Text

Annual Radiological Environmental Operating Report for the Period of January 1 Through December 31, 2010
	ML111250367
Person / Time
Site:	Clinton
Issue date:	04/30/2011
From:	; Exelon Nuclear, Teledyne Brown Engineering Environmental Services
To:	; Office of Nuclear Reactor Regulation
References
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	Download: ML111250367 (129)
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Intentionally left blank Docket No: 50461 CLINTON POWER STATION Annual Radiological Environmental Operating Report 1 January Through 31 December 2010 Prepared By Teledyne Brown Engineering Environmental Services Exel n PA Nuclear Clinton Power Station Clinton, IL61727 April 2011

Intentionally left blank Table Of Contents I. Sum m ary and Conclusions .............................................................................................. 1 I1. Introduction ............................................................................................................. 3 A. Objectives of the REM P .................................................................................. 3 B. Im plem entation of the O bjectives .................................................................. 3 II1. Program Description ................................................................................................ 4 A. Sam ple Collection ......................................................................................... 4 B. Sam ple Analysis ............................................................................................ 6 C. Data Interpretation ......................................................................................... 6 D. Program Exceptions ....................................................................................... 7 E. Program Changes ......................................................................................... 10 IV. Results and Discussion ......................................................................................... 11 A. Aquatic Environm ent ..................................................................................... 11

1. Surface W ater ................................................................................... 11

2. Drinking Water ..................................... 12

3. W ell W ater ....................................................................................... 12

4. Fish ..................................................................................................... 13

5. Sedim ent ............................................................................................ 13 B. Atm ospheric Environm ent ........................................................................... 14

1. Airborne .............................................................................................. 14

a. Air Particulates ....................................................................... 14

b. Airborne Iodine ...................................................................... 15

2. Terrestrial ............................................................................................ 15

a. M ilk .......................................................................................... 15

b. Food Products ......................................................................... 15

c. G rass ....................................................................................... 16 C. Am bient Gam m a Radiation ......................................................................... 16 D. Land Use Survey ............................................. 17 E. Summary of Results - Inter-laboratory Comparison Program ............... 17 V. References ................................................................................................................... 19 i

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Clinton Power Station, 2010 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Radiological Environmental Monitoring Program - Sampling Locations, Table B-1 Distance and Direction, Clinton Power Station, 2010 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection, Clinton Power Station, 2010 Figures Figure B-1 Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2010 Figure B-2 Environmental Sampling Locations Between One and Two Miles from the Clinton Power Station, 2010 Figure B-3 Environmental Sampling Locations Between Two and Five Miles from the Clinton Power Station, 2010 Figure B-4 Environmental Sampling Locations Greater Than Five Miles from the Clinton Power Station, 2010 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1. 1 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2010.

ii

Table C-11.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-11.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-11.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-111.1 Concentrations of Tritium in Well Water Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-111.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-IV.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-VI.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-VI.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-VI.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-VII.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-VIII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-VIII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-IX.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-IX.2 Concentrations of Gamma Emitters in Grass Samples Collected in the Vicinity of Clinton Power Station, 2010.

Table C-X.1 Quarterly TLD Results for Clinton Power Station, 2010.

Table C-X.2 Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Special Interest and Control Locations for Clinton Power Station, 2010.

Table C-X.3 Summary of the Ambient Dosimetry Program for Clinton Power Station, 2010.

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Figqures Figure C-1 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of CPS, 2010.

Figure C-2 Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of CPS, 2010.

Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2010 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2010 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2010 Appendix E Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Clinton Power Station (CPS) by Exelon covers the period 1 January 2010 through 31 December 2010. During that time period, 1,576 analyses were performed on 1,461 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of CPS had no adverse radiological impact on the environment.

There were zero (0) radioactive liquid releases from CPS during 2010. Releases of gaseous radioactive materials were accurately measured in plant effluents.

There were no gaseous effluent releases that approached the limits specified in the CPS Offsite Dose Calculation Manual (ODCM). The highest calculated offsite dose received by a member of the public due to the release of gaseous effluents from Clinton Power Station was 3.36 E-02 or 0.0336 mRem.

Surface, drinking, and well water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of gross beta and 1-131. Naturally occurring K-40 was detected at levels consistent with those detected in previous years. No fission or activation products were detected. Gross beta activities detected were consistent with those detected in previous years. No tritium activity was detected and the required lower limit of detection (LLD) was met.

Fish and shoreline sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish or shoreline sediment samples.

Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Cosmogenic Be-7 and naturally occurring K-40 were detected at levels consistent with those detected in previous years. No fission or activation products were detected.

High sensitivity 1-131 analyses were performed on weekly air samples. All required LLDs were met.

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the required LLDs.

Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.

Food product samples were analyzed for concentrations of gamma emitting nuclides. Concentrations of Cosmogenic Be-7 and naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.

Grass samples were analyzed for concentrations of gamma emitting nuclides.

Concentrations of Cosmogenic Be-7 and naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.

Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. Levels detected were consistent with those observed in previous years.

II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on 15 February 1987. The site encloses approximately 13,730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated on approximately 150 acres. The cooling water discharge flume - which discharges to the eastern arm of the lake - occupies an additional 130 acres.

Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13,730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa Anna Townships.

A Radiological Environmental Monitoring Program (REMP) for CPS was initiated in 1987. The preoperational period for most media covers the periods May 1980 through 27 February 1987 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Global Dosimetry on samples collected during the period 1 January 2010 through 31 December 2010.

A. Objectives of the REMP The objectives of the REMP are to:

1. Provide data on measurable levels of radiation and radioactive materials in the site environs.

2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.

B. Implementation of the Objectives The implementation of the objectives is accomplished by:

1. Identifying significant exposure pathways.

2. Establishing baseline radiological data of media within those pathways.

3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.

Ill. Program Description A. Sample Collection This section describes the general collection methods used by Environmental Inc. (Midwest Labs) to obtain environmental samples for the CPS REMP in 2010. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-I through B-3, Appendix B. The sampling methods used by Environmental Inc. (Midwest Labs) are listed in Table B-2.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, well water, fish, and shoreline sediment. Two gallon water samples were collected monthly from continuous samplers located at three surface water locations (CL-90, CL-91 and CL-99) and one drinking water location (CL-14). A monthly grab sample was obtained from one surface water location (CL-13).

Quarterly samples were obtained from two well water locations (CL-7D and CL-12). All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of largemouth bass, crappie, carp, bluegill and channel catfish the species most commonly harvested from the lakes by sporting fishermen, were collected semiannually at two locations, CL-19 and CL-1 05 (control). Shoreline sediment samples composed of recently deposited substrate were collected at one location semiannually, CL-7B.

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, food produce and grass. Airborne iodine and particulate samples were collected and analyzed weekly at ten locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15, and CL-94). The control location was CL-11.

Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.

Milk samples were collected biweekly at one location (CL-1 16) from May through October, and monthly from November through April to coincide with the grazing season. All samples were collected in new unused plastic bottles from the bulk tank at that location, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Food products were collected once a month from June through October at four locations (CL-1 14, CL-1 15, CL-1 17 and CL-1 18). The control location was CL-1 14. Various broadleaf vegetable samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Grass samples were collected biweekly at four locations (CL-1, CL-2, CL-8 and CL-1 16) from May through October. The control location was CL-1 16. All samples were collected in new unused plastic bags and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct radiation measurements were made using Panasonic 814 calcium sulfate (CaSO 4 ) thermoluminescent dosimeters (TLD). The TLD locations were placed around the CPS site as follows:

An inner ring consisting of 16 locations (CL-1, CL-5, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42 CL-43, CL-44, CL-45, CL-46, CL-47, CL-48 and CL-63). An additional three locations were installed as part of a volunteer comparison study near and within the site perimeter (CL-5MM, CL-46MM and CL-47MM).

An outer ringq consisting of 16 locations (CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80 and CL-81). CL-58MM was installed as part of a volunteer comparison study extending to approximately 5 miles from the site.

A special interest set consisting of seven locations (CL-37, CL-41, CL-49, CL-64, CL65, CL-74 and CL-75) representing special interest areas.

A supplemental set consisting of 14 locations (CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99, and CL-1 14).

CL-1 1 represents the control location for all environmental TLDs.

The specific TLD locations were determined by the following criteria:

1. The presence of relatively dense population;

2. Site meteorological data taking into account distance and elevation for each of the sixteen-22 1/2 degree sectors around the site, where estimated annual dose from CPS, if any, would be most significant;

3. On hills free from local obstructions and within sight of the vents (where practical);

4. And near the closest dwelling to the HVAC and VG stacks in the prevailing downwind direction.

Two TLDs - each composed of two CaSO 4 thermoluminescent phosphors enclosed in plastic - were placed at each location in a vented PVC conduit located approximately three feet above ground level. The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis.

B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the CPS REMP in 2010. The analytical procedures used by the laboratories are listed in Table B-2.

In order to achieve the stated objectives, the current program includes the following analyses:

1. Concentrations of beta emitters in drinking water and air particulates.

2. Concentrations of gamma emitters in surface, drinking and well water, air particulates, milk, fish, grass, sediment and vegetables.

3. Concentrations of tritium in surface, drinking and well water.

4. Concentrations of 1-131 in air, milk, vegetables and drinking water.

5. Ambient gamma radiation levels at various on-site and off-site environs.

C. Data Interpretation The radiological and direct radiation data collected prior to CPS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this report, CPS was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required CPS detection capabilities for environmental sample analysis.

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity resulting in a negative number. A minimum detectable concentration (MDC) was reported in all cases where positive activity was not detected.

Gamma spectroscopy results for each type of sample were grouped as follows:

For surface water, well water, fish, sediment, and milk 14 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140, La-140, and Ce-144 were reported.

For drinking water, grass, and vegetation 15 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, La-140, and Ce-144 were reported.

For air particulate 11 nuclides, Be-7, K-40, Co-60, Nb-95, Zr-95, Ru-103, Ru-106, Cs-134, Cs-137, Ce-141 and Ce-144, were reported.

Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D. Program Exceptions The exceptions described below are those that are considered 'deviations' from the Radiological Environmental Monitoring Program as required by the Station's ODCM. By definition, 'deviations' are permitted as delineated within NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and within Radiological Assessment Branch Technical Position, Revision 1, November 1979, which states.... "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons".... The below section addresses the reporting requirements found within Section 7.1 of the Station's ODCM.

April 28, 2010, IR # 1062603 The vendor technician discovered that ODCM drinking water compositor CL-14 was not collecting sample as expected. Plant personnel performed maintenance and returned the compositor to service, however, the April, 2010 sample did not meet the definition of a composite.

May 25, 2010, IR # 1076800 During an unplanned power outage affecting the Service Building, power was lost to ODCM drinking water compositor CL-14, rendering it unable to collect samples and meet the requirement for composite sampling for the month of May, 2010.

July 28, 2010, IR # 1095275 During a potable water outage on July 28, 2010, ODCM drinking water compositor CL-14 was unable to obtain aliquot samples and meet the requirement of composite sampling.

August 25, 2010, IR # 1106720 Due to low levels of rain fall, the vendor was unable to obtain sufficient amounts of lettuce and swiss chard to constitute valid samples for the August 2010 monthly vegetation samples from gardens CL-114, CL-115, CL-117 and CL-118. The vendor supplemented the weight with other available broad leaf plants.

September 29, 2010, IR 1186555 The sample collector was unable to obtain enough vegetation for the September monthly sample for CL-1 14, so the weight was supplemented with other available vegetation. At the ODCM program owner's request, unscheduled supplemental vegetation sampling was conducted on October 13, 2010. For informational purposes, weed and tree leaf material was collected from the areas of CL-1 14, CL-115, CL-117, and CL-118.

October 13, 2010, IR # 1125934 On October 13, 2010, non-ODCM air samplers CL-4 and CL-6 were found without power and unable to sample due to a rain storm in the area the same morning. Flow and subsequent volumes could not be determined for analysis purposes.

November 3, 2010 IR # 1142421 On November 3, 2010, ODCM Water Compositor CL-91 was found with no flow through the instrument by the sample collection vendor. Troubleshooting was performed and flow was re-established. On November 10, 2010, CL-91 was again found with no flow. Further troubleshooting identified a worn length of tubing which, upon replacement, corrected the no-flow condition. The vendor collected grab samples during this timeframe.

November 20, 2010, IR # 1143173 During a 12 kV bus outage, the ODCM drinking water compositor CL-14 was without power and unable to sample on November 20, 2010 from 05:07 to 16:05. The compositor was isolated for approximately 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months .

November 24, 2010, IR # 1144688 On November 24, 2010, ODCM Air Sampler CL-15 and NON-ODCM Air Sampler CL-94 were found with no power by the sampling vendor. The vendor was able to collect samples, and all LLDs were achieved, however, continuous sampling was not achieved.

December 1, 2010, IR # 1150469 While performing routine sample collection and equipment verification activities on December 1,2010, the sampling vendor discovered that NON-ODCM Air Sampler CL-6 had experienced an apparent power outage of approximately 111 hours0.00128 days 0.0308 hours 1.835317e-4 weeks 4.22355e-5 months at some point since the previous time the monitor was checked on November 24, 2010.

December 22, 2010 IR# 1155368 On December 22, 2010, the non-ODCM water compositor CL-99 was found to be unable to collect samples due to apparent freezing of the North Fork Creek. The condition was discovered by the sampling vendor while performing the weekly equipment inspections. While the compositor had collected some liquid sample, the November sample did not meet the definition of a composite.

Program exceptions were reviewed to understand the causes of the exception and to return to ODCM sample compliance before the next sampling frequency period.

The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E. Program Changes Although there were no changes to the program in 2010, during a 2008 annual NRC ODCM REMP inspection, there was an enhancement. An Inspector observed the orientation of an environmental area TLD and as an enhancement, suggested that if relocated approximately sixty (60) feet closer towards the Station, would serve better as a direct line of sight in a cleared opening, unobstructed from tree branches and leaves.

Over the twenty (20) plus years of Unit Operation, the surrounding environment consisting of tress and their branches have grown, thus challenging the guidance ANSI N545-1975, which requires TLDs should be moved as far as possible from large or dense objects that may cause directional anomalies or otherwise perturb the radiation field. Although historical reviews were performed that resulted in no anomalous data relative to the radiation field, as part of our extent of condition, all environmental TLDs were evaluated as to locations and their respective orientations with the following determination:

Completed:

" A review of the results from adjacent Environmental Area TLD data sectors revealed no significant patterns or variances.

An extent of condition review examined all Environmental Area TLD locations and their respective orientations and identified three (3) additional locations as candidates for additional monitoring.

Clinton Power Station has installed four (4) TLDs in close proximity to the original TLDs: CL-5MM, CL-46MM, CL-47MM and CL-58MM.

These Environmental Area TLDs located within the same meteorological sector near the four (4) locations, were measured and studied for comparison (Table C-X.1).

o TLDs CL-05MM, CL-47MM, and CL-58MM showed a slight increase in the first quarter of 2010 by a difference of 0.5, 3.0, and 0.8 mRem respectively. The second and third quarter of 2010 showed less exposure than the originally installed locations.

o TLD CL-46MM showed a slight increase for all four quarters of 2010, averaging 3.2 mRem higher than the originally installed location.

o TLD CL-05MM was slightly higher in the fourth quarter of 2010 by a difference of 1.0 mRem.

Clinton Power Station will continue this comparison study throughout 2011.

Because the TLD results from this study are not part of the ODCM REMP averages, the results are for comparison purposes only.

IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken hourly, from a continuous compositor at three locations (CL-90, CL-91 and CL-99) on a monthly schedule and grab samples were taken monthly from one station (CL-1 3). The following analyses were performed.

Iodine-131 Monthly samples from location CL-90 were analyzed for 1-131 activity (Table C-1.1, Appendix C). No 1-131 was found and the required LLD was met.

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.2, Appendix C). The required LLD was met.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). Naturally occurring K-40 was found in one of 12 samples at location CL-13, three of 12 samples at location CL-90, one of 12 samples at location CL-91 and three of 12 samples at location CL-99. No other nuclides were detected and all required LLDs were met.

2. Drinking Water Monthly samples were collected from a continuous compositor at one location (CL-14). The following analyses were performed:

Gross Beta Monthly samples were analyzed for concentrations of gross beta (Tables C-I1.1, Appendix C). Gross beta was found in three of 12 samples. The values ranged from 2.0 to 4.4 pCi/I. Concentrations detected were consistent with those detected in previous years.

Tritium Monthly samples were composited quarterly and analyzed for tritium activity (Table C-I1.2, Appendix C). The required LLD was met.

Gamma Spectrometry Monthly samples were analyzed for gamma emitting nuclides (Table C-11.3, Appendix C). Naturally occurring K-40 was found in one sample at location CL-14. No other nuclides were detected and all required LLDs were met.

3. Well Water Quarterly grab samples were collected at two locations (CL-7D and CL-12, consisting of CL-12R [a raw water sample from this well]

and CL-12T [same well water, but after treatment and available for consumption]). The following analyses were performed:

Tritium Samples from all locations were analyzed for tritium activity (Table C-111.1, Appendix C). The required LLD was met.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-111.2, Appendix C). Naturally occurring K-40 was found in one of four samples for locations CL-12T. No other nuclides were detected and all required LLDs were met.

4. Fish Fish samples comprised of carp, largemouth bass, bluegill, crappie and channel catfish were collected at two locations (CL-19 and CL-1 05) semiannually. The following analysis was performed:

Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C).

Naturally occurring K-40 was found at both stations. No fission or activation products were found. No other nuclides were detected and the required LLDs were met.

5. Shoreline Sediment Aquatic shoreline sediment samples were collected at CL-7B semiannually. The following analysis was performed:

Gamma Spectrometry Shoreline sediment samples were analyzed for gamma emitting nuclides (Table C-V.1, Appendix C). Naturally occurring K-40 was detected in both samples. No fission or activation products were found. No other nuclides were detected and the required LLDs were met.

B. Atmospheric Environment Airborne

a. Air Particulates Continuous air particulate samples were collected from 10 locations on a weekly basis. The 10 locations were separated into three groups: Group I represents locations within one mile of the CPS site boundary (CL-2, CL-3, CL-4, CL-6, CL-15, and CL-94). Group II represents the locations at an intermediate distance within one to five miles of CPS (CL-1, CL-7, and CL-8), and Group III represents the control location greater than five miles from CPS (CL-1 1). The following analyses were performed:

Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-VI.1 and C-VI.2 and Figure C-1, Appendix C).

Detectable gross beta activity was observed at all locations.

Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of CPS. The results from the On-Site locations (Group I) ranged from 6 to 39 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from 6 to 41 E-3 pCi/mi3 with a mean of 18 E-3 pCi/m 3 . The results from the Control locations (Group Ill) ranged from 6 to 37 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3 . Comparison of the 2010 air particulate data with previous years data indicate no effects from the operation of CPS (Figure C-5, Appendix C). In addition, a comparison of the weekly mean values for 2010 indicate no notable differences among the three groups.

Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-VI.3, Appendix C).

Naturally occurring isotope Be-7 due to cosmic ray activity was detected in all samples. Naturally occurring K-40 was detected in two samples. No other nuclides were detected and all required LLDs were met.

b. Airborne Iodine Continuous air samples were collected from 10 locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94) and analyzed weekly for 1-131 (Table C-VII.l, Appendix C). All results were less than the MDC and the required LLD was met.

2. Terrestrial

a. Milk Samples were collected from CL-1 16 biweekly May through October and monthly November through April, to coincide with the grazing season. The following analyses were performed:

Iodine-131 Milk samples were analyzed for concentrations of 1-131 (Table C-VIII.1, Appendix C). The required LLD was met.

Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VIII.2, Appendix C).

Naturally occurring K-40 activity was found in all samples.

No other nuclides were detected and all required LLDs were met.

b. Food Products Broadleaf vegetation samples and substitutes as noted in exceptions were collected from four locations (CL-1 14, CL-1 15, CL-1 17 and CL-1 18) monthly June through October, to coincide with the harvest season. The following analyses were performed:

Gamma Spectrometry Each food product sample, cabbage, swiss chard, lettuce, and substitutions as noted earlier were analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C).

Naturally occurring Be-7 due to cosmic ray activity was detected in all samples. Naturally occurring K-40 activity was found in all samples. No other nuclides were detected and all required LLDs were met.

c. Grass Samples were collected from four locations (CL-1, CL-2, CL-8, and CL-1 16) biweekly May through October. The following analyses were performed:

Gamma Spectrometry Each grass sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.2, Appendix C).

Naturally occurring Be-7 due to cosmic ray activity was detected in all samples. Naturally occurring K-40 activity was found in all samples. No other nuclides were detected and all required LLDs were met.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO 4 ) thermoluminescent dosimeters. Fifty-four TLD locations were established around the site. Results of TLD measurements are listed in Tables C-X.1 to C-X.3, Appendix C.

A total of 216 TLD measurements were made in 2010. The average dose from the inner ring was 18.7 mR/quarter. The average dose from the outer ring was 19.0 mR/quarter. The average dose from the special interest group was 18.7 mR/quarter. The average dose from the supplemental group was 17.9 mR/quarter. The quarterly measurements ranged from 13.8 to 23.7 mR/quarter.

The inner ring and outer ring measurements compared well to the Control Station, CL-11, which ranged from 14.9 mR/quarter to 21.3 mR/quarter with an average measurement of 17.4 mR/quarter. A comparison of the Inner Ring and Outer Ring data to the Control Location data indicate that the ambient gamma radiation levels from all the locations were comparable. The historical ambient gamma radiation data from the control location were plotted along with similar data from the Inner and Outer Ring Locations (Figure C-2, Appendix C).

16-

At the end of 2010, the data comparison between the original and newly installed TLDs showed comparable results.

D. Land Use Survey A Land Use Survey conducted during the July through October 2010 growing season around the Clinton Power Station (CPS) was performed by Environmental Inc. (Midwest Labs) for Exelon to comply with Clinton's Offsite Dose Calculation Manual, section 5.2. The purpose of the survey was to document the nearest resident, milk producing animal and garden of greater than 538 ft2 in each of the sixteen 22 1/2 degree sectors around the site. The distance and direction of all locations from the CPS Station HVAC vent stack were positioned using Global Positioning System (GPS) technology. There were no changes required to the CPS REMP, as a result of this survey. The results of this survey are summarized below.

Distance in Miles from the CPS Station HVAC Vent Stack Sector Residence Garden Milk Farm Miles Miles Miles 1 N 0.9 0.9 0.9 2 NNE 1.0 3.0 2.3 3 NE 1.3 2.2 >5.0 4 ENE 1.8 2.7 >5.0 5E 1.0 1.0 >5.0 6 ESE 3.2 3.3 >5.0 7 SE 2.4 2.4 >5.0 8 SSE 1.7 >5.0 >5.0 9S 3.0 3.0 >5.0 10 SSW 2.9 >5.0 >5.0 11 SW 0.7 3.5 >5.0 12 WSW 2.2 2.3 3.4 13W 1.2 2.1 >5.0 14 WNW 1.6 >5.0 >5.0 15 NW 1.6 >5.0 >5.0 16 NNW 1.3 1.3 1.3 E. Summary of Results - Inter-Laboratory Comparison Program The primary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for 19 analytes (Appendix D). The PE samples, supplied by Analytics Inc.,

Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.

2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.

The MAPEP defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/- 20% to +/- 30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

For the primary laboratory, 16 out of 18 analytes met the specified acceptance criteria. Two analytes did not meet the specified acceptance criteria for the following reason:

1. Teledyne Brown Engineering's ERA November 2010 Sr-89 in water result of 77.8 pCi/L was higher than the known value of 68.5 pCi/L, resulting in a found to known ratio of 1.14. NCR 10-09 was initiated to investigate this failure. Since the ratio of 1.14 fell within an acceptance range of 20%, Teledyne considers this an acceptable result.

2. Teledyne Brown Engineering's ERA November 2010 Zn-65 in water result of 11.0 pCi/L was lower than the known value of 102 pCi/L. NCR 10-09 was initiated to investigate this failure. The Zn-65 result of 111 was incorrectly reported as 11.0.

For the secondary laboratory, Environmental, Inc., 14 out of 14 analytes met the specified acceptance criteria.

The Inter-Laboratory Comparison Program provides evidence of the counting systems and methods, and that the laboratories are producing accurate and reliable data.

V. References

1. American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," ANSI N545-1975.

2. Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission).

3. CPS 2010 Annual Radioactive Effluent Release Report.

4. "Environmental Radioactivity," M. Eisenbud, 1987 (E187).

5. "Natural Radon Exposure in the United States," Donald T. Oakley, U.S.

Environmental Protection Agency. ORP/SID 72-1, June 1972.

6. Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards," May 13, 1960.

7. International Commission on Radiation Protection, Publication 2, "Report of Committee II on Permissible Dose for Internal Radiation," (1959) with 1962 Supplement issued in ICRP Publication 6; Publication 9, "Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 26 (1977).

8. International Commission on Radiation Protection, Publication No. 39 (1984), "Principles of Limiting Exposure to the Public to Natural Sources of Radiation".

9. "Radioactivity in the Environment: Sources, Distribution and Surveillance," Ronald L. Kathren, 1984.

10. National Council on Radiation Protection and Measurements, Report No.

22, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52).

11. National Council on Radiation Protection and Measurements, Report No.

39, "Basic Radiation Protection Criteria," January 1971.

12. National Council on Radiation Protection and Measurements, Report No.

44, "Krypton-85 in the Atmosphere - Accumulation, Biological Significance, and Control Technology," July 1975.

13. National Council on Radiation Protection and Measurements, Report No.

91, "Recommendations on Limits for Exposure to Ionizing Radiation,"

June 1987.

14. National Council on Radiation Protection and Measurements, Report No.

93, "Ionizing Radiation Exposure of the Population of the United States,"

September 1987.

15. National Research Council, 1990, Committee on Biological Effects of Ionizing Radiation (BEIR V), Board on Radiation Effects Research on Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation".

16. United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the 'Environs of Nuclear Power Plants," Revision 1, April 1975.

17. United States Nuclear Regulatory Commission, Regulatory Guide 4.13, "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, "Revision 1, July 1977.

18. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, "Revision 1, October 1977.

19. United States Nuclear Regulatory Commission Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program,"

Revision 1, November 1979.

20. United States Nuclear Regulatory Commission, Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Norm Operations) - Effluent Streams and the Environment," Revision 1, February 1979.

21. Technical Specifications, Clinton Power Station, Unit No. 1, Docket No.

50-461, Office of Nuclear Reactor Regulation, 1986. Facility Operating License Number NPF-62.

22. Clinton Power Station, Updated Safety Analysis Report.

23. Clinton Power Station, Unit 1, Off-Site Dose Calculation Manual.

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT