ML20082M641
| ML20082M641 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1994 |
| From: | Bowling M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 95-199, NUDOCS 9504240309 | |
| Download: ML20082M641 (139) | |
Text
{{#Wiki_filter:__ _ _ _ - _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _
,, VIHOINIA ELECTHIC AND POwEn COMPANY
- HICHMOND,VIROINIA 202 61 April 19,1995 United States Nuclear Regtilatory Commission Serial No. 95-199 Attention: Dw;ument Control Desk NAPS /JHIJCMC Washington, O. 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 Unit Nos.1 and 2 for 1994. If you have any questions or require additional information, please contact us. Very truly yours, M. L. Bowling, Manager Nuclear Licensing and Programs cc: U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station 1 95o42403o9 941231 l PDR ADDCK 05ooo338 R PDR I
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ - - - - - - - -_ L __ __
i l l l M VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION Radiological Environmental Monitoring Program January 1,1994 to December 31, 1994 'a't
)
l l 1 Prepared by VIRGINEA ELECTRIC AND PO1YER COMPANY and (3 TELEDYNE BRO 1YN ENGINEERING R/ 1 I
v. Annual Radiological Environmental Operating Report North Anna Power Station January 1,1994 to December 31, 1994 Prepared by: n - [ James B. Breeden, Supervisor Radiological Analysis Reviewed by: i' / O e,icn w. 0, eye, Supervisor Health Physics Technical Services Approved by: ' A ' Alan H. S[dford Superintendent Radiological Protection O 2
I 7 s Table O_f Contents (_/ Section Title Eage Preface.........................................................................................7 Execu tive Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 I. In tro d u cti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 II. Nuclear Power And The Environment: In Perspective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 III. S am plin g An d A n alysis Pro gram............. ...... .............. .............. .. ......... 25 IV. Program Exceptions........................................................................41 V. Summary And Discussion Of 1994 Analytical Results........................ ........ 42 A. Airborne Exposure Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42
- 1. Air Iodine /Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42
- 2. Precipi tati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44
- 3. Soil............................................................................45 o
O B. Waterbome Exposure Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45
- 1. Groun d/Well Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45
- 2. Ri ver Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5
- 3. S urface Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 C. Aquatic Exposure Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
- 1. Sed im ent/S il t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
- 2. S h oreline Soil . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 1
D. Ingestion Exposure Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50
- 1. Milk..............................................................................50
- 2. Fish..............................................................................51 l
- 3. Fo o d/V e g e t a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . 51 E. Direct Radiation Exposure Pathway . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53
- 1. TLD D o s i m e t e r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 VI. Co ncl u si o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4 I
V l l 4 3
<,,s Table Of Contents (Continued)
-'V
- Section Ilde P_ age VII. R e fe r e n c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 7 VIII. Appen dices . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 8 Appendix A - Radiological Environmental Monitoring ................................'.58 Program Annual Summary Tables- 1994 ,
Appendix B - Data Tables .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 Appendix C - Land Use Census - 1994 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 6 Appendix D - Synopsis of Analytical Proced ums . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 90 i Appendix E - EPA Interlaboratory Comparison Program ........................... 102 List of Trending Granhs '
- 1. Gross B eta in Air Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3 ;
- 2. Tritium in River Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3 :
- 3. Tri ti o m o S u rface W ate r.. . . . . . . . . .. .. .. .... . .. .. . . . .. . ... . .. . . .. . . . .. .. . ... . . .. . .. . .. . . . .. . 46 ;
e
- 4. Cobalt-58 in Sediment Silt..................................................................46 !
- 5. Cobalt-60 in Sediment Silt..................................................................48 h
- 6. Cesium- 134 in Sediment Silt. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 8
- 7. Cesium- 137 in Sediment Silt. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49
- 8. Cesi um - 134 in Fish . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 f
- 9. Cesi um - 137 in Fish . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2 l 0. Environmental Radiation - TLDs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 i
7 4 f r
i i i List of Fleures ! i
) 4 d Fieurc .Ilite P_agt
- 1. Atomic S tructure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
- 2. Alpha Panicle . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
- 3. B eta Particle . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
- 4. GammaRay..................................................................................14
- 5. The Penetrating Ability of Various Types of Radiation.................................15
- 6. Uni t Com parison . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15
- 7. The Curie, a Measurement of Activity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16
- 8. Average Annual Dose Equivalent to Persons in the U.S.
from Various Radiation S ources . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 q 9 Estimated Average Days of Life Expectancy Lost Due to V Various Health Risks........................................................................19
- 10. Reactor Vessel with Fuel Assemblies, Rods, and Fuel Pellets....... .. .............. 20
- 11. Fission: a Chain Reaction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21
- 12. PWR System Diag ram . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22
- 13. Containment Schematic . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3
- 14. North Anna Radiological Monitoring Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 a
5
- List of Tables i%' )
Table Page
- 1. Urani u m Isotopes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
- 2. Radiological Sampling Station Distance and Direction ftom Unit 1................................................................................26
- 3. North Anna Power Station Sample Analysis Program..... ............. ......... .. 38
- 4. REMP Exceptions for Scheduled Sampling and Analysis During 1994......................................................................41 Appendix B Tables B-1 Iodine- 131 Concentration in Filtered Air . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 B-2 Concentrations of Gross Beta in Air Paniculates........ ..... . .......... ............... 66 B-3 Gamma Emitter, Strontium 89, and Strontium 90 Concentrations in Air Paniculates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 70 B-4 Gamma Emitter and Tritium Concentration in River Water ........................... 73 g B-5 Gamma Emitter Con een tra tio n in S oil................................................... 73
( i B-6 Gamma Emitter, Strontium, and Tritium Concentrations in Ground and Well Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 74 B-7 Gamma Emitter, Strontium, and Tritium Concentrations in Ri ver Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4 B-8 Gamma Emitter, Strontium, and Tritium Concentrations in Surface Water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 B-9 Gamma Emitter, Strontium, and Tritium Concentrations in Surface Water State-Spli t Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76 B-10 Gamma Emitter Concentrations in Sediment Silt . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . 77 B-11 Gamma Emitter Concentrations in Shoreline Soil ............. . ....... .. .. ......... .... 77 B-12 Gamma Emitter Q neentrations in Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 8 B-13 G am ma Emitter Coneentration s in Fish.................................................. 80 B-14 Gamma Emitter Concentrations in Food / Vegetation .. .. . ... ... .... . .. ........ .. .... .. 81 B-15 Din ct Radiation Measurements Q u art erly An n u al TLD R e sults.. .......... . ... ..... ..... .... .............. ..... .. ..... 83 i n (~) B-16 Direct Radiation Measurements ; S ec t o r Q u arte rl y TLD Re sul ts...... ...... ..... .. .. ....... ........ .......... ......... ..... 84 i i 6
- Preface I
This report is submitted as required by Technical Specification 6.9.1.8, Annual l Radiological Environmental Operanng Report for North Anna Power Stations, Units 1 and 2. j Virginia Electric and Power Company Docke4 Nos. 50-338 and 50-339. ; i I i l i t l l N O : l 4 l i I 1 4 f 1 i l O 7
Executive Summary O This document is a detailed mpon on the 1994 Nonh Anna Nudear Power Station Radiological Environmental Monitoring Progmm (REMP). Radioactivity levels fmm January 1 through December 31,1994 in water, silt, shoreline sediment, milk, aquatic biota, focxl products, vegetation, and direct exposure pathways have been analyzed, evaluated, and summarized. The REMP is designed to ensure that mdiological efiluent releases are As Inw As is Reasonably Achievable (ALGA), no undue environmental effects occur, and the health and safety of the public is protected. The progmm also detects any unexpeaed environmental pmcesses whidi could allow mdiation accumulations in the environment or fcxxl pathway chains. Radiation and radioactivity in the environment is con-stantly monitored within a 25 mile mdius of the station. Virginia Power also colleas samples wi'hin this area. A g number of sampling locations for each medium were selected y using available meteomlogical, land use, and water use data. L
*j l Two types of samples are obtained. The first type, control samples, are collected from areas that are beyond the measur- g c + ,
able influence of North Anna Nuclear Power Station or any
- 37 other nuclear facility. These samples are used as reference .
1% data. Normal background radiation levels, or mdiation present due to causes other than Nonh Anna Power Station, can thus Y h - O be compared to the envimnment surrounding the nudear power station. Indicator samples are the second sample type . obtained. These samples show how ~ :h mdiation is 1 contributed to the environment by the plant. Indicator . i samples are taken from areas close to the station where any . Sc..
" ~
plant contribution will be at the highest concentmtion. - Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resultin<; values are used as a " pre-operational baseline." Analysis results from the indicator samples .ae compared to lx>th current contml sample values and the pre-operational baseline to deternine if changes in mdioactivity levels are attributable to station opemtions, other causes such c.s the Chemobyl accident, or natuml variation. Teledyne Ilrown Engineerin.g provides sample analyses for various mdioisotopes as appropri-ate for each sample me6. Panicipation in the Envimnmental Protection Agency's (EPA) Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy. Typically, mdioactivity levels in the environment am so low that analysis values frequently fall below the minimum detection limits of state-of-the-an measurement methods. I krause of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detea specified minimum Inwer Limits of Detection (11D). This ensures that analyses are as accumte as possible. Samples with extremely O iow ieveis a mduion -hidi c mnm be dereaed am d>emfbre ren<med a beins beiow the uD.
'Ihe NRC also mandates a " reporting level." Licensed nuclear facilities must report any releases 8
1
equal to or greater than this reponing level. Environmental radiation levels am sometimes referred a to as a percent of the reponing level. O Analytical results are divided into hve categories based on exposure pathwnys: Airbome, waterbome, aquatic, ingestion, and direct mdiation. Each of these pathways is described below: The aidx>me exposure pathway includes airbome iodine, airbome paniculate, precipita-tion, and soil samples. The overall 1994 aidx>me results were very similar to previous years and to preoperationallevels. No increase was noted and there were no detections offission products or other man-made isotopes in the aidx>me paniculate media during 1994.
- Mie waterix>me exposure pathway includes ground /well water, river water, and surface water samples. No man-made or natumi isotopes were detected in Irake Anna surface water except for tritium. The average tritium activity in 1994 was 14.3% of the NRC mponing level.
This lus essentially remained unchanged from 1993 levels. The aquatic exposure pathway includes sediment / silt and shoreline samples. Nonh Anna sediment contained some cesium-137. During the pmopemtional period, cesium-137 was detected. Sediment contamination, however, does not provide a direct dose pathyray to man. In shoreline soil, which may provide a direct dose pathway, only cesium-137 was detected. Cesium-137 levels decreased from 662 pCi/kg in 1993 to 134 pCi/kg in 19)4. The ingestion exposure patimuy includes milk, fish, and food / vegetation samples. lodine-131 was not detected in any 1994 milk samples. Although cesium-137 has been detected m in the past, it was not detected in 1994 milk samples. Strontium-90 was detected at levels (_) comparable to 1989, and lower than preopemtional years. Both stmntium-90 and cesium-137 are attributable to atmospheric nuclear weapons testing in the past. Naturally occurring potassium-40 was detected at normal environmental levels. Fish samples during 1994 contained cesium-137 at a slightly higher activity tlun preoperational levels. Steam generator repairs and better liquid waste processing, however, have reduced these activity levels from previous years. Vegetation samples wem statistically similar to both control and pmoperational levels. Vie direct radiation exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially the same since the preoperational period in 1977. During 1994, as in previous years, operation of the Nonh Anna Nuclear 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 lx>undary due to liquid and gaseous effluents released from the site during 1994 was 0.44 millirem. For reference this dose may be compamd to the 360 millirem average annual exposure to every person in the United States from natum! and man-made sources. Natumi sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes less than 0.1%. These results demonstrate not only compliance with fedeml and state regulations, but also demonstate the adequacy of radioactive effluent control at the Nonh Anna Nuclear Power Station. O V 9 l _.______---__i
- .WRGINIA ELECTRIC AND POWER COMPANY
/ \ NORTH ANNA POWER STATION RADIOL 9GICAL ENVIRONMENTAL OPERATING PROGRAM
- l. INTRODUCTION The operational radiological environmental monitoring program conducted 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 1,1994 through December 31,1994 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 Fmdericksburg, Virginia. The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply systems and turbine generator furnished by Westinghouse Electric Corporation. 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. {} 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 North Anna Power Station includes Technical Specifications which address the mlease 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 esponsible for collecting the various indicator and control environmental samples. Teledyne Brown Engineering is responsible for sample analysis and submitting reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with control levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally O occurrias isotones. oata coiiecica prior to the etaat overatioa is u8ed to iadicate the de8ree 10
^ i -3 . of natural variation to be expected. 'Ihis preoperational data is compamd with data collected j 0..1 durina the operationai ghase to assist in evaiuatins the radieio icai impact of the piant ; operation. 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 'I 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 am i based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet ; the criterion of"As Low As Is Reasonably Achievable". I E. This report documents the results of the Radiological Environmental Monitoring Program ; for 1994 and satisfies the following objectives of the program: l
- 1. Provides measurements of radiation and of radioactive materials in those exposure l pathways and for those radionuclides that lead to the highest potential radiation l exposure of the maximum exposed members of the public resulting from the station '!
operation. l
- 2. Supplements the radiological effluent monitoring program by verifying that !
Q_ radioactive effluents are within allowable limits. !
- 3. Identifies radioactivity changes in the environment.
'l
- 4. Verifies that the plant operations have no detrimental effect on the health and safety of l the public.
1 e O l 11
IL Nuclear Power And The Environrnent: O In Perspective Coal, oil, ratural gas, nuclear power, and hydropower have all been used to mn the naton's electric gene ating stations, Each method, however, has its dmwbacks. Coal-fimd power can damage the environment during the mining process, or by airbome discharges such as fly-ashand chemicals which conuibute to acid min.. 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 signi'icant impact on the environment. Nuclear energy provides an attemate source ofenergy which is readily available. The opemtion of nuclear power stations lus a very small impact on the environment. In fact, hundreds of acres 1 adjoining Surry Power Station are a state waterfowl refuge, and Izake Anna, next to North Anna l 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, backgmund information about ! basic mdiation chamcteristics, risk assessment, reactor opemtion, efIluent control, environmental monitoring, and mdioactive waste is provided in this section. ; i Furularnentals TheAtom (V3 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. 'Ihe ; nucleus consists of neutrons and protons. Electrons move in an orbit around the nucleus and are ! negatively charged. Protons and neutmns are nearly identical in size and weight, and each is about 2000 times heavier than an election. The proton, however, has a positive charge, while the neutron has no clurge, it is electrically neutml. Figure 1 presents a simple diagmm of an atom. l g 7 p/# Protons Positive Charge Negative Charge Nucleus
@ ~ Neutrons Neutral Charge g j i
KC665
, . . . ( , . y. y .9 ,;..; ,. .y ,,., c g m , 5 y :.
- .:. ..e~. ..~... . . _ a. p ;
.o
3.;. . . -
.. .w,@.
; . .t;l
; . g%x,x: m
- i , p. ' ~
..;tg;w, s&3.( . m :, s::
,a x; :. ...
- .; ; . . ; .ww:
2 .
. : / : ~ -' ' . ?. c ;~.',. . .. i Isotopes O The nemuer of gretons in the atom of any pecific eiement is ahvays the same. ror examgie, all hydrogen atoms have one proton whemas all oxygen atoms have eight protons. Unlike protons, 12
w 1 l the number af neutmns in the nucleus of an element may vary. Atoms with the same number of a protons, but a different number of neutrons, are called isotopes. Table 1 lists the isotopes of U uranium. Isotopes Symbols Number Number ofPmtons ofNeutmns Uranium-235 23sU 92 143 Uranium-236 2*U 92 144 Umnium-237 257U 92 145 Uranium-238 2"U 92 146 Uranium-239 2"U 92 147 Uranium-240 2*U 92 148 Table 1. Uranium Isotopes Radiation andRadioactivity : Radkmuclides O V Nomully, the pans of an atom are in a balanced or stable state. A small percentage of atoms natumily contain excess energy and therefore are not stable atoms. If the nucleus of an atom contains excess energy, it may be called a mdioactive atom, a radioisotope, or radionuclide. The excess energy is usually due to an imbalance in the number of elearons, protons, and/or neutrons which make up the atom. Radionuclides can be natuntily occurring, such as umnium-238, thorium-232 and potassium-40, or man-made, such as icxline-131, cesium-137, and cobalt 40. Radioactit'e Decay Radioactive atoms attempt to reach a stable (non-radioactive) state tluough a process known as radioactive decay. Radioactive decay is the release ofenergy from the atom tinough the emission of paniculate and/or electiomagnetic radiation. Particulate mdiation may be in the fami of electrically charged panicles such as alpha (2 protons plus 2 neutrons) or beta panicles (1 electron), or may be electrically neutral, such as neutmns. Part of the electromagnetic spectrum consists of gamma rays and X-rays which are similar to light and microwaves, but have a much higher energy. Half-Life g A radioacive half-life is the amount of time required for a radioactive substance to lose half U ofits activity through the process of radioactive decay. Cobalt 40 has a half 4ife of about 5 years. 13 I l i
After 5 years, 50% ofits mdioaaivity is gone, and after 10 years,75% has decayed away. Radioactive g half-lives vary from millionths of a second to millions of years. V Radioaaive atoms may decay directly to a stable state or may undergo a series of decay stages. During the decay process, several daughter products may be formed which eventually transform l~ ;9 stable atoms. Natundly occurring mdium-226, for example, has 10 successive daughter ; pmducts (including radon) resulting finally with lead-206 as a stable fonn. l Types OfRadiation Two types of radiation are considered in the nuclear industry, paniculate and elearomagnetic. Paniculatemdiation may \ come from the nucleus of an atom in the form of an ejected alpha particle. 7 5 Alpha panicles consists of two pmtons g together with two neutrons. N g. ; , Alpha particles have a very limited M 2 Protrons
" 2 Neutrons ability to penetmte matter. A piece of s paper will stop all alpha mdiation. For this z.,... ..,
reason, alpha mdiation from sources out- lT:f #2-p side the lxxfy are not considered to be a d radiation hazard. A beta panicleis like an electron that ' 7 5 has been ejected fmm the nucleus of an g atom. Skin or a thin piece of aluminum will stop beta mdiation. Exposure to beta N g. , 7 radiation can be a hazard to the skin or 'D *1 Neutron 1 Electron transforms (ejected beta)+ to 1 Protron (in nucleus) lens of the eye. Ilecause of their limited s ability to penetate the lxxly, beta and alplu radiation are a health cr icem primarily if alpha or beta emitters are MN swallowed or inhaled where hey might cause internal mdiation exposv . e. G;unma rays are like X-mys, except that they come from the nucleus of an atom whi'e X-rays 7 come from the electron rings. g Electromagnetic Gamma rays can penetmte deep into > radiation indistinguishable the lxxly and thus give a "whole-lxx.ly" 2 mdiation dose. Several inches ofconcrete xessa or lead will stop lxxh gamma and X-rays. Ue4 Gj[ E M O r>sec showsihe agemximaie gene-- ing ability of various types of mdiation. 14
l l m a = Alpha pv " 5 - k-.) p = Beta -
>j y = Gamma ,
g f -
% ~ '
._ ? -
1 a gg3W b, m$$$A c ,3;..
,u
^ ; &
- 0 f, M T; - '
y%a +l$$$$$ , y .'
~ , c ' ,,
4 ?? :' ^ l Radioactive Material Paper Alurrsnum 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 several inches of concrete or lead. xese4 f(]j {@e penatistich Ab ]Iof Various 1ppes of Ray Quantities And Units OfRadioactive Measurernent Sevemi quantities and units are used to describe mdioactivity and its effects. In the following O sections two ierms rem and activitv. witi he e ed to describe amounts of mdiation. . Rem measures the potential effect of mdiation exposure on human cells. Smidi doses are counted in millirem. Each millirem is equal to one thousandth of a rem. Fedeml standards limit exposure for an individual member of the public to 100 millirem annually, companxi with the avemge 300 millirem received from natural sources and approximately 60 millirem from medical applications. R " 1 inch 1 millirem
)1 2 L"###es"###aEP#########aEE L"#.E.".E.".P##.R."T"a."" #.%%T 4
O
' #aP#afiEEm"##esiEs"aEs"am"afmEEE g
B 7 '#eEmang g "uP "se n"af "se" " E E m'Is"am"# 1 8 yi y #'eEm"."an" anni e." g 10 am".T,gs,e,seg# EP# ... # #s.%gEs,gsas .T."sEP.Tei gem ii 12 LT#.%T."LT##T'LT#.T#1 LT##.P.T#.T.T.'UL'LT#.EE.1
. ==. a.
.=E. T-
..E Just as L"=P#mEEE=1EEEEPaEP=PmEr"sEEEE Twelve inches equats one foot 1000 millirem equals 1 rern
~
O ;;;jyddareQn caFWXf;QM 15
1 Curie
- g. Activityis the numberofnucleiin a
't) sample that disintegmte (decay) every second. Each time a nucleus disinte- M Uf, grates, mdiation is emitted. The unit of : h::::=::: . activity is the curie. A Curie (Ci) is the - amount of mdioactive ::~:: :: Trial which - decays at a rate of 37 bitwn atoms per 10 : ::
;i second. Smaller units of the Curie are : ; :';:{: 1 curie
- (;: ::
often used. Two common units are the microcurie (uCi), one millionth of a :-/ Curie, and the picocurie (pCD, one 10 Tons of Thorium-232 1 Gram Radium-226 trillionth of a Cune. A Cune is a mea- (radiation source) (radiation source) surement of mdioactivity, 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, e on at o di m-226 is one Curie of mdioactivity, but it would take 9,170,000 grams ('about 10 tons) of thorium-232 to obtain one Curie. Sources OfRadiation p' v BackgtvundRadiation Radiation is not a new creation of the nuclear power industry; it is a natund occurrence on the earth. Mankind has always lived with mdiation and always will. Every second of ourlives, over 7,000 atoms undergo mdioactive decay in the Ixxly of the average adult. Radioactivity exists natumlly in the soil, water, air and space. All of these common sources of mdiation contribute to the natumi background radiation that we are exposed to each day. The earth is constantly showered by a steady stream of high energy gamma mys. These mys come from space and are known as cosmic mdiation. 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 mdiation. Because of this, people living at higher altitudes or even flying in an airplane are exposed to more mdiation. Ittdioactive atoms commonly found in the atmosphere as a result ofcosmic my intemctions include beryllium-7, carbon-14, tritium, and sodium-22. Other natuml sources of radiation include mdionuclides naturally found in soil, water, food, building materi:ds and even people. People have ahvays been mdioactive, in part because the carbon found in our lxxiies is a mixture of all carbon isotopes, lx)th non-radioactive and mdioactive. Approximately two-thirds of the whole 1xxty dose from natum! sourtes is contributed byItidongas. Alx>utone-thirdofthenatumilyoccuringextemalterrestrialandinte nalwholelxxly O radiation do,e is uttribetabie to a natemiiv mdioaaive i otone of eota ium. gota siem-40.
. 16
Man-Made Q In addition to natumlly occuning radiation, people are also exposed to man-made radiation. The large;t sources of these exposures are from medical X-rays, fluoroscopic examinations, mdioactive dmgs, and tobacco. Small doses are received from consumer aroducts such as television, smoke alanns, and feitilizers. Very small doses result from the proc uction of nuclear power. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium-90, cesium-137, carbon-14, and tritium. Man-Made Sources
^g'~
~
Nuclear Power (0.1%) M id krap Miscellaneous (0.1%) r*;per"*;%g Occupational (1.4%) nsumer Goods (15.6%) ht her 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 O V , , - y; +4 - Occupational Miscellaneous 0.90
, ,1 Environmental 0.06
,g m"T 1 , .y Nuclear Power 0.05 s..-. ,
,,p
> ~ - o
' j' '
%ps&hwah Radon M,.9 >
Natural Background c va em;J55.6%)g meaH ,* Radon and Radon Daughters 200.00
%> s s .
Cosmic Rays 27.00 M 1 , an-Ma 7. Cosmogenic Radiation 1.00 l g 4 Terrestnal Radiction 28.00 l M, . h . Internal Radiation 40.00 l 1 1 Total 360.00 MREM Per Year W g < ema 1.1 %
> g.(
Terrestria 7.8 smic s .8%) Tu"$0nTAE?$tei YCs"ol$'NEiENN#"* 17 _
Efects OfRadiation Studies The efTects ofionizing radiation on human health luve been under study for mom tlun eighty years. Scientists have obtained valuable knowledge through the study oflabomtory animals that were exposed to mdiation under contmiled conditions. It has pmven diflicult, however, to mlate the biological effects of irmdiated labomtory animals to the potential health effects on humans. llecause of this, hunun populations irmdiated under various circumstances have been studied in great depth. These groups include.
- Survivors of the atomic bomb.
- Persons undergoing medicil radiation tmatment.
- Ittdium dial painters during World War I who ingested large amounts of mdioactivity by " tipping" the paint brushes with their lips.
- Uranium miners, who inhaled large amounts of mdioactive dust while mining pitchblende (umnium ore).
- Early radiologists, who accumulated large doses of mdiation from early X-ray p
~./ equipment while being unaware of the potential luzards. Analysis of these groups has increased our knowledge of health effects resulting from large radiation doses. Less is known about the efTects oflow doses of mdiation. To be on the consen ative side, we assume that health effects occur proportionally to those observed following a large dose of mdiation. That is, if one dose of mdiation causes an effect, then half the dose will cause lulf the effect. Itidiation scientists agree that this assumption overestimates the risks associated with low level mdiation exposure. The effects predicted in this manner have not been actually obsen ed in individuals exposed to low level radiation. ; Ifealtb Risks l 1 1 Since the actual effects of exposure to low level radiation are difficult to measure, scientists often l refer to the possible risk involved. The problem is one of evaluating alternatives, 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. Risks am a pan of everyday life. The question is to determine how great the risks are. We accept the inevitability of automobile accidents. Iluilding safer cars or wearing seat belts will reduce the risk ofinjury. You could choose to not drive to be even safer, but pedestrians and bicyclists are also injumd by cars. Reducing the risk of injury from automobiles to zero requires -m moving to a place where there are no automobiles. U 18
While accepting the many daily risks ofliving, some people feel tlut their demands for energy c should be met on an essentially risk-free basis. Attention is focused on safeguanling the public, ; (,j developing a realistic assessment of the risks, and placing them in perspedive. Ilecause you cannot see, feel, taste, hear, or smell mdiation, it is often a source of concern. We i luve the same lack of sensory perception for things such as mdio waves, carbon monoxide, and snull concentmtions of numerous cancer causing substances. Although these dsks are just as real as the dsks associated with radiation, they luve not generated the same degree of concem as 1 mdiation. l 1 Most risks are with us throughout our lives, and their effects can be added up over a lifetime to obtain a total efred on our life span. The typical life span for an American woman is now 76 years, whereas men average 71 years of age. Figum 9 shows a number of different factors that ' decreased our avemge life expectancy. Days Activity 2500 '
- 1. Smoking 1 Pack of Cigarettes a Day 1 2. Being 20% Overweight 2000 -
JE 3. Construction
- 4. Agriculture 1500 -~ E 5. Auto Accidents
- 6. Avg Alc h I nsumpti n per Person
("7 I 7. Home Mcidents 1000 -
- 8. Allindustry Hazards i
, 9. Rad;ation Dose of 6.5 Millirem per 500 - Year for 30 Years 0
- Qm , ,
NcRP Report No. 95, 'Radation Exposure of the U.S. C 3d',Qn,jy'o'y'y"*joTn* *N'$,*p] , 1 2 3 4 5 6 7 8 9 Wasurernents W987, Bethesda3D 206u KC562 The American Cancer Society estinutes tlut alx)ut 30 percent of all Americans 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 mdiation exposum ofone mm in addition to natural background radiation, then it is expected tlut three more may develop cancer during their lifetime. This increases the risk from 30 percent to 30.03 percent. IIence, the risks of mdiation exposure are snull 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, 3 you can decide wlut to do or what not to do. (G 19
,m NuclearReactor Operation Electricity in the United States is being produced using fossil fuel, umnium, or falling water.
{ A fossil-fueled power station hums coal, oil or natum! gas in a boiler to produce energy. Nuclear l power stations use umnium fuel and the heat produced fmm the fission process to make energy. I In both cases, they heat and boil water to produce steam. The steam is used to drive a turbine which tums a generator and produces electricity. i NuclearFuel ' Umnium (U) is the basic ingredient in nuclear fuel, consisting of U-235 and U-238 atoms. ! Natum! uninium contains less than one percent U-235 when it is mined. Commercial nuclear power plants use fuel with a U-235 content of approximately thme percent. The process used to increase the U-235 concentration is known as enriclunent. Reactor Operation After enriclunent, 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 about 3/4 inches long and 3/8 inches in diameter. The pellets are placed into 12 foot long metal tulws 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 m assemblies (Figum 10). U Reactor Vessel O O9 Fuel Rod M U a% M.(. .T '. Control Rods ).d ON16 ~ g Water Level
"'"'s$ -
l l
- coolant iniet Nozzle A 1 i ,
Fuel Rod Assembly lj Fuel Rod Assembhes Fuel Pellet Thermal SNeld 1 I l i
} I,l
,N - -
j / l cae Support S(minid, ,/ ) WT424 U E io;neactor eneswispddAsam6 es,;NodhaNi. {. l l 20 l l __-_____ __ a
Fission O, Nuclear energy is produced by a process called fission. Fission occurs in a reactor when uranium is split into g, , , fragments producing heat and releas-
- ga" ing neutrons. These neutons strike ke W other umnium atoms, causing them to [8 "'.
split (fission) and release more heat MT427 and neutrons. This is called a cluin reaction (Figure 11) and is controlled h Heavy Atom o Free Neutron by the use of reactor control rods. O Fission Fragment m* Heat Contmlrods arean essenti:d pan of the nuclear reactor. Control rods con-gg]gy p}g (((( 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 contml axis are insened completely into the core. When the control rcxis are withdrawn, the chain reaction begins and heat is genemted. Design & Operation Surry Power Station and Nonh Anna Power Station use a Pressurized Water Reactor (PWR) l Q system to generate electricity. There are two complete and independent PWR systems on-site at both Surry and Nonh 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 Vesel. The reactor core is always surrounded by water. The fissioning of the umnium fuel makes the fuel rods get hot. 'Ihe hot fuel rods heat the water, which serves as a coolant that carries away heat. l In a pressurized water reactor, heat is moved fmm place to place by moving water, the reactor's coolant. The water flows in closed loops. 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 (psi), it doesn't boil. The hot water then flows to the steam genemtor. The steam generator is a heat exclunger. Reactor coolant passes through it but doesn't mix with the steam generator (secondary) w;uer. Instead, heat from the primary water is transferred 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 lus 3 steam generators. j l The steam is piped to a steam turbine that tums an electric generator. The exluusted steam ' from the turbine is cooled and convened back to water in a condenser. The condenser is also a heat exchanger; in it heat passes fmm the steam to a third kx)p of water. In Surry's case theJames River provides the third loop water. At Nonh Anna Power Station third loop water is from lake Anna. The steam tums back to liquid and is pumped back to the steam genemtor. Figure 12 is (] a diagram of typical nuclear reactor systems. 21
- Pressure le System o - a:am-~~ Contamment Spray Syshm sumummme Man Steam System Reactor Containment Building so-mmme %*,,c= lino ng sgy,)
conden orconhnosy wm summumime Mam Feedwater System summmmme Awohary Food Water System gy,g commment sorav muw. ( Turbine Building
%, 1 %
g Radiation Monitor y,,n Electncal Auxiliary Building y",y'
" ' smarn we.= = y, g Power
'Chavocal Filte, Tuftnne 88""#8 Refuelmg W Fan condenser
. -~-
.n. ..
; SprayPump _
g a m W Or h cm inJa.,. ~' F he W ,_ , 4 - 3 C: . su um'ka Or Rwer
. Nume C trol ak Reactor Venel e-- Feed Pump
, e ~~ ~ Q% ,, a ;
}
w I -> W I y Aumhary Feed Pump Eme w l B L_ \ Re.c= c-mniPom,
?g"'""E p contamment sump d
-{ l}.. / ; PWR$ystem.D Containnumt Nuclear power plants are designed to prevent the escape of large quantities of mdiation and 1 mdioactive substances. Two principles are used. First, thick, heavy walls are used as shielding l to absod) mdiation 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 dimct hit from a jet airliner. 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 even heavier than an ordinary steam boiler because of the need to minimize the chance ofmpture and release of any mdioactive materials. The mactor pmssure vessel is made from a stainless steel 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 Q airtight 1/2 inch steel liner sun ounds the entire interior of the containment. If the reactor pressure vessel or any of the primary piping should break, the escaping steam would be trapped inside the i liner. 22
s 1 I A
\ 21/2 Feet Thick Concrete
[O 1/2 inch Steel Liner 3/8 inch Steol Liner 3 l l Steam 41/2 Feet Thick Concrete Generators 4 S P der l h Man Ll b iMI .. 122 Feet - Reactor
- .-r r r:
'R
$ik.
.A
_Y, , !! b,,:: :C:C: :h,
) : # wTos Y
l 0 .:C2 + 3 ., > ,, :3fp.:. Uner 10 Feet Thick Concrete 126 Feet > f h .f 8 .
@ men .
[A Finally, the building's reinforced concmte 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 natuml and man-made events like earthquakes and even the direct impact from a large commercial jet aircraft. Operating ihe ReactorSafely Accidents The most serious accident that could luppen in a nuclear power plant invohes overheating in the nuclear reactor core. Such an accident would result from a loss-of-coolant accident or LOCA. During a LOCA, primary coolant would no longer circulate tiuough the reactor core to remove heat. O Circulation could be lost if a combination of pipes burst, for example. Conceivably, a dry, overheated reactor com could melt through the pressure vessel. 23
%e reactor itselfis designed to respond autonutically to such an emergency. Opemtors are 73 also tmined to make corrections forany system failure. The automatic and operator msponses luve V two goals: to prevent damage to the reactor, and prevent the wlease of radiation. Shutting the reactor down is relatively easy. Contml rods dmp in and chemical to stop the nuclear maction are injected into the coolant. Iosing the coolant itself tends to stop the cluin maction because the coolant is needed to keep the nuclear chain reaction going. Within 10 seconds of shutdown, the amount of heat is less than 5 percent of the amount pmduced at full power and within 15 minutes, less than 1 percent.
To carry heat away during an accident, all reactors luve Emergency Core Cooling Systems (ECCS). The ECCS consists of primary and back-up pumps and reservoirs of coolant tlut opemte separately frum those that normally circulate through the system. A nuclear mactor lus nuny different back-up safety systems designed so tlut if one fails another is always available. Workers There are many different jobs at a nuclear power plant and t hey are filled by people with diverse backgrounds. All employees are initially tmined and then retmined annually by the company. Virginia Power's Tmining centers are fully accredited by the National Academy for Nuclear Tmining and the Institute for Nuclear Power Opemtions. The opemtors are tested and certified by the United States Nuclear Regulatory Commission (NRC). ( Safety Statistics V Job safety is another measure of assumnce tlut the station is being properly opemted. Surry Power Station attained 5,000 nun hours without a lost time accident and is continuing that record into 1995. Nonh Anna Power Station lus attained over 3,000,000 man hours without a lost time accident. Surnanasy Nuclear energy provides an alternate source of energy which is readily available. The opemtion of a nuclear power station has a very snull impact on the environment. Radiation is not a new creation of the nuclear power industry; it is a rutuml occunence on the canh. Mankmd lus always lived with mdiation and always will. Radioactivity exists nat umlly in the soil, water, air and space. All these common sources of mdiation contribute to the rutuml luckgmund radiation to which we are exposed. In addition to natumlly occurring mdiation and mdioactivity, people are also exposed to man-made mdiation. Very small doses result from the production of nuclear power. Nuclear power plants are designed to prevent the escape of mdiation and radioactive I substances. O- = A nuclear reactor lus many different back-up safety systems designed so tlut if one fails ; another is available. i 24
O p O III. SAhfPLING AND ANALYSIS PROGRAh! fi 6 l l l 1 l l
]
O
]
.i
~
Ill. - SAMPLING AND ANALYSIS PROGRAM !
"A.. . Sampling Program j l
- 1. Table 2 summarizes the sampling program for North Anna Power Station during : .j 1994. Figure 1 indicates the locadons of the environmen'tal monitoring stations.
- 2. For routine TLD measurements, two dosimeters made of CaSO4:Dy in a teflon card _
are deployed 'at each sampling location. Several TLDs are co-located with NRC and .; Commonwealth of Virginia direct radiation recording devices. 'Ihese are indicated as !
"co-locanon" samples. !
- 3. In addidon to the Radiological Environmental Monitoring Program required by North Anna Technical Specificadons, Virginia Electric and Power Company (VEPCO) splits samples with the Commonwealth of Virginia. All samples listed in Table I are ;
collected by VEPCO personnel except for those labeled state split. All samples are .; shipped to Teledyne Brown Engineering lo:ated in Westwood, New Jersey. - O 4- ^ii s>= ries iisted in Table 2 are taken at indicator locations except those iabeled .
" control".
7 i z!
-O- 1 i
25
d V --V
- TABLE 2 (Page 1 of 5)
North Anna Ibwer Station - 1994 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECI'lON FROM UNIT NO. I Distance Compas= Collection Simple Media Location Station Miles Direction Degrees Frequency Remarks Emironmental NAPS Sewage 01 0.20 NE 42* Quarterly On-site State Split Thermoluminescent Tiratment Plant & Annually Dosimetry (TLD) Fredericks IIall 02 5.30 SSW 225' Quarterly State Split
& Annually Mineral,Va 03 7.10 WSW 243' Quarterly
& Annually Wares Crossroads 04 5.10 WNW 287' Quarterly State Split
& Annually Route 752 05 4.20 NNE 3P Quarterly
& Annually Sturgeon's Creek 05A 3.20 N 11' Quarterly Marina & Annually levy, VA 06 4.70 ESE I15' Quarterly State Split Co-location
& Annually Bumpass, VA 07 7.30 SSE 167* Quarterly State Split
& Annually E:x1 of Route 685 21 1.00 WNW 301' Quarterly Exclusion Bourxiary N & Annually
- State Split, Co-location Route 700 22 1.00 WSW 242' Quarterly Exclusion Boundary
& Annually State Split
' Aspen Ilills' 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 10' Quarterly On-Site Sturgeon's Creek N-2/34 3.20 N 11* '2uarterly Marina Parking lot 'C' NNE-3/35 0.25 NNE 32* Quarterly On-Site (on-site)
Good flope Church NNE-4/36 4.96 NNE 25' Quarterly State Split Parking tot 'B' NE-5/37 0.20 NE 42' Quarterly On-Site Lake AnnaMarina NE-6/38 1.49 NE 34' Quarterly Weather Tower Fence ENE-7/39 0.36 ENE 74' Quarterly On-Site Route 689 ENE-8/40 2.43 ENE 65* Quarte +1y Near Training E-9/41 0.30 E 91* Quarterly On-Site Facility
O! d "D ~' TABLE 2 - (Page 2 of 5) North Anna Ibwer Station - 1994 RADIOLOGICAL SAMP11NG STA110NS DISTANCE AND DIRECI1ON fROM UNIT NO. I Distance Compass CoHection Srmple Media Location Station Miles Direction Dearces Frequency Rensarks Eavironmental " Morning Glory flill' E-10/42 2.85 E 93* ' Quaterly Thermoluminescent Island Date ESE-II/43 0.12 ESE 103'- Quaierly On-Site Dosimetry (TLD) Route 622 ESE-12/44 4.70 ESE 115' Quaterly VITCO Biology Lab SE-13/45 0.75 SE 138* Quaterly On-Site Route 701 (Den Entrance) SE-14/46 5.88 SE 137* Quarterly "Arpen Ilills' SSE-15/47 - 0.93 SSE 158' Quarterly Exclusion Boundary Elk Creek SSE-16/48 2.33 SSE 165* Quaterly Warehouse Compound Gate S-17/49 0.22 S 173*. Quarterly On-Site Elk Circk Church S-18/50 1.55 S 178' Qtuterly NAPS Access Road SSW.19/51 0.36 SSW FYl* Quarterly On-Site Route 618 SSW-20/52 5.30 SSW 205* Quaterly NAPS Access Road SW-21/53 0.30 SW 218' Quaterly On-Site N 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 Bounday) NAPS RadioTower W-25/57 0.31 W 279* Quarterly : On-Sine Route 685 W-26/58 1.55 W 274' Quarterly ( End of Route 685 WNW-27/59 1.00 WNW 30l' Quarterly Exclusion Boundary II. Purcelfs Private Rd. WNW-28/60 1.52 WNW 303* Quarterly Co-location End of #1/r2 Intake NW-29/61 0.15 NW 321' Quairrly On-Site Lake AnnaCampground 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' Quarterly Bumpass Pbst Office C-1/2 7.30 SSE 1.67* Quarterly Control Orange.VA - C-3/4 22.00 NW 325' Quarterly Contml Mineral.VA C-5/6 7.10 - WSW- 243' Quarterly Control - Louisa.VA C-7/8 11.54 WSW- 257 Quarterly Control
p p/ p V L. V TABLE 2 (Page 3 of 5) North Anna Power Station - 1994 RADIOLOGICAL SAMP13NG STAllONS DISTANCE AND DIR1rilON FROM UNITNO. I Distance Compass Collection Srmple Media Location Station Miles Direction Degrees Frequency Remarks Airborne Particulate NAPS Sewage 01 0.20 NE 42' Weekly On Site State Split exd Radiciodine Treatment Plant Fredericks IIall 02 5.30 SSW 205* Weekly Mineral. VA 03 7.10 WSW 243' Weekly Wares Crossroads 04 5.10 WNW 287' Weekly Route 752 05 4.20 NNE 2P Weekly Sturgeon's Creek Marina 05A 3.20 N 11' Weekly levy, VA 06 4.70 ESE I15' Weekly Bumpass, VA 07 7.30 SSE 167' Weekly End of Route 685 21 1.00 WNW 30l* Weekly Exclusion Boundary Route 700 22 1.00 WSW 242' Weekly Exclusion Boundary State Split
- Aspen Ilills" 23 0.93 SSE 158' Weekly Exclusion Boundary Orange, VA 24 22.00 NW 325' Weekly Control Srrface Water Waste IIcat 08 1.10 SSE 148' Monthly State Split rv Treatment Facility 5 (Second Cooling Lagoon)
- Lake Anna (upstream) 09 2.20 NW 320* Monthly Control State Split (Route 208 Bridge)
- Lake Anna (upstiram) 09A 12.90 WNW 295* Monthly Control (Route 669 Bridge)
River Water North Anna River 11 5.80 SE 128' Monthly (downstream) Ground Water Biology Lab OIA 0.75 SE 138' Quarterly State Split (Well Water) Precipitation Biology Lab OIA 0.75 SE 138' Monthly Aquatic Sediment Waste IIcat 08 1.10 SSE 148* Semi-Annually State Split Treatment Facility (Second Cooling lagoon) Lake Anna (upstream) 09 2.20 NW 320* Semi-Annually Control. State Split North Anna River 11 5.80 SSE 128* Semi-Annualiv (Downstream) In Octoter 1991 the Surface Water Sample location at station 09 was moved to 09A.
O O O! ~ TABLE 2 (Page 4 of 5) North Anna Power Station - 1994 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO.1 Distance Compass Collection - Simple Media Location Station Miles Direction Degrees Frequency Remarks Shoreline Soil lake Anna (upstream) 09 2.20 NW 32r Send-Annually State Split (Route 208 Bridge) Soil - NAPS Sewage 01 0.20 NE 42" - Once/3 years On-Site Treatment Plant Fredericks llall 02 5.30 SSW 205' Once/3 years Mineral VA 03 7.10 WSW 243' Once/3 years Wares Cmssmads 04 5.10 WNW 287' Once/3 years Route 752 05 4.20 NNE 27 Once/3 years Sturgeon's Creek Marina 05A 3.20 N 11' Once/3 years levy, VA 06 4.70 ESE 115' Once/3 years Bumpass, VA 07 7.30 SSE 167' Once/3 yean _ 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 Boundan)
" Aspen Ilills" 23 0.93 SSE 158' Once/3 years Exclusion Boundary Orange, VA 24 22.00 NW 325' Once/3 years Contml Milk IIolladay Dairy 12 8.30 NW 31 7 Monthly State Split (R.C. Goodwin)
Terreirs Dairy 13 5.60 SSW 205* Monthly State Split (Fredericks IIall) Fish"* Waste llent 08 1.10 SSE 148' ~ Semi-Annually State Split Treatment Facility (Second Cooling Lagoon) Lake Anna (upstream) 09 2.20 NW 32 7 Semi-Annually State Split (Route 208 Bridge) Lake Orange
- 25 16.5 NW 312' Semi-Annually . Control t
! Food Products Route 713 14 1.20. NE 43' Monthly if available (Broadleaf or at harvest Vegetation) Route 614 15 " 1.70(1.37) SE 133* Monthlyif available ' j or at harvest t l Added as result of 1990 Quality Assurance Audit.
** laation changed as a result of 1991 Land Use Census to garden at 1.37 miles Octeer 1991.
t
*** Fish sarnple no longer obtamed at station #09.
O O O TABLE 2 (Page 5 of 5) North Anna Ibwer Station - 1994 RADIOLOGICAL SAMIUNG STATIONS DISTANCE AND DIRirI1ON FROM UNIT NO.1 Distance Compass CoIIection S:mple Media Location Station Miles Direction Degrees Frequency Rernerks Food Products Route 629/522 16 12.60 NW 314' Monthly if av41abic . (Eroadleaf or at harvest Vegetation) Emi of Route 685 21 1.00 WNW 301' Monthlyif available or at harvest AspenIlills 23 Oc)3 SSE 158' Monthly if available or at harvest O
-.- ---..-n.-,.,.. ,- ,-,-,,u----e.,-.,. . . , . . . , - .e-a.~r-, -.,~- e ----<--,,,n -.._,rm. -m,,.,v -m--e. ..w.-,,n,< a . + - . , v..n- e.-...n-- .-..---~.n... 1 .,~. ,.s.-
Legend For The North Anna Power Station j Q) Environmental Monitoring Stations Overview Maps l I
. Map Environmental Sta Map Environmental Sta Designation Identification Designation Identification 1 (a) 01,NE-5/37 7/8 C-7&8 1A 01A,SE-13/45 1/33 N-1/33 ;
2 (a) 02,SSW-20/52 31/63 NNW-31/63 , 3 (a) 03,C-5/16 29/61 NW-29/61 4 (a) 04 3/35 NNE-3/35 5 (a) 5 7/39 ENE-7/39 , 5A (a) 05A,N-2/34 9/41 E-9/41 6 (a) 6,ESE-12/44 11/93 ESE-11/43 7 (a) 07,C-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 V 11 11-River Water, Sediment 25/57 W-25/57 12 12-Milk 16/48 SSE-16/48 13 13-Milk 18/50 S-18/50 14 14-Vegetation, NE-6/38 14/46 SE-14/46 15 Vegetation 22/54 SW-22/54 - 16 Vegetation 26/58 W-26/58 21 (a) 21,WNN-27/59 28/60 WNW-28/60 22 (a) 22,WSW-24/56 32/64 NNW-32/64 23 (a) 23-SSE-15/47 8/40 ENE-8/40 24 (a)(b) 24,C-3&4 4/36 NNE-40/36 25 (c) 25-Fish 1&42 E-10/42 l 4 (a) Indicates air sample station, annual and quarterly TLD, Triennial soil (b) InOrange (c) In Lake Orange 1 31
_. a _ . - _ r w- - - e. a - M
, O O O j
=
, W
- 1 I
ESE
=~
k2ns l SE ssw i j % imi (sms O Nis&" ~ k257m l
= Rad o ca Mon o gL t ons m._-___._
m .___+..-.m ___. - - _ _ . _ _ - -_m,._____m__ - _
O O O North Anna Environmental Map e
@ Fixed Environmental Sampling Location
_s ANNE
. m e_ ,
t _ NE @ Residents k.f:y p ENRY h Meat Animals og POST 0AK & fI MARG
.'VN1NSEIWYPERMiSSN p LANES l @' N"***"[*""""**""*"'"""
CORWER O
. SNELL
$ ~ KENSU , s- % INDIAN CL ERES ygg
~5 VILLA yl
\,% ,
NE y q 656
~
THORI
=
y,3*T-C 8 i hT C0flNER HANIS
=::::=- s ' 5 fDRD C0L M f i 1 614 DUERSONS M .
SCAD ti T 1L n RREv5 5'D"' 7
// g) CROSSROADS 73g S ' g- f l ..
i (i,o) 51 i' 4W 1614 GATEWOOD MARYE j.S N FARL Y . .g y n - 1 . Y .-. . Q d esmos
. . _ . . . _ _ . - , _ . _ ~ - - -. ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ . _ _ .
O O O re y 6ntwam** CO l N s AAygg BLANTOWS 80 7 C PIBE ST j .g MER C C e f .f ' Sougp, IO E e PARTLOW Afk js , _ s
, l l .& y l$O 671 \
. 601
,. 3,
,65 4 is' -Hi:.: -:>
./: 671 RG s.n f ^:: , ,", . .-e . . e . 4
( pcM m 7;y 1 99 g U Caroli [ $' f Mill i d h .:l ts t - GREE $ "' .\ 3
'_ Q5 con .t gs e f i CEDAR FORK f
BUMP .y
- I -
w.
~-I J
,3 [' North Anna Environmental Map
# $ Fixed Environmental Sampling Location f n iy EAVERDAM f */4,,,%i*;;A::y $ TLD Sampling I'SOf "A""I 1 j# if J' 7
Garden J l S /s4. 5 TORE k.
T
@ Residents
[ .k' ' O. h Meat Animals HCKHAM " 2 n i DRNER - .g l onoinal e a by Acc d exerene, k. suo Genormi or n way. I Al mardne. VA 22312. USED WITH PERMISSION No other reproducten
+$-
P s # 8 rnay be made without ew wnteen permosen of ADc, CB3282
O O O It0 RED 105S1NG f~ $
-$ $f k lb (t'g 4
16 5 p . {2 3 %
% < 12
) ,xf
' EI I f !
touisA y]=== x _ _. - # a N
/ MINERA ,t _.g 8 s. cree g l
WSW [
<s Indestrial Air Park E
/
/*
A L l 61 g Y ' l 3 T ON N lPE 3 FREDERI s
%- \ ' iP 3 3
\ j $r'lll 5 f \
North Anna Unvironmental Map ) . _ cucnoo n e, g Fixed Environmental Sampling Location
$ TLD Sampling * #
M0 ET
$ Garden ! % THREE MILE GA ND
~ '1 Residents e ma,_,, , o,-s _3y /
g55 _=m_,.~,. .- -= =====. Uf ,. CB3283A
o o o
""""c '
< -~
1 (~ 1 \ \\ NNW e ., h. e NW g T7 s P TE 62 .[ C AA
\ D IEL y, I
, NTON .,
ac TATION , WNg ?. 'x A. -
]651 ,
4 'k j, 4 p q CROSSRO
* +; s Y
I I I llMUtNNILL \ (' gN A..
- m. .. .32"-
- p. . *:'.*. -
651 N s I E sj6'
..g:.. ' . ,JF 1$L 33 (4
l u
* ..- VAWTEN.. N' f
-CORNER V 4# jj f y p'ER
' [
64,, % 12 - / I j L<mi.m [ - ' " ' OLLADA E p s . STATE North An a Environmental Map
$ Fixed Environmental Sampling Location isss v j
68 h ,,
$ TLD Sampling % wa g (61 { - -
9 Garden ICKI N CR [SROADS F eat n mais [' , e-4Wf
======
. CB32819
'I e !
'B.
^
. Analysis Program i
{.O - l
- 1. Table 3 summarizes the analysis program conducted by Teledyne Brown Engineering j for North Anna Power Station during 1994. !
5 1 9 i l i i t i i i n
;O t
~l f
f l
'?
I l l i O 37
i TABLE 3 (Page 1 of 3)
- k. NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM !
SAMPLE MEDIA FREQUENCY A N A LYSIS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2mRi2mR mR/std. month , Dosimetry (TLD) l (84 Routine Station TLD's) 12 Station TLD's Annually Gamma Dose 2mRi2mR mR/std. month Airborne Weekly I-131 0.07 pCi/m 3 Radioiodine Airborne Weekly Gross Beta 0.01 pCi/m 3 Particulate Quanerly @ Gamma Isotopic pCi/m 3 Cs-134 0.05 Cs-137 0.06 . Annually Sr-89 (c) pCi/m3 (2nd Quaner Sr oG (c) Composite) Surface Water Monthly I-131 1(b) pCi/l ! Gamma Isotopic pCi/l , Mn-54 15 : Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 , Nb-95 15 l Cs-134 15 Cs-137 18 Ba-140 60 , La-140 15 ! Quarterly (a) Tritium (H-3) 2000 pCi/l 2nd Quanerly Sr-89 (c) pCi/l Composite Sr-90 (c)
- LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed.
O (a) (b) Quarterly Composites of each location's samples are used for the required analysis. LLD for non-drinking water is 10 pCi/ liter. (c) There are no required IlEs for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering. 38
l l TABLE 3 (Page 2 of 3) : v NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS River Water Monthly I-131 1(b) pCi/l Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a) Tritium (H-3) 2000 pCi/l 2nd Quaner Sr-89 (c) pCi/l Sample Sr-90 (c) Ground Water Quanerly(a) Gamma Isotopic pCi/l (Well Water) 2nd Quaner Mn-54 15 O Composite Fe-59 Co-58/Co-60 30 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 1(b) Cs-134 15 > i Cs-137 18 Ba-140 60 La-140 15 Quarterly (a) Tritium (H-3) 2000 pCi/l 2nd Quaner Sr-89 (c) Composite Sr-90 (c) Aquatic Semi-Annually Gamma Isotopic pCi/kg (dry) , Sediment Cs-134 150 Cs-137 180 Annually Sr-89 (c) pCi/kg (dry) Sr-90 (c) l Precipitation Monthly Gross Beta pCi/l Semi-Annual Gamma Isotopic pCi/l Composite
- LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may O (a) de ie-er t8 = teese iieico.
Quarterly Composites of each location's samples are used for the arquired analysis. (b) LLD for non-drinking water is 10 pCi/ liter. (c) There are no required LLD's for strontium-89B0.11D's are those achieved by Teledyne Brown Engineering. 39
B TABLE 3 !
; (Page 3 of 3) (
l NORTH ANNA POWER STATION ! SAMPLE ANALYSIS PROGRAM i t SAMPLE MEDIA FREQUENCY ANALYSIS LLD* , REPORT UNITS f Shoreline Soil Semi-Annual Gamma Isotopic pCi/kg (dry)- l Cs-134 150 ! Cs-137 180 i Annually . Sr-89 (a) ! Sr (a) - Soil Once per 3 yrs. GammaIsotopic pCi/kg (dry) I Cs-134 150 Cs-137 180 i Once per 3 yrs. Sr-89 (a) pCi/kg (dry) l Sr-90 (a) , Milk Monthly I-131 1 pCi/1 i Monthly Gamma Isotopic pCi/l i Cs-134 15 Q Cs-137 Ba-140 18 60 La-140 15 Quarterly Sr-89 (a) pCi/1 l Sr-90 (a) Fish Semi-Annual Gamma Isotopic pCi/kg (wet) Mn-54 130 . Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Monthly if Gamma Isotopic pCi/kg (wet) (Broadleaf 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 nuct' ides which can be detected and reponed. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
)
- I LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed. '
(a) There are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering. 40
_ _ -4 O
)
l 1 O iv. raooaiu excserious i j j i 1 i O l l
)
l 1
Table 4 REMP Exceptions For Scheduled J Sampling And Analysis During 1994 - North Anna a Location Description Date of Sampling Reason (s) for Loss / Exception ENE-7 Dimet Radiation / 03/30/94 TLD was missing from sampling locction. TID O O 41
l l O O v.
SUMMARY
AND DISCUSSION OF 1994 ANALYTICAL RESULTS O
a V. Summary And Discussion of 1994 Analytical Results O Data from the radiological analyses of environmental media collected during 1994 are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Quality Assurance Muual and are explained in the Teledyne Brown Engineering Analytical Procedures. A synopsis of analyncal procedures used for the enviromr. ental samples is provided in Appendix D. In addinon 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 am dependent on sample size, detector efficiency, length of counting time, chemical yield, when appropriate, and the radioactive decay factor from time of coundng to time of collection. Teledyne Brown Engineering's analytical ] methods meet the Lower Limit of Detecdon (LLD) requirements given in Table 2 of the USNRC Branch Technical Position of Radiological Monitoring (November 1979, Revision 1) and the ODCM. The following is a discussion and summary of the results of the environmental measun:ments taken during the 1994 reponing period. A. Airborne Exposure Pathway
- 1. AirIodine/Particulates Charcoal cartridges used to collect airborne iodine were collected weekly and analyzed by gamma spectrometry for iodine-131. The results are presented in Table B-1. All results were below the required lower limit of detecdon. For air particulates, gross beta activity was observed in all fifty-two control samples with an average concentradon of 0.020 pCi/m3 and a range of 0.013 to 0.033 pCi/m3. The average measurement for the indicator locations was 0.010 pCi/m3 with a range of 0.010 to 0.078 pCi/m3. The results of the gross beta activities are presented in Table B-2. The gross beta activities for 1994 were comparable to levels measured in the 1982-1993 period. Prior to that period the gross beta
' activities were higher due to atmospheric nuclear weapons testing by other countries. l 42
mw i l l l TRENDING GRAPH-1: GROSS BETA IN AIR PARTICULATES ! I E I
& \
0.1 - - - - - - - - --------4 I l lg 0.01:
>------------------------@---------_(
MtN ' I l 0.001 m usu m.m m mm m m m mm mmim;m.mmim.;m mm m.m m umm m.m,m u m.mm m mim m,mm mm m, l l 198G 1937 1988 1989 1990 1 991 1992 1993 1994 l
--G - Control-Sta-24 -e-- Indicator --A Average Pre op -+ - Required LLD's TRENDING GRAPH 2: TRITIUM IN RIVER WATER-STATION 11 ;
10000; ,
= - - - - -
+-----------------.----__---_--y 3 1000-E z
6 1003 E E 10, Oa I i i i s a i i 1985 1986 1987 1938 1989 1990 1991 1992 1993 1994 l 1 Tritium -4 Required LLD's O During the preoperatonal period. trilium was not detected in the samples analyzed. l 43 ; 1
L P T
. During the preoperational period of July 1,1974 through March 31,1978 gross beta A.s activities ranged frbm a low of 0.005 pCi/m3 to a high of 0.75 pCi/m3, Air particulate filters wem composited by locanons 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 0.097 pCi/m3 with a range of 0.084 to 0.117 pCi/m3. The indicator locations had an average concentration of 0.089 pCi/m3 and a range of 0.064 to 0.151 pCi/m3. During 'the;
- preoperational period, beryllium-7 was measured at comparable levels, as would be '
expected. Naturally' occurring potassium-40 was detected in one_ control samples with a . concentration of 0.006 pCi/m3. Potassium-40 was detected in eight indicator samples with an average concentration of 0.013 pCi/m3 and a range of 0.004 to 0.029 pCi/m3. . All other : gamma emitters were below the detection limits. During the preoperational period gamma ray spectroscopy measured several fission products in numerous air particulate filters. All - isotopes were attributed to atmospheric nuclear weapons testing conducted before the preoperational period. Among the isotopes measured were zirconium-95, ruthenium-103, ruthenium-106, cesium-137, cerium-141 and cerium-144. O The second quarter composites of air particulate filters from all twelve stations were analyzed for strontium-89 and 90. There was no detection of these fission products at any of the eleven indicator stations nor at the control station.
- 2. Precipitation A sample of rain water was collected monthly at station 01A, on site,0.75 miles,138 degrees SE and analyzed for gross beta activity. The results am presented in Table B-4.
The average gross beta activity for 1994 in the twelve samples was 3.9 pCi/ liter with a . range from 2.3 to 13 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 thc se measured in 1986 thm 1993. During the preoperational period gross beta activity in vain water was expressed in nCi per square meter of the collector surface, thus a direct ecmpariso a can not be made to the 1994 period. During the preoperational period, tritium wts measured in over half of the few quarterly composites made. The tritium activity ranged from 100 to 330 pCi/ liter. 44
l / . l
- 3. Soil !
h' Soil samples are collected every three years from twelve stations. Since they wem collected in 1992, soil was not sampled during 1994. B. Waterborne Exposure Pathway l
- 1. Gmund/WellWater i
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 pmsented in -
'l Table B-6. No gamma emitting isotopes or tritium were detected during 1994. He second -
l quaner sample was analyzed for strontium-89 and strontium-90. There were no detections .j of these isotopes above the detection level. No gamma emitting isotopes were detected ; during the pmoperational period. Tritium was measumd in most of the samples during that ! period with concentrations between 80 and 370 pCi/ liter. !
- 2. River Water A sample of water from the North Anna River was collected monthly at station 11,5.8 0:
miles downstream from the discharge iagoon,128 desmes SSE. The results are presented in Table B-7. The samples were analyzed by gamma spectmscopy monthly. The samples : were analyzed for tritium quarterly on a composite sample. The second quarter samples I were analyzed in addition for stmntium-89 and strontium-90. l
~
Potassium-40 was measured in one sample with a concentration of 118 pCi/ liter. All other j gamma emitters were below the detection level. No detections of strontium-89 or l strontium-90 occurred. Tridum was measured in all four samples with an average level of l 2400 pCi/ liter and a range of 1800 to 3100 pCi/ liter. This is lower than the the average ; level measured in 1993 of 2750 pCi/ liter and a range of 1700 to 4000 pCi/ liter. No river l water samples were collected during the preoperational period. }
- i
- 3. Surface Water -i i
Samples of surface water were collected monthly from two stations. Stanon 08 is at the '] discharge lagoon,1.1 miles,148 degrees SSE on Lake Anna. Station 09A is located 12.9 I miles WNW. He samples were analyzed for iodine-131 by radiochemical separation. No iodine was detected in the 24 samples analyzed. The results are presented in Table B-8. The samples were also analyzed by gamma ray spectrometry. Naturally occurring 45
l I TRENDING CRAPH - 3: TRITIUM IN SURFACE WATER - STA 08 ,_.s 10000
. l l
.o f . .... __ ______ . ______________ _e E
1
- S '
. 1000 -
B g - I I
~
l ___ _ _ _ _ _ _ _________A 100 - ,,,1,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, 1 4/77 4/78 4/79 4/80 4/81 4/82 4/83 4/84 4/85 4/86 4/87 4/88 4/89 4/90 4/91 4/92 4/93 4/94
--G -- Tritum .+- Required LLD's _A Average Pre-op Unit 1 critical on 06/06/78. Unit 2 critical on 12/14/80.
G V TRENDING GRAPH -4: COBALT-58 IN SEDNENT SILT 1000
@ 100 -
k 5 E : . - l E 10-^
't
$ l R :
1 ,, , . , . , , , , , . , , , , , , , , 03'85 03'8G 04/87 03'88 04'89 0390 0391 0392 0393 1093 O&94
-5_ Ctaton-8 Gtaton-09 Control Sta-09A -+- Staton-11 O During the preoperational period, cobalt-58 was not detected in the samples analyzed.
46
R h
.. . . i potassium-40 was measured in one sample'with a concentration of 57.0 pCi/ liter. All other - i gamma emitters were below their detection levels at both station.
A quarterly composite from each station was prepared and analyzed for tritium. The tritium W activity at station 08 for the quarterly composites was at an average level of 2850 pCi/ liter - !
. with a range of 1800 to 3300 pCi/ liter. The tritium level had been increasing since the - j middle of 1978 when the average level was below 300 pCi/ liter. However, during IN94 !
the results were within the same range as those measused in 1986 thru 1993. During the q picoperational period tritium was measured in several samples with concentrations between , 90 and 250 pCi/ liter. Tritium was not detected at station 09A. ~ { Samples of surface water were collected by the Commonwealth of Virginia from two l stations. Station W-33 is located at the discharge lagoon while station W-27 is located on f 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. The results ase' j presented in Table B-9. All gamma emitters were below their detection levels. j Four samples from each station were analyzed for tritium'during 1994. The average ! activity at station W-33 in all samples was 2600 pCi/ liter with a range of 1500 to 3500 ] pCi/ liter. This is lower than the 2850 pCi/ liter measured during 1993 at this station. 1 Tritium was measuied in two samples at station W-27 with an average activity of 1510 ) pCi/ liter and a range of 1500 to 1520 pCi/ liter. This is slightly higher than the average of ; 1200 pCi/ liter measured at station W-27 during 1993. ) C. Aquatic Exposure Pathway
- 1. Sediment / Silt 1
Sediment samples were collected during March and August from each of thiee locations ! and were analyzed by gamma spectrometry. The results are presented in Table B-10._ One man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in three samples with an average activity of 69.9 pCi/kg (dry weight) and a range from 47.4.to 108 pCi/kg (dry weight). The highest acading for cesium-137 was obtained from station 08 located 1.10 miles SSE. Naturally occurring potassium-40 was observed in all six samples with an average activity of 12120 pCi/kg (dry weight) and a range from 1610 to 20600 pCi/kg (dry weight), j ( -- Radium-226 was measured in three samples with an average concentration of 1773 pCi/kg l l 47
.__ _ _ . . __ _ _ _ _ _ _ 2 .i
l l l TRENDING CRAPH - 5: CO.TALT-60 IN SEDNENT SILT 1000; (3 V - l E 100- l E 3.
! ^
0 A^ 0 0 0 1 a-4- i
~
E / o 10- ~ 4 3 1 . . . . . . . . . . . . i . . . i . . . 03'85 03'80 03'87 03'88 04'89 03'90 03'91 03'92 0393 10'93 OS94
-a- Station-8 Station-09 -i- Control-Sta-09A -+- Station-11 During the preoperational period, cobalt-00 was not detected in the samples analyzed.
O TRENDING GRAPH - 6: CESIUM-134 IN SEDNENT SILT 1000 i a i 100 - k*3 g
- u:- .- -
L - N 'o-0" - 1 1 . . . . . . . . . . . . . . . . . . . . 03'85 03'8G 03'87 03'88 04'89 0390 0391 0392 03'93 1G'93 OS94
- Staton 8 --o- Staton-09 Control-Sta-09A -+-- Staton-11 -+-- Required LLD's O During the preoperational period, cesium-134 was not detected in the samples analyzed.
48
1 1 TRENDING GRAPH -7: CESIUM-137 IN SEDNENT SILT 10000. O : V : i 1000 3
+-
_ _ _ _ _ -4 4 k 100; , Z ' 3 E, " _e a M k 1 i i i i i i i i i e i i i i i i i i i i 3/85 3/8G 3/87 3/88 3/89 3/90 3/91 3,92 3,93 1G'93 8/94
-m-- Station-8 ,
Control-Sta-09A --A Average Pre-Op
--+ - Station-09 --+-- Station-11 _+ Required LLD's
(~~ TRENDING GRAPH -8: CESIUM-134 IN FISH 1000_ b 4._ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ - , 100 - E 5 ; e : ,s s -
\ l:
0 - P4-5_5-71
$ 10-
't 1 a I K : l q
1 i i i i i i i i i i i i i i i i i . . . i i i i i i i i i i i i 4/80 4/82 4/84 4/85 4/8G 12'8G 8/87 12/87 C/8812/88 G/891G'891G901G'9110921093 8/94
--5_- Staton-08 -_4- Staton-09 Control-Gta-25 -+ Required LLD's b During the preoperational period, cesium-134 was not detected in the samples analyzed.
Station 25 replaced station 09. 49
I 1
- - (dry weight) and a range of 1350 to 2230 pCi/kg (dry weight). Also naturally occurring. .
' thorium-228 was observed in all six samples with an average concentration of 760 pCi/kg (dry weight) and a range of 182 to 1360 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 period sediment samples wem analyzed by gamma ray. spectroscopy. Cesium-137 was measured in'most of the samples with concentrations : between 33 and 1210 pCi/kg (dry weight).1 Strontium-90 was measured in most of the. samples with concentrations between 60 and 540 pCi/kg (dry weight). - Strontium-89 was not measured. Potassium-40, radium-226, and thorium-228, all naturally occurring, were - measumd at backgmund levels. l
- 2. Shomline 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 msults are presented in Table B-11. The naturally occurring nuclide potassium-40 was measured in both samples with an average activity of 2280 pCi/kg (dry weight) and a range of 1820 to 2740 pCi/kg (dry weight). Thorium-228 was measumd in both samples at an average of 456 pCi/kg (dry weight) and a range of 304 to 608 pCi/kg (dry weight). Radium-226 was measured in one sample with an activity of 923 pCi/kg
~
(dry weight). Cesium-137, a fission product, was monitored in both samples with an average level of 134 pCi/kg (diy weight) and a range of 104 to 163 pCi/kg (dry weight). The September sample was analyzed for strontium and there were no detections of . strontium-89 or strontium-90.
' D. Ingestion Exposure Pathway
- 1. Milk The results of the iodine-131 analysis of mill. samples are presented in Table B-12. A -
sample was collected monthly from two stations. A total of 24 samples were analyzed during 1994. There were no measurements of iodine-131 above the detection limits. The milk samples wem also analyzed by gamma ray spectroscopy and the results are also O presented in Table B-12. A total of 24 samples were analyzed. Naturally occurring 50
i potassium-40 was measured in all samples with an average of 1332 pCi/ liter and a range of O U 1160 to 1510 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 1994. All other gamma emitters were below their detection levels. A ' quarterly composite was pmpamd from each of the two collection stations and analyzed for strontium-89 and stmntium-90. Strontium-89 was not detected at levels above LLD in any . of the samples monitomd. Strontium-90 was detected in the eight samples monitored with an average level of 1.83 pCi/ liter and a range of 1.1 to 2.9 pCi/ liter. This is similar to activities determined in pmvious 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 i during 1994. These samples wem analyzed by gamma ray spectroscopy and the naturally O occurrias isotore potassi== s to ad ia ti s = vies at a ver se or 1855 eci/*s (wet weight) with a range of 1550 to 2380 pCi/kg (wet weight). The fission product cesium-137 was measured in four samples at an average of 51.0 pCi/kg (wet weight) and a range ! of 43.1 to 68.3 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). All other gamma emitters wem below their detection levels.
- 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 j was monitored in 34 of the 35 samples with an average activity level of 18372 pCi/kg (wet weight) and a range of 5090 to 41800 pCi/kg (wet weight). Cosmogenic beryllium-7 was detected in 34 of the 35 samples with an average concentration of 2069 pCi/kg (wet weight) and a range of 175 to 5730 pCi/kg (wet weight).~ Radium was measured in one sample with an activity of 1170 (wet weight). The termstrial nuclide thorium-228 was detected in two samples at an average activity of 200 pCi/kg (wet weight) and a range of 184 to 215 pCi/kg (wet weight).
51
TRENDING CRAPH - 9: CESIUM-137 IN F3H 10000 0 : 1000. n . g .- g n 100:
,__ ________V__ ,
_ _ _ _ _ _ _ _ _ _ _ , l k ~ g _ m.
* \
/ A . ,# ,
/
CD S i i 10; ./ 2 5/80 5/83 4/85 8/86 7/87 4/88 12/88 10/89 10/90 10/91 4/03 8/94 1
--E- Station-08 --#-- Station-09 Station-25 --A Average Pre-op -, Required LLD l Staton 25 replaced staton 09. l O TRENDING GRAPH - 10: ENVIRONMENTAL RADIATON -TLD's 10
- l A_ _ _ _ _ _ _ _ _ _ _ _ _ _
t*:, W e _ 2 t -
$ ~
Ni G 8 2 m M 1 E . . i i .. iiiiiie i i i i iiiie i e i e i i i i e i ii 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 1/94 7/94 4 e l E ' _-5-_ Environmental TLD's Sector TLD's --A Average Pre-op l O 52
The fission product cesium-134 was not detected at levels above LLD during 1994. O Cesium-137 was detecied in isve sampies with an average concentration of lio pCi/kg (wet weight) and a range of 47.8 to 277 pCi/kg (wet weight). These results are consistent with those measured in previous years. Cesium-137 was measured in broadleaf garden vegetadon 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 am pmsented in Table B-15. Individual measurements of extemal radiadon levels in the environs of the North Anna site had an average dose of 5.5 mR/ standard month with a range of 3.3 to 7.9 mR/ standard month. This is comparable to the preoperadonal range.
The control station, No. 24, had an average reading of 4.6 mR/ standard month with a range of 3.8 to 5.7 mR/ standard month. Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North O inna site. rwe aadges are piaced at each iocation. The resuits am pmsented in Tesie 8
- 16. The average level of the 32 locations (two badges at each location) was 5.9 mR/ standard month with a range of 3.0 to 9.8 mR/ standard month. The eight control
'ILDs, collected quarterly from four locations, showed an average reading of 4.8 mR/ standard month with a range of 3.3 to 7.2 mR/ standard month. During the preoperational period (stardng in 1977), when the calculation of the TLD dose included a correction for the in-transit dose, the doses were measured between 4.3 and 8.8 mR/ standard month.
O 53
b 6 O 9 I i I F P O vi. couctusions t i l 1 I l i 1 1 4 0 ! i I i l I
o VI. Conclusions U The results of the 1994 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 gross beta concentrations of all the indicator locations for 1994 followed the gross beta concentrations at the control location. The gross beta concentrations wem comparable to levels observed since 1982 except for a five week period in 1986 which was influenced by the Chernobyl accident. Gross beta concentrations in the preoperadonal period wem aighly variable, ranging from 0.0043 to 0.75 pCi/ cum, due to occasional atmospheric nuclear weapons tests. Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). There were no detections above the LLD for fission products nor other man-made isotopes in the particulate media during 1994. Iodine-131 was not detected in the 624 charcoal filters analyzed during 1994. A precipitation sample was collected monthly during 1994 and analyzed for gross beta (] activity. All the gross beta activities wem comparable to those measured in pmvious 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 1994. During the pmoperational period the average tritium activity was 165 pCi/ liter. Waterborne Exposure Pathway i No man-made or natural isotopes were monitored in the surface water af Lake Anna except tritium. The average tritium activity during 1994 at the waste heat treatment facility was 2850 pCi/ liter which is 14.0% of the mporting level for a water sample. In 1993 the tritium level was 2400 pCi/ liter. 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 measurement of 2237 pCi/ liter as compared to 2300 pCiditer for 1993. The upstream location had two measurements at an average of 1510 l pCi/li% as compamd to 1200 pCi/ liter for 1993. No gamma emitting isotopes were detected. E4
i i i I (3 V River water collected from the North Anna River,5.8 miles downstream of the site had an average tritium level of 2400 pCi/ liter. The average tritium in 1993 had been 2750 pCi/ liter. One measurement of naturally occurring potassium-40 was detectted. Ground water from the environmental well on site contained no gamma emitters. There wem also no detections of tritium in ground /well water during 1994. Aquatic Pathway Sediment / silt samples provide a sensitive indicator of discharges from nuclear power stations. The sediment from North Anna environmental samples indicated that one man-made isotope was present. Cesium-137 was detecad in three samples at two locations. During the preoperational period, cesium-137 was measured in samples of aquatic sediment. Sediment contamination does not provide a direct dose pathway to man. The samples of shomline soil monitored downstream of the site contained no measurement of cesium-134. Cesium-137 was measured in both samples at an average level of 134 pCi/kg which was lower than the average of 662 pCi/kg detected in 1993. Ingestion Pathway Iodine-131 was not detected in any of the twenty-four milk samples using the radiochemical separation method. Although cesium-13' Nas been detected occasionally in previous years and attributed to past atmospheric nuclear weapo..s testing there were no detections during 1994. Strontium-90 was measumd in all eight milk samples. Strontium-90 is attributed to past atmospheric nuclear weapons testing. No strontium-89 was detected in any of the milk samples. Naturally occurring potassium-40 was measured in all the milk samples at normal environmental levels. Activity in fish and vegetation samples along with milk does pmsent a dimet dose pathway to man. Fish samples during 1994 showed the pmsence 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 1993. Only cesium-137 was measured in preoperational envimnmental 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. Repairs to the steam generators and better liquid waste processing have reduced these activity 55
c . . . . . .. . . - .- . .- - . - - - . . i levels in effluents and thus decreased activity levels are now being observed in the fish. The. 10 avmge ievei of -dvay in 19;4 of cesium-m -s 3.0.uihe repordng icvel. 1 Vegeiation samples contained the man-made isotope cesium-137. The cesium-137 activity levels during 1994 and in pmoperational samples were statistically similar to the 1993 levet l Direct Exposure Pathway : The direct exposum pathway as measured in the environment of the North Anna site by l 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 j whole body dose due to natural terrestrial and cosmic radiadon and the internal dose from natural 1 radionuclides. t Program Conclusions l The msults were as expected for normal environmental samples. Naturally occurring f activity was observed in sample media in the expected activity ranges. Occasional samples of ! O nearly all media showed the presence of man-made isotopes. These have been discussed f individually in the text. Observed activities were at very low concentrations and had no significant j dose consequence. ; As a method of referencing the measured radionuclide concentrations in sample media to ! the dose consequence, the data may be compar,:J to the Reporting Level Concentrations listed in l 1 the Offsite Dose Calculation Manual. 'Ihese concentrations am based upon 25% of the annual dose , commitment recommended by 10CFR50, Appendix I, to meet the criterion "As Low as is l Reasonably Achievable." Based upon the evidence of the environmental monitoring program the l station is operating within regulatory limits. Thus, no unusual radiological characteristics were j observed in the environs of the Nonh Anna Nuclear Power Station during 1994. ! i I O ; l l 56 1 l
f O 1 I e i O vii. aerenesces l l l i O
i VII. References a .- .
- 1. Virginia Electric and Power Company, Nonh Anna Power Station Technical i'
. Specifications, Units 1 and 2.
- 2. Virginia Electric and Power Company, Station Administrative Procedum, VPAP-2103, "Offsite Dose Calculation Manual. !
- 3. Title 10 Code of Federal Regulation, Part 50 (10CFR50), " Domestic Licensing of L Production and Utilization Facilities." j
- 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.
j
- 6. USNRC Branch Technical Position, " Acceptable Radiological Environmental Monitoring j Program," Rev.1, November 1979. ;
- 7. NUREG 0472, " Radiological Effluent Technical Specifications for PWRs," Rev. 3,
. March 1982. ,
- 8. National Council on Radiadon Protection and Measurements, Report No. 39, " Basic-Radiati n Pr tecu n Criteria," Washington, D.C., January 1971.
O: .{
- 9. National Council on Radiadon Protection and Measumments, Report No. 45, " Natural' .!
Background Radiation in the United States," Washington, D.C., November 1975.
'l
- 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, !
- 11. National Council on Radiation Protecdon and Measurements, Repon No. 95, " Radiation - !
Exposure of the U.S. Population from Consumer Products and Miscellaneous Soumes," ! Washington, D.C., December 1987. l
- 12. DOE /NE-0072, " Nuclear Energy and Electricity, The Harnessed Atom," US Dept. of l Energy,1986. :
- 13. Eichholz, G., " Environmental Aspects of Nuclear Power," Iewis Publishers, Inc.,1985. l
- 14. Eisenbud, M., " Environmental Radioactivity," Academy Press, Inc., Orlando, F1,1987. ,
- 15. Fitzgibbon, W., " Energy Skill Builders, Nuclear Reactor," Enterprise for Educadon, Inc., [
1987. !
- 16. Glasstone, S., and Jordan, W., " Nuclear Power and its Environmental Effects," American !
Nuclear Society,1982. I i O l I i i 57 j i
.O ; !
f i i t I i i i i L I i APPENDIX A ! RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l ANNUAL
SUMMARY
TABLES - 1994 i l 1 i i i I I l I i O
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1994 1 Docket No. 50-338/339 Page 1 of 6 i AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Weasure-(Unit) Type No. Range Direction Range Range monts Airlodine 1-131 624 0.04 -(0/572) N/A N/A -(0/52) 0 (pCi/m3) . . Airborne Gross 624 5 18.8(572-572) 24 22.0 mi NW 20.4(52/52) 20.4(52/52) O Particulates Beta (9.3-78) (13-33) (13-33) (IE-03 pCi/m3) Gamma 48 Be-7 48 10 89.1(44/44) 04 5.1 miWNW 102(4/4) 96.8(4/4) 0 (64.4-151) (75.2-151) (83.5-117) K-40 48 10 12.5(8/44) 03 7.1 miWSW 28.9(1/4) 6.36(1/4) 0 (3.69-28.9) O Sr-8e 12 3 .<0/11) N/A N/A -<0/i > 0 Sr-90 12 0.4 -(0/11) N/A N/A -(0/1) 0 Ground Gamma 4 Well , Water K-40 4 60 -(0/4) N/A N/A -(0/0) 0 (pCi/ liter) - - Tritium 4 2000 -(0/4) N/A N/A -(0/0) O Sr-89 1 -(0/1) N/A N/A -(0/0) 0 Sr-90 1 0.4 -(0/1) N/A N/A -(0/0) 0 l' 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
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 1994 Docket No. 50-338/339 Page 2 of 6 i l All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range monts River Gamma 12 Water (pCi/ liter) K-40 12 200 118(1/12) 11 5.8 mi SSE 118(1/12) -(0/0) 0 Tritium 4 2000 2400(4/4) 11 5.8 mi.SSE 2400(4/4) -(0/0) 0 (1800-3100) (1800-3100) - i Sr-89 1 3 -(0/1) MA N/A -(0/0) O Sr-90 1 0.4 -(0/1) MA N/A -(0/0) 0
~ ~
0 Precipitation Monthly (pCi/ liter) Gross 12 4 3.93(12/12) 01 A 0.2 mi. 3.93(12/12) -(0/0) O Beta (2.3-13) PE (2.3-13) - Gamma 2 , (Semi-Annually) j Be-7 2 70 -(0/2) MA N/A -(Q/0) 0 Tritium 2 2000 -(0/2) N/A MA -(0/0) 0 i i Surface 1-131 24 0.5 -(0/12) MA N/A -(0/12) 0 WMu - - (pCi/ liter) Regular Gamma 24 Monthlies K-40 24 200 57.0(1/12) 08 1.10 mi 57.0(1/12) -(0/12) 0 SSE - - Tritium 8 2000 2850(4/4) 08 1.10 mi 2400(4/4) -(0/4) 0
) (1800-3300) SSE (1900-3300) -
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
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
o) t North Anna Nuclear Power Station, Louisa County, Virginia - 1994 Docket No. 50-33&339 Page 3 of 6 i AllIndicator Control Non- l Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range monts Surface St-89 1 -(0/1) N/A N/A -(0/1) 0 WMu - (pCi/ liter) Regular Sr-90 1 -(0/1) N/A N/A -(Oh) O Monthlies - - Surface Gamma 24 Water (pCi/ liter) K-40 24 200 -(0/24) N/A N/A -(0/0) O State Splits - - Tritium 8 2000 2237(6/8) W33 2600(4/4) -(0/0) 0 (1500-3500) (1500-3500) - Sediment Gamma 6 Sitt ! (pCi/kg K 40 6 200 11955(4/4) 11 5.8 mi 19900(2/2) 12450(2/2) 0 l (dry)) (1610-20600) SSE (19200-20600) (12400-12500) Cs-137 6 194 69.9(3/4) 08 1.10 mi 77.7(2/2) -(0/2) 0 (47.4 108) SSE (47.4-108) - ; Ra-226 6 100 1985(2/4) 11 5.8 mi 1985(2/2) 1350(1/2) 0 l (1740-2230) SSE (1740-2230) - l Th-228 6 30 821(4/4) 11 5.8 mi. 1230(2/2) G40(2/2) 0 , (182-1360) SSE (1100-1360) (471-808) Sr-89 3 4.0 -(Q/2) N/A N/A -(0/1) 0 (Annually) - - Sr-90 3 0.8 -(Or2) N/A N/A -(0/1) 0 (Annually) - - 0 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
o RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sl:CMARY d North Anna Nuclear Power Station, Louisa County, Virginia - 1994 l Docket No. 50-338/339 Page 4 of 6 AllIndicator Control Non-Medium or AN/Alysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range rnents Shoreline Gamma 2 Soil (pCi/kg K-40 2 200 2280(2/2) 9 2.2 mi. NW 2280(2/2) -(0/0) 0 (dry)) (1820-2740) (1820-2740) - Cs-137 2 40 134(2/2) 9 2.2 mi. NW 134(2/2) -(0/0) 0 (104-163) (104-163) Ra-226 2 100 923(1/2) 9 2.2 mi. NW 923(1/2) -(Q/0) 0 Th-228 2 30 456(2/2) 9 2.2 mi. NW 456(2/2) -(0/0) 0 ' (304-608) (304-608) - Sr 89 1 4.0 -(0/2) N/A N/A -(0/0) 0 (Annually) - - Sr-90 1 0.8 -(0/2) N/A N/A -(0/0) 0 (Annually) - - Milk l-131 24 0.5 -(0/24) N/A N/A -(0/0) 0 (pCi/ liter) - - Gamma 24 K-40 24 100 1332(24/24) 12 8.3 mi. NW 1381(12/12) -(0/0) 0 (1160-1510 (1260-1510) Sr 89 8 5 -(0/8) N/A N/A -(0/0) 0 (Quarterly) - - Sr-90 8 0.8 1.83(8/8) 13 5.60 mi. SSW 2.15(4/4) -(0/0) 0 (Quarterty) (1.1-2.9) (1.6-2.9) - r 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. I 61
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1994 Docket No. 50-338/339 Page 5 of 6 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean h4easure. (Unit) Type No. Range Direction Range Range monts Fish Gamma 8 , PCi/kg (wet) K-40 8 200 1835(4/4) 25 16.5 mi. NW 1875(4/4) 1875(4/4) 0 (1570-2320) (1550-2380) (1550-2380) Cs-137 8 40 51.0(4/4) 08 1.10 mi. SSE 51.0(4/4) -(0/4) 0 (43.1 68.3) (43.1-68.3) - Food Gamma 35 Vegetation Dose (pCi/kg Be-7 35 - 2069(34/35) 16 12.6 mi 2370(7/7) -(0/0) 0 (wet)) (175-5730) NW (305-5730) - K-40 35 - 18372(34/35) 23 0.93 mi. 24686(7/7) -(0/0) 0 Q (5090-41800) SSE (12800-41800) - Cs-137 35 80 110(5/35) 21 1.00 mi. 150(3/7) -(0/0) 0 (47.8-277) WNW (78.8-277) - Ra-226 35 - 1170(1/35) 21 1.00 mi. 1170(1/7) -(0/0) 0 WNW - Th-228 35 - 200(2/35) 23 0.93 mi 215(1/7) -(0/0) 0 (184-215) SSE - - O i 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. 62
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 1994 Docket No. 50-338/339 Page 6 of 6 1 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine ! Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range monts Direct Gamma 48 02 5.55(44/44) 01 0.2 mi. NE 7.50(4/4) 4.55(4/4) 0 Radiation Dose (3.3-7.9) (7.1 7.9) (3.8-5.7) (mR/std. month) c (Regular TLDs) Direct Gamma 12 0.2 5.10(11/11) 01 0.2 mi. NE 7.0(1/1) 3.8(1/1) 0 Radiation Dose (3.9-7.0) - - (mR/std. Month) (Annual TLDs) Direct Gamma 287 0.2 6.06(255/255) 21/53 0.30 mi. 8.33(8/8) 4.78(32/32) 0 Radiation Dose (3.0-9.8) SW (7.8-9.5) (3.3-7.2) O (mR/std. Month) (Sector TLDs) . 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. 63
*-A, m O
I O APPENDIX B DATA TABLES
)
0 1
i TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR d North Anna Power Station, Louisa County, Virginia - 1994 pCl/m312 Sigma Page 1 of 2 Collection STATIONS [ Date 01 02 03 04 05 OSA 06 07 21 22 23 24 ! JANUARY 1 12/29-01/05 <.02 <.02 <.02 <.03 < .L1 <.02 <.02 <.02 <.03 <.02 <.009 <.02 [ 01/05-01/12 <.02 <.02 <.02 <.02 <.008 <.02 <.02 <.02 <.02 <.01 <.008 <.01 ! 01/12-01/19 <.02 <.02 <.02 < .OR <.01 <.02 <.02 <.02 <.02 <.02 <.009 <.008 ! 01/19-01/26 <.02 <.02 <.02 <.02 <.01 <.01 <.01 <.01 <.01 <.009 <.02 <.01 t 01/26-02/02 <.03 <.02 <.02 <.02 < .0 i <.01 <.01 <.01 <.01 <.009 <.02 <.01 ; FEBRUARY ; 02/02-02/09 <.02 <.02 <.02 <.02 <.01 <.03 <.03 <.03 <.03 <.02 <.02 < .01 02/09-02/16 <.03 <.03 <.02 <.02 <.02 <.02 < .06(a) <.02 <.03 <.01 <.03 <.01 ! 02/16-02/23 c .02 <.02 <.02 <.02 <.009 <.02 <.02 <.02 <.02 <.01 <.02 <.02 ! 02/23-03/02 <.02 <.02 <.02 <.02 <.01 <.01 <.01 <.01 <.01 <.009 <.03 <.02 l MARCH 03/02-03/09 <.02 <.02 <.02 <.02 <.01 <.02 <.02 <.02 <.02 <.01 <.01 <.009 03/09-03/16 <.02 <.02 <.02 <.02 <.01 <.02 <.02 <.02 <.02 <.01 <.02 <.01
% 03/16-03/24 <.02 <.02 <.02 <.02 <.009 <.02 <.02 <.02 <.02 <.01 <.02 <.01 s 03/24-03/30 <.05 <.06 <.05 <.05 < .03 < .03 < .04 < .04 < .04 <.02 < .02 < .03 APRIL 03/30-04/06 <.01 <.01 <.01 <.01 <.009 <.02 <.02 <.02 <.02 <.01 <.01 <.01 04/06-04/13 <.02 <.02 <.02 <.02 <.009 <.02 <.02 <.02 <.02 <.01 <.02 <.02 04/13-04/20 <.02 <.02 <.02 <.02 <.009 <.02 <.02 <.02 <.02 <.01 <.02 <.02 04/20-04/27 <.01 <.01 <.01 <.01 <.008 <.02 <.02 <.02 <.02 <.01 <.009 <.02 04/27-05/04 <.02 <.02 <.02 <.02 <.01 <.02 <.02 <.02 <.02 <.01 <.03 <.03 MM 05/04-05/12 <.02 <.02 <.02 <.02 <.01 <.009 <.009 <.009 <.009 <.007 <.01 <.008 05/12-05/18 <.02 <.02 <.02 <.02 <.009 <.02 <.02 <.02 <.02 <.01 <.02 <.02 05/18-05/25 <.01 <.01 <.01 <.01 <.01 <.04 <.04 <.04 <.04 <.03 <.02 <.01 05/25-06/01 <.02 <.02 <.02 <.02 <.01 <.02 <.02 <.02 <.02 <.009 <.01 <.01 .
JUNE 06/01-06/08 <.02 <.02 <.02 <.02 <.02 <.02 <.02 <.02 <.02 <.01 <.02 <.02 06/08-06/15 <.02 <.02 <.02 <.02 <.01 <.02 <.02 <.02 <.02 <.01 <.02 <.02 06/15-06/23 <.02 <.02 < .02 <.02 <.01 <.02 <.02 <.02 <.02 <.01 <.02 <.01 ' 06/23-06/29 <.03 < .04 (a) < .03 <.03 <.01 <.02 <.02 <.02 <.02 <.01 <.008 <.01 fh a 1 (a) Low sample volume. 64
i TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR V North Anna Power Station, Louisa County, Virginia - 1994 pCi/m3 12 Sigma Page 2 of 2 ; Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JULY 06/29-07/06 <.01 <.01 <.01 <.01 <.008 <.02 <.02 <.02 <.02 <.007 <.01 <.01 07/06-07/13 <.02 <.02 <.02 <.02 <.01 <.02 <.02 <.02 <.02 <.01 <.02 <.02 07/13-07/20 <.01 <.01 <.01 <.01 <.005 <.01 <.01 <.01 <.01 <.008 <.01 <.01 07/20-07/27 <.01 <.02 <.01 <.01 <.007 <.02 <.01 <.01 <.01 <.009 <.02 <.02 07/27-08/03 <.02 <.02 <.02 <.02 <.01 <.02 <.02 <.02 <.02 <.02 <.02 <.02 AtrauSI 08/03-08/10 <.02 <.02 <.02 <.02 <.007 <.01 <.01 <.01 <.01 <.009 <.02 <.02 7 08/10-08/17 <.02 <.02 <.02 <.02 <.008 <.02 <.02 <.02 <.02 <.01 <.02 <.02 08/17-08/24 <.01 <.01 <.01 <.01 <.006 <.01 <.01 <.01 <.01 <.008 <.02 <.02 08/24-08/31 <.02 <.02 <.02 <.02 <.009 <.01 <.01 <.01 <.01 <.009 <.02 <.02 SEPTEMBER 08/31-09/07 <.02 <.02 <.02 <.02 <.007 <.01 <.01 <.01 <.01 <.009 <.02 <.02 A 09/07-09/14 <.02 <.02 <.02 <.02 <.008 <.02 <.02 <.02 <.02 <.01 <.01 <.009 U 09/14-09/21 <.02 <.02 <.02
<.02
<.02 <.008 <.02
<.02
<.02
<.02
<.02 <.02 <.01 <.01 <.009 09/21-09/28 <.02 <.02 <.02 <.009 <.02 <.02 <.01 <.01 <.01 QQTOBER 09/28-10/05 <.01 <.01 <.01 <.01 <.006 <.01 <.01 <.01 <.01 <.008 <.02 <.02 10/05-10/12 <.01 <.01 <.01 <.01 <.006 <.01 <.01 <.01 <.01 <.008 <.02 <.02 10/12-10/19 <.01 <.01 <.02 <.01 <.007 <.01 <.01 <.01 <.01 <.008 <.02 <.02 10/19-10/26 <.02 <.02 <.02 <.02 <.007 <.02 <.02 <.02 <.02 <.02 <.01 <.01 10/26-11/02 <.006 <.006 <.006 <.006 <.004 <.006 <.006 <.006 <.006 <.005 <.01 <.01 NOVEMBER 11/02-11/09 <.02 <.02 <.02 <.02 <.007 <.01 <.01 <.01 <.01 <.009 <.02 <.02 11/09-11/16 <.01 <.01 <.01 <.01 <.006 <.02 <.02 <.02 <.02 <.01 <.01 <.01 11/16-11/23 <.03 <.03 <.03 <.03 <.01 <.02 <.02 <.02 <.02 <.02 <.03 <.03 11/23-11/30 <.02 <.02 <.02 <.02 <.007 <.01 <.01 <.01 <.01 <.009 <.02 <.02 DECEMBER 11/30-12/07 <.01 <.01 <.01 <.01 <.007 <.01 <.01 <.01 <.01 <.009 <.01 <.01 12/07-12/14 <.02 <.02 <.02 <.02 <.007 <.01 <.01 <.01 <.01 <.009 <.01 <.008 12/14-12/21 <.02 <.02 <.02 <.02 <.007 <.01 <.01 <.01 <.01 <.009 <.02 <.02 12/21-12/28 <.02 <.02 <.02 <.02 <.008 <.02 <.02 <.02 <.02 <.01 <.01 <.009 O
65
TABLE B-2 (Page I of 4) NOR111 ANNA-1994 CONCENTRATIONS OFGROSS BETA IN AIR PARTICULAlliS 1.9E-03 pC1/m3 12 Sigpna COLLECTION 1994 AVERAGE DATE 01 02 03 04 05 95A 96 97 '21 22 23 24 i 2 s.d. _lANUARY 12/294)lA)5 201 2 191 2 191 2 201 2 171 2 151 2 161 2 16i 2 17i 2 13 i 2 15 i 2 20i 2 17 i 5 01/05-01/12 201 2 1512 201 2 201 2 141 2 181 2 12i 2 17 i 2 181 2 1712 17i 2 191 2 17 1 5 01/12-01/19 181 2 181 2 181 2 201 2 181 2 161 2 18i 2 161 2 191 2 171 2 18i 2 14 i 2 181 3 01/19-01/26 251 2 2212 211 2 23 i 2 241 2 2512 27i 2 27i 2 25 i 2 171 2 211 2 26i 2 -24 1 6 01/26-02A)2 161 2 141 2 17i 2 181 2 161 2 15 i 2 17i 2 131 2 1412 13 i 2 15i 2 171 2 15 1 3 FEBRUARY 02/02-02/09 22i 2 261 2 33i 2 28 i 2 261 2 26i 2 19 i 2 241 2 23 i 2 23i 2 261 2 271 2 251 7 02/09-02/16 14 i 2 161 2 191 2 15 i 2 131 2 14 i 2 20i 4 (a) 141 2 15 i 2 14 i 2 1712 1512 16 i 4 02/16-02/23 191 2 181 2 181 2 171 2 181 2 17i 2 16 i 2 14i 2 1412 131 2- 14i 2 18i 2 161 4 02/23-03A)2 13i 2 171 2 171 2 161 2 141 2 1412 1512 161 2 14i 2 121 2 16i 2 141 2 151 3 MARCH 03/32-03/09 141 2 12i 2 171 2 17i 2 17 i 2 131 2 14i 2 171 2 15 i 2 15 1'2 16 i 2 15 i 2 15 i 3 03A)9-03/16 161 2 16i 2 18 i 2 19i 2 141 2 161 2 1512 161 2 16 i 2 15 i 2 1512 16i 2 16 1 3 03/16-03/24 1512 12i 2 12i 2 15i 2 121 2 14i 2 9.911.5 141 2 101 2 '13 i 2 131 2 18i 2 131 5 03/24-03/30 1412 131 2 12i 2 141 2 12i 2 15 i 2 14i 2 12i 2 13i 2 9.3 i 1.5 14 i 2 1512 13i 3 Average 17 i 7 17 i 8 19118 19 i 8 17 i 9 17 i 8 16 i 8 17 i 9 16 i 8- 15 i 7 17 i 7 18 i 8 17 1 2 i 2 s.d. (:) low sample volume. . . _ _ . _ . . . . _ . _ __._ _ . _ _ ._,. _ . - _ __~- - , . . . _ . _ - , . . _ - . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _. _ _ . . _ . _ _ . _ _ _ _ . . _ _.-
v ., O O d, t a; r TABLE B-2 (Page 2 of 4)
. NOR111 ANNA - 1994 CONCINIRAT10NS OF GROSS BETA IN AIR PARTICULATI!S i 1.9E.e3 pCl/an 31 2 Seguna e COLLECTION 1994 AVERAGE DATE 01 02 03 84 05 SSA 86 07 21 22 23 24 i 2 ad.
APRIL 03/3044A)6 161 2 19 i 2 17 i 2 22i 2 1712 201 2 161 2 20i 2 19 i 2 17 i 2 - 20 i 2 20 i 2 19 i 4 04A)6-04/13 ;912 15 i 2 17 i 2 15 i 2 15 i 2 1512 141 2 1512 1512 13 i 2 16 i 2 16 i 2' 15 i 3 04/13 4 4/20 18i 2 211 2 181 2 171 2 15 i 2 16i 2 191 2 18i 2 13 2 181 2 131 2 171 2 .171 5 ! 04/20-04/27 231 2 201 2 211 2 231 2 201 2 181 2 17 i 2 211 2 18 i 2 181 2 -19i 2 171 2 20 i 4 ; 04/27-05 S 4 17 i 2 161 2 16i 2 171 2 16 i 2 171 2 16i 2 16i 2 1512 1712 14i 2 161 2 16 i 2 MAI 05 S 4-05/12 171 2 12 i 1 15 i 2 17i 2 12 i 1 15 i 2 Ili 1 14 i 1 131 a 131 1 131 1 16i 2 14 1 4' 05/12 45/18 14 i 2 12 2 12i 2 14 i 2 13i 2 12i 2 12i 2 11 i 2 13i 2 14 i 2 13i 2 14i 2 13i 2 'S 05/18 45/25 191 2 1512 15 i 2 191 2 161 2 131 2 16i 2 14 i 2 14 i 2 13i 2 141 2 161 2 15 i 4
$ 05/25-06A)1 191 2 17i 2 1812 201 2 191 2 191 2 171 2 181 2 17 i 2 1512 181 2 201 2 18 i 3 JUNE 06A)l46A)8 181 2 18i 2 16 i 2 17i 2 12 i 2 18i 2 171 2 17 i 2 14i 2 191 2 181 2 17 i 2 171 4-06/08-06/15 251 2 2112 20 i 2 201 2 22i 2 25 i 2 22i 2 25 i 2 24i 2- 231 2 22i 2 271 2 231 4 06/15-06/23 24i 2 221 2 22i 2 20i 2 19 i 2 221 2 211 2 20i 2 211 2 22i 2 231 2 241 2 221 3 i 06/23-06/29 16i 2 78 i 19(a) 18i 2 18 i 2 17 i 2 18i 2 171 2 191 2 16i 2 17 i 2 Idi 2 191 2 23 i 35 Average 19 i 7 22 i 34 17 i 5 18 i 5 16 i 6 18 i 7 17 i 6 18 i 7 16 i 7 17 i 7 17 i 7 18 i 7 18 t 6 i 2 s.d.
t (a) Results confirmed by recalculation. Iow sample vohune. l _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ . _ . _ _ _ . . . . - . . . . _ - . . , ~ ,........_.......,.~...~m.- , - . - . . , . . , . . . - . . _ , . _ . ~ . _.....m.,._ . . . . , - . _ , _ . - _ , . . ~ . ~ . , , , . , . , . . . . . . .i ,
O O O TABLE B-2 (Page 3 of 4) NORT11 ANNA-1994 CONCDTIRA'IlONS OFGROSS BETAIN AIR PARTICULATES 1.9E-03 pCum 3 i 2 Sigma COLLECTION 1994 AVERAGE DATE 01 92 03 04 95 95A e6 07 21 22 23 24 i 2 s.d.' _IULY 06/29-07/06 201 2 22 i 2 181 2 20i 2 171 2 201 2 201 2 181 2 191 2 21 i 2 22 i 2 21i 2- 201 ~ 3 ' 07/06-07/13 181 2 2213 181 2 171 2 18 i 2 20i 2 17 i 2 22 i 2 16i 2 16 i 2 19 i 2 21i 2 191 4 07/13-07/20 22i 2 14 i 2 181 2 171.2 151 2 171 2 14 i 2 161 2 1512 131 2 161 2 21i 2 17 i 5 07/20 47/27 181 2 181 2 14i 2 171 2 171 2 18i 2 17i 2 201 2 14 i 2 161 2 20 2 13 i 2 17 i 4 07/27 48/03 171 2 12 i 2 141 2 15 i 2 141 2 14 i 2 13i 2 15 i 2 1412 15 i 2 131 2 17 i 2 - 14 1 3 AUGUST 08/03-08/10 18 i 2 19 i 2 191 2 161 2 1812 1912 161 2 13 i 2 17i 2 201 2 20i 2 22 i 2 18 i 5 - 08/1048/17 211 2 201 2 19 i 2 20i 2 19 i 2 201 2 191 2 1912 20 i 2 21i 2 21 i 2 211 2 201 2 08/17 48/24 121 2 141 2 12i2 131 2 131 2 131 2 13 i 2 121 2 13 i 2 12 i 2 15 i 2 161 2 13t 3 08/24-08/31 31i 2 26i 2 231 2 291 2 28i 2 261 2 251 2 27 i 2 23i 2 221 2 32i 2. 311 2 271 7 SEliEMBER 08/31 49/07 21 i 2 20i 2 18i 2 201 2 221 2 201 2 191 2 201 2 221 2 22i 2 20i 2 221 2 21 i 3 09/07-09/14 28i 2 271 2 271 2 23 2 27i 2 241 2 261 2 221 2 2512 26i 2 28i 2 29i 2 26 i 4 09/14-09/21 331 2 331 2 30i 2 32 2 281 2 261 2 301 2 31 i 2 311 2 291 2 34i 2 33i 2 31 i 5 09/21-09/28 191 2 16i 2 1512 16i 2 15 i 2 171 2 14 t 2 14 i 2 16i 2 16 i 2 15 i 2 18i 2 16 i 3 Average 21 i 12 20 i 12 19 i 19 20 i11 19 i 11 29 i 8 19 i 11 19111 19 i l e 19 i l e 21 i 13 22 i 12 20 1 2 i 2 s.d. .-__m--_.-- eu __ mr-.4-__ -= '
*m.- __-m w9~- -- w.- ,=w.w. -- -- v .-w e- c. ,n--m e -a -% - 44_ e - __a.e-y w en -.---e m-ne., ._,w.v ,.er ye iwm---me * =# w ---' . - ww
U fd -Q
. k' J a TABLE B-2 (Page 4 of 4)
NOR111 ANNA-1994 CONCENTRAllONS OF GROSS BETA IN AIR PARTICULATES 1.9E-93 pCl/m3 12 Sigma COLLECTION 1994 AVERAGE-DATE el 92 03 94 05 95A 66 97 21 22 23 24 i 2 s.d. ocroBER 09/28-10 45 20i 2 20 i 2 211 2 21i 2 19i 2 18i 2 17i 2 191 2 20i 2 20 i 2 20 i 2 21i 2 20 1 3 1005-10/12 22i 2 211 2 22i 2 211 2 21i 2 20 i 2 16i 2 221 2 221 2 19i 2 22i 2 231 2 211 4 10/12 10/19 241 2 2512 21 i 2 241 2 26i 2 24 i 2 231 2 211 2 24 i 2 211 2 2412 30i 2 241 5 10/19-10/26 32i 2 231 2 29 i 2 301 2 25i 2 31 i 2 25i 2 271 2 261 2 251 3 2912 32i 2 28 i 6 10/26-1142 141 2 141 2 151 2 15i 2 Ili 2 1412 11i 2 14 i 2 15i 2 13 i 2 121 2 15 i 2 14 i 3 NOVEMBER 11/02-11/09 25i 2 21i 2 181 2 22i 2 221 2 201 2 1912 181 2 20 i 2 19i 2 181 2 231 2 201 4 m 11/09 11/16 241 2 26 i 2 22i 2 231 2 24i 2 291 2 211 2 291 2 24 i 2 281 2 23i 2 27i 2 25 i 5
- 17i 2 17i 2 11/16-11/23 18i 2 191 2 17i 2 181 2 IS i 2 191 2 181 2 17 i 2 16i 2 211 2' 181 3 11/23-11 0 0 201 2 20i 2 191 2 19i 2 191 2 171 2 181 2 161 2 18 i 2 16i 2 161 2 181 2 18 i 3 DECEMBER 11/30-12/07 281 2 241 2 26i 2 261 2 25 i 2 25 i 2 21 i 2 251 2 26i 2 231 2 241 2 271 2 25 1 4 12M712/14 24i 2 22i 2 18i 2 181 2 19 i 2 17 i 2 181 2 191 2 191 2 201 2 211 2 21i 2 20 i 4 12/14-12/21 161 2 19i 2 17i 2 181 2 181 2 1812 171 2 15i 2 18 i 2 191 2' 171 2 171 2 17i 2 12/21-12/28 27i 2 231 2 221 2 25 i 2 24i 2 23i 2 24i 2 22i 2 251 2 22i 2 26i 2 261 2 24 i 3 Quarter Avg. 22 i le 21 i 6 21 i 8 22 i 8 21 i 8 21 1 le 19 i 8 29 i 9 21 i 7 20 i 8 ' 21 i 9 23 i I e 21 i 9 i 2 s.d.
Annual Avg. 20i19 29 i 19 19 i 9 29 i 8 18 i 9 19 i 9 18 i 8 18 i 9 18 i 9 18 i 9 19 1 le 20 i l e 19 i l e i 2 s.d. . _ _ _ - _ _ _ _ _ . _ _ _ _ _ _ - . . . _ _ _ . _ . - - - _ - . . . . . . _ . _ . . - _ . _ . _ ._ ._ _ _ . - . _ - . - - - - - . _ . - . , _ _ . - , . - _ _ . _ . _ - ~ . . - . - ~ _ . _ .
TABLE B-3: GAMMA EMITTER
- STRONTIUM-89, AND STRONTIUM-90 CONCENTRATIONS IN AIR PARTICULATES U North Anna Power Station, Louisa County, Virginia - 1994 1.0 E-03 pCl/m3 2 Sigma Page 1 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/29-03/30 03/3046/29 06/29-0W28 OW28-12/28 i 2 s.d. :
STA-01 Sr-89 (a) < 0.7 (a) (a) - Sr-90 (a) < 0.1 (a) (a) - Be-7 68.3 i 6.8 98.8 i 9.9 90.9 i 9.1 75.7 i 7.6 83.4 i 27.8 K-40 <9 <5 <5 <9 - Co-60 < 0.3 < 0.3 < 0.3 < 0.3 - Ru-103 < 0.3 < 0.3 < 0.2 < 0.3 - Cs-134 < 0.3 < 0.3 < 0.2 < 0.3 - Cs-137 < 0.3 < 0.3 < 0.2 < 0.3 - Th-228 < 0.4 < 0.4 < 0.5 < 0.4 - STA-02 Sr-89 (a) < 0.8 (a) (a) - Sr-90 (a) <.009 (a) (a) - Be-7 119 12 80.4 i 8.0 76.9 i 7.7 73.317.3 87.4 42.5 K-40 <4 <8 <4 <5 - Co-60 < 0.3 < 0.3 < 0.2 < 0.2 - Ru-103 < 0.6 < 0.4 < 0.3 < 0.3 - Cs-134 < 0.2 < 0.3 < 0.3 < 0.3 - Cs-137 < 0.3 < 0.3 < 0.2 < 0.3 - O- Th-228 < 0.4 < 0.4 < 0.5 < 0.5 -
)
STA-03 Sr-89 (a) < 0.7 (a) (a) -
)
Sr-90 (a) < 0.1 (a) (a) - Be-7 119112 91.9 9.2 70.917.1 73.3 i 7.3 88.8 i 44.5 K-40 28.9 i 3.2 <10 <3 <8 28.91 32 Co-60 < 0.3 < 0.3 < 0.3 < 0.3 - < Ru-103 < 0.7 < 0.4 < 0.2 < 0.3 - l Cs-134 < 0.3 < 0.3 < 0.2 < 0.3 - l Cs-137 < 0.2 < 0.3 < 0.2 < 0.3 - ! Th-228 < 0.4 < 0.4 < 0.3 < 0.3 - 1 STA-04 Sr-89 (a) < 0.7 (a) (a) - l Sr-90 (a) < 0.1 (a) (a) - j Be-7 151 115 106 i11 75.2 i 7.5 75.9 i 7.6 102 71 j K-40 <5 <4 <4 < 10 - 4 Co-60 < 0.3 < 0.3 < 0.2 < 0.3 -
< 0.7 1 Ru-103 < 0.3 < 0.2 < 0.3 -
Cs-134 < 0.3 < 0.2 < 0.2 < 0.3 - Cs-137 < 0.3 <02 < 0.2 < 0.3 - Th-228 < 0.5 < 0.4 < 0.3 < 0.4 - O All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed only on second quarter samples. 70 , l
TABLE B-3: GAMMA EMITTER
- STRONTIUM-89, AND STRONTIUM-90
- c. CONCENTRATIONS IN AIR PARTICULATES ,
\ North Anna Power Station, Louisa County, Virginia - 1994 1.0 E-03 pCi/m3 i 2 Sigma Page 2 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/29 03/30 03/3006f29 06/29-OlW28 09/28-12/28 i 2 s.d. STA-OS Sr-89 (a) < 0.7 (a) (a) - Sr-90 (a) < 0.1 (a) (a) - Be-7 114i 11 81.1 i 8.1 67.016.7 76.01 7.6 84.5141.0 , K-40 4.091 2.05 24.413.3 <8 5.031 2.01 11.2122.9 i Co-60 < 0.2 < 0.3 < 0.3 < 0.3 - r Ru-103 < 0.7 < 0.3 < 0.3 < 0.3 - l Cs-134 < 0.2 < 0.3 < 0.2 < 0.2 - Cs-137 < 0.2 < 0.2 < 0.3 < 0.2 - Th-228 < 0.4 < 0.3 < 0.4 < 0.4 - . t STA-06A Sr-09 (a) < 0.7 (a) (a) - Sr 90 (a) <.009 (a) (a) - Be-7 134 i 13 114 i 11 70.517.1 69.617.0 97.01 64.4 K-40 <5 <5 <5 11.512.4 11.5 i 2.4 ; Co-60 < 0.3 < 0.3 < 0.3 < 0.3 - Ru-103 < 0.9 < 0.4 < 0.3 < 0.2 - Cs-134 < 0.4 < 0.3 < 0.2 < 0.2 - Cs-137 < 0.3 < 0.3 < 0.3 < 0.2 - Th-228 < 0.7 < 0.5 < 0.5 < 0.3 - STA-06 Sr-89 (a) < 0.4 (a) (a) - Sr-90 (a) <.008 (a) (a) - Be-7 105 i11 87.8 i 8.8 64.416.4 82.6 i 8.3 85.0133.4 K40 <9 <4 <8 <5 - Co-60 < 0.3 < 0.2 < 0.3 < 0.3 - Ru-103 < 0.9 < 0.3 < 0.3 < 0.3 - Cs-134 < 0.4 < 0.2 < 0.3 < 0.3 - Cs-137 < 0.4 < 0.2 < 0.3 < 0.3 - Th-228 < 0.4 < 0.4 < 0.3 < 0.5 - STA-07 Sr-89 (a) <1 (a) (a) - Sr-90 (a) < 0.1 (a) (a) - Be-7 1171 12 96.319.6 68.9 i 6.9 69.9 i 7.0 88.0 i 46.2 K-40 3.69 1.83 <6 <10 <4 3.69 i 1.83 Co 60 < 0.2 < 0.4 < 0.4 < 0.3 - Ru-103 < 0.7 < 0.4 < 0.4 < 0.3 - Cs-134 < 0.3 < 0.3 < 0.3 < 0.2 - Cs-137 < 0.3 < 0.3 < 0.3 < 0.2 - Th-228 < 0.4 < 0.6 < 0.4 < 0.4 - O All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed only on second quarter samples. , l 71
1 1 TABLE B-3: GAMMA EMITTER
- STRONTIUM-89, AND STRONTIUM-90
, CONCENTRATIONS IN AIR PARTICULATES North Anna Power Station, Louisa County, Virginia - 1994 1.0 E 03 pCi/m3 12 Sigma Page 3 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/29-03/30 03/30 06/29 06/29-09/28 09/28-12/28 1 2 s.d.
STA-21 St-89 (a) < 0.7 (a) (a) - Sr-90 (a) < 0.1 (a) (a) - Be-7 108 1 11 80.318.0 75.5 i 7.5 81.0 i 8.1 86.2129.5 K-40 <5 <9 <4 <6 - Co-60 < 0.2 < 0.3 < 0.2 < 0.2 - Ru-103 < 0.6 < 0.4 < 0.2 < 0.4 - Cs-134 < 0.2 < 0.3 < 0.2 < 0.3 - Cs-137 < 0.3 < 0.3 < 0.2 < 0.3 - Th-228 < 0.3 < 0.4 < 0.4 < 0.6 - STA-22 Sr 89 (a) < 0.8 (a) (a) - Sr-90 (a) <.009 (a) (a) - Be-7 101 110 90.7 i 9.1 64.9 i 6.5 67.1 6.7 80.9 i 35.5 K-40 <10 <5 18.212.9 <9 18.2 i 2.9 Co-60 < 0.3 < 0.3 < 0.3 < 0.3 - Ru-103 < 0.9 < 0.3 < 0.3 < 0.3 - Cs-134 < 0.4 < 0.3 < 0.3 < 0.3 - O Cs-137 Th-228
< 0.3
< 0.5
< 0.3
< 0.4
< 0.3
< 0.3
< 0.3
< 0.4 STA-23 Sr-89 (a) < 0.9 (a) (a) -
Sr-90 (a) < 0.1 (a) (a) - Be-7 122 i 12 M .2 1 9.4 93.2 i 9.3 79.7 i 8.0 97.3135.5 K-40 <6 3.841 1.72 <5 <5 3.84 i 1.72 Co-60 < 0.3 < 0.2 < 0.3 < 0.3 - Ru-103 < 0.8 < 0.3 < 0.3 < 0.3 - Cs-134 < 0.2 < 0.2 < 0.3 < 0.2 - Cs-137 < 0.2 < 0.3 < 0.3 < 0.4 - Th 228 < 0.5 < 0.4 < 0.5 < 0.5 - STA-24 Sr-89 (a) < 0.5 (a) (a) - Sr-90 (a) <.007 (a) (a) - Be-7 1171 12 103110 83.5 i 8.3 83.5 i 8.4 96.8 i 32.7 K-40 6.36 i 2.37 <10 <4 <5 6.3612.37 Co-60 < 0.3 < 0.4 < 0.3 < 0.2 - Ru-103 < 0.8 < 0.4 < 0.2 < 0.2 - Cs-134 < 0.3 < 0.3 < 0.2 < 0.2 - Cs-137 < 0.3 < 0.4 < 0.2 < 0.3 - Th-228 < 0.4 < 0.5 < 0.4 < 0.3 - O All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed only on second quarter samples. 72
TABLEB-4: GROSS BETA, TRITIUM, AND GAMMA EMITTER * & CONCENTRA110NS IN PRECIPITATION Station 01A -(On Site) North Anna Power Station, Louisa County, Virginia - 1994 pCl/It 2 Sigma Page 1 of 1 { Collection Dates Gross Beta Rainfall (inches) 12/29/93-01/26/94 3.1 1 0.8 3.43 01/26/94-02/23/94 2.9 i 0.8 4.63 02/23/94 03/29/94 2.5 1 0.6 9.62 03/29/94-04/27/94 3.71 0.7 126 04/27/94-05/25/94 3.7i 0.9 2.52 05/25/94-06/29/94 4.61 0.9 1.86 06/29/94-07/27/94 2.7 i 0.7 926 07/27/94-08/31/94 2.4 1 0.6 9.40 , 08/31/94-09/28/94 2.8 i 0.9 3.48 09/28/94-10/26/94 3.5 1 0.7 1.52 10/26/94-11/30/94 2.31 0.6 1.86 11/30/94 12/28/94 13 1 1 1.10 t O . I Average i 2 s.d. 3.9 i 5.9 i SEMI-ANNUAL PRECIPITATION COMPOSITES , 12/29/93-06/29/94 06/29/94-12/28/94 Be-7 = < 30 Be-7 = < 40 H-3 = < 200 H-3 = < 100 - TABLE B-5 SOIL Soil samples are collected every three years frorn twelve stations. Since the samples were collected in 1992, Table B-5 will not be included in the 1994 report. O
- All gamma emitters other than those listed were <LLD.
73
i , TABLE B-6: GAMMA EMITTER
- STRONTIUM, AND TRITIUM CONCENTRATIONS t) IN GROUND AND WELL WATER North Anna Power Station, Louisa County, Virginia - 1994 pCi/li 2 Sigma Page 1 of 1 Collection Dates H-3 Sr-89 Sr-90 Be-7 K 40 1-131 Ba-140 Th-228 STAT!ON 01 A 03/30/94 < 200 (a) (a) < 30 < 60 < 0.4 <7 <7 06/29/94 < 200 <2 < 0.3 < 20 < 50 < 0.2 <5 <5 09/28/94 < 200 (a) (a) < 30 < 50 < 0.1 <5 <7 12/28/94 < 200 (a) (a) < 30 < 50 < 0.2 <5 <7 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
- TRONTIUM, AND TRITIUM CONCENTRATIONS IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 1994 pC1/li 2 Sigma Page 1 of 1 Collection Dates Sr-69 Sr-90 H-3 B+7 K-40 1-131 Co 137 Ba-140 Ra-226 Th-228 STATION - 11 01/21/94 (a) (a) 1900 i 200 < 30 < 100 < 0.2 <4 <5 < 70 <6 02/17/94 (a) (a) (b) < 40 118 i 38 < 0.3 <5 <8 < 90 <7 03/23/94 (a) (a) (b) < 30 < 100 < 0.3 <4 <6 < 70 <6 04/20/94 <1 < 0.2 1800 i 200 < 30 < 50 < 0.2 <4 <5 < 60 <5 05/18/94 (a) (a) (b) < 30 < 50 < 0.2 <4 <5 < 60 <5 06/21/94 (a) (a) (b) < 30 < 50 < 0.2 <4 <5 < 60 <6 07/19/94 (a) (a) 2800 1 200 < 30 < 50 < 0.2 <4 <5 < 60 <6 ,
08/23/94 (a) (a) (b) < 30 < 50 < 0.2 <4 <4 < 60 <6 j 09/23/04 (a) (a) (b) < 40 < 100 < 0.2 <4 <7 < 70 <7 { 10/20/94 (a) (a) 31001200 < 30 < 60 < 0.2 <4 <6 < 80 <7 ! 11/22/94 (a) (a) (b) < 30 < 50 < 0.2 <4 <7 < 60 <5 12/21/94 (a) (a) (b) < 40 < 100 < 0.3 <5 <6 < 90 <8 Average 12 s.d. 2400 1 1296 118 1 38 O All gamma emitters other than those listed were <LLD. (a) St-89/90 analyses performed only on second quarter samples. (b) Tritium analysis performed on quarterly composite. 74 l l
TABLE B-8: GAMMA EMITTER
- STRONTIUM, AND TRITIUM CONCENTRATIONS IN 0,: SURFACE WATER North Anna Power Station, Louisa County, Virginia - 1994 pCl/li2 Sigma Page 1 of 1 Collection Dates H-3 1-131" Sr-89 Sr-90 Be-7 K-40 Cs-137 Ba-140 Ra-226 Th-228 STATION.- 08 01/21 18001200 < 0.2 (a) (a) < 30 < 50 <3 <4 < 60 <6 02/17 (b) < 0.3 (a) (a) < 30 < 50 <4 <5 < 70 <6 03/23 (b) < 0.2 (a) (a) < 30 < 40 <3 <6 < 60 <6 04/20 3200 t 200 < 0.2 <2 < 0.3 < 30 < 100 <4 <5 < 80 <7 05/18 (b) < 0.2 (a) (a) < 30 < 100 <4 <6 < 70 <6 06/21 (b) < 0.2 (a) (a) < 40 < 100 <4 <7 < 70 <6 07/19 33001200 < 0.3 (a) (a) < 30 < 70 <3 <7 < 60 <5 08/23 (b) < 0.2 (a) (a) < 40 < 100 <4 <6 < 70 <6 09/23 (b) < 0.3 (a) (a) < 30 < 70 <3 <6 < 60 <5 10/20 31001200 < 0.2 (a) (a) < 30 57.0125.4 <4 <6 < 70 <6 11/22 (b) < 0.2 (a) (a) < 30 < 60 <5 <6 < 70 <6 12/21 (b) < 0.3 (a) (a) < 30 < 50 <4 <7 < 70 <7 O
V Avg. 2850i1409 57.0 25.4
- 12. s.d.
STATION - 09A 01/21 < 100 < 0.2 (a) (a) < 20 < 50 <3 <3 < 60 <6 02/17 (b) < 0.3 (a) (a) < 40 < 100 <4 <7 < 70 <6 03/23 (b) < 0.2 (a) (a) < 30 < 50 <3 <4 < 60 <6 04/20 < 200 < 0.2 <3 <1 < 30 < 60 <5 <6 < 70 <6 05/18 (b) < 0.1 (a) (a) < 30 < 50 <5 <6 < 70 <6 06/21 (b) < 0.2 (a) (a) < 30 < 60 <5 <6 < 70 <6 07/19 < 200 < 0.2 (a) (a) < 30 < 60 <4 <6 < 90 <7 08/23 (b) < 0.1 (a) (a) < 30 < 50 <4 <4 < 70 <6 09/23 (b) < 0.2 (a) (a) < 3f, < 50 <3 <6 < 70 <6 10/20 < 200 < 0.2 (a) (a) < 30 < 50 <3 <6 < 60 <6 11/22 (b) < 0.2 (a) (a) < 40 < 100 <4 <8 < 70 <6 12/21 (b) < 0.3 (a) (a) < 30 < 80 <3 <5 < 70 <6 All gamma emitters other than those listed were <LLD. l-131 by radiochemistry (a) Analysis performed only with second quarter. (b) Analysis performed quarterly. 75
l l l TABLE B-9: GAMMA EMITTER
- STRONTIUM, AND TRITIUM CONCENTRATIONS G IN SURFACE WATER State-Split Samples North Anna Power Station, Louisa County, Virginia - 1994 pCi/li 2 Sigma 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 < 30 < 70 < 0.7 <3 < 10 < 60 <6 02/28 (a) < 30 < 30 < 0.4 <2 < 10 < 40 <4 03/31 (a) < 30 < 50 < 0.4 <4 <10 < 60 <6 04/30 < 200 < 50 < 60 < 0.6 <5 < 10 < 100 < 10 05/31 (a) < 30 < 40 < 0.7 <2 <9 < 50 <5 06/30 (a) < 40 < 40 < 0.6 <4 < 10 < 60 <6 07/31 15201200 < 50 < 60 < 0.4 <5 < 10 < 100 < 10 08/31 (a) < 40 < 50 < 0.7 <4 < 10 < 90 <8 09/30 (a) < 50 < 60 < 0.4 <5 < 10 < 100 < 10 ,
10/31 15001200 < 40 < 60 < 0.4 <5 <10 < 100 < 10 11/30 (a) < 30 < 50 < 0.9 <3 <10 < 60 <6 12/31 (a) < 40 < 60 < 0.4 <5 < 10 < 100 < 10 Avg. 1510t28 i 2 s.d. SIATION - W-33 01/31 2200 1 200 < 30 < 50 < 0.3 <3 < 10 < 60 <6 02/28 (a) < 20 < 40 < 0.3 <2 < 10 < 50 <4 03/31 (a) < 30 < 50 < 0.5 <3 <9 < 70 <6 04/30 1500 i 200 < 40 < 40 < 0.6 <4 < 10 < 60 <6 05/31 (a) < 40 < 80 < 0.7 <3 < 10 < 60 <6 06/30 (a) < 30 < 50 < 0.8 <3 <9 < 60 <6 07/31 3200i 200 < 30 < 40 < 0.4 <3 <9 < 60 <6 08/31 (a) < 30 < 40 < 0.7 <3 < 10 < 50 <5 09/30 (a) < 40 < 50 < 0.4 <3 < 10 < 60 <6 10/31 35001 200 < 30 < 40 < 0.4 <3 <8 < 60 <6 11/30 (a) < 30 < 50 <1 <3 <8 < 70 <6 12/31 (a) < 30 < 40 < 0.5 <4 < 10 < 60 <6 Avg. 260011840 i 2 s.d. All gamma emitters other 'han those listed were <LLD. (a) Tritium analysis performed on the first monthly composite of each quarter. 76
l TABLE B-10: GAMMA EMITTER
- CONCENTRATION IN SEDIMENT SILT North Anna Power Station, Louisa County, Virginia - 1994 pCilkgi 2 Sigma Page 1 of 1 STA-06 STA-09A STA-11 STA-06 STA-09A STA-11 Average Nuclide 03/10 03/10 03/10 08/23 08/23 08/23 12 Sigma Sr49 (a) (a) (a) < 400 < 300 < 400 -
Sr-90 (a) (a) (a) < 40 < 30 < 40 - Be-7 < 300 < 400 < 300 < 200 < 300 < 200 - K-40 64101640 1240011200 19200 i 1900 1610i260 12500 i 1200 20600 1 2100 12120i 14569 Mn-54 < 30 < 30 < 40 < 20 < 40 < 30 - Co-58 < 30 < 40 < 30 < 20 < 40 < 30 - Co-60 < 30 < 40 < 40 < 30 < 30 < 30 - Cs-134 < 40 < 40 < 40 < 20 < 40 < 40 - Cs-137 47.4 i 27.0 < 50 54.4 i 29.4 108 1 24 < 40 < 40 69.9 i 66.3 Ra 226 < 900 1350 i 530 1740i 490 < 500 < 900 22301 420 1773i C82 < Th-228 640i64 808 i 81 13601 140 182 i 26 471i50 1100 i 110 760 853 1 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 ant. lyses performed annually. TABLE B-11: GAMMA EMITTER
- CONCENTRATION IN SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 1994 pCl/kgi 2 Sigma Page 1 of 1 Station 49 Station-09 Average Nuclide 03/23 09/23 2 Sigma Sr-89 (a) < 200 -
Sr-90 (a) < 30 - Be-7 < 200 < 200 - > K-40 2740 1 280 1820 240 2280 1301 Mn-54 < 20 < 20 - Co 58 < 20 < 20 - Oc #4 < 30 < 20 - Cs-134 < 30 < 20 - Cs-137 163 1 26 104 20 134 i 83 , Ra-226 923 382 < 400 923 i 382 Th-228 608 1 61 304 30 456 i 430 0
- All gamma emitters other than those listed were <LLD.
(a) Strontium 89/90 analyses parformed annually. 77
i TABLE B-12: GAMMA EMITTER
- CONCENTRATION IN MILK l North Anna Power Station, Louisa County, Virginia - 1994 l pCilli 2 Sigma Page 1 of 2 >
MONTH NUCLIDE STATION-12 STATION-13 JANUARY Sr-89 (a) (a) Sr-90 (a) (a) ; K-40 1510 1 150 1160 i 120 l Cs-137 <4 <4 l-131 < 0.2 < 0.3 FEBRUARY Sr-89 (a) (a) ! Sr-90 (a) (a) I K-40 12901 130 1230 1 120 Cs-137 <4 <4 l-131 < 0.3 < 0.3 ; MARCH Sr-89 <2 <2 i Sr-90 1.41 0.3 1.6i 02 , K-40 1370 i 140 1200 i 120 l Cs 137 <5 <4 ! l-131 < 0.3 < 0.3 i O AeRiL Sr-ee Sr-90 (a) (a) (e) (a) , K-40 1420 140 1310 1 130 Cs-137 <5 <5 i 1-131 < 0.2 < 0.2 l MAY Sr-89 (a) (a) : Sr-90 (a) (a) K-40 1370 i 140 1210 i 120 Cs-137 <4 <5 l-131 < 0.3 < 0.2 ; JUNE Sr-89 <2 <2 Sr-90 2.01 0.2 2.31 02 K-40 1260 i 130 1200 i 120 ; Cs-137 <4 <4 l-131 < 0.2 < 0.3 ,
?
O
- All gamma emitters other than those listed were <LLD.
(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter. t 78 ,
, TABLE B-12: GAMMA EMITTER
- CONCENTRATION IN MILK
,Lx) North Anna Power Station, Louisa County, Virginia - 1994 pCilli2 Sigma Page 2 of 2 MONTH NUCLIDE STATION-12 STATION-13 JULY Sr-89 (a) (a) Sr-90 (a) (a) K-40 1360 1 140 1390 1 140 Cs-137 <4 <4 l-131 < 0.3 < 0.4 x AUGUST Sr-89 (a) (a) Sr-90 (a) (a) K-40 14701 150 1370 1 140 Cs-137 <4 <5 l-131 < 0.3 < 0.3 SEPTEMBER Sr-89 <1 <1 Sr-90 1.51 02 2.91 02 K-40 1330 i 130 1390 i 140 Cs-137 <4 <4 l-131 < 0.2 < 0.2 O ocroasa sr-89 Sr-90 (a) (a) (a) K-40 14001 140 1340 1 130 Cs-137 <5 <4 l-131 < 0.2 < 0.2 NOVEMBER Sr-89 (a) (a) Sr-90 (a) (a) K-40 14401 140 1280 i 130 Cs-137 <5 <4 l-131 < 0.2 < 0.2 DECEMBER Sr-89 <3 <3 l Sr-90 1.11 02 1.8i 02 K-40 1350 i 140 1320 i 130 Cs-137 <4 <3 1-131 < 0.3 < 0.3 O
- All gamma emitters other than those listed were <LLD.
(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter. 79
TABLE B-13: GAMMA EMITTER
- CONCENTRATION IN FISH North Anna Power Station, Louisa County, Virginia - 1994 pCl/kg12 Sigma Page 1 of 1 Collection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 04/04 08 Fish (b) 18201220 < 20 < 20 47.4 i 19.0 ;
04/05 08 Catfish (a) 23201 230 < 20 < 20 68.3116.7 04/05 25 Fish (b) 23801 240 < 20 < 30 < 30 04/06 25 Catfish (a) 17701240 < 30 < 30 < 30 08/2:6 08 Fish (b) 15701 230 < 20 < 20 45.2 i 18.2 08/26 25 Fish (b) 1550 210 < 20 <*J i < 20 08/26 08 Catfish (a) 16301170 <10 < 20 43.1112.0 08/26 25 Catfish (a) 1800i190 < 20 < 20 < 20 0 Avg. 18551645 51.0123.3 1 2 s.d. O
- All gamma emitters other than those listed were <LLD.
i (a) Bottom dwelling species of gamefish. (b) Non-bottom dwelling species of gamefish. 80
TABLE B-14: GAMMA'EM11TER* CONCENTRATION IN FOODNEGETATION n U North Anna Power Station, Louisa County, Virginia - 1994 pCl/kg12 Sigma Page 1 of 2 Collection Date Be-7 K-40 1-131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 STATION 14 There were no food / vegetation samples during the first quarter 1994, due to seasonal unavailability. 04/20 1990 i 570 < 3000 <10 < 90 < 60 < 80 < 1000 < 200 05/18 < 200 13700 1400 < 40 < 20 < 20 < 20 < 300 < 20 06/20 696 i 197 286001 2900 < 10 < 30 < 30 < 20 < 500 < 40 07/27 3630 i 590 113001 1100 < 60 < 80 < 50 < 50 < 1000 < 100 08/24 993 1 182 22500 i 2300 < 20 < 20 < 20 < 20 < 400 < GO 09/21 3660i 420 10900i 1100 < 20 < 60 < 50 < 50 < 800 < 80 10/19 2860 1 420 5320 540 < 30 < 60 < 50 47.8126.8 < 1000 < 100 There were no food / vegetation samples during November and December 1994, due to seasonal unavailability. SIATION 15 pV There were no food / vegetation samples during the first quarter 1994, due to seasonal unavailability. 04/20 2000 1 450 238001 2400 <10 < 60 < 50 < 60 < 900 1PAi61 05/18 343 i 122 232001 2300 < 30 < 20 < 20 < 20 < 300 < 20 06/20 892 1 160 167001 1700 < 20 < 20 < 20 < 20 < 300 < 30 07/27 1080 1 170 24200i 2400 < 30 < 30 < 20 < 20 < 300 < 30 08/24 730 124 148001 1500 < 30 < 20 < 20 < 20 < 400 < 30 , 09/21 2150 1 380 13100 1 1300 < 20 < 50 < 40 < 40 < 700 < 70 1 10/19 4360 1 570 25800 1 2600 < 40 < 70 < 60 < 70 < 1000 < 100 There were no food / vegetation samples during November and December 1994, due to seasonal unavailability. STATION 16 There were no food / vegetation samples during the first quarter 1994, due to seasonal unavailability. 04/20 392 i 67 7460 1 750 <8 < 10 <8 <8 < 200 < 20 05/18 906 i 370 174001 1700 < 20 < 60 < 40 < 50 < 800 < 90 ) 06/20 5730 1 570 7720 770 < 10 < 50 < 40 <40 < 900 < 80 07/27 305 1 147 215001 2200 < 20 < 20 < 20 < 20 < 300 < 30 08/24 2440 1 330 15200i 1500 < 20 < 50 < 50 < 50 < 800 < 80 09/21 2380 i 440 168001 1700 < 30 < 60 < 60 < 50 < 1000 < 100 10/19 4440 1 540 5860 1 660 < 40 < 60 < 50 < 50 < 900 < 80 There were no food / vegetation samples during November and December 1994, due to seasonal unavailability. f) a All gamma emitters other than those listed were <LLD. 81
i-c TABLE B-14: GAMMA EMITTEW CONCENTRATION IN FOODNEGETATION (j North Anna Power Station, Louisa County, Virginia - 1994 ! pCi/kgi2 Sigma Page 2 of 2 Collection : Date Be-7 K 40 1-131 Ru-103 Cs-134 Cs-137 Re-226 Th-228 l STATION 21 ! i There were no food / vegetation samples during the first quarter 1994, due to seasonal unavailability. 04/20 779 1 186 136001 1400 <9 < 30 < 20 277i 28 < 400 < 40 05/18 2220 1 470 229001 2300 < 30 < 70 < 60 < 60 < 1000 < 100 ! 06/20 756 i 242 32000i 3200 < 10 < 40 < 30 78.81 21.9 < 500 < 40 ! 07/27 788 1 241 22100 1 2200 < 40 < 40 < 30 95.5 i 22.6 < 400 < 40 08/24 3940 1 400 130001 1300 < 30 < 50 < 50 < 50 < 900 < 80 l 09/21 3650 1 420 17300 i 1700 < 30 < 50 < 50 < 40 170 630 < 70 10/19 3690 i 410 5090 i 510 < 40 < 50 < 40 < 40 < 900 < 80 There were no food / vegetation samples during November and December 1994, due to seasonal unavailability. , STATION 23 O There were no feed /vesetation sampies durin9 the firsi 9earter 1994. due io seasonai uaavaiiabiiity. 04/20 2440 i 270 150001 1500 <8 < 40 < 30 < 30 < 500 - 215127 05/18 175 70 145001 1400 < 30 < 10 <10 <10 < 200 <10 06/20 378 1 109 235001 2400 <10 < 20 < 10 <10 < 200 < 20 07/27 468 i 201 265001 2600 < 40 < 30 < 20 < 20 < 400 < 40 08/24 1610 i 250 38700i 3900 < 30 < 40 < 40 < 40 < 600 < 60 09/21 2680 1 350 12800 i 1300 < 20 < 50 < 40 50.5 i 29.3 < 700 < 60 10/19 4790 1 480 41800i 4200 < 40 < 40 < 40 < 40 < 600 < 60 i There were no food / vegetation samples during November and December 1994, due to seasonal unavailability. Avg 2069 1 3082 18372 1 17679 110 i 191 1170i630 2001 44 i 2 s.d. , l 1 l O
- l All gamma emitters other than those listed were <LLD.
82
l TABLE B-15: DIRECT RADIATION MEASUREMENTS - QUARTERLY AND ANNUAL O, TLD RESULTS North Anna Power Station, L0uisa County, Virginia - 1994 mR/Std. Month (30.4 days)i 2 Sigma Page 1 of 1 Station First Qtr Second Qtr Third Otr Fourth Qtr Quarterly Annual TLD Number 01A)S/94 03/30/94 06/29/94 09/28/94 Average 06/30/93 03/30/94 06f29/94 09/28/94 01/05/95 06/29/94 01 7.7 1 0.2 7.3 i 0.3 7.1 1 0.2 7.9 1 0.5 7.5 1 0.7 7.0 i 0.2 02 4.3 0.2 4.2 1 0.1 3.5 1 0.1 4.7 1 0.1 4.2 i 1.0 4.0 0.1 03 4.4 i 0.2 4.2 1 0.4 3.3 0.2 4.9 i 0.1 4.2 1.3 3.9 i 0.1 04 4.5 1 0.1 4.3 1 0.3 3.8 1 0.1 4.8 1 0.2 4.4 1 0.8 4.0 1 0.1 05 5.3 1 0.1 6.8 1 0.8 4.5 1 0.1 5.9 0.3 5.6 i 1.9 4.9 i 0.2 05A 5.3 0.4 5.7 1 0.3 4.4 0.1 7.0 i 0.4 5.6 2.2 4.8 i 0.2 06 6.2 0.2 7.1 i 0.4 6.1 0.1 6.9 i 0.2 6.6 1 1.0 5.9 i 0.3 07 5.1 1 0.2 5.9 1 1.8 4.3 1 0.0 5.7 i 0.1 5.3 i 1.4 5.0 i 0.6 21 5.110.1 4.910.1 4.2 1 0.1 5.5 i 0.2 4.9 1 1.1 4.6 0.2 22 6.0 1 0.3 5.9 0.1 5.2 0.1 7.2 i 0.5 6.1 1 1.7 5.810.1 23 6.4 1 0.2 7.8 i 0.6 5.6 1 0.1 7.1 1 0.7 6.7 1 1.9 6.2 1 0.4 24 3.8 0.1 4.6 i 0.2 4.1 0.1 5.7 i 0.1 4.6 1 1.7 3.8 i 0.1 Average 5.3 i 2.2 5.7 1 2.6 4.7 2.2 6.1 1 2.1 5.5 i 2.5 5.0 1 2.1 1 2 s.d. 83
TABLE B-16: DIRECT RADIATION MEASUREMENTS-0 SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1994 mR/Std. Month (30.4 days)i 2 Sigma Page 1 of 2 Station 01/05-03/30 03/30 06/29 06/29 09/28 09/28-01/05 1 2 S.d. N-1 5.71 02 5.5 i 1.9 4.5 1 2.1 6.4 1 0.2 5.5 i 1.6 N-2 5.1103 5.6 i 0.5 4.3 1 0.3 6.410.2 5.4 i 1.8 NNE-3 6.21 0.3 7.8 1 2.2 6.3 1 0.4 9.1 i 2.0 7.4 i 2.8 NNE-4 5.0i 02 5.9 i 0.7 4.6 i 0.2 5.9 i 0.4 5.4 i 1.3 NE-5 7.4 i 0.6 6.8 i 0.5 6.9 i 0.2 8.8 i 0.5 7.5 1.8 NE-6 7.4 i 0.5 3.7 i 0.2 3.0 i 0.1 4.4 0.1 3.6 i 1.2 ENE-7 (a) 5.6 i 1.2 5.9 i 0.1 6.8 i 0.4 6.1 1 1.2 ENE-8 4.3 i 0.1 5.5 i 1.0 4.3 1 0.9 5.2 1 0.2 4.8 i 1.2 E-9 6.31 03 6.0 1 0.9 6.4 1 0.3 8.3 1 0.4 6.8 i 2.1 E-10 5.51 0.3 5.3 1 0.9 5.3 1 0.2 6.2 i 0.2 5.6 i 0.9 ESE 11 5.5 i 0.3 5.4 i 0.8 5.3 i 0.2 6.410.2 5.7 1 1.0 ESE-U 5.8i 02 6.6 1 0.5 6.2 i 0.3 6.9 i 0.1 6.4 1 1.0 SE-13 6.4 i 0.7 6.3 i 1.0 5.5 i 0.3 6.1 i 0.8 6.1 1 0.8 SE-14 7.81 02 7.4 1 0.6 7.6 1 0.5 8.2 1.0 7.8 i 0.7 SSE-15 6.4 0.7 6.2 0.7 6.110.1 6.8 i 0.2 6.4 i 0.6 SSE-16 4.81 02 4.9 i 0.4 4.3 1 0.8 7.110.6 5.3 1 2.5 S-17 6.21 05 6.3 i 1.0 6.0 1 0.3 8.3 1 0.6 6.7 i 2.1 S-18 3.9 0.1 4.9 1 0.4 3.6 1 0.2 5.0 i 0.1 4.4 1.4 SSW 19 8.0 i 0.1 8.7 1 0.9 8.4 i 0.3 8.9 i 0.2 8.5 0.8 SSW-20 4.01 0.4 5.0 i 0.4 3.4 i 0.2 5.8i03 4.6 1 2.1 SW-21 7.81 0.4 8.8 1 0.5 8.1 i 0.8 9.5 i 1.8 8.6 1.5 ' SW-22 6.413.1 6.0 1 0.3 5.7 0.1 7.9 i 0.9 6.5 i 2.0 WSW-23 5.0 1 0.1 5.3 1 0.1 4.9 i 0.5 7.0 1 0.4 5.6 1 2.0 i WSW-24 5.910.2 6.3 i 1.1 5.6 i 0.3 7.6 i 0.3 6.4 i 1.8 W-25 6.7 i 0.9 7.911.2 6.6 1 0.4 8.2102 7.4 i 1.6 W-26 4.61 02 5.3 1 0.4 4.5 i 0.2 4.8 i 0.5 4.8 1 0.7 WNW-27 4.8 0.1 4.8 1 0.2 6.5 i 1.4 6.0 1 0.3 5.5 1.7 WNW-28 ~ 5.01 02 5.4 1 0.7 4.5 i 0.1 5.7 0.1 5.2 1 1.0 NW-29 6.91 2.6 8.7 1 2.2 7.1 1 0.2 7.9 i 0.3 7.7 1 1.6 1 NW-30 4.5 i 0.1 5.0 i 0.5 4.3 i 0.1 6.6 i 0 3 5.1 i 2.1 : NNW-31 5.31 02 5.7 i 1.0 4.6 1 0.2 5.5 i 0.3 5.3 i 1.0 l NNW-32 5.01 0.1 5.6 1 1.7 4.7 1 0.3 5.6 1 0.1 5.2 1 0.9 N-33 5.9 1 0.2 5.7 0.8 5.5102 6.8 1 0.5 6.0 1 1.1 N-34 5.01 03 6.2 1 0.3 5.7 i 0.2 6.110.2 5.8 i 1.1 NNE-35 62 03 7.3 i 0.8 62 0.1 8.0 1 1.1 6.9 1 1.8 NNE-36 5.1 1 0.2 5.6 1 0.5 5.1 1 0.4 5.8 1 0.1 5.4 i 0.7 NE-37 7.410.1 8.1 i 1.5 7.3 1 1.0 7.3 1 0.7 7.5 i 0.8 NE-38 3.31 02 3.7 1 0.2 3.1 0.2 4.3102 3.6 i 1.1 ENE-39 6.110.2 6.2 1 0.4 6.3 i 0.3 7.710.1 6.6 i 1.5 ENE-40 4.4 i 0.1 4.7 0.3 42i02 5.3 i 0.1 4.7 i 1.0 E-41 6.1102 7.2 1 1.0 6.3 1 0.4 6.7 1.0 6.6 i 1.0 E-42 5.5103 5.6 0.5 5.4 1 0.8 6.2 1 0.2 5.7 0.7 ESE-43 5.81 0.4 5.8 1 0.6 5.2 1 0.1 62 0.1 5.8 i 0.8 ESE-44 5.8i 02 6.9 1 1.0 6.1 0.1 6.6 i 0.1 6.4 i 1.0 SE-45 5.9 i 02 6.5 i 0.2 5.410.1 8.3 i 1.2 6.5 1 2.5 O (a) Could not locate. 84
l i 1 i I TABLE B-16: DIRECT RADIATION MEASUREMENTS l SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1994 mR/Std. Month (30.4 days)i 2 Sigma Page 2 of 2 Station First Qtr Second Qtr Third Qtr Fourth Qtr Average l Number 01/05 03/30 03/30-06/29 06/29 OlW28 09/28-01/05 1 2 S.d. j SE-46 7.9 1 0.4 7.9 1 0.5 8.2 i 0.1 8.6102 8.2 i 0.7 SSE-47 6.4 i 02 6.4 1 0.2 6.1 i 0.1 7.0 i 0.2 6.5 1 0.8 SSE-48 4.9 i 0.1 5.0 1 0.4 4.7 1 0.0 6.0 i 0.9 52i12 l S-49 6.3i 02 6.4 0.1 6.2 1 0.2 7.1 i 0.2 6.5 1 0.0 I S-50 3.9 i 0.1 5.3 1 0.9 3.5 1 0.1 6.2 1 0.6 4.7 i 2.5 SSW-51 7.9 i 0.3 92 i1.1 8.7102 8.8 2.9 8.7i1.1 SSW-52 3.9 1 0.0 4.3 1 0.1 3.7 i 0.2 4.9 i 0.2 4.2 1 1.1 SW-53 7.8 i 0.5 8.4 1 0.7 7.7 i 0.2 8.5 1 0.2 8.1 1 0.8 SW-54 6.1 1 0.6 7.5 i 0.8 5.8 1 0.1 6.6 i 0.5 6.5i1.5 ' WSW-55 4.9 i 0.1 5.6 1 0.3 4.9 i 0.1 5.7 i 0.5 5.3 1 0.9 WSW-56 5.8 i 0.1 6.7 1 0.5 5.5 1 0.1 7.8 1 0.8 6.5 i 2.1 W-57 7.01 0.3 8.3 1 0.6 6.8 1 0.2 7.7 1.5 7.5 i 1.4 W-58 4.6 i 0.1 6.1 i 0.7 4.5 i 0.0 6.2 i 0.5 5.4 i 1.9 WNW-59 4.7i 0.1 5.4 1 0.4 4.1 1 0.2 6.3 1.6 5.1 i 1.9 WNW-60 5.1 i 0.5 5.2 1 0.2 4.7 i 0.1 6.0 0.1 5.311.1 NW-61 7.21 0.2 7.4 1 0.5 8.3 1 0.5 9.8 1 0.5 8.2 i 2.4 NW-62 4.61 02 5.0 1 0.5 4.2 1 0.1 7.4 i 1.5 5.3 1 2.9 O NNW-63 NNW-64 5.3 i 0.5 5.110.1 5.3 0.3 6.5 1 0.6 4.8 1 0.2 4.9 1 0.2 6.1 1 0.3 6.9 i 0.5 5.4 i 1.1 5.9 i 2.0 C1 4.51 02 5.5 1 0.8 4.3 i 0.1 5.4 1 0.3 4.9 i 1.2 C-2 4.6 i 0.2 4.1 0.6 4.3 i 0.1 5.6 1 0.0 4.7 i 1.3 C-3 3.5 i 0.1 5.0 1 0.4 4210.1 5.5 i 0.1 4.6 i 1.8 C-4 3.4 t 0.1 5.5 i 0.9 3.9 i 0.1 5.3 0.2 4.5 i 2.1 C-5 3.9 i 0 2 4.1 1 0.3 3.3 1 0.1 4.7 1 0.1 4.011.2 C-6 4.01 02 3.5 02 3.3 1 0.1 5.1 1 0.4 4.011.6 C-7 6.1 1 0.9 5.4 1 0.5 5.2 i 0.1 7.2 1 0.3 6.011.8 C-8 5.61 0.1 5.2 1 0.2 5.4 t 0.2 6.5 i 0.2 5.7 1 1.1 Average 5.5 i 2.4 6.0 1 2.6 5.4 i 2.7 6.7 1 2.5 5.9 1 2.3 r l O 85
-ma e- 24se 4 _
l i l O. l l l i l 1 i l l 1 I O APPENDIX C LAND USE CENSUS - 1994 e i l O I i i 86
VIRGINIA POWER - NORTH ANNA POWER STATION Annual Radiological Environmental Land Use Census Data for 1994 July (1-31) Milk
- Milk
- Nearest Nearest Site Meat Veg. Garden ,
Sector Resident Boundary Cow Animal Goat 500 Sq Ft. ' KM KM KM KM KM KM N 2.14 1.40 3.23 2.98 NNE 1.51 1.36 4.22 1.87 NE 1.57 1.32 2.51 1.80 ENE 3.17 1.31 4.12 3.17 E 2.03 1.33 2.53 ESI', 2.60 1.37 7.74 5.63 SE 2.20 1.41 2.20 2.20 G SSE 1.47 1.47 3.83 1.55 V 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 t WNW 1.61 1.64 6.13 4.28 NW 1.57 1.56 1,77 NNW 1.72 1.45 3.57 1.80
- Note: No milk cow or goats within a five mile radius of North Anna Power Station KM = Kilometer 87
VIRGINIA POWER 7 NORTH ANNA POWER STATION U, Annual Radiological Environmental Land Use Census Data for 1994 July (1-31) l Nearest Nearest Site Milk
- Meat Milk
- Veg. Garden Sector Resident Boundarf Cow Animal Goat 500 Sq Ft. J M M M M M M N 1.33 0.87 2.01 1.85 NNE 0.94 0.85 2.62 1.16 l NE 0.98 0.82 1.56 1.12 i 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 SSE 0.91 0.91 2.38 0.96 S 1.04 0.94 1.44 1.04 SSW 1.43 1.01 4.11 1.37 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 i NNW 1.07 0.90 2.22 1.12 i i l I
- Note: No milk cow or goats within a five mile radius of North Anna Power Station M = Mile l
88
1 l VIRGINIA POWER ,, NORTH ANNA POWER STATION COMPARISON OF THE 1994 TO 1993 LAND USE CENSUS , i I. No changes were observed in the nearest resident status. l I II. No changes were observed in the nearest site boundary distances. I III. No changes were observed in the nearest milk cow / goat status. 1 IV. Changes in nearest vegetable garden as compared to previous year are as -l follows. l
- a. N Sector: 3.07 Km (1993) to 2.98 Km (1994) <
- b. NNE Sector: 2.72 Km (1993) to 1.87 Km (1994)
- c. NE Sector 2.51 Km (1993) to 1.80 Km (1994)
- d. NNW Sector: 1.91 Km (1993) to 1.80 Km (1994) f C V. No changes were observed in the nearest meat animal status. ,
f l l i h i l O 89
O O APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES o 90
ANALYTICAL PROCEDURES SYNOPSIS t Appendix D is a synopsis of the analytical procedures performed on samples collected for ! the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Brown Engineering and include those l recommended by the USNRC Branch Technical Position, Rev.1, November 1979. l ANALYSIS TITLE PAGE Gross Beta Analysis of Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92 Airborne Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92 Water...............................................................................................93 ; Analysis of Samples for Tritium (Liquid Scintillation) ........ - ................................94 f 1 Analysis of Samples for Strontium-89 and -90... ... .... . . .. . .... ...... . .... . .. . . . . . ... . . .. . . .. ....... 95 ; Total W ate r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 95 , Milk................................................................................................95 Soil an d Sedimen t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 95 f7
%)
Organic S oli ds . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 96 Air P a r t i c u l a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 96 Analysis of Samples for Iodine- 131 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 Milk or Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 8 G am ma Spec trometry of Sam ples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 : Milk and Wate r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Dried Solids other than Soils and Sediment. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Fish................................................................................................99 , Soils and S e d i m e n 1s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Charcoal Cartridges (Air Iodine) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Airbome Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Envimnmental Dosimetry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101 91
. 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) ,
~
I 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) = ((Str)- (B/t))/(2.22 V E) TWO SIGMA ERROR (pCi/m3) = 2((Str2) + (B/t2))1/2 /(2.22 V E) j LLD (pCi/m3) = 4.66 (B1/2)/(2.22 V E t) where. ; S = Gross counts of sample including blank j B = Counts of blank E = Counting efficiency
^ T = Number of minutes sample was counted U t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) l O
92
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 separadon 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 the customer, the sample is filtemd through No. 54 filter paper before evaporation, removing particles gmater 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 which allow for the change in effective counting efficiency caused by the residue mass. G Detection Capability Detecdon 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 cormctions am made and the mponed activity refers to the counting time. The minimum detectable level (MDL) for water samples is nominally 1.6 picoCuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/l at the 2.83 sigma level), assuming that I liter of I sample is used and that y gram of sample residue is mounted on the planchette. These figures am based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively. The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per i liter. These values mflect a beta counting efficiency of 0.38. O 93
L ANALYSIS OF SAMPLES FOR TRITIUM i O <Liseid scintiliaden) : Water Ten milliliters of water am mixed with 10 ml of a liquid scintillation " cocktail" and then the ! i mixtum is counted in an automanc liquid scintillator. Calculadon of the msults, the two sigma error and the lower limit detecdon (LLD) in pCi/l: RESULT' = (N-B)/(2.22 V E) ; TWO SIGMA ERROR = 2((N + B)/At)lC/ (2.22 V E)
.,l i
LLD = 4.66 (B/At)la/(2.22 V E ) h where: N = the gross epm of the sample B = the background of the detectorin cpm { 2.22 = conversion factor changing dpm to pCi
'Q V E
=
=
volume of the sample in ml efficiency of the detector At = coundng dme for the sample ; r i t i 1 l t i F C O : i
}
94 .
ANALYSIS OF SAMPLES g Q FOR STRONTIUM-89 AND -90 Water Stable strondum 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 am 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 m-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 acdvity. Strontium-89 activity is determined by precipitating SCO 3from 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 stronnum is precipitated as phosphate, then is dissolved and pmcipitated as SrN0 3 using fuming (90%) nitric acid. A barium chromate scavenge Q and an iron (ferne hydroxide) scavenge am 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 m-pmeipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 acdvity. Strondum-89 is determined by precipitating SCO3 from the sample after yttrium separadon. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium canier is added and the sample is leached in hydrachloric acid. The mixtum is filtered and strontium is precipitated from the liquid pordon as phosphate. Strontium is precipitated as Sr(NO3)2 using fuming (90& nitric acid. A barium chromate scavenge and an imn (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum j of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re- I 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 O SC 3 * " * *"* v'" """i"" *e""'"'i " ' "'**i vi'"'* i' = ""'*d " " "v' " v'^"c' * ; and is covemd with an 80 mg/cm2 aluminum absorber for low level beta counting. 95
~
3 l l O organic soiids A wet portion of the sample is dried and then ashed in a muffle furnace. Stable stmntium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO3 ) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addidon of stable yttrium carder and a minimum of 5 days period for yttrium ingrowth. Yttrium is then pre-cipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on 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/cm 2 aluminum absorber for low level beta counting. Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(NO 3 )2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is O verformed, foiiewed by addition of stabie yttrium carrier and a 7 to 10 day period ror yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-pmcipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 acdvity. Strontium-89 activity is determined by pmcipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covemd 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 pCi/ volume or pCi/ mass: RESULT Sr-89 = (N/Dt-BC-BA)/(2.22 V Yg DFSR-89ESR-89)
'IWO SIGMA ERROR Sr-89 = 2((N/Dt+BC+BA )/At)l/2 /(2.22 V YS DFSR-89 ESR-89) l l
LLD Sr-89 = 4.66((B C /
+BA)/At)1/2 (2.22 V YS DFSR-89 ESR-89) l RESULT St-90 = (N/At - B)/(2.22 V Y1 Y2DF IF E)
TWO SIGM A ERROR Sr-90 = 2((N/At+B)/At)l/2/ (2.22 V Y1 Y2DF E IF)) O LLD St-90 = 4.66<B/A1)i/2/ <2.22 v Yi v2 1F DF E) 96
WIIERE: N = total counts from sample (counts) (,) At = counting time for sample (min) , BC = backgmund rate of counter (cpm) using absorber configuration 2.22 = dpm/pCi V = volume or weight of sample analyzed BA = background addition from Sr-90 and ingrowth of Y-90 B3 = 0.016 (K) + (K) EY/ abs)(IGy_90) Y3 = chemicalyield of strontium DF SR-89 = decay factor from the mid collection date to the counting date for SR%9 IISR-89 = efficiency of the counter for SR-89 with the 80 mg/cm.sq. aluminum absorber K = (NAt B C)Y-90(Ey.90IFy.90
/ DFY-90Y1)
DFy.99) = the decay factor for Y-90 from the " milk" time to the mid count time i E Y-90 = efficiency of the counter for Y-90 IFy.99 = ingrowth factor for Y-90 from scavenge time to milking time IGy,99 = the ingrowth factor for Y-90 into the strontium mount from q I V the " milk" time to the mid count time 0.016 = the efficiency of measuring SR-90 through a No. 6 absorber EY/ abs = the efficiency of counting Y-90 through a No. 6 absorber B = background' rate of counter (cpm) Yg = chemical yield of >ttrium 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 factcr for Y-90 fmm scavenge time to the radio-chemical milking time 97
.. ANALYSIS OF SAMPLES FOR JODINE-131
(
.V(G Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch tmatment with anion exchange resin is used to remove iodine from the sample. 'Ihe iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution and is pmcipitated as palladium iodide. The pmcipitate 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 iodide 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 DF)
'IWO 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 E = efficiency of the counter for 1-131, corrected for self absorption effects by the formula E = E3(exp-0.0061M)/(exp-0.0061Ms ) Es = efficiency of the counter determined from an 1-131 standard mount Ms = mass of Pd12 on the standard mount,mg M = mass of PDI2on the sample mount, mg 98
m l GAMMA SPECTROMETRY OF SAMPLES O Milk and Water A 1.0 liter Marinelli beaker is filled with a reprewntative 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 j As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 1000 minutes ; with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Soils and Sediments ; 1 Soils and sediments are dried at a low temperature,less than 100 C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height and analysis. l Charcoal Cartridges (Air Iodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a ! Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated t for both positions. The detection limit for I-131 of each charcoal cartridge can be determined [ (assuming no positive I-131) uniquely from the volume of air which passed through it. In the ! event I-131 is observed in the initial counting of a set, each charcoal cartridge is then counted
]
separately, positioned on the face of the detector. Air Particulate 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) 99
detector coupled to a mini-computer-based data acquisition system which performs pulse height n () analysis. ; A mini-computer software program defines peaks by certain changes in the slope of the - spectrum. The program also compams the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The calculation of j results, two sigma enor and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass: j l RESULT = (S-B)/(2.22 t E V F DF) ! TWO SIGMA ERROR = 2(S+B)1/2/ (2.22 t E V F DF) l LLD = 4.66(B)l/2 /(2.22 t E V F DF) where: S = Area,in counts, of sample peak and background (region of spectrum ofinterest) B = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on either j side of the peak l t = length of time in minutes the sample was counted l 2.22 = dpm/pCi l E = detector efficiency for energy ofinterest and geometry of sample I V = sample aliquot size (liters, cubic meters, kilograms, or grams) F = fmetional gamma abundance (specific for each emitted gamma) DF = decay factor from the mid-collection date to the counting date I I 100
f I r ENVIRONMENTAL DOSIMETRY ( ( Teledyne Brown Engineering uses a CaSO 4 :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 exposum period the TLDs are placed in a Teledyne Brown Engineering Model 8300. One founh of the metangular 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. l The transit controls am mad in the same manner. - Calculations of results and the two sigma error in net milliroentgen (mR): RESULT = D = (Di+D2+D 3 +D 4 )/4 TWO SIGMA ERROR = 2((D;-D)2+(92 -D)2+(93 9)2,(p4 9)2)f3)1/2 WlIERE: Di = the net mR of area 1 of the TLD, and similarly for D2, D3, and D4 , D1
" Il M -A 1 Ig = the instrument reading of the field dose in area 1 l
K = the known exposure by the Cs-137 source ; Rg = the instrument reading due to the Cs-137 dose on area 1 l t A = average dose in mR, calculated in similar manner as above, l of the transit control TLDs f D = the avenge net mR of all 4 areas of the TLD. ! i l O 101
O l l APPENDIX E EPA INTERLABORATORY COMPARISON PROGRAM 1 l O 102
EPA 1nterlaboratory Comparison Program Teledyne Brown Engineering pardeipates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. In this section the 1994 data summary tables and trending graphs are presented for isotopes in the various sample media applicable to the North Anna Power Station's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encounten:d in a few cases and the steps taken to prevent reoccurrence. O i I l 1 0 103
, . .,y b/ k.)
VEPCO - NORTH ANNA EPA IN'IERLABORATORY COMPARISON PROGRAM 1994 (Page 1 of 3) EPA Date TI Mailed Date EPA EPA TI Mona Dev. " Warning - Preparation Re suits Issued Results Media Nuclide Results(a) Results(b) (Known)(c) "* Action 01/14/94 03/04/94 05/13/94 Water Sr-89 25.0 1 5.0 24.00 1 1.00 -0.35 Sr-90 15.0 i 5.0 15.67 i 1.53 0.23 01/28/94 02/25/94 04/12/94 Water Gr-Alpha 15.0 1 5.0 21.67 1 0.58 2.31 ' (d) Gr-Beta 62.0 i 10.0 72.33 i 3.79 1.79 02/04/94 03/04/94 04/26/94 Water I-131 Il9.0 i 12.0 Il0.33 i 0.00 -1.30 02/11/94 04/14/94 05/23/94 Water Ra-226 19.9 i 3.0 21.00 i 1.00 0.64 Ra-228 14.7 i 3.7 15.67 i 1.53 0.45 03/04/94 03/31/94 05/13/94 Water H-3 4936.0 i 494.0 4833.33 il52.75 -0.36 04/19/94 06/13/94 OG/02/94 Water Gr-Beta ll7.0 i 18.0 102.67 i 6.43 -1.38 Sr-89 20.0 i 5.0 19.00 i 1.00 -0.35 Sr-90 14.0 1 5.0 13.00 i 0.00 -0.35 Co-60 20.0 i 5.0 23.67 i 3.21 1.27 g Cs-134 34.0 i 5.0 34.00 i 1.73 0.00
- Cs-137 29.0 1 5.0 34.00 i 2.65 1.73 Gr-Alpha 86.0 1 22.0 78.00 i 3.00 -0.63 Ra-226 20.0 i 3.0 15.67 i 1.53 -2.50 " (e)
Ra-228 20.1 i 5.0 15.33 i 0.58 -1.65 06/10/94 07/15/94 10/31/94 Water Co-60 50.0 i 5.0 43.00 1 2.00 -2.42 " (f) Zn-65 134.0 i 13.0 13.33 i 0.58 -16.08 "" (g) Ru-106 252.0 1 25.0 201.33 i 9.29 -3.51 ' * (h) Cs-134 40.0 i 5.0 29.33 i 3.79 -3.70 ' * (1) Cs-137 49.0 1 5.0 49.67 i- I.53 0.23 Ba-133 98.0 i 10.0 85.00 1 3.00 -2.25 " (J) 06/17/94 08/10/94 10/03/94 Water Ra-226 15.0 1 2.3 15.33 1 0.58 0.25 Ra-228 15.4 i 3.9 16.33 i I.53 0.41 07/22/94 08/19/94 10/14/94 Water Gr-Alpha 32.0 i 8.0 25.33 i 2.89 -1.44 Gr-Beta 10.0 i 5.0 16.00 1 0.00 2.08 * * (k) 08/05/94 08/29/94 10/24/94 Water H-3 9951.0 i 995.0 9700.00 1100.04 -0.44
\,
VEPCO - NORTH ANNA EPA INTERLABORATORY COMPARISON PROGRAM 1994 (Page 2 of 3) EPA Date T1 Malled Date EPA EPA TI Norm Dev. " Warning Preparation Re salts Issued Results Media Nuclide Results[a) Results(b) (Known) *" Action 08/26/94 11/14/94 12/23/94 Air Filter Gr-Alpha 35.0 1 9.0 31.33 i 2.08 -0.71 Gr-Beta 56.0 i 10.0 59.33 i 3.21 0.58 Sr-90 20.0 i 5.0 18.00 i 1.00 -0.69 Cs-137 15.0 i 5.0 17.00 i 1.73 0.69 09/16/94 11/1I/94 09/10/94 Water U 10.2 i 2.6 9.70 1 0.52 2.12 * * (1) Ra-226 10.0 i 1.5 10.67 i 0.58 0.77 Ra-228 10.2 i 3.6 9.70 1 0.52 -0.33 09/30/94 12/08/94 02/06/95 Milk Sr-89 25.0 1 5.0 24.33 1 2.52 -0.23 Sr-90 15.00 1 5.0 17.67 i 1.53 0.92 I-131 75.0 i 8.0 81.67 i 5.86 1.44 Cs-137 59.0 t 5.0 70.33 1 4.62 3.93 (m) K 1715.0 i 86.0 1740.00 i153.95 0.50 10/07/94 11/15/94 12/23/94 Water 1-131 79.0 i 8.0 71.00 1 3.00 -1.73
- 10/18/94 12/20/94 03/03/95 Water Gr-Beta 142.0 1 21.0 120.00 i 0.00 -1.81 @ Sr-89 25.0 i 5.0 24.67 i 2.08 -0.12 Sr-90 15.0 i 5.0 14.33 i 1.15 -0.23 Co-60 40.0 i 5.0 41.00 i 1.00 0.35 Cs-134 20.0 i 5.0 21.67 i 1.53 0.58 Cs-137 39.0 i 5.0 41.67 2.31 0.92 Gr-Alpha 57.0 i 14.0 51.33 i 1.53 -0.70 Ra-226 9.9 i 1.5 11.33 1 0.58 1.66 Ra-228 10.1 1 2.5 9.33 1 0.58 -0.53 10/28/94 12/08/94 02/15/95 Water Gr-Alpha 57.0 i 14.0 47.00 1 3.00 -1.24 Gr-Beta 23.0 1 5.0 25.33 i 1.53 0.81 11/04/94 12/30/94 02/13/95 Water Co-60 59.0 i 5.0 52.00 i 0.00 -2.42 " (n)
Zn-65 100.0 i 10.0 81.33 i 7.02 -3.23 * ** (n) Cs-134 24.0 i 5.0 19.67 i 2.52 -1.50 Cs-137 49.0 i 5.0 54.33 i 2.31 1.85 Ba-133 73.0 1 7.0 58.33 i 2.89 -3.63 (n) Footnotes: (1) Average i experimental sigma. (b) Expected laboratory precisdon (I sigma. I determinattan) (c) Normaltzed deviation from the known.
O O O VEPCO - NORTH ANNA EPA INTERLABOPAMRY COMPARISON PROGRAM 1994 (Page 3 of 3) EPA Date TI Malled Date EPA EPA TI Norna Dev. " Warning Preparation Re suits Issued Results Media Nuclide Restdts(a) Resulte(b) (Known) *" Action Footnotes: (Cmt.) (d) 1here appears to be variation 'n self-absorption matrix.1he EPA confirms that the compositkin of their tap water from take Mead, we'.2s seasonally which can cause vertation in alpha. beta results No corrective action required at this time since results are within i 3 sigma cmtrol limits. (c) No specific or apparent reason found. Data sheets vertited and detector efDdencies calibrated. W!!! act care in making dilutions arul using carect sample type m emwntration of ackis. WID check future samples to see if a pattern develops. (f) A secoruf allquot was analyzed. paying parucular attention to volume al! quoted. The result. 52 pct /l. was in good agreement with the EPA. The three original results. each counted on a different detector, showed good predston. The measurtsnent of Co 60 has not been a poblem. Future EPA cross-checks will be weighted and results followed to check for a possible trerul "out of controli (g) The average value of three analyses on the 'lleport of Analysts
- was 133 pct / liter which is in good agreement with the EPA. Appan rtly, incorrect results were entered into the EPA computer. Future data will be printed from the computer screen to check entries.
(h) The EPA has indicated that the Radiation Quality Assurance Program has been expertencing problems with the ruthentum-106 analysts. See attached !ctter from EPA. [0 The first aliquot. geparai according to EPA diluuon instructions was emnted on four detectors in the 1 !!ter Marinelli geometry with Cs-134 results (based on the 796 kev peak) in pCl/l of 32.0. 25.1. 31.7. arut 30.8 The 31.7 result was not reported. Ilad that tren reported instead of 25.1. the average would have been 31.5 arul the normalized deviation would have been -2.94 instead of -3.70. A second aliquot was prepared and a sin $e measurement was made with the result d 31.1 pct /L An urmilluted aliquot was measured in a 150 ml geometry with the result d 33.5 pct /l. That result is comparable with the Marinellt results. Thus none di m sample preparation (dilution, volume determinauon. maintaining correct p!I, etc.). sample geometry, or detectcr effleterry seem to be the cause of the low results, (j) 1here is no apparent reason for the mw result, however the average valut 85 pct /l ts in good agreement to the grand average (80.46). No om.uGvc action planned. (k) EPA result fw gross beta in water were corrected for 20% crosstalk into t!w Nta char nel from the Th-230 alpha spike. Recent measurements show that the crosstalk can be much higher (37% forTennelec counter #3 and 54% for gamma products cater #1). The normaltred devtation from the grand average was mly 0.38. Future results will be corrected with specific crosstalk values determined by counting Th-230 standards. (1) possible aliquoting error. The instrument calibration. spike. and blank results all appear normal. No procedural changes are planned. Previous results were well within one normalized deviation. Future measurements will be reviewed to determine if a trend in results above the two sigma warning limit is occurring (m) The milk sample was counted four times. The reported Cs-137 values were based on one aliquot of I liter volume and an allquot of 0.865 liter counted two times. It is suspected that the 0.865 liter volume was incorrectly determined. If I liter (the usual volume for counting milk samples) is used in the calculation. then the average of three results equals 63.6 pC1/1 which gives a normalized deviation to the Known of 1.59. The fourth count (a 1 liter aliquot) had a Cs-137 equal to 64.2 pCl/l which is in good agreement with the average d the other three. Teledyne will set up a log for recording aliquots used fw EPA samples and reewd how the aliquot volume was determined. In) The EPA requires that water samples be diluted before gamma analysts. That imposes a feature not appropriate for the handling of wi msntal samples. As in the 06/10/94 water - sample. It appears that the first aliquot may not have been accurately prepared. A second aliquot was prepared and counted three times with results in pC1/1 and normalized deviation of: Co-60 60.6 +0.55 Zn-65 100, 0.0 Cs-134 22.9 -0.38 Cs-137 58.5 43.29 Da-133 69.8 -0.79 Four of the five are now in good agreement with the EPA results. The Cs-137 is high. but within the controllimits when my= cd to the grand average deviatim of alllaboratories of 2.89. The grand average was 51.9 pct /1. For future samples d this type we will have two technicians each prepare an aliquot and compare the counting results to check forr w= oUm technique differences.
,o D g rs ,,
< a >., j
,I UNITED STATES ENVIRONMENTAL PROTECTION AGENCY i e OFFICE OF RESE ARCH AND DEVELOPMEf4T
\
- ent***
ENVIRONMENTAL MONITORING SYSTEMS LA80RATORY LAS VEGAS
/Q P O SOK 93478 (j LAS VEGAS NEVADA 39193 3478 (702/798 2100 FTS 545 210o1 l
Dear Participant:
The Radiation Quality Assurance Program has been experiencing problems with the Ruthenium-106 currently used in the Performance Evaluation (PE) Studies and in the Standards Distribution Program. If these problems can be satisfactorily resolved, this analyte vill once again be placed into this PE Study. If the problems cannot be resolved, the Ruthenium-106 vill be replaced. Formal written notice vill be given to all participants that are enrolled in the Gamma in Vater PE Study before the Ruthenium-106 is reintroduced or replaced. At that time, new calibration standards vill be available to all participants in the Gamma in Vater PE Study. Sincerely, ( O George Dilbeck Chemist Performance Evaluation Program Radioanalysis Branch (RSA-RADQA) i O 107
O O O EPA CROSS CHECK PROGRAM =- GROSS ALPHA IN AIR PARTICULATES (pg.1 of 1) 80 60 - - 40 - r - 6c. t > i [ r i I ( I ( lj l u e t I qp g h 20 -
) " <>
' f.Ln l' l, l '
) .
f i E
,] ,
i , x ,, i lo l, - 0 - -
-20 . . . . . .. . . . . . . i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 o Tli 3 Sigma o EPAi 3 Sigma
O O O 4 EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICULATES (pg.1 of 1) + 160 j 140 - -
"o 120 -
100 .- n - Un. 80 - - e g' ' g j < >' < g ]' I
- 60 -
l u -
, l' t !k .o o < <
40 -
.h.- '
i n l" -
, , , 5t >
j 20 - - 0 , , , , , , 1981 1983 1985 1987 1989 1991 '1993 1995 4 o - Tli3 SPjw o EPA 13 Sigma
- . _ . - _ _ _ _ _ _ _ _ . - . _ . . . - . . - - - . . _ _ - - _ . _ _ _ - . _ _ _ _ _ _ .. . ._-___._.____..._.,__.-__.2..._.-__-.._.~.--.__-..~_ _ . _ _ _ _ _ - - . - - - _ - _ _ - - _ . _
O O O EPA CROSS CHECK PROGRAM STRONTIUM-90 IN AIR PARTICULATES (pg.1 of 1) 80 70 - 60 - 50 - 40 - i l - k 30 - d - e -
- s;j3l b ,f g 10 -11 s-
]
)
j' t , . r r O -
-10 - -
-20 . , , , , , . -
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 o Tli 3 Sigma o EPAi3 Sigma i _____m _. ._..___________.____m_ _.___m.______ _ _ ._______.____._m___. _ _ _.___ _ ___ __ _ . - - - . - _
- ,- - w - - . = -+v--
O O 0: EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES (pg.1 of 1) M 60 - -
. ii -
40 - i t - 6a 8 t < j <> a , 1 - - C >- 20 !i , , i 1
) >
,j k -
l
<> , > J l,
< f, <
(< l ,,
, , j l fo l ,
"o g, i ,
0 -- - '-
-20 , . , , , , , , , , , , , ,
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 a Tli 3 Sigma o EPAi3 Sigma l \ l - .. - - .. . - . . - - ... - _. .
O O O. EPA CROSS CHECK PROGRAM STRONTIUM-89 IN MILK (pg.1 of 1) 100 80 - - l s , , i r s i 60 - - I l i,, .5 b 3
~
40 I rI Igl T 1 I r" 1 8 II
~
U * m" n. j " Ia oJ. .' '. ,
, i. .i , o ii ii, i ! i '
- pg .
l 1 1 .
<, "l, b Il i i n '
jt . 1 1 0 o o - -
-20 , , , , , , ,
1981 1983 1985 1987 1989 1991 1993 1995 m Tli 3 Sigma o EPA i 3 Sigma
O O d i EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK (pg.1 of 1) 8o 60 - t <> -
' li i 1 1 .
4> 40 - t i l s
= 0
} v h ,, y % Y j 8 h' , ,
a 20 ' n
<> -' gf 2 i 1 -
i Wt , 1 , 1. I 11 g r a p EY $ ! A '< > 1> i Itl 5
'l ;
. .L 0 - II - l l -20 , , , , , , , 1981 1983 1985 1987 '1989 1991 1993 1995 ; a Tii3 Sigma
- EPAi2 Sigma
. . - . . _.-,.--..-.--,--..-,--_-.__--......-:--.-,-.....-.~.-..,....-,...-..,-....-.~-....,e ~_ . . . . - . . - - . . . . . . . ~ ~ - . - . . - . . . . _ . . - - , - ~ . - . _m..
O O O. EPA CROSS CHECK PROGRAM l POTASSIUM-40 IN MILK (pg.1 of 1) 2600
- 2400 - -
2200 - - 2000 , 1800
.t >
g 6 I g 1 q ,
' l l 3 1600 l'
t d r *([ > i i -
=
I t' 'f ,
< > 1 1 ' ',
i l 4 o i ,I L ll'i , is o l i. o ' ' ' ' ' ' M o. 1400 .
, i t -
1200 - 1000 - l 8% - - - 600 , , , , . , , , l 1981 1983 1985 1987 1989 1991 1993 1995 { a Tli3 Sigma o EPAi3 Sigma
, _ . . _.~ _ . _ - . , _ . _ . . _ . - _ . _ .,_-_ . . - _ -
O O .O EPA CROSS CHECK PROGRAM IODINE-131 IN MILK (pg.1 of 1) 160 l 140 - o 120 - 1 1 i n 100 - 8
.i, ip .. -
il 80 - ' ' -
, i, 11 E
2 60 - a > ri i 'l' - -
~ u ,
< b g si W & '
lI , i l 40 I I' ' I t I ! '< > -
.i l l ,
l la r ,s 20 " ll a g g ll I 8 '
,I
, g O o -
I
-20 . . . . .
1981 1983 1985 1987 1989 1991 1993 1995 s Tl13 Sigma o EPA 13 Sigma
O O- O EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK (pg.1 of 1) 100 80 - Il
<+
ll 60 i , i 'I il ll ii i-ii l
'il i < >
', , Il ,
p ,.I 1 1
- n. I t i
*, 40 j
11 - - l l > l i
- 3 -l j, si
' s , ,.
U , m EL 11 11 .l> Il , i l l'i l 20 -
.i. fi -
11, I li 0 - 20 , , , , , , , 1981 1983 1985 1987 1989 1991 1993 1995 m Tli3 Sigma o EPA 13 Sigma
O O O 9 t EPA CROSS CHECK PROGRAM < GROSS ALPHA IN WATER (pg.1 of 1)
- 180 160 - -
2 140 - - 120 - - 100 -
<> g .
6 t>- 80 - , q i , ,
- g. -
l Y u ,
- n. 60 -
; i i ,
. < > .1 1
4 > l r
l g' l 40 - <> i , .
.i ' t i t i ,
- i 4 ,
<> i i.
> 'i,
'l E "
i i< li ll l
' '- E l 20 f'i i i' i l l
<i l l 3E I l l.
'k E<
i t - J"
<> < i -< >
bS M ldih= Tii31' l o"d ' P ' I' " O -
-20 , , , , , , , , , , t 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1995
, '1994 l l a Tli 3 Sigma o EPAi3 Sigma t _ _ _ . _ _____________.m__ _ _____ ____.m_ _. ~, __-_ . _ _._ __m . . - . _ _ , _ , _ , . . , - , _ _ . - .. ... .w... s _ ---w,--,. - , -+ +
O O O 1 EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 2 of 2) 260 220 - 180 - l , e 140 - , > <> - e 5 100 - g ,, I I - w E 60 - l ' o ' '-
' ' ' ' k' 'f .
g i '
=
"u. -
a 20 I p
-"I:.,'W< > c. e
. , . " i = , > . .
} .
-ma . . . . . . , ,
1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 m Tli3 Sigma o EPAi3 Sigma
O O O EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg.1 of 2) 220 200 - - 180 - - 11 160 - - i s i, 140 - ' -
?
~
^
g
- 120 - "
, si
% i 6g 100 -
{ G ' I - 80 - t i 60 - I -
'.3 .
40 - g
'I '
L . o i i l 20 - ', ,,g * ' < [ l' h .
' l , ,
f - 0 - *
- l -20 . . . .
1981 1982 1983 1984 1985 1986 l n Tl13 sigma o EPAi3 sigma
O- O 10. , L 'T EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2) 16000 s 14000 - - 4 r
~
< h I 12000 - -
+
s@ -
- 8000 - -
g t 5
}
s000 - i i . q ..
< < i .<
l 4000 '[ ,, i s i g < 1 5 ,, l ' il t k
~ ' 'B D 2000 - d -
l 0 . i 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 a Tii3 Sigers o EPAi3 Sigma i
.f
. t
,_ .. -. __ - . - - _ , , . - __...-..,,..,_._,,,.-m,.
. ...,..~.-...,,..........4 . , , , , . . . , . . . , , , , . , _ _ . . _ , - . . . . . _ . . _ . _ _ . . _ _ _ . _ . ,_,
O O OL EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg.1 of 2) 5000 4000 -
,1
, y .- ,i
~
! ., r, i ' I i ki g, I ,, f.- ,,, , ,f ' 2000 ha { ig,
< g ,,
b M#
'O -
1000 - h - 0 - -
-1000 , , ,
1981 1982 1983 1984- 1985 a Tl13 sigma o EPA 13 sigma , I
. , . , _ . . _ _ - _ , - , . _ . . , , _ . . . . r - , . , , , . - - , _ . . . . . _ - _ _ _ . _ , , .. ._ - , _ . _ . . . _ . _ , _ . - . _ - . - , _ _ . . . _ _ .
e O O o . EPA CROSS CHECK PROGRAM IODINE-131 IN WATER (pg.1 of 1) 160 140 - . t I 120 - 81 < , si I 100 - g l, ,, t 11 80 ' ,, l g 60 - , .
~ !
g o- ,, N !. < > ii 40
, , l
<> t i ' la
<> ' l l s.
j g
, , g g, , , .. .
20 , t i g ,, _ g c g DE 'O { II E '- O - -
-20 , , , , , , , , , , ,
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 , n Tli 3 Sigma o EPAi3 Sigma
-. -._.-------,.,-n---,,,--.-,--,.--,,.--,-.---,,....-,-~,,---.----.-----...-----~.--..,,--,-------.-...--.---~.--,--n- - - - - - -.
.---u - _ - - - - - - - - - - - - - -
O O O EPA CROSS CHECK PROGRAM o COBALT-60 IN WATER (pg. 2 of 2) 100 go . . o l l 60 -
. i ,
o ' a o ,
. o ,
- n. Il'
- 40 -
on o, , ou il H U o o n ol i o o" I , o ll 20 -
$5 o! '
o - o no o" o{ .
., ,I.
0 - -
-20 , , , , . .
1988 1989 1990 1991 1992 1993 1994 1995 m Tli3 Sigma o EPAi3 Sigma
O O D EPA CROSS CHECK PROGRAM COBALT-60 IN WATER (pg 1 of 2) 100 , 80 - e .
. i i i ,
60 - - e. e <> , 2
- D 40 --
O " t <
& I. T l' {
g , l, i t i , - E A i I - fn ' ' 20 - ' ' f ' ~ n, i 8 li i l' m .. li i i l ' { ,
<1 < .
1 0 - o e o - - '- t 1
-20 . . . . . .
1981 1982 1983 1984 1985 1986 1987 1988 f n Tii3 sigma o EPA 13 sigma i
. . +_ _ - - -m , __________-____________________.____,~-..ws - - '
e-- _+.--tw _+u_w-u -s-, _..-v+ -. --,---w er., m _.----_-.-2_ .-w,_ =m _ _ .m .
O. O O EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 2 of 2) 100 30 . . 60 - l l , 6 , 3 40 -
<, ,, a>' ',, -
U b 1 1 '
< >l l m 5 < >
i ' I l ' l
- a. l l . <,
i l >., '
. l l <
g , 1 1 j >q 20 - 'i ' q i < > 1 < i-g ' 4 , i ' s , , < ,j i
- d q , <>
g 0 - -
-20 , , , , . . , . , .
1988 1989 1990 1991 1992 1993 1994 1995 i a Tli3 Sigma o EPAi3 Sigma %.-.~.__- _ . . _ , _ . - . . _ . - _ _ - . _ . . _ . _ _ - - _ . _ , _ _ _ , _ _ . - _ . _ _ _ _ . . . _ , , ._. ..
.-_.,.-.._....~ .,_ _ _,. _ _ _. ,__.. _,._ , .__ _ .... .,,'._._....-,,,,_......._.,,._..__.,-,.-_.s .m._'.....
O O OL EPA CROSS CHECK PROGRAM CESlUM-134 IN WATER (pg.1 of 2) 100 80 - . a 60 - i l
% '1 <
_ t . . .
- 40 -
,, t ,
L) < . . . i .
< , i , l!
$ L I
i
' ll
.. j f< ,' ll 20
' t ,
~
< l, i
[i < i i O - - - - -
-20 , , , , , ,
1981 1982 1983 1984. 1985 1986 1987 1988 .I n Tli 3 sigma o EPA 13 sigma
- ~
O O O. EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 2 of 2) 120 100 - . i 1 1 i 80 - - - i 60 - m si
. - l i.
3 <>
< i
- 1. i i .
F ' ' h* 40 - < i <>
. '. i l si . o.
l l .. .. ,, ., , , ,
>i , i ri l l l ,
20 - < ' I ri
' ' i p- .
' i <i l l l
g , , <
>f ,_
,p u
;,, ,, i
, ,, " ,i
< > < >. <> n ,
0 - - -
-20 . . .
. . , , . , , j 1988 1989 1990 1991 1992 1993 1994 1995 m Tli3 Sigma o EPAi3 Sigma
,-,w..w -n, _ - , - , - ,,,,----,,,,e,- -n-u, .-~--a, ,+m-,, ,em y ,,,,,an.,-n.--,n-,,,,,..-,a-,.w,-_,,,.,.,--a,.,,,---s ,- ,n,,4,.,.e ,-e,..,< .,,-e> -,m.,e-,, ,ve-- , ,,...e-a, - - - , _ - . , -,
l O O O I l l EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg.1 of 2) 80 l l 60 -
$ 40 -
g , 5 - i fL . l . I O ' '
< \
' C li
- n. [
M g 20 - k i , a g o < [ '18 .. .
., i. ; , < { ,,,, .s.i1 0 - - . .
-20 , , , , ,
1981 1982 1983 1984 1985 1986 1987 o Tli 3 sigma o EPA 13 sigma
. -- -,, ., . - . . . .- - - _ - _ . -- .-. ~ _ . . . - . . - . . - . . _ . . . . . . -
l i O O 0; I i EPA CROSS CHECK PROGRAM I l i STRONTIUM-89 IN WATER (pg. 2 of 2) j 80 80 - - 1 l 1, ,..I .
. . 1 1 .
40 - I I i ' < it *
.. I I , ,
, i
' }
=
yp I ,. , i . y 3 5 . , i ., .' . . i i l i i
@ U !
,j
- n. to - ' > 1 < >
g i n, -
\ .
ji ! , i n 'i > <> .
. - t > .I , t h , .
1 y . . 1 g I I li T u n gi m > . 0 - - 4
-20 . , , . . . , , . . . . . . , , . ,
1984 1985 1988 1987 1988 1989 1990 1991 1992 1993 1994 1995 s Tli3 Sigma o EPAi3 Sigma _ . _ _ _ . . _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ - ._ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ _ _ _ = _ _
b O O D. .7 t I EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg.1 of 2)- 100 . M - 4
- 80 - -
i > S- , S ,
=
C 40 -
.. . *l, -
g
'i ,
.. i
. l l
'!I I pq p 1 6 >
'j l > *
- l' ' -
20 1 'l l l p l l,
.l >
l :. [' I . . , , D .D .l 0 2" - .- - ,
-20 , , ,
1981 1982 1983 1984 1985 a Tli3 sigma
- EPA f3 sigma
o o 9 EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER (pg.1 of 1) 80 60 - . 40 i . . , , if ' e s i 3 t, i i.
..l f . ,
r E U 1r i l, 'i ili. W >. O E 20 -
, ,,. ii ..
i , .. g i, .. q i .
- q , ,p n. ..
.' s.- o . . .
s,r ,
.[ .p i , . <,-
i ,
.< , ,i ,
..ll ,i , ;
n . , 0 - g' ' 1981 1983 1985 1987 1989 1991 1993 1995 m Tli3 Sigma o EPAi3 Sigma _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ , __ __}}