ML18010A611

Radiological Environ Operating Rept 1991,Harris Nuclear Project.

ML18010A611
Person / Time
Site:	Harris
Issue date:	12/31/1991
From:	Cahill D, Minard K CAROLINA POWER & LIGHT CO.
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ML18010A609	List: ML18010A608 ML18010A611 ML18010A613 ML18010A614
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NUDOCS 9204280358
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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 RADIOLOGICAL ENVIRONMENTAL OPERATING 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.............................

~.....L 1st Of FigureS~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~L ist 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..................................

3-2.4 Surface Water......................................

3 3.5 Groundwater 3-2 3-3 3 o6 Milk~~~~~~~~~~~~~~~~~~~~~~3-3 3.7 Bottom Sediment....................................

3.8 Shoreline Sediment 3-3 3-3 3.9 Food Crops 3.10 External Radiation Exposure..3.11 Comparison with Preoperational and 1990 Operational Data o 3-4 3-4 3-4 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 Ds~~~~~~~~~~~~~~TL~~~~~~~~~~~~~~~~~~~~~~~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 ANALYTICAL PROCEDURES

..............................

6-1 6.1 Gloss Beta~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~6-1 6 o~.2 ir1t1um o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~6 1 6 3 Iodme 131...........................

~............

6 1 6.4 Gamma Spectrometry

.............

6.5 Thermoluminescent Dosimetry 6.6 BPA Laboratory Intercomparison Program 6,7'ower Limits of Detection..........

~~~~~~~~~~~~~~~~~~~~6 2~~6-3 6-4~~~~~~~~~~~~~~~~~~~~6 2 U AOSUUKM.PSE91HNPREO.REP LIST OF FIGURIM~Pa e~~~~0~~~~~~~~~~~~~~~~~~~~~~~2 7 F~i>re 2-1 Shearon Harris Nuclear Power Plant-Radiological Environmental Sampling Points 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:;:::;:::::Ra'dio'iii'iclide'.:::::':.:

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Harris Lake Surface Water Fish SHNPP Drinking Water Harris Lake Shoreline Sediment Harris Lake Bottom Sediment H-3 H-3 H-3 Co-58 Cs-137 Mn-54 Co-57 Co-58 Co-60 Cs-137 Sb-125 7.81 B+3 pCi/E (24/24)See above 5.27 B+3 pCi/E (11/12)6.85E-2pCi/g (5/8)4.798-2pCi/g (1/8)2.52E+0 pCi/g (3/3)2.54B-1 pCi/g (3/3)1.12B+1 pCi/g (3/3)4.13B+1 pCi/g (3/3)3.70E-1 pCi/g (3/3)3.25E+0 pCi/g (1/3)No ingestion pathway.No dose calculated.

.01 (T.B.).10 (T.B)1.8E-4 1.3E-4 No dose calcu-lated as water shielding elimi-nates dose at surface.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 RADIOLOGICAL 3PPGRONMXNTAL MO RING PROGRAM DATA

SUMMARY

Shearon Harris Nuclear Power Plant Wake County, North Carolina Docket Number: STN 50-400 Calendar Year: 1991 Air Cartridge (pCi/m)1-131 310(3)1.4F 2 All less than LLD All less than LLD All less than LLD Air Patticulate (pCi/m)Gross Beta 310(3)1.2E-3 1.33E-2 (259/259)4.22F 3-3.60E-2 SR 1912 3.4 miles SSW 1.51E-2 (52/52)7.58F 3-3.60F 2 1.26E-2 (51/51)5.80E-3-1.99E-2 Gamma Refer to All less than LLD Table 6-1 All less than LLD All less than LLD Drinking Water (PCi/1)1-131 156 4.0E-1 All less than LLD All less than LLD All less than LLD Gross Beta 36 2.0E+0 4.34E+0 (24/24)2.32E+0-8.16E+0 Li!!ington Cape Fear River 17 miles SSE 5.55E+0 (12/12)2.94E+0-8.16E+0 6.18E+0 (12/12)2.59E+0-1.17E+1 Gamma 36 Refer to Table 6-1 All less than LLD All less than LLD All less than LLD Tritium 36(5)1.2E+3 5.27E+3 (ll/24)SHNPP site 5.27E+3 (11/12)All less than LLD 3.77E+3-6.96E+3 0.1 mile SSW 3.77E+3-6.96E+3 Bottom-Feeders (pCi/g, wet)Refer to All less than LLD All less than LLD AH less than LLD Table 6-1 FreeSwimmers (pCi/g, wet)Refer to Table 6-1 All less than LLD All less than LLD All less than LLD U:LOSVREM.FS$

1HNPREO

TABLE 1 RADIOLOGICAL 1<2VVIRONMENTAL MOb G PROGRAM DATA

SUMMARY

Shearon Harris Nuclear Power Plant Wake County, North Carolina Docket Number: STN 50-400 Calendar Year: 1991 Food Crop (pCi/g, wet)Gamma 49(3)Cs-137 4.86F 2 (3/26)SR 1167 4.86F 2 (3/14)1.79E-2 (1/23)1.7F 2 4.61E-2-5.35E-2 1.7 miles NNW 4.61E-2-5.35E-2 Single Value Groundwater (pCi/1)Gamma 20 Refer to Table 6-1 All less than LLD All less than LLD All less than LLD Tritium 20 ICE+3 All less than LLD All less than LLD All less than LLD Milk (pCi/1)1-131 72 4.0F 1 All less than LLD All less than LLD All less than LLD Gamma 72 Refer to All less than LLD Table 6-1 All less than LLD All less than LLD Bottom Sediments()(pCi/g, dry)Gamma 3 Mn-54 Co-57 2.52E+0 (3/3)Harris Lake 2.52E+0 (3/3)4.4F 2 2.07E+0-3.13E+0 3.8 miles S 2.07E+0-3.13E+0 3.1E-2 2.54F 1 (3/3)Hams Lake 2.54E-1 (3/3)1.31E-1-4.31E-1 3.8 miles S 1.31E-1-4.31E-1 No control No control Co-58 3.7E-2 1.12E+1 (3/3)Hams Lake 1.12E+1 (3/3)3.10E+0-2.07E+1 3.8 miles S 3.10E+0-2.07E+1 No control 3.7E-2 4.13E+1 (3/3)1.52E+1-8.26E+1 Hams Lake 4.13E+1 (3/3)3.8 miles S 1.52E+1-8.26E+1 No control Cs-137 5.3F 2 3.70F 1 (3/3)Hams Lake 3.70E-1 (2/3)2.29E-1-5.61E-1 3.8 miles S 2.29F 1-5.61E-1 No control Sb-125 1.2F 1 3.25E+0 (I/3)Single Value Hams Lake 3.8 miles S 3.25E+0 (1/3)Single Value No control U:LOSUQKM.FS't91HNPREO

TABLE 1 RADIOLOGICAL EN'VIRONMENTAL MO t.)G PROGRAM DATA

SUMMARY

Shearon Harris Nuclear Power Plant Wake County, North Carolina Docket Number: STN 50-400 Calendar Year: 1991 Shoreline Sediments ipCi/g, dr))Gamma 8 Co-58 3.7E-2 6.85F 2 (5/8)2.04F 2-1.20F I Harris Lake 8.99E-2 l2/4)3.8 miles S 5.98E-2-1.20E-I No control Cs-137 5.3F 2 4.79E.2 (I/8)Single Value Harris Lake 3.8 miles S 4.79E-2 (I/4)Single Value No control Surface Water(5)(6)

('P CI/I)1-131 104 4.0E-I All less than LLD All less than LLD All less than LLD Gross Beta 36 2.0E+0 4.58E+0 (24/24)Lillington 5.55E+0 (12/12)6.18E+0 (12/12)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 36 Refer to Table 6-1 AH less than LLD All less than LLD All less than LLD Direct Radiation (mR/week)Tritium 48 TLD 162()1.2E+3 7.81E+3 (24/36)Harris Lake 8.09E+3 (4/4)All less than LLD 5.48E+3-1.16E+4 3.8 miles S 6.25E+3-1.16E+4 9.60E-I (158/158)Int SR1149 and 1.33E+0 (4/4)9.00E-I (4/4)7.00E-I-1.40E+0 US I 4.7 miles 1.20E+0-1.40E+0 9.00E-I-9.00E-I 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 will yield a net count above system background which will be 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 Milk Samples 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 RADIOLOGICAL F<2PGRO MONITORING PROGRAM SHEARON HARIUS NUCLEAR POWER PLANT Air Cartridge (AC)1-2.5 miles N 2-1.5 miles NNE 4-3.2 miles NNE 5->12 miles NW-Pittsboro (Control)'6-4.6 miles S 47-3.4 miles SSW Continuous operating sam-pling with sample collection at least once per seven days or as required by dust loading Weekly 30,000 cu.It (900 cu m).',".ll,::,i':.'!~Si' l~rii"A~iii~f':

I-131 (charcoal cartridge)

Air Particulate (AP)Sediment from Shoreline SS Bottom Sediment'D 1-2.5 miles N 2-1.5 miles NNE 4-32 miles NNE 5->12 miles NW-Pittsboro (Control)'6-4.6 miles S 47-3.4 miles SSW 26-4.6 miles S 41-3.8 miles S 52-3.8 miles S Continuous operating sam-pling with sample collection at least onco per seven days or as required by dust loading Weekly 30,000 cu.It.(900 cu m)Semiannually 500g Quarterly Co ositc Seiniannually 500g Gross Beta'amma Isotopic'amma Isotopic'amma Isotopic'rinking Water (DW)Groundwater (GW)'ood Products (FC)38-6.1 miles WSW (Control)'0-17 mi!es SSE-Lillington 51-0.1 mile SSW-SHNPP Site 39-0.7 mile SSW 57-0.4 mile SSW 58-0.5 mila WSW 59-0.5 milo NNE 60-0.5 mile ESE 44-Sita varies within Hams Lake 45-Sita varies in Cape Fear River above Buckhorn Dam Contro 54-1.7 miles NNE-Wilkins or Moms 55-1.7 miles NNW-L.L.Goodwin 5->12 miles WNW, NW(or NNW-Pittsboro Control During growing season when inilk sampling is not per formed Weekly Monthly Coinpositc Quarterly Seiniannually Monthly 8 liters 8 liters 1 kg each FreaSwimmers Bottom-Feeders 500g I-131 Gamma Isotopic'ritium Gross Beta Tritium Gamma Isotopic'amma Isotopic'n ediblo portion for each Gamma Isotopic'ilk (MK)42-7.5 miles SSE-Maple Knoll Dairy 43-2.2 miles N-Goodwin's Dairy 5->12 miles NW-Strowd's Dairy Contin When animals on pasture Semimonthly 8 liters I-131 Gamma Isotopic'urface Water (SW)'6-4.6 miles S 38-6.1 miles WSW (Control)'0-17 miles SSE-Lillington Weekly Monthly Composite 8 liters I-131 Gamma Isotopic'ritium Gross Beta U:tOSUtREPtLFSt91HNPREO.REP TAB RADIOLOGICAL ENVIRONMENT MONITORING PROGRAM SHEARON HARRIS NUCLEAR POWER PLANT Direct Radiation Monitors (TLD)YLDs 1-2.5 miles N 2-1.5 miles NNE 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 Continuous measurement with an integrated readout at least once per quarter f:::,,:~Ci-" le'Ce'*.,",::;:"':

Not applicable

",:".i';:.R~im Te Aiiiil".":".:;:",,"':"" Ganuna Dose 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 the'ompositing period (e.g., monthly).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 tres ITIS OWI N!SOO Ol 0 j I 0*OCTVT CNJRTL*, 34~*I'NIJ 64 Figure 2-2.Shearon Harris Nuclear Power Plant RADIOLOGICAL ENVIRONMENTAL SAMPLING POINTS 64~IJ ISOC~giles!905/a Q I RE I ere g//IISS No II 19 5 II JS II J7)F sip!)VeO f+IIS IIJS I II55 0 I 0 Z 4 I I (Iel srNNO>0 VI err'I'"her ISN oy PTNNV Ro'Sv)J tl!Sny OO'!SIC///Mile onsal lto.+'!IRS 21 II5t 22"35'ISC I I S prig I.~4 4dfd~f elf J l5 I r SVNSET OJ LAKE Rrt I!95 SASS LAKE 5 NITN I er<O o 36Ste Coi!SIC 42 0!N CR RNNT RO I SS 26~Miles//42 CROSSROJO HARRIS F'ESc'GIr , 24 tile 23 Bu 25 Dun litt I ltd an'RVL LO~+4)'>>I JOS Lft I,N o>~0 ans sroads IR ROC MLS"o IS!I,\id%I II I I~(eI flfrlil On 4 II Rr 4 SSTTS QO j l>>',-'I'.'7'It~J 1 401 FUQ, Y YAR IAA I I f Z Iee yd I I~I~I le 55 otr oV C.!5/I J I RO, ltrr~rIA, OOr~/OO/I IRIS'ig MI)es Sow 0 42 I VorOR 0 Itto'RROLO.I~le VV NO Ad+CJ drerr I~lt r J I'ear 0 SLCT dor+o IICS Jvtere IJOr.so 40~co yo lair I455 4ORT~I~I IO+IJ CIO fr i I Cape ar ot 4 40 LILLINGTON IJIS 2-7 e Figure 2-2 Shearon Harris Nuclear Power Plant RADIOLOGlCAL ENVIRONMENTAL SAMPLING POlNTS o'IENDSHIP NEW HILL 1 I I I 1 I 4\I 20 SON SAL 43 49 I 1149 54 2~~1152 MERRY OAKS 15 16 141 EXCLUSION BOUNOARY I I I I I I I I I/11 12 60 58~39 10 9 r'05 r 0 1115 I p I I r/27 47 HARRIS lAKE 5 1 26 r~~1915 lg 1 I I Q~~1116 I I\\Lsr SCALE LMlas)I r r I 1 1 I 1552 1407 2-8 7 I (<<(Or 0>>D~RADIOLOGICAL ENVIRONME trcc 25('VI O/(745"l Figure 2-3 Shearon Harris Nuclear Power Plant NTAL SAMPLING POINTS 64 I 4~I (~I (<'.c,-D eo DROO>969)I5~<<<lr<I~~rr h~*.4~r 1/(945 a Crr RC(t l977 0 RO lTTSBORO Il ins lsf ads (a<t (945+RO l97 Iroo l94((907 31 90d Gcl 7'+o'2 3Q'l II<<rd S(tl(Oa OC (~/~Q I Rt'/(~at'((DRr I(o~//I onsal It(2*Ro I I to(W DO>>(tt RO z tSOO l IS02 r/T r~gileS 046+tl z Gg ucc t(46 F'4 T~4 I(66 z (o RO SR(5>><((49+e v 4o TG O ter Z(2 (6<F55 (ro od (ct6" (ltd Black o r (46(+(44S Crrc>C(tct5 RO~500 PCS 502 root co r425 (cS ror(Soc 29 a 4~r>>ttc (9(6 4+(9I6 28 a((an<c>>SCC>>Y RDr Cot I i (9(2 27 42 SS cr (les But(,0'I/1 oa l 0 C 14(5 lC ct Crt (4(5 (4P (4 4 5~'" (Oot (500 I I r<505 42 4 C r rcr (559 G i(a ao (5(O O74 0/V'/(4<d Colon 40 pro(>>CR(tr<4 l557 C C<(X I (509I541 oP p<<o+" (5 4/I~/RO Itrr lg n'l(les CII r$44<hhlsn~n~Sr 7 (565 OO'4 42 2-9 Or(

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AP, AC, TL AP AC TL TL i<'Stition'No!!i<

<i%":Refo'i"to"Fl

"'r'e-'.Yi 29 30 31Ã'::Reit lo:<SÃ4.TL TL TL 10 12 13 14 15 16 17 18 19 20 21 26 27 28 2-2 2-1 2-1, 2-2 2-1 2-2 2-2.2-3 2-2 2-3 AP AC TL AP, AC, MK, FC, TL TL TL TL TL TL TL TL TL TL TL TL TL TL TL TL TL TL TL TL AP, AC, SW, SS TL TL TL 32 33 34 35 37 38 39 41 42 43 44 45 47 48 49 50 51 52 53 54 55 56 57-60 2-1 2-1 2-1 2-1 2-1 2-2 2-1 2-2 2-3 2-2 TL TL TL TL TL TL SW DW GW SW DW SS FH FH AP AC TL TL TL DW SD TL FC FC TL GWAC Air Cartridge AP Air Particulate SD Bottom Sediment FC.Food Crop.FH Fish GW Groundwater MX Milk SW Surface Water DW Drinking Water TL TLD SS Shoreline Sediment UAOSUKEP>LFS(91HNPREO.REP 2-10 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, if anything, 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.

MilkDuring 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-54-were 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 P C l 0.15 CP&L ENVlRONMENTAL SURVElLLANCE GROSS BETA ACTIVITY FOR AIR PARTICULATE SAMPLES PLANT=HNPP SAMPLE POINT=0001 P E o.Io R G U M 00 E 0.05 T E R n 0.00 SAMPLE DATES SOLID LINE FOR SAMPLE STATION.BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=0.02 ISOTOPIC ANALYSIS REQUIRED ABOVE 0.10 II' P C I 0.15 CPM.ENVIRONMENTAL SURVEILLANCE GROSS BETA ACTIVITY FOR AIR PARTICULATE SAMPLES PLANT=HNPP SAMPLE POINT=0002 P E o.Io R C U 0.05 T E R n 0.00 0 1 0 E C 9 0 0 0 1 1 J J U U N 1.9 9 I 1 SAMPLE DATES SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=0.02 ISOTOPIC ANALYSIS REQUIRED ABOVE 0.10 p~

P C I 0.15 CP&L ENVIRONMENTAL SURVEILLANCE GROSS BETA ACTIVITY FOR AIR PARTICULATE SAMPLES PLANT=HNPP SAMPLE POINT=0004 P E o.Io R C U M 0.05 T E R 0.00 0 I 0 E C 9 0 0-1 A P R 9 1 SAMPLE DATES 0-1 A U 0 9 1 ,.0 1-S E P 9 1 0 I 0 C T 9 1 0 1 H 0 ,V 9 1 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=0.02 ISOTOPIC ANALYSIS REQUIRED ABOVE 0.10 I g P C I 0.15 CPEL ENVIRONMENTAL SURVEILlANCE GROSS BETA ACTIVITY FOR AIR PARTICULATE SAMPLES PLANT=HNPP SAMPLE POINT=0026 P E-o.Io R C U M p 0.05 T E R 0.00 y r 0 1'll h R 9 1 0 0 I 1 J U U N L 9 9 1 1 SAMPLE DATES 0 0 I h S U=E G P 9 9 1 1 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=0.02 ISOTOPIC ANALYSIS REQUIRED ABOVE 0.10 P C I 0.IS CPEL ENVIRONMENTAL SURVEILLANCE GROSS BETA ACTIVITY FOR AIR PARTICULATE SAMPLES PLANT=HNPP SAMPLE POINT=0047 P E R C U 0.05 T E R 0.00 0.0 1 1 J F h E N 8 9 9 1 1 SAMPIE DATES 0 1 S E P 9 1 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=0.02 ISOTOPIC ANALYSIS REQUIRED ABOVE 0.10 20.00 CPQ ENVlRONMENTAL SURVEILlANCE GROSS BETA ACTIVITY FOR DRINKING WATER SAMPLES PLANT=HNPP SAMPLE POINT=0040 18.DD P C 16.00 I 14.00 P E I2 F 00 R 1D.DD L 8.00 T E 6.00 R 4.00 y~r 2.00 0.00 SAMPLE DATES=0 0 1 1 0 J A C II 9 9 1 2 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=4.84

20.00 CPM ENVlRONMENTAL SURVEILlANCE GROSS BETA ACTIVITY FOR DRINKING WATER SAMPLES PLANT=HNPP SAMPLE POINT=0051 I S.00 P Q 16.00 I 14.00 P 12.00 R 10.00 I T R R 6.DD 6.00 4.00 2.DD 0.00 0.1 ll A Y 9 1 0 1 J U-1.~9 1 SAMPLE DATES 0.1 J A II 9 2 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=4.84

~V 7500.00 CP&L ENVIRONMENTAL SURVEILLANCE TRITIUM ACTIVITY FOR DRINKING WATER SAMPLES PLANT=HNPP SAMPLE POINT=0040 P Q 6000.00 I P E<500.00 R L 3000.00 T (A F R 1500.00 A OO 0.00 0 1 0 E C 9 0 0 0 1 1 J J U U H 1.9 9 1 1 SAMPLE DATE 0 1~0 C 9 1 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION SAMPLE DATA MAY OVERLAY CONTROL DATA H

7500.00 CPM ENNRONMENTAL SURVEILLANCE TRITIUM ACTIVITY FOR DRINKING WATER SAMPLES PLANT=HNPP SAMPLE POINT=0051 P Q 6000.00 I P E 4500.00 R L 3000.00 T a E R 1500.00 0.00 SAMPLE DATE 0 I A U G 9 I SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION SAMPLE DATA MAY OVERLAY CONTROL DATA 20.00 CP&L ENVIRONMENTAL SURVEILLANCE GROSS BETA ACTIVITY FOR SURFACE WATER SAMPLES PLANT=HNPP SAMPLE POINT=0026 18.00 P C 16..00 I 1$.00 P E 12.00 R 10.00 L 8.00 T 6.00 R 4.00 2.00 0.00 0 I 0 E 0 9.0 0 0 I J J V U N 1.9 9 I 1 0 0 1 I N 0 0 E V C 9.9 I 1 SAMPLE DATES SOLID LINE FOR SAMPLE STATION.BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=3.55 e

20.00 CP&L ENVIRONMENTAL SURVEILLANCE GROSS BETA ACTIVITY FOR SURFACE WATER SAMPLES PLANT=HNPP SAMPLE POINT=0040 18.00 P Q 16.00 I 14.00 P E 12 F 00 10.00 L 8.00 T E 6.00 R 4.00 2.00 0.00 0 0 1 1 0 J E A C II 9 9 0 0 0 1 1 J J V U II I.9 9 1 1 SAMPLE DATES SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION PRE-OP AVERAGE=3.55

15000.0 CPM ENVIRONMENTAL SURVEILLANCE TRITIUM ACTIVITY FOR SURFACE WATER SAMPLES PLANT=HNPP.

SAMPLE PO)NT=0026 P C 12000.0)P E.9000.00 R L)6000.00 T R 3000.00 0.00 SAMPLE DATE SOLID LINE FOR SAMPLE STATiON BROKEN LINE FOR CONTROL STATION SAMPLE DATA MAY OVERLAY CONTROL DATA

7500.00 CPEL ENVlRONMENTAL SURVEILlANCE TRITIUM ACTIVITY FOR SURFACE WATER SAMPLES PLANT=HNPP SAMPLE POINT=0040 P C 6000.00 I P E 4500.00 R L 3000.00 T o E R 1500.00 0.00 SAMPLE DATE 0 0 1'0 I1 C'0 T V 9 9 1 1 0 1 J A N 9 2 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION SAMPLE DATA MAY OVERLAY CONTROL DATA

15000.0 CPM ENVIRONMENTAI SURYEILIANCE TRITIUM ACTIVITY FOR SURFACE WATER SAMPLES PLANT=HNPP SAMPLE POINT=026S P Q 12000.0 I P 9000.00 R I 6DDD.DD T E R 3000.00 0.00 0 0 1 1 J f A-E II 8 9 9 1 1 0=0 1 1 J A U U 1.C 9 9 1 1 SAMPLE DATE 0 0 1 1 S 0 E C P T 9 9 1 1 0 0 0 1 1 1 II 0 J 0 E A V C II 9 9 9 1 1 2 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION SAMPLE DATA MAY OVERLAY CONTROL DATA

i.

I5000.0 CP&L ENVIRONMENTAL SURVEILlANCE TRITIUM ACTIVITY FOR SURFACE WATER SAMPLES PLANT=HNPP SAMPLE POINT=041 S P.C I2000.0 I P E 9000.00 R L 6000.00 T E R 3000.00 0.00 0 I 0 E C 9 0 SAMPLE DATE SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION SAMPLE DATA MAY OVERLAY CONTROL DATA

,I 15000.0 CPM ENVIRONMENTAL SURVEILLANCE TRITIUM ACTIVITY FOR SURFACE WATER SAMPLES PLANT=HNPP SAMPLE POINT=052S P Cl 12000.0 I P E 9000.00 R L 6000.00 I T R 3000.00 0.00 0 1 0 E C 9 0 SAMPLE DATE SOI ID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION SAMPLE DATA MAY OVERLAY CONTROL DATA 10.00 CPM ENVIRONMENTAL SURVEILIANCE IODINE-131 ACTIVITY FOR MILK SAMPLES PLANT=HNPP POINT=0005 9.00 P C S.00 I 7.00 P F 6.00 R.5.00 L 4.00 M E 3.00 R 2.00 1.00 0.00 STATION'0005'S THE CONTROL POINT 0 1 J Ij.L 9 1 SAMPLE DATE SYIIBOi (LiD 0 1 N 0 V 9.1 REPORTING LEVEL IS 3.0 I~

10.00 CP&L ENVIRONMENTAL SURVEILLANCE IODINE=131 ACTIVITY FOR MILK SAMPLES PLANT=HNPP POINT=0042 P C 8.00 I 7.00 P 6.00 R 5.00 L<.00 T 5.00 R 2.00 1.00 0.00 0 0 1 1 f'E II-B 9 9 1 1 0 0 1 1 A.II P A R Y 9 9 1 1 SAMPLE DATE SYIIBOL<LLD STATION'0005'S THE CONTROL POINT REPORTING LEVEL IS 3.0 10.00 CPM ENVIRONMEMTAl SURVEILLANCE IODINE-131 ACTIVITY FOR MILK SAMPLES PLANT=HNPP POINT=0043 9.00 P C 8.00 I 7.00 P E 6.00 R 5.00 L 4.00 T cr E 500 R 2.00 1.00 0.00 0 0 1 I f M E A B R 9 9 I I 0 0 0 1 I I M J J A-U U Y N 1.9 9 9 I 1 1 SAMPLE DATE STIIBOL<LED 0 0 I I A S U f.G P 9 9 1 1 0 0 1 1 N 0 0-E V C 9 9 1 1 STATION'0005'S THE CONTROL POINT REPORTING LEVEL IS 3.0 0

CPEL ENVIRONMENTAL SURVEILLANCE GAMMA ACTIVITY FOR BOTTOM SEDIMENT SAMPLES PLANT=HNPP SAMPLE POINT=0052 120.00 110.00 IOO.OO C 9O.OO so.oo E R vo.oo 6o.oo R A so.oo M 40.00 D R ao.oo Y 20.00 10.00 0.00 ISJAN91 14LIAY91 05NOV91 SAMPLE DATE I sotol I: CZZZI co-sz tREERH co-ss tZHB co-6o 2K's-I sr MK2 II<<-54~~st-125 SOLID LINE FOR SAMPLE STATION BROKEN LINE FOR CONTROL STATION SAMPLE DATA MAY OVERLAY CONTROL DATA V

2.0000 CP&L ENVIRONMENTAL SURVEILLANCE TLD AVERAGES FOR INNER AND OUTER RING LOCATIONS PLANT=HNPP 1.8000 1.8000 1.4000 I L L 1.2000 I FI l.0000 M 0.8000 E R 0.8000 W 0.4000 E O.2OOO 0.0000 INNER OUTER INNER OUTER INNER OUTER INNER OUTER I5EEB91 I 5IIAY91 15AUG91 I5NOV91 SAMPLE DATE OATE AVERAGE(1983

-1 987)=0.9786

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.Milk animal.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 MethodsIn 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 i~I f~)'L 8 a=ylI 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.

If this 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.Milk goats are not located within the five-mile radius.2.Milk cows 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.U AOSUQKP>LFS(91HNPREO.REP 5-3 h I I I I I:.I I I H"1 P s>C,'l I E l'I'I I I lj t)I I g~

TABLE 5-1 DISTANCE TO THE NEARFST SPECIAL LOCATIONS FROM THE SHEARON HARRIS NUCLEAR POWER PLANT (MILES).,:.;::;'::::Re'Side'rice',:',:

<<,Milk::::'Aiik'iial.'i:

II';.'

,',,',.Gar'Beii':::."':::::

::::m'Meat':'Ai'iiiiial'":,:

~ect"ir";:;:::,::Excliisioii:':

ou'idaii,:::,I:

i::::;~10:',;::I 1~199:;:.:'QP0 O'I:: N 1.32 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 1.33 1.8 1.8 4.6 1.7 1.7 3.5 3.5 1.33 1.33 2.3 2.3 2.0 3.6 2.3 2.3 3.6 3.8 2.3 2.3 1.33 1.9 1.9 4.7 4.7 2,2 2.2 1.33 2.7 2.7 2.7 4.4 44 4.4 1.33 4.3 4.3 4.3 4.4 4.3 4.3 SSB SSW SW WSW W 1.33 1.36 1.33 1.33 1.33 1.33 4.4 4.4 3.9 3.9 2.8 2.8 4.3 4.3 2.8 2.8 4.6 3.9 3.9 2.8 2.8 4.3 4.3 2.9 2.9 4.3 2.9 2.9 WNW 1.33 2.1 2.1 2.1 2.9 3.6 1.26 2.1 2.1 3.8 3.8 3.8 3'1.26 1.5 1.5 1.7 1.7 1.7 1.7 Distance estimates are 1 0.1 mile except at exclusion boundary.UAOSUUKPLLPSE91HNPREO.REP 5-4 4I-I ii II~4 k)J 4 P(l jl>I I't ji li I TABLE 5-2 MEAT ANIMAL TYPE AT NEAMNT LOCATION TO SHNPP BY SECTOR (1991),':::Sector',::

N 2.2 3.5 2.3 Beef, Hogs, Chickens Chickens Beef SSH 2.2 4.4 4.3 Chickens Chickens Chickens SSW SW WSW 2.9 Chickens 3.8 1.7 Hogs, Chickens Beef UAOSUKEPLLFSE91HNPREO.REP 5-5

]b b'4~bl[b bb b I'~~II+~b I b\,.III b~I b~0 ,~~~~~I.I'bbb b'll~b" b Ib b~I 6.0 ANALYTICAL PROCEDURF3 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.U:LOSULRENLFSE91HNPREO.REP 6-1

'/I,'I"'*r'~)II~rrr ll)Il~lf I'r P tl/r~l~gr rr n ,~W lr) 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, Air particulate 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.UAOSUUKRLFSE91HNPREO.REP 6-2 JlI>>r I>>~l)'II I I=~V>>>>J~Q"/j>>ff'ICI~>>IC>>')I'flf>>~4>>~>>~,>>,)IVO 0 fi I'":3>tt I~I'~>>I'4>>>>>>7,')>>fJ

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The exposure reported is corrected for exposure received in transit and during storage through the use of control dosimeters.

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~2 Standard Deviation 63 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.

UAOSUKBPELFSE91HNPREO.REP 6-3 I~P 5"It'P I I'~, t I lt I('I PJ ll>l Iig$)4'll 1 1li)I g~~,i'r I gati!(/)>*II Il I, r,'l It tl l(I'I I I I'~i II tlf fit 1 6.7 Lower Limits of Detection All samples analyzed met the LLD required by Technical Specification 4.12.1 and Table 4.12.1-1.TABLE 6-1 TYPICAL LOWER LIMITS OF DETECTION (A PRIOR/GAhBCA SPECTROMETRY Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-La-140 Other Expected Gamma Emitters 18 pCi/E 3 3 7 4 8 3 7 0 4Q 4 3 6 1 to 111 Cs-134 Cs-137 Ba-La-140 Other Ex ected Gamma Emitters p<.':<,:<p<<:.";<::::

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<:,I'ig<v,LD (g<,:>;"<g@4g".:;g4M+h 0,001 pCi/m'.001 0.001 0.001 to 0.012 Cr-51 Mn-54 Co-58 Co-60 I-131 Cs-134 Cs-137 Ba-La-140 Other Ex ected Gamma Emitters 31 pCi/4 5 5 7, 0 4~6 5 11 3 to 44*NaI well crystal analysis of resin concentrates of samples.UAOSNRENLFS<91HNPREO.RHP 6-4 II I d I'.

TABLE 6-1 TYPICAL LOWER LIMITS OF DETECTION (A PRIOR/GAMMA SPECTROMETRY'r-51 Mn-54 Co-57 Co-58 Fe-59, Co-60 Nb-95 Zr-95's-134 Cs-137 Other Ex ected Gamma Emitters'69 pCi/kg" 44 31 37 79 37'5.107 74'3 38 to 2804 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 I-131', Cs-134 Cs-137 Other Ex ected Gamma Emitters 180 pCi/kg 34 37.87'2" 23 38 34 16 to 1064 Cr-51 Mn-54 Co-58 Co-60 I-131 Cs-134 Cs-137 Other Expected Gamma Emitters h 121 pCi/kg 16.15 19 15 17'7 13 to 450U AOSUUKPQ.FSE91HNPREO.REP 6-5 y r,