ML20217H486
| ML20217H486 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1997 |
| From: | Breeden J, Larry Jones, Matthews W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 98-239, NUDOCS 9804290396 | |
| Download: ML20217H486 (123) | |
Text
e VIHOINIA ELECTHIC AND POWER COMI%NY RICIIMOND,VIHOINIA 202 61 April 24,1998 United States Nuclear Regulatory Commission Serial No.98-239 Attention: Document Control Desk NAPS /JHL Washington, D. C. 20555 Docket Nos.
50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Pursuant to Technical Specification 6.9.1.8, enclosed is the Annual Radiological Environmental Operating Report for North Anna Power Station Units 1 and 2 for 1997.
If you have any questions or require additional information, please contact us.
Very truly yours, Ud.4/
W. R. Matthews Site Vice President Enclosure Commitments made by this letter: None cc:
U. S. Nuclear Regulatory Commission l
Region 11 Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 l
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Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station b0
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9804290396 971231 PDR ADOCK 0500o338 R
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION Radiological Environmental Monitoring Program.
January 1,1997 to December 31, 1997 Prepared by l
l VIRGINIA ELECTRIC AND POWER ConfPANY and TELEDYNE BROWN ENGINEERING I
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Annual Radiological Environmental Operating Report j
North Anna Power Station January 1,1997 to December 31,1997 I
Prepared by-Q
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James B. Breeden Supervisor Radiological Analysis and Material Control
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LuthgY B. Jones Supervisor He(althPhysics Technical Services l
i Approved by:
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~ /[lan H. Stafford l
Superintendent Radiological Protection l
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Table Of Contents
!'C Section Title Page Preface..........................................................................................6 Executi ve S ummary......................................................................... 7 i
I I.
Introd u c tion................................................................................. 10 l
II.
S a m plin g An d A n aly sis Progra m.......................................................... 13 III.
Program Exceptions........................................................................30 IV.
Sununary And Discussion Of 1997 Analytical Results................................ 32 A.
Airborne Exposure Pathway........................................................ 3 3 1.
Air Iodine /Particulates......................................................... 33 l
2.
Precipi tation................................................................... 3 5 3.
Soil...........................................................................36 B.
Waterborne Exposure Pathway..................................................... 36 1.
G round/Well Water............................................................ 3 6 2.
Ri ver Wate r..................................................................... 3 6 3.
S urface Water.................................................................. 3 6 i
l C.
Aquatic Exposure Pathway........................................................ 3 8 l.
Sedimen t/S il t................................................................... 3 8 2.
S hore li ne S o i l................................................................. 4 2 D.
Ingestion Exposure Path way...................................................... 42 i
1.
Milk..........................................................................42 2.
Fish............................................................................43 3.
Fo o d / V e g e t a t i o n........................................................... 43 E.
Direct Radiation Exposure Pathway.............................................. 44 1.
TLD D o s i m e t e rs............................................................ 44 V.
Con cl u s i o n............................................................................. 4 i
I e
8)
Table Of Contents (Continued)
Seetion Title Par.e VI.
R e fe r e n c e s.............................................................................
VII.
A ppe n d ice s............................................................................. 5 0 Appendix A - Radiological Environmental Monitoring................................ 50 Program Annual Summary Tables - 1997 Appendix B - Data Tables................................................................ 57 Appendix C - Land Use Census - 199 7............................................... 8 0 I
Appendix D - Synopsis of Analytical Procedures...................................... 83 Appendix E - Interlaboratory Comparison Program.................................. 94 List of Trendine Graphs 1.
Gross Beta in Air Particulates............................................................. 34 2.
Tritium in River Water.................................................................. 3 1
3.
Tri tiu m in S u rface Wat e r..........................................
.............37 4.
Cobalt-58 in Sediment Silt..
.......................................................37 5.
Cobalt-60 in Sediment Silt...............................................................39 6.
Cesium-134 in Sediment Silt......................................................... 39 7.
Cesium-137 in Sediment Silt............................................................ 40 8.
Ce s i um-13 4 i n Fish...............................................
......................40 9.
Ce sium-13 7 i n Fi sh................................................................. 41 10.
Environmental Radiation - TLDs..................................................... 41 Ov i
+
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p List of Tables Table Page 1.
Radiological Sampling Station Distance and Direction from Unit 1..............................................................................15 l
2.
North Anna Power Station Sample Analysis Program............................... 27 3.
REMP Exceptions for Scheduled Sampling and Analysis During 1997....................................................................31 Appendix B Tables B-1 Iodine-131 Concentration in Filtered Air............................................... 57 i
B-2 Concentrations of Gross Beta in Air Particulates...................................... 59 B-3 Gamma Emitter, Strontium 89, and Strontium 90 Concentrations in Air Particulates..................................................... 63 B-4 Gamma Emitter and Tritium Concentration in Precipitation........................... 66 i
B-5 Gamma Emitter Concentration in Soil................
.........................66 i
i B-6 Gamma Emitter, Strontium, and Tritium Concentrations in Ground and Well Water............................................................. 67 B-7 Gamma Emitter, Strontium, and Tritium Concentrations in Rive r Wate r............................................................................... 67 B-8 Ganuna Emitter, Strontium, and Tritium Concentrations i n Surface Water......................................................................... 68 B-9 Gamma Emitter, Strontium, and Tritium Concentrations in Surface Water S tate-Split Samples................................................. 69 B-10 Gamma Emitter Concentrations in Sediment Silt....................................... 70 B-11 Gamma Emitter Concentrations in Shoreline Soil................................... 70 B-12 Gamma Emitter Concentrations in Milk................................................. 71 B-13 Gamma Emitter Concentrations in Fish......
....................................73 B-14 Gamma Emitter Concentrations in Food / Vegetation................................... 74 B-15 Direct Radiation Measurements Q u a rte rly A nn u al TL D R e s ult s.......................................................... 76 B-16 Direct Radiation Measurements Sector Quarterly TLD Results........................
...............................77 e
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Preface This report is submitted as required by Technical Specification 6.9.1.8, Annual Radiological Environmental Operating Report for North Anna Power Stations, Units 1 and 2, j
Virginia Electric and Power Company Docket Nos. 50-338 and 50-339.
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Executive Summary O
This document is a detailed report on the 1997 North Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31,1997 in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated, and summarized. The REMP is designed to ensure that radiological effluent releases are As Low As is Reasonably Achievable (ALARA), no undue environmental effects occur, and the health and safety of the public is protected. The program also detects any unexpected environmental processes which could allow radiation accumulations in the environment or food pathway chains.
Radiation and radioactivity in the environment is constantly monitored within a 25 mile radius of the station. Virginia Power also collects samples within this ama. A number of sampling locations for each medium were selected using available meteorological, land use, and water use data. Two types of samples are obtained. The first type, control samples, are collected from areas that at : beyond the measurable influence of North Anna Nuclear Power Station or any other nuclear facility. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station, can thus be compared to the p
environment surrounding the nuclear power station. Indicator samples are the second sample type J
obtained. These samples show how much radiation is contributed to the environment by the plant.
Indicator samples are taken from areas close to the station where any plant contribution will be at the highest concentration.
Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a " pre-operational baseline."
Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, other causes such as the Chernobyl accident, or natural variation.
Teledyne Brown Engineering provides sample analyses for various radioisotopes as appropriate for each sample media. Participation in the Environmental Protection Agency's (EPA)
Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods.
Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for Q
radiologicalenvironmental monitoring must be able to detect specified minimum Lower Limits of b
7
l Detection (LLD). This ensures that analyses are as accurate as possible. Samples with extremely O
1 w levels f radiati n whi h cann t be detected are therefore reponed as being below the LLD.
The NRC also mandates a " reporting level." Licensed nuclear facilities must report any releases equal to or greater than this reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level.
Analytical results are divided into five categories based on exposure pathways: Airborne, waterborne, aquatic, ingestion, and direct radiation. Each of these pathways is described below:
The airborne exposure pathway includes airborne iodine, airborne particulate, precipitation, and soil samples. The overall 1997 airborne results were very similar to previous years and to preoperational levels. No increase was noted and there were no detections of fission products or other man-made isotopes in the airborne particulate media during 1997.
The waterborne exposure pathway includes ground /well water, river water, and surface water samples. No man-made or natural isotopes were detected in Lake Anna surface water except for tritium. The average tritiurn activity in 1997 was 16% of the NRC reporting level. This has essentially remained unchanged from 1995 levels.
The aquatic exposure pathway includes sediment / silt and shoreline samples. North Anna sediment contained some cesium-137. During the preoperational period, cesium-137 was detected. Sediment contamination, however, does not provide a direct dose
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pathway to man. In shoreline soil, which may provide a direct dose pathway, only
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cesium-137 was detected. Cesium-137 levels were 159 pCi/kg in 1997.
The ingestion exposure pathway includes milk, fish, and food / vegetation samples.
Iodine-131 was not detected in any 1997 milk samples. Although cesium-137 has been detected in the past, it was not detected in 1997 milk samples. Strontium-90 was detected at levels comparable to 1989, and lower than preoperational years. Both strontium-90 and cesium-137 are attributable to atmospheric nuclear weapons testing in the past. Naturally occurring potassium-140 was detected it normal environmental levels.
Fish samples during 1997 contained cesium-137 at a slightly higher activity than preoperational levels. Steam generator rf. pairs and better liquid waste processing, however, have reduced these activity levels from previous years. Vegetation samples were statistically similar to both control and preoperational levels.
The direct radiation exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained essentially the same since the preoperational period in 1977.
During 1997, as in previous years, operation of the North 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 site boundary due to liquid and gaseous effluents released from the site during 1997 was 0.29 millirem. For reference, this
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dose may be compared to the 360 millirem average annual exposure to every person the United O
States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes less than 0.1%.
These results demonstrate not only compliance with federal and state regulations, but also demonstrate the adequacy of radioactive effluent control at the North Anna Nuclear Power Station.
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VIRGINIA ELECTRIC AND POWER COMPANY O
xORru AuxA power srArIOx RADIOLOGICAL ENVIRONMENTAL OPERATING PROGRAM 1.
INTRODUCTION The operational radiological environmental monitoring program conducted for 1997 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 1,1997 through December 31,1997 are summarized.
A. The North Anna Power Station of Virginia Electric and Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles south west of Fredericksburg, Virginia.
I 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.
Q B. The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license for North Anna Power Station includes Technical Specifications which address the release of radioactive effluents.
Inplant monitoring is used to ensure release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in North Anna Power Station Offsite Dose Calculation Manual (ODCM).
C.
Virginia Electric and Power Company is responsible for collecting the various indicator and control environmental samples. Teledyne 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 Q
occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This preoperational data is compared with data collected t
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l during the operational phase to assist in evaluating the radiological impact of the plant O
overatioa.
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D.
Occasional samples of environmental media show the presence of man-made isotopes. As l
a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed l
in the USNRC Regulatory Guide 4.8 and North Anna's ODCM. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".
I E.
This report documents the results of the Radiological Environmental Monitoring Program l
for 1997 and satisfies the following objectives of the program:
1.
Provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation.
2.
Supplements the radiological effluent monitoring program by verifying that
'p radioactive effluents are within allowable limits.
!0 3.
Identifies radioactivity changes in the environment.
I 4.
Verifies that the plant operations have no deu; mental effect on the health and safety of the public.
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SAhfPLING AND ANALYSIS PROGRAh!
O A.
Sampling Program i
1.
Table I summarizes the sampling program for North Anna Power Station during 1997. Figure 1 indicates the locations of the environmental monitoring stations.
2.
For routine TLD measurements, two dosimeters made of CaSO4:Dy in a teflon card i
are deployed at each sampling location. Several TLDs are co-located with NRC and Commonwealth of Virginia direct radiation recording devices, t
3.
In addition to the Radiological Environmental Monitoring Program required by Nonh i
l Anna Technical Specifications, Virginia Electric and Power Company (VEPCO) splits l
samples with the Commonwealth of Virginia. All samples listed in Table I are shipped to Teledyne Brown Engineering located in Westwood, New Jersey.
i 4.
All samples listed in Table 1 are taken at indicator locations except those labeled l
" control".
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Map Environmental Sta Map Environmental Sta Designation Identification Designation Identification 1
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B. Analysis Program 1. Table 2 sununarizes the analysis program conducted by Teledyne Brown Engineering for North Anna Power Station during 1997, i I O 26
TABLE 2 (Page 1 of 3) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2mRi2mR mR/std. month Dosimetry (TLD) (84 Routine Station TLD's) 12 Station TLD's Annually Gamma Dose 2mRi2mR mR/std. month 3 Airborne Weekly I-131 0.07 pCi/m Radiolodine 3 Airborne Weekly Gross Beta 0.01 pCi/m Particulate 3 Quarterly (a) Gamma Isotopic pCi/m Cs-134 0.05 Cs-137 0.06 Annually St.89 (c) pCi/m3 (2nd Quarter Sr-90 (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 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a) Tritium (H-3) 2000 pCi/l 2nd Quarterly Sr-89 (c) pCi/l Composite Sr-90 (c) l l l LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed. qQ (a) Quarterly Composites of each location's samples are used for the required analysis. (b) LLD for non-drinking water is 10 pCi/ liter. (c) There are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering. 27 1
TABLE 2 (Page 2 of 3) O-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 l Cs-137 18 I Ba-140 60 La-140 15 Quarterly (a) Tritium (H-3) 2000 pCi/l 2nd Quarter Sr-89 (c) pCi/l Sample Sr-90 (c) Ground Water Quarterly (a) Gamma Isotopic pCi/l l - O (Well Water) 2nd Quarter Mn-54 15 Composite Fe-59 30 Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 1(b) Cs-134 15 l Cs-137 18 1 Ba-140 60 j La-140 15 4 l Quarterly (a) Tritium (H-3) 2000 pCi/l l 2nd Quarter Sr-89 (c) l Composite Sr-90 (c) l Aquatic Semi-Annually Gamma Isotopic pCi/kg (dry) Sediment Cs-134 150 Cs-137 180 l Annually Sr-89 (c) pCi/kg (dry) l Sr-90 (c) l Precipitation Monthly Gross Beta pCill Semi-Annual Gamma Isotopic pCi/l Composite LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed. (a) Quarterly Composites of each location's samples are used for the required analysis. (b) LLD for non-drinking water is 10 pCi/ liter. (c) There are no required LLD's for strontium-89/90. LLD's are those achieved by Tcledyne Brown Engineering. 28
TABLE 2 (Page 3 of 3) O noara AxxA eowEa STArios SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS l Shoreline Soll Semi-Annual Gamma Isotopic pCi/kg (dry) l Cs-134 150 Cs-137 180 i l Annually Sr-89 (a) J Sr-90 (a) { Soll once per 3 yrs. Gamma Isotopic pCi/kg (dry) Cs-134 150 Cs-137 180 Once per 3 yrs. Sr-89 (a) pCi/kg (dry) Sr-90 (a) Milk Monthly I-131 1 pCi/l Monthly Gamma Isotopic pCi/l Cs-134 15 ) Cs-137 18 { O' Ba-140 60 j La-140 15 Quarterly Sr-89 (a) pCi/l Sr-90 (a) Fish Semi-Annual Gamma Isotopic pCi/kg (wet) Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Monthlyif Gamma Isotopic pCi/kg (wet) (Hroadleaf available or Vegetation) at harvest Cs-134 60 Cs-137 80 I-131 60 pCi/kg (wet) l Note: This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be iden.tified and reported. LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by 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 Tcledyne Brown Engineering. ~ 29
O i l l l lO 111. raocaiu excerrious O l 30 l 1
r Appendix B j REMP Exceptions For Scheduled O samr na and snaissis vacina 1997 norzh anna u l Location Description Date of Sampling Reason (s) for Loss / Exception l STA-14 Food / Vegetation 05/21/97 LLD for I-131 not met because the first analysis produced low chemical yield (11.8). Analysis was repeated but unable to meet LLD due to the i short half-life ofI-131. STA-16 Food / Vegetation 08/20/97 LLD for I-131 not met. Sample not received at lab until 15 days after collection. Sample was counted 4 times but could not meet SPEC. i STA-Surface Water 09/15/97 LLD for I-131 not met due to the long lapse of W27 time from collection to receipt at laboratory. STA-33 Surface Water 07/31/97 LLD for I-131 not met due to the long lapse of 09/15/97 time from collection to receipt at laboratory. l l0 I O 31
O IV.
SUMMARY
AND DISCUSSION OF 1997 ANALYTICAL RESULTS hO 32
I 1 I V. Summary And Discussion of 1997 Analytical Results O l U Data from the radiological analyses of environmental media collected during 1997 are i tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Quality Assurance Manual and are explained in the Teledyne Brown Engineering Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Appendix D. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Appendix E. Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-an measurement methods. The "less than" values in the data tables were calculated for each specific analysis and are dependent on sample size, detector efficiency, length of counting time, chemical yield, when appropriate, and the radioactive decay factor from time of counting to time of collection. Teledyne Brown Engineering's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, Radiological Monitoring Exceptable Program (November 1979, Revision 1) and the ODCM. The following is a discussion and summary of the results of the environmental measurements taken during the 1997 reponing period. A. Airborne Exposure Pathway 1. Air Iodine /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 detection. For air particulates, gross beta activity was observed in all fifty-two control samples with an average concentration of 0.023 pCi/m3 and a range of 0.010 to 0.081 pCi/m3. The average measurement for the indicator 3 locations was 0.021 pCi/m3 with a range of 0.007 to 0.043 pCi/m. The results of the l gross beta activities are presented in Table B-2. The gross beta activities for 1997 were comparable to levels measured in the 1982-1996 period. Prior to that period the gross beta O activities were higher due to atmospheric nuclear weapons testing performed in other 33
TRENDING CRAPH-1: CROSS BETA IN AIR PARTICULATES l t i l [ 0.1 __________y l f l 1 > 0.01+ - - - - - - - - - - - - - - - - - -
4 1
1 O.001 n o n,n o n n n n i n n n n n o n n n.,, n,, n n,,, u n,, n n o, n. n.n n, u n n i n i n.. n ni n.. n n u n n. i n n n n i n i n n o.n, 1986 1987 1987 1988 1989 1989 1990 1991 1991 1992 1993 1993 1994 1995 1995 1996 1997 1997 ) Control-Sta-24 --*-- Indicator --e Average Pre op - + Required LLD's O TRENDING GRAPH 2: TRITlUM IN RIVER WATER-STATION 11 10000 y +--------------------
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g 1000-1 100-BI '; i 1 i 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 l Durin9 the preoperational period, tritium was not detected in the samples analyzed. Tritium - + - Required LLD's 34 l t
countries. During the preoperational period of July 1,1974 through March 31,1978 gross
- O beta activities ranged from a low of 0.005 pCi/m3 o a high of 0.75 pCi/m3, t
Air particulate filters were composited by locations on a quarterly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table B-3. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in all 48 composite samples. The average measurement for the control location was 0.117 pCi/m3 with a range of 0.052 to 0.175 pCi/m3. The indicator locations had an average concentration of 0.118 pCi/m3 and a range of 0.054 to 0.181 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 3 concentration of 0.004 pCi/m. Potassium-40 was detected in five indicator samples with an average concentration of 0.007 pCi/m3 and a range of 0.003 to 0.018 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, rtthenium-106, cesium-137, cerium-141 and cerium-144. 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 a; the control station. 2. Precipitation A sample of rain water was collected monthly at station Ol A, on site,0.75 miles,138 degrees SE and analyzed for gross beta activity. The results are presented in Table B-4. The average gross beta activity for 1997 in the twelve samples was 3.5 pCi/ liter with a range from 1.5 to 9.6 pCi/ liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritium. Beryllium-7 was not detected during 1997. All other gamma emitters were below their detection limits. Tritium was not detected in the semi-annual composite samples. These results were comparable to or lower than those measured j in 1986 thru 1996. During the preoperational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface, thus a direct comparison can not be made to the 1997 period. During the preoperational period, tritium was measured in over half of the few quarterly composites made. The tritium activity ranged from 100 to O 330 c i/iiter. c 35
3. Soil q V Soil samples are collected every three years from twelve stations. Since they were collected in 1995 they were not collected in 1997. B. Waterborne Exposure Pathway 1. Ground /Well Water Water was sampled quarterly from the on site well at the metrology laboratory. These samples were analyzed for gamma radiation and for tritium. The results are presented in Table B-6. No gamma emitting isotopes were detected during 1997. The second quarter sample was analyzed for strontium-89 and strontium-90. There were no detections of these isotopes above the detection level. Tritium was measured in one sample with a cor. centration of 240 pCi/ liter. No gamma emitting isotopes were detected during the preoperational period. Tritium was measured 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 miles downstream from the discharge lagoon,128 degrees SSE. The results are presented in Table B-7. The samples were analyzed by gamma spectroscopy monthly. The samples were analyzed for tritium quarterly on a composite sample. The second quarter samples were analyzed in addition for strontium-89 and strontium-90. Potassium-40 was not detected during 1997 and all other gamma emitters were below the detection level. No detections of stronnum-89 or strontium-90 occurred. Tritium was measured in all four samples with an average level of 2650 pCi/ liter and a range of 2300 to 3000 pCi/ liter. This is lower than the average level measured in 1996 of 2950 pCi/ liter and a range of 2400 to 3800 pCi/ liter. No river water samples were collected during the preoperational period. 3. Surface Water Samples of surface water were collected monthly from two stations. Station 08 is at the discharge lagoon,1.1 miles,148 degrees SSE on Lake Anna. Station 09A is located 12.9 (') miles WNW. The samples were analyzed for iodine-131 by radiochemical separation. No U 36
i TRENDING GRAPH - 3: TRITIUM IN SURFACE WATER - STA 08 10000, O ..g 1000 - 1 ____________j 100 ,4,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, 1/77 1/79 1/81 1/83 1/85 1/87 1/89 1/91 1/93 1/95 1/97 - Tritium Required LLD's --A Average Preep l TRENDING GRAPH -4: COBALT-58 IN SEDIREENT SILT l 1000 i W 100 : g 5 5 -a 10 : 1 0345 0346 0447 0348 0449 03/90 03/91 0342 03 S3 1043 0844 8/95 846 8/97 During the preoperational period', cobalt-58 was not detected in the samples analyzed. f -e-Station-8 Station 09 Control Sta 09A -+- Station-11 I 37 i
i iodine was detected in the 24 samples analyzed. The results are presented in Table B-8. The samples were also analyzed by ganuna ray spectrometry. No gamma emitters were above their detection level at either sampling station. A quarterly composite from each station was prepared and analyzed for tritium. The tritium i activity at station 08 for the quarterly composites was at an average level of 3100 pCiMiter with a range of 2400 to 3600 pCiMiter. The tritium level had been increasing since the middle of 1978 when the average level was below 300 pCiMiter. However, during 1997 the re.sults were within the same range as those measured in 1986 thru 1996. During the preoperational period tritium was measured in several samples with concentrations between 90 and 250 pCiMiter. Tritium was not detected at station 09A. l Samples of surface water were collected by the Commonwealth of Virginia from two stations. Station W-33 is located at the discharge lagoon while station W-27 is located on the North Anna River at the RT. 208 Bridge, which is upstream of the site. Twenty-four samples were collected and analyzed by gamma ray spectroscopy. The results are presented in Table B-9. All gamma emitters were below their detection levels. Four samples from each station were analyzed for tritium during 1997. The average O activiir at station w-33 in all samples was 2650 pCiniter with a range of 2300 to 3400 pCiMiter. This is slightly lower than the 2985 pCiMiter measured during 1996 at this station. Tritium was measured in two samples at station W-27 with an average activity of 1600 pCiMiter and a range of 1300 to 1900 pCiMiter. This is higher than the average of 800 pCiMiter measured at station W-27 during 1996. C. Aquatic Exposure Pathway 1. Sediment / Silt i Sediment samples were collected during February and August from each of three 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 65 pCi/kg (dry weight) and a range from 48.0 to 90.1 pCi/kg (dry weight). The highest reading for cesium-137 was obtained from station 11 located 5.80 miles SSE. Naturally occurring potassium-40 was observed in all six samples with an average activity of 12483 pCi/kg (dry weight) and a range from 2500 to 18200 pCi/kg (dry weight). 38
TRENDING CRAPH - 5: COBALT 40 IN SEDIMENT SILT 1000-0 100: E N ../\\. c g 10: l 3 l a l 1 03/85 03/86 03/87 0328 04/89 03/90 03/91 03/92 03/93 10/93 06S4 08/95 08/96 08/97 l -s-Station-8 -*- Station-09 + Control-Sta-09A --+- Station-11 1 l During the preoperational period, cobalt-60 was not detected in the samples analyzed. TRENDING GRAPH - 6: CESIUM-134 IN SEDIMENT SILT lO 1000.: k M ir - + v ~ g 100 _ Le 6,'. '^ 3 l 10 : l 5 l ~ l 1 i i i i i e i e i i e i i i e i 03/85 03/86 03/87 03/88 04/89 03/90 03/91 03/92 03/93 10/93 08S4 08SS 08/96 08/97 f -- 5-- Station-8 --* - Station 09 -- Control-StaGA 0 Station-11 --+- Required LLD's During the preoperational period, cesium-134 was not detected in the samples analyzed. 39
TRENDING C RAPH - 7: CESIUM-137 IN SEDIMENT SILT 10000_ 10 1000 E y _____A g +. 2 100 E3o 10-1 i i i i i i i i i i i i i i i 3/85 3/86 3/87 3/88 3/89 3/90 3/91 3/92 3/93 10/93 8/94 08/95 08/96 08/97 --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. +___ l. .....________._.4 100-- i N t E 4 \\ t T Pl 105 A m q l 1 i.. i.. ...ii >>ie i i i.... .iie i.. ie i ii I 4/80 4/83 4/85 10/86 8/87 3/88 12/88 8/89 10/90 4/92 10/93 03/95 08/96 -- G-- Station-08 --*- Station @ Control-Sta-25 -+ Required LLD's O-During the preoperational period, cesium-134 was not detected in the samples analyzed. Station 25 replaced station 09. 40
TRENDING CRAPH - 9: CESIUM-137 IN FISH 10000 1000 9 m - M +-- p 100 s 15E m 10 l l 1 5/80 5/83 4/85 8/86 7/87 4/88 12/88 10/89 10/90 10/91 4/93 8/94 03/96 --a-Station-08 -*- Station-09 Station-25 --A Average Pre-op -+- Required LLD i l I Station 25 replaced station 09. i 1 !l /' TRENDING GRAPH - 10: ENVIRONMENTAL RADIATON - TLD's 10 H l c .g_ - h w* d. 1 l E 1 \\ s 1 i 1/86 10/86 7/87 4/88 1/89 10/89 7/90 4/91 1/92 10/92 7/93 4/94 1/95 10/95 07/96 4/97 --G-- Environrnental TLD's --*- Sector TLD's -A Average Pre-op 41
f l Radium-226 was measured in all six samples with an average concentration of 1468 pCi/kg 1t-d (dry weight) and a range of 970 to 1990 pCi/kg (dry weight). Also naturally occurring, l thorium-228 was observed in all six samples with an average concentration of 978 pCi/kg l (dry weight) and a range of 580 to 1800 pCi/kg (dry weight). The August samples were analyzed for strontium-89 and strontium-90. There were no detections of strontium-89 or l strontium-90 in aquatic sediment / silt. 1 During the preoperational period sediment samples were analyzed by gamma ray l spectroscopy. Cesium-137 was measured in most of the samples with concentrations between 33 and 1210 pCi/kg (dry weight). Strontium-90 was measured in most of the samples with concentrations between 60 and 540 pCi/kg (dry weight). Strontium-89 was not measured. Potassium-40, radium-226, and thorium-228, all naturally occurring, were l measured at background levels. 2. Shoreline Soil A sample of shoreline sediment was collected in February and August from station 09,2.2 miles upstream of the North Anna Power Station. The samples were analyzed by gamma ray spectrometry. The results are presented in Table B-11. The naturally occurring nuclide ifq O potassium-40 was measured in both samples with an average activity of 1805 pCi/kg (dry weight) and a range of 770 to 2840 pCi/kg (dry weight). Cosmogenic beryllium-7 was not l measured during 1997. Thorium-228 was measured in both samples at an average of 244 pCi/kg (dry weight) and a range of 240 to 247 pCi/kg (dry weight). Radium-226 was measured in one sample with a concentration of 1160 pCi/kg (dry weight). Cesiurn-137, a fission product, was monitored in both samples with an average level of 159 pCi/kg (dry weight) and a range of 147 to 170 pCi/kg (dry weight). l The August sample was analyzed for strontium and there were no detections of strontium-89 or strontium-90. l D. Ingestion Exposure Pathway 1. Milk The results of the iodine-131 analysis of milk samples are presented in Table B-12. A sample was collected monthly from two stations. A total of 24 samples wee analyzed during 1997. There were no measurements of iodine-131 above the detection limits.The O miik samgics were ai e aneiyzed by 8amma ray specire copy end the resuits are aise 42
\\ presented in Table B-12. A total of 24 samples were analyzed. Naturally occurring Q potassium-40 was measured in all samples with an average of 1281 pCi/ liter and a range of 1020 to 1430 pCi/ liter. The fission product cesium-137 has been detected sporadically in i recent years and the activity has been attributed to global fallout from past atmospheric f weapons testing. However, cesium-137 was not detected at levels above LLD in any milk ) samples during 1997. All other gamma emitters were below their detection levels. A l quanerly composite was prepared from each of the two collection stations and analyzed for strontium-89 and strontium-90. Strontium-89 was not detected at levels above LLD in any 1 of the samples monitored. Strontium-90 was detected in the eight samples monitored with i an average level of 1.16 pCi/ liter and a range of 0.45 to 1.8 pCi/ liter. This is similar to r l activities determined in previous years and lower than the preoperational levels of 2.2 to i 5.4 pCi/ liter. 2. Fish Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. The results are presented in Table B-13. Eight samples of fish were collected during 1997. These samples were analyzed by gamma ray spectroscopy and the naturally l occurring isotope potassium-40 was found in all samples at an average of 1783 pCi/kg (wet l weight) with a range of 1050 to 2270 pCi/kg (wet weight). The fission product cesium-l 137 was measured in four samples at an average of 33.2 pCi/kg (wet weight) and a range of 24.7 to 37.4 pCi/kg (wet weight). During the preoperational period cesium-137 was l measured in one-fourth of the fish samples collected with concentrations between 31 and 66 pCi/kg (wet weight). All other gamma emitters were below their detection levels. 3. Food / Vegetation Thirty-five food samples were collected from five locations and analyzed by gamma l spectrometry. The results are presented in Table B-14. Naturally occurring potassium-40 l was monitored in all 35 samples with an average activity level of 13615 pCi/kg (wet l weight) and a range of 3640 to 25400 pCi/kg (wet weight). Cosmogenic beryllium-7 was detected in 33 of the 35 samples with an average concentration of 3588 pCi/kg (wet weight) and a range of 644 to 13200 pCi/kg (wet weight). Radium was measured in one sample with an activity of 1110 (wet weight). The terrestrial nuclide thorium-228 was detected in five samples at an average activity of 337 pCi/kg (wet weight) and a range of 114 to 740 O eCi/ks (wet weishi). l 43 L
l l (] Neither cesium-134 nor cesium-137, both of which are fission products, were detected at levels above LLD during 1997, though cesium-137 has been detected in some samples at l low-levels in previous years. Cesium-137 was measured in broadleaf garden vegetation during the preoperational period with concentrations between 53 and 98 pCi/kg (wet 1 weight). E. Direct Radiation Exposure Pathway l 1. TLD Dosimeters Thermoluminescent dosimeters (TLDs) determine environmental radiation doses and the results are presented in Table B-15. Individual measurements of external radiation levels in the environs of the North Anna site had an average dose of 6.1 mR/ standard month with a range of 3.6 to 9.1 mR/ standard month. This is comparable to the preoperational range. The control station, No. 24, had an average reading of 5.8 mR/ standard month with a range of 4.6 to 6.5 mR/ standard month. Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North O Anna site. Two badges are placed at each location. The results are presented in Table B-
- 16. The average level of the 32 locations (two badges at each location) was 6.6 mR/ standard month with a range of 3.9 to 10.1 mR/ standard month, The eight control TLDs, collected quarterly from four locations, showed an average reading of 5.7 mR/ standard month with a range of 3.9 to 7.6 mR/ standard month. During the preoperational period (starting 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.
1 44 l
O l O V. CONCLUSIONS O l t
r 1 V. Conclusions OV l The results of the 1997 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 sununary. Airborne Exposure Pathway Air particulate gross beta concentrations of all the indicator locations for 1997 followed the gross beta concentrations at the control location. The gross beta concentrations were comparable to levels observed since 1982 except for a five week period in 1986 which was influenced by the l Chernobyl accident. Gross beta concentrations in the preoperational period were highly variable, ranging from 0.0043 to 0.75 pCi/ cum, due to occasional atmospheric nuclear weapons tests. Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). There were no detections above the LLD for fission products nor other man-made isotopes in the particulate media during 1997. Iodine-131 was not detected in the charcoal filters analyzed during 1997. l A precipitation sample was collected monthly during 1997 and analyzed for gross beta activity. All the gross beta activities were comparable to those measured in previous years. During the preoperational period the average gross beta activity was 0.92 pCi/ 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 reporting period in 1997. During the preoperational period the average tritium activity was 165 pCi/ liter. Waterborne Exposure Pathway No man-made or naturalisotopes were monitored in the surface water of Lake Anna except tritium. The average tritium activity during 1997 at the waste heat treatment facility was 3100 l pCi/ liter which is 16.0% of the reporting level for a water sample. In 1996 the tritium level was 3150 pCi/ liter. The preoperational level was 150 pCi/ liter and has been rising since 1977. Tritium was not measured upstream of the site, at station 09A. The samples of surface water collected by the Commonwealth of Virginia at the waste heat treatment facility had similar tritium results with a measurement of 2650 pCi/ liter as compared to 2985 pCi/ liter for 1996. The upstream location had two measurements at an average activity of O 16oo ci'iiter as compared to 8oo ci'iiter for 1996. No 8amma emitii"8 >otone= *ere detected. e r i 45
I i O River water collected from the North Anna River,5.8 miles downstream of the site had an average tritium level of 2650 pCi/ liter. The average tritium in 1996 had been 2950 pCi/ liter. No gamma emitters were detected. Ground water from the environmental well on site contained no gamma emitters. There were also no detections of tritium in ground /well water during 1997. Aquatic Pathway l l Sediment / silt samples provide a sensitive indicator of discharges from nuclear power stations. The sediment from North Anna environmental samples indicated that one man-made isotope was present. Cesium-137 was detected in three samples at three locations. During the l preoperational period, cesium-137 was measured in samples of aquatic sediment. Sediment l contamination does not provide a direct dose pathway to man. The samples of shoreline soil monitored downstream of the site contained no measurement l of cesium-134. Cesium-137 was measured in both samples at an average level of 159 pCi/kg which was lower than the average of 510 pCi/kg detected in 1996. q IO Ingestion Pathway Iodine-131 was not detected in any of the twenty-four milk samples using the l radiochemical separation method. Although cesium-137 has been detected occasionally in previous years and attributed to past atmospheric nuclear weapons testing there were no detections during 1997. Strontium-90 was measured in all eight milk samples. Strontium-90 is attributed to past atmospheric nuclear weapons testing. No strontium-89 was detected in any of the milk samples. Naturally occurring potassium-40 was measured in all the milk samples at normal environmental l levels. Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples during 1997 showed the presence of one man-made isotope, cesium-137. This isotope was at an activity level somewhat higher than preoperational levels but statistically similar to levels in 1987 through 1996. Only cesium-137 was measured in preoperational environmental fish samples. Due to primary and secondary steam generator problems experienced f at North 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 V 46 l
levels in effluents and thus decreased activity levels are now being observed in the fish. The O average level of activity during 1997 of cesium-137 was 1.7.% of the reporting level. l l No vegetation samples contained the man-made isotope cesium-137 during 1997. Cesium-137 has been measured in the past and in preoperational samples. l Direct Exposure Pathway } The direct exposure pathway as measured in the environment of the North Anna site by thermoluminescent dosimetry has remained essentially the same since the preoperational period in 1977 at 6 milliroentgens per month or 0.2 milliroentgens per day. The average dose levels monitored have shown a normal fluctuation about these levels which are less than the estimated whole body dose due to natural terrestrial and cosmic radiation and the intemal dose from natural radionuclides. Program Conclusions 1 The results were as expected for normal environmental samples. Naturally occurring { activity was observed in sample media in the expected activity ranges. Occasional samples of O n;uly all media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence. As a method of referencing the measured radionuclide' concentrations in sample media to the dose consequence, the data may be cornpared to the Reporting Level Concentrations listed in the Offsite Dose Calculation Manual. These concentrations are bar.ed upon 25% of the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion "As Low as is Reasonably Achievable." Based upon the evidence of the er:vironmental monitoring program the station is operating within regulatory limits. Thus, no unusual radiological characteristics were observed in the environs of the Nonh Anna Nuclear Power Station during 1997. l \\ O l 47 l J
O O v1. aercaexces l O 48
VI. References 1% V i I 1. Virgir.ia Electric and Power Company, North Anna Power Station Technical Specifications, Units 1 and 2. 2. Virginia Electric and Power Company, Station Administrative Procedure, VPAP-2103, "Offsite Dose Calculation Manual. 3. Title 10 Code of Federal Regulation, Part 50 (10CFR50), " Domestic Licensing of Production and Utilization Facilities." 4. United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," October,1977. 5. United States Nuclear Regulatory Commission, Regulatory Guide 4.8 " Environmental Technical Specifications for Nuclear Power Plants," December,1975. 6. USNRC Branch Technical Position, " Acceptable Radiological Environmental Monitoring Program," Rev.1, November 1979. 7. NUREG 0472, " Radiological Effluent Technical Specifications for PWRs," Rev. 3, March 1982. (~) v .O V 49
O O APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
TABLES - 1997 0
f RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1997 Docket No. 50 338/339 Page 1 of 6 All indicator Controf Non-Medium or Analysis Locations Location with Hlohest Mean Location routine l Pathway LLD* Repoded l Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments l Air lodine 1-131 624 0.04 -(0/572) N/A N/A -(0/52) 0 3 (pCl/m ) Airborne Gross 624 5 20.6(572-572) 24 22.0 mi NW 23.0(52/52) 23.0(52/52) O Particulates Beta (7.0-43) (10-81) (10-81) 3 (1E-03 pCi/m ) Gamma 48 Be-7 48 10 118(44/44) 01 0.20 mi NE 127(4/4) 117(4/4) 0 (53.5-181) (57.5-164) (51.8-175) K-40 48 10 7.04(5/44) 21 10 mi WNW 18.0(1/4) 3.79(1/4) 0 (3.38-18.0) St-89 12 3 -(0/11) N/A N/A -(0/1) 0 f] l Sr-90 12 0.4 -(0/11) N/A N/A -(0/1) 0 Ground Gamma 4 Well j l Water K-40 4 60 -(0/4) N/A N/A -(0/0) 0 l (pCi/ liter) Tritium 4 2000 240(1/4) 01 A 0.75 mi SE 240(1/4) -(0/0) 0 l Sr-89 1 3 -(0/1) N/A N/A -(0/0) 0 l Sr-90 1 0.4 -(0/1) N/A N/A -(0/0) 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. 50
l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1997 Docket No. 50-338/339 Page 2 of 6 Allindicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-l (Unit) Type No. i Range Direction Range Range ments River Gamma 12 Water l (pCi/ liter) K-40 12 200 -(0/12) N/A N/A -(0/0) 0 Tritium 4 2000 2650(4/4) 11 5.8 mi.SSE 2650(4/4) -(0/0) 0 (2300-3000) (2300-3000) Sr-89 1 3 -(0/1) N/A N/A -(0/0) 0 Sr-90 1 0.4 -(0/1) N/A N/A -(0/0) 0 O Precipitation Monthly ( (pCi/ liter) Gross 12 4 3.51(12/12) 01 A 0.2 mi. 3.51(12/12) -(0/0) 0 Beta (1.5-9.6) NE (1.5-9.6) Gamma 2 (Semi-Annually) Tritium 2 2000 -(0/2) N/A N/A -(0/0) 0 Surface I-131 24 0.5 -(0/12) N/A N/A -(0/12) 0 l Water I (pCi/ liter) Regular Gamma 24 Monthlies K-40 24 200 -(0/12) N/A N/A -(0/12) 0 Tritium 8 2000 3100(4/4) 08 1.10 ml 3100(4/4) -(0/4) 0 (2400-3600) SSE (2400-3600) 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 51
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 1997 Docket No. 50-338/339 Page 3 of 6 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments Surface Sr-89 1 -(0/1) N/A N/A -(0/1) 0 Water (pCl/ liter) Regular Sr-90 1 -(0/1) N/A N/A -(0/1) 0 Monthlies Surface Gamma 24 Water (pCi/ liter) K-40 24 200 -(0/24) N/A N/A -(0/0) 0 State Splits Tritium 8 2000 2200(6/8) W33 2650(4/4) -(0/0) 0 (300-4200) (2300-3400) Sediment Gamma 6 Silt (pCl/kg Be-7 6 -(0/4) 09A 2.20 ml 442(1/2) 442(1/2) 0 NW (dry)) K-40 6 200 12825(4/4) 11 5.8 mi 16600(2/2) 11800(2/2) 0 (2500-18200) SSE (15000-18200) (11600-12000) Cs 137 6 194 90.1(1/4) 11 5.8 mi 90.1(1/2) 51.7(2/2) 0 (48-55.4) SSE Ra-226 6 100 1555(4/4) 11 5.8 mi 1630(2/2) 1555(2/2) 0 (970-1990) SSE (1600-1660) (1500-1610) Th-228 6 30 1240(4/4) 11 5.8 mi. 1475(2/2) 681(2/2) 0 (580-1800) SSE (1150-1800) (580-782) Sr-89 3 4.0 -(0/2) N/A N/A -(0/1) 0 (Annually) St-90 3 0.8 -(0/2) N/A N/A -(0/1) 0 (Annually) 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. 52
i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OV North Anna Nuclear Power Station, Louisa County, Virginia - 1997 Docket No. 50-338/339 Page 4 of 6 AllIndicator Control Non-Medium or AN/Alysis Locations Location with Highest Mean Location routine I Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Wieasure-(Unit) Type No. Range Direction Range Range ments Shoreline Gamma 2 Soil (pCi/kg Be-7 2 -(0/2) -(0/0) 0 (dry)) K-40 2 200 1805(2/2) 8 1.10 mi SSE 1805(2/2) -(0/0) 0 (770-2840) (770-2840) Cs-137 2 40 159(2/2) 8 1.10 mi SSE 159(2/2) -(0/0) 0 (147-170) (147 170) Ra-226 2 100 1160(1/2) 8 1.10 mi SSE 1160(1/2) -(0/0) 0 O T"-228 2 3o 244(2'2) 8 ' 'o mi sse 244(2'2) -co'o) o (240-247) (240-247) Sr-89 1 4.0 -(0/1) N/A N/A -(0/0) 0 (Annually) Sr-90 1 0.8 -(0/1) N/A N/A -(0/0) 0 (Annually) Milk l-131 24 0.5 -(0/24) N/A N/A -(0/0) 0 l (pCi/ liter) Gamma 24 K-40 24 100 1276(12/12) 12 8.3 mi. NW 1287(12/12) -(0/0) 0 (1020-1410) (1130-1430) Sr-89 8 5 -(0/8) N/A N/A -(0/0) 0 (Quarterly) St-90 8 0.8 1.16(8/8) 12 8.3 ml. NW 1.22(4/4) -(0/0) 0 -(Quarterly) (0.45-1.8) (0.45-1.8) 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. 53
I I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1997 Docket No. 50-338/339 Page 5 of 6 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD* Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit) Type No. Range Direction Range Range ments Fish Gamma 8 pCl/kg (wet) K-40 8 200 1705(4/4) 25 16.5 mi. NW 1860(4/4) 1860(4/4) 0 (1050-2270) (1560-2030) (1560-2030) Cs-137 8 40 33.2(4/4) 08 1.10 ml. SSE 33.2(3/4) -(0/4) 0 (24.7-37.4) (24.7-37.4) Food Gamma 35 Vegetation Dose 3588(33/35) 21 1.00 mi 4903(7/7) -(0/0) 0 i (pCi/kg Be-7 35 (wet)) (644-13200) WNW (2060-13200) 13615(35/35) 23 0.93 mi 15659(7/7) -(0/0) 0 K-40 35 [] (3640-25400) SSE (4310-25400) Cs-137 35 80 -(0/35) N/A N/A -(0/0) 0 I Ra-226 35 1110(1/35) 21 1.00 mi. 1110(1/7) -(0/0) 0 WNW 337(5/35) 14 1.20 mi 740(1/7) -(0/0) 0 Th-228 35 (114-740) NE l l l l 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. 54
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1997 Docket No. 50-338/339 Page 6 of 6 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-l (Unit) Type No. Range Direction Range Range m ents l l Direct Gamma 48 0.2 6.12(44/44) 01 0.2 mi. NE '8.30(4/4) 5.75(4/4) 0 Radiation Dose (3.6-9.1) (7.5-9.1) (4.6-6.5) (mR/std. month) (Regular TLDs) Direct Gamma 12 0.2 5.96(11/11) 01 0.2 mi. NE 8,1(1/1) 5.6(1/1) 0 Radiation Dose (4.6-8.1) (mR/std. Month) (Annual TLDs) l-Direct Gamma 288 0.2 6.70(256/256) 19/51 0.30 mi. 8.15(8/8) 5.73(32/32) 0 Radiation Dose (4.0-10.1) SW (7.2-9.0) (3.9-7.6) p (mR/std. Month) () (Sector TLDs) l I I l 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. i 55
O APPENDIX B DATA TABLES I I llO
TABLE B-1: IODINE-131 CONCENTRATIONS IN FILTERED AIR O North Anna Power Station, Louisa County, Virginia - 1997 3 pCl/m i2 Sigma Page 1 of 1 Collection STATIONS Date 01 02 03 04 05 OSA 06 07 21 22 23 24 JANUARY 01/02-01/08 <.02 <.02 <.02 <.02 <.008 <.009 <.009 <.009 <.009 <.006 <.02 <.02 01/08-01/15 <.01 <.01 <.01 <.01 <.007 <.009 <.009 <.009 <.009 <.006 <.01 <.01 01/15-01/22 <.008 <.008 <.008 <.008 <.006 <.008 <.008 <.008 <.008 <.006 <.01 <.01 01/22-01/29 <.008 <.008 <.008 <.008 <.007 <.009 <.009 <.009 <.009 <.006 <.01 <.01 FEBRUARY 01/29-02/05 <.01 <.01 <.01 <.01 <.007 <.009 <.009 <.009 <.009 <.006 <.01 <.01 02/05 02/12 <.009 <.009 <.009 <.009 <.007 <.009 <.009 <.009 <.009 <.007 <.01 <.01 02/12-02/19 <.02 <.02 <.02 <.02 <.008 <.01 <.01 <.01 <.01 <.009 <.01 <.01 l 02/19-02/26 <.007 <.007 <.007 <.007 <.006 <.006 <.006 <.006 <.006 <.005 <.01 <.01 MARCH I l 02/26-03/05 <.01 <.01 <.01 <.01 <.007 <.008 <.008 <.008 <.008 <.005 <.01 <.01 03/05-03/12 <.01 <.01 <.01 <.01 <.007 <.01 <.01 <.01 <.01 <.009 <.009 <.009 03/12-03/19 <.009 <.01 <.01 <.01 <.008 <.01 <.01 <.01 <.01 <.007 <.02 <.02 s 03/19-03/26 <.008 <.008 <.008 <.008 <.005 <.007 <.007 <.007 <.007 <.005 <.01 <.01 03/26-04/02 <.01 <.01 <.01 <.01 <.007 <.01 <.01 <.01 <.01 <.009 <.01 <.01 APRIL l 04/02-04/10 <.006 <.006 <.006 <.006 <.005 <.006 <.006 <.006 <.006 <.004 <.01 <.009 04/10-04/16 <.02 <.02 <.02 <.02 <.009 <.01 <.01 <.01 <.01 <.007 <.02 <.02 04/16-04/23 <.009 <.009 <.009 <.009 <.008 <.01 <.01 <.01 <.01 <.007 <.02 <.009 l 04/23-04/30 <.02 <.01 <.01 <.01 <.007 <.01 <.01 <.01 <.01 <.009 <.01 <.01 MAY 04/30-05/07 <.01 <.01 <.01 <.01 <.008 <.01 <.01 <.01 <.01 <.007 <.009 <.009 05/07-05/14 <.01 <.01 <.01 <.01 <.007 <.008 <.008 <.008 <.008 <.005 <.01 <.01 05/14-05/21 <.007 <.007 <.007 <.007 <.005 <.01 <.01 <.01 <.01 <.008 <.01 <.01 05/21-05/28 <.009 <.009 <.009 <.009 <.007 <.01 <.01 <.01 <.01 <.007 <.006 <.009 JUNE 05/28-06/04 <.008 <.008 <.008 <.008 <.005 <.01 <.01 <.01 <.01 <.009 <.01 <.01 l 06'04 06/11 <.01 <.01 <.01 <.01 <.008 <.009 <.009 <.009 <.009 <.007 <.008 <.008 06/11-06/18 <.01 <.01 <.01 <.01 <.009 <.009 <.009 <.009 <.009 <.006 <.01 <.02 06/18-06/25 <.01 <.01 <.01 <.01 <.009 <.01 <.01 <.01 <.01 <.009 <.01 <.01 06/25-07/02 <.01 <.01 <.01 <.01 <.008 <.01 <.01 <.01 <.01 <.008 <.02 <.01 l l l O l 57 ~
l l TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR O North Anna Power Station, Louisa County, Virginia - 1997 pCi/m3 i2 Sigma Page 2 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JULY l 07/02-07/09 <.008 <.008 <.008 <.008 <.006 <.008 <.008 <.008 <.008 <.006 <.01 <.01 07/09-07/16 <.008 <.008 < 008 <.008 <.007 <.008 <.008 <.008 <.008 <.006 <.01 <.01 07/16-07/23 <.01 <.01 <.01 <.01 <.007 <.008 <.009 <.009 <.009 <.006 <.01 <.01 07/23-07/30 <.02 <.02 <.02 <.02 <.01 <.03 <.03 <.03 <.03 <.02 <.04 <.04 AUGUST 07/30-08/06 <.005 <.005 <.005 <.005 <.004 <.008 <.008 <.008 <.008 <.006 <.01 <.009 08/06-08/13 <.02 <.02 <.02 <.02 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.01 08/13-08/20 <.01 <.01 <.01 <.01 <.006 <.008 <.008 <.008 <.008 <.005 <.01 <.01 08/20-08/27 <.009 <.009 <.009 <.009 <.007 <.008 <.008 <.008 <.008 <.006 <.02 <.01 SEPTEMBER 08/27-09/04 <.008 <.009 <.008 <.008 <.006 <.009 <.009 <.009 <.009 <.007 <.008 <.007 09/04-09/11 <.01 <.01 <.01 <.01 <.007 <.02 <.02 <.02 <.02 <.01 <.01 <.009 09/11-09/17 <.02 <.02 <.02 <.02 <.009 <.02 <.02 <.02 <.02 <.01 <.008 <.01 ,l g 09/17-09/24 <.02 <.02 <.02 <.02 <.008 <.02 <.02 <.02 <.02 <.01 <.008 <.008 ) l 09/24-10/01 <.01 <.01 <.01 <.01 <.007 <.009 <.009 <.009 <.009 <.006 <.01 <.01 l OCTOBER l 10/01-10/08 <.01 <.01 <.01 <.01 <.009 <.01 <.01 <.01 <.01 <.007 <.01 <.006 10/08-10/15 <.01 <.01 <.01 <.01 <.000 <.008 <.008 <.008 <.008 <.005 <.01 <.02 i l 10/15-10/22 <.01 <.01 <.01 <.01 <.009 <.01 <.01 <.01 <.01 <.007 <.01 <.01 10/22-10/29 <.01 <.01 <.01 <.01 <.006 <.007 <.007 <.007 <.007 <.005 <.008 < 008 NOVEMBER t i 10/29-11/05 <.01 <.01 <.02 <.01 <.007 <.009 <.009 <.009 <.008 <.006 <.008 <.009 11/05-11/12 <.007 <.007 <.008 <.008 <.005 <.006 <.006 <.007 <.006 <.004 <.01 <.01 11/12-11/19 <.01 <.01 <.01 <.01 <.007 <.01 <.01 <.02 <.01 <.01 <.008 <.04 (a) 11/19-11/25 <.008 <.009 <.009 <.008 <.007 <.01 <.01 <.01 <.01 <.01 <.02 <.02 11/25-12/03 <.01 <.01 <.01 <.01 <.007 <.01 <.01 <.01 <.01 <.008 <.01 <.01 DECEMBER 12/03 12/10 <.01 <.01 <.01 <.01 <.006 <.006 <.006 <.006 <.006 <.005 <.01 <.01 12/10-12/17 <.01 <.01 <.01 <.01 <.009 <.008 <.008 <.008 <.007 <.006 <.01 <.008 12/17-12/23 <.02 <.02 <.02 <.02 <.02 <.02 <.02 <.02 <.02 <.01 <.02 <.02 12/23-12/31 <.02 <.02 <.02 <.02 <.008 <.01 <.01 <.01 <.01 <.01 <.007 <.006 j ( O (a) Low sample volume; sampler not running. Volume estimated at minimum of 75 cu. m. 58 i
E G. 4393 7345 35546 9 d As i ii1 1i11 1i111 i R2 220 3694 8945 1 1 E 2222 2111 11111 1 8 Vi A 2222 2222 22222 8 4 111i 111i i11i1 1 2 2222 2121 I7046 134i 3714 l 9 1211 1 0 2222 2222 22222 1 3 1111 11i1 i1 i1 i 2 1271 7605 I1211 1 9146 l 2222 2121 9 2222 2222 22222 7 2 ii1i 1111 11111 1 2 2341 4897 19277 0 2222 2111 1121 1 2 4 3 4 2222 2221 12212 9 1 1111 1111 i1i11 i S 2 0000 5230 I. 482 1 E 2212 1118 7 9 13 11 1 T A L U C 1 2222 2222 2222 6 1 7R 7 1111 1111 111t1 1 A 0 7918 1663 111 11 05725 P 6 1121 2111 1 a R m A I 7 ig 9 N S 9 2 1 I 2 2222 2222 22222 8 A Ti 6 1 1i 1111 1i11 i ) 1 1 4 A E 0 o N B 3 2450 4786 1221 20236 f 9 E I N S 2222 2111 1 L m 1 B ge A S / i OC a A P l i T T R p ( 2222 2222 22222 7 R G 3 A 111i 1111 1i111 1 O F 0 5 N O 0 033i 4695 20857 9 E 2222 2111 12111 1 SN 0 O1 ITA 2222 2222 22222 6 R T 5 1i1i 1111 11111 1 N 0 9866 01 91 3794 1111 1 1 8 E 2212 21 11 1 C NOC 2222 2222 22222 8 4 1111 i 1i i11i 1 0 4340 4704 9047 l 9 2222 212I I1211 1 2222 2222 22222 8 3 1i1i ii1i i 111 1 0 4159 4585 i9847 8 2221 2111 l111 1 1 2222 2222 I2222 9 2 i111 1111 1i111 1 0 9017 7703 1121 1 08047 6 1221 11 21 1 2222 2222 22222 7 1 0 i1 t 1111 i111 1 4451 7908 49168 0 2222 2121 11211 2 N O Y g I v Y )8529 R 5296 52962 TE A. R A/// 12 01 120 CT 122 A 01 //// I ///// r d. E A A 1 1 1 1 U 2222 I 33334 0000 0000 C 00000 e L D U R t s 2852 l 9529 R 65296 r L N 00I2 l 201 1 12 a2 / / 1 / //// A 201 O A l1/ 1 E 1222 ///// u 23333 C J O000 E 0000 M 00000 Qi mo t
E 5563 5334 33654 2 Gd.s A i i 111i i1111 i 13149 R2 913l 7794 E 122I 1111 11221 8 1 i V O A 222I 2222 22222 8 4 i1 11 i 11111 1 2 33430 0710 121 2121 19705 11222 8 1 2222 2222 22222 9 3 11i1 111 11111 1 2 1151 9806 24270 1121 11222 9 2221 1 4 0 2222 2222 12222 1 2 i1i1 1i1 111i1 1 2 9363 7693 9.1 1 8 3969 1221 1111 21 9 1 4 l 2221 i222 22222 l 1111 i111 11111 i 1 S 2 3852 0715 33553 I 1118 1121 11222 7 T 1 TA L U I 4 C T 2221 2222 12222 9 R 7 1i1 11i1 111i1 1 A 0 6231 7781 02917 1111 11121 6 P 22 1 a 9 1 R m I g A 7 i 9 N S 9 3 2 1 I 2 2222 2222 2222 9 1 A Ti 6 111 1i1i 11 1 1 ) H 4 A E 0 o N B 18131 9462 4.1 1 6 1815 f 3 21 221 1111 E 2 N S m 8 1 L e / A S . OA i l g OC l a l P T T R p i ( 2222 2222 21222 7 R G A 3 111i 1111 11111 1 O F 0 5 N O 0 7032 7703 11121 7 31817 E 1221 1121 1 SN 0 1 O I T e A 2222 l 2222 2222 1 R 5 11ii 1111 1111i i I N 0 026i 8782 01128 E 222l 1111 11221 7 1 C N O l C 2222 2222 2222 l 1 4 1i1i 11i 11111 i 0 156l 8604 04159 222I 1121 11221 8 1 2222 2222 12222 9 3 0 11i1 ii1i 1111 1 5060 0021 6029 1 9 11222 2221 1221 1 2222 9 2222 2222 l 2 0 111 1i11 i iii1 1 008 9030 8603 1l1I221 7 1221 1121 1 e 2222 l 2222 2222 i 1 0 1111 i1ii i11 1 i 9462 0795 4151 1 11 11222 9 1221 21 1 N O g O I v TE 0630 7418 41852 A. / I23 0122 01 12) CT 1 / / / //// / ///A 4444 5555 66667 r d. EA L 0004 0000 E 00000 e L t s D 2063 Y 0741 I - - - - N 20112 a2 84185 r L R ) 1 12 3012 O P K/// A //// ///// u 4544 1555 U 56666 C A 0000 M 0000 J 00000 Q1
0 E 4553 6453 79765 1 Gd. s A 11ii i111 i1i11 i R2 0650 4789 79718 2222 2211 22231 4 E 2 i V O A 0 2222 2222 22322 1 4 11i1 11 i 11111 1 2 2792 6992 02039 6 2 2222 2212 33331 e 2222 2222 22222 l 3 1111 iii1 i111i i 2 2890 7099 00806 2222 2311 33231 5 2 0 2222 2222 22222 1 2 1i11 11 1 r111i 1 2 2710 59791 91923 2222 221 23232 52 2222 2222 22222 8 111i 1111 11i1 1 1 S 2 98144 E 4679 0255 1 1221 0 2221 221 1 T 2 ALU C IT 2222 2222 22222 9 R 7 1ii1 i111 1i111 1 A 0 0649 4728 34275 22221 2 P 2221 2211 a 2 R m I g A 7 i 9 N S 0 9 I 2 2222 2222 22222 1 1 2 A T 1 6 1i11 i1i1 1i111 1 B 4) A E 0 3 7116 7778 49417 fo N B 1221 1211 22231 1 E 3 N S m 2 L e / A S i . OA ( T R p g B a OC l P i 2222 2222 22222 9 T R G A 3 1ii1 i 1i 1111i i O F 0 5 N O 640 3567 48595 1 0 22221 3 E 2222 221 1 S 2 N 0 I O IT 0 A 2222 2222 22222 1 RT 5 1i11 1111 i1111 1 N 0 7438 3889 71598 23221 3 E 1221 221 1 2 C N O 0 C 2222 2222 22222 1 4 1111 ii11 11ii1 1 0 0850 6909 61849 2222 2221 23231 52 1 2222 2222 22222 1 3 0 i1i1 ii11 111i1 i 0868 7810 04939 2221 2222 33231 6 2 l 2222 2222 22322 l 2 0 ii11 i111 i11ii i 8440 5670 81 139 4 1222 2212 23331 2 l 2222 2222 22222 l 1 0 ii11 111 11 i i 9952 7899 93948 23231 5 1222 2211 2 N O R O g E v ITE 9630 6307 B 8 1741 A 0123 T 0122 M S1120 CT //// //// //// 7777 S 8888 99990 r d. E A 0000 U 0000 E 00001 e L t s D Y G 0630 T 74174 r 2963 L L 0///2 3012 P 201 12 a2 01 O U 7777 7888 E 89999 U //// ///// u C J 0000 A 0000 S 00000 Q1 O
0 7 9 4 E d 9174 75384 3452 1 1 Gs A 1 i1 11i1 1ii i 1 R2 7558 05327 3926 1131 4 1 3321 21232 E 2 2 1 V O A )a ( 2 5 1 3322 22122 2222 3 2 4 11i1 111i1 11ii 1 1 2 1000 27147 3096 1221 9 3 4432 21822 2 2 8 3 3222 22232 2232 1 1 3 11ii 11111 1111 1 i 2 9388 98777 1016 32 1231 4 2 3321 111 2 2 9 3 3322 22222 2232 1 1 2 1iii 111ii i11 1 1 2 0847 02314 4725 4321 21132 1131 3 1 2 2 3 2 2222 22222 2232 1 1 i11i ii111 i1 1 i i 1 S 2 9625 55777 3926 E 2221 1 8 22 1131 111 2 1 TALUC 7 2 IT 2222 22232 2232 1 1 R 7 1111 i11i1 1 1 i i A 0 1804 358M2 1131 2 9 111 7 4664 P 3221 2 1 a R m IA g 7 i 9 NS 6 3 9 I 1 2 2222 22232 2222 1 1 2 A T 1 6 i 1 i11i 1 i1 1 ) B 4 A E 0 6428 88860 4308 fo N B 3 3321 11133 1231 4 0 E m 2 2 4 N S L e A S / OB i g OC a 1 A P T T R p 5 1 l ( 2222 22232 2221 1 1 R G A 3 ii1 111i1 i1i1 1 1 O F 0 5 N O 0 4215 85825 3894 32 1121 2 0 E 3321 111 S 2 2 l N 0 m O1 5 I 7 T 7 2 f A 2322 22222 2232 1 1 o R T 5 11 1 i1111 11i 1 i mu N 0 6848 14577 2805 m E 3321 21122 1131 3 0 i 2 2 C n N im O 8 4 ta C 3322 22232 2232 1 1 d 4 i11 111i1 1iii 1 i e t a 0 9659 96860 4177 33 1231 5 2 m 3321 111 2 2 i ts e e 0 4 m 3322 22232 2232 2 1 0 1i11 11ii 11i1 1 i lu 3 o 1108 64824 0625 v. 4431 21132 1131 4 2 2 2 g n in nu r 0 5 t 3322 22232 2232 2 1 o 2 n 0 111 11111 1111 1 i r 0181 15766 2715 e 4422 21 132 1131 5 1 lp 2 2 mas 8 3 3322 22232 2232 1 1 e m 1 0 1111 111ii 11ii 1 i lo u 3869 29046 4036 4321 21232 1231 5 3 v 2 2 c N ip O O R R g g m v v a I E E 0731 A R 8529 TE 52953 s A. w B 01 20 B 1123 E 0122 CT 1 //// //// ///// 0000 M M 2222 r d. d. o E B 1111 11112 l A E E e a 11111 1111 L O 1852 V 95295 C 3073 r u t s s l D L T 00I2 20112 0112 a2 n2 O C O / / /// E //// u n ) / / / / 0000 01 111 2222 a Qi Ai C O N D ( 1111 1111 11111 no ct
TABLE B-3: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN AIR l
PARTICULATES ~O North Anna Power Station, Louisa County, Virginia - 1997 3 l 1.0 E-03 pCi/m i 2 Sigma Page 1 of 3 l l First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 01/02-04/02 04/02-07/02 07/02-10/01 10/01-12/31 i 2 s.d. STA-01 Sr-89 (a) <3 (a) (a) Sr-90 (a) < 0.4 (a) (a) Be-7 148i 15 138 i 14 164 i 16 57.5 i 5.7 127 i 95 K-40 3.38 i 1.76 <4 <6 <6 3.38 i 17.6 Co-60 < 0.3 < 0.2 < 0.2 < 0.2 Ru-103 < 0.7 < 0.4 < 0.6 < 0.3 Cs-134 < 0.2 < 0.2 < 0.2 < 0.2 Cs-137 < 0.3 < 0.2 < 0.2 < 0.2 Th-228 < 0.4 < 0.5 < 0.3 < 0.3 STA-02 Sr-89 (a) <3 (a) (a) l St-90 (a) < 0.2 (a) (a) Be-7 -123 1 12 113 11 157 i 16 57.4 i 5.7 113 i 83 K-40 < 10 <4 <5 <5 Co-60 < 0.3 < 0.3 < 0.3 < 0.3 Ru-103 < 0.8 < 0.4 < 0.6 < 0.3 Cs-134 < 0.3 < 0.2 < 0.2 < 0.2 Cs-137 < 0.3 < 0.2 < 0.3 < 0.3 , U^ Th-228 < 0.4 < 0.4 < 0.4 < 0.4 STA-03 Sr-89 (a) <3 (a) (a) l Sr-90 (a) < 0.4 (a) (a) Be-7 156 i 16 1071 11 175 17 60.9 i 6.1 125 103 K-40 <4 <4 <5 <5 Co-60 < 0.3 < 0.3 < 0.2 < 0.3 Ru-103 < 0.6 < 0.3 < 0.5 < 0.3 l Cs-134 < 0.2 < 0.2 < 0.2 < 0.2 Cs-137 < 0.2 < 0.3 < 0.2 < 0.2 Th-228 < 0.4 < 0.4 < 0.3 < 0.3 I STA-04 Sr-89 (a) <3 (a) (a) Sr-90 (a) < 0.4 (a) (a) l Be-7 130 13 105 10 173 i 17 61.6 i 6.2 117 i 93 K-40 <6 <4 <4 <4 l Co-60 < 0.2 < 0.2 < 0.2 < 0.2 l Ru-103 < 0.6 < 0.3 < 0.5 < 0.3 Cs-134 < 0.2 < 0.2 < 0.2 < 0.2 Cs-137 < 0.2 < 0.2 < 0.3 < 0.3 Th-228 < 0.3 < 0.4 < 0.4 < 0.3 O All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed oniy on second quarter samples. 63
TABLE B-3: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES O
North Anna Power Station, Louisa County, Virginia - 1997 3 l 1.0 E-03 pCl/m i 2 Sigma Page 2 of 3 l First Second Third Fourth Quarter Quarter Quarter Quarter /.verage Station Nuclide 01/02-04/02 04/02-07/02 07/02-10/01 10/01-12/31 i 2 s.d. i STA-05 Sr-89 (a) <3 (a) (a) Sr-90 (a) < 0.4 (a) (a) Be-7 1741 17 99.41 9.9 159 1 16 55.1 i 5.5 122 i 10 K-40 4.02 2.00 < 10 <10 3.80 2.02 3.911 0.31 Co-60 < 0.3 < 0.3 < 0.3 < 0.3 Ru-103 < 0.8 < 0.5 < 0.8 < 0.5 Cs-134 < 0.3 < 0.3 < 0.4 < 0.3 Cs-137 < 0.3 < 0.3 < 0.4 < 0.3 Th-228 < 0.5 < 0.5 < 0.6 < 0.5 STA-05A Sr-89 (a) <2 (a) (a) Sr90 (a) < 0.3 (a) (a) Be-7 163 10 1101 10 169 i 17 54.315.4 124 i 107 j K-40 <4 <5 <5 <5 l Co-60 < 0.2 < 0.2 < 0.2 < 0.2 Ru-103 < 0.6 < 0.4 < 0.6 < 0.3 Cs-134 < 0.3 < 0.3 < 0.2 < 0.3 Cs-137 < 0.2 < 0.2 < 0.3 < 0.3 Th-228 < 0.4 < 0.4 < 0.5 < 0.4 STA-06 Sr-89 (a) <3 (a) (a) Sr-90 (a) < 0.3 (a) (a) Be-7 166i 17 89 9 144 14 57.2 1 5.7 114i 100 K 40 <5 <6 <7 6.021 2.36 6.021 2.36 Co-60 < 0.3 < 0.2 < 0.3 < 0.3 Ru-103 < 0.9 < 0.4 < 0.6 < 0.4 l Cs-134 < 0.3 < 0.3 < 0.3 < 0.3 Cs 137 < 0.3 < 0.2 < 0.2 < 0.3 Th-228 < 0.7 < 0.3 < 0.4 < 0.4 STA-07 St-89 (a) <1 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 115i 12 1101 10 169 i 17 62.216.2 114 i 87 K-40 <8 <5 <4 <5 Co-60 < 0.2 < 0.2 < 0.3 < 0.2 Ru-103 < 0.6 < 0.3 < 0.6 < 0.3 Cs-134 < 0.3 < 0.3 < 0.3 < 0.2 Cs-137 < 0.3 < 0.2 < 0.2 < 0.2 Th-228 < 0.4 < 0.5 < 0.5 < 0.4 All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed only on second quarter samples. 64
TABLE B-3: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES O
Nortn Anna eower station. touise county. vir9 nie - 1997 i 3 1.0 E-03 pCl/m i 2 Sigma Page 3 of 3 i First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 01/02-04/02 04/02-07/02 07/02-10/01 10/01 12/31 i 2 s.d. STA-21 Sr-89 (a) <2 (a) (a) Sr-90 (a) < 0.3 (a) (a) l Be-7 95.9 i 9.6 110 i 10 133 i 13 53.5 i 5.3 98.11 66.0 l K-40 <5 16 i 3 <9 18.0 i 4.0 18.0 i 4.0 Co-60 < 0.3 < 0.4 < 0.3 < 0.4 Ru-103 < 0.6 < 0.4 < 0.8 < 0.4 Cs-134 < 0.2 < 0.3 < 0.3 < 0.4 Cs-137 < 0.3 < 0.3 < 0.3 < 0.3 Th-228 < 0.4 < 0.4 < 0.4 < 0.4 STA-22 Sr-89 (a) <2 (a) (a) l Sr-90 (a) < 0.4 (a) (a) Be-7 142i 14 99i 10 1811 18 55.8 i 5.6 119 i 108 K-40 <6 <4 <4 <4 Co-60 < 0.2 < 0.2 < 0.2 < 0.2 Ru-103 < 0.6 < 0.3 < 0.5 < 0.3 Cs-134 < 0.2 < 0.2 < 0.2 < 0.2 1 Cs-137 < 0.2 < 0.2 < 0.2 < 0.2 l Th-228 < 0.3 < 0.4 < 0.3 < 0.3 STA-23 Sr-89 (a) <3 (a) (a) Sr-90 (a) < 0.4 (a) (a) Be-7 146 15 120 i 10 174117 59.1 i 5.9 125 i 98 i K-40 <4 <4 <4 <4 l Co-60 < 0.2 < 0. < 0.2 < 0.2 Ru-103 < 0.5 < 0.3 < 0.5 < 0.3 Cs-134 < 0.2 < 0.2 < 0.2 < 0.2 Cs-137 < 0.3 < 0.2 < 0.2 < 0.2 Th-228 < 0.3 < 0.3 < 0.3 < 0.3 STA-24 Sr-89 (a) <2 (a) (a) Sr-90 (a) < 0.2 (a) (a) Be-7 131 13 110 i 10 175 18 51.8 i 5.2 117 i 102 K-40 < 10 <7 <7 3.79 1.97 3.79 i 1.97 Co-60 < 0.3 < 0.3 < 0.3 < 0.3 Ru-103 < 0.9 < 0.4 < 0.7 < 0.4 Cs-134 < 0.4 < 0.2 < 0.3 < 0.3 Cs-137 < 0.3 < 0.3 < 0.3 < 0.3 Th-228 < 0.5 < 0.4 < 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. 65
1 TABLE B-4: GROSS BETA, TRITIUM AND GAMMA EMITTER
- q CONCENTRATIONS IN PRECIPITATION Station 01A -(On Site)
North Anna Power Station, Louisa County, Virginia - 1997 pCi/l 2 Sigma Page 1 of 1 Collection Dates Gross Beta Rainfall (inches) 12/26/96-01/29/97 2.8 i 0.6 2.34 01/29/97-02/26/97 3.5 0.7 2.35 02/26/97-03/26/97 3.4 i 0.7 5.68 03/26/97-04/30/97 4.410.7 2.74 04/30/97-05/28/97 9.6 i 1.6 0.92 4 05/28/97-06/25/97 2.1 i 0.6 4.92 06/25/97-07/30/97 2.9 i 0.7 3.76 07/30/97-08/27/97 3.2 i 0.7 2.80 l 08/27/97-09/24/97 3.4 0.7 2.36 09/24/9710/29/97 (a) 2.2 i 0.6 3.36 10/29/97-11/25/97 1.5 0.6 2.97 i 11/25/97-12/31/97 3.1 i 0.7 2.28 O Average i 2 s.d. 3.5 i 4.1 (a) Sample volume 700 mis due to lower than normal precipitation. l SEMI-ANNUAL PRECIPITATION COMPOSITES 12/26/96-06/25/97 06/25/97-12/31/97 Be-7 = < 20 Be-7 < 40 = H-3 = < 200 H-3 < 300 = TABLE B-5 SOIL Soil samples are collected every three years from twelve stations. Since the samples were collected in 1995, Table B-5 will not be included in the 1997 report. All gamma emitters other than those listed were <LLD. l l 66
1 i TABLE B-6: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS Q IN GROUND AND WELL WATER North Anna Power Station, Louisa County, Virginia - 1997 pCI/li 2 Sigma Page 1 of 1 l l Collection Dates Sr-89 Sr 90 H-3 Be 7 K-40 1-131 Ba-140 Th-228 STATION 01 A l 03/26/97 (a) (a) < 200 < 30 < 60 < 0.2 <8 <9 06/25/97 < 0.8 < 0.4 < 200 < 30 < 50 < 0.3 <5 <6 09/24/97 (a) (a) < 200 < 30 < 60 < 0.2 <6 <7 12/31/97 (a) (a) 240i160 < 40 < 90 <8 <6 <7 Average 12 sd 240 i 160 All gamma emitters other than those listed were <LLD. (a) Strontium-89/90 analyses performed only on second quarter sample. l TABLE B-7: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS Q IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 1997 pCl/li 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131 Cs-137 Ba-140 Ra-226 Th-228 STATION - 11 01/14/97 (a) (a) 2300i 200 < 40 < 60 < 0.2 <4 <5 < 100 <9 02/13/97 (a) (a) (b) < 30 < 50 < 0.4 <4 <7 < 80 <7 03/11/97 (a) (a) (b) < 40 < 100 < 0.2 <5 <6 < 80 <7 04/14/97 <1 < 0.3 2400 300 < 30 < 50 < 0.5 <4 <6 < 80 <7 05/12/97 (a) (a) (b) < 40 < 100 < 0.2 <5 <8 < 80 <7 l 06/16/97 (a) (a) (b) < 30 < 80 < 0.3 <3 <4 < 60 <6 07/14/97 (a) (a) 30001 300 < 30 < 40 < 0.2 <4 <4 < 60 <5 l 08/08/97 (a) (a) (b) < 40 < 50 <1 <3 < 10 < 80 <7 09/16/97 (a) (a) (b) < 30 < 60 < 0.3 <3 <7 < 60 <5 10/13/97 (a) (a) 29001 300 < 30 < 100 < 0.2 <4 <5 < 70 <6 11/12/97 (a) (a) (b) < 30 < 80 < 0.2 <3 <4 < 60 <5 12/15/97 (a) (a) (b) < 30 < 50 < 0.4 <4 <4 < 60 <5 Average i 2 s.d. 2650 1 702 ( All gamma emitters other than those listed were <LLD. (a) Sr-89/90 analyses performed only on second quarter samples. (b) Tritium analysis performed on quarterly composite. 67 1 l
TABLE B-8: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS IN lQ SURFACE WATER North Anna Power Station, Louisa County, Virginia - 1997 pCl/li 2 Sigma Page 1 of 1 C:llection Dates Sr-89 Sr 90 H-3 Be-7 K-40 1-131 " Cs-137 Ba-140 Ra-226 Th-228 l STATION - 08 i 01/14 (a) (a) 24001 200 < 30 < 60 < 0.2 <4 <6 < 70 <7 02/13 (a) (a) (b) < 30 < 50 < 0.4 <3 <6 < 70 <6 03/11 (a) (a) (b) < 30 < 50 < 0.2 <4 <7 < 70 <6 04/14 <1 < 0.6 32001300 < 30 < 90 < 0.4 <4 <6 < 70 <6 05/12 (a) (a) (b) < 30 < 50 < 0.2 <4 <5 < 70 <6 06/16 (a) (a) (b) < 40 < 100 < 0.4 <5 <5 < 90 <7 07/14 (a) (a) 3200 i300 < 30 < 60 < 0.2 <4 <6 < 80 <7 08/08 (a) (a) (b) < 30 < 60 <1 <4 <9 < 70 <6 09/16 (a) (a) (b) < 30 < 40 < 0.3 <3 <6 < 70 <6 10/13 (a) (a) 3600 i 300 < 20 < 40 < 0.2 <3 <5 < 50 <5 11/12 (a) (a) (b) < 30 < 50 < 0.2 <3 <4 < 80 <7 12/15 (a) (a) (b) < 30 < 50 < 0.4 <4 <5 < 70 <6 O Avg. 3100i1007 i i 2. s.d. STATION - 09A 01/14 (a) (a) < 200 < 30 < 50 < 0.2 <4 <6 < 80 <7 02/13 (a) (a) (b) < 30 < 70 < 0.4 <3 <6 < 60 <6 03/11 (a) (a) (b) < 30 < 100 < 0.2 <4 <6 < 70 <6 04/14 <1 < 0.3 < 200 < 30 < 70 < 0.5 <3 <5 < 60 <6 05/12 (a) (a) (b) < 30 < 100 < 0.2 <4 <5 < 70 <6 06/16 (a) (a) (b) < 30 < 50 < 0.4 <3 <5 < 70 <7 07/14 (a) (a) < 200 < 30 < 50 < 0.2 <4 <5 < 70 <6 08/08 (a) (a) (b) < 40 < 50 < 0.9 <4 <9 < 80 <7 09/16 (a) (a) (b) < 30 < 90 < 0.3 <4 <8 < 70 <6 10/13 (a) (a) < 300 < 30 < 50 < 0.2 <3 <4 < 70 <6 I 11/12 (a) (a) (b) < 20 < 50 < 0.2 <3 <4 < 70 <6 12/15 (a) (a) (b) < 30 < 70 < 0.4 <4 <6 < 60 <5 h All gamma emitters other than those listed were <LLD. l-131 by radiochemistry (a) Analysis performed only with second quarter. (b) Analysis performed quarterly. 68 I
i TABLE B-9: GAMMA EMITTER
- AND TRITIUM CONCENTRATIONS i
() IN SURFACE WATER State-Spilt Samples North Anna Power Station, Louisa County, Virginia - 1997 pCl/li2 Sigma Page 1 of 1 l l Collection Dates H-3 Be-7 K-40 1-131 Cs-137 Ba-140 Ra-226 Th-228 l l STATION - W 27 l l l 01/31 < 200 < 30 < 40 < 0.3 <3 <5 < 50 <5 02/28 (a) < 30 < 70 < 0.5 <3 <8 < 60 <6 03/31 (a) < 30 < 60 < 0.8 <3 <6 < 50 <5 l 04/30 < 200 < 30 < 50 < 0.5 <4 <9 < 70 <6 05/31 (a) < 30 < 100 < 0.3 <4 <5 < 70 <6 06/30 (a) < 30 < 50 < 0.5 <3 <6 < 70 <6 07/31 1300 1200 < 30 < 50 <1 <4 < 10 < 70 <6 08/31 (a) < 40 < 90 < 0.8 <4 < 10 < 70 <7 09/15 (a) < 60 < 100 < 3 (b) <5 < 30 < 80 <8 10/31 1900 i 300 < 30 < 50 < 0.5 <4 <7 < 80 <7 11/30 (a) < 30 < 50 < 0.6 <4 <8 < 70 <6 p 12/31 (a) < 40 < 90 <1 <4 < 20 < 70 <6 d Avg. 1600 i 849 i 2 s.d. l l STATION - W-33 01/31 2500i200 < 30 < 50 < 0.3 <3 <4 < 70 <6 02/28 (a) < 40 < 50 < 0.5 <4 < 10 < 80 <7 03/31 (a) < 30 < 90 < 0.7 <4 <8 < 70 <6 04/30 2400 200 < 30 < 70 < 0.4 <3 <9 < 60 <5 05/31 (a) < 30 < 60 < 0.3 <3 <6 < 80 <7 06/30 (a) < 40 < 100 < 0.5 <4 < 10 < 80 <7 07/31 3400i 300 < 30 < 50 < 2 (b) <4 < 10 < 60 <5 l 08/31 (a) < 30 < 50 <1 <4 <8 < 70 <6 I 09/15 (a) < 30 < 40 < 3 (b) <3 < 20 < 60 <5 10/31 2300 i 300 < 30 < 50 < 0.4 <3 <6 < 70 <6 11/30 (a) < 30 < 70 < 0.7 <4 <9 < 60 <5 12/31 (a) < 50 < 100 <1 <5 < 20 < 80 <7 Avg. 2650 i 1013 i 2 s.d. All gamma emitters other than those listed were <LLD. i (a) Tritium analysis performed on the first monthly composite of each quarter. (b) LLD not met due to the long delay from collection date to receipt at laboratory. 69 i
TABLE B-10: GAFAMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN Q
SEDIMENT SILT North Anna Power Station, Louisa County, Virginia - 1997 pCl/kg i 2 Sigma Page 1 of 1 STA-08 STA-09A STA-11 STA-08 STA-09A STA-11 Average Nuclide 02/05 02/05 02/05 08/18 08/18 08/18 i 2 Sigma Sr-89 (a) (a) (a) < 800 < 1000 < 900 Sr 90 (a) (a) (a) < 200 < 300 < 200 Be 7 < 400 442 206 < 300 < 300 < 300 < 400 442 i 206 K-40 15600 i 1600 11600 i 1200 18200 1800 25001 400 12000 1000 15000t 2000 124831 10933 Mn-54 < 50 < 30 < 40 < 20 < 30 < 40 Co-58 < 40 < 30 < 40 < 30 < 30 < 40 Co-60 < 40 < 30 < 40 < 30 < 20 < 40 Cs-134 < 60 < 30 < 40 < 40 < 30 < 60 Cs-137 < 50. 55.4128.8 90.11 28.9 < 40 48122 < 40 65i 45 Ra 226 19901 790 16101 430 1660t 530 970i 500 15001 400 1600 i 600 14681 569 Th-228 14301 140 7821 78 11501 120 580i 60 5801 60 18001 200 978i 1030 1 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 analyses performed annually. O TABLE B-11: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 1997 pCl/kg i 2 Sigma Page 1 of 1 Station-08 Station-08 Average Nuclide 02/05/97 08/18/97 i 2 Sigma Sr-89 (a)
< 1000 Sr-90 (a) < 200 Be-7 < 200 < 300 K-40 2840 1 340 770 i 220 1805 2927 Mn-54 < 20 < 20 Co-58 < 20 < 30 Co-60 < 20 < 30 Cs 134 < 20 < 30 Cs-137 147 24 170 i 30 159 i 33 Ra-226 1160 i 420 < 500 1160 i 420 Th-228 247 i 34 2401 30 244 10 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 analyses performed annually. 70
1 I i TABLE B-12: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN MILK
\\ O North Anna Power Station, Louisa County, Virginia - 1997 pCi/li 2 Sigma Page 1 of 2 MONTH NUCLIDE STATION-12 STATION-13 JANUARY Sr-89 <1 <1 Sr-90 0.81 0.16 0.97 i 0.16 K-40 11501 120 1020 i 100 l Cs-137 <4 <5 l-131 < 0.2 < 0.2 FEBRUARY Sr-89 (a) (a) Sr-90 (a) (a) l K-40 1370 i 140 1170 i 120 l Cs-137 <4 <4 l-131 < 0.5 < 0.2 MARCH Sr-89 (a) (a) Sr-90 (a) (a) K-40 1430 i 140 1160 i 120 Cs-137 <4 <4 l-131 < 0.3 < 0.2 APRIL Sr-89 <2 <2 Sr-90 1.8 i 0.3 1.6 i 0.2 K-40 1250 130 12401 120 Cs-137 <4 <5 1-131 < 0.3 < 0.2 MAY Sr-89 (a) (a) Sr-90 (a) (a) K-40 13201 130 12501 130 Cs-137 <4 <4 l-131 < 0.3 < 0.2 JUNE Sr-89 (a) (a) Sr-90 (a) (a) K-40 1130 i 110 1400 140 Cs-137 <5 <4 l-131 < 0.3 < 0.3 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 analyses performed on the last monthly sample of each quarter. I 71
TABLE B-12: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN MILK O
North Anna Power Station, Louisa County, Virginia - 1997 pCi/li 2 Sigma Page 2 of 2 MONTH NUCLIDE STATION-12 STATION-13 JULY Sr-89 <5 <2 Sr-90 1.8 i 0.5 1.2 i 0.2 K-40 11701 120 1410 i 140 Cs-137 <4 <4 l-131 < 0.2 < 0.2 AUGUST Sr-89 (a) (a) Sr-90 (a) (a) K-40 1280 i 130 12101 120 Cs-137 <4 <4 l-131 < 0.2 < 0.2 SEPTEMBER Sr-89 (a) (a) St-90 (a) (a) K-40 12901 130 14101 140 l Cs-137 <4 <4 l-131 < 0.2 < 0.3 OCTOBER Sr 89 <2 <2 (q) Sr-90 0.451 0.28 0.63 i 0.26 K-40 1330 130 1360 140 Cs-137 <4 <4 l-131 < 0.2 < 0.2 NOVEMBER Sr-89 (a) (a) Sr-90 (a) (a) K-40 1340 130 13801 140 Cs 137 <4 <3 1131 < 0.4 < 0.5 DECEMBER Sr89 (a) (a) Sr-90 (a) (a) K-40 1380 i 140 1300 i 130 Cs-137 <5 <4 l-131 < 0.2 < 0.2 All gamma emitters other than those listed were <LLD. (a) Strontium 89/90 analyses performed on the last monthly sample of each quarter. 72
i l l l TABLE B-13: GAMMA EMITTER
- CONCENTRATIONS IN FISH lO sorin anne eower station. touise county. virginia - 1997
) l I l pCi/kg i2 Sigma Page 1 of 1 Collection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 l 02/04 25 Fish (a) 1830i 180 < 10 < 10 < 20 02/04 25 Catfish (b) 2020 i 210 < 20 < 20 < 20 l 02/06 08 Fish (a) 2270 i 230 < 20 < 20 35.0 i 16.3 02/06 08 Catfish (b) 22501 220 < 10 < 10 37.4 i 13.4 08/21 08 Fish (a) 1250 i 180 < 10 < 20 35.8115.0 08/19 25 Fish (a) 1560i' 160 < 20 < 20 < 20 08/19 08 Catfish (b) 1050i 140 < 20 < 20 24.7 i 12.5 l 08/19 25 Catfish (b) 2030 i 200 < 10 < 10 < 10 Avg. 1783 i 909 33.2 i 11.5 i 2 s.d. 1 I I i l l I l O All gamma emitters other than those listed were <LLD. (a) Non-bottom dwelling species of gamefish. l (b) Bottom dwelling species of fish. 73
TABLE B-14: GAMMA EMITTER
- CONCENTRATIONS IN FOODNEGETATION
(] North Anna Power Station, Louisa County, Virginia - 1997 pCi/kg i 2 Sigma Page 1 of 2 Collection Date Be-7 K-40 I-131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 Thers were no food / vegetation samples for all stations during January, February, March, November and December due to seasonal unavailability. STATION 14 04G5 1510 i 150 6640 660 < 60 < 20 < 20 < 20 < 200 < 20 05/21 2430i 460 188001 1900 < 70 (a) < 60 < 50 < 50 < 900 < 80 06/18 6441 242 16100 i 1600 < 50 < 40 < 30 < 30 < 500 < 50 07/16 3800t 400 18000i 2000 < 30 < 50 < 40 < 40 < 700 < 60 l 08/20 27201 420 5730 570 < 50 < 50 < 50 < 50 < 800 < 70 09/17 42201 460 116001 1200 < 10 < 60 < 50 < 50 < 900 740 1 74 10/15 3280 i 330 3640 i 360 < 30 < 30 < 20 < 20 < 300 < 30 6 STATION 15 O o4/2s s720* s7o 4e200*,900 < eo < 4o < 4o < 4o < eoo 144
- s8 05/21 2270 i 520 9700 970
< 20 < 70 < 60 < 60 < 1000 < 100 06/18 703 i 295 177001 1800 < 40 < 50 < 40 < 40 < 600 < 60 07/16 24401 240 216001 2200 < 40 < 30 < 30 < 20 < 400 < 30 08/20 7800 780 5450 i 680 < 60 < 90 < 80 (c) < 80 < 1000 325 i 98 09/17 18801 430 9470 i 950 <5 < 70 < 50 < 60 < 900 < 90 [ 10/15 5790 i 580 14300 i 1400 < 40 < 70 < 60 < 60 < 1000 < 90 l STATION 16 04G5 1480 170 127001 1300 < 40 < 20 < 20 < 20 < 300 < 30 05/21 2400 i 350 15900 1 1600 < 20 < 40 < 40 < 40 < 700 < 60 06/18 7331 212 169001 1700 < 30 < 30 < 30 < 30 < 500 < 50 3 07/16 4300 1 400 44001 400 < 40 < 30 < 30 < 30 < 600 < 60 08/20 5100 1 510 105001 1000 < 70 (b) < 30 < 30 < 20 < 400 < 40 09/17 4850 i 490 12000 1200 <5 < 40 < 30 < 30 < 600 < 60 10/15 26601 270 138001 1400 < 40 < 30 < 20 < 20 < 400 < 40 All gamma emitters other than those listed were <LLD. j (a) LLD not met because the first analysis produced a low chemical yield (11.8%). The analysis was repeated producing a higher yield (50.7%), however, by that time the detection limit was too difficult to obtain because of the short half-life of I-131. O-(b) LLD not met. Sample received at lab 15 days after collection. Sample countert 4 times but LLD could not be met. 1 (c) The LLD for Cs 134 could not be met due to low density of the matrix. Only 569 illed a one liter mannelli. f l 74
TABLE B-14: GAMMA EMITTEW CONCENTRATION IN FOODNEGETATION O North Anna Power Station, Louisa County, Virginia - 1997 pCi/kg i 2 Sigma Page 2 of 2 Collection Date Be-7 K-40 1-131 Ru 103 Cs-134 Cs-137 Ra-226 Th 228 i STATlOft21 04/25 13200i 1300 188001 1900 < 50 < 60 < 50 < 50 < 800 125 i 58 05/21 2060 400 15400 i 1500 < 20 < 50 < 40 < 50 < 1000 < 80 j 06/18 < 500 17700 i 1800 < 30 < 60 < 60 < 50 < 900 < 80 l 07/16 2110 390 22600 i 2300 < 30 < 50 < 50 < 50 < 800 < 70 08/20 4500 i 450 6730 i 670 < 40 < 20 < 20 < 10 < 300 < 30 09/17 4060 i 470 11700i 1200 <7 < 60 < 50 < 50 < 1000 < 90 10/15 3490 i 430 9860i 990 < 30 < 60 < 60 < 50 1110 i 600 380i73 i l STATION 23 04/25 45901 460 25400 1 2500 < 30 < 60 < 50 < 50 < 800 < 70 05/21 2010 i 360 17200 1700 < 30 < 60 < 50 < 60 < 800 < 80 06/18 < 500 15600 1600 < 40 < 50 < 50 < 50 < 800 < 80 07/16 7600 i 800 11000 i 1000 < 30 < 70 < 50 < 50 < 900 < 90 l 08/20 4150 1 420 16900 i 1700 < 50 < 50 < 40 < 40 < 700 < 70 i 09/17 2380 i 400 19200 i 1900 <7 < 60 < 50 < 50 < 800 < 70 10/15 1540 1 320 4310 1 430 < 40 < 50 < 40 < 40 < 700 < 60 Average 3588i 4998 13615 i 11250 1110 i600 337 i 509 i 2 s.d. l l l I O All gamma emitters other than those listed were <LLD. 75
TABLE B-15: DIRECT RADIATION MEGSUREMENTS - QUARTERLY AND ANNUAL 0 TLD RESULTS 1 North Anna Power Station, Louisa County, Virginia - 1997 mR/Std. Month (30.4 days)i 2 Sigma Page 1 of 1 Station First Otr Second Otr Third Qtr Fourth Qtr Quarterly Annual TLD Number 12/27/96 04/02/97 07/02/97 10/01/97 Average 07/03/96-04/02/97 07/02/97 10/01/97 01/07/98 07/02/97 01 7.5 i 0.1 8.3 1 0.3 8.3 0.2 9.110.5 8.3 i 1.3 8.1 i 0.2 02 3.6 i 0.2 4.7 i 0.2 5.2 i 0.1 5.4 0.2 4.7 1 1.6 4.6 i 0.1 03 4.0 i 0.1 4.7 i 0.2 4.8 i 0.1 5.2 0.2 4.7 i 1.0 4.6 i 0.1 04 4.2 1 0.3 5.1 1 0.6 5.4 i 0.1 5.7 i 0.1 5.1 i 1.3 5.4 0.9 05 4.9 i 0.2 6.0 1 0.3 6.6 1 0.8 6.7 i 0.2 6.1 i 1.7 5.9 i 0.1 05A 4.7 1 0.3 5.8 i 0.3 5.8 1 0.1 6.2 1 0.1 5.6 1.3 5.3 1 0.2 06 6.3 0.1 7.1 i 0.2 7.6 1 0.2 8.3 1 0.3 7.3 i 1.7 7.1 i 0.3 07 4.8 1 0.2 5.5 i 0.2 6.0 0.2 6.3 0.3 5.7 1.3 5.6 i 0.2 21 4.8 i 0.0 5.5 i 0.2 5.8 0.2 5.9 i 1.1 5.5 i 1.0 5.3 i 0.2 22 6.0 0.2 6.6 1 0.2 6.9 i 0.1 7.8 1 0.1 6.8 i 1.5 6.4 1 0.2 i 23 6.4 i 0.1 7.4 1 0.2 8.1 i 0.2 8.2 i 0.2 7.5 i 1.7 7.6 i 0.1 24 4.6 i 0.1 5.8 i 0.4 6.1 1 0.1 6.5 i 0.2 5.8 i 1.6 5.6 i 0.1 Average 5.2 i 2.3 6.0 i 2.2 6.4 i 2.3 6.8 2.5 6.1 i 2.6 6.0 i 2.3 i 2 s.d. I O 76
TABLE B-16: DIRECT RADIATION MEASUREMENTS-0 SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1997 l mR/Std. Month (30.4 days)i 2 Sigma Page 1 of 2 Statior First Qtr. Second Qtr. Third Qtr. Fourth Otr. Average l Numbe 12/27-04/02 04/02-07/02 07/02-10/01 10/01-01/07 t 2 s.d. l N-1 6.2 i 0.3 6.61 0.3 7.1 1 0.3 7.4 i 0.1 6.8 i 1.1 N-2 4.9 i 0.2 4.9 i 0.1 6.0 i 0.1 6.1 1 0.1 5.5 i 1.3 NNE-3 8.61 0.2 8.710.2 9.7 i 0.1 10.1 0.1 9.3 i 1.5 NNE-4 5.310.1 5.7 i 0.6 6.6 1 0.1 6.5 i 0.3 6.0 i 1.3 NE-5 7.8 i 0.2 7.61 0.3 8.7 i G.3 8.8 1 0.4 8.2 i 1.2 NE-6 5.31 0.2 5.410.2 6.4 1 0.2 6.5 1 0.1 5.9 i 1.3 ENE-7 6.41 0.1 6.8 i O.4 7.8 i 0.2 7.8 1 0.2 7.2 i 1.4 ENE-8 4.5 i 0.1 4.4 i 0.1 0.6 i 0.0 6.4 1 0.3 5.2 1 1.9 E-9 6.7 i 0.2 6.8 i 0.3 8.2 0.3 8.1 1 0.3 7.5 i 1.6 E-10 5.91 0.2 6.1 i 0.5 7.0 1 0.3 6.9 1 0.6 6.5 i 1.1 ESE-11 5.9 i 0.1 5.8 i 0.2 6.9 0.2 7.0 i 0.5 6.4 i 1.3 ESE 12 6.5 i 0.1 6.5 i 0.2 8.0 0.3 7.8 i 0.4 7.2 i 1.6 SE-13 6.5 1 0.2 6.51 0.2 7.3 i 0.2 7.6 i 0.5 7.0 i 1.1 SE-14 8.4 i 0.2 8.310.4 9.4 i 0.2 9.8 i 0.1 9.0 i 1.5 SSE-15 6.6 i 0.2 6.7 0.1 7.9 i 0.1 8.1 1 0.4 7.3 i 1.6 SSE-16 4.9 i 0.2 5.5 i 0.4 5.9 i 0.1 5.9 i 0.1 5.6 1 0.9 S-17 8.1 i 0.3 8.41 0.3 9.4 i 0.5 9.3 i 0.2 8.8 i 1.3 ^ S 18 4.3 i 0.0 4.310.1 5.2 i 0.1 5.3 i 0.3 4.8 i 1.1 SSW 19 7.210.2 7.9 i 0.3 8.6 i 0.3 8.3 i 0.3 8.0 i 1.2 SSW-20 4.1 i 0.1 4.210.1 5.0 1 0.1 5.1 1 0.1 4.6 i 1.0 SW-21 5.410.2 5.410.3 6.3 i 0.2 6.4 i 0.4 5.9 i 1.1 SW-22 6.2 i 0.2 6.6 i 0.4 7.3 1 0.1 7.2 i 0.5 6.8 i 1.0 WSW-23 7.6 i 0.2 7.5 i 0.3 8.2 i 0.2 8.6 i 0.1 8.0 i 1.0 WSW-24 6.2 i 0.2 6.4 i 0.3 7.2 i 0.2 7.4 i 0.4 6.8 i 1.2 W-25 7.7 i 0.2 8.4 i 0.3 8.7 1 0.3 8.8 i 0.3 8.4 i 1.0 W 26 4.7 i 0.2 4.8 i 0.3 5.6 i 0.1 6.0 i 0.4 5.3 i 1.3 WNW-27 4.9 i 0.1 4.9 i 0.1 5.9 i 0.3 5.8 1 0.4 5.4 i 1.1 WNW 28 4.7 i 0.1 5.21 0.1 5.9 i 0.2 6.2 0.1 5.5 i 1.4 NW-29 7.6 i 0.3 8.1 1 0.1 8.9 i 0.3 8.9 1 0.7 8.4 i 1.3 NW-30 4.6 i 0.3 4.510.1 5.5 1 0.1 5.8 i 1.0 5.1 i 1.3 NNW 31 5.3 0.2 5.7 i 0.2 6.3 1 0.1 6.7 i 0.1 6.011.2 NNW-32 5.3 i 0.1 5.7 i 0.2 6.8 1 0.6 6.8 i 0.3 6.2 i 1.5 N-33 6.3 i 0.3 6.3 i 0.4 7.4 i 0.2 7.2 0.4 6.8 i 1.2 N-34 4.8 0.1 5.0 i 0.1 5.8 1 0.1 5.9 i 0.3 5.4 i 1.1 NNE-35 8.4 i 0.3 8.5 i 0.1 9.6 1 0.3 9.9 i 0.3 9.1 1 1.5 NNE-36 5.31 0.3 5.610.3 6.8 1 0.1 6.8 i 0.4 6.1 1 1.6 NE-37 7.5 0.2 7.81 0.3 8.5 1 0.3 8.7 i 0.4 8.1 1 1.1 NE-38 5.1 0.1 5.51 0.2 6.4 1 0.2 6.5 i 0.3 5.9 i 1.4 ENE-39 6.5 0.2 6.8 i 0.4 7.6 1 0.3 7.5 i 0.4 7.1 1 1.1 ENE-40 4.4 i 0.1 4.710.3 5.6 1 0.2 6.4 1 0.3 5.3 i 1.8 E-41 6.6 i 0.2 6.710.4 8.0 1 0.2 8.1 i 0.3 7.4 1 1.6 E-42 5.9 i 0.3 6.11 0.2 7.3 t 0.2 7.0 0.3 6.6 1.4 ESE-43 6.01 0.3 6.110.2 7.1 1 0.3 7.2 i 0.2 6.6 i 1.3 ESE-44 6.310.2 6.7 i 0.5 7.8 i 0.3 7.7 0.2 7.1 1.5 SE-45 6.2 i 0.1 6.710.2 7.1 i 0.2 7.4 0.3 6.911.0 O l 77
l TABLE B-16: DIRECT RADIATION MEASUREMENTS SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1997 mR/Std. Month (30.4 days)i 2 Sigma Page 2 of 2 1 Station First Qtr Second Qtr Third Qtr Fourth Qtr Average Number 12/27-04/02 04/02-07/02 07/02-10/01 10/01-01/07 i 2 S.d. SE-46 8.5 i 0.2 8.6 i 0.3 9.4 1 0.2 9.8 i 0.4 9.1 i 1.3 SSE-47 6.3 i 0.3 7.010.1 7.6 i 0.2 8.2 i 0.2 7.3 i 1.6 SSE-48 4.9 i 0.3 5.21 0.~ 6.2 i 0.2 6.2 i 0.2 5.6 i 1.4 S-49 8.110.3 9.0 0.4 9.6 0.6 9.7 i 0.3 0.1 i 1.5 S-50 4.010.3 4.3 i 0.2 5.2 i 0.2 5.3 0.2 4.7 i 1.3 SSW-51 7.3 i 0.2 8.2 i 0.9 9.0 1 0.4 8.7 i 0.3 8.3 i 1.5 SSW-52 4.3 i 0.2 4.4 i 0.5 5.0 1 0.1 5.4 i 0.4 4.8 i 1.0 SW-53 4.9 i 0.4 5.510.4 6.1 1 0.2 6.5 1 0.3 5.8 i 1.4 SW-54 6.2 i 0.2 6.410.2 7.3 0.2 7.6 i 0.2 6.9 i 1.4 WSW-55 7.410.3 7.7 i 0.3 8.5 i 0.1 9.0 0.3 8.2 i 1.5 WSW-56 5.9 i 0.2 6.4 i 0.2 7.1 1 0.1 7.6 1 0.4 6.8 i 1.5 W 57 7.7 i 0.3 8.0 i 0.2 8.9 i 0.2 9.3 i 0.1 8.5 i 1.5 W 58 4.7 i 0.1 4.8 i 0.2 5.7 i 0.1 6.0 i 0.1 5.3 i 1.3 WNW-59 4.6 i 0.1 4.8 i 0.1 5.7 i 0.2 5.9 1 0.2 5.3 i 1.3 WNW-60 4.4 i 0.1 4.9 i 0.2 5.8 0.1 6.2 i 0.1 5.3 i 1.6 I NW-61 7.4 0.3 8.2 i 0.1 8.6 i 0.4 9.0 1 0.2 8.3 i 1.4 NW-62 4.41 0.1 4.7 0.2 5.2 i 0.2 5.7 i 0.1 5.0 i 1.1 Ip NNW-63 5.4 i 0.1 5.4 i 0.2 6.1 1 0.2 6.6 i 0.1 5.9 i 1.2 !d NNW-64 5.3 i 0.2 5.7 i 0.3 6.5 1 0.2 6.8 1 0.1 6.1 i 1.4 C-1 4.7 i 0.1 5.7 i 0.2 5.9 i 0.2 6.6 1 0.2 5.7 1.6 C-2 4.71 0.1 5.6 i 0.3 6.0 0.3 6.4 0.2 5.7 i 1.5 C-3 4.7 i 0.2 5.6 0.3 6.1 1 0.2 6.6 i 0.2 5.8 i 1.6 C-4 4.410.9 5.7 i 0.1 5.9 i 0.1 6.8 i 0.0 5.7 i 2.0 C-5 3.9 i 0.1 4.7 i 0.2 5.0 1 0.1 5.410.2 (a) 4.8 i 1.3 C-6 3.9 0.1 4.51 0.3 4.9 i 0.1 5.6 0.2 4.7 i 1.4 C-7 5.7 i 0.1 6.5 i 0.1 6.9 i 0.1 7.5 i 0.3 6.7 i 1.5 C-8 5.9 i 0.1 6.7 0.2 7.1 0.1 7.6 1 0.6 6.8 i 1.4 l Average 5.9 i 2.6 6.2 0.6 7.0 i 2.7 7.2 i 2.6 6.6 i 2.8 l l l l ( l O (a) Value based on areas 1,2, and 3. Area 4 was outside the acceptance enteria when compared to average of other areas. 78
i l I O
- O ArrENoix c LAND USE CENSUS.1997 l
l l O 79
l VIRGINIA POWER NORTH ANNA POWER STATION
- O A...ai Radioio,icai Environmentai Land use Census Data for 1997 July (1-31) l Nearest Nearest Site Milch
- Meat Milch
- Veg. Garden l
Sector Resident Boundary Cow Animal Goat 500 Sq Ft. t KM KM KM KM KM KM l N 2.14 1.40 3.23 2.98 i 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 1.95 1.33 1.95 ESE 2.53 1.37 7.74 5.63 SE 2.20 1.41 2.20 2.20 SSE 1.47 1.47 3.83 2.30 'O l S 1.67 1.52 2.32 1.96 i SSW 2.30 1.62 6.61 2.20 l SW 4.83 1.70 4.83 l WSW 2.86 1.75 2.86 2.86 l W 2.48 1.71 3.20 j l WNW l.61 1.64 6.13 4.28 NW l.57 1.56 1.77 NNW l.72 1.45 3.57 1.80 l O
- Note:
No milch cow or goats within a five mile radius of North Anna Power Station M = Mile 80
VIRGINIA POWER NORTH ANNA POWER STATION iO A i R aioio8 e i Eaviro me i i toaa use ce sos not ror 1997 i Juiy (1-31) i Nearest Nearest Site Milch
- Meat Milch
- Veg. Garden Sector Resident Boundary Cow Animal Goat 500 Sq Ft.
M M M M M M N 1.33 0.87 2.01 1.85 NNE 0.94 0.85 2.62 1.16 NE 0.98 0.82 1.56 1.12 ENE 1.97 0.81 2.56 1.97 E 1.21 0.83 1.21 ESE 1.57 0.85 4.81 3.50 SE 1.37 0.88 1.37 1.37 SSE 0.91 0.91 2.38 1.43 S 1.04 0.94 1.44 1.22 SSW l.43 1.01 4.11 1.37 SW 3.00 1.06 3.00 WSW l.78 1.09 1.78 1.78 W l.54 1.06 1.99 4 WNW l.00 1.02 3.83 2.66 NW 0.98 0.97 1.10 NNW l.07 0.90 2.22 1.12
- Note:
No milch cow or goats within a five mile redius of Nonh Anna Power Station KM = Kilometer 81 L
i VIRGINIA POWER NORTH ANNA POWER STATION 'O COMPARISON OF THE 1997 TO 1996 LAND USE CENSUS l I. No changes were observed in the nearest resident. II. No changes were obseived in the nearest site boundary distances. Ill. No changes were observed in the nearest milch cow / goat status. IV. No changes were observed in the nearest vegetable garden. V. No changes were observed in the nearest meat animal status. !O l l l l O i i 82 -)
O O APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES O
ANALYTICAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed on samples collected for the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO r.ad Teledyne Brown Engineering and include those recommended by the USNRC Branch Technical Position, Rev.1. November 1979. ANALYSIS TITLE PAGE Gross Beta Analysis of S amples...................................................................... 84 Airborne Particulates.......................................................................... 84 { l Water..............................................................................................85 { l l Analysis of Samples for Tritium (Liquid Scintillation)............................................. 86 Analysis of S amples for S trontium-89 and -90....................................................... 87 Total Wate r...................................................................................... 8 7 Milk..............................................................................................87-S oil and S ediment............................................................................... 87 O Organ ic S olids.................................................................................. 8 7 U l Air ParticuIates...................................................................................88 Analysis of S amples for Iodine-131.................................................................. 90 M ilk o r Wate r................................................................................... 90 i Gamma Spectrometry of S amples...................................................................... 91 l ~ l M il k an d Wat e r................................................................................. 9 1 Dried Solids other than Soils and Sediment................................................. 91 4 Fish..............................................................................................91 1 Soils and Sediments...........................................................................91 l l Charcoal Canridges ( Air Iodine).............................................................. 91 Airborne Paniculate s........................................................................... 91 1 Environ mental Dosimetry............................................................................... 93 Ov 1 1 83
GROSS BETA ANALYSIS OF SAMPLES l O Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) j daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused l air particulate filter, supplied by the customer,is counted as the blank. l l Calculations of the results, the two sigma error and the lower limit of detection (LLD): RESULT (pCi/m3) ((STT) -(B/t))/(2.22 V E) = 2((S/r2) + (B/t ))l/2 (2.22 V E) 2 / TWO SIGMA ERROR (pCi/m3) = 4.66 (B10)/(2.22 V E t) LLD (pCi/m3) = where: Gross counts of sample including blank S = Counts of blank B = Counting efficiency E = Number of minutes sample was counted T = Number of minutes blank was counted t = Sample aliquot size (cubic meters) V = i j O 84
r i DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES Introduction j The procedures described in this section are used to measure the overall radioactivity of l ) water samples without identifying the radioactive species present. No chemical separation techniques are involved. One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size. After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter i 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. O Detection Capability 2 Detection capability depends upon the sample volume actually represented on the planchette, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time. The minimum detectable level (MDL) for water samples is nominally 1.6 picoCuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/l at the 2.83 sigma level), assuming that I liter of I sample is used and that y gram of sample residue is mounted on the planchette. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency j and background of 0.2 and 1.2 cpm, respectively. i The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per liter. These values reflect a beta counting efficiency of 0.38. I l {G y 85
ANALYSIS OF SAMPLES FOR TRITIUM ,O Water Approximately 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zine conversion column heated to 400* C. The hydrogen is loaded into a one liter proponional detector and the volume is determined by recording the pressure. The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic rays. Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/l: 2(3.234)T V (C - B)/(C V ) RESULT = u g o u s 2(3.234) Tu V (E)l/2 (C V ) / TWO SIGMA ERROR = g s s 3.3 (3.234)T V (E)l/2 (C V ) / LLD = u g g s l tritium units of the standard l where: Tg = conversion factor changing tritium units to pCi/l i 3.234 = volume of the standard used to calibrate the efficiency of the detector in V = s l PSI' volume of the sample loaded into the detector in psia V = s the net epm of the standard of volume VN Cu = the gross epm of the sample of volume V3 l Co = the background of the detector in epm B = counting time for the sample At = Sfr2 + B/t2 E = O 86
1 ANALYSIS OF SAMPLES \\ l O) FOR STRONTIUM-89 AND -90 'L l Water Stable strontium carrier is added to I liter of sample and the volume is reduced by I evaporation. Strontium is precipitated as Sr(NO )2 using nitric acid. A barium scavenge and an 3 iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO from the sample after yttrium separation. This precipitate is mounted on a 3 nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Milk Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrN0 using fuming (90%) nitric acid. A barium chromate scavenge 3 O and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the j { sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC0 from the sample after yttrium separation. This precipitate 3 is mounted on a nylon planchette and is covered with an 80 mg/cm2 ahminum absorber for low level beta counting. Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO )2 using 3 fuming (90% nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a I low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating ) SrC0 fr m the sample after yttrium separation. This precipitate is mounted on a nylon planchette p 3 v and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. 87 J
g) Organic Solids ( A wet ponion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO ) using 3 fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then pre-cipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium l 2 separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm aluminum absorber for low level beta counting. Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(NO )2 using fuming (90%) nitric acid. A barium 3 scavenge is used to remove some interfering species. An iron (terric hydroxide) scavenge is V performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrC0 from the sample 3 after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with 80 2 mg/cm aluminum absorber for low level beta counting. Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/ volume or pCi/ mass: ESR-89) DFSR-89 = (N/Dt-B -B )/(2.22 V YS RESULT Sr 89 C A TWO SIGMA ERROR Sr-89 = 2((N/Dt+B +B )/At)l/2 (2.22 V Y DFSR-89 / ESR-89) C A 3 = 4.66((B +B )/At)l/2 (2.22 V YS DFSR-89 ESR-89) C A / LLD Sr-89 i RESULT Sr-90 = (N/At - B)/(2.22 V Yj Y DF IF E) 2 = 2((N/At+B)/At)l/2 (2.22 V Y Y DF E IF)) / i 2 TWO SIGMA ERROR Sr-90 = 4.66(B/At)1/2 (2.22 V Yj Y IF DF E) '() / 2 LLD Sr-90 r l l 88
total counts from sampic (counts) WHERE: N = counting time for sample (min) At = background rate of counter (cpm) using absorber configuration B = C dpm/pCi 2.22 = volume or weight of sampie analyt.ed V = background addition from Sr-90 and ingrowth of Y-90 B = A 0.016 (K) + (K) EY/ abs)(IG -90) 13 Y = A chemical yield of strontium Y = 3 decay factor from the mid collection date to the counting DF = SR 89 I date for SR-89 efficiency of the counter for SR-89 with the 80 mg/cm.sq. E = SR-89 aluminum absorber Y Y IF -90DFy.90 j) (NAt - B )Y-90 (E -90 C / Y K = the decay factor for Y-90 from the " milk" time te the mid DFY-90) = count time cfficiency of the counter for Y-90 E = Y-90 ingrowth factor for Y-90 from scavenge time to milking time j IF = Y 90 the ingrowth factor for Y-90 into the strontium mount from IG = Y-90 O the " milk" time to the mid count time \\g the efficiency of measuring SR-90 through a No. 6 absorber 0.016 = the efficiency of counting Y-90 through a No. 6 absorber j EY = / abs background rate of counter (cpm) 11 = chemical yield of yttrium Y = g chemical yield of strontium Y = 2 decay factor of yttrium from the radiochemical milking time to DF = the mid count time efficiency of the counter for Y-90 E = ingrowth factor for Y-90 from scavenge time to the radio-IF = chemical milking tirae /3 V 89
ANALYSIS OF SAMPLES FOR 10 DINE-131 Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from l 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 so!ution and is precipitated as palladium iodide. The sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchette for low level beta counting. The chemical yield is corrected by measuring the stable 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: (N/At-B)/(2.22 E V Y DF) RESULT = l 2((N/At+B)/At)l/2 (2.22 E V Y DF) / TWO SIGMA ERROR = = 4.66(B/At)l/2 (2.22 E V Y DF) / LLD = total counts from sample (counts) where: N = counting time for sample (min) At = background rate of counter (cpm) B = dpm/pCi 2.22 = volume or weight of sample analyzed V = chemic:.1 yield of the mount or sample counted Y = decay factor from the collection to the counting date DF = efficiency of the counter for 1-131, corrected for self j E = absorption effects by the formula E,(exp-0.0061M)/(exp-0.0061M,) E = efficiency of the counter detennined from an 1-131 E, = standard mount mass of Pdl2 n the standard mount, mg Ms = mass of PD12 n the sample mount. mg M = O 90
j GAhihfA SPECTROhfETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature,less than 100 C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. j Fish As much as possible (up to the total sample) of the edible portion of the samp% 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. 1 Soils and Sediments Soils and sediments are dried at a low temperature, less than 100*C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height and analysis. Charcoal Cartridges (Air Iodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for I-131 of each charcoal cartridge can be determined (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 thineen 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) l 91
i detector coupled to a mini-computer-based data acquisition system which performs pulse height O anaiysis. A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, halflife, detector ef0ciency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass: (S-B)/(2.22 t E V F DF) RESULT = 2(S+B)l/2 (2.22 t E V F DF) / TWO SIGMA ERROR = 4.66(B)l/2 (2.22 t E V F DF) / LLD = Area, in counts, of sample peak and background where: S = (region of spectrum ofinterest) Background area, in counts, under sample peak, B = determined by a linear interpolation of the representative backgrounds on either side of the peak length of time in minutes the sample was counted = dpm/pCi 2.22 = detector efficiency for energy of interest E = and geometry of sample sample aliquot size (liters, cubic meters, kilograms, V = or grams) fractional gamma abundance (specific for each F = emitted gamma) decay factor from the mid-collection date to the DF = counting date 92 l
I ENVIRONMENTAL DOSIMETRY / A i U Teledyne Brown Engineering uses a CaSO :Dy thermoluminescent dosimeter (TLD) which 4 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 i i features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs. Following the field exposure period the TLDs are placed in a Teledyne Brown Engineering Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner. Calculations of results and the two sigma error in net milliroentgen (mR): i D = (D +D +D +D V4 RESULT = g 2 3 4 2((D D)2 (9 -D)2+(9.D)2+(9 0)2y3)W TWO SIGMA ERROR p = g 2 3 4 the net mR of area 1 of the TLD, and similarly for D, D, and D4 WiiERE: D 2 3 = i I K/R - A DI l g the instrument reading of the field dose in area i I = g the known exposure by the Cs-137 source j K = the instrument reading due to the Cs-137 dose on area 1 R = g average dose in mR, calculated in similar manner as above, A = of the transit control TLDs the average net mR of all 4 areas of the TLD. D = O 93
!O i i i O ArreNnIx e INTERLABORATORY COMPARISON PROGRAM O
i Interlaboratory Comparison Program Teledyne Brown Engineering participates in the EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. Beginning with 1996 the EPA l discontinued providing milk and air particulate filter samples. For replacements, we have purchased comparable spiked samples from Analytics,Inc. In this section the third quarter 1997 data summary tables are presented for isotopes in the various sample media applicable to the North Anna Power Station's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence. O O i 94
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ANALYTICS CROSS CHECK COMPARISON PROGRAM 1997 O Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a) Result Ratio (b) E0975-396 Milk 1-131 18 1 1 20 i 1 0.90 TI#41238 Ce-141 L.T.1. 232 i 12 l 03/20/97 Cr-51 381 i 38 387 19 0.98 Cs-134 132i 13 143 i 7 0.92 Cs-137 128 i 13 114 6 1.12 Co-58 89 i 9 79 i 4 1.13 Mn-54 195 i 20 176 i 9 1.11 Fe-59 161i 16 144 i 7 1.12 Zn-65 171 i 17 165 i 8 1.04 CO-60 179i 18 176 i 9 1.02 E0976-396 Milk Sr-89 13 i 3 25 i 1 0.52 (c) TI#41239 Sr-90 16 i 1 19 1 0.84 03/20/97 E1092-396 Air Filter Ce-141 143 8 132 i 7 1.08 TI #49899-901 Cr-51 229 i 17 198 10 1.16 06/19/97 Cs-134 74 i 4 81 i 4 0.91 Cs-137 143 i 8 115 i 6 1.24 Co-58 89 i 5 77 i 4 1.16 Mn-54 102i 6 84 i 4 1.21 Fe-59 98 i 6 75 i 4 1.31 Zn-65 188 11 139 i 7 1.35 Co-60 113 i 7 104 5 1.09 E1093-396 Cartridge I-131 106i 6 88 i 4 1.20 TI #49902-04 06/19/97 E1094-396 Air Filter Sr-90 88 5 96 i 5 0.92 T1 #49893-95 06/19/97 E1095-396 Air Filter Gross Alpha 103 i 6 93 i 5 1.11 T1 #49896-98 Gross Beta 210 i 6 193 i 10 1.09 06/19/97 E1204-396 Milk 1-131 97 i 10 87 i 4 1.11 TI#57520 Cc-141 83 i 8 77 i 4 1.08 09/18/97 Cr-51 323 t 40 304 i 15 1.06 Cs-134 98 i 10 102 5 0.96 Cs-137 117 i 12 107 5 1.09 Co-58 64 i 6 60 i 3 1.07 1 Mn-54 99 i 10 88 4 1.13 Fe-59 132 13 119 i 6 1.11 Zn-65 218 i 22 196 i 10 1.11 Co-60 2091 21 197 i 10 1.06 l 97
ANALYTICS CROSS CHECK COMPARISON PROGRAM 1997 O Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a) Result Ratio (b) E1203-396 Milk Sr-89 14 i 1 15 i 1 0.93 i TI#57517 Sr-90 18 1 14 i 1 1.29 l 09/18/97 Footnotes: (a) Teledyne Results - counting error is two standard deviations. Units are pC1/ liter for water and milk. For gamma results. if two standard deviations are less than 10%, then a 10% eror is reported. Units are total pCi for air particulate filters. (b) Ratio of Teledyne Brown Engineering to Analytics results. (c) Caused by incorrect rinsing of the strontium extraction column. Additional training was conducted on 9/5/97 and was documented in the analyst's training file. Subsequent tests on two milk samples spiked with Sr-89 produced good results. i f l O 98
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