ML18010B083

Radiological Environ Operating Rept,1992 for Shearon Harris Nuclear Power Plant

ML18010B083
Person / Time
Site:	Harris
Issue date:	12/31/1992
From:	Vaughn G CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-930082, NUDOCS 9305040274
Download: ML18010B083 (96)

Text

...ACCELERAT DOCUMENT DISTRmUTION SYSTEM REGULAT.

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FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION VAUGHN,G.E.

Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION 5CC ~c//~3 A~

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SUBJECT:

"Radiological Environ 0

'pt,1992 For Shearon Harris Nuclear Power Plant."

/930429 r.

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Carolina Power & Light Company P.O. Box 165 ~ New Hitl, NC 27562 G.E.VAVGHN Vice President Harris Nuctear Plant APR 2 9 l99>

Letter Number:

HO-930082 NRC-810 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO.

50-400 LICENSE NO. NPF-63 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Gentlemen:

In accordance with Technical Specifications 6.9.1.3 for the Shearon Harris Nuclear Power Plant, Unit No.

1, Carolina Power and Light Company herewith submits the enclosed Annual Radiological Environmental Monitoring Report for 1992.

G.

E.

Vaughn'icePresident Harris Nuclear Plant MGW:dmw Enclosure cc:

Mr. S.

D. Ebneter (NRC-RII)

Mr. J.

E. Tedrow (NRC-SHNPP)

MEM/HO-930082/1/OS1 930S040274 92i231 PDR ADOCK OS000400 R

PDR 030075

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a ioo ica nvlrOAITlen a era jn e or 1992 HARRIS NUCLEAR PROJECT CAROLINAPOWER & LIGHT

..9305040274

Harris Energy 4 Environmental Center Carolina Power 4 Light Company New Hill, North Carolina RADIOLOGICALENVIRONMENTALOPERATING REPORT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT JANUARY 1 THROUGH DECEMBER 31, 1992 Prepared by:

Reviewed by:

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TABLE OF CONTENTS able of Contents..............................

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o lll List of Tables

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v 1.0

SUMMARY

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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

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3.2 Drinking Water..... ~......

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o 3-2 3.4 Surface Water.......................

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3 2 3.5 Groundwater...........................

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3 3 3.7 Bottom SedIment......,,...,............................

3-3 3.8 Shoreline Sediment...............,,...................,

3-3 3.9 Food Crops..........

3.10 Aquatic Vegetation...

3.11 External Radiation Exposure..

3.12 Comparison with Preoperational

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and 1991 Operational Data

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~ 3 4 4.0 MISSED SAMPLES AND ANALYSES...........................

4-1 4.1 Air Cartridge and Air Particulates 4-1 4.2 Food Crops.......

4-1 4 ~3 TLDs

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5.0 LAND-USE CENSUS.......

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5 1 5.1 Introduction

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5.2 Requirements

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TABLE OF CONTENTS (continued) 5.3 Methods...

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.4 Results....

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6.0 ANALYTICALPROCEDURES................................

6-1 6 ~1 Gross Beta

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,2 Trltlum...................,.........................

6-1 6-1 6 ~3 Iodnle 131 ~...,,

6 1 6.4 6.5 6.6 6.7 Gamma Spectrometry Thermoluminescent Dosimetry..

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

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LIST OF FIGURES

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~Pa e 2-1 Shearon Harris Nuclear Power Plant-Radiological Environmental Sampling Points.................................

2-7 2-2 Shearon Harris Nuclear Power Plant-Radiological Environmental Sampling Points...,..........

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2 8 2-3 Shearon Harris Nuclear Power Plant-Radiological Environmental Sampling Points..............,..................

2-9 2-4 Legend for Figures 2-1, 2-2, 2-3....................

2.10 3-1 Gross Beta Activityfor AirParticulate Samples (Sample Point 0001)......

3-9 3-2 Gross Beta Activityfor AirParticulate Samples (Sample Point 0002)......

3-10 3-3 Gross Beta Activityfor AirParticulate Samples (Sample Point 0004)......

3-11 3-4 Gross Beta Activityfor AirParticulate Samples (Sample Point 0026)......

3-12 3-5 Gross Beta Activityfor Air Particulate Samples'(Sample Point 0047)......

3-13 3-6 Gross Beta Activityfor Drinking Water Samples (Sample Point 0040).....

3-14 3-7 Gross Beta Activityfor Drinking Water Samples (Sample Point 0051).....

3-15 3-8 Tritium Activityfor Drinking Water Samples (Sample Point 0040)........

3-16 3-9 Tritium Activityfor Drinking Water Samples (Sample Point 0051)........

3-17 3-10 Gross Beta Activityfor Surface Water Samples (Sample Point 0026)......

3-18 3-11 Gross Beta Activityfor Surface Water Samples (Sample Point 0040)......

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3-12 Tritium Activityfor Surface Water Samples (Sample Point 0026).........

3-20 U:iOSUgKPgFS52HNPREO.REP

LIST OF FIGURES (Continued)

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~Pa e 3-13 Tritium Activityfor Surface Water Samples (Sample Point 0040).........

3-21 3-14 Iodine-131 Activityfor MilkSamples (Sample Point 0005)..............

3-22 3-15 Iodine-131 Activityfor MilkSamples (Sample Point 0042)..............

3-23 3-16 Iodine-131 Activityfor MilkSamples (Sample Point 0043) 3-24 3-17 Gamma Activityfor Bottom Sediment Samples (Sample Point 0052) '......

3-25 3-18 Gamma Activityfor Shoreline Sediment (Sample Point 0041)...........

3-26 3-19 Gamma Activityfor Aquatic Vegetation Samples (Sample Point 0026).....

3-27 3-20 Gamma Activityfor Aquatic Vegetation Samples (Sample Point 0041).....

3-28 3-21 TLD Averages for Inner and Outer Ring Locations

.. 3-29 U:iosTRREPCZS52HNPREO.REP lv

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LIST OF TABLES.

Table

~Pa e 1-1 Radiological Environmental Monitoring Program Data Summary.........

1-3 2-1 Radiological Environmental Monitoring Program....................

2-4 5-1 Distance to the Nearest Special Locations from the Shearon Harris Nuclear Power Plant (miles)........................

5-4 5-2 Meat Animal %ape at Nearest Location to the Shearon Harris Nuclear Power Plant by Sector..................................

5-5 6-1 Typical Lower Limits of Detection (a priori)

Gamma Spectrometry.....

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1.0

SUMMARY

This report presents the results of the Radiological Environmental Monitoring Program conducted during 1992 for the Shearon Harris Nuclear Power Plant (SHNPP) and fu1611s the reporting requirements of Technical Speci6cations 6.9.1.3.

The program was conducted in accordance with Technical Speci6cation 4.12.1, the Off-Site Dose Calculation Manual and applicable procedures, Approximately 950 samples of 12 different media types f'rom indicator stations were compared to approximately 250 control samples.

Aquatic vegetation (Hydrilla verticillata) in Harris Lake was added to the sampling program to serve as a possible indicator of long-term radionuclide buildup. No detectable activity or activities not differing &om the corresponding control samples occurred in 95 percent of the indicator samples.

Radioactivity in environmental samples which could be attributed to plant operations in 1992 is as follows:

",":s,-'::;,.'";,;- '~,',;"" '. "'.,'Q':,.'~:;

,'.:;i',.-,::"...'I.:':::;!Enylroi'i'm'e'iital':,i'.':,.,I',:I,::;::,':

-'-';":.:;':::::-;-"'<<%8'='Media4""e:"~'-:4 i:-':4Radion<<uclidevk>>'::.'ai'id'.: Occu'rre'iice~;:::

"': 'i".'-.':In'diyldii'il<g',:i'j Harris Lake Surface Water Fish SHNPP Drinking Water Hams Lake Shoreline Sediment Harris Lake Bottom Sediment Harris Lake Aquatic Ve etation H-3 H-3 H-3 Cs-137 Mn-54 Co-57 Co-58 Co-60 Cs-137 Sb-125 Co-58 1.11 E+4 pCi/Z.

(16/16)

See above 7.54 E-I pCi/8 12/12 6.72E-2 Ci/g I/

7.93E-I pCi/g 8/4) 1.67E-I pCi/g (3/4) 1.81E+0 Ci/

(4/4) 3.08E+ I pCi/g (4/4) 3.68E-I pCi/g (4/4) 1.98E+0 pCi/g 3/4 6.51E-2 Ci/g 2/2 No ingestion pathway.

No dose calculated.

0.02

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0.21 (T.B) 3.1E-4 (T.B.)

No dose calcu-lated'as water shielding elimi-nates dose at surface.

No dose calculated U:iosthREPCSQ91HNPREO.REP

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Overall, the radiological environmental data indicates that SHNPP operations in 1992 had no signi6cant impact on the environment or public health and safety.

A statistical summary of all the data for 1992 has been compiled and summarized in Table 1-1.

The only impact of the plant on the environment in its six years of operation has been (1) a slow but steady increase in the annual average tritium activity in Harris Lake water from 3.4E+3 pCi/8 in 1987 to 1.1E+4 pCi/8 in 1992 and (2) the accumulation of activation products (primarily cobalt and manganese) in bottom sediment near the cooling tower discharge point. No plant-related activity has been detected in Qsh 'collected from Harris Lake or in the community drinking water supply downstream at Lillington, N.C.

U:foslRREPgFS51HNPREO.REP 1-2

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1-1 RADIOLOGICALENVIRONMENTAL ITORING PROGRAM DATA

SUMMARY

Shearon Harris Nuclear Power Plant Wake County, North Carolina Docket Number:

STN 50400 Calendar Year:

1992 AirCartridge (pa/m )

I-131 3IP>

8.0F 3 Allless than LLD Allless than LLD Allless than LLD AirParticulate.

Gross Beta 3lif'>

1'-3 1.17E-2 (259/259) 3.06E 2.91E.2 SR 1912 3.4 miles SSW 130E.2 (52/52) 435E 3 - 286E-2 1.12E.2 (52/52) 5.17E.3 - 256E-2 Gamma 24 Refer to Table 6-1 Allless than LLD Allless than LLD Allless than LLD Drinking Water (pQ/1) 1-131 156 4.0E-1 Allless than LLD Allless than LLD Allless than ILD Gross Beta 36 2.0E+0 3.99E+0 (24/24)

Ullington 4.79E+0 (12/12) 4.99E+0 (12/12) 2.24E+0 - 6$7E+0 Cape Fear Rher 230E+0 - 6$E+0 239E+0 - 7A8E+0 17 miles SSE Gamma 36 Refer to Allless than LLD Allless than LLD Table 6-1 Allless than LLD Tritiuin ICE+3 754E+3 (12/24)

SHNPP site 754E+3 (12/12)

Allless than LLD 553E+3 - 934E+3 0.1 mile SSW 553E+3 - 934E+3 Fish Bottom-Feeders (pCI/g, wet)

Gamma 4

Refer to Allless than LLD Allless than LLD Allless than LLD Table 6-1 Free-Swimmers (pa/g, wet)

Gamma 8

Refer to Allless than LLD Table 6-1 Allless than LLD Allless than LLD U:~OSUQEPCSS52HNPREO

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TAB (cont.)

RADIOLOGICALENVIRONMENTAL TORING PROGRAM DATA

SUMMARY

Shearon Harris Nuclear Power Plant Wake County, North Carolina Docket Number:

STN 50400 Calendar Year:

1992 Food hp (pQ/8, wet)

Gamma 44Cs)

Cs-137 323E-2 (3/27)

SR 1167 323E-2 (3/14)

Allless than LLD 1.9E-2 3.03F 2 - 3.61E-2 1.7 miles NNW 3.03F 2 - 3.61E-2 Groundwater (pQ/1)

Gamma 20 Refer to Table 6-1 Allless than LLD Allless than LLD No control Milk (pQ/I)

Tritium 20 1-131 72 le+3 Allless than LLD 4.0E-1 Allless than LLD Allless than LLD No control Allless than LLD Allless than LLD Gamma 72 Refer to Table 6-1 Allless than ILD Allless than LLD Allless than LLD Bottom Sediments<'>

(pQ/8 de)

Gamma 4

Mn-54 Co-57 7.93F 1 (4/4)

Harris Lake 7.93F 1 (4/4) 3.1E-2 2.148.1 - 136E+0 38 miles S 2.14F 1 - 136E+0 2.6E 2 1.67E-l (3/4)

Harris Lake 1.67E-1 (3/4) 6.288 2.24E-1 3.8 miles S 6.28E 224E-1 No control No control 181 E+0 (4/4) 2.19E.1 - 338E+0 Harris Lake 1$1E+0 (4/4) 3S miles S 2.19F 1 - 338E+0 No control 23E-2 3.08E+1 (4/4)

Harris Lake 3.08E+1 (4/4) 432E+0 - 5.64E+1 38 miles S 432E+0 - 5QE+1 No control Cs-137 3.1E-2 3.68E-1 (4/4) 3.07F 1 - 4$5E>>1 Harris Lake 3.68E 1 (4/4) 3$ miles S 3.07F 1 - 4$5E-1 No control I

. Sb-125 7.1E-2 1.98E+0 (3/4)

Harris Lake 1.98E+0 (3/4) 1.03E+0 - ESSE+0 38 miles S 1.03E+0 - X55E+0 No control U:iOS~EPCSS52HNPREO

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TAB RADIOLOGICALENVIRONMENTAL (cont.)

ITORING PROGRAM DATA

SUMMARY

Shearon Harris Nuclear Power Plant Wake County, North Carolina Docket Number:

STN 50400 Calendar Year:

1992 Shoreline Sediments (pa/g. dn)

Gamma 8

Cs-137 3.1F 2 6.72E.2 (1/8)

Single Value Harris Lake 3$ miles S 6.72P 2 (1/4)

Single Value No control Surface Water<sXs>

(~)

I-131 104 5.0E-1 Allless than LLD Allless than LLD Allless than LLD Gross Beta 36 2.0E+0 4.10E+0 (24/24)

Llllington 4.79E+0 (12/12) 4.99E+0 (12/12)

ICE+0 - 6ZE+0 Cape Fear River 230E+0 - 6$7B+0 239E+0 - 7A8E+0 17 miles SSE Gamma 36 Refer to Allless than LLD Table 6-1 Allless than LLD Allless than LLD Aquatic Vcgetations (pa/g, wet)

.Tritium 48 Gamma 3

ICE+3 1.08E+4 (24/36)

Harris Lake 1.11E+4 (16/16)

Allless than LLD 4.75E+3 - 1.62E+4 3$ miles S 522E+3 - 1.62E+4 1.7E-2 651E-2 (2J2)

Harris Lake 729E-2 (1/1)

Allless than LLD 5.73E 7.29E.2 3S miles S Single Value Direct Radiation (mR/week)

'KD 1 mR 9.79E-1 (160fl60)

Int SR1149 and IPSE+0 (4/4) 8.75E-1 (4/4) 7.00E 1AOE+0 US 1 4.7 miles 1.10E+0 - IAOB+0 8.00E 9.00E-1 NE U:~OSUQEPQSPg2HNPREO

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FOOTNOTES TO TABLE 1-1

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1.

The Lower Limit of Detection (LLD) is the smallest concentration of radioactive material in a sample that willyield a net count above system background which willbe detected with 95 percent probability and with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

2.

Mean and range are based on detectable measurements only.

The fractions of all samples with detectable activities at specific locations are indicated in parentheses.

3.

Refer to Section 4, Missing Samples and Analyses.

4.

Bottom sediment and aquatic vegetation sampling are not required by the technical specifications, 5.

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

6.

Lake surface waters are only required to be analyzed for tritium quarterly, but composite samples and analyses were performed monthly.

Quarterly grab samples collected at the time of bottom sediment sampling were also analyzed.

These additional analyses were intended to better characterize the impact ofplant operations on Harris Lake.

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2.'0 GENERAL INFORMATION This section (1) describes the pertinent characteristics of the plant and its environs; (2) provides the details ofthe monitoring program including sample locations, types, f'requencies, and analyses; and (3) presents maps showing the distribution ofsampling sites around the plant.

2.1 Plant and Location The Shearon Harris Nuclear Power Plant (SHNPP) is a pressurized water reactor designed to produce 860 MWe (net). Criticalitywas initiallyachieved on January 3, 1987.

The SHNPP site is located in the extreme southwest corner of Wake County, North Carolina.

The plant is approximately 16 miles southwest of Raleigh and approximately 15 miles northeast of Sanford.

This location is on the northwest shore of Harris Lake which is a 4,000-acre reservoir created by the impoundment ofBuckhorn Creek. The reservoir provides process and cooling tower makeup water for the plant and also serves as the receiving body for liquid efQuents such as yard runoff, cooling tower blowdown, and radioactive waste processing system.

The main dam for the reservoir is approximately 4.6 miles south of the plant. The spillway at the dam Qows into Buckhorn Creek which, after Qowing south for approximately two miles, enters the Cape Fear River.

There are no industrial or residential structures on CP&Lproperty. Carolina Power &Light cooperates with various state agencies to provide public access forboating, Qshing, hunting, and other recreational uses on the property'such as boat ramps and access areas.

The majority of the land within scattering of Qelds and residential timber and pulpwood production.

basis within this area including an Qve miles of the site is wooded with a properties.

Much of the land is used for Agricultural activities occur on a limited operating commercial dairy.

The population within ten miles of the plant is, for the most part, considered rural.

Towns in this area with notable populations include Apex, Holly Springs, and Fuquay-Varina (see Figure 2-2).

U:ioSWREPCSS51NHPREO.REP 2-1

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

Major crops include tobacco,

soybeans, and corn for grain.

Livestock production includes

hogs, beef,

poultry, and dairy products, Commercial Gsh and she116sh catches &om waters within 50 miles of the station discharge are negligible.

Recreational Gshing is popular in the area.

Since there are no estuarine or saltwater bodies, sport6shing is confined to

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

2.2 Radlolo cal Environmental Monitorin Pro ram The purposes ofthe SHNPP Radiological Environmental Monitoring Program are to:

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Provide an evaluation ofthe environmental impact ofreleases ofradio-active materials from the plant.

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

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Detect unanticipated pathways for the transport of radionuclides through the environment.

The following locations are designated as control locations for the respective measurements and are intended to indicate conditions away &om SHNPP inQuence:

Pittsboro ) 12 miles NW (Sample Station 5)

Airborne Particulate (Qlter) Samples Charcoal Cartridge Samples-Airborne I-131 Thermoluminescent Dosimeter Area Monitors MilkSamples Food Products UhoslAREPQFS51NHPREO.REP 2-2

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J Ca e Fear Steam Electric Plant 6.1 Miles WSW (Sample Station 38)

Surface Water Samples Drinking Water Samples Upstream of the Buckhorn Dam on the Cape Fear River Site Varies in 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 Speci6cation 4.12,1. Harris Lake bottom sediment and aquatic vegetation

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.

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Tl 2-1 RADIOLOGICALENVIRON AL MONITORING PROGRAM SHEARON HARRIS NUCLEAR POWER PLANT AirCartridge (AC)

I-XS miles N 2-15 miles NNE 4-32 miles NNE 5<<> 12 miles NW>>Pittsboro (Control)s 26-4.6 miles S 47-3.4 miles SSW Continuous operating sam-pling with sample collection at least once per seven days or as required by dust load-mg Weekly 30,000 cu. ft.

(900 cu m) aid if~e~AigaIj~~g 1-131 (charcoal car-tridge)

AirParticulate (AP)

Sediment from Shoreline Bottom Scdimenty SD I-25 miles N 2-15 miles NNE 4-32 miles NNE 5-> 12 miles NW-Pittsboro (Control)s 26-4.6 miles S 47-3.4 miles SSW 26-4.6 miles S 41-3$ miles S 52-3$ miles S Continuous operating sam-pling with sample collection at least once per seven days or as required by dust load-ing 30,000 cu. ft.

(900 cu m)

Quarterly Com ite Semiannually 500g Semiannually 500g Gamma Isotopics Gamma Isotopics Gamma Isotopics Drinking Water (DW)

Groundwater (GW)v Fish (FH)

Food Products (FC) 38-6.1 miles WSW (Control)s 40-17 miles SSE-Iillington 51-0.1 mile SSW-SHNPP Site 39-0.7 mile SSW 57-0.4 mile SSW 58-05 mile WSW 59-05 mile NNE 6~5 mile ESE 44-Stc varies within Harris Lake 45-Site varies in Cape Fear River above Buckhorn Dam 'ontrol S 54-1.7 miles NNE-Wilkins or Morris 55-1.7 miles NNW<<L L Goodwin 5->12 miles WNW, NW( or NNW-Pittsboro Control s During growing season when mdk sampling is not performed Wcckly Monthly Composites Quarterly Semiannually Monthly 8 liters 8 liters 1 kg each Free-Swimmers Bottom-Feeders 1-131 Gamma Isotopics Wltium Gross Beta Tritium Gamma Isotopics Gamma Isotopics on edible portion for each Gamma Isotopics Milk(MK) 42-75 miles SSE-Maple Knoll Dairy 43-22 miles N-Goodwin's Daiy 5->12 miles PV-Strowd's Dairy Control When animals on pasture Semimonthly 8 liters I-131 Gamma Isotopic Surfap Water (SW) 26-4.6 miles S 38-6.1 miles WSW (Control)s 40-17 miles SSE-Lillington Weekly Monthly Composites 8 liters 1-131 Gamma Isotopics Tritium Gross Beta U:$OSUQEPLFS81HNPREO.REP

T 2-1 RADIOLOGICALENVIRON AL MONITORING PROGRAM SHEARON HARRIS NUCLEAR POWER PLANT Anuatic Vegetation (AV)

Direct Radiation Monitors OLD) 26-4.6 miles S 41-3$ miles S 61-25 miles E Control s ILDs I-XS miles N 2-15 miles NNE 3-2.6 miles ENE 4-3.2 miles NNE 5-)12 miles NW-Pittsboro (Control)s 6-0.9 mile ENE 7-Rg mile E 8-tl.7 mile ESE 9-23 miles SE 10-22 miles SSE 11-0.7 mile S 12-0$ mile SSW 13-0.7 mile SW 14-1.4 miles W 15-1.8 miles W 16-1.7 miles WNW 17-1.4 miles NW 18-13 miles NNW 19-4.9 miles NNE 20-4.7 miles NE 21-48 miles ENE 22-4.6 miles E 23-5.0 miles ESE 24-4.7 miles SE 25-48 miles SSE 26-4.6 miles S 27-48 miles SSW 28-4$ miles SW 29-5.6 miles WSW 30-5.1 miles W 31-45 miles WNW 32-6.4 miles NW 33-4.4 miles NNW 34-8.6 miles NE-Apex 35-6.9 miles F -Holly Springs36-112 miles E 37-9.7 miles ESE-Fuquay-Varina 48-45 miles N 49-2.6 miles NE 50-2S miles ESE 53-55 miles NW 56-28 miles WSW Continuous measuremcnt with an integrated readout at least once per quarter Annual Not applicable Gamma Isotopics U:iOSUREPQSS51HNPREO.REP

4

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NOTES TO TABLE 2-1 1,

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

Figure 2-4 provides a legend explaining Figures 2-1 through 2-3.

2.

Particulate samples wiH 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 foHowing Qlter change to allow for radon and radon-daughter decay. Ifgross beta activity is greater than ten times the yearly mean of the control sample station activity, a gamma isotopic analysis willbe performed on the individual samples.

3.

Control sample stations (or background stations) are located in areas that are unaffected by plant operations.

All other sample stations that have the potential to be affected by radioactive emissions from plant operations are considered indicator stations.

4.

Gamma isotopic analysis means the identi6cation and quantitation of gamma-emitting radionuclides that may be attributable to the e61uents from the plant operations.

Composite samples willbe collected with equipment which is capable of collecting an aliquot at time intervals which are very short (e,g., every two hours) relative to the 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.

Bottom sediment and aquatic vegetation sampling and analysis is not required by RETS, Samples are collected to provide additional environmental characterization.

8.

Weekly I-131 analyses are not required for surface water samples.

However, water samples collected at Locations 38 and 40 serve also as drinking water samples.

I-131 analyses are performed on samples &om these two locations, 9.

Groundwater Sampling Locations 57-60 provide additional environmental characterization.

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3.0 INTERPRETATIONS AND CONCLUSIONS 3.1 Air All 311 air cartridge samples from indicator and control stations had I-131 activities which were less than the LLD (see Table 6-1).

Gross beta activity was detectable in all airborne particulate samples from the Qve indicator locations.

The 259 samples had an average concentration of 1.17F 2 pCi/m3.

Similar gross beta activities were observed at the control location in Pittsboro which had an average concentration of 1.12E-2 pCi/m3 in 52 samples.

No gamma activity was detected in quarterly composite Qlter samples &om either the indicator or control locations.

Figures 3-1 through 3-5 provide a graphic representation of the gross beta activity at the indicator locations compared to the control location for the period Janua~ through December 1992.

3.2

~DH Id W

None of the 104 drinking water samples collected at the SHNPP and the Lillington Municipal water supply nor the 52 control samples collected from the Cape Fear River above the Buckhorn Dam contained detectable I-131 activity during 1992.

Figures 3-6 and 3-7 provide graphic representation of the gross beta activity during 1992 for Locations 40 (Lillington)and 51 (SHNPP site). The solid line is the indicator location, while the broken line is the control location at the Cape Fear Plant.

The average monthly gross beta concentrations at the indicator and control locations were similar with activities of 3.99 and 4.99 pCi/I, respectively.

Analyses for gamma-emitting radionuclides indicated all concentrations were less than the lower limitof detection for drinking water.

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

U:>oswRnpcssgl HNpREO.REp 3-1

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Tritium activities in drinking water at the SHNPP, which is drawn &om the Harris Lake, ranged &om 5.5E+3 to 9.3E+3 pCi/L The average activity in 1992 was 7.5E+3 pCi/I. No tritium was detected in the Lillingtonmunicipal water supply or the control station samples.

The total body dose to occupationally exposed personnel at SHNPP from the ingestion of an average activity of 7.5E+3 pCi/i of tritium in drinking water during the year was calculated using the USNRC Regulatory Guide 1.109, Equation A-2. This dose was estimated at 0,2 mrem for the year of 1992.

Figures 3-8 and 3-9 present the tritium activities at the sample locations versus the control values, Ash Analyses for gamma-emitting radionuclides in two samples of bottom-feeding Qsh and in four samples of &ee-swnnming species (sun6sh and largemouth bass) &om the indicator location, Harris Lake, revealed no detectable activity for 1992.

Assuming that the Qsh are in equilibrium with the tritium activity in the lake, the total body dose to the maximum exposed individual due to tritium was calculated by Regulatory Guide 1.109, Equation A-3, to be 0.02 mrem/year.

3.4 Surface Water Surface water samples were collected and analyzed weekly for I-131. Water samples collected during 1992 contained no detectable I-131 (LLD( 5E-01 pCi/1).

Average gross beta concentrations at the indicator and control locations were 4.1 pCi/I and 5.0 pCi/l, respectively.

Figures 3-10 and 3-11 provide a graphic representation of the gross beta activity in surface water during 1992 for Locations 26 (Harris Lake) and 40 (Lillington). The solid line is the indicator location, while the broken line is the control location.

U:ioslRREPCJ$ 51HNPREO.REP 3-2

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I Surface water samples were analyzed for gamma-emitting radionuclides and tritium. Allconcentrations ofman-made gamma-emitters were less than their respective lower limits of detection (see Table 6-1).

Tritium activity was

'etectable in the Harris Lake surface water at an annual average concentration of 1.1E+4 pCi/1.

This value included an additional twelve samples taken in the Harris Lake.

No tritium activity above the LLD of 1.2E+3 pCi/1 was detected in the surface water downstream at Lillington or in the Cape Fear at the control location.

Figures 3-12 and 3-13 present the tritium activities in surface water during 1992.

3.5 Groundwater Groundwater samples are collected on site at SHNPP and analyzed for gamma-emitting radionuclides and tritium.

Concentrations of these radionuclides were aH less than their respective lower limits of detection during 1992.

3.6 Milk Of the 72 indicator and control milk samples taken and analyzed for 1992, none contained detectable concentrations of I-131 or other gamma-emitting radionuclides of plant efQuent origin.

Figures 3-14 to 3-16 present graphical information on the I-131.

3.7 Bottom Sediment Sampling of bottom sediment is not a requirement of the plant technical specifications;

however, samples are collected near the discharge of the cooling tower blowdown pipe to serve as an indicator of plant liquid discharges.

In 1992, four samples were collected.

Activation products of cobalt and manganese were detected in each sample and fallout Cs-137 was also observed.

Sb-125 was detected in three of four samples at an average concentration of 2.0 pCi/g.

Co-60, Co-58, Co-57, and Mn-54 were the predominate nuclides with average concentrations of 30.8, 1.8, 0.2, and 0.8 pCi/g, respectively.

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Figure 3-17 presents the results of these analyses.

3.8 Shoreline Sediment Shoreline sediment samples were collected (1) opposite the discharge structure and (2) near the main dam on four occasions in 1992.

Detectable concentrations of Cs-137 were observed in one ofeight samples collected with a concentration of 6.7E-2 pCi/g.

The dose to the maximum exposed individual was calculated using Regulatory Guide 1.109, Equation A-7, to be 3.1F 4 mrem/year total body.

Figure 3-18 presents the results of these analyses.

M

~FdC In addition to milk sampling, a food product sampling program was maintained.

Various crops were collected during a growing season which basically continued year round. The species selected were primarilybroad-leaf vegetables most sensitive to direct fallout of airborne radionuclides.

Crops sampled in 1992 included mustard greens, turnip greens,

cabbage, collards, broccoli, and tomatoes.

Gamma spectrometry analyses of the 'food crops &om indicator locations detected Cs-137 in 3 of 27 samples at an average concentration of 3.2E-2 pCi/g (wet).

Cs-137 was not detected in 17 control samples.

Since Cs-137 is &equently found in this environment

&om worldwide fallout and the observed concentrations were only slightly above the LLD of 1.9E-2 pCi/g, these concentrations are not considered to be the result of plant eQluents.

3.10 A uatic Ve etation Aquatic vegetation (Hydrilla) was collected &om three locations in Harris Lake in 1992.

Sampling locations were in the vicinity of the cooling tower blowdown discharge point, the main

dam, and a site near Holleman's crossroads which served as a control point.

Co-58 was detected in both indicator samples at an average of 6.5E-2 pCi/g.

U:)OSWREP4PS51HNPREO.REP 3-4

I

Figures 3-19 and 3-20 present the results of these analyses.

3.11 External Radiation Ex sure Thermoluminescent dosimeters were used to monitor ambient radiation exposures in the plant environs.

The average weekly dose rate from the indicator locations was 1 mrem/wk and 0.9 mrem/wk from the control station.

The highest indicator location was 4.7 miles northeast of the plant and averaged 1.2 mrem/wk.

This is the same location identi6ed since 1989 as having the highest value. The differences among these locations is attributed to variations in soils and local geology and are not the result of plant operations.

Comparison ofthe weekly dose rates forTLDs within three miles (inner ring) of the plant with those at approximately Gve miles (outer ring) is presented in Figure 3-21 and shows that the outer ring, if anything, demonstrates a

greater dose rate than does the inner ring.

This presentation supports the interpretation that elevated dose rates are mostly a product of the local geology.

3.12 Com arison with Prep rational and 1991 0 erational Data Comparison of the 1992 environmental data with preoperational and 1991 operational data shows that, in most cases, the analyses involves activities' LLDwhich does not allow statistical treatment.

Conclusions and compara tive statements are based on inspection and judgment.

Air Sam les I-131 was detected in air samples for a six-week period following the Chernobyl incident in April 1986.

With this exception, no I-131 has been detected in air samples collected from 1986 through 1992.

Gross beta activities in air remained at 1.2E-2 pCi/m~, a value similar to preoperational data and to the 1989-91 values, UAOSIAREPQSS51 HNPREO.REP 3-5

~

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Drinkin Water As in previous years, no I-131 was detected in any of the 1992 drinking water

samples, This has been the experience for the preoperational and operational period with the exception of 1986 when the fallout from Chernobyl was detected.

In 1992 as in previous years, no tritium was detected in the community water supply at Lillington. Tritium again was detectable in the SHNPP drinking water.

Since this water supply is not a primary source of water for members of the general public, it is not considered a public water supply.

The water is consumed by employees during working hours.

During 1992, 12 monthly samples of the SHNPP drinking water contained measurable tritium at an average concentration of 7.5E+3 pCi/8an increase over the 2.8E+3 pCi/8 seen in 1990 and the 5.3E+3 pCi/8 in 1991.

The maximum radiological exposure &om this pathway is estimated at 0,2 mrem/yr.

Fish During 1992 as in 1989-91, no gamma-emitting radionuclides

&om plant operations were detected in any of the Gsh samples.

Surface Water I-131 activities in samples of surface waters taken &om the Harris Lake and the Cape Fear River, including a downstream location at Lillington, remained less than detectable as they have been since plant operations began in 1987.

The average gross beta activities were similar to the levels observed in 1985-91

(-4 pCi/4) but less than the activity in the control samples, Tritium activity in Harris Lake has increased measurably f'rom the preoperational concentrations of less than 1.2E+3 pCi/1 to a 1992 average of 1.08E+4 pCi/i. This is an increase over the values of 6.3E+3 and 7.8E+3 pCi/1 in 1990 and 1991, respectively.

Since the surface water tritium activity affects the activity in Qsh, it is estimated that the dose to the maximum exposed individual &om consuming 21 kg of Gsh would be 0.02 mrem.

U:iOSWREPg2$ 51HNPREO.REF 3-6

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Groundwater No tritium or gamma-emitter activity has been observed over the period

&om 1985-1992.

Milk During 1992 as in all past years with the exception of the Chernobyl period, no I-131 concentrations were detected in milk samples throughout the entire year.

There were also no other gamma-emitting radionuclides &om plant operations detected in the milk.

Bottom Sediment In the pre'operational period of 1985-1986, sediment samples collected from the lake bottom in the vicinity of the cooling tower blowdown discharge structure had shown low concentrations (0.3 pCi/g) of Cs-137.

Activation products &om plant operations were Grst detected in 1987.

Over the period 1988-1992, Mn-54, Co-57, 58, 60, and Cs-137 were consistently observed in sediment.

On occasion Cr-51, Fe-59, and Zr-Nb-95 have also been detected.

Sb-125 appeared in 1990 and continues to be observed.

As in past years, specific nuclide activities were variable in samples collected in 1992. No long-term trends are readily identi6able.

These results are likely du'e to the difficulties of sampling bottom sediments.

Due to the lake water shielding of radiation &om these depositions, no radiological exposure to the public can be attributed to these radionuclides.

Shoreline Sediment This sample media demonstrates the same inconsistencies in nuclide activities as bottom sediment.

In 1987 three radionuclides.of possible plant origin-Co-58, Cs-137, and Mn-54were detected in shoreline sediment samples.

In 1988 the concentrations of these radionuclides diminished.

In 1989 none of the radionuclides were detected.

During 1990, Co-58 and Cs-137 were detected in three of six samples at concentrations only slightly above their respective LLDs. In 1991, Co-58 was detected in Qve of eight samples at levels ranging from 2.0E-2 to 1.2E-1 2pCi/g. This year Cs-137 was detected in only one of eight samples at a level of 6.7E-2 pCi/g.

U:(OS QREPQSS51HNPREO.REP 3-7

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Food Cro s

Traces of Cs-137 were detected in 3 of 27 indicator samples at an average concentration of 3.2F 2 pCi/g in 1992. These observations are similar to the 1991 data and somewhat greater than the LLD of 1.9F 2 pCi/g for this radionuclide. Cs-137 has been randomly observed in past years both at the indicator locations and at the control locations. In 1988, Cs-137 was detected at the control location at similar concentrations, but no gamma-emitting radionuclides occurred in the control samples for the years 1989 and 1990.

The results for 1991 in food crops are considered consistent with normal fluctuations of fallout in the area and not indicative of adverse trends.

The 41 TLD locations surrounding the plant showed virtually no change in the average weekly ambient beta-gamma environment from 1985 through 1992.

The location with the maximum average recorded exposure was the same as for 1989-91 and is located 4.7 miles northeast of the plant.

Inspection of Figure 3-21 indicates that no plant eKuent ef'feet is demonstrated in the measurements especially since the average of the inner ring of TLDs (closest to the plant) are less than the outer measurements.

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4.0 MISSED SAMPLES AND ANALYSES 4.1 Air Cartrid e and AirParticulates No sample at Location AC/AP-4 on December 21, 1992, due to tripped breaker.

4.2

~Fd C Food crops were not available at Locations 5 and 54 in April.

Food crops were not available at Location 55 in August.

4.3 TLDs TLD 6 was missing in the Qeld on April8, 1992, during collection for the Qrst quarter.

TLD 9 was missing in the Qeld on July 6, 1992, during collection for the second quarter.

TLDs 10 and 29 were missing in the Qeld January 5, 1993, during collection for the fourth quarter.

U:5OSNREPLFS51HNPREO.REP 4-1

5.0 LAND-USE CENSUS 5.1 Introduction Technical SpeciQcation 3/4.12.2 for the Shearon Harris Nuclear Power Plant requires that a land-use census be conducted annually around the site.

The objective is to evaluate any changes in the use of land which could impact on the radiological health of members of the public.

The census employs whatever approach provides the best results, i.e., door-to-door survey, aerial survey, or by consulting local agricultural authorities.

The 1992 land-use census was conducted during June.

5.2 R~i Technical SpeciGcations 3/4.12.2 requires that the survey be conducted:

1.

Within a Gve-mile radius of the plant.

2, Annually during the growing season.

3.

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

a.

Milkanimal.

b.

Residence.

c, Garden of greater than 500 square feet producing broad-leaf vegetation.

These requirements were supplemented with identi6cation ofthe nearest meat animals in each of the 16 compass sectors.

5.3 Methods In accordance with this guidance, the 1992 land-use census was conducted using a door-to-door survey method.

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

V:~OSWREP4FS51HNPREO.REP 5-1

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Resident and road locations were identiQed within a Qve-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, and represent recent locations of structures and roads in this'ocale.

Moncure, Cokesbuty, Fuquay-Varina, Merry Oaks, New Hill, and Apex quadrangle maps were used.

The maps were combined, and Qve concentric circles at one-mile increments were drawn with the plant at the center.

Sixteen compass sectors were created in 22.5-degree increments on the map.

Each sector was centered on the compass direction.

The combined map was used to identify the nearest residences which were confirmed by Geld observation.

The nearest garden, milk animal (cow or goat), and meat animal (beef, hogs, or fowl) were located by inspection of Qelds and residential lots and by interviews with residents within the Qve-mile radius.

The survey was performed by CP&L in June during fair weather and good visibility. The survey started close to the plant in each sector and extended out to the Gve-mile perimeter.

All roads within the Gve-mile zone were traveled.

Barns, small

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

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

In some cases when the owner was not home, a neighbor was interviewed to obtain the desired'information. Ifthis was not possible, the property was either revisited at a later time-or information was determined by visual inspection, 5.4 Results Table 5-1 summarizes the locations of the nearest residence, milk cow, milk goat, garden, and meat animal in each of the 16 compass sectors.

The data gathered during the observation and the 35 recorded visitations resulted in the following observations:

1.

The nearest residence in each sector remained unchanged from 1991.

2.

Milkcows are located in the N sector.

This location is a commercial dairy that is currently part of the SHNPP Radiological Environmental Monitoring Program.

Refer to Table 5-1.

U:5oswREpQss51HNpREO.REp 5-2

3.

The nearest garden location in the WNW changed from 2.9 to 2.1 miles &om the plant. No garden was present in the ESE sector within 5 miles of the plant.

4.

Meat animals are found in 9 of the 16 compass sectors and are summa-rized in Table 5-2, The nearest meat animal in the NNE sector changed &om 3.5 to 3.1 miles.

U:5OSWREPgJR91HNPREO.REP 5-3

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TABLE 5-1 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FROM THE SHEARON HARIUS NUCLEAR POWER PLANT (MILES)

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SSW 1.33 1.33 1.33 1.33 1.36 1.33 1.9 2.7 4,3 4.4 3.9 1.9 2.7 4.3 4,4 3.9 4.7 4.4 4.4 4.6 3.9 4.7 4,4 4.6 3.9 2,2 4.4 4,3 2.2 4.4 4.3 SW 1.33 2,8 2,8 2,8 2.8 WSW 1.33 4.3 4,3 4.3 4.3 1.33 2.8 2.8 2,9 2,9 2.9 2.9 WNW NW NNW 1.33 1.26 1.26 2.1 2.1 1.5 2,1 2.1 1.5 2.9 3.8 1.7 2.1 3.8 1.7 3.8 1.7 3.8 1.7 Distance estimates are ~ 0.1 mile except at exclusion bounda~.

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TABLE 5-2 MEATANIMALTYPE AT NEAREST LOCATION TO SHNPP BY SECTOR (1992)

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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 LLD for air particulates is approximately 1.2E-3 pCi/m3 forSHNPP samples. Airparticulate 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 ofthe sample and counting a planchet on a Tennelec Low-Background Alpha/Beta Counting System for 50 minutes.

Typical LLD for gross beta is 2.0E+0 pCi/Z.

6.2 Tritium Liquid samples requiring tritium analysis are Qrst distilled. Five millilitersof the distillate are mixed with ten milliliters of liquid scintillation cocktail and counted in a liquid scintillation counter for 50 minutes, The LLD is approximately 1.2E+3 pCi/Z.

6.3 Iodine-131 Iodine-131 airborne concentrations are analyzed by the intrinsic germanium spectrometry systems.

The cartridges are placed on the detector, and each charcoal cartridge is counted individually with an 'approximate LLDof 8.0E-3 pCi/m3.

Iodine-131 in milk and drinking water is determined either by radiochemical or instrumental methods.

Analysis involves the use of anion-exchange resins and either direct gamma analysis of the resin with a sodium iodide (NaI) well-detector or sodium hypochloride elution of the resin and organic extraction followed by precipitation as silver iodine.

The precipitate is collected on a tared Qlter, dried, and counted on a low-background beta counter.

The LLDusing the NaI detector or the radiochemical separation is 0.4 pCi/8 for milk and water using a 25,000-second count time.

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'-'Se 6.4 Gamma S ectromet Gamma spectrum analysis utilizes intrinsic germanium detectors with thin aluminum windows housed in steel and lead shields.

The analyzer system is the Nuclear Data 6685.

Table 6-1 summarizes LLD values derived from instrument sensitivity based upon a blank sample background.

Air particulate Qlter quarterly composites are placed in a Petri dish and analyzed directly for 3,000 seconds.

Liquid samples, except milk, are boiled down to a small volume, transferred to a 250-ml polypropylene beaker with lid, and analyzed for 20,000 seconds.

One-liter milksamples are analyzed in a Marinelli beaker for 57,000 seconds.

Shoreline and bottom sediments are dried, weighed, and then analyzed in a Marinelli beaker for 5,000 seconds.

Food crop samples are weighed wet and analyzed in a Marinelli beaker for 20,000 seconds.

Fish samples are cleaned,

dressed, and placed in a Marinelli beaker for analysis for 5,000 seconds.

6.5 Thermoluminescent Dosimet Each area monitoring station includes a TLD packet which is a polyethylene bag containing three calcium sulfate phosphors contained in a Panasonic UD-814 badge.

The TLD is lighttight and the bag is weather-resistant.

Dosimeters are machine annealed before Qeld placement.

Following exposure in the Qeld, each dosimeter is read utilizing a Panasonic TLD reader.

This instrument integrates the light photons emitted from traps as the dosimeter is heated above 150'C.

The photons from the lower-energy traps are automatically eliminated through a preheat cycle.

Calibration is checked regularly using dosimeters irradiated to known doses.

Prior to the measurement of each dosimeter, the instrument is checked through use of an internal constant light source as a secondary standard.

The minimum sensitivity of the dosimeters used is approximately 1 mR.

U:ioSWRBPgSS51HNPREO.REP 6-2

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

6.6 EPA Laborato Intercom arison Pro m

The Radiochemistry Laboratory at the Harris Energy & Environmental Center in New Hill, North Carolina, provides radioanalybcal services for CP&L's nuclear plant radiological environmental surveillance programs.

In ful611ment of Technical Speci6cation 3/4.12,3, 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 1992, 62 analyses were completed on 22 samples representing three major environmental media (i.e., water, milk, air Qlters). Data on the known activities and the normalized standard deviations for the 62 analyses have been received from EPA. Acomparison ofthe average of our reported values with the EPA known activity and its normalized standard deviation is provided below:

Standard Deviation From Known Activity Percent of Analyses s

1 Standard Deviation s 2 Standard Deviation 63 94 a 3 Standard Deviation 98 One of 62 samples exceeded the three sigma action level.

A gross beta analysis of a water sample received in January 1992 fell outside the 3o limit.

The beta self-absorption curve was redone and the sample reanalyzed.

The results were then ( 10 from the known activity.

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6.7 Lower Limits of Detection Allsamples analyzed met the LLDrequired by Technical Specification 4.12.1 and Table 4.12.1-1.

TABLE 6-1 TYPICALLOWER LIMITSOF DETECTION (A PRIORI)

GAMMASPECTROMETRY Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-La-140 Other Expected Gamma Emitters 3 ~CL?e 7

7 3

0.4' 4

12 2 to 65

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I-131 Cs-134 Cs-137 Other Expected Gamma Emitters 0.019 pCi/m~.

0.001 0.001 0.001 to 0.022 I-131 Cs-134 Cs-137 Other Expected Gamma Emitters O.4" gCVe 4

1 to 86

• NaI well crystal analysis of resin concentrates of samples.

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GAMMASPECTROMETRY Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-134 Cs-137 Sb-125 Other Expected Gamma Emitters 248 pCi/kg (dry) 31 26 27 23 35 31 23 to 1750 I

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Other Expected Gamma Emitters 23 pCi/kg (wet) 23 51 29 47 30 24 9 to 572 I-131 Cs-134 Cs-137 Other Expected Gamma Emitters 21 pCi/kj; (wet) 2X 18 19 14 to 308 U:iOSRREPCSS51 HNPREO.REP 6-5

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