0.3 - < 0.8 < 0.9 < 0.8 - < 0.8 < 0.8 - < 0.3 - < 0.7 < 0.6 < 0.4 - < 0.9 < 0.9 < 0.4 - (a) <1 (a) (a) - < 0.3 (a) (a) - 81.019.2 76.9 i 9.1 132 i 13 85.6 66.7. < 30 < 30 < 20 - < 0.9 < 0.9 < 0.6 - s Ru 103 <1 <1 <1 <2 - <1 < 0.9 < 0.6 - < 0.8 < 0.8 < 0.6 - <1 <1 < 0.8 - (a) <1 (a) (a) - < 0.3 (a) (a). - 97.119.7 78.319.3 154 i 15 95.7 i 85.5-K-40 < 10 <10 <10 <7 - < 0.8 < 0.5 . < 0.4 - < 0.7 < 0.7 <1 - < 0.7 < 0.5 <03 - < 0.6 < 0.6 < 0.4 - <1 <1 < 0.7 - emitters other than those listed were <LLD. analyses performed annually.

TABLE B-3:-GAMMA EMITTER 1, STRONTIUM-89, AND STRONTIUM-90 CONCENTRATIONS IN AIR PARTICULATES ~ G -V' . N0rth Anna Power Station, Louisa County, Virginia - 1993 1.0 E-03 pCi/m3 12 Sigma January 1 to December 31,1993 Page 2 of 3 1 First Second Third Fourth Quarter Quarter Quarter Quarter . Average Station Nuclide - 12/30-03/31 03/31-06/30 U/30-09/29 09/29-12/29 i 2 s.d.' STA-05. Sr-89 (a) <1 (a) (a) - , Sr-90 (a) < 0.2 (a). (a) . Be-7 44.517.4 80.9 i 8.1 101111 113111 84.9 i 60.0 K-40 32.4 i 8.1 21.1 i 6.4 < 10 35.3 i 4.8 29.6 i 15.0 Co-60 <1 < 0.8 < 0.7 < 0.4 - Ru-103 < 0.9 < 0.9 < 0.9 <1 - Cs-134 < 0.8 < 0.8 < 0.7 < 0.4 ' - Cs-137 < 0.7 < 0.8 < 0.8 < 0.4 - Th-228 <1 <1 <1 < 0.5 - STA-05A Sr-89 (a) <1 (a) (a) - Sr 90 (a) < 0.3 (a) (a) - Be-7 82.0 i 10.0 97.319.8 89.2110.6 139 i 14 102 i 51 K-40 15.7 5.8 < 10 < 10 < 10 15.7 i 5.8 Co-60 <1 < 0.7 < 0.8 < 0.6 - Ru-103 <1 < 0.9 <1 <1 - Cs 134 < 0.7 < 0.8 < 0.8 < 0.5 - CF 137 < 0.8 < 0.7 < 0.7 < 0.5 - - Th-228 <1 <1 <1 < 0.8 - STA-06 Sr-89 (a) <2 (a) (a) - Sr 90 (a) < 0.3 (a) (a) -

                                                                                                      .i Be-7        52.117.2        77.7 i 7.8      75.318.0     139 14         86.0 i 74.3 K         < 10             < 10           < 10         <9                -      ,

Co-60 < 0.8 < 0.8 < 0.7 < 0.4 - Ru-103 < 0.8 < 0.8 < 0.7 <1 - Cs 134 < 0.6 < 0.7 < 0.6 < 0.4 - Cs-137 < 0.6 < 0.7 < 0.7 < 0.4 - Th-228 <1 <1 <1 < 0.7 - STA-07 Sr-89 (a) <1 (a) (a) - Sr-90 (a) < 0.3 -(a) (a)- - Be-7 63.6 t 9.9 115i12 101 112 138 i 14 104 i62 K-40 < 20 < 20 < 20 <10 - Co-60 < 0.8 < 0.8 < 0.5 < 0.4 - Ru-103 <1 < 0.9 <1 '<1 - Cs-134 <1 < 0.9 < 0.7 < 0.6 - Cs-137 < 0.9 < 0.7 < 0.8 < 0.5 - Th 228 <2 <2 <2 <1 - 0 1 All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed annually. 71

    -            TABLE B-3: GAMMA EMITTER 1, STRONTIUM-89, AND STRONTIUM-90 CONCENTRATIONS IN AIR PARTICULATES TO                         North Anna Power Station, Louisa County, Virginia - 1993 1.0 E-03 pCi/m3 t 2 Sigma          January 1 to December 31,1993           Page 3 of 3 First          Second          Third      Fourth Quarter         Quarter        Quarter     Quarter        Average Station       Nuclide      12/30-03/31    03/31-06/30     06/30-09/29 09/29-12/29'        2 s.d.

STA-21 Sr 89 (a) <1 (a) (a) - Sr 90 (a) < 0.2 (a) (a) - Be-7 49.0 i 7.4 63.2 8.2 59.8 i 7.8 116 i 12 72.0 59.9 K-40 13.2 i 6.2 13.7 6.5 < 20 < 20 13.510.7 Co-60 < 0.7 <1 < 0.9 < 0.6 - Ru 103 <1 <1 <1 <1 - Cs-134 < 0.8 < 0.9 < 0.8 < 0.6 - Cs-137 <1 < 0.9 < 0.8 < 0.5 - Th-228 <1 <1 <1 < 0.7 - STA-22 Sr-89 (a) <2 (a) (a) - Sr-90 (a) < 0.3 (a) (a) - Be-7 46.8 7.6 62.6 i 7.4 65.018.6 118i12 -73.1 62.0 K-40 <10 < 10 15.3 6.5 <7 , 15.3 6.5 Co-60 <1 < 0.9 < 0.9 < 0.4 - Ru-103 < 0.9 < 0.8 < 0.9 <1 - Cs-134 < 0.8 < 0.7 < 0.7 < 0.4 - Cs-137 <1 <1 <1 < 0.6 O. Th-228 <1 <1 <1 < 0.7 - STA 23 Sr-89 (a) < 0.9 (a) (a) - Sr-90 (a) < 0.1 (a) (a) - Be-7 52.6 i 8.3 55.5 i 6.6 64.517.2 125 i 13 74.4 i 68.2 K-40 < 30 10.4 4.9 < 10 <8 10.4 i 4.9-Co-60 <1 < 0.7 < 0.8 < 0.4 - Ru-103 <1 < 0.7 < 0.8 <1 - Cs 134 <1 < 0.6 < 0.6 < 0.4 - Cs-137 <1 < 0.8 < 0.9 < 0.5 - Th-228 <1 <1 <1 < 0.5 - STA-24 Sr-89 (a) <1 (a) (a) - Sr-90 (a) < 0.2 (a) (a) - Be-7 50.217.6 66.8110.0 70.8 10.3 136 15 '81.0175.5

                                        <10                            < 30        < 20 K-40                            < 30                                         -

Co-60 < 0.8 <1 <1 < 0.8 - Ru-103 < 0.8 <1. <1 <2 - Cs-134 < 0.6 <1 <1 < 0.8 - Cs 137 s 0.6 <1 < 0.8 < 0.7 - Th 228 <1 <1 <1 <1 - O 1 All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed annually. 72

TABl.E B-4: GROSS BETA, TRITIUM, AND GAMMA EMITTER 1 ' CONCENTRA110NS IN PRECIPITATION

                                         ' Station 01A -(On Site)

North Anna Power Station, Louisa County, Virginia - 1993 pCl/li 2 Sigma January 1 to December 31,1993 Page 1 of 1 Collection Dates Gross Beta Rainfall (Inches) 12/30/92-01/27/93 2.5 1 0.7 3.77 01/27/93 02/24/93 2.9 i 0.7 2.14 02/24/93-03/31/93 2.7 1 0.7 6.30 03/31/93-04/28/93 2.51 0.8 6.00 04/28/93-05/26/93 4.41 0.8 4.91 05/26/93-06/30/93 16 i 1 3.17 06/30/93 07/28/93 13 1 2 0.79 07/28/93-08/25/93 3.4 i 0.8 2.59 08/25/93-09/29/93 4.01 0.9 3.76 09/29/93-10/27/93 4.31 0.8 1.55 10/27/93-11/24/93 3.01 0.9 2.02 11/24/93-12/29/93 <1 7.94 O Average i 2 s.d. 5.3 1 9.3 SEMI-ANNUAL PRECIPITATION COMPOSITES 12/30/02-06/30/93 '06/30/93-12/29/93 Be-7 = < 30 Be-7 = < 30 H-3 = < 100 H-3. = < 100 TABLE B-5 SOIL Soil samples are collected every three years from twelve stations. Since the samples were collected in 1992, Table B-5 will not be included in the 1993 report.- Q 1 All gamma emitters other than those listed were <LLD. 73

TABLE B-6: . GAMMA EMITTER1 , STRONTIUM, AND TRITIUM CONCENTRATIONS

  .Q                                                               IN GROUND AND WELL WATER North Anna Power Station, Louisa County, Virginia - 1993 pCi/li 2 Sigma                                                                January 1 to December 31,1993                                   Page 1 of 1 Collection Date          H-3       Sr-89                         Sr-90                                                             Be-7      K-40         1131      Ba-140      Th-228 STATION 01A 03/31/93       < 100       (a)                                     (a)                                                    < 30      < 50         < 0.1      <7          <6 06/30/93       < 200      < 0.9                          < 0.2                                                            < 30      < 50         <0.5        <5         <5 09/29/93       < 100                                                                                                      < 30      < 50         < 0.3       <8         <6 12/29/93       < 200                                                                                                      < 30      < 60         < 0.3      <8          <7 1

All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed only on second quarter sample. TABLE B-7: GAMMA EMITTER 1, STRONTIUM, AND TRITIUM CONCENTRATIONS IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 1993 O eci'i*2siome ae""erv ' io oecember a' '993 Pe9e'o" Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40 1131 Cs-137 Ba-140 Ra-226 Th-228 STATION - 11 01/07/93 (a) (a) 4000 i 200 < 30 < 100 < 0.3 <4 <5 < 70 .<6 02/18/93 3900 i 200 < 30 < 100 < 0.2 <4 <7 < 70 <6 03/16/93 3500 200 < 30 < 80 < 0.2 <3 <5 < 60 <5 04/08/93 <2 < 0.2 2300 1 200 < 30 < 80 < 0.2 <3 <6 < 60 <5 05/11/93 2300 1 200 < 30 < 100 < 0.3 <4 <6 < 80 <7 06/14/93 1700 1 200 '< 30 < 50 < 0.2 <4 .<7 < 60 <6 07/14/93 2000 200 < 30 < 50 < 0.2 <3 <7 < 70 <0 ! 08/12/93 (b) < 30 < 80 < 0.1 <4 <6 < 70 <7 09/13/93 < 30 < 50 < 0.2 <3 <7 < 80 <8 10/1a'93 2300 200 < 40 < 90 < 0.2 <4 < 10 < 70 <6 I 11/22/93 < 50 139 36 < 0.2 <5 <9 < 90 <7 12/15/93 < 30 < 80 < 0.2 <3 <5 < 60 <5 Average i 2 s.d. 2750 1 1808 139 1 36 O 1 All gamma emitters other than those listed were <LLD. (a) Sr-89/90 analyses performed on second quarter samples. (b) Analysis frequency change to quarterly, as this is minimum requirement of program. 74

TABLE B-8: GAMMA EMITTER 1,- STRONTIUM, AND TRITIUM CONCENTRATIONS. Q IN SURFACE WATER North Anna Power Station, Louisa County, Virginia - 1993 pCilli 2 Sigma January 1 to December 31,1993 Page 1 of 1 Collection Dates H-3 1-131 2 Sr-89 St-90 Be-7 K-40 Cs-137 Ba-140 ' Ra-226 Th-228 STAT 101L.DA 01/07 3300 1 200 < 0.3 (a) (a) < 30 < 50 <4 <5 < 80 <7 02/18 (b) < 0.2 < 30 < 60 <4 <6 < 80 <7 03/16 < 0.2 < 30 < 60 <4 <6 < 80 <7 04/08 2200 1 200 < 0.2 < 0.9 < 0.9 < 30 < 50 <4 <7 < 60 <6 05/11 < 0.3 < 40 < 60 <4 <7 < 90 <7 06/14 < 0.2 < 30 < 50 <3 <6 < 70 <6 07/14 1900 200 < 0.3 < 30 < 100 <4 <6 < 70 <6 08/12 < 0.1 < 30 < 100 <4 <5 < 80 '7 09/13 < 0.3 < 30 < 80 <3 <7 < 60 <5 10/18 2200 1 200 < 0.2 < 40 < 50 <4 <10 < 80 <7 11/22 < 0.2 < 30 < 50 <4 < 10 < 70 <7 12/15 < 0.2 < 20 < 40 <3 <5 < 50 <5 Avg. 2400 i 1233 i 2. s.d. STATION - 09A 01/07 < 100 < 0.2 (a) (a) < 30 < 60 <4 <5 < 100 <9 02/18 (b) < 0.2 < 30 < 80 <3 <5 < 60 <6 03/16 < 0.2 < 30 < 70 <3 <5 < 60 <5 04/08 < 200 < 0.2 < 0.9 < 0.2 < 30 < 50 <3 <6 < 60 <6 05/11 < 0.7 < 40 < 70 <4 <7 < 100 <8 06/14 < 0.2 < 30 < 60 <4 <7 < 90 <7 07/14 < 200 < 0.2 < 30 < 80 <3- <4 < 60 <5 OW12 < 0.1 < 30 < 90 <4 <5 < 70 . <7 09/13 < 0.4 < 20 < 80 <3 <5 < 50 <S 10/18 < 200 < 0.2 < 40 < 60 <4 <10 < 100 <9 I 11/22 < 0.2 < 30 < 100 <4 <9 < 70 <6 ; 12/15 < 0.2 < 20 < 40 <2 <4 < 50 <5 i 1 All gamma emitters other than those listed were <LLD. p 2 [.131 by radiochemistry (a) Analysis performed only with second quarter. (b) Analysis performed quarterly i 75 ; i

TABLE B-9: GAMMA EMi1TER1, STRONTIUM, AND TRITIUM CONCENTRATIONS IN SURFACE WATER

'Q[

State-Split Samples North Anna Power Station, Louisa County, Virginia - 1993 pCi/li 2 Sigma January 1 to December 31,1993 Page 1 of 1 , Collection Dates H-3 Be-7 K-40 1-131 Cs-137 ' Ba-140 Ra-226 Th-228 STATION - W-27 01/31 < 100 < 40 < 50 <1 <3 < 10 < 60 <6 02/28 (a) < 30 < 50 <1 <3 < 10 < 60 <6 OT31 < 30 < 50 < 10 <3 <8- < 70 <6 04/30 < 200 < 40 < 50 < 0.7 <3 < 10 < 60 <6 05/31 < 30 < 30 < 0.7 <2 < 10 < 40 <4 06/30 < 40 < 40 < 0.7 <3 < 10 < 60 <6 07/31 10001 200 < 30 < 80 < 0.4 <3 <8 < 70 <6 08/31 < 30 < 40 < 0.8 <3 < 10 < 50 <5 09/30 < 30 < 40 < 0.6 <3 < 10 < 50 <5 10/31 1400 1 100 < 40 < 80 < 0.7 <3 < 10 < 60 <6 11/30 < 30 < 40 < 0.8 <3 < 10 < 70 <6

     '12/31                         < 40       < 50             <20(b)       <4      < 10           < 90    <9 Avg.           12001566 2 s.d.

STATlON - W-33 01/31 3800 1 200 < 30 < 50 <1 <3 < 10 < 70 <6 02/28 (a) < 30 < 50 <1 <3 <6 < 60 <6 03/31 < 30 < 60 < 10 <3 <9 < 80 <7 04/30 25001200 < 30 < 50 < 0.7 <3 <9 < 60 <6 l 05/31 < 20 < 40 < 0.7 <2 <8 < 40 <4 06/30 < 30 < 50 < 0.7 <3 < 10 < 60 <6 07/31 22001200 < 40 < 100 < 0.5 <4 < 10 < 80 <7 OW31 < 30 < 40 <1 <2 < 10 < 50 <5 ! 09/30 < 40 < 50 < 0.6 <3 < 10 < 60 <6 10/31 2900 200 < 30 < 40 < 0.5 <4 <10 < 60 <5 11/30 < 30 < 30 < 0.8 <2 < 10 < 40 <4

                                    < 30       < 40                          <3       < 10          < 60    <6~

12/31 < 20 (b) Avg. 2850i1390 l 1 2 s.d. l

                                                                                                                'l 1     All gamma emitters other than those listed were <LLD.                                                l 1O    <e) Tritiem eeeixsie done neerieriv.

(b) LLD for lodine-131 not met due to late sample receipt from the State of Virginia. 1 76

o b O Cr TABLE B-10: GAMMA EMITTER 1 CONCENTRATION IN SEDIMENT SILT North Anna Power Station, Louisa County, Virginia - 1993 pCi/kg i 2 Sigma January 1 to December 31,1993 Page 1 of 1 ST A-0 8 ST A-09 A ST A-11 ST A-08 STA-09 A ST A-11 ST A-0 8 STA-09 A ST A-11 Average Nuclide 03/16 03/16 03/16 09/13 09/13 09/13 10/18 10/18 10/18 i 2 Sigma Sr-89 (a) (a) (a) < 100 < 20 < 80 (a) (a) (a) - Sr-90 (a) (a) (a) < 30 < 20 < 20 (a) (a) (a) - Be-7 < 300 < 300 < 300 < 300 < 200 < 400 < 200 < 300 <500 - K-40 20501300 10700i1100 16300 i 1600 2480i330 14900 i 1500 14200t1400 2920 1290 13100 i1300 1720011700 10428 112480 Mn-54 < 20 < 30 < 40 < 30 < 30 < 40 < 20 < 30 < 50 - Co-58 < 30 < 30 < 30 < 30 < 30 < 40 < 20 < 40 < 50 - Co-60 < 40 < 30 < 40 82.2123.1(t} < 30 < 40 30.7117.3 < 30 < 50 56.5 72.8 Cs-134 < 30 < 40 < 50 < 30 < 30 < 50 < 20 < 40 < 60 - Cs-137 160128 < 40 < 40 313 1 32 45.9 2I.0 < 40 138 1 22 147i25 < 50 161 i193 Ra-226 10901500 < 900 20001610 < 600 863i362 2140 i 620 645i308 1390 i480 2190 850 1485 i1301 Th-228 532153 345 147 1370 1 140 349 i 36 391139 963i96 374 1 37 610 161 1130 i 110 674 i769 1 AR gamma emmers other than those Itsted were <LLD. (a) Strontium 89/90 analyses performed arwiually. (b) Confirmed by a reanalysis.

e. TABLE B-11: GAMMA EMITTER 1 CONCENTRATION IN SHORELINE SOIL O North Anna Power Station, Louisa County, Virginia - 1993 pCl/kg i 2 Sigma January 1 to December 31,1993 Page 1 of 1 i Station-09 Station-09 Average Nuclide 03/16 09/13 2 Sigma Sr 89 (a) < 100 - Sr-90 (a) < 30 - Be 7 < 600 < 300 - K-40 8190i820 44401 440 631515303 Mn-54 < 50 < 30 - Co 58 < 50 < 30 - Co-60 < 50 < 30 - Cs-134 < 70 < 40 - Cs-137 1150 i 110 174 i 33 66211380 Ra 226 21801 890 1290 450 1735i1259 Th-228 1320 1 130 1080 1 110 12001339 O 1 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 analyses performed annually. 78

~~

1 1 TABLE B-12: GAMMA EMITTERI CONCENTRATION IN MILK O North Anna Power Station, Louisa County, Virginia - 1993 pCi/li 2 Sigma January 1 to December 31,1993 Page 1 of 2 l MONTH NUCLlDE STATION-12 STATION-13 l JANUARY Sr-89 <2 <2 Sr-90 1.5 1 0.3 1.5 1 0.2 K-40 1360-1140 1280i 130 .l Cs-137 <4 < 0.5 I l131 < 0.3 < 0.3 ! l FEBRUARY Sr-89 (a) (a) j Sr-90 l (a) (a) K-40 1500 150 1290i 130 Cs-137 <4 <5 l-131 < 0.2 < 0.3 i MARCH Sr 89 (a) (a) Sr-90 (a) (a) K-40 13501140 12001120 Cs-137 <5 <4 l-131 < 0.3 < 0.4 O ^eRiL Sr-89 Sr-90

                                                                  <1 1.0 t 0.2
                                                                                          <2 2.1 1 0.3 K-40                          1370 1 140             1380 1 140 Cs 137                            <5                      <4 1-131                            < 0.2                  < 0.3 MAY                          Sr-89                             (a)                     (a)

Sr 90 (a) (a) K-40 1380 1 140 1320 130 Cs-137 <5 <5 l-131 < 0.3 < 0.3 JUNE Sr 89 (a) (a) Sr-90 (a) (a) K-40 1350 130 1280 130 Cs-137 <4 <3 1131 < 0.3 < 0.3 O 1 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 analyses performed quarterly. 79

TAB'LE B-12: GAMMA EMITTER 1 CONCENTRATION IN MILK Q . North Anna Power Station, Louisa County, Virginia - 1993 pCl/li 2 Sigma January 1 to December 31,1993 Page 2 of 2 MONTH NUCLIDE STATION-12 STATION-13 i JULY Sr-89 <1 <2 ' Sr-90 1,7i0.2 2.1 1 0.2 K-40 1190 i 120 1310 1 130 Cs-137 <6 <5 l-131 < 0.2 <0.2 AUGUST Sr49 (a) (a) Sr-90 (a) (a) K-40 1290 i 130 13701140 Cs-137 <4 <4 l-131 < 0.2 < 0.3 SEPTEMBER Sr-89 (a) (a) Sr 90 (a) (a) K-40 14001140 1230 1 120 Cs-137 <4 <4 l-131 < 0.5 < 0.2 OCTOBER Sr.89 <2 <2 O s<-90 K-40 2.o

o.a 15001150 2.'
o.2 1280 130 Cs-137 <5 <5 l-131 <0.2 < 0.3 NOVEMBER Sr-89 (a) (a)

St-90 (a) (a) K-40 14801 150 1290 1 130 Cs 137 <4 <4 l131 < 0.3 < 0.3 DECEMBER Sr-89 (a) (a) Sr-90 (a) (a) K-40 1470i150 13401130- . Cs 137 <4 <4 l131 <0.2 < 0.2 .; i h 1 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 analyses performed quarterly. 80 t

   , . - ,                                                                        -                  ..          --.         ,      --.,,e,

TABLE B-13: GAMMA EMITTER 1 CONCENTRATION IN FISH b North Anna Power Station, Louisa County, Virginia - 1993 pCi/kg i 2 Sigma January 1 to December 31,1993 Page 1 of 1 Collection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 04/06 25 Catfish 18801190 < 20 < 20 < 20 ' 04/07 08 2390 i 280 < 20 < 30 66.5123.1 04/07 25 2460i260 < 20 < 20 < 20 04/08 08 Catfish 20501210 <10 < 20 90.3 i 15.6 10/20 25 1580 i 180 < 20 < 20 < 20 10/21 08 1560 i 230 < 20 < 20 81.8 i 19.4 10/21 08 Catfish 1200 1 230 < 30 < 30 39.5 i 21.6 10/20 25 Catfish 1330 1 210 < 20 < 20 < 20 O Avg. 1806i937 69.5 i 44.6 i 2 s.d. O 1 All gamma emitters other than those listed were <LLD. 81

TABLE B-14: GAMMA EMITTERI CONCENTRATION IN FOODNEGETATION O sorin Anne eower station, touisa county, virginie - ,993 pCi/kg 2 Sigma January 1 to December 31,1993 Page 1 of 2 Collection Dato Bo-7 K-40 1-131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 STATIOf[14 There were no food / vegetation samples during the first quarter 1993, due to seasonal unavailability. 04/28 3690 1 370 17400 i 1700 < 20 < 40 < 40 < 40 < 600 < 50 05/19 1950 1 260 12400 i 1200 < 20 c 30 < 30 < 30 < 600 < 60 06/23 1480 340 21100 1 2100 < 50 < 50 < 40 < 40 < 600 < 70 07/21 1980 260 173001 1700 < 20 < 30 < 30 < 30 < 600 < 60 08/18 208 76 156001 1600 < 30 < 10 <9 <9 246 117 < 10 09/14 290 86 200001 2000 < 50 < 20 < 10 < 10 < 200 < 20 10/20 1380 150 16900i 1700 < 30 < 20 < 20 < 20 < 300 < 30 There were no food / vegetation samples during November and December 1993, due to seasonal unavailability. STATION 15 Q V Thero were no food / vegetation samples during the first quarter 1993, due to seasonal unavailability. 04/28 2130 i 300 22900 2300 < 20 < 50 < 40 < 40 < 700 < 60 05/19 500 116 8950 900 < 20 < 20 < 20 < 20 < 200 < 20 06/23 626 121 24000 1 2400 < 30 < 20 < 20 87.8 i 14.6 < 300 < 30 07/21 766 i 167 16200 i 1600 < 30 < 20 < 20 71.2 i 16.3 < 300 < 30 j 08/18 468 1 161 14500 1 1500 < 50 < 20 < 20 77.2 i 17.2 < 300 < 30 09/15 616 133 151001 1500 < 50 < 20 < 20 < 20 < 300 < 20 10/20 1710 1 330 15600 1600 < 50 < 50 < 30 < 30 < 600 < 60 There were no food / vegetation samples during November and December 1993, due to seasonal unavailability. STAILQN 16

                                                                                                               'l There were no food / vegetation samples during the first quarter 1993, due to seasonal unavailabihty.         -)'

04/28 1800 1 260 16900 1 1700 < 40 < 30 < 30 < 30 < 500 < 50 05/19 2260 230 116001 1200 < 20 < 30 < 30 < 30 < 500 < 50 06/23 651 i 316 17200 i 1700 < 50 < 50 < 40 < 40 < 700 < 70 07/21 592 i 81 165001 1600 < 20 < 10 < 10 12.216.6 < 100 <10 08/18 767 124 6930 i 690 < 40 < 20 <10 23.3 i 2.3 < 200 < 20 09/15 609 1 238 79501 790 < 40 < 40 < 30 < 30 < 500 < 50 10/20 3520 i 460 9930 i 990 < 40 < 60 < 40 < 40 < 900 < 80 There were no food / vegetation samples during November and December 1993, due to seasonal unavailability. O 1 All gamma emitters other than those listed were <LLD. 82

t TABLE B-14: GAMMA EMITTER 1 CONCENTRATION IN FOCDNEGETATION North Anna Power Station, Louisa County, Virginia - 1993 pCi/kg i2 Sigma January 1 to December 31,1993 Page 2 of 2 Collection Date Be-7 K-40 1-131 Ru-103 - Cs-134 Cs-137 Ra-226 . Th-228 STATION 21 There were no food / vegetation sa.mples during the first quarter 1993, due to seasonal unavailab:lity. 04/28 5120 510 19100 1900 < 20 < 50 < 50 < 50 < 800 < 80 - 05/19 169i 45 6410.1 640 < 50 <6 <6 71.4 i 7.1 < 100 <9 06/23 577 1 175 21000i 2100 < 30 < 30 < 20 353i35 < 300 < 30 07/21 445 121 185001 1800 < 30 < 20 < 20 34.1 i 16.1 < 300 48.5 i 21.7 08/18 2410 1 240 14300i 1400 < 50 < 40 < 30 83.3 i 23.4 < 400 <40 ; 09/15 868 298 10200 i 1000 < 40 < 50 < 40 81.8128.3 < 800 < 80 10/20 2660 390 53701 540 < 30 < 60 < 40 < 40 < 700 <70 -l There were no food / vegetation samples during November and December 1993, due to seasonal unavailability. STATION 23 There were no food / vegetation samples during the first quarter 1993, due to seasonal unavailability. 04/28 2650 1 270 14300 1400 < 50 < 40 < 30 < 30 < 600 266i30 05/19 1460 1 250 125001 1300 < 20 < 30 < 30 < 30 < 500 ' 50 06/23 2920 i 480 20800 2100 < 50 < 70 < 60 < 50 < 1000 < 100 07/21 2990 300 20700 2100 < 40 < 30 < 30 < 30 < 500 120 i 28 08/18 1780 330 15000 i 1500 < 50 < 50 < 40 < 40 < 700 167 132 09/15 1960 1 270 13900 1400 < 30 < 40 < 30 < 30 < 600 < 60 10/20 2230 290 133001 1300 < 30 < 40 < 30 < 30 < 500 101 26 There were no food / vegetation samples during November and December 1993, due to seasonal unavailability. Avg. 1607 2326 1515319457 89.5 i 193 246 i 117 141 i 164 O- 1 All gamma emitters other than those listed were <LLD. 83

TABLE B-15: DIRECT RADIATION MEASUREMENTS - QUARTERLY AND ANNUAL TLD RESULTS j 1 North Anna Power Station, Louisa County, Virginia - 1993 mR/Std. Month (30.4 days)i 2 Sigma January 1 to December 31,1993 Page 1 of 1 Station First Otr Second Otr Third Otr Fourth Otr Quarterly Annual TLD Number 12/28/92 03/31/93 06/30/93 09/29/93 Average 07/01/92 03/31/93 06/30/93 09/29/93 01/05/94 06/30/93 01 7.510.3 9.3 1 0.5 6.9 i 0.2 7.9 0.3 7.9 i 2.0 8.0 1 0.3 02 3.9 i 0.1 5.7 1 0.6 4.1 1 0.1 5.6 1 0.5 4.8 1 1.9 4.3 1 0.2 03 3.9 i 0.1 5.3 1 0.8 4.0 i 0.1 5.0 1 0.5 4.6 1 1.4 4.4i0.2 04 4.9 1 1.6 5.8 1 0.3 4.3 i 0.0 4.8 1 0.1 5.0i1.2 4.7 i 0.8 05 4.8 i 0.2 5.9 i 0.8 5.2 i 0.1 5.5i0.4 5.4i0.9 5.7 i 0.5 05A 5.0 1 0.2 6.5 0.5 4.9 i 0.1 5.7 i 0.1 5.511.5 5.5i0.8 06 6.2 i 0.2 6.910.2 6.5i0.2 7.5 i 1.3 6.8 1 1.1 6.7 i 0.2 07 4.710.3 6.4 1 0.5 4.9 i 0.2 5.5 0.2 5.4 i 1.5 5.2i0.7 21 4.7 i 0.2 5.0 1 0.2 4.8 i 0.1 6.1 i 0.7 5.2i1.3 5.9 1 0.0 22 6.4 i 0.2 6.8 1 0.9 6.2 1 0.1 6.6 i 0.5 6.5 1 0.5 6.5 1 0.2 23 6.3 0.2 6.9 1 1.3 6.8 1 0.3 9.7 i 1.6 7.4 3.1 6.510.3 24 3.6 i 0.2 4.3 1 1.5 3.4 i 0.1 4.2 1 0.2 3.9 i 0.9 3.9 i 0.3 Average 5.2 i 2.4 6.2 1 2.5 5.2 1 2.3 6.2 i 3.1 5.7 1 2.4 5.6 1 2.4 1 2 s.d. O 84

1 TABLE B-16: DIRECT RADIATION MEASUREMENTS -

 .                                  SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1993 l       mR/Std. Month (30.4 days)i 2 Sigrna           January 1 to December 31,1993          Page 1 of 2 Station .       First Otr         Second Qtr             Third Qtr       Fourth Qtr        Average Number         12/30-03/31        03/31-06/30         06/30-09/29        09/29 01/05       i 2 S.d.

N1 6.3 i 0.4 7.0 i 0.3 6.010.2 6.8 1 0.4 6.5 1 0.9 N-2 5.1.i 0.1 4.9 i 0.2 4.9 i 0.1 5.3i0.1 5.1 1 0.4 NNE-3 6.7 i 0.1 6.6 1 0.3 6.610.3 7.1 i 0.3 6.810.5 NNE-4 5.01 0.1 5.2 i 0.4 5.4 i 0.1 5.4 0.5 5.3 1 0.4 NE-5 7.61 0.1 7.7 i 1.0 7.010.2 7.6i0.3 7.5 1 0.6 NE-6 3.61 0.1 5.3 i 0.9 3 4 1 0.1 4.010.3 4.1 i 1.7 ENE 7 6.1 1 0.2 6.3 i 0.7 6.. . 0.3 8.0 1 0.3 6.7 1 1.8 ENE-8 4.5 i 0.1 4.8 1 0.9 4.4 i 0.1 5.6i1.2 4.8 i 1.1 E-9 6.7 i 0.3 6.5 1 0.3 6.9 1 0.1 7.1 1 0.2 6.8 1 0.5 E-10 5.6 1 0.1 6.8 1 0.7 6.0 1 0.2 6.2i0.2 6.211.0 ESE-11 5.71 0.3 5.610.2 5.710.2 7.010.4 6.011.3 . ESE-12 6.4 i 0.3 7.7 i 0.6 6.7i0.2 7.8i2.3 .7.2i1.4 SE-13 6.8 i 0.0 7.5 i 0.1 6.2 i 0.2 7.3 i 0.7 7.0i1.2 SE-14 8.3 1 0.3 8.7 1.1 7.8 i 0.4 10.212.5 8.8 i 2.1 SSE-15 6.81 0.1 6.7 1 0.2 6.9 i 0.2 7.7 i 0.2 7.0 1 0.9 . SSE-16 5.01 0.1 5.1 1 0.2 5.1 1 0.2 6.6t0.2 5.5t1.5 S-17 7.7 i 0.1 7.0 i 0.6 6.3 1 0.1 7.0 1 0.2 7.0 1 1.1 S-18 3.9 0.3 4.5 i 0.8 3.8 i 0.1 5.3 i 0.2 4.4 i 1.4 SSW-19 7.9 1 1.2 8.7 i 0.5 9.1 1 0.1 10.510.9 9.1 1 2.2 O SSW 20 SW.21 4.21 0.0 8.5 0.1 4.8 1 0.6 8.8 1 1.0 4.0i0.2 8.2 1 0.2 4.8 i 0.2 9.510.1 4.5i0.8 8.8 1 1.1 SW-22 6.1 1 0.2 6.9 1 0.6 7.0 i 0.5 6.6 1 0.3 6.7 1 0.8 WSW-23 5.3 1 0.1 6.6 1 1.1 5.3 0.3 6.610.7 6.011.5 WSW 24 6,5 i 0.1 7.3 1 0.7 6.7 i 0.1 6.7 i 0.1 6.8 1 0.7 - W-25 9.1 i 0.3 7.6 1 0.4 7.3i0.3 7.7i0.2 7.9 1.6 W 26 4.8 0.3 4.7 1 0.2 4.710.1 6.3 1 0.9 5.1 i 1.6 - WNW-27 5.0 1 0.2 5.1 i 0.3 5.0 0.2 5.5 i 0.1 5.2i0.5 WNW 28 5.01 0.2 6.5i3.2 5.2i0.4 5.410.2 '5.511.3 NW-29 7.7 i 0.2 7.2 1 0.4 7.3 1 0.3 8.2 1 0.6 7.6 1 0.9 NW-30 4.81 0.1 5.2 1.5 4.6 1 0.2 6.010.9 5.211.2 NNW 31 5.3 1 0.1 5.3 1 0.3 5.1 i 0.2 6.9 i 1.7 5.7i1.7 NNW 32 5.41 0.1 5.6 1 1.5 5.210.1 5.810.0 5.510.5-N-33 6.2 1 0.2 6.1 0.2 5.211.5 6.410.5 6.011.1 N.34 5.2 i 0.1 5.010.5 5.010.2 5.5t0.2 5.2 1 0.5 NNE 35 6.4 1 0.5 6.5 0.3 6.6 1 0.2 7.2 1 0.5 6.710.7 NNE-36 5.1 1 0.2 5.5 1 0.2 5.4 1 0.1 5.6i0.3 5.4i0.4 NE 37 7.4 i 0.2 8.8 i 0.9 7.210.3 8.711.3 8.0i1.7 NE-38 3.51 0.1 4.1 0.6 3.510.1 4.6 1 0.5 3.9 1 1.1 ENE-39 6.3 1 0.1 6.5 1 0.2 6.4 i 0.5 7.9i0.6 6.811.5 ENE-40 4.51 0.2 5.6 1 0.3 4.610.3 5.010.3 4.9i1.0-E-41 6.71 0.1 6.6 i 0.4 6.6 1 0.3 7.2 i 1.0 6.8 i 0.6 E-42 5.8 i 0.3 6.8i0.7 6.2 i 0.3 6.810.2 6.4i1.0 ESE-43 5.7 1 0.2 5.8 1 0.3 ' 5.9 i 0.7 6.5 0.4 6.010.7 ESE-44 6.31 0.2 6.2 i 0.2 6.8 1 0.1 6.5i0.2 6.510.5 SE 6.91 0.1 7.0i0.5 6.1 1 0.1 7.010.6 6.8 i 0.9 O l l l 85 l

TABLE B46: DIRECT RADIATION MEASUREMENTS 0 SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1993 mR/Std. Month (30.4 days)i 2 Sigma January 1 to December 31,1993 Page 2 of 2 Station First Otr Second Otr Third Qtr Fourth Otr Average Number 12/30-03/31 03/31 06/30 06/30-09/29 09/29-01/05 i 2 S.d. SE-46 7.3 i 3.1 9.9 i 3.6 8.3 i 0.3 9.4 0.3 8.7 i 2.3 SSE-47 6.7 1 0.1 6.7 i 1.1 7.2 i 0.3 7.1 i 0.7 6.9 i 0.5 SSE-48 5.2 i 0.2 5.010.1 5.110.1 6.2 1 1.4 5.411.1 S 49 7.9 i 0.1 7.9 1 0.9 6.6 i 0.1 7.0 1 0.6 7.4 i 1.3 S-50 3.9 i 0.1 4.0 i 0.2 4.0 i 0.1 5.6 i 0.8 4.4 1 1.6 SSW-51 8.4 1 0.3 8.4 1 0.2 8.3 i 2.3 9.4 i 0.4 8.611.0 SSW-52 3.5 i 1.1 4.5 1 0.5 4.2 1 0.1 5.1 1 0.7 4.3 1.3 SW-53 8.4 1 0.2 8.811.5 8.2 1 0.1 10.410.8 9.0 i 2.0 SW 54 6.3 i 0.2 6.4 i 0.6 6.4 i 0.3 6.7 1 0.4 6.5 0.3 WSW-55 5.2 i 0.1 5.3 0.1 5.210.3 6.7 1 0.6 5.611.5-WSW-56 6.4 i 0.2 7.4 i 1.1 6.6 1 0.0 8.1 1 0.4 7.1 i 1.6 W 57 9.2 i 0.5 7.8 i 0.3 6.9 i 0.2 9.0 1 0.6 8.2 1 2.2 W-58 4.8 i 0.2 5.1 i 0.3 4.8 i 0.1 5.2 1 0.3 5.0 i 0.4 WNW-59 5.0 1 0.2 5.2 1 0.2 5.1 1 0.3 5.910.4 5.3 i 0.8 WNW-60 5.41 0.2 5.2 0.2 5.0i0.1 5.7 i 0.1 5.3 i 0.6 NW-61 6.6 i 2.8 7.9 i 0.6 7.7i0.3 8.2 i 2.1 7.6 i 1.4 NW-62 4.51 0.5 5.1 1 0.2 4.9 1 0.2 6.2 1 1.1 5.2i1.5 NNW-63 5.61 0.3 5.510.2 5.1i0.2 6.0 t 0.2 5.6 1 0.7 NNW-64 5.3 0.2 5.7 0.3 5.5 0.2 5.7 i 0.2 5.6 i 0.4

 .] C-1             3.91 1.3                 6.210.2         5.0i0.3               5.4 i 0.3                 5.1 1 1.9 C2              4.7               0.1    5.1 1 0.2       4.810.2               6.8 1 0.9                 5.4 i 2.0           ,

C-3 3.6 i 0.1 3.9 i 0.0 3.6 i 0.1 4.3 i 0.1 3.9i0.7 C-4 3.4 i 0.1 3.9i0.2 3.7 i 0.1 4.1 i 0.1 3.8 1 0.6 C5 3.91 0.1 4.4 1 0.3 4.2 1 0.1 4.6 i 0.2 4.3 i 0.6 . C6 4.01 0.1 4.2 1 0.1 4.4 0.3 4.6 1 0.1 4.3 i 0.5 j C7 5.61 0.1 7.010.7 6.1 1 0.1 6.5 0.3 6.3 1 1.2 C-8 5.4 i 0.2 6.1 i 0.3 5.6i0.1 6.1 i 0.2 5 8 i 0.7 J Average 5.8 1 2.9 6.2 1 2.8 5.8 1 2.6 6.7 1 2.9 6.1 i 0.9 II O 86

Ol l r O APPENDIX C LAND USE CENSUS - 1993

                                                                                                                         ,l O                                                                                                                         l

_ _ _. . _ . , - , _ . . ~ VIRGINIA POWER NORTH ANNA POWER STATION O Amm i Roaioiogic.i Enviroome t.11 oa u. ce.... o.t. ror 1993 Juiy (1-31) i Nearest Nearest Site Milk

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

M M M -M M M N 1.33 0.87 2.01 1.91 NNE 0.94 0.85 2.62 1.69 NE 0.98 0.82 1.56 1.56 ENE 1.97 0.81 2.56 1.97 E 1.26 0.83 1.57 ESE 1.62 0.85 4.81 3.50 SE 1.37 0.88 1.37 1.37 i SSE 0.91 0.91 2.38 0.96 .! O. . i S 1.04 0.94 1.44 1.04 SSW 1.43 1.01 4.11 1.37 I SW 3.00 1.06 3.00 WSW 1.78 1.09 1.78 1.78 W 1.61 1.06 1.99 WNW 1.00 1.02 3.83 2.66 ] NW 0.98 0.97 1.10 NNW 1.07 0.90 2.22 1.19

Note: No milk cow or goats within a five mile radius of North Anna Power Station M = Mile 87

VIRGINIA POWER NORTH ANNA POWER STATION'

p. '

V Annual Radiological Environmental Land Use Census Data for 1993 July (1-31) Nearest Nearest Site Milk

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

KM KM KM KM KM KM N 2.14 1.40 3.23 3.07 , NNE 1.51 1.36 4.22 2.72 NE 1.57 1.32 2.51 2.51 ENE 3.17 1.31 4.12 3.'17 E 2.03 1.33 2.53 - ESE 2.60 1.37 7.74 5.63 SE 2.20 1.41 2.20 2.20 SSE 1.47 1.47 3.83 1.55 S 1.67 1.52 2.32 1.67 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 2.60 1.71 3.20 , WNW 1.61 1.64 6.13 4.28 NW 1.57 1.56 1.77 NNW 1.72 1.45 3.57 1.91 O

Note: No milk cow or goats within a five mile radius of North Anna Power Station KM = Kilometer 88

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

VIRGINIA ' POWER NORTIl ANNA POWER' STATION COMPARISON OF TIIE 1993 TO 1992 LAND USE CENSUS

1. Changes of nearest resident as compared to previous year are as follows: ..,

1 N Sector: 2.17 Km (1992) to . 2.14 Km (1993) a. NNE Secton 2.17 Km (1992) to 1.51 Km (1993) b.

c. NE Sector 1.90 Km (1992) to 1.57 Km (1993) j

d. W Secton 2.46 Km (1992) to 2.60 Km (1993)

e. WNW Secton 2.20 Km (1992) to 1.61 Km (1993)

f. NW Secton 1,63 Km (1992) to 1.57 Km (1993)

II. No changes were observed in the nearest site boundary distances. ! III. No changes were observed in the nearest milk cow / goat status. .l l Q IV. Changes in nearest vegetable garden as compamd to previous year am as follows: I

a. NNE Secton 2.17 Km (1992) to' 2.72 Km (1993) _ l

b. SSE Secton 1.47 Km (1992) to 1.55 Km (1993) ]

c. SSW Secton 6.61 Km (1992) to 2.20 Km (1993) l

d. W Secton 6.58 Km (1992)' to 3.20 Km (1993) ,

c. WNW Sector: 4.09 Km (1992) to 4.28 Km (1993) 4

/ V. No changes were observed in the nearest meat animal status. ] q w l'. O 89

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

1

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                                                                                      .I OL l

I j 1 l i i l 1

                                                                                      -l l

l v APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 1

                                                                                    -J l

O y

ANALYTICAL PROCEDURES SYNOPSIS P d Appendix D is a synopsis of the analytical procedums 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 Tcledyne Isoto)es and include those recommended by the USNRC Branch Technical Position, Rev.1, Novem 3er 1979. i ANALYSIS TITLE PAGE Gross Beta Analysis of Samples ..... ....... .. ... ................................................91 Ai rborn Panicu lates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 Analysis of Sarr ples for Tritium (Liquid Scintillation) .................... ........ . .........93 A nalysis of Samples for Strontium-89 and -90. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94 Total Water.. . ... .... .. . .... ..............................................94 Milk . . . ... ... .. ..... . . ... .........................................94 Soil and Sediment.... ... .. ... ... .. .... ... . ....... .......................94 . t Organic Solids . . . ... . .. . . ... . ........... . . .. ........ .......... .. .............95

                       ""'t i c "' "' "                                                                                                                                      95 O              ^ir                                               -

Analysis of Samples for Iodine-131. ... .. ... ..........................................97 Milk or Water . . . . . . . . . . . . ... ..... ......................................97 G amma S pec trom etry o f Sam ples . ._ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 Milk and Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. ........ .... ..... ...... .... 98 Dried Solids other than Soils and Sediment. .. .... ... .......................98 i Fish.............................................................................98 Soils and Sediments............................................................ . 98 Charcoal Cartridges (AirIodine) . .....................................................98 Airbome Particulates . . . . . . . . . . . . . . . . . ...............................................99 Environmental Dosimetry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 , 1 I i I

                                                                                                                                                                                 .1 i

90 .l ;

GROSS BETA ANALYSIS OF SAMPLES O 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((S/T2) + (B/t 2))1/2 /(2.22 V E) LLD (pCi/m3) = 4.66 (B1/2)/(2.22 V E t) where: S = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) 4 O 91

DETERMINATION OF GROSS BETA ACTIVITY 0 IN WATER SAMPLES Introduction The procedures described in this section are used to measure the overall radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved. One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by tqe customer, the sample is fiitered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size. After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel 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 O which eiiow for tne cnange in effective counting efficiency caused by the residue mass. 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 1 level), assuming that 1 liter of sample is used and that g 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 1 is 0.9 picoCuries per liter. These values reflect a beta counting efficiency of 0.38. ) 92 l l i

ANALYSIS OF SAMPLES FOR TRITIUM

 - d,                               (Liquid Scintillation)

Water Ten milliliters of water are mixed with 10 ml of a liquid scintillation

       " cocktail" and then the mixture is counted in an automatic liquid scintillator.

Calculation of the results, the two sigma error and the lower limit i detection (LLD) in pCl/l: RESULT = (N-B)/(2.22 V E)

      'IWO SIGMA ERROR           =   2((N + B)/At)1/2/ (2.22 V E) 11D                        =   4.66 (B/At}1/2/(2.22 V E )

where: N = the gross cpm of the sample B = the background of the detector in cpm O 2.22 = conversion factor changing dpm to pCi V = volume of the sample in ml E = efficiency of the detector At = counting time for the sample O 93

1 l I ANALYSIS OF SAMPLES ; FOR STRONTIUM-89 AND -90 Water Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO3 )2 using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a 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 to infer Sr-90 activity. Strontium 89 activity is determined by precipitating SrCO3 rom f the sample after yttrium separation. This precipitate is mounted on a 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 SrN03 using fuming O (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 rninimum 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 SrC03 rom f the sample after yttrium separation. This precipitate is mounted on a nylon plant h 4to and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Soll 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(NO3 )2 using 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 O oxaiate. Tne yttrium oxaiate is mounted on a nyion pianche"e and is counted in a iow level beta counter to infer Sr 90 activity. Strontium-89 activity is determined by pre-94

cipitating SrC03from the sample after yttrium separation. This precipitate is mounted V(~N. on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Organic Solids A wet portion of the sample is dried and then ashed in a muffle furnaca. Stable strontium carrier is added and the ash is teached in hydrochloric acid. .The sample is filtered and strontium is precipitated f9m the liquid portion as phosphate. Strontium is precipitated as Sr(NO3 ) using fe;ning (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 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 determined by precipitating SrC0 3 rom f the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 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(NO3 )2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is performed, followed by addition of stoole yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precl aitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate i4 mounted on a nylon planchette and is counted in a low lovel beta counter to infer strontium 90 activity. Strontium-89 activity is determine: ly precipitating SrC03 rom f the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with 80 mg/cm2aluminum absorber for low level beta counting. Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCl/ volume or pCi/ mass: - RESULT Sr-89 = (N/Dt-B C

                                               -B A
                                                  )/(2.22 V Yg DFSR-89 ESR-89)

Q TWO SIGMA ERROR Sr-89 /

                                     = 2((N/Dt+BC+BA)/At) / (2.22 V Yg DFSR-89 ESR-89)

LLD Sr-89 = 4.66((B C

                                               +B A         /
                                                  )/At)1/2 (2.22 V YS DFSR-89 ESR-89) 95

RESULT Sr-90 = (N/At - B)/(2.22 V Y1 Y2DF IF E) l TWO SIGMA ERROR Sr-90 = 2((N/At+B)/At)1/2/ (2.22 V Yj Y2 DF E IF)) i LLD Sr-90 = 4.66(B/At)1/2/ (2.22 V Yj Y2IF DF E) WHERE: N = total counts from sample (counts) At = counting time for sample (min) BC = background rate of counter (cpm) using absorber configuration 2.22 = dpm/pCi V = volume or weight of sample analyzed BA = background addition from St-90 and ingrowth of Y-90 BA = 0.016 (K) + (K) EY/abs) (IGy.go) Y3 = chemical yield of strontium DF SR-89 = decay f actor from the mid collection date to the counting date for SR-89 E SR-89 = efficiency of the counter for SR-89 with the 80 mg/cm.sq. aluminum absorber K = (NAt - BC)Y-90/ (Ey.go IFy.go DFy. goy1 ) D Fy 99)

                           =  the decay factor for Y-90 from the " milk" time to the mid count time Ey.go       =  efficiency of the counter for Y 90 IFy.go      =  ingrowth factor for Y-90 from scavenge time to milking time       l IG Y-90     =  the ingrowth factor for Y-90 into the strontium rnount from the " milk" time to the rnid count time 0.016       =  the efficiency of measuring SR-90 through a No. 6 absarber EY/ abs     =  the efficiency of counting Y 90 through a No. 6 absorber B           =  background rate of counter (cpm)

Y3 = chemical yield of yttrium Y2 = . chemical yield of strontium DF = decay factor of yttrium from the radiochemical milking time to ! the mid count time E = efficiency of the counter for Y-90 IF = ingrowth factor for Y-90 from scavenge time to the radio-chemical milking time O 96

1 ANALYSIS OF SAMPLES FOR IODINE-131 1 Milk or Water 1 l l 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 j iodine is then stripped from the resin with sodium hypochlorite solution, is reduced l with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free I 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 nylon planchette for low level beta counting. The chemical yield is corrected by.- measuring the stable lodide content of the milk or the water with a specific ion electrode. Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/l: RESULT = (N/At B)/(2.22 E V Y OF) .O TWO SIGMA ERROR = 2((N/At+B)/At)1/2 / (2.22 E V Y DF) LLD = = 4 66(B/At)1/2 / (2.22 E V Y DF) where: N = total counts from sample (counts) at = counting time for sample (min) B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date ! I E = efficiency of the counter for I-131, corrected for self absorption effects by the formula E = Es(exp-0.0061M)/(exp-0.0061Ms) 1 Es = efficiency of the counter determined from an 1-131 standard mount Ms = mass of Pd1p on the standard mount, mg M = mass of PDigon the sample rnount, mg 97 l

GAMMA SPECTROMETRY OF SAMPLES O 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. Schs and Sediments Soils and sedim9nts 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 lodine) 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 1-131 of each charcoal cartridge can be determined (assuming no positive 1-131) uniquely from the volume of air which passed through it. In the event 1-131 is observed in the initial counting of a J set, each charcoal cartridge is then counted separately, positioned on the face'of the - detector. 98 , 1 1

I l l 1 I l O Air Particulate The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(LI) detector coupled to a mini-computer based data acquisition system l which performs pulse height analysis. ! A mini computer software program defines peaks by certain changes in the ! slope of the spectrum. The program also compares the energy of each peak with a l 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 pCl/ mass: RESULT = (S-8)/(2.22 t E V F DF) TWO SIGMA ERROR = 2(S+B)1/2/ (2.22 t E V F DF) LLD = 4.66(B)1/2/ (2.22 t E V F DF) - where: S = Area, in counts, of sample peak and background (region of spectrum of interest) i B = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on either side of the peak t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest l and geometry of sample f V = sample aliquot size (liters, cubic meters, kilograms, or grams) F = fractional gamma abundance (specific for each emitted gamma) DF = decay factor from the mid-collection date to the counting date O

-99

ENVIRONMENTAL DOSIMETRY O: Teledyne isotopes uses a CaSO4:Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs. Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed.to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner. Calculations of results and the two sigma error in net milliroentgen (mR): RESULT = D = (D3 +D2+D 3 4D 4 )/4 TWO SIGMA ERROR = 2((D3 -D)2+(D2-D)2+(D3-D)2+(94.D)2)/3)1/2 WHERE: D3 = the net mR of area 1 of the TLD and similarly for D2, D3 , and D4 D1

                            =   11 K/R3 A 1

3

                            =   the instrument reading of the field dose in area 1 K       =   the known exposure by the Cs-137 source R3      =   the instrument reading due to the Cs-137 dose on area 1 A       =   average dose in mR, calculated in similar manner as above, of the transit control TLDs D       =   the average not mR of all 4 areas of the TLD.                           _

1 I I I O 100 i i s .

l O i l l O APPENDIX E EPA INTERLAllORATORY COMPARISON PROGRAM b l O

i i l EPA Interlaboratory Comparison Program \ .O I Teledyne Isotopes participates in the US EPA Interlaboratory Comparisor l 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, in this -! section trending graphs (since 1981) and the 1992 data summary tables are presented for isotopes in the various sample media applicable to the Surry 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. 1 m O O 101 ;

O O O VEPCO - NORTH ANNA EPA INIERIABORATORY COMPARISON PROGRAM 1993 (Page 1 of 2) EPA Date TI Malled Date EPA EPA TI Norm Dev. ** Warning Preparation Re sults Issued Results Media Nuclide Results(a) Results(b) (Known) "* Action 01/15/93 03/23/93 04/26/93 Water Sr-89 15.0 i 5.0 12.67 i 1.15 -0.81 Sr-90 10.0 t 5.0 8.33 i 1.15 -0.58 01/29/93 02/22/93 05/10/93 Water Cr-Alpha 34.0 i 9.0 17.33 i 1.15 -3.21 (c) Gr-Beta 44.0 1 5.0 52.00 t 1.00 2.77 (d) 02/05/93 03/04/93 04/20/93 Water I-131 100.0 10.0 106.67 i 5.77 1.15 03/05/93 04/30/93 06/10/93 Water Ra-226 9.8 1 1.5 7.67 i 0.12 -2.46 (e) Ra-228 18.5 i 4.6 19.33 i 2.31 0.31 04/20/93 07/02/93 08/16/93 Water Gr-Beta 177.0 27.0 150.0 i 0.00 -1.73 Sr-89 41.0 1 5.0 35.33 i 1.53 -1.96 Sr-90 29.0 1 5.0 27.33 1 0.58 -0.58 Co-60 39.0 5.0 40.67 i 3.51 0.58 Cs-134 27.0 i 5.0 23.67 i 1.53 -1.15 Cs-137 32.0 5.0 34.33 1 2.08 0.81 Gr-Alpha 95.0 1 24.0 94.33 i 1.15 -0.05 Ra-226 24.9 i 3.7 19.00 i 1.00 -2.76 ** (e) Ra-228 19.0 i 4.8 18.33 i 0.58 -0.24 o" -0.84 ro 06/04/93 07/02/93 8/16/93 Water H-3 9844.0 i 984.0 9366.67 1152.75 06/11/93 07/23/93 08/27/93 Water Co-60 15.0 5.0 16.33 i 1.53 0.46 Zn-65 103.0 i 10.0 121.33 1 2.08 3.18 (f) Ru-106 119.0 i 12.0 106.33 i 15.89 -1.83 Cs-134 5.0 i 5.0 5.67 i 0.58 0.23 Cs-137 5.0 5.0 6.67 i 0.58 0.58 Ba-133 99.0 t 10.0 104.33 i 9.29 0.92 07/16/93 09/14/93 12/02/93 Water Sr-89 34.0 i 5.0 31.67 i 2.52 -0.81 Sr-90 25.0 5.0 24.00 1 0.00 -0.35 07/23/93 08/20/93 10/23/93 Water Gr-Alpha 15.0 t 5.0 18.67 i 2.08 1.27 Gr-Beta 43.0 i 6.9 42.67 i 2.52 -0.08 08/27/93 11/05/93 12/28/93 Air Filter Gr-Alpha 19.0.i 5.0 17.0 i O.00 -0.69 Gr-Beta 47.0 t 5.0 49.00 i 1.73 0.69 Sr-90 19.0 t 5.0 17.67 1 0.58 -0.46 Cs-137 9.0 1 5.0 9.67 0.58 0.23

Footnoteslocated at end of table.

0- O O VEPCO - NORTH ANNA EPA INTERLSBORATORY COMPARISON PROGRAM 1993 (Page 2 of 2) EPA . Date "Il Malled ' Date EPA EPA TI Norm Deir. ** Warning Preparation Re suits Iasued Results Media Nuclide Resulta(a) Results(b) (Known) *" Action 09/09/93 11/12/93 12/21/93' Water Ra-226 14.9 1 2.2 15.33 i. 0.58 0.34 Ra-228 20.4 5.1 20.67 i 1.15 0.09 09/24/93 11/24/93 01/24/94- Mllk Sr-89 30 0 5.0 35.67 1 3.51 1.96 Sr-90 25.00 1 5.0 24.00 1.73 -0.35 1-131 120.0 t 12.0 126.67 1. 5.77 0.96 , Cs-137 49.0 1 5.0 50.67 i 1.15 0.58 K 1679.0 i 84.0 1620.00 i 17.32 -1.22

10/08/93 11/10/93 12/23/93 Water I-131 117.0 12.0 103.33 i 5.77 -1.97 10/29/93 11/02/93 01/17/94 Water Gr-Alpha 20.0 1 5.0 20.33 i 2.08 0.12 Gr-Beta 15.0 1 5.0 15.67 i 2.08 0.23 11/05/93 11/02/93 01/17/94 Water H-3 7398.0 1 740.0 6900.00 100.00 -1.17 11/02/93 12/23/93 02/14/93 Water Co-60 30.0 1 5.0 28.67 i 2.89 -0.46 Zn-65 150.0 i 15.0 152.00 i 9.17 0.23 5 Ru-106 201.0 i 20.0 177.33 i 5.51 -2.05 ** (g) u Cs-134 59.0 1 5.0 53.33 1 4.93 -1.96 Cs-137 40.0 1 5.0 41.33 1 3.06 0.46

                                                                                                                                                                                           **    (g) i                                                                                          Ba-133                  79.0        8.0             69.33 1    3.06          -2.09 Photnotes (t) Average i Wm,&aal sypna. .                 .

(b) Expected labora preciskm (1 sqpna, I determination) (c) The EPA switched Am-241 toh-230 alpha ydke We cahbrated with D-230. using sodium nitrate to generate a self-absorption curve. De EPA water. however has 3 minerals which have greater self-absorption that the sodium nitrate matrtx. he EPA has agreed to send us a gallon of their water which we can use to prepare a self. absorption curve withTh-230. . (c0 By overs 4 pit, we dk! not use the spedal self-absorption curve which we had previously dertved using EPA water and Cs.137 starmiard. We will use the EPA curve in the future. We may also re<$erive tids curve using a water sample which the EPA has agreed to serxl us. (c) . He counting data and 1, dyw." were ver18ed. Poembly some effidendes used were erroneously high. causing low values. A less hkely cause is an errw in dilution. New Ra-226 standards will be prepared. Closer monitoring of out of control efBdendes will be done and extra care in preparation of the sample will be =*tnined. (0 ' The calentattans were checked and found to be carect. %e results of six gamma emitting isotopes were reported to the EPA. The results of four were within 1 normmH=d deviation: a alth, within 2 normahwd deviations. Only the Zn-65 average was outside the control limits. %ere is no obvious reason why one isotope should be outside the control limits, while five other isotopes were within control Itmits. (g) An inve=Hgannn is being conducted; results will be avaGable shortly. 2

V _: : ._ . _- _ - -

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4 O O O ! 1 EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICULATES (pg.1 of 1) 160 140 - g 120 - 6 100 - D - o b

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O O O EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK (pg.1 of 1) 80 60 - > o - n 1 o - r 40 - C "o - U II 4, D

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d: O- O. ~ h. EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK (pg.1 of 1) . 2600 . 2400 - t 2200 I - - 2000 1800 5

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f~ eq w V EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK (pg.1 of 1) 100 80 - g3 o 3 60 -

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O O O EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg.1 of 2) 220 200 - 180 - II , 160 - d3 140 - 8 3 . ,, 120 - - 3 i, r

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                                                                                                                                               *u EPA CROSS CHECK' PROGRAM IODINE-131 IN WATER 160 140 -

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C O O EPA CROSS CHECK PROGRAM COBALT-60 IN WATER (pg. 2 of 2) 100 80 - o 11 60 - T

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O O O EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg.1 of 2) 100 80 - 60 - <!' - ik . '5

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O O O EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 2 of 2) 80 60 - o,, o

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