ML15118A543
| ML15118A543 | |
| Person / Time | |
|---|---|
| Site: | Surry, 07200002, 07200055 |
| Issue date: | 04/20/2015 |
| From: | Lawrence D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 15-149 | |
| Download: ML15118A543 (77) | |
Text
VIRGINI4, ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 20, 2015 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Serial No.
SS&L/JSA Docket Nos.15-149 RO 50-280 50-281 72-2 72-55 DPR-32 DPR-37 SNM-2501 License Nos.
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 Surry Power Station. Accordingly, enclosed is the Surry Power Station AREOR for the period of January 1, 2014 through December 31, 2014, which includes environmental monitoring for the Surry ISFSI.
If you have any further questions, please contact Jason Eggart at 757-365-2010.
Sinc el DobuglaC.
C.Lawrence Director Safety & Licensing Surry Power Station Attachment Commitments made in this letter: None
ýA2
Serial No.15-149 Docket Nos.: 50-280 50-281 72-2 72-55 cc:
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 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.
Docket Nos.:
15-149 50-280 50-281 72-2 72-55 ATTACHMENT 1 2014 Annual Radiological Environmental Operating Report SURRY POWER STATION UNITS I AND 2 VIRGINIA ELECTRIC AND POWER COMPANY
Surry Power Station 2014 Annual Radiological Environmental Operating Report
- "Dominuoit
Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2014 to December 31, 2014
Annual Radiological Environmental Operating Report Surry Power Station January 1, 2014 to December 31, 2014 Prepared by:
Reviewed by:
Reviewed by:
Approved by:
P.F. Blount Health Physicist P. R. Harris Supervisor Radiological Analysis Supervisor Health Physics Technical Services M a -g e J.RW
. P og a rt Maaer Radiological Protection and Chemistry 2
Table of Contents PREFA CE...............................................................................................................................................
4
- 1. EX ECU TIV E SU M M ARY...............................................................................................................
5
- 2. PROGRA M DESCRIPTION......................................................................................................
7 2.1 Introduction.............................................................................................................................
7 2.2 Sam pling and Analysis Program........................................................................................
8
- 3. AN ALYTICAL RESU LTS........................................................................................................
20 3.1 Sum m ary of Results........................................................................................................
20 3.2 Analytical Results of 2014 REM P Sam ples...................................................................
28
- 4.
D ISCU SSION OF RESU LTS.................................................................................................
49 4.1 Gam m a Exposure Rate...................................................................................................
49 4.2 Airborne Gross Beta.........................................................................................................
50 4.3 Airborne Radioiodine......................................................................................................
52 4.4 Air Particulate Gam m a...................................................................................................
52 4.5 Cow M ilk..............................................................................................................................
53 4.6 Food Products.......................................................................................................................
53 4.7 W ell W ater............................................................................................................................
53 4.8 River W ater...........................................................................................................................
53 4.9 Silt.........................................................................................................................................
54 4.10 Shoreline Sedim ent........................................................................................................
56 4.11 Fish......................................................................................................................................
56 4.12 Oysters................................................................................................................................
57 4.13 Clam s..................................................................................................................................
57 4.14 Crabs...................................................................................................................................
57
- 5. PROGRAM EX CEPTION S.....................................................................................................
58
- 6. CON CLU SION S.............................................................................................................................
59 REFEREN CES....................................................................................................................................
61 APPEN D ICES.....................................................................................................................................
63 APPEN D IX A : LAN D U SE CEN SU S......................................................................................
64 APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS...........................
66 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, and the Surry Independent Spent Fuel Storage Installation (ISFSI) Technical Specifications, Appendix C, Item 1.3.1.
4
- 1. EXECUTIVE
SUMMARY
This document is a detailed report of the 2014 Surry Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 2014, 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 represent normal background radiation levels.
Background radiation levels 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 natural variation, or other causes such as the Chemobyl and Fukushima Daiichi accidents that released radioactive material to the environment.
Teledyne Brown Engineering, Inc. (TBE) provides 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 possible. The USNRC also mandates a reporting 5
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 2014 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 radionuclides such as beryllium-7, potassium-40, radium-226, thorium-228 and thorium-232 were 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 radionuclides beryllium, potassium, radium and thorium were detected at average environmental levels. The terrestrial exposure pathway includes milk and food products. Iodine-131 was not detected in any 2014 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90 was 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 2014, 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 2014 was 0.036 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 2014 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 nominal gross electrical output of 910 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. Teledyne Brown Engineering is 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 2014 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 2014 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 Teledyne Brown Engineering and Global Dosimetry Solutions for Surry Power Station. All samples, with the exception of the TLDs, are shipped to 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
nIm M
M M
M m=m m-M
=
M
=
=
M
=M Table 2-1 SURRY - 2014 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Onsite (Stored in a lead shield outside the protected Environmental TLDs Control West North West Surry Station Discharge North North West North North North East North East East North East East West West South West South West South South West South South South East South East Station Intake Hog Island Reserve Bacon's Castle Route 633 Alliance Surry Route 636 and 637 Scotland Wharf Jamestown Colonial Parkway Route 617 and 618 Kingsmill Williamsburg Kingsmill North Budweiser Water Plant (00)
(02)
(03)
(04)
(05)
(06)
(07)
(08)
(09)
(10)
(11)
(12)
(13)
(14)
(15)
(16)
(18)
(19)
(20)
(21)
(22)
(23)
(24)
(25)
(26)
(27)
(28)
(29)
(30)
(31)
(32)
(33) 0.2 0.4 0.2 0.3 0.3 0.3 0.4 0.3 0.1 0.4 0.3 0.3 0.4 0.6 0.9 1.6 2.0 4.5 4.9 5.1 7.7 4.0 5.0 6.3 3.8 4.9 4.6 7.8 5.5 5.8 5.0 WNW NW NNW N
NNE NE ENE E
SSE SE ESE NNE SSW SW WSW WSW W
WNW NW NNW NNW N
N NNE NNE NE 2930 3210 3290 40 280 440 670 890 2710 2520 2280 2010 1820 1570 1350 1150 260 2020 2270 2470 2560 2700 2840 3080 3330 3400 20 00 120 270 460 Quarterly area)
Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Near Resident Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Population Center Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Population Center Quarterly Apx. 5 mile Quarterly Population Center Quarterly Apx. 5 mile 9
Table 2-1 SURRY - 2014 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Location Environmental BASF TLDs Lee Hall Goose Island Fort Eustis Newport News James River Bridge Benn's Church Smithfield Rushmere Route 628 Air Charcoal Surry Station and Particulate Hog Island Reserve Bacon's Castle Alliance Colonial Parkway BASF Fort Eustis Newport News Distance Collection Station Miles Direction Degrees Frequency Remarks (34) 5.1 ENE 700 Quarterly Apx. 5 mile (35)
(36)
(37)
(38)
(39)
(40)
(41)
(42)
(43)
(SS)
(HIR)
(BC)
(ALL)
(CP)
(BASF)
(FE)
(NN) 7.1 5.1 4.9 19.3 17.1 17.0 13.4 5.3 5.1 ENE E
NNE NNE SSW WSW NNW ENE ESE SE 750 900 1040 1300 1420 1590 1670 1560 1770 180 260 2020 2470 3330 700 1040 1300 Quarterly Population Center Quarterly Apx. 5 mile Quarterly Apx. 5 mile Quarterly Population Center Quarterly Control Location Quarterly Control Location Quarterly Control Location Quarterly Apx. 5 mile Quarterly Apx. 5 mile 0.3 2.0 4.5 5.1 3.8 5.1 4.9 19.3 0.4 4.9 0.1 2.0 0.3 Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Site boundary location with highest D/Q Control Location River Water Surry Station Discharge Scotland Wharf Well Water Surry Station Hog Island Reserve Construction Site (SD)
(SW)
(SS)
(HIR)
(CS)
NW 3230 WNW 2840 Monthly Monthly Control Location SW NNE E
2270 280 870 Quarterly Onsite Quarterly Quarterly Shoreline Sediment Silt Hog Island Reserve Chickahominy River Chickahominy River Surry Station Discharge (HIR) 0.6 (CHIC) 11.2 (CHIC) 11.2 (SD) 1.3 N
70 Semi-Annually WNW 3010 Semi-Annually Control Location WNW 3000 Semi-Annually Control Location NNW 3410 Semi-Annually 10
Table 2-1 SURRY-2014 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Media Location Milk Colonial Parkway Williams Epps Station (CP)
(WMS)
(EPPS)
Distance Miles 3.7 27.5 4.8 Direction Degrees NNW 3360 S
1750 SSW 2000 Collection Frequency Monthly Monthly Control Location Monthly Remarks Oysters Point of Shoals Mulberry Point Lawne's Creek (POS)
(MP)
(LC)
(CHIC)
(SD)
(lI) 6.4 4.9 2.4 SSE ESE SE 1570 Semi-Annually 1240 Semi-Annually 1310 Semi-Annually Clams Chickahominy River Surry Station Discharge Jamestown Island Surry Station Discharge Surry Station Discharge 11.2 WNW 1.3 NNW 3.9 NW 3000 Semi-Annually Control Location 3410 Semi-Annually 3240 Semi-Annually Fish Crabs (SD)
(SD) 1.3 NNW 3410 Semi-Annually 1.3 NNW 3410 Annually Annually Annually Crops Brock's Farm (Corn, Peanuts, Slade's Farm Soybeans)
(BROCK) 3.8 (SLADE) 3.2 S
S 1830 1790 11
Table 2-2 SURRY - 2014 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*
REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2
mR/Std. Month Dosimetry (TLD)
Air Iodine Weekly 1-131 0.07 pCi/m 3 Air Particulate Weekly Gross Beta 0.01 pCi/m 3 Quarterly (a)
Gamma Isotopic pCi/m 3 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 Co-58 15 Fe-59 30 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 Co-58 15 Fe-59 30 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 - 2014 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA Shoreline Sediment FREQUENCY Semi-Annually Silt Semi-Annually Monthly ANALYSIS Gamma Isotopic Cs-134 Cs-137 Gamma Isotopic Cs-134 Cs-137 1-131 Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 LLD*
REPORT UNITS pCi/kg - dry 150 180 150 180 pCi/kg - dry pCi/L Milk I
15 18 60 15 pCi/L pCi/L Oysters Quarterly Composite of CP monthly sample Semi-Annually Semi-Annually Annually Sr-89 Sr-90 NA NA Clams Gamma Isotopic Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 130 130 260 130 260 130 150 130 130 260 130 260 130 150 130 130 260 130 260 130 150 pCi/kg - wet pCi/kg - wet pCi/kg - wet Crabs Footnotes located at end of table.
13
Table 2-2 SURRY - 2014 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*
REPORT UNITS Fish Semi-Annually Gamma Isotopic pCi/kg - wet Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Gamma Isotopic 1-131 Cs-134 Cs-137 130 130 260 130 260 130 150 Food Products Annually pCi/kg - wet 60 60 80 Note: This table is not a complete listing of nuclides that can be detected and reported. Other peaks that are 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
n m-n
-n--m--m-m n
(1~
~11 Fiur
- 1.
Sr Raioogca
I =
m =
=
m
=
m m
m m
=
m m
m n
m m
Iz 0F
I
=
M
=
-M M
M
=
M-M M
M M
=
=
M z
C)0 TS Figure 3. 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.
I
-n m-M
-=-
M M
M M
M MM Figure 4. Surry Emergency Plan Map Air Sampling Stations Nearest Residents O
- TLDSampling Nearest Milk Animal z
Nearest Garden Crop Samples 0
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.
I
-m-
=
M
------
M M
M M
MM 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.
..s..
- y
- 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 - 2014 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 I Distance Mean Mean Reported (Units)
Type No.
LLD Range Name IDirection Range Range Measurements Direct Radiation TLD (mR/
Std Month)
Gamma 164 2
5.7 (151/152)
(4.0 - 8.0)
STA-9 0.3 mi E
7.9 (414) 6.0 (12/12)
(7.8 - 8.0)
(5.0 - 7.9) 0 Air Gross Particulate Beta (1E-3 pCi/m3) 416 10 14.3 (363/364)
(3.69 - 33.1)
BC 4.5 mi 17.0 (52/52) 14.3 (52/52)
SSW (3.69 - 27.0)
(8.39 - 34.1) 0 Gamma 32 Be-7 K-40 32 32 115(28/28)
(71.2-167) 14.9 (2/28)
(11.5 - 18.2)
BC 4.5 mi 135 (4/4) 105 (4/4)
SSW (98.4-167)
(82.1-124)
ALL 5.1 mi 18.2 (1/4)
WSW (18.2 - 18.2)
Cs-1 34 32 50
< LLD N/A N/A
< LLD
< LLD
< LLD
< LLD
< LLD 0
0 0
0 Air Iodine 1-131 (1E-3 pCi/m3) 416 70
< LLD N/A
< LLD
< LLD 0
Milk (pCi/Liter)
Sr-89 Sr-90 4
4
< LLD N/A
< LLD N/A N/A 0
0 1.56(2/4)
(1.26-1.85)
CP 3.7 mi 1.56 (2/4)
NNW (1.26 - 1.85)
Gamma 36 K-40 1-131 36 1295 (24/24)
(891-1560)
EPPS 4.8 mi 1298 (12/12) 1275 (12/12)
SSW (891 - 1560)
(1120 - 1460) 36 1
< LLD Cs-134 36 15
< LLD N/A N/A N/A
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 0
0 0
0 21
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSUMMAR Y Surry Power Station, Surry County, Virginia -2014 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
Th-228 36
<LLD WMS 27.5 mi 27.3 (1/12) 27.3 (1/12) 0 S
(27.3 - 27.3)
(27.3 - 27.3)
Food Gamma 3
Products (pCi/kg vet)
K-40 3
8167 (3/3)
Slade 3.2 mi 13900 (1/1)
N/A 0
(4180 - 13900)
S (13900-13900) 1-131 3
60
< LLD N/A
< LLD N/A 0
Cs-134 3
60
< LLD N/A
< LLD N/A 0
Cs-137 3
80
< LLD N/A
< LLD N/A 0
Well H-3 12 2000
< LLD N/A
< LLD N/A 0
Water (pCi/Liter)
Gamma 12 Mn-54 12 15
< LLD N/A
< LLD N/A 0
Co-58 12 15
< LLD N/A
< LLD N/A 0
Fe-59 12 30
< LLD N/A
< LLD N/A 0
Co-60 12 15
< LLD N/A
< LLD N/A 0
Zn-65 12 30
< LLD N/A
< LLD N/A 0
22
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia -2014 Docket No. 50-280-281 Page 3 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 Well Gamma 12 Water (pCi/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-137 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
River H-3 8
2000
< LLD N/A
< LLD N/A 0
Water (pCi/L'ter)
Gamma 24 K-40 24 102 (6/12)
SD 0.4 mi 102 (6/12) 75.7 (4112) 0 (49.9 - 121)
NW (49.9 - 121)
(47.2 - 105)
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
Co-60 24 15
< LLD N/A
< LLD
< LLD 0
23
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Medium or Pathway Analysis Sampled Total (Units)
Type No.
River Gamma 24 Water (pCi/Liter)
Zn-65 24 Nb-95 24 Zr-95 24 1-131 24 Cs-134 24 Cs-137 24 Ba-140 24 La-140 24 Th-228 24 Th-232 24 Silt Gamma 4
(pCi/kg dry)
Be-7 4
K-40 4
Cs-134 4
Cs-137 4
Surry Power Station, Surry County, Virginia -2014 Docket No. 50-280-281 Page 4 of 7 Indicator Control Locations Location with Highest Mean Locations Non-Routine Mean Distance Mean Mean Reported LLD Range Name Direction Range Range Measurements 30 15 30 10 15 18 60 15
< LLD
" LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 9.00 (1112)
(9.00 - 9.00) 10.7 (1/12)
(10.7 - 10.7)
N/A N/A N/A N/A N/A N/A N/A N/A SW SD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 9.57 (1/12)
(9.57 - 9.57) 10.7 (1/12)
(10.7 - 10.7)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 4.9 mi WNW 0.4 mi NW 2110 (1/2)
(2110- 2110) 17700 (2/2)
(15200-20200)
< LLD 189 (2/2)
(147-230)
SD SD N/A CHIC 1.3 mi 2110 (1/2)
NNW (2110 - 2110) 1.3 mi 17700(2/2)
NNW (15200-20200)
< LLD 11.2 mi 248(2/2)
WNW (199-297)
< LLD 16050 (2/2)
(12800-19300)
< LLD 248 (2/2)
(199-297) 0 0
0 0
150 180 24
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2014 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 (pCi/kg dry)
Gamma 4
Ra-226 4
Th-228 4
Th-232 4
2520 (1/2)
(2520 - 2520) 1445 (2/2)
(1090 - 1800) 1190 (2/2)
(1090 - 1290)
CHIC 11.2 mi 3440(1/2) 3440(1/2)
WNW (3440 - 3440) (3440 - 3440)
CHIC 11.2 mi 1540 (212) 1540(2/2)
WNW (1300 - 1780) (1300 - 1780)
CHIC 11.2 mi 1330 (212) 1330 (2/2)
WNW (1140-1520) (1140-1520) 0 0
0 Shoreline Sediment (pCi/kg dry)
Gamma K-40 4
4 7205 (2/2)
(6520 - 7890)
HIR 0.6 mi 7205(2/2) 3175(2/2)
N (6520 - 7890) (1580 - 4770)
Cs-134 4
150
180
< LLD N/A N/A
< LLD
< LLD
< LLD
< LLD 0
0 0
0 0
0 Ra-226 4
Th-228 4
Th-232 4
< LLD 98.5 (2/2)
(95.0 - 102)
< LLD CHIC 11.2 mi 1770(1/2) 1770(1/2)
WNW (1770 - 1770) (1770 - 1770)
CHIC 11.2 mi 1840 (2/2) 1840 (212)
WNW (1290 - 2390) (1290 - 2390)
CHIC 11.2 mi 1930 (212) 1930 (212)
WNW (1410 - 2450) (1410 - 2450)
Fish (pCi/kg wet)
Gamma 4
2093 (4/4)
(1230 - 2590)
SD 1.3 mi 2093(4/4)
NNW (1230 - 2590) 4 130
< LLD 4
130
< LLD 4
260
< LLD N/A N/A N/A
< LLD
< LLD
< LLD N/A N/A N/A N/A 0
0 0
0 25
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station., Surry County, Virginia - 2014 Docket No. 50-280-281 Page 6 of 7 Medium or Pathway Analysis Sampled Total (Units)
Type No.
LLD Fish Gamma 4
(pCi/kg wet)
Co-60 4
130 Zn-65 4
260 Cs-134 4
130 Cs-137 4
150 Oysters Gamma 6
(pci/kg wet)
K-40 6
Mn-54 6
130 Co-58 6
130 Fe-59 6
260 Co-60 6
130 Zn-65 6
260 Cs-134 6
130 Cs-137 6
150 Indicator Control Locations Location with Highest Mean Locations Non-Routine Mean Distance Mean Mean Reported Range Name Direction Range Range Measurements
< LLD
< LLD
< LLD
< LLD N/A N/A N/A N/A
< LLD
< LLD
< LLD
< LLD N/A N/A N/A N/A 0
0 0
0 938 (5/6)
(595 - 1560)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD LC N/A N/A N/A N/A N/A N/A N/A 2.4 mi 1270 (1/2)
SE (1270 - 1270)
< LLD
< LLD
< LLD
< LLD
< LLD
" LLD
< LLD N/A N/A N/A N/A N/A N/A N/A N/A Clams Gamma (pCi/kg wet)
6 6
381 (1/4)
(381 - 381)
< LLD CHIC 11.2 mi 736 (1/2) 736 (1/2)
WNW (736 - 736)
(736 - 736)
N/A
< LLD
< LLD 0
0 130 26
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSUMMAR Y Surry Power Station, Surry County, Virginia - 2014 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 Direction Range Range Measurements Clams Gamma 6
(pCi/kg viet)
Co-58 6
130
< LLD N/A
< LLD
< LLD 0
Fe-59 6
260
< LLD N/A
< LLD
< LLD 0
Co-60 6
130
< LLD N/A
< LLD
< LLD 0
Zn-65 6
260
< LLD N/A
< LLD
< LLD 0
Cs-134 6
130
< LLD N/A
< LLD
< LLD 0
Cs-137 6
150
< LLD N/A
< LLD N/A 0
Crabs Gamma (pCi/kg vet)
K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-1 34 Cs-137 130 130 260 130 260 130 150 1530 (1/1)
(1530- 1530)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD SD N/A N/A N/A N/A N/A N/A N/A 1.3 mi 1530 (1/1)
NNW (1530 - 1530)
< LLD
< LLD
< LLD
< LLD
< LLD N/A N/A N/A N/A N/A N/A N/A N/A
< LLD
< LLD 27
3.2 Analytical Results of 2014 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 (2a) 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 2a uncertainty.
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 1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.
12.
13.
14.
given according to sample type as indicated below.
Gamma Exposure Rate Air Particulates, Weekly Gross Beta Radioactivity Air Particulates, Weekly 1-131 Air Particulates, Quarterly Gamma Spectroscopy Cow Milk Food Products Well Water River Water Silt Shoreline Sediment Fish Oysters Clams Crabs 28
TABLE 3-2: GAMMA EXPOSURE RATE Surry Power Station, Surry County, Virginia - 2014 mR/Std Month +/- 2 Sigma Page 1 of 1 STATION FIRST SECOND THIRD FOURTH AVERAGE NUMBER QUARTER QUARTER QUARTER QUARTER
+/-2 SIGMA 02 6.6 +/- 0.4 6.7 +/- 0.8 7.0 +/- 1.0 7.3 +/- 0.5 6.9 +/- 0.6 03 6.5 +/- 0.2 6.4 +/- 0.1 6.6 +/- 0.6 6.4 +/- 0.7 6.5 +/- 0.2 04 5.9 +/- 0.7 6.1 +/- 0.7 6.1 +/- 1.4 6.1 +/- 0.5 6.1 +/- 0.2 05 6.5 +/- 0.7 6.2 +/- 0.4 6.4 +/- 0.9 6.5 +/- 1.0 6.4 +/- 0.3 06 6.1 +/- 0.7 6.2 +/- 0.4 6.4 +/- 0.8 6.3 +/- 0.8 6.3 +/- 0.3 07 6.4 +/- 0.8 6.1 +/- 0.4 6.6 +/- 1.0 6.6 +/- 1.3 6.4 +/- 0.5 08 5.7 +/- 0.8 5.7 +/- 0.5 5.9 +/- 1.0 6.0 +/- 1.1 5.8 +/- 0.3 09 8.0 +/- 0.7 7.8 +/- 0.4 7.9 +/- 1.0 7.9 +/- 0.7 7.9 +/- 0.2 10 6.1 +/- 0.6 5.9 +/- 0.3 6.4 +/- 1.4 6.5 +/- 0.8 6.2 +/- 0.6 11 5.3 +/- 0.4 5.3 +/- 0.1 5.2 +/- 0.9 5.5 +/- 0.7 5.3 +/- 0.3 12 5.5 +/- 0.6 5.4 +/- 0.3 5.7 +/- 0.7 5.6 +/- 0.7 5.6 +/- 0.3 13 6.3 +/- 0.4 5.9 +/- 0.5 6.4 +/- 0.7 6.5 +/- 0.4 6.3 +/- 0.5 14 6.1 +/- 0.6 5.9 +/- 0.5 6.1 +/- 0.8 6.2 +/- 1.2 6.1 +/- 0.3 15 6.3 +/- 0.6 6.2 +/- 0.4 6.4 +/- 0.6 6.9 +/- 0.8 6.5 +/- 0.6 16 5.6 +/- 0.4 5.7 +/- 0.3 5.8 +/- 0.6 5.8 +/- 1.0 5.7 +/- 0.2 18 4.6 +/- 0.4 4.8 +/- 0.3 4.9 +/- 0.6 4.7 +/- 0.8 4.8 +/- 0.3 19 5.3 +/- 0.3 5.2 +/- 0.4 5.0 +/- 0.7 5.6 +/- 0.9 5.3 +/- 0.5 20 4.9 +/- 0.7 4.9 +/- 0.6 4.8 +/- 0.5 4.8 +/- 1.1 4.9 +/- 0.1 21 5.2 +/- 0.6 5.0 +/- 0.4 4.8 +/- 0.8 5.0 +/- 0.3 5.0 +/- 0.3 22 4.4 +/- 0.8 4.2 +/- 0.3 4.5 +/- 0.5 5.0 +/- 0.3 4.5 +/- 0.7 23 5.9 +/- 0.9 6.0 +/- 0.8 6.1 +/- 1.1 6.0 +/- 0.4 6.0 +/- 0.2 24 4.9 +/- 0.4 4.7 +/- 0.4 4.9 +/- 0.5 5.1 +/- 0.4 4.9 +/- 0.3 25 6.1 +/- 0.6 6.1 +/- 0.6 6.4 +/- 0.9 6.2 +/- 0.7 6.2 +/- 0.3 26 6.2 +/- 0.8 6.3 +/- 0.5 6.0 +/- 1.1 6.1 +/- 0.6 6.2 +/- 0.3 27 5.2 +/- 1.3 4.8 +/- 0.3 4.8 +/- 0.7 5.0 +/- 0.7 5.0 +/- 0.4 28 4.8 +/- 0.8 4.6 +/- 0.5 4.5 +/- 0.9 5.0 +/- 0.8 4.7 +/- 0.4 29 4.3 +/- 0.8 4.4 +/- 0.2 4.4 +/- 0.8 4.6 +/- 0.5 4.4 +/- 0.3 30 4.9 +/- 0.6 4.7 +/- 0.6 4.7 +/- 1.1 4.8 +/- 0.6 4.8 +/- 0.2 31 4.2 +/- 0.6 4.0 +/- 0.3 4.0 +/- 0.8 4.2 +/- 0.4 4.1 +/- 0.2 32 A
4.9 +/- 0.3 5.2 +/- 0.5 5.3 +/- 0.8 5.1 +/- 0.4 33 4.8 +/- 0.7 4.6 +/- 0.4 4.7 +/- 0.7 4.8 +/- 0.5 4.7 +/- 0.2 34 5.5 +/- 0.7 5.4 +/- 0.2 5.4 +/- 0.1 5.2 +/- 0.7 5.4 +/- 0.3 35 6.1 +/- 0.6 6.1 +/- 0.4 6.4 +/- 0.4 6.5 +/- 0.9 6.3 +/- 0.4 36 6.4 +/- 0.5 6.3 +/- 0.4 6.2 +/- 0.5 6.4 +/- 0.7 6.3 +/- 0.2 37 5.0 +/- 0.7 5.2 +/- 0.5 5.1 +/- 0.8 5.7 +/- 0.5 5.3 +/- 0.6 38 7.7 +/- 0.6 7.1 +/- 0.3 7.5 +/- 0.7 7.5 +/- 1.2 7.5 +/- 0.5 39-C 5.1 +/- 0.7 5.0 +/- 0.3 5.0 +/- 0.4 5.3 +/- 0.9 5.1 +/- 0.3 40-C 5.5 +/- 0.9 5.3 +/- 0.5 5.1 +/- 1.0 5.8 +/- 1.4 5.4 +/- 0.6 41-C 7.7 +/- 0.8 7.3 +/- 0.5 7.3 +/- 0.5 7.9 +/- 0.9 7.6 +/- 0.6 42 5.6 +/- 0.3 5.3 +/- 0.4 5.3 +/- 0.5 6.1 +/- 1.3 5.6 +/- 0.8 43 5.0 +/- 0.5 4.7 +/- 0.3 4.7 +/- 0.2 5.2 +/- 1.3 4.9 +/- 0.5 A - TLD found missing at collection.
29
TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2014 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 07 January 14 January 21 January 28 February 04 February 11 February 18 February 25 March 04 March 11 March 17 March 24 17.4 +/-
15.9 +/-
14.3 +/-
13.4 +/-
18.9 +/-
18.5 +/-
17.0 +/-
11.3 +/-
16.1 +/-
14.9 +/-
9.73 +/-
12.9 +/-
3.03 2.79 2.84 2.81 2.92 2.99 3.06 2.59 2.78 2.99 2.86 2.69 Qtr. Avg. +/- 2 s&d.
15.0 +/- 5.66 9.29 +/- 2.52 15.1 +/- 2.75 13.0 +/- 2.80 10.8 +/- 2.71 14.8 +/- 2.76 19.1 +/- 3.09 17.1 +/- 3.15 10.0 +/- 2.58 21.6 +/- 3.12 11.3 +/- 2.83 9.66 +/- 2.90 9.13 +/- 2.50 13.4 +/- 8.32 10.4 +/- 2.38 10.2 +/- 2.74 11.8 +/- 2.73 15.1 +/- 2.67 8.17 +/- 1.75 11.4 +/- 2.58 14.9 +/- 2.88 11.5 +/- 2.66 11.8 +/- 2.77 7.11 +/- 2.47 9.98 +/- 2.48 7.29 +/- 2.40 15.4 +/- 3.01 11.2 +/- 5.53 13.2 16.3 18.4 17.0 23.1 27.0 20.9 16.8 24.3 19.5 19.1 15.4
+/- 2.80
+/- 2.86
+/- 3.11
+/- 3.08
+/- 3.20
+/- 3.48
+/- 3.33
+/- 2.97
+/- 3.06
+/- 3.58
+/- 3.50
+/- 2.91 13.0 +/-
18.6 +/-
17.9 +/-
15.2 +/-
21.2 +/-
24.0 +/-
19.3 +/-
11.3 +/-
21.2 +/-
16.8 +/-
12.6 +/-
12.9 +/-
2.77 2.93 3.03 2.93 3.05 3.28 3.19 2.59 2.84 3.41 3.06 2.71 11.9 +/- 2.71 16.5 +/- 2.88 14.9 +/- 2.88 17.2 +/- 3.05 17.2 +/- 2.85 24.1 +/- 3.31 13.5 +/- 2.93 10.8 +/- 2.60 23.9 +/- 3.01 17.0 +/- 3.43 13.2 +/- 3.13 12.9 +/- 2.74 10.9 13.1 16.8 12.0 18.4 22.7 17.6 10.2 17.7 15.5 12.4 10.6
+/- 2.62
+/- 2.65
+/- 2.97
+/- 2.76
+/- 2.90
+/- 3.23
+/- 3.11
+/- 2.55
+/- 2.69
+/- 3.31
+/- 3.05
+/- 2.56 11.2 14.4 7.64 14.6 18.9 24.3 18.6 10.9 19.7 12.8 10.9 13.1
+/- 2.66
+/- 2.74
+/- 2.42
+/- 2.89
+/- 2.94
+/- 3.31
+/- 3.17
+/- 2.60
+/- 2.80
+/- 3.18
+/- 2.97
+/- 2.72 15.5 +/- 2.87 18.4 +/- 2.94 14.9 +/- 2.85 12.6 +/- 2.76 16.2 +/- 2.77 22.8 +/- 3.20 15.4 +/- 2.98 12.8 +/- 2.68 17.3 +/- 2.66 11.9 +/- 3.09 12.5 +/- 3.04 11.1 +/- 2.58 19.3 +/- 7.98 17.0 +/- 8.11 16.1 +/- 8.55 14.8 +/- 7.78 15.4 +/- 8.76 15.1 +/- 6.63 April April April April April 01 08 15 22 29 13.9 +/-
10.8 +/-
11.9 +/-
13.8 +/-
10.3 +/-
2.53 2.73 2.69 2.56 1.82 15.2 12.2 18.7 18.1 3.69
+/- 2.68
+/- 2.90
+/- 3.13
+/- 2.88
+/- 1.55 13.2 +/-
10.9 +/-
14.4 +/-
18.0 +/-
12.0 +/-
May 06 May 13 May 20 May 27 June 03 June 10 June 17 June 24 11.4 18.9 13.3 12.1 7.78 12.3 8.69 14.0
- 2.54
- 3.05
+/- 2.73
+/- 2.73 15.3 +/- 2.82 21.3 +/- 3.23 15.8 +/- 2.92 16.2 +/- 3.04 10.9 +/- 2.70 14.4 +/- 2.78 11.6 +/- 2.78 17.7 +/- 3.16 10.1 20.8 14.7 13.6 10.6 13.8 10.8 20.4
+/-
+/-
+/-
+/-
+/-
+
+/-
+/-
2.51 2.74 2.85 2.83 1.89 2.47 3.16 2.82 2.83 2.65 2.69 2.73 3.24 13.7 +/- 2.56 11.7 +/- 2.82 14.9 +/- 2.90 17.8 +/- 2.85 10.5 +/- 1.86 12.7 +/- 2.66 19.5 +/- 3.12 14.7 +/- 2.86 11.6 +/- 2.75 10.3 +/- 2.65 11.4 +/- 2.57 11.6 +/- 2.66 15.1 +/- 2.91 12.4 11.0 14.7 12.9 10.6 9.73 18.6 15.5 11.6 8.79 10.7 9.91 15.1
+/- 2.47
+/- 2.76
+/- 2.88
+/- 2.53
+/- 1.84
+/- 2.45
+/- 3.04
+/- 2.87
+/- 2.73
+/- 2.57
+/- 2.51
+/- 2.53
+/- 2.90 12.4 9.68 11.2 16.6 11.4 9.77 20.5 11.7 13.2 8.23 10.9 10.2 20.9
+/- 2.48
+/- 2.69
+/- 2.69
+/- 2.76
+/- 1.89
+/- 2.46
+/- 3.14
+/- 2.67
+/- 2.82
+/- 2.51
+/- 2.52
+/- 2.56
+/- 3.20 11.0 +/- 2.37 9.39 +/- 2.63 11.6 +/- 2.68 14.8 +/- 2.63 10.4 +/- 1.81 14.3 +/- 2.70 16.9 +/- 2.93 12.1 +/- 2.65 11.2 +/- 2.68 8.39 +/- 2.49 10.3 +/- 2.46 13.9 +/- 2.72 16.9 +/- 2.97
+/-
+/-
+/-
+/-
2.47 2.58 2.47 2.91 Qtr. Avg. +/- 2 s~d.
12.2 +/- 5.57 14.7 +/- 8.87 14.1 +/- 7.19 13.5 +/- 5.63 30 12.4 +/- 5.66 12.8 +/- 8.07 12.4 +/- 5.47
TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2014 1.OE-3 pCi/m3 + 2 Sigma Page 2 of 2 COLLECTION SAMPLING LOCATIONS DATE SS HIR BC ALL CP BASF FE NN July 01 July 08 July 15 July 22 July 29 August 05 August 12 August 19 August 26 September 02 September 10 September 16 September 23 September 29 11.9 +/- 2.64 10.8 +/- 2.54 13.4 +/- 2.70 10.2 +/- 2.49 10.5 +/- 2.58 10.4 +/- 2.54 15.3 +/- 2.89 13.4 +/- 2.78 11.1 +/- 2.57 14.3 +/- 2.80 8.96 +/- 2.30 11.3 +/- 2.79 19.4 +/- 3.11 12.5 +/- 3.11 Qtr. Avg. +/- 2 &d.
12.4 +/- 5.35 9.35 +/- 2.50 11.9 +/- 2.63 14.5 +/- 2.79 9.36 +/- 2.47 12.8 +/- 2.74 10.1 +/- 2.55 17.0 +/- 3.01 13.5 +/- 2.81 10.4 +/- 2.57 13.3 +/- 2.78 8.85 +/- 2.30 9.18 +/- 2.65 18.6 +/- 3.08 12.1 +/- 3.09 12.2 +/- 6.00 14.5 +/- 2.64 18.1 +/- 2.92 10.4 +/- 2.62 9.71 +/- 2.62 18.2 +/- 2.93 15.6 +/- 3.27 8.81 +/- 2.37 17.6 +/- 2.89 10.2 +/- 2.92 17.4 +/- 2.95 12.8 +/- 2.52 12.3 +/- 2.74 11.9 +/- 2.60 13.7 +/- 6.87 12.6 +/- 6.81 17.2 +/- 2.96 14.3 +/- 2.80 17.6 +/- 2.97 13.5 +/- 2.72 13.2 +/- 2.75 9.15 +/- 2.49 21.2 +/- 3.23 18.0 +/- 3.05 14.4 +/- 2.82 13.7 +/- 2.81 13.2 +/- 2.58 12.6 +/- 2.91 26.4 +/- 3.51 13.7 +/- 3.23 15.6 +/- 8.54 13.1 +/- 5.49 12.4 +/- 2.65 11.3 +/- 2.58 14.4 +/- 2.74 11.6 +/- 2.57 10.9 +/- 2.58 11.7 +/- 2.64 20.3 +/- 3.12 14.2 +/- 2.81 14.1 +/- 2.75 12.4 +/- 2.68 11.1 +/- 2.42 10.4 +/- 2.73 17.0 +/- 2.99 11.5 +/- 3.04 11.9 +/- 2.64 12.0 +/- 2.64 13.7 +/- 2.72 9.69 +/- 2.45 11.9 +/- 2.65 11.9 +/- 2.62 16.4 +/- 2.95 13.3 +/- 2.77 15.4 +/- 2.86 14.1 +/- 2.78 10.2 +/- 2.38 9.57 +/- 2.67 17.8 +/- 3.05 13.7 +/- 3.21 13.0 +/- 4.89 13.1 +/- 2.55 15.7 +/- 2.77 11.2 +/- 2.65 10.9 +/- 2.68 21.5 +/- 3.08 13.9 +/- 3.16 11.2 +/- 2.49 17.1 +/- 2.84 10.7 +/- 2.91 15.0 +/- 2.82 12.9 +/- 2.53 11.7 +/- 2.69 10.3 +/- 2.50 13.5 +/- 6.41 13.9 +/- 6.69 10.9 +/- 2.55 11.0 +/- 2.58 13.8 +/- 2.72 11.1 +/- 2.53 11.4 +/- 2.62 11.4 +/- 2.60 15.7 +/- 2.91 14.6 +/- 2.82 12.1 +/- 2.64 13.4 +/- 2.73 7.82 +/- 2.23 10.2 +/- 2.70 17.3 +/- 3.02 11.3 +/- 3.02 12.3 +/- 4.88 11.6 +/- 2.43 17.8 +/- 2.88 9.47 +/- 2.53 11.6 +/- 2.69 17.4 +/- 2.84 18.1 +/- 3.38 11.9 +/- 2.52 20.8 +/- 3.03 13.6 +/- 3.07 16.5 +/- 2.88 14.8 +/- 2.60 12.7 +/- 2.73 9.51 +/- 2.43 14.3 +/- 7.15 13.4 +/- 6.61 12.0 +/- 2.61 A
11.6 +/- 3.44 13.8 +/- 2.72 15.8 +/- 2.85 9.90 +/- 2.49 18.6 +/- 3.03 17.2 +/- 2.96 14.1 +/- 2.75 11.9 +/- 2.63 9.10 +/- 2.30 12.5 +/- 2.86 18.7 +/- 3.08 10.5 +/- 2.98 13.5 +/- 6.41 13.2 +/- 4.83 10.3 +/- 2.49 12.9 +/- 2.65 14.9 +/- 2.73 11.6 +/- 2.51 12.8 +/- 2.67 8.85 +/- 2.38 17.3 +/- 2.94 15.7 +/- 2.85 12.3 +/- 2.60 13.6 +/- 2.73 12.2 +/- 24.5 11.5 +/- 2.74 17.0 +/- 2.96 13.9 +/- 3.18 October 07 October 14 October 21 October 28 November 04 November 10 Noember 18 November 25 December 01 December 08 December 16 December 23 December 30 14.9 +/- 2.65 18.0 +/- 2.88 8.35 +/- 2.46 13.4 +/- 2.81 21.5 +/- 3.09 16.6 +/- 3.30 14.8 +/- 2.67 20.8 +/- 3.03 10.3 +/- 2.90 18.1 +/- 2.97 14.7 +/- 2.61 11.8 +/- 2.68 10.9 +/- 2.53 15.8 +/- 2.72 24.4 +/- 3.24 13.9 +/- 2.84 16.1 +/- 3.01 20.7 +/- 3.09 20.3 +/- 3.55 17.4 +/- 2.85 25.4 +/- 3.30 15.0 +/- 3.20 21.3 +/- 3.18 19.9 +/- 2.91 16.2 +/- 2.96 16.0 +/- 2.85 18.6 +/- 7.29 17.0 +/- 8.86 14.2 +/- 2.58 19.1 +/- 2.93 10.6 +/- 2.59 12.3 +/- 2.75 21.4 +/- 3.07 17.0 +/- 3.31 12.5 +/- 2.55 20.7 +/- 3.02
-0.90 +/- 2.06 21.1 +/- 3.12 16.9 +/- 2.72 15.2 +/- 2.87 11.3 +/- 2.56 16.0 +/- 7.86 15.0 +/- 7.62 31 14.2 +/- 2.56 18.6 +/- 2.91 11.3 +/- 2.63 12.8 +/- 2.76 20.1 +/- 2.99 19.7 +/- 3.45 12.3 +/- 2.53 20.8 +/- 3.03 12.7 +/- 3.03 33.1 +/- 3.67 17.4 +/- 2.74 17.5 +/- 2.99 11.0 +/- 2.52 17.0 +/- 11.9 14.7 +/- 9.39 14.8 +/- 2.55 18.7 +/- 2.91 8.79 +/- 2.44 12.7 +/- 2.74 20.1 +/- 2.95 17.9 +/- 3.32 13.9 +/- 2.59 20.4 +/- 2.96 15.1 +/- 3.13 0.69 +/- 1.80 34.1 +/- 3.44 14.5 +/- 2.80 12.1 +/- 2.55 16.9 t 12.8 14.3 +/- 8.45 Qtr. Avg. + 2 sd.
14.9 +/- 8.02 Ann. Avg.
2 sd 13.6 +/- 6.62
TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2014 1.OE-3 pCi/m3 +/- 2 Sigma Page I of 2 COLLECTION I SAMPLING LOCATIONS DATE SS HIR BC ALL CID BASF FE NN-C January 07 January 14 January 21 January 28 February 04 February 11 February 18 February 25 March 04 March 11 March 17 March 24 April 01 April 08 April 15 April 22 April 29 3.94 +/- 27.3
-16.4 +/- 18.1 0.65 +/- 20.5 2.03 +/- 17.9 0.02 +/- 18.7
-19.6 +/- 23.6 8.11 +/- 18.8 11.1 +/- 19.8
-18.4 +/- 33.0
-23.3 +/- 15.0 7.05 +/- 19.3 1.62 +/- 23.1
-4.32 +/- 15.8 11.9 +/- 19.0
-4.87 +/- 16.7 0.22 +/- 29.4
-14.1 +/- 16.5 15.5 +/- 25.8 7.52 +/- 14.6 1.05 +/- 29.2 5.10 +/- 16.2 2.74 +/- 28.4
-8.54 +/- 28.2
-3.97 +/- 19.6 4.01 +/- 24.5 3.86
-16.4 0.67 2.08 0.02
-20.2 8.45 11.5
-18.9
-23.8 7.20 1.66
-4.39 12.2
-4.98 0.23
-14.3 15.8 7.65 1.07 5.21
+/- 26.7
+/- 18.1
+/- 20.9
+/- 18.3
+/- 19.3
+/- 24.4
+/- 19.6
+/- 20.5
+/- 33.9
+/- 15.3
+/- 19.7
+/- 23.6
+/- 16.1
+/- 19.4
+/- 17.1
+/- 30.0
+/- 16.7
+/- 26.3
+/- 14.9
+/- 29.7
+/- 16.6 3.93 +/- 27.2
-16.7 +/- 18.5 0.67 +/- 21.0 2.11 +/- 18.5 0.02 +/- 19.3
-20.3 +/- 24.5 8.39 +/- 19.5 11.5 +/- 20.4
-16.5 +/- 29.7
-26.0 +/- 16.8 7.33 +/- 20.0 1.70 +/- 24.1
-4.49 +/- 16.5 12.3 +/- 19.7
-5.07 +/- 17.3 0.23 +/- 30.6
-14.4 +/- 16.9 15.9 +/- 26.5 7.70 +/- 15.0 1.07 +/- 29.9 5.30 +/- 16.9 2.79 +/- 29.0
-8.88 +/- 29.3
-4.22 +/- 20.9 4.09 +/- 25.0 3.90 +/-
-16.3 +/-
0.65 +/-
2.05 +
0.02 +/-
19.7 +
8.16 +/-
11.1 +
-15.9 +
-25.8 +/-
7.12 +
1.64 +/-
-4.34 +/-
11.9 +
-4.91 +/-
0.23 +
-14.1 +
27.0 18.0 20.4 18.0 18.8 23.7 19.0 19.8 28.6 16.6 19.4 23.4 15.9 19.0 16.8 29.8 16.6 3.48 +/-
-9.89 +/-
-11.5 +/-
3.56 +/-
18.5 +/-
2.46 +/-
-7.37 +/-
7.41 +/-
4.96 +/-
-9.00 +/-
-8.88 +/-
-10.6 +/-
0.48 +/-
-1.23 +/-
4.59 +/-
16.0 +/-
-1.97 +/-
21.9 20.4 22.3 29.3 18.5 19.2 21.8 19.6 31.9 17.2 19.8 26.0 15.6 19.7 23.7 21.2 14.3 26.3 15.8 33.8 17.6 3.42
-9.67
-11.4 3.53 18.3 2.44
-7.29 7.38 4.90
-8.84
-8.76
-10.4 0.47
-1.21 4.55 15.7
-1.93
-2.85
-12.0
-12.7 13.0
-3.65 38.5
-2.53 7.53
+/- 21.5
+/- 19.9
+/- 22.0
+/- 29.1
+/- 18.3
+/- 19.0
+/- 21.5
+/- 19.5
+/- 31.6
+/- 16.8
+/- 19.6
+/- 25.5
+/- 15.4
+/- 19.5
+/- 23.5
+/- 20.8
+/- 14.0
+/- 25.7
+/- 15.5
+/- 33.1
+/- 17.5
+/- 28.6
+/- 29.6
+/- 16.5
+/- 24.9 3.45
-9.68
-11.4 3.51 18.4 2.43
-7.30 7.35 4.92
-8.90
-8.78
-10.4 0.47
-1.22 4.56 15.8
-1.95
-2.85
-12.1
-12.7 13.0
-3.60 38.3
-2.54 7.48
+/- 21.6
+/- 20.0
+/- 22.0
+/- 28.9
+/- 18.4
+/- 19.0
+/- 21.6
+/- 19.4
+/- 31.7
+/- 17.0
+/- 19.6
+/- 25.6
+/- 15.5
+/- 19.5
+/- 23.5
+/- 20.9
+/- 14.2
+/- 25.8
+/- 15.6
+/- 33.2
+/- 17.4
+/- 28.3
+/- 29.4
+/- 16.5
+/- 24.7 3.37 +/-
-9.55 +/-
-11.2 +
3.46 +
18.1 +
2.39 +
-7.14 +
7.18 +
4.83 +
-8.74 +/-
-8.65 +/-
-10.2 +/-
0.46 +/-
-1.19 +
4.46 +
15.5 +
-1.90 +
-2.81 +
-11.8 +/-
-12.4 +/-
12.8 +
-3.53 +/-
37.6 +/-
-2.46 +/-
7.37 +/-
21.1 19.7 21.7 28.5 18.1 18.7 21.1 19.0 31.1 16.6 19.3 25.1 15.1 19.0 23.0 20.6 13.8 25.5 15.3 32.5 17.1 27.7 28.9 16.0 24.3 May 06 May 13 May 20 May 27 June 03 June 10 June 17 June 24 15.5 7.52 1.05 5.12 2.74
-8.63
-4.23 3.97
+/- 25.9
+/- 14.6
+/- 29.3
+/- 16.3
+/- 28.4
+/- 28.5
+/- 20.9
+/- 24.3
-2.90
-12.3
-12.9 13.2
-3.64 38.7
-2.57 7.58
+/-
+
+/-
+/-
2.83 +/- 29.1
-8.75 +/- 28.9
-4.01 +/- 19.8 4.05 +/- 24.7
+/- 28.6
+/- 29.8
+/- 16.7
+/- 25.0 32
TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2014 1.0E-3 pCi/m3 1 2 Sigma Page 2 of 2 COLLECTIONI SAMPLING LOCATIONS
[
DATE SS HIR BC ALL CP BASF FE NN-C July 01 July 08 July 15 July 22 July 29 August 05 August 12 August 19 August 26 September 02 September 10 September 16 September 23 September 29 October 07 October 14 October 21 October 28 November 04 Notember 10 November 18 No'tmber 25 December 01 December 08 December 16 December 23 December 30
-5.45 +/-
45.5 +/-
1.69 +/-
-1.25 +/-
-15.1 +
-28.8 +/-
-2.73 +/-
-6.92 +/-
0.51 +/-
-15.1 +/-
-11.7 +/-
4.43 +/-
3.67 +/-
14.7 +/-
3.46 +/-
3.47 +/-
11.8 +/-
1.31 +/-
-7.71 +/-
-11.1 +/-
25.2 +/-
-8.69 +/-
2.68 +/-
13.8 +/-
6.76 +/-
7.98 +/-
-9.20 +/-
22.5 34.5 26.5 27.7 19.2 30.7 21.5 21.1 33.7 20.3 38.5 15.7 21.1 37.8 19.1 22.3 25.6 6.37 17.2 25.0 25.6 34.7 16.1 15.6 15.7 30.9 23.2
-5.51 45.9 1.72
-1.28
-15.3
-29.3
-2.76
-7.00 0.52
-15.4
-11.8 4.45 3.68 14.7
+/- 22.8
+/- 34.8
+/- 27.0
+/- 28.4
+/- 19.6
+/- 31.2
+/- 21.8
+/- 21.4
+/- 34.4
+/- 20.7
+/- 38.6
+/- 15.8
+/- 21.2
+/- 37.7
-5.43 +/-
46.4 +/-
1.73 +/-
-1.26 +/-
-15.1 +/-
-29.3 +/-
-2.75 +/-
-6.97 +/-
0.53 +/-
-15.5 +/-
-11.9 +/-
4.51 +/-
3.76 +/-
14.9 +/-
22.5 35.2 27.2 28.1 19.4 31.2 21.8 21.3 34.6 20.8 39.0 16.0 21.7 38.4
-5.34 +/- 22.1 45.4 +/- 34.4 1.67 +/- 26.3
-1.24 +/- 27.6
-14.9 +/- 19.0
-29.1 +/- 31.0
-2.68 +/- 21.2
-6.84 +/- 20.9 0.51 +/- 33.6
-15.0 +/- 20.2
-11.6 +/- 38.1 4.42 +/- 15.7 3.66 +/- 21.1 14.5 +/- 37.4 3.39 +/- 18.7 3.43 +/- 22.0 11.7 +/- 25.3 1.30 +/- 6.35
-7.63 +/- 17.1
-11.0 +/- 24.8 25.2 +/- 25.6
-8.64 +/- 34.5 2.64 +/- 15.9 13.8 +/- 15.5 6.72 +/- 15.6 7.94 +/- 30.7
-9.18 +/- 23.1 31.9 +/- 20.8 34.8 +/- 36.2 12.4 +/- 26.3 9.88 +/- 23.6
-10.6 +/- 19.1
-0.04 +/- 29.5 3.44 +/- 22.3 2.70 +/- 17.7
-25.1 +/- 42.1 2.29 +/- 23.8 8.54 +/- 39.3 14.8 +/- 33.8 5.59 +/- 23.0
-22.3 +/- 34.1
-0.70 +/- 15.5 6.38 +/- 25.8
-7.33 +/- 24.6
-5.05 +/- 7.43
-2.41 +/- 13.7 9.68 +/- 21.1
-22.4 +/- 27.3 19.8 +/- 38.2 5.43 +/- 16.2
-1.93 +/- 12.1
-1.32 +/- 9.23 2.64 +/- 34.9
-2.99 +/- 19.4 31.5 34.7 12.3 9.81
-10.6
-0.04 3.42 2.67
-24.8 2.28 8.51 14.7 5.55
-21.9
-0.68 6.33
-7.25
-4.98
+/- 20.5
+/- 36.1
+/- 26.1
+/- 23.4
+/- 19.1
+/- 29.6
+/- 22.2
+/- 17.5
+/- 41.5
+/- 23.7
+/- 39.1
+/- 33.6
+/- 22.9
+/- 33.4
+/- 15.1
+/- 25.6
+/- 24.3
+/- 7.33 31.2 +/- 20.4 A
16.3 +/- 34.4 9.94 +/- 23.7
-10.6 +/- 19.0 3.48 +/- 19.3 3.53 +/- 22.7 12.0 +/- 25.9 1.32 +/- 6.44
-7.77 +/- 17.4
-11.2 +/- 25.2 25.5 +/- 25.9
-8.77 +/- 35.0 2.70 +/- 16.3 13.9 +/- 15.7 6.82 t 15.9 8.12 +/- 31.4
-9.27 +/- 23.3 3.51 3.52 12.0 1.34
-7.86
-11.4 25.8
-8.84 2.70 14.1 6.91 8.10
-9.32
+/- 19.4
+/- 22.6
+/- 26.1
+/- 6.51
+/- 17.6
+/- 25.5
+/- 26.2
+/- 35.3
+/- 16.2
+/- 15.9
+/- 16.1
+/- 31.3
+/- 23.5
-0.04 +/-
3.37 +/-
2.65 +/-
-24.6 +/-
2.26 +/-
8.42 +/-
14.8 +/-
5.53 +/-
-21.9 +/-
-0.67 +/-
6.30 +/-
-7.21 +/-
-4.96 +/-
-2.37 +/-
9.58 +/-
-22.0 +/-
19.7 +/-
5.41 +/-
-1.91 +/-
-1.30 +/-
2.61 +/-
-2.95 +/-
29.1 21.8 17.4 41.2 23.5 38.7 33.7 22.8 33.4 15.1 25.4 24.2 7.30 13.5 20.9 26.8 37.9 27.1 11.9 9.06 34.4 19.2 31.0 +/- 20.2 33.7 +/- 35.0 12.0 +/- 25.3 9.47 +/- 22.6
-10.4 +/- 18.7
-0.04 +/- 28.3 3.31 +/- 21.5 2.61 +/- 17.2
-23.9 +/- 40.0 2.25 +/- 23.3 8.25 +/- 38.0 14.3 +/- 32.7 5.42 +/- 22.4
-21.7 +/- 33.1
-0.66 +/- 14.7 6.22 +/- 25.1
-7.01 +/- 23.6
-4.91 +/- 7.22
-2.38 +/- 13.6 9.64 +/- 21.0
-22.2 +/- 27.0 19.7 +/- 38.0 5.39 +/- 16.1
-1.91 +/- 11.9
-1.29 +/- 9.04 2.60 +/- 34.4
-2.94 +/- 19.1
-2.31 +/-
9.37 +/-
-21.6 +/-
40.2 +/-
5.28 +/-
-1.87 +/-
-1.27 +/-
2.56 +/-
-2.87 +/-
13.2 20.4 26.4 40.6 15.7 11.7 8.90 33.8 18.6 A - Air sampler found inoperable 33
TABLE 3-5: GAMMA EMITTER CONCENTRATION IN FILTERED AIR Surry Power Station, Surry County, Virginia - 2014 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 Cs-137 Be-7 K-40 HIR Cs-1 34 Cs-1 37 Be-7 0.39 +/- 0.81 0.52 +/- 0.84 113 +/- 25.5 0.65 +/- 1.06 0.55 +/- 1.06 117 +/- 31.2 0.49 +/- 0.74
-0.09 +/- 0.65 167 +/- 27.3 0.88 +/- 0.73 0.11 +/- 0.72 118 +/- 26.2 0.69 +/- 0.74 0.36 +/- 0.76 91.2 +/- 26.4 0.44 +/- 0.72
-0.05 +/- 0.69 154 +/- 28.5 0.20 0.16 94.9 11.5 0.40
-0.40 116 0.39
-0.78 122 0.46
-0.17 94.1 18.2
+
+
0.55 0.44 18.5 6.52 0.51
+/- 0.71 0.24 +/- 0.50 74.2 +/- 19.0 100 +/- 39.7
+ 0.62
+/- 0.62
+ 23.0
+ 0.62
+/- 0.58
+/- 20.6 BC Cs-1 34 Cs-1 37 Be-7 ALL Cs-1 34 Cs-1 37 Be-7 K-40 0.53
-0.11 89.7
+/- 0.57
+/- 0.56
+/- 20.1 0.77 +/-
0.44 +/-
132 +/-
1.14 1.13 30.8
+/-
+/-
+/-
+
CP Cs-134 Cs-1 37 Be-7 0.15 +/- 0.69 0.20 +/- 0.66 167 +/- 29.6
-0.39 0.26 167
+/- 0.78
+/- 0.84
+/- 29.1 0.42 +/-
0.13 +/-
110 +/-
BAS F Cs-1 34 Cs-1 37 Be-7 0.53 0.04 120
+
+/-.
FE Cs-134 Cs-1 37 Be-7 0.46 +/-
-0.50 +/-
106 +/-
0.77 0.78 23.4 0.70 0.71 25.3 1.32 1.27 30.0 0.41 +/-
1.03 +/-
149 +/-
1.85 0.46 134 0.13 0.02 116
+
+/-
_+
+/-
+/-
+/-
1.30 1.14 33.4 1.39 1.07 36.0 0.67 0.62 26.7
-0.80
-0.30 92.0
-0.51 0.39 126 0.08 0.24 97.6
+/-
+/-
+/-
+/-
+/-
+/-
+/-
_+
_+
0.75 0.73 21.8 11.5 0.60 0.56 18.3 0.71 0.57 23.9 0.52 0.51 26.0 0.60 0.61 27.9 0.64 0.25 78.5
-0.12
-0.33 98.4 0.64 0.52 71.2
-0.45 0.15 85.6 0.09 0.60 116
-0.53 0.21 109
-0.07 0.06 82.1
+/-
+
+/-
+
+/-
+/-
+/-
+/-
+/-
0.78 0.47 23.5 0.91 0.74 28.8 0.75 0.67 19.8 1.15 0.98 32.8 0.74 0.63 25.6 1.17 1.04 27.1 0.61 0.53 22.6 132 +/- 82.4 119 +/- 46.7 119 +/- 26.9 105 +/- 37.6 101 +/- 38.0 135 +/- 62.1 96.8 +/- 51.0 NN-C Cs-1 34 Cs-1 37 Be-7
-0.89
-0.23 124
+/-
+
+
34
TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Power Station, Surry County, Virginia - 2014 pCi/Liter +/- 2 Sigma Page 1 of 3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C JANUARY Cs-1 34 Cs-1 37 Ba-140 La-i40 1-131 K-40 FEBRUARY Cs-1 34 Cs-1 37 Ba-140 La-140 1-131 K-40
-9.07 1.18 25.5 2.29 0.02 1230 5.37 5.24 27.8 7.78 0.45 174 2.46 0.29
-10.2
-0.50 0.29 1240 3.41 3.53 21.2 4.54 0.45 147
-7.86 0.31
-3.14
-0.82
-0.39 1280 MARCH Cs-1'34 Cs-1 37 Ba-140 La-140 1-131 K-40 Sr-89 Sr-90 APRIL Cs-1 34 Cs-1 37 Ba-1 40 La-1 40 1-131 K-40
-1.26
-4.13
-1.85
-3.27 0.17 1280
-4.81
-1.52 7.68 1.65 0.22 1240
-1.15 2.10
-0.45 2.20 0.06 1240 3.13 3.23 18.4 4.35 0.47 132 3.45 3.54 17.2 4.91 0.51 120
-2.63 1.26
-2.44
-2.26 0.03 1330
-0.80 0.16
-9.37 0.60 0.13 1190 3.98 0.35 3.35 2.97 14.5 4.83 0.32 108 2.99 2.49 12.9 3.42 0.50 116 3.08 0.41
-4.63 0.69
-7.41
-0.32
-0.04 1120
-2.37
-0.81
-1.08 1.31
-0.47 1120 4.72 4.71 23.3 5.53 0.45 164 2.81 2.73 12.9 4.74 0.35 118 3.86 3.69 18.5 5.81 0.48 141 3.13 3.16 15.3 4.15 0.48 113 2.72 2.81 14.0 3.70 0.50 109
-5.41 3.09
-1.04
-5.39 0.37 1150 3.86 4.16 20.2 5.75 0.50 134
-6.11 3.54 1.87
-0.30
-0.15 1260 35
TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Power Station, Surry County, Virginia - 2014 pCi/Liter +/- 2 Sigma Page 2 of 3 I
COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C MAY Cs-1 34 Cs-1 37 Ba-140 La-1 40 1-131 K-40 Th-228 JUNE Cs-1 34 Cs-137 Ba-140 La-140 1-131 K-40 Sr-89 Sr-90 JULY Cs-1 34 Cs-1 37 Ba-140 La-140 1-131 K-40 1.54 1.34 9.32 2.89
-0.24 1520
-8.89
-0.39 6.02 2.41
-0.09 1560
-3.47
-1.11
-19.0
-1.23
-0.08 1410
-2.89
-0.17
-3.59
-0.09
-0.46 1400 4.12 4.52 23.0 5.34 0.34 183
-4.31
-1.49 18.8 5.08 0.01 1270 4.08 4.16 19.5 5.40 0.35 164
-9.19 2.74 8.61
-1.25
-0.39 1270 27.3
-5.63
-1.76 1.50 2.29
-0.16 1230 3.55 3.26 19.1 5.42 0.34 135 5.26 5.15 25.2 6.88 0.23 196 2.93 3.99 18.0 6.45 0.39 156 3.63
-0.88
-17.4 8.17
-0.09 1450
-1.86 1.26
-4.46
-0.03 16.4
-0.67
-0.34 1280 0.42 1.09 16.4 2.48 0.16 1390 4.98 5.05 26.5 7.26 0.32 157 2.82 0.40 5.02 4.54 21.9 5.73 0.39 151 2.60 2.85 19.2 4.91 0.41 101 4.61 4.49 21.5 6.26 0.33 140 14.1 5.06 4.75 21.0 6.92 0.30 177 4.17 4.43 19.3 6.60 0.32 197 2.85 2.63 17.9 5.74 0.38 92.4 0.17
-1.85
-1.17
-2.58
-0.31 1460 1.65 1.97
-2.92 0.69
-0.05 1320 AUGUST Cs-1 34 Cs-I 37 Ba-140 La-140 1-131 K-40 36
TABLE 3-6: GAMMA EMITTER AND STRONTIUM CONCENTRATIONS IN MILK Surry Power Station, Surry County, Virginia - 2014 pCi/Liter +/- 2 Sigma Page3 of 3 COLONIAL NUCLIDE EPPS PARKWAY WILLIAMS-C SEPTEMBER Cs-134
-3.63 +/- 3.48
-2.81
+/- 3.72 0.48 +/- 4.00 Cs-137
-1.72 +/- 3.83 2.61
+/- 4.26 1.01
+/- 3.81 Ba-140
-10.2 +/- 24.0 10.0
+/- 26.2 14.7 +/- 25.7 La-140
-0.12 +/- 7.38
-2.40 +/- 8.78
-2.76 +/- 6.79 1-131
-0.99 +/- 0.49 0.10 +/- 0.54
-0.41
+/- 0.50 K-40 1300 +/- 138 1230 +/- 142 1350 +/- 119 Sr-89 3.06 +/- 2.71 Sr-90 1.85
+/- 0.54 OCTOBER Cs-134
-5.19 +/- 5.69 0.68 +/- 3.64
-6.48 +/- 5.29 Cs-137 1.30
+/- 5.95 2.62 +/- 4.10
-0.79 +/- 5.10 Ba-140 11.6
+/- 31.4 16.0
+/- 19.9 0.36 +/- 27.3 La-140
-1.74 +/- 8.17 1.58
+/- 6.64
-11.9 +/- 10.1 1-131
-0.16 +/- 0.25
-0.18 +/- 0.24
-0.05 +/- 0.25 K-40 1320 +/- 188 1200 +/- 159 1330 +/- 214 NOVEMBER Cs-134 2.28 +/- 3.90
-4.37 +/- 3.08
-3.43 +/- 3.03 Cs-137 1.74
+/- 4.17 0.40 +/- 3.17 1.20 +/- 3.34 Ba-140 6.79 +/- 17.8
-4.63 +/- 13.9
-7.20 +/- 16.6 La-140
-2.49 +/- 5.65
-2.19 +/- 3.89 1.12 +/- 4.68 1-131
-0.70 +/- 0.50 0.75 +/- 0.51
-0.35 +/- 0.52 K-40 1340 +/- 150 1380 +/- 117 1290 +/- 143 DECEMBER Cs-134
-2.34 +/- 4.19 1.71
+/- 2.48
-1.83 +/- 3.33 Cs-137
-2.07 +/- 4.36 3.43 +/- 2.68 0.35 +/- 3.19 Ba-140
-26.9 +/- 27.6 7.60 +/- 18.4 7.24 +/- 22.3 La-140 2.43 +/- 6.77
-0.19 +/- 4.31 8.03 +/- 6.45 1-131
-0.17 +/- 0.26
-0.38 +/- 0.27
-0.28 +/- 0.44 K-40 1240 +/- 115 891
+/- 117 1270 +/- 113 Sr-89 1.85 +/- 2.57 Sr-90 0.85 +/- 0.62 37
TABLE 3-7: GAMMA EMITTER CONCENTRATION IN FOOD PRODUCTS Surry Power Station, Surry County, Virginia - 2014 pCi/kg (wet): 2 Sigma SAMPLING COLLECTION SAMPLE LOCATIONS DATE TYPE Page I of 1 BROCK FARM Cs-134 10/28/2014 Corn
-13.0 +/- 17.4 Cs-134 10/28/2014 Peanuts
-6.77 +/- 15.9 Cs-1 37
-4.03 +/- 15.7 Cs-1 37 12.1 +/- 17.8 ISOTOPE 1-131 5.98 +/- 35.8 1-131 8.06 +/- 29.3 K-40 4180 +/- 563 K-40 6420 +/- 662 I
Cs-134 Cs-1 37 12/4/2014 Soybeans
-0.88 +/- 9.63 0.21 +/- 9.81 1-131 K-40 0.65 +/- 18.3 13900 +/- 605 SLADE FARM 38
TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN WELL WA TER Surry Power Station, Surry County, Virginia - 2014 pCi/Liter - 2 Sigma Page I of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE SS 3/4/2014 6/17/2014 9/2/2014 12/8/2014 3/4/2014 6/17/2014 9/2/2014 12/8/2014 3/4/2014 6/17/2014 9/2/2014 12/8/2014 Mn-54
-1.70 +/- 2.91
-0.36 +/- 3.01
-0.02 +/- 1.79 0.84 +/- 3.46 Nb-95 0.70 +/- 2.89 0.65 +/- 3.40 0.72 +/- 1.88 0.49 +/- 3.22 Ba-140 1.68 +/- 14.0 2.58 +/- 15.7 1.90 +/- 9.98 2.77 +/- 14.7 Mn-54
-6.92 +/- 3.35 0.26 +/- 2.18 0.58 +/- 3.06
-3.82 +/- 4.74 Nb-95
-1.67 +/- 3.51
-0.72 +/- 2.40 2.20 +/- 3.15
-0.15 +/- 4.64 Ba-140
-0.39 +/- 16.4
-4.78 +/- 11.8 0.85 +/- 13.7 4.32 +/- 17.5 Co-58
-0.07 +/- 2.66 0.02 +/- 3.34
-0.08 +/- 1.95 0.17 +/- 3.28 Zr-95 4.03 +/- 5.13 3.75 +/- 5.67 0.46 +/- 3.40 0.22 +/- 5.87 La-140
-1.26 +/- 3.96
-1.99 +/- 5.23
-0.40 +/- 3.25 1.32 +/- 3.97 Co-58
-0.54 +/- 3.70
-1.26 +/- 2.64
-1.74 +/- 2.98
-0.33 +/- 4.52 Zr-95 0.90 +/- 5.70 0.94 +/- 4.49 0.66 +/- 4.76 0.57 +/- 8.69 La-140 2.43 +/- 4.55
-2.48 +/- 3.16
-4.22 +/- 5.53 0.98 +/- 6.08 Fe-59
-4.10 +/- 6.26 8.05 +/- 7.01 5.65 +/- 3.54 3.16 +/- 7.03 1-131 0.06 +/- 0.60
-0.53 +/- 0.33
-0.28 +/- 0.38
-0.44 +/- 0.21 H-3 668 +/- 591
-84.0 +/- 746
-116 +/- 810
-93.5 +/- 753 Fe-59
-2.79 +/- 6.69 0.22 +/- 5.14 0.14 +/- 6.61 3.08 +/- 9.46 1-131 0.09 +/- 0.57 0.00 +/- 0.35
-0.91 +/- 0.41
-0.17 +/- 0.17 H-3 197 +/- 551
-280 +/- 717 44.7 +/- 831 185 +/- 788 Co-60
-2.31 +/- 2.67
-2.99 +/- 3.18 0.35 +/- 1.88
-0.77 +/- 2.62 Cs-I 34
-2.23 +/- 3.34
-6.08 +/- 3.48 1.15 +/- 1.87 3.64 +/- 6.03 Zn-65
-4.07 +/- 7.00 2.57 +/- 8.00
-4.32 +/- 3.59 1.24 +/- 6.87 Cs-137
-2.46 +/- 3.36 3.99 +/- 3.38
-0.23 +/- 1.92 2.75 +/- 3.87 HIR 3/4/2014 6/17/2014 9/2/2014 12/8/2014 3/4/2014 6/17/2014 9/2/2014 12/8/2014 3/4/2014 6/17/2014 9/2/2014 12/8/2014 Co-60 0.45 +/- 3.70
-2.40 +/- 3.01
-1.12 +/- 3.22 0.48 +/- 4.80 Cs-134 1.09 +/- 3.80
-0.22 +/- 2.78
-4.15 +/- 2.84 2.98 +/- 5.41 Zn-65
-5.27 +/- 7.48 1.10 +/- 5.37
-1.80 +/- 6.30
-6.88 +/- 10.9 Cs-137 0.83 +/- 3.48 0.24 +/- 2.74
-0.69 +/- 2.78 1.24 +/- 5.37 39
TABLE 3-8: GAMMA EMITTER AND TRITIUM CONCENTRA TIONS IN WELL WA TER Surry Power Station, Surry County, Virginia - 2014 pCi/Ijter +/- 2 Sigma Page 2 of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE CS 3/4/2014 6/17/2014 9/2/2014 12/8/2014 3/4/2014 6/17/2014 9/2/2014 12/8/2014 Mn-54
-0.19 +/- 2.37
-3.03 +/- 3.04
-1.65 +/- 2.67
-0.88 +/- 2.79 Nb-95
-1.02 +/- 2.45
-0.13 +/- 3.29 1.91 +/- 2.43 0.57 +/- 2.82 Ba-140
-1.73 +/- 11.5 1.37 +/- 14.4 4.10 +/- 14.3 8.99 +/- 10.9 Co-58 0.71 +/- 2.34
-1.16 +/- 2.99
-2.26 +/- 2.44
-0.80 +/- 2.60 Zr-95
-1.18 +/- 4.00 3.97 +/- 5.35
-1.00 +/- 4.99
-1.74 +/- 4.98 La-140 0.20 +/- 3.66 1.43 +/- 4.20
-1.06 +/- 4.17
-0.55 +/- 3.37 Fe-59
-4.82 +/- 5.07 4.21 +/- 5.88
-0.29 +/- 4.60
-0.40 +/- 5.90 1-131
-0.11 +/- 0.15
-0.06 +/- 0.33 0.02 +/- 0.42
-0.49 +/- 0.22 Co-60 0.15 +/- 2.47
-0.95 +/- 3.07 1.44 +/- 2.41
-0.89 +/- 2.80 Cs-1 34 0.80 +/- 2.72 1.63 +/- 4.07
-1.77 +/- 2.80
-2.21 +/- 3.09 Zn-65 2.02 +/- 5.08
-3.57 +/- 6.79
-1.93 +/- 5.01
-9.09 +/- 6.42 Cs-137
-0.50 +/- 2.39
-0.44 +/- 3.15 0.34 +/- 2.87 1.56 +/- 2.95 3/4/2014 6/17/2014 9/2/2014 12/8/2014 847 630 235 62.2 H-3
+_
+
598 865 854 777 40
TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS IN RIVER WA TER Surry Power Station, Surry County, Virginia - 2014 pCi/liter +/- 2 Sigma Page 1 of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE Mn-54 Co-58 SD 1/14/2014 2/11/2014 3/17/2014 4/7/2014 5/13/2014 6/10/2014 7/8/2014 8/12/2014 9/10/2014 10/14/2014 11/10/2014 12/8/2014
-1.32
-0.42
-0.91 1.31 1.15 0.06 0.34
-0.74 0.27
-1.71 2.95
-0.21
+
+
+
+/-
2.84 1.95 3.33 2.09 2.76 1.10 2.67 1.08 1.78 2.01 3.56 2.40
-1.94 0.69
-1.14 0.43 0.59
-1.29
-1.86
-0.36
-0.25
-0.55 0.00
-0.10
+
+
+
+
+
- +/-
3.15 2.13 3.71 1.93 2.71 1.10 3.15 1.14 2.09 2.23 3.41 2.05 Fe-59
-0.46 +/- 6.26
-0.91
+/- 4.21
-0.15 +/- 8.11 0.81
+/- 4.28
-0.31
+/- 5.90
-0.46 +/- 2.09 2.19 +/- 6.22 0.67 +/- 2.25 5.44 +/- 4.25
-2.95 +/- 4.41 1.74 +/- 6.65 1.07 +/- 4.23 1-131 0.45 +/- 5.58 0.97 +/- 4.17
-0.52 +/- 6.06 0.56 +/- 4.28
-0.19 +/- 5.15
-0.91 +/- 2.06
-4.40 +/- 5.67
-1.14 +/- 2.09
-0.40 +/- 5.37
-3.51 +/- 6.39
-2.29 +/- 5.75
-2.03 +/- 3.47
-0.33 1.00
-0.33
-1.94
-0.32 0.84
-1.05 0.74 0.58
-0.23 1.77 2.12
_+
+
_+
+_
+/-
3.43 2.17 3.73 2.19 2.63 1.03 2.67 1.15 1.61 1.79 3.48 2.66
-4.98 1.03
-2.27
-2.86
-4.64 1.37
-7.22
-3.71
-4.17 2.81 6.94
-0.24 Co-60 Zn-65
+
+/-
+
+
+
-+/-
+/-
+
7.16 4.12 8.80 4.59 5.27 2.62 6.53 2.56 4.42 4.32 6.99 4.74 Nb-95 1/14/2014 2/11/2014 3/17/2014 4/7/2014 5/13/2014 6/10/2014 7/8/2014 8/12/2014 9/10/2014 10/14/2014 11/10/2014 12/8/2014 1/14/2014 2/11/2014 3/17/2014 4/7/2014 5/13/2014 6/10/2014 7/8/2014 8/12/2014 9/10/2014 10/14/2014 11/10/2014 12/8/2014
-1.66 0.50
-2.62 1.85 2.75 0.32
-1.07
-0.16
-0.05
-0.53 0.04 0.64
+
+
+
- 1
+
3.20 2.10 3.84 2.18 3.13 1.14 3.00 1.18 2.07 2.07 3.62 2.20 Zr-95 1.01
+/- 5.64
-1.73 +/- 3.47 1.77 +/- 6.48
-1.69 +/- 3.48
-1.74 +/- 4.91 1.17 +/- 2.03
-0.40 +/- 5.39
-0.34 +/- 1.99
-1.53 +/- 3.53 0.76 +/- 3.87 1.23 +/- 6.98
-0.55 +/- 4.20 La-140
-2.08 +/- 3.73
-2.30 +/- 3.36
-7.44 +/- 7.35 1.31
+/- 3.47
-2.21 +/- 3.60 0.10 +/- 1.49 3.40 +/- 5.34
-0.53 +/- 1.92
-0.63 +/- 3.76
-2.28 +/- 4.01
-3.64 +/- 6.26
-0.30 +/- 2.21 Cs-134
-2.91 2.12 1.43
-2.38
-5.28 0.53
-3.98
-3.84
-0.28 0.87
-2.74
-4.41
+/-
+_
+
+/-
_+
_+
3.23 1.89 3.43 2.57 3.43 1.61 2.87 1.16 2.17 2.15 3.70 2.63 1.38
-1.00
-1.63 0.55
-2.75 0.28 2.03
-1.00 0.34 0.12
-1.25
-0.72 Cs-1 37
- -p
+
+
+/-
+/-
+
- +/-
3.11 2.18 3.82 2.11 2.84 1.23 3.06 1.16 1.88 1.93 3.69 2.60 Ba-140 H-3 K-40 Th-228 3.38 3.27
-8.24 4.42
-3.38 3.42
-3.22
-1.86 6.27 17.7
-1.54 1.14
+/-
+/-
+/-
+/-.
+/-
+/-
_+
15.7 9.63 19.3 10.6 12.6 5.72 15.6 5.58 13.5 14.0 17.0 9.68 71.2 +/- 856 225 + 627 49.9 120 93.7 0.00 + 1150 119 121
+
_+
+
+
+
26.6 64.0 29.6 42.6 38.4 9.00 +/- 6.33
-570 +/- 956 110 +/- 47.2 Th-232 10/14/2014 10.7 +/- 6.52 41
TABLE 3-9: GAMMA EMITTER AND TRITIUMCONCENTRATIONS IN RIVER WATER Surry Power Station, Surry County, Virginia - 2014 pCi/Liter +/- 2 Sigma Page2 of 2 SAMPLING COLLECTION LOCATIONS DATE ISOTOPES Mn-54 Co-58 SW-C 1/14/2014 2/11/2014 3/17/2014 4/8/2014 5/13/2014 6/10/2014 7/8/2014 8/12/2014 9/10/2014 10/14/2014 11/10/2014 12/8/2014
-0.16
-1.63 1.32 0.92
-1.29 0.52 3.25 1.92
-0.71
-1.34 0.74 2.43
+/-
+/-
+/-
+
+/-
+/-
+/-
+
+
+
+
+
3.26 2.32 2.77 2.34 2.87 1.03 2.60 1.20 2.17 1.70 2.58 2.53
-1.93 0.21 0.20
-1.13 0.80
-0.17 1.49 0.70
-0.10
-0.07
-0.44 0.71
+
+
+
+
+
+/-
+/-
+
+
+/-
+
+/-
3.55 2.36 2.76 2.39 2.88 1.03 2.56 1.28 2.28 2.00 2.50 2.57 Fe-59
-2.62 +/- 5.24 1.04 +/- 4.64 1.58 +/- 5.45 1.28 +/- 5.11 0.64 +/- 4.98
-0.25 +/- 2.26
-3.77 +/- 5.46 0.39 +/- 2.55
-2.31 +/- 5.04
-4.81 +/- 4.03
-2.56 +/- 5.75 4.46 +/- 5.44 1-131
-1.01
+/- 5.69 2.64 +/- 5.18
-2.28 +/- 5.92 0.21
+/- 4.86
-2.19 +/- 5.58
-0.89 +/- 2.01
-5.02 +/- 4.98 0.05 +/- 2.59
-0.36 +/- 6.05
-0.80 +/- 5.56
-6.27 +/- 5.24
-0.44 +/- 3.40 Co-60 Zn-65 3.16
-0.22 0.00 0.58 4.27
-0.16
-4.29 0.48 0.60 0.65
-1.04
-0.08
+
+/-
+
+/-
+/-
+
+
+/-
+
+/-
+
+
2.48 2.17 2.37 2.47 2.72 0.99 2.64 1.26 2.01 1.81 2.97 2.82
-4.36
-1.86
-8.24
-8.62
-5.11
-6.80
-9.28
-3.76 1.14
-2.26
-6.30
-6.47
+/-
+/-
+/-
+/-
+
+/-
+
+/-
+
+
+/-
+/-
5.47 5.40 5.67 4.99 6.10 2.46 5.94 2.51 5.80 4.38 5.91 5.70 Nb-95 1/14/2014 2/11/2014 3/17/2014 4/8/2014 5/13/2014 6/10/2014 7/8/2014 8/12/2014 9/10/2014 10/14/2014 11/10/2014 12/8/2014 1/14/2014 2/11/2014 3/17/2014 4/8/2014 5/13/2014 6/10/2014 7/8/2014 8/12/2014 9/10/2014 10/14/2014 11/10/2014 12/8/2014 1.27 1.97 3.46 1.39
-0.71
-0.42 1.56 0.09 1.37 0.10 0.36 0.91
+
+
+
+
+
+
+
+/-
+
+
+
+
3.36 2.47 2.80 2.37 2.80 1.10 2.80 1.30 2.40 1.95 2.55 2.70 Zr-95
-0.46 +/- 6.56
-3.37 +/- 3.91
-5.63 +/- 4.87 2.94 +/- 4.14 1.24 +/- 5.12 1.01
+/- 1.94
-1.94 +/- 4.49
-0.90 +/- 2.24 1.97 +/- 4.07 1.87 +/- 3.41 3.21 +/- 4.46
-2.48 +/- 4.68 La-140
-1.44 +/- 3.27 0.54 +/- 3.98
-1.94 +/- 3.86
-1.37 +/- 3.73
-0.23 +/- 4.06
-0.45 +/- 1.62 1.85 +/- 3.92 0.72 +/- 1.82 0.95 +/- 4.60 1.48 +/- 3.80 0.93 +/- 4.62 1.90 +/- 3.00 Cs-1 34 Cs-1 37 1.02
-5.06
-0.06
-3.93
-4.89
-0.17
-4.66
-2.67 1.18
-0.17
-3.70
-1.38
+
+
+
+/-
+/-
+/-
+/-
+
+/-
+/-
+
+/-
3.31 2.77 5.27 2.81 3.52 1.23 2.90 1.40 2.32 3.08 3.10 3.49
-1.79 1.15
-0.63
-0.69 1.35 0.26 2.06 0.65 1.47
-0.18 0.84 0.22
+
+/-
+
+/-
+
+
+
+/-
+
+/-
+/-
+/-
3.88 2.66 2.72 2.59 3.19 1.13 2.81 1.33 2.16 1.80 3.00 2.90 Ba-140 H-3 K-40 Th-228
-6.16
-4.87
-4.00 2.64 8.73
-0.38 6.49
-0.93
-7.08 4.90
-6.18
-5.52
+/-
+/-
+/-
+
+
+/-
+
+
+
+
+
+
16.4 13.3 15.4 12.0 15.1 5.34 13.4 6.60 16.1 11.9 13.7 10.9
-19.4 +/- 841 303 +/- 637
-642 +/- 995
-596 +/- 953 47.2 +/- 28.6 105 +/- 41.9 70.9 +/- 46.8 79.8 +/- 50.8 9.57 +/- 4.76 42
TABLE 3-10: GAMMA EMITTER CONCENTRATIONS IN SILT Surry Power Station, Surry County, Virginia - 2014 pCi/kg (dry) +/- 2 Sigma Page 1 of I SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPE SD Cs-134 3/11/2014 35.6 +/- 53.8 9/10/2014 16.5 +/- 63.2 Cs-137 147 +/- 73.0 230 +/- 116 K-40 15200 +/- 1420 20200 +/- 2120 Th-232 1090 +/- 194 1290 +/- 258 Th-228 1090 +/- 116 1800 +/- 181 Ra-226 2520 +/- 1630 Be-7 3/11/2014 9/10/2014 2110 +/- 809 Cs-134 CHIC-C 3/11/2014
-10.9 +/- 59.0 9/10/2014 29.4 +/- 54.3 Cs-137 K-40 297 +/- 85.6 12800 +/- 1450 199 +/- 87.8 19300 +/- 1880 Th-232 1140 +/- 185 1520 +/- 306 Th-228 1300 +/- 140 1780 +/- 165 3/11/2014 9/10/2014 Ra-226 3440 +/- 2050 43
TABLE 3-11: GAMMA EMITTER CONCENTRATIONS IN SHORELINE SEDIMENT Surry Power Station, Surry County, Virginia - 2014 pCi/kg (dry) +/- 2 Sigma Page 1 of I SAMPLING COLLECTION LOCATIONS DATE ISOTOPE HIR Cs-134 2/11/2014 10.8 +/- 24.0 8/19/2014
-19.3 +/- 20.0 Cs-I 37 7.81 +/- 22.4
-5.42 +/- 18.2
-31.1
+/- 43.8
-7.89 +/- 29.1 K-40 7890 +/- 838 6520 +/- 781 4770 +/- 894 1580 +/- 473 Th-228 95.0 +/- 50.9 102 +/- 69.3 2390 +/- 139 1290 +/- 88.8 Th-232 CHIC-C 2/11/2014 132 +/- 44.3 8/19/2014
-14.8 +/- 28.9 2450 +/- 244 1410 +/- 125 Ra-226 2/11/2014 8/19/2014 1770 +/- 968 44
TABLE 3-12: GAMMA EMITTER CONCENTRATION IN FISH Surry Power Station, Surry County, Virginia - 2014 pCi/kg (wet) + 2 Sigma Page I of 1 SAMPLING COLLECTION SAMPLE LOCATION DATE TYPE ISOTOPE SD 4/8/2014 4/8/2014 10/7/2014 10/7/2014 4/8/2014 4/8/2014 10/7/2014 10/7/2014 Catfish White Perch Catfish White Perch Catfish White Perch Catfish White Perch K-40 2590 +/- 703 1230 +/- 1150 2120 +/- 991 2430 +/- 1310 Co-60 15.4 +/- 29.3 0.73 +/- 40.1 22.2 +/- 31.4
-21.4 +/- 53.1 Mn-54 9.12 +/- 32.9 4.11 +/- 35.7 1.84 +/- 36.0
-38.5 +/- 62.7 Zn-65 27.4 +/- 67.7
-25.3 +/- 66.2
-78.8 +/- 106 36.5 +/- 137 Co-58 13.8 +/- 30.5
-30.8 +/- 47.7 6.91 +/- 39.7
-3.43 +/- 69.4 Cs-134
-25.6 +/- 33.7
-0.53 +/- 35.6
-6.33 +/- 41.3
-13.4 +/- 79.1 Fe-59 62.8 +/- 67.5
-26.7 +/- 71.1
-52.4 +/- 86.9 10.4 +/- 156 Cs-1 37 10.8 +/- 35.5
-49.1 +/- 35.9 0.61 +/- 36.8 51.0 +/- 68.9 45
TABLE 3-13: GAMMA EMITTER CONCENTRATIONS IN OYSTERS Surry Power Station, Surry County, Virginia - 2014 pCi/kg (wet) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE POS MP Mn-54 3/12/2014
-0.14 +/- 23.0 9/10/2014
-10.5 +/- 40.4 Zn-65 3/12/2014
-14.7 +/- 51.0 9/10/2014
-62.9 +/- 104 Mn-54 3/12/2014 19.1
+/- 26.0 9/10/2014 14.4 +/- 21.7 Zn-65 3/12/2014
-5.11
+/- 54.2 9/10/2014
-24.9 +/- 57.1 Mn-54 3/12/2014 6.04 +/- 11.9 9/10/2014
-8.01
+/- 26.0 Zn-65 3/13/2013
-26.1
+/- 25.4 9/10/2014
-0.56 +/- 62.5 Co-58
-43.9 +/- 28.1
-12.3
+/- 48.9 Cs-134
-15.1
+/- 25.9 27.5 +/- 49.4 Co-58 18.0
+/- 29.8
-2.70 +/- 29.2 Cs-134
-18.0 +/- 36.5 9.59 +/- 28.2 Co-58 4.42 +/- 13.4
-18.0 +/- 29.9 Cs-134 9.74 +/- 12.5 13.4 +/- 30.8 Fe-59 30.3 +/- 53.5
-53.5 +/- 87.2 Cs-137 9.47 +/- 24.5 18.0 +/- 42.2 Fe-59 16.3 +/- 52.9
-14.2 +/- 56.5 Cs-1 37 21.1 +/- 28.9
-7.86 +/- 30.3 Fe-59
-5.24' +/- 29.0 41.9 +/- 63.5 Cs-1 37 3.45 +/- 11.5
-21.1
+/- 29.1 Co-60 13.7 +/- 20.9 25.8 +/- 43.2 K-40 595 +/- 461 1560 +/- 1010 Co-60 5.92 +/- 19.3 25.1
+/- 28.5 K-40 618 +/- 454 646 +/- 642 Co-60
-8.79 +/- 12.3 19.3 +/- 25.0 K-40 1270 +/- 608 LC 46
TABLE 3-14: GAMMA EMITTER CONCENTRA TIONS IN CLAMS Surry Power Station, Surry County, Virginia - 2014 pCi/kg (wet) +/- 2 Sigma Page 1 of I SAMPLING COLLECTIONJ LOCATIONS DATE ISOTOPE JI Mn-54 3/11/2014 6.28 +/- 20.3 9/10/2014 0.63 +/- 34.1 Zn-65 3/11/2014
-19.2
+/- 41.7 9/10/2014 5.59 +/- 70.7 Mn-54 3/11/2014 1.98 +/- 19.6 9/10/2014
-18.2 +/- 29.2 Zn-65 3/11/2014
-30.1
+/- 38.5 9/10/2014
-89.5 +/- 85.5 SD Co-58
-7.23 +/- 20.8
-33.6 +/- 31.8 C9-134 1.09 +/- 20.8
-1.41
+/- 38.1 Co-58
-8.86 +/- 20.3
-7.23 +/- 33.2 Cs-134
-29.3 +/- 19.1
-12.2 +/- 43.3 Co-58
-3.95 +/- 22.8 9.23 +/- 37.0 Cs-1 34
-37.7 +/- 22.3
-17.8 +/- 40.6 Fe-59 11.4 +/- 41.3 52.5 +/- 74.1 Cs-1 37
-1.33
+/- 18.5
-14.4 +/- 35.0 Fe-59
-42.6
+/- 50.8
-53.5 +/- 75.8 Cs-137
-0.93 +/- 19.1 10.1
+/- 36.9 Fe-59 21.3 +/- 50.5
-7.86
+/- 86.8 Cs-137
-4.12 +/- 19.2
-15.6
-5.96 +/- 16.5
-2.83 +/- 28.5 K-40 381
+/- 342 Co-60
-2.70 +/- 17.7
-1.77 +/- 29.5 Mn-54 CHIC-C 3/11/2014 3.44 +/- 18.8 9/10/2014
-4.42 +/- 34.1 Zn-65 3/11/2014
-87.2 +/- 45.0 9/10/2014
-54.7 +/- 88.8 Co-60 14.9 +/- 19.0 13.8 +/- 25.0 K-40 736 + 566 47
TABLE 3-15: GAMMA EMITTER CONCENTRATIONS IN CRABS Surry Power Station, Surry County, Virginia - 2014 pCi/kg (wet) +/- 2 Sigma Page 1 of 1 SAMPLING COLLECTION1 LOCATIONS DATE ISOTOPE SD K-40 6/10/2014 1530 +/- 630 Co-60
-3.84 +/- 28.5 Mn-54 15.5
+/- 30.5 Zn-65
-73.1
+/- 64.2 Co-58
-14.9 +/- 30.9 Cs-134
-22.5 +/- 34.6 Fe-59 59.1
+/- 54.3 Cs-137 25.0 +/- 31.5 48
- 4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2014 and tabulated in Section 3, are discussed below.
The procedures and specifications followed in the laboratory for these analyses are as required in 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 2014 was from external sources, such as fallout from nuclear weapons tests (cesium-137) and naturally occurring radionuclides.
Naturally occurring nuclides such as beryllium-7, potassium-40, radium-226, thorium-228 and thorium-232 were detected in numerous samples.
The following is a discussion and summary of the results of the environmental measurements taken during the 2014 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. In 2013, Panasonic UD-814 environmental TLDs replaced Harshaw environmental TLDs that were used since 2001. Benchmarking showed that Panasonic UD-814 TLDs were the industry best environmental TLD with improved precision over the Harshaw TLDs. Along with implementing new environmental 49
TLDs in 2013, an improved method for calculating control dosimeter dose was implemented to estimate transit dose. A program review found that control dosimeters cannot be used directly to assess the transit dose, since control dosimeters also accrue dose from cosmic radiation while stored in the shielded storage cask/cave. Therefore, additional calculations must be made in order to determine the transit dose component.
This transit dose component was determined by processing the control dosimeters, and subtracting out the monitoring period storage dose. Previously, control dosimeters were assumed to be a direct measurement of transit dose which resulted in a non-conservative (lower) result of reported field doses. The field dose with the replacement TLDs is higher than that of the previously used TLDs as the greater precision and accuracy of the replacement TLD along with improved control dosimeter dose provides a more representative response to ambient radiation.
Figure 4-1: DIRECTRADIATION MEASUREMENT TLD RESULTS 8
7 C
0 25 (13 1,
000-
-- *Si i te i
Bi i0 ii I -- --Site Boundry
--o---Mile
-*-Avg Control I 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 50
not measurable. As evident in Figure 4-2, the control gross beta concentrations deviated from the norm for the sampling periods of December 1-8 and 8-16. The gross beta concentration was less than the minimum detectable concentration for the period December 1-8. The sample particulate filter was not as loaded with material (lighter in color) as typically found, however, the sampler was fully functional. For the sampling period December 8-16, the sample particulate ifiter was loaded with more material than typically found. This may explain the higher than usual gross beta concentration. Historically, gross beta concentrations of this magnitude are not atypical.
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.
Figure 4-2: 2014 GROSS BETA IN AIR PARTICULATES 0.045 0.040 0.035 0.030 0.025 UC. 0.020 0.015.
A" A A A
0.010 0.005 0.000 0-C.4 O
0 Ni
ý0 (7
M 02
~
0 I~O
Avg Indicator --
v oto 51
Figure 4-3: GROSS BETA IN AIR PARTICULATES HISTORICAL TREND 1.OE+00 1.OE-01 1.OE-02 1.OE-03 0
r-00 a,
0
-UAvglndicator
-Agoto
-Avg-PreOp
-Required LLD 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 and the Fukushima Daiichi nuclear incident in 2011.
4.4 Air Particulate Gamma 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 potassium-40 and beryllium-7, which is produced by cosmic processes.
No man-made radionuclides were identified. These analyses confirm the lack of station effects.
52
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 carefully evaluated when trying to determine if there is any station effect.
Results of gamma spectroscopy indicate no detectable station related radioactivity in the milk samples. In years past, cesium-137 had 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 2014.
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.
No strontium-89 was detected in the four composites analyzed. Strontium-90 was detected in two of the composite samples at an average concentration of 1.56 pCi/L. Sr-90 is not a component of the station radiological effluents and is a product of nuclear weapons testing fallout which 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. 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.
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 53
monthly samples are also composited and analyzed for tritium on a quarterly basis. Tritium was not detected and, with the exception of natural products, no other gamma emitters were detected.
The naturally occurring radionuclides detected were potassium-40, thorium-228 and thorium-232.
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.
Naturally occurring potassium-40, radium-226, thorium-228 and thorium-232 were detected. Historically, cobalt-60 has been detected in samples obtained from the indicator location (SD). Cobalt-60 has not been detected since 2003. Trend graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-4 and 4-5.
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 2014, cesium-137 was detected with an average indicator location concentration of 189 pCi/kg and an average control location concentration of 248 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.
54
Figure 4-4: COBALT-60 IN SILT I.OE+04 1.OE+03 1.OE+02 1.0E+01 1.0 E + 0 0 00 0..0
..0
.00 0
['
00 00 Co o
W=
Sai 0
0 Control - Chickahominy Station Discharge Chickahorniny 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 2014.
55
Figure 4-5: CESIUM-1 37 IN SILT 1.OE+04 O
1.OE+03 C.,
1.0E+02 I
Control-Chih 00 0
0 00 0D 00 0N Cp ORNur0 0
I
-e-Control - Chickahomniny
-a-Station Discharge
-Ave-Pre Op
-nRequired 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, radium-226, thorium-228 and thorium-232 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.
56
4.12 Oysters Oysters were collected from three 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 three 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 was 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.
57
- 5. PROGRAM EXCEPTIONS There were two REMP exceptions for scheduled sampling and analysis during 2014.
- 1. The Ist quarter indicator environmental TLD #32 was missing when TLDs were collected. Therefore, there was no gamma dose evaluation available at this location for the 1st quarter.
- 2. The Fort Eustis air sampler was inoperable for the sampling period of 7/01/14 to 7/08/14. The sampler housing was found dislodged, but still tethered by the electrical conduit, from the power pole to which it was mounted. The high winds from the remnants of hurricane Arthur are suspected to have caused this damage. As a result, the required lower limits of detection were unattainable for gross beta and iodine-131 due to insufficient sample volume collection.
58
- 6. CONCLUSIONS The results of the 2014 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 and potassium-40.
Air particulate gross beta concentrations at all of the indicator locations for 2014 trend well with the control location.
> Milk - 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 averages of the previous years.
Strontium-90 was detected in two samples at an average concentration of 1.56 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.
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 2014.
> 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 - River water samples were analyzed for gamma emitting radionuclides and tritium. Only the naturally occurring gamma emitting radionuclides potassium-40, thorium-228 and thorium-232 were detected.
Tritium was not detected.
> 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 59
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, 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.
60
REFERENCES 61
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.
62
APPENDICES 63
APPENDIX A: LAND USE CENSUS Year 2014 64
LAND USE CENSUS*
Surry Power Station, Surry County, Virginia January I to December 31, 2014 Page 1 of 1 I
l Nearest Nearest Nearest Nearest Sector Direction Resident Garden**
I Cow I
Goat A
B C
D E
F G
H J
K L
M N
P Q
R N
NNE NE ENE E
WNW NW NNW 4.1 @ 100 1.9 @ 320 4.7 @ 350 (a)
(a)
(a) 2.8 @ 1420 2.7 @ 1580 1.7 @ 1810 1.9 @ 1920 2.3 @ 2210 0.4 @ 2440 3.1 @ 2600 4.9 @ 2830 4.6 @ 3210 3.8 @ 3380 (a)
(a)
(a)
(a)
(a)
(a)
(a) 2.7 @ 1580 2.0 @ 1830 1.9 @ 1920 4.7 @ 2280 3.6 @ 2450 3.4 @ 2600 (a)
(a) 4.4 @ 3340 (a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a) 4.8 @ 2000 (a)
(a)
(a)
(a)
(a) 3.7 @ 3360 (a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
Locations are listed by miles and degrees heading relative to true north from center of Unit #1 Containment.
- Area greater than 50 m2 and contains broadleaf vegetation.
(a) None 65
APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS Year 2014 66
INTRODUCTION This appendix covers the Interlaboratory Comparison Program (ICP) of Teledyne Brown Engineering (TBE). 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 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 1-131 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 the 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 TBE ICP results are included in the following tables for the first through the fourth quarters of 2014. Four analyses did not meet the acceptance criteria. TBE initiated non-conformance reports (NCRs) to document and address the analyses.
The results of the NCRs are as follows.
- 1. NCR 14-04, MAPEP filter sample 14-RdF30 failed Sr-90. The TBE value of 0.822 Bq/sample was lower than the known value of 1.18 Bq/sample, failing below the lower acceptance limit of 0.83 Bq/sample. The rerun result was still low, but fell within the lower acceptance range of 0.836. The rerun result was statistically the same number as the original result. No cause could be found for the slightly low results.
- 2. NCR 14-08, ERA water sample RAD-99 failed 1-13 1. The TBE value of 15.8 pCi/L was lower than the known value of 20.3 pCi/L, failing below the lower acceptance limit of 16.8. The result was evaluated as failed with a found to 67
known ratio of 0.778. No cause could be found for the slightly low result.
All ERA 1-131 evaluations since 2004 have been acceptable.
- 3. NCR 14-09, MAPEP filter sample 14-RdF31 failed Sr-90. The TBE value of 0.310 Bq/sample was lower than the known value of 0.703 Bq/sample. The high gravimetric yield of 117% (typical yields of 60% to 70%) could indicate a larger than normal amount of calcium in the filter and could account for the low activity.
- 4. NCR 14-09, MAPEP filter sample 14-GrF31 failed Gross Alpha. The TBE value of 0.153 Bq/sample was lower than the known value of 0.53 Bq/sample. The AP sample was counted on the wrong side. The AP was flipped over and recounted with acceptable results.
68
ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value(a) Value (b) TBE/Analytics Evaluation(d)
March 2014 E10854 Milk Sr-89 pCi/L 95.1 91.7 1.04 A
Sr-90 pCi/L 10.9 15.1 0.72 W
E10855 Milk 1-131 pCi/L 96.6 99 0.98 A
Ce-141 pCi/L 112 119 0.94 A
Cr-51 pCi/L 449 491 0.91 A
Cs-134 pCi/L 186 210 0.89 A
Cs-137 pCi/L 250 253 0.99 A
Co-58 pCi/L 248 268 0.93 A
Mn-54 pCi/L 292 297 0.98 A
Fe-59 pCi/L 230 219 1.05 A
Zn-65 pCi/L 312 323 0.97 A
Co-60 pCi/L 321 337 0.95 A
E10857 Filter Ce-141 pCi 53 53.9 0.98 A
Cr-51 pCi 232 223 1.04 A
Cs-134 pCi 100 95 1.05 A
Cs-137 pCi 122 115 1.06 A
Co-58 pCi 122 121 1.01 A
Mn-54 pCi 135 135 1.00 A
Fe-59 pCi 111 99 1.12 A
Zn-65 pCi 140 147 0.95 A
Co-60 pCi 187 153 1.22 W
E10856 Charcoal 1-131 pCi 74.1 76.4 0.97 A
June 2014 E10913 Milk Sr-89 pCi/L 85.9 91.3 0.94 A
Sr-90 pCi/L 13.8 14.5 0.95 A
E10914 Milk 1-131 pCi/L 86.5 90.9 0.95 A
Ce-141 pCi/L 111 124 0.90 A
Cr-51 pCi/L 255 253 1.01 A
Cs-134 pCi/L 147 162 0.91 A
Cs-137 pCi/L 123 120 1.03 A
Co-58 pCi/L 105 112 0.94 A
Mn-54 pCi/L 155 156 0.99 A
Fe-59 pCi/L 106 102 1.04 A
Zn-65 pCi/L 251 252 1.00 A
Co-60 pCi/L 218 224 0.97 A
Footnotes are on page 3 of 3.
69
ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
June 2014 E10916 Filter Ce-141 pCi Cr-51 pCi Cs-134 pCi Cs-137 pCi Co-58 pCi Mn-54 pCi Fe-59 pCi Zn-65 pCi Co-60 pCi 95.1 215 122 95.1 88.7 115 72.6 193 179 92.6 190 122 89.8 84.1 116 76.7 189 168 E 10915 Charcoal 1-131 pCi 85.6 85.2 September 2014 E10946 Milk Sr-89 pCi/L Sr-90 pCi/L 90.7 96.9 14.0 16.4 E10947 E10949 Milk 1-131 pCi/L Ce-141 pCi/L Cr-51 pCi/L Cs-134 pCi/L Cs-1 37 pCi/L Co-58 pCi/L Mn-54 pCi/L Fe-59 pCi/L Zn-65 pCi/L Co-60 pCi/L 92.0 117 281 141 186 137 138 162 75.2 286 97.8 212 106 131 85.7 93 113 53 202 97.6 126 288 158 193 143 142 158 73.0 297 82.1 188 103 126 93.0 92 103 47.5 193 1.03 1.13 1.00 1.06 1.05 0.99 0.95 1.02 1.07 1.00 0.94 0.85 0.94 0.93 0.98 0.89 0.96 0.96 0.97 1.03 1.03 0.96 1.19 1.13 1.03 1.04 0.92 1.01 1.10 1.12 1.05 0.93 0.90 0.83 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A Filter Ce-141 pCi Cr-51 pCi Cs-134 pCi Cs-137 pCi Co-58 pCi Mn-54 pCi Fe-59 pCi Zn-65 pCi Co-60 pCi E 10948 Charcoal 1-131 pCi 83.9 89.8 December 2014 E 11078 Milk Sr-89 pCi/L Sr-90 pCi/L 85.7 95.7 12.9 15.6 Footnotes are on page 3 of 3.
70
ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b)
TBE/Analytics Evaluation (d)
December 2014 E11079 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 85.9 205 402 156 194 122 220 183 287 224 96.4 171 73.1 99.0 57.5 107 74.2 144 114 95.1 219 406 164 198 130 225 175 297 235 102.0 190 76.9 92.6 60.8 105 81.6 139 110 0.90 0.94 0.99 0.95 0.98 0.94 0.98 1.05 0.97 0.95 0.95 0.90 0.95 1.07 0.95 1.02 0.91 1.04 1.04 0.95 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A E11081 Filter Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E11080 Charcoal 1-131 pCi 93.5 98.2 (a)
(b)
(c)
(d)
Teledyne Brown Engineering reported result.
The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
Ratio of Teledyne Brown Engineering to Analytics results.
Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls vwthin 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 <.70 and > 1.30.
71
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)
March 2014 14-MaW30 Water Am-241 Cs-134 Cs-137 Co-57 Co-60 Mn-54 Zn-65 Bq/L Bq/L Bq/L BqIL Bq/L Bq/L Bq/L 0.764 20.7 28.0 26.5 15.6 13.5
-0.201 0.720 23.1 28.9 27.5 16.0 13.9 0.504 - 0.936 16.2-30 0 20.2 - 37.6 19.3-35.8 11.2 -20.8 9.7-18.1 (1) 14-RdF30 14-GrF30 14-RdF31 14-GrF31 AP Sr-90 Bq/sample 0.8220 AP Gr-A Bq/sample 0.606 Gr-B Bq/sample 0.7507 AP Sr-90 Bq/sample 0.310 AP Gr-A Bq/sample 0.153 Gr-B Bq/sample 0.977 1.18 0.83-1.53 1.77 0.53-3.01 0.77 0.39-1.16 0.703 0.492 - 0.914 0.53 0.16-0.90 1.06 0.53-1.59 A
A A
A A
A A
N (2)
A A
N (3)
N (3)
A September 2014
- The MAPEP cross check isotope list has been reduced due to duplication of effort or analysis not being performed for clients.
(1) False positive test.
(2) AP, Sr-90 rerun was within the lowrange of the acceptqance criteria. The original and rerun results were statistically the same. No cause could be identified for the slightly low Sr-90 activity. NCR 14-04 (3) AP, Sr-90 gravimetric yield was very high at 117%. Could indicate larger than normal amounts of calcium in the AP. A second fuming HNO 3 separation would be required to remove the excess calcium; The Gross Alpha AP was counted on the wrong side.
When flipped over and recounted the results ware acceptable. NCR 14-09 (a) Teledyne Brown Engineering reported result.
(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.
72
ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b)
Limits Evaluation (c)
May 2014 RAD-97 Water Sr-89 pCi/L Sr-90 pCi/L Ba-133 pCi/L Cs-1 34 pCi/L Cs-1 37 pCi/L Co-60 pCi/L Zn-65 pCi/L Gr-A pCi/L Gr-B pCi/L I-131 pCi/L U-Nat pCi/L H-3 pCi/L MRAD-20 Filter Gr-A pCi/filter 38.25 24.65 89.1 45.55 91.15 65.10 244 45.65 27.95 23.75 9.61 8435 28.0 30.4 18.6 46.8 88.0 99.0 92.5 325 29.9 27.5 15.8 5.74 6255 27.3 36.7 26.5 87.9 44.3 89.1 64.2 235 61.0 33.0 25.7 10.2 8770 27.5 - 43.6 19.2-30.9 74.0 - 96.7 35.5 -48.7 80.2-101 57.8-73.1 212 -275 31.9 -75.8 21.4-40.7 21.3-30.3 7.95-11.8 7610-9650 A
A A
A A
A A
A A
A A
A A
46.0 15.4-71.4 November 2014 RAD-99 Water Sr-89 pCi/L Sr-90 pCi/L Ba-133 pCi/L Cs-1 34 pCi/L Cs-1 37 pCi/L Co-60 pCi/L Zn-65 pCi/L Gr-A pCi/L Gr-B pCi/L 1-131 pCi/L U-Nat pCi/L H-3 pCi/L Filter Gr-A pCi/filter 31.4 21.8 49.1 89.8 98.8 92.1 310 37.6 27.4 20.3 5.80 6880 22.8-38.1 15.6-25.7 40.3 - 54.5 73.7 - 98.8 88.9-111 82.9-104 279 - 362 19.4-48.1 17.3-35.3 16.8-24.4 4.34 - 6.96 5940 - 7570 A
A A
A A
A A
A A
N(1)
A A
MRAD-21 36.9 12.4 - 57.3 A
(1) The Iodine-131 was evaluated as failed with a ratio of 0.778. No cause could be found for the slighly low activity. TBE would evaluate this as acceptable with warning. A rerun was not possible due to 1-131 decay. All ERA Iodine-131 evaluations since 2004 have been acceptable. NCR 14-08 (a) Teledyne Brown Engineering reported result.
(b) The ERA 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) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.
73