RNP-RA/12-0052, Radiological Environmental Operating Report - 2011

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Radiological Environmental Operating Report - 2011
ML12144A406
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 05/14/2012
From: Hightower W
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/12-0052
Download: ML12144A406 (57)
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Text

TS 5.6.2 j Progress Energy Serial: RNP-RA/12-0052 MAY 14 2012 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 Ladies and Gentlemen:

In accordance with the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, Technical Specifications, Section 5.6.2, "Annual Radiological Environmental Operating Report," enclosed is the Radiological Environmental Operating Report for the period January 1,2011, through December 31,2011.

If you have any questions concerning this report, please contact me at (843) 857-1329.

Sincerely, l(U& &4AA~io W. Richard Hightodvfr Supervisor - Licensing/Regulatory Programs WRH/mjp Enclosure c: V. M. McCree, NRC, Region II A. T. Billoch Col6n, NRC, NRR (w/o Enclosure)

NRC Resident Inspector Progress Energy Carolinas, Inc.

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2011 4ik H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 CAROLINA POWER & LIGHT COMPANY ALSO KNOWN AS PROGRESS ENERGY CAROLINAS, INC.

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR THE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 JANUARY 1 THROUGH DECEMBER 31, 2011

TABLE OF CONTENTS Title Page Table of C ontents .................................................................................................................... i List of Figures ................................................................................................................................ ii List of Tables ................................................................................................................................ iii Executive Sum m ary .............................................................................................................. 1 Radiological Environmental Monitoring Program ................................................................ 3 Purpose and Requirements for the Radiological Monitoring Program .................. 3 G eneral Site D escription ............................................................................................... 4 Radiological Monitoring Program Quality Assurance ............................................. 5 Radiological Monitoring Program General Description .......................................... 6 Summary of Radiological Monitoring Program ...................................................... 12 Interpretations and C onclusions .............................................................................. 22 M issed Surveillances ................................................................................................... 27 A nalytical Procedures ................................................................................................. 29 L and U se C ensus .......................................................................................................................... 37 Purpose of the L and U se C ensus ............................................................................. 37 M ethodology .................................................................................................................... 38 Land U se C ensus Results ............................................................................................ 38 Report Data for H BR SEP (R N P) ......................................................................................... 51 i

LIST OF FIGURES Figure Page 1 Location of HBRSEP (H. B. Robinson Steam Electric Plant, Unit No. 2) 4 2 Radiological Sampling Locations (Near Plant) 7 3 Radiological Sampling Locations (Distant from Plant) 8 4 Plot of Air Particulate Gross Beta Activity (Locations 1 and 2) 40 5 Plot of Air Particulate Gross Beta Activity (Locations 1 and 3) 41 6 Plot of Air Particulate Gross Beta Activity (Locations 1 and 4) 42 7 Plot of Air Particulate Gross Beta Activity (Locations 1 and 5) 43 8 Plot of Air Particulate Gross Beta Activity (Locations 1 and 6) 44 9 Plot of Air Particulate Gross Beta Activity (Locations 1 and 7) 45 10 Plot of Air Particulate Gross Beta Activity (Locations 1 and 55) 46 11 Plot of Air Particulate Gross Beta Activity (Locations 1 and 60) 47 12 Plot of Air Particulate Gross Beta Activity (Locations 1 and 61) 48 13 Plot of Surface Water Tritium Activity (Locations 40, 41, 57, and 66) 49 14 Plot of TLD Averages for Inner and Outer Rings 50 11

LIST OF TABLES Table Page 1 Media Used to Assess Exposure Pathways to Man 6 2 Radiological Monitoring Sampling Locations 9 3 Radiological Environmental Monitoring Program Data Summary 14 4 Potential Dose Pathways 20 5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 21 6 Typical/Worst Case Lower Limits of Detection (a priori) for Gamma Spectrometry 35 7 Land Use Census Comparisons (2010-2011) Nearest Pathway (miles) 39 iii

EXECUTIVE

SUMMARY

The H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP) is operated by Carolina Power &

Light Company; also known as Progress Energy Carolinas, Inc.; under a license granted by the Nuclear Regulatory Commission (NRC). The HBRSEP Technical Specifications and the HBRSEP Off-Site Dose Calculation Manual establish the requirements of the Radiological Environmental Monitoring Program. This report provides the results of the Radiological Environmental Monitoring program from January 1, 2011, through December 31, 2011.

The Radiological Environmental Monitoring program was established in 1973. Radiation and radioactivity in various environmental media have been monitored for more than 38 years.

Monitoring is also provided for control locations that would not be impacted by operation of the HBRSEP. Using these control locations and data collected prior to operation allows comparison of data collected at locations near HBRSEP that could potentially be impacted by its operation. The pre-operational monitoring program began in December 1968.

Monitoring results for environmental media are summarized as follows:

> During 2011, REMP samples obtained from air monitoring (air cartridge and air particulate),

and surface water locations identified the presence of low levels of radioactive iodine- 131.

The detectable concentrations were not a result of RNP operations given the following facts:

" The REMP sample results detected the presence of Iodine- 131 in the specific environmental media samples from March 14, 2011, to April 25, 2011.

  • The concentrations detected at the indicator samples were also identified at RNP control samples and throughout the region.

As such, the atypical detection of these radionuclides in both indicator and control samples is credibly attributed to the trans-Pacific transport of airborne releases from the Fukushima Dai-ichi nuclear power plant following the March 11, 2011, Tohoku earthquake and tsunami and is not related to the operation of RNP.

>' Air-monitoring results are similar or less than the concentrations of radioactivity from pre-operation monitoring. These observations are also consistent with past operational data other than during the timeframe of fallout from the Fukushima Dai-ichi nuclear power plant.

> Milk monitoring has not been conducted due to the unavailability of milk samples in the area since July 17, 1998, when the dairy ceased operation. Milk sampling will resume if a new sample location is identified. Broadleaf sampling is conducted, since no milk animals are located within five miles of the plant in any sector.

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>* Terrestrial vegetation includes broadleaf vegetation and food products. Results indicate detectable concentrations of Cs- 137 in both the indicator and control locations for broadleaf vegetation with comparable results. The Cesium-137 concentrations were also comparable to previous years. No other gamma by-product/plant-related activity was detected in any samples, except for K-40 and other naturally occurring gamma activity. Sampling of miscellaneous food products (non-leafy) in the vicinity of the site is conducted when leafy vegetables are not being grown. The concentrations identified were comparable to previous years' data.

> Aquatic organism surveillances include fish and aquatic vegetation. Fish samples revealed detectable concentrations of Cs-137 activity in both indicator and control locations. No other gamma by-product/plant-related activity was detected in any fish sample, except for K-40 and other naturally occurring gamma activity. The concentrations observed are consistent with previous years' data. The aquatic vegetation is used for long term trending and there is no dose contribution to the public. Cesium- 137 activity was detected in two indicator and one control sample at concentrations consistent with previous years' data.

> Surface water results indicate no by-product/plant-related gamma activity, except for the I-131 activity identified in one indicator sample in 2011, which was during the Fukushima.

Dai-ichi nuclear power plant incident. Surface water (non-drinking water) results indicate that the surface water from Lake Robinson shows the presence of tritium, which is attributed to plant operation; but is well below the EPA reportable non-drinking water limit (30,000 pCi/Liter) and drinking water limit (20,000 pCi/Liter). The tritium concentrations observed are not irreversible to the environment due to plant operations (See Figure 13) and are consistent with previous years' data. Refer to the Interpretations and Conclusions Section /

Surface Water.

>' Ground water results show the presence of tritium; however, the results are well below the EPA reportable non-drinking water limit (30,000 pCi/Liter) and drinking water limit (20,000 pCi/Liter). Refer to the Interpretations and Conclusions Section / Ground Water.

> Sediment surveillance includes both shoreline and bottom sediment. The shoreline sediment gamma analyses identified naturally occurring gamma activity and no gamma by-product/plant-related activity was detected in any shoreline sediment sample collected in 2011. These samples are used to calculate groundplane dose to the public. During 2011, bottom sediment results indicated the presence of Cs- 137 at concentrations consistent with previous years. Bottom sediment is used for long term trending and there is no public dose associated with these samples.

> External radiation dose showed no measurable change from pre-operational data The continued operation of HBRSEP has not significantly contributed radiation or the presence of radioactivity in the environmental media monitored. The measured concentrations of radioactivity are well within applicable regulatory limits.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PURPOSE AND REQUIREMENTS FOR THE RADIOLOGICAL MONITORING PROGRAM The purpose of the radiological monitoring program is to measure accumulation of radioactivity in the environment, to determine whether this radioactivity is the result of operation of the HBRSEP, and to assess the potential dose to the off-site population based on the cumulative measurements of radioactivity of plant origin. Radiological environmental monitoring programs provide an additional verification of the containment and radiological controls of nuclear generating stations.

Requirements are established for the radiological monitoring program in the Technical Specifications and the Off-Site Dose Calculation Manual (ODCM).

Additional guidance regarding the radiological monitoring program may be found in the following:

> NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977

> NRC Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revision 1, July 1977

> NRC Regulatory Guide 4.15 revision 1, Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Streams and the Environment, Revision 1, February 1979

> NRC Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants, Revision 1, April 1975

> NRC Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, For comment, December 1975

> Radiological Assessment Branch Technical Position, An Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979 3

General Site Description The HBRSEP (Unit No. 2) consists  ;ý /, -.-

of a pressurized water reactor with a N

design rating of 800 MWe (Mega-watts electric). The site is shared with a pulverized coal unit (Unit No. 1), which established 0OWo, commercial operation in 1960. .W ,.W ." .11,.

Commercial production was initiated by Unit No. 2 on March 7, 1971. The HBRSEP is located in Darlington County, South Carolina.

The site is along state route 151 approximately five (5) miles 34 northwest of Hartsville, South Carolina and is displayed on the ,Db 111% U map of northeastern South Carolina Figure 1: Location of HBRSEP (Figure 1). The site is also approximately twenty five (25) miles northwest of Florence, South Carolina.

Lake Robinson is adjacent to the plant and is the source of cooling water. The lake was impounded during the construction of Robinson Unit No. 1 (coal fired). The lake is fed by Black Creek and is approximately 2,250 acres in area. The plant intake is at the southern portion of the lake near the dam. The discharge is to a canal which conveys the cooling water to a point 4.2 miles north of the plant, where it returns to Lake Robinson.

The local economy supports primarily industrial and agricultural contributions. Fishing, boating, and swimming are popular activities on Lake Robinson and other nearby lakes. These activities contribute to the radiological pathways by consumption of fish and immersion related to swimming and boating. Consumption of milk and food products contributes to the ingestion pathway. No milk animals are located within five miles of the plant in any sector at this time, so broadleaf sampling is conducted to simulate the milk ingestion pathway.

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RADIOLOGICAL MONITORING PROGRAM QUALITY ASSURANCE A required component of the environmental radiological monitoring program is the Quality Assurance Program. The standards for the Quality Assurance Program are established in the NRC Regulatory Guide (R.G.) 4.15 revision 1, "Quality Assurance for Radiological Monitoring Programs. According to R.G. 4.15 revision 1, the purpose of the Quality Assurance Program is to

"(1) to identify deficiencies in the sampling and measurement processes to those responsible for these operations so that corrective action can be taken, and (2) to obtain some measure of confidence in the results of the monitoring programs in order to assure the regulatory agencies and the public that the results are valid." NRC Regulatory Guide 4.15 B, Pg. 4.15-2 revision 1. This provides the opportunity to implement corrective actions that address possible deficiencies.

Examples of the activities of the Quality Assurance Program include:

> regular review of sample collection and records

> regular review of laboratory procedures and methods

> participation in an Environmental Interlaboratory Comparison Program, which provides an independent assessment of the quality of laboratory results.

> the use of known concentrations of radioactivity in test samples by the laboratory to ensure consistent quality results on an ongoing basis.

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RADIOLOGICAL MONITORING PROGRAM GENERAL DESCRIPTION Although the contribution to background radiation is small, Carolina Power & Light Company; also known as Progress Energy Carolinas, Inc.; has established this program to measure the exposure pathways to man. An exposure pathway describes the source of the radiological exposure. The primary forms of potential radiological emissions from the plant are airborne and liquid discharge.

The pathways monitored are external dose, ingestion of radioactive materials, and the inhalation of radioactive material. Specific methods and different environmental media are required to assess each pathway. Table 1 provides a list of the media used to assess each of these pathways.

Table 1 Media Used to Assess Exposure Pathways to Man Purpose of Samples Sample Media Shoreline Sediment External Dose Thermoluminescent Dosimetry (TLD)

Milk (Broadleaf Vegetation)

Ingestion Food Products Fish (Surface Water)

Ground Water Inhalation Air Samples (Particulate & Radioiodine)

Trending Aquatic Vegetation Bottom Sediment Surface Water (Tritium)

Sampling Locations Sampling locations are chosen based upon meteorological factors, pre-operational monitoring, and results of the land use surveys. A number of locations are selected as controls. Control stations are selected because they are very unlikely to be affected by operation of the plant. Sample locations may be seen in Figures 2 and 3. A description of each sample location may be found in Table 2.

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Radiological Sampling Locations

@1M 8GeoS1n41rGbbalCow-. - 3. "I" \

Figure 2: Radiological Sampling Locations (Near Plant)

Stations not shown include 1, 7-18, 20-39, 41, 45,46,47,49, 52, 54, 57, 58, 66, 71, 76, and 79.

Sample Types Sample Locations Air Cartridge & Particulate 1-7, 55, 60, 61 Shoreline Sediment 44, 57 Ground Water 42,64,68-73,75-79,81-82 Broadleaf Vegetation 50,51,52,62,67 Surface Water 40,41,57,66 Thermoluminescent Dosimeter 1-39, 55, 56, 61,65 Fish 45-47 Food Products 49,54,58 Aquatic Vegetation & Bottom Sediment 41,45,46,66 7

Radiological Sampling Locations Figure 3: Radiological Sampling Locations (Distant from Plant)

Stations not shown include 1, 2, 6, 7, 26, 41, 42, 47 (varies), 49 (varies), 50 - 52, 54 - 58 (varies), 60

- 62, 65 - 73, 75 - 79, and 81 - 82.

Sample Types Sample Locations Air Cartridge & Particulate 1-7, 55, 60, 61 Shoreline Sediment 44, 57 Ground Water 42, 64, 68 - 73, 75 - 79, 81 - 82 Broadleaf Vegetation 50,51,52,62,67 Surface Water 40,41,57,66 Thermoluminescent Dosimeter 1-39,55, 56, 61, 65 Fish 45-47 Food Products 49, 54, 58 Aquatic Vegetation & Bottom Sediment 41, 45, 46, 66 8

Table 2 Radiological Monitoring Sampling Locations for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP)

Sample Type Location & Description Frequency Sample Size Analysis Air Cartridge 1--24.4 miles ESE Florence, S.C.* Weekly 510m 3 Iodine (AC) 2--0.2 miles S Information Center 3--0.5 miles N Microwave Tower 4--0.4 miles ESE Spillway 5--0.9 miles ENE East shore of lake near Johnson's Landing 6--0.2 miles SSW Information Center 7--6.4 miles ESE CP&L facility on RR Ave.,

Hartsville 55--0.2 miles SSE South of West Settling Pond 60--0.2 miles SE Robinson Picnic Area 61--0.3 miles WSW West Parking lot near RR tracks Air Particulate 1--24.4 miles ESE Florence, S.C.* Weekly' 510 m' Gross Beta (AP) 2--0.2 miles S Information Center (Weekly) 3--0.5 miles N Microwave Tower 4--0.4 miles ESE Spillway 5--0.9 miles ENE East shore of lake near Johnson's Landing Composite 6--0.2 miles SSW Information Center Gamma 7--6.4 miles ESE CP&L facility on RR Ave., (Quarterly)

Hartsville 55--0.2 miles SSE South of West Settling Pond 60--0.2 miles SE Robinson Picnic Area 61--0.3 miles WSW West Parking lot near RR tracks Fish (FI) 45--Site varies within Lake Robinson Semiannual 495 grams Gamma (Bottom Feeders 46--Site varies within Prestwood Lake (wet) (edible

& Free 47--Control station, Any lake not influenced by plant portions)

Swimmers) discharge*

Broadleaf 50--SSE Close to Site Boundary Monthly 350 grams Gamma Vegetation (BL) 51 --SSW Close to Site Boundary (As available) (wet) Iodine 52-- 0 miles W near Bethune*

62--SE Close to Site Boundary 67--S Close to Site Boundary Shoreline 44--I.6 miles NNE East shore of lake, Shady Rest Semiannual 575 grams Gamma Sediment (SS) Club 57--Ash Pond Shore Aquatic Veg. 41 --7.2 miles NNW Black Creek (upstream)* Annual 420 grams Gamma (AV) & 45--Site varies within Lake Robinson and Bottom 46--Site varies within Prestwood Lake 575 grams Sediments (SD) 66--Black Creek between Prestwood Lake discharge

& upstream of Sonoco Spray Farm (downstream)

Ground Water 42--Unit I Deep Wells Quarterly 1.5 liters Gamma (GW) 64--0.6 miles SE Artesian Well Grab Tritium 69--Well B Behind the Training Building 70--Well C Btwn the O&M Building & Fab Shop 71--0.87miles NNW (MW-03A) Btwn Ash Pond &

RR tracks 72--.10 miles E (MW-06) 20 ft from FP/FH 7 fire hydrant & Unit 1 North Deep Well Pump 73--0.11 miles ENE (MW-13) Btwn Discharge Canal & Unit 1 Stand Alone Fuel Oil Tanks Control Stations 9

Table 2 (Continued)

Radiological Monitoring Sampling Locations for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP)

Sample Type Location & Description Frequency Sample Size Analysis Ground Water 75--0.05 miles NE (PSW-02) By Unit I boundary Quarterly 1.5 liters Gamma (GW) Fence to Unit 2 across paved rd. from Hydrogen Grab Tritium Continued Gas Tanks 76--0.49 miles N (PSW-03) NE comer of the MET Tower Station 77--0.25 miles SSE (TS-OIB) By entrance rd. to Unit I 78--0.17 miles SSE (TS-02C) NE comer by East Settling Pond influent by fence 79--I.0 miles N (TS-07C) S comer by cove &

Discharge Canal 81--0.19 miles SSE (TS- 17B) W of West Settling Pond across paved rd.

Ground Water Quarterly 6.5 liters Gamma, (GW) 68--Well A Btwn Unit I Switchyard & breakroom Grab Tritium, Iodine Continued Ground Water Quarterly 6.5 liters Gamma, (GW) 82--0.3 miles SSE (PDW-01) By entrance rd. to Grab Tritium, Iodine, Continued Unit 1 Gross Beta Surface Water 40--0.6 miles ESE Black Creek at Old Camden Road Monthly 4 liters Gamma (SW) (S-16-23) Composite Tritium 41--8.0 miles N Black Creek at US Hwy 1*

57--Ash Pond 66--Black Creek between Prestwood Lake discharge

& upstream of Sonoco Spray Farm (downstream)

Food Products 58--Site varies from plant Annual at 350 grams Gamma (FP) 49--10.0 miles W or greater than 5 miles from Harvest (edible plant

  • portions) 54--10.1 miles E Auburndale Plantation (if irrigating from Black Creek)
  • Control Stations 10

Table 2 (Continued)

Radiological Monitoring Sampling Locations for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP)

Sample Type Location & Description Frequency Sample Analysis I I I Size I Thermoluminescent 1--24.4 miles ESE Florence, S.C. *2 Quarterly Not TLD Dosimetry (TLD) 2--0.2 mile S Information Center" Applicable Reading 3--0.5 mile N Microwave Tower 4--0.4 mile ESE Spillway Gamma 5--0.9 mile ENE East shore of lake near2 Johnson's Landing Dose 6--0.2 mile SSW Information Center"1, 7--6.4 miles ESE CP&L Facility on RR Ave., Hartsville 8--0.8 mile SSE Transmission right-of-way 9--1.0 mile S Transmission right-of-way 10--1.0 mile WSW Clyde Church of God 1I--I1.0 mile SW Old Camden Road 12--4.2 miles SSW off of Old Camden Road 13--0.7 miles W Comer of Saluda and Sandpit Roads 14--0.8 mile WNW First Baptist Church of Pine Ridge 15--0.7 miles NW Transmission right-of-way 16--4.0 mile NNW South side of Darlington Co. I.C. Turbine Plant 17--1.2 miles N Darlington Co. Plant emergency fire pump 18--0.7 mile SE Near Old Black Creek RR trestle 19--4.0 mile E Old Camden Road (#S-16-23) 20--I.0 mile ENE New Market Road (#S-16-39) 21--1.4 miles NE New Market Road (#S-1 6-39) 22--4.7 miles NNE Shady Rest entrance off of Cloverdale Drive 23--1.0 miles ESE New Market Road (#S-16-39) 24--4.6 miles NW Sowell Road (#S-13-711) 25--4.0 miles NNW Lake Robinson Road (#S-13-346) 26--5.0 miles N Lake Robinson Road (#S-13-346) 27--5.4 miles NNE Prospect Church Road (#S-13-763) 28--4.3 miles NE New Market Road (#S-I 3-39) 29-,4.0 miles ENE Ruby Road (#S-16-20) 30--4.4 miles E Ruby Road (#S-16-20) 31--4.6 miles ESE on Lakeshore Drive 32-4.0 miles SE Transmission right-of-way 33-4.5 miles SSE on Bay Road (#S-16-493) 34--4.7 miles S on Kellybell Road (#S-16-772) 35--4.5 miles SSW Kelly Bridge Road (#S-31-51) 36--5.0 miles SW on Kingston Drive 37--5.0 miles WSW Pine Cone Road 38-4.9 miles W at Union Church Road 39--5.1 miles WNW King's Pond Road 55--0.2 miles SSE South of the West Settling Pond 2

56--0.4 miles NNW North of the center of the 7P-ISFSI' 2 61--0.3 miles WSW West parking lot near RR tracks 65--0.3 miles WNW Northwest of the 24P-ISFS12

  • Control Station 1 Required for monitoring of the 7P-ISFSI 2 Required for monitoring of the 24P-ISFSI 11

SUMMARY

OF RADIOLOGICAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) was conducted in accordance with the HBRSEP Off-Site Dose Calculation Manual (ODCM) and approved procedures.

The purpose of the REMP is to measure accumulation of radioactivity in the environment, to determine whether this radioactivity is the result of the operation of the HBRSEP, Unit No. 2, and to assess the potential dose to the off-site population based on the cumulative measurements of radioactivity of plant origin. Approximately 1,487 samples were collected from indicator and control locations and 1,607 analyses and measurements were made during 2011. Detectable radioactivity resulting from plant operation was found in 31 out of 36 indicator samples of surface water (Table 3). Only the tritium activity measured in the surface water of Lake Robinson and in fish samples constituted a source of public exposure. The highest concentration of any plant related radionuclide releases to the environment was tritium in Lake Robinson at an average concentration of 2.29E+3 pCi/Liter. Using the methodology of Regulatory Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, dated October 1977," via fish consumption, is listed below. The maximum possible exposure to an individual from the evaporation of tritium in Lake Robinson is 0.163 mrem/yr. to a child.

AIe Group 2011 Dose (mrem)

Adult 0.005 Teenager 0.004 Child 0.003

1. A statistical summary of all the data gathered in 2011 has been compiled in Table 3.
2. Radioactivity in environmental samples attributed to plant operations in 2011, for which there is a potential dose pathway to the public, is summarized in Table 4.
3. All detectable radionuclides in the environmental samples for 2011 were less than reporting levels as defined in HBRSEP ODCM. Table 5 summarizes the reporting levels.
4. Environmental sampling and analyses performed during 2011 demonstrated that the HBRSEP, Unit No. 2 continues to operate with minimum impact on the environment and minimal dose to the general public.

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5. The following locations are used as control locations and are intended to indicate conditions away from the HBRSEP influence:

Thermoluminescent Dosimeters, 24.4 miles ESE, Florence, S.C.

Airborne and Particulate Samples (Location 1)

Surface Water 8.0 miles N, Black Creek at US Highway 1 (Location 41)

Bottom Sediment and Aquatic 7.2 miles NNW, Black Creek Vegetation (upstream,)

(Location 41)

Fish Any lake not influenced by plant discharge (Location 47)

Broadleaf Vegetation 10 Miles W, near Bethune (Location 52)

Food Products 10.0 miles W or greater than 5 Miles from plant (Location 49 - Bethune - site varies) 13

TABLE 3 H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 261 Darlington County, South Carolina Calendar Year 2011 ILocation w/Hlighest Annual Mean' Medium or Pthwa Type and Total ,Lower Limit of All IndicatornLocations Namne, Distance, Mean 'Control Locations Number of Samnpled or'*

Measure (Unit of NO. of Mesuements Detetlon D

~n~ndli Mean t tt unitrec Ransge!'

Rangee l Mean Ranne t Nontine o

L 2Yorte) R MPsrtret erormed ______ Measurements Air Cartridge 1-131 7.07E-2 (37/468) East shore of Lake 8.23E-2 (4/52) 8.10E-2 (4/52)

(pCi/mr) 5200) i0) 5.1E-2 1.85E 1.36E- I near Johnson's 3.37E 1.36E-1 2.21E 1.22E- 10 Landing 0.9 miles ENE Air Particulate Gross Beta 2.44E-2 (468/468) Microwave Tower 2.68E-2 (52/52) 2.51 E-2 (52/52) 0 (pCi/m3) 520(') 2.6E-3 9.46E 3.88E-2 0.5 miles N 1.42E 3.88E-2 9.1OE 3.70E-2 Gamma 3.1E-2 1.61E-2 (16/73) Microwave Tower 1.91E-2 (1/8) 1.67E-2 (3/8) 0 81 9.67E 2.44E-2 0.5 miles N Single value 1.27E 2.05E-2 1-131ls) t 1.68E-3 (1/73) Information Center 1.68E-3 (1/8) All less than LLD 0 Cs-137 s) 2.2E-3 Single value 0.2 miles S Single value Aquatic Vegetation"S) Gamma 2.57E-2 (2/3) Site varies within 3.92E-2 (1/1) 2.46E-2 (1/1) 0 (pCi/g, wet) 4 2.OE-2 1.2 IE 3.92E-2 Lake Robinson Single value Single value 0 Cs-137 Broadleaf Vegetation Gamma 5.05E-2 (17/48) Close to Site 5.84E-2 (4/12) 3.41E-2 (9/12) 0 (pCi/g, wet) 6001" 3.2E-2 1.20E 9.40E-2 Boundary (BL-62) 5.55E 6.18E-2 2.12E 7.90E-2 Cs-137 SE Fish Gamma 4.33E0+ (4/4) Site varies within 4.94E+0 (2/2) 4.42E+0 (2/2) 0 Free-Swimmer 6 5.9E-I 3.67E00 - 5,05E00 Lake Robinson 4.84E0t0 - 5.05E00 4.30E. 0 - 4.53E+0 (pCi/g, wet) K-40 5.51 E-2 (4/4) Site varies within 5.52E-2 (2/2) 7.48E-2 (2/2)

Cs-137 7.4E-2 3.87E 7.18E-2 Lake Robinson 3.87E-2 -7.18E-2 7.20E 7.76E-2 0 14

TABLE 3 (Cont.)

HBRSEP RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 261 Darlington County, South Carolina Calendar Year 2011 I Locationwllliglhest Annual Mecan Meimr0ahw~ay Type and Total Lower Limit Ali .Indicator - Name, Distance, and , Mean, Control Loations N~umber of Sampleor-7, N.-f o Dtcto0 oainnei D7don Due Rag M Norojo L easurement)-. n ......... ......... ..... Measurements Fish Gamma Bottom-Feeder 6 3.72E40 (4/4) Site varies within 3.92E10 (2/2) 3.80E+0 (2/2) 0 (pCi/g, wet) K-40 5.9E- 3.24E 4.61E-10 Prestwood Lake 3.24E-f 0 - 4.61E-E0 3.42E-00-4.17EI0 Cs-137 7.4E-2 4.57E-2 (4/4) Site varies within 5.51E-2 (2/2) 5.73E-2 (2/2) 0 2.70E 6.07E-2 Prestwood Lake 4.96E 6.07E-2 5.68E 5.79E-2 Food Products Gamma 2.71E0 (3/3) Site varies from Plant 2.71E-i 0 (3/3) 3.96E40 (3/3) 0 (pCi/g, wet) 6 (3 3.2E-1 1.63E+0 - 3.86E40 (FP-58) 1.63E+0 - 3.86E- 0 2.59E40 - 6.28E40 K-40 Cs-137 3.2E-2 All less than LLD All less than LLD 0 Ground Water Gamma See Table 6 All less than LLD ---- -------- No control 0 (pCi/I) 60(3 GW-82 (PDW-Ol) by Gross Beta 9.OE-1lts 1.28E+0 (4/4) Entrance Rd. ta U/I 1.28E+0 (4/4) 4 8.0E-1 -2.38E+ 8.00 Na contol 0 0.3 miles SSE 1-131 See Table 6 All less than LLD ----..... No control 0 8

Tritium 2.2E+2")1 GW-79 (TS-07C) S 60(ý) 6.19E+I2 (42/60) comer by cove & 2.11E+3 (4/4) 2.4 IE+2 - 2.35E+3 Discharge Canal 1.80E+3 - 2.35Et3 No control 1.0 mile N 15

TABLE 3 (Cont.)

HBRSEP RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 261 Darlington County, South Carolina Calendar Year 2011 16

TABLE 3 (Cont.)

HBRSEP RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATA

SUMMARY

H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 261 Darlington County, South Carolina Calendar Year 2011 MediUm or Pathway -Type andTotal oiwerisnltof. All Indl5tator . Name¢stance,-and  ; Meana t

. Control Locationsq, Sampled'or WNo C'f Detectlon(LDt. Locatio'ns Me'an'~lan~ 5 Nuher of MeNduiW r (U niltof( MeOasurements "Range - ' fRie . Nd nro utlne Surface Water Gamma 1.4E11 1.78E+1 (1/36) Ash Pond 1.78E11 (1/12) All less than LLD 0 (pCi/l) 48 Single value Single value 1-131(')

Tritium 2.2E+2(" 1.66E+/-3 (31/36) Black Creek at Old 2.29E+3 (12/12) 0 48 3.11 E 6.77E+3 Camden Rd.

0.6 miles ESE TLD 1 TLD N/A 1.40E+I (164/164) Pine Cone Rd. 1.94E+1 (4/4) 1.27E+l (4/4) 0 (mR/qtr)y6 16813n 9.00E+0 - 2.06E+H 5.0 miles WSW 1.87E+1 - 2.06E+1 1.20E+l - 1.32E+1 17

FOOTNOTES TO TABLE 3

1. Lower Limit of Detection (LLD) is the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal. Due to counting statistics and varying volumes, occasionally lower LLDs are achieved. Refer to Analytical Procedures Section/Gamma Spectrometry for an explanation of how LLD values were derived.
2. Mean and range are based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parentheses.
3. Missing samples are discussed in Missed Surveillances.
4. Three types of broadleaf vegetation samples are collected monthly when available from four locations for a possible total of 144 samples.
5. Bottom sediment and aquatic vegetation sampling are not required by plant Offsite Dose Calculation Manual (ODCM). Sampling and analysis is performed to monitor any radionuclide accumulation in the lake.
6. TLD exposure is reported in milliroentgen (mR) per 90-day period (quarter) beginning in 1995. This is the exposure standard (mR/std. qtr.) used to compare data to the Nuclear Regulatory commission (NRC).
7. The tritium LLD was lowered to approximately 2.20E+2 pCi/L for samples that typically demonstrate activity less than the LLD (groundwater and surface water control). The LLD was lowered to be consistent with the LLD used by the state laboratory. Other samples that typically exhibit activity greater than the LLD have a tritium Lower Limit of Detection (LLD) of 1.OE+3 pCi/L.
8. During 2011, REMP samples obtained from air monitoring (air cartridge and air particulate),

and surface water locations identified the presence of low levels of radioactive iodine- 131.

The detectable concentrations were not a result of RNP operations given the following facts:

18

" The REMP sample results detected the presence of Iodine- 131 in the specific environmental media samples from March 14, 2011, to April 25, 2011.

" The concentrations detected at the indicator samples were also identified at RNP control samples and throughout the region.

As such, the atypical detection of these radionuclides in both indicator and control samples is credibly attributed to the trans-Pacific transport of airborne releases from the Fukushima Dai-ichi nuclear power plant following the March 11, 2011, Tohoku earthquake and tsunami and is not related to the operation of RNP.

19

TABLE4 Potential Dose Pathways Highest Annual Mean Maximum Individual Sample Media Radionuclide (Average) Concentration Dose and Occurrence Surface H-3 2.29E+3 (pCi/L) 0.005 millirem/yr - child Water (12/12) (from fish)

Surface H-3 2.29E+3 (pCi/L) 0.163 millirem/yr - child Water (12/12) (Evaporation from Lake Robinson using RNP 2011 Meteorology Data) 20

TABLE 5 Reporting Levels for Radioactivity Concentrations in Environmental Samples Radionuclide Water Airborne Fish Milk Food Products 3

(pCi/). (pCi/m ) (pCi/kg, wet) (pCi/l) (pCi/kg, wet)

H-3 2E+04a-Mn-54 1E+03 3E+04 Fe-59 4E+02 1E+04 Co-58 1E+03 ---- 3E+04 Co-60 3E+02 1E+04 Zn-65 3E+02 2E+04 Zr-Nb-95 4E+02 1-131 2E+Oob 9E-01 3E+00 1E+02 Cs-134 31E+01 1E+01 1E+03 6E+01 1E+03 Cs-137 5E+01 2E+01 2E+03 7E+01 2E+03 Ba-La-140 2E+02 3E+02 aFor drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

bjfno drinking water pathway exists, a value of 20 pCi/L may be used.

21

INTERPRETATIONS AND CONCLUSIONS Air Sampling The majority (>92%) of the 520 air cartridge (AC) samples from indicator and control stations had 1-131 concentrations less than the typical/worst case LLD of 5.1E-2 pCi/m 3. The air samplers operated for a total of 99.95% availability for the 2011 year. 1-131 was detected in air samples for a four week period following the Fukushima Dai-ichi nuclear power plant incident after the March 11, 2011, earthquake and tsunami (CR # 455413 and 456837).

For the period of January 1, 2011, to December 31, 2011, the gross beta activity was detectable in all airborne particulate (AP) samples, with acceptable runtime, from the nine indicator locations. The 468 indicator samples had an average concentration of 2.44E-2 pCi/m 3. Similar gross beta activities were observed at the control location in Florence, which had an average concentration of 2.5 1E-2 pCi/m 3 in 52 control samples. Figures 4 through 12 provide a graphic representation of the gross beta activity at the indicator locations compared to the control location for the year 2011. AP weekly samples that exhibit an elevated gross beta activity above the set administrative limits typically have a gamma isotopic analysis done and the results indicate all natural gamma activity. No plant-related gamma activity was observed for any air particulates during 2011, except for the 1-131 activity that was detected in 16 individual AP weekly indicator samples and three individual AP weekly control samples (CR # 455413 and 456837). The natural gamma concentrations are typical of the natural environment and are not attributed to plant operations and the 1-131 activity was not attributed to the plant operations, but to the Fukushima Dai-ichi nuclear power plant incident of March 11, 2011. Refer to the Missed Surveillance Section on the AC and AP Missed Surveillances in the 2011 collection year (CR #

465832, 465851, 469880, and 486916).

No plant-related gamma activity was detected in the quarterly composite filter samples from either the indicator or control locations; however, Cs-137 was detected in one set of quarterly composite samples (2 nd Qtr. 2011 AP-2 [CR # 479195]). Typical/worst case LLDs for air particulates are contained in Table 6.

22

Broadleaf Vegetation Broadleaf vegetation sampling is accomplished by collecting cherry, sassafras, and wax myrtle leaves in 2011. Three species of samples, when available, are collected monthly at five locations (one control and four indicator locations at the site boundary selected using historical meteorology with the highest calculated annual average ground level deposition). Broadleaf sampling is conducted since no milk animals are located within a radius of approximately five miles of the plant and is used to simulate dose to an individual via the milk pathway for compliance purposes.

During 2011, 17 of 48 samples taken from the indicator sites demonstrated detectable concentrations of Cs-137 for an average value of 5.05E-2 pCi/g (wet). The control samples had detectable concentrations of Cs- 137 in 9 of 12 samples with a mean concentration of 3.41 E-2 pCi/g (wet). Upon comparing these results, it is concluded that the indicator values reflect fallout Cs-137 contamination. Past sampling experience further supports this interpretation.

Refer to the Missed Surveillance Section for missed (unavailable) surveillances (CR # 443720, 449839, 455768, 489662, 490435, 497027, 501430, and 506243).

Fish Samples of free-swimming and bottom-feeding fish were taken from Lake Robinson and Prestwood Lake (the first downstream lake) and compared to similar fish from a control lake, which is unaffected by plant operation. During 2011, 4 out of 4 bottom-feeding fish and 4 out of 4 free-swimming fish (indicator sites) demonstrated detectable concentrations of Cs-137 for an average value of 4.57E-2 pCi/g (wet) and 5.51E-2 pCi/g (wet), respectively. The control samples had detectable concentrations of Cs-137 for 2 out of 2 bottom-feeding fish and 2 out of 2 free-swimming fish for an average concentration of 5.73E-2 pCi/g (wet) and 7.48E-2 pCi/g (wet), respectively. Upon comparing these results, it is concluded that the indicator values reflect fallout Cs-137 contamination. Past sampling experience further supports this interpretation.

23

Ground Water No by-product/plant-related gamma activity associated with plant operations was detected in the sixty (60) samples of ground water collected in 2011. The ground water samples had detectable concentrations of tritium activity in forty-two (42) out of sixty (60) samples, for an average concentration of 6.19E+2 pCi/L; with a range of 2.41E+2 pCi/L to 2.35E+3 pCi/L. During 2011, eight (8) ground water samples were analyzed for 1-131 to the Drinking water levels (<1 pCi/L).

No detectable concentrations of 1-131 activity were detected in the eight samples.

Milk Milk monitoring has not been conducted due to the unavailability of milk samples in the area since July 17, 1998, when the dairy ceased operation. Milk sampling will resume if a new sample location is identified. Broadleaf sampling is conducted since no milk animals are located within a radius of approximately five miles of the plant in any sector and is used to calculate dose to an individual via the vegetation-milk-man pathway. Refer to Broadleaf Vegetation Section for additional information.

Food Products During 2011, food product (FP) samples (collards, cucumbers, and squash) were obtained from the control location (FP-49) and from the indicator location (FP-58). No gamma activity associated with plant operation was detected in any control or indicator samples.

Shoreline Sediment In 2011, no gamma activity associated with plant operation was detected in any sample in the semiannual shoreline sediment samples. Only naturally occurring gamma activity was detected.

No Cs-137 activity was detected in 2011; however, Cs-137 activity seen in past years was attributed to worldwide fallout and not the plant operation.

24

Bottom Sediment The bottom sediment samples are used as indicators of buildup of radioactivity in the environment and do not constitute a dose pathway. Cs-137 activity was detectable in two of the three indicator bottom sediment samples in 2011, with an average concentration of 4.01 E-1 pCi/g (dry). The control sample indicated detectable Cs-137 activity with a concentration of 1.41E- 1 pCi/g (dry). Cobalt-60 (Co-60) activity was detectable in one of the three indicator samples with an average concentration of 1.46E- 1 pCi/g (dry). The Co-60 in the bottom sediment is attributed to plant operation. This concentration is similar to previous years and does not indicate a buildup in the environment. No other gamma activity, except for naturally occurring gamma activity, was detected in the annual bottom sediment samples in 2011.

Aquatic Vegetation The aquatic vegetation samples are considered to be sensitive environmental indicators used as long term trending and do not constitute a dose pathway. In 2011, there were three aquatic vegetation indicator samples collected and one aquatic vegetation control sample collected. The aquatic vegetation samples collected pose no dose consequence since this is not a dose pathway to the public. Cesium (Cs)-137 activity was also detected in two out of three indicator samples and the control sample with an average indicator value of 2.57E-2 pCi/g (wet) and the control value of 2.46E-2 pCi/g (wet). The Cs-137 in both the control and indicator samples appears to be fallout Cs-137 contamination. This concentration is similar to previous years and does not indicate unexpected levels in the environment.

Surface Water Surface waters of Lake Robinson indicated the presence of tritium which is attributed to plant operation. This tritium activity is cyclic and follows the Robinson Plant fuel cycle. Figure 13 displays the tritium activity throughout 2011. These surface waters do not supply drinking water at any downstream location and are not used for irrigation. Therefore, radiological dose via this pathway is limited to the consumption of fish (0.005 mrem/yr.) and evaporation of tritium (0.163 mrem/yr. using RNP 2011 Meteorology Data) from Lake Robinson and its subsequent inhalation and ingestion from vegetable gardens and meat producing animals. Using the methodology of Regulatory Guide 1.109, a dose of 0.168 millirem/year to the maximum exposed individual could be assigned to this pathway.

25

The monthly composite gamma analyses for surface water samples revealed no radionuclides typical of plant effluents. The RNP environmental monthly Ash Pond Surface Water (SW-57) composite sample from March 7, 2011, to April 5, 2011, (midpoint date March 21, 2011) indicated iodine- 131 (1-131) activity (1.78E+1 pCi/Liter). Other than the detected 1-131 activity, the gamma analysis of the composite surface water only detected natural occurring nuclides.

None of the other RNP composite surface water samples during this timeframe identified any detectable 1-131 activity, only natural occurring nuclides. Iodine- 131 was not identified in any monthly composite sample from this location prior to or after this stated collection period. The identification of the 1-131 activity is indicative of the Fukushima Dai-ichi nuclear power plant incident due to the March 11, 2011, earthquake and tsunami that hit Japan (CR # 459285).

External Radiation Direct radiation exposure in the HBRSEP environs was measured by the placement of thermoluminescent dosimeters (TLDs) around the plant forming an inner ring at approximately 1 mile and an outer ring at approximately 5 miles. The average of inner versus outer ring dose measurements is shown on Figure 14.

Asiatic Clams Benthic samples from Lake Robinson during 2011 continue to confirm the absence of any substantial populations of Asiatic clams (Corbiculafluminia). The natural chemistry of the lake (i.e., low alkalinity and hardness) inhibits their proliferation.

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MISSED SURVEILLANCES Air Cartridge and Air Particulates Any REMP weekly air samples (Air Cartridge - AC or Air Particulate - AP (APAC)) that exceed 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> of down time in a surveillance period will be reported as a "missed surveillance". However, this sample will still be counted and the data reported; whereas a "missed sample" indicates that no sample was available and no data was reported.

All AP and AC samples were available for counting in 2011.

Missed Samples:

  • APAC-07, May 16 - Total down time was 41.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. The air sampler was found not running as a result of a lighting hit (CR # 465832 and 465851).

Other down time in June of 2011 was identified that did not meet the definition of "missed surveillances" and the information pertaining to this event can be found in the corrective action program (CR # 469880). Damaged Petri dishes for two AP weekly samples (AP-1 and AP-7) collected August 29, 2011, through September 5, 2011, were documented. These samples were determined to be valid samples (CR # 486916).

Broadleaf Vegetation Broadleaf vegetation (BL) samples were not available during the months of January, February, March, April, September, October, November, and December of 2011 due to the seasonal nature of broadleaf vegetation (CR # 443720, 449839, 455768, 489662, 490435, 497027, 501430, and 506243).

The BL samples received in August of 2011 were opened and scattered within the sample shipment box. The plant personnel were contacted and the integrity of the August BL samples was discussed. It was decided that August BL samples would be resampled (CR # 485033).

27

Thermoluminescent Dosimeters (TLDs)

Four out of the possible 172 TLD samples were missing during 2011.

First Quarter - TLD # 26 was missing in the field (CR # 459892).

First Quarter - TLD # 31 was not changed out in early January 2011 when the TLD change out occurred. There was not a valid TLD in the field; therefore, the period during January 2011 until the deployment of the new TLD, the area was not monitored as required by the ODCM (CR # 445416).

First Quarter - TLD # 39 was not noted as missing on the sample shipment paperwork from RNP, but was not received at HEEC for processing; therefore, it is missing (CR # 465172).

Second Quarter - TLD # 12 was missing in the field where it was attached to a tree.

The area had been cleared of trees. The area was searched, but the TLD was not found (CR # 478138).

Second Quarter - Incorrect RNP transit environmental TLDs were returned to HEEC for processing. The 3 rd Qtr. 2011 RNP transit TLDs were returned to HEEC for processing when the 2 nd Qtr. 2011 transit TLDs should have been sent. TLD results had to be recalculated using the correct RNP transit TLDs (CR # 481938).

Fourth Quarter - TLD # 38 was missing in the field. The tree that the TLD was located had been removed from the area and a search of the area did not locate the missing TLD (CR # 507298).

28

ANALYTICAL PROCEDURES Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background Alpha/Beta Counting System. The LLD for air particulates is approximately 2.6E-3 pCi/m3 for RNP samples. Air particulate samples are mounted in 2-inch stainless steel planchets and typically counted directly for 50 minutes.

Gross beta activity in ground water is determined by evaporating 1.0 Liter of the sample, transferring it to a weighed planchet, and counting the planchet on a Tennelec Low-Background Alpha/Beta Counting System for 50 minutes. Typical/worst case LLD for gross beta is 9.OE- 1 pCi/L.

Tritium Liquid samples requiring tritium analysis are treated with a small amount of sodium hydroxide, potassium permanganate crystals, and then distilled. Five milliliters of the distillate are mixed with thirteen milliliters of liquid scintillation cocktail and counted in a liquid scintillation counter typically for 400 minutes. The lower LLD (approximately 2.20E+2 pCi/L) was established for consistency with the state laboratory for valid comparisons.

Iodine-131 Iodine- 131 airborne concentrations are analyzed by the high-purity germanium (Ge) gamma spectrometry systems. The cartridges are placed on the detector and each charcoal cartridge is typically counted for 900 seconds individually with an approximate LLD of 5.1 E-2 pCi/m3 .

Iodine- 131 in ground water and surface water is determined by an instrumental method.

Analysis involves passing 4 liters of sample over an anion exchange resin and direct gamma analysis of the resin with a high-purity Ge detector. The LLD using the Ge detector is approximately 1.OE+0 pCi/L using 40,000-second count time. Refer to Table 6 for Typical/Worst Case LLDs.

29

Gamma Spectrometry Gamma spectrum analysis uses high-purity germanium detectors with thin aluminum windows housed in steel and lead shields. The analyzer system is the Canberra APEX Gamma Spectroscopy System. Table 6 summarizes worst case LLD values derived from using the instrument with the worst sensitivity, typical sample volumes, typical count times, typical worst background count, and worst case on decay (from collection to counting).

Air particulate quarterly composite filters are placed in a Petri dish and analyzed directly for a typical count time of 900 seconds.

Liquid samples are transferred to Marinelli beakers and analyzed by gamma counting. One-liter ground water samples are gamma scanned directly in a 1-Liter Marinelli beaker for 14,000 seconds and the surface water samples for 73,000 seconds.

Shoreline and bottom sediments are dried, ground, weighed, and then analyzed in a 1-liter Marinelli beaker for 840 seconds (>1000 grams, dry) or 1,380 seconds (<1000 grams, dry).

Broadleaf and aquatic vegetation and food product samples are weighed as sampled (wet) and analyzed in a Marinelli beaker for typically 7,500 seconds.

Fish samples are prepared by placing small raw, edible portions of the fish in a 1-liter Marinelli beaker for gamma analysis and are typically counted for 1,500 seconds.

Thermoluminescent Dosimetry 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 light tight and the bag is weather-resistant.

Dosimeters are machine annealed before field placement. Following exposure in the field, each dosimeter is read utilizing a Panasonic TLD reader. This instrument integrates the light photons emitted from traps as the dosimeter is heated. Calibration is calculated using dosimeters irradiated to known doses for each set of dosimeters measured. Prior to the measurement of each dosimeter, the instrument is checked through use of an internal constant light source as a 30

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

Interlaboratory Comparison Program The Radiochemistry Laboratory at the Harris Energy & Environmental Center in New Hill, North Carolina, provides radioanalytical services for Progress Energy Carolinas, Inc.'s nuclear plant radiological environmental surveillance programs. In fulfillment of ODCM Operational Requirements, the laboratory is a participant in the Eckert & Ziegler Analytics Environmental Cross Check Program and uses its performance in this program as a major determinant of the accuracy and precision of its analytical results.

The Interlaboratory Comparison Program entails measurements on each instrument that is used to determine concentrations of radioactive material in the various media that are analyzed as part of the REMP. From these individual measurements, average results are calculated for each sample medium. During 2011, 82 average results were reported for the year on 17 samples representing seven major environmental media (i.e., water, milk, air filters, air filters composite, soil, air cartridges, and simulated vegetation). Data on the known activities, the uncertainties, and the ratios to the known for the 82 average results have been received from Eckert & Ziegler Analytics. The results were compared to the criteria established in the NRC Inspection Manual (Procedure 84750) for Radioactive Waste Treatment, Effluent, and Environmental Monitoring (see below results).

All of the 82 average results were within the acceptance criteria. During 2011, there were 401 individual measurements of which 398 (99.3%) were passing. The individual measurements were evaluated and results falling outside the acceptable ratio criteria had an evaluation performed to identify any recommended remedial actions and to reduce anomalous errors (CR #

485925). Complete documentation of any evaluation will be available and provided to the NRC upon request.

31

Environmental Cross Check Performance Summary for 2011 Sample Nuclide Quarter Units HEEC EZA HEEC/EZA Evaluation Value Value Ratio Gross beta water Gross beta I st pCi/L 260 247 1.05 Agreement I "Qtr E7457-668 3"a Qtr E8110-668 3td pCi/L 257 249 1.03 Agreement 4th Qtr E8237-668 4 pCi/L 259 252 1.03 Agreement Gross beta filter Gross beta 2 nd pCi 80.8 74.6 1.08 Agreement 2 ndQtr E7850-668 th 4"' Qtr E8236-668 4 pCi 66.2 65.5 1.01 Agreement Tritium in water H-3 1St pCi/L 4250 4530 0.94 Agreement I ý Qtr E7456-668 th 4th Qtr E8235-668 4 pCi/L 10600 10900 0.97 Agreement Iodine Cartridge 1-131 2 nd pCi 86.0 85.9 1.00 Agreement 2nd Qtr E7849-668 4"h QtrE8238-668 _________

4 th pCi 91.8 89.6 1.03 Agreement Gamma Milk 1-131 1A pCi/L 97.0 96.9 1.00 Agreement E7458-668 Cr-51 1st pCi/L 309 298 1.04 Agreement Cs-134 1st pCi/L 124 130 0.95 Agreement Cs-137 I St pCi/L 224 205 1.09 Agreement Co-58 1st pCi/L 116 113 1.02 Agreement Mn-54 ISt pCi/L 286 266 1.07 Agreement Fe-59 I st pCi/L 193 175 1.11 Agreement Zn-65 Ist pCi/L 281 261 1.08 Agreement Co-60 Ist pCi/L 179 172 1.04 Agreement Gamma Soil Cr-51 ist pCi/g 0.526 0.489 1.08 Agreement E7459-668 Cs-134 1st pCi/g 0.223 0.214 1.04 Agreement Cs-137 1st pCi/g 0.480 0.425 1.13 Agreement Co-58 1st pCi/g 0.192 0.186 1.03 Agreement Mn-54 ist pCi/g 0.475 0.436 1.09 Agreement Fe-59 1st pCi/g 0.325 0.286 1.14 Agreement Zn-65 1st pCi/g 0.472 0.428 1.10 Agreement Co-60 1st pCi/g 0.298 0.281 1.06 Agreement Gamma Ce-141 3rd pCi/g 0.156 0.169 0.92 Agreement Vegetation Cr-51 3 pCi/g 0.546 0.573 0.95 Agreement E8111-668 Cs-134 3 pCi/g 0.289 0.325 0.89 Agreement Cs-137 pCi/g 0.280 0.288 0.97 Agreement Co-58 3rd pCi/g 0.236 0.247 0.96 Agreement Mn-54 pCi/g 0.378 0.382 0.99 Agreement Fe-59 37r pCi/g 0.145 0.139 1.04 Agreement Zn-65 3rd pCi/g 0.456 0.457 1.00 Agreement Co-60 3 pCi/g 0.383 0.397 0.96 Agreement 32

Environmental Cross Check Performance Summary for 2011 Sample Nuclide Quarter Units HEEC EZA HEEC/EZA Evaluation Value Value Ratio Gamma Filter Ce-141 2d pCi 52.0 52.3 0.99 Agreement 2nd Qtr E7847-668 pCi 66.0 69.0 0.96 Agreement 3rd Qtr E8112-668 Cr-51 2 pCi 137 135 1.02 Agreement 3rd pCi 226 234 0.96 Agreement Cs-134 2nd pCi 132 124 1.06 Agreement pCi 136 133 1.02 Agreement Cs-137 2d pCi 99.0 90.2 1.10 Agreement 3rd pCi 118 118 1.00 Agreement Co-58 2d pCi 101 99.1 1.02 Agreement 37- pCi 97.0 101 0.96 Agreement Mn-54 2d pCi 98.0 90.1 1.09 Agreement 3rd pOi 165 156 1.06 Agreement Fe-59 2d pCi 98.0 80.6 1.22 Agreement 3rd pCi 67.0 56.8 1.18 Agreement Zn-65 2d pCi 203 170 1.19 Agreement 3rd pCi 209 187 1.12 Agreement Co-60 2d pCi 135 127 1.06 Agreement 3r'd pCi 158 163 0.97 Agreement Gamma 13 Filter Ce-141 2d pCi 62.0 64.7 0.96 Agreement Composite Cr-51 pCi 166 167 1.00 Agreement E7848-668 Cs-p134 2d pCi 159 154 1.04 Agreement Cs-137 pCi 117 112 1.05 Agreement Co-58 2 pCi 122 123 0.99 Agreement Mn-54 2d pCi 115 112 1.03 Agreement Fe-59 2 nd Ci 113 99.8 1.13 Agreement Zn-65 2d pCi 237 211 1.12 Agreement Co-60 2d pCi 161 157 1.02 Agreement 33

Environmental Cross Check Performance Summary for 2011 Sample Nuclide Quarter Units HEEC EZA HEEC/EZA Evaluation Value Value Ratio Gamma Water 1-131 2nd pCi/L 102 101 1.01 Agreement 2nd Qtr E7846-668 3rd pCi/L 82.0 80.1 1.02 Agreement 3Yd Qtr E8109-668 Ce-141 2Pd pCi/L 94 93.5 1.01 Agreement 3rd pCi/L 93.0 91.5 1.02 Agreement Cr-51 2ni pCi/L 251 241 1.04 Agreement 3rd pCi/L 329 310 1.06 Agreement Cs-134 2nd pCi/L 210 222 0.95 Agreement 3rd pCi/L 166 176 0.94 Agreement Cs-137 2 pCi/L 174 161 1.08 Agreement 3rd pCi/L 166 156 1.06 Agreement Co-58 2d pCi/L 179 177 1.01 Agreement 3rd pCi/L 140 134 1.05 Agreement Mn-54 2d pCi/L 169 161 1.05 Agreement Tr- pCi/L 220 207 1.06 Agreement Fe-59 2nd pCi/L 159 144 1.10 Agreement 3rd pCi/L 87.0 75.2 1.16 Agreement Zn-65 2d pCi/L 334 305 1.10 Agreement 3__d pCi/L 270 247 1.09 Agreement Co-60 2d pCi/L 239 228 1.05 Agreement 3rd pCi/L 218 215 1.01 Agreement Lower Limits of Detection The samples analyzed met the "a priori" LLD required by the ODCM. Typical/Worst Case "a priori" LLD values for the samples analyzed are listed in Table 6.

34

Table 6 Typical/Worst Case Lower Limits of Detection (a priori)

Gamma Spectrometry Sur~faceeWateuGoundwýater.6Samulesi .

A~~ 4 CU _______7_

Mn-54 3/6 Co-58 3/6 Fe-59 6/12 Co-60 2/7 Zn-65 5/12 Zr-Nb-95 5-4/11 -10 1-131 14/13 Cs-134 3/7 Cs-137 3/6 Ba-La-140 23-8/31-12 II T 11 (I)W1 II Cs-134 3.1 E-3 Cs-137 2.2E-3 35

Table 6 (cont.)

Mn-54 60 Co-58 70 Fe-59 141 Co-60 66 Zn-65 127 Cs-134 73 Cs-137 74 1-131 45/41 Cs-134 34 /29 Cs-137 32/20 36

LAND USE CENSUS PURPOSE OF THE LAND USE CENSUS The land use census identifies the pathways (or routes) that radioactive material may reach the general populations near commercial nuclear generating stations. This is accomplished by completing studies that identify how the surrounding lands are used by the population. A comprehensive census of the use of the land within a five-mile distance of the plant is completed during the growing season. This information is used for dose assessment and to identify changes to the stations sampled and the type of samples. These results ensure that the Radiological Environmental Monitoring Program (REMP) is based upon current data regarding human activity in the vicinity of the plant. Therefore, the purpose of the land use census is to ensure the monitoring program is current, as well as to provide data for the calculation of estimated radiation exposure.

The pathways that are evaluated are:

" Ingestion Pathway - Results from eating food products that may have radioactive materials deposited on them, incorporated radioactive materials from the soil or atmosphere. Another pathway is through drinking milk from local cows or goats if present. The grass used to feed these animals may have incorporated or had deposited on it radioactive materials that can be transferred to the milk.

  • Direct Radiation Exposure Pathway- Results from deposition of radioactive materials on the ground or from passage of these radioactive materials in the air.
  • Inhalation Pathway- Results from breathing radioactive materials transported in the air.

37

Methodology The following must be identified within the five (5) mile radius of the plant for each of the sixteen meteorological sectors (compass direction the winds may blow, for example NNE [North North East]):

  • The nearest resident
  • The nearest garden of greater that 500 square feet, producing broadleaf vegetables
  • The nearest milk animal

" The nearest meat/egg producing animal The primary methods are visual inspection from the roadside within the five (5) mile radius and personal contact with the individuals.

Land Use Census Results The HBRSEP (RNP) Land Use Census was performed July 2011 to meet the requirements of the HBRSEP's ODCM. The last HBRSEP land use census was performed in June 2010. The 2011 and 2010 results of the survey for the nearest resident, garden, milk producing animal, and meat/egg producing animal for each meteorological sector are compared in Table 7.

No milk producing animals were identified within the five-mile radius of the site in any sector.

Also, no garden (at the time of the census) is currently growing leafy vegetables. Vegetables like tomatoes, squash, okra, cucumbers, etc. are examples of the vegetables of choice for this area and are what is typically grown and sampled in the past. Sampling of these vegetables (non-leafy) will continue until leafy vegetables can be identified. Milk sampling will resume if a new sample location is identified. The results of the 2011 Land Use Census and 10 year average meteorological data were reviewed. No changes that require an ODCM change, additional dose calculations, or procedure changes were identified.

38

TABLE7 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 LAND USE CENSUS COMPARISONS (2010-2011)

NEAREST PATHWAY (MILES)

SECTOR RESIDENT GARDEN MEAT/ EGG MILK 2010 2011 2010 2011 2010 2011 2010 2011 N 2.81 2.81 3.31 3.29* ---- 4.75* ......

NNE 1.51 1.51 2.64 2.08* 2.59 2.59 NE 1.03 1.03 2.74 1.10* ----.....

ENE 0.83 0.83 3.80 1.07* 2.44 2.44 ......

E 0.90 0.90 1.05 1.05 2.98 2.98 ......

ESE 0.62 0.62 1.28 1.28 0.70 0.70 SE 0.38 0.38 1.20 1.20 2.00 2.00 ......

SSE 0.33 0.33 2.37 2.37 2.37 2.37 S 0.40 0.40 2.25 2.25 2.62 2.62 ......

SSW 0.37 0.37 0.84 0.84 0.84 0.84 SW 0.46 0.46 0.79 0.79 3.54 3.54 ......

WSW 0.45 0.45 0.60 0.88* 3.46 0.88* ......

W 0.54 0.54 0.70 0.70 0.84 0.84 WNW 0.60 0.60 0.70 0.83* 4.27 4.27 NW 1.59 1.59 2.43 2.43 2.09 2.07*

NNW 2.04 2.04 3.80 3.80 2.36 .

  • Changes or new locations from 2010.

C*Changes in mileage due to GPS readings.

39

Figure 4 For HBRSEP from 1/1/2011 To 12/31/2011 AIRPARnlCULATE for GROSS ELA -Actiity (*Clacublc meter)

Location 2 0,2 M S-INFORMATION CENTER _ Locmion 1 24A PA ESE-FLORENCE -CONTROL 0 .0 4 . .................. ... . .. .. . . .... . . . .

0.035 -----_---_-_

0.03 0.025 -&

Zp0.02 ----- -______

0.01 0.005 Jan-l1 Apr-11 Jul-11 Oc t-11 Mate 40

Figure 5 For HBRSEP from 1/1/2011Tlo 12/31/2011 AIR PARTICULATE for GROSS BDITA- Activity (pCVcubic meter)

-Lo.tlon 3 0.5 Mr N-MICROWAVETOWER -L Lo.ti~n 1 24.4 MI ESE-FLORENCE-CONTROL 0.045 0 .0 4 -.. ..... . . . .. .. ... . . . . ...... ....

0.03S 0.03- - .

4 0.025 .......

0.0o21-----------....

0 .00 5 ... . .. . . . . . . . .

0 Jan-11 Apr-11 Jul-11 OCIt-11 Dante 41

Flgur. 6 For HBRSEP from 1/1/2011 To 12/31/ 2011 AIRIPAERFICULATIE for (NtDSS (TA - Actftt(pCi/aabic meter)

.-- Locato41 0.4 PA ESE -SPILLWAY _eLocation 24.4 hMESE-FLORENCE

-CONtTROL.

0.04 -- -_ _ _ _- - -- - _ _ _ _ _ _

0.035S- - - _- ~ ___

0.03 0.025S ---- - - __

200.02 0.015 - -------

0.01 - -------- - - ------------- -________

0.005s---- - - ------.-.- __________

0 ------.------- - --- ,-.---..---

Jan-11 Apr-il Jul-il Oct-li Date 42

Figure 7 For HBRSEP from 1/1/2011 lb 12/31/2011 AIR PAKIICULATE for GIKSS B'IA - AdiitV (pCi/cubic meter)

-- Locations 0.9 MI ENE- EASTSHREOF LAKENEARJOHNSONS LANDING ,Locmationl 24.4M ESE- FLORENCE-CONTROL 0.04 0.035 0.03-0.025 0 .0 2 ..... .... . . . . . . . .. .. ... .. . . ..... ....

0.015 0

JIon-11 Apr-11 Jul-11 Oct-ll Date 43

Figure 8 For HBRSEP from 1/1/2011 To 12/31/2011 AIR PAIlnCULATE for GROSS UWIA - Actty kt(Cicusblc meter)

Location6 02 MI SSW- INFORMATION CENTER ,.,Locationl 24.4 M ESE- FLORENCE-CONTROL 0.035 - - - -------- ------------ -- - --- - -

0.03 0.025 -- "--

0.02 O.015 0.01 -_

0.005 0

Jan-11 Apr-11 Jul-12 Oct-1 1 Date 44

Figure 9 For HBRSEP from 1/1/2011 To 12/31/2011 AIR PARTICULATE for GROSS BETA - Acthulty (pCi/cubic meter) rLocation7 6.4 MI ESE-CP&L FACIUTYON RRAVE.,HARlIV1LLE -Locmton 1 24.4 MI ESE-FLORENCE-CONTROL 0.04 ..........

0-035 0.035 0.035 ---------------

0.025 0.02 ......

0 .0 15 -- ---------

0.01 0.005 Jan-11 Aor-11 Jul-11 Oct 11 Date 45

Figure 10 For HBRSEP from 1/1/2011 To 12/31/2011 AIRPARTICULATE for GIOSS BUfA - Activity (pCI/cubic meter)

-,mLo:ation 55 0.2 MI SSE -SOUTH OF WESTSEPTLING POND -.- Location 1 24.4 MI ESE- FLORENCE -CONTROL 0.04 ..........

0.035 ____ -------

0.03 - -------

0.025 0.02 -- ---- v-0.015- -

0.01 0,005 0

Jan-1l Apr-11 Jul-l1 Oct-ll Date 46

Figure 11 For HBRSEP from 1/1/2011 To 12/31/2011 AIRPAIRTICULATE for GROSS BETA - ActivttV fpCi/cbk meter)

-Lmoaton.60 0,2 F SE - ROBINSON PICNIC AREA -- 41-Loctionl 24.4MI ESE -FLORENCE -CONTROL 0.04 -- -

0.035 - ------ - - --- -___ A---------

h-0.03 ___ _

0.025 0.02 0,015 0.01 -- ----- - - -_

0.005 -

0 A---- -u --- Ot-Jan-11 Apr-11 Jul-il oct-s11 Date 47

Figure 12 For HBRSEP from 1/1/2011 To 12/31/2011 AIRPARTICULATE for GOIMS BETA -Actity (pCi/cubic meter)

- Loc.*Iol61 0.3MI WSW -WESTPARKINGLOTNEAR RRTRACMKS Loction1 24.4 MI ESE- FLORENCE-CONTROL 0.04 A

0.035 0.03 0.025 641 w IT V4V"UIV'W I

V4TV ýk\ vljvi A-0.02 U S 0.015 II 0.01 +

0.005 o 4 Jan-11 Apr-li Jul-11 Oct-11 Date 48

Figure 13 RNP 2011 Surface Water Tritium

--- Location 41 8.0 miles N Black Greek at US I - Control

- Location 57 Ashpond 8000 -A---Location 40 0.6 miles ESE Black Creek at Old Camden Rd.

7000

-v Location 66 Black Creek between Prestwood Lake discharge&

uostream of Sonoco soray farm 5000 4000

< 3000 2000 1000 0

NN N N N N N

N r

Dates 49

Figure 14 RNP 2011 TLD Averages for Inner and Outer Ring Locations 18 16 14 12 S

  • 1 10 0

8 I

I a

6 4

2 0

2/15/111 2115/11 5115/111 5115/11 8/15 1/1 /11 11115/111115111 Inner Outer Inner Outer Inner Outer Inner Outer 50

HBRSEP (RNP)

TLD Report

  • 9 pages Analysis Report
  • 49 pages Gamma Isotopic Report 0 87 pages 51
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