ML031340703
| ML031340703 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 05/31/2003 |
| From: | Entergy Nuclear Vermont Yankee |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| BVY 03-45 | |
| Download: ML031340703 (23) | |
Text
Figure 6.22 - Exposure Rate at Inner Ring TLDs DR33, 35, 37 & 39 9
8.5 8
7.5
- 7 0
h-6 5.5 -
5-4.5 -
4-1995 1996 1997 1998 1999 2000 2001 2002 2003 Retrieval Date
Figure 6.23 - Exposure Rate at Outer Ring TLDs DR10, 12, 14 & 16 9
8.5 8
7.5 1.
o 0
7 M '
0 6.5 S
6 5.5 5
4.5 4 =
1995 1996 1997 1998 1999 2000 2001 2002 2003 Retrieval Date c 3
Figure 6.24 - Exposure Rate at Outer Ring TLDs DR18, 20, 22 & 24 9
8.5 8
7.5 L.
0 7
6.5 2 6 w ~5 5.5 5
4.5 4
1995 1996 1997 1998 1999 2000 2001 2002 2003 Retrieval Date mwmmmm
Figure 6.25 - Exposure Rate at Outer Ring TLDs DR26, 28, 30 & 32 9
8.5 8
7.5 I0 7
=
.0 c-i 6.5 5.5 5
4.5 4 -
1995 1996 1997 1998 1999 2000 2001 2002 2003 Retrieval Date O'N'W"A I CZ7.
Figure 6.26 - Exposure Rate at Outer Ring TLDs DR 34, 36, 38 & 40 a
10 9.5 9
8.5 8
1.
o 7.5 xD I
Cn1 rf 7
. 6.5 6
5.5 5
4.5 4 f 1995 1996 1997 1998 1999 2000 2001 2002 2003 Retrieval Date A A CZC
Figure 6.27 - Exposure Rate at Control TLDs DR04 & 05 9
8.5 8
7.5 L.
0 7
I' I
(% c-i 6.5 C) 6 5.5 5
4.5 4 -
1995 1996 1997 1998 1999 2000 2001 2002 2003 Retrieval Date a on, f Fe' ,..
1 M I II , , , " 1. V .!k ----------
CZ7
7 QUALITY ASSURANCE PROGRAM 7.1 Framatome ANL Environmental Laboratory (E-LAB) - Environmental TLD Quality Assurance Program Routine quality control (QC) testing was performed for each type of dosimeter issued by the Framatome A-NP E-LAB Dosimetry Services Section. The dosimeter types included Panasonic 808 and 814 whole body dosimeters, combination 808/814 neutron dosimeters, extremity dosimeters and Panasonic environmental dosimeters. QC dosimeters were irradiated in-house as well as by a third party. All testing methods used by the accredited third-party tester conform to ANSI N13.11-1993 or ANSI N13.32-1995.
Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the Framatome ANP E-LAB Dosimetry Services Section is provided by the dosimetry quality assurance testing program. This program includes the National Voluntary Laboratory Accreditation Program, independent third party performance testing by Battelle Pacific Northwest Labs and internal performance testing conducted by the Laboratory QA Officer. Under these programs, dosimeters are irradiated to ANSI specified testing criteria and submitted for processing to the Dosimetry Services Group as "unknowns".
The bias and precision of TLD processing is measured against this standard and is used to indicate trends and changes in performance. Instrumentation checks, although routinely performed by the Dosimetry Services Section and representing between 5-10% of the TLDs processed, are not presented in this report because they do not represent a true process check sample since the doses are known to the processor.
Ninety performance tests were conducted in 2002 by Framatome ANP E-LAB Dosimetry Services Section and the third party tester. Of these, 100% of the dosimeter evaluations met the acceptance criteria for bias (+ 20.1%) and precision (:12.8%). Third Party QC results are summarized below.
Dosimeter Type Number Free in Air Tested % passed bias criteria % passed precision criteria Panasonic Environmental 90 100 100 Summary of Third Party Testing Dosimeter Type Exposure Period NVLAB Category Free in Air Panasonic Environmental Q1/2002 IV, high energy 5.6 +/- 1.2 0..068 Panasonic Environmental Q2/2002 IV, high energy 8.8 i 1.1 0.099 Panasonic Environmental Q3/2002 IV, high energy 7.1 +/- 3.1 0.102 Note: Results are expressed as the delivered exposure for environmental TLD. NVLAB Category IV, High energy photons (Cs-137 or Co-60).
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7.2 Teledyne Brown Engineering Laboratory -Environmental Services (TBE-SE) 7.2.1 Operational Quality Control Scope 7.2.1.1 Inter-laboratory The TBE-ES Laboratory QC Program is designed to monitor the quality of analytical procassing associated with environmental, effluent (IOCFR Part 50), and waste characterization (IOCFR Part 61) samples.
Quality Control of environmental radioanalyses involves the internal process control program and independent third party programs administered by Analytics, Inc and Environmental Resource Associates (ERA).
TBE-ES participates in the Quality Assessment Program (QAP) administered by the Department of Energy (DOE) Environmental Measurements Laboratory (EML) and the DOE Mixed Analyte Performance Evaluation Program (MAPEP). The MAPEP is a set of performance evaluation samples (e.g. Water, soil, air filters, etc.) designed to evaluate the ability and quality of analytical facilities performing sample measurements which contain hazardous and radioactive (mixed) analytes. TBE-ES also participates in the New York State Department of Health Environmental Laboratory Approval Program (NYELAP).
Quality Control for radioanalyses during this reporting period was divided among internal process check samples, third party process checks prepared by Analytics, Inc.
(which was submitted by users or secured directly by TBE-ES for QC purposes), ERA, DOE's EML, MAPEP, NYELAP and the Bioassay Environmental Radioactivity Cross Check Program (BERCCP).
7.2.1.2 Intra-laboratory The internal Quality Control program is designed to include QC functions such as instrumentation checks (to ensure proper instrument response), blank samples (to which no analyte radioactivity has been added), instrumentation backgrounds, duplicates, as well as overall staff qualification analyses and process controls. Both process control and qualification analyses samples seek to mimic the media type of those samples submitted for analyses by the various laboratory clients. These process controls (or process checks) are either actual samples submitted in duplicate in order to evaluate the accuracy of laboratory measurements, or blank samples which have been "spiked" with a known quantity of a radioisotope that is of interest to laboratory clients. These QC samples which represent either "single" or "double-blind" unknowns, are intended to evaluate the entire radiochemical and radiometric process.
To provide direction and consistency in administering the quality assurance program, TBE-ES has developed and follows an annual quality control and audit assessment schedule. The plan describes the scheduled frequency and scope of Quality Assurance and Control considered necessary for an adequate QA/QC program conducted throughout the year. The magnitude of the process control program combines both internal and external sources targeted at 5% of the routine sample analysis load.
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7.2.1.3 QA Program (Internal and External Audits)
During each reporting period at least one internal assessment is conducted in accordance with the pre-established TBE-ES Quality Control and Audit Assessment Schedule. In addition, the laboratory may be audited by prospective customers during a pre-contract audit, and/or by existing clients who wish to conduct periodic audits in accordance with their contractual arrangements. The Nuclear Utilities Procurement Issues Committee (NUPIC) conducts audits of TBE-ES as a function of a Utilities Radiological Environment Measurement Program (REMP).
TBE-ES Laboratory-Knoxville has successfully completed the NUPIC, Vermont Yankee Nuclear Power Station, Nebraska Public Power, BWX Technologies, the State of Tennessee, Westinghouse, Inc., the National Laboratory Accreditation Program (NELAP) which was conducted by the New York State Department of Health, Boeing Rocketdyne, DOE Environmental Management Consolidated Audit Program (EMCAP, Global Nuclear Fuels (GNF), Excelon Energy and Fluor-Daniel Femald audits. These audits were each a comprehensive review of TBE-ES's Quality and Technical programs used to assess the laboratory's ability to produce accurate and defensible data for our clients. No significant deficiencies, which would adversely impact data quality, were identified during any of these audits. Administrative findings identified during these inspections are usually addressed promptly, according to client specifications.
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7.2.2 Analytical Services Quality Control Synopsis 7.2.2.1 Results Summary 7.2.2.1.1 Environmental Services Quality Control During this annual reporting period, twenty-one nuclides associated with six media types were-analyzed by means of the laboratory's internal process control, Analytics, ERA and DOE quality control programs. Media types representative of client company analyses performed during this reporting period were selected. The results for these programs are presented in Tables 7.2. Below is a synopsis of the media types evaluated:
- Air Filter
- Charcoal (Air Iodine)
- Milk
- Soil
- Vegetation
- Water 7.2.2.1.2 Analytics Environmental Cross-Check Program Fourteen nuclides were evaluated during this reporting period. All but one of the 95 environmental analyses performed were within the acceptable criteria. In one sample, coincidental summing resulted in low Cesium-134 activity. Elimination of the coincidental summing resulted in an activity of 110 Pico Curies (pCi) which compared well to the known activity of 114 pCi. No further action was required.
7.2.2.1.3 Summary of Participation in the Department of Energy (DOE) Monitoring Programs TBE-ES participated in the EML program. During this reporting period, 13 nuclides were evaluated. All of the 46 environmental analyses were within acceptable criteria.
TBE-ES participated in the semi annual Mixed Analyte Performance Evaluation Program (MAPEP) for liquid analyses (MAPEP-00-W8). All eight nuclides were evaluated and were acceptable. All of the 13 environmental analyses performed were within the acceptable criteria.
7.2.2.1.5 Summary of participation in the ERA Program During this reporting period, eight nuclides were analyzed under ERA criteria.
All 16 environmental analytical results were acceptable.
7.2.2.2 Intra-Laboratory Process Control Program The TBE-ES Laboratory's internal process control program evaluated 8 10 individual samples.
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7.2.2.2.1 Spikes All 405 environmental spikes were analyzed with statistically appropriate activity reported for each spike.
7.2.2.2.2 Analytical Blanks During this reporting period, all but 18 of the 405 environmental analytical blanks analyzed reported less than MDC. The activity detected for the 18 blanks is indistinguishable from natural background.
7.2.2.2.3 Duplicates All 157 duplicate sets analyzed were within acceptable limits.
7.2.2.2.4 Non-Conformance Reports There were three non-conformance reports issued for this reporting period. No Vermont Yankee data was impacted by the non-conformance in each of these cases.
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Table 7.2.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide ( Units Value (a) Value (b) TBE/Analytics Evaluation (d)
February, 2002 A15211-55 Liquid Sr-89 uCi/mL 1.60E-03 2.03E-03 0.79 Sr-90 2.90E-04 3.64E-04 0.80 A15213-55 Liquid H-3 uCi/mL 1.08E-03 1.19E-03 0.90 March, 2002 E3064-396 Milk Sr-89 pCi/L 80 83 0.96 Sr-90 28 27 1.04
- 3065-396 Milk 1-131 pCi/L 86 92 0.93 Ce-141 300 326 0.92 Cr-51 256 267 0.96 Cs-134 94 122 0.77 Cs-137 252 266 0.95 Mn-54 217 224 0.97 Fe-59 108 116 0.93 Zn-65 218 221 0.99 Co-60 147 158 0.93 E3067-396 AP 1-131 pCi 202 199 1.02 Cr-51 166 163 1.02 Cs-1 34 77 74 1.04 Cs-1 37 162 162 1.00 Mn-54 135 136 0.99 Fe-59 70 70 1.00 Zn-65 128 134 0.96 Co-60 95 96 0.99 E3066-396 Charcoal 1-131 pCi 66 77 0.86 May, 2002 A15521-55 Liquid Gr-Alpha uCi/mL 8.48E-04 7.15E-04 1.19 A A15520-55 Liquid Sr-89 uCi/mL 2.63E-03 3.25E-03 0.81 A Sr-90 2.51 E-04 2.70E-04 0.93 A A15522-55 Liquid H-3 uCVmL 1.35E-03 1.46E-03 0.92 A 102
Table 7.2.1 (cont.)
ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)
Identification Reported Known Ratio (c)
MonthlYear Number Matrix Nuclide (1) Units Value (a) Value (b) TBE/Analytics Evaluation (d)
June, 2002 E3220-396 Milk 1-131 pCi/L 86 87 0.99 A Ce-141 84 90 0.93 A Cr-51 197 235 0.84 A Cs-1 34 110 120 0.92 A Cs-1 37 96 91 1.05 A Co-58 95 100 0.95 A Mn-54 106 95 1.12 A Fe-59 95 81 1.17 A Zn-65 186 180 1.03 A Co-60 132 125 1.06 A June, 2002 E3222-396 AP Ce-141 pCi 85 75 1.13 A Cr-51 199 196 1.02 A Cs-1 34 96 100 0.96 A Cs-1 37 92 76 1.21 w Co-58 98 83 1.18 A Mn-54 87 79 1.10 A Fe-59 85 67 1.27 w Zn-65 182 150 1.21 w Co-60 121 104 1.16 A August, 2002 A16018-55 Liquid Sr-89 uCi/mL 4.12E-03 4.99E-03 0.83 A Sr-90 2.43E-04 2.64E-04 0.92 A A16020-55 Liquid H-3 uCi/mL 1.93E-03 2.OOE-03 0.97 A September, 2002 A15989-148 Liquid Sr-89 uCi/mL 4.02E-03 4.99E-03 0.81 A Sr-90 2.49E-04 2.64E-04 0.94 A E3324-396 Milk Sr-89 pCi/L 106 92 1.15 A Sr-90 39 39 1.00 A September, 2002 E3325-396 Milk 1-131 pCi/L 84 80 1.05 A Ce-141 168 160 1.05 A Cr-51 210.5 227 0.93 A Cs-1 34 127 132 0.96 A Cs-137 136 127 1.07 A Co-58 93 97 0.96 A M-n-54 165 152 1.09 A Fe-59 90 89 1.01 A Zn-65 196 187 1.05 A Co-60 147 149 0.99 A 103
Table 7.2.1 (cont.)
ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)
Identification Reported Known Ratio (c)
MonthlYear Number Matrix Nuclide (1) Units Value (a) Value (b) TBE/Analytics Evaluation (d)
September, 2002 E-3327-396 Filter Ce-141 pCi 115 110 1.05 A Cr-51 163.6 156 1.05 A Cs-134 79 90 0.88 A Cs-137 95 87 1.09 A Co-58 71 67 1.06 A Mn-54 118 104 1.13 A Fe-59 76 61 1.25 w Zn-65 155 130 1.19 A Co-60 108 102 1.06 A E3326-396 Charcoal 1-131 pCi 73 85 0.86 A December, 2002 E3520-396 Milk Sr-89 pCi/L 88 68 1.29 w Sr-90 40 38 1.05 A E3521-396 Milk 1-131 pCi/L 97 86 1.13 A Ce-141 136 ill 1.23 w Cr-51 347 346 1.00 A Cs-134 97 99 0.98 A Cs-137 229 220 1.04 A Co-58 143 139 1.03 A Mn-54 162 142 1.14 A Fe-59 80 72 1.11 A Zn-65 217 178 1.22 w Co-60 172 164 1.05 A December, 2002 E3523-396 Filter Ce-141 pCi 108 128 0.84 A Cr-51 370 398 0.93 A Cs-134 79 114 0.69 N (2)
Cs-137 226 253 0.89 A Co-58 141 160 0.88 A Mn-54 152 163 0.93 A Fe-59 89 83 1.07 A Zn-65 196 206 0.95 A Co-60 170 189 0.90 A E3522-396 Charcoal 1-131 pCi 84 96 0.88 A Analytics known values were incorrectly calculated. Revised (as shown) evaluation was acceptable.
(1) Only analyses performed routinely for the REMP are included on this table.
(2) Coincidental summing resulted in low Cesium-134 activity. Elimination of the coincidental summing resulted in an activity of 110 pCi.
No futher action required.
(a) Teledyne Brown Engineering reported result.
(b) The Analytics known value is equal to 100% of the parameter present In the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
fc) Ratio of Teledyne Brown Engineering to Analytics results.
(d) Analytics evaluation: A= acceptable. Reported result falls within ratio limits of 0.80-1.20. W=acceptable with waming.
Reported result falls within ratio limits of 0.70-0.79 and 1.21-1.30. N=not acceptable. Reported result is outside the ratio limilits of < 0. 70 and > 1.30.
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Table 7.2.2 DOE/EML ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 2)
Identification Reported Known Ratio (c)
Month/Year Number Media Nuclide 1) Units Value (a) Value (b) TBE/EML Evaluation (d)
June, 2002 QAP 56 AP Co-60 Bq/filter 31.7 30.52 1.04 A Cs-137 30.4 28.23 -1.08 A Gr-Beta 1.21 1.30 0.93 A Mn-54 38.3 38.53 0.99 A Sr-90 4.68 4.832 0.97 A Soil Ac-228 Bqlkg 50 51.167 0.98 A Bi-212 35.9 53.43 0.67 A Bi-214 46.3 53.933 0.86 W Cs-137 1300 1326.67 0.98 A K-40 608 621.67 0.98 A Pb-212 49.4 51.1 0.97 A Pb-214 49.1 54.367 0.90 A Sr-90 46.6 53.756 0.87 A Vegetation Co-60 Bq/kg 11.7 11.23 1.04 A Cs-137 346 313.667 1.10 A K-40 952 864.33 1.10 A Sr-90 477 586.28 0.81 A June, 2002 QAP 56 Water Co-60 Bq/L 367 347.33 1.06 A Cs-134 2.93 3.357 0.87 w Cs-137 59.6 56.067 1.06 A Gr-Beta 895 1030 0.87 A H-3 285 283.7 1.00 A Sr-90 5.78 7.579 0.76 w
_ X 105
Table 7.2.2(cont.)
DOE/EML ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2)
Identification Reported Known Ratio (c)
Month/Year Number Media Nuclide (1) Units Value (a) Value (b) TBE/EML Evaluation (d)
December, 2002 QAP 57 AP Co-60 Bq/filter 24.1 23.0 1.05 A Cs-1 37 36.1 32.5 1.11 A Gr-Beta 0.813 0.871 0.93 A Mn-54 58.3 52.2 1.12 A Sr-90 5.86 5.561 1.05 A Soil Bi-212 Bqlkg 23.2 45.93 0.51 w Bi-214 32.4 33.63 0.96 A Cs-I 37 835 829.33 1.01 A K-40 671 637.67 1.05 A Pb-212 42.00 43.43 0.97 A Pb-214 44.46 35.2 1.26 A Sr-90 41.00 41.16 1.00 A December, 2002 QAP 57 Vegetation Co-60 Bqlkg 11.5 9.66 1.19 A Cs-137 345 300.67 1.15 A K-40 1690 1480 1.14 A Sr-90 457 476.26 0.96 A Water Am-241 Bq/L 2.89 3.043 0.95 A Co-60 303 268.67 1.13 W Cs-134 59 60.2 0.98 A Cs-137 85.8 81.43 1.05 A Gr-Beta 817 900 0.91 A H-3 353 227.3 1.55 w Sr-90 8.58 8.69 0.99 A (1) Only analyses performed routinely for the REMP are included on this table.
(a) Teledyne Brown Engineering reported result.
(b) The DOEIEML known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) Ratio of Teledyne Brown Engineering to DOEIEML results.
(d) DOEIEML evaluation: A =acceptable. W=acceptable with waming, N=not acceptable.
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Table 7.2.3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)
Identification Reported Known Ratio (c)
Month/Year Number Media Nuclide (1) Units Value (a) Value (b) TBE/ERA Evaluation (d).
May, 2002 Rad 49 Water Gr-Beta pCi/L 162 189 0.86 A Co-60 39.3 39.1 1.01 A Cs-1 34 15.5 17.1 0.91 A Cs-137 52.2 52.1 1.00 A Sr-89 27.2 31.7 0.86 A Sr-90 25.1 28.3 0.89 A 1-131 13.35 14.7 0.91 A H-3 14600 17400 0.84 A November, 2002 Rad 51 Water H-3 pCi/L 10100 10200 0.99 A 1-131 7.94 6.76 1.17 A Gr-Beta 280 330 0.85 A Sr-89 41.7 47.6 0.88 A Sr-90 6.75 7.56 0.89 A Co-60 122 104 1.17 A Cs-134 60.0 55.5 1.08 A Cs-137 140 117 1.20 A (1) Only analyses performed routinely for the REMP are included on this table.
(a) Teledyne Brown Engineering reported result.
(b) The ERA known value is equal to 100% of the parameterpresent in the standard as determined by gra vimetric and/or voluimetric measurements made during standard preparation.
(c) Ratio of Teledyne Brown Engineering to ERA results.
(d) ERA evaluation:A=acceptable. Reportedresultfalls withinratiolimitsofO.60-1.20. W=acceptable with warning.
Reported result falls within ratio limits of 0.70-0.79 and 1.21-1.30. N=not acceptable. Reported result is outside the ratio limits of < 0.70 and > 1.30.
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Table 7.2.4 MAPEP ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)
Identification Reported Known Month/Year Number Media Nuclide () Units Value (a) Value (b) Control Limits Evaluation (c)
March. 2002 01-W9 Water Mn-54 Bq/L 253 246 172.20 - 319.80 A Co-57 141 143 100.10-185.90 A Co-60 143 141 98.70 - 183.30 A Cs-1 34 26.0 28.5 19.95 - 37.05 A Cs-1 37 270 286 200.20 - 371.80 A Sr-90 4.71 4.8 3.39 - 6.24 A August, 2002 02-S9 Soil Mn-54 Bq/kg 679 546 382.2 - 709.8 w Co-57 289 246 172.2 - 319.8 A Co-60 109 87.5 61.25 - 113.75 w Cs-1 34 948 862 603.4- 1120.6 A Cs-1 37 131 111 77.7 - 144.3 A Zn-65 1020 809 556.3 - 1051.7 w K40 722 652 456.4 - 847.6 A (1) Only analyses performed routinely for the REMP are included on this table.
(a) Teledyne Brown Engineering reported result.
(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric andKor voltimetric measurements made during standard preparation.
(r) DOEIMAPEP evaluation: A=acceptable, W=acceptable with waming, N=not acceptable.
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- 8. Land Use Census VYNPS Off-site Dose Calculation Manual 3/4.5.2 requires that a Land Use Census be conducted annually between the dates of June I and October 1. The Census identifies the locations of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of five miles of the plant. It also identifies the nearest milk animal (within three miles of the plant) to the point of predicted highest annual average D/Q value due to elevated releases from the plant stack in each of the three major meteorological sectors. The 2002 Land Use Census was conducted in the summer of 2002 in accordance with the ODCM.
Following the collection of field data and in compliance with Off-site Dose Calculation Manual (ODCM)
Section 10.1, a dosimetric analysis is performed to compare the census locations to the "critical receptor" identified in the ODCM. This critical receptor is the location that is used in the Method 1 screening dose calculations found in the ODCM (i.e. the dose calculations done in compliance with ODCM Surveillance 4.3.3). If a Census location has a 20% greater potential dose than that of the critical receptor, this fact must be announced in the annual Radioactive Effluent Release Report for that period. A re-evaluation of the critical receptor would also be done at that time. No changes in the census from year 2001 occurred for the 2002 census, therefore no such revision of the 2001 calculations were required.
Pursuant to ODCM 3.5.2.a, a dosimetric analysis would be performed, using site specific meteorological data, to determine which milk animal locations would provide the optimal sampling locations. If any location had experienced a 20% greater potential dose commitment than at a currently sampled location, the new location would be added to the routine environmental sampling program in replacement of the location with the lowest calculated dose (which is eliminated from the program). The 2002 Land Use Census did not identify any locations, meeting the criteria of ODCM Table 3.5.1, with a greater potential dose commitment than at currently sampled locations. No changes to the Radiological Environmental Monitoring Program (REMP) were required based on the Land Use Census.
The results of the 2002 Land Use Census are included in this report in compliance with ODCM 4.5.2 and ODCM 10.2. The locations identified during the Census may be found in Table 8.1.
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TABLE 8.1 2002 LAND USE CENSUS LOCATIONS*
SECTOR NEAREST RESIDENCE NEAREST MILK ANIMAL Km (Mi) Km (Mi)
N 1.5 (0.9) ----
NNE 1.4 (0.9) 5.5 (3.4) Cows NE 1.3 (0.8)
ENE 1.0(0.6)
E 0.9 (0.6)
ESE 2.8 (1.8)
SE 2.0 (1.2) 3.6 (2.2) Cows**
SSE 2.1(1.3)
S 0.5 (0.3) 2.2 (1.4) Covs**
SSW 0.5 (0.3)
SW 0.4 (0.3) 8.2 (5.1) Cows WSW 0.5 (0.3) 9.6 (6.0) Goats W 0.6 (0.4) 0.8 (0.5) Cows WNW 1.1(0.7) 7.5 (4.7) Cows NW 2.6 (1.6) ----
NNW- 2.6,(1.6)
- Sectors and distances are relative to the plant stack as determined by a Global Positioning System survey conducted in 1997.
- Location of nearest milk animal within 3 miles of the plant to the point of predicted highest annual average D/Q value in each of the three major meteorological sectors.
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- 9.
SUMMARY
During 2002 as in all previous years of plant operation, a program was conducted to assess the levels of radiation or radioactivity in the Vermont Yankee Nuclear Power Station environment. Over 800 samples were collected (including TLDs) over the course of the year, with a total of over 2700 radionuclide or exposure rate analyses performed. The samples included ground water, river water, sediment, fish, milk, silage, mixed grass, storm drain sediment, and storm drain water. In addition to these samples, the air surrounding the plant was sampled continuously and the radiation levels were measured continuously with environmental TLDs.
Three of the objectives of the Radiological Environmental Monitoring Program (REMP) are:
- To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the station.
- To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.
- To verify the adequacy and proper functioning of station effluent controls and monitoring systems. .
Low levels of radioactivity from three sources (discussed below) were detected in samples collected off-site as a part of the radiological environmental monitoring program. Most samples had measurable levels of K-40, Be-7, Th-232 or radon daughter products. These are the most common of the naturally-occurring radionuclides. Many samples (particularly milk, river water, mixed grass, and sediment) had fallout radioactivity from atmospheric nuclear weapons tests conducted primarily from the late 1950s through 1980. Several samples from onsite locations (from the plant storm drain system) had low levels of radioactivity resulting from emissions from the Vermont Yankee plant. In all cases, the possible radiological impact was negligible with respect to exposure from natural background radiation. In no case did the detected levels exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment.
111
- 10. REFERENCES
- 1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
- 2. NCRP Report No. 94, Exposure of the Population in the United States and CanadafromNatural BackgroundRadiation, National Council on Radiation Protection and Measurements, 1987.
- 3. Ionizing Radiation: Sources and Biological Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly.
- 4. Kathren, Ronald L., Radioactivity and the Environment - Sources, Distribution, and Surveillance, Harwood Academic Publishers, New York, 1984.
- 5. Till, John E. and Robert H. Meyer, ed., RadiologicalAssessment - A Textbook on Environmental Dose Analysis, NUREG/CR-3332, U.S. Nuclear Regulatory Commission, Washington, D.C.,
1983.
- 6. NUREG/CR-3130, Influence of Leach Rate and Other Parameters on Groundwater Migration, February 1983.
_, .. =
112