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| issue date = 04/30/2010 | | issue date = 04/30/2010 | ||
| title = Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report | | title = Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report | ||
| author name = Stanley B | | author name = Stanley B | ||
| author affiliation = Virginia Electric & Power Co (VEPCO) | | author affiliation = Virginia Electric & Power Co (VEPCO) | ||
| addressee name = | | addressee name = | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 30, 2010 Attention: | {{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 30, 2010 Attention: Document Control Desk Serial No. 10-206 U.S. Nuclear Regulatory Commission SS&LITJN RO Washington, D. C. 20555-0001 Docket Nos. 50-280 50-281 72-2 72-55 License Nos. DPR-32 DPR-37 SNM-2501 Gentlemen: | ||
Document Control Desk Serial No. 10-206 U.S. Nuclear Regulatory Commission SS&LITJN RO Washington, D. C. 20555-0001 Docket Nos. 50-280 50-281 72-2 72-55 License Nos. DPR-32 DPR-37 SNM-2501 Gentlemen: | VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Surry Units 1 and 2 Technical Specification 6.6.B.2 requires the submittal of an Annual Radiological Environmental Operating Report (AREOR) for Surry Power Station. Surry Independent Spent Fuel Storage Installation (ISFSI) Technical Specification Appendix C, Item 1.3.1 requires that the Surry ISFSI be included in the environmental monitoring for the Surry Power Station. Accordingly, enclosed is the Surry Power Station AREOR for the period of January 1, 2009 through December 31, 2009, which includes environmental monitoring for the Surry ISFSI. | ||
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Surry Units 1 and 2 Technical Specification 6.6.B.2 requires the submittal of an Annual Radiological Environmental Operating Report (AREOR) for Surry Power Station. Surry Independent Spent Fuel Storage Installation (ISFSI) Technical Specification Appendix C, Item 1.3.1 requires that the Surry ISFSI be included in the environmental monitoring for the Surry Power Station. Accordingly, enclosed is the Surry Power Station AREOR for the period of January 1, 2009 through December 31, 2009, which includes environmental monitoring for the Surry ISFSI.If you have any questions or require additional information, please contact Paul Harris at 757-365-2692. | If you have any questions or require additional information, please contact Paul Harris at 757-365-2692. | ||
Sincerely, B. L. Stanley Director Station Safety and Licensing Surry Power Station Attachment Commitments made in this letter: None S&eAS Serial No. 10-206 Docket Nos.: 50-280 50-281 72-2 72-55 copy: United States Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 NRC Senior Resident Inspector Surry Power Station Director Division of Radiological Health 109 Governor Street, Room 730 Richmond, Virginia 23219 Serial No. 10-206 Docket Nos.: 50-280 50-281 72-2 72-55 Attachment I 2009 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station 2009 Annual Radiological Environmental Operating Report DoMn' | Sincerely, B. L. Stanley Director Station Safety and Licensing Surry Power Station Attachment Commitments made in this letter: None S&eAS | ||
Serial No. 10-206 Docket Nos.: 50-280 50-281 72-2 72-55 copy: United States Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 NRC Senior Resident Inspector Surry Power Station Director Division of Radiological Health 109 Governor Street, Room 730 Richmond, Virginia 23219 | |||
........................................................................................................ | |||
7 2.1 Introduction | Serial No. 10-206 Docket Nos.: 50-280 50-281 72-2 72-55 Attachment I 2009 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION VIRGINIA ELECTRIC AND POWER COMPANY | ||
.............................................................................................................................. | |||
7 2.2 Sam pling and Analysis Program ........................................................................................ | Surry Power Station 2009 Annual Radiological Environmental Operating Report DoMn | ||
'kDOminiont | |||
20 3.1 | |||
20 3.2 Analytical Results of 2009 REM P Sam ples ................................................................... | Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2009 to December 31, 2009 | ||
49 4.1 Gam m a Exposure Rate ................................................................................................... | in Annual Radiological Environmental Operating Report Surry Power Station January 1, 2009 to December 31, 2009 HI In Prepared by: | ||
49 4.2 A irborne Gross Beta .............................................................................................................. | P. F. Blount ID Health Physicist ID Reviewed by: | ||
50 4.3 A irborne Radioiodine | P. R. Harris Supervisor Radiological Analysis Reviewed by: | ||
............................................................................................................. | Sii B. A. Hilt Supervisor Health Physics Technical Services Approved by: | ||
52 4.4 Air Particulate Gam | Manager Radiological Protection and Chemistry II 2 | ||
52 4.5 Cow M ilk .............................................................................................................................. | |||
52 4.6 Food Products ................................................................. | Table of Contents PREFA CE .............................................................................................................................................. 4 | ||
53 4.7 W ell W ater ............................................................................................................................ | : 1. EX ECUTIV E SU M MARY ....................................................................................................... 5 | ||
53 4.8 River W ater ........................................................................................................................... | : 2. PRO GRA M D ESCRIPTION ........................................................................................................ 7 2.1 Introduction .............................................................................................................................. 7 2.2 Sam pling and Analysis Program ........................................................................................ 8 | ||
53 4 .9 S ilt ......................................................................................................................................... | : 3. AN A LY TICAL RESU LTS ........................................................................................................ 20 3.1 Summ ary of Results .............................................................................................................. 20 3.2 Analytical Results of 2009 REM P Sam ples ................................................................... 28 | ||
: 4. D ISCU SSION OF RESU LTS ................................................................................................. 49 4.1 Gam m a Exposure Rate ................................................................................................... 49 4.2 A irborne Gross Beta .............................................................................................................. 50 4.3 A irborne Radioiodine ............................................................................................................. 52 4.4 Air Particulate Gam ma ..................................................................................................... 52 4.5 Cow M ilk .............................................................................................................................. 52 4.6 Food Products ................................................................. 53 4.7 W ell W ater ............................................................................................................................ 53 4.8 River W ater ........................................................................................................................... 53 4 .9 S ilt ......................................................................................................................................... 53 4.10 Shoreline Sedim ent ........................................................................................................ 55 4 .1 1 Fish ...................................................................................................................................... 55 4.12 Oysters ................................................................................................................................ 56 4.13 Clam s .................................................................................................................................. 56 4.14 Crabs ................................................................................................................................... 56 | |||
55 4 .1 1 | : 5. PRO GRAM EX CEPTION S ..................................................................................................... 57 | ||
: 6. CON CLU SION S ............................................................................................................................. 58 REFEREN CES .................................................................................................................................... 60 APPEN DICES ..................................................................................................................................... 62 APPEN D IX A : LAN D U SE CEN SU S ...................................................................................... 63 APPENDIX B: | |||
56 4.13 Clam s .................................................................................................................................. | |||
56 4.14 Crabs ................................................................................................................................... | |||
58 REFEREN CES .................................................................................................................................... | |||
60 APPEN DICES ..................................................................................................................................... | |||
62 APPEN D IX A : LAN D U SE CEN SU S ...................................................................................... | |||
63 APPENDIX B: | |||
==SUMMARY== | ==SUMMARY== | ||
OF INTERLABORATORY COMPARISONS | OF INTERLABORATORY COMPARISONS ........................... 65 3 | ||
........................... | |||
65 3 PREFACE This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report, for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281.4 | PREFACE This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report, for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281. | ||
4 | |||
: 1. EXECUTIVE | : 1. EXECUTIVE | ||
==SUMMARY== | ==SUMMARY== | ||
This document is a detailed report of the 2009 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2009, in air, water, silt, shoreline sediment, milk, aquatic biota, food products and direct exposure pathways have been analyzed, evaluated and summarized. | |||
The REMP is designed to confirm 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 are protected. | This document is a detailed report of the 2009 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2009, in air, water, silt, shoreline sediment, milk, aquatic biota, food products and direct exposure pathways have been analyzed, evaluated and summarized. The REMP is designed to confirm 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 are protected. | ||
The program also detects any unexpected environmental processes that could allow radiation accumulations in the environment or food pathway chains.Radiation and radioactivity in the environment are monitored within a 20-mile radius of the station. Surry Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained. | The program also detects any unexpected environmental processes that could allow radiation accumulations in the environment or food pathway chains. | ||
The first type, control samples, is collected from areas that are beyond the measurable influence of Surry Power Station or any other nuclear facility. | Radiation and radioactivity in the environment are monitored within a 20-mile radius of the station. Surry Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained. The first type, control samples, is collected from areas that are beyond the measurable influence of Surry 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 Surry Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration. | ||
These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than Surry Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. | 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 control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident or natural variation. | ||
These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration. | GEL Laboratories LLC and Teledyne Brown Engineering, Inc. provide radioanalyses for this program and Global Dosimetry Solutions, Inc. provides thermoluminescent dosimetry (TLD) services. Participation in an 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 United States Nuclear Regulatory Commission (USNRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as 5 | ||
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 control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident or natural variation. | |||
GEL Laboratories LLC and Teledyne Brown Engineering, Inc. provide radioanalyses for this program and Global Dosimetry Solutions, Inc. provides thermoluminescent dosimetry (TLD) services. | possible. The USNRC also mandates a reporting level for radionuclides. Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level. | ||
Participation in an Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy. | Environmental radiation levels are sometimes referred to as a percent of the reporting level. | ||
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 United States Nuclear Regulatory Commission (USNRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as 5 possible. | Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, aquatic, terrestrial and direct radiation exposure. The airborne exposure pathway includes radioactive airborne iodine and particulates. The 2009 airborne results were similar to previous years. No station related radioactivity was detected and natural radioactivity levels remained at levels consistent with past years' results. Aquatic exposure pathway samples include well and river water, silt and shoreline sediments, crabs, fish, clams and oysters. Naturally occurring potassium-40 was detected at average environmental levels. No man-made radionuclides were detected in well water. This trend is consistent throughout the operational environmental monitoring program. No man-made radionuclides were detected in river water. Silt samples indicated the presence of cesium- 137 and naturally occurring radionuclides. The cesium- 137 activity was present in the control and indicator locations and is attributable to global fallout from past nuclear weapons testing and nuclear accidents such as Chernobyl. Shoreline sediment, which may provide a direct exposure pathway, contained no station related radionuclides. Naturally occurring potassium-40 and thorium-228 were detected at average environmental levels. The terrestrial exposure pathway includes milk and food products. Iodine-131 was not detected in any 2009 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90 was again detected in milk and this activity is attributable to past atmospheric nuclear weapons testing. No man-made radionuclides were detected in food product samples. Consistent with historical data, naturally occurring potassium-40 was detected in milk and food products. The direct exposure pathway measures environmental radiation doses using TLDs. TLD results have remained relatively constant over the years. | ||
The USNRC also mandates a reporting level for radionuclides. | During 2009, as in previous years, the operation of Surry Power Station has created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2009 was 0.001 millirem. For reference, this dose may be compared to the 620 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 50% of radiation exposure to man, while nuclear power contributes less than 0.1%. | ||
Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level.Environmental radiation levels are sometimes referred to as a percent of the reporting level.Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, aquatic, terrestrial and direct radiation exposure. | These results demonstrate compliance with federal and state regulations and also demonstrate the adequacy of radioactive effluent controls at Surry Power Station. | ||
The airborne exposure pathway includes radioactive airborne iodine and particulates. | 6 | ||
The 2009 airborne results were similar to previous years. No station related radioactivity was detected and natural radioactivity levels remained at levels consistent with past years' results. Aquatic exposure pathway samples include well and river water, silt and shoreline sediments, crabs, fish, clams and oysters. Naturally occurring potassium-40 was detected at average environmental levels. No man-made radionuclides were detected in well water. This trend is consistent throughout the operational environmental monitoring program. No man-made radionuclides were detected in river water. Silt samples indicated the presence of cesium- 137 and naturally occurring radionuclides. | : 2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2009 Surry Power Station operational Radiological Environmental Monitoring Program (REMP). The Dominion Surry Power Station is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 855 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973. | ||
The cesium- 137 activity was present in the control and indicator locations and is attributable to global fallout from past nuclear weapons testing and nuclear accidents such as Chernobyl. | The United States Nuclear Regulatory Commission 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 is Reasonably Achievable. To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications that address the release of radioactive effluents. In-plant monitoring is used to ensure that these 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 station environs is also included in Surry Power Station Technical Specifications. | ||
Shoreline sediment, which may provide a direct exposure pathway, contained no station related radionuclides. | Dominion personnel are responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions Incorporated is responsible for processing the TLDs. GEL Laboratories LLC and Teledyne Brown Engineering are responsible for sample analyses. The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. Measured values are compared with control values, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radionuclides. Data collected prior to station operation is used to indicate the degree of natural variation to be expected. This pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation. | ||
Naturally occurring potassium-40 and thorium-228 were detected at average environmental levels. The terrestrial exposure pathway includes milk and food products. | Occasionally, samples of environmental media may show the presence of man-made radionuclides. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants", | ||
Iodine-131 was not detected in any 2009 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. | (December, 1975) and VPAP-2103S, Offsite Dose Calculation Manual (Surry). | ||
Strontium-90 was again detected in milk and this activity is attributable to past atmospheric nuclear weapons testing. No man-made radionuclides were detected in food product samples. Consistent with historical data, naturally occurring potassium-40 was detected in milk and food products. | 7 | ||
The direct exposure pathway measures environmental radiation doses using TLDs. TLD results have remained relatively constant over the years.During 2009, as in previous years, the operation of Surry Power Station has created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2009 was 0.001 millirem. | |||
For reference, this dose may be compared to the 620 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 50% of radiation exposure to man, while nuclear power contributes less than 0.1%.These results demonstrate compliance with federal and state regulations and also demonstrate the adequacy of radioactive effluent controls at Surry Power Station.6 | 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." | ||
: 2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2009 Surry Power Station operational Radiological Environmental Monitoring Program (REMP). The Dominion Surry Power Station is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. | This report documents the results of the REMP for 2009 and satisfies the following objectives of the program: | ||
Each unit is designed with a gross electrical output of 855 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973.The United States Nuclear Regulatory Commission 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 is Reasonably Achievable. | ) To provide 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 member of the public resulting from station operations. | ||
To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications that address the release of radioactive effluents. | To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits. | ||
In-plant monitoring is used to ensure that these release limits are not exceeded. | > To identify changes in radioactivity in the environment. | ||
As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the station environs is also included in Surry Power Station Technical Specifications. | > To verify that station operations have no detrimental effect on the health and safety of the public. | ||
Dominion personnel are responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions Incorporated is responsible for processing the TLDs. GEL Laboratories LLC and Teledyne Brown Engineering are responsible for sample analyses. | 2.2 Sampling and Analysis Program Table 2-1 summarizes the 2009 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." Dominion personnel collect all samples listed in Table 2-1. | ||
The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. | Table 2-2 summarizes the analysis program conducted by GEL Laboratories LLC, Teledyne Brown Engineering and Global Dosimetry Solutions for Surry Power Station. All samples, with the exception of the TLDs, are shipped to GEL Laboratories LLC, located in Charleston, SC, or Teledyne Brown Engineering, located in Knoxville, TN, for analysis. The TLDs are shipped to Global Dosimetry Solutions, located in Costa Mesa, CA, for processing. | ||
Measured values are compared with control values, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radionuclides. | The Surry Radiological Monitoring Locations maps (Figures 1 - 5) denote sample locations for Surry Power Station. The locations are color coded to designate sample types. | ||
Data collected prior to station operation is used to indicate the degree of natural variation to be expected. | 8 | ||
This pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation. | |||
Occasionally, samples of environmental media may show the presence of man-made radionuclides. | -- == -.. - !E !m - - - - = m Table 2-1 SURRY - 2009 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Onsite (Stored in a lead shield outside the protected Environmental Control (00) Quarterly area) | ||
As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants", (December, 1975) and VPAP-2103S, Offsite Dose Calculation Manual (Surry).7 These concentrations are based upon the annual dose commitment recommended by | TLDs West North West (02) 0.2 WNW 2930 Quarterly Site Boundary Surry Station Discharge (03) 0.4 NW 3210 Quarterly Site Boundary North North West (04) 0.2 NNW 3290 Quarterly Site Boundary North (05) 0.3 N 40 Quarterly Site Boundary North North East (06) 0.3 NNE 280 Quarterly Site Boundary North East (07) 0.3 NE 440 Quarterly Site Boundary East North East (08) 0.4 ENE 670 Quarterly Site Boundary East (09) 0.3 E 890 Quarterly Site Boundary West (10) 0.1 W 2710 Quarterly Site Boundary West South West (11) 0.4 WSW 2520 Quarterly Site Boundary South West (12) 0.3 SW 2280 Quarterly Site Boundary South South West (13) 0.3 SSW 2010 Quarterly Site Boundary South (14) 0.4 S 1820 Quarterly Site Boundary South South East (15) 0.6 SSE 1570 Quarterly Site Boundary South East (16) 0.9 SE 1350 Quarterly Site Boundary Station Intake (18) 1.6 ESE 1150 Quarterly Site Boundary Hog Island Reserve (19) 2.0 NNE 260 Quarterly Near Resident Bacon's Castle (20) 4.5 SSW 2020 Quarterly Apx. 5 mile Route 633 (21) 4.9 SW 2270 Quarterly Apx. 5 mile Alliance (22) 5.1 WSW 2470 Quarterly Apx. 5 mile Surry (23) 7.7 WSW 2560 Quarterly Population Center Route 636 and 637 (24) 4.0 W 2700 Quarterly Apx. 5 mile Scotland Wharf (25) 5.0 WNW 2840 Quarterly Apx. 5 mile Jamestown (26) 6.3 NW 3080 Quarterly Apx. 5 mile Colonial Parkway (27) 3.8 NNW 3330 Quarterly Apx. 5 mile Route 617 and 618 (28) 4.9 NNW 3400 Quarterly Apx. 5 mile Kingsmill (29) 4.6 N 20 Quarterly Apx. 5 mile Williamsburg (30) 7.8 N 00 Quarterly Population Center Kingsmill North (31) 5.5 NNE 120 Quarterly Apx. 5 mile Budweiser (32) 5.8 NNE 270 Quarterly Population Center Water Plant (33) 5.0 NE 460 Quarterly Apx. 5 mile 9 | ||
To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.> To identify changes in radioactivity in the environment. | |||
> To verify that station operations have no detrimental effect on the health and safety of the public.2.2 Sampling and Analysis Program Table 2-1 summarizes the 2009 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled"control." Dominion personnel collect all samples listed in Table 2-1.Table 2-2 summarizes the analysis program conducted by GEL Laboratories LLC, Teledyne Brown Engineering and Global Dosimetry Solutions for Surry Power Station. All samples, with the exception of the TLDs, are shipped to GEL Laboratories LLC, located in Charleston, SC, or Teledyne Brown Engineering, located in Knoxville, TN, for analysis. | Table 2-1 SURRY - 2009 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental BASF (34) 5.1 ENE 700 Quarterly Apx. 5 mile TLDs Lee Hall (35) 7.1 ENE 750 Quarterly Population Center Goose Island (36) 5.1 E 900 Quarterly Apx. 5 mile Fort Eustis (37) 4.9 ESE 1040 Quarterly Apx. 5 mile Newport News (38) 19.3 SE 1300 Quarterly Population Center James River Bridge (39) 17.1 SE 1420 Quarterly Control Location Benn's Church (40) 17.0 SSE 1590 Quarterly Control Location Smithfield (41) 13.4 SSE 1670 Quarterly Control Location Rushmere (42) 5.3 SSE 1560 Quarterly Apx. 5 mile Route 628 (43) 5.1 S 1770 Quarterly Apx. 5 mile Air Charcoal Surry Station (SS) 0.3 NNE 180 Weekly Site boundary location with highest D/Q and Particulate Hog Island Reserve (HIR) 2.0 NNE 260 Weekly Bacon's Castle (BC) 4.5 SSW 2020 Weekly Alliance (ALL) 5.1 WSW 2470 Weekly Colonial Parkway (CP) 3.8 NNW 3330 Weekly BASF (BASF) 5.1 ENE 700 Weekly Fort Eustis (FE) 4.9 ESE 1040 Weekly Newport News (NN) 19.3 SE 1300 Weekly Control Location River Water Surry Station Discharge (SD) 0.4 NW 3230 Monthly Scotland Wharf (SW) 4.9 WNW 2840 Monthly Control Location Well Water Surry Station (SS) 0.1 SW 2270 Quarterly Onsite Hog Island Reserve (HIR) 2.0 NNE 280 Quarterly Construction Site (CS) 0.3 E 870 Quarterly Shoreline Hog Island Reserve (HIR) 0.6 N 70 Semi-Annually Sediment Chickahominy River (CHIC) 11.2 WNW 3010 Semi-Annually Control Location Silt Chickahominy River (CHIC) 11.2 WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.3 NNW 3410 Semi-Annually 10 | ||
The TLDs are shipped to Global Dosimetry Solutions, located in Costa Mesa, CA, for processing. | |||
The Surry Radiological Monitoring Locations maps (Figures 1 -5) denote sample locations for Surry Power Station. The locations are color coded to designate sample types.8 | Table 2-1 SURRY - 2009 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Milk Colonial Parkway (CP) 3.7 NNW 3360 Monthly Williams (WMS) 27.5 S 1750 Monthly Control Location Epps (EPPS) 4.8 SSW 2000 Monthly Oysters Point of Shoals (POS) 6.4 SSE 1570 Semi-Annually Mulberry Point (MP) 4.9 ESE 1240 Semi-Annually Clams Chickahominy River (CHIC) 11.2 WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.3 NNW 3410 Semi-Annually Hog Island Point (HIP) 2.4 NE 520 Semi-Annually Lawne's Creek (LC) 2.4 SE 1310 Semi-Annually Jamestown Island (JI) 3.9 NNW 3240 Semi-Annually Fish Surry Station Discharge (SD) 1.3 NNW 3410 Semi-Annually Crabs Surry Station Discharge (SD) 1.3 NNW 3410 Annually Crops Brock's Farm (BROCK) 3.8 S 1830 Annually (Corn, Peanuts, Slade's Farm (SLADE) 3.2 S 1790 Annually Soybeans) 11 | ||
--== -.. -!E !m ----= m Table 2-1 SURRY -2009 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental TLDs | |||
Table 2-2 SURRY - 2009 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYS IS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2 mR/Std. Month Dosimetry (TLD) 3 Air Iodine Weekly 1-131 0.07 pCi/mr Air Particulate Weekly Gross Beta 0.01 pCi/r3 3 | |||
Quarterly (a) Gamma Isotopic pCi/rn Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium (H-3) 2000 pCi/L Composite of monthly sample Monthly 1-131 10 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 Well Water Quarterly Tritium (H-3) 2000 pCi/L 1-131 1 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 Footnotes located at end of table. | |||
12 | |||
Table 2-2 SURRY- 2009 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Shoreline Sediment Semi-Annually Gamma Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Silt Semi-Annually Gamma Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Nilk Monthly 1-131 I pCi/L Gamma Isotopic pCi/L Cs-134 15 Cs-137 18 Ba-140 60 La- 140 15 Quarterly Sr-89 NA pCi/L Composite of CP Sr-90 NA monthly sample Oysters Semi-Annually 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 Clams Semi-Annually 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 Crabs Annually 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 Footnotes located at end of table. | |||
13 | |||
Table 2-2 SURRY- 2009 SAMPLE ANALYSIS PROGRAM SAAMPLE MEDIA FREQUENCY ANALYSIS LLD* R1EPORT UNITS Fish Semi-Annually 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 Annually Gamma Isotopic pCi/kg - wet 1-131 60 Cs-134 60 Cs-137 80 Note: This table is not a complete listing of nuclides that can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, are also identified and reported. | |||
* LLD is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. LLDs indicate those concentrations to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than these listed values. | |||
(a) Quarterly composites of each location's weekly air particulate samples are analyzed for gamma emitters. | |||
NA None assigned 14 | |||
= =- -= = = =m - m = = =- = m = = | |||
IC) | |||
I~. | |||
I~. | |||
0 | |||
=m=- m m = m= = = mm m =- = m = mm m=n | |||
=mmm M---- M- = M M = M m Figure 3. Surry Emergency Plan Map 0 Air Sampling Stations Nearest Residents 0 | |||
* TLD Sampling Nearest Milk Animal z | |||
* Nearest Garden Aquatic Samples 00K Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC. | |||
((2 (pVWIrARFO W Surry 7~ | |||
;ýLAZY OAK"" | |||
w s" CORNER (61ý (IX\ II | |||
.~II | |||
("3l | |||
ý95 TE XT0N Figure 4. Surry Emergency Plan Map Air Sampling Stations Nearest Residents Li . TLD Sampling Nearest Milk Animal z~ | |||
* Nearest Garden Crop Samples 1W Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC. | |||
= M = = = = m=m=- M = = = M Figure 5. Surry Emergency Plan Map Air Sampling Stations Nearest Residents | |||
* TLD Sampling Nearest Milk Animal | |||
* Nearest Garden Aquatic Samples Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC. | |||
: 3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the Surry Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Revision 1, November 1979. A more detailed analysis of the data is given in Section 4. | |||
20 | |||
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | |||
==SUMMARY== | ==SUMMARY== | ||
Surry Power Station, Surry County, Virginia -2009 Docket No. 50-280-281 Page 1 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Direct | |||
(4.7-6.2) | Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 1 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Direct Gamma 164 2 3.3 (152/152) STA-9 0.3 mi 5.6(414) 3.7(12/12) 0 Radiation (1.2-6.2) E (4.7-6.2) (1.8- 6.5) | ||
(1.8- 6.5) | TLD (mR/ | ||
(114-164)Cs-1 34 32 50 < LLD Cs-1 37 32 60 < LLD N/A | Std Month) | ||
Air Gross 416 10 23.9 (364/364) ALL 5.1 mi 27.4 (52/52) 23.2 (52/52) 0 Particulate Beta (7.1 -60.2) WSW (8.2- 60.2) (10.1 - 47.2) | |||
(1E-3 pCi/m3) | |||
Gamma 32 Be-7 32 144 (28/28) ALL 5.1 mi 165 (4/4) 139 (4/4) 0 (106- 197) WSW (134-197) (114-164) | |||
Cs-1 34 32 50 < LLD N/A " LLD < LLD 0 Cs-1 37 32 60 < LLD N/A < LLD < LLD 0 Air Iodine 1-131 416 70 < LLD N/A < LLD < LLD 0 (IE-3 pCi/m3) | |||
Milk Strontium 4 (pCi/Luter) | |||
Sr-89 4 < LLD N/A < LLD < LLD 0 Sr-90 4 1.12(1/4) CP 3.7 mi 1.12(1/4) N/A 0 (1.12- 1.12) NNW (1.12- 1.12) | |||
Gamma 36 K-40 36 1360 (24/24) CP 3.7 mi 1397 (12/12) 1308 (12/12) 0 (1220 - 1510) NNW (1260- 1510) (1150- 1420) | |||
Th-228 36 < LLD N/A < LLD 13.0 (1/12) 0 (13.0- 13.0) 1-131 36 1 < LLD N/A < LLD " LLD 0 Cs-134 36 15 < LLD N/A < LLD < LLD 0 Cs-137 36 18 < LLD N/A < LLD < LLD 0 21 I-f 4k | |||
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | |||
==SUMMARY== | ==SUMMARY== | ||
Surry Power Station, Surry County, Virginia -2009 Docket No. 50-280-281 Page 2 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Milk (pCi/Liter) | Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 2 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Milk Gamma 36 (pCi/Liter) | ||
Ba-140 36 60 < LLD N/A < LLD " LLD 0 La- 140 36 15 < LLD N/A < LLD < LLD 0 Food Gamma Products (pCi/kg wet) K-40 8097 (3/3) Slade 3.2 mi 8995 (2/2) N/A 0 (3190 - 14800) S (3190-14800) | |||
Th-228 10.4 (1/3) Slade 3.2 mi 10.4(1/2) N/A (10.4 - 10.4) S (10.4 - 10.4) 1-131 60 < LLD N/A < LLD N/A 0 Cs- 134 60 < LLD N/A < LLD N/A 0 Cs-137 80 " LLD N/A < LLD N/A 0 0 | |||
(15.4 -15.4)< LLD< LLD | Well H-3 2000 < LLD N/A < LLD N/A 0 Water (pCi/Liter) | ||
Gamma K-40 37.5 (1/12) SS 0.1 mi 37.5 (1/12) N/A 0 (37.5 - 37.5) SW (37.5 - 37.5) | |||
Ac-228 15.4 (1/12) CS 0.3 mi 15.4(1/12) N/A 0 (15.4- 15.4) E (15.4 - 15.4) | |||
Mn-54 15 < LLD N/A < LLD N/A 0 Co-58 15 < LLD N/A < LLD N/A 0 Fe-59 30 < LLD N/A " LLD N/A 0 Co-60 15 " LLD N/A < LLD N/A 0 22 | |||
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | |||
==SUMMARY== | ==SUMMARY== | ||
Surry Power Station, Surry County, Virginia -2009 Docket No. 50-280-281 Page 3 of 7 | Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 3 of 7 Medium or Indicator Control L | ||
Nb-95 12 15 < LLD N/A < LLD N/A 0 Zr-95 12 30 < LLD N/A < LLD N/A' 0 1-131 12 1 < LLD N/A < LLD N/A 0 Cs-134 12 15 < LLD N/A < LLD N/A 0 Cs-1 37 12 18 < LLD N/A < LLD N/A 0 Ba-140 12 60 < LLD N/A < LLD N/A 0 La-140 12 15 < LLD N/A < LLD N/A 0 | Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Nell Zn-65 12 30 < LLD N/A < LLD N/A 0 Nater 0pCi/Liter) | ||
Gamma 24 K-40 | Nb-95 12 15 < LLD N/A < LLD N/A 0 Zr-95 12 30 < LLD N/A < LLD N/A' 0 1-131 12 1 < LLD N/A < LLD N/A 0 Cs-134 12 15 < LLD N/A < LLD N/A 0 Cs-1 37 12 18 < LLD N/A < LLD N/A 0 Ba-140 12 60 < LLD N/A < LLD N/A 0 La-140 12 15 < LLD N/A < LLD N/A 0 Fliver H-3 8 2000 < LLD N/A < LLD N/A 0 Water (pCi/Liter) | ||
Co-60 24 15 < LLD Zn-65 24 30 < LLD Nb-95 24 15 < LLD | Gamma 24 K-40 24 138.4 (4/12) SD 0.4 mi 138.4 (4/12) 105.9 (5/12) 0 (75.7- 188) NW (75.7- 188) (27.2 - 167) | ||
Th-228 24 < LLD SW 4.9 mi 5.52 (1/12) 5.52 (1/12) 0 WNW (5.52 - 5.52) (5.52 - 5.52) | |||
( | Ra-226 24 < LLD SW 4.9 mi 34.6 (1/12) 34.6 (1/12) 0 WNW (34.6 - 34.6) (34.6 - 34.6) | ||
Mn-54 24 15 " LLD N/A < LLD < LLD 0 Co-58 24 15 < LLD N/A < LLD < LLD 0 Fe-59 24 30 < LLD N/A < LLD < LLD 0 23 | |||
( | |||
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSUMMAR Y Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 4 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements River Co-60 24 15 < LLD N/A < LLD < LLD 0 Water (pCi/Liter) | |||
Zn-65 24 30 < LLD N/A < LLD < LLD 0 Nb-95 24 15 < LLD N/A < LLD < LLD 0 Zr-95 24 30 < LLD N/A < LLD < LLD 0 1-131 24 10 < LLD N/A < LLD < LLD 0 Cs-134 24 15 < LLD N/A < LLD < LLD 0 Cs-137 24 18 < LLD N/A < LLD < LLD 0. | |||
Ba-140 24 60 < LLD N/A < LLD < LLD 0 La-140 24 15 < LLD N/A < LLD < LLD 0 Silt Gamma 4 (pCi/kg dry) | |||
K-40 4 14700 (212) CHIC 11.2 mi 16550 (2/2) 16550 (2/2) 0 (14000-15400) WNW (16100-17000) (16100-17000) | |||
Cs-134 4 150 < LLD N/A < LLD < LLD 0 Cs-137 4 180 214(2/2) SD 1.3 mi 214(2/2) 184(2/2) 0 (154-274) NNW (154-274) (182-186) | |||
Th-228 4 1080 (2/2) CHIC 11.2 mi 1295(2/2) 1295(2/2) 0 (1010- 1150) WNW (1210-1380) (1210-1380) | |||
Th-230 4 644 (1/2) CHIC 11.2 mi 1310(1/2) 1310(1/2) 0 (644 - 644) WNW (1310-1310) (1310-1310) | |||
Th-232 4 1030 (1/2) CHIC 11.2 mi 1180(2/2) 1180(2/2) 0 (1030 - 1030) WNW (1020- 1340) (1020- 1340) 24 I,, | |||
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSUMMAR Y Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 5 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Silt TI-208 4 231 (1/2) CHIC 11.2 mi 418 (1/2) 418 (1/2) 0 (pCi/kg dry) (231 -231) WNW (418-418) (418-418) | |||
Pb-212 4 1010 (1/2) CHIC 11.2 mi 1380 (1/2) 1380 (1/2) 0 (1010 - 1010) WNW (1380 - 1380) (1380 - 1380) | |||
Pb-214 4 874 (1/2) CHIC 11.2 mi 1250 (1/2) 1250 (1/2) 0 (874 - 874) WNW (1250 - 1250) (1250 - 1250) | |||
Bi-214 4 644 (1/2) CHIC 11.2 mi 1310 (1/2) 1310 (1/2) 0 (644 - 644) WNW (1310- 1310) (1310- 1310) | |||
Ra-226 4 2192 (2/2) SD 1.3 mi 2192 (2/2) 1435(2/2) 0 (644 - 3740) NNW (644- 3740) (1310 - 1560) | |||
Ra-228 4 < LLD CHIC 11.2 mi 1340 (1/2) 1340 (1/2) 0 WNW (1340- 1340) (1340- 1340) | |||
Ac-228 4 < LLD CHIC 11.2 mi 1340 (1/2) 1340(1/2) 0 WNW (1340 - 1340) (1340 - 1340) | |||
U-234 4 644 (1/2) SD 1.3 mi 644 (1/2) < LLD 0 (644 - 644) NNW (644- 644) | |||
Shoreline Gamma 4 Sediment (pCi/kg dry) K-40 4 5735 (2/2) HIR 0.6 mi 5735 (2/2) 4140 (2/2) 0 (5290 - 6180) N (5290 - 6180) (2160 - 6120) | |||
Cs-134 4 150 < LLD N/A < LLD < LLD 0 Cs-137 4 180 < LLD N/A < LLD < LLD 0 Th-228 4 < LLD CHIC 11.2 mi 103 (1/2) 103 (1/2) 0 WNW (103-103) (103-103) | |||
Fish Gamma 4 (pCi/kg wet) | |||
K-40 4 2163 (3/4) SD 1.3 mi 2163(3/4) N/A 0 (2060 - 2230) NNW (2060 - 2230) | |||
Mn-54 4 130 < LLD N/A < LLD N/A 0 Co-58 4 130 < LLD N/A < LLD N/A 0 25 | |||
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | |||
==SUMMARY== | ==SUMMARY== | ||
Surry Power Station, Surry County, Virginia -2009 Docket No. 50-280-281 Page 6 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean I Distance Mean Mean Reported (Units) Type No. LLD Range Name IDirection Range Range Measurements Fish Fe-59 4 260 < LLD N/A < LLD N/A 0 (pCi/kg wet)Co-60 4 130 < LLD N/A < LLD N/A 0 Zn-65 4 260 < LLD N/A < LLD N/A 0 Cs-1 34 4 130 < LLD N/A < LLD N/A 0 Cs-1 37 4 150 < LLD N/A < LLD N/A 0 Oysters Gamma 4 (pCi/kg wet)K-40 4 | Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 6 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean I Distance Mean Mean Reported (Units) Type No. LLD Range Name IDirection Range Range Measurements Fish Fe-59 4 260 < LLD N/A < LLD N/A 0 (pCi/kg wet) | ||
Co-60 4 130 < LLD N/A < LLD N/A 0 Zn-65 4 260 < LLD N/A < LLD N/A 0 Cs-1 34 4 130 < LLD N/A < LLD N/A 0 Cs-1 37 4 150 < LLD N/A < LLD N/A 0 Oysters Gamma 4 (pCi/kg wet) | |||
K-40 4 1050 (1/4) POS 6.4 mi 1050 (1/4) N/A (1050 - 1050) SSE (1050 - 1050) | |||
Mn-54 4 130 < LLD N/A < LLD N/A Fe-59 4 260 < LLD N/A < LLD N/A Co-58 4 130 < LLD N/A < LLD N/A Co-60 4 130 < LLD N/A < LLD N/A Zn-65 4 260 < LLD N/A < LLD N/A Cs-134 4 130 < LLD N/A < LLD N/A Cs-137 4 150 < LLD N/A < LLD N/A Clams Gamma 8 (pCi/kg wet) | |||
K-40 8 445 (2/6) LC 2.4 mi 458 (1/2) 851 (1/2) 0 (431 - 458) SE (458 - 458) (851 -851) | |||
Th-228 8 < LLD CHIC 11.2 mi 164 (1/2) 164(1/2) 0 WNW (164- 164) (164- 164) 26 | |||
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM | |||
==SUMMARY== | ==SUMMARY== | ||
Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 7 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name IDirection Range Range Measurements Clams Mn-54 8 130 < LLD N/A < LLD < LLD 0 (pCi/kg vwet) | |||
Co-58 8 130 < LLD N/A < LLD < LLD 0 Fe-59 8 260 < LLD N/A < LLD < LLD 0 Co-60 8 130 < | |||
Sr-90 was detected in one of the four composites analyzed at a concentration of 1.12 pCi/L. The average Sr-90 concentration for the ten year period of 1999 to 2009 is 1.82 pCi/L. Sr-90 is not a component of the station radiological effluents. | Sr-90 was detected in one of the four composites analyzed at a concentration of 1.12 pCi/L. The average Sr-90 concentration for the ten year period of 1999 to 2009 is 1.82 pCi/L. Sr-90 is not a component of the station radiological effluents. | ||
The Sr-90 detected is a product of nuclear weapons testing fallout which has been well documented. | The Sr-90 detected is a product of nuclear weapons testing fallout which has been well documented. | ||
52 I, j, 4.6 Food Products Three samples were collected and analyzed by gamma spectroscopy. | 52 | ||
The results of the analyses are presented in Table 3-7. As expected, naturally occurring potassium-40 was detected in all samples. The average concentration is consistent with that observed in previous years. Naturally occurring thorium-228 was also detected in one of three samples. No station related radioactivity was detected.4.7 Well Water Well water is not considered to be affected by station operations because there are no discharges made to this pathway. However, Surry Power Station monitors well water quarterly at three indicator locations and analyzes for gamma radiation and for tritium. The results of these analyses are presented in Table 3-8. Consistent with past monitoring, no station related radioactivity was detected. | |||
Naturally occurring potassium-40 and actinium-228 were detected in one sample each. No gamma emitting isotopes were detected during the pre-operational period.4.8 River Water Samples of the James River water are collected monthly and the results are presented in Table 3-9. All samples are analyzed by gamma spectroscopy. | I, j, | ||
The monthly samples are also composited and analyzed for tritium on a quarterly basis. Naturally occurring potassium-40, thorium-228 and radium-226 were detected in some samples. No station related radioactivity was detected.4.9 Silt Silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Sampling of this pathway provides a good indication of the dispersion effects of effluents to the river. Buildup of radionuclides in silt could indirectly lead to increasing radioactivity levels in clams, oysters, crabs and fish.Samples of silt are collected from two locations, one upstream and one downstream of the station. The results of the gamma spectroscopy analyses are presented in Table 3-10. Trend graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-4 and 4-5.Historically, cobalt-60 has been detected in samples obtained from the indicator location (SD). Cobalt-60 has not been detected since 2003.53 Cesium-137 was detected, as expected, in both the control and indicator samples.The levels detected indicate a continual decreasing trend seen for over a decade.The detection of cesium-137 in both the control and indicator samples and decreasing levels indicate that the presence of cesium-137 is the result of accumulation and runoff into the river of residual weapons testing fallout. Its global presence has been well documented. | 4.6 Food Products Three samples were collected and analyzed by gamma spectroscopy. The results of the analyses are presented in Table 3-7. As expected, naturally occurring potassium-40 was detected in all samples. The average concentration is consistent with that observed in previous years. Naturally occurring thorium-228 was also detected in one of three samples. No station related radioactivity was detected. | ||
During the pre-operational period, cesium-137 was detected in most silt samples with an average concentration as indicated in Figure 4-5. In 2009, cesium-137 was detected with an average indicator location concentration of 214 pCi/kg and an average control location concentration of 184 pCi/kg. These activities continue to represent fallout from nuclear weapons testing. Both indicator and control cesium-137 activities trend closely as shown in Figure 4-5.Figure 4-4: COBALT-60 | 4.7 Well Water Well water is not considered to be affected by station operations because there are no discharges made to this pathway. However, Surry Power Station monitors well water quarterly at three indicator locations and analyzes for gamma radiation and for tritium. The results of these analyses are presented in Table 3-8. Consistent with past monitoring, no station related radioactivity was detected. Naturally occurring potassium-40 and actinium-228 were detected in one sample each. No gamma emitting isotopes were detected during the pre-operational period. | ||
-- Station | 4.8 River Water Samples of the James River water are collected monthly and the results are presented in Table 3-9. All samples are analyzed by gamma spectroscopy. The monthly samples are also composited and analyzed for tritium on a quarterly basis. Naturally occurring potassium-40, thorium-228 and radium-226 were detected in some samples. No station related radioactivity was detected. | ||
Station Discharge was <MDC activity 1996 through 1998 and 2004 through 2009.54 Figure 4-5: CESIUM-1 37 IN SILT 1.OE+04 C0 1.OE+03J I I.OE+02 C- | 4.9 Silt Silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Sampling of this pathway provides a good indication of the dispersion effects of effluents to the river. Buildup of radionuclides in silt could indirectly lead to increasing radioactivity levels in clams, oysters, crabs and fish. | ||
---- Station Discharge | Samples of silt are collected from two locations, one upstream and one downstream of the station. The results of the gamma spectroscopy analyses are presented in Table 3-10. Trend graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-4 and 4-5. | ||
-Asg Pre-Op -Required LLD 4.10 Shoreline Sediment Shoreline sediment, unlike river silt, may provide a direct dose to humans.Buildup of radionuclides along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. The results are presented in Table 3-11.The naturally occurring radionuclides potassium-40 and thorium-228 were detected at concentrations equivalent to normal background activities. | Historically, cobalt-60 has been detected in samples obtained from the indicator location (SD). Cobalt-60 has not been detected since 2003. | ||
The activities of these radionuclides indicate a steady trend. There were no radionuclides attributable to the operation of the station found in any shoreline sediment samples.4.11 Fish The radioactivity measured in fish sampled from the station discharge canal and analyzed by gamma spectroscopy is presented in Table 3-12. These results are the same as those seen over the last decade. No activity was observed in this media except for naturally occurring potassium-40. | 53 | ||
55 4.12 Oysters Oysters are collected from two different locations. | |||
The results of the oyster analyses are presented in Table 3-13.There were no gamma emitting radionuclides detected in oysters sampled except for naturally occurring potassium-40. | Cesium-137 was detected, as expected, in both the control and indicator samples. | ||
No station related radioactivity has been detected in this media since 1991. The absence of station related radionuclides is attributable to the replacement of steam generators in 1982 and past improvements made to liquid effluent treatment systems.4.13 Clams Clams are analyzed from four different locations. | The levels detected indicate a continual decreasing trend seen for over a decade. | ||
The results of the gamma spectroscopy analyses are presented in Table 3-14. Like oysters, no station related radioactivity was detected. | The detection of cesium-137 in both the control and indicator samples and decreasing levels indicate that the presence of cesium-137 is the result of accumulation and runoff into the river of residual weapons testing fallout. Its global presence has been well documented. During the pre-operational period, cesium-137 was detected in most silt samples with an average concentration as indicated in Figure 4-5. In 2009, cesium-137 was detected with an average indicator location concentration of 214 pCi/kg and an average control location concentration of 184 pCi/kg. These activities continue to represent fallout from nuclear weapons testing. Both indicator and control cesium-137 activities trend closely as shown in Figure 4-5. | ||
Naturally occurring potassium-40 and thorium-228 were detected.4.14 Crabs A crab sample was collected in June from the station discharge canal and analyzed by gamma spectroscopy. | Figure 4-4: COBALT-60 INSILT 1.OE+04 1.OE+03 1.OE+02 C., | ||
The results of the analysis are presented in Table 3-15. Other than naturally occurring potassium-40, no other gamma emitting radionuclides were detected in the sample. This is consistent with pre-operational data and data collected over the past decade.56 | 1.0E+01 L.OE+00 Cl ý0 00 0 l ' 00 0 C ' 00 0 lcf \ 00 N | ||
: 5. PROGRAM EXCEPTIONS There were four REMP exceptions for scheduled sampling and analysis during 2009.The gross beta minimum detectable concentration (MDC) was 1.16E-02 pCi/m 3.for the November 17 Hog Island Reserve (HIR) air sample. This concentration is greater than the lower limit of detection (LLD) concentration of 1.00E-02 pCi/m 3.Although an MDC is a posteriori measurement, Surry Power Station requires that this value be less than or equal to the required LLD. This ensures that REMP samples are analyzed to required program elements. | N N N 00 00 00 00 00 CNcr 0ý N ON 0ý,C 0 0 0 0 Control - Chickahominy -- Station Discharge Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were <MDC, Minimum Detectable Concentration. Station Discharge was <MDC activity 1996 through 1998 and 2004 through 2009. | ||
The cause for the higher MDC was a lower than normal sample volume due to loss of power at the HIR air sampling station. The loss of power resulted from a nor'easter that moved through the area during the sample period. Detection of gross beta activity in air samples is routine. Detectable gross beta activity was determined in this HIR air sample with the reduced volume and normal sample count time. Due to the detectable activity, the slightly elevated MDC was considered minor and a follow-on analysis to meet the 1.00E-02 pCi/m 3 MDC was not requested. | 54 | ||
The iodine-131 minimum detectable concentration (MDC) was 7.01E-02 pCi/m | |||
An alternate sampling location, Jamestown Island, was selected and sampled throughout 2008.- In 2009, clams continued to be sampled at the Jamestown Island location in place of the Hog Island Point location.57 | Figure 4-5: CESIUM-1 37 IN SILT 1.OE+04 C0 1.OE+03J I j | ||
: 6. CONCLUSIONS The results of the 2009 Radiological Environmental Monitoring Program for Surry Power Station have been presented in previous sections. | I.OE+02 | ||
This section presents conclusions for each pathway.Direct Radiation Exposure Pathway -Control and indicator location averages continue to indicate a steady relationship and trend over the long term.Airborne Exposure Pathway -Analysis of charcoal cartridge samples for radioiodines indicated no positive activity was detected. | 'C- 0 00 C' ct1 0 00 C N ~' ' 0 C ~ 0 0 C -0~0 -~ r-0 ~ 00 00 0' | ||
Quarterly gamma isotopic analyses of the composite particulate samples identified only naturally occurring beryllium-7. | 0 0 0 0 | ||
Air particulate gross beta concentrations at all of the indicator locations for 2009 trend well with the control location.BMilk -Milk samples are an important indicator measuring the effect of radioactive iodine and radionuclides in airborne releases. | 0 00' 0 | ||
Cesium-137 and iodine-131 were not detected in any of the thirty-six samples. Naturally occurring potassium-40 was detected at a similar level when compared to the average of the previous year.Strontium-90 was detected in one of four samples this year at a concentration of 1.12 pCi/L. Strontium-90 is not a component of station effluents, but rather, a product of nuclear weapons testing fallout.Food Products -As expected, naturally occurring potassium-40 was detected in all three samples and naturally occurring thorium-228 was detected in one of three samples. In the past, cesium-137 has occasionally been detected in these samples and is attributable to global fallout from past nuclear weapons testing. Cesium-137 was not detected in any of the three samples collected in 2009.Well Water -Well water samples were analyzed and the analyses indicated that there were no man-made radionuclides present. This trend is consistent throughout the monitoring period. No radioactivity attributable to the operation of the station was identified. | 0' 0' 0' | ||
> River Water -All river water samples were analyzed for gamma emitting radionuclides. | 10 01 00 C, | ||
Only the naturally occurring radionuclides potassium-40 thorium-228 and radium-226 were detected. | C> | ||
Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2009.> Silt -Cesium-137 was detected in both the control and indicator samples.The presence of cesium- 137 is attributable to residual weapons testing fallout; its presence has been well documented. | C' ct~q C:' | ||
Cobalt-60 has not been 58 detected since 2003.Shoreline Sediment -Naturally occurring radionuclides were detected at concentrations equivalent to normal background activities. | ei C> | ||
There were no radionuclides attributable to the operation of Surry Power Station found in any sample.Aquatic Biota Fish -As expected, naturally occurring potassium-40 was detected. | 10 | ||
There were no other gamma emitting radionuclides detected in any of the fish samples.Oysters and Clams -Other than naturally occurring potassium-40 and thorium-228, there were no other gamma emitting radionuclides detected in any of the oyster or clam samples.Crabs -Naturally occurring potassium-40 was detected. | .N C | ||
No other gamma emitting radionuclides were detected.59 REFERENCES 60 References | 00C' C | ||
: 1. NUREG-0472, "Radiological Effluent Technical Specifications for PWRs", Draft Rev. 3, March 1982.2. 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 | I - Control - Chickahominy ---- Station Discharge - Asg Pre-Op - Required LLD 4.10 Shoreline Sediment Shoreline sediment, unlike river silt, may provide a direct dose to humans. | ||
Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.9. NCRP Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," March 2009.61 APPENDICES 62 APPENDIX A: LAND USE CENSUS Year 2009 63 LAND USE CENSUS*Surry Power Station, Surry County, Virginia January 1 to December 31, 2009 Page 1 of 1 i i I Nearest Nearest Nearest Nearest Sector I Direction Resident Garden** I Cow Goat N | Buildup of radionuclides along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. The results are presented in Table 3-11. | ||
** Area | The naturally occurring radionuclides potassium-40 and thorium-228 were detected at concentrations equivalent to normal background activities. The activities of these radionuclides indicate a steady trend. There were no radionuclides attributable to the operation of the station found in any shoreline sediment samples. | ||
4.11 Fish The radioactivity measured in fish sampled from the station discharge canal and analyzed by gamma spectroscopy is presented in Table 3-12. These results are the same as those seen over the last decade. No activity was observed in this media except for naturally occurring potassium-40. | |||
55 | |||
4.12 Oysters Oysters are collected from two different locations. The results of the oyster analyses are presented in Table 3-13. | |||
There were no gamma emitting radionuclides detected in oysters sampled except for naturally occurring potassium-40. No station related radioactivity has been detected in this media since 1991. The absence of station related radionuclides is attributable to the replacement of steam generators in 1982 and past improvements made to liquid effluent treatment systems. | |||
4.13 Clams Clams are analyzed from four different locations. The results of the gamma spectroscopy analyses are presented in Table 3-14. Like oysters, no station related radioactivity was detected. Naturally occurring potassium-40 and thorium-228 were detected. | |||
4.14 Crabs A crab sample was collected in June from the station discharge canal and analyzed by gamma spectroscopy. The results of the analysis are presented in Table 3-15. Other than naturally occurring potassium-40, no other gamma emitting radionuclides were detected in the sample. This is consistent with pre-operational data and data collected over the past decade. | |||
56 | |||
: 5. PROGRAM EXCEPTIONS There were four REMP exceptions for scheduled sampling and analysis during 2009. | |||
The gross beta minimum detectable concentration (MDC) was 1.16E-02 pCi/m 3 . | |||
for the November 17 Hog Island Reserve (HIR) air sample. This concentration is greater than the lower limit of detection (LLD) concentration of 1.00E-02 pCi/m 3 . | |||
Although an MDC is a posteriori measurement, Surry Power Station requires that this value be less than or equal to the required LLD. This ensures that REMP samples are analyzed to required program elements. The cause for the higher MDC was a lower than normal sample volume due to loss of power at the HIR air sampling station. The loss of power resulted from a nor'easter that moved through the area during the sample period. Detection of gross beta activity in air samples is routine. Detectable gross beta activity was determined in this HIR air sample with the reduced volume and normal sample count time. Due to the detectable activity, the slightly elevated MDC was considered minor and a follow-on analysis to meet the 1.00E-02 pCi/m 3 MDC was not requested. | |||
3 The iodine-131 minimum detectable concentration (MDC) was 7.01E-02 pCi/m for the November 03 Fort Eustis (FE) air sample and 7.16E-02 pCi/m 3 for the November 17 Hog Island Reserve (HIR) air sample. These concentrations are greater than the lower limit of detection (LLD) concentration of 7.OOE-02 pCi/m 3 . | |||
For the second half of 2009, an efficiency correction factor normally used to determine the iodine- 131 concentration in air samples was not applied. Upon discovery of this error, the correction factor was applied to all air samples for the second half of 2009. This resulted in the higher than normal MDCs for these two air samples. A reanalysis of the two samples was not performed due to the short half-life of iodine- 131 and the extended time period between sample collection and discovery of the correction factor error. | |||
During the March 2008 clam sampling campaign, clams were not found at the Hog Island Point sample location. An alternate sampling location, Jamestown Island, was selected and sampled throughout 2008.- In 2009, clams continued to be sampled at the Jamestown Island location in place of the Hog Island Point location. | |||
57 | |||
: 6. CONCLUSIONS The results of the 2009 Radiological Environmental Monitoring Program for Surry Power Station have been presented in previous sections. This section presents conclusions for each pathway. | |||
Direct Radiation Exposure Pathway - Control and indicator location averages continue to indicate a steady relationship and trend over the long term. | |||
Airborne Exposure Pathway - Analysis of charcoal cartridge samples for radioiodines indicated no positive activity was detected. Quarterly gamma isotopic analyses of the composite particulate samples identified only naturally occurring beryllium-7. Air particulate gross beta concentrations at all of the indicator locations for 2009 trend well with the control location. | |||
BMilk - Milk samples are an important indicator measuring the effect of radioactive iodine and radionuclides in airborne releases. Cesium-137 and iodine-131 were not detected in any of the thirty-six samples. Naturally occurring potassium-40 was detected at a similar level when compared to the average of the previous year. | |||
Strontium-90 was detected in one of four samples this year at a concentration of 1.12 pCi/L. Strontium-90 is not a component of station effluents, but rather, a product of nuclear weapons testing fallout. | |||
Food Products - As expected, naturally occurring potassium-40 was detected in all three samples and naturally occurring thorium-228 was detected in one of three samples. In the past, cesium-137 has occasionally been detected in these samples and is attributable to global fallout from past nuclear weapons testing. Cesium-137 was not detected in any of the three samples collected in 2009. | |||
Well Water - Well water samples were analyzed and the analyses indicated that there were no man-made radionuclides present. This trend is consistent throughout the monitoring period. No radioactivity attributable to the operation of the station was identified. | |||
> River Water - All river water samples were analyzed for gamma emitting radionuclides. Only the naturally occurring radionuclides potassium-40 thorium-228 and radium-226 were detected. Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2009. | |||
> Silt - Cesium-137 was detected in both the control and indicator samples. | |||
The presence of cesium- 137 is attributable to residual weapons testing fallout; its presence has been well documented. Cobalt-60 has not been 58 | |||
detected since 2003. | |||
Shoreline Sediment - Naturally occurring radionuclides were detected at concentrations equivalent to normal background activities. There were no radionuclides attributable to the operation of Surry Power Station found in any sample. | |||
Aquatic Biota Fish - As expected, naturally occurring potassium-40 was detected. There were no other gamma emitting radionuclides detected in any of the fish samples. | |||
Oysters and Clams - Other than naturally occurring potassium-40 and thorium-228, there were no other gamma emitting radionuclides detected in any of the oyster or clam samples. | |||
Crabs - Naturally occurring potassium-40 was detected. No other gamma emitting radionuclides were detected. | |||
59 | |||
REFERENCES 60 | |||
References | |||
: 1. NUREG-0472, "Radiological Effluent Technical Specifications for PWRs", | |||
Draft Rev. 3, March 1982. | |||
: 2. 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. | |||
: 3. United States Nuclear Regulatory Commission, Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants", | |||
December 1975. | |||
: 4. United States Nuclear Regulatory Commission Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979. | |||
: 5. Dominion, Station Administrative Procedure, VPAP-2103S, "Offsite Dose Calculation Manual (Surry)". | |||
: 6. Virginia Electric and Power Company, Surry Power Station Technical Specifications, Units 1 and 2. | |||
: 7. HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992. | |||
: 8. NUREG/CR-4007, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984. | |||
: 9. NCRP Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," March 2009. | |||
61 | |||
APPENDICES 62 | |||
APPENDIX A: LAND USE CENSUS Year 2009 63 | |||
LAND USE CENSUS* | |||
Surry Power Station, Surry County, Virginia January 1 to December 31, 2009 Page 1 of 1 i i I Nearest Nearest Nearest Nearest Sector I Direction Resident Garden** I Cow Goat N 4.1 @ 100 (a) (a) (a) | |||
NNE 1.9 @ 320 (a) (a) (a) | |||
NE 4.7 @ 350 (a) (a) (a) | |||
ENE (a) (a) (a) (a) | |||
E (a) (a) (a) (a) | |||
ESE (a) (a) (a) (a) | |||
SE (a) (a) (a) (a) | |||
SSE 3.1 @ 1490 (a) (a) (a) | |||
S 1.7 @ 1810 1.9 @ 1890 (a) (a) | |||
SSW 2.3 @2120 4.3 @ 193- 4.8 @ 2000 (a) | |||
SW 2.3 @ 2210 3.6 @ 2230 (a) (a) | |||
WSW 0.4 @ 2440 3.6 @ 2450 (a) (a) | |||
W 3.1 @ 2600 3.4 @ 260- (a) (a) | |||
WNW 4.9 @ 2830 (a) (a) (a) | |||
NW 4.6 @ 3210 (a) (a) (a) | |||
NNW 3.8-@338- 4.4 @ 3340 3.7 @ 336- (a) | |||
* Locations are listed by miles and degrees heading relative to true northfrom center of Unit #1 Containment. | |||
** Area greaterthan 50 m 2 and contains broadleafvegetation. | |||
(a) None 64 | |||
APPENDIX B: | |||
==SUMMARY== | ==SUMMARY== | ||
OF INTERLABORATORY COMPARISONS Year 2009 65 EfTRODUCTION This appendix covers the Interlaboratory Comparison Program (ICP) of GEL Laboratories LLC (GEL) and Teledyne Brown Engineering (TBE). GEL and TBE use QA/QC samples provided by Eckert & Ziegler Analytics, Inc., Environmental Resource Associates (ERA) and the Mixed Analyte Performance Evaluation Program (MAPEP) to monitor the quality of analytical processing associated with the REMP. Each provider has a documented Quality Assurance program and the capability to prepare Quality Control materials traceable to the National Institute of Standards and Technology (NIST). The providers supply the samples to GEL and TBE, and upon receipt, the laboratories perform the analyses in a normal manner. The results are then reported to the provider for evaluation. | OF INTERLABORATORY COMPARISONS Year 2009 65 | ||
The suite of QA/QC samples is designed to provide sample media and radionuclide combinations that are offered by the providers and included in the REMP and typically includes:) milk for gamma nuclides and low-level iodine- 131 analyses,> milk for Sr-89 and Sr-90 analyses,> water for gamma nuclides, low-level iodine- 131, and gross beta analyses,> water for tritium, Sr-89, and Sr-90 analyses,> cartridge for l- 13 1 analyses,> air filter for gamma nuclide, gross beta, and Sr-90 analyses.The accuracy of each result reported to Eckert & Ziegler Analytics, Inc. is measured by the ratio of GEL and TBE result to the known value. Accuracy for all other results is based on statistically derived acceptance ranges calculated by the providers. | |||
An investigation is undertaken whenever the ratio or reported result fell outside of the acceptance range.RESULTS The GEL and TBE ICP results are included in the following tables for the first through the fourth quarters of 2009. One result did not meet the acceptance criteria and is discussed as follows.* 2nd quarter milk -The root cause of the Sr-90 failure was determined to be a batch quality control issue. The carrier yield for the second separation was greater than 100%. The elevated yield caused the Sr-90 result to be biased low.66 | EfTRODUCTION This appendix covers the Interlaboratory Comparison Program (ICP) of GEL Laboratories LLC (GEL) and Teledyne Brown Engineering (TBE). GEL and TBE use QA/QC samples provided by Eckert & Ziegler Analytics, Inc., Environmental Resource Associates (ERA) and the Mixed Analyte Performance Evaluation Program (MAPEP) to monitor the quality of analytical processing associated with the REMP. Each provider has a documented Quality Assurance program and the capability to prepare Quality Control materials traceable to the National Institute of Standards and Technology (NIST). The providers supply the samples to GEL and TBE, and upon receipt, the laboratories perform the analyses in a normal manner. The results are then reported to the provider for evaluation. The suite of QA/QC samples is designed to provide sample media and radionuclide combinations that are offered by the providers and included in the REMP and typically includes: | ||
A | ) milk for gamma nuclides and low-level iodine- 131 analyses, | ||
> milk for Sr-89 and Sr-90 analyses, | |||
A | > water for gamma nuclides, low-level iodine- 131, and gross beta analyses, | ||
> water for tritium, Sr-89, and Sr-90 analyses, | |||
A | > cartridge for l- 13 1 analyses, | ||
> air filter for gamma nuclide, gross beta, and Sr-90 analyses. | |||
The accuracy of each result reported to Eckert & Ziegler Analytics, Inc. is measured by the ratio of GEL and TBE result to the known value. Accuracy for all other results is based on statistically derived acceptance ranges calculated by the providers. An investigation is undertaken whenever the ratio or reported result fell outside of the acceptance range. | |||
RESULTS The GEL and TBE ICP results are included in the following tables for the first through the fourth quarters of 2009. One result did not meet the acceptance criteria and is discussed as follows. | |||
* 2nd quarter milk - The root cause of the Sr-90 failure was determined to be a batch quality control issue. The carrier yield for the second separation was greater than 100%. The elevated yield caused the Sr-90 result to be biased low. | |||
66 | |||
Reported | Ij ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM GEL LABORATORIES LLC (PAGE 1 OF 2) | ||
Identification Reported Known Quarter Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d) 1st Quarter 2009 E6582-278 Charcoal 1-131 pCi 77.7 79.4 0.98 E6584-278 Milk 1-131 pCi/L 79.7 79.3 1.01 Ce-1 41 pCi/L 97.8 94.9 1.03 Cr-51 pCi/L 297 305 0.97 Cs-1 34 pCi/L 90.6 93.7 0.97 Cs-1 37 pCi/L 116 111 1.04 Co-58 pCi/L 123 119 1.03 Mn-54 pCi/L 133 128 1.04 Fe-59 pCi/L 116 99.9 1.16 Zn-65 pCi/L 172 156 1.10 Co-60 pCi/L 150 142 1.06 E6585-278 Water 1-131 pCi/L 75.5 69 1.09 Ce-141 pCi/L 122 120 1.02 Cr-51 pCi/L 392 387 1.01 Cs- 134 pCi/L 119 119 1.00 Cs-137 pCi/L 144 141 1.02 Co-58 pCi/L 159 151 1.05 Mn-54 pCi/L 180 162 1.11 Fe-59 pCi/L 128 127 1.01 Zn-65 pCi/L 224 197 1.13 Co-60 pCi/L 192 180 1.06 Footnotes are on page 2 of 2. | |||
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ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM GEL LABORATORIES LLC (PAGE 2 OF 2) | |||
Identification Reported Known Quarter Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d) 2nd Quarter 2009 E6729-278 Charcoal 1-131 pCi 92.7 95.5 0.97 A E6730-278 Milk Sr-89 pCi/L 85.1 112 0.76 A Sr-90 pCi/L 10.9 16.7 0.65 N E6731-278 Milk 1-131 pCi/L 89.8 102.0 0.88 A Ce-1 41 pCi/L 284 284 1.00 A Cr-51 pCi/L 404 400 1.01 A Cs-1 34 pCi/L 158.0 166 0.95 A Cs-137 pCi/L 192 192 1.00 A Co-58 pCi/L 94.8 91.9 1.03 A Mn-54 pCi/L 142 137 1.04 A Fe-59 pCi/L 123 122 1.01 A Zn-65 pCi/L 179 175 1.02 A Co-60 pCi/L 315 312 1.01 A E6732-278 Water 1-131 pCi/L 85.2 88.3 0.97 A Ce-141 pCi/L 229 216 1.06 A Cr-51 pCi/L 311 304 1.02 A Cs-134 pCi/L 137 126 1.09 A Cs-137 pCi/L 151 146 1.04 A Co-58 pCi/L 72.1 70 1.03 A Mn-54 pCi/L 107 104 1.03 A Fe-59 pCi/L 90.4 92.9 0.97 A Zn-65 pCi/L 138 133 1.04 A Co-60 pCi/L 242 237 1.02 A (a) GEL reported result. | |||
(b) Reference value. | |||
(c) Ratio GEL to Eckert& Ziegler Analytics. | |||
(d) Evaluation: A= Acceptable, N= Not Acceptable. | |||
68 | |||
DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) | |||
GEL LABORATORIES LLC (PAGE 1 OF 1) | |||
Identification Reported Known Acceptance Quarter Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c) 2nd Quarter 2009 09-GrF20 Filter Gr-Beta Bq 0.297 0.28 0.140 - 0.419 A Gr-Alpha Bq 0.069 0.35 >0.0 - 0.696 A 09-RdF20 Filter Co-57 Bq 1.347 1.30 0.91 -1.69 A Co-60 Bq 1.413 1.22 0.89-1.59 A Cs-134 Bq 2.763 2.93 2.05 - 3.81 A Cs-137 Bq 1.487 1.52 1.06 - 1.98 A M n-54 Bq 2.403 2.27 1.590 - 2.952 A Zn-65 Bq 1.613 1.36 0.95- 1.77 A Sr-90 Bq 0.692 0.64 0.448 - 0.832 A 09-GrW20 Water ' Gr-Beta Bq/L 1.337 1.27 0.64- 1.91 A Gr-Alpha Bq/L 0.506 0.64 >0.0 - 1.270 A 09-MaW20 Water Co-57 Bq/L 18.8 18.9 13.2 -24.6 A Co-60 Bq/L 16.8 17.21 12.05 - 22.37 A Cs-1 34 Bq/L 21.9 22.5 15.8-29.3 A Cs-137 Bq/L 0.0 0 (1) A Mn-54 Bq/L 15.1 14.66 10.26 - 19.06 A Sr-90 Bq/L 7.43 7.21 5.05 - 9.37 A Zn-65 Bq/L 14.6 13.6 9.5- 17.7 A (a) GEL reported result. | |||
(b) Reference value. | |||
(c) Evaluation: A= Acceptable, N = Not Acceptable. | |||
(1) False positive test. | |||
69 | |||
ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM GEL LABORATORIES LLC (PAGE 1 OF 1) | |||
Identification Reported Known Acceptance Quarter Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c) 1st Quarter 2009 RAD-76 Water Gr-Alpha pCi/L 51.3 52.3 27.3 - 52.3 A Gr-Beta pCi/L 41.9 46.1 31.0-53.3 A H-3 pCi/L 3760 4230 3610 -4660 A 1-131 pCi/L 25.1 22.2 18.4-26.5 A Sr-89 pCi/L 72.8 65 52.7 - 73.0 A Sr-90 pCi/L 36.5 41.9 30.8-48.1 A (a) GEL reported result. | |||
(b) Reference value. | |||
(c) Evaluation: A= Acceptable, N = Not Acceptable. | |||
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ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 2) | |||
Identification Reported Known Ratio (c) | |||
Month/Year Number Matrix Nuclide Units Value(a) Value (b) TBE/Analytics Evaluation(d) | |||
September 2009 E6897-396 Milk Sr-89 pCi/L 113 107 1.06 A Sr-90 pCi/L 17.4 18.8 0.93 A E6898-396 Milk 1-131 pCi/L 89.2 98.6 0.90 A Ce-141 pCi/L 249 275 0.91 A Cr-51 pCi/L 213 221 0.96 A Cs-134 pCi/L 104.0 123 0.85 A Cs-137 pCi/L 172 185 0.93 A Co-58 pCi/L 96.3 99.4 0.97 A Mn-54 pCi/L 201 206 0.98 A Fe-59 pCi/L 154 147 1.05 A Zn-65 pCi/L 213 204 1.04 A Co-60 pCi/L 154 160 0.96 A E6900-396 Filter Ce-141 pCi 181 161 1.12 A Cr-51 pCi 145 130 1.12 A Cs-134 pCi 71.8 72 0.99 A Cs-137 pCi 115 109 1.06 A Co-58 pCi 62 58 1.06 A Mn-54 pCi 129 121 1.07 A Fe-59 pCi 97 98 0.98 A Zn-65 pCi 110 120 0.92 A Co-60 pCi 98.7 94.1 1.05 A E6899-396 Charcoal 1-131 pCi 89.5 92.3 0.97 A Footnotes are on page 2 of 2. | |||
71 | |||
ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2) | |||
Identification Reported Known Ratio (c) | |||
Month/Year Number Matrix Nuclide Units Value(a) Value (b) TBE/Analytics Evaluation(d) | |||
December 2009 E6946-396 Milk Sr-89 pCi/L 131 131 1.00 A Sr-90 pCi/L 19.3 17.9 1.08 A E6947-396 Milk 1-131 pCi/L 79.2 87.3 0.91 A Ce-141 pCi/L 193 202 0.96 A Cr-51 pCi/L 512 548 0.93 A Cs-134 pCi/L 222 253 0.88 A Cs-137 pCi/L 163 179 0.91 A Co-58 pCi/L 200 211 0.95 A Mn-54 pCi/L 178 178 1.00 A Fe-59 pCi/L 176 178 0.99 A Zn-65 pCi/L 326 345 0.94 A Co-60 pCi/L 240 256 0.94 A E6949-396 Filter Ce-141 pCi 103 103 1.00 A Cr-51 pCi 290 280 1.04 A Cs-134 pCi 116 129 0.90 A Cs-137 pCi 93.4 91.5 1.02 A Co-58 pCi ill 108 1.03 A Mn-54 pCi 81.0 90.8 0.89 A Fe-59 pCi 106 90.8 1.17 A Zn-65 pCi 155 176 0.88 A Co-60 pCi 135 131 1.03 A E6948-396 Charcoal 1-131 pCi 93.3 93.9 0.99 A (a) Teledyne Brown Engineering reported result. | |||
(b) The Eckert & Ziegler 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. | |||
(c) Ratio of Teledyne Brown Engineering to Eckert &Ziegler Analytics results. | |||
(d) Eckert& Ziegler Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20. W = Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of< 0.70 and> 1.30. | |||
72 | |||
DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) | |||
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1) | |||
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) . Range Evaluation (c) | |||
September 2009 09-MaW21 Water Cs-134 Bq/L 26.5 32.2 22.5-41.9 A Cs-137 Bq/L 37.2 41.2 28.8 - 53.6 A Co-57 Bq/L 32.2 36.6 25.6 -47.6 A Co-60 Bq/L 14.0 15.40 10.8-20.0 A H-3 Bq/L 705 634.1 443.9 - 824.3 A Mn-54 Bq/L -0.1015 (1) A Sr-90 Bq/L 13.9 12.99 9.09- 16.89 A Tc-99 Bq/L 8.06 10.0 7.0- 13.0 A Zn-65 Bq/L 26.2 26.9 18.8-35.0 A 09-GrW21 Water Gr-Alpha Bq/L 1.27 1.047 >0.0 - 2.094 A Gr-Beta Bq/L 9.70 7.53 3.77- 11.30 A 09-RdF21 Filter Am-241 Bq/sample -0.0040 (1) A Cs- 134 Bq/sample -0.02 (1) A Cs-137 Bq/sample 1.4 1.4 0.98- 1.82 A Co-57 Bq/sample 5.98 6.48 4.54- 8.42 A Co-60 Bq/sample 1.01 1.03 0.72- 1.34 A Mn-54 Bq/sample 5.16 5.49 3.84-7.14 A Sr-90 Bq/sample 0.925 0.0835 0.585 - 1.086 A Zn-65 Bq/sample 4.39 3.93 2.75-5.11 A 09-GrF21 Filter Gr-Alpha Bq/sample 0.357 0.659 >0.0 - 1.318 A Gr-Beta Bq/sample 1.403 1.320 0.66- 1.98 A (1) False positive test. | |||
(a) Teledyne Brown Engineering reported result. | |||
(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined bygravimetric and/or volumetric measurements made during standard preparation. | |||
(c) DOE/MAPEP evaluation: A = Acceptable, W = Acceptable with warning, N = Not Acceptable. | |||
73 | |||
ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE 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) | |||
October 2009 RAD 79 Water Sr-89 pCi/L 64.75 62.2 50.2-70.1 A Sr-90 pCi/L 30.30 30.7 22.4 - 35.6 A Ba-133 pCi/L 97.9 92.9 78.3- 102 A Cs-134 pCi/L 76.8 79.4 65.0 - 87.3 A Cs-137 pCi/L 59.9 54.6 49.1 -62.9 A Co-60 pCi/L 121 117 105- 131 A Zn-65 pCi/L 115 99.5 89.6-119 A Gr-Alpha pCi/L 19.6 23.2 11.6-31.1 A Gr-Beta pCi/L 28.5 26.0 16.2-33.9 A 1-131 pCi/L 22.1 22.2 18.4-26.5 A H-3 pCi/L 16133 16400 14300 - 18000 A (a) Teledyne Brown Engineering reported result. | |||
(b) The ERA known value is equal to 100% of the parameter present in the standard as determined bygravimetric and/or volumetric measurements made during standard preparation. | |||
(c) ERAevaluation: A= Acceptable. Reported result falls within the Warning Limits. NA= NotAcceptable. Reported result falls outside of the Control Limits. CE = Check for Error. Result falls within the Control Limits and outside of the Warning Limit. | |||
74}} | |||
Latest revision as of 23:45, 11 March 2020
| ML101320229 | |
| Person / Time | |
|---|---|
| Site: | Surry, 07200002, 07200055  |
| Issue date: | 04/30/2010 |
| From: | Stanley B Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| 10-206 | |
| Download: ML101320229 (78) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 30, 2010 Attention: Document Control Desk Serial No.10-206 U.S. Nuclear Regulatory Commission SS&LITJN RO Washington, D. C. 20555-0001 Docket Nos. 50-280 50-281 72-2 72-55 License Nos. DPR-32 DPR-37 SNM-2501 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Surry Units 1 and 2 Technical Specification 6.6.B.2 requires the submittal of an Annual Radiological Environmental Operating Report (AREOR) for Surry Power Station. Surry Independent Spent Fuel Storage Installation (ISFSI) Technical Specification Appendix C, Item 1.3.1 requires that the Surry ISFSI be included in the environmental monitoring for the Surry Power Station. Accordingly, enclosed is the Surry Power Station AREOR for the period of January 1, 2009 through December 31, 2009, which includes environmental monitoring for the Surry ISFSI.
If you have any questions or require additional information, please contact Paul Harris at 757-365-2692.
Sincerely, B. L. Stanley Director Station Safety and Licensing Surry Power Station Attachment Commitments made in this letter: None S&eAS
Serial No.10-206 Docket Nos.: 50-280 50-281 72-2 72-55 copy: United States Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 NRC Senior Resident Inspector Surry Power Station Director Division of Radiological Health 109 Governor Street, Room 730 Richmond, Virginia 23219
Serial No.10-206 Docket Nos.: 50-280 50-281 72-2 72-55 Attachment I 2009 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION VIRGINIA ELECTRIC AND POWER COMPANY
Surry Power Station 2009 Annual Radiological Environmental Operating Report DoMn
'kDOminiont
Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2009 to December 31, 2009
in Annual Radiological Environmental Operating Report Surry Power Station January 1, 2009 to December 31, 2009 HI In Prepared by:
P. F. Blount ID Health Physicist ID Reviewed by:
P. R. Harris Supervisor Radiological Analysis Reviewed by:
Sii B. A. Hilt Supervisor Health Physics Technical Services Approved by:
Manager Radiological Protection and Chemistry II 2
Table of Contents PREFA CE .............................................................................................................................................. 4
- 1. EX ECUTIV E SU M MARY ....................................................................................................... 5
- 2. PRO GRA M D ESCRIPTION ........................................................................................................ 7 2.1 Introduction .............................................................................................................................. 7 2.2 Sam pling and Analysis Program ........................................................................................ 8
- 3. AN A LY TICAL RESU LTS ........................................................................................................ 20 3.1 Summ ary of Results .............................................................................................................. 20 3.2 Analytical Results of 2009 REM P Sam ples ................................................................... 28
- 4. D ISCU SSION OF RESU LTS ................................................................................................. 49 4.1 Gam m a Exposure Rate ................................................................................................... 49 4.2 A irborne Gross Beta .............................................................................................................. 50 4.3 A irborne Radioiodine ............................................................................................................. 52 4.4 Air Particulate Gam ma ..................................................................................................... 52 4.5 Cow M ilk .............................................................................................................................. 52 4.6 Food Products ................................................................. 53 4.7 W ell W ater ............................................................................................................................ 53 4.8 River W ater ........................................................................................................................... 53 4 .9 S ilt ......................................................................................................................................... 53 4.10 Shoreline Sedim ent ........................................................................................................ 55 4 .1 1 Fish ...................................................................................................................................... 55 4.12 Oysters ................................................................................................................................ 56 4.13 Clam s .................................................................................................................................. 56 4.14 Crabs ................................................................................................................................... 56
- 5. PRO GRAM EX CEPTION S ..................................................................................................... 57
- 6. CON CLU SION S ............................................................................................................................. 58 REFEREN CES .................................................................................................................................... 60 APPEN DICES ..................................................................................................................................... 62 APPEN D IX A : LAN D U SE CEN SU S ...................................................................................... 63 APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS ........................... 65 3
PREFACE This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report, for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281.
4
- 1. EXECUTIVE
SUMMARY
This document is a detailed report of the 2009 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2009, in air, water, silt, shoreline sediment, milk, aquatic biota, food products and direct exposure pathways have been analyzed, evaluated and summarized. The REMP is designed to confirm 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 are protected.
The program also detects any unexpected environmental processes that could allow radiation accumulations in the environment or food pathway chains.
Radiation and radioactivity in the environment are monitored within a 20-mile radius of the station. Surry Power Station personnel collect a variety of samples within this area. A number of sampling locations for each medium are selected using available meteorological, land use, and water use data. Two types of samples are obtained. The first type, control samples, is collected from areas that are beyond the measurable influence of Surry 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 Surry Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station 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 control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident or natural variation.
GEL Laboratories LLC and Teledyne Brown Engineering, Inc. provide radioanalyses for this program and Global Dosimetry Solutions, Inc. provides thermoluminescent dosimetry (TLD) services. Participation in an 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 United States Nuclear Regulatory Commission (USNRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLDs). This ensures that analyses are as accurate as 5
possible. The USNRC also mandates a reporting level for radionuclides. Licensed nuclear facilities must report the radionuclide activities in those environmental samples that are equal to or greater than the specified reporting level.
Environmental radiation levels are sometimes referred to as a percent of the reporting level.
Analytical results are reported for all possible radiation exposure pathways to man. These pathways include airborne, aquatic, terrestrial and direct radiation exposure. The airborne exposure pathway includes radioactive airborne iodine and particulates. The 2009 airborne results were similar to previous years. No station related radioactivity was detected and natural radioactivity levels remained at levels consistent with past years' results. Aquatic exposure pathway samples include well and river water, silt and shoreline sediments, crabs, fish, clams and oysters. Naturally occurring potassium-40 was detected at average environmental levels. No man-made radionuclides were detected in well water. This trend is consistent throughout the operational environmental monitoring program. No man-made radionuclides were detected in river water. Silt samples indicated the presence of cesium- 137 and naturally occurring radionuclides. The cesium- 137 activity was present in the control and indicator locations and is attributable to global fallout from past nuclear weapons testing and nuclear accidents such as Chernobyl. Shoreline sediment, which may provide a direct exposure pathway, contained no station related radionuclides. Naturally occurring potassium-40 and thorium-228 were detected at average environmental levels. The terrestrial exposure pathway includes milk and food products. Iodine-131 was not detected in any 2009 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90 was again detected in milk and this activity is attributable to past atmospheric nuclear weapons testing. No man-made radionuclides were detected in food product samples. Consistent with historical data, naturally occurring potassium-40 was detected in milk and food products. The direct exposure pathway measures environmental radiation doses using TLDs. TLD results have remained relatively constant over the years.
During 2009, as in previous years, the operation of Surry Power Station has created no adverse environmental effects or health hazards. The maximum total body dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2009 was 0.001 millirem. For reference, this dose may be compared to the 620 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 50% of radiation exposure to man, while nuclear power contributes less than 0.1%.
These results demonstrate compliance with federal and state regulations and also demonstrate the adequacy of radioactive effluent controls at Surry Power Station.
6
- 2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2009 Surry Power Station operational Radiological Environmental Monitoring Program (REMP). The Dominion Surry Power Station is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. The site consists of two units, each with a pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 855 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973.
The United States Nuclear Regulatory Commission 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 is Reasonably Achievable. To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications that address the release of radioactive effluents. In-plant monitoring is used to ensure that these 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 station environs is also included in Surry Power Station Technical Specifications.
Dominion personnel are responsible for collecting the various indicator and control environmental samples. Global Dosimetry Solutions Incorporated is responsible for processing the TLDs. GEL Laboratories LLC and Teledyne Brown Engineering are responsible for sample analyses. The results of the analyses are used to determine if changes in radioactivity levels may be attributable to station operations. Measured values are compared with control values, which vary with time due to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radionuclides. Data collected prior to station operation is used to indicate the degree of natural variation to be expected. This pre-operational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of station operation.
Occasionally, samples of environmental media may show the presence of man-made radionuclides. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",
(December, 1975) and VPAP-2103S, Offsite Dose Calculation Manual (Surry).
7
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."
This report documents the results of the REMP for 2009 and satisfies the following objectives of the program:
) To provide 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 member of the public resulting from station operations.
To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.
> To identify changes in radioactivity in the environment.
> To verify that station operations have no detrimental effect on the health and safety of the public.
2.2 Sampling and Analysis Program Table 2-1 summarizes the 2009 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled "control." Dominion personnel collect all samples listed in Table 2-1.
Table 2-2 summarizes the analysis program conducted by GEL Laboratories LLC, Teledyne Brown Engineering and Global Dosimetry Solutions for Surry Power Station. All samples, with the exception of the TLDs, are shipped to GEL Laboratories LLC, located in Charleston, SC, or Teledyne Brown Engineering, located in Knoxville, TN, for analysis. The TLDs are shipped to Global Dosimetry Solutions, located in Costa Mesa, CA, for processing.
The Surry Radiological Monitoring Locations maps (Figures 1 - 5) denote sample locations for Surry Power Station. The locations are color coded to designate sample types.
8
-- == -.. - !E !m - - - - = m Table 2-1 SURRY - 2009 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Onsite (Stored in a lead shield outside the protected Environmental Control (00) Quarterly area)
TLDs West North West (02) 0.2 WNW 2930 Quarterly Site Boundary Surry Station Discharge (03) 0.4 NW 3210 Quarterly Site Boundary North North West (04) 0.2 NNW 3290 Quarterly Site Boundary North (05) 0.3 N 40 Quarterly Site Boundary North North East (06) 0.3 NNE 280 Quarterly Site Boundary North East (07) 0.3 NE 440 Quarterly Site Boundary East North East (08) 0.4 ENE 670 Quarterly Site Boundary East (09) 0.3 E 890 Quarterly Site Boundary West (10) 0.1 W 2710 Quarterly Site Boundary West South West (11) 0.4 WSW 2520 Quarterly Site Boundary South West (12) 0.3 SW 2280 Quarterly Site Boundary South South West (13) 0.3 SSW 2010 Quarterly Site Boundary South (14) 0.4 S 1820 Quarterly Site Boundary South South East (15) 0.6 SSE 1570 Quarterly Site Boundary South East (16) 0.9 SE 1350 Quarterly Site Boundary Station Intake (18) 1.6 ESE 1150 Quarterly Site Boundary Hog Island Reserve (19) 2.0 NNE 260 Quarterly Near Resident Bacon's Castle (20) 4.5 SSW 2020 Quarterly Apx. 5 mile Route 633 (21) 4.9 SW 2270 Quarterly Apx. 5 mile Alliance (22) 5.1 WSW 2470 Quarterly Apx. 5 mile Surry (23) 7.7 WSW 2560 Quarterly Population Center Route 636 and 637 (24) 4.0 W 2700 Quarterly Apx. 5 mile Scotland Wharf (25) 5.0 WNW 2840 Quarterly Apx. 5 mile Jamestown (26) 6.3 NW 3080 Quarterly Apx. 5 mile Colonial Parkway (27) 3.8 NNW 3330 Quarterly Apx. 5 mile Route 617 and 618 (28) 4.9 NNW 3400 Quarterly Apx. 5 mile Kingsmill (29) 4.6 N 20 Quarterly Apx. 5 mile Williamsburg (30) 7.8 N 00 Quarterly Population Center Kingsmill North (31) 5.5 NNE 120 Quarterly Apx. 5 mile Budweiser (32) 5.8 NNE 270 Quarterly Population Center Water Plant (33) 5.0 NE 460 Quarterly Apx. 5 mile 9
Table 2-1 SURRY - 2009 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental BASF (34) 5.1 ENE 700 Quarterly Apx. 5 mile TLDs Lee Hall (35) 7.1 ENE 750 Quarterly Population Center Goose Island (36) 5.1 E 900 Quarterly Apx. 5 mile Fort Eustis (37) 4.9 ESE 1040 Quarterly Apx. 5 mile Newport News (38) 19.3 SE 1300 Quarterly Population Center James River Bridge (39) 17.1 SE 1420 Quarterly Control Location Benn's Church (40) 17.0 SSE 1590 Quarterly Control Location Smithfield (41) 13.4 SSE 1670 Quarterly Control Location Rushmere (42) 5.3 SSE 1560 Quarterly Apx. 5 mile Route 628 (43) 5.1 S 1770 Quarterly Apx. 5 mile Air Charcoal Surry Station (SS) 0.3 NNE 180 Weekly Site boundary location with highest D/Q and Particulate Hog Island Reserve (HIR) 2.0 NNE 260 Weekly Bacon's Castle (BC) 4.5 SSW 2020 Weekly Alliance (ALL) 5.1 WSW 2470 Weekly Colonial Parkway (CP) 3.8 NNW 3330 Weekly BASF (BASF) 5.1 ENE 700 Weekly Fort Eustis (FE) 4.9 ESE 1040 Weekly Newport News (NN) 19.3 SE 1300 Weekly Control Location River Water Surry Station Discharge (SD) 0.4 NW 3230 Monthly Scotland Wharf (SW) 4.9 WNW 2840 Monthly Control Location Well Water Surry Station (SS) 0.1 SW 2270 Quarterly Onsite Hog Island Reserve (HIR) 2.0 NNE 280 Quarterly Construction Site (CS) 0.3 E 870 Quarterly Shoreline Hog Island Reserve (HIR) 0.6 N 70 Semi-Annually Sediment Chickahominy River (CHIC) 11.2 WNW 3010 Semi-Annually Control Location Silt Chickahominy River (CHIC) 11.2 WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.3 NNW 3410 Semi-Annually 10
Table 2-1 SURRY - 2009 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Milk Colonial Parkway (CP) 3.7 NNW 3360 Monthly Williams (WMS) 27.5 S 1750 Monthly Control Location Epps (EPPS) 4.8 SSW 2000 Monthly Oysters Point of Shoals (POS) 6.4 SSE 1570 Semi-Annually Mulberry Point (MP) 4.9 ESE 1240 Semi-Annually Clams Chickahominy River (CHIC) 11.2 WNW 3000 Semi-Annually Control Location Surry Station Discharge (SD) 1.3 NNW 3410 Semi-Annually Hog Island Point (HIP) 2.4 NE 520 Semi-Annually Lawne's Creek (LC) 2.4 SE 1310 Semi-Annually Jamestown Island (JI) 3.9 NNW 3240 Semi-Annually Fish Surry Station Discharge (SD) 1.3 NNW 3410 Semi-Annually Crabs Surry Station Discharge (SD) 1.3 NNW 3410 Annually Crops Brock's Farm (BROCK) 3.8 S 1830 Annually (Corn, Peanuts, Slade's Farm (SLADE) 3.2 S 1790 Annually Soybeans) 11
Table 2-2 SURRY - 2009 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYS IS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2 mR/Std. Month Dosimetry (TLD) 3 Air Iodine Weekly 1-131 0.07 pCi/mr Air Particulate Weekly Gross Beta 0.01 pCi/r3 3
Quarterly (a) Gamma Isotopic pCi/rn Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium (H-3) 2000 pCi/L Composite of monthly sample Monthly 1-131 10 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 Well Water Quarterly Tritium (H-3) 2000 pCi/L 1-131 1 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 Footnotes located at end of table.
12
Table 2-2 SURRY- 2009 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Shoreline Sediment Semi-Annually Gamma Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Silt Semi-Annually Gamma Isotopic pCi/kg - dry Cs-134 150 Cs-137 180 Nilk Monthly 1-131 I pCi/L Gamma Isotopic pCi/L Cs-134 15 Cs-137 18 Ba-140 60 La- 140 15 Quarterly Sr-89 NA pCi/L Composite of CP Sr-90 NA monthly sample Oysters Semi-Annually 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 Clams Semi-Annually 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 Crabs Annually 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 Footnotes located at end of table.
13
Table 2-2 SURRY- 2009 SAMPLE ANALYSIS PROGRAM SAAMPLE MEDIA FREQUENCY ANALYSIS LLD* R1EPORT UNITS Fish Semi-Annually 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 Annually Gamma Isotopic pCi/kg - wet 1-131 60 Cs-134 60 Cs-137 80 Note: This table is not a complete listing of nuclides that can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, are also identified and reported.
- LLD is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. LLDs indicate those concentrations to which environmental samples are required to be analyzed. Actual analysis of samples may be lower than these listed values.
(a) Quarterly composites of each location's weekly air particulate samples are analyzed for gamma emitters.
NA None assigned 14
=- -= = = =m - m = = =- = m =
IC)
I~.
I~.
0
=m=- m m = m= = = mm m =- = m = mm m=n
=mmm M---- M- = M M = M m Figure 3. Surry Emergency Plan Map 0 Air Sampling Stations Nearest Residents 0
- TLD Sampling Nearest Milk Animal z
- Nearest Garden Aquatic Samples 00K Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.
((2 (pVWIrARFO W Surry 7~
- ýLAZY OAK""
w s" CORNER (61ý (IX\ II
.~II
("3l
ý95 TE XT0N Figure 4. Surry Emergency Plan Map Air Sampling Stations Nearest Residents Li . TLD Sampling Nearest Milk Animal z~
- Nearest Garden Crop Samples 1W Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.
= M = = = = m=m=- M = = = M Figure 5. Surry Emergency Plan Map Air Sampling Stations Nearest Residents
- TLD Sampling Nearest Milk Animal
- Nearest Garden Aquatic Samples Original © 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA 22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.
- 3. ANALYTICAL RESULTS 3.1 Summary of Results In accordance with the Surry Offsite Dose Calculation Manual (ODCM), a summary table of the analytical results has been prepared and is presented in Table 3-1. This data is presented in accordance with the format of the USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Revision 1, November 1979. A more detailed analysis of the data is given in Section 4.
20
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 1 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Direct Gamma 164 2 3.3 (152/152) STA-9 0.3 mi 5.6(414) 3.7(12/12) 0 Radiation (1.2-6.2) E (4.7-6.2) (1.8- 6.5)
TLD (mR/
Std Month)
Air Gross 416 10 23.9 (364/364) ALL 5.1 mi 27.4 (52/52) 23.2 (52/52) 0 Particulate Beta (7.1 -60.2) WSW (8.2- 60.2) (10.1 - 47.2)
(1E-3 pCi/m3)
Gamma 32 Be-7 32 144 (28/28) ALL 5.1 mi 165 (4/4) 139 (4/4) 0 (106- 197) WSW (134-197) (114-164)
Cs-1 34 32 50 < LLD N/A " LLD < LLD 0 Cs-1 37 32 60 < LLD N/A < LLD < LLD 0 Air Iodine 1-131 416 70 < LLD N/A < LLD < LLD 0 (IE-3 pCi/m3)
Milk Strontium 4 (pCi/Luter)
Sr-89 4 < LLD N/A < LLD < LLD 0 Sr-90 4 1.12(1/4) CP 3.7 mi 1.12(1/4) N/A 0 (1.12- 1.12) NNW (1.12- 1.12)
Gamma 36 K-40 36 1360 (24/24) CP 3.7 mi 1397 (12/12) 1308 (12/12) 0 (1220 - 1510) NNW (1260- 1510) (1150- 1420)
Th-228 36 < LLD N/A < LLD 13.0 (1/12) 0 (13.0- 13.0) 1-131 36 1 < LLD N/A < LLD " LLD 0 Cs-134 36 15 < LLD N/A < LLD < LLD 0 Cs-137 36 18 < LLD N/A < LLD < LLD 0 21 I-f 4k
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 2 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Milk Gamma 36 (pCi/Liter)
Ba-140 36 60 < LLD N/A < LLD " LLD 0 La- 140 36 15 < LLD N/A < LLD < LLD 0 Food Gamma Products (pCi/kg wet) K-40 8097 (3/3) Slade 3.2 mi 8995 (2/2) N/A 0 (3190 - 14800) S (3190-14800)
Th-228 10.4 (1/3) Slade 3.2 mi 10.4(1/2) N/A (10.4 - 10.4) S (10.4 - 10.4) 1-131 60 < LLD N/A < LLD N/A 0 Cs- 134 60 < LLD N/A < LLD N/A 0 Cs-137 80 " LLD N/A < LLD N/A 0 0
Well H-3 2000 < LLD N/A < LLD N/A 0 Water (pCi/Liter)
Gamma K-40 37.5 (1/12) SS 0.1 mi 37.5 (1/12) N/A 0 (37.5 - 37.5) SW (37.5 - 37.5)
Ac-228 15.4 (1/12) CS 0.3 mi 15.4(1/12) N/A 0 (15.4- 15.4) E (15.4 - 15.4)
Mn-54 15 < LLD N/A < LLD N/A 0 Co-58 15 < LLD N/A < LLD N/A 0 Fe-59 30 < LLD N/A " LLD N/A 0 Co-60 15 " LLD N/A < LLD N/A 0 22
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 3 of 7 Medium or Indicator Control L
Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Nell Zn-65 12 30 < LLD N/A < LLD N/A 0 Nater 0pCi/Liter)
Nb-95 12 15 < LLD N/A < LLD N/A 0 Zr-95 12 30 < LLD N/A < LLD N/A' 0 1-131 12 1 < LLD N/A < LLD N/A 0 Cs-134 12 15 < LLD N/A < LLD N/A 0 Cs-1 37 12 18 < LLD N/A < LLD N/A 0 Ba-140 12 60 < LLD N/A < LLD N/A 0 La-140 12 15 < LLD N/A < LLD N/A 0 Fliver H-3 8 2000 < LLD N/A < LLD N/A 0 Water (pCi/Liter)
Gamma 24 K-40 24 138.4 (4/12) SD 0.4 mi 138.4 (4/12) 105.9 (5/12) 0 (75.7- 188) NW (75.7- 188) (27.2 - 167)
Th-228 24 < LLD SW 4.9 mi 5.52 (1/12) 5.52 (1/12) 0 WNW (5.52 - 5.52) (5.52 - 5.52)
Ra-226 24 < LLD SW 4.9 mi 34.6 (1/12) 34.6 (1/12) 0 WNW (34.6 - 34.6) (34.6 - 34.6)
Mn-54 24 15 " LLD N/A < LLD < LLD 0 Co-58 24 15 < LLD N/A < LLD < LLD 0 Fe-59 24 30 < LLD N/A < LLD < LLD 0 23
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSUMMAR Y Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 4 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements River Co-60 24 15 < LLD N/A < LLD < LLD 0 Water (pCi/Liter)
Zn-65 24 30 < LLD N/A < LLD < LLD 0 Nb-95 24 15 < LLD N/A < LLD < LLD 0 Zr-95 24 30 < LLD N/A < LLD < LLD 0 1-131 24 10 < LLD N/A < LLD < LLD 0 Cs-134 24 15 < LLD N/A < LLD < LLD 0 Cs-137 24 18 < LLD N/A < LLD < LLD 0.
Ba-140 24 60 < LLD N/A < LLD < LLD 0 La-140 24 15 < LLD N/A < LLD < LLD 0 Silt Gamma 4 (pCi/kg dry)
K-40 4 14700 (212) CHIC 11.2 mi 16550 (2/2) 16550 (2/2) 0 (14000-15400) WNW (16100-17000) (16100-17000)
Cs-134 4 150 < LLD N/A < LLD < LLD 0 Cs-137 4 180 214(2/2) SD 1.3 mi 214(2/2) 184(2/2) 0 (154-274) NNW (154-274) (182-186)
Th-228 4 1080 (2/2) CHIC 11.2 mi 1295(2/2) 1295(2/2) 0 (1010- 1150) WNW (1210-1380) (1210-1380)
Th-230 4 644 (1/2) CHIC 11.2 mi 1310(1/2) 1310(1/2) 0 (644 - 644) WNW (1310-1310) (1310-1310)
Th-232 4 1030 (1/2) CHIC 11.2 mi 1180(2/2) 1180(2/2) 0 (1030 - 1030) WNW (1020- 1340) (1020- 1340) 24 I,,
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSUMMAR Y Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 5 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name Direction Range Range Measurements Silt TI-208 4 231 (1/2) CHIC 11.2 mi 418 (1/2) 418 (1/2) 0 (pCi/kg dry) (231 -231) WNW (418-418) (418-418)
Pb-212 4 1010 (1/2) CHIC 11.2 mi 1380 (1/2) 1380 (1/2) 0 (1010 - 1010) WNW (1380 - 1380) (1380 - 1380)
Pb-214 4 874 (1/2) CHIC 11.2 mi 1250 (1/2) 1250 (1/2) 0 (874 - 874) WNW (1250 - 1250) (1250 - 1250)
Bi-214 4 644 (1/2) CHIC 11.2 mi 1310 (1/2) 1310 (1/2) 0 (644 - 644) WNW (1310- 1310) (1310- 1310)
Ra-226 4 2192 (2/2) SD 1.3 mi 2192 (2/2) 1435(2/2) 0 (644 - 3740) NNW (644- 3740) (1310 - 1560)
Ra-228 4 < LLD CHIC 11.2 mi 1340 (1/2) 1340 (1/2) 0 WNW (1340- 1340) (1340- 1340)
Ac-228 4 < LLD CHIC 11.2 mi 1340 (1/2) 1340(1/2) 0 WNW (1340 - 1340) (1340 - 1340)
U-234 4 644 (1/2) SD 1.3 mi 644 (1/2) < LLD 0 (644 - 644) NNW (644- 644)
Shoreline Gamma 4 Sediment (pCi/kg dry) K-40 4 5735 (2/2) HIR 0.6 mi 5735 (2/2) 4140 (2/2) 0 (5290 - 6180) N (5290 - 6180) (2160 - 6120)
Cs-134 4 150 < LLD N/A < LLD < LLD 0 Cs-137 4 180 < LLD N/A < LLD < LLD 0 Th-228 4 < LLD CHIC 11.2 mi 103 (1/2) 103 (1/2) 0 WNW (103-103) (103-103)
Fish Gamma 4 (pCi/kg wet)
K-40 4 2163 (3/4) SD 1.3 mi 2163(3/4) N/A 0 (2060 - 2230) NNW (2060 - 2230)
Mn-54 4 130 < LLD N/A < LLD N/A 0 Co-58 4 130 < LLD N/A < LLD N/A 0 25
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 6 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean I Distance Mean Mean Reported (Units) Type No. LLD Range Name IDirection Range Range Measurements Fish Fe-59 4 260 < LLD N/A < LLD N/A 0 (pCi/kg wet)
Co-60 4 130 < LLD N/A < LLD N/A 0 Zn-65 4 260 < LLD N/A < LLD N/A 0 Cs-1 34 4 130 < LLD N/A < LLD N/A 0 Cs-1 37 4 150 < LLD N/A < LLD N/A 0 Oysters Gamma 4 (pCi/kg wet)
K-40 4 1050 (1/4) POS 6.4 mi 1050 (1/4) N/A (1050 - 1050) SSE (1050 - 1050)
Mn-54 4 130 < LLD N/A < LLD N/A Fe-59 4 260 < LLD N/A < LLD N/A Co-58 4 130 < LLD N/A < LLD N/A Co-60 4 130 < LLD N/A < LLD N/A Zn-65 4 260 < LLD N/A < LLD N/A Cs-134 4 130 < LLD N/A < LLD N/A Cs-137 4 150 < LLD N/A < LLD N/A Clams Gamma 8 (pCi/kg wet)
K-40 8 445 (2/6) LC 2.4 mi 458 (1/2) 851 (1/2) 0 (431 - 458) SE (458 - 458) (851 -851)
Th-228 8 < LLD CHIC 11.2 mi 164 (1/2) 164(1/2) 0 WNW (164- 164) (164- 164) 26
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2009 Docket No. 50-280-281 Page 7 of 7 Medium or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine Sampled Total Mean Distance Mean Mean Reported (Units) Type No. LLD Range Name IDirection Range Range Measurements Clams Mn-54 8 130 < LLD N/A < LLD < LLD 0 (pCi/kg vwet)
Co-58 8 130 < LLD N/A < LLD < LLD 0 Fe-59 8 260 < LLD N/A < LLD < LLD 0 Co-60 8 130 < LLD N/A < LLD < LLD 0 Zn-65 8 260 < LLD N/A < LLD < LLD 0 Cs-134 8 130 < LLD N/A < LLD < LLD 0 Cs-137 8 150 < LLD N/A < LLD < LLD 0 Crabs Gamma 1 (pCi/kg vet)
K-40 1 1590 (1/1) SD 1.3 mi 1590 (1/1) N/A 0 (1590 - 1590) NNW (1590 - 1590)
Mn-54 1 130 < LLD N/A < LLD N/A 0 Co-58 1 130 < LLD N/A < LLD N/A 0 Fe-59 1 260 < LLD N/A < LLD N/A 0 Co-60 1 130 < LLD N/A < LLD N/A 0 Zn-65 1 260 < LLD N/A < LLD N/A 0 Cs-134 1 130 < LLD N/A < LLD N/A 0 Cs-1 37 1 150 < LLD N/A < LLD N/A 0 27
3.2 Analytical Results of 2009 REMP Samples Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods.
The reported error is two times the standard deviation (27) of the net activity.
Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Results are considered positive when the measured value exceeds 2y uncertainty.
GEL Laboratories LLC and Teledyne Brown Engineering analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", (November 1979, Revision 1) and the Surry ODCM.
Data are given according to sample type as indicated below.
- 1. Gamma Exposure Rate
- 2. Air Particulates, Weekly Gross Beta Radioactivity
- 3. Air Particulates, Weekly I- 131
- 4. Air Particulates, Quarterly Gamma Spectroscopy
- 5. Cow Milk
- 6. Food Products
- 7. Well Water
- 8. River Water
- 9. Silt
- 10. Shoreline Sediment
- 11. Fish
- 12. Oysters
- 13. Clams
- 14. Crabs 28
TABLE 3-2: GAAMM EXPOSURE RA TE Sunry Power Station, Surry County, Virginia - 2009 mRIS td Month +/- 2 Sigma Page 1 of 1 STATION FIRST SECOND THIRD FOURTH AVERAGE NUMBER QUARTER QUARTER QUARTER QUARTER +/- 2 SIGMA 02 3.9 +/- 0.5 3.6 +/- 0.5 4.7 +/- 1.1 5.1 +/- 0.4 4.3 +/- 1.4 03 4.2 +/- 1.2 4.0 +/- 0.4 4.0 +/- 0.6 5.1 +/- 0.2 4.3 +/- 1.1 04 3.0 +/- 0.6 3.5 +/- 0.2 4.1 +/- 0.7 4.1 +/- 0.3 3.7 +/- 1.1 05 3.7 +/- 1.1 3.0 +/- 0.2 3.8 +/- 0.5 4.6 +/- 0.9 3.8 +/- 1.3 06 3.3 +/- 0.5 3.9 +/- 0.9 5.2 +/- 1.6 4.6 +/- 0.7 4.3 +/- 1.7 07 3.9 +/- 1.4 3.4 +/- 0.5 4.0 +/- 0.9 4.4 +/- 0.7 3.9 +/- 0.8 08 3.5 +/- 1.0 2.9 +/- 0.7 3.7 +/- 0.7 3.9 +/- 0.3 3.5 +/- 0.9 09 6.2 +/- 0.7 4.7 +/- 0.5 5.3 +/- 0.5 6.2 +/- 0.3 5.6 +/- 1.5 10 4.5 +/- 0.7 3.7 +/- 1.7 4.1 +/- 0.5 5.1 +/- 1.1 4.4 +/- 1.2 11 2.0 +/- 0.1 2.8 +/- 0.8 2.7 +/- 0.1 2.7 +/- 0.3 2.6 +/- 0.7 12 3.8 +/- 0.8 2.8 +/- 0.7 3.5 +/- 1.2 3.8 +/- 0.8 3.5 +/- 0.9 13 3.3 +/- 1.2 3.6 +/- 0.6 3.6 +/- 0.9 3.8 +/- 0.7 3.6 +/- 0.4 14 3.4 +/- 1.4 3.2 +/- 0.2 3.8 +/- 0.6 4.2 +/- 0.3 3.7 +/- 0.9 15 4.9 +/- 0.9 3.2 +/- 0.4 4.4 +/- 0.6 4.6 +/- 0.7 4.3 +/- 1.5 16 4.3 +/- 0.2 3.2 +/- 1.0 3.4 +/- 0.2 4.6 +/- 0.4 3.9 +/- 1.4 18 2.0 +/- 0.3 2.0 +/- 0.7 2.0 +/- 2.9 2.5 +/- 0.9 2.1 +/- 0.5 19 2.7 +/- 1.0 2.1 +/- 0.3 2.9 +/- 0.3 2.8 +/- 0.5 2.6 +/- 0.7 20 2.3 +/- 1.0 2.1 +/- 0.6 2.9 +/- 1.3 2.4 +/- 1.7 2.4 +/- 0.7 21 2.8 +/- 1.6 2.1 +/- 0.4 2.9 +/- 0.5 2.9 +/- 1.2 2.7 +/- 0.8 22 1.4 +/- 0.4 1.7 +/- 0.4 1.9 +/- 0.5 2.2 +/- 1.8 1.8 +/- 0.7 23 4.5 +/- 0.3 3.1 +/- 0.7 3.8 +/- 0.9 4.1 +/- 1.8 .3.9 +/- 1.2 24 2.7 +/- 1.5 3.1 +/- 0.8 2.8 +/- 0.5 3.1 +/- 0.5 2.9 +/- 0.4 25 2.7 +/- 0.4 2.5 +/- 0.4 3.6 +/- 0.4 4.3 +/- 2.0 3.3 +/- 1.7 26 4.1 +/- 1.1 2.8 +/- 0.2 3.9 +/- 0.4 4.0 +/- 1.0 3.7 +/- 1.2 27 2.2 +/- 0.4 2.2 +/- 0.4 2.5 +/- 0.8 2.9 +/- 0.2 2.5 +/- 0.7 28 2.3 +/- 0.4 1.8 +/- 0.4 2.7 +/- 0.8 2.8 +/- 0.4 2.4 +/- 0.9 29 2.0 +/- 0.9 1.6 +/- 0.2 2.3 +/- 0.4 2.1 +/- 0.3 2.0 +/- 0.6 30 2.2 +/- 1.1 1.7 +/- 0.3 2.6 +/- 0.4 2.7 +/- 0.3 2.3 +/- 0.9 31 1.2 +/- 0.3 1.5 +/- 0.4 2.1 +/- 0.9 2.5 +/- 0.4 1.8 +/- 1.2 32 2.4 +/- 0.7 2.3 +/- 0.8 2.7 +/- 1.2 2.3 +/- 0.1 2.4 +/- 0.4 33 3.5 +/- 0.3 2.5 +/- 0.3 3.0 +/- 0.6 3.0 +/- 0.4 3.0 +/- 0.8 34 2.5 +/- 0.6 2.4 +/- 0.4 2.8 +/- 0.5 3.3 +/- 0.6 2.8 +/- 0.8 35 4.7 +/- 1.2 3.2 +/- 0.4 3.7 +/- 0.6 4.0 +/- 0.6 3.9 +/- 1.3 36 3.2 +/- 0.3 3.5 +/- 0.8 3.7 +/- 0.2 5.1 +/- 0.3 3.9 +/- 1.7 37 3.0 +/- 1.7 2.4 +/- 0.9 3.1 +/- 0.7 3.2 +/- 0.5 2.9 +/- 0.7 38 4.7 +/- 0.4 4.5 +/- 0.4 4.9 +/- 1.0 6.0 +/- 2.4 5.0 +/- 1.3 39-C 2.3 +/- 1.3 1.8 +/- 0.5 2.7 +/- 0.4 3.0 +/- 1.0 2.5 +/- 1.0 40-C 3.8 +/- 0.6 2.6 +/- 0.9 3.1 +/- 0.9 3.6 +/- 0.9 3.3 +/- 1.1 41 -C 5.5 +/- 1.5 4.4 +/- 0.3 5.6 +/- 1.4 6.5 +/- 0.6 5.5 +/- 1.7 42 2.5 +/- 0.4 2.4 +/- 0.2 3.2 +/- 0.2 3.2 +/- 1.1 2.8 +/- 0.9 43 2.4 +/- 0.2 2.1 +/- 0.5 2.3 +/- 3.6 2.6 +/- 0.3 2.4 +/- 0.4 29
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!mom --- - ---- ME TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2009 1.OE-3 pCi/m3 :- 2 Sigma Page I of 2 COLLECTION SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN-C January 06 44.7 +/- 9.3 36.8 +/- 9.1 47.8 +/- 9.5 41.5 +/- 9.3 39.9 +/- 9.4 40.0 +/- 9.2 39.4 +/- 9.1 32.4 +/- 9.0 January 13 37.9 +/- 13.0 30.9 +/- 12.9 39.1 +/- 12.4 39.1 +/- 12.0 40.9 +/- 12.1 37.5 +/- 11.9 34.6 +/- 11.7 35.3 +/- 11.7 January 20 -p47.5 +/- 10.0 40.1 +/- 9.8 40.4 +/- 9.7 48.8 +/- 10.3 39.8 +/- 10.0 46.1 +/- 10.0 40.6 +/- 10.0 47.2 +/- 10.1 January 27 58.1 +/- 10.3 46.3 +/- 9.9 48.8 +/- 10.0 51.5 +/- 10.4 43.6 +/- 9.9 51.1 +/- 10.2 52.4 +/- 10.2 46.6 +/- 10.0 February 03 43.6 +/- 11.4 31.5 +/- 11.0 39.4 +/- 11.2 55.5 +/- 11.8 35.9 +/- 11.2 33.3 +/- 11.1 39.4 +/- 11.1 42.2 +/- 11.2 February 10 44.4 +/- 9.3 37.9 +/- 9.0 37.0 +/- 9.0 60.2 +/- 9.8 37.5 +/- 9.0. 46.0 +/- 9.3 43.5 +/- 9.3 44.6 +/- 9.2 February 17 36.2 +/- 11.0 31.4 +/- 10.5 36.7 +/- 10.6 38.4 +/- 11.4 26.8 +/- 10.6 35.5 +/- 10.9 29.2 +/- 10.7 32.6 +/- 10.9 February 24 33.1 +/- 11.7 30.5 +/- 11.4 30.7 +/- 11.4 45.7 +/- 12.3 26.6 +/- 11.4 33.6 +/- 11.7 39.9 +/- 11.8 33.4 +/- 11.8 March 04 35.3 +/- 11.3 30.0 +/- 10.8 29.0 +/- 10.7 39.1 +/- 11.4 28.4 +/- 10.8 31.0 +/- 10.9 28.0 +/- 10.9 28.9 +/- 11.1 March 10 47.2 +/- 12.1 47.1 +/- 11.8 34.9 +/- 11.5 54.9 +/- 12.4 33.6 +/- 11.5 48.8 +/- 12.1 38.8 +/- 11.9 43.3 +/- 11.9 March 17 31.0 +/- 9.6 26.8 +/- 9.3 30.6 +/- 9.5 38.9 +/- 10.1 25.3 +/- 9.3 32.9 +/- 9.6 30.3 +/- 9.6 39.8 +/- 9.7 March 24 37.8 +/- 13.6 26.3 +/- 13.1 31.9 +/- 13.2 39.4 +/- 13.6 34.9 +/- 13.2 36.2 +/- 13.4 29.5 +/- 13.3 35.0 +/- 13.3 March 31 23.9 +/- 9.7 19.0 +/- 9.5 26.1 +/- 9.6 31.2 +/- 9.9 24.8 +/- 9.7 29.4 +/- 9.8 24.2 +/- 9.8 22.7 +/- 9.7 Qtr. Avg. +/- 2 &d. 40.1 +/- 17.5 33.4 +/- 16.0 36.3 +/- 13.7 44.9 +/- 17.1 33.7 +/- 13.2 38.6 +/- 14.4 36.1 +/- 15.5 37.2 +/- 14.8 April 07 28.5 +/- 10.9 17.2 +/- 10.5 27.1 +/- 10.7 29.1 +/- 11.0 18.1 + 10.5 23.6 +/- 10.7 20.6 +/- 10.6 22.0 +/- 10.5 April 14 35.7 +/- 12.9 33.4 +/- 12.8 38.7 +/- 12.9 40.5 +/- 13.6 25.7 +/- 12.7 34.6 +/- 13.2 28.6 +/- 13.0 31.9 +/- 12.9 April 21 34.8 +/- 11.5 27.5 +/- 11.2 37.4 +/- 11.3 34.8 +/- 11.8 28.1 +/- 11.2 33.1 +/- 11.4 29.4 +/- 11.4 29.1 +/- 11.4 April 28 35.2 +/- 12.5 28.4 +/- 12.0 41.0 +/- 12.3 40.6 +/- 12.8 35.2 +/- 12.1 38.0 +/- 12.2 34.1 +/- 12.3 35.4 +/- 12.4 May 05 30.2 +/- 10.4 27.8 +/- 10.1 40.6 +/- 10.4 34.6 +/- 10.7 25.7 +/- 10.1 33.3 +/- 10.3 28.3 +/- 10.3 26.9 +/- 10.1 May 12 19.9 +/- 10.1 17.4 +/- 9.8 22.1 +/- 9.9 25.2 +/- 10.4 17.5 +/- 9.8 17.3 +/- 9.9 18.3 +/- 10.0 20.6 +/- 9.9 May 19 29.3 +/- 3.4 26.2 +/- 3.2 33.5 +/- 3.7 31.8 +/- 3.7 26.2 +/- 3.2 27.1 +/- 3.4 26.4 +/- 3.3 27.3 +/- 3.3 May 26 15.7 +/- 9.9 13.6 +/- 9.9 17.5 +/- 9.9 16.5 +/- 10.4 13.3 +/- 9.9 13.0 +/- 10.0 14.3 +/- 10.1 11.6 +/- 9.9 June 02 19.4 +/- 10.6 15.4 +/- 10.5 25.2 +/- 10.6 23.1 +/- 11.0 20.0 +/- 10.6 16.7 +/- 10.6 18.8 +/- 10.6 17.3 +/- 10.5 June 08 22.4 +/- 12.0 21.0 +/- 11.9 31.4 +/- 12.2 29.8 +/- 12.6 21.4 +/- 11.7 27.0 +/- 12.1 23.4 +/- 12.1 22.6 +/- 12.2 June 16 25.1 +/- 10.5 19.7 +/- 10.3 31.3 +/- 10.6 23.9 +/- 10.7 17.5 +/- 10.2 20.1 +/- 10.3 20.0 +/- 10.2 21.6 +/- 10.0 June 22 21.3 +/- 14.0 18.5 +/- 14.0 37.1 +/- 14.4 32.8 +/- 14.9 21.2 +/- 13.9 24.0 +/- 14.2 23.5 +/- 14.1 20.8 +/- 14.0 June 30 27.9 +/- 8.3 23.6 +/- 8.3 40.9 +/- 8.8 35.3 +/- 8.9 24.7 +/- 8.3 30.4 +/- 8.4 26.7 +/- 8.4 28.4 +/- 8.3 Qtr. Avg. +/- 2 s.d. 26.6 +/- 13.1 22.3 +/- 12.0 32.6 +/- 15.4 30.6 +/- 14.0 22.7 +/- 11.5 26.0 +/- 15.5 24.0 +/- 11.0 24.3 +/- 12.8 30
TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2009 1.0E-3 pCi/m3 4- 2 Sigma Page 2 of 2 COLLECTION SS SAMPLING LOCATIONS DATE 55HIR BC ALL CP BASF FE NN-C July 07 11.4 +/- 2.8 10.6 +/- 2.8 13.4 +/- 2.9 15.7 +/- 3.1 10.1 -+ 2.7 14.7 +/- 3.0 13.5 +/- 2.9 12.4 - 2.8 July 14 12.3 +/- 2.8 10.7 +/- 2.7 11.3 +/- 2.8 13.0 +/- 2.9 11.5 -+ 2.8 13.4 +/- 2.9 10.3 +/- 2.7 11.1 - 2.8 July 21 16.2 +/- 3.7 12.4 +/- 3.5 17.4 +/- 3.8 25.7 +/- 4.2 17.8 -+ 3.8 18.3 +/- 3.8 16.1 +/- 3.8 18.9 - 3.8 July 28 22.8 +/- 3.8 15.9 +/- 3.5 26.4 +/- 3.9 21.7 +/- 3.8 22.1 -+ 3.7 15.6 +/- 3.5 18.8 +/- 3.7 20.7 - 3.7 August 03 10.8 +/- 3.8 11.3 +/- 3.8 23.9 +/- 4.5 12.3 +/- 4.0 7.7 +/- 3.6 15.2 +/- 4.0 12.4 +/- 3.9 20.9 - 4.3 August 11 20.4 +/- 3.6 15.1 +/- 3.4 26.8 +/- 3.9 18.9 +/- 3.6 14.1 +/- 3.4 22.0 +/- 3.7 19.8 +/- 3.6 20.8 - 3.6 August 18 17.7 +/- 3.1 14.0 +/- 2.9 26.0 +/- 3.5 16.7 +/- 3.1 18.5 +/- 3.1 13.9 +/- 2.9 17.1 +/- 3.1 16.7 - 3.0 August 25 13.6 +/- 3.5 14.5 +/- 3.5 15.9 +/- 3.6 16.7 +/- 3.7 12.3 +/- 3.4 15.2 +/- 3.5 13.4 +/- 3.5 12.1 - 3.3 September 01 21.5 +/- 3.6 20.9 +/- 3.6 28.0 +/- 3.9 22.3 +/- 3.7 18.1 -+ 3.4 23.1 +/- 3.7 20.6 +/- 3.6 17.9 - 3.4 September 09 19.1 +/- 3.1 16.7 +/- 3.0 22.9 +/- 3.3 19.9 +/- 3.3 21.1 -+ 3.2 16.3 +/- 3.0 21.1 +/- 3.3 15.1 - 3.0 September 15 13.2 +/- 3.8 12.1 +/- 3.8 20.0 +/- 4.2 16.7 +/- 4.2 14.4 -+ 3.9 14.3 +/- 4.0 15.9 +/- 4.1 19.9 - 4.2 September 22 14.9 +/- 3.5 17.5 +/- 3.6 23.3 +/- 3.8 22.1 +/- 3.8 16.6 -+ 3.4 19.6 +/- 3.6 19.4 +/- 3.6 16.0 - 3.5 September 29 8.2 +/- 3.3 9.5 +/- 3.3 13.6 +/- 3.6 10.6 +/- 3.5 9.4 -+ 3.3 12.8 +/- 3.5 11.2 +/- 3.5 10.3 - 3.4 Qtr. Avg. +/- 2 &d. 15.5 +/- 9.0 13.9 +/- 6.5 20.7 +/- 11.5 17.9 +/- 8.9 14.9 +/- 9.1 16.5 +/- 6.6 16.1 +/- 7.4 16.4 +/- 7.8 October 06 16.8 +/- 3.7 12.7 +/- 3.5 14.7 +/- 3.7 16.1 +/- 3.8 11.4 +/- 3.4 14.2 +/- 3.5 17.0 +/- 3.7 12.1 +/- 3.4 October 13 18.0 +/- 3.7 14.8 +/- 3.4 15.2 +/- 3.6 14.4 +/- 3.6 18.7 +/- 3.6 16.0 +/- 3.5 15.0 +/- 3.5 14.7 +/- 3.5 October 20 10.5 +/- 2.8 7.9 +/- 2.6 9.3 +/- 2.7 8.2 +/- 2.6 8.3 +/- 2.6 7.1 +/- 2.5 8.5 +/- 2.6 10.1 +/- 2.7 October 27 17.3 +/- 3.5 15.9 +/- 3.4 15.1 +/- 3.5 21.2 +/- 3.8 18.5 +/- 3.6 19.2 +/- 3.6 20.0 +/- 3.7 16.4 +/- 3.5 November 03 7.8 +/- 2.5 9.7 +/- 2.6 11.6 +/- 2.8 11.5 +/- 2.8 10.3 +/- 2.6 10.1 +/- 2.6 13.2 +/- 2.8 11.1 - 2.7 November 10 25.3 +/- 3.3 18.5 +/- 3.0 22.1 +/- 3.3 26.4 +/- 3.5 22.0 +/- 3.1 20.9 +/- 3.1 22.5 +/- 3.2 20.4 - 3.1 November 17 14.9 +/- 3.3 20.6 +/- 8.2 15.9 +/- 3.4 17.2 +/- 3.5 13.1 +/- 3.2 24.4 +/- 3.7 14.8 +/- 3.3 15.7 - 3.3 November 24 21.4 +/- 3.2 16.1 +/- 3.1 14.6 +/- 3.0 17.6 +/- 3.1 17.3 +/- 3.0 15.4 +/- 2.9 15.0 +/- 2.9 15.9 - 2.9 December 01 16.1 +/- 3.5 9.6 +/- 3.3 10.6 +/- 3.3 12.6 +/- 3.4 10.7 +/- 3.2 9.6 +/- 3.2 11.2 +/- 3.3 14.3 - 3.4 December 08 18.1 +/- 3.6 10.1 +/- 3.3 15.1 +/- 3.6 11.2 +/- 3.4 12.9 +/- 3.3 17.1 +/- 3.6 10.2 +/- 3.3 10.8 - 3.2 December 15 17.0 +/- 3.0 14.9 +/- 3.0 18.9 +/- 3.2 18.4 +/- 3.2 13.8 +/- 2.8 17.7 7 3.1 15.3 +/- 3.0 15.3 - 2.9 December 22 20.5 +/- 3.4 16.2 +/- 3.3 19.8 +/- 3.5 22.2 +/- 3.6 20.4 +/- 3.4 19.5 +/- 3.4 17.8 +/- 3.4 21.0 - 3.5 December 28 11.9 +/- 3.7 10.6 +/- 3.7 13.4 +/- 3.9 12.7 +/- 3.8 10.0 +/- 3.6 11.1 - 3.7 12.4 +/- 3.8 15.4 - 3.9 Qtr. Avg. +/- 2 s.d. 16.6 +/- 9.3 13.7 +/- 7.8 15.1 - 7.2 16.1 +/- 10.2 14.4 +/- 8.9 15.6 +/- 10.0 14.8 +/- 7.8 14.9 +/- 6.7 Aknn. Avg. + 2 &d. 24.7 +/- 23.4 20.8 +/- 19.6 26.2 - 21.1 27.4 +/- 26.5 21.4 +/- 18.9 24.2 +/- 22.1 22.8 +/- 20.1 23.2 +/- 20.9 31
TABLE 3-4: IODINE-131 CONCENTRA TION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2009 1.OE-3 pCi/m3 4 2 Sigma Page 1 of 2 COLLECTIONI SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN-C January 06 -3.2 + 7.2 -1.2 + 7.1 1.1 +/- 7.8 5.6 + 7.5 5.6 +/- 8.3 -4.2 +/- 6.9 0.9 +/- 5.5 0.0 + 4.7 January 13 3.4 + 5.8 -0.7+ 4.9 1.4 +/- 5.6 0.0 + 5.1 6.0 +/- 6.7 0.4 +/- 4.6 2.0 +/- 4.9 -4.0 + 5.5 January 20 1.1 + 4.7 -1.2 + 4.6 -2.3 +/- 3.1 -0.5 + 4.5 1.2 +/- 6.9 0.4 +/- 4.6 5.2 +/- 5.0 -6.8 + 4.7 January 27 1.4 + 4.9 -0.9+ 4.7 1.6 +/- 4.2 2.0 + 5.5 -5.2 +/- 7.0 1.2 +/- 4.9 -4.1 +/- 5.9 1.5 + 5.2 February 03 -0.5 + 5.3 4.7+ 5.1 1.4 +/- 5.3 0.7 + 5.9 0.9 +/- 4.9 0.1 +/- 3.9 -0.3 + 4.8 5.5 + 6.8 February 10 -1.9 + 6.4 -2.1 + 6.9 1.5 +/- 3.9 -2.0 + 6.1 -2.2 +/- 4.4 0.2 +/- 4.2 -3.4 +4.7 -1.6 + 3.6 February 17 -0.6 + 6.9 1.5+ 5.2 3.0 +/- 7.4 5.0 + 6.9 -3.3 +/- 5.7 -0.5 +/- 5.5 1.2 +6.1 4.2+ 4.9 February 24 0.6 + 4.4 -0.7+ 4.2 -2.7 +/- 5.8 -5.4 + 5.4 0.1 +/- 4.5 0.3 +/- 4.5 -0.5 +4.2 -2.6 + 4.5 March 04 -8.6 + 7.4 0.1+ 6.4 -0.8 +/- 6.5 4.7 5.0 2.2 +/- 5.2 -1.8 +/- 7.8 2.4 + 8.6 -1.8 + 5.4 March 10 -0.3 + 4.5 -6.4+ 7.1 -1.3 +/- 5.4 8.3 8.9 0.3 +/- 5.3 0.9 +/- 5.9 -2.5 + 5.9 -0.8 + 7.5 March 17 12.2 + 22.3 12.3 + 13.3 -0.9 +/- 15.6 3.9 16.7 -6.9 +/- 14.0 2.2 +/- 12.6 -4.1 + 16.0 10.0 + 18.2 March 24 -7.9 + 18.1 0.6+ 15.2 -10.1 +/- 12.0 0.9 14.7 13.2 +/- 12.7 11.8 +/- 16.4 0.9 + 15.6 -0.7 + 10.4 March 31 9.2 + 7.2 1.2+ 5.2 -1.4 +/- 4.7 2.7 4.2 -3.4 +/- 7.7 8.8 +/- 7.3 -6.8 +6.5 -1.1 + 4.9 April 07 0.0 + 4.7 1.4+ 5.4 -0.7 +/- 4.4 -2.7 4.6 -0.9 +/- 5.0 0.6 +/- 6.3 0.1 + 7.0 3.4+ 4.2 April 14 0.6 + 6.1 -0.5+ 4.1 -2.0 +/- 5.2 6.1 4.1 0.3 +/- 4.1 3.9 +/- 7.0 -3.1 + 4.9 -0.4 + 5.7 April 21 0.8 + 5.5 2.1+ 5.3 0.7 +/- 4.2 0.9 4.4 -0.5 +/- 4.3 -3.1 +/- 6.4 7.4 + 6.4 4.3+ 4.2 April 28 -4.5 + 6.0 1.0+ 4.7 1.1 +/- 4.3 0.8 6.2 -4.8 +/- 5.6 -1.2 +/- 3.9 1.1 +/- 3.7 -2.2 + 7.2 May 05 2.9 + 5.0 0.2+ 6.5 0.5 +/- 6.4 3.9 5.1 5.5 +/- 6.5 3.1 +/- 5.4 4.0 + 4.9 3.2+ 4.6 May 12 0.4 + 7.2 -0.4+ 5.3 -1.6 +/- 5.2 2.9 5.9 1.8 +/- 8.1 -1.8 +/- 4.4 2.2 + 6.6 -3.5 + 4.4 May 19 -0.5 + 4.3 1.4+ 4.5 -1.2 +/- 4.7 -3.1 4.8 5.4 +/- 5.9 -2.7 +/- 7.5 -3.6 +4.1 -2.5 + 4.0 May 26 2.0 + 4.6 2.2 +/- 8.3 2.0 +/- 4.4 1.7 7.2 -0.2 +/- 5.5 1.5 +/- 7.8 1.4 + 4.8 -1.4 + 5.0 June 02 -1.5 + 6.8 -3.7 +/- 4.4 -2.4 +/- 4.8 0.2 4.6 -4.8 +/- 5.7 -6.0 +/- 5.3 -2.5 +6.3 -2.3 + 6.1 June. 08 -10.8 + 7.1 -5.9 +/- 5.2 -1.8 +/- 4.7 -1.0 5.6 -3.2 +/- 8.1 4.0 +/- 7.3 0.9 + 5.5 2.6+ 4.8 June 16 0.3 + 4.7 -1.4 + 4.0 9.0 +/- 6.0 2.5 6.4 -4.0 +/- 4.4 -2.6 +/- 4.2 2.1 + 3.8 -1.4 + 3.9 June 22 -0.8 + 6.6 -2.4 + 5.0 2.1 +/- 7.1 4.6 5.3 1.6 +/- 4.2 0.0 +/- 7.2 2.2 +/- 6.1 -1.1 + 4.8 June 30 0.4 + 6.5 -1.2 + 4.3 -2.5 +/- 6.5 5.5 3.9 -0.2 +/- 4.9 -0.4 +/- 5.0 -1.8 +/- 5.6 0.8+ 3.8 32
TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2009 1.OE-3 pCi/m3 - 2 Sigma Page 2 of 2 COLLECTION SAMPLING LOCATIONS
- DATE SS HIR BC ALL CP BASF FE NN-C July 07 -2.5 +/- 14.9 -2.5 +/- 14.8 -2.5 +/- 14.8 -1.9 +/- 11.5 -5.2 +/- 17.4 -5.1 +/- 17.3 -5.2 +/- 17.4 -2.1 + 7.2 July 14 -6.0 +/- 27.9 -6.0 +/- 27.6 -6.0 +/- 27.6 -6.2 +/- 28.9 -13.2 +/- 20.5 -13.4 +/- 20.8 -13.4 +/- 20.8 -13.1 +/- 20.4 July 21 -37.7 +/- 24.1 -37.5 + 24.0 -37.4 +/- 23.9 -39.2 +/- 25.1 19.3 +/- 36.3 19.5 +/- 36.7 19.5 +/- 36.7 3.9 + 42.7 July 28 -8.6 +/- 15.8 -8.6 +/-15.7 -8.7 +/- 15.9 -8.9 +/- 16.3 -6.6 +/- 18.6 -6.7 +/- 18.7 -6.7 +/- 19.0 -6.6 + 18.5 August 03 -2.9 +/- 16.3 -2.9 + 16.1 -2.9 +/- 16.6 -3.0 +/- 16.8 -13.2 +/- 21.0 -13.2 +/- 21.1 -13.4 +/- 21.3 -13.2 + 21.0 August 11 -6.2 +/- 19.1 -6.1 + 18.9 -6.2 +/- 19.4 -6.4 +/- 19.7 -9.7 +/- 31.7 -9.7 +/- 31.7 -9.7 +/- 31.7 -9.7 + 31.5 August 18 -4.6 +/- 12.9 -4.6 +/- 12.7 -4.7 +/- 13.1 -4.7 +/- 13.2 -4.0 +/- 15.9 -4.0 +/- 16.1 -4.1 +/- 16.2 -4.0 + 15.9 August 25 7.3 +/- 13.8 7.2 + 13.6 7.4 +/- 14.0 7.5 +/- 14.2 -0.3 +/- 12.2 -0.3 +/- 12.3 -0.3 - 12.4 -0.3_+12.1 September 01 -0.2 +/- 9.2 -0.2 +/-+9.1 -0.2 +/- 9.4 -0.2 +/- 9.5 -1.6 +/- 10.5 -1.6 +/- 10.6 -1.6 +/- 10.8 -1.5 + 10.5 September 09 1.6 +/- 26.2 1.6 +/- 26.5 1.7 +/- 27.7 1.7 +/- 28.4 -4.7 +/- 30.8 -4.8 +/- 31.1 -4.8 +/- 31.5 -4.7_+30.5 September 15 -13.5 +/- 25.9 -13.5 +/- 26.0 -14.2 +/- 27.3 *-14.6 +/- 28.2 7.9 +/- 14.3 8.0 +/- 14.4 8.1+/- 14.7 7.8 + 14.2 September 22 -6.4 +/- 29.3 -6.3 +/- 28.9 -6.2 +/- 28.8 -6.4 +/- 29.4 '-1.5-+/- 25.7 -1.5 +/- 26.0 -1.5 - 26.2 -1.5 + 26.0 September 29 -11.6 +/- 15.0 -11.4 +/-+14.8 -11.6 +/- 15.0 -11.9 +/- 15.4 -0.4 +/- 13.8 -0.4 +/- 13.9 -0.4 +/- 14.1 -0.4 + 13.8 October 06 -4.8 +/- 25.8 -4.7 +/- 25.4 -4.9 +/- 26.2 -4.9 +/- 26.4 6.4 +/- 22.6 6.4 +/- 22.5 6.5_+/-22.8 6.3 + 22.1 October 13 3.0 +/- 22.3 3.0 +/- 21.7 3.0 +/- 22.4 3.1 +/- 22.7 -0.4 +/- 19.7 -0.4 +/- 19.8 -0.4 +/- 20.1 -0.4 + 19.9 October 20 -12.1 +/- 32.7 -11.8
- 31.9 -12.3 _ 33.2 -12.2 + 33.0 0.1 +/- 39.8 0.1 +/- 39.9 0.1_+/-40.4 0.1_+39.5 October 27 1.9 +/- 20.4 1.9
- 20.1 2.0 _ 20.8 2.0 _ 20.9 -12.7 +/- 32.8 -12.8 +/- 33.2 -12.8 +/- 33.3 -12.5 + 32.4 November 03 2.7 +/- 35.8 2.7 +/- 35.3 2.7_+36.6 2.8 _ 36.7 -53.5 +/- 45.0 -53.9 +/- 45.4 -54.4 +/- 45.8 -53.6 + 45.1 November 10 10.2 +/- 28.8 10.0 +/- 28.2 10.6 _ 29.7 10.5 _ 29.4 9.0 +/- 33.1 9.0 +/- 33.2 9.2_+/-33.6 9.2_+33.7 November 17 -1.0 +/- 22.5 28.7 +/- 41.1 -1.0 _ 22.8 -1.0 _ 22.9 8.4 +/- 15.2 8.4 +/- 15.4 8.5_+/-15.5 8.3 + 15.2 November 24 -2.3 +/- 14.9 -2.5 +/- 15.7 -2.4 _ 15.3 -2.4 _ 15.3 3.1 +/- 18.1 3.1 +/- 18.2 3.1_+/-18.4 3.1_+18.1 December 01 6.5 +/- 33.7 6.7 +/- 34.3 6.7_+34.3 6.7 +/- 34.4 0.4 +/- 44.1 0.4 +/- 44.2 0.5_+/-44.7 0.4 + 43.8 December 08 16.0 +/- 21.8 16.2 +/- 22.1 16.4 _ 22.4 16:5 _ 22.5 3.6 +/- 14.2 3.7 +/- 14.6 3.6_+/-14.4 3.5 + 14.0 December 15 10.1 +/- 17.0 10.4 +/- 17.5 10.4 _ 17.5 10.6 +/-+17.8 9.0 +/- 17.9 9.2 +/- 18.3 9.1_+/-18.1 '9.0
. + 17.9 December 22 -3.6 +/- 17.9 -3.7 +/- 18.4 -3.8 _ 18.7 -3.8 +/- 18.7 4.2 +/- 27.6 4.2 +/- 28.0 4.2_+/-27.9 4.2 + 28.0 December 28 0.4 +/- 21.7 0.4 +/- 22.2 0.4 _ 22.1 0.4 _ 22.1 -13.7 +/- 37.7 -13.7 +/- 37.8 -13.9 _ 38.3 -13.8 + 38.0 33
TABLE 3-5: GAMMA EMITTER CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2009 1.OE-3 pCi/m3 = 2 Sigma Page 1 of 1 SAMPLING FIRST SECOND THIRD FOURTH AVERAGE LOCATIONS NUCLIDE QUARTER QUARTER QUARTER QUARTER +/-2 SIGMA SS Cs-134 -0.04 + 0.15 0.19 + 0.20 0.00 + 0.71 3.22 +* 1.77
+/- +_ _+
Cs-1 37 -0.10 0.14 -0.12 0.21 -0.57 0.65 -0.06 1.23
+ +_ +_
Be-7 139 14.8 149 16.1 194 30.2 124 38.2 152 +/- 60
+
+
+ +
HIR Cs-1 34 -0.04 0.16 0.21 0.23 0.26 + 0.88 -0.27 0.93
+ +/- J+/-
Cs-1 37 0.08 0.13 0.11 0.22 0.62 0.74 -0.46 0.99
+ 4., +
Be-7 112 12.6 118 (13.7 139 35.4 118 38.6 122 +/- 24 BC Cs-134 -0.03 + 0.15 -0.12 +/- 0.24 -0.42 + 1.03 1.98 +/- 1.55 Cs-1 37 0.14 + 0.12 0.21 +/- 0.18 -0.79 + 1.00 -0.15 +/- 1.20 Be-7 118 + 12.7 181 +/- 19.2 190 + 39.9 119 +/- 30.4 152 +/- 78 ALL Cs-1 34 0.00 + 0.19 -0.06 +/- 0.24 0.74 +/- 1.28 1.09 +/- 1.30
_+ + +
Cs-1 37 0.03 0.13 0.00 0.21 -0.41 1.25 -0.71 +/- 1.21
+9 + +
Be-7 153 15.1 177 18.9 197 42.4 134 +/- 42.5 165 +/- 55 CP Cs-1 34 0.16 + 0.18 0.11 +/- 0.23 -0.03 + 0.79 0.46 +/- 1.16 Cs-1 37 -0.21 + 0.18 -0.07 +/- 0.17 0.38 + 0.69 0.04 +/- 0.86 Be-7 106 + 11.9 145 +/- 14.8 153 + 32.0 164 +/- 34.5 142 +/- 50 BASF Cs-1 34 -0.07 + 0.17 -0.10 +/- 0.23 0.36 + 0.94 -0.43 +/- 0.97 Cs-1 37 0.02 + 0.13 -0.01 +/- 0.19 -0.04 + 0.62 0.59 +/- 0.91 Be-7 114 + 12.2 158 +/- 16.9 151 + 36.2 110 +/- 33.0 133 +/- 50 FE Cs-134 0.01 +/- 0.22 -0.02 _+ 0.18 1.60 + 1.35 -1.35 _+ 0.90
+
1.14 + 0.69 Cs-137 0.04 0.14 0.07 + 0.15 0.47 0.56 4+/- _+ 40.5 +
Be-7 114 13.7 147 15.6 174 126 29.6 140 +/- 53 NN-C Cs-1 34 -0.02 . 0.18 0.12 +/- 0.23 0.40 +/- 1.04 0.12 +/- 1.26 Cs-137 0.03 . 0.13 -0.02 +/- 0.20 0.00 +/- 0.95 0.60 +/- 1.09 Be-7 114 . 13.5 151 +/- 15.9 127 +/- 36.5 164 +/- 34.4 139 +/- 45 34
TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Power Station, Surry County, Virginia - 2009 pCi/Liter +/- 2 Sigma Page 1 of 3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C JANUARY Cs-1 34 0.85 1.22 0.00 1.34 -1.61 2.04 Cs-I 37 0.91 1.09 -0.46 1.66 0.37 2.38 Ba-140 0.64 3.95 2.49 5.31 -0.60 5.89 La-140 0.16 1.32 -1.90 1.76 -0.40 1.86 1-131 -0.07 0.32 0.17 0.41 0.31 0.40 K-40 1440 96.5 1470 107 1370 122 FEBRUARY Cs-1 34 0.83 1.58 -0.09 1.56 -0.06 2.09 Cs-137 0.51 1.30 0.31 1.35 -1.05 1.41 Ba-I 40 1.72 4.33 -0.34 4.69 -2.06 5.43 La-I 40 -0.62 1.43 0.16 1.70 -0.09 1.61 1-131 -0.15 0.26 -0.05 0.29 0.01 0.23 K-40 1410 107 1510 126 1400 113 MARCH Cs-134 -0.05 1.34 2.98 1.62 -0.42 1.86 Cs-137 0.02 1.17 0.45 1.34 -0.15 1.27 Ba-140 2.59 4.74 -2.68 6.07 4.28 5.42 La-140 -0.47 1.47 -0.90 1.68 0.30 1.72 1-131 0.29 0.37 0.11 0.24 0.32 0.25 K-40 1420 120 1510 121 1340 101 Sr-89 0.01 0.71 Sr-90 0.74 0.40 APRIL Cs-i 34 0.15 1.75 1.09 + 1.55 -0.04 1.68
+ 1.44 1.88 1.49 Cs-I 37 0.31 1.54 0.02 6.08 4.41 + 5.56 1.42 5.56 Ba-i 40 6.19
+.
La-i 40 0.02 1.71 0.40 1.59 0.96 1.56 1-131 -0.18 0.25 0.10 + 0.30 0.05 0.28 K-40 1410 124 1510 + 116 1400 111 35
TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surny Power Station, Surry County, Virginia - 2009 pCi/Liter +/- 2 Sigma Page 2 of 3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C MAY Cs-1 34 -0.01 1.40 0.52 1.35 1.05 1.61 Cs-1 37 -0.07 1.53 0.94 1.23 0.48 1.30 Ba-1 40 2.51 4.87 0.82 4.46 1.68 5.02 La-1 40 -0.51 1.29 -0.30 1.43 -1.55 1.83 1-131 0.20 0.45 0.09 0.24 -0.11 0.20 K-40 1410 109 1490 113 1420 119 JUNE Cs-1 34 0.67 1.64 -0.86 1.75 -0.89 2.17 Cs-137 1.16 1.42 0.42 1.50 0.58 3.05 Ba-140 -1.40 5.39 -0.76 5.98 1.50 4.93 La-140 -0.27 1.71 -1.79 1.69 -0.52 1.54 1-131 0.53 0.36 0.02 0.41 -0.10 0.37 K-40 1290 109 1450 115 1390 121 Sr-89 -0.47 0.81 Sr-90 -0.01 0.69 JULY Cs-1 34 0.86 1.32 -0.80 0.79 -0.14 1.21 Cs-137 1.76 1.29 0.67 0.90 0.40 1.08 Ba-140 -0.37 9.63 -3.12 6.40 2.60 8.70 La-140 -1.31 2.63 -0.60 1.59 -1.45 2.33 1-131 0.07 0.39 0.06 0.43 0.14 0.38 K-40 1230 52.9 1300 56.2 1250 52.8 AUGUST Cs-1 34 -1.72 3.90 0.39 3.78 -5.79 4.21 Cs-1 37 0.71 4.24 3.24 3.49 -0.47 3.66 Ba-1 40 -9.66 19.3 7.05 15.5 -8.04 18.4 La-140 -1.43 4.53 -1.06 4.74 2.47 6.04 1-131 0.14 0.49 0.29 0.31 0.16 0.55 K-40 1220 140 1290 124 1270 143 36
TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Power Station, Surry County, Virginia - 2009 pCi/Liter A-2 Sigma Page 3 of 3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C SEPTEMBER Cs-1 34 -2.67 2.76 -3.43 + 4.35 1.07 + 3.32
+ +
Cs-1 37 1.71 3.01 -0.52 3.99 -3.29 3.27
+ +
Ba-1 40 7.76 + 13.5 2.94 20.2 -0.33 18.3
+ +
La-1 40 -2.70 -+ 4.53 0.45 4.48 -0.72 5.81
+ _+
1-131 -0.08 -+ 0.42 -0.10 0.40 -0.11 0.35
+ _+
K-40 1250 110 1260 144 1230 132
+
Th-228 13.0 9.95 Sr-89 1.31 +/- 2.59 Sr-90 1.12 +/- 0.68 OCTOBER Cs-1 34 0.45 -+ 2.28 -1.00 3.74 2.58 + 2.85
+l +{
Cs-1 37 1.51 2.11 -1.63 3.93 1.36 + 3.22
+
Ba-1 40 -10.1 8.88 1.66 18.3 -7.80 + 15.7
_+
La-1 40 -0.45 2.83 3.36 4.70 -0.97 + 3.72 1-131 0.10 0.14 0.06 0.35 -0.15 + 0.40 K-40 1230 86.5 1370 143 1150 129
+
NOVEMBER Cs-134 2.17 4.11 -2.20 4.52 -0.43 + 4.09 Cs-1 37 -0.93 4.57 -0.36 4.03 1.38 + 4.07 Ba-140 -8.26 23.1 -13.1 21.7 -4.37 + 21.7 La-140 1.28 7.38 -0.92 6.51 -1.40 + 6.88 1-131 0.18 0.45 0.03 0.43 0.12 _+ 0.41 K-40 1300 171 1300 146 1240 147
+
+ +
-+
DECEMBER Cs-1 34 1.40 4.96 -4.05 + 4.41 1.00 + 3.84 Cs-137 -3.61 4.38 2.60 4.01 -0.07 + 4.00 Ba-140 -1.41 19.7 3.04 18.9 -3.00 + 19.9 J
La-140 3.45 5.77 1.37 5.46 -1.42 _+ 5.08 1-131 0.06 0.21 0.00 0.18 0.02 + 0.20 K-40 1270 167 1300 141 1240 136 Sr-89 0.76 2.70 Sr-90 0.43 0.44 37
TABLE 3-7: GAMMA EMITTER CONCENTRATION IN FOODPRODUCTS Surry Power Station, Surry County, Virginia - 2009 pCi/kg (wet) +/- 2 Sigma Page 1 of I SAMPLING COLLECTION SAMPLE I LOCATIONS DATE TYPE Cs-134 Cs-137 1-131 K-40 Th-228 SLADE 11/17/2009 Corn -0.39 +/- 3.26 1.42 +/- 2.85 7.04 +/- 20.7 3190 +/- 126 10.4 +/- 7.46 FARM 11/17/2009 Soybeans -5.03 +/- 4.63 8.23 +/- 4.40 -1.79 +/- 31.5 14800 +/- 249 -1.16 +/- 7.61 BROCK 11/18/2009 Peanuts 1.33 +/- 5.19 2.33 +/- 5.12 2.37 +/- 33.2 6300 +/- 231 6.07 +/- 14.2 FARM 38
TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WA TER Surry Power Station, Surry County, Virginia - 2009 pCi/Liter- 2 Sigma Page 1 of 2 SAMPLING COLLECTIONl LOCATIONS DATE ISOTOPE Mn-54 Fe-59 Co-58 Co-60 Zn-65 SS 03/10/2009 -0.02 +/- 0.95 0.18 +/- 2.17 0.55 +/- 0.98 1.41 +/- 1.09 -0.95 +/- 2.56 06/01/2009 -0.32 +/- 1.12 1.49 +/- 1.92 0.43 +/- 1.00 0.23 +/- 1.03 0.54 +/- 2.25 09/01/2009 -0.17 +/- 1.26 1.75 +/- 3.27 0.58 +/- 1.44 0.76 +/- 1.23 0.12 +/- 3.25 12/08/2009 -0.72 +/- 1.79 -3.08 +/- 4.45 0.27 +/- 1.74 0.58 +/- 2.14 -4.21 +/- 4.22 Zr-95 Nb-95 1-131 Cs-1 34 Cs-137 03/10/2009 -0.47 +/- 1.70 -1.55 +/- 2.46 -0.02 +/- 0.26 0.07 +/- 1.19 -0.17 +/- 1.00 06/01/2009 0.93 +/- 1.83 0.30 +/- 0.99 0.06 +/- 0.27 0.18 +/- 1.31 -0.26 +/- 1.09 09/01/2009 1.41 +/- 2.60 1.92 +/- 1.48 -0.37 +/- 0.40 0.22 +/- 1.43 0.36 +/- 1.27 12/08/2009 -2.81 +/- 3.42 1.16 +/- 1.94 0.19 +/- 0.48 1.20 +/- 2.26 -1.10 +/- 1.91 Ba-140 La-140 H-3 K-40 03/10/2009 0.57 +/- 4.01 0.48 +/- 1.44 -113 +/- 284 06/01/2009 0.78 +/- 4.33 0.27 +/- 1.70 -29.1 +/- 123 09/01/2009 -7.76 +/- 15.20 3.03 +/- 4.58 277 +/- 594 37.5 + 24.0 12/08/2009 -1.90 +/- 12.60 0.50 +/- 3.98 0.00 +/- 400 Mn-54 Fe-59 Co-58 Co-60 Zn-65 HIR 03/10/2009 0.03 +/- 0.90 1.14 +/- 1.84 -0.37 +/- .0.87 0.32 +/- 0.93 -5.48 +/- 2.27 06/01/2009 -0.44 +/- 1.16 1.28 +/- 2.26 0.11 +/- 1.05 0.81 +/- 1.16 -2.71 +/- 2.51 09/01/2009 -0.03 +/- 1.26 1.17 +/- 3.37 0.85 +/- 1.48 0.73 +/- 1.31 -3.19 +/- 2.94 12/08/2009 0.23 +/- 0.55 0.45 +/- 1.94 -0.26 +/- 0.64 -0.05 +/- 0.72 0.41 +/- 1.13 Zr-95 Nb-95 1-131 Cs-l 34 Cs-1 37 03/10/2009 -0.28 +/- 1.60 -0.84 +/- 1.03 -0.04 +/- 0.30 0.37 +/- 1.15 0.05 +/- 0.98 06/01/2009 -0.51 +/- 1.90 0.12 +/- 1.15 -0.15 +/- 0.32 0.03 +/- 1.37 0.17 +/- 1.16 09/01/2009 2.44 +/- 2.68 2.29 +/- 1.55 -0.01 +/- 0.41 0.24 +/- 1.43 -0.08 +/- 1.33 12/08/2009 0.10 +/- 1.28 -0.05 +/- 0.72 0.58 +/- 0.55 0.19 +/- 0.49 -0.01 +/- 0.57 Ba -140 La-140 H-3 03/10/2009 1.71 +/- 3.95 -0.48 +/- 1.35 -2755 _
262 06/01/2009 -2.36 +/- 4.91 -0.47 +/- 1.69 143 159 09/01/2009 1.03 +/- 15.2 0.41 +/- 4.96 376 455 12/08/2009 -0.44 +/- 7.22 -1.83 +/- 2.96 442 437 39
TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WA TER Surry Power Station, Surry County, Virginia - 2009 pCi/Uter +/- 2 Sigma Page 2 of 2 SAMPLING COLLECTION/
LOCATIONS DATE ISOTOPE Mn-54 Fe-59 Co-58 Co-60 Zn-65 CS 03/10/2009 0.25 +/- 1.04 0.42 +/- 2.09 -0.31 +/- 0.98 -0.38. +/- 1.09 -1.72 +/- 2.65 06/01/2009 -0.20 +/- 1.12 -0.91 +/- 2.39 -1.65 +/- 1.17 0.57 +/- 1.21 1.58 +/- 2.67 09/01/2009 -1.33 +/- 1.17 0.47 +/- 2.87 -0.11 +/- 1.29 0.48 +/- 1.06 -1.82 +/- 2.74 12/08/2009 0.36 +/- 0.45 0.31 +/- 1.29 0.41 +/- 0.56 0.14 +/- 0.41 -0.52 +/- 0.93 Zr-95 Nb-95 1-131 Cs-134 Cs-I 37 03/10/2009 -1.06 +/- 1.69 -0.29 +/- 1.13 -0.03 + 0.20 -1.57 +/- 1.31 0.46 +/- 1.10 06/01/2009 0.79 +/- 1.98 -0.71 +/- 1.26 0.05 + 0.48 -0.53 +/- 1.37 -0.10 +/- 1.23 09/01/2009 -0.02 +/- 2.43 0.85 +/- 1.47 0.23 +/- 0.46 -0.24 +/- 1.24 0.85 +/- 1.18 12/08/2009 0.53 +/- 0.95 -0.37 +/- 0.57 0.63 + 0.54 0.01 +/- 0.41 0.18 +/- 0.47 Ba-140 La-140 H-3 Ac-228 03/10/2009 2.07 +/- 4.44 -0.52 +/- 1.43 34.5 298 06/01/2009 2.71 +/- 5.29 -0.64 +/- 1.74 -97.7 98.7 09/01/2009 -2.20 +/- 12.90 -0.73 +/- 3.86 231 438 15.4 +/- 10.4 12/08/2009 -2.96 +/- 6.34 -0.41 +/- 2.01 -115 388 40
TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WA TER Surny Power Station, Surry Couinty, Virginia - 2009 pCi/UIter +/- 2 Sigma Page 1 of 2 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE M n-54 Fe-59 Co-58 Co-60 Zn-65 SD 01/13/2009 0.05 +/- 0.90 0.07 +/- 1.76 -0.32 +/- 0.90 -0.97 + 1.64 -1.66 +/- 1.89 02/10/2009 -0.75 +/- 1.22 -1.91 +/- 2.49 -0.13 +/- 1.20 0.25 + 1.19 1.80 +/- 2.99 03/10/2009 -0.82 +/- 0.92 -0.21 +/- 1.84 0.23 +/- 0.88 0.24 + 1.02 -0.24 +/- 2.42 04/14/2009 0.37 +/- 1.12 -0.05 +/- 2.03 -0.09 +/- 1.09 0.61 + 1.24 -1.18 +/- 2.45 05/19/2009 0.28 +/- 1.21 0.99 +/- 2.48 0.09 + 1.25 0.34 + 1.30 -4.69 +/- 2.71 06/16/2009 0.43 +/- 0.94 1.60 +/- 1.93 0.15 + 0.97 0.06 + 1.06 -2.02 +/- 2.16 07/14/2009 0.15 +/- 1.57 -1.36 +/- 3.56 -0.17 + 1.49 -0.31 + 1.52 -0.43 +/- 3.74 08/25/2009 0.77 +/- 2.88 -3.08 +/- 5.99 -2.29 + 2.58 -0.62 + 3.16 0.07 +/- 6.75 09/09/2009 1.46 +/- 2.77 -0.56 +/- 5.90 -2.82 + 2.61 -2.79 + 2.78 2.06 +/- 5.48 10/13/2009 -1.92 +/- 3.03 4.53 +/- 7.69 -1.44 + 3.26 2.28 + 3.19 -11.5 +/- 7.43 11/10/2009 -1.51 +/- 3.10 -1.12 +/- 6.64 -1.05 + 3.31 -0.19 + 3.10 -0.19 +/- 7.79 12/15/2009 0.15 +/- 1.44 0.04 +/- 3.80 0.33 + 1.89 -0.02 + 1.67 -4.33 +/- 3.56 Zr-95 Nb-95 1-131 Cs-1 34 Cs-137 01/13/2009 -0.31 + 1.52 1.26 +/- 0.99 -0.61 +/- 1.37 0.11 + 1.11 -0.56 + 1.47 02/10/2009 -1.94 + 2.14 -0.15 +/- 1.63 0.58 +/- 1.71 0.55 + 1.54 0.87 + 1.30 03/10/2009 -0.25 + 2.47 0.57 +/- 1.07 -0.81 +/- 1.24 2.07 + 1.17 -0.78 + 1.05 04/14/2009 0.87 + 1.87 0.03 +/- 2.13 0.87 +/- 1.51 -0.03 + 1.37 0.15 + 1.18 05/19/2009 0.29 + 2.26 -0.14 +/- 1.36 -0.48 +/- 1.83 1.09 + 1.49 0.16 + 1.38 06/16/2009 -0.26 + 1.75 0.32 +/- 1.10 -0.32 +/- 1.43 0.60 + 1.31 0.44 + 1.07 07/14/2009 -0.53 + 3.39 -0.04. +/- 1.59 -0.59 +/- 5.50 1.41 + 1.75 -0.58 + 1.78 08/25/2009 4.40 + 5.87 0.46 +/- 3.41 -2.39 +/- 5.24 -1.10 + 3.00 1.41 + 3.57 09/09/2009 1.71 + 4.94 1.71 +/- 3.91 -1.86 +/- 4.90 1.56 + 2.76 1.06 + 3.18 10/13/2009 5.22 + 6.31 -0.41 +/-.,3.46 -1.37 +/- 6.02 -8.47 + 3.69 0.64 + 3.17 11/10/2009 -5.72 + 5.70 0.49 +/- 3.41 -0.90 +/- 5.66 -1.51 + 4.00 -0.98 + 3.62 12/15/2009 2.06 + 3.37 1.17 +/- 1.91 3.09 +/- 5.47 0.29 + 1.75 -0.83 + 1.72 Ba-140 La-140 H-3 K-40 01/13/2009 0.86 + 3.75 -0.94 +/- 1.29 02/10/2009 -2.00 + 5.00 -1.27 +/- 1.87 03/10/2009 -2.33 + 3.86 -0.42 +/- 1.17 140 + 285 75.7 +/- 25.7 04/14/2009 0.92 + 4.70 1.29 +/- 1.76 05/19/2009 -8.82 + 7.98 0.24 + 1.83 06/16/2009 -0.25 + 4.06 1.33 + 1.50 159 + 326 07/14/2009 -3.92 + 11.8 0.58 + 3.25 08/25/2009 3.12 + 13.1 -1.62 + 4.91 188 +/- 73.0 09/09/2009 10.2 + 14.0 -0.01 + 4.05 -82.7 + 999 154 +/- 44.5 10/13/2009 1.61 + 15.8 -3.35 + 5.14 136. +/- 61.6 11/10/2009 22.2 + 16.0 3.95 + 5.98 12/15/2009 -1.86 + 13.2 -0.24 + 4.13 -417 _+ 1170 41
TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WA TER Surry Power Station, Sunry County, Virginia - 2009 pCi/Liter +/- 2 Sigma Page2 of 2 SAMPLING COLLECTION1 LOCATIONS DATE ISOTOPES Mn-54 Fe-59 Co-58 Co-60 Zn-65 SW-C 01/13/2009 -0.38 + 0.82 0.16 + 1.68 -0.48 +/- 0.81 -0.03 + 0.86 -1.36 + 1.84 02/10/2009 -0.55 _+ 1.02 -2.93 + 3.57 -0.25 +/- 1.19 -0.11 + 1.13 -1.10 + 2.48 03/10/2009 -0.23 + 1.07 0.81 + 2.09 -1.70 +/- 1.38 -0.80 4. 1.23 -1.45 + 2.29 04/14/2009 0.07 + 0.89 0.04 4. 1.70 -0.34 +/- 0.86 -0.73 + 0.96 -1.85 4+ 2.02 05/19/2009 0.25 + 1.17 0.16 + 2.17 0.09 +/- 1.17 -0.82 + 1.20 -2.48 4+ 2.51 06/16/2009 0.06 + 0.73 0.75 + 1.51 0.21 +/- 0.73 0.31 + 0.84 -0.15 + 1.70 07/14/2009 0.07 _+ 0.77 -0.08 + 1.78 -0.77 +/- 0.82 0.67 4. 0.72 -1.12 + 1.82 08/25/2009 0.54 + 3.20 -6.26 + 7.76 -0.88 +/- 3.42 0.48 + 3.20 5.51 + 4.93 09/09/2009 1.93 _+ 2.76 -5.77 + 6.95 -1.99 +/- 3.03 -2.77 + 3.49 -0.68 + 7.46 10/13/2009 0.20 + 2.59 -3.19 + 6.01 0.37 +/- 2.99 1.26 + 2.94 -4.02 +_ 6.90 11/10/2009 0.21 + 3.14 -3.68 + 5.85 0.52 +/- 3.08 0.35 + 2.33 -6.61 4+ 6.98 12/15/2009 -0.08 0.36 -0.81 + 0.98 -0.19 +/- 0.44 -0.20 4. 0.38 0.06 + 0.72 Zr-95 Nb-95 -131 Cs-134 Cs-137 01/13/2009 0.42 + 1.44 -0.04 +/- 1.23 -0.17 1.13 0.65 0.99 0.09 + 0.86 02/10/2009 -1.18 4+ 2.03 -1.07 +/- 1.58 -0.88 1.45 0.32 4. 1.39 -1.53 + 1.83 03/10/2009 -0.46 + 1.91 0.91 +/- 1.13 -0.54 +{
1.41 0.02 _+ 1.30 -0.37 _+ 1.14 04/14/2009 -0.57 4+ 1.58 1.09 +/- 0.99 -0.37 +}
1.83 0.55 4+ 1;05 0.64 + 1.01 05/19/2009 0.47 2.00 -1.61 + 1.80 0.68 1.56 0.61 _+ 1.37 -1.17 _+ 1.19 06/16/2009 0.38 + 1.29 0.25 +/- 0.81 -0.26 1.12 -0.19 + 0.88 0.87 _+ 0.79 07/14/2009 -1.02 _+ 1.54 -0.03 - 0.87 1.19 +r 4.64 -0.27 + 0.83 0.23 +_ 0.77 08/25/2009 2.19 6.37 0.05 - 3.14 2.85 5.51 -2.20 _+ 3.07 -1.11 + 3.14 09/09/2009 0.32 + 5.68 0.06 +/- 3.62 3.74 5.43 -2.03 3.59 0.42 4+ 3.47 10/13/2009 2.41 +_ 4.92 0.99 + 3.12 -0.74 5.63 0.69 _+ 2.85 2.78 _+ 2.88 11/10/2009 -2.12 5.24 0.17 +/- 3.28 -1.63 5.76 -1.18 3.30 -1.75 _+ 3.00 12/15/2009 -0.08 0.73 -0.09 +/- 0.47 3.59 3.63 -0.21 0.33 -0.28 0.37 Ba-140 La-140 H-3 K-40 01/13/2009 -0.31 4. 3.42 -1.26 +/- 1.21 02/10/2009 -1.32 4.32 -0.14 +/- 1.64 03/10/2009 2.44 4.59 -0.53 +/- 1.57 -95.8 +/- 263 04/14/2009 -0.01 _+ 3.79 1.04 +/- 1.38 05/19/2009 -2.02 + 6.56 -1.01 + 1.79 06/16/2009 0.86 + 3.47 0.15 +/- 1.13 -183 +/- 302 07/14/2009 6.61 _+ 8.39 -1.01 +/- 2.70 27.2 _+ 18.1 08/25/2009 -16.8 _+ 14.5 -4.48 +/- 7.12 98.2 + 77.6 09/09/2009 10.3 13.7 -1.43 _ 4.83 -227 +/- 982 167 + 66.7 10/13/2009 8.00 _+ 15.1 1.98 +/- 5.08 108 + 69.5 11/10/2009 1.70 15.4 1.16 +/- 4.84 129 61.1 12/15/2009 0.57 5.07 -0.41 +/- 1.81 -266 +/- 1180 Th-228 Ra-226 12/15/2009" 5.52 +/- 2.47 34.6 +/- 32.9
TABLE 3-10: GAMMA EMITTER CONCENTRATIONS IN SILT Surry Power Station, Sunry County, Virginia - 2009 pCi/kg (dry) - 2 Sigma Page 1 of 1 SAMPLING COLLECTION I LOCATIONS DATE ISOTOPE I Cs-1 34 Cs-1 37 K-40 Th-232 Th-228 SD 03/10/2009 47.7 +/- 60.3 274 +/- 74.1 14000 +/- 1.760 1010 +/- 140 09/23/2009 18.0 +/- 48.3 154 +/- 97.1 15400 +/- 1640 1030 +/- 222 1150 +/- 116 Pb-212 TI-208 U-234 Th-230 Ra-226 03/10/2009 1010 +/- 140 231 +/- 75.9 644 +/- 169 644 +/- 169 644 +/- 169 09/23/2009 3740 +/- 1530 Pb-214 Bi-214 03/10/2009 874 +/- 178 644 +/- 169 09/23/2009 Cs-1 34 Cs-137 K-40 Th-232 Ra-228 CHIC-C 03/10/2009 122 +/- 63.2 182 +/- 91.8 17000 +/- 1910 1340 +/- 378 1340 +/- 378 09/23/2009 1.75 +/- 50.7 186 +/- 63.5 16100 +/- 1670 1020 +/- 164 Ac-228 Th-228 Pb-212 TI-208 Th-230 03/10/2009 1340 +/- 378 1380 +/- 167 1380 +/- 167 418 +/- 105 1310 +/- 251 09/23/2009 1210 +/- 121 Ra-226 Pb-214 Bi-214 03/10/2009 1310 +/- 251 1250 +/- 215 1310 +/- 251 09/23/2009 1560 +/- 1520 43
TABLE 3-11: GAMMA EMITTER CONCENTRATIONS IN SHORELINE SEDIMENT Surry Power Station, Surry County, Virginia - 2009 pCi/kg (dry) +/- 2 Sigma Page I of I SAMPLING COLLECTIOND LOCATIONS DATE Cs-I 34 Cs-I 37 K-40 Th-228 HIR 02/10/2009 6.23 +/- 24.0 -6.05 +/- 23.4 6180 +/- 932 08/25/2009 15.0 +/- 21.0 3.63 +/- 18.8 5290 +/- 662 CHIC-C 02/10/2009 11.3 +/- 24.0 6.60 +/- 18.1 2160 +/- 487 08/25/2009 -7.02 +/- 24.8 3.65 +/- 22.0 6120 +/- 767 103 +/- 47.6 44
TABLE 3-12: GAMMA EMITTER CONCENTRATION IN FISH Surry Power Station, Surry County, Virginia - 2009 pCi/kg (wet) - 2 Sigma Page 1 of I SAMPLING COLLECTION SAMPLE LOCATION DATE TYPE ISOTOPE K-40 Co-58 Co-60 Cs-134 SD 04/01/2009 Catfish 2060 +/- 216 -0.91 +/- 3.64 -0.69 +/- 3.84 -1.41 +/- 4.97 04/01/2009 White Perch 2230 +/- 253 -1.03 +/- 5.96 0.82 +/- 7.37 -1.20 +/- 6.69 10/07/2009 Catfish 2200 +/- 788 14.5 +/- 44.2 -15.1 +/- 34.8 32.7 +/- 46.4 10/07/2009 White Perch -3.61 +/- 42.6 0.00 +/- 0.00 -6.43 +/- 47.7 Cs-1 37 Fe-59 Mn-54 Zn-65 04/01/2009 Catfish 4.15 +/- 3.47 -8.02 +/- 10.2 1.22 +/- 3.83 -6.81 +/- 9.51 04/01/2009 White Perch 2.32 +/- 6.16 -16.6 +/- 16.6 1.48 +/- 5.82 11.6 +/- 14.3 10/07/2009 Catfish 7.89 +/- 39.5 -15.6 +/- 91.2 -12.9 +/- 36.8 -39.5 +/- 94.3 10/07/2009 White Perch -13.5 +/- 39.0 -38.9 +/- 82.0 -1.80 +/- 34.0 7.77 +/- 93.7 45
TABLE 3-13: GAMMA EMITTER CONCENTRATIONS IN OYSTERS Surry Power Station, Surry County, Virginia - 2009 pCi/kg (wet) +/- 2 Sigma Page 1 of I SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE Co-58 Co-60 Cs-1 34 Cs-137 POS 03/10/2009 -1.31 +/- 6.51 -9.40 +/- 5.98 2.76 +/- 5.41 5.41 +/- 4.47 09/23/2009 -5.16 +/- 29.5 14.3 +/- 21.6 7.03 +/- 24.8 7.31 +/- 21.1 Fe-59 Mn-54 Zn-65 K-40 03/10/2009 7.50 +/- 14.5 -5.84 +/- 4.83 -4.29 +/- 12.6 09/23/2009 -26.4 +/- 59.6 -14.4 +/- 21.6 -36.8 +/- 58.6 1050 +/- 396 Co-58 Co-60 Cs-1 34 Cs-137 MP 03/10/2009 2.81 +/- 6.19 1.61 + 3.66 -1.98 +/- 5.10 3.48 +/- 4.16 09/23/2009 -17.1 +/- 19.2 -8.10 +/- 18.3 -0.82 +/- 19.4 -12.0 +/- 17.9 Fe-59 Mn-54 Zn-65 03/10/2009 -0.69 +/- 12.9 3.70 +/- 4.09 -0.59 +/- 12.4 09/23/2009 10.3 +/- 46.1 13.9 +/- 15.5 25.7 + 41.5 46
TABLE 3-14: GAMMA EMITTER CONCENTRATIONS IN CLAMS Surry Power Station, Surry County, Virginia - 2009 pCi/kg (wet) +/- 2 Sigma Page I of I SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE Co-58 Co-60 Cs-* 34 Cs-I 37 JI 03/10/2009 -3.72 + 6.00 0.48 +/- 5.14 -1.27 +/- 4.95 4.98 +/- 3.83 09/23/2009 -15.0 + 22.7 0.77 +/- 22.1 -11.5 +/- 23.1 -10.1 +/- 19.8 Fe-59 Mn-54 Zn-65 K-40 03/10/2009 -2.52 +/- 12.1 -1.78 +/- 4.39 -6.14 +/- 9.51 09/23/2009 -77.8 +/- 47.9 -6.37 +/- 20.5 -108 +/- 55.6 431 +/- 400 Co-58 Co-60 Cs-134 Cs-137 SD 03/10/2009 -7.63 +/- 6.41 0.03 +/- 6.39 -1.54 + 5.81 -0.64 +/- 5.34 09/23/2009 -27.6 +/- 37.9 -9.57 +/- 20.8 11.5 + 31.9 -40.2 +/- 30.0 Fe-59 Mn-54 Zn-65 03/10/2009 6.24 +/- 13.9 3.31 +/- 5.22 -2.37 +/- 10.6 09/23/2009 -0.30 +/- 85.4 -13.2 +/- 32.2 -61.4 +/- 77.8 Co-58 Co-60 Cs-134 Cs-1 37 LC 03/10/2009 5.31 +/- 6.22 -3.03 +/- 5.72 2.06 +/- 6.11 -3.21 +/- 5.36 09/23/2009 -4.08 +/- 38.5 12.4 +/- 22.6 9.05 +/- 32.6 -11.6 +/- 31.4 Fe-59 Mn-54 Zn-65 K-40 03/10/2009 -7.60 +/- 16.1 -4.57 +/- '5.98 -8.28 +/- 13.8 458 +/- 128 09/23/2009 -43.0 +/- 83.6 -9.45 +/- 31.8 -4.06 +/- 66.7 Co-58 Co-60 Cs-134 Cs-1 37 CHIC-C 03/10/2009 -1.28 +/- 7.10 0.26 +/- 7.53 2.23 +/- 6.75 2.59 +/- 5.94 09/23/2009 17.3 +/- 31.5 6.34 +/- 25.3 -9.03 +/- 26.7 -8.08 +/- 27.6 Fe-59 Mn-54 Zn-65 K-40 03/10/2009 4.84 +/- 15.8 -0.89 +/- 6.52 -3.10 +/- 13.5 09/23/2009 -56.2 +/- 66.5 -32.0 +/- 24.4 -36.0 +/- 70.7 851 +/- 514 Th-228 03/10/2009 09/23/2009 164 +/- 74.8 47
I ý, -
TABLE 3-15: GAMMA EMITTER CONCENTRATIONS IN CRABS Surry Power Station, Surry County, Virginia - 2009 pCi/kg (wet) +/- 2 Sigma Page 1 of I SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE K-40 Co-58 Co-60 Cs-1 34 SD 06/24/2009 1590 +/- 175 -1.21 +/- 3.85 -1.26 +/- 3.51 0.10 +/- 3.97 Cs-137 Fe-59 Mn-54 Zn-65
-1.84 +/- 3.97 3.02 +/- 9.45 -0.59 '+/- 3.35 -2.17 +/- 8.12 48
- 4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2009 and tabulated in Section 3, are discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the GEL Laboratories LLC and the Teledyne Brown Engineering quality assurance manuals and laboratory procedures. In addition to internal quality control measures performed by the laboratories, they also participate in an 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 Interlaboratory Comparison Program are provided in Appendix B.
The predominant radioactivity detected throughout 2009 was from external sources, such as fallout from nuclear weapons tests (cesium-137, strontium-90) and naturally occurring radionuclides. Naturally occurring nuclides such as beryllium-7, potassium-40, and thorium-228 were detected in numerous samples.
The following is a discussion and summary of the results of the environmental measurements taken during the 2009 reporting period.
4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation. Two TLDs, made of CaF and LiF elements and specifically designed for environmental monitoring, are deployed at each sampling location.
TLDs are placed in two concentric rings around the station. The inner ring is located in the vicinity of the site boundary, and the outer ring is located at approximately five miles from the station. TLDs are also placed in special interest areas, such as population centers and nearby residences. Additional TLDs serve as controls. Ambient radiation comes from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station.
The results of the TLD analyses are presented in Table 3-2. Figure 4-1 shows a historical trend of TLD exposure rate measurements, comparing the average of indicator TLDs located near the site boundary and at 5 miles to the average of all control TLD locations. Control and indicator averages indicate a steady relationship.
49
Figure 4-1: DIRECT RADIATION MEASUREMENT TLD RESULTS 8
7 6"
0 5'
4 '
2.
I*
00 00
'l (4 C C-l 4 Cl C"4 C1 C
- Site Boundry - 5 Mile
- Avg Control 4.2 Airborne Gross Beta Air is continuously sampled by passing it through glass fiber particulate filters.
The filters collect airborne particulate radionuclides. Once a week the samples are collected and analyzed for gross beta activity. Results of the weekly gross beta analyses are presented in Table 3-3. A review of the results from control and indicator locations continues to show no significant variation in measured activities (see Figure 4-2 and 4-3). This indicates that any station contribution is not measurable.
Gross beta activity found during the pre-operational and early operating period of Surry Power Station was higher because of nuclear weapons testing. During that time, nearly 740 nuclear weapons were tested worldwide. In 1985 weapons testing ceased, and with the exception of the Chernobyl accident in 1986, airborne gross beta results have remained steady.
50
Figure 4-2: 2009 GROSS BETA IN AIR PARTICULATES 0.060 0.050 0.040
.--0.030 ,
0.020 "
0.010 f 0.000 !
t0 '- A '0n-ao w --. - Ag l ('n 0r 0
--- Avg Indicator
- Avg Control Figure 4-3: GROSS BETA IN AIR PARTICULATES HISTORICAL TREND 1.0E+00 1.OE-01 W
I Mr 1.0E-02 1.0E-03 . . . . .
0 - ('4 m1 I t \O N
'-- 0 C, 0 - ('4 N m ' t z r x 00 C C, C Cv ON C7v Cv a, C7, a, C, 0 0 0 0 0 0 0 0 0 Avg Inia("4 ('g ('r ('g ('4 ('- q ('4 (4 ('e ('-4
-U Avg Indicator 0 Avg Control Avg The-Op - Required LLD 51
4.3 Airborne Radioiodine Air is also continuously sampled for radioiodines by passing it through charcoal cartridges. Once a week the charcoal cartridge samples are collected and analyzed. The results of the analyses are presented in Table 3-4. All results are below the lower limit of detection. No positive iodine-131 was detected. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl.
4.4 Air ParticulateGamma The air particulate filters from the weekly gross beta analyses are composited by location and analyzed quarterly by gamma spectroscopy. The results are listed in Table 3-5. The results indicate the presence of naturally occurring beryllium-7, which is produced by cosmic processes. No man-made radionuclides were identified. These analyses confirm the lack of station effects.
4.5 Cow Milk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the fact that consumption of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint. This pathway also shows measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there is any station effect.
Analysis results for cow milk are contained in Table 3-6. All results show a lack of detectable iodine-131 above the LLD of 1 pCi/L. Results of gamma spectroscopy indicate no other detectable station related radioactivity in the milk samples. In years past, cesium- 137 has been detected sporadically. The occurrences were attributed to residual global fallout from past atmospheric weapons testing. Cs-137 was not detected at a level above the LLD in 2009.
At the request of the Commonwealth of Virginia, a quarterly composite sample is prepared from the monthly milk samples from the Colonial Parkway collection station. The composite samples are analyzed for strontium-89 and strontium-90.
Sr-90 was detected in one of the four composites analyzed at a concentration of 1.12 pCi/L. The average Sr-90 concentration for the ten year period of 1999 to 2009 is 1.82 pCi/L. Sr-90 is not a component of the station radiological effluents.
The Sr-90 detected is a product of nuclear weapons testing fallout which has been well documented.
52
I, j,
4.6 Food Products Three samples were collected and analyzed by gamma spectroscopy. The results of the analyses are presented in Table 3-7. As expected, naturally occurring potassium-40 was detected in all samples. The average concentration is consistent with that observed in previous years. Naturally occurring thorium-228 was also detected in one of three samples. No station related radioactivity was detected.
4.7 Well Water Well water is not considered to be affected by station operations because there are no discharges made to this pathway. However, Surry Power Station monitors well water quarterly at three indicator locations and analyzes for gamma radiation and for tritium. The results of these analyses are presented in Table 3-8. Consistent with past monitoring, no station related radioactivity was detected. Naturally occurring potassium-40 and actinium-228 were detected in one sample each. No gamma emitting isotopes were detected during the pre-operational period.
4.8 River Water Samples of the James River water are collected monthly and the results are presented in Table 3-9. All samples are analyzed by gamma spectroscopy. The monthly samples are also composited and analyzed for tritium on a quarterly basis. Naturally occurring potassium-40, thorium-228 and radium-226 were detected in some samples. No station related radioactivity was detected.
4.9 Silt Silt is sampled to evaluate any buildup of radionuclides in the environment due to the operation of the station. Sampling of this pathway provides a good indication of the dispersion effects of effluents to the river. Buildup of radionuclides in silt could indirectly lead to increasing radioactivity levels in clams, oysters, crabs and fish.
Samples of silt are collected from two locations, one upstream and one downstream of the station. The results of the gamma spectroscopy analyses are presented in Table 3-10. Trend graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-4 and 4-5.
Historically, cobalt-60 has been detected in samples obtained from the indicator location (SD). Cobalt-60 has not been detected since 2003.
53
Cesium-137 was detected, as expected, in both the control and indicator samples.
The levels detected indicate a continual decreasing trend seen for over a decade.
The detection of cesium-137 in both the control and indicator samples and decreasing levels indicate that the presence of cesium-137 is the result of accumulation and runoff into the river of residual weapons testing fallout. Its global presence has been well documented. During the pre-operational period, cesium-137 was detected in most silt samples with an average concentration as indicated in Figure 4-5. In 2009, cesium-137 was detected with an average indicator location concentration of 214 pCi/kg and an average control location concentration of 184 pCi/kg. These activities continue to represent fallout from nuclear weapons testing. Both indicator and control cesium-137 activities trend closely as shown in Figure 4-5.
Figure 4-4: COBALT-60 INSILT 1.OE+04 1.OE+03 1.OE+02 C.,
1.0E+01 L.OE+00 Cl ý0 00 0 l ' 00 0 C ' 00 0 lcf \ 00 N
N N N 00 00 00 00 00 CNcr 0ý N ON 0ý,C 0 0 0 0 Control - Chickahominy -- Station Discharge Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were <MDC, Minimum Detectable Concentration. Station Discharge was <MDC activity 1996 through 1998 and 2004 through 2009.
54
Figure 4-5: CESIUM-1 37 IN SILT 1.OE+04 C0 1.OE+03J I j
I.OE+02
'C- 0 00 C' ct1 0 00 C N ~' ' 0 C ~ 0 0 C -0~0 -~ r-0 ~ 00 00 0'
0 0 0 0
0 00' 0
0' 0' 0'
10 01 00 C,
C>
C' ct~q C:'
ei C>
10
.N C
00C' C
I - Control - Chickahominy ---- Station Discharge - Asg Pre-Op - Required LLD 4.10 Shoreline Sediment Shoreline sediment, unlike river silt, may provide a direct dose to humans.
Buildup of radionuclides along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. The results are presented in Table 3-11.
The naturally occurring radionuclides potassium-40 and thorium-228 were detected at concentrations equivalent to normal background activities. The activities of these radionuclides indicate a steady trend. There were no radionuclides attributable to the operation of the station found in any shoreline sediment samples.
4.11 Fish The radioactivity measured in fish sampled from the station discharge canal and analyzed by gamma spectroscopy is presented in Table 3-12. These results are the same as those seen over the last decade. No activity was observed in this media except for naturally occurring potassium-40.
55
4.12 Oysters Oysters are collected from two different locations. The results of the oyster analyses are presented in Table 3-13.
There were no gamma emitting radionuclides detected in oysters sampled except for naturally occurring potassium-40. No station related radioactivity has been detected in this media since 1991. The absence of station related radionuclides is attributable to the replacement of steam generators in 1982 and past improvements made to liquid effluent treatment systems.
4.13 Clams Clams are analyzed from four different locations. The results of the gamma spectroscopy analyses are presented in Table 3-14. Like oysters, no station related radioactivity was detected. Naturally occurring potassium-40 and thorium-228 were detected.
4.14 Crabs A crab sample was collected in June from the station discharge canal and analyzed by gamma spectroscopy. The results of the analysis are presented in Table 3-15. Other than naturally occurring potassium-40, no other gamma emitting radionuclides were detected in the sample. This is consistent with pre-operational data and data collected over the past decade.
56
- 5. PROGRAM EXCEPTIONS There were four REMP exceptions for scheduled sampling and analysis during 2009.
The gross beta minimum detectable concentration (MDC) was 1.16E-02 pCi/m 3 .
for the November 17 Hog Island Reserve (HIR) air sample. This concentration is greater than the lower limit of detection (LLD) concentration of 1.00E-02 pCi/m 3 .
Although an MDC is a posteriori measurement, Surry Power Station requires that this value be less than or equal to the required LLD. This ensures that REMP samples are analyzed to required program elements. The cause for the higher MDC was a lower than normal sample volume due to loss of power at the HIR air sampling station. The loss of power resulted from a nor'easter that moved through the area during the sample period. Detection of gross beta activity in air samples is routine. Detectable gross beta activity was determined in this HIR air sample with the reduced volume and normal sample count time. Due to the detectable activity, the slightly elevated MDC was considered minor and a follow-on analysis to meet the 1.00E-02 pCi/m 3 MDC was not requested.
3 The iodine-131 minimum detectable concentration (MDC) was 7.01E-02 pCi/m for the November 03 Fort Eustis (FE) air sample and 7.16E-02 pCi/m 3 for the November 17 Hog Island Reserve (HIR) air sample. These concentrations are greater than the lower limit of detection (LLD) concentration of 7.OOE-02 pCi/m 3 .
For the second half of 2009, an efficiency correction factor normally used to determine the iodine- 131 concentration in air samples was not applied. Upon discovery of this error, the correction factor was applied to all air samples for the second half of 2009. This resulted in the higher than normal MDCs for these two air samples. A reanalysis of the two samples was not performed due to the short half-life of iodine- 131 and the extended time period between sample collection and discovery of the correction factor error.
During the March 2008 clam sampling campaign, clams were not found at the Hog Island Point sample location. An alternate sampling location, Jamestown Island, was selected and sampled throughout 2008.- In 2009, clams continued to be sampled at the Jamestown Island location in place of the Hog Island Point location.
57
- 6. CONCLUSIONS The results of the 2009 Radiological Environmental Monitoring Program for Surry Power Station have been presented in previous sections. This section presents conclusions for each pathway.
Direct Radiation Exposure Pathway - Control and indicator location averages continue to indicate a steady relationship and trend over the long term.
Airborne Exposure Pathway - Analysis of charcoal cartridge samples for radioiodines indicated no positive activity was detected. Quarterly gamma isotopic analyses of the composite particulate samples identified only naturally occurring beryllium-7. Air particulate gross beta concentrations at all of the indicator locations for 2009 trend well with the control location.
BMilk - Milk samples are an important indicator measuring the effect of radioactive iodine and radionuclides in airborne releases. Cesium-137 and iodine-131 were not detected in any of the thirty-six samples. Naturally occurring potassium-40 was detected at a similar level when compared to the average of the previous year.
Strontium-90 was detected in one of four samples this year at a concentration of 1.12 pCi/L. Strontium-90 is not a component of station effluents, but rather, a product of nuclear weapons testing fallout.
Food Products - As expected, naturally occurring potassium-40 was detected in all three samples and naturally occurring thorium-228 was detected in one of three samples. In the past, cesium-137 has occasionally been detected in these samples and is attributable to global fallout from past nuclear weapons testing. Cesium-137 was not detected in any of the three samples collected in 2009.
Well Water - Well water samples were analyzed and the analyses indicated that there were no man-made radionuclides present. This trend is consistent throughout the monitoring period. No radioactivity attributable to the operation of the station was identified.
> River Water - All river water samples were analyzed for gamma emitting radionuclides. Only the naturally occurring radionuclides potassium-40 thorium-228 and radium-226 were detected. Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2009.
> Silt - Cesium-137 was detected in both the control and indicator samples.
The presence of cesium- 137 is attributable to residual weapons testing fallout; its presence has been well documented. Cobalt-60 has not been 58
detected since 2003.
Shoreline Sediment - Naturally occurring radionuclides were detected at concentrations equivalent to normal background activities. There were no radionuclides attributable to the operation of Surry Power Station found in any sample.
Aquatic Biota Fish - As expected, naturally occurring potassium-40 was detected. There were no other gamma emitting radionuclides detected in any of the fish samples.
Oysters and Clams - Other than naturally occurring potassium-40 and thorium-228, there were no other gamma emitting radionuclides detected in any of the oyster or clam samples.
Crabs - Naturally occurring potassium-40 was detected. No other gamma emitting radionuclides were detected.
59
REFERENCES 60
References
- 1. NUREG-0472, "Radiological Effluent Technical Specifications for PWRs",
Draft Rev. 3, March 1982.
- 2. 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.
- 3. United States Nuclear Regulatory Commission, Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",
December 1975.
- 4. United States Nuclear Regulatory Commission Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.
- 5. Dominion, Station Administrative Procedure, VPAP-2103S, "Offsite Dose Calculation Manual (Surry)".
- 6. Virginia Electric and Power Company, Surry Power Station Technical Specifications, Units 1 and 2.
- 7. HASL-300, Environmental Measurements Laboratory, "EML Procedures Manual," 27th Edition, Volume 1, February 1992.
- 8. NUREG/CR-4007, "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," September 1984.
- 9. NCRP Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," March 2009.
61
APPENDICES 62
APPENDIX A: LAND USE CENSUS Year 2009 63
LAND USE CENSUS*
Surry Power Station, Surry County, Virginia January 1 to December 31, 2009 Page 1 of 1 i i I Nearest Nearest Nearest Nearest Sector I Direction Resident Garden** I Cow Goat N 4.1 @ 100 (a) (a) (a)
NNE 1.9 @ 320 (a) (a) (a)
NE 4.7 @ 350 (a) (a) (a)
ENE (a) (a) (a) (a)
E (a) (a) (a) (a)
ESE (a) (a) (a) (a)
SE (a) (a) (a) (a)
SSE 3.1 @ 1490 (a) (a) (a)
S 1.7 @ 1810 1.9 @ 1890 (a) (a)
SSW 2.3 @2120 4.3 @ 193- 4.8 @ 2000 (a)
SW 2.3 @ 2210 3.6 @ 2230 (a) (a)
WSW 0.4 @ 2440 3.6 @ 2450 (a) (a)
W 3.1 @ 2600 3.4 @ 260- (a) (a)
WNW 4.9 @ 2830 (a) (a) (a)
NW 4.6 @ 3210 (a) (a) (a)
NNW 3.8-@338- 4.4 @ 3340 3.7 @ 336- (a)
- Locations are listed by miles and degrees heading relative to true northfrom center of Unit #1 Containment.
- Area greaterthan 50 m 2 and contains broadleafvegetation.
(a) None 64
APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS Year 2009 65
EfTRODUCTION This appendix covers the Interlaboratory Comparison Program (ICP) of GEL Laboratories LLC (GEL) and Teledyne Brown Engineering (TBE). GEL and TBE use QA/QC samples provided by Eckert & Ziegler Analytics, Inc., Environmental Resource Associates (ERA) and the Mixed Analyte Performance Evaluation Program (MAPEP) to monitor the quality of analytical processing associated with the REMP. Each provider has a documented Quality Assurance program and the capability to prepare Quality Control materials traceable to the National Institute of Standards and Technology (NIST). The providers supply the samples to GEL and TBE, and upon receipt, the laboratories perform the analyses in a normal manner. The results are then reported to the provider for evaluation. The suite of QA/QC samples is designed to provide sample media and radionuclide combinations that are offered by the providers and included in the REMP and typically includes:
) milk for gamma nuclides and low-level iodine- 131 analyses,
> milk for Sr-89 and Sr-90 analyses,
> water for gamma nuclides, low-level iodine- 131, and gross beta analyses,
> water for tritium, Sr-89, and Sr-90 analyses,
> cartridge for l- 13 1 analyses,
> air filter for gamma nuclide, gross beta, and Sr-90 analyses.
The accuracy of each result reported to Eckert & Ziegler Analytics, Inc. is measured by the ratio of GEL and TBE result to the known value. Accuracy for all other results is based on statistically derived acceptance ranges calculated by the providers. An investigation is undertaken whenever the ratio or reported result fell outside of the acceptance range.
RESULTS The GEL and TBE ICP results are included in the following tables for the first through the fourth quarters of 2009. One result did not meet the acceptance criteria and is discussed as follows.
- 2nd quarter milk - The root cause of the Sr-90 failure was determined to be a batch quality control issue. The carrier yield for the second separation was greater than 100%. The elevated yield caused the Sr-90 result to be biased low.
66
Ij ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM GEL LABORATORIES LLC (PAGE 1 OF 2)
Identification Reported Known Quarter Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d) 1st Quarter 2009 E6582-278 Charcoal 1-131 pCi 77.7 79.4 0.98 E6584-278 Milk 1-131 pCi/L 79.7 79.3 1.01 Ce-1 41 pCi/L 97.8 94.9 1.03 Cr-51 pCi/L 297 305 0.97 Cs-1 34 pCi/L 90.6 93.7 0.97 Cs-1 37 pCi/L 116 111 1.04 Co-58 pCi/L 123 119 1.03 Mn-54 pCi/L 133 128 1.04 Fe-59 pCi/L 116 99.9 1.16 Zn-65 pCi/L 172 156 1.10 Co-60 pCi/L 150 142 1.06 E6585-278 Water 1-131 pCi/L 75.5 69 1.09 Ce-141 pCi/L 122 120 1.02 Cr-51 pCi/L 392 387 1.01 Cs- 134 pCi/L 119 119 1.00 Cs-137 pCi/L 144 141 1.02 Co-58 pCi/L 159 151 1.05 Mn-54 pCi/L 180 162 1.11 Fe-59 pCi/L 128 127 1.01 Zn-65 pCi/L 224 197 1.13 Co-60 pCi/L 192 180 1.06 Footnotes are on page 2 of 2.
67
ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM GEL LABORATORIES LLC (PAGE 2 OF 2)
Identification Reported Known Quarter Number Matrix Nuclide Units Value (a) Value (b) Ratio (c) Evaluation (d) 2nd Quarter 2009 E6729-278 Charcoal 1-131 pCi 92.7 95.5 0.97 A E6730-278 Milk Sr-89 pCi/L 85.1 112 0.76 A Sr-90 pCi/L 10.9 16.7 0.65 N E6731-278 Milk 1-131 pCi/L 89.8 102.0 0.88 A Ce-1 41 pCi/L 284 284 1.00 A Cr-51 pCi/L 404 400 1.01 A Cs-1 34 pCi/L 158.0 166 0.95 A Cs-137 pCi/L 192 192 1.00 A Co-58 pCi/L 94.8 91.9 1.03 A Mn-54 pCi/L 142 137 1.04 A Fe-59 pCi/L 123 122 1.01 A Zn-65 pCi/L 179 175 1.02 A Co-60 pCi/L 315 312 1.01 A E6732-278 Water 1-131 pCi/L 85.2 88.3 0.97 A Ce-141 pCi/L 229 216 1.06 A Cr-51 pCi/L 311 304 1.02 A Cs-134 pCi/L 137 126 1.09 A Cs-137 pCi/L 151 146 1.04 A Co-58 pCi/L 72.1 70 1.03 A Mn-54 pCi/L 107 104 1.03 A Fe-59 pCi/L 90.4 92.9 0.97 A Zn-65 pCi/L 138 133 1.04 A Co-60 pCi/L 242 237 1.02 A (a) GEL reported result.
(b) Reference value.
(c) Ratio GEL to Eckert& Ziegler Analytics.
(d) Evaluation: A= Acceptable, N= Not Acceptable.
68
DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
GEL LABORATORIES LLC (PAGE 1 OF 1)
Identification Reported Known Acceptance Quarter Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c) 2nd Quarter 2009 09-GrF20 Filter Gr-Beta Bq 0.297 0.28 0.140 - 0.419 A Gr-Alpha Bq 0.069 0.35 >0.0 - 0.696 A 09-RdF20 Filter Co-57 Bq 1.347 1.30 0.91 -1.69 A Co-60 Bq 1.413 1.22 0.89-1.59 A Cs-134 Bq 2.763 2.93 2.05 - 3.81 A Cs-137 Bq 1.487 1.52 1.06 - 1.98 A M n-54 Bq 2.403 2.27 1.590 - 2.952 A Zn-65 Bq 1.613 1.36 0.95- 1.77 A Sr-90 Bq 0.692 0.64 0.448 - 0.832 A 09-GrW20 Water ' Gr-Beta Bq/L 1.337 1.27 0.64- 1.91 A Gr-Alpha Bq/L 0.506 0.64 >0.0 - 1.270 A 09-MaW20 Water Co-57 Bq/L 18.8 18.9 13.2 -24.6 A Co-60 Bq/L 16.8 17.21 12.05 - 22.37 A Cs-1 34 Bq/L 21.9 22.5 15.8-29.3 A Cs-137 Bq/L 0.0 0 (1) A Mn-54 Bq/L 15.1 14.66 10.26 - 19.06 A Sr-90 Bq/L 7.43 7.21 5.05 - 9.37 A Zn-65 Bq/L 14.6 13.6 9.5- 17.7 A (a) GEL reported result.
(b) Reference value.
(c) Evaluation: A= Acceptable, N = Not Acceptable.
(1) False positive test.
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ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM GEL LABORATORIES LLC (PAGE 1 OF 1)
Identification Reported Known Acceptance Quarter Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c) 1st Quarter 2009 RAD-76 Water Gr-Alpha pCi/L 51.3 52.3 27.3 - 52.3 A Gr-Beta pCi/L 41.9 46.1 31.0-53.3 A H-3 pCi/L 3760 4230 3610 -4660 A 1-131 pCi/L 25.1 22.2 18.4-26.5 A Sr-89 pCi/L 72.8 65 52.7 - 73.0 A Sr-90 pCi/L 36.5 41.9 30.8-48.1 A (a) GEL reported result.
(b) Reference value.
(c) Evaluation: A= Acceptable, N = Not Acceptable.
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ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 2)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value(a) Value (b) TBE/Analytics Evaluation(d)
September 2009 E6897-396 Milk Sr-89 pCi/L 113 107 1.06 A Sr-90 pCi/L 17.4 18.8 0.93 A E6898-396 Milk 1-131 pCi/L 89.2 98.6 0.90 A Ce-141 pCi/L 249 275 0.91 A Cr-51 pCi/L 213 221 0.96 A Cs-134 pCi/L 104.0 123 0.85 A Cs-137 pCi/L 172 185 0.93 A Co-58 pCi/L 96.3 99.4 0.97 A Mn-54 pCi/L 201 206 0.98 A Fe-59 pCi/L 154 147 1.05 A Zn-65 pCi/L 213 204 1.04 A Co-60 pCi/L 154 160 0.96 A E6900-396 Filter Ce-141 pCi 181 161 1.12 A Cr-51 pCi 145 130 1.12 A Cs-134 pCi 71.8 72 0.99 A Cs-137 pCi 115 109 1.06 A Co-58 pCi 62 58 1.06 A Mn-54 pCi 129 121 1.07 A Fe-59 pCi 97 98 0.98 A Zn-65 pCi 110 120 0.92 A Co-60 pCi 98.7 94.1 1.05 A E6899-396 Charcoal 1-131 pCi 89.5 92.3 0.97 A Footnotes are on page 2 of 2.
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ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value(a) Value (b) TBE/Analytics Evaluation(d)
December 2009 E6946-396 Milk Sr-89 pCi/L 131 131 1.00 A Sr-90 pCi/L 19.3 17.9 1.08 A E6947-396 Milk 1-131 pCi/L 79.2 87.3 0.91 A Ce-141 pCi/L 193 202 0.96 A Cr-51 pCi/L 512 548 0.93 A Cs-134 pCi/L 222 253 0.88 A Cs-137 pCi/L 163 179 0.91 A Co-58 pCi/L 200 211 0.95 A Mn-54 pCi/L 178 178 1.00 A Fe-59 pCi/L 176 178 0.99 A Zn-65 pCi/L 326 345 0.94 A Co-60 pCi/L 240 256 0.94 A E6949-396 Filter Ce-141 pCi 103 103 1.00 A Cr-51 pCi 290 280 1.04 A Cs-134 pCi 116 129 0.90 A Cs-137 pCi 93.4 91.5 1.02 A Co-58 pCi ill 108 1.03 A Mn-54 pCi 81.0 90.8 0.89 A Fe-59 pCi 106 90.8 1.17 A Zn-65 pCi 155 176 0.88 A Co-60 pCi 135 131 1.03 A E6948-396 Charcoal 1-131 pCi 93.3 93.9 0.99 A (a) Teledyne Brown Engineering reported result.
(b) The Eckert & Ziegler 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.
(c) Ratio of Teledyne Brown Engineering to Eckert &Ziegler Analytics results.
(d) Eckert& Ziegler Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20. W = Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of< 0.70 and> 1.30.
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DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) . Range Evaluation (c)
September 2009 09-MaW21 Water Cs-134 Bq/L 26.5 32.2 22.5-41.9 A Cs-137 Bq/L 37.2 41.2 28.8 - 53.6 A Co-57 Bq/L 32.2 36.6 25.6 -47.6 A Co-60 Bq/L 14.0 15.40 10.8-20.0 A H-3 Bq/L 705 634.1 443.9 - 824.3 A Mn-54 Bq/L -0.1015 (1) A Sr-90 Bq/L 13.9 12.99 9.09- 16.89 A Tc-99 Bq/L 8.06 10.0 7.0- 13.0 A Zn-65 Bq/L 26.2 26.9 18.8-35.0 A 09-GrW21 Water Gr-Alpha Bq/L 1.27 1.047 >0.0 - 2.094 A Gr-Beta Bq/L 9.70 7.53 3.77- 11.30 A 09-RdF21 Filter Am-241 Bq/sample -0.0040 (1) A Cs- 134 Bq/sample -0.02 (1) A Cs-137 Bq/sample 1.4 1.4 0.98- 1.82 A Co-57 Bq/sample 5.98 6.48 4.54- 8.42 A Co-60 Bq/sample 1.01 1.03 0.72- 1.34 A Mn-54 Bq/sample 5.16 5.49 3.84-7.14 A Sr-90 Bq/sample 0.925 0.0835 0.585 - 1.086 A Zn-65 Bq/sample 4.39 3.93 2.75-5.11 A 09-GrF21 Filter Gr-Alpha Bq/sample 0.357 0.659 >0.0 - 1.318 A Gr-Beta Bq/sample 1.403 1.320 0.66- 1.98 A (1) False positive test.
(a) Teledyne Brown Engineering reported result.
(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined bygravimetric and/or volumetric measurements made during standard preparation.
(c) DOE/MAPEP evaluation: A = Acceptable, W = Acceptable with warning, N = Not Acceptable.
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ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE 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)
October 2009 RAD 79 Water Sr-89 pCi/L 64.75 62.2 50.2-70.1 A Sr-90 pCi/L 30.30 30.7 22.4 - 35.6 A Ba-133 pCi/L 97.9 92.9 78.3- 102 A Cs-134 pCi/L 76.8 79.4 65.0 - 87.3 A Cs-137 pCi/L 59.9 54.6 49.1 -62.9 A Co-60 pCi/L 121 117 105- 131 A Zn-65 pCi/L 115 99.5 89.6-119 A Gr-Alpha pCi/L 19.6 23.2 11.6-31.1 A Gr-Beta pCi/L 28.5 26.0 16.2-33.9 A 1-131 pCi/L 22.1 22.2 18.4-26.5 A H-3 pCi/L 16133 16400 14300 - 18000 A (a) Teledyne Brown Engineering reported result.
(b) The ERA known value is equal to 100% of the parameter present in the standard as determined bygravimetric and/or volumetric measurements made during standard preparation.
(c) ERAevaluation: A= Acceptable. Reported result falls within the Warning Limits. NA= NotAcceptable. Reported result falls outside of the Control Limits. CE = Check for Error. Result falls within the Control Limits and outside of the Warning Limit.
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