ML18010A611
| ML18010A611 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/31/1991 |
| From: | Cahill D, Minard K CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18010A609 | List: |
| References | |
| NUDOCS 9204280358 | |
| Download: ML18010A611 (98) | |
Text
1991 HARRIS NUCLEAR PROJECT CAROLINA POWER 5. LIGHT COMPANY 9204280358 920421 PDR ADOGK 05000400 R
PDR'
J Harris Energy 4 Environmental Center Carolina Power Jk Light Company New Hill, North Carolina RADIOLOGICALENVIRONMENTALOPERATING REPORT FOR THE SHEARON HARMS NUCLEAR POWER PLANT JANUARY 1 THROUGH DECEMBER 31, 1991 Prepared by:
Reviewed by:
C TABLE OF CONTEXTS Table of Contents............................. ~.....
L1st Of FigureS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
List of Tables v 1 .0
SUMMARY
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 1 2.0 GENERAL INFORMATION................................ 2-1 2.1 Plant and Location............,......',,...,,...,...., 2-1 2.2 Radiological Environmental Monitoring Program ................ 2-2 3.0 INTERPRETATIONS AND CONCLUSIONS...................... 3-1 3 .1 Air ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-1 3.2 Drinking Water..............,....,...,... ~ ~ 3-1 3 3
~ Fish.................................. 3-2 3 .4 Surface Water...................................... 3-2 3 .5 Groundwater 3-3 3 o6 Milk ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-3 3.7 Bottom Sediment.................................... 3-3 3.8 Shoreline Sediment 3-3 3.9 Food Crops 3-4 3.10 External Radiation Exposure .. 3-4 3.11 Comparison with Preoperational and 1990 Operational Data 3-4 o
4.0 MISSED SAMPLES AND ANALYSES ....................,.... 4-1 4.1 Air Cartridge and Air Particulates 4-1 4.2 F Ood CI'Ops ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 1 4.3 TLDs ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
5.0 LAND-USE CENSUS .................................... 5-1 5.1 Introduction........................... ~.... 5 1
~ ~ ~ ~
5 .2 Requirements 5-1 UAOSNREPK,FS591HNPREO.REP
TABLE OF CONTENTS (continued) 5..3 Methods ....................................... 5 1 5 4
~ Results ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 5 2 6.0 ANALYTICALPROCEDURES .............................. 6-1 6 .1 Gloss Beta ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-1 o ~
6 .2 ir1t1um o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 1 6 3 Iodme 131 ........................... ~............ 6 1 6.4 Gamma Spectrometry ............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 2 6.5 Thermoluminescent Dosimetry ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 2 6.6 BPA Laboratory Intercomparison Program ~ ~ 6-3 6,7'ower Limits of Detection.......... 6-4 U AOSUUKM.PSE91HNPREO.REP
LIST OF FIGURIM F~i>re ~Pa e 2-1 Shearon Harris Nuclear Power Plant Radiological Environmental Sampling Points ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 27 2-2 Shearon Harris Nuclear Power Plant Radiological Environmental Sampling Points ............. ~.............. ~ . 2-8 2-3 Shearon Harris Nuclear Power Plant Radiological Environmental Sampling Points .............................. 2-9 2-4 Legend for Figures 2-1, 2-2, 2-3 ............,................ 2-10 3-1 Gross Beta Activity for Air Particulate Samples (Sample Point 0001) ....... 3-8 3-2 Gross Beta Activity for Air Particulate Samples (Sample Point 0002) ....... 3-9 3-3 Gross Beta Activity for Air Particulate Samples (Sample Point 0004) ....... 3-10 3-4 Gross Beta Activity for Air Particulate Samples (Sample Point 0026) ....... 3-11 3-5 Gross Beta Activity for Air Particulate Samples (Sample Point 0047) .... ~ .. 3-12 3-6 Gross Beta Activity for Drinking Water Samples (Sample Point 0040)..... ~ . 3-13 3-7 Gross Beta Activity for Drinking Water Samples (Sample Point 0051)....... 3-14 3-8 Tritium Activity for Drinking Water Samples (Sample Point 0040)......... 3-15 3-9 Tritium Activity for Drinking Water Samples (Sample Point 0051)......... 3-16 3-10 Gross Beta Activity for Surface Water Samples (Sample Point 0026)........ 3-17 3-11 Gross Beta Activity for Surface Water Samples (Sample Point 0040)........ 3-18 3-12 Tritium Activity for Surface Water Samples (Sample Point 0026).......... 3-19 UAOSUUKNLPSE91HNPREO.REP
LIST OF FIGURES (Continued)
F~ire ~Pa e 3-13 Tritium Activity for Surface Water Samples (Sample Point 0040)...,...... 3-20 3-14 Tritium Activity for Surface Water Samples (Sample Point 026S).......... 3-21 3-15 Tritium Activity for Surface Water Samples (Sample Point 041S).......... 3-22 3-16 Tritium Activity for Surface Water Samples (Sample Point 052S)....'...... 3-23 3-17 Iodine-131 Activity for Milk Samples (Sample Point 0005).............. 3-24 3-18 Iodine-131 Activity for Milk Samples (Sample Point 0042)........,..... 3-25 3-19 Iodine-131 Activity for Milk Samples (Sample Point 0043).............. 3-26 3-20 Gamma Activity for Bottom Sediment Samples (Sample Point 0052)........ 3-27 3-21 TLD Averages for Inner and Outer Ring Locations .................. 3-28 UAOSULREP)LPS<91HNPREO.RBP lv
LIST OF TABLES Table ~Pa e 1-1 Radiological Environmental Monitoring Program Data Summary .......... 1-3 2-1 Radiological Environmental Monitoring Program.................... 2-4 5-1 Distance to the Nearest Special Locations from the Shearon Harris Nuclear Power Plant (miles) ...................... 5-4 5-2 Meat Animal Type at Nearest Location to the Shearon Harris Nuclear Power Plant by Sector........... ~................... 5-5 6-1 Typical Lower Limits of Detection (a priori)
Gamma Spectrometry ........,........................., . 6-4 UAOSUQKNLFS>91HNPREO.RBP
1.0
SUMMARY
This report presents the results of the Radiological Environmental Monitoring Program conducted during 1991 for the Shearon Harris Nuclear Power Plant (SHNPP) and fulfills the reporting requirements of Technical Specifications 6.9.1.3. The program was conducted in accordance with Technical Specification 4.12.1, the Off-Site Dose Calculation Manual, and applicable procedures.
Approximately 900 samples of 11 different media types from indicator stations were compared to approximately 200 control samples. No detectable activity or activities not differing from the corresponding control samples occurred in 96 percent of the indicator samples.
Radioactivity in environmental samples which could be attributed to plant operations in 1991 is as follows:
- .';
- ;..::.,:';::::::::Av'edge.':',;,":,:.'::,::,"'i:,:::I"., :',':,,,"':
- Ra'dio'iii'iclide'.
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Harris Lake Surface H-3 7.81 B+3 pCi/E No ingestion Water (24/24) pathway. No dose calculated.
Fish H-3 See above .01 (T.B.)
SHNPP Drinking Water H-3 5.27 B+3 pCi/E .10 (T.B)
(11/12)
Harris Lake Shoreline Co-58 6.85E-2pCi/g 1.8E-4 Sediment (5/8)
Cs-137 4.798-2pCi/g 1.3E-4 (1/8)
Harris Lake Bottom Mn-54 2.52E+0 pCi/g No dose calcu-Sediment (3/3) lated as water Co-57 2.54B-1 pCi/g shielding elimi-(3/3) nates dose at Co-58 1.12B+1 pCi/g surface.
(3/3)
Co-60 4.13B+1 pCi/g (3/3)
Cs-137 3.70E-1 pCi/g (3/3)
Sb-125 3.25E+0 pCi/g (1/3)
UAOSUQKPLLFS191HNPREO.RHP
Overall, the radiological environmental data indicates that SHNPP operations in 1991 had no significant impact on the environment or public health and safety.
A statistical summary of all the data for 1991 has been compiled and summarized in Table 1-1.
The only impact of the plant on the environment in its five year's of operation has been (1) a slow but steady increase in the annual average tritium activity in Harris Lake from 3.4B+3 pCi/l in 1987 to 7.8B+3 pCi/E in 1991 and (2) the accumulation of activation products (primarily cobalt and manganese) in bottom sediment near the cooling tower discharge point.
UAOSUUKRLFS(91HNPREO.RFP 1-2
TABL RADIOLOGICAL3PPGRONMXNTAL MO RING PROGRAM DATA
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1991 Air Cartridge 1-131 1.4F 2 All less than LLD All less than LLD All less than LLD (pCi/m ) 310(3)
Air Patticulate Gross Beta 1.2E-3 1.33E-2 (259/259) SR 1912 1.51E-2 (52/52) 1.26E-2 (51/51)
(pCi/m ) 310(3) 4.22F 3 - 3.60E-2 3.4 miles SSW 7.58F 3-3.60F 2 5.80E 1.99E-2 Gamma Refer to All less than LLD All less than LLD All less than LLD Table 6-1 Drinking Water 1-131 4.0E-1 All less than LLD All less than LLD All less than LLD (PCi/1) 156 Gross Beta 2.0E+0 4.34E+0 (24/24) Li!!ington 5.55E+0 (12/12) 6.18E+0 (12/12) 36 2.32E+0- 8.16E+0 Cape Fear River 2.94E+0- 8.16E+0 2.59E+0 - 1.17E+ 1 17 miles SSE Gamma Refer to All less than LLD All less than LLD All less than LLD 36 Table 6-1 Tritium 1.2E+3 5.27E+3 (ll/24) SHNPP site 5.27E+3 (11/12) All less than LLD 36(5) 3.77E+3 - 6.96E+3 0.1 mile SSW 3.77E+3 - 6.96E+3 Refer to All less than LLD All less than LLD AH less than LLD Bottom-Feeders Table 6-1 (pCi/g, wet)
FreeSwimmers Refer to All less than LLD All less than LLD All less than LLD (pCi/g, wet) Table 6-1 U:LOSVREM.FS$ 1HNPREO
TABLE 1 RADIOLOGICAL1<2VVIRONMENTALMOb G PROGRAM DATA
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1991 Food Crop Gamma (pCi/g, wet) 49(3) 4.86F 2 (3/26) SR 1167 4.86F 2 (3/14) 1.79E-2 (1/23)
Cs-137 1.7F 2 4.61E 5.35E-2 1.7 miles NNW 4.61E 5.35E-2 Single Value Groundwater Gamma Refer to All less than LLD All less than LLD All less than LLD (pCi/1) 20 Table 6-1 Tritium ICE+3 All less than LLD All less than LLD All less than LLD 20 Milk 1-131 4.0F 1 All less than LLD All less than LLD All less than LLD (pCi/1) 72 Gamma Refer to All less than LLD All less than LLD All less than LLD 72 Table 6-1 Bottom Sediments( ) Gamma No control (pCi/g, dry) 3 2.52E+0 (3/3) Harris Lake 2.52E+0 (3/3)
Mn-54 4.4F 2 2.07E+0 - 3.13E+0 3.8 miles S 2.07E+0 - 3.13E+0 Co-57 3.1E-2 2.54F 1 (3/3) Hams Lake 2.54E-1 (3/3) No control 1.31E 4.31E-1 3.8 miles S 1.31E 4.31E-1 Co-58 3.7E-2 1.12E+1 (3/3) Hams Lake 1.12E+1 (3/3) No control 3.10E+0- 2.07E+1 3.8 miles S 3.10E+0- 2.07E+1 3.7E-2 4.13E+ 1 (3/3) Hams Lake 4.13E+1 (3/3) No control 1.52E+1 - 8.26E+1 3.8 miles S 1.52E+1- 8.26E+1 Cs-137 5.3F 2 3.70F 1 (3/3) Hams Lake 3.70E-1 (2/3) No control 2.29E 5.61E-1 3.8 miles S 2.29F 1- 5.61E-1 Sb-125 1.2F 1 3.25E+0 (I/3) Hams Lake 3.25E+0 (1/3) No control Single Value 3.8 miles S Single Value U:LOSUQKM.FS't91HNPREO
TABLE 1 t.)
RADIOLOGICALEN'VIRONMENTALMO G PROGRAM DATA
SUMMARY
Shearon Harris Nuclear Power Plant Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1991 Shoreline Sediments Gamma ipCi/g, dr)) 8 Co-58 3.7E-2 6.85F 2 (5/8) Harris Lake 8.99E-2 l2/4) No control 2.04F 2- 1.20F I 3.8 miles S 5.98E 1.20E-I Cs-137 5.3F 2 4.79E.2 (I/8) Harris Lake 4.79E-2 (I/4) No control Single Value 3.8 miles S Single Value Surface Water(5)(6) 1-131 4.0E-I All less than LLD All less than LLD All less than LLD
('P CI/I) 104 Gross Beta 2.0E+0 4.58E+0 (24/24) Lillington 5.55E+0 (12/12) 6.18E+0 (12/12) 36 2.70E+0- 8.16E+0 Cape Fear River 2.94E+0- 8.16E+0 2.59E+0- I'.17E+I 17 miles SSE Gamma Refer to AH less than LLD All less than LLD All less than LLD 36 Table 6-1 Tritium 1.2E+3 7.81E+3 (24/36) Harris Lake 8.09E+3 (4/4) All less than LLD 48 5.48E+3-1.16E+4 3.8 miles S 6.25E+3-1.16E+4 Direct TLD 9.60E-I (158/158) Int SR1149 and 1.33E+0 (4/4) 9.00E-I (4/4)
Radiation 162( ) 7.00E-I - 1.40E+0 US I 4.7 miles 1.20E+0 - 1.40E+0 9.00E-I - 9.00E-I (mR/week) NE U:<OSUIREM.FSSIHNPREO
FOOTNOTES TO TABLE 1-1 1.~ The Lower Limit of Detection (LLD) is the smallest concentration of radioactive material in a sample that willyield a net count above system background which willbe detected with
~
95 percent probability and with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
- 2. Mean and range are based on detectable measurements only. The fractions of all samples with detectable activities at specific locations are indicated in parentheses.
- 3. Refer to Section 4, Missing Samples and Analyses.
- 4. Bottom sediment sampling is not required by the technical specifications.
- 5. Although quarterly composite samples are required, monthly composite samples are used to provide more frequent and sensitive analyses.
6.~ Lake surface waters are only required to be analyzed for tritium quarterly, but additional
~
sampling and analyses were performed monthly. These additional analyses were intended to better characterize the impact of plant operations on Harris Lake.
UAOSMREP)LFS591HNPREO.REP 1-6
2.0 GEM<MAL INFORMATION This section (1) describes the pertinent 'characteristics of the plant and its environs; (2) provides the details of the monitoring program including sample locations, types, frequencies, and analyses; and (3) presents maps showing the distribution of sampling sites around the plant.
2.1 Plant and Location The Shearon Harris Nuclear Power Plant (SHNPP) is a pressurized water reactor designed to produce 860 MWe (net). Criticality was initially achieved on January 3, 1987.
The SHNPP site is located in the extreme southwest corner of Wake County, North Carolina. The plant is approximately 16 miles southwest of Raleigh and approximately 15 miles northeast of Sanford. This location is on the northwest shore of Harris Lake which is a 4,000-acre reservoir created by the impoundment of Buckhorn Creek. The reservoir provides process and cooling tower makeup water for the plant and also serves as the receiving body for liquid effluents such as yard runoff, cooling tower blowdown, and radioactive waste processing system.
The main dam for the reservoir is approximately 4.6 miles south of the plant. The spillway at the dam flows into Buckhorn Creek which, after flowing south for approximately two miles, enters the Cape Fear River.
There are no industrial or residential structures on CP&L property. Carolina Power & Light cooperates with various state agencies to provide public access for boating, fishing, hunting, and other recreational uses on the property such as boat ramps and access areas.
The majority of the land within five miles 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 area including an operating commercial dairy.
The population within ten miles 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 Figure 2-2).
UAOSNRERLPS)91NHPREO.REP 2-1
Within a 50-mile radius of the plant, much of the land is devoted to agricultural activity. Major crops include tobacco, soybeans, and corn for grain, Livestock production includes hogs, beef, poultry, and dairy products. Commercial fish and shellfish catches from waters within 50 miles of the station discharge are negligible. Recreational fishing is popular in the area. Since there are no estuarine or saltwater bodies, sportfishing is confined to freshwater streams, rivers, private ponds, and impoundments such as Harris Lake and Jordan Lake.
2.2 Radiolo ical Environmental Monitorin Pro ram The purposes of the SHNPP Radiological Environmental Monitoring Program are to:
~ Provide an evaluation of the environmental impact of releases of radio-active materials from the plant.
~ Measure any accumulation of radioactivity in the environment and to assess trends,
~ Detect unanticipated pathways for the transport of radionuclides through the environment.
The following locations are designated as control locations for the respective measurements and are intended to indicate conditions away from SHNPP influence:
Pittsboro ) 12 miles NW (Sample Station 5)
Airborne Particulate (filter) Samples Charcoal Cartridge Samples Airborne I-131 Thermoluminescent Dosimeter Area Monitors MilkSamples Food Products U:EOSUREP)LFS>91NHPREO.REP 2-2
Ca e Fear Steam Electric Plant 6.1 Miles WSW (Sample Station 38)
Surface Water Samples Drinking Water Samples Upstream of the Buckhorn Dam on the Cape Fear River Site Varies in thi cale (Sample Station 45)
Pish Samples The current radiological environmental monitoring program is detailed in Table 2-1 and has been based on plant Technical Specification 4.12.1. Harris Lake bottom sediment sampling, although not a requirement, is a component of the program, Figures 2-1, 2-2, and 2-3 show the environmental monitoring locations.
Figure 2-4 provides a legend for Figures 2-1 through 2-3.
UAOSUQKPQ.PS591NHPREO.REP 2-3
TAB RADIOLOGICALF<2PGRO MONITORING PROGRAM SHEARON HARIUS NUCLEAR POWER PLANT
.',".ll,::,i':.'!~Si' l~rii"A~iii~f':
Air Cartridge (AC) 1-2.5 miles N Continuous operating sam- Weekly 30,000 cu. It I-131 (charcoal cartridge) 2-1.5 miles NNE pling with sample collection (900 cu m) 4-3.2 miles NNE at least once per seven days 5-> 12 miles NW-Pittsboro (Control)'6-4.6 or as required by dust loading miles S 47-3.4 miles SSW Air Particulate (AP) 1-2.5 miles N Continuous operating sam- Weekly 30,000 cu. It. Gross 2-1.5 miles NNE pling with sample collection (900 cu m) 4-32 miles NNE at least onco per seven days Beta'amma 5-> 12 miles NW-Pittsboro (Control)'6-4.6 or as required by dust loading miles S Quarterly 47-3.4 miles SSW Co ositc Isotopic'amma Sediment from 26-4.6 miles S Seiniannually 500g Shoreline SS 41-3.8 miles S Isotopic'amma Bottom Sediment'D 52-3.8 miles S Semiannually 500g Isotopic'rinking Water (DW) 38-6.1 miles WSW (Control)'0-17 Weekly 8 liters I-131 mi!es SSE-Lillington 51-0.1 mile SSW-SHNPP Site Monthly Gamma Isotopic'ritium Coinpositc Gross Beta Groundwater 39-0.7 mile SSW Quarterly 8 liters Tritium 57-0.4 mile SSW Gamma 58-0.5 mila WSW 59-0.5 milo NNE Isotopic'amma (GW)'ood 60-0.5 mile ESE 44-Sita varies within Hams Lake Seiniannually 1 kg each Isotopic'n 45-Sita varies in Cape Fear River FreaSwimmers ediblo portion for each above Buckhorn Dam Contro Bottom-Feeders Products (FC) 54-1.7 miles NNE-Wilkins or Moms During growing season when Monthly 500g Gamma 55-1.7 miles NNW-L. L. Goodwin inilk sampling is not per 5->12 miles WNW, NW( or NNW-Isotopic'ilk formed Pittsboro Control (MK) 42-7.5 miles SSE-Maple Knoll Dairy When animals on pasture Semimonthly 8 liters I-131 43-2.2 miles N-Goodwin's Dairy Gamma 5-> 12 miles NW-Strowd's Dairy Contin Isotopic'urface Water (SW)'6-4.6 miles S Weekly 8 liters I-131 38-6.1 miles WSW (Control)'0-17 miles SSE-Lillington Monthly Gamma Isotopic'ritium Composite Gross Beta U:tOSUtREPtLFSt91HNPREO.REP
TAB RADIOLOGICALENVIRONMENT MONITORING PROGRAM SHEARON HARRIS NUCLEAR POWER PLANT
-" le'Ce'*.,",::;:"':
f:::,,:~Ci ",:".i';: . R~im Te Aiiiil". ":".:;:",,"':""
Direct Radiation YLDs Continuous measurement with Not applicable Ganuna Dose Monitors (TLD) 1-2.5 miles N an integrated readout at least 2-1.5 miles NNE once per quarter 3-2.6 miles ENE 4-3.2 miles NNE 5-) 12 miles NW-Pittsboro (Control/
6-0.9 mile ENE 7-0.8 mile E 8-0.7 mile ESE 9-2.3 miles SE 10-2.2 miles SSE 11-0.7 mile S 12-0.8 mile SSW 13-0.7 mile SW 14-1.4 miles W 15-1.8 miles W 16-1.7 miles WNW 17-1.4 miles NW 18-1.3 miles NNW 19-4.9 miles NNE 20-4.7 miles NE 21-4.8 miles ENE 22-4.6 miles E 23-5.0 miles ESE 24-4.7 miles SE 25-4.8 miles SSE 26-4.6 miles S 27-4.8 miles SSW 28-4.8 miles SW 29-5.6 miles WSW 30-5.1 miles W 31-4.5 miles WNW 32-6.4 miles NW 33-4.4 miles NNW 34-8.6 miles NE-Apex 35-6.9 miles E-Holly Springs 36-11.2 miles E 37-9.7 miles ESE-Fuquay-Varina 48-4.5 miles N 49-2.6 miles NE 50-2.8 miles ESE 53-5.5 miles NW 56-2.8 miles WSW U:tOSNREPtLFS(91HNPREO.REP
NOTES TO TABLE 2-1
- 1. Sample locations are shown on Figures 2-1, 2-2, and 2-3. Figure 2-4 provides a legend explaining Figures 2-1 through 2-3.
- 2. Particulate samples will be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more following filter change to allow for radon and radon-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 two hours) relative to period (e.g., monthly). the'ompositing
- 6. The dose will be calculated for the maximum organ and age group using the methodo-logy contained in Regulatory Guide 1.109, Rev. 1, and the actual parameters particular to the site.
- 7. Bottom sediment sampling and analysis is not required by RETS. Samples are collected to provide additional environmental characterization.
- 8. Weekly I-131 analyses are not required for surface water samples. However, water samples collected at Locations 38 and 40 serve also as drinking water samples. I-131 analyses are performed on samples from these two locations.
- 9. Groundwater Sampling Locations 57-60 provide additional environmental characteriza-tion.
U AOSUKEP)LFS<91HNPREO.REP 2-6
Figure 2-2.
tres Shearon Harris Nuclear Power Plant POINTS Ol 0 RADIOLOGICALENVIRONMENTALSAMPLING I' 64 ITIS ~ IJ j I NIJ 64 OCTVT CNJRTL
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3.0 INT1MAPRETATIONS AND CONCLUSIONS 3.1 Air All 310 air cartridge samples from indicator and control stations had I-131 activities which were less than the LLD (see Table 6-1).
Gross beta activity was detectable in all airborne particulate samples from the five indicator locations. The 259 samples had an average concentration of 1.33E-2 pCi/m'. Similar gross beta activities were observed at the control location in Pittsboro which had an average concentration of 1.26E-2 pCi/m in 51 samples.
No gamma activity was detected in quarterly composite filter samples from either the indicator or control locations.
Figures 3-1 through 3-5 provide a graphic representation of the gross beta activity at the indicator locations compared to the control location for the period January through December 1991.
3.2 D~W None of the 104 drinking water samples collected at the SHNPP and the Lillington Municipal water supply nor the 52 control samples collected from the Cape Fear River above the Buckhorn Dam contained detectable I-131 activity during 1991.
Figures 3-6 and 3-7 provide graphic representation of the gross beta activity during 1991 for Locations 40 (Lillington) and 51 (SHNPP site). The solid line is the indicator location, while the broken line is the control location at the Cape Fear Plant.
The average monthly gross beta concentrations at the indicator and control locations were similar with activities of 4.34 and 6.18 pCi/1, respectively.
Analyses for gamma-emitting radionuclides indicated all concentrations were less than the lower limit of detection for drinking water. Table 6-1 contains typical LLD values for gamma-emitting radionuclides in drinking water.
Tritium activities in drinking water at the SHNPP, which is drawn from the Harris Lake, ranged from 3.8E+3 to 7.0E+3 pCi/1. The average activity in 1991 was U:EOSUKEP)LFSE91HNPREO.REP 3-1
5.3E+3 pCi/1. No tritium was detected in the Lillington municipal water supply or the control station samples.
The total body dose to occupationally exposed personnel at SHNPP from the ingestion of 5.3E+3 pCi/I of tritium in drinking water during the year was calculated using the USNRC Regulatory Guide 1.109, Equation A-1. This dose was estimated at 0.1 mrem for the year of 1991.
Figures 3-8 and 3-9 present the tritium activities at the sample locations versus the control values.
3.3 Fish Analyses for gamma-emitting radionuclides in two samples of bottom-feeding fish and in four samples of free-swimming species (sunfish and largemouth bass) from the indicator location, Harris Lake, revealed no detectable activity for 1991.
3.4 Surface Water Surface water samples were collected and analyzed weekly for I-131. Water samples collected during 1991 contained no detectable I-131 (LLD ( 4E-01 pCi/1).
Average gross beta concentrations at the indicator and control locations were-4.6 pCi/1 and 6.2 pCi/1, respectively.
Figures 3-10 and 3-11 provide a graphic representation of the gross beta activity in surface water during 1991 for Locations 26 (Harris Lake) and 40 (Lillington).
The solid line is the indicator location, while the broken line is the control location.
Surface water samples were analyzed for gamma-emitting radionuclides and tritium. All concentrations of man-made gamma-emitters were less than their respective lower limits of detection (see Table 6-1). Tritium activity was detectable in the Harris Lake surface water at an annual average concentration of 7.8E+3 pCi/1. This value included an additional six samples taken in the Harris Lake. No tritium activity above the LLD of 1.2E+3 pCi/1 was detected in the surface water downstream at Lillington or in the Cape Pear at the control location.
UAOSUKEP>LFS(91HNPREO.REP 3-2
Figures 3-12 through 3-16 present the tritium activities in surface water during 1991.
3.5 Groundwater Groundwater samples are collected on site at SHNPP and analyzed for gamma-emitting radionuclides and tritium. Concentrations of these radionuclides were all less than their respective lower limits of detection during 1991.
3.6 Milk Of the 72 indicator and control milk samples taken and analyzed for 1991, none contained detectable concentrations of I-131 or other gamma-emitting radionuclides of plant effluent origin.
Figures 3-17 to 3-19 present graphical information on the I-131, 3.7 Bottom Sediment Sampling of bottom sediment is not a requirement of the plant technical specifica-tions; however, samples are collected near the discharge of the cooling tower blowdown pipe to serve as an indicator of plant liquid discharges. In 1991, three samples were collected. Activation products of cobalt and manganese were detected in each sample and fallout Cs-137 was also observed. Sb-125 was detected in a single sample at a concentration of 3.2 pCi/g. Co-60, Co-58, and Mn-54 were the predominate nuclides with average concentrations of 41.3, 11.2, and 2.5 pCi/g, respectively.
Figure 3-20 presents the results of these analyses.
3.8 Shoreline Sediment Shoreline sediment samples were collected (1) opposite the discharge structure and (2) near the main dam on three occasions in 1991. Detectable concentrations of Co-58 were observed in five of eight samples collected with an average concentration of 6.8E-2 pCi/g. Cs-137 occurred as a single value in one of eight samples at a concentration of 4.8E-2 pCi/g. These activities are only slightly UAOSUKEPK,FSE91HNPREO.REP 3-3
above their respective LLDs (see Table 6-1), and dose attributed to their presence was less than 0.001 mrem to the maximum exposed individual.
3.9 ~93 C In addition to milk sampling, a food product sampling program was maintained.
Six crop species were collected during a growing season which occurred in eight months of the year. The species selected were primarily broad-leaf vegetables most sensitive to direct fallout of airborne radionuclides. Crops sampled in 1991 included mustard greens, turnip greens, lettuce, cabbage, collards, and tomatoes.
Gamma spectrometry analyses of the food crops from indicator locations detected Cs-137 in 3 of 26 samples at an average concentration of 4.8E-2 pCi/g (wet).
Cs-137 was detected in 1 of 23 control samples. Since Cs-137 is frequently found in this environment from worldwide fallout and the observed concentrations were only slightly above the LLD of 1.3E-2 pCi/g, these concentrations are not considered to be the result of plant effluents.
3.10 External Radiation Ex osure Thermoluminescent dosimeters were used to monitor ambient radiation exposures in the plant environs. The average weekly dose rate from the indicator locations was 1 mrem/wk and 0.9 mrem/wk from the control station. The highest indicator location was 4.7 miles northeast of the plant and averaged 1.3 mrem/wk. This is the same location identified in 1989 and 1990 as having the highest value. The differences among these locations is attributed to variations in soils and local geology and are not the result of plant operations.
Comparison of the weekly dose rates for TLDs within three miles (inner ring) of the plant with those at approximately five miles (outer ring) is presented in Figure 3-21 and shows that the outer ring, ifanything, demonstrates a greater dose rate than does the inner ring. This presentation supports the interpretation that elevated dose rates are mostly a product of the local geology.
3.11 Com arison with Prep erational and 19900 erationalData Comparison of the 1991 environmental data with preoperational and 1990 operational data shows that, in most cases, the analyses involves activities ( LLD UAOSUUKPELPSE91HNPREO.REP 3-4
which does not allow statistical treatment. Conclusions and comparative statements are based on inspection and judgment.
Air Sam les With this exception, no I-131 has been detected in air samples collected from 1986 through 1991. I-131 was detected for a six-week period following the Chernobyl incident in April 1986.
Gross beta activities in air remained at 1.3B-2 pCi/m, a value similar to preoperational data and to the 1989-90 values.
As in previous years, no I-131 was detected in any of the 1991 drinking water samples. This has been the experience for the preoperational and operational period with the exception of 1986 when the fallout from Chernobyl was detected.
In 1991 as in previous years, no tritium was detected in the Lillington water supply. Tritium again was detectable in the SHNPP drinlmg water. Since this water supply is not a primary source of water for members of the general public, it is not considered a public water supply. The water is consumed by employees during working hours. During 1991, 11 of 12 monthly samples of the SHNPP drinking water contained measurable tritium at an average concentration of 5.3B+3 pCi/E an increase over the 2.8B+3 pCi/E seen in 1990. The maximum radiological exposure from this pathway is estimated at 0.1 mrem/yr.
~Fi h During 1991 as in 1989-90, no gamma-emitting radionuclides from plant operations were detected in any of the fish samples. Data from previous years has occasionally indicated the presence of Cs-137 and Mn-54.
Surface Water I-131 activities in samples of surface waters taken from the Harris Lake and the Cape Fear River, including a downstream location at Lillington, remained less than detectable as they have been since plant operations began in 1987.
UAOSUUU? PELFS(91HNPREO.REP 3-5
The average gross beta activities were slightly higher than the levels observed in 1985-90 (4.6 vs. 3.4 pCi/E) but less than the activity in the control samples.
Tritium activity in Harris Lake has increased measurably from the preoperational concentrations of less than 1.2E+3 pCi/1 to a 1991 average of 7.81E+3 pCi/l.
This is an increase over the 1990 value of 6.3E+3 pCi/1. Since the surface water tritium activity affects the activity in fish, it is estimated that the dose to the maximum exposed individual from consuming 21 kg of fish would be 0.01 mrem.
Groundwater No tritium or gamma-emitter activity has been observed over the period from 1985-1991.
Milk During 1991 as in aH past years with the exception of the Chernobyl period, no I-131 concentrations were detected in milk samples throughout the entire year.
There were also no other gamma-emitting radionuclides from plant operations detected in the milk.
Bottom Sediment In the preoperational period of 1985-1986, sediment samples collected from the lake bottom in the vicinity of the liquid discharge structure had shown low concentrations (0.3pCi/g) of Cs-137. During 1987 additional activation products, likely from plant operations, were detected beginning in July. As in 1990, Co-57; Co-58; Co-60; Mn-54; Cs-137; and Sb-125 were detected in bottom sediment samples in 1991. Inconsistent changes in nuclide activity occurred from 1990, i.e., Mn-54, Co-60, and Sb-125 increased; Co-58 decreased; Co-57 and Cs-137 were unchanged. These results are likely due to the difficulties of sampling bottom sediments. Due to the lake water shielding of radiation from these depositions, no radiological exposure to the public can be attributed to these radio nuclides.
UAOSUQKP>LFS>91HNPREO.REP 3-6
Shoreline Sediment Previous years'ampling indicated that in 1987 three radionuclides of possible plant origin-Co-58, Cs-137, and Mn-54were detected in shoreline sediment samples. In 1988 the concentrations of these radionuclides diminished. In 1989 none of the radionuclides were detected. During 1990, Co-58 and Cs-137 were detected in three of six samples at concentrations only slightly above their respective LLDs. In 1991, Co-58 was detected in five of eight samples at levels ranging from 2.08-2 to 1.28-1 pCi/g.
~Food Cro s Cs-137 was detected in 3 of 26 indicator samples at an average concentration of 4.9E-2 pCi/g in 1991. This value is somewhat above the Lower Limit of Detection of 1.9E-2 pCi/gm for this radionuclide and is slightly higher than values randomly observed in past years both at the indicator locations and at the control locations. In 1988, Cs-137 was detected at the control location at similar concentrations, but no gamma-emitting radionuclides occurred in the control samples for the years 1989 and 1990. The results for 1991 in food crops are considered consistent with normal fluctuations indigenous to the area and not indicative of adverse trends.
The 41 TLD locations surrounding the plant showed virtually no change in the average weekly ambient beta-gamma environment from 1985 through 1991. The location with the maximum average recorded exposure was the same as for 1989 and 1990 and is located 4.7 miles northeast of the plant. Inspection of Figure 3-21 indicates that no plant effluent effect is demonstrated in the measurements especially since the average of the inner ring of TLDs (closest to the plant) are less than the outer measurements.
UAOSUUKP)LFS591HNPREO.REP 3-7
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4.0 MISSED SAMPLES AND ANALYSES 4.1 Air Cartrid e and Air Particulates No sample at Location AC/AP-2 on July 15, 1991, due to tripped breaker.
No sample at Location AC/AP-5 on September 23, 1991, due to tripped breaker.
4.2 ~Fd C Food crops were not available at Location 54 in April, October, and November.
Food crops were not available at Location 55 in April and August.
4.3 TLDs TLD 25 was missing in the field due to vandalism for the first quarter.
TLD 34 was missing the field due to vandalism for the fourth quarter.
UAOSNREM.FS(91HNPREO.REP 4-1
5.0 LAND-USE CENSUS 5.1 Introduction Technical Specification 3/4.12.2 for the Shearon Harris Nuclear Power Plant requires that a land-use census be conducted annually around the site. The objective is to evaluate any changes in the use of land which could impact on the radiological health of members of the public. The census employs whatever approach provides the best results, i.e., door-to-door survey, aerial survey, or by consulting local agricultural authorities. The 1991 land-use census was conducted during June.
5.2 R~i Technical Specifications 3/4.12.2 requires that the survey be conducted:
- 1. Within a five-mile radius of the plant.
- 2. Annually during the growing season.
- 3. In each of the 16 compass sectors to identify the nearest:
- a. Milkanimal.
- b. Residence.
- c. Garden of greater than 500 square feet producing broad-leaf vegetation.
These requirements were supplemented with identification of the nearest meat animals in each of the 16 compass sectors.
5.3 Methods In accordance with this guidance, the 1991 land-use census was conducted using a door-to-door survey method. A standard questionnaire was used during an interview to record pertinent data.
UAOSNREPU.FS)91HNPREO.REP 5-1
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Resident and road locations were identified within a five-mile radius zone surrounding SHNPP using U.S. Geological Survey topographic quadrangle maps (7.5-minute series). These maps were revised in 1981, based on aerial photo-graphs, and represent recent locations of structures and roads in this locale.
Moncure, Cokesbury, Fuquay-Varina, Merry Oaks, New Hill, and Apex quadrangle maps were used. The maps were 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 compass direction.
The combined map was used to identify the nearest residences which were confirmed by field observation. The nearest garden, milk animal (cow or goat),
and meat animal (beef, hogs, or fowl) were located by inspection of fields and residential lots and by interviews with residents within the five-mile radius.
The survey was performed by CP&L in June during fair weather and good visibility. The survey started close to the plant in each sector and extended out to the five-mile perimeter. All roads within the five-mile zone were traveled.
Barns, small sheds, and pasture-like fields were observed as indicators of grazing livestock. These indicators were followed up with an interview of the property owner. In some cases when the owner was not home, a neighbor was interviewed to obtain the desired information. Ifthis was not possible, the property was either revisited at a later time or information was determined by visual inspection.
5.4 Results Table 5-1 summarizes the locations of the nearest residence, milk cow, milk goat, garden, and meat animal in each of the 16 compass sectors. The data gathered during the observation and the 35 recorded visitations resulted in the following observations:
- 1. Milkgoats are not located within the five-mile radius.
- 2. Milkcows are located in the N sector. This location is a commercial dairy that is currently part of the SHNPP Radiological Environmental Monitoring Program. Refer to Table 5-1.
UAOSMREPU.FS)91HNPREO.REP 5-2
- 3. All changes in garden locations resulted in increased distances from the plant.
- 4. Meat animals are found in 9 of the 16 compass sectors and are summarized in Table 5-2.
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TABLE 5-2 MEAT ANIMALTYPE AT NEAMNT LOCATION TO SHNPP BY SECTOR (1991)
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6.0 ANALYTICALPROCEDURF3 6.1 Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background Alpha/Beta Counting System. The LLD for air particulates is approximately 1.2E-3 pCi/m'or SHNPP samples. Air particulate samples are mounted in 2-inch stainless steel planchets and counted directly.
Gross beta activity in drinking and surface waters is determined by evaporating 1 liter of the sample and counting a planchet on a Tennelec Low-Background Alpha/Beta Counting System for 50 minutes. Typical LLD for gross beta is 2.0E+0 pCi/E.
6.2 Tritium Liquid samples requiring tritium analysis are first distilled. Five milliliters of the distillate are mixed with ten milliliters of liquid scintillation cocktail and counted in a liquid scintillation counter for 50 minutes. The LLD is approximately 1.2E+3 pCi/l.
6.3 Iodine-131 Iodine-131 airborne concentrations are analyzed by the intrinsic germanium spectrometry systems. The cartridges are placed on the detector, and each charcoal cartridge is counted individually with an approximate LLD of 1.4E-2 pCi/m'.
Iodine-131 in milk and drinking water is determined either by radiochemical or instrumental methods. Analysis involves the use of anion-exchange resins and either direct gamma analysis of the resin with a sodium iodide (NaI) well-detector or sodium hypochloride elution of the resin and organic extraction followed by precipitation as silver iodine. The precipitate is collected on a tared filter, dried, and counted on a low-background beta counter. The LLD using the NaI detector or the radiochemical separation is 0.4 pCi/E for milk and water.
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6.4 Gamma S ectromet Gamma spectrum analysis utilizes intrinsic germanium detectors with thin aluminum windows housed in steel and lead shields. The analyzer system is the Nuclear Data 6685. Table 6-1 summarizes LLD values derived from instrument sensitivity based upon a blank sample background, Airparticulate filter quarterly composites are placed in a Petri dish and analyzed directly.
Liquid samples, except milk, are boiled down to a small volume, transferred to a 250-ml polypropylene beaker with lid, and analyzed directly. One-liter milk samples are analyzed in a Marinelli beaker.
Shoreline and bottom sediments are dried, weighed, and then analyzed in a Marinelli beaker.
Food crop samples are weighed wet and analyzed in a Marinelli beaker.
Fish samples are cleaned, dressed, and placed in a Marinelli beaker for analysis.
6.5 Thermoluminescent Dosimet Each area monitoring station includes a TLD packet which is a polyethylene bag containing three calcium sulfate phosphors contained in a Panasonic UD-814 badge. The TLD is lighttight and the bag is weather-resistant.
Dosimeters are machine annealed before field placement. Following exposure in the field, each dosimeter is read utilizing a Panasonic TLD reader. This instrument integrates the light photons emitted from traps as the dosimeter is heated above 150'C. The photons from the lower-energy traps are automatically eliminated through a preheat cycle. Calibration is checked regularly using dosimeters irradiated to known doses. Prior to 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.
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6.6 EPA Laborato Intercom arison Pro ram The Radiochemistry Laboratory at the Harris Energy & Environmental Center in New Hill, North Carolina, provides radioanalytical services for CP&L's nuclear plant environmental surveillance 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 1991, 54 analyses were completed on 20 samples representing three major environmental media (i.e., water, milk, air filters). Data on the known activities and the normalized standard deviations for the 54 analyses have been received from EPA. A comparison of the average of our reported values with the EPA known activity and its normalized standard deviation is provided below:
Standard Deviation From Known Activity Percent of Analyses M 1 Standard Deviation 63
~ 2 Standard Deviation 93 6 3 Standard Deviation 97 One of 54 samples exceeded the three sigma action level. A gross beta analysis of a water sample received in May 1991 fell outside the 30 limit. Independent verification of the sample analyses was accomplished by reanalysis. This result was well within the known activity limits and indicated a contamination problem from the beakers or planchets used in the initial sample analysis, The potential sources of contamination were discarded.
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TABLE 6-1 TYPICAL LOWER LIMITS OF DETECTION (A PRIOR/
GAhBCA SPECTROMETRY Cr-51 18 pCi/E Mn-54 3 Co-58 3 Fe-59 7 Co-60 4 Zn-65 8 Nb-95 3 Zr-95 7 I-131 0 4Q Cs-134 4 Cs-137 3 Ba-La-140 6 Other Expected 1 to 111 Gamma Emitters p<.':<,:< p<<:.";<:::: X<< < <NN:<::."<: <:<gje'::: << <$ 'j<."j6;;i;".;;:Sp< <<.y'N
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Cs-134 6 Cs-137 5 Ba-La-140 11 Other Ex ected Gamma Emitters 3 to 44
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GAMMA SPECTROMETRY'r-51 pCi/kg Mn-54 44 Co-57 31 Co-58 37 Fe-59, 79 Co-60 37'5 Nb-95 Zr-95 Cs-137
's-134 Emitters'69'3 .107 74 Other Ex ected Gamma 38 to 2804 Cr-51 180 pCi/kg Mn-54 34 Co-58 37.
Fe-59 87'2 Co-60 Zn-65 I-131 ', "
23 Cs-134 38 Cs-137 34 Other Ex ected Gamma Emitters 16 to 1064 Cr-51 121 pCi/kg Mn-54 16 Co-58 .15 Co-60 19 I-131 15 Cs-134 17 '7 Cs-137 Other Expected Gamma Emitters 13 to 450 h
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