Text

Environ Surveillance Rept,1986
	ML18004B812
Person / Time
Site:	Harris
Issue date:	12/31/1986
From:	Pasteur R, Shearin R, Zimmerman S; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NLS-87-100, NUDOCS 8705290114
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ACCESSION NBR: 8705290114 DOC. DATE,: 86/}2/31 NOTARIZED:

NO FACIL: 0-400 Shearon Harris Nuclear Power Planti Unit }i Carolina AUTH. NANE AUTHOR AFFILIATION PASTEUR'. D.

Carolina Power 5 Light Co.

SHEAR IN> R. L.

Carolina Power Zc Lig"t Co.

ZINNERilANIS. R Carolina Power 5 Liaht Co.

REC IP. NANE RECIPIENT AFFILI*TlON DOCKET 05000400 SUB JECT:

"Environ Survei llance Rep tI Jan-Dec

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arotlno Po'"-e'er.'!"'nt Comoony MAY 26 SERIAL: NLS-87-100 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk V/ashington, DC 20555 SHEARON HARRIS NUCLEAR PO'NER PLANT DOCKET NO. 50-000/LICENSE NO. NPF-63 PREOPERATIONAL ENVIRONMENTALRADIOLOGICAL SURVEILLANCE REPORT Gentlemen:

Carolina Power dc Light Company (CPRL) submits for your information the Shearon Harris Nuclear Power Plant (SHNPP) Preoperational Environmental Radiological Surveillance Report for the 1986 calendar year.

The achievement of initial criticality on 3anuary 3, 1987 and the submittal of this report concludes the Preoperational Environmental Radiological Surveillance Program.

The initial Radiological Environmental Operating Report willbe submitted in 1988 in accordance with Technical Specif ication 6.9.1.3.

If you have any questions, please contact Mr. 3ames D. Kloosterman at (919) 836-8055.

Yours very truly, SRZ/lah (51903DK)

Attachment S

. Zi merman ager Nuclear Licensing Section cc:

Mr. B. C. Buckley (NRC)

Dr. 3. Nelson Grace (NRC-RII)

Mr. G. F. Maxwell (NRC-SHNPP) 411 Payettevilte Street

~ P. O. Box 1551

~ Raleign, N, C. 27602

L January I, 3 986 December 31, 1986

.F

(;<<5 SHEARON HARRIS NUCLEAR POWER PLANT CAROLINAPOWER & LIGHT COMPANY 870gP>0114 861231 pgR Agocg, 05000400 R

C.

I l

Shearon Harris Energy

& Environmental Center Carolina Power

& Light Company New Hill, North Carolina P REOP ERAT IONA L ENVIRONMENTAL RAOIOLOGICAL MONITORING STUOY FOR SHEARON HARRIS NUCLEAR POWER PLANT JANUARY 1 THROUGH OECEMBER 31, 1986 Prepared by:

a'~

Roger 0. Pasteur Senior Specialist - Environmental Reviewed by:

ona1 d L. Shears n Project Specialist - Environmental Approved by:

Ballard S.

ays Principal Specialist Environmental

TABLE OF CONTENTS

~Pa e'ist List of Figures..........................................

of Tables...........................................

~ ~ ~ ~ ~ ~ ~ ~ o ~ ~

~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

1.0 IHTRODUCTIOH........................................

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1.1 Plant and Location......................

1.2 Environmental Monitoring Program........

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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

1-1 1-2 2.0 PROGRAM

SUMMARY

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

2-1 3.0 INTERPRETATIONS AND CONCLUSIONS...............

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3-1 3.1 Airo ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3 ~ 2 Mi1k o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3.3 Food Crop Vegetation...........

3.4 Shoreline Sediment.............

3.5 Bottom Sediment................

3.6 Surface Water..................

3.7 Drinking Water.................

3.8 Groundwater....................

3 o9 Fi sh ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3. 10 External Radiation Exposure....

3.11 Dose Commitments from Chernobyl

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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

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

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

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

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

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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

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

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

3-1 3-1 3-2 3-3 3-4 3-4 3-5 3-5 3-5 3-6 3-6 4.0 MISSED SAMPLES AND ANALYSES...................

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~

iation)..

~ ~ ~ o ~ ~ ~ ~

4.1 Air Cartridge and Air Particulate.......

4.2 Surface Hater and Drinking Hater........

4.3 Thermoluminescent Oosimeters (Direct Rad 4-1 4-1 4-1 5.0 LAND-USE CENSUS.....................

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

5-1 5.1 Introduction..................

5.2 Requirements..................

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

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

5-1 5-1 6.0 ANALYTICALPROCEDURES...............

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~

6-1 6.1 6.2 6.3 6.4 6.5 6.6 6.7

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

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

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

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

ram...................

~ ~ ~ ~ ~

Prog

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

Gross Beta....................

T t I 1tium ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Iodine-131....................

Gamma Spectrometry............

Thermoluminescent Dosimetry...

EPA Laboratory Intercomparison Lower Limits of Detection.....

6-1 6-1 6-1 6-2 6-2 6-3 6-4

LIST OF FIGURES

~Fi ere Title Pacae 1-1 Shearon Harris Nuclear Power Plant Environmental Radiological Sampling Points........................- " ~"

1-2 Shearon Harris Nuclear Power Plant Environmental Radiological Sampling Points..........................-. "

1-3 Shearon Harris Nuclear Power Plant Environmental Radiological Sampling Points.............................

~

1-4 Legend for Figures 1-1, 1-2, and 1-3....................--

3-1 Air Particulate Gross Beta Activity vs.

Time at Station 01 and Control Site..................................... "".

1-9 1-10 1-11 1-12 3-8 3-2 Air Particulate Gross Beta Activity vs.

Time at Station 02 and Control Site.....................................--- "

3-9 3-3 Air Particulate Gross Beta Activity vs. Time at Station 03 and Control Site....................................---- "

3-10 3-4 Air Particulate Gross Beta Activity vs. Time at Station 04 and Control Site..........................................

3-11 3-5 Air Particulate Gross Beta Activity vs.

Time at Station 26 and Control Site..........................."

~ "- ~ ~" ~ ~ ~ ~ ~

3-12 3-6 Surface Water Gross Beta Activity vs.

Time at Station 26 and Control Site..........................-.--"-.-.-"-"

3-13 3-7 Surface Water Gross Beta Activity vs. Time at Station 40 and Control Site..........................................

3-14 i

~ M

~ ~

3-8 Drinking Water Gross Beta Activity vs.

Time at Station 40 and Control Site...........................-.--.--- "-.--

3-9 Orinking Water Gross Beta Activity vs.

Time at Station 51 and Control Site..........................................

3-10 Gross Beta Activity 1977 Versus 1986......................

3-15 3-16 3-17

r I

I

LIST OF TABLES Table Title

~Pa e'-1.

Radiological Environmental Monitoring Program................

1-4 2-1 Environmental Radiological Monitoring Program Summary........

2-3 5-1 Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant (miles).......................-. "

5-4 5-2 Locations within 5-mile Radius Zone of SHNPP ilk Animal..................................................

5-5 M

5-3 Meat Animal Type at Nearest Location to SHNPP by Sector......

5-6 6-1 Typical Lower Limits of Detection Ge(Li)

Gamma pectrometry................................................

S 6-5

PREOPERATIONAL ENVIRONMENTAL RAOIOLOGICAL MONITORING STUOY

1. 0 INTRODUCTION This report summarizes the Preoperational Environmental Radiological Monitoring Study conducted for the Shearon Harris Nuclear Power Plant (SHNPP) during calendar year 1986.

This is the fourth annual report summary for the site.

Oata analysis and interpretation in this re-port were performed entirely by Carolina Power

& Light Company staff.

1.1 Plant and Location The Shearon Harris Nuclear Power Plant is a pressurized water reactor designed to produce 868 MWe (net).

Criticality was achieved on Janu-ary 3, 1987.

The SHNPP site is located in the extreme southwest corner of Wake

County, North Carolina, and the southeast corner of Chatham

County, North Carolina.

The plant is approximately 16 miles southwest of Raleigh and 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 will provide process and cooling tower makeup water for the plant and will also serve as the receiving body for liquid effluents such as yard runoff, cooling tower

blowdown, 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.

1-1

l I

There are no industrial, recreational, or residential structures on CP&L property.

However, Carolina Power

& Light cooperates with vari-ous state agencies to provide public access for boating, fishing,'unting, and other recreational uses which are not inconsistent with the primary purpose of the lands and waters.

As such, some recre-ational facilities, such as boat ramps and access

areas, are located on station property for public use.

The majority of the land within the 5-mile radial area of the site is wooded with a scattering of fields and residential properties.

Much of the land is used for timber and pulpwood production.

Agricultural activities occur on a limited basis within this range; however, there are two operating commercial dairies.

The population within a 10-mile radial area of the plant is, for the most part, considered rural.

Towns in this area with notable popu-lations include Apex, Holly Springs, and Fuquay-Varina (see Figures 1-1 and 1-2).

Within a 50-mile radius of the plant, much of the land is devoted to agricultural activity.

Major crops include tobacco and soybeans and corn for grain.

Livestock production includes

hog, beef,

poultry, and dairy products.

Commercial fish and shellfish catch from waters within 50 miles of the station discharge is negligible.

Recreational fishing is popular in this range of the plant.

Since there are no estuarine or saltwater

bodies, sportfishing is confined to freshwater

streams, rivers, private ponds, and impoundments such as Harris Lake and Jordan Lake.

R

~

-r 1.2 Environmental Monitorin Pro ram The significant elements of the preoperational dose estimates (see SHNPP Environmental Report operating license stage) were used to establish the present preoperational surveillance program.

These

elements, combined with technical judgment and requirements from the 1-2

SHNPP technical speci ficat ions, wi 1 1 eventual ly def ine the final environmental surveillance program once the station becomes opera-tional.

The outline of this report follows the guidelines found in'ection 6.9.1.3 of NUREG

0452, Revision 4

(Westinghouse Standard Technical Specifications).

The current environmental program is detailed in Table 1-1 and has been based on NUREG 0472, Revision 3,

of March 1979 (Draft Radiological Effluent Technical Specifications for PWRs).

The environmental monitoring program may change based on revised guidance found in NUREG 0452, Revision 5.

Figures 1-1, 1-2, and 1-3 show the environmental monitoring locations.

Figure 1-4 pro-vides a legend for Figures 1-1 through 1-3.

1-3

I-I

TABLE 1-1 ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAM SHEARON HARRIS NUCLEAR POWER PLANT Y

Ex sure Pathw Sampling Point1

~HB I tl Sa li Fre uenc Typical Sample Size S

le Anal sis Air Cartridge (AC)

Air Particulate (AP)

I 12.5 miles N

21.5 miles NNE 32.6 miles NE 43.2 miles NNE 5

> 12 miles NW-Pittsboro (Control) 264.6 miles S

12.5 miles N

2--1.5 miles NNE 3--2.6 miles NE 43.2 miles NNE 5

> 12 miles NW-Pittsboro (Control) 26--4.6 miles S

Continuous operating sampler with sample collection at least once per 7 days or as required by dust loading.

Continuous operating sampler with sample collection at least once per 7 days or as required by dust loading Weekly Weekly guarterly5 Composite 30,000 cu ft I-131 (900 cu m)

(charcoal cartridge) 30,000 cu ft Gross Beta (900 cu m)

Gamma Isotopic Sediment from Shoreline (SS)

Bottom Sediment (SD) 264.6 miles S

413.8 miles S

523.8 miles S

Semiannually Semiannually 500 g

500 g

Gamma Isotopi Gamma Isotopic

TABLE l-l (continued) r Ex sure Pathw Drinking water (DW)

Groundwater (GW)

Fish (FH)

Food Products (FC)

Milk (MK)

Surface Water (SW)

Sampling Point>

and Descri tion 386.1 miles WSW (Control) 4017 miles SSELil 1 ington 510.1 mile SSW SHNPP Site 390.7 mile SSW 44--S ite vari es within Harri s Lake 45Site varies in Cape Fear Riv~r above Buckhorn Dam (Control) 462.3 miles NENursing Home 432.2 miles NGoodwin's Dairy 5> 12 miles WNW, NW,3or NNW--

Pittsboro (Control) 427.5 miles SEMaple Knoll Dairy 195.0 miles NNEOlive's Dairy 43--2.2 miles NGoodwin's Dairy 5

> 12 mile~

NWStrowd's Dairy (Control) 26--4.6 miles S

386.1 miles WSW (Control) 40--17 miles SSE--Lillington Sa li Fre uenc Weekly Monthly Composite quarterly Semi annual ly Monthly during growing season Semimonthly when animals on pasture Weekly Monthly Composite Typical Sample Size 2 gallons 2 gallons 1 kg each Free-Swimmers Bottom-Feeders 500 g

2 gallons 2 gallons Sa le Anal si s I-131 Gama Isotopic Tritium Gross Beta Gamma Isotopic Ganja Isotopic on edible portion for each Gamma Isotopic 1-131 Gamma Isotopic I-131 Gamma Isotopic Tritium Gross Beta

TABLE l-l (continued) v Ex sure Pathw Sampl ing Point1 and Descri tion S

li Fre uenc Typical Sample Size Sam le Anal sis Direct Radiation Monitors (TLD)

TLOs 12.5 miles N

21.5 miles NNE 3--2.2 miles NE 43.2 miles NNE 5

> 12 miles NM-Pittsboro (Control) 6--0.9 mile ENE 7--0.8 mile E

80.7 mile SE 92.3 miles ESE 102.2 miles SSE 110.7 mile S 120.8 mile SSW 130.7 mile SM 141.1 miles W

15--1.8 miles M

161.7 miles WNW 171.4 miles NM 181.3 miles NNM 19--4.9 miles NNE 204.7 miles HE 214.8 miles ENE 22--4.6 miles E

235.0 miles ESE 244.7 miles SE 25--4.8 miles SSE 26--4.6 miles S

27--4.8 miles SSW 28--4.8 miles SW Continuous measurement with an integrated readout at least once per quarter Hot Applicable Gamma Dose

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TABLE 1-1 (continued)

~t Ex sure Pathw Sampling Point>

and Descri tion 295.6 miles MSM 305.1 miles M

31--4.5 miles WNM 324.8 miles NM 334.4 miles NHM 348.6 miles NE--Apex 35--6.9 miles EHolly Springs 3611.2 miles E

379.7 miles ESEFuquay-Varina 48--4.5 miles N

492.6 miles NE 502.8 miles ESE 53--5.5 miles NM Sa li Fre uenc Cont inuous measurement with an integrated readout at least once per quarter Typical Sample Size Hot appl icable

NOTES TO TABLE 1-1 ENVIRONMENTAL RAO IOLOGICAL MONITORING PROGRAM 1.

Sample locations are shown on Figures 1-1, 1-2, and 1-3.

Figure 1-4 provides a legend explaining Figures 1-1 through 1-3.

2.

Particulate samples will be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) relative to the compositing period (e.g., monthly).

6.

The dose will be calculated for.the maximum organ and age group using the methodology contained in Regulatory Guide 1.109, Rev.

1, and the actual parameters particular to the site.

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Figure 1-4 LEGEND REFER TO FIGURE 1-3 1-3 1-3 1-3 1-1 1-3 1-3 1-3 1-3 1-3 1-3 1-3 1-3 1-3 1-3 1-3 1-3 1-3 1-2 1-2, 1-3 1-2 1-2 1-2 1-2 1<<2, 1-3 STATION NUMBER I

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8 9

10 II 12 13 14 15 16 17 18 19 20 21 22 23 24 25 SAMPLE TYPE AP, AC, TL AP, AC, TL AP, AC, TL AP, AC, TL AP, AC, MK, FC, TL TL TL TL TL TL TL TL TL Tl.

TL TL TL TL MK) TL TL TL TL TL TL TL REFER TO FIGURE 1-2, 1-3 l-l, 1-3 1-1) 1-3 1-1 1-1 1-1l-l 1-2 1-2 1-2 1-2 1-2 1-1 1-3 1-2 1-3 1-2 1<<3 1-3 1-1 1-3 1-2 1-3 1-3 1-3 1-3 1-1 STATION NUMBER 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 48 49 50 51 52 53 SAMPLE TYPE AP) AC)

SW ~

SS ) TL TL TL TL TL TL TL TL TL TL TL TL SW, DW GW SW, DW SS MK MK) FC FH FH FC TL TL TL DW SD TL AC AP SD FC FH GW MK SW DW TL SS Air Cartridge Air Particulate Bottom Sediment Food Crop F Ish Groundwater Ml I Ic Surface Water Drinking Water TLD Shoreline Sediment 1

2.0 PROGRAM

SUMMARY

The purposes of the Environmental Radiological Monitoring Program are:

To measure any accumulation of radioactivity in the environment and to assess whether this radioactivity is the result of the operation of the Harris Plant.

To provide an evaluation of the environmental impact of operating releases of radioactive materials from the Harris Plant.

To compare population doses from environmental sample data with corresponding doses predicted in the Final Environmental Statement.

As SHNPP is not yet operational, this report serves largely to provide a firm baseline of environmental measurements for later comparison.

Pre-operational and operational environmental radiological reports in the years to come will have formats similar to 'the present report.

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

Pittsboro

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

Airborne Particulate (filter) Samples Charcoal Cartridge Samples - Airborne I-131 Thermoluminescent Oosimeter Area Monitors Milk Samples Food Products 2-1

Ca e Fear Steam Electric Plant 6.1 miles MSW (Sample Station 38)

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

Fish Samples Tab 1 e 2-1 summari zes the resul ts of the preoperati onal environmental monitoring program for calendar year 1986.

2-2

~C

TABLE 2-1 ENVIRONHENTAL RADIOLOGICAL HONITORING PROGRAH SUHHARr Shearon Harris Nuclear Power Plant Wake County, North Carolina Oockel Number:

STN 50-400 Calendar Year:

1986 Medium or Pathway Sampled or Heasured (Unit of Heasurement)

Type and Total No. of Heasurements Performed Typical Lower Limit of Detection (LLD)

All Indicator Locations Hean Ran e

Name, Distance, and Direction Hean Ran e

Location w/Hl hest Annual Hean Control Locations Hean Ran e

Air Cartridge (pCi/m )

Air Particulate (pCI/m )

1-131 309 Gross Beta 309 3,0E-2 I 3E-3 7,67E 2,26E"I 2,82E-2 (257/257) 5 ~ 15E 2,27E-I I OE-2 to 9.13E-2 (23/257)

Dixie Pipeline 2.5 miles N

1,20E-I (4/51)

I ~43E I 97E"I 3,04E-2 (51/51) 5,20E 2 ~ 17E-I 9 49E-2 (4/52) 2,02E "2 1,84E-I 2.75E-2 (52/52) 6.44E 1,86E-I Drinking Water (pCi/I)

Gamma 24 Co-57 Cs-134 Cs-137 Ru-103 1-131 156 Gross Beta 36 Gamma 36 Tritium I,OE-3 6,8E-3 5 ~7E-3 I OE-3 3,0E-I B,OE-I Refer to Table 6-1 1.2Et3 9.98E-5 (I/20)

Single Value 5 ~47E-3 (5/20) 4,63E 6'9E-3 I ~ IOE-2 (5/20) 8 ~ IOE 1,21E-2 4,64E-3 (5/20) 3 74E 5 '2E-3 3,83E-I (4/104) 2,98E-I - 4,80E-I 4 06EtO (24/24) 2,33EtO 8,66Et0 All less than LLD All less than LLD Spillway on main reservoir 4.6 miles S

Barricade 1,5 mlles NNE Harris Energy d

Environmental Center 2.6 mlles NE New Hill Baptist Church 3.2 miles NNE Lilllngton Cape Fear River 17 mlles SSE Llllington Cape Fear River 17 miles SSE All less than LLD All less than LLD 9,98E-5 (I/20)

Single Value 6,39E"3 (I/4)

Single Value 1,21E-2 (I/4)

Single Value 5 ~42E-3 (I/4)

Single Value 3.83E-I (4/52) 2,98E-I - 4,80E-I 5,03Et0 (i2/12) 2 94EtO - 8.66EtO All less than LLO 5'7E-3 (I/4)

Single Value 9,93E-3 (I/4)

Single Value 4,18E-3 (I/4 )

Single Value 2,74E-I (2/52) 1,65E-I - 3,83E-I 4 84Et0 (12/12) 2,69Et0 - 7 '5Et0 All less than LLD Al I less than LLD

TABLE 2-1 (cont,)

ENVIRONHENTAL RADIOLOGICAL HONITORING PROGRAH SUHHARY Shearon tlarrls Nuclear Power Plant Make County, North Carolina Docket Number:

STN 50-400 Calendar Year:

1986 Hedium or Pathway Sampled or Heasured (Unit of Heasurement)

Fish (pCI/g wet)

Bottom Feeders Free-Swimmers (pCi/g wet)

Type and Total No, of Heasurements Performed Gamma Cs-134 Cs-137 Gamma Typical Lower Limit of Detection (LLD) 5,4E-2 4 ~ IE-2 5,4E-2 All Indicator Locations Hean Ran e

All less than LLD All less than LLD All less than LLD

Name, Distance, and Direct Ion All less than LLD Hean Ran e

All less than LLD All less than LLD Location w/III hest Annual Hean Control Locations Hean Ran e

3 74E-2 (I/2)

Single Value 2 31E-I (I/2)

Single Value 1,76E-I (I/2)

Single Value Food Crop (pCI/g wet)

Groundwater (pci/I )

Cs-134 Cs-137 Gamma Cs-137 Gamma Tritium 4 ~ IE-2 1,6E-2 Refer to Table 6-1 1,2Ei3 3,80E-2 (I/2)

Single Value 3.05E-2 (I/2)

Single Value All less than LLD All less than LLD Site varies within Harris Reservoir James

~ Rest Home 2,3 mlles NE All less than LLD All less than LLD 3,80E"2 (I/2)

Single Value 3 05E-2 (I/2)

Single Value 6 ~ 18E" I

( I/2)

Single Value Al I less than LLD All less than LLD All less than LLD Hilk (pCI/I) 1-13'I 96 Gamma 96 Cs-137 I-131 3,0E-I 4,7EOO 4.0EiO 4,9IEtO (8/72) 4 ~ 53E-I - 1,74E+I 6.19E<0 (10/72) 2,95EtO - I,36Etl I ~33E+I (3/72) 6.53E~O 2.34E+I Goodwin ~s Dairy 2.2 mlles N

Goodwin ~s Dairy 2,2 miles N

Goodwin's Dairy 2.2 miles N

7 '9EtO (3/24) 8,20 I 74E>l I ~ 12E>I (2/24) 8,7IE>0 - I.36EtI 2 34E+I (I/24)

Single Value 2,06EtO (4/24 )

3 07E-I -5,67EiO All less than LLD 8.84EtO (I/24)

Single Value

TABLE 2-1 (cont.)

ENVIRONHENTAL RADIOLOGICAL HONITORING PROGRAH SUHHARY Shearon Harris Nuclear Power Plant Make County, North Carolina Docket Number:

STN 50-400 Calendar Year:

1986 Hedlum or Path~ay Sampled or Heasured (Unit of Heasurement)

Type and Total No. of Heasurements Performed Typical Lower Limit of

'etection (LLD)

All Indicator Locations Hean Ran e

Name, Distance, and Direction Hean Ran e

Location w/Hl hest Annual Hean Control Locations Hean Ran e

Bottom Sediments (pCI/g dry)

Shoreline Sediments (pCI/g dry)

Surface Mater (pCI/I)

Direct Radiation (mR/week)

Gamma Cs-137 Gamma Cs-134 Cs-137 1-131 134 Gross Beta 36 Gamma 36 Tritium 36 TLD 159 3 ~ IE-2 5,0E-2 3 ~ IE-2 3,0E-I B,OE-I Refer to Table 6-1 1.2Ei3 I,OE >0 3 ~ 18E-I (2/2) 2,33E-I - 4,04E-I 2,60E-2 (I/4)

Single Value 3,90E-2 (I/4)

Single Value 3,23E-I (6/82) 1.03E-I 4,80E-I 4 ~ 50EtO (24/24) 2,88EtO - 8,88EtO All less than LLD All less than LLD I ~ 12Eto (155/155) 8,0E-I - 1,7EtO Harris Reservoir 3.8 miles S

Harris Reservoir 4.6 mlles S

Harris Reservoir 4.6 ml les S

Llllington Cape Fear River 17 mlles SSE Lllllngton Cape Fear River 17 miles SSE All less than LLD All less than LLD US I 8 SR 1149 4,7 miles NE 3 ~ 18E-2 (2/2) 2,33E-I - 4,04E-I 2,60E-2 (I/4)

Single Value 3,90E-2 (I/4)

Single Value 3,83E-I (4/52) 2,98E-I - 4,80E-I 5,03EtO (12/12) 2,94E<0 8,66EtO I.47E40 (4/4)

I ~ 3EtO - I,7E>0 No control No control No control 2,74E-I (2/52) 1.65E-I 3,83E-I 4 84E<0 (12/12) 2,69EtO - 7 ~ 35EtO Al I less than LLD All less than LLD I,07EiO (4/4) 9,0E-I -

I ~ 3E<0

~

I NOTATIONS FOR TABLE 2-1 1.

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

4.66 s

LLO =

E V. 2.22 Y. exp (-x t )

i e Where:

LLO

= Lower limit of detection in pCi per unit volume or mass sb

= (N/tb)

= Standard deviation of the background (cpm)

I/2 N

= Background count rate (cpm)

~

tb

= Background count time (min)

~ 'I

II 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 LLO values for the gamma spectrometry system.

This expression is not used for direct radiation measurements.

2.

Mean and range are based on detectable measurements only.

The fractions of detectable measurements at specific locations are indicated in paren-theses.

~ y 3.

Measurements are in excess at 99.5 percent confidence limit of ten times the control station value or ten times the lower limit of detection, whichever is larger.

2-6

~

P 4.

Refer to Section 4, Missing Samples and Analyses.

5.

No man-made radioactivity detected.

6.

Bottom sediment sampling is not required by the technical specifications but performed to better characterize the radiological characteristics of this environmental medium.

7.

Food crops consisted of collards,

beans, and peas.

8.

Although quarterly composite samples are

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

2-7

3.0 INTERPRETATIONS AHO CONCLUS IOHS Ll

~A' Analysis of 257 air cartridge samples from indicator locations re-vealed an average I-131 concentration of 9. 13E-02 pCi/m from 23 of 3

257 samples.

The control samples presented a similar distribution averaging 9;49E-02 pCi/m for 4 of 52 samples.

The I-131 activity was observed after the Chernobyl accident (April 26, 1986) for ap-proximately six weeks and was consistent with concentrations ob-served by the environmental sampling programs from other CPKL faci-lities.

All other radionuclide analyses for the year were less than their respective lower limits of detection

(< LLO).

Gross beta measurements in airborne particulate samples from the five indicator locations had an average concentration of 2.82E-02 pCi/m in 257 of 257 samples.

Similar gross beta activity was ob-served at the control location in Pittsboro at an average concen-tration of 2.75E-02 pCi/m in 52 of 52 samples.

These concen-trations may be compared to the 1985 indicator and control values of 1.46E-02 pCi/m and 1.39E-02 pCi/m

, respectively.

If the concen-3 3

trations from the five weeks of elevated activity after the Chernobyl accident are

excluded, the resulting gross beta average for 1986 for the indicator locations would be 1.80E-02 pCi/m.

Figures. 3-1 through 3-5 provide a

graphic representation of the gross beta activity compared to time (January Oecember 1986).

The prominent peak which occurs is the result of the Chernobyl accident.

The solid line is the indicator

location, while the broken line is the control location.

L2

~BI k1 il*t Orinking water samples collected during 1986 contained I-131 at a

concentration of 3.83E-1 pCi/liter in 4 of 104 samples from indi-cator locations.

The control samples collected from the Cape Fear 3-1

~

River above the Suckhorn Dam contained I-131 in 2 of 52 samples at a

concentration of 2.74E-1 pCi/liter.

All I-131 activity occurred during the six-week period after the Chernobyl accident.

Excluding this

period, all I-131 values were less than the lower limit of detection.

Figures 3-6 and 3-7 provide a graphic representation of the gross beta activity during 1986 for locations 40 (Lillington) and 51 (SHNPP site).

The solid line is the indicator location, while the broken line is the control location.

Average gross beta concentrations at the indicator and control lo-cations were similar with concentrations of 4.06E+0 and 4.84E+0 pCi/liter, respectively.

The 1985 concentrations for the indicator and control locations were 3.22E+0 and 3.58E+0 pCi/liter, respectively.

Increased gross beta activity was observed during the six weeks after the Chernobyl accident and was the major influence that increased the annual. average above the previous norm.

Analyses for tritium and gamma-emitting radionuclides indicated all concentrations were less that the lower limit of detection for drinking water.

Table 6-1 contains typical LLD values for gamma-emitting radionuclides.

Doses from the ingestion of drinking water during the six-week period after the Chernobyl accident were calculated for the Lilling-ton water sample using guidance provided by Regulatory Guide 1.109 criteria for the most critical organ of the maximum individual.

For I-131, the critical organ for all age groups is the thyroid.

The highest possible dose was 0.2 mrem/yr to the infant for the consump-tion of 38 liters of untreated water from the Cape Fear River.

3.3 Fish Analyses for gamma-emitting radionuclides in bottom-feeding fish (catfish) from the indicator

location, Harris Reservoir, revealed 3-2

~

concentrations were less than the lower limit of detection;

however, Cs-134 and Cs-137 were detected in one of two control samples col-lected from the Cape Fear River at concentrations of 3.74E-02 and 2.31E-1 pCi/gram, wet, respectively.

Samples of free-swimming species (sunfish and largemouth bass) were analyzed and found to contain Cs-137 at a concentration of 3.80E-2 pCi/gram, wet, in one of two indicator samples.

Cs-137 was detected in one of two control samples at a

concentration of 6.18E-1 pCi/gram, wet.

The control sample also contained Cs-134 in one of two samples at a concentration 1.76E-l pCi/gram, wet.

The Cs-134 most likely results from the Chernobyl accident.

The Cs-137 acti-vity is likely from fallout from nuclear weapons testing in previous years.

Doses from the consumption of fish were calculated for Cs-134 and Cs-137 for the critical organ of the maximum individual using guid-ance provided by Regulatory Guide

1. 109.

For Cs-134, the critical organ for the age groups was the liver.

The highest dose from eat-ing the maximum quantities of fish was 0.55 mrem/yr.

For Cs-137, the liver was the critical organ for the teen and adult, while the bone was the critical organ for the child.

The maximum possible dose was to the teen at 1.47 mrem/yr.

The calculations and para-meters are provided in Section 3.11.

3.4 Food Food crops are required to be collected when a milk sampling program cannot be performed.

Even though the milk sampling program was performed for three indicator dairies and one control dairy, food product samples were collected for historical data.

The three crops sampled during August were collards,

beans, and peas.

Gamma spectrometry analysis of food crops detected Cs-137 at a con-centration of 3.05E-02 pCi/gram,

wet, in one of two indicator samples.

The control sample activity for man-made radionuclides was 3-3

~

J less than the lower limit of detection.

The Cs-137 activity is due to fallout from nuclear weapons testing during previous years and is not attributable to plant operations.

Oose calculations were performed for the critical organ of the maxi-mum individual using guidance provided by Regulatory Guide

1. 109.

The critical organ for the adult and teen is the liver, while the bone is the critical organ for the child.

The maximum possible dose from Cs-137 for consuming 26 kilograms of broadleaf vegetables dur-ing the year would be 0.26 mrem.

The calculations and parameters are provided in Section 3. 11.

3.5 Groundwater Groundwater samples are collected and analyzed for gamma-emitting radionuclides and tritium.

All concentrations of man-made radio-nuclides were less that the lower limit of detection.

6.6

~ktlk 6 I-131 was detected in 8 of 72 milk samples from indicator locations at a concentration of 4.91E+0 pCi/liter.

Control samples, collected from the Strowd Oairy near Pittsboro, contained I-131 in 4 of 24 samples at an average concentration of 2.06E+0 pCi/liter.

All of the I-131. was detected in the six weeks after the Chernobyl acci-dent.

Using the model provided by Regulatory Guide 1. 109, the dose commitments from the Chernobyl I-131 are provided in Section 3.11.

The doses are calculated for the maximum individual (thyroid) at an average concentration of 3.96 pCi/liter.

Gamma isotopic analyses revealed Cs-. 137 and I-131 at average concen-trations of 6. 19 and 13.3 pCi/liter, respectively, in the indicator samples.

I-131 was observed in the control location at an average concentration of 11.2 pCi/liter.

3-4

3.7 Bottom Sediment Samples of bottom sediment were collected near the discharge of the cooling tower blowdown pipe semiannually.

Both samples contained Cs-137 at an average concentration of 3.18E-1 pCi/gram, dry.

This can be compared to the 1985 average concentration of 2.30E-1 pCi/g, dry.

The Cs-137 is attributable to fallout from past atmospheric nuclear testing.

3.8 Shoreline Sediment Shoreline sediments were collected and analyzed for gamma-emitting radionuclides.

Both Cs-134 and Cs-137 were present in one of four samples at a concentration of 2.60E-2 pCi/g and 3.90E-2 pCi/g, re-spectively.

These results occurred in the sample collected in August.

Since fuel was not on site at that time, the Cs-134 activ-ity can likely be attributed to the Chernobyl accident.

Cs-137 activity is the result of fallout from past atmospheric nuclear testing.

3.9 Surface Water Surface water samples were collected and analyzed weekly for I-131.

Water samples collected during 1986 contained I-131 at a

concentration of 3.23 pCi/liter in 6 of 82 samples from indicator locations.

The control location had I-131 at a concentration of 2.74E-l pCi/liter in 2 of 52 samples.

All samples containing I-131 activity occurred during the six-week period following the Chernobyl accident.

Excluding this six-week period, all I-131 surface water concentrations were less than the lower limit of detection.

Average gross beta concentrations at the indicator and control loca-tions were 4.50E+0 pCi/liter and 4.84E+0 pCi/liter, respectively.

The 1985 gross beta concentrations were 3.26E+0 pCi/liter and 3-5

3.58E+0 pCi/liter for indicator and control locations.

Elevated gross beta activity was observed during the six weeks following the Chernobyl accident.

Figures 3-8 and 3-9 provide a graphic representation of the gross beta activity in surface water during 1986 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 radionuclides were less than the lower limit of detection.

3.10 External Radiation Ex osure e 4

~ ~

-f Thermoluminescent dosimeters were used to monitor ambient radiation exposures in the environs.

The average weekly dose rate from the indicator locations were

1. 12 mrem per week for 155 of 155 TLO meas-urements and 1.07 mrem per week from the control location.

The 1985 average dose rates were 1.11 mrem per week and 0.93 mrem per week for indicator and control locations, respectively.

3.11 DOSE COMMITMEHTS FROM CHERHOBYL Dose commitments for the I-131 from the Chernobyl accident are as follows:

Dose to Thyroid (I-131)

Adult Teen Child Infant Dose due to Milk Ingestion (mrem)

Dose due to Air Inhalation (mrem)

Dose due to Drinking Water (mrem)

Total Thyroid Dose (mrem) 0.13 0.15 0.17 0.16 0.20 0.13 0.05 0.06 0.61 0.72 1.08 2.31 0.28 0.44 0.86 2.09 3-6

Oose due to Fish Ingestion Cs-134 (mrem)

Oose to Liver Adult Teen Child Infant 0.55 0.55 0.47 Oose due to Fish Ingestion Cs-137 (mrem) 1.4 1.47 1.33 Oose due to Food Crops Cs-137 (mrem)

Total Oose to Liver (mrem) 2.17 2.21 2.05 0.21 0.18 0.25

No significant ingestion assumed by this pathway Figure 3-10 is a graphic representation of the gross beta activities for 1986 (solid line),

1977 Brunswick Nuclear Project (dotted line),

and 1977 Robinson Nuclear Project (broken line).

The increased activities from Chernobyl are seen on the solid line from early Hay until mid June.

The large peaks on the dotted and broken lines are the result of atmospheric bomb testing performed by the Peoples Republic of China during 1977.

The increases in gross beta activity from the Chernobyl accident are significantly less than the in-creases in gross beta activity from the Chinese nuclear tests.

3-7

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4.0 MISSING SAMPLES ANO ANALYSES 4.1 Air Cartridge and Air Particulate AC/AP-02 February 24, 1986 Low volume due to sampler malfunction AC/AP-01 March 10, 1986 Low volume due to sampler malfunction AC/AP-02 April 01, 1986 Low volume due to tripped breaker 4.2 Surface Water/Or inking Water Technical specifications require I-131 analysis on drinking water samples.

The drinking water sample collected from Lillington (OW-

40) is also a surface water sample (SW-40).

Orinking water samples require I-131, gross

beta, gamma spectrometry, and tritium analyses.

Surface water samples require only gamma and tritium analyses.

I-131 analyses were performed on the surface water samples from the Harris Reservoir (SW-26) through July 1986.

Thirty samples were analyzed from this location.

A total of 134 surface water samples was analyzed for I-131.

The gamma and tritium analyses are performed monthly.

4.3 Thermoluminescent Oosimeters (Oirect Radiation)

TLO-24 7LO-31 TLO-27 TLO-14 TLO-31 First quarter 1986 Second quarter 1986 Third quarter 1986 Fourth quarter 1986 Fourth quarter 1986 Missing in field at time of collection Missing in field at time of collection Missing in field at time of collection Hissing in field at time of collection Hissing in field at time of collection 4-1

5.0 LAHO-USE CENSUS 5.1 Introduction The Technical Specifications for the Shearon Harris Nuclear Power Plant (SHNPP) require that an annual land-use census be conducted within a

five-mile radius of the site.

Technical Specification 4.12.2 specifies that the census shall be conducted during the growing season using that information that will provide the best results such as by a door-to-door

survey, aerial

survey, or by consulting local agricultural authorities.

The 1986 land-use census was conducted during August and September 1986.

5.2

~R Technical Specification 3.12.2 requires:

A.

The survey is to be conducted within a five-mile radius of the plant.

B.

The survey shall be conducted annually.

C.

The survey in each of the 16 compass sectors shall identify the nearest:

1.

Milk animal.

2.

Residence.

3.

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

These requirements were supplemented with identification of the nearest meat animals in each of the 16 compass sectors.

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5.3 Methods In accordance with this guidance, the 1986 land-use census was conducted using a door-to-door survey method.

A standard questionnaire was used during an interview to record pertinent data.

Resident and road locations were located within the 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 photographs of that time and represent recent locations of struc-tures and roads in this locale.

Moncure, Cokesbury, Fuquay-Varina, Merry

Oaks, New Hill, and Apex quadrangle maps were used.

The maps were com-

bined, 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 residence.

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 inter-views with residents within the five-mile radius zone.

The survey was performed by CPEL during August and September.

The survey was conducted during fair weather and visibility was good.

The survey started close to the plant in each sector and extended out to the five-mile perimeter.

Roads within the five-mile zone were traveled.

8arns, small

sheds, and pasture-like fields were observed as indicators of grazing livestock.

These indicators were followed up with an interview with the owner of the property.

In some cases when the owner was not

home, a neighbor was interviewed to obtain the desired information.

If this was not possible, the property was revisited at a later time or information was determined by visual inspection.

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5.4 Results Table 5-1 summarizes the locations of the nearest milk cow, milk goat, meat

animal, residence, and garden in each of the 16 compass sectors.

The data resulted from 149 recorded visitations and permitted the follow-ing observations:

A.

Milk goats were not located within the five-mile radius.

B.

Milk cows are located in the N and NNE sectors.

These loca-tions are commercial dairies that are currently part of the SHNPP environmental sampling program.

Refer to Table 5-2.

C.

Heat animals are found in 13 of the 16 compass sectors and are summarized in Table 5-3.

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TABLE 5-1 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE SHEARON HARRIS NUCLEAR POWER PLANT {MILES)

Sector N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Exclusion

~Bounder 1.32 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.36 1.33 1.33 1.33 1.33 1.33 1.26 1.26 Residence 2.1 1.7 2.3 2.0 1.9 2.7 4.1 4.4 3.9 2.8 4.3 2.7 2.1 1.8 1.5 Milk Cow 2.1 4.6 Milk Goat Garden 2.1 1.7 2.3 4.3 4.6 2.7 4.1

> 5.0

> 5.0 4.4 4.8 4.3 3.0 3.0 1.8 1.9 Meat Animal 2.1 1.9 2.3 2.0 4.6 4.3 4.4 2.8 4.3 3.1 2.1 1.8 1.9 As of September 10, 1986.

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

5 4 h

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TABLE 5-2 LOCATIONS WITHIN 5-MILE RADIUS ZONE OF SHNPP MILK ANIMAL Sector N

Distance

~Mi1es

+

2.1 Milk Anima1 Cow Animal or Milk

~Usa e

Commercial and Private*"+

Age Structure of Immediate Consumers~

Adult, Teen NNE 4.6 Cow Commercial and Private***

Adult, Child

Distance estimates are +/- 0.1 mile.

~If information available.

~Does not imply consumption.

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TABLE 5-3 MEAT ANIMAL TYPE AT NEAREST LOCATION TO SHNPP BY SECTOR Sector N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Distance Miles

2.1 1.9 2.3 4.3 4.6 4.3 4.4 2.8 4.3 3.1 2.1 1.8 1.9 Meat Animal Hogs Beef Beef, Hogs, Fowl, Goats

Beef, Fowl Beef Hogs Hogs Beef Hogs Hogs Beef

Beef, Hogs, Fowl Beef a~ ~

Oistance estimates +/- 0.1 mile.

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6.0 ANALYTICALPROCEDURES 6.1 Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background Alpha/Beta Counting System.

The LLO for air par-ticulates is approximately 0.0013 pCi/m3 for Robinson and Harris Nuclear Projects and 0.0038 for Brunswick Nuclear Project.

Air particulate samples are mounted in 2-inch stainless steel plan-chets and counted directly.

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 on a liquid scintillation counter for 50 minutes.

The LLO is approximately 1200 pCi/l.

6.3 Iodine-131 Iodine-131 airborne concentrations are quantified by the Ge(Li) gamma spectrometry systems.

The cartridges are placed on the detec-tor and each charcoal cartridge is counted individually with an approximate LLO of IE-2 to 3E-2 pCi/m.

Iodine-131 in milk and 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 beta-gamma coincidence system or by low-background beta counter.

The LLD is approximately 0.3 pCi/liter for milk and 0.4 pCi/1 for water.

6-1

6.4 Gamma S ectrometr Ge Li Gamma spectrum analysis utilizes germanium or Ge(Li) detectors with thin aluminum windows housed 'n steel and lead shields.

The analyzer systems are Nuclear Data 4420 and 6685.

Table 5-1 summa-rizes LLD values derived from instrument sens'itivity based upon a

blank sample background.

Air particulate 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.

Shoreline sediments are

dried, weighed, and then analyzed in a

Marinel 1 i beaker.

Food products and broadleaf vegetation 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

~

~'4 Each area monitoring station includes a

TLD packet, which is a

po lyethylene bag containing three calcium sulfate phosphors con-tained in a Panasonic UD-814 badge.

The TLO is lighttight and the bag is weather resistant.

Oosimeters are machine annealed before field placement.

Following exposure in the field, each dosimeter is read utilizing a Panasonic TLO reader.

This instrument integrates the light photons emitted from traps deexcited above 150'C.

The lower-energy traps are auto-matically eliminated through a

preheat cycle.

Calibration is 6-2

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P 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 approx-imately I 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 8

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.

Ouring

1986, 21 samples representing 3

major environmental media (water, milk, and air filters) and urine were analyzed.

Oata on the known activities and the 3

sigma control limits for 50 of the 52 required analyses have been received from the EPA.

These 21 samples required triplicate determinations of the concentrations of radio-nuclides.

A comparison of the average of our reported values with the EPA known activity and its standard deviation can be summarized as follows:

Standard Oeviation (sigma)

From Known Activit Percent of Anal ses 1 sigma

< 2 sigma

< 3 sigma 44 80 94 6-3

~

Of the 50 determinations, 3

(6 percent) fell outside the 3

sigma control limit.

In April and September of 1986, analyses of filters for gross beta activity were 20.6 percent and 23.7 percent higher than the known

values, respectively.

The CP&L values were calculated using an efficiency determined with a Cs-137 standard.

The unknown contained Cs-137 and Sr-90.

When the gross beta analysis was recalculated using a Sr-90 standard for the efficiency, the resultant analytical values were within an acceptable range of less than or equal to 2.0 (April) and 1.5 (September) normalized deviations of the true values.

Resolution of the problem was achieved by performing two new gross beta efficiency calibrations using Cs-137 and Sr-90.

The Sr-90 generated efficiency will be used for determining gross beta for EPA comparison purposes.

~

e In October, an EPA water sample contained Ru-106.

CP&L analysis based on a

gamma assay was 18.5 percent lower than the known value.

The values for the other five radionuclides were less than or equal to 2.5 times the normalized deviation from their respective known values.

Ru-106 is determined using a low-abundance peak (9.8 percent) at 621.8 kev.

An improved software version is being in-stalled into the N06685 system that can perform a

more sensitive analysis thereby improving the analytical efficiency and reli-ability.

6.7 Lower Limits of Detection Typical "a priori" LLO values for the samples analyzed are listed in Table 6-1.

6-4

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

Ge(Li) Ganrna Spectrometry Surface Water Sam les*

res wa er Isotope Cr-51 Mn-54 Co-58 Co-60 Zn-65 Zr-Nb-95 I-131 Cs-134 Cs-137 La-140 Other Expected Gamma Emitters (LLD) 28 pci/1 6

4 7

11 5

4 5

5 7

2 122 Isotope Air Particulates*

(quarterly Composite)

(LLD)

Cs-134 Cs-137 8a-140 La-140 Other Expected Gamma Emitters 0.0068 pCi/cubic meter 0.0057 0.039 0.015 0.0035 to 0.063

The sample activities were decayed from the middle of the sampling period rather than from the end of the sampling period.

This resulted in LLD values that appear higher than values calculated from the end of the period.

6-5

Isotope Cr-51 Mn-54 Co-58 Co-60 Cs-134 Cs-137 La-140 Groundwater Sam les (LLD) 19 pCi/1 3.4 3.0 4.0 4.0 3.4 4.5 Other Expected Gamma Emitters 0.21 to 116 Mi 1 k (gamma scan)

Isotope (LLD)

Cr-51 Mn-54 Co-58 Co-60 I-131 Cs-134 Cs-137 La-140 Other Expected Gamma Emitters 33 pci/1 5

3.8 6.4 4.0 5.8 4.7 6.7 2.7 to 53 6-6

~ ~

Shoreline Sediments Isotope (LLO)

Cr -51 Mn-54 Co-58 Co-60 Cs-134 Cs-137 Other Expected Gamma Emitters 201 pCi/kg 33 33 55 50 31 19 to 721 Fish Isotope (LLD)

Cr-51 Mn-54 Co-58 Co-60 Zn-65 I-131 Cs-134 Cs-137 Other Expected Gamma Emitters 248 pCi/kg 46 36 20 83 24 54 41 18 to 690 6-7

Food Products and Ve etation Isotope (LLD)

Cr-51 Mn-54 Co-58 Co-60 I-131 Cs-134 Cs-137 Other Expected Gamma Emitters 120 pCi/kg 18 19 19 14 19 16 9 to 248 6-8

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ML18004B812

Text

SUMMARY

SUMMARY

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