ML18005A866

Radiological Environ Operating Rept,1988.

ML18005A866
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Site:	Harris
Issue date:	12/31/1988
From:	Cahill D, Padgett J CAROLINA POWER & LIGHT CO.
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NUDOCS 8905020143
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Text

January 1, 1988 December 31, 1988 5

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HARRIS NUCLEAR PROJECT CAROLINA POWER 8 LIGHT COMPANY 89'05020i43 89'0426 PDR ADOCK 05000400 R PDC

Harris Energy 5 Environmental Center Carolina Power 5 Light Company New Hill, North Carolina RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR THE HARRIS NUCLEAR PROJECT JANUARY 1 THROUGH DECEMBER 31, 1988 Reviewed by:

Daniel F. Cahill Technical Specialist - Health Physics Approved by:

J. A. Padgett Princi a Health Physics Specialist

i TABLE OF CONTENTS

~Pa e Table of Contents.... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

List of Figures...... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

List of Tables....... ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ iv 1.0

SUMMARY

o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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 Airo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-1 3.2 Drinking Water......................... ~ ~ 3-1 3.3 F isho ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-2 3.4 Surface Water ......................... ~ ~ 3-3 3.5 Groundwater............................ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-3 3.6 M i 1k o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-3 3.7 Bottom Sediment........................ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-4 3.8 Shoreline Sediment..................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-4 3.9 Food C1 ops."......"."..............- ~ ~ 3-5 3.10 External Radiation Exposure............ ~ ~ 3-5 3.11 Comparison with Preoperational and 1987 Operational Data....................... 3-5 4.0 HISSED SAMPLES AND ANALYSES........................ 4-1 4.1 Air Cartridge and Air Particulate............ ~ ~ ~ 4-1 4~2 Fi sh ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ 4-1 4.3 Thermoluminescent Dosimeters (TLD)........... ~ ~ ~ 4-1 5.0 LAND-USE CENSUSo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-1 5.1 Introduction............................ ~ ~ ~ 5-1 5.2 Requirements............................ ~ ~ ~ 5-1 5.3 M ethods................................. ~ ~ ~ 5-1 5.4 R esults................................. ~ ~ ~ 5-2 6.0 ANALYTICAL PROCEDURES......................... 6-1 6.1 G ross Beta.............................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-1 6.2 T ritium................................. ~ ~ ~ 6-1 6.3 Iodine-131.............................. ~ ~ ~ 6-1 6.4 Gamma Spectrometry...................... ~ ~ ~ 6-2 6.5 Thermoluminescent Dosimetry............. ~ ~ ~ 6-2 6.6 EPA Laboratory Intercomparison Program.. ~ ~ ~ 6-3 6.7 Lower Limits of Detection............... ~ ~ ~ 6-4

LIST OF FIGURES

~F$ use Title ~Pa e 2-1 Harris Nuclear Project Radiological Environmental S ampling Points........................................... 2-9 2-2 Harris Nuclear Project Radiological Environmental S ampling Points........................................... 2-10 2-3 Harris Nuclear Project Radiological Environmental S ampling Points........................................... 2-11 2-4 Legend for Figures 1, 2-2, and 2-3......................

2-. 2-12 Air Particulate Samples Gross Beta Activity 3-1 Location 1.....................;..................... 3-10 3-2 3-3 Location 2........................................... 3-11 Locati on 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-12 3-4 3-5 Location 4........................................... 3-13 Locati on 26 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-14 Drinking Water Samples - Gross Beta Activity 3-6 Location 40.......................................... 3-15 3-7 Location 51.......................................... 3-16 Drinking Water Samples - Tritium Activity 3-8 Location 40............................ 3-17 3-9 Location 51 o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t~~~~~~~~~ 3-18 Surface Water Samples - Gross Beta Activity 3-10 Location 26 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-19 3-11 Location 40......................... 3-20 Surface Water Samples - Tritium Activity 3-12 Location 2 6 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-21 3-13 Location 2 6S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-22 3-14 Location 4 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-23 3-15 Location 4 1S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-24 3-16 Location 5 2S ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ 3-25 Milk Samples - I-131 Activity 3-17 Location 5................. 3-26 3-18 Location 19................ 3-27 Location 42................ 3-28

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3-20 Locatson 43.......................................... 3-29 Bottom Sediment Samples Gamma Activity 3-21 Location 52.......................................... 3-30 Shoreline Sediment Samples - Gamma Activity 3-22 Location 26.......................................... 3-31 3-23 Location 41.......................................... 3-32 3-24 TLD Averages for Inner and Outer Rings.................... 3-33

LIST OF TABLES Table Title ~Pa e 1-1 Radiological Environmental Monitoring Program Data S ummary...................................................... 1-3 2-1 Radiological Environmental Monitoring Program................ 2-4 5-1 Distance to the Nearest Special Locations from the Harris Nuclear Project (miles)...................................... 5-4 5-2 Milk Animal Locations Within 5-mile Radius Zone of the Harris Nuclear Project....................................... 5-5 5-3 Meat Animal Type at Nearest Location to the Harris Nuclear P roject by Sector............................................ 5-6 6-1 Typical Lower Limits of Detection Ge(Li) Gamma S pectrometry................................................. 6-5

1.0

SUMMARY

This report presents the results of the Radiological Environmental Moni-toring Program conducted during 1988 for the Harris Nuclear Project (HNP). The program was conducted in accordance with Technical Specifica-tion 4.12.1, the Off-Site Dose Calculation Manual, and applicable pro-cedures.

Over 1,200 samples from 11 environmental media types were analyzed during the year. No detectable radioactivity (or activity which did not differ significantly from the corresponding control) was observed in 1,557 of 1,605 analyses.

Radioactivity in environmental samples which could be attributed to plant operations in 1988 is as follows:

Highest Environmental Average Activity Maximum Individual Media Radionuclide and Occurrence Dose mrem r Harris Lake Surface Water 4,820 pCi/1 (24/24) 0.009 (T.B.)

HNP Drinking Water H-3 2,450 pCi/l (9/12) 0.045 (T.B.)

Harris Lake Fish Mn-54 18 pCi/kg (1/4) 0.005 (GI/LLI)

Harris Lake Mn-54 4.37E-2 pCi/g (2/12) Sum of Doses Shoreline Co-58 2.22E-2 (1/12) 3.6E-4 (T.B.)

Sediment Cs-137 2. 29E-2 (2/12) 1-1

Harris Lake Cr-51 1.60E+0 pCi/g (1/12) No dose Bottom Mn-54 1.40E+1 (12/12) calculated.

Sediment Co-57 2.56E-1 (10/12) Water shielding Co-58 2. 40E+1 (12/12) eliminates Fe-59 8.99E-1 (6/12) dose at surface.

Co-60 1.39E+1 (12/12)

Zr-95 5.75E-1 (3/12)

Nb-95 8.52E-1 (12/12)

Cs-137 3.02E-1 (7/12)

Overall, the radiological environmental data indicates that HNP opera-tions in 1988 had no significant impact on the environment or public health and safety.

A statistical summary of all the data gathered in 1988 has been compiled in Table 1-1. No nonroutine measurements were reported during the year.

1-2

S 0-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

Harris Nuclear Project Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1988 Type and Typical Lower All Indicator Location w/Hl hest Annual Mean Medium or Pathway Total No, of Limit of Locations Name, Control Locations Sampled or Measured Measurements Detection Mean(2) Distance, and Mean( ) Mean(2)

(Unit of Measurement) Performed (LLD) Ran e Direction Ran e Ran e Air Cartridge 1-131 8.0E-3 Al I less than LLD All less than LLD All less than LLD (pCi/m ) 310(3)

Air Particulate Gross Beta 1.57E-2 (258/258) Dixie Pipeline 1.64E-2 (52/52) 1.49E-2 (52/52)

(pCi/m ) 3io'3' 3E "3 5.14E-3 4.71E-2 2.5 miles N 5ol4E 4o71E-2 8o08E-3 2e92E-2 Gamma Refer to All less than LLD All less than LLD All less than LLD 24 Table 6-1 Drinking Water 1-131 3,0E-I All less than LLD All less than LLD All less than LLD (pci/I) 156 Gross Beta 2 OE<0 4,21E+0 (24/24) Lillington 4,68E+0 (12/12) 4,80E<0 (12/12) 36 2,24E+0 7,24E+0 Cape Fear River 2.66E>0 7.24E+0 3 ~ 14E <0 6,60E+0 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 2,45E+3 (9/24) SHNPP site 2,45E+3 (9/12) All less than LLD 36 (6) 1 45E+3 - 3 '9E+3 0,1 mile SSW 1,45E+3 3 '9E+3 Fish Gamma Refer to All less than LLD All less than LLD All less than LLD Bottom-Feeders 2(3) Table 6-1 (pCI/g wet)

Free-Swimmers Gamma 1,79E-2 (I/4) Site varies 1,79E-2 (I/4) All less than LLD (pCi/g wet) Single value within Harris Mn-54 1.3E-2 Lake

TABL (cont.)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

Harris Nuclear Project Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1988 Type and Typical Lower All Indicator Location w/Hl hest Annual Mean Medium or Pathway Total No of Limit of Locations Name, Control Locations Sampled or Measured Measurements Detection Mean(2) Distance, and Mean(2) Mean(2)

(Unit of Measurement) Performed (LLD)(' Ran e Direction Ran e Ran e Food Crop(5) Gamma All less than LLD All less than LLD 4.31E-2 (I/12)

(pCi/g wet) 45 Single value Cs-137 I ~ 3E-2 Groundwater Gamma Refer to All less than LLD All less than LLD All less than LLD (pCi/I) Table 6-1 Tritium 1.2E+3 All less than LLD All less than LLD All less than LLD Milk 1-131 3 OE-I All less than LLD All less than LLD All less than LLD (pcl/I ) 96 Gamma 9,66E<0 (I /72) Goodwin 's Dairy 9.66E+0 (I/24) 4,25EOO (I/24) 96 Single value 2.2 miles N Single value Single value Cs-137 5,0EOO Bottom Sediments Gamma (pCi/g dry) 12(7) 2 ~ 56E-I (10/12) Harris Lake 2 ~ 56E-I (10/12) No control Co-57 2,8E-2 6,05E-2 - 6.12E-I 3,8 miles S 6,05E-2 - 6 ~ 12E-I Co-58 3,6E-2 2 ~ 40E+I (12/12) Harris Lake 2 ~ 40E+ I (12/12) No control 1.71E+0 - 6.49E+I 3.8 mi les S 1,71EtO - 6,49E+I Co-60 3,6E-2 i,39E+I (12/12) Harris Lake 1,39E+I (12/12) No control 8 ~ 55E-I - 4 ~ 17E+I 3.8 miles S 8,55E-I 4 ~ 17E+I Cr-51 2,6E-I 1,60E40 (I/12) Harris Lake 1,60E+0 (I/12) No control Single value 3.8 miles S Single value Cs-137 3.9E-2 3,02E-I (7/12) Harris Lake 3,02E-I (7/12) No control 1,26E-I 7,48E-I 3.8 miles S 1,26E-I 7,48E-I Fe-59 6,9E-2 8o99E I (6/12) Harris Lake 8,99E-I (6/12) No control 2 40E-I - 2,53E+0 3.8 miles S 2,40E-I - 2,53EOO

0 TAB (cont.)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

Harris Nuclear ProJect Docket Number: STN 50-400 Wake County, North Carolina Calendar Year: 1988 Type and Typical Lower All Indicator Location w/Hi hest Annual Mean Medium or Pathway Total No, of Limit of Locations Name, Control Locations Sampled or Measured Measurements Detection Mean(2) Distance, and Mean(2) Mean (2)

(Unit of Measurement) Performed (LLD)(' Ran e Direction Ran e Ran e Bottom Sediments>> Mn-54 5,0E-2 1.04E+1 (12/12) Harris Lake 1,04E 41 (12/12) No control (pCi/g dry) 5.91E-1 - 2,99E+I 3.8 miles S 5,91E-I - 2 99E+1 Nb-95 5,2E-2 8,52E-I (12/12) Harris Lake 8,52E-I (12/12) No control 1,29E-I - 2,68E<0 3 8 miles S 1,29E-I - 2 68E+0 Zr-95 9.0E-2 5,75E-1 (3/12) Harris Lake 5,75E-I (3/12) No control 2,29E-I - I ~ 12E+0 3.8 miles S 2,29E-I - '2EOO 1

Shoreline Sediments Gamma (pCi/g dry) 24 (7) 3,6E-2 2,22E-2 (I/24) Harris Lake 2,22E-2 (I/12) No control Co-58 Single value 3.8 miles S Single value Cs-137 3,9E-2 2,29E-2 (2/24) Harris Lake 2,29E-2 (2/12) 2,04E 2 '5E-2 3.8 miles S 2,04E 2,55E-2 No control Mn-54 5,0E "2 4,37E-2 (2/24) Harris Lake 4,37E-2 (2/12) 3,47E-2 " 5,27E-2 4.6 miles S 3,47E-2 5.27E-2 No control Surface Water 1-131 3,0E "I All less than LLD All less than LLD All less than LLD (pCi/I ) 104 Gross Beta 2,0E+0 4 47E+0 (24/24) Lillington 4 68E+0 (12/12) 4,80E+0 (12/12) 36 2,66E+0 7,24EtO Cape Fear River 2.66E~O - 7,24E+0 3 ~ 14E 40 6,60E 00 17 miles SSE Gamma Refer to All less than LLD All less than LLD All less than LLD 36 Table 6-1 Tritium 1,2Et3 4,75E+3 (46/58) Harris Lake 4,82E+3 (24/24) All less than LLD 70(6) (7) 2,89E+3 - 6,73E+3 4.6 miles S 2,89E+3 6,34E+3 Direct TLD I mR 1,04EtO (156/156) Fuquay-Varina 1,42E+0 (4/4) 9,25E-I (4/4)

Radiation i60(3) 7.0E-I - 1.6E<0 9.7 miles ESE 1.2E<0 1.6E<0 9,00E-I I,OE tO (mR/week)

NOTATIONS FOR TABLE 1-1

1. The lower limit of detection is given by the following general equation:

4.66 s b

LLD =

E . V . 2.22 . Y . exp (-x i

te )

Where:

LLD = Lower limit of detection in pCi per unit volume or mass sb = (N/tb) 1/2 = Standard deviation of the background (cpm)

N = Background count rate (cpm) tb = Background count time (min)

E = Counting efficiency (counts per disintegration)

V = Volume or mass of sample 2.22 = Conversion factor (dpm/pCi)

Y = Fractional chemical yield, when applicable

= Radioactive decay constant for the ith nuclide te = Elapsed time between sample collection and counting See Table 6-1 for listing of LLD values for the gamma spectrometry system. This expression is not used for direct radiation measurements.

2. Pean 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, Hissing Samples and Analyses.

1-6

4. Bottom sediment sampling is not required by the technical specifications but monthly samples were collected to better characterize the radiologi-cal characteristics of Harris Lake.

5. Food crops consisted of cabbage, turnip greens, mustard greens,'ucum-bers, broccoli, green beans, okra, lima beans, squash, tomatoes, peas, and collards.

6. Although quarterly composite samples are required, monthly composite samples are used to provide more frequent and sensitive analyses.

7. Although Harris Lake shoreline sediment sampling is only required semi-annually, samples were collected and analyzed monthly.

Similarly, lake surface waters are only required to be analyzed for tritium quarterly but additional sampling and analyses were performed monthly. These additional analyses were designed to better characterize the impact of plant operations on Harris Lake.

1-7

2.0 GENERAL 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 Harris Nuclear Project (HNP) is a pressurized water reactor designed to produce 868 MWe (net). Criticality was achieved on Janu-ary 3, 1987.

The HNP site is located in the extreme southwest corner of Wake County, North Carolina, and the southeast corner of Chatham County, North Carolina. The plant is approximately 16 miles southwest of Raleigh and approximately 15 miles northeast of Sanford. This loca-tion is on the northwest shore of Harris Lake which is a 4000-acre reservoir created by the impoundment of Buckhorn Creek. The reser-voir 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 4.5 miles south of the plant. The spillway at the dam flows into Buckhorn Creek which, after flowing south for approximately 2 miles, enters the Cape Fear River.

There are no industrial or residential structures on CPEL property.

However, Carolina Power 8 Light cooperates with various state agencies to provide public access for boating, fishing, hunting, and other recreational uses which are not inconsistent with the primary purpose of the lands and waters. As such, some recreational facil-ities, such as boat ramps and access areas, are located on station property for public use.

2-1

P ~

The majority of the land within the 5-mile radial area of the site is wooded with a scattering of fields and residential properties. Much of the land is used for timber and pulpwood production. Agricultural activities occur on a limited basis within this area including two

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operating commercial dairies.

The population within a 10-mile radial area of the plant is, for the most part, considered rural. Towns in this area with notable popu-lations include Apex, Holly Springs, and Fuquay-Varina (see Fig-ure 2-2).

Within a 50-mile radius of the plant, much of the land is devoted to agricultural activity. Major crops include tobacco and soybeans and corn for grain. Livestock production includes hogs, beef, poultry, and dairy pr oducts. Commerci al fi sh and shel 1 f i sh catches from waters within 50 miles of the station discharge are negligible.

Recreational fishing is popular in this range of the plant. 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 HNP Radiological Environmental Monitor ing Program are to:

To provide an evaluation of the environmental impact of releases of radioactive materials from the plant.

To measure any accumulation of radioactivity in the environment and to assess trends.

To detect unanticipated pathways for the transport of radio-nuclides through the environment.

The following locations are designed as Control Locations for the respective measurements and are intended to indicate conditions away from HNP influence.

2-2

l Pittsboro > 12 miles WNW NW or NNW (Sample Station 5)

Airborne Particulate (filter) Samples Charcoal Cartridge Samples - Airborne I-131 Thermoluminescent Dosimeter Area Monitors Milk Samples Food Products Ca e Fear Steam Electric Plant 6.1 Miles WSM (Sample Station 38)

Surface Water Samples Drinking Mater Samples Upstream of the Buckhorn Dam on the Cape Fear River Site Varies in This Locale (Sample Station 45)

Fish Samples The current radiological environmental monitoring program is detailed in Table 2-1 and has been based on plant Technical Specifica-tion 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.

2-3

TABLE 2-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM HARRIS NUCLEAR PROJECT Typical Sampling Point> Sample Ex osure Pathw and Descri tion S li Fre uenc Size S le Anal sis Air Cartridge 1 2.5 miles N Continuous operating Weekly 30,000 cu ft I-131 (AC) 2 1.5 miles NNE sampler with sample (900 cu m) (charcoal 3 2.6 miles ENE collection at least once cartridge) 4 3.2 miles NNE per 7 days or as 5 > 12 miles NW- required by dust loading Pittsboro (Control) 26--4.6 miles S Air Particulate 1--2.5 miles N Continuous operating Weekly 30,000 cu ft Gross Beta (AP) 2--1.5 miles NNE sampler with sample (900 cu m) 3--2.6 miles ENE collection at least once quarterly 4--3.2 miles NNE per 7 days or as Composite Gamma Isotopic 5--> 12 miles NW- required by dust loading Pittsboro (Control) 26 4.6 miles S Sediment 26 4.6 miles S Semiannually 500 g Gamma Isotopic from Shoreline 41--3.8 miles S (SS)

Bottom 52 3.8 mil es S Semiannually 500 g Gamma Isotopic Sediment (SD)

TABLE 2-1 (continued)

Typical Sampling Point> Sample

~E" P th and Descri tion S li Fre uenc Size S le Anal sis Drinking 38 6.1 miles WSW (Control) Weekly 8 liters I-131 water 40--17 miles SSE Li1 1ington (DW) 51--0.1 mile SSW--HNP Site Monthly Composite Gamma Isotopic Tritium Gross Beta Groundwater 39 0.7 mile SSW quarterly 8 liters Gamma Isotopic (GW)

Fish 44--Site varies within Harris Lake Semiannually 1 kg each Gamma Isotopic (FH) 45--Site varies in Cape Fear Riv~r Free-Swimmers on edible above Buckhorn Dam (Control) Bottom-Feeders portion for each Food 46 2.3 miles NE--Nursing Home Monthly during 500 g Gamma Isotopic Products 43--2.2 miles N Goodwin's Dairy growing season 54--1.7 miles NNE Wilkins or when milk sampling Norris is not performed 55 1.7 miles NNW L.L. Goodwin (FC) 5 > 12 miles WNW, NW,3or NNW-Pittsboro (Control)

Mi lk 42--7.5 miles SSE Maple Knoll Semimonthly when 8 liters I-131 Dairy animals on pasture Gamma Isotopic (NK) 19 4.6 miles NNE Olive's Dairy 43 2.2 miles N Goodwin's Dairy 5--> 12 mile~ NW Strowd's Dairy (Control)

Surface 8 26--4.6 miles S Weekly 8 liters I-131 Water 38--6.1 miles WSW (Control)

(SW) 40 17 miles SSE--Lil lington Monthly Composite Gamma Isotopic Tritium Gross Beta

TABLE 2-1 (continued)

Typical Sampling Point> Sample Ex osure Pathw S li Fre uenc Size S le Anal sis TLDs Direct Radiation 1 2.5 miles N Continuous measurement Not Appl icable Gamma Dose Monitors 2--1.5 miles NNE with an integrated readout (TLD) 3 2.6 miles ENE at least once per quarter 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--1.1 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 f 23--5.0 miles ESE 24--4.7 miles Sf 25--4.8 miles SSE 26 4.6 miles S 27 4.8 miles SSW 28 4.8 miles SW

TABLE 2-1 (continued)

Typical Sampling Point> Sample Ex osure Pathw and Descri tion S li Fre uenc Size S le Anal sis 29--5.6 miles WSW Continuous measurement Not applicable Gamma Oose 30 5.1 miles W with an integrated readout 31 4.5 miles WNW at least once per quarter 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

NOTES TO TABLE 2-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

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 thoron 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 oper-ations are considered indicator stations.

4. Gamma isotopic analysis means the identification and quantitation of gamma-emitting radionuclides that may be attributable to the effluents from the plant operations.

5. Composite samples will be collected with equipment which is capable of collecting an aliquot at time intervals which are very short (e.g., every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) relative to the compositing period (e.g., monthly).

6. The dose will be calculated for the maximum organ and age group using the methodology contained in Regulatory Guide 1. 109, Rev. 1, and the actual parameters particular to the site.

7. A reanalysis of plant meteorological data indicated the new garden loca-tions needed to be added in the sectors with the highest D/g values.

Sampling Points 54 and 55 were added to the program and Points 43 and 46 will be dropped at the conclusion of the 1988 growing season.

8. Weekly I-131 analyses are not required for surface water samples. How-ever, 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.

2-8

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F lgure 2-4 LEGEND FOR FIGURES 2-1, 2-2, 2-3 REFER TO STATION REFER TO STATION FIGURE NUMBER SAMPLE TYPE FIGURE NUMBER SAMPLE TYPE 1-3 I AP, AC, TL 1-2, 1-3 26 APp ACJ SWJ SSp TL 1-3 2 AP, AC, TL 1-1, 1-3 27 TL 1-3 3 AP, AC, TL 1-1, 1-3 28 TL 1-3 4 AP, AC, TL 1-1 29 TL 1-1 5 APp ACp MKp FC~ TL l-l 30 TL 1-3 6 TL 1-1 31 TL 1-3 7 TL 1-1 32 TL 1-3 8 TL 1-2 33 TL 1-3 9 TL 1-2 34 TL 1-3 10 TL 1-2 35 TL 1-3 ll TL 1-2 36 TL 1-3 12 TL 1-2 37 TL 1-3 13 TL 1-1 38 SW, DW 1-3 14 TL 1-3 39 GW 1-3 15 TL 1-2 40 SW, DW 1-3 16 TL 1-3 41 SS 1-3 17 TL 1-2 42 MK 1-3 18 TL 1-3 43 MK, FC 1-2 19 MK, TL 1-3 44 FH 1-2, 1-3 20 TL 1-1 45 FH 1-2 21 TL 1-3 46 FC 1-2 22 TL 1-2 48 TL 1-2 23 TL 1-3 49 TL 1-2 24 TL 1-3 50 TL 1-2, 1-3 25 TL 1-3 51 DW 1-3 52 SD 1-1 53 TL 1-3 54 FC 1-3 55 FC AC Air Cartridge AP Air Particulate SD Bottom Sediment FC Food Crop FH Fish GW Groundwater MK Ml I k SW Surface Water DW Drinking Water TL TLD SS Shoreline Sediment 2-12

3.0 INTERPRETATIONS AND CONCLUSIONS 3.1 Air All 310 air cartridge samples from indicator and control locations had I-131 activities which were less than the LLD.

Gross beta activity was detectable in all airborne particulate sam-ples from the five indicator locations. The 258 samples had an average concentration of 1.57E-02 pCi/m . Similar gross beta activ-ities were observed at the control location in Pittsboro which had an average concentration of 1.44E-02 pCi/m in 52 samples. No gamma activity was detected on 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 indicator locations compared to the control location for the period January-December 1988.

3.2 ~tkf II Neither the drinking water samples collected at the HNP and the Lillington Municipal water supply nor the control samples collected from the Cape Fear River above Buckhorn Dam contained detectable I-131 activity during 1988.

Figures 3-6 and 3-7 provide a graphic representation of the gross beta activity during 1988 for Locations 40 (Li llington) and 51 (HNP 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 4.2E+0 and 4.BE+0 pCi/1, respectively.

3-1

Analyses for gamma-emitting radionuclides indicated all concentra-tions were less that the lower limit of detection for drinking water. Table 6-1 contains typical LLO values for gamma-emitting radionuclides in drinking water.

Tritium activities in drinking water at the HNP which is. drawn from Harris Lake ranged from 1,450 to 3,190 pCi/l. The average activity pless in 1988 was 2,450 + 800 pCi/1. No tritium activity was detected in the Lillington municipal water supply or the control station sam-

~

The total body dose to occupationally exposed personnel at SHNPP from the ingestion of 2,450 pCi/1 of tritium in drinking water dur-ing the year was calculated using the USNRC Regulatory Guide 1. 109, Equation A-1. The total body dose is estimated to be 4.5E-2 mrem for 1988.

Figures 3-8 and 3-9 present the tritium activities at the sample locations versus the control values.

3.3 Analyses for gamma-emitting radionucl ides in bottom-feeding fish (catf i sh) from the indicator location, Harri s Lake and the control location on the Cape Fear River above Buckhorn Oam, revealed no detectable gamma activity.

Eight samples of free-swimming species (sunfish and largemouth bass) were collected in 1988 from Harris Lake and the Cape Fear River. A single sample from Harris Lake was found to contain a trace of Mn-54 activity at a level of 18 pCi/kg. No gamma radionuclide activity was detected in any of the four control samples. Using Equation A-1 of Regulatory Guide 1.109, it may be estimated that the adult con-sumption of 21 kg/year of fish containing 18 pCi of Mn-54/kg would result in a dose to the GI-LLI of 5.3E-3 mrem.

3-2

3.4 Surface Mater Surface water samples were collected and analyzed weekly for I-131. Water samples collected during 1988 contained no detectable I-131 (LLD < 3E-1).

Average gross beta concentrations at the indicator and control loca-tions were 4.5E+0 pCi/1 and 4.8E+0 pCi/1, respectively.

Figures 3-10 and 3-11 provide a graphic representation of the gross beta activity in surface water during 1988 for Locations 26 (Harris Lake) and 40 (Lillington). The solid line is the indicator loca-tion, 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 the lower limit of detection. Tritium activity was de-tectable in Harris Lake surface water at an annual average of 4.82E+3 pCi/1. This value included an additional 34 samples taken in Harris Lake. No tritium activity above the LLD of 1.2E+3 was detected in surface water downstream at Lillington or the Cape Fear River control location.

Figures 3-12 through 3-16 present the tritium activities in surface water during 1988.

3.5 Groundwater Groundwater samples are collected on site at HNP and analyzed for gamma-emitting radionuclides and tritium. Concentrations of radio-nuclides were all less that the lower limit of detection.

3.6 Milk I-131 was not detected in either the 72 milk samples from indicator locations or the 24 samples from the control location (LLD < 3E-1 pCi/1).

3-3

Gamma isotopic analyses revealed only Cs-137 in one of 72 samples from the indicator samples. Cs-137 was also observed in a single sample from the control location at an activity of 4.2 pCi/l. The rare occurrence of this radionuclide in the sample media during the year, along with its presence within one week in a control sample, indicates that no relationship to plant operations can be estab-lished.

Figures 3-17 to 3-20 contain information on the I-131 activities.

3.7 Bottom Sediment Sampling of bottom sediment is not a requirement of the plant tech-nical specifications; however, samples are collected near the dis-charge of the cooling tower blowdown pipe in order to observe one aspect of plant liquid discharges. In 1988, 12 samples were col-lected. Activation products of cobalt and manganese were detected in each sample and radionuclides of five other species were seen less frequently. The annual mean values for the predominant nuclides were Co-58 (24 pCi/g), Co-60 (13.9 pCi/g), and Mn-54 (10.4 pCi/g).

Figure 3-21 presents the results of monthly analyses.

3.8 Shoreline Sediment Shoreline sediment samples were collected monthly (1) opposite the discharge structure and (2) near the spillway on the main dam in 1988. Traces of Mn-54, Co-58, and Cs-137 were occasionally detected but considering the levels and counting errors, no definite trend toward increased activities can be established.

Regulatory Guide 1.109, Equation A-l, was used to estimate the dose to the maximally exposed individual. The annual skin dose to a teenager is estimated at 3.6E-4 millirem/yr from these three nu-clides.

3-4

Figures 3-22 and 3-23 provide data on those samples which contained activity.

3.9 ~Food Cro s Food crops are required to be collected when a milk sampling program cannot be performed. Even though the milk sampling program was per-formed for three indicator dairies and one control dairy, food pro-duct samples were collected for historical data. The 12 crops sampled during the growing season included lettu'ce, cabbage, col-lards, broccoli, turnips, and mustard greens.

Gamma spectrometry analysis of food crops from indicator locations showed all gamma emitters less than LLD. Cs-137 at a concentration of 4.3E-2 pCi/g, wet, was detected in one of 12 control samples.

3.10 External Radiation Ex osure Thermoluminescent dosimeters were used to monitor ambient radiation exposures in the environs. The average weekly dose rate from the indicator locations was 1.0 mrem/wk and 0.9 mrem/wk from the control location. The highest indicator location nine miles from the plant averaged only 0.5 mR/wk more than the control. This difference is likely associated with local and/or geological differences and unre-lated to plant activities since the dose rates are similar to their preoperational levels.

Comparison of the weekly dose rates for TLDs within three miles of the plant with those at approximately five miles is presented in Figure 3-24 and shows no differences.

3.11 COMPARISON WITH PREOPERATIONAL AND 1987 OPERATIONAL DATA The environmental impact of plant operations during 1988 can be gauged by comparisons with the preoperational and 1987 data. Since 3-5

much of the data involves activities < LLD, they neither require nor lend themselves to rigorous statistical treatment. The conclusion and comparative statements are based on inspection and judgment.

Air Sam les No I-131 was detectable in air samples during 1988 or in the first year of operation, 1987. In 1986, I-131 was present in samples for a six-week period following the Chernobyl incident of April 26, 1986. The activities during that period averaged 9E-2 pCi/m with a maximum reading of 2E-1 pCi/m . In 1985 all charcoal cartridge activities were less than LLD (2E-2 pCi/m ).

Gross beta activities on quarterly composite air filters during 1988 were unchanged from 1987 when they had returned to their pre-Chernobyl and preoperational levels of approximately 1.5E-2 pCi/m 3 .

Drinkin Water I-131 activity which was detectable by radiochemical analyses in 1986 due to Chernobyl fallout returned to the LLD levels seen in 1985 and 1987 (< 3E-1 pCi/1) and remained at less than detectable levels in 1988.

Gamma and gross beta activities in 1988 were basically unchanged from 1985 to 1987.

In 1988 as in 1987 and 1986, no tritium was detectable in the Lil-lington Municipal Water Supply. The tritium activity in HNP drink-ing water, however, was detectable in 9 of 12 monthly composite samples at an average level of 2,450 pCi/1. This was an increase in occurrence and average activity over 1987.

3-6

Fish In 1986 evidence of fallout Cs-137 and Cs-134 was present in fish from the control location; in 1987 only Cs-137 was present in both control and Harris Lake fish; in 1988 a trace of Mn-54 was detected in a single fish sample from Harris Lake.

Surface Water Samples are taken from Harris Lake and the Cape Fear River at Lil-lington. I-131 activities were less than LLO (< 3E-1 pCi/1) in 1988 and 1987 at both locations which represented a reduction from 1986 samples obtained during the Chernobyl incident. Average gross beta activity in 1985-1988 was essentially unchanged over this period.

Tritium activity in Harris Lake increased measurably from preopera-tional levels of less than LLO (1.2E+3 pCi/l) activities to an aver-age level of 3.3E+3 pCi/1 in 1987 to a level of 4.82E+3 pCi/1 in 1988. Since the surface water H-3 activity affects the activity in fish, it is estimated that the dose to be the maximum exposed indi-vidual from tritium in these fish is about 9.4E-3 mrem/yr.

Groundwater No tritium or gamma emitter activity has been observed in ground-water over the period 1985-1988.

Milk I-131 activities in 1988 and 1987 were less than LLO (< 3E-1 pCi/l).

This constituted a return to the 1985 preoperational level following the increased levels in 1986 preoperational samples which resulted from Chernobyl.

Cs-137 which was not detectable in 1985 milk samples and had an average of 6 pCi/1 in 1986 was sporadically observed in samples 3-7

during 1987 at activities similar to those resulting from the Cher-nobyl incident. In 1988 the radionuclide was observed in only a single control and indicator sample.

Bottom Sediment Sediment samples collected from the lake bottom in the vicinity of the plant liquid discharge structure had shown low Cs-137 activities in the preoperational period 1985-1986. During 1987 additional fis-sion and activation products were detected beginning in July. The principal constituents were Co-58, 60, and Mn-54. In 1988 nearly all species present had increased over their 1987 levels. The increases were especially noticeable in the Co-57, 58, and 60 activ-ities. Nevertheless, the direct public health implications of activity in the sediment are negligible by virtue of their location, 13 meters below the surface of the lake.

Shoreline Sediment The shoreline across from the plant discharge structure had shown no man-made gamma activity in 1985; fresh fission product activity (Cs-134/137) in 1986; in 1987, an apparent two fol d increase in Cs-137 activity along with the presence of two additional nuclides, Co-58 and Mn-54, at levels approximately twice their LLDs

(( 3.3E-2 pCi/g). In 1988 lower shoreline deposits of all three nuclides were observed. However, this may have been a function of sampling errors rather than a downward trend. It can be stated that no increase in shoreline activity occurred in 1988 as a result of plant operations.

~Food Cro s No detectable gamma activity was observed in broadleaf vegetation from indicator locations in 1988 or 1987. Crops from the control location had detectable Cs-137 activity in both years.

3-8

TLD The 41 TLD locations surrounding the plant showed virtually no change in the average weekly ambient beta-gamma environment from 1985 through 1988. The location with the maximum reading in 1988 also had to the maximum observed in 1987 and similarly high readings during the preoperational period.

3-9

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M 0.02 Y

0.01 0.00 13JAN88 19JUL88 SAMPLE DATE ISOTOPE g+gg MN-54

COL ENVIRONA SURVEILLANCE GAMMAA IVITY FOR SHORELINE SEDIMENT SAMPLES PLANT=HNP 'AMPLE POINT=0041 0.03 0.02-0.02-0.02 0.02 0.02 0.02 0.02 0.02 P

C 0.02 I 0.02 P

0.01-E 0. 01 R 0.01 G 0.01-R 0.01 A

M 0.01

0. 01 D . 0.01 R

Y 0.01

0. 01

0. 00 0.00 0.00 0.00 0.00 0.00 14MAR88 19JUL88 '60CT88 SAMPLE DATE ISOTOPE KEZQ CO-58 Hmmg CS-137

CPBcL ENVIRON SuRVEILLANCE TLD AVEI GES FOR INNER AND OUTER RING LOCATIONS PLANT=HNPI 2.0000 1.8000

1. 6000

1. 4000 I

L

1. 2000 I

1. 0000 P

E 0.8000 R

E 0.6000 E

K 0.4000 0.2000 0.0000 INNER OUTER INNER OUTER INNER OUTER INNER OUTER SAMPLE DATE 15FEBBB 15MAYBB 15AUGBB 15NOVBB DATE PRE-OP AVERAGE (1983 1987)I = 1,12

0

~

4.0 MISSED SAMPLES AND ANALYSES 4.1 Air Cartrid e and Air..Particulate AC/AP-02 January 12, 1988 Not analyzed. No power at sampling location AC/AP-02 August 15, 1988 Not analyzed. Breaker tripped.

4.2 Fish No samples of bottom-feeder fish (Catfish) were available for the second semiannual collection made in November 1988.

4.3 Thermoluminescent Dosimeters (TLOs)

TLO-25 Second quarter 1988 Missing in field at time of collection TLO-31 Third quarter 1988 Missing in field at time of collection TLO-9 Fourth quarter 1988 Missing in field at time of collection TLO-28 Fourth quarter 1988 Missing in field at time of collection 4-1

5.0 LAND-USE CENSUS 5.1 Introduction Technical Specification 3/4.12.2 for the Harris Nuclear Project requires that a land-use census be conducted annually around the site. The objec-tive 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 1988 land-use census was conducted during May.

2.2 ~t Technical Specification 3/4.12.2 requires that the survey be conducted:

a. Within a five-mile radius of the plant.

b. Annually during the growing season.

c. In each of the 16 compass sectors to identify the nearest:

1. Milk animal.

2. Residence.

3. Garden of greater than 500 square feet producing broadleaf vege-tation.

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 1988 land-use census was conducted using a door-to-door survey method. A standard questionnaire was used during an interview to record pertinent data.

5-1

Resident and road locations were identified within a five-mile radius zone surrounding HNP using U.S. Geological Survey topographic quadrangle maps (7.5-minute series). These maps were revised in 1981 based on aerial photographs 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 incre-ments 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) was located by inspection of fields and residential lots and by interviews with residents within the five-mile radius.

The survey was performed by CP5L in May 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 28 recorded visitations resulted in the following observations:

A. Milk goats are not located within the five-mile radius.

5-2

B. Milk cows are located in the N and NNE sectors. These loca-tions are commercial dairies that are currently part of the HNP radiological environmental monitoring program. Refer to Table 5-2.

C. Meat animals are found in 11 of the 16 compass sectors and are summarized in Table 5-3.

5-3

TABLE 5-1 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FROM THE HARRIS NUCLEAR PROJECT (MILES)

Exclusion Milk Milk Meat Sector ~Bound ar Residence Cow Goat Garden Animal N 1.32 2.2 2.2 2.2 2.2 NNE 1.33 1.7 4.6 1.7 1.8 NE 1.33 2.3 2.3 2.3 ENE 1.33 3.6 E 1.33 1.9 1.9 1.9 ESE 1.33 2.7 2.7 4.3 SE 1.33 4.3 4.3 SSE 1.33 4' S 1.36 SSW 1.33 3.9 3.9 SW 1.33 2.8 2.8 2.8 vsv 1.33 4.3 4.3 4.3 1.33 2.7 3.0 3.1 WNW 1.33 2.1 2.1 2.5 NW 1.26 1.8 1.8 1.8 NNW 1.26 1.5 1.7 1.7 As of May 1988.

Distance estimates are +/- 0.1 mile except at exclusion boundary.

5-4

TABLE 5-2 MILK ANIMAL LOCATIONS WITHIN 5-MILE RADIUS OF HNP Animal Distance Milk or Milk Sector ~Miles

• Animal ~Usa e 2.2 Cow Commercial and Private**

NNE 4.6 Cow Commercial and Private**

• Distance estimates are +/- 0.1 mile.

++Does not imply consumption.

5-5

TABLE 5-3 MEAT ANIMAL TYPE AT NEAREST LOCATION TO HNP BY SECTOR Sector Distance Miles

• Meat Animal N 2.2 Hogs NNE 1.8 Beef NE 2.3 Beef ENE E 1.9 Chickens, Rabbits ESE 4.3 Hogs SE SSE S

SSW SW 2.8 Chickens, Goats WSW 4.3 Hogs W 3.1 Rabbits, Chickens WNW 2.5 Chickens NW 1.8 Beef NNW 1.7 Beef, Hogs

• Distance estimates +/- 0. 1 mile.

• • Survey limited to a 5-mile radius.

5-6

6.0 ANALYTICAL PROCEDURES 6.1 Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background Alpha/Beta Counting System. The LLD for air par-ticulates is approximately 1.5E-3 pCi/m3 for HNP 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 LLO for gross beta is 1.96 E+0 pCi/l.

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 1200 pCi/1.

6.3 Iodine-131 Iodine-131 airborne concentrations are analyzed by the Ge(Li) gamma spectrometry systems. The cartridges are placed on the detector and each charcoal cartridge is counted individually with an approximate LLD of BE-3 pCi/m .

Iodine-131 in milk and drinking water is analyzed by use of anion-exchange resin, sodium hypochlorite leach, and organic extraction.

Iodine is precipitated as silver iodide, collected on a tared filter, dried, and counted on a low-background beta counter. The LLD is approximately 0.4 pCi/1 and 0.3 pCi/1 for milk 'and water respectively.

6-1

6.4 Ganma S ectrometr Ge Li Gamma spectrum analysis utilizes Germanium or Ge(Li) detectors with thin aluminum windods housed in steel and lead shields. The ana-lyzer 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 Dosimetr Each area monitoring station includes a TLD packet, which is a polyethylene bag containing three calcium sulfate phosphors con-tained 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 6-2

e

~

I

from traps as the dosimeter is heated above 150'C. The photons from the lower-energy traps are automatically eliminated through a pre-heat cycle. Calibration is checked regularly using dosimeters irradiated to known doses. Prior to the measurement of each dosim-eter, 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.

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

6.6 EPA Laborator Intercom arison Pro ram The Radiological Environmental Laboratory at the Harris Energy 5 Environmental Center in New Hill, North Carolina, provides radio-analytical services for CP&L's nuclear plant environmental surveil-lance programs. The laboratory is a participant in the EPA cross-check program and uses its performance in this program as a major determinant of the accuracy and precision of its analytical results.

During 1988, 69 analyses were completed on 27 samples representing 4 major environmental media (water, milk, air filters, and food).

Data on the known activities and the normalized standard deviations for the 69 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 Activit Percent of Anal ses

< 1 standard deviation 68

< 2 standard deviation 83

< 3 standard deviation 93 6-3

Of the 69 determinations, 5 (7 percent) fell outside the 3 standard deviation control limit.

In September 1988, gross beta on a sample analyzed for alpha and beta was +3.58 normalized standard deviations above the mean.

Reanalyses of the sample yielded 10.0 pCi/1 and 8 pCi/1 compared with a true value of 10.0 pCi/1 subsequent gross beta analyses yielded a +0.92 and a +1.15 normalized standard deviation.

In October 1988, 3 of 6 isotopes in a gamma analysis were above 3 times the normalized standard deviations. These were Co-60 at

+5.89, Cs-134 at +11.55, and Cs-137 at +9.58. Cr-51, Zn-65, and Ru-106 were all less than 1 normalized standard deviation from the mean. It was found, upon investigation, that the sample had been contaminated during preparation and the importance of cleanliness and care was reemphasized. Subsequent analysis of unkown samples for gamma emitters revealed no problems.

In November 1988, a sample analyzed for gross a and which contained Ra-226, Ra-228 and natural uranium was 3.29 normalized standard deviations above the mean. Investigations revealed that the wrong efficiency of 0.105 instead of 0.12 has been read from the self-absorption curve. Use of an efficiency of 0.12 would have resulted in 2.02 normalized standard deviations above the mean. Gross alpha analyses run after this sample yielded normalized standard devi-ations of -0.23 and -0.12.

6.7 Lower Limits of Detection All samples analyzed met the LLD required by Technical Specifi-cation 4.12.1 and Table 4.12.1-1. Typical "a priori" LLD values for the samples analyzed are listed in Table 6-1.

6-4

Table 6-1 Typical Lower Limits of Detection (a priori)

Ge(Li) Ganma Spectrometry Surface Water Groundwater Sam les Isotope (LLD)

Cr-51 19 pci/1 Mn-54 3 Co-58 3 Co-60 3 Zn-65 7 Zr-Nb-95 5 I-131 7 Cs-134 3 Cs-137 3 La-140 7 Other Expected 1 to Gamma Emitters 79 Air Particulates*

(quarterly Composite)

Isotope (LLO)

Cs-134 0.001 pCi/m Cs-137 0.001 La-140 0.006 Other Expected 0.001 to Gamma Emitters 0.017 6-5

Milk Isotope (LLD)

Cr-51 27 pci/1 Mn-54 4 Co-58 4 Co-60 6 I-131 4 Cs-134 5 Cs-137 5 La-140 5 Other Expected 2 to Gamma Emitters 95 Sediment Isotope (LLD)

Cr-51 263 pCi/kg Mn-54 50 Co-57 28 Co-58 36 Fe-59 69 Co-60 36 Nb-95 52 Zr-95 90 Cs-134 61 Cs-137 39 Other Expected 28 to Gamma Emitters 618 Fish Isotope (LLD)

Cr-51 174 pCi/kg Mn-54 13 Co-58 32 Co-60 38 Zn-65 62 I-131 28 Cs-134 33 Cs-137 29 Other Expected 13 to Gamma Emitters 617 6-6

I Food Products and Ve etation Isotope (LLD)

Cr-51 105 pCi/kg Mn-54 15 Co-58 17 Co-60 18 I-131 12 Cs-134 16 Cs-137 13 Other Expected 8 to Gamma Emitters 306 6-7

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