ML20135C700
| ML20135C700 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/31/1984 |
| From: | Lei W CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20135C676 | List: |
| References | |
| NUDOCS 8509110507 | |
| Download: ML20135C700 (93) | |
Text
{{#Wiki_filter:Shearon Harris Energy & Environmental Center Carolina Power & Light Company New Hill, North Carolina PRE 0PERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING REPORT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT JANUARY 1, 1983, THROUGH DECEMBER 31, 1984 Prepared by: A
// Wayne Lei Senior Sp Wialist - Environmental Reviewed and Recommended by:
ch& E shR.~L. Shearinpsar >
- 0. F. Cahill ~
~~
Project Specialist - Environmental Project Specialist - Environmental Approved b :
. [1 G. H.~Warriner Principal Specialist - Environmental hh kD hO '
R-
t Table Of Contents 1 Page List of Tab 1es......................................................... ii List of Figures........................................................ 111
1.0 INTRODUCTION
.................................................. 1-1 1.1 Plant and Location............................................ 1-1 1.2 Environmental Monitoring Program.............................. 1-3 2.0 PROGRAM
SUMMARY
............................................... 2-1 3.0 INTERPRETATIONS AND CONCLUSIONS............................... 3-1 3.1 Air........................................................... 3-1 3.2 M11k.......................................................... 3-2 3.3 Food Crop Vegetation.......................................... 3-3 3.4 Shoreline Sediment............................................ 3-4 3.5 Bottom Sediment............................................... 3-4 3.6 Surface Water................................................. 3-5 3.7 Drinking Water................................................ 3-6 3.8 Groundwater................................................... 3-7 3.9 Fish.......................................................... 3-8 3.10 External Radiation Exposure................................... 3-8 3.11 Special Sampling of Environmental Media....................... 3-9 3.11.1 Venison....................................................... 9 3.12 Ambient Environmental Dose Estimates.......................... 3-10 3.12.1 Methods and Assumptions....................................... 3-10 3.12.2 Dose Estimates................................................ 3-12 4.0 MISSING SAMPLES AND ANALYSES.................................. 4-1 4.1 Air Cartridge and Air Particulate............................. 4-1
- 4.2 External Radiation (TLD)...................................... 4-1 5.0 ANALYT I CAL PROC EDU RES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 I 5.1 Gross Beta.................................................... 5-1 5.2 Tritium....................................................... 5-1 5.3 Iodine-131.................................................... 5-1 5.4 G amma S p e ct rome try . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 5.5 Thermoluminescent Dosimetry........................
- .......... 5-2 5.6 EPA Laboratory Intercomparison Program........................ 5-3 6.0 LAND-USE CENSUS 6.1 Introduction.................................................. 6-1 6.2 Requirements.................................................. 6-1 6.3 Methods....................................................... 6-2 6.4 Results....................................................... 6-3 f
7.0 REFERENCES
.................................................... 7 , i
List Of Tables Table Title Page 1-1 Radiological Environmental Monitoring Program.................... 1-4 2-1 'ironmental Radiological Monitoring Program Summary 1983....... 2-2 2-2 Environmental Radiological Monitoring Program Summary 1984....... 2-8 2-3 Environmental Radiological Monitoring Program Summary , 1983-1984........................................................ 2-13 3-1 Ambient Dose Estimates for the Fish Ingestion Pathwa9............ 3-13 3-2 Ambient Dose Estimates for the Water Ingestion Pathway........... 3-14 3-3 Ambient Dose Estimates for the Leafy Vegetable Ingestion Pathway.......................................................... 3-15 3-4 Ambient Dose Estimates for the Milk Ingestion Pathway............ 3-16 5-1 Typical Lower Limits of Detection Ge (Li) Gamma Spectrometry..................................................... 5-7 6-1 Distance to the Nearest Special Locations from the Shearon Harris Nuclear Power Plant (Miles)............................... 6-4 { { 11
List Of Figures , Figures Title Page 1-1 Shearon Harris Nuclear Power Plant Environmental Radiological Sampling Points..................................... 1-18 1-2 Shearon Harris Nuclear Power Plant Environmental Radiological Sampling Points..................................... 1-19 1 Shearon Harris Nuclear Power Plant Environmental Radiological Sampling Points..................................... 1-20 1-4 Legend for Figures 1-1, 1-2, and 1-3............................. 1-21 3-1 Air Particulate Gross Beta Activity vs. Time at Station 01 and Control Site................................................. 3-17 3-2 Air Particulate Gross Beta Activity vs. Time at Station 02 and Control Site................................................. 3-19 3-3 Air Particulate Gross Beta Activity vs.. Time at Station 03 and Control Site................................................. 3-21 3-4 Air Particulate Gross Beta Activity vs. Time at Station 04 and Control Site................................................. 3-23 3-5 Air Particulate Gross Beta Activity vs. Time at Station 26 and Control Site................................................. 3-25 3-6 Surface Water Gross Beta Activity vs. Time at Station 26 and Control S1te................................................. 3-27 3-7 Surface Water Gross Beta Activity vs. Time at Station 40 and Control Site................................................. 3-29 3-8 Drinking Water Gross Beta Activity vs. Time at Station 40 and Control Site................................................. 3-31 3-9 Drinking Water Gross Beta Activity vs. Time at Station 51 and Control S1te................................................. 3-33 l 111
PRE 0PERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING STUDY
1.0 INTRODUCTION
This report summarizes the Preoperational Environmental Radiological Monitoring conducted for the Shearon Harris Nuclear Power Plant (SHNPP) during calendar years 1983 and 1984. The report concludes a two-year preoperational study determining the background radiological characteristics of the SHNPP locale and accomplishes the program objectives described in Section 6.1.5.1 of the SHFPP Environmental Report - Operating License (ER0L) stage.1 Data analysis and interpre-tation in this report were performed entirely by Carolina Power & Light Company. 1.1 Plant and Location The Shearon Harris Nuclear Power Plant is a pressurized water reactor designed to produce 868 MWe (net). Fuel loading is projected for March 1986. The SHNPP site is located in the extreme southwest corner of Wake County, North Carolina, and the southeast corner of Chatham County, North Carolina. The plant is approximately 16 miles southwest of Raleigh and about 15 miles northeast of Sanford. This location is on the northwest shore of Harris Lake which is a 4000-acre reservoir created by the impoundment of Buckhorn Creek. The reservoir will provide process and cooling tower makeup water for the plant and will also serve as the receiving body for liquid effluents such as yard runoff, cooling tower blowdown, radioactive waste processing system, etc. The main dam for the reservoir is about 4.5 miles south of the plant. The spillway at the dam flows into Buckhorn Creek which, after flowing south for about 2 miles, enters the Cape Fear River. 1-1
There are no industrial, recreational, or residential structures on CP&L property. However, Carolina Power & Light cooperates with various state agencies to provide public access for boating, fishing, hunting, and other recreational uses which are not inconsistent with the primary purpose of the lands. and waters. As such, some recre-ational facilities such as boat ramps and access areas are located on station property for public use. In addition, one temporary residence has- been permitted in the preoperational _ phase to facilitate plant construction needs. The majority of the-land within the 5-mile radial area of the site is wooded with a scattering of fields and residential properties. Much of the land is used for timber and pulpwood production. Agricultural activities occur on a limited basis within this range; however, there are two operating commercial dairies., The population within a 10-mile radial area of the plant is, for the most part, considered rural. Towns in this area with notable populations include Apex, Holly Springs, and Fuquay-Varina'(see Figures 1-1 and 1-2). Within a 50-mile radius of the plant, much of the land is' devoted to scm form of agricultural activity. Major crops include tobacco and soybeans and corn for grain. Livestock production includes hog, beef, poultry, and dairy products. Commercial fish and shellfish catch -from waters within 50 miles of the station discharge is negligible. Recreational- fishing is _ popular in this range of the plant. Since there are no estuarine or saltwater bodies, sport fishing is confined to freshwater streams, rivers, private ponds, and
. impoundments such as Harris Lake and Jordan Lake.
1-2 _ _ - _ _ _ _ _ _ _ _ _ 1
l l l 1.2 Environmental Monitoring Program l 1 The significant elements of the preoperational dose estimates (see SHNPP Environmental Report--operating license stage) were used to [ establish the present preoperational surveillance program. These elements, combined with technical judgment and requirements from the SHNPP technical specifications, will eventually define the final environmental surveillance program once the station becomes operational. The outline of this report follows the guidelines found in Section 6.9.1.3 of NUREG 0452, Revision 4 (Westinghouse Standard Technical Specifications). The current envisonmental program is detailed in Table 1-1. The surveillance has been based on NUREG 0472, Revision 3, of March 1979 (Draft Radiological Effluent Technical Specifications for PWRs). The environmental monitoring program may change based on revised gui.ance found in NUREG 0452, Revision 5. Figures 1-1, 1-2, and 1-3 show the environmental monitoring locations. Figure 1-4 provides a legend for Figures 1-1 through 1-3. 1 4 1-3
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4 TABLE l-1 RADIOLOGICAL ENVIROINENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point. Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis
- 1. Airborne 1 0.1 mi. S on SR 1134 Continuous operating Weekly Gross Beta 2 Particulates from SR 1011 intersection. sampler with sample Weekly I-131 and Radio- N sector 2.5 mi. from collection, as required, (charcoal lodine site, by dust loading but at canisters) least once per 7 days. Quarterly Gamma Isotopic4 ,5 Composite by Location 2 1.4 mi. S on SR 1134 Continuous operating Weekly Gross Beta 2 from SR 1011 inter- sampler with sample Weekly I-131
- section. NNE sector 1.5 collection, as required. (charcoal 1 mi. from site. by dust loading but at canisters) least once per 7 days. Quarterly Gamma Isotopic4 ,5 Composite by Location 3 0.9 mi. S on SR 1127 Continuous operating Weekly Gross Beta 2 from US 1 intersection. sampler with sample Weekly I-131 HE&EC. NE sector 2.6 mi. collection, as required. (charcoal from site. by dust loading but at canisters) least once per 7 days. Quarterly Gamma Isotopic4 ,5 Composite by Location 4 0.7 mi. N on SR 1135 from Continuous operating Weekly Gross Beta 2 US 1 intersection, at sampler with sample Weekly I-131 New Hill. NNE sector, collection, as required, -
(charcoal 3.5 mi. from site, by dust loading but at canisters) least once per 7 days. Quarterly Gamma Isotopic4 ,5 Composite by Location
9 TABLE l-1 RADIOLOGICAL ENVIR00 MENTAL MONITORING PROGRAM Sample Exposure Patlesey Point Sample Point Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis
- 1. Airborne 5 Pittsboro. Continuous operating Weekly Gross Beta 2 Particulates > 12 mi. WNW sampler with sample Weekly I-131 and Radio- sector from site collection, as required. (charcoal iodine (Control Station)3 by dust loading but at canisters)
(continued) least once per 7 days. Quarterly Gamma Isotopic4 ,5 Composite by Location 26 Harris Lake Spillway. Continuous operating Weekly Gross Beta 2 . S sector. 4.7 mi. from sampler with sample Weekly I-131 !
- site. collection, as required, (charcoal i
by dust loading but at canisters) 1 east once per 7 days. Quarterly Gamma Isotopic4 ,5 Composite by Location
- 2. Direct 1 0.1 mi. S on SR 1134 Continuous measurement Quarterly Gamma Dose Radiation from SR 1011 inter- with an integrated :
section. N sector 2.5 readout at least al. from site. Once per quarter. I 1.4 mi. S on SR 1134 2 Continuous measurement Quarterly Gamma Dose i from SR 1011 inter- with an integrated section. NNE sector readout at least 4 1.5 mi. from site. Once per quarter.
TABLE l-1 RADIOLOGICAL ENVIROPMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency frequency Analysis
- 2. Direct 3 0.4 mi. 5 on SR 1127 Continuous measurement Quarterly Gamma Dose Radiation from US 1 inter- with an integrated (continued) section. NE sector readout at least 2.2 mi. from site. once per quarter.
4 0.5 mi. N on SR 1135 Continuous measurement Quarterly Gamma Dose from intersection US 1. with an integrated New Hill. NNE sector readout at least 3.2 mi. from site. once per quarter. _. 5 Pittsboro. WNW sector. Continuous measurement Quarterly Gamma Dose J, > 12 mi. f rca si t with an integrated TControlStation)g . readout at least once per quarter. 6 Intersection of Continuous measurement Quarterly Gamma Dose SR 1134 and SR 1135. with an integrated ENE sector 0.9 mi. readout at least from site. Once per quarter. 7 Extension of SR 1134. Continuous measurement Quarterly Gamma Dose E sector 0.8 mi. from with an integrated l site. readout at least l once per quarter. 8 Dead end of road. Continuous measurement Quarterly Gamma Dose Extension of SR 1134. with an integrated SE sector 0.7 mi. readout at least from site. once per quarter. I L - - - - ----------- - -
TABLE l-1 RADIOLOGICAL ElfVIR0000 ENTAL pellITORIls PROGRAM Sample Exposure Patinsey Point Sample Point. Descript!on Samplim and Analysis and/or Sample ID Ilo. Distance, and Direction Collection rrequency Frequency Analysis
- 2. Direct 9 1 mi. S on SR 1130 from Continuous measurement Quarterly Gamma Dose Radiation intersection of SR 1127, with an integrated (continued) 1115, and 1130. Holleman's readout at least Crossroads. ESE sector 2.3 once per quarter.
mi. from site. 10 SR 1130 5 of intersection Continuous measurement Quarterly Gamma Dose of SR 1127. 1115, and with an integrated 1130. SSE section 2.2 readout at least mi. from site. once per quarter. [ 11 SHNPP site. S sector Continuous measurement Quarterly Gamma Dose 0.7 mi. af site. with an integrated readout at least once per quarter. 12 SHNPP site. SSW sector Continuous measurement Quarterly Gamma Dose 0.8 mi. of site. with an integrated readout at least once per quarter. 13 SHNPP site. SW sector Continuous measurement Quarterly Gamma Dose 0.7 mi. of site. with an integrated readout at least I once per quarter. 14 SHNPP site. Access road to Continuous measurement Quarterly Gamma Dose aux. reservoir. W sector with an integrated 1.1 mi. from site. readout at least i once per quarter.
TABLE l-1 1 RADIOLOGICAL EWIROISIENTAL MONITORING PROGRAM Sample Exposure Pathway Polet Sample Point. Description Sampling and Analysis and/or Sample 10 No. Distance, and Direction Collection Frequency Frequency Analysis
- 2. Direct 15 SR 1191. W sector 1.8 Continuous measurement Quarterly Gamma Dose Radiation mi. from site. with an integrated (continued) readout at least once per quarter.
16 1.2 af. E of intersection Continuous measurement Quarterly Gamma Dose of US I and SR 1011. with an integrated WNW sector. 1.7 mi. from readout at least site. once per quarter.
- 17 Intersection of US 1 and Continuous measurement Quarterly Gamma Dose a, Aux. reservoir NW sector with an integrated 1.4 mi. from site. readout at least once per quarter.
18 0.2 mi. M on US 1 from Continuous measurement Quarterly Gamma Dose Station 17. NNW sector with an integrated 1.3 mi. from site. readout at least once per quarter. 19 0.6 mi. E on SR 1142 Continuous measurement Quarterly Gamma Dose from intersection of SR with an integrated l 1142. NNE sector 4.9 al. readout at least ! from site, once per quarter. l l 20 US 1 at intersection Continuous measurement Quarterly Gamma Dose l SR 1149. NE sector 4.7 with an integrated af. from site. readout at least once per quarter.
TABLE 1-1 RADIOLOGICAL ENVIR00 MENTAL MONITORING PROGRAM Sample Exposure Patlasty Point Sample Point. Description Sampling and Analysis and/or Sample 10 No. Distance, and Direction Collection Frequency Frequency Analysis
- 2. Direct 21 1.2 mi. W on SR 1152 Continuous measurement Quarterly Gamma Dose Radiation from intersection SR with an integrated (continued) 1153. ENE sector 4.8 mi. readout at least from site. Once per quarter.
22 Formerly Ragan's Dairy on Continuous measurement Quarterly Gamma Dose i SR 1115. E sector 4.6 with an integrated mi. from site, readout at least once per quarter. 23 Holloman Cemetery on Continuous measurement Quarterly Gamma Dose
, SR 1116. ESE sector with an integrated 5.0 mi. from site. readout at least
- once per quarter.
24 Sweet Springs Church on Continuous measurement Quarterly Gamma Dose SR 1116. SE sector 4.7 with an integrated mi. from site, readout at least once per quarter. 25 0.2 mi. W on SR 1402 Continuous measurement Quarterly Gamma Dose from intersection of SR with an integrated 1400. SSE sector 4.8 readout at least once si. from site. per quarter. 26 Harris Lake Spillway. Continuous measurement Quarterly Gamma Dose S. sector 4.6 mi. from with an integrated site. readout at least once per quarter.
TABLE 1-1 RADIOLOGICAL ENVIR00 MENTAL MDNITORING PROGRAM Sample Exposure Pathmey Point Sample Point. Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis
- 2. Direct 27 NC 42 at United Methodist Continuous measurement Quarterly Gamma Dose Radiation Church. SSW sector 4.8 with an integrated (continued) mi. from site. readout at least once per quarter.
28 0.6 mi. on SR 1924 from Continuous measurement Quarterly Gamma Dose intersection of SR 1916. with an integrated SW sector 4.8 mi. from readout at least site. once per quarter. _ 29 Parking lot of Chembond Continuous measurement Quarterly Gamma Dose
- 2. Corp. on SR 1916. WSW with an integrated o sector 5.6 mi. from site. readout at least once per quarter.
30 Exit intersection of SR Continuous measurement Quarterly Gamma Dose 1972 and US 1. W sector with an integrated 5.1 mi. from site. readout at least once per quarter. 31 SR 1910 from intersec- Continuous measurement Quarterly Gamma Dose tion of SR 1908 and SR with an integrated 1909. WNW sector 4.5 readout at least mi. from site. once per quarter. 32 SR 1008 intersection Continuous measurement Quarterly Gamma Dose of SR 1975. NW sector with an integrated 4.8 mi. from site, readout at least once per quarter.
TABLE l-1 RADIOLOGICAL ENVIR0 MENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency frequency Analysis '
- 2. Direct 33 SR 1142. 1.7 mi. from Continuous measurement Quarterly Gamma Dose Radiation intersection of SR 1141. with an integrated (continued) NNW sector 4.4 mi. from readout at least site. Once per quarter.
34 Apex (Population Center). Continuous measurement Quarterly Gamma Dose NE sector 8.6 mi. from with an integrated site, readout at least once per quarter.
- 35 Holly Springs. Continuous measurement Quarterly Gamma Dose a E sector 6.9 mi. from with an integrated -- site. readout at least once per quarter.
36 SR 1393 at intersection Continuous measurement Quarterly Gamma Dose of SR 1421. E sector with an integrated 11.2mi.fromsitg readout at least once per quarter. (Control Station) 37 US 401 at CP&L office, Continuous measurement Quarterly Gamma Dose Fuquay-Varina (Population with an integrated Center). ESE sector 9.7 readout at least mi. from site. Once per quarter. l 48 SR 1142. 1.5 mi. from Continuous measurement Quarterly Gamma Dose I intersection of SR 1141. with an integrated-N sector 4.5 mi. from readout at least site. Once per quarter.
TABLE 1-1 RADIOLOGICAL ENVIROMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point. Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis
- 2. Direct 49 Across SR 1127 from Garnes' Continuous measurement Quarterly Gamma Dose Radiation Store. NE sector 2.6 mi. with an integrated (continued) from site. readout at least once per quarter.
50 SR 1127 W from inter- Continuous measurement Quarterly Gamma Dose section of SR 1115 and with an integrated 1130. ESE sector 2.8 mi. readout at least from site. Once per quarter. 7 53 SR 1972 N from inter- Continuous measurement Quarterly Gamma Dose g section of SR 1910 and with an integrated SR 1972. NW sector readout at least once 5.5 mi. from site. per quarter. 30 Waterborne
- a. Surface 2G Spillway on Main Res. Composite sample 5 Monthly Gross Beta Water S sector 4.6 mi. from collected over a Monthly Gamma Isotopic4 site. period of 5 31 days. Quarterly Tritium 38 Cape Fear Steam Electric Composite sample 5 Monthly Gross Beta PlantIntakeStrugture collected over a Monthly Gamma Isotopic 4 (Control Station) period of 5 31 days. Quarterly Tritium WSW sector 6.1 mi. from site.
40 U.S. Geological Survey Composite sample 5 Monthly I-135 Gauging Station. collected over a Monthly Gamma Isotopic 4 Lillington at intersection period of 5 31 days. Quarterly Tritium of NC 210 and the Cape fear River. SSE sector approx. 17 mi. from site.
TABLE l-1 RADIOLOGICAL ENVIR0l#4 ENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis
- 3. Waterborne (continued)
- b. Ground- 39 On-site deep well Grab sample. Quarterly Gamma Isotopic4 water in the proximity of Quarterly. Quarterly Tritium the diabase dikes. SSW sector 0.7 mi. of site.
- c. Drinking 38 Cape fear Steam Composite sample 5 I-131 on I-131 Electric Plant Intake over two-week period each compo-
-- Control if I-131 analysis is sitewheg
'. Structurg (WSW sector performed, monthly Station) . the dose 6.1 mi. from site. composite otherwise. calculated for the consumption of the water is greater than 1 mrem per yr.
Monthly Gross Beta Monthly Gamma Isotopic4 Quarterly Tritium 40 U.S. Geological Survey Composite sample 5 I-131 on I-131 Gauging Station, over two-week period each compo-Lillington at intersection if I-131 analysis is sitewheg of NC 210 and the Cape performed, monthly the dose Fear River. SSE sector composite otherwise. criculated approx. 17 mi. from site. for the water is greater than 1 mrem per year. Monthly Gross Beta Monthly Gamma Isotopic Quarterly Tritium
TABLE 1-1 RADIOLOGICAL ENVIRO MENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point. Description Sampling and Analysis and/or Sample -ID No. Distance, and Direction Collection Frequency Frequency Analysis
- 3. Waterborne 51 SHNPP Water Treatment I-31 on I-131 (continued) Building on site. each composite when the dose is greater than 1 mrem per yr.
Monthly Gross Beta
- Monthly Gamma Isotopic 4
-
- Quarterly Tritium
- d. Sediment 26 Harris Lake Spillway. Surface soil sample. Semiannually Gamma Isotopic 4 from S sector 4.6 mi. from Semiannually ,
Shoreline site. 41 Shoreline of mixing zone Surface soil sample. Semiannually Gamma Isotopic 4 of cooling tower blowdown Semiannually. line. S sector 3.8 mi. from site.
- e. Bottom 52 Harris Lake in the Bottom Sediment. Semiannually Gamma Isotopic Sediment vicinity of the mixing Sample Semiannually.
zone of the cooling tower. S sector 3.8 mi. from site.
I TABLE 1-1 RADIOLOGICAL ENVIRO MENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point. Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis
- 4. Ingestion
- a. Milk 42 Maple Knoll Dairy on SR Grab samples semi- Each sample I-131 &
1403. SE sector 7.5 mi. monthly when animals Gamma from site, are on pasture-- Isotopic 4 monthly at other times. 19 Olive's Dairy on SR 1178. Grab samples semi- Each sample I-131 & NNE sector 5.0 mi. from monthly when animals Gamma Isotopic 4 site. are on pasture-- i monthly at other times.
- 4. Ingestion 43 Goodwin's Dairy Farm on SR Grab samples semi- Each sample I-131 &
(continued) 1134 N sector 2.5 mi. monthly when animals Gamma Isotopic 4 from site. are on pasture-- monthly at other times. 5 Strowd's Dairy, Pittsboro Grab samples semi- Each sample I-131 & Station)3 > 12 mi. NW monthly when animals Gamma Isotopic 4 sector of site. are on pasture-- i monthly at other times.
- b. Fish 44 Site varies within One sample of each Semianually Gamma Isotopic 4 the Harris impoundment. of the following: on edible
- 1. Free swimmers portion
- 2. Bottom feeders for each Semianually.
45 Site varies above One sample of each Semianually Gamma Isotopic 4 Buckhorn Dam on of the following: on edible Cape Fear River 1. Free swimmers portion (UnaffectedbySige) 2. Bottom feeders for each (Control Station) Semianually.
TABLE l-1 l RADIOLOGICAL ENVIR00 MENTAL NONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis
- c. Food 46 SR 1182. (Nursing Home) Broadleaf vegetation At time of Gamma Isotopic 4 Products NE sector 2.3 mi. from at time of each each harvest site. harvest.
43 Goodwin's Farm on SR 1134. Broadleaf vegetation At time of Gamma Isotopic4 N sector 2.5 mi. from at time of each each harvest site. harvest. 5 Pittsbor (Control Broadleaf vegetation At time of Gamma Isotopic 4 Station)g. WNW sector
. at time cf each each harvest 7 approx. 12 mi. from site. harvest.
E i
NOTES TO TABLE 1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- 1. Sample locations are shown on Figures 1-1, 1-2, and 1-3. Figure 1-4 provides a legend explaining Figures 1-1 through 1-3,
- 2. Particulate samples will be analyzed for gross beta radioactivity 24 hours or more following filter change to allow for radon and thorium daughter decay. If gross beta activity is greater than ten times the yearly mean of the control sample station activity, a gamma isotopic analysis will be performed on the individual samples.
- 3. Control sample stations (or background stations) are located in areas that are unaffected by plant operations. All other sample stations that have the potential to be affected by radioactive emissions from plant operations are considered indicator stations.
- 4. Gamma isotopic analysis means the identification and quantitation of gamma-emitting radionuclides that may be attributable to the effluents from the plant operations.
- 5. Composite samples will be collected with equipment which is capable of collecting an aliquot at time intervals which are very short (e.g., every 2 hours) relative to the compositing period (e.g., monthly).
- 6. The dose will be calculated for the maximum organ and age group using the methodology contained in Regulatory Guide 1.109, Rev.1, and the actual parameters particular to the site.
)
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l 2.0 PROGRAM SIM1ARY The purposes of the Environmental Radiological Monitoring Program are:
- To measure any accumulation of radioactivity in the environment and to assess whether this radioactivity is the result of the operation of the Harris Plant.
To provide an evaluation of the environmental impact of operating releases of radioactive materials from the Harris Plant.
- To compare population doses from envircnmental sample data wtth corresponding doses predicted in the Final Environmental Statement.
As SHNPP is not yet operational, the present report serves to provide a firm baseline of environmental measurements for later comparison. Preoperational and operational environmental radiological reports in the years to come will have similar formats. The following locations are designated as Control Locations for the respective measurements and are intended to indicate conditions away from Harris Plant influence. Pittsboro > 12 miles, WNW (SampleStation'5) Airborne Particulate (filter) Samples Charcoal Cartridge Samples - Airborne I-131 n Thermoluminescent Oosimeter Area Monitors Milk Samples Food Products Cape Fear Steam Electric Plant 6.1 alles, WSW (Sample Station 38) Surface Water Samples Drinking Water Samples l l Upstream of the Buckhorn Dam on the Cape Fear i River-Site Varies in this Locale (Sample Station 45) Fish Samples Tables 2-1 and 2-2 summarize the results of the preoperational environmental monitoring program for calendar years 1983 and 1984, respectively. Table 2-3 resummarizes the data for both years '!' combined. l 2-1 1
.~ .
- ,a 1
,_ TABLE,2-1 PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Supe 4ARY t 3
~ Shearon Harris Nuclear Power Plant , Docket Nwnber $1N 50-400 ,
Wake County. North Carolina Calendar Year: 1983 Type and Lower All Indicator Location w/ Highest Annual Mean Medium or Pathway Total No. of. Limit of Locations (2) Name, Control Locations No. of Nonroutine Sampled or Measured Measurements Detection Mean Distance. and Mean Mean Reported (Unit of Measurement) Performed (LLD) (t) Range Direction Range (2) Range (2) Measurements (3) Air Cartridge I l-131 (pCi/m ) 310 2.00E-2 All less than LLD All less than LLD All less than LLD 0 Air ParticulateI "I Gross Beta I.73E-2 (258/258) Diale Pipeline 1.88E-2 (52/53) 1.58E-2 (52/52) 3 (pCI/m ) 310 1.00E-3 2.57E 4.58E-2 2.5 mile?. N 4.20E 4.03E-2 4.69E 3.47E-2 0 Gamma See N 24 Table 5-1 All less than LLD IN All less than LLD All less than LLD 0 N Sediment from Gamma Shoreline ( ' 1 See Table 5-1 All less than LLD IN (pci/g) All less than LLD Not required 0 Drinking Water 1-131 (pCl/l ) 36 Weekly II 3.00E-1 All less than LLD All less than LLD All less than LLD 0 Monthly Gross Beta 5.98E O (6/6) SHNPP Water Treat 7.36E o (3/3) 5.07E O (3/3) Composite (8) 9 8.00E-1 2.2IE O - 1.68E I Facility on site 2.21E O - 1.68E I 3.43E O - 6.72E O O Camma See 9 Table 5-1 All less than LLD(5) All less than LLD All less than LLD 0 Tritium 9 5.20E 2 All less than LLD All less than LLD All less than LLD 0 1
- c. - - . . --.
TABLE 2-1 (cont inued ) PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Shearon Herris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1983 Type and Lower All Indicator Location w/ Highest Annual Mean Medium or Pathway Total No. of Limit of Locations (2) Name, Control Locations No. of Nonroutine Sampled or Measured Measurements Detection Mean Distance, end Mean Mean Reported (Unit of Measurement) Performed (LLD) (I) Range Direction Range (2) Range (2) Measurements (3) Fish FleshI 'I t - Camma Botton Feeder 4 See (pCi/g dry) Table 5-1 All less than LLDI 'I All less than LLD All less than LLD 0* Free Swimmers Gamma See 4 Table 5-1 All less than LLD II All less than LLD All less than LLD O m (pCi/g dry) Food Crop (10) g,,,, (pCi/g dry) 9 9.86E-2 (t/6) Goodwin's Farm 9.86E-2 (1/3) 1.26E-1 (2/3) Cs-137 8.00E-3 (Single value) 2.3 miles N ($1ngle value) 1.25E 1.27E-l O Groundwater Gamma See (pCi/l) 2 Table 5-1 All less than LLDI 'I All less than LLD Not required 0 Tritium 2 5.2E 2 All less than LLDI 'I All less than LLD Not required 0 Milk IIII l-131 (pci/l) 24 4.00E-1 All less than LLD All less than LLD All less than LLD 0 Gamma fiee All less than LLD II 24 Table 5-1 All less than LLD All less than LLD 0
....- . ~. . . . . - . . .. - _ _ . .- - -. . . . . _ . - --- - - . - . . . . . - - - - _ - _ - _ _ _ _ _ _ _ - _ _ _ - - -
TABLE 2-1 (cont inusd ) PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number STN 50-400 Wake County, North Carolina Calendar Years 1983 Type and All Indicator Location w/ Highest Annual Mean -l" Medium or Pathway Total No. of Lower Limit of Locations (2) Name, Control Locations No. of Nonroutine Sampled or Measured Measurements Detetection Mean Distance, and Mean Mean Reported (Unit of Measurement) Performed (LLD) (1) Range Direction Range (2) Range (2) Measurements (3) i Surface Water 1-131(12) (pCl /l ) 124 3.00E-1 All less than LLD All less than LLD All less than LLD 0 Monthly Composite Gross Beta 3.22E O (24/24) Municipal Water 3.43E O (12/12) 3.69E O (12/12) 36 1.57E O - 5.75E O Treatment # Lill. 1.57E O - 5.75E O 1.97E O - 6.72E O 8.00E-1 15 miles SSE O m Gamma See i
- Table 5-1 All less than LLD UI 36 All less than LLD All less than LLD 0 II I Tritium 5.70E 2 Municipal Water 5.70E 2 All less than LLD 18 (Single value) Treatment # Lill. (Single value) 5.2E 2 17 miles SSE O Quirterly Composite Tritium II3I 5.30E 2 6 5.2E 2 All less than LLD All less than LLD (Single value) 0 !
Direct' TLD II4I Radiation 1.21E O (141/141) US I # SR 1849 1.77E O (4/4) 1.05E O (4/4) (mR/ week) 145 1.00E O 6.00E 2.20E O' 4.7 miles NE 1.50E O - 2.20E O 8.00E-l - 1.20E O O 9 1 M
, *- , e- ,
NOTATIONS FOR TABLE 2-1
~
- 1. The lower limit of detection is given by the following general equation:
4.66 s LLO = E . V . 2.22 . Y . exp (-19 t,) 1 l Where: LLD = Lower limit of detection in pC1 per unit volume or mass sb = (N/tb) = Standard deviation of the background (cpm) N = Background count rate (cpm) t b = Background count time (min) l
; E = Counting efficiency (counts per disintegration)
V = Volume or mass of sample 2.22 = Conversion factor (dpm/pci) , Y = Fractional chemical yield, when applicable. Aj = Radioactive decay constant for the ith nuclide t, = Elapsed time between sample collection and counting See Table 5-1 for listing of LLD values for the gamma spectrometry system. Th)s expression is not used for direct' radiation measurements.. 2-5
( . l
- 2. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
- 3. Measurements are in excess at 99.5 percent confidence limit of ten times the control station value or ten times the lower limit of detection, whichever is larger.
- 4. Air cartridge and particulate samples were not analyzed from Station 02 in the first quarter due to a loss of power to the sampler. Loss of power was also the reason for no analysis of air cartridge and particulate samples from Station 26 during the third quarter.
i j 5. No man-made radioactivity detected.
- 6. Sediment collection was initiated in 1983 from Sample Station 26 only. Sample Station 41 was established for sampling beginning in calendar year 1984.
- 7. Drinking water sampling was initiated October 11, 1983. Thus only 36 indicator and control samples were collected for I-131 analysis.
- 8. Monthly composites of indicator and control samples were initiated in October 1983. Thus only -three samples per location were available for analysis.
- 9. Fish sampling was initiated in July 1983 and a second collection made in November 1983. Minimum sampling requirement is semiannual.
- 10. Food crops consisted of collards, cabbage,- turnips, and greens.
Quarterly sampling was initiated in July -1983; therefore, only samples from two quarters were available for analysis.
- 11. Monthly milk collection and analysis were initiated in July 1983.
f f 2-6
t
- 12. Surface water sampling frequency through May of 1983 was twice per
. calendar month at each location. From June to December, the sampling frequency was once per week at each location. .
- 13. Tritium analysis was quarterly from January through June 1983 and monthly from July through December.
- 14. In the first quarter, the TLDs from Station 18 were missing; in the second quarter, TLDs from Stations 9,15, 23, and 36 were missing; in the third quarter, TLDs from Stations 12, 15, 23, 31, 33, and 34 were missing; and in the fourth quarter, TLDs 24, 27, 31, and 36 were missing.
2-7.
~
TABLE 3-3 PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1984 t Type and Lower All Indicator Location w/ Highest Annual Mean Medium or Pathway Total No. of Limit of Locations (2) Name, Centrol Locations No. of Nonroutine Sampled or Measured Measurements Detection Mean Distance, and Mean Mean Reported (Unit of Measurement) Performed (LLD) (l) Range Direction Range (2) Range (2) Measurements (3) Air Cartridge I4I l-131 (pCl/m ) 318 2.00E-2 All less than LLD All less than LLD All less than LLD 0 7 03 Air Particulate I4I Gross Beta 1.62E-2 (265/265) Dixie Pipeline 1.80E-2 (53/53) 1.58E-2 (53/53) 3 (pCl/m ) 318 1.00E-3 4.49E 3.57E-2 2.5 miles N 7.59E 3.57E-2 6.67E 2.85E-2 0 Gamma See 24 Table 5-1 All less than LLD All less than LLD All less than LLD 0 Sediment from Gamma Shoreline 4 See (pCI/g dry) Table 5-1 All less than LLD IN All less than LLD Not required 0 Botton Sediments Gamma 5.51E-1 (1/1) Harris Lake 5.51E-1 (1/1 ) (pCl/g dry)(6) 3 3,, g3;ng,,y,,,,3 g,,,,g 7,,, g3g,gg,y,,,,, Cs-137 Table 5-1 3.8 miles S Not required 0 e-
TABLE 2-2 (continutd) PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SLM4ARY Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1984 Type and Lower All Indicator Location w/ Highest Annual Mean Medium or Pathway Total No. of Limit of Locations (2) Name, Control Locations Mo. of Nonroutine Sampled or Measured Measurements Detetection Mean Distance, and Mean Mean Reported (Dnit of Measurement) Performed (LLD) (1 ) Range Direction Range (2) Range (2) Measurements (3) Drinking Water 1-131 (pCl/l) 159 Weekly 3.00E-1 All less than LLD All less than LLD All less than LLD 0 Monthly . Gross Beta 2.99E O (23/24) USGS Gage 3.03E O (12/12) 3.11E O (12/12) Composite 36 8.00E-1 1.44E O - 7.22E O Stetion # 1.67E O - 5.56E O 1.56E O - 5.86E O O 1 Lillingtoa + 17 miles SSE ro y Gamma See 36 Table 5-1 All less than LLD(5) All less than LLD All less than LLG 0 Tritium 36 S.20E 2 All less than LLD All less than LLD All less than LLD 0 Fish Flesh: Gamma Botton Feeder 8 See 1.42E-1 (1/4 ) Harris Lake 1.42E-1 (1/4) 4.08E-2 (1/4) (pCl/g dry) Cs-137 Table 5-1 (Single value) site varies (Single value) (Single value) 0 ( Free Swimmers Gamma See (pCl/g dry) 8 Table 5-1 4.51E-2 (1/4) Harris Lake 4.51E-2 (1/4) 5.74E-2 (1/4) O Cs-137 (Single value) site varies (Single value) (Single value) Food Crop III Gamma See (pCI/g dry) 6 Table 5-1 All less than LLD II All less than LLD All less than LLD 0 Groundwater Gamma See (pCI/l) 4 Table 5-1 All less than LLD All less than LLD Not required 0 Triflue 4 5.2E 2 All less than LLD All less than LLD Not required 0
=
._. . _. _ _ _ .~ .. _. _ _ _ _ _
l 7 TABLE 2-2 (continuid) l PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
l Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 , Wake County, North Carolina Calendar Year: 1984 i Type and All Indicator Location w/ Highest Annual Mean Medium or Pathway . Total No. of Lower Limit of Locations (2) Name, Control Locations No. of Nonroutine Sampled or Measured Measurements Detetection Mean Distance, and Mean Mean Reported , (Unit of Measurement) Performed (LLD) (1) Range Direction Range (2) Range (2) Measurements (3) Milk l-131 (pCl/l) 96 4.00E-1 All less than LLD All less than LLD All less than LLD 0 Gamma 96 5.55E O (1/72) Olive's Dairy 5.55E O (1/24) All less than LLD 0 N Cg-137 (Single-value) 5.0 miles NNE (Single value) O Surface Water' l-131 (pCl /l ) 159 3.00E-1 All less than LLD All less ther. LLD All less than LLD 0 Monthly Composite Gross Seta 2.98E O (24/24) USGS Gage 3.03E O (12/12) 3.IlE O (12/12) 36 1.67E O - 5.56E O Station e Lill. , I.67E O - 5.56E O 1.56E O - 5.86E O 8.00E-1 17 miles SSE O 4 Gamma See 36 Table 5-1 All less than LLD(5) All less than LLD All less than LLD 0
' Tritium (8)- ~"
36 5.2E 2 All less than LLD All less than LLD All less than LLD 0 4 III Direct. TLD Radiation 1.09E O (152/152) US 1 # SR II49 1.42E O (4/4) 9.50E-1 (4/4) (mR/ week) 156 1.00E O 7.00E-l - 1.70E O 4.7 miles NE 1.30E O - 1.70E O 8.00E 1.00E O O b
NOTATIONS FOR TABLE 2-2
- 1. The lower limit of detection is given by the following general equation:
4.66 s
" E . V. 2.22 . Y . exp (-Ag t )
Where: . LLD = Lower limit of detection in pCi per unit volume or mass sb = (N/t b)l/2 = Standard deviation of the background (cpm) N = Background count rate (cpm) t b = Background count time (min) E = Counting efficiency (counts per disintegration) V = Volume or. mass of sample 2.22 = Conversion factor (dpm/pC1) Y = Fractional chemical yield, when applicable lj = Radioactive decay constant for the ith nuclide t e = Elapsed time between sample collection and counting See Table 5-1 for listing of LLD values for the gamma spectrometry system. This expression is not used for direct radiation measurements.
- 2. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
2-11
- 3. Measurements are in excess at 99.5 percent confidence limit of ten times the control station value or ten times the lower limit of detection, whichever is larger.
- 4. On July 23, 1984, an electrical malfunction caused lowered air volumes to be sampled at Stations 1, 2, and 3.
- 5. No man-made radioactivity detected.
- 6. Bottom sediment sampling is not required but performed to better characterize the radiological characteristics of this environmental medium.
- 7. Food crops consisted of collards, cabbage, and mustard greens.
- 8. Although quarterly composite samples are required, monthly composite samples are used to provide more frequent and sensitive analyses.
- 9. In the first quarter, the TLDs from Stations 7 and 27 were missing; in the third quarter, TLDs from Stations 12 and 31 were missing; and in the fourth quarter, TLDs 16 and 25 were missing. TLD Station 53, in the NW sector, 5.5 miles from the site was added to the surveillance program during the last half of the year.
2-12
TABLE 2-3 PREOPERATIONAL ENVIRONMENTAL RADtOLOGICAL MONITORING PROGRAM SLM4ARY Shearon Harris Nuclear Power Plant Docket Nuu.ber: STN 50-400 Wake County, North Carolina Calendar Years: 1983-1984 Type and Lower All Indicator Location w/ Highest Blannual Mean Medium or Pathway Total No. of Limit of Locations (2) Name, Control Locations No. of Norroutine Sampled or Measured Measurements Detection Mean Distance, and Mean Mean Reported (Unit of Measurement) Performed (LLD) (1 ) Range Direction Range (2) Range (2) Measurements (3) Air Cartridge I-131 (pCI/m ) 628 2.00E-2 All less than tLD All less than LLD All less than LLD 0 4 Air Particulate Gross Beta 1.67E-2 (523/523) Dixie Pipeline 1.58E-2 (105/105) 3
. (pCl/m ) 628 1.00E-3 2.57E 4.58E-2 2.5 miles N f.69E 3.47E-2 0 N
b w Gamma See 40 Table 5-1 All less than LLD All less than LLD All less than LLD 0 Sediment from Gamma Shoreline 5 See (pCl/g dry) Table 5-1 All less than LLD UI All less than LLD Not required 0 Botton Sediments (5) g,,,, (pCl/g dry) 1 See 5.51E-l (1/l) Harris Lake Mixing Zone Cs-137 Table 5-1 (Single value) 3.8 miles S Not Required 0
, . . ___. ____ _ . . _ _ . . _ .. _ _ _ _ _ . _ _ _ - _ _ _ _ _ m- _ _ _ _ _ . - - - _ _ . _ _ _ _ _. _ _. . _ . _ - . _ . -
TABLE 2-3 (cont. ) PREOPERATIONAL ENVIRONMENTAL RADt0 LOGICAL MONITORING PROGRAM
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Years: 1983-1964 Type and Lower All Indicator Location w/ Highest Blannual Mean Medium or Pathway Total No. of Limit of Locations (2) Name, Control Locations No. of Nonroutine Sampled or Measured Measurements Detection Mean Distance,'and Mean Mean Reported (Unit of Measurement) Performed (LLD) (1 ) Range Direction Range (2) Range (2) Measurements (3) Drinking Water 1-131 (pCl/1) 195 3.00E-1 All less than LLD All less than LLD All less than LLD 0 weekly Gross Beta 3.61E O (29/30) SHNPP Water Treat. 3.89E O (14/15) 3.51E O (15/15) Monthly 45 8.00E-1 1.44E O - 1.68E I Facility on site 1.44E O - 1.68E 1 1.56E O - 6.72E O O ! r- ,. Gamma See 45 Table 5-1 All less than LLD U) All less than LLD All less than LLD 0 Tritium 45 5.20E 2 All less than LLD All less than LLD All less than LLD 0 ; Fish Flesh: Gamma Botton Feeder 12 See 1.42E-1 (1/6) Harris take 1.42E-1 (1/6) 4.08E-2 (1/6) (pCi/g dry) Cs-137 Table 5-1 (Single value) Site varies (Single value) (Single value) 0 Free Swimmer Gamma (pCl/g dry) 12 See 4.51E-2 (1/6) Harris Lake 4.51E-2 (1/6) 5.74E-2 (1/6) Cs-137 Table 5-1 (Single value)- Site varies (Single value) (Single value) 0
TABLE 2-3 (cont. ) PREOPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number; STN 50-400 Wake County, North Carolina Calendar Years: 1983-1984 Type and All Indicator Location w/ Highest Riannual Mean Medium or Pathway Total No. of Lower Limit of Locations (2) Name, Control Locations No. of Nonroutine Sampled or Measured Measurements Detetection Mean Distance, and Mean Mean Reported (Unit of Measurement) Performed (LtD) (1) Range Direction Range (2) Range (2) Measurements (3) Food Crop (6) g,,,, (pci/g dry) 15 See Goodwin's Farm 9.86E-2 (1/12) 1.26E-1 (2/3) Cs-137 Table 5-1 9.86E-2 (1/12) 2.5 miles N (Single value) 1.25E 1.27E-1 O rv Groundwater Gamma See g 6 Table 5-1 All less than LLD All less than LLD Not required 0 Tritium 6 5.2E 2 All less than LLD All less than LLD All less than LLD 0 Milk l-131 120 4.00E-1 All less than LLD All less than LLD All less than LLD 0 Gamma 121 See 5.55E O (1/90) Olive's Dairy 5.55E O (1/30) Cs-137 Table 5-1 (Single value) 5.0 miles NNE All less than LLD 0 Surface Water 1-131 (pci/I) 282 3.00E-l All less than LLD All less than LLD All less than LLD 0 Monthly Composite Gross Beta USGS Station 72 3.10E O (48/48) # Lillington 3.23E O (24/24) 3.40E O (24/24) 8.00E-I 1.57E O - 5.75E O 17 miles SSE I.57E O - 5.75E O I.56E O - 6.72E O O Gamma See I4I 72 Table 5-1 All less than LLD All less than LLD All less than LLD 0 USGS Station III Tritium 5.70E 2 # Lillington 5.70E 2 54 5.2E 2 (Single value) 17 miles SSE (Single value) All less than LLD 0 Quarteriy Composite Tr1 tium 5.30E 2 6 5.2E 2 All less than LLD All less than LLD (Single value) 0 Direct Radiation TLD I.15E O (293/293) US 1 # SR 1149 1.6E O (8/8) 1.00E O (8/8) (mR/ week) 301 1.00E O 6.00E-I - 2.20E O 4.7 miles NE I .3E O - 2.2E O 8.00E 1.20E O O
l l i i l NOTATIONS FOR TABLE 2-3
- 1. The lower limit of detection is given by the following general equation:
4.66 s b
" E x V x 2.22 . Y , exp (-A t )
$e Where:
LLD = Lower limit of detection in pCi per unit volume or mass sb = (N/t b)1/ = Standard deviation of the background (cpm) N = Background count rate (cpm) tb = Background count time (min) E = Counting efficiency (counts per disintegration) V = Volume or mass of sample 2.22'= Conversion factor (dpm/pC1) 5 Y = Fractional chemical yield, when applicable 15 = Radioactive decay constant for the ith nuclide t e = Elapsed time between sanple collection and counting See Table 5-1 for listing of LLO values for the gamma spectrometry system. This expression is not used for direct radiation measurements.
- 2. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
2-16 1
t
- 3. Measurements are in excess at 99.5 percent confidence limit of ten times the control station value or ten times the lower limit of detection, whichever is larger.
- 4. No man-made radioactivity detected.
- 5. Bottom sediment sampling is not required but performed to better characterize the radiological characteristics of this environmental medium.
- 6. Food crops consisted of collards, cabbage, mustard greers. turnips, and greens.
- 7. Although quarterly composite samples are required, monthly composite samples are used to provide more frequent and sensitive analyses.
Monthly composite collection was initiated in July 1983. 1 e i J 4 2 - -
3.0 INTERPRETATIONS AND CONCLUSIONS 3.1 Air Samples 3.1.1 1983 In 1983, analysis of 310 air cartridge samples from control and indicator stations for I-131 showed that all measurements were below the lower limit of detection (LLD) of 2.00 E-2 pCi/m3. All gamma spectrometric analyses for man-made radioactivity in airborne particulate were also less than the respective LLDs for individual radionuclides (see Table 5-1). Gross beta measurements in airborne particulate samples from five indicator stations ranged from 2.57 E-3 to 4.58 E-2 pCi/m3 with a mean of 1.73 E-2 pC1/m3 . Similar gross beta radioactivity was observed at the control site in Pittsboro with values ranging from 4.69 E-3 to 3.47 E-2 pCi/m 3 and averaging '1.58 E-2 pC1/m3 . Figures 3-1 through 3-5 depict the gross beta measurement trends during 1983 l for' each indicator station. The gross beta activity concentra-tions at both indicator and control sites are comparable to monthly average values (3 E-2 to 6 E-2 pC1/m3) observed in 1978-79 atColumbia,SouthCarolina.(1) 3.1.2 1984 Analysis of 318 air cartridge samples from control and indicator stations for I-131 showed that all measurements were below the lower limit of detection (LLD) of 2.0 E-2 pC1/g3 in 1984. _All gamma spectrometric analyses for man-made radioactivity in airborne particulate were also less than the respective LLDs for individual radionuclides (see Table 5-1). _ Gross beta measurements in airborne particulate samples from five indicator stations ranged from 4.49 E-3 to 3.57 E-2 pC1/m3 with a mean of 1.62 E-2 pC1/m3 . Similar gross beta radioactivity was observed at the control site in Pittsboro with values ranging from 6.67 E-3 to 3 2.85 E-2 pC1/m 3 and averaging 1.58 E-2 pCi/m . Figures 3-1 t 3-1 l
through 3-5 depict the gross beta measurement trends during 1984 for each indicator station. The gross beta activity concentra-tions at both indicator and control sites are again comparable to monthly average values (3 E-2 to 6 E-2 pCi/m 3) observed in 1978-79 at Columbia, South Carolina.(I) 1 3.2 Milk Sampling 3.2.1 1983 In 1983, iodine-131 analysis in 24 milk samples from control and indicator stations resulted in values that were all less than the lower limit of detection of 4.00 E-1 pCi/1. Gamma spectrometric analyses in these samples showed all man-made gamma emiters in concentrations below the respective radionuclide LLDs (see Table 5-1). 3.2.2 1984 For 1984, iodine-131 analysis in 96 milk samples from control and indicator stations resulted in values that were all less than the lower limit of detection of 4.0 E-1 pC1/l. Gamma spectrometric analyses in these samples showed Cs-137, a man-made gamma-emitting fission product, in one sample from indicator Station MK-19. The observed activity concentration was 5.55 t 4.22 pCi/1* and occurred on April 3, 1984. All other man-made radionuclides were below their respective LLDs at the control Station (MK-5). The single occurrence of Cs-137 activity' compares well with Cs-137 concentrations observed periodically in milk samples collected at Charlotte, North Carolina, from July 1978 to June 1979.(1) The reported concentrations in this time interval ranged from -2 to 18 pC1/1.
*All error terms are i 1 o counting error only unless otherwise noted.
3-2
3.3 Food Crop Vegetation 3.3.1 1983 Cesium-137 was detectable in 1 of 6 samples of broad-leaved food . crop vegetation at indicator locations in 1983. The single value was 9.86 E-2 8.23 E-2 pCi/g dry in turnips and greens obtained from a farm about 2.3 miles north of the plant center. The equivalent wet-weight concentration at this location was 7.62 6.36 E-3 pCi/g wet. Cs-137 was also detected in 2 out of 3 samples of cabbage at the control location near Pittsboro. The Cs-137 concentrations in the two control samples were 1.25 E-1
~
i 0.34 E-1 pCi/g dry and 1.27 E-1 t 0.33 E-1 pCi/g dry, respectively. The equivalent fresh-weight values were 1.53 0.42 E-2 pCi/g wet and 1.29 0.34 E-2 pCi/g wet, respectively. The source of the Cs-137 at both indicator and control sites is fallout due to past above-ground testing of nuclear weapons. In the northern temperate latitudes, maximum deposition of the radionuclide occurred in 1963.(2) Although a number of factors can influence the uptake of Cs-137 in plants, it is generally recognized that soils deficient -in potassium, which is a chemical , congener to cesium, contribute- to increased metabolic uptake of radiocesium via root structures.(3) Moreover, because of the relatively long radiological life of Cs-137 (t1/2 - 30 yr), soil becomes the "long-term" compartment for the nuclide in terrestrial ecosystems. In some cases, this trophic level may provide a l constant reservoir of the nuclide for plants seeking scarce or biologically unavailable nutrient potassium. Experiments in cultivated and abandoned field plots have demonstrated the long-term availability of Cs-137 -for metabolic incorporation by plants.(4) In the absence of detailed experimentation or other evidence, it is reasonable to conclude that the presence of Cs-137 in vegetation collected in the SHNPP- environs was due to (1) i fallout from nuclear weapons testing and (2) the close chemical similarity between cesium and potassium which, under the 3-3
i i 1 l l ! appropriate conditions, can foster indiscriminate uptake of radiocesium by plants. 3.3.2 1984 In 1984 no anthropogenic radionuclides were observed at either indicator or control stations for food crop vegetation. All gamma spectrometric analyses showed such activities to be less than the respective LLDs for individual nuclides (see Table 5.1). 3.4 Shoreline Sediment 3.4.1 1983 In 1983 one sample of sediment was collected .and analyzed gamma spectrometrically, and the results indicated that all man-made gamma-emitting radionuclides were below the respective LLDs (see Table 5.1). 3.4.2 1984 In 1984 the four samples of shoreline sediment were collected and analyzed gamma spectrometrically. The results indicated again that all man-made gamma-emitting radionuclides were below the respective LLDs (see Table 5.1). 3.5 Botton Sediment In 1984 one sample of bottom sediment collected near the outfall of the cooling tower blowdown pipe indicated that all anthropogenic gamma-emitting radionuclides were below the respective LLDs (see Table 5.1) except for Cs-137. The observed value was 5.51 0.37 E-1 pCi/g dry for a sample collected on July 2, 1984. This result is attributable to fallout from past open-air nuclear testing. The concentration is comparable to the 1984 mean Cs-137 concentrations of 3.35 E-1 and 2.79 E-1 pCi/g dry 3-4
I i. i. observed in bottom sediments at control locations near CP&L's Brunswick and Robinson sites, respectively.(5, 6) The 5.51 E-1 pCi/g dry Cs-137 concentration is lower but still comparable to . the 2.31 1 0.18 (1 S0 sampling error) pCi/g dry mean concentration observed in bottom sediments of the' Hudson River in 1969-70(7). I This mean concentration was typical of the fallout Cs-137 concentration in sediments at sampling points upstream of the Indian Point reactor site on the Hudson River.
~ 3.6 Surface Water 1
3.6.1 1983 i Iodine-131 determinations in surface water samples from control and indicator locations were below the lower limit of detection of 3.00 E-1 pCi/l in 1983. Gamma spectrometric analyses for 1 anthropogenic radionuclides also indicated values less than the
; respective LLDs for individual nuclides (see Table 5.1). Tritium l
was detectable at 5.70 E 2 pC1/1 in the- September monthly composite sample at the municipal water intake structure at Lillington**. All other samples indicated H-3 concentrations less
- than the LLO of 5.20 E 2 pCi/1. Gross beta measurements at the two indicator stations ranged from 1.57 to 5.75 pC1/1 and averaged 3.22 pCi/1.- Similar gross beta measurements were observed at the control location with values ranging from 1.97 to 6.72 pCi/l and averaging 3.69 pC1/1. Figures 3-6 and 3-7 depict the gross beta trends at the indicator sites.
4 The major . source of tritium in the surface waters of the-world is fallout from open-air testing of thermonuclear ' devices. The testing injected large quantities of tritium into the
**This sampling point now resides about 0.25 mile downstream from the , municipal intake structure. The sampling device is housed in the USGS gauge station at this location.
3-5 i
. - , -, - . - - - n. . ,,
l stratosphere.(8) The NCRP observed that H-3 concentrations in precipitation at Ottawa, Canada, increased by over two orders of magnitude above natural background as a result of weapons testing.(9) Prior to 1952 the natural H-3 concentration in Ottawa was less than 20 pC1/1 in rainfall, while in 1963 the concentration increased to 9600 pCi/1. By 1968 the H-3 concentration fell to 650 pCi/l at this location. Due to its relatively long radiological life and its equilibrium loss rate
- with the stratospheric " reservoir," tritium concentrations on the order of several hundred pCi per liter can still be expected in terrestrial waters.
3.6.2 1984 For 1984, iodine-131 determinations in surface water samples from control and indicator locations were below the lower limit of detection of 3 E-1 pCi/1. Gamma spectrometric analyses for anthropogenic radionuclides also indicated values less than the respective LLDs for individual nuclides (see Table 5.1). All tritium samples indicated H-3 concentrations less than the LLO of 5.2 E 2 pCi/1. Gross beta measurements at the two indicator stations ranged from 1.67 to 5.56 pC1/1 and averaged 2.98 pCi/1. Similar gross beta measurements were observed at the control location with values ranging from 1.56 to 5.86 pCi/l and averaging 3.11 pCi/1. Figures 3-6 and 3-7 depict the gross beta trends at the indicator sites. 3.7 Drinking Water 3.7.1 1983 In 1983, iodine-131 assays in drinking water samples from control and indicator stations were below the lower limit of detection of 3.00 E-1 pCi/1. Gamma spectrometric analyses for man-made radionuclides also indicated values less than the respective LL0s 3-6 ; 1 l
for individual nuclides (see Table 5-1). Tritium concentrations at indicator and control sites were all below the LLD of 5.20 E 2 pCi/1. Average gross beta concentrations at indicator.and control locations were similar at 5.98 pC1/1 and 5.0/ pCi/1, respec-tively. Figures 3-8 and 3-9 show gross beta concentration trends , for each indicator station. 3.7.2 1984 Iodine-131 assays in drinking water samples from control and indicator stations were below the lower limit of detection of 3 E-1 pCi/1 in 1984. Gamma spectrometric analyses for man-made radionuclides also indicated values less than the respective LL0s for individual nuclides (see Table 5-1). Tritium concentrations-at indicator and control sites were all below the LLD of 5.20 E 2 pC1/1. Average gross beta concentrations at indicator and control locations were similar at 2.99 pC1/1 and 3.11 pC1/1, respec-tively. Figures 3-8 and 3-9 show gross beta concentration trends for each indicator station. 4 3.8 Groundwater j 3.8.1 1983 Gamma spectrometric analysis of two groundwater samples showed all i man-made radionuclides to be less than the respective LLDs for 4 individual nuclides in 1983. Tritium concentrations were below the LLD of 5.2 E 2 pC1/1. 3.8.2 1984 In 1984,-gamma spectrometric analysis of groundwater samples again showed all man-made radionuclides to be less than the respective LLDs for individual nuclides. Tritium concentrations were below
*he LLD of 5.2 E 2 pC1/1.
3-7
3.9 Fish 3.9.1 1983-In 1983, gama spectrometric analysis of, bottom-feeding and free-swiming fish showed all anthropogenic ' radionuclides below the respective LL0s for individual nuclides (see Table 5-1). 3.9.2 1984 In 1984, gama spectrometric analysis of bottom-feeding and free-swiming fish showed all anthropogenic radionuclides below the respective LLDs for individual nuclides (see Table 5-1) with the exception of Cs-137. Single samples of both bottom-feeding and free-swiming fish were observed to have 2.51 0.51 E-2 (March 16,1984) and 8.91 t 5.27 E-3 (November 6,1984) pCi/g wet, respectively. The equivalent Cs-137 concentrations on a dry-weight basis were 1.42 0.29 E-1 pCi/g dry and 4.51 2.67 E-2 pCi/g dry for the bottom-- and free-swi ming- fish samples, respectively. Comparable Cs-137 concentrations were also seen in control samples (Table 2-2). The wet-weight Cs-137 concentrations are comparable to the 1.69 0.12 E-2 pCi/g wet (standard error of the mean) mean seen in seven species of Hudson River fish during 1969-70(7) . This average concentration can be attributed to fallout as the fish were collected at points upstream of the Indian Point reactor site. 3.10 External Radiation Exposure 3.10.1 1983 Thermoluminescent detector (TLD) area monitors averaged 1.2 mR/ week or about 7 uR/hr at indicator locations in 1983. The control station at Pittsboro averaged 1.05 mR/ week or about 6.3 uR/hr. These exposure rates are comparable to the 1.8 to 3-8
3.3 urad/hr terrestrial absorbed dose rates to air generally i observed along the Atlantic and Gulf Coastal plain states.(9) Correcting for cosmic-ray contributions which typically account for 30 to 50 percent of the total dose from all external environmental radiation, the exposure rates observed in the SHNPP environs are quite reasonable.(9) The 1983 measurements also compare well with the 6-9 uR/hr range obtained independently by an ~ aerial radiological survey of the SHNPP site.(10) The survey was conducted during June 19-26, 1984, and represents the total exposure contribution from both terrestrial and cosmic-ray sources over a 263-km2 area centered over the plant. 3.10.2 1984 In 1984 the TLD area monitors averaged 1.09 mR/ week or about 6.5 uR/hr at indicator locations. The control station at Pittsboro averaged 1.42 mR/ week or about 8.5 uR/hr. These exposure rates are again comparable to the 1.8 to 5.5 urad/hr terrestrial
)'
absorbed dose rates to air generally observed along the Atlantic and Gulf Coastal plain states.(9) If corrected for the approximate 30 to 50 percent cosmic-ray contributions, the 1984 exposure rates observed in the SHNPP environs are reasonable and again conform to the aerial survey results mentioned earlier. 3.11 Special Sampling of Environmental. Media When available, special environmental media may be sampled that is of potential interest for dose pathway assessment in the ~ SHNPP environs. This section presents the available data as of this writing. 3.11.1 Venison On May 1,1985, a road kill deer carcass was obtained about three miles from the plant center in the NE sector. Meat from the 3-9
l carcass was taken for gamma spectrometric analysis. The analysis ; was performed in triplicate with a fresh-weight mass of about 1 kg for each sample. Sample preparation followed the same technique used for fish or similar biologic material (see Section 5.4). Only Cs-137 was observed in the samples. The table below summarizes the data. Sample Cs-137 Concentration * , ID No. pCi/q wet pCi/q dry 1 2.46 0.56 E-2 1.18 ! 0.27 E-1 2 1.77 0.45 E-2 7.99 2.03 E-2 3 3.05 t 0.40 E-2 1.45 t 0.19 E-1
- 1 a counting error only The mean Cs-137 concentration was 2.43 1 0.64 E-2 pCi/g (1 SD sampling error) and 1.14 0.33 E-1 pCi/g (1 SD sampling error) for fresh and dry weights, respectively.
i
! 3.12 Ambient Environmental Dose Estimates 3.12.1 Methods and Assumptions Since detectable concentrations of two man-made radionuclides, i.e., Cs-137 and H-3 were observed in water and food media, it was of interest to estimate the dose that these radionuclides may deliver to human consumers living in the SHNPP environs. The methods of Regulatory Guide 1.109(11) were used to assess the ,
upper boundary dose that may be delivered to receptors through exposure pathways where measurable radioactivity , existed. Equation 3-1 below was used to perform the' dose calculations. 3-10
. J
( -
, $1pj=Cjp Uap Daipj Eq. 3-1 where:
R aipj
= Total annual dose to organ j, age group a, nuclide 1, and pathway p (mrem /yr)
C jp = Concentration of nuclide i in the media of
~ pathway p (pCi/1 or pCi/g)
,- U ap = Usage factor for age group a and pathway p (dimensionless)
! D ajpj = = Cose f actor for age group a, nuclide 1, path-way p, and organ j (mrem /pC1)
; The following usage factors were taken from Reg. Guide 1.109 for a
" maximum individual" consuming the listed food type.
-Usage Factor Food Infant _ Child ' Teen Adult Water (1/yr) 330 510 510 70 i i
Leafy ' Vegetables (kg/yr) -- 26 42 64 Fish (kg/yr) -
. ;-- 6.9 16 21 g.
Milk (1/yr) 330 330 400 , 310 The following radionuclide concentrations were used for each of the listed' food -types. The data are taken from Jearlier isections in this chapter , and are the , largest concentrations, observed in
, s each medium. .i
. ,~ 3-11 i< a
.(, -c
't. ,. ,
I- Concentration (pCi/1 or pCi/q wet) L Food Cs-137 H-3 l Water --- 5.7 E2 , L ' 3 Leafy Vegetables 1.53 E-2 --- ) , Fish- 2.51 -E-2 --- Milk 5.55 E0 --- 3.12.2 Dose Estimates 1 Tables 3-1 through 3-4 provide the environmental dose estimates in each of the food types described in the previous section. Annual i dose estimates are provided for bone, liver, total body, thyroid, kidney, lung, and the GI-LLI. The doses < .are segregated by age group. Table 3-1 provides dose estimates for consumption of fish with a . Cs-137 concentration of 2.51 E-2 pCi/g wet. The results show the lung of a teenaged consumer receiving the highest dose from.this pathway. From Table 3-2, it is seen that a child drinking water , with a tritium concentration of 5.70 E2 pC1/1 receives the highest dose for all organs when compared against the other age groups.- -Leafy vegetable ingestion at a Cs-137 -concentration of 1.53 E-2 pCi/g wet results in the highest dose being delivered to the . liver of a teenager.. (Table 3-3). Finally, ~ ingestion of milk at a Cs-137 concentration of 5.55 pC1/1 shows the liver of an infant to receive the highest annual dose of 1.12 mrem in this exposure pathway (Table 3-4).
, u .: '
i 3-12 s a
- 5;;g
, 1 i s Table 3-1 y .,_. Ambient Dose Estimates for the
' Fish Ingestion Pathway Annual Dose (mrem)
Organ Child Teen Adult Bone. 5.66 E-2 4.50 E-2 4.20 E-2 Liver 5.42 E-2 5.98 E-2 5.75 E-2 T. Body 8.00 E-3 2.08 E-2 3.76 E-2 Thyroid ND* ND ND
, Kidney 1.77 E-2 2.04 E-2 1.95 E-2
'h, Lung 6.36 E-3 7.91 E-2 6.48 E-3 GI-LLI 3.39 E-4 8.51- E-4 1.11 E-3
*ND = No Data 9
s
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'3-13 J 'q , .l', ,
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r Table 3-2 Ambient Oose Estimates for the Water Ingestion Pathway Annual Dose (mrem) Organ Infant Child Teen Adult Bone .ND* NO NO NO-Liver 5.79 E-2 8.45 E-2 4.41 E-2 4.37 E-2 T. Body. 5.79 E-2 8.45 E-2 4.41 E-2 4.37 E-2 Thyroid 5.79 E-2 8.45 E-2 4.41- E-2 4.37 E-2 Kidney 5.79 E-2 8.45 E-2 4.41 E-2 4.3/ E-2 Lung 5.79 E-2 -_8.45 E-2 4.41' E-2 4.37 E-2 GI-LLI 5.79 _E-2 - 8.45 E-2 4.41 E-2 4.37 E-2
*ND = No Data I
5 s 3-14
Table 3-3 ( Ambient Oose Estimates for the Leafy Vegetable Ingestion Pathway Annual Dose (mrem) Organ Child Teen -Adult Bone- 1.30 E-1 7.20 E-2 7.80 E-2 Liver 1.25 E-1 9.57 E-2 1.07 E-1 T. Body 1.84_ E-2 3.34 E-2 6.99 E-2 Thyroid ND* NO ND Kidney 4.06 E-2 3.26 E-2 3.62 E-2 Lung 1.46 E-2 1.27- E ~1.20 E-2 GI-LLI 7.80 E-4 1.36 E-3 2.07 E-3
*ND = No Data O
3-15 a
i. Table 3-4 Ambient Dose Estimates for the Milk-Ingestion Pathway Annual Dose (mrem) Organ' Infant Child Teen Adult , Bone 9.56 E-1 5.99 E-1 2.49 E-1 1.37 E-1 Liver 1.12 E-0 5.73 E-1 3.31 E-1 1.88 E-1 T. Body 7.93 E-2' 8.46 E-2 1.15 'E-1 1.23 E-1 Thyroid ND ND ND ND Kidney 3.00 E-1 1.87 E-1 1.13 E-1 6.37 E-2 Lung 1.22 E-1 6.72 E-2 4.37 E 2.12 E-2 GI-LLI 3.50 E-3 3.59 E-3 4.71 E-3 3.63 E-3 ND = No Data Y i r 3-16 )
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4.0 MISSING SAMPLES AND ANALYSES 4.1 Air Cartridge and Air Particulate In 1983 air cartridge and particulate samples were not analyzed from Station 2 (week of January 10) in the first quarter due to loss of power of the sampler. Loss of power was also the reason for no analysis of air cartridge and particulate samples from Station 26 (weeks of July 11 and July 18) during the third quarter. 4.2 External Radiation (TLD) 4.2.1 1983 The following TL0s were declared missing in the field in 1993: Quarter Monitoring Station 1 None 2 9, 15, 23, and 36 3 12, 15, 23, 31, 33, and 34 4 24, 27, 31, and 36 In the first quarter, the TLD from Station 18 was found damaged in the field and was consequently unusable. The number of TL0s missing in the field was significantly reduced in the following year (see below) due to a more judicious placement of detectors in areas or positions less accessible to either vandals or wild animals. 4.2.2 1984 The following TLDs were declared missing in the field in 1984: Quarter Monitoring Station 1 7 and 27 2 None 3 12 and 31 4 16 and 25 4-1
5.0 ANALYTICAL PROCEDURES 4 5.1 Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background Alpha / Beta Counting System. The lower limit of 3 detection is approximately 0.001 pCi/m for air particulates. Air particulate samples are mounted in 2-inch stainless steel plan-chets and counted directly. Acidified water samples are evaporated to a low volume, transferred ! onto a 2-inch tared stainless steel planchet, evaporated to total dryness, then counted on the Tennelec with appropriate self-absorption correction, based upon sample weight. The lower limit of detection is 8 E-1 pC1/1. t 5.2 Tritium . Liquid samples requiring tritium analysis are first distilled. Five milliliters of the distillate are mixed with ten milliliters of 11guld scintillation cocktail and counted in an LKB 1211 liquid scintillation counter for up to 300 minutes. The lower limit of detection is 520 pC1/1. 5.3 Iodine-131 Iodine-131 airborne concentrations are quantified by the Ge (L1) gamma spectrometry systems. Cartridges are placed on the detector and counted individually. 1 Iodine-131 in milk is analyzed by use of anion-exchange resin,, sodium hypochlorite leach, and organic extraction. Iodine is pre-cipitated as silver iodide, collected on a tared filter, dried, and counted on a beta-gamma coincidence system or by low-background beta counter. The lower limit of detection is 0.3 pC1/1. 5-1
I 5.4 Gamma Spectrometry Gamma spectrum analysis utilizes germanium or Ge (Li) detectors with thin aluminum windows housed in steel and lead shields. The detec-tors are coupled to Nuclear Data 4420 or 6685 computer-assisted multichannel analysis systems. Table 5-1 summarizes LLO values derived from instrument sensitivity based upon a blank sample back-ground. Air particulate composites are fitted into a petri dish and analyzed directly. Liquid samples are evaporated to a small volume, transferred to a polyethylene beaker, and analyzed directly. Shoreline sediment and food crop vegetation are dried, weighed, and then analyzed in a Marinelli beaker. Fish samples are cleaned and dressed similar to meal preparation. These samples are then dried at 100*C and ground to produce a homogeneous mixture. These are placed in a polyethylene beaker for analysis. 5.5 Thermoluminescent 00simetry Each area monitoring station includes a polyethylene packet, which is a polyethylene bag containing three calcium sulfate phosphors, contained in a Panasonic U0-814 badge. The badge is lighttight and the bag is weather resistant. Dosimeters are machine-annealed before field placement. Following receipt from the field, each dosheter is read utilizing Panasonic TLD readers. This instrument integrates the light photons emitted from traps deexcited above 150*C. The lower-energy traps are auto-matica11y eliminated through a preheat cycle. Calibration is check-
'ed regularly using dosimeters irradiated to known doses. Prior to 5-2 J
the measurement of each dosimeter, the instrument is checked through use of an internal constant light source as a secondary standard. The minimum sensitivity of the dosimeters used is approximately 1 mR. 1 The exposure reported is corrected for exposure received in storage. - through the use of control dosimeters. 5.6 EPA Laboratory Intercomparison Program
, The Radiological Environmental Laboratory at the Harris Energy &
Environmental Center in New Hill, North Carolina, provides radio-analytical services for CP&L's nuclear plant environmental surveil-lance programs. The laboratory is a participant in the EPA cross-check program and uses its performance in this program as a major determinant of the accuracy and precision of its analytical results. During 1983, 28 samples comprising the four major types of environ-mental media (milk, water, food, and air filters) were received. A total of 83 individual radionuclide analyses was performed on these samples. A summary of the analytical results is as follows: Normalized Deviation , From Known Value (8) Percent of Analyses 5 0.5 40
, 5 1.0 59 5 1.5 75 5 2.0 82 5 2.5 89 5 3.0 90 Eight of eighty-three analyses exceeded three standard de/1ations from the known values. These results required investigative and corrective actions as follows:
5-3
_ _ _. _. _ - .. . .. . __ . _.m -_ _ e
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In February 1983, an Sr-89 value for milk was reported which was 32 percent lower than. the known activity. The beta counter was recalibrated for Sr-89 and Y-90 efficiencies. Two subsequent Sr-89
, analyses of milk were within acceptable limits.
*~
In June 1983, two gross beta' analyses performed within;three days of one another were low by 13 and 19 percent,- respectively. ' Recali-
' bration of . the beta detector resulted in subsequent gross beta values within acceptable limits.
In February and May 1983, Ru-106 analysis of two mixed-gamma samples , were low in one case and high in another. . At the same time, the activities reported for the five other nuclides in-the mixture were very close i.o the known values. The erratic results are primarily
~
due to the.need to rely on a low-abundance (9.9 percent) Ru-106 peak at 621.8 kev to calculate sample activity. The most abundant energy line is too close to the positron annihilation peak for accurate quantitative analyses.
.In_May and June 1983, low Sr-90 activities were reported for a water and a milk sample. The levels. vere,approximately 30 percent lower 6r.d' were traced to the use of a two-year-old yttrium carrier solution which was no longer e.t,its' stated concentration. A monthly standardization program for e all' carrier solutions used in '
radiochemical analyses was initiated. In December '1983, the Sr-90 activity reported for a milk sample was
?' lower by a factor of 4. The Sr-89 ' activity was correct, and other possible sources of error were eliminated. Technician erroriat' a' a , o critical step in the yttrium analyses was suspected.
In 1984, 32 samples comprising the .four major environmental media (water, milk, food, and air filters)-and urine were analyzed. Data on the known activities and the 3 a control limits for 30 of 'the samples have ' been received from EPA. These 30 samples required' t - triplicate determination of the activity of 86 radionuclides. A 5-4 r
, s
( k'
comparison of the average of our reported values with the EPA known
~
nuclide activity and its standard deviation can be summarized as I follows:
/
Standard Deviation (o) From Known Activity Percent of Analyses
<1o 40
<2a 65
<3o 85 Thirteen of the eighty-six analyses (15 percent) fell outside the 3 / '
. o control limit. However, 6 of the 13 involved strontium-90 analyses for which EPA reports an unusually tight 3 a value (i.e., 2.6 pCi/ unit versus 8.7 pCi/ unit for comparable activities of strontium-89, chromium-51, cobalt-60, cesium-137, zinc-65, ruthenium 106, cesium-137, gross alpha, and gross beta and ,10.4 pCi/ unit for iodine). If one applies a larger 3 e value of 8.7 pCi/ unit to the Sr-90 activities, all six of our results for a total , of 92 percent of the laboratory's analyses fall within the EPA , control limits. Because of the exceptionally narrow limits for Sr-90, no corrective action toward our analytical methods was considered necessary. The remaining seven results, which were beyond the control limits, were randomly distributed -in time ~ and among nuclides. No trend developed and no corrective actions were deemed necessary. For example: One gross beta result on an April water sample was lower than the known activities by 18 percent; _ but subsequent analyses ir. May, July, September, and October were within limits. The Cs-137 activity reported for the June milk . sample was 28 percent _ higher. Subsequent Cs-137 analyses,. including the October milk sample, were within control limits. 5-5
,-p g3
A natural potas,sium value for a food sample was only 12 percent
~
higher but still outside the control limit. l - The Zn-65 Ru-106, and Cr-51 values in the October mixed-gamma sample were 16, 34, and 38 percent higher, respectively, while the other three components of the mixture, Co-60, Cs-134, and Cs-137, were within 1-2 o of the known values.
- A single Cr-51 value in the January mixed gamma was 75 percent higher. Cr-51 analyses are difficult because of the low-gamma abundance (9.8 percent), low energy,(320 kev) and the short half-life (27.8 days). - The June - sample activityz was within limits but, . as cited above, the October sample value was out of the control limit.
Y e h 1 ~ i i v 5-6
)
l l Tcble 5-1-1 1983 Typical Lower Limits of Detection (LLD) Ge (L1) Ganna Spectrometry l Air Samples LLO Cs-134 2.0 E-3 pC1/m 3 Cs-137 1.0 E-3 Ba-140 4.0 E-3 La-140 1.0 E-3 Other Expected 1.0 E-3 to Gamma Emitters 2.0 E-2 Water Samples L0 Cr-51 16 pC1/1 Co-58 3
, Co-60 4 Mn-54 2 Cs-134 3 Cs-137 3 Ba-140 7 La-140 3 Other Expected 3 to Gamma Emitters 50 Shoreline and Bottom Sediments LLD Cs-134 2.4 E-2 pCi/g (dry)
Cs-137 2.1 E 2 Cr-51 9.1 E-2 Co-58 1.8 E-2 Co-60 3.3 E-2 Mn-54 1.8 E-2 Other Expected 1.0 E-2 to Gamma Emitters 9.0 E-2 5-7
. . . _ . = . ,
Fish and Food Crop Vegetation {. ! LLD
.I-131 7.0 E-3 pCi/g (wet) i Cs-134 8.0 E 4- Cs-137 8.0 E-3 Cr 5.0 E-2 F Co-58 7.0 E-3 -
4 Co-60 1.0 E-2 Mn-54 7.0 E-3 Other Expected 7.0 E-3 to Gamma Emitters 7.0.E-2 I. ' f I
! 1 a
i 1 i 1 i i t i
- e
+
.i' l
i i 4 , i-j- k 4
- 5-8 E
- . . . , + . . . . .u - . - - ,- --_ ,, - - ,, , , . , , - . , - . . . . ,
( Tabla 5-1-2 1984 Typical Lower Limits of Detection (LLD) Ge (L1) Gannia Spectrometry Air Samples (LLD) Cs-134 1.0 E-3 pC1/m 3 Cs-137 1.0 E-3 Ba-140 2.0 E-3 La-140 1.0 E-3 Other Expected 1.0 E-3 to Gamma Emitters 2.0 E-2 Water Samples (LLD) Cr-51 16 pC1/1 Co-58 3 - Co-60 4 Mn-54 2 Cs-134 3 Cs-137 3 i Ba-140 7 La-140 3 Other Expected 3 to Gamma Emitters 50 Shoreline Sediments (LLD) < Cs-134 2.4 E-2 pCi/g (dry) Cs-13,' 2.1 E-2 Cr-51 9.1 E-2. Co-58 1.8 E-2 Co-60 3.3 E-2 Mn-54 1.8 E-2 Other Expected 1.0 E-2 to - Gamma Emitters 1.6 E-1 5-9
I
. >. : 0
{.
.t .
i- Fish'and Food Crop Vegetation 1 l ! (LLD) ! I-131 7.0 E-3 pC1/g-(wet)
- Cs-134 8.0 E-3 ,
- Cs-137 8.0 E-3 L Cr-51 5.0 E-2 i Co-58 7.0 E-3~
Co-60 '1.0 E-2 Mn-54 7.0 E-3
' Other Expected 7.0 E-3 to Gama Emitters 7.0 E-2 1
J i-a. i
}I 4
l 4 4 f 4 l 1-a } 4 1 4 5-10 A
6.0 LAND-USE CENSUS 6.1 Introduction . Implementation of the Radiological Effluent Technical Specifications (RETS) for the Shearon Harris Nuclear Power Plant (SHNPP) will require that an annual land-use census be conducted within a five-mile radius of the site. Regulatory guidance for the conduct of the survey is provided in NUREG 0472(12) and NUREG 0133(13). This guidance will be manifested in the Standard Technical Specifications for the plant. Although it is not yet a formal requirement, a land-use census has been conducted since 1982 utilizing the regulatory guidance listed above. The bases, methods, and results from the 1984 survey are presented in this section. The survey was conducted on August 20-22, 1984. 6.2 Requirements i I Regulatory guidance found in NUREG 0472, Revision 3, gives the following-requirements for conducting a land-use census in the vicinity of a i nuclear power plant: A. The survey is to be conducted within a five-mile radius of the plant. B. The survey shall be conducted annually. C. The survey in each of the 16 compass sectors shall identify the nearest:
- 1. Milk animal.
- 2. Residence.
- 3. Garden of greater than 500 square feet producing fresh, leafy vegetables.
6-1
, _.-__,,e__
' These requirements were supplemented with identification of the nearest meat animal.
4 NUREG 0472 further specifies (see Section 3/4.12.2, Bases for Land-Use Census): The best survey information from door to door, aerial, or i . consulting with local ~ agricultural authorities shall be used." i 6.3 Methods i
- In accordance with this guidance, the 1984 land-use census was conducted using 'a door-to-door survey method. A standard questionnaire was used
] during an interview to record pertinent data. j . -; Resident and road locations were located within the five-mile radius zone surrounding SHNPP using United States Geological Survey topographic quad-rangle maps (7.5-minute series). These maps were revised in 1981 based
; on aerial . photographs of that time and represent recent locations of l structures and roads in this locale. Moncure, Cokesbury, Fuquay-Varina, Merry Oaks, New Hill, and Apex quadrangle maps were used. The maps were ,
j combined, and five concentric circles at one-mile increments were . drawn with the plant at the center. Sixteen compass ~ sectors were' created in 22.5-degree increments on the map. Each sector was centered on the com-l pass direction. i j The combined map was used to identify the nearest residence. The nearest 4 I garden, milk animal (cow or goat), and meat animal (beef, hogs, or fowl) 4 were located by inspection of fields and residential lots and by inter-views with residents within the five-mile radius zone. l Two CP&L employees performed the survey on August 20-22, 1984. The j survey was conducted during fair-weather and visibility was good. The {, survey started close to the plant in each sector and extended out to the . l five-mile -perimeter. All roads within the five-mile- zone were l traveled. Barns, small sheds, and pasture-like fields were observed as
- indicators of grazing livestock. These indicators were followed up with 6-2, 1
J - ,-w- - w w -, gmm
an interview with the owner of the property. In some cases when the owner was not home, a neighbor was interviewed to obtain the desired information. If this was not possible, the property was revisited at a later time or information was determined by visual inspection. All l interviews were conducted in the presence of both CP&L employees. 6.4 Results Table 6-1 summarizes the locations of the nearest milk cow, milk goat, meat animal, residence, and garden in each of the 16 compass sectors. The data resulted from 76 recorded visitations and permitted the follow-ing observations: A. Milk goats are located in the N, NNE, NE, and ESE sectors. Most of the goats reside on residential lots with the milk con-sumed on the premises. B. Milk cows are located in the NE, N, and NNE sectors. The N and NNE locations are commercial dairies that.are currently part of the SHNPP environmental sampling program. The milk at the cow location in the NE sector is neither pasteurized nor used by the producers. l 1 e 6-3
i TABLE 6.1 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (MILES)* Exclusion Milk Milk Meat Sector Boundary Residence Cow Goat Garden Animal N 1.32 2.2 2.2 4.1 2.2 2.8 NNE 1.33 1.7 4.7 3.6 1.8 1.8 NE 1.33 2.3 2.3 2.3 2.3 2.3 ENE 1.33 2.0 - - 2.0 2.0 E 1.33 1.9 - - 1.9 4.7 ESE 1.33 2.7 - 4.9 2.8 4.1 SE 1.33 4.2 - - 4.3 4.3 SSE 1.33 - - - - - S 1.36 - - - - - SSW 1.33 4.0 - - 4.0 4.2 SW 1.33 2.7 . 2.7 2.8 WSW 1.33 4.3 - - 4.3 4.3 W 1.33 2.7 - - 2.7 3.1 WNW 1.33 2.2 - - 2.2 2.2 NW 1.26 1.7 1.7 - 1.7 1.7 NNW 1.26 1.6 - - 1.6 1.7
*As of August 22, 1984.
Distance estimates are ! 0.1 mile except at Exclusion Boundary. 6-4
7.0 REFERENCES
- 1. Carolina Power & Light Company. 1982. Shearon Harris Nuclear Power
( Plant, Environmental Report - Operating License Stage. r
- 2. National Council on Radiation Protection and Measurements. 1977.
Cesium-137 from the Environment to Man: Metabolism and Dose. Report
- No. 52, 48 pp.
- 3. Davis, J. J. 1963. Cesium and Its Relationships to Potassium in Ecol-ogy. In: Radioecology. V. Shultz and A. W. Klement (eds.). Reinhold Publishing Company. New York. pp. 539-556.
- 4. Cline, J. F., and W. H. Rickard. 1972. Radioactive Strontium and Cesium in Cultivated and Abandoned Field Plots. Health Physics 23:317-324.
- 5. Carolina Power & Light Company. 1984. Environmental Surveillance Report January 1,1984, to December 31, 1984, for the Brunswick Steam Electric Plant.
- 6. Carolina Power & Light Company. 1984. Environmental Surveillance Report January 1,1984, to December 31, 1984, for the H.B. Robinson Steam Elec-tric Plant Unit 2.
- 7. Lentsch, J. W. 1974. The Fate of Gamma-Emitting Radionuclides Released into the Hudson River Estuary and an Evaluation of their Environmental Significance. New York University. Ph.D. Thesis. 627 pages.
- 8. Eisenbud, M. 1973. Environmental Radioactivity. Academic Press. New York. 542 pp.
- 9. National Council on Radiation Protection and Measurements. 1975. Natu-ral Background Radiation in the United States. Report No. 45, 163 pp.
- 10. EG and G Energy Measurements. 1984. An Aerial Radiological Survey of the Shearon Harris Nuclear Power Plant. EGG-10282-1060. 16 pages.
- 11. U.S. Nuclear Regulatory Commission. 1977. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose cf Evaluating Compliance with 10CFR Part 50, Appendix I. Regulatory Guide 1.109.
- 12. U.S. Nuclear Regulatory Commission. 1979. Draft Radiological Effluent Technical Specifications for PWRs. Revision 3, NUREG 0472.
- 13. U.S. Nuclear Regulatory Commission. 1978. Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants. NUREG 0133.
7-1 _ _ _ _ _ _ _ _}}