ML061250401
| ML061250401 | |
| Person / Time | |
|---|---|
| Site: | Surry, 07200002  |
| Issue date: | 05/01/2006 |
| From: | Jernigan D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 06-358 | |
| Download: ML061250401 (75) | |
Text
VIRGINIA ELECTRIC AND) POWER COMPANY RIChMOND, VIRGINIA 23261 May 1, 2006 United States Nuclear Regulatory Commission Serial No.06-358 Attention: Document Control Desk SS&L/TJN Washington, D. C. 20555-0001 Docket Nos. 50-280 50-281 72-2 License Nos. DPR-32 DPR.-37 SNI'V1-2501 Gentle men:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Surry UJnits 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.1.3.1 requires that the Surry ISFSI be included in the environmental monitoring for the Surry Power Station.
Accordingly, enclosed is the Surry Power Station AREOR for the period of January 1, 2005 through December 31, 2005 which includes environmental monitoring for the Surry ISFSI.
If you heave any questions or require additional information, please contact Paul Harris at 75 765-2692.
eryf uly yours, DonalE.&egan Site Vice President Surry Power Station Attachment Commitments made in this letter: None
copy: US Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.E., Suite 23T85 Atlanta, Georgia 30303-8931 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, Virginia 23218
Serial No. 06-:358 Docket Nos.: 50-.280 50-281
,'2-2 ATTACHMENT 2005 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION UNITS 1 AND 2 LICENSE NOS. DPR-32 AND DPR-37 INDEPENDENT SPENT FUEL STORAGE INSTALLATION LICENSE NO. SNM-2501 VIRGINIA ELECTRIC AND POWER COMPANY
LU LL L
L L
L L
LL L
L L
L L;I L
L Su r ry Power Station 2005 Annual Radiological Environmental Operating Report Do~minionf
Dominion Surry Power Station Radiological Environmental Monitoring Program January 1, 2005 to December 31, 2005
Annual Radiological Environmental Operating Report Surry Power Station January 1, 2005 to December 31, 2005 Prepared by:
Reviewed by:
Reviewed by:
Approved by:
/6X)Sx 13' C/
P. F. Blount Health Physicist P. R. Harris Supervisor Radiological Analysis D. K. Miller id 2
Table of Contents PREFACE.......................................
4
- 1. EXECUTIVE
SUMMARY
5
- 2. PROGRAM DESCRIPTION.......................................
7 2.1 Introduction......................................
7 2.2 Sampling and Analysis Program......................................
8
- 3. ANALYTICAL RESULTS.....................................
20
- 3. 1 Summary of Results.....................................
20 3.2 Analytical Results of 2005 REMP Samples.....................................
27
- 4. DISCUSSION OF RESULTS.....................................
49
- 4. 1 Gamma Exposure Rate.....................................
49 4.2 Airborne Gross Beta.....................................
51 4.3 Airborne Radioiodine.....................................
52 4.4 Air Particulate Gamma.....................................
53 4.: Cow Milk.....................................
53 4.6 Food Products.....................................
54 4.7 Well Water.....................................
54 4.8 River Water.54 4.9) Silt.........................
54 4.:0 Shoreline Sediment..........................
56 4.1 1 Fish..............................
56 4.:12 Oysters..............................
56 4.1.3 Clams..............................
57 4.14 Crabs..............................
57
- 5. PROGRAM EXCEPTIONS..............................
58
- 6. CONCLUSIONS..............................
59 REFERENCES...............................
61 APPENDICES...............................
63 APPENDIX A: LAND USE CENSUS 64 APPE]NDIX 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.
4
- 1. EXECUTIVE
SUMMARY
This document is a detailed report of the 2005 Surry Power Station Radiological Environmental Monitoring Program (REMP).
Radioactivity levels from January 1 through December 31, 2005, 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, are collected from areas that are beyond the measurable influence of Surry Power Station or any other nuclear facility. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than Surry Power Station, can be compared to the environment surrounding the station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the station. Indicator samples are taken from areas close to the station where any station contribution will be at the highest concentration.
Prior t.o 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 compeared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, or causes such as the Chernobyl accident or natural variation.
The AREVA NP Environmental Laboratory provides radioanalyses for this program and Global Dosimetry Solutions Incorporated 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 level for certain radionuclides.
Licensed nuclear facilities must xreport the radionuclide activities in those environmental samples that are 5
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 2005 airborne results were similar to previous years. No plant related radioactivity was detected and fallout or natural radioactivity levels remained at levels consistent with past years' results. Aquatic exposure pathway samples include well and river water, silt and shoreline sediments, crabs, fish, clams and oysters.
Naturally occurring potassium-40 was detected at average environmental levels.
No man-made radioisotopes were detected in well water.
This Irend is consistent throughout the operational environmental monitoring program. Silt samples indicated the presence of cesium-137.
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. Cobalt-60, which has been detected in silt in the past, has not been detected since 2003. Shoreline sediment, which may provide a direct exposure
- pathway, contained no station related radioisotopes.
Naturally occurring potassium-40 and thorium-228 were detected at average environmental levels.
The terrestrial exposure pathway includes milk and food products.
Iodine-131 was not detected in any 2005 milk samples and has not been detected in milk prior too or since the 1986 Chernobyl accident. Strontium-90 was again detected in mi]k and this activity is attributable to past atmospheric nuclear weapons testing.
No man-made radioisotopes 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 enviromnental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained relatively constant over the years.
During 2005, as in previous years, the operation of Surry Power Station has created no adverse environmental effects or health hazards. The maximum dose calculated for a hypothetical individual at the station site boundary due to liquid and gaseous effluents released from the station during 2005 was 0.002 millirem.
For reference, this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources.
Natural sources in the environment provide approximately 82% of radiation exposure to man, while nuclear power contributes less than 0.1%.
These results demonstrate not only compliance with federal and state regulations but also demonstrate the adequacy of radioactive effluent controls at Surry Power Station.
6
- 2. PROGRAM DESCRIPTION 2.1 Introduction This report documents the 2005 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 EL pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 855 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973.
The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, constructed and operated to keep levels of radioactive material in effluents to unrestricted areas As Low As is Reasonably Achievable (ALARA).
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. The AREVA NP Environmental Laboratory 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 levels, which vaiy with time clue to external events, such as cosmic ray bombardment, nuclear weapons test fallout and seasonal variations of naturally occurring radioisotopes.
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 radioisotopes.
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).
These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As is Reasonably 7
Achiev~able."
This report documents the results of the REMP for 2005 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 2005 sampling program for Surry Power Station. All samples listed in Table 2-1 are taken at indicator locations except those labeled "control."
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. Table 2-2 summarizes the analysis program conducted by AREVA NP Environmental Laboratory and Global Dosimetry Solutions for Surry Power Station during the year 2005.
On June 30, 1998, the Commonwealth of Virginia, Department of Health, discontinued its comparative analysis (state split) program with Surry Power Station.
Although the routine splitting of samples with the Commonwealth of Virginia has been discontinued, samples will be split at the request of the state.
Dominion personnel collect all samples listed in Table 2-1. All samples, with the exception of the TLDs, are shipped to AREVA NP Environmental Laboratory, located in Westborough, MA, for analysis.
The TLDs are shipped to Global Dosimetry Solutions, located in Costa Mesa, CA, for processing.
8
T E
FY F
UT 4
V a Fi FE i Table 2-1 SURRY - 2005 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Environmental Control (00)
TLDs West North West (02)
Surry Station Discharge (03)
North North West (04)
North (05)
North North East (06)
North East (07)
East North East (08)
East (09)
West (10)
West South West (11)
South West (12)
South South West (13)
South (14)
South South East (15)
South East (16)
Station Intake (18)
Hog Island Reserve (19)
Bacon's Castle (20)
Route 633 (21)
Alliance (22)
Surry (23)
Route 636 and 637 (24)
Scotland Wharf (25)
Jamestown (26)
Colonial Parkway (27)
Route 617 and 618 (28)
Kingsmill (29)
Williamsburg (30)
Kingsmill North (31)
Budwei ser
.3-Water Plant (33) 0.2 mi WNW 0.4 mi NW 0.2 mi NNW 0.3 mi N
0.3 mi NNE 0.3 mi NE 0.4 mi ENE 0.3 mi E
0.1mi W
0.4 mi WSW 0.3 mi SW 0.3 mi SSW 0.4 mi S
0.6 mi SSE 0.9 mi SE 1.6 mi ESE 2.0 mi NNE 4.5 mi SSW 4.9 mi SW 5.1 mi WSW 7.7 mi WSW 4.0 mi W
5.0 mi WNW 6.3 mi NW 3.8 mi NNW 4.9 mi NNW 4.6 mi N
7.8mi N
5.5 mi NNE 5.0 mi NE Quarterly Onsite (Stored in lead container outside protected area) 2930 Quarterly Site Boundary 3210 Quarterly Site Boundary 3290 Quarterly Site Boundary 40 Quarterly Site Boundary 280 Quarterly Site Boundary 440 Quarterly Site Boundary 670 Quarterly Site Boundary 890 Quarterly Site Boundary/Exclusion 2710 Quarterly Site Boundary 2520 Quarterly Site Boundary 2280 Quarterly Site Boundary 2010 Quarterly Site Boundary 1820 Quarterly Site Boundary 1570 Quarterly Site Boundary 1350 Quarterly Site Boundary 1150 Quarterly Site Boundary 260 Quarterly Near Resident 2020 Quarterly Apx. 5 mile 2270 Quarterly Apx. 5 mile 2470 Quarterly Apx. 5 mile 2560 Quarterly Population Center 2700 Quarterly Apx. 5 mile 2840 Quarterly Apx. 5 mile 3080 Quarterly Apx. 5 mile 3330 Quarterly Apx. 5 mile 3400 Quarterly Apx. 5 mile 20 Quarterly Apx. 5 mile 00 Quarterly Population Center 120 Quarterly Apx. 5 mile LI Qaeuartly Iupuna.ony PU.Pa iI 460 Quarterly Apx. 5 mile 9
r-7 ur a=1 r-n 177 7 ni 17 77 Z-CI-U7 r7Z FIT rXF FM T ITT
[TI Table 2-1 SURRY - 2005 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks BASF Lee Hall Goose Island Fort Eustis Newport News James River Bridge Benn's Church Smithfield Rushmere Route 628 (34)
(35)
(36)
(37)
(38)
(39)
(40)
(41)
(42)
(43) 5.1 mi 7.1 mi 5.1 mi 4.9 mi 19.3 mi 17.1 mi 17.0 mi 13.4 mi 5.3 mi 5.1 mi ENE ENE E
700 750 900 1040 1300 1420 1590 1670 1560 1770 Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Apx. 5 mile Population Center Apx. 5 mile Apx. 5 mile Population Center Control Location Control Location Control Location Apx. 5 mile Apx. 5 mile Air Charcoal and Particulate Surry Station Hog Island Reserve Bacon's Castle Alliance Colonial Parkway BASF Fort Eustis Newport Newvs (SS)
(HIR)
(BC)
(ALL)
(CP)
(BASF)
(FE)
(NN) 0.3 mi 2.0 mi 4.5 mi 5.1 mi 3.8 mi 5.1 mi 4.9 mi 19.3 mi NNE NNE SSW WSW NNW ENE ESE SE 180 260 2020 2470 3330 700 1040 130° Weekly Weekly Weekly Weekly Weekly Weekly Weekly Weekly Site Boundary (Highest D/Q)
Control Location River Water Surry Station Discharge Scotland Wharf (SD) 0.4 mi NW 3230 Monthly (SW) 4.9 mi WNW 2840 Monthly Control Location Well Water Surry Station Hog Island Reserve (SS) 0.1 mi SW (HIR) 2.0 mi NNE 227° Quarterly 280 Quarterly Onsite Shoreline Sediment Hog Island Reserve Chickahominy River (IMR) 0.6 mi N
(CHIC) 11.2 mi WNW 70 Semi-Annually 3010 Semi-Annually Control Location
.3331 0...
Surry Station Discharge
" nLH-.,
(SD)
I I.
Al
'MT11v 300 In o
miAnn_:
l 1 A, alis YY VNW 341° Semhihl-Annually 1.3 ml NNW 3410 Semi-Annually
'..AJ U T ^aLiUIA 10
iE=
r-1 I
rE=
xiCrr FM7 17
=
177L G Fly r=
E=-
[=7 rh.
r-iE= n Table 2-1 SURRY - 2005 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Collection Sample Media Location Station Distance Direction Degrees Frequency Remarks Milk Colonial Parkway Williams Epp's (CP)
(WMS)
(EPPS) 3.7 mi 27.5 mi 4.8 mi NNW S
SSW 3360 Monthly 1750 Monthly 2000 Monthly Control Location Oysters Point of Shoals Mulberry Point (POS) 6.4 mi SSE (MP) 4.9mi ESE 1570 Semi-Annually 1240 Semi-Annually Clams Chickahominy River Surry Station Discharge Hog Island Point Lawne's Creek (CHIC)
(SD)
(HIP)
(LC) 11.2 mi 1.3 mi 2.4 mi 2.4mi WNW NNW NE SE 3000 3410 520 1310 Semi-Annually Control Location Semi-Annually Semi-Annually Semi-Annually Fish Crabs Surry Station Discharge Surry Station Discharge (SD) 1.3 mi NNW 3410 Semi-Annually 3410 Annually (SD) 1.3 mi NNW Food Products (Corn, Peanuts, Soybeans)
Brock's Farm Slade's Farm (BROCK) 3.8 mi S
(SLADE) 3.2 mi S
1830 Annually 1790 Annually 11
Table 2-2 (Page 1 of 3)
SURRY - 2005 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*
REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2
mRIStd. Month Dosimetry (TLD)
Air Iodine Weekly 1-131 0.07 pCi/mr3 Air Particulate Weekly Gross Beta 0.01 pCi/mr3 Quarterly (a)
Gamma Isotopic pCi/m3 Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium (H-3) 2000 pCi/L Composite of monthly sample Monthly I-131 10 pCi/L Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Well Water Quarterly Tritium (H-3) 2000 pCi/L I-131 1
Gamma Isotopic pCi/L Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Footnotes located at end of table.
12
Table 2-2(Cont.)
(Page 2 of 3)
SURRY - 2005 SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*
REPORT UNITS Shoreline Sediment Semi-Annual Gamma Isotopic pCi/kg - dry Cs-134 Cs-137 150 180 Silt Semi-Annual Monthly Gamma Isotopic Cs-134 Cs-137 150 180 pCi/kg - dry pCi/L Milk.
1-131 1
Gamma Isotopic Cs-134 Cs-137 Ba-140 La-140 pCi/L 15 18 60 15 Oysters Semi-Annual Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 pCi/kg - wet 130 260 130 130 260 130 150 Clams Semi-Annual Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 pCi/kg - wet 130 260 130 130 260 130 150 Crabs Annually Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 pCi/kg - wet 130 260 130 130 260 130 150 Footnotes located at end of table.
13
Table 2-2 (Cont.)
SURRY - 2005 SAMPLE ANALYSIS PROGRAM SAM rDT 4F4lrTA tRDFnTr1NWv r.nr..Ca-
- v
-J2 r
x Fis h Semi-Annual ANALYSIS Gamma Isotopic Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 LLD*
REPORT UNITS pCi/kg - wet 130 260 130 130 260 130 150 Fo3d Products Annually Gamnmna Isotopic 1-13 1 Cs-134 Cs-137 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 measurable and identifiable, together with the above nuclides, are also identified and reported.
- 1LD 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.
14
e I
I v01 l^l Fe CO
-=-
-=-
-=-
-=-
m Figure 3. Surry Emergency Plan Map A
Air QRnmnlinr.Rt::tinnc l
NI::rmct Qncirhnntc TLD Sampling
- Nearest Milk Animal rSs \\3
- Nearest Garden Aquatic Samples X
bOriginal O 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.
CO 21
m W' 'o Srry
~j SORRY
/AIIA~
C
~
i*Ž
~
wsw Io:
Ul (6-1 A:1 iQNX ELIERO*'
,ij
,,11.
Figure 4. Surry Emergency Plan Map
- Air Sampling Stations
- Nearest Residents TLD Sampling Nearest Milk Animal Nearest Garden Crop Samples 0
W 0
w
'4 zO 0n 8
o 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.
C104
-M-
-M-
-M-Figure 5. Surry Emergency Plan Map
- Air Sampling Stations *Nearest Residents TLD Sampling Nearest Milk Animal Nearest Garden Aquatic Samples Original 0 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA22312. USED WITH PERMISSION. No other reproduction may be made without the written permission of ADC.
+
nt It(
(7,of
- 3. ANALYTICAL RESULTS 3.1 Simmary 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 IJSNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Progrun", 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 - 2005 Docket No. 50-280-281 Page I of 6 Mediurn or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-Routine SampTed Total Mean Distance Mean Mean Rep Drted Type I No. LLD*
Range Name I Direction Range Range Measurements Air Iodine 1-131 416 70
< LLD N/A
< LLD
< LLD 0
Air Gross 416 10 19.8 (363/364)
BASF 5.1 mi 21.0(52/52) 20.8 (51/52) 0 Particul ate Beta (6.9 - 40.9)
ENE (8.3 - 39.5)
(8.6 - 36.9)
(YE.3pC1413)
Gamma 32 Be-7 32 118(28/28)
FE 4.9mi 132(4/4) 116(4/4) 0 (87-150)
ESE (110 - 150)
(107-124)
Cs-134 32 50
< LLD N/A
< LLD
< LLD 0
Cs-137 32 60
< LLD N/A
< LLD
< LLD 0
River Water (pCilter)
H-3 8
2000
< LLD N/A
< LLD
< LLD Gamma 24 K-40 24 99.2 (5/12)
(79-126)
SD 0.4 mi 99.2 (5/12) 86 (1/12)
NW (79-126)
(86 -86) i0 I)
Mn-54 24 15
< LLD N/A
< LLD
< LLD Co-58 24 15
< LLD N/A
< LLD Fe-59 24 30
< LLD N/A
< LLD N/A
< LLD Zn-65 24 30
< LLD N/A
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD Nb-95 24 15
<HLD N/A
< LLD Zr-95 1-131 24 30
< LLD 24 10
< LLD N/A
< LLD N/A
< LLD
- 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.
21
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2005 Docket No. 50-280-281 Page 2 of 6
[ediurn or Indicator Control Pathway Analysis Locations Location with Highest Mean Locations Non-FRoutine Samp ed Total Mean Distance Mean Mean Rep Drted LJ ni>)
Type I No. LLD*
Range Name Direction Range Range Measurements River Cs-134 24 15
< LLD N/A
< LLD
< LLD 0
Water (pCi4Jter)
Cs-137 24 18
< LLD N/A
< LLD
< LLD D
Ba-140 24 60
< LLD N/A
< LLD
< LLD 0
La-140 24 15
< LLD N/A
< LLD
< LLD 0
Well H-3 8
2000
< LLD N/A
< LLD N/A D
Water (pCitier)
Gamma 8
Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-1 37 Ba-1 40 15 15 30 15 30 15 30 1
is 18 60
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
<LLD N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
- 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.
22
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2005 Docket No. 50-280-281 Page 3 of 6 Mediurn or Indicator Control Pathwray Analysis Locations Location with Highest Mean Locations Non-Floutine Sampled Total Mean Distance Mean Mean Reported (Unts)
Type No. LLD*
Range Name Direction Range Range Measurements Well La-140 8
15
< LLD N/A
< LLD N/A 0
Water (pCii er)
Silt Gamma 4
(oCikg dry)
Be-7 4
790 (1/2)
SD 1.3 ml 790 (1/2)
< LLD 0
(790 - 790)
NNW (790 -790)
K-40 4
16850 (2/2)
SD 1.3 mi 16850 (22) 16135 (22) 0 (16800-16900)
NNW (16800-16900) (15070-17200)
Cs-134 4
150
< LLD N/A
< LLD
< LLD 0
Cs-137 4
180 229 (212)
SD 1.3 ml 229 (212) 215 (22) 0 (223 - 235)
NNW (223 - 235)
(179-250)
Th-228 4
1090 (22)
CHIC 11.2 mi 1200 (22) 1200 (212) 0 (1030 -1150)
WNW (1160 -1240)
(1160 -1240)
Shoreline Gamma 4
Sediment (pCikgdyl)
K-40 4
4300 (2/2)
HIR 0.6 ml 4300 (212) 1230 (22) 0 (3840 - 4760)
N (3840 - 4760)
(610 - 1850)
Cs-134 4
150
< LLD N/A
< LLD
180
< LLD N/A
< LLD
< LLD
)
Th-228 4
511 (1/2)
CHIC 11.2 mi 904 (1/2) 904 (1/2) 1)
(511 - 511)
WNW (904 - 904)
(904-904)
Milk (pCi'ter)
Sr-89 4
< LLD N/A
1.8 (1/4)
(1.8 - 1.8)
CP 3.7 ml 1.8 (1/4)
NNW (1.8 -1.8)
N/A 0
Gamma 36 K-40 36 1389 (24/24)
(1240 - 1560)
EPPS 4.8 mi 1391 (12/12) 1341 (12/12)
SSW (1270-1560) (1170-1520) 03
- LLD is the Lower Limit of Detection as defined and required in the USNRC Branch Technical Position on a:
Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
23
TABLE 3-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Power Station, Surry County, Virginia - 2005 Docket No. 50-280-281 Page 4 of 6 Miurn or Indicator Control Pathway Analysis Locations Location with Hi ghest Mean Locations Non-Floutine Samp' ed Total Mean Distance Mean Mean Rep Drted Type I No. LLD*
Range Name I Direction I Range Range Measurements Milk 1-131 36 1
< LLD N/A
<LLD
<LLD 0
CpsDtLer)
Cs-134 36 15
< LLD N/A
<LLD
<LLD 0
Cs-1 37 36 1 8
< LLD NVA
<LLD
<LLD 0
Ba-140 36 60
< LLD N/A
< LLD
<LLD D
La-140 36 15
< LLD N/A
<LLD
< LLD 3
Clams Gamma 8
(pCikg we.)
K-40 8
Mn-54 8
Co-58 8
Fe-59 8
Co-60 8
Zn-65 8
130 130 260 130 260 130 150 323 (6/6)
(229 - 460)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD LC N/A N/A N/A N/A N/A 2.4 mi 360(2/2)
SE (340-380)
< LLD
< LLD
<LLD
<LLD
<LLD 208 (2/2)
(180-236)
<LLD
<LLD
< LLD
<LLD
<LLD
< LLD
< LLD Cs-1 34 Cs-1 37 8
8 N/A NWA
<LLD
<LLD Oysters Gamma (pC&kg wet.
4 4
401 (414)
(240 - 532)
< LLD POS N/A 6.4 mi 436 (2/2)
SSE (340-532)
< LLD N/A N/A I)
I) 130
- 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.
24
TABLE341: RADIOLOGICAL ENVIROAMENTAL MONITORING PROGRAM
SUMMARY
SurryPower Station, Surry County, Virginia - 2005 Docket No. 50-280-281 Page 5 of 6 Medium or Indicator Control Pathmay Analysis Locations Location with H hest Mean Locations Non-FRoutine Sampled ITotal Mean lDistance N
Mean Reported (UW!)
Type I No.
o LLD*
Range Name I Direction Rane Range Measu vernts Oysters Fe-59 4
260
<LLD N/A
< LLD N/A 0
(pC~kg Ve!J Co-58 4
130
<LLD N/A
<LLLD WA 0
Co-60 4
130
< LLD N/A
< LLD NA 0
Zn-65 4
260
< lD N/A
< LLD NA 0
Cs-134 4
130
< LLD N/A
< LLD N/A 0
Cs-137 4
150
<LLD N/A
<LLD NA 0
Crabs (pQ~kg m.)
Gamma 1
K-40 1
2010(1/1)
(2010- 2010)
SD 1.3 mi 2010(1/1)
NNW (2010 - 2010)
NWA I)
Nh-54 1
130
< LLD Co-58 1
130
< LLD Fe-59 1
260
130
< LLD Zn-65 1
260
< LLD Cs-134 1
130
150
< LLD N/A
<LLD WA
<LLD N/A N'A N/A 03 03 03 N/A
<LLD N/A
<LlD WA NWA
<LLD WA
<LLD N/A NWA WA 03 0) 1)
WA
<LLD
- 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.
25
L T"IE 3-1: RADIO0ICAL ENVRONMENTAL MONfTOPJNG PROGRAM
SUMMARY
SurryPower Station, SurTy County, Virginia -2005 L
Docket No. 50-280-281 Page 6 of 6 Medium or Indicator Control Pathmray Analvsis Locations Location with Highest Mean Locations Non-Foutine Sa.nped lTota Mean l Distance Mean Mean Reported (UnSa Type I No. LLD*
Range Name I Directioni Range FRange Measurerents Fish Gamrm 4
K-40 4
1598 (414)
SD 1.3 rni 1598(4/4)
N/A 0
(1200-2310)
NNW (1200 - 2310)
Mn-54 4
130
< LLD A
< LLD N/A 0
Co-58 4
130
<LLD N/A
<LLD NWA 0
Fe-59 4
260
< LLD N/A
< LLD N/A 0
Co-60 4
130
<LLD N/A
<LLD N/A 0
Zn-65 4
260
<LLD N/A
<L L)
NA 0
Cs-134 4
130
< LLD N/A
< LLD N/A 0
Cs-137 4
150
< LWD N/A
< LW N/A 0
Food Gamna 3
Products (pcauge)
K-40 3
7633 (313)
Slade 3.2 mi 17270(1/1)
NWA (2C90 - 17270)
S (17270-17270) 1-131 3
60
< LWD N/A
<LW N/A 0
Cs-134 3
60
<ILD N/A
<LlW N/A 0
Cs-137 3
80
< LW N/A
<LLW N/A 0
Direct Gamma 164 2
3.9 (156/156)
STA-9 0.3 ni 6.7(4/4) 4.4(12112) 0 Radiation (1.6-7.6)
E (6.2 -7.6)
(2.0- 7.0) 7WD (nS' Sd Monn)
- LLD i<. 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.
26 U
L L
3.2 Analytical Results of 2005 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 (2o) 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 1.5 times the listed 2a error (i.e., the measured value exceeds 3a).
AREVA NP Environmental Laboratory 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 I-131 Air Particulates, Quarterly Gamma Spectroscopy Cow Milk Food Products Well Water River Water Silt Shoreline Sediment Fish Oysters Clams Crabs 27
TABLE 3-2: GAMMA EXPOSURE RATE Surry Nuclear Power Station, Surry County, Virginia - 2005 mR/Std Month +/-2 Signa Page I of I STATION FIRST SECOND THIRD FOURTH AVERAGE 2I I
UMER QUARTER QUARTER QUARTER QUARTER
+/-t 2 SIGMAL 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 34 35 36 37 38 39 40 41 42 43 6.0 0.2 5.9 0.3 5.3 0.5 5.0+/-0.2 5.3+/-0.4 4.7 0.6 4.9+/-0.7 7.6+/-0.5 5.4 0.3 4.3 0.3 4.3 0.5 5.0 0.5 4.8 1.4 5.4 1.0 4.8 +/- 0.4 2.9 +/- 1.0 2.9 +/- 1.1 3.6 +/- 0.5 3.5 +/- 0.6 2.9 +/- 0.3 5.1 +/-0.8 3.6 0.3 3.9 0.7 3.8 0.2 3.0 1.2 3.1 0.4 2.9 0.3 2.9 0.5 2.6 0.6 3.6 0.3 3.5 1.0 3.7 0.3 5.1 0.4 5.0 0.1 3.8 0.5 6.2 0.9 3.6 0.2 4.5 +/- 0.3 7.0 +/- 0.4 3.7 +/- 0.7 3.5 +/- 0.5 4.7 +/- 0.3 4.8 +/- 1.1 4.3 +/- 0.4 3.7 +/- 0.7 4.6 +/- 0.3 4.3 +/- 0.3 4.0 +/- 0.5 6.2 +/- 1.1 4.1 +/-0.2 3.1 +/-0.9 3.7 +/- 0.7 3.7 +/- 0.2 3.4 +/- 0.7 4.6 +/- 0.6 3.0 +/- 0.2 1.7 +/- 0.3 3.0 +/- 0.4 2.7 +/- 1.3 3.2 +/- 0.4 2.3 +/- 0.3 4.0 +/- 0.2 2.3 +/- 0.9 3.3 +/- 0.3 4.4 +/- 0.3 2.7 +/- 0.1 2.7 +/- 0.3 2.5 +/- 0.3 2.7 +/- 0.4 2.1 +/-0.2 3.1 0.3 3.2 0.5 2.9 0.8 4.1 0.1 3.6 1.0 2.1 +/-0.2 5.9 +/- 0.3 2.0 +/- 0.3 3.1 +/- 1.1 6.0 +/- 0.5 3.3 +/- 0.3 2.7 +/- 0.2 5.0 +/- 0.6 5.3 +/- 0.9 4.5 +/- 0.8 4.2 +/- 0.2 4.5 +/- 0.3 4.6 +/- 0.6 4.6 +/- 0.4 6.4 +/- 0.8 4.7 +/- 0.2 3.8 +/- 0.3 3.7 +/- 0.7 4.6 +/- 0.3 4.2 +/- 0.5 5.0 +/- 0.4 3.8 +/- 0.3 2.6 +/- 0.2 2.8 +/- 0.5 3.0 +/- 0.2 3.1 +/-0.3 1.6 +/- 0.4 4.0 +/- 0.3 3.1 +/-0.2 2.8 +/- 1.0 4.1 +/- 0.8 3.0 +/- 0.4 2.1 +/-0.4 2.7 +/- 0.1 2.8 +/- 0.5 2.4 +/- 0.4 2.7 +/- 0.3 3.1 +/-0.2 3.1 +/- 0.3 4.2 +/- 0.4 4.0 +/- 0.9 2.7 +/- 0.8 5.9 +/- 0.6 2.5 +/- 0.9 3.6 +/- 0.5 5.9 +/- 0.6 3.3 +/- 0.4 2.9 +/- 0.8 5.5 0.6 5.7 1.1 4.7 1.2 4.7 1.2 4.9 0.8 4.8 +/- 0.7 4.6 +/- 0.7 6.9 +/- 0.5 4.9 +/- 0.9 3.9 +/- 1.3 4.3 +/- 1.2 5.4 +/- 0.9 4.4 0.7 5.4 1.3 4.6 0.9 3.1 0.8 3.1 1.2 3.6 1.9 3.6 1.2 2.8 1.4 4.2 i 0.8 3.7 +/- 1.5 4.3 +/- 0.3 4.9 +/- 1.0 3.0 +/- 0.9 3.0 +/- 1.0 2.7+/- 0.7 3.1 0.2 2.5 0.6 3.3 +/- 1.7 3.8 +/- 1.7 3.6 +/- 0.5 4.7 i 0.9 4.6 +/- 1.2 3.5 +/- 1.0 6.3 +/- 0.9 3.3 +/- 1.0 4.1 +/- 1.3 6.6 +/- 1.1 3.6 +/- 1.2 3.8 +/- 2.2 5.3 +/- 0.6 5.4 +/- 0.5 4.7 +/- 0.4 4.4 +/- 0.6 4.8 +/- 0.4 4.6 +/- 0.2 4.5 +/- 0.4 6.8 +/- 0.6 4.8 +/- 0.5 3.8 +/- 0.5 4.0 +/- 0.3 4.7 +/- 0.7 4.2 +/- 0.6 5.1 +/-0.4 4.1 +/-0.8 2.6 +/- 0.6 3.0 +/- 0.1 3.2 +/- 0.5 3.4 +/- 0.2 2.4 +/- 0.6 4.3 +/- 0.5 3.2 +/- 0.6 3.6 +/- 0.7 4.3 +/- 0.5 2.9 +/- 0.2 2.7 +/- 0.5 2.7 +/- 0.2 2.9 +/- 0.2 2.4 +/- 0.2 3.2 +/- 0.4 3.4 +/- 0.3 3.3 +/- 0.4 4.5 +/- 0.5 4.3 +/- 0.6 3.0 +/- 0.8 6.1 +/-0.2 2.9 +/- 0.7 3.8 +/- 0.6 6.4 +/- 0.5 3.5 +/- 0.2 3.2 +/- 0.5 28
[=7 r-z ITT XL
- 77 ET-UT
[
17CONENRAIO till FTLTRE AIR E
E
,1TA CONCE NTRA TION IN FIL TE RED A IR TABLE 3-3: GROSS BL Surry Nuclear Power Station, Surry County, Virginia - 2005 l.oE,3 pCi/m3 +/- 2 Sigma Page 1 of 2 l COLLECTION I SAMPLING LOCATIONS I
DATE I
SS HIR BC ALL CP BASF FE NN-C January 04 January 11 January 18 January 25 February 01 February 08 February 15 February 22 February 28 March 07 March 15 March 22 March 29 31.5 +/- 5.1 13.6 +/- 4.4 24.3 +/- 5.2 25.4 +/- 5.4 23.5 21.8 19.0 24.2 16.5
+ 5.1
+/- 4.7
+/- 4.8
+/- 5.2
+ 3.5 23.9 +/- 4.6 9.4 +/- 4.1 19.7 +/- 4.9 20.9 +/- 5.0 20.5 +/- 4.9 21.3 +/- 4.7 17.5 +/- 4.7 20.9 +/- 4.9 20.2 +/- 3.6 18.2 +/- 4.7 16.6 +/- 4.4 21.0 +/- 2.7 8.4 +/- 3.8 29.0 +/- 5.0 9.6 +/- 4.1 24.3 +/- 5.1 27.5 +/- 5.3 22.8 +/- 5.0 24.3 +/- 4.8 21.0 +/- 4.8 29.4 +/- 5.3 15.2 +/- 3.4 16.7 +/- 4.7 17.6 +/- 4.4 21.2 +/- 2.7 8.5 +/- 3.7 29.7 +/- 5.0 12.3 +/- 4.2 25.9 +/- 5.2 26.5 +/- 5.3 24.3 +/- 5.1 22.7 +/- 4.7 21.2 +/- 4.8 28.3 +/- 5.2 16.7 +/- 3.4 20.9 +/- 4.8 17.9 +/- 4.4 24.7 +/- 2.8 10.8 +/- 3.9 31.9 +/- 5.1 14.6 +/- 4.4 25.5 +/- 5.2 24.8 +/- 5.2 20.1 +/- 4.9 24.5 +/- 4.8 21.3 +/- 4.8 27.7 +/- 5.2 17.2 +/- 3.5 19.4 +/- 4.8 18.3 +/- 4.4 22.3 +/- 2.7 10.6 +/- 3.9 31.9 +/- 5.1 12.0 +/- 4.3 24.5 +/- 5.1 24.2 +/- 5.2 18.5 +/- 4.8 22.3 +/- 4.6 17.8 +/- 4.7 23.6 +/- 5.0 16.8 +/- 3.4 18.8 +/- 4.7 17.0 +/- 4.3 20.5 +/- 2.7 10.4 +/- 3.9 31.3 +/- 5.1 16.4 +/- 4.5 21.0 +/- 4.9 27.6 +/- 5.4 22.4 +/- 5.0 19.1 +/- 4.5 17.1 +/-4.6 22.7 +/- 5.0 14.8 +/- 3.4 30.4 10.1 23.0 29.1
+/- 5.1
+/- 4.2
+/- 5.2
+/- 5.9 18.8 +/- 4.9 19.6 +/- 4.6 22.1 +/- 5.0 27.9 +/- 5.7 18.2 +/- 3.6 23.2 +/- 5.1 20.6 +/- 4.7 21.2 +/- 2.9 12.8 +/- 4.1 18.8 +/- 4.8 16.5 +/- 4.5 26.3 +/- 3.0 10.2 +/- 3.9 19.1 17.0 22.5 11.3
+/- 4.7
+/- 4.3
+/- 6.0 (a)
+/- 4.0 Qtr. Avg. +/-t2 s.d.
April 05 April 12 April 19 April 26 May 03 May 10 May 17 May 24 May 31 June 07 June 14 June 21 June 28 20.9 +/- 11.6 11.1 +/-3.8 14.5 +/- 4.7 19.2 +/- 4.4 18.7 +/- 4.6 13.5 +/- 4.5 12.5 +/- 4.7 16.1 +/- 4.4 12.7 +/- 4.6 10.3 +/- 4.0 11.6 +/- 3.9 17.0 +/- 4.3 10.3 +/- 3.8 21.5 +/- 4.4 18.3 +/- 9.2 20.5 + 13.5 10.1 +/- 3.7 13.3 +/- 4.6 17.8 +/- 4.2 13.1 +/- 4.0 14.8 +/- 4.5 15.8 +/- 4.8 11.1 +/-4.0 10.1 +/- 4.4 7.8 +/- 2.1 6.9 +/- 3.6 9.5 +/- 3.8 8.3 +/- 3.6 14.4 +/- 4.0 9.6 +/- 3.6 14.7 +/- 4.7 15.8 +/- 4.1 15.6 +/- 4.2 14.6 +/- 4.5 11.3 +/- 4.6 16.2 +/- 4.3 15.0 +/- 4.6 15.1 +/- 4.2 12.7 +/- 4.0 12.5 +/- 4.0 11.0 +/- 3.8 16.3 +/- 4.1 21.7 +/- 11.7 14.5 +/- 3.9 16.5 i 4.8 20.3 +/- 4.4 22.4 +/- 4.6 18.5 14.9 17.8 18.2 12.5 12.4 13.2 10.1 17.0
+/- 4.7
+/- 4.7
+/- 4.4
+/- 4.8
+/- 4.1
+/- 3.9
+/- 4.0
+/- 3.7
+/- 4.1 21.4 +/- 11.3 8.1 +/- 3.6 16.7 +/- 4.8 20.8 +/- 4.4 18.8 +/- 4.5 15.9 +/- 4.6 16.2 +/- 4.8 18.5 +/- 4.5 17.1 +/-4.7 19.4 +/- 4.5 11.8 +/- 3.9 15.3 +/- 4.2 14.9 +/- 4.0 23.3 +/- 4.5 13.5 +/- 3.9 17.6 +/- 4.8 21.3 +/- 4.4 16.2 +/- 4.3 18.0 +/- 4.7 18.6 +/- 4.9 15.8 +/- 4.3 15.3 +/- 4.6 14.5 +/- 4.2 11.7 +/- 3.9 16.6 +/- 4.2 13.7 +/- 4.0 21.4 +/- 4.4 19.9 + 11.3 20.2 + 10.6 11.5 +/- 3.8 19.6 +/- 4.9 18.0 +/- 4.3 18.8 +/- 4.6 21.1 +/- 4.9 15.6 +/- 4.8 18.5 +/- 4.5 14.9 +/- 4.6 14.5 +/- 4.2 13.6 +/- 4.0 16.7 +/- 4.2 14.5 +/- 4.0 16.9 +/- 4.1 21.3 +/- 11.7 13.6 +/- 4.0 14.9 +/- 4.8 17.0 +/- 4.3 22.2 +/- 4.8 19.8 +/- 4.8 19.8 +/- 5.2 16.3 +/- 4.4 13.2 +/- 4.7 14.9 +/- 4.3 12.7 +/- 4.0 15.6 +/- 4.2 11.1 +/-3.8 21.9 +/- 4.4 Qtr. Avg. +/- 2 s.d.
14.5 + 7.3 11.8 +/- 6.7 13.9 +/- 4.4 16.0 +/- 7.0 16.7 +/- 7.7 16.5 +/- 5.8 16.5 +/- 5.4 16.4 +/- 7.1 29
U7 r-r-
r-- r-_-
U717 izz 177 n
U r
r7 rzz v7i r7 r7 r--J r
=7 TABLE 3-3: GROSS BETA CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2005 1.OE-3 pCi/ni3 2 Sigma Page 2 of 2 1 COLLECTION I
SAMPLING LOCATIONS I
I DAT e I
July 05 July 12 July 19 July 26 August 02 August 09 August 16 August 23 August 30 September 06 September 13 September 20 September 28 13.0 +/- 4.0 20.7 +/- 4.6 7.9 +/- 3.9 22.1 +/-4.5 25.3 +/- 3.4 34.6 +/- 5.4 18.6 +/- 4.5 26.7 +/- 4.9 16.5 +/- 4.2 19.2 +/- 4.7 21.6 +/- 4.6 21.1 +/- 5.2 25.9 +/- 5.0 7.5 +/- 3.7 12.5 +/- 4.1
<5.9 22.2 +/- 4.5 26.5 +/- 3.4 33.1 +/- 5.4 18.1 +/-4.5 21.7 +/- 4.6 14.8 +/- 4.2 17.2 +/- 4.6 24.4 +/- 4.8 19.6 +/- 5.1 29.6 +/- 5.2 14.7 +/- 4.1 20.3 +/- 4.5 9.1 +/- 4.0 20.1 +/- 4.4 25.8 +/- 3.4 33.8 +/- 5.4 18.2 +/- 4.5 25.1 +/-4.8 16.0 +/- 4.3 20.5 +/- 4.7 21.5 +/- 4.8 21.1 +/- 5.1 29.3 +/- 5.3 15.9 +/- 4.2 20.9 +/- 4.5 10.9 +/- 4.1 25.7 +/- 4.7 25.6 +/- 3.4 40.3 +/- 5.7 14.3 +/- 4.3 27.4 +/- 4.9 14.0 +/- 4.2 19.3 + 4.6 24.6 +/- 4.9 23.5 +/- 5.2 33.0 + 5.4 16.2 +/- 4.2 22.1 +/- 4.6 9.9 +/- 4.0 14.5 +/- 4.8 (b) 24.4 +/- 3.3 32.4 +/- 5.3 19.2 +/- 4.8 21.7 +/- 4.6 18.3 +/- 4.4 17.0 +/- 4.5 22.6 +/- 4.8 20.9 +/- 5.0 30.0 +/- 5.3 12.9 +/- 4.0 19.6 +/- 4.5 8.3 +/- 4.0 26.0 +/- 4.7 28.7 +/- 3.5 39.5 +/- 5.7 20.8 +/- 4.6 25.3 +/- 4.8 18.4 +/- 4.5 20.8 +/- 4.7 21.2 +/- 4.7 23.7 +/- 5.2 35.1 +/- 5.6 14.9 +/- 4.1 25.3 +/- 4.8 10.0 +/- 4.1 26.9 +/- 4.7 24.1 +/- 3.3 40.9 +/- 5.8 15.5 +/- 4.3 25.3 +/- 4.8 18.0 +/- 4.4 20.1 +/- 4.7 24.6 +/- 4.9 23.5 +/- 5.1 30.5 +/- 5.3 13.9 +/- 4.1 22.4 +/- 4.7 8.6 +/- 4.0 24.0 +/- 4.6 16.9 +/- 4.4 (c) 23.4 +/- 5.1 (d) 16.3 +/- 4.7 22.8 +/- 4.7 23.3 +/- 4.7 20.3 +/- 4.7 24.7 +/- 4.9 22.6 +/- 5.2 32.2 +/- 5.4 Qtr. Avg. +/- 2 s.d.
October 04 October 11 October 18 October 25 21.0 +/- 13.2 22.5 8.7 15.1 29.2
+/- 4.7
+/- 4.5
+/- 4.2
+/- 5.2 20.6 +/- 14.5 20.0 +/- 4.6 11.7 +/- 4.6 11.8 +/- 4.0 32.3 +/- 5.3 21.2 +/- 12.8 15.4 +/- 4.3 9.7 +/- 4.5 14.8 +/- 4.2 32.5 +/- 5.4 22.7 +/- 16.4 16.1 +/- 4.3 10.3 +/- 4.7 18.4 +/- 4.4 30.2 +/- 5.2 20.7 +/- 12.1 16.6 t 4.3 7.1 +/- 4.3 16.4 +/- 4.3 30.6 +/- 5.3 23.1 +/- 16.6 23.0 +/- 15.6 25.0 8.8 16.3 29.0
+/- 4.7
+/- 4.4
+/- 4.3
+/- 5.2 21.9 7.3 14.1 29.4
+/- 4.6
+/- 4.3
+/- 4.1
+/- 5.2 20.9 +/- 11.7 19.1 +/- 4.4
<6.7 16.9 +/- 4.4 35.6 +/- 5.5 November 01 November 08 November 15 November 22 November 29 December 05 December 13 December 20 December 27 14.9 +/- 4.7 31.7 +/- 5.1 28.7 +/- 5.0 11.8 +/- 4.1 14.6 +/- 4.5 23.6 +/- 5.3 27.4 +/- 4.6 20.5 +/- 4.8 26.9 +/- 5.0 12.9 +/- 4.6 32.9 +/- 5.1 23.2 +/- 4.8 10.7 +/- 4.2 17.8 +/- 4.7 26.2 +/- 5.4 27.8 +/- 4.6 18.6 +/- 4.6 30.9 +/- 5.2 14.7 +/- 4.8 34.7 +/- 5.2 22.6 +/- 4.7 11.2 +/- 4.2 13.7 +/- 4.5 25.9 +/- 5.4 28.2 +/- 4.7 17.7 +/- 4.7 28.9 +/- 5.1 16.0 +/- 4.8 32.0 +/-t 5.0 28.2 +/- 5.0 14.4 +/- 4.3 18.4 +/- 4.7 14.5 +/- 4.8 33.4 +/- 5.1 23.6 +/- 4.7 12.4 +/- 4.2 14.2 +/- 4.5 29.4 +/- 5.5 27.2 +/- 4.6 17.7 + 4.6 29.1 +/- 5.2 21.7 +/- 5.1 33.9 +/- 5.1 31.6 +/- 5.2 16.9 +/- 4.5 17.2 +/- 4.7 32.9 +/- 5.7 28.7 +/- 4.7 22.1 +/- 4.9 32.6 +/- 5.3 14.9 +/-
33.7 +/-
26.2 +/-
14.7 +/-
19.4 +/-
4.7 5.1 4.9 4.3 4.7 16.8 36.9 30.6 13.2 16.0
+/- 4.9
+/- 5.3
+/- 5.2
+/- 4.3
+/- 4.6 27.7 26.1 22.6 33.4
+/- 5.5
+/- 4.5
+/- 4.8
+/- 5.3 27.9 +/- 5.5 28.5 +/- 4.6 22.7 +/- 4.9 34.8 +/- 5.4 31.1 +/- 5.7 30.4 +/- 4.8 24.5 +/- 5.0 30.0 +/- 5.2 Qtr. Avg. t 2 s.d.
21.2 +/- 15.0 A
J. I _.
I A 4
21.3 +/- 16.4 20.8 +/- 16.9 A
4
^
44 4f 4
4O 0
I V.V
'@ 4.1 l
l lV.
22.6 f 15.0 a"IO 1 nn ov.U
- SI.I 20.9
- 16.7 4^ n
.4^
^
Z;.o k
1o.W 24.4 +/- 15.8 na f
4A 4 C.IV 22.7 +/- 16.7
^^a 4^
^
eU.U 2
I la.V 25.1
- 16.7
^^
a.
4n n r.V I
I3 30
E 77 rUT U77 I-F7
[71
[77 C7 UTI E7
[777 UT IZIIZ
[7 UT
[71 rFiT
[77 Table 3-3 Footnotes (a) Air sampler not operational at sample change out on 3/22/05. Power pole case ground wire was broken.
Sample volume based on sampler timer indication of 24.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Volume was sufficient to meet required LLD.
(b) Air sampler not operational at sample change out on 7/26/05. Sample volume based on elapsed timer indication of 137.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Volume was sufficient to meet required LLD.
(c) Air sampler had reduced flow rate at sample change out 8/2/05 and flow rate could not be adjusted.
As found flow rate was 35.4 liters/minute versus a typical flow rate of 56.6 liters/minute. Sampler was also inoperable for approximately 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> based on the sampler timer indication. Suspect power outage due to storms in the area during the sample period. Sample volume was sufficient to meet required LLD.
(d) Air sampler not operational at sample change out on 8/9/05. Sample volume based on sampler timer indication of 49.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Volume was sufficient to meet required LLD.
31
r-r FIT UZ Fzz-Ur7 ETI E77 r7IX r-T FE-r7-~l I
FIT
£71
£-
E77
£77 C7 TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2005 I
1.OE,3 pCi/m3 +/- 2 Sigma COLLECTION I DATE l
55 SAMPLING LOCATIONS ALL CP Page I of 2 FE NN-C l
HIR BC BASF F
January 04 January 11 January 18 January 25
<41
<22
<27
<21
<35
<28
<31
<20
<12
<25
<27
<21
<38
<22
<22
<22
<32
<24
<21
<20
<34
<23
<24
<22
<35
<27
<29
<24
<33
<27
<18
<25 February 01 February 08 February 15 February 22 February 28 March 07 March 15 March 22 March 29 April 05 April 12 April 19 April 26 May 03 May 10 May 17 May 24 May 31 June 07 June 14 June 21 June 28
<27
<24
<33
<28
<27
<26
<21
<22
<26
<23
<21
<36
<33
<21
<20
<34
<25
<28
<27
<23
<40
<19
<33
<26
<24
<28
<27
<24
<19
<26
<23
<33
<20
<30
<38
<22
<24
<30
<26
<26
<26
<26
<34
<31
<28
<25
<37
<29
<22
<26
<25
<19
<25
<24
<23
<30
<35
<26
<19
<35
<27
<28
<25
<27
<27
<20
<28
<28
<39
<29
<26
<26
<17
<24
<21
<35
<18
<45
<36
<21
<24
<33
<30
<33
<28
<25
<31
<23
<30
<24
<35
<30
<26
<26
<23
<24
<30
<27
<17
<33
<32
<19
<24
<31
<23
<26
<25
<25
<37
<21
<33
<22
<33
<27
<27
<29
<19
<20
<25
<26
<18
<33
<36
<20
<28
<31
<29
<29
<24
<28
<32
<18
<30
<30
<32
<25
<29
<25
<21
<13 (a)
<23
<31
<18
<38
<38
<22
<23
<32
<25
<29
<25
<21
<36
<24
<26
<30
<23
<32
<22
<32
<26
<24
<22
<28
<14
<36
<33
<28
<24
<39
<25
<32
<23
<16
<29
<24 32
177 F7 r=;
17m Erl EEL Eh 7 r17-EL E L 7 C7 7
E7:l IL
[ 7 TABLE 3-4: IODINE-131 CONCENTRATION IN FILTERED AIR Surry Nuclear Power Station, Surry County, Virginia - 2005 1.OE-3 pCirm3
- 2 Sigma Page 2 of 2
(;CLLEt;IOIN I
SAMPLING LOCATIONS I
DATE SS HIR BC ALL CP BASF FE NN I
July 05 July 12 July 19 July 26 August 02 August 09 August 16 August 23 August 30 September 06 September 13 September 20 September 28 October 04 October 11 October 18 October 25
<23
<34
<25
<17
<29
<27
<30
<28
<26
<28
<28
<25
<27
<20
<37
<31
<35
<29
<35
<22
<19
<27
<24
<22
<23
<28
<26
<31
<19
<29
<25
<33
<31
<25
<28
<37
<23
<23
<17
<28
<26
<22
<25
<26
<28
<22
<30
<25
<35
<32
<28
<30
<29
<16
<24
<25
<30
<25
<27
<29
<25
<25
<24
<30
<24
<39
<24
<37
<23
<30
<21
<28 (b)
<27
<18
<24
<26
<29
<27
<29
<25
<32
<24
<43
<24
<27
<29
<23
<24
<23
<26
<27
<21
<26
<37
<25
<29
<28
<33
<28
<40
<24
<23
<29
<33
<21
<40
<25
<23
<22
<27
<26
<22
<30
<29
<27
<25
<31
<28
<31
<29
<32
<20
<28
<47 (c)
<38 (d)
<29
<25
<36
<24
<32
<25
<38
<24
<38
<30
<28 November 01 November 08 November 15 November 22 November 29 December 05 December 13 December 20 December 27
<40
<28
<42
<44
<29
<36
<29
<27
<38
<36
<27
<40
<39
<35
<39
<26
<29
<38
<40
<29
<29
<38
<29
<33
<23
<31
<46
<41
<26
<38
<36
<35
<37
<29
<25
<46
<43
<13
<38
<39
<28
<30
<25
<31
<39
<30
<23
<36
<40
<21
<27
<25
<26
<47
<43
<27
<35
<42
<24
<26
<26
<30
<39
<54
<26
<30
<40
<20
<30
<21
<23
<46 33
r-- r
Fir r-_77 177 177-177- [
77 7-177 171-iZ77.
177-17 77-177-F7Z 177 FT Table 3-4 Footnotes (a) Air sampler not operational at sample change out on 3/22/05. Power pole case ground wire was broken.
WSsmple volume hnsed an sampler timer indiratiron of 9a.5 hnii-rs. volume wxas sulfficient to meet required LLD.
(b) Air sampler not operational at sample change out on 7/26/05. Sample volume based on elapsed timer indication of 137.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Volume was sufficient to meet required LLD.
(c) Air sampler had reduced flow rate at sample change out 8/2/05 and flow rate could not be adjusted.
As found flow rate was 35.4 liters/minute versus a typical flow rate of 56.6 liters/minute. Sampler was also inoperable for approximately 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> based on the sampler timer indication. Suspect power outage due to storms in the area during the sample period. Sample volume was sufficient to meet required LLD.
(d) Air sampler not operational at sample change out on 8/9/05. Sample volume based on sampler timer indication of 49.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Volume was sufficient to meet required LLD.
34
TABLES3-5: G o4M 7ER CONCENTR4IONINFILTEREDAIR Suiy Nuclear Pbmer Station, Sun' Cuntr, Virginia - 2005 LOE-3 pCl/nB 2 Sigr PaRge of 1 CRST SECOND)
TIRD FOURTH AVERA]
ILo S
MJCUIDEI QUARTER QUARTER ouARTER QUARTER
+/-F 2 SIGAf9 Ss CS134 CS-137 Be-7 FIR BC ALL CS-134 CS-137 Be-7 CS-134 C&-137 Be-7 Cs-134 Ca-137 Be-7
<1.8
<0.8 104 +/- 22
<1.2
<0.6 107 +/- 19
<1.4
<0.9 113 +/- 25
<1.0
<1.0 105 +/- 22
<0.8
<0.8 122 +/- 24
<1.0
<0.8 100 +/- 24
<1.1
<1.0 150 +/- 24
<1.0
<1.0 118 +/- 26
<1.4
<0.8 87 +/- 27
<1.7
<1.1 94 +/- 26
<1.5
<1.5 102 +/- 27
<1.5
<1.2 108 +/- 30
<1.6
<1.6 124 +/- 29
<1.4
<1.4 106 +/- 31
<1.0
<1.6 135 +/- 32
<1.4
<1.0 116 +/- 30
<1.7
<1.6 129 +/- 29
<1.0
<2.0 130 + 30
<1.4
<0.9 118 +/- 28
<1.6
<1.3 99 +/- 28
<1.5
<1.9 112 +/- 29
<1.2
<1.6 139 +/- 29
<1.0
<1.4 132 +/- 28
<1.8
<1.6 107 +/- 29
<1.5
<1.6 149 +/- 36
<1.3
<1.9 112 +/- 32
<1.6
<1.1 133 +/- 34
<1.6
<1.2 125 +/- 34
<1.2
<0.9 108 +/- 26
<1.0
<1.4 137 +/- 32
<1.6
<1.5 110 +/- 31
<1.5
<1.1 124 +/- 30 117 +/-27 111 +/-15 117 +/-+13 109 +11 117 +/-8 121 +/-+2) 132 +/- 17 116 +/-7 CP CS-134 CS-137 Be-7 BASF Cs-134 Cs-137 BE-7 FE Os-134 Os-137 Be-7 NN-C Cs-134 Cs&137 Be-7 35
TABLE3-6:
I4MMEMIT ERANDSTRONTIUMCONCENTRATIONSIN MILK Surry Nuclear Power Station, Surry County, Virginia - 2005 pCluter t2Signa Pap 1 of 3 COLONIAL JUCLDE I
EPPS PARKWAY WIlLUAMS-C JANUARY Cs-1 34 Cs-1 37 Ba-1 40 La-1 40 K40
<5
<6
<10
<1 1450 +/- 120
<6
<7
<8
<1 1380 +/- 120
<6
<6
<7
<8
<1 1330 t 110 FEBRUARY Cs-134 Cs-i 37 Ba-1 40 La-140 1-131 K-40 MARCH Cs-1 34 Cs-i 37 Ba-1 40 La-140 1-121 K-43 Sr-E9 Sr-EO
<7
<7
<11
<13
<1 1400 +/- 140
<9
<7
<10
<11
<1 1300 +/- 130
<8
<7
<10
<11
<1 1500 +/- 140
<8
<7
<10
<12
<1 1190 +/- 130
<6
<10
<11
<1 1260 +/- 130
<9
<7
<7
<13
<15
.<1 1170 +/- 140 APRIL Cs-134 Cs-137 Ba-140 La-110 1-131 K4)
<9
<8
<12
<14
<1 1560 +/- 190
<10
<8
<11
<13
<1 1300 +/- 170
<9
<8
<13
<15
<1 1380 + 160 36
TABLE3-6: 'EMRMETERANDSTRONTIUM CONCENTRATIONSIN MILK Surry Nuclear Power Station, Surry County, Virginia - 2005 pa/liter +/- 2 Signia Pagre 2 of 3 COLONIAL
]JCLDE I EPPS PARKWAY WILUAMS-C MAY CS-134 CS-1 37 Ba-140 La-1 40 1-131 K-40 JUNE Cs-1 34 Cs-1 37 Ba-1 40 La-140 1-131 K-40 Sr-EG Sr-SO JULY Cs-1 34 Cs-1 37 Ba-140 La-140 1-131 K-4)
AUGUST CsX1:34 Cs-1i37 Ba-140 La-140 1-131 K-4)
<7
<6
<11
<12
<1 1350 +/- 130
<8
<5
<10
<12
<1 1370 +/- 130
<9
<6
<9
<10
<1 1430 +/- 150
<6
<6
<10
<11
<1 1480 +/- 120
<7
<6
<8
<9
<1 1380 +/- 120
<7
<7
<10
<11
<1 1430 +/- 120
<7 1.76 +/- 0.69
<7
<8
<11
<12
<1 1540 +/- 140
<7
<7
<12
<14
<1 1390 +/- 150
<9
<8
<12
<14
<1 1170 +/- 150
<7
<6
<11
<13
<1 1480 +/- 140
<9
<10
<12
<14
<1 1520 +/- 180
<7
<7
<12
<14
<1 1310 +/- 130 37
TABLE3-6: (iMM4EXM ER ADSTRONTIUMCONCENTRATIONSINAMLK Surry Nuclear Powver Station, Surry County, Virginia - 2005 pc/Liter +/- 2 Sigm Page 3 of 3 COLONIAL j
IDE EPPS PARKWAY WILLIAMS-C SEPTEMBER Cs-1 34 Cs-1 37 Ba-1 40 La-1i40 1-131 K-40 Sr-89 Sr-90 OCTOBER Cs-1 34 Cs-1 37 Ba-140 La-1i40 1-131 K-43
<8
<7
<12
<14
<1 1370 +/- 160
<8
<6
<11
<12
<1 1390 +/- 140
<9
<8
<13
<14
<1 1240 +/- 160
<9
<2
<6
<8
<10
<12
<1 1400 +/- 140
<7
<8
<11
<13
<1 1340 + 140
<6
<6
<10
<11
<1 1360 + 120 NOVEMBER Cs-1 34 Cs-1 37 Ba-1i40 La-140 1-131 K-43 DECEMBER Cs-1:34 Cs-1 :37 Ba-140 La-1140 1-131 K-4)
Sr-E9 Sr-SO
<8
<8
<10
<12
<1 1320 +/- 150
<8
<8
<13
<14
<1 1270 +/- 150
<7
<7
<11
<13
<1 1370 +/- 130
<7
<6
<11
<12
<1 1450 +/- 130
<10
<2
<8
<6
<12
<13
<1 1370 +/- 130
<8
<7
<10
<10
<1 1470 +/- 140 38
TABLE3-7: G4AM4 EMJ7lV i7? CONCENTRATIONINFOODPRODUCJS Surry Nuclear Poer Station, Sury County, Virginia -2005 pCVkg (et) +/-2 Signx Pag 1 of 1 I SAMPLING COLLECnION SAMIPLE I ILOCATI DATE TYPE I Cr,134 CS-137 1-131 K-40 L
BROCK 11/02105 FARM 11/02105 Com Peanuts
<12
<24
<33
<13
<22
<34
<30
<37
<57 2090 +/- 190 3540 +/-410 17270 +/-9E0 SLADE FARM 11/02105 Soybeans 39
TA13LE3-8 G4MMEAMIAND TR1UMCONCENARATIONS IN WELL WATER Surry Nuclear Pomer Station, Surry County, Virginia -2005 pCaliter+/- 2Sig Page I of I SAMPUNG COLLECTION LOCATIONS DATE ISOTOPE SS 03/15/05 06/14/05 09/20(05 12/13/05 03/15/05 06'14/05 09/20/05 12/13105 03/15/05 06/14/05 09/20/05 12/13/05 Ba-140
<8
<11
<8
<10 Fe-59
<16
<19
<6
<12 Zn-65
<14
<17
<6
<10 Ba-140
<8
<12
<10
<11 Fe-59
<10
<21
<10
<10 Zn-65
<11
<19
<9
<12 Co-58
<6
<9
<3
<5 1-131
<1
<1
<1
<1 Zrm95
<10
<13
<5
<8 Co-58
<5
<9
<4
<8 1-131
<1
<1
<1
<1 Zr-95
<7
<14
<9
<11 Co 60
<5
<9
<3
<6 La-140
<9
<13
<9
<11 Cs-134
<6
<8
<3
<6 Mn-54
<5
<7
<3
<5 Cs-137
<6
<8
<3
<6 Nb-95
<6
<11
<4
<6 H-3
<1000
<560
<1400
<1500 HIR 0315/05 06/14/05 09/20/05 12/13/05 CO60
<5
<7
<4
<8 La-140
<9
<14
<11
<12 Cs-134
<5
<9
<4
<7 Mn-54
<5
<7
<4
<6 Cs-137
<5
<8
<4
<6 Nb-95
<5
<8
<5
<8 0215/05 06/14/05 09/20/05 12/13105 03115/05 06/14/05 0920/05 12/13/05 H-3
<1000
<560
<1400
<1500 40
TABLE 3-9: GAMMA EMITTERAND TRITIUM CONCENTRATIONS IN RIVER WATER Surry Nuclear Po~wr Station, Surry County, Virginia - 2005 pC/Liter +/- 2 Sig=rxl Page I of 2 SAMPLING COLLECTION LOCATIONS DATE I
ISOTOPE Ba-140 Co-58 Co-60 Cs-134 Cs-137 SD 01/11/05
<7
<4
<4
<4
<3 02/15/05
<9
<3
<4
<4
<4 03'29/05
<10
<5
<6
<5
<6 04/19/05
<12
<6
<6
<6
<6 05/24/05
<5
<3
<3
<4
<3 06/14/05
<9
<6
<6
<6
<6 07/26/05
<7
<4
<4
<4
<4 08/16/05
<8
<4
<5
<5
<4 09/20/05
<9
<5
<5
<5
<6 10/25/05
<10
<6
<6
<6
<6 11/22/05
<9
<6
<5
<5
<5 12/1305
<10
<6
<6
<6
<6 Fe-59 1-131 La-140 Mn-54 Nb-95 01/11/05
<10
<8
<8
<4
<4 02/15/05
<10
<9
<10
<4
<4 03/29/05
<15
<10
<11
<5
<6 04/19/05
<16
<10
<14
<6
<7 05/24/05
<9
<6
<6
<3
<3 06/14/05
<12
<10
<10
<5
<6 07/26/05
<10
<6
<9
<4
<5 08/16/05
<13
<8
<9
<4
<5 09/20/05
<13
<10
<10
<5
<6 10/25/05
<10
<10
<12
<6
<7 11/22/05
<11
<10
<10
<5
<6 12113/05
<10
<10
<11
<5
<7 Zn-65 Zr-95 H-3 K-40 01/11/05
<9
<7
<50 02/15/05
<11
<7
<55 03/29/05
<7
<8
<950
<63 04/19/05
<14
<12
<71 05/24/05
<6
<5
<47 06/14/05
<13
<9
<1200
<74 07/26/05
<8
<6 92 +/- 42 08/16/05
<9
<8 126 44 09/20/05
<18
<8
<1200 99 +/- 48 10/25/05
<13
<9 79 +/- 50 11/22/05
<14
<8 100 +/- 48 12/13/05
<18
<10
<1400
<77 41
TABLE 3-9: GAMMA EMITTER AND TRITIUM CONCENTRATIONS INRIVER WATER Surry Nuclear Power Station, Surry County, Virginia - 2005 pCi/Liter +/-2 Sigma Page 2 of 2 SAMPLING COLLECTIONI LOCATIONS DATE ISOTOPES L
sw-C 01/11/05 02115/05 03'29/05 04/19/05 05/24/05 06/14/05 07/26/05 08/16/05 09/20/05 10/25/05 11/22/05 12/13/05 01/11/05 02/15/05 03'29/05 04/19/05 05/24/05 06/14/05 07/26/05 08/16/05 09/20/05 10/25/05 11/22/05 12/13/05 01/11/05 02/15/05 03/29/05 04/19/05 05/24/05 06/14/05 07/26/05 08/16/05 09/20/05 10/25/05 11/22/05 12/13/05 Ba-140
<7
<6
<7
<12
<9
<9
<7
<8
<9
<10
<8
<8 Fe-59
<11
<9
<9
<15
<12
<12
<12
<13
<12
<10
<11
<10 Zn-65
<15
<9
<7
<11
<10
<11
<10
<10
<11
<15
<19
<14 Co-58
<4
<4
<4
<5
<4
<5
<4
<5
<5
<6
<5
<6 1-131
<6
<10
<8
<9
<10
<10
<9
<7
<8
<10
<10
<10 Zr-95
<7
<7
<6
<9
<7
<9
<7
<7
<9
<11
<8
<10 Co-60
<4
<4
<4
<7
<5
<6
<4
<5
<5
<6
<5
<5 La-140
<8
<7
<8
<14
<10
<10
<7
<9
<10
<11
<9
<9 H-3
<950
<1200
<1200
<1400 Cs-134
<4
<4
<5
<6
<5
<6
<5
<4
<5
<7
<5
<6 Mn-54
<4
<4
<4
<6
<5
<5
<4
<4
<5
<6
<5
<5 Cs-137
<4
<3
<4
<5
<5
<5
<5
<4
<5
<6
<5
<5 Nb-95
<5
<5
<5
<5
<5
<6
<5
<5
<5
<6
<8
<6 K-40
<52
<49
<51
<66
<75
<68
<21
<63 86 +/- 57
<80
<64
<80 42
TABLE3-10: GAM EM7TER CONCEATRAT1ONSINSILT Surry Nuclear Pomer Station, Surry County, Virginia - 2005 pa/kg (dry) +/-2 Sigma Page I of I CSAMPUNG COLLECTIONI LOCATIONS DATE Be_7 K-40 Th-228 Cs-134 Cs-137 SD 03/17/05 09/27/05 CHIC-C 03/16/05 09/27/05
<820 16900 +/- 1800 790 +/- 400 16800 +/- 1200
<1200 17200 +/- 2500
<520 15070 +/- 910 1150 +/- 230 1030 +/- 120 1160 +/- 320 1240 +/- 100
<84
<47
<140
<34 235 +/- 77 223 +/- 49 250 +/- 100 179 +/- 41 43
TABLE3-11: G4 EMAETER CONCENTRATIONSINSHORELINESEDIMEN)
Surry Nuclear Pover Station, Surry County, Virginia - 2005 p0kg (dry) +/- 2 Sig=m Page I of I SAMPUNG COLLECTIONl LOCATION3 DATE I
Be-7 K-40 Th-228 Cs-134 Cs-137J HIR 02/08/05 0816/05
<200
<240
<240
<280 4760 +/- 520 3840 + 480 610 +/- 220 1850 +/- 420
<110 511 + 60 904 +/- 69
<120
<36
<110
<29
<130
<26
<26
<29
<31 CHIC-C 02/08/05 08116/05 44
TABLE 3-12.' GAMMA EM1TTER CONCENTRATIONIN FISH Surry Nuclear Power Station, Surry County, Virginia - 2005 pCi/kg (wet) +/- 2 Sigma Page I of I SAMPLING COLLECTION SAMPLE LOCATION DATE TYPE I
ISOTOPE SD 04/26/05 04/26/05 11/01/05 11/01/05 Catfish White Perch Catfish White Perch K-40 1400 +/- 590 1200 +/- 620 1480 +/- 440 2310 +/- 540 CO-58
<64
<71
<39
<36 Co-60
<48
<60
<35
<41 Cs-134
<52
<63
<34
<40 04/26/05 04/26/05 11/01/05 11/01/05 Catfish White Perch Catfish White Perch Cs-137
<56
<67
<34
<28 Fe-59
<130
<160
<74
<66 Mn-54
<70
<50
<34
<38 Zn-65
<130
<130
<120
<83 45
TABLE 3-13: GAMMA EMITTER CONCENTRATIONS IN OYSTERS Surry Nuclear Power Station, Surry County, Virginia -2005 pCi/kg (wet) +/- 2 Sigma Page I of I SAMPLING COLLECTION_
LOCATIONS DATE ISOTOPE POS 03/16/05 09/27/05 03/16/05 09/27/05 K40 340 +/- 110 532 t 77 Cs-137
<10
<9 K40 240 +/- 100 490 +/- 100 Cs-137
<9
<11 Co-58
<11
<8 Fe-59
<41
<17 Co-58
<11
<11 Fe-59
<41
<23 Co-60
<10
<7 Mn-54
<10
<7 Co-60
<11
<9 Mn-54
<9
<10 Cs-134
<9
<7 Zn-65
<22
<15 Cs-134
<10
<15 Zn-65
<38
<22 MP 03/16/05 09/27/05 03/16/05 09/27/05 46
TABLE 3-14: GAMMA EMITTER CONCENTRATIONS IN CLAMS Surry Nuclear Power Station, Surry County, Virginia - 2005 pCi/kg (wet) +/- 2 Sigma Page I of 1 SAMPLING COLLECTION LOCATIONS DATE ISOTOPE HIP 03/16/05 09/27/05 03/16/05 09/27/05 SD 03/16/05 09/27/05 K-40 230
+/- 100 297 +/- 95 Cs-137
<10
<8 K-40 229 +/- 59 460 +/- 110 Cs-137
<6
<10 K-40 180 +/- 110 236 +/- 95 Cs-1 37
<11
<9 Co-58
<12
<10 Fe-59
<37
<20 Co-58
<7
<10 Fe-59
<20
<20 Co-58
<13
<9 Fe-59
<40
<21 Co-60
<11
<9 Mn-54
<10
<9 Co-60
<5
<11 Mn-54
<6
<9 Co-60
<11
<9 Mn-54
<10
<9 Cs-134
<10
<9 Zn-65
<21
<20 Cs-1 34
<6
<9 Zn-65
<17
<22 Cs-134
<12
<10 Zn-65
<25
<19 03/16/05 09/27/05 CHIC-C 03/16/05 09/27/05 03/16/05 09/27/05 LC 03/16/05 09/27/05 K-40 340 +/- 110 380 +/- 79 Cs-137
<12
<7 Co-58
<12
<8 Fe-59
<41
<18 Co-60
<12
<8 Mn-54
<10
<7 Cs-1 34
<10
<8 Zn-65
<23
<17 03/16/05 09/27/05 47
TABLE3-15: GAMMA EMIATER CONCENTR4TIONSINCRABS Surry Nuclear Povxer Station, Surry County, Virginia - 2005 pGlkg (wet) +/-2 Signx Page 1 of 1 SAPMPUNG COLLECTION LOCATIONS DATE I
ISOTOPE SD K-40 06/16/05 2010 +/- 380 Cs-137
<25 Co-58
<30 Fe-59
<97 CoO-6
<28 Mn-54
<26 Cs-134
<28 Zn-65
<50 48
- 4. DISCUSSION OF RESULTS Data from the radiological analyses of environmental media collected during 2005 and tabulated in Section 3, are discussed below.
The procedures and specifications followed in the laboratory for these analyses are as required in the AREVA NP Environmental Laboratory quality assurance manual and laboratory procedures.
In addition to internal quality control measures performed by the laboratory, it also participates 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 2005 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-4-0, and thorium-228 were detected in numerous samples.
The following is a discussion and summary of the results of the environmental measurements taken during the 2005 reporting period.
4.1 Gamma Exposure Rate A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation. 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 'LD locations.
Control and indicator averages indicate a steady relationship.
Two dosimeters made of CaF and LiF sensitive elements, and specifically designed for environmental monitoring, are deployed at each sampling location. In 2001, these TLDs replaced the previously used CaSO4:Dy in Teflon TLDs. The dose with the replacement TLDs is lower than that of the previously used TLDs. This is due to the increased sensitivity of the replacement TLD that provides a greater response to ambient radiation and improved statistical analysis.
49
Figure 4-1: DIRECT RADIATION MEASUREMJENT TLD RESULTS 8-7 -
6 -
(0 2 2 1
00 0
so a,
_N 0
Go CS4 0
0 rn To S
't 0 0 0 Cl Cq I-*
Site Boundry 5Mile A AvgControl The five-year trend since ILD type replacement indicates a gradual and across the board increase in ambient exposure.
However, the trend of the control and indicator locations continue to show the same historical relationship.
This indicates that the increasing trend is not related to the operation of Surry Power Station.
Global Dosimetry Solutions was contacted to comment on this trend.
Although Global acknowledged the trend, Global's assessment is that the increase is very slight per period and well below the overall measurement uncertainty for the entire ILD processing system (errors associated 'LD badge fade, instrument calibrations, background changes, etc.) This trend was also evident with the ILD exposures at North Anna Power Station, Dominion's other Virginia nuclear power station. This trend will continue to be monitored.
An evaluation of the control locations ambient exposures determined that control ERD location #41 might be introducing a high bias to the average control exposure.
Tie high bias from TLD #41 was not apparent prior to 2001 when the CaSO4:Dy 'LDs were in use. 'LD #41 is located 13.4 miles from Surry Power Station in a gravel commuter parking lot. A survey of the parking lot determined that the ambient exposure rate was twice the exposure rate at ILD #20, which is located in a grassy area approximately 5 miles from the power station. The survey data directly corresponds with the 'LD exposure data for 'LDs #41 and #20. The most probable cause for the higher ambient exposure at this control 'LD location is the natural product content in the granite rock base of the parking lot. The 50 cJX
same phenomenon was also noticed in TLD exposure data for TLDs #9 and #38.
These TLDs are also located in areas with a gravel base. A new location for TLD
- 41 is under evaluation with test TLDs and relocation should occur in 2006.
4.2 Airborne Gross Beta Air is continuously sampled by passing it through glass fiber particulate filters.
The filters collect airborne particulate radionuclides. Once a week the samples are collected and analyzed for gross beta activity. Results of the weekly gross beta analyses are presented in Table 3-3. A review of the results from control and indicator locations continues to show no significant variation in measured activities (see Figure 4-2 and 4-3). This indicates that any station contribution is not measurable.
Surry Power Station changed analytical laboratories for REMP sample analysis in 2002.
For the period 1994 to 2001, the average indicator and control concentrations were 0.0173 and 0.0177 pCi/m 3, respectively. For the period 2002 to present, the average indicator and control concentrations were 0.021.3 and 0.0219 pCi/m3, respectively.
Indicator and control data continue the historical trend of statistically comparable concentrations and radioactive gaseous effluents released from Surry Power Station continue to decline. The slight increase in average concentrations appears to be attributable to the laboratory change in 2002. A review of the 2002 - 2005 gross beta in particulate filter matrix data from the Interlaboratory Comparison Program determined an average laboratory bias of only 13.7%. Therefore, the laboratory analytic performance is acceptable.
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, except as noted above.
51
Rgure 4-2:2005 GROSS BETA IN AIR PARTICULATES 0.040 I
0.035 0.030 0.025 i
E 0.020 0a.
0.015 0.010 0.005 0.000 AAA
............Y s
iA.
£ jg[
lWX rr r r r r r r
0 6
00 I
I I I
'r ON C' I I
I
'sI 0
OI I
eI I IO 0
N Ot 0
-)
el o
t 0
0 0r -
cr
-M ol CO C_
M W
O s
O 00000 CZ O,
I) 00 Cl gs 0
_ q OR Q O1 Q
O o
.5 C5S 00--ClC_
l Avg Indicator --- -.- Ave Control I Rgure 4-3: GROSS BETA IN AIR PARTICULATES HISTORICAL TREND 1.OE+00 -
1.OE-01 L)
,E 1.OE-02 Iw _
NW 1.OE-03 -(a)
'sO N
00 ON 0
l
't
'sO N
00 0~
O N 00 0
ON O O
ON ON ON 0O ON ON ON 0
° 0
Clj Cl C
Cl C
r Avg Indicator
+
Avg Control -
Avg-Pre Op -
Required LLD 4.3 Airborne Radioiodine Air is also continuously sampled for radioiodines by passing it through charcoal 52 OC(
cartridges.
Once a week the charcoal cartridge samples are collected and analyzed. The results of the analyses are presented in Table 3-4. All results are below the lower limit of detection.
No positive iodine-131 was detected. These results are similar to pre-operational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl.
4.4 A tr Particulate Gamma The air particulate filters from the weekly gross beta analyses are composi.ted by location and analyzed quarterly by gamma spectroscopy. The results are listed in Table 3-5. The results indicate the presence of naturally occurring beryllium-7, which is produced by cosmic processes.
Examination of pre-operational data indicates comparable measurements of Be-7, as would be expected.
No man-made radionuclides were identified. These analyses confirm the lack of station effects.
4.5 Cow Milk Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the fact that consumption of milk is significant, results in this pathway usually being the imost critical from the plant release viewpoint.
This pathway also shows measurable amounts of nuclear weapons testing fallout.
Therefore, this media needs to be evaluated very carefully when trying to determine if there is any station effect.
Analysis results for cow milk are contained in Table 3-6. All results show a lack of detectable iodine-131 above the LLD of 1 pCi/L. Results of gamima spectroscopy indicate no other detectable station related radioactivity in the milk samples. In years past, cesium-137 has been detected sporadically.
The occurrences were attributed to residual global fallout from past atmospheric weapons testing. Cs-137 was not detected at a level above the LLD in 2005.
At the request of the Commonwealth of Virginia, a quarterly composite sample is prepared from the monthly milk samples from the Colonial Parkway collection station. The composite samples are analyzed for strontium-89 and strontium-90.
Sr-90 was detected in one of the four composites analyzed, at a concentration of 1.76 pCi/L. The average Sr-90 concentration for the ten year period of 1996 to 2005 is 1.90 pCi/L. The Sr-90 detected is not a part of station effluents but, rather, a product of nuclear weapons testing fallout. This conclusion can be made based upon: the lack of any positive indications of Sr-90 in effluents to account for such measurements, the lack of any positive indications of Sr-89 which is chemically similar and generally released in comparable quantities from the 53
station, and the trend of consistent declining levels since the pre-operational period.
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 rater 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 two indicator locations and analyzes for gamma radiation amd 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 Rfver Water Samples of the James River water are collected monthly and the results are presented in Table 3-9. All samples are analyzed by gamma spectroscopy. The monthly samples are also composited and analyzed for tritium on a quarterly basis. With the exception of naturally occurring potassium-40 observed in some samples analyzed, no other gamma emitters were 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 and trending graphs of cobalt-60 and cesium-137 in silt appear in Figures 4-4 and 4-5.
Historically, cobalt-60 has been detected in samples obtained from the indicator location (SD). However, no cobalt-60 was detected in 2004 and 2005.
54
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 Cs-137 in both the control and indicator samples and decreasing levels indicate that the presence of Cs-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, Cs-137 was detected in most silt samples with an average concentration as indicated in Figure 4-5. In 2005, cesium-137 was detected with an average indicator location concentration of 229 pCi/kg and an average control location concentration of 215 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.
Rgure 4-4: COBALT-60 IN SILT I.OE+04 1 OE 03 LOE+02 L.OE+O1 1.OE+OO, e'
0\\
00 0~
eq
'0 00 0
r' 0
00 0
c N-N-
N 00 00 00 00 00 a,
0\\
0 0~
0 0
0E 0
O>
O 0>
e oC' o',
Ov o§ o
0 0
0 0
aim cs ci l
Control - Chickahominy AStation DischargcI Chickahominy had detectable activity in 1982 and 1984 through 1994. Other years were <MDL.
Station Discharge was <MDL activity 1996 through 1998, 2004 and 2005.
55 COO6
Rgure 4-5: CESIUM-1 37 IN SILT 1.OE+04 I.OE+03 6
A 1.OE+02 rs t
00 0
e 00 0
°°
° 0
00 0
e' l
N N
N-N 00 00 00 00 00 a,
a~,
C' 0.
+
Control -Chickahominy -A-- Station Discharge Ave-Pre Op -Required LLD 4.10 Shoreline Sediment Shoreline sediment, unlike river silt, may provide a direct dose to humans.
Buildup of radioisotopes 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 radioisotopes potassium-40 and thorium-228 were detected at concentrations equivalent to normal background activities.
The activities of these radioisotopes indicate a steady trend. There were no radioisotopes 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.
4.12 Oysters Oysters are collected from two different locations.
The results of the oyster 56 0 0 9
analyses are presented in Table 3-13.
There were no gamma emitting radioisotopes detected in oysters sampled except for naturally occurring potassium-40. No station related radioactivity has been detected in this media since 1991. The absence of station related radionuclides is attributable to the replacement of steam generators in 1982 and. past improvements made to liquid effluent treatment systems.
4.13 Clams Clams are analyzed from four different locations.
The results of the gamma spectroscopy analyses are presented in Table 3-14.
Like oysters, no station related radioactivity was detected.
Naturally occurring potassium-40 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 radioisotopes were detected in the sample. This is consistent with pre-operalional data and data collected over the past decade.
57
LI i
- 5. PROGRAM EXCEPTIONS U
There were no REMP exceptions for scheduled sampling and analysis during 2005.
L U
U U
U 1 1 L
IL LI L
L L
L L
58
- 6. CONCLUSIONS The results of the 2005 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.
An evaluation of selected TLD locations is underway and location changes may occur in 2006.
> Airborne Exposure Pathway - Analysis of charcoal cartridge samples for radioiodines indicated no positive activity was detected. Quarterly gamma isotopic analyses of the composite particulate samples identified only naturally occurring beryllium-7. Air particulate gross beta concentrations at all of the indicator locations for 2005 trend well with the control location.
The 2002 - 2005 average concentration trend is 23% higher tham the average concentration trend from 1994 through 2001. The contract laboratory Interlaboratory Comparison Program data for particulate filter gross beta analyses was closely reviewed and no issues were identified. For the 2002 - 2005 period, the average vendor gross beta analysis was within 3.7% of the spike sample activity. Gaseous effluent release data was also reviewed and determined not to be a factor as the long term trend of activity released continues to decline. Due to satisfactory vendor performance, good effluent management practices and because the gross beta activity in the control and indicator locations show no significant variation, the increased gross beta trend seen in 2002 - 2005 is not attributable to the operation of Surry Power Station and may be more related to the change in analytical laboratories beginning in 2002.
>. Milk - Milk samples are an important indicator measuring the effect of radioactive iodine and radioisotopes in airborne releases. Cesium-137 and iodine-131 were not detected in any of the thirty-six samples.
Naturally occurring potassium-40 was detected at a similar level when compared to the average of the previous year.
Strontium-90 was detected in one of four samples this year at a concentration of 1.76 pCi/L. Strontium-90 is not a part 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 2005.
> Well Water - Well water samples were analyzed and the analyses indicated 59
r,
that there were no man-made radioisotopes present.
This trend is consistent throughout the monitoring period. No radioactivity attributable to the operation of the station was identified.
> River Water - All river water samples were analyzed for gamma emitting radioisotopes.
Naturally occurring potassium-40 was detected in six samples. Tritium was not detected at levels exceeding the lower limit of detection for any samples in 2005.
> Silt - Cesium-137 was detected in both the control and indicator samples.
The presence of Cs-137 is attributable to residual weapons testing fallout; its presence has been well documented. Cobalt-60 has not been detected since 2003.
> Shoreline Sediment - Naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities. There were no radioisotopes attributable to the operation of Surry Power Station found in any sample.
Aquatic Biota
> Fish - As expected, naturally occurring potassium-40 was detected in all four samples There were no other gamma emitting radioisotopes detected in any of the fish samples.
> Oysters and Clams - Other than naturally occurring potassium-40, there were no other gamma emitting radioisotopes detected in any of the oyster or clam samples.
> Crabs - Naturally occurring potassium-40 was detected. No other gamma emitting radioisotopes 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 1OC'FR50, 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.
62
L L
L Ii L
L L
APPENDICES U
L L
U L
63
APPENDIX A: LAND USE CENSUS Year 2005 64
LAND USE CENSUS*
Surry Power Station, Surry County, Virginia January 1 to December 31, 2005 Page 1 of 1 l
Nearest Nearest Nearest Nearest l
I Direction I
Resident I
Garden**
I Cow I
Goat l
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)
(a) 4.4 @ 1630 1.7 @ 1810 2.3 @ 2120 2.3 @ 2210 0.4 @ 2440 3.1 @ 2600 4.9 @ 2830 4.6 @ 3210 3.8 @ 3380 (a) 1.9 @ 320 4.9 @ 560 (a)
(a)
(a)
(a)
(a) 1.8 @ 1830 4.3 @ 1930 3.6 @ 2230 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 Containmnent.
- Area greater than 50 m2 and contains broadleaf vegetation.
(a) None 65
APPENDIX B:
SUMMARY
OF INTERLABORATORY COMPARISONS YEAR 2005 66
INTRODUCTION This appendix covers the Intercomparison Program of the AREVA NP Inc.
Environmental Laboratory.
AREVA NP uses QA/QC samples provided by Analytics, Inc. to monitor the quality of analytical processing associated with the Radiological Environmental Monitoring Program (REMP).
The suite of Analytics QA/QC samples is designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program in terms of sample number, matrices, and nuclicles. It was modified to more closely match the media mix presently being processed by AREVA NP and includes:
milk for gamma (10 nuclides) and low-level (LL) iodine-131 analyses once per
- quarter, m
milk for Sr-89 and Sr-90 analyses during the 1st and 3rd quarters,
> water for gamma (10 nuclides), low-level (LL) iodine-131, and gross beta analyses during the 1st and 3rd quarters,
> water for Sr-89 and Sr-90 analyses during the 1st and 4th quarters,
> water tritium analysis during the 2nd and 4th quarters,
> air filter for gamma (9 nuclides) analyses during the 2nd and 4th quarters,
> air filter for gross beta analysis during each quarter,
> filter for Sr-90 analysis during the 2nd and 4th quarters.
In addition to the Analytics Intercomparison Program, AREVA NP also participates in other intercomparison programs. These programs are the National Institute of Standards and Technology (NIS'I1 Measurement Assurance Program (MAP), the Environmental Resource Associates (ERA) Proficiency Test (P11 Program, the Department of Energy (DOE) Quality Assessment Program (QAP)!. and the Mixed Analyte Performance Evaluation Program (MAPEP).
RESULTS Intercomparison program results are evaluated using AREVA NP's internal bias acceptance criteria as defined below:
> within 25% of the known for gross beta in water,
> within 25% of the known for samples containing both Sr-89 and Sr-90,
> within 15% of the known value for other radionuclides, or
> within two sigma of the known value.
AREVA NP investigates any sample analysis result that does not pass these criteria.
Analytics Intercomparison Program results are included on the pages that follow for the first quarter through the fourth quarter of 2005. A total of 104 analysis results were obtained with 104 passing acceptance criteria, a 100% success rate.
67
ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY QA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 1 OF 4) 1st Quarter Identification Reported Known 2005 Number Matrix Nuclide Units Value (a)
Value (b)
Ratio (c)
Evaluation (d)
E4463-162 Milk 1-131LL 1-131 Ce-141 Cr-51 Cs-1 34 Cs-i 37 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/L 91.2 95.9 229 334 137 133 118 166 117 203 145 92.3 92.3 229 334 139 130 115 160 111 198 144 0.99 1.04 1.00 1.00 0.99 1.03 1.02 1.04 1.05 1.03 1.01 A
A A
A A
A A
A A
A A
E4464-162 Milk Sr-89 Sr-90 E4459-162 Water Gr-Beta E4460-162 Water 1-131 1-131LL Ce-141 Cr-51 Cs-i 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E4461-162 Water Sr-89 Sr-90 pCi/L 93.8 pCi/L 16.1 pCi/L 279 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 69.3 66.2 219 346 130 127 108 160 114 192 138 1.07 17.9 292 65.9 65.9 221 322 134 125 111 154 107 191 139 103 17.2 0.88 0.90 0.96 1.05 1.00 0.99 1.07 0.97 1.01 0.97 1.04 1.07 1.01 1.00 0.92 0.90 A
A A
A A
A A
A A
A A
A A
A A
A pCi/L 94.6 pCi/L 15.6 E4462-162 Filter Gr-Beta pCi 162 157 1.04 A
Footnotes are on page 4 of 4.
68
ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY OA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 2 OF 4) 2nd Quarter Identification Reported Known 2005 Number Matrix Nuclide Units Value (a) Value (b)
Ratio (c)
Evaluation (d)
E4603-162 Milk 1-131 pCi/L 1-131LL pCi/L Ce-141 pCi/L Cr-51 pCi/L Cs-1 34 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 86.8 85.7 96.3 295 87.7 186 5.83 124 67 149 138 86.9 86.9 92.4 303 95 189 5.30 125 63.9 155 145 1.00 0.99 1.04 0.98 0.92 0.98 1.10 0.99 1.05 0.96 0.96 A
A A
A A
A A
A A
A A
E4599-162 Water H-3 pCi/L E4600-162 Filter Gr-Beta pCi E4601-162 Filter Ce-141 pCi Cr-51 pCi Cs-1 34 pCi Cs-1 37 pCi Co-58 pCi Mn-54 pCi Fe-59 pCi Zn-65 pCi Co-60 pCi 9060 9100 125 59.3 207 59.1 131 3.55 88.6 40.1 112 89.4 90.5 13.0 127 58.9 193 60.6 120 3.4 79.7 40.7 98.8 92.3 97.5 12.6 1.00 0.99 1.01 1.07 0.98 1.09 1.04 1.11 0.99 1.13 0.97 0.93 1.03 A
A A
A A
A A
A A
A A
A A
E4602-162 Filter Sr-89 Sr-90 pci pci Footnotes are on page 4 of 4.
69
ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY OA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 3 OF 4) 3rd Quarter Identification Reported Known 2005 Number Matrix Nuclide Units Value (a)
Value (b)
Ratio (c)
Evaluation (d) m E4690-162 Milk 1-131 LL pCi/L 99.0 94.3 1.05 A
1-131 pCi/L 90.0 94.3 0.95 A
Ce-i 41 pCi/L 228.5 233 0.98 A
Cr-51 pCi/L 306.3 338 0.91 A
Cs-134 pCi/L 118.3 122 0.97 A
Cs-137 pCi/L 196.5 195 1.01 A
Co-58 pCi/L 64.0 63.4 1.01 A
Mn-54 pCi/L 94.7 92.0 1.03 A
Fe-59 pCi/L 63.3 61.0 1.04 A
Zn-65 pCi/L 121.7 123 0.99 A
Co-60 pCi/L 165.2 167 0.99 A
E4691-162 Milk Sr-89 pCi/L 139.6 146 0.96 A
Sr-90 pCi/L 10.8 11.5 0.94 A
E4686-162 Water Gr-Beta pCi/L 128.5 123 1.05 A
E4687-162 Water 1-131 pCi/L 77.2 78.2 0.99 A
1-131 LL pCi/L 78.3 78.2 1.00 A
Ce-141 pCi/L 276.4 282 0.98 A
Cr-51 pCi/L 353.7 408 0.87 A
Cs-134 pCi/L 137.3 148 0.93 A
Cs-137 pCi/L 231.1 235 0.98 A
Co-58 pCi/L 72.5 77 0.94 A
Mn-54 pCi/L 113.2 111 1.02 A
Fe-59 pCi/L 74.7 74 1.01 A
Zn-65 pCi/L 152.3 149 1.02 A
Co-60 pCi/L 192.1 202 0.95 A
E4689-162 Filter Gr-Beta pCi 120.8 112 1.08 A
Footnotes are on page 4 of 4.
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ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM AREVA NP ENVIRONMENTAL LABORATORY OA PROGRAM AREVA NP Inc. ENVIRONMENTAL LABORATORY (PAGE 4 OF 4) 4th Quarter Identification Reported Known 2005 Number Matrix Nuclide Units Value (a)
Value (b)
Ratio (c)
Evaluation (d)
E4841-162 Milk 1-131 pCi/L 74.1 74.6 0.99 A
1-131 LL pCi/L 72.4 74.6 0.97 A
Ce-141 pCi/L 217 224 0.97 A
Cr-51 pCi/L 190 193 0.99 A
Cs-134 pCi/L 86.4 87.3 0.99 A
Cs-137 pCi/L 187 189 0.99 A
Co-58 pCi/L 78.7 77.5 1.02 A
Mn-54 pCi/L 153 152 1.01 A
Fe-59 pCi/L 87.8 82.4 1.07 A
Zn-65 pCi/L 148 154 0.96 A
Co-60 pCi/L 106 111 0.95 A
E4836-162 Water H-3 pCi/L 13700 13200 1.04 A
E4837-162 Water Sr-89 pCi/L 80.3 91.4 0.88 A
Sr-90 pCi/L 7.18 7.4 0.97 A
E4838-162 Filter Gr-Beta pCi 146 136 1.08 A
E4839-162 Filter Ce-141 pCi 122 131 0.93 A
Cr-51 pCi 113 113 1.00 A
Cs-134 pCi 48 51 0.94 A
Cs-137 pCi il1 111 1.01 A
Co-58 pCi 44.2 45.2 0.98 A
Mn-54 pCi 93.5 88.9 1.05 A
Fe-59 pCi 44.6 48.1 0.93 A
Zn-65 pCi 95.8 89.9 1.07 A
Co-60 pCi 59.1 64.6 0.91 A
E4840-162 Filter Sr-89 pCi 103 121 0.86 A
Sr-90 pCi 9.05 9.7 0.93 A
(a) AREvA reported result.
(b) TheAnalytics standard.
(c) Rati: of AR EVA to Analytics results.
(d) Analytics evaluation: A= Acceptable. W= Acceptable with warning. U= Unacceptable.
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