0CAN051201, Units 1 and 2, Annual Radiological Environmental Operating Report for 2011

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Units 1 and 2, Annual Radiological Environmental Operating Report for 2011
ML12129A104
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 05/07/2012
From: Pyle S
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
0CAN051201
Download: ML12129A104 (45)
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Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Licensing Arkansas Nuclear One 0CAN051201 May 7, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Annual Radiological Environmental Operating Report for 2011 Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6

REFERENCE:

Entergy letter dated April 27, 2012, Annual Radioactive Effluent Release Report for 2011 (0CAN041201)

Dear Sir or Madam:

In accordance with Arkansas Nuclear One (ANO), Unit 1 Technical Specification (TS) 5.6.2 and Unit 2 TS 6.6.2, the submittal of an annual radiological environmental operating report for the previous year is required by May 15 of each year. The subject ANO report for the calendar year 2011 is enclosed.

This report fulfills the reporting requirements of the TSs referenced above.

The radionuclides detected by the radiological environmental monitoring program during 2011 were significantly below the regulatory limits. The operation of the ANO station during 2011 had no harmful effects nor resulted in any irreversible damage to the local environment.

Based on ANOs review, no environmental samples from the monitoring program equaled or exceeded the reporting levels for radioactivity concentration due to ANO effluents when averaged over any calendar quarter. A map of all sampling locations and a corresponding table providing the respective distances and directions from the reactor building is included in the Offsite Dose Calculation Manual submitted as part of the Annual Radioactive Effluent Release Report (Reference 1).

This letter contains no new commitments.

0CAN051201 Page 2 of 2 If you have any questions or require additional information, please contact me.

Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/rwc

Enclosure:

Annual Radiological Environmental Operating Report for 2011 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

Enclosure to 0CAN051201 Annual Radiological Environmental Operating Report for 2011

Enclosure to 0CAN051201 Page 1 of 42 Table of Contents Summary..................................................................................................................................2 1.0 Introduction ....................................................................................................................5 1.1 Radiological Environmental Monitoring Program ................................................5 1.2 Pathways Monitored............................................................................................5 1.3 Land Use Census................................................................................................6 2.0 Interpretation and Trends of Results .............................................................................16 2.1 Air Particulate and Radioiodine Sample Results.................................................16 2.2 Thermoluminescent Dosimetry (TLD) Sample Results .......................................16 2.3 Water Sample Results ........................................................................................16 2.4 Sediment Sample Results ...................................................................................17 2.5 Milk Sample Results............................................................................................18 2.6 Fish Sample Results ...........................................................................................19 2.7 Food Product Sample Results.............................................................................19 2.8 Interlaboratory Comparison Results....................................................................19 2.9 Land Use Census Results...................................................................................19 3.0 Radiological Environmental Monitoring Program Summary ..........................................20 3.1 2011 Program Results Summary ........................................................................20 Tables Table 1.1 Radiological Environmental Sampling Program ...............................................7 Table 2.1 2011 Land Use Census ....................................................................................20 Table 3.1 Radiological Environmental Monitoring Program Summary .............................21 Figures Figure 1-1 Sample Collection Sites - NEAR FIELD ..........................................................13 Figure 1-2 Sample Collection Sites - FAR FIELD .............................................................14 Figure 1-3 Sample Collection Sites - SITE MAP...............................................................15 Attachments 2011 Radiological Monitoring Report Summary of Monitoring Results........25 Interlaboratory Comparison Program...........................................................37 Sediment Dose Calculations........................................................................42

Enclosure to 0CAN051201 Page 2 of 42 Summary The Annual Radiological Environmental Operating Report (AREOR) presents data obtained through analyses of environmental samples collected for Arkansas Nuclear One's (ANOs)

Radiological Environmental Monitoring Program (REMP) for the period January 1, 2011 through December 31, 2011. This report fulfills the requirements of ANO Unit 1 Technical Specification (TS) 5.6.2 and Unit 2 TS 6.6.2.

During 2011, as in previous years, ANO detected radionuclides attributable to plant operations at the discharge location (Station 8) where previously monitored liquid radioactive effluent from the plant is periodically discharged in accordance with the regulatory criteria established in the Offsite Dose Calculation Manual (ODCM). ANO personnel routinely monitor results from this area in order to note any trends. The review of results from this area indicates the following:

  • Tritium levels in the surface water media continue to be below regulatory reporting limits and are consistent with concentrations that would typically be seen at this location as discussed in Section 2.3 of this AREOR.

Gross beta concentrations at the Station 14 (City of Russellville) indicator drinking water location continue to remain consistent with previous operational measurements and similar to the levels detected at the Station 57 (City of Danville) control drinking water location.

In 2011, ANO detected radioactivity attributed to the Fukushima Daiichi Nuclear Power Plant accident (Mach 11, 2011). CR-ANO-C-2011-00916 Radiological Environmental Monitoring Program ANO established the REMP prior to the station becoming operational (1974) to provide data on background radiation and radioactivity normally present in the area. ANO has continued to monitor the environment by sampling air, water, sediment, fish and food products, as well as measuring radiation directly. ANO also samples milk if milk-producing animals are present commercially within five miles of the plant.

The REMP includes sampling indicator and control locations within an approximate 20-mile radius of the plant. The REMP utilizes indicator locations near the site to show any increases or buildup of radioactivity that might occur due to station operation, and control locations farther away from the site to indicate the presence of only naturally occurring radioactivity. ANO personnel compare indicator results with control and preoperational results to assess any impact ANO operation might have had on the surrounding environment.

In 2011, ANO personnel collected environmental samples for radiological analysis. They compared results of indicator locations with control locations and previous studies and concluded that overall no significant relationship exists between ANO operation and effect on the plant environs. The review of 2011 data, in many cases, showed undetectable radiation levels in the environment and in all instances, no definable trends related to significant pathways associated with ANO.

Enclosure to 0CAN051201 Page 3 of 42 Harmful Effects or Irreversible Damage The REMP monitoring did not detect any harmful effects or evidence of irreversible damage in 2011. Therefore, no analysis or planned course of action to alleviate problems was necessary.

Reporting Levels ANO's review indicates that no samples equaled or exceeded reporting levels for radioactivity concentration in environmental samples due to ANO effluents, as outlined in ODCM Table 2.6-3, when averaged over any calendar quarter. Therefore, 2011 results did not trigger any Radiological Monitoring Program special reports.

Radioactivity Not Attributable to ANO The ANO REMP has detected radioactivity attributable to other sources. These include the 25th Chinese nuclear test explosion in 1980 and the radioactivity plume release due to reactor core degradation at the Chernobyl Nuclear Power Plant in 1986. Prior to 1981, the ANO REMP detected radioactivity resulting from nuclear weapons testing, with Cesium-137 continuing to be periodically detected. In 2011, ANO detected I-131 radioactivity attributed to the Fukushima Daiichi Nuclear Power Plant accident (March 11, 2011).

Comparison to Federal and State Programs ANO personnel compared REMP data to state monitoring programs as results became available. Historically, the programs used for comparison have included the U.S. Nuclear Regulatory Commission (NRC) Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network and the Arkansas Department of Health (ADH).

The NRC TLD Network Program was discontinued in 1998. Historically these results have compared to those from the ANO REMP. ANO TLD results continue to remain similar to the historical average and continue to verify that plant operation is not affecting the ambient radiation levels in the environment.

The ADH and the ANO REMP entail similar radiological environmental monitoring program requirements. These programs include collecting air samples and splitting or sharing sample media such as water, sediment and fish. Both programs have obtained similar results over previous years.

Sample Deviations

  • Milk The REMP did not include milk sampling within five miles of ANO in 2011 due to unavailability. The ODCM requires collection of milk samples, if available commercially within 5 miles of the plant. ANO personnel collected vegetation samples to monitor the ingestion pathway, as specified in the ODCM, because of milk unavailability.

Enclosure to 0CAN051201 Page 4 of 42

  • Required Lower Limit of Detection (LLD) Values; the following REMP LLDs were not met on short lived isotopes; o REMP Station # 8 (discharge canal surface water), 5/31/11, (I-131) o REMP Station # 58, Ground Water Monitoring Well 4/19/11 (I-131, Ba-140, La-140, Nb-95) o REMP Station # 59, Ground Water Monitoring Well 4/19/11 (I-131, Ba-140, La-140, Nb-95) o REMP Station # 61, Ground Water Monitoring Well 4/19/11, 7/26/11 (I-131, Ba-140, La-140, Nb-95)

These missed LLDs are the result of the conditions identified in CR-HQN-2011-0545 and CR-RBS-2011-5352. The failure to meet the required LLD's on short lived isotopes was due to equipment availability and laboratory capacity. Actions were taken to prevent reoccurrence of this situation.

This condition carried over into the analysis of second quarter 2011 Non-REMP ground water samples as part of the site Ground Water Protection Initiative (GPI) program. All of the remaining LLD analyses taken in support of the GPI were less than the LLD as required by the ODCM and EN-CY-111,"Radiological Ground Water Monitoring Program."

o Except as identified above, LLDs during this reporting period were within the acceptable limits required by Table 2.6-2 of the ODCM.

  • Air Samples Listed below are air sampler deviations that occurred during 2011 due to electrical power outages and equipment failure. These deviations did not result in the exceedance of the LLD values specified in the ODCM. As described in footnote (a) to ODCM Table 2.6-1, deviations are permitted from the required sampling schedule due to malfunction of sampling equipment and other legitimate reasons.

Station Sampling Period Comment On 1/18/11, the run time meter had failed. Run 06 01/04/2011 - 01/18/2011 time meter replaced. (CR-ANO-C-2011-00164)

On 4-12-11, air sample pump discovered not 07 03/29/2011 - 04/12/2011 operating. Replaced sample pump.

(CR-ANO-C-2011-00954)

On 12-6-11, pump running with fewer than expected run time hours recorded. Indicates a 56 11/22/2011 - 12/06/2011 power outage during sampling period.

(CR-ANO-C-2011-03218)

  • Missed Samples No samples were missed during 2011.
  • Unavailable Results ANO received analytical results in adequate time for inclusion in this report.

Enclosure to 0CAN051201 Page 5 of 42 Program Modifications ANO added an additional Storm Water Runoff collection station (STR-6) to the REMP per CR-ANO-C-2011-00424. Storm water sampling is designated as "Not required for ODCM compliance". No other modifications to the REMP were made during 2011.

Attachments contains results of air, TLD, water, sediment, fish, and food product samples collected in 2011. TLDs were analyzed by a vendor (AREVA). All remaining samples were analyzed by River Bend Stations (RBS) Environmental Laboratory. also contains RBS participation in the interlaboratory comparison program during 2011. contains dose calculations performed for sediment using a generalized equation from 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.

1.0 Introduction 1.1 Radiological Environmental Monitoring Program ANO established the REMP to ensure that plant operating controls properly function to minimize any associated radiation endangerment to human health or the environment. The REMP is designed for:

  • Analyzing applicable pathways for anticipated types and quantities of radionuclides released into the environment.
  • Considering the possibility of a buildup of long-lived radionuclides in the environment and identifying physical and biological accumulations that may contribute to human exposures.
  • Considering the potential radiation exposure to plant and animal life in the environment surrounding ANO.
  • Correlating levels of radiation and radioactivity in the environment with radioactive releases from station operation.

1.2 Pathways Monitored The airborne, direct radiation, waterborne and ingestion pathways are monitored as required by the ODCM. A description of the ANO REMP utilized to monitor the exposure pathways is described in Table 1.1 and shown in Figures 1-1, 1-2 and 1-3.

Section 2.0 of this report provides a discussion of 2011 sampling results and Section 3.0 provides a summary of results for the monitored exposure pathways.

Enclosure to 0CAN051201 Page 6 of 42 1.3 Land Use Census ANO personnel conducts land use census biannually (once every two years) as required by ODCM Section 2.6.2. The latest land use census was conducted in 2011. The purpose of this census is to identify changes in uses of land within five miles of ANO that would require modifications to the REMP or ODCM. The most important criteria during this census are to determine location in each sector of the nearest:

1) Residence
2) Animal milked for human consumption
3) Garden of greater than 500 square feet producing fresh leafy (broadleaf) vegetables*
  • ANO personnel did not perform a garden census since ODCM Section 2.6.2 allows the routine sampling of broadleaf vegetation in the highest D/Q sector near the site boundary in lieu of the garden census.

The method used by ANO personnel for conducting the land use census is as follows:

  • ANO personnel conducted door-to-door (drive by) field surveys in order to locate the nearest resident in each meteorological sector.
  • Consultation with local agricultural authorities is used for the identification of commercial milk providers within five-miles of the Unit-1 reactor building.
  • As a result of these surveys, the following information is obtained in each meteorological sector:
1) Nearest permanent residence
2) Nearest milking animal
  • ANO personnel identify locations on the map, measure distances to ANO (or use a GPS system) and record results.
  • Locations, if any, are identified which yield a calculated dose or dose commitments greater than those currently calculated in the ODCM.
  • ANO personnel compare results to previous census.

Enclosure to 0CAN051201 Page 7 of 42 TABLE 1.1 RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency Radioiodine and Particulates Station 2 (243° - 0.5 miles) - South 2 samples close to the Site Boundary, in of the sewage treatment plant.

(or near) different sectors with the highest calculated annual average Station 56 (264° - 0.4 miles) - West ground level D/Q. end of the sewage treatment plant.

Radioiodine and Particulates Radioiodine Canister - Analyze at 1 sample from the vicinity of a Station 1 (88° - 0.5 miles) - Near Continuous operation of least once per 14 days for I-131.

community having the highest calculated the meteorology tower. sampler with sample collection Airborne annual average groundlevel D/Q. as required by dust loading but Particulate Sampler - Analyze for at least once per 14 days. gross beta radioactivity following Radioiodine and Particulates filter change.

Station 7 (210° - 19.0 miles) -

1 sample from a control location Entergy Supply Yard on Highway 10 15 - 30 km (10 - 20 miles) distance. in Danville.

Radioiodine and Particulates Station 6 (111° - 6.8 miles) -

Entergy local office in Russellville One location sampled voluntarily by ANO.

(305 South Knoxville Avenue).

Thermoluminescent dosimetry (TLDs) Station 1 (88° - 0.5 miles) - On a pole near the meteorology tower.

16 inner ring stations with two or more dosimeters in each meteorological sector Station 2 (243° - 0.5 miles) - South in the general area of the Site Boundary. of the sewage treatment plant.

Direct Station 3 (5° - 0.7 miles) - West of Once per 92 days. Gamma Dose - Once per 92 days.

Radiation ANO Gate #2 on Highway 333 (approximately 0.35 miles)

Station 4 (181° - 0.5 miles) - West of May Cemetery entrance on south side of the road.

Enclosure to 0CAN051201 Page 8 of 42 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency TLDs Station 56 (264° - 0.4 miles) - West end of the sewage treatment plant.

16 inner ring stations with two or more dosimeters in each meteorological sector Station 108 (306° - 0.9 miles) -

in the general area of the Site Boundary South on Flatwood Road on a utility pole.

Station 109 (291° - 0.6 miles) -

Utility pole across from the junction of Flatwood Road and Round Mountain Road.

Station 110 (138° - 0.8 miles) -

Bunker Hill Lane on the first utility pole on the left.

Direct Radiation Station 145 (28° - 0.6 miles) - Near Once per 92 days. Gamma Dose - Once per 92 days.

west entrance to the RERTC on a utility pole.

Station 146 (45° - 0.6 miles) -

South end of east parking lot at RERTC on a utility pole.

Station 147 (61° - 0.6 miles) - West side of Bunker Hill Road, approximately 100 yards from intersection with State Highway 333.

Station 148 (122° - 0.6 miles) -

Intersection of Bunker Hill Road with Scott Lane on county road sign post.

Enclosure to 0CAN051201 Page 9 of 42 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency TLDs Station 149 (156° - 0.5 miles) - On a utility pole on the south side of 16 inner ring stations with two or more May Road.

dosimeters in each meteorological sector in the general area of the Site Boundary Station 150 (205° - 0.6 miles) -

North side of May Road on a utility pole past the McCurley Place turn.

Station 151 (225° - 0.4 miles) -

West side of sewage treatment plant near the lake on a metal post.

Station 152 (338° - 0.8 miles) -

South side of State Highway 333 on a road sign post.

Direct Radiation TLDs Station 6 (111° - 6.8 miles) - Once per 92 days. Gamma Dose - Once per 92 days.

Entergy local office in Russellville 8 stations with two or more dosimeters in (305 South Knoxville Avenue).

special interest areas such as population centers, nearby residences, schools, and Station 7 (210° - 19.0 miles) -

in 1 - 2 areas to serve as control Entergy Supply Yard on Highway 10 locations. in Danville.

Station 111 (120° - 2.0 miles) -

Marina Road on a utility pole on the left just prior to curve.

Station 116 (318° - 1.8 miles) -

Highway 333 and Highway 64 in London on a utility pole north of the railroad tracks.

Enclosure to 0CAN051201 Page 10 of 42 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency TLDs Station 125 (46° - 8.7 miles) -

College Street on a utility pole at the 8 stations with two or more dosimeters in southeast corner of the red brick special interest areas such as population school building.

centers, nearby residences, schools, and in 1 - 2 areas to serve as control Station 127 (100° - 5.2 miles) -

locations. Arkansas Tech Campus on a utility pole across from Paine Hall.

Direct Radiation Station 137 (151° - 8.2 miles) - On Once per 92 days. Gamma Dose - Once per 92 days.

a speed limit sign on the right in front of the Morris R. Moore Arkansas National Guard Armory.

Station 153 (304° - 9.2 miles) -

Knoxville Elementary School near the school entrance gate on a utility pole.

Surface Water Station 8 (166° - 0.2 miles) - Plant 1 indicator location (influenced by plant discharge canal.

discharge) Gamma isotopic and tritium Once per 92 days.

analyses once per 92 days.

Station 10 (95° - 0.5 miles) - Plant 1 control location (uninfluenced by plant intake canal.

discharge)

Waterborne Drinking Water Station 14 (70° - 5.1 miles) -

Russellville city water system from 1 indicator location (influenced by plant the Illinois Bayou. I-131, gross beta, gamma isotopic discharge) Once per 92 days. and tritium analyses once per 92 Station 57 (208° - 19.5 miles) - days.

1 control location (uninfluenced by plant Danville public water supply discharge) treatment on Fifth Street.

Enclosure to 0CAN051201 Page 11 of 42 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency Sediment Station 8 (243° - 0.9 miles) - Plant discharge canal.

1 indicator location (influenced by plant Waterborne discharge) Gamma isotopic analysis once per Station 16 (287° - 5.5 miles) - Once per 365 days.

365 days.

Panther Bay on south side of 1 control location (uninfluenced by plant Arkansas River across from mouth discharge) of Piney Creek.

Milk 1 indicator sample location within five-mile distance if commercially available. Currently, no available milking Gamma isotopic and I-131 Once per 92 days.

animals within 8 km of ANO. analyses once per 92 days.

1 control sample location at a distance of

>five-miles when an indicator exists.

Fish Station 8 (212° - 0.5 miles) - Plant 1 sample of commercially and/or discharge canal.

recreationally important species in Gamma isotopic on edible portions vicinity of plant discharge. Station 16 (287° - 5.5 miles) - Once per 365 days.

once per 365 days.

Panther Bay on south side of Ingestion 1 sample of same species in area not Arkansas River across from mouth influenced by plant discharge. of Piney Creek.

Food Products 1 sample of broadleaf (edible or non-edible) near the Site Boundary from one Station 13 (273° - 0.5 miles) - West of the highest anticipated annual average from ANO toward Gate 4 onto groundlevel D/Q sectors, if milk sampling Flatwood Road. Gamma. isotopic and I-131 is not performed. Three per 365 days.

analyses three times per 365 days Station 55 (208° - 16.5 miles) -

1 sample location of broadleaf vegetation Intersection of Highway 27 and 154.

(edible or non-edible) from a control location 15 - 30 km (10 - 20 miles) distant, if milk sampling is not performed.

Enclosure to 0CAN051201 Page 12 of 42 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Distance Sampling and Collection Type and Frequency Of Requirement Pathway and Direction Frequency Analyses 1 sample location of Groundwater from a Station 58 (GWM-1, 22° - 0.3 miles) - Once per 92 days Control, Tritium and Gamma control location up gradient from the North of Protected Area on Owner Control Isotopic, once per 92 days.

protected area Area (OCA). South of Outside Fab-Shop, west side of access road 3 sample locations of Groundwater from Station 59 (GWM-2, 185° - 0.1 miles) - Once per 92 days Indicator, Tritium and Gamma indicator locations down gradient from South of Protected Area on OCA. Near Isotopic, once per 92 days.

Ground the protected area. Security barriers and discharge canal.

water Station 60 (GWM-3, 206° - 0.1 miles) - Once per 92 days Indicator, Tritium and Gamma South of Protected area on OCA. West of Isotopic, once per 92 days.

Station number 59 near wood line.

Station 61 (GWM-4, 245° - 0.1 miles) - Once per 92 days Indicator, Tritium and Gamma West of Protected Area on OCA. Edge of Isotopic, once per 92 days.

parking lot, east of equipment laydown area

Enclosure to 0CAN051201 Page 13 of 42 FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD SR 333 152 108 Training 145 Center 146 147 109 13 1 West Access Rd. 10 56 2 8C 36 Scott Ln.

151 148 8S May Rd. Bunker Cemetery Bunker Hill Ln.

Hill Rd.

149 150 4 110 Arkansas Nuclear One REMP Sample Locations (Near Field)

Lake Dardanelle Revised 24May05

Enclosure to 0CAN051201 Page 14 of 42 FIGURE 1-2 SAMPLE COLLECTION SITES - FAR FIELD 1

2 0° 16 340° 20° US HWY 7 TO HARRISON 15 320° 40° INTERSTATE 40 3

TO FORT SMITH SR 5 PINEY BAY USE AREA Dover 125 SR 333 300° 60° 164 EAST TO 153 U.S.

MORELAND HWY 14 64 4

14 SR 24 TO MORELAND 280° ARKANSAS RIVER 116 INTERSTATE 40 80° 16 LONDON US 13 J I H G F E D C B HWY 64 5

DELAWARE STATE PARK 127 260° DARDANELLE STATE PARK 111 ARKANSAS TECH UNIVERSITY 100° U.S. HWY 22 HWY 524 LAKE DARDANELLE DARDANELLE STATE PARK RUSSELLVILLE 6

12 DARDANELLE LOCK AND DAM HWY 22 DAM SITE EAST PARK HWY 7T 6 240° 120° HWY 155 HWY 7 SR 247 TO POTTSVILLE MT. NEBO HWY 27 137 STATE PARK DARDANELLE 11 220° HWY 28 140° 7

HWY 7 200° 160° 10 180° 8

HWY 7 TO HOT SPRINGS HWY 27 TO DANVILLE INSET DANVILLE (SEE INSET) 9 N W E HWY 154 S

HWY 27 55 HWY 10 Entergy Substation 7

Petit Jean River 57 HWY 10 Cowger Lake City of Danville Arkansas Nuclear One HWY 80 HWY 27 REMP Sample Locations (Far Field)

Enclosure to 0CAN051201 Page 15 of 42 FIGURE 1-3 SAMPLE COLLECTION SITES - SITE MAP 58 STR-3 Switch STR-2 Yard STR-4 STR-6 West Access Road 61 STR-5 60 59 STR-1 N

Lake Dardanelle W E S

Arkansas Nuclear One REMP Sample Locations Site Map

Enclosure to 0CAN051201 Page 16 of 42 2.0 Interpretation and Trends of Results 2.1 Air Particulate and Radioiodine Sample Results The REMP has detected radioactivity in the airborne pathway attributable to other sources.

These include the 25th Chinese nuclear test explosion in 1980, the radioactive plume release due to reactor core degradation at Chernobyl Nuclear Power Plant in 1986 and the Fukushima Daiichi Nuclear Power Plant accident (Mach 11, 2011).

During 2011, Iodine-131 was detected in the radioiodine cartridges, as a result of the Fukushima Daiichi Nuclear Power Plant accident. As in past years, there were no other detections of I-131. Indicator gross beta air particulate results for 2011 were within the range of levels obtained in previous years of the operational REMP and well below preoperational levels as seen below. Results are reported as annual average picocuries per cubic meter (pCi/m3).

Monitoring Period Result 2000 - 2010 (Minimum Value) 0.020 2011 Value 0.030 2000 - 2010 (Maximum Value) 0.032 Preoperational 0.050 In the absence of plant-related gamma radionuclides, gross beta activity is attributed to naturally occurring radionuclides. Table 3.1, which includes gross beta concentrations and provides a comparison of the indicator and control means and ranges, emphasizes the consistent trends seen in this pathway to support the presence of naturally occurring activity. Therefore, it can be concluded that the airborne pathway continues to be unaffected by ANO operations.

2.2 Thermoluminescent Dosimetry (TLD) Sample Results ANO reports measured dose as net exposure (field reading less transit reading) normalized to 92 days and relies on comparison of the indicator locations to the control as a measure of plant impact. ANOs comparison of the inner ring and special interest area TLD results to the control, as seen in Table 3.1, identified no noticeable trend that would indicate that the ambient radiation levels are being affected by plant operations. In addition, the inner ring value of 8.5 millirem (mrem) shown in Table 3.1 is within the historical bounds of 2000 - 2010 annual average results, which have ranged from 6.7 to 8.8 mrem. Overall, ANO concluded that the ambient radiation levels are not being affected by plant operations.

2.3 Water Sample Results Analytical results for 2011 surface water and drinking water samples were similar to those reported in previous years.

Surface water samples were collected and analyzed for gamma radionuclides and tritium.

Gamma radionuclides were below detectable limits which is consistent with results seen in previous operational years. Tritium continues to be detected at the indicator location (Station 8) where previously monitored liquid radioactive effluent from the plant is periodically discharged in

Enclosure to 0CAN051201 Page 17 of 42 accordance with the regulatory criteria established in the ODCM. However, the levels detected are consistent with concentrations that would typically be seen at this location as shown below.

Results are reported as annual average picocurie per liter (pCi/l).

Monitoring Period Result 2000 - 2010 (Minimum Value) 272.0 2011 Value 915.5 2000 - 2010 (Maximum Value) 1023.4 Preoperational 200.0 ANO personnel have noted no definable increasing trends associated with the tritium levels at the discharge location. Levels detected during 2011 and previous operational years have been well below regulatory reporting limits. Therefore, the operation of ANO had no definable impact on this waterborne pathway during 2011 and levels of radionuclides remain similar to those obtained in previous operational years.

Drinking water samples were collected from two locations (indicator and control). Although ANO personnel utilize Station 14 (City of Russellville) as an indicator location due to the potential for the drinking water pathway to exist, the City of Russellville has not withdrawn water from Lake Dardanelle in the past several years.

Drinking water samples were analyzed for gross beta radionuclides, Iodine-131, gamma radionuclides and tritium. Gamma radionuclides, Iodine-131 and tritium concentrations were below the LLD limits at the indicator and control locations, which is consistent with preoperational and operational years. Gross beta concentrations at the indicator and control locations are similar as shown in Table 3.1. Listed below is a comparison of 2011 indicator results to preoperational and operational years. Results are reported as annual average pCi/l.

Radionuclide 2011 2000 - 2010 Preoperational Gross Beta 1.84 2.84 2.0 Iodine-131 < LLD < LLD < LLD Gamma < LLD < LLD < LLD Tritium < LLD < LLD 200.0 ANO personnel have noted no definable trends associated with drinking water results at the indicator location. Therefore, the operation of ANO had no definable impact on this waterborne pathway during 2011 and levels of radionuclides remain similar to those obtained in previous operational years.

Groundwater samples were collected from four REMP locations (1 control, and 3 indicator locations). During 2011, ANO incorporated sixteen additional groundwater monitoring wells into the sites Groundwater Protection Initiative (GPI) site program. Sample data was compiled, organized and is reviewed annually at a minimum to:

Enclosure to 0CAN051201 Page 18 of 42

  • Analyze for increasing or decreasing trends at individual sample points, wells or groups of wells.
  • Review the radionuclides detected to determine whether changes should be made to the analysis suites or sampling frequencies for each sampling location.
  • Evaluate the locations of radionuclides in ground water to determine if changes should be made to the sampling locations.
  • Review current investigation levels and determine if changes should be made.
  • Determine if any change to the ODCM is required.
  • Determine if a corrective actions/remediation is required.

Groundwater samples were analyzed for Tritium and Gamma radionuclides. Tritium and Gamma concentrations were below the LLD limits at the indicator and control locations. Listed below is a comparison of 2011 indicator results to past operational years. Results are reported as annual average pCi/l. REMP Groundwater data is captured in Tables 8.1 and 8.2.

Therefore, ANO operations had no significant impact on the environment or public by this waterborne pathway.

Radionuclide 2011 2006 - 2010 Iodine-131 < LLD < LLD Gamma < LLD < LLD Tritium < LLD < LLD 2.4 Sediment Sample Results Sediment samples were collected from two locations in 2011 and analyzed for gamma radionuclides. During 2011, CS-137 was detected at Station # 16 (control) at a level of 45.5 pCi/kg. As in past reports, this value is attributed to past weapons testing. (CR-ANO-C-2011-02976). Station # 16 was resampled which resulted in less than LLD values. Listed below is a comparison of 2011 indicator results to past operational years. Therefore, ANO operations had no significant impact on the environment or public by this waterborne pathway. Results are reported as pCi/kg.

Monitoring Period Result 2000 - 2010 (Minimum Value) 41.79 2011 Value 661.0 2000 - 2010 (Maximum Value) 1170.0 Since reporting levels for radionuclides in sediment have not been established, an evaluation of potential dose to the public from this media was performed as shown in Attachment 3.

2.5 Milk Sample Results Milk samples were not collected during 2011 due to the unavailability of indicator locations within five-miles of ANO.

Enclosure to 0CAN051201 Page 19 of 42 2.6 Fish Sample Results Fish samples were collected from two locations and analyzed for gamma radionuclides. In 2011, gamma radionuclides were below detectable limits which are consistent with the preoperational monitoring period and operational results since 1997. Therefore, based on these measurements, ANO operations had no significant radiological impact upon the environment or public by this ingestion pathway.

2.7 Food Product Sample Results The REMP has detected radionuclides prior to 1990 that are attributable to other sources.

These include the radioactive plume release due to reactor core degradation at Chernobyl Nuclear Power Plant in 1986 and atmospheric weapons testing.

In 2011, food product samples were collected when available from two locations and analyzed for Iodine-131 and gamma radionuclides. The 2011 levels remained undetectable, as has been the case in previous years. Therefore, based on these measurements, ANO operations had no significant radiological impact upon the environment or public by this ingestion pathway.

2.8 Interlaboratory Comparison Results RBS Environmental Laboratory analyzed interlaboratory comparison samples for ANO to fulfill the requirements of ODCM Section 2.6.3. Attachment 2 contains these results.

2.9 Land Use Census Results The latest land use census (performed in 2011) did not identify any new locations that yielded a calculated dose or dose commitment greater than those currently calculated (see Table 2.1).

Also, the land use census identified no milk-producing animals within a five-mile radius of the plant site. ANO personnel chose not to perform a garden census in 2009, which is allowed by ODCM Section 2.6.2, in lieu of broadleaf vegetation sampling in the meteorological sector (Sector 13) with the highest D/Q.

Enclosure to 0CAN051201 Page 20 of 42 TABLE 2.1 2011 LAND USE CENSUS Nearest Residence Within Five Miles Direction Sector Distance (miles)

N 1 0.9 NNE 2 1.3 NE 3 0.9 ENE 4 0.8 E 5 0.8 ESE 6 0.8 SE 7 0.8 SSE 8 0.8 S 9 0.8 SSW 10 0.7 SW 11 2.8 WSW 12 0.7 W 13 0.8 WNW 14 0.8 NW 15 1.0 NNW 16 0.9 3.0 Radiological Environmental Monitoring Program Summary 3.1 2011 Program Results Summary Table 3.1 summarizes the 2011 REMP results. ANO personnel did not use values reported as less than LLD or activity attributed to the Fukushima Daiichi Nuclear Power Plant accident when determining ranges and means for indicator and control locations.

Enclosure to 0CAN051201 Page 21 of 42 TABLE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: ANO - Units 1 and 2 Docket No: 50-313 and 50-368.

Location of Facility: Pope County, Arkansas Reporting Period: January - December 2011 Sample Type Type / Indicator Location with Highest Annual Mean Control Number of Number of LLDb Locations Mean Locations Mean Non-Routine (Units)

Analysesa (°F)c [Range] Locationd Mean (°F)c [Range] (°F)c [Range] Resultse Air Particulates 0.030 (78 / 78) Station 1 0.031 (26 / 26) 0.027 (52 / 52)

GB / 130 0.01 0 (pCi/m3) [0.016 - 0.050] (88°, 0.5 mi) [0.016 - 0.050] [0.017 - 0.047]

Airborne Iodine I-131 / 122* 0.07 < LLD N/A N/A < LLD 0 (pCi/ m3)

(f)

Inner Ring TLDs Gamma / 64 8.5 (64 / 64) Station 56 10.3 (4 / 4) N/A 0 (mR/Qtr) [6.1 - 10.3] (264°, 0.4 mi) [9.8 - 10.8]

Special Interest Gamma / 28 (f) 7.6 (28 / 28) Station 116 8.8 (4 / 4) N/A 0 TLDs (mR/Qtr) [5.3 - 8.8] (318°, 1.8 mi) [8.2 - 9.5]

(f) Station 127 8.8 (4 / 4) N/A 0 (100°, 5.2 mi) [8.3 - 9.7]

(f) Station 137 8.8 (4 / 4) N/A 0 (151°, 8.2 mi) [8.3 - 9.5]

Control TLD Gamma / 4 (f) N/A N/A N/A 6.9 (4 / 4) 0 (mR/Qtr) [5.9 - 8.2]

  • Fukushima Accident contributors removed from calculations.

Enclosure to 0CAN051201 Page 22 of 42 TABLE 3.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Sample Type Type / Indicator Location with Highest Annual Mean Control Number of Number of LLDb Locations Mean Locations Mean Non-Routine (Units)

Analysesa (°F)c [Range] Locationd Mean (°F)c [Range] (°F)c [Range] Resultse H-3 / 8 3000 1017.0 (3 / 4) Station 8 1017.0 (3 / 4) < LLD 0

[651.0 - 1718.0] (166°, 0.2 mi) [651.0 - 1718.0]

GS / 24 Mn-54 15 < LLD N/A N/A < LLD 0 Fe-59 30 < LLD N/A N/A < LLD 0 Co-58 15 < LLD N/A N/A < LLD 0 Co-60 15 < LLD N/A N/A < LLD 0 Surface Water Zn-65 30 < LLD N/A N/A < LLD 0 (pCi/l)

Zr-95 30 < LLD N/A N/A < LLD 0 Nb-95 15 < LLD N/A N/A < LLD 0 I-131 15 < LLD N/A N/A < LLD 0 Cs-134 15 < LLD N/A N/A < LLD 0 Cs-137 18 < LLD N/A N/A < LLD 0 Ba-140 60 < LLD N/A N/A < LLD 0 La-140 15 < LLD N/A N/A < LLD 0

Enclosure to 0CAN051201 Page 23 of 42 TABLE 3.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Sample Type Type / Indicator Location with Highest Annual Mean Control Number of Number of LLDb Locations Mean Locations Mean Non-Routine (Units)

Analysesa (°F)c [Range] Locationd Mean (°F)c [Range] (°F)c [Range] Resultse GB / 8 4 2.13 ( 2 / 4 ) Station 14 1.55 (4 / 4) 2.19 (3 / 4) 0

[ 1.92 - 2.34 ] (70°, 5.1 mi) [0.63 - 2.30] [0.98 - 3.62]

I-131 / 8 1.0 < LLD N/A N/A < LLD 0 H-3 / 8 2000 < LLD N/A N/A < LLD 0 GS / 8 Mn-54 15 < LLD N/A N/A < LLD 0 Drinking Water Fe-59 30 < LLD N/A N/A < LLD 0 (pCi/1) Co-58 15 < LLD N/A N/A < LLD 0 Co-60 15 < LLD N/A N/A < LLD 0 Zn-65 30 < LLD N/A N/A < LLD 0 Zr-95 30 < LLD N/A N/A < LLD 0 Nb-95 15 < LLD N/A N/A < LLD 0 Cs-134 15 < LLD N/A N/A < LLD 0 Cs-137 18 < LLD N/A N/A < LLD 0 Ba-140 60 < LLD N/A N/A < LLD 0 La-140 15 < LLD N/A N/A < LLD 0 GS / 3 Bottom Cs-134 150 < LLD N/A < LLD < LLD 0 Sediment Cs-137 180 661 (1/1) Station 8 661 (1/1) 45.5 (2/2) 0 (pCi/kg)

Mn-54 None 29.3 (1/1) (243°, 0.9 mi)

Enclosure to 0CAN051201 Page 24 of 42 TABLE 3.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Sample Type Type / Indicator Location with Highest Annual Mean Control Number of Number of LLDb Locations Mean Locations Mean Non-Routine (Units)

Analysesa (°F)c [Range] Locationd Mean (°F)c [Range] (°F)c [Range] Resultse GS / 2 Mn-54 130 < LLD N/A N/A < LLD 0 Fe-59 260 < LLD N/A N/A < LLD 0 Co-58 130 < LLD N/A N/A < LLD 0 Fish (pCi/kg)

Co-60 130 < LLD N/A N/A < LLD 0 Zn-65 260 < LLD N/A N/A < LLD 0 Cs-134 130 < LLD N/A N/A < LLD 0 Cs-137 150 < LLD N/A N/A < LLD 0 I-131 / 6 60 < LLD N/A N/A N/A 0 Food Products GS / 6 (pCi/kg)

Cs-134 60 < LLD N/A N/A N/A 0 Cs-137 80 < LLD N/A N/A N/A 0 a

GB = Gross beta; I-131 = Iodine-131; H-3 = Tritium; GS = Gamma scan.

b LLD = Required lower limit of detection based on ANO Units 1 and 2 ODCM Table 2.6-2.

c Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis (F).

d Locations are specified (1) by name and (2) degrees relative to reactor site.

e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.

f LLD is not defined in ANO Units 1 and 2 ODCM Table 2.6-2.

Enclosure to 0CAN051201 Page 25 of 42 Annual Radiological Environmental Operating Report for 2011 ATTACHMENT 1

SUMMARY

OF MONITORING RESULTS Table of Contents Table 1.1 Air Particulate ................................................................................................... 26 Table 1.2 Radioiodine Cartridge....................................................................................... 27 Table 2.1 Thermoluminescent Dosimeters (Inner Ring)................................................... 28 Table 2.2 Thermoluminescent Dosimeters (Special Interest Areas) ................................ 29 Table 3.1 Surface Water (Gamma Isotopic) ..................................................................... 30 Table 3.2 Surface Water (Tritium) .................................................................................... 31 Table 4.1 Drinking Water (Gross beta, I-131 and Gamma Isotopic) ................................ 32 Table 4.2 Drinking Water (Tritium) ................................................................................... 33 Table 5.1 Sediment .......................................................................................................... 33 Table 6.1 Fish................................................................................................................... 33 Table 7.1 Food Products .................................................................................................. 34 Table 8.1 Groundwater Data (Gamma Isotopic)............................................................... 35 Table 8.2 Groundwater Data (Tritium).............................................................................. 36

Enclosure to 0CAN051201 Page 26 of 42 Table 1.1 Sample Type: Air Particulate Analysis: Gross Beta Units: pCi/m3 Station 1* Station 2 Station 56 Station 6 Station 7 Start Date End Date (Indicator) (Indicator) (Indicator) (Control) (Control)

Required LLD 0.01 0.01 0.01 0.01 0.01 12/21/2010 01/04/2011 0.033 0.040 0.037 0.029 0.035 01/04/2011 01/18/2011 0.047 0.044 0.046 0.033 0.047 01/18/2011 02/01/2011 0.044 0.043 0.041 0.034 0.042 02/01/2011 02/15/2011 0.028 0.026 0.028 0.021 0.026 02/15/2011 03/01/2011 0.025 0.023 0.022 0.017 0.022 03/01/2011 03/15/2011 0.024 0.025 0.025 0.022 0.025 03/15/2010 03/29/2011 0.031 0.027 0.030 0.024 0.028 03/29/2010 04/12/2011 0.027 0.025 0.023 0.024 0.017 04/12/2011 04/26/2011 0.020 0.018 0.019 0.017 0.021 04/26/2011 05/10/2011 0.024 0.021 0.021 0.018 0.019 05/10/2011 05/24/2011 0.016 0.017 0.016 0.018 0.019 05/24/2011 06/07/2011 0.026 0.026 0.026 0.022 0.025 06/07/2011 06/21/2011 0.026 0.026 0.027 0.023 0.026 06/21/2011 07/05/2011 0.027 0.024 0.028 0.021 0.026 07/05/2011 07/19/2011 0.026 0.024 0.025 0.022 0.026 07/19/2011 08/02/2011 0.026 0.024 0.026 0.021 0.025 08/02/2011 08/16/2011 0.026 0.026 0.025 0.020 0.025 08/16/2011 08/30/2011 0.037 0.038 0.038 0.032 0.036 08/30/2011 09/13/2011 0.042 0.040 0.038 0.037 0.033 09/13/2011 09/27/2011 0.034 0.039 0.033 0.027 0.031 09/27/2011 10/11/2011 0.037 0.035 0.033 0.030 0.036 10/11/2011 10/25/2011 0.035 0.033 0.033 0.029 0.032 10/25/2011 11/08/2011 0.037 0.036 0.035 0.031 0.035 11/08/2011 11/22/2011 0.028 0.026 0.027 0.024 0.026 11/22/2011 12/06/2011 0.034 0.032 0.033 0.026 0.035 12/06/2011 12/20/2011 0.050 0.047 0.045 0.036 0.044

  • Station with highest annual mean.

Enclosure to 0CAN051201 Page 27 of 42 Table 1.2 Sample Type: Radioiodine Cartridge Analysis: Iodine-131 Units: pCi/m3 Station 1* Station 2 Station 56 Station 6 Station 7 Start Date End Date (Indicator) (Indicator) (Indicator) (Control) (Control)

Required LLD 0.07 0.07 0.07 0.07 0.07 12/21/2010 01/04/2011 < 0.019 < 0.024 < 0.016 < 0.020 < 0.020 01/04/2011 01/18/2011 < 0.025 < 0.020 < 0.020 < 0.022 < 0.023 01/18/2011 02/01/2011 < 0.022 < 0.020 < 0.016 < 0.021 < 0.018 02/01/2011 02/15/2011 < 0.015 < 0.020 < 0.017 < 0.016 < 0.013 02/15/2011 03/01/2011 < 0.041 < 0.035 < 0.022 < 0.035 < 0.015 03/01/2011 03/15/2011 < 0.027 < 0.027 < 0.028 < 0.018 < 0.021 03/15/2010 03/29/2011 0.068** 0.071** 0.076** 0.062** 0.090**

03/29/2010 04/12/2011 0.035** < 0.034 0.037** 0.040** < 0.032 04/12/2011 04/26/2011 < 0.025 < 0.020 < 0.023 < 0.015 < 0.024 04/26/2011 05/10/2011 < 0.019 < 0.018 < 0.023 < 0.021 < 0.026 05/10/2011 05/24/2011 < 0.020 < 0.025 < 0.020 < 0.021 < 0.026 05/24/2011 06/07/2011 < 0.021 < 0.019 < 0.046 < 0.022 < 0.021 06/07/2011 06/21/2011 < 0.016 < 0.013 < 0.017 < 0.019 < 0.018 06/21/2011 07/05/2011 < 0.021 < 0.017 < 0.021 < 0.016 < 0.018 07/05/2011 07/19/2011 < 0.015 < 0.021 < 0.018 < 0.016 < 0.017 07/19/2011 08/02/2011 < 0.021 < 0.024 < 0.026 < 0.024 < 0.022 08/02/2011 08/16/2011 < 0.017 < 0.020 < 0.017 < 0.016 < 0.020 08/16/2011 08/30/2011 < 0.012 < 0.011 < 0.012 < 0.012 < 0.011 08/30/2011 09/13/2011 < 0.018 < 0.017 < 0.018 < 0.013 < 0.016 09/13/2011 09/27/2011 < 0.013 < 0.022 < 0.013 < 0.013 < 0.011 09/27/2011 10/11/2011 < 0.010 < 0.014 < 0.013 < 0.010 < 0.015 10/11/2011 10/25/2011 < 0.018 < 0.021 < 0.016 < 0.014 < 0.020 10/25/2011 11/08/2011 < 0.010 < 0.011 < 0.015 < 0.015 < 0.018 11/08/2011 11/22/2011 < 0.019 < 0.017 < 0.014 < 0.016 < 0.012 11/22/2011 12/06/2011 < 0.016 < 0.017 < 0.015 < 0.018 < 0.020 12/06/2011 12/20/2011 < 0.016 < 0.026 < 0.026 < 0.022 < 0.021

  • Station with highest annual mean.
    • identifies Fukushima Nuclear Power Plant influence.

Enclosure to 0CAN051201 Page 28 of 42 Table 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring (Indicators) 1st Qtr 11 2nd Qtr 11 3rd Qtr 11 4th Qtr 11 Annual Mean 11 Station (mrem) (mrem) (mrem) (mrem) (mrem) 1 9.0 8.4 9.7 9.0 9.0 2 8.8 8.3 9.2 9.0 8.8 3 5.6 5.7 7.1 6.0 6.1 4 8.3 8.4 8.9 8.4 8.5

  • 56 10.8 9.8 10.6 10.0 10.3 108 8.8 9.2 9.9 9.4 9.3 109 8.9 8.3 10.4 9.9 9.4 110 8.6 7.7 9.3 8.8 8.6 145 8.5 7.3 8.9 8.7 8.4 146 8.9 8.2 8.7 8.8 8.7 147 7.1 6.7 7.9 7.4 7.3 148 8.9 7.7 9.4 8.7 8.7 149 7.8 7.6 8.7 8.0 8.0 150 9.2 7.3 8.9 8.8 8.6 151 8.1 8.4 9.3 9.5 8.8 152 6.9 6.8 7.6 7.7 7.3
  • Station with highest annual mean.

Enclosure to 0CAN051201 Page 29 of 42 Table 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - (Population Centers & Schools)

Station 1st Qtr 11 2nd Qtr 11 3rd Qtr 11 4th Qtr 11 Annual Mean 11 (mrem) (mrem) (mrem) (mrem) (mrem) 6 7.6 7.0 7.7 7.2 7.4 111 5.7 6.0 6.0 6.0 5.9

  • 116 8.3 8.2 9.5 9.0 8.8 125 5.2 5.2 5.7 5.0 5.3
  • 127 8.4 8.8 9.7 8.3 8.8
  • 137 8.8 8.3 9.5 8.6 8.8 153 7.6 7.8 9.9 8.7 8.5
  • Stations with highest annual mean.

Special Interest Areas - (Control)

Station 1st Qtr 11 2nd Qtr 11 3rd Qtr 11 4th Qtr 11 Annual Mean 11 (mrem) (mrem) (mrem) (mrem) (mrem) 7 6.9 5.9 8.2 6.7 6.9

Enclosure to 0CAN051201 Page 30 of 42 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Date Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Required LLD 15 15 30 15 30 15 30 15 15 18 60 15 Station 8 (Indicator) 12/31/2010 01/31/2011 < 5.29 < 4.45 < 4.62 < 4.22 < 9.49 < 6.50 < 7.12 < 8.12 < 4.82 < 4.03 < 22.12 < 8.67 Station 10 (Control) 12/31/2010 01/31/2011 < 4.90 < 5.15 < 12.63 < 4.53 < 11.16 < 8.53 < 12.16 < 10.90 < 6.13 < 5.30 < 25.14 < 10.57 Station 8 (Indicator) 01/31/2011 02/28/2011 < 5.04 < 5.66 < 11.11 < 4.28 < 9.62 < 7.24 < 9.32 < 5.81 < 4.65 < 6.44 < 17.40 < 3.51 Station 10 (Control) 01/31/2011 02/28/2011 < 3.49 < 4.75 < 6.37 < 3.84 < 9.76 < 5.21 < 7.89 < 6.31 < 4.75 < 3.81 < 17.57 < 6.94 Station 8 (Indicator) 02/28/2011 03/31/2011 < 3.94 < 3.08 < 6.51 < 3.24 < 9.22 < 4.07 < 5.72 < 6.43 < 3.42 < 3.98 < 17.99 < 7.46 Station 10 (Control) 02/28/2011 03/31/2011 < 5.83 < 4.37 < 4.79 < 3.07 < 9.66 < 4.17 < 8.17 < 6.10 < 4.68 < 5.65 < 15.35 < 6.33 Station 8 (Indicator) 03/31/2011 04/30/2011 < 2.98 < 3.51 < 7.37 < 3.33 < 8.43 < 4.78 < 6.94 < 14.92 < 3.48 < 3.72 < 26.47 < 8.94 Station 10 (Control) 03/31/2011 04/30/2011 < 4.82 < 4.76 < 9.23 < 3.49 < 8.59 < 5.43 < 8.65 < 14.58 < 4.09 < 4.35 < 38.05 < 11.86 Station 8 (Indicator) 04/30/2011 05/31/2011 < 2.02 < 2.56 < 5.94 < 2.05 < 3.57 < 3.46 < 3.98 <15.22* < 2.47 < 1.82 < 23.27 < 9.14 Station 10 (Control) 04/30/2011 05/31/2011 < 1.99 < 2.09 < 6.09 < 2.13 < 4.29 < 2.84 < 4.33 < 14.21 < 2.45 < 2.24 < 22.53 < 8.68 Station 8 (Indicator) 05/31/2011 06/30/2011 < 4.74 < 4.26 < 9.14 < 4.37 < 8.47 < 4.23 < 7.98 <13.06 < 4.08 < 3.72 < 25.90 < 11.03 Station 10 (Control) 05/31/2011 06/30/2011 < 3.04 < 3.04 < 7.97 < 2.74 < 7.36 < 5.03 < 5.50 < 9.66 < 3.95 < 3.60 < 26.43 < 5.53 Station 8 (Indicator) 06/30/2011 07/31/2011 < 2.94 < 3.46 < 7.48 < 3.31 < 7.68 < 4.37 < 6.45 < 9.25 < 4.26 < 3.86 < 20.04 < 7.55 Station 10 (Control) 06/30/2011 07/31/2011 < 4.04 < 3.67 < 9.94 < 3.56 < 8.57 < 5.88 < 6.44 < 8.96 < 4.02 < 4.17 < 23.03 < 8.62 Station 8 (Indicator) 07/31/2011 08/31/2011 < 5.74 < 4.88 < 11.90 < 4.94 < 6.52 < 6.00 < 9.20 < 6.37 < 4.61 < 5.62 < 25.60 < 7.78 Station 10 (Control) 07/31/2011 08/31/2011 < 4.91 < 5.51 < 7.16 < 5.69 < 12.20 < 8.29 < 12.20 < 6.66 < 4.56 < 4.26 < 31.80 < 10.40 Station 8 (Indicator) 08/31/2011 09/30/2011 < 7.07 < 7.15 < 15.20 < 7.27 < 12.50 < 7.71 < 12.50 < 12.80 < 5.69 < 6.78 < 33.80 < 13.80 Station 10 (Control) 08/31/2011 09/30/2011 < 5.21 < 4.58 < 10.60 < 4.90 < 9.89 < 6.46 < 9.40 < 8.60 < 6.16 < 7.04 < 23.00 < 8.31 Station 8 (Indicator) 09/30/2011 10/31/2011 < 3.87 < 3.37 < 10.50 < 3.91 < 6.99 < 4.52 < 7.66 < 14.50 < 3.79 < 4.34 < 36.60 < 14.40 Station 10 (Control) 09/30/2011 10/31/2011 < 3.60 < 3.41 < 6.36 < 4.03 < 7.51 < 5.85 < 8.49 < 13.70 < 3.54 < 3.44 < 26.20 < 8.28 Station 8 (Indicator) 10/31/2011 11/30/2011 < 4.76 < 5.42 < 13.60 < 13.80 < 10.60 < 6.01 < 9.46 < 9.75 < 4.70 < 4.59 < 30.30 < 9.54 Station 10 (Control) 10/31/2011 11/30/2011 < 4.84 < 5.43 < 11.80 < 5.66 < 12.00 < 6.32 < 10.70 < 7.33 < 4.96 < 6.27 < 23.40 < 12.70 Station 8 (Indicator) 11/30/2011 12/31/2011 < 6.47 < 5.41 < 11.20 < 5.31 < 10.40 < 7.47 < 11.30 < 11.10 < 4.67 < 5.88 < 31.20 < 14.50 Station 10 (Control) 11/30/2011 12/31/2011 < 5.78 < 4.10 < 8.43 < 4.96 < 10.20 < 5.60 < 9.02 < 9.65 < 4.27 < 5.88 < 34.40 < 13.10

  • identifies a missed LLD value.

Enclosure to 0CAN051201 Page 31 of 42 Table 3.2 Sample Type: Surface Water Analysis: Tritium Units: pCi/l Location Begin Date End Date H-3 Required LLD 3000 Station 8 (Indicator) 12/31/2010 03/31/2011 651 Station 10 (Control) 12/31/2010 03/31/2011 < 432 Station 8 (Indicator) 03/31/2011 06/30/2011 1718 Station 10 (Control) 03/31/2011 06/30/2011 < 405 Station 8 (Indicator) 06/30/2011 09/30/2011 < 653 Station 10 (Control) 06/30/2011 09/30/2011 < 654 Station 8 (Indicator) 09/30/2011 12/31/2011 682 Station 10 (Control) 09/30/2011 12/31/2011 < 639

Enclosure to 0CAN051201 Page 32 of 42 Table 4.1 Sample Type: Drinking Water Analysis: Gross Beta, Iodine-131, Gamma Isotopic Units: pCi/l Collection Gross Location I-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Date Beta Required LLD 4.0 1.0 15 15 30 15 30 15 30 15 18 60 15 Station 14 (Indicator) 03/15/2011 < 1.25 < 0.82 < 5.16 < 3.93 < 8.27 < 2.85 < 9.53 < 4.73 < 5.25 < 4.59 < 4.26 < 19.09 < 6.55 Station 57 (Control) 03/15/2011 1.93 < 0.83 < 2.68 < 4.09 < 6.83 < 2.65 < 5.16 < 4.31 < 6.78 < 4.14 < 4.00 < 20.95 < 5.55 Station 14 (Indicator) 06/07/2011 2.34 < 0.89 < 3.38 < 2.82 < 7.19 < 3.07 < 7.50 < 3.70 < 6.79 < 3.47 < 3.14 < 21.11 < 7.79 Station 57 (Control) 06/07/2011 0.98 < 0.87 < 3.90 < 3.65 < 8.70 < 2.40 < 8.33 < 8.31 < 4.11 < 3.84 < 4.11 < 20.08 < 9.71 Station 14 (Indicator) 09/13/2011 < 1.86 < 0.89 < 4.91 < 4.74 < 3.30 < 5.21 < 6.28 < 4.86 < 7.61 < 4.21 < 5.40 < 24.80 < 10.20 Station 57 (Control) 09/13/2011 < 1.87 < 0.94 < 6052 < 5.72 < 13.00 < 3.72 < 12.80 < 4.98 < 11.80 < 6.41 < 4.96 < 23.10 < 7.13 Station 14 (Indicator) 12/20/2011 1.92 < 0.95 < 4.57 < 5.64 < 13.30 < 6.90 < 11.40 < 5.87 < 11.10 < 5.64 < 5.16 < 24.90 < 7.67 Station 57 (Control) 12/20/2011 3.62 < 0.87 < 5.61 < 5.90 < 8.82 < 3.95 < 9.92 < 5.87 < 6.70 < 4.28 < 4.62 < 31.00 < 11.90

Enclosure to 0CAN051201 Page 33 of 42 Table 4.2 Sample Type: Drinking Water Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 2000 Station 14 (Indicator) 03/15/2011 < 511 Station 57 (Control) 03/15/2011 < 517 Station 14 (Indicator) 06/07/2011 < 403 Station 57 (Control) 06/07/2011 < 412 Station 14 (Indicator) 09/13/2011 < 605 Station 57 (Control) 09/13/2011 < 604 Station 14 (Indicator) 12/20/2011 < 642 Station 57 (Control) 12/20/2011 < 640 Table 5.1 Sample Type: Sediment Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Cs-134 Cs-137 Mn-54 Required LLD 150 180 N/A Station 8 (Indicator) 10/13/2011 < 24.10 661 29.30 Station 16 (Control)* 10/25/2011 < 14.60 45.5 N/A Station 16 (Control)** 11/23/2011 < 18.30 < 20.60 N/A

  • Positive Cs-137 detection. Back ground detection from past weapons testing.

CR-ANO-C-2011 02976.

    • Station # 16 resample after positive Cs-137 detection.

Table 6.1 Sample Type: Fish Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Required LLD 130 130 260 130 260 130 150 Station 8 (Indicator) 9/29/2011 < 14.20 < 15.00 < 45.20 < 15.80 < 23.90 < 11.10 < 11.50 Station 16 (Control) 9/27/2011 < 11.70 < 12.10 < 39.30 < 7.99 < 26.00 < 6.98 < 7.48

Enclosure to 0CAN051201 Page 34 of 42 Table 7.1 Sample Type: Food Products Analysis: Iodine-131, Gamma Isotopic Units: pCi/kg Location Collection Date I-131 Cs-134 Cs-137 Required LLD 60 60 80 Station 13 (Indicator) 06/16/2011 < 57.91 < 25.78 < 35.86 Station 55 (Control) 06/16/2011 < 59.89 < 40.59 < 46.61 Station 13 (Indicator) 07/18/2011 < 44.42 < 31.73 < 35.47 Station 55 (Control) 07/18/2011 < 40.05 < 38.88 < 36.13 Station 13 (Indicator) 08/29/2011 < 40.40 < 43.80 < 36.50 Station 55 (Control) 08/29/2011 < 29.90 < 22.90 < 26.10

Enclosure to 0CAN051201 Page 35 of 42 Table 8.1 Sample Type: Groundwater Analysis: Iodine-131, Gamma Isotopic Units: pCi/l Collection Cs-Sample # I-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Ba-140 La-140 Date 137 Required LLD 15 15 15 30 15 30 15 30 15 18 60 15 58* 02/08/2011 < 14.97 < 4.99 < 5.37 < 9.48 <4.98 < 10.22 < 7.29 < 9.22 < 4.71 < 4.52 < 32.78 < 10.89 59 02/08/2011 < 11.50 < 4.22 < 4.66 < 10.08 < 4.43 < 8.16 < 5.46 < 7.57 < 4.33 < 4.10 < 26.06 < 7.83 60 03/07/2011 < 12.15 < 8.49 < 6.91 < 12.77 < 8.81 < 12.33 <8.72 < 11.94 < 8.24 < 9.25 < 42.16 < 14.47 61 02/08/2011 < 14.91 < 5.38 < 4.53 < 9.69 < 4.45 < 9.29 < 5.60 < 8.84 < 5.76 < 4.78 < 29.98 < 11.31 58* 04/19/2011 Missed < 6.74 < 10.03 < 29.66 < 5.62 < 12.27 Missed < 18.12 < 4.70 < 4.83 Missed Missed 59 04/19/2011 Missed < 4.66 < 6.91 < 24.96 < 3.70 < 11.22 Missed < 13.33 < 4.68 < 4.43 Missed Missed 60 04/19/2011 < 14.87 < 1.06 < 1.23 < 3.17 < 1.05 < 2.26 < 1.98 < 2.44 < 1.07 < 1.09 < 21.05 < 8.16 61 04/19/2011 Missed < 3.89 < 6.95 < 26.84 < 3.07 < 9.18 Missed < 14.16 < 3.80 < 3.09 Missed Missed 58* 08/11/2011 < 12.60 < 2.16 < 1.99 < 4.98 < 1.94 < 4.50 < 3.14 < 5.21 < 1.53 < 1.99 < 20.80 < 6.36 59 07/26/2011 < 11.26 < 4.01 < 4.71 < 8.06 < 3.42 < 8.92 < 5.68 < 7.04 < 4.68 < 4.30 < 21.28 < 8.00 60 07/26/2011 < 12.28 < 3.31 < 3.20 < 6.23 < 3.06 < 5.55 < 4.07 < 5.34 < 3.20 < 2.66 < 25.28 < 7.82 61 07/26/2011 < 8.53 < 2.68 < 3.95 < 7.38 < 3.55 < 8.13 < 5.20 < 5.13 < 3.74 < 3.65 < 18.92 < 7.07 58* 11/30/2011 < 11.00 < 3.63 < 4.98 < 11.30 < 4.22 < 8.30 < 5.12 < 7.42 < 4.62 < 4.85 < 36.00 < 14.50 59 11/29/2011 < 14.60 < 4.00 < 4.58 < 8.21 < 5.01 < 9.23 < 5.70 < 8.08 < 3.99 < 5.47 < 24.60 < 13.20 60 11/29/2011 < 13.30 < 4.16 < 4.51 < 11.60 < 3.81 < 9.09 < 5.92 < 9.58 < 4.09 < 4.79 < 26.60 < 13.30 61 11/29/2011 < 13.10 < 4.50 < 5.32 < 10.50 < 4.43 < 10.10 < 6.99 < 8.58 < 4.97 < 6.28 < 32.70 < 11.80

Enclosure to 0CAN051201 Page 36 of 42 Table 8.2 Sample Type: Groundwater Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 3000 Station 58 (Control) 03/07/2011 < 396 Station 59 (Indicator 03/08/2011 < 391 Station 60 (Indicator) 03/07/2011 < 390 Station 61 (Indicator) 03/08/2011 < 420 Station 58 (Control) 04/19/2011 < 403 Station 59 (Indicator) 04/19/2011 < 403 Station 60 (Indicator) 04/19/2011 < 403 Station 61 (Indicator) 04/19/2011 < 404 Station 58 (Control) 07/27/2011 < 717 Station 59 (Indicator) 07/26/2011 < 645 Station 60 (Indicator) 07/26/2011 < 651 Station 61 (Indicator) 07/26/2011 < 700 Station 58 (Control) 11/30/2011 < 655 Station 59 (Indicator) 11/29/2011 < 656 Station 60 (Indicator) 11/29/2011 < 658 Station 61 (Indicator) 11/29/2011 < 660

Enclosure to 0CAN051201 Page 37 of 42 Annual Radiological Environmental Operating Report for 2011 ATTACHMENT 2 INTERLABORATORY COMPARISON PROGRAM Table 9.1 Sample Type: Interlaboratory Comparison Analysis: Iodine-131, Gamma Isotopic Calendar Year: 2011 1st Quarter dated March 17, 2011 Analytics E7481-125 Gross Beta in Water Range of 0.80 to 1.25 RBS Ref Lab Ref Lab RBS 1-s RBS/Ref Pass/

Nuclide Mean Value uncertainty Resolution pCi/L Lab Ratio Fail pCi/L pCi/L pCi/L Cs-137 199 19 247 4.13 59.8 0.80 Pass (1) 3rd Quarter dated Sept. 15, 2011 Analytics E8137-125 Gross Beta filter Range of 0.80 to 1.25 RBS Ref Lab Ref Lab RBS 1-s RBS/Ref Pass/

Nuclide Mean Value uncertainty Resolution pCi/filter Lab Ratio Fail pCi/filter pCi/filter pCi/filter Cs-137 84.2 1.41 82.1 1.37 59.9 1.03 Pass Analytics E8136-125 H-3 in water Range of 0.80 to 1.25 RBS Ref Lab Ref Lab RBS 1-s RBS/Ref Pass/

Nuclide Mean Value uncertainty Resolution pCi/L Lab Ratio Fail pCi/L pCi/L pCi/L H-3 9060 419 9010 151 59.7 1.01 Pass

Enclosure to 0CAN051201 Page 38 of 42 Table 9.1 (continued)

Sample Type: Interlaboratory Comparison Analysis: Tritium, Gamma Isotopic Analytics E8138-125 Gamma Filter Range of 0.80 to 1.25 RBS Ref Lab Ref Lab RBS 1-s RBS/Ref Pass/

Nuclide Mean Value uncertainty Resolution pCi/filter Lab Ratio Fail pCi/filter pCi/filter pCi/filter Ce-141 58.2 2.80 59.6 0.995 59.7 0.98 Pass Cr-51 188 11.9 202 3.38 59.8 0.93 Pass Cs-134 94.3 4.20 115 1.91 60.2 0.82 Pass Cs-137 101 4.20 102 1.70 60.0 0.99 Pass Co-58 83.9 3.90 87.1 1.45 60.1 0.96 Pass Mn-54 134 4.00 135 2.25 60.0 0.99 Pass Fe-59 52.1 2.60 49.0 0.818 59.9 1.06 Pass Zn-65 157 6.40 161 2.69 59.9 0.97 Pass Co-60 134 4.50 140 2.34 59.8 0.95 Pass Analytics E8139-125 Gamma Soil Range of 0.80 to 1.25 RBS Ref Lab Ref Lab RBS 1-s RBS/Ref Pass/

Nuclide Mean Value uncertainty Resolution pCi/g Lab Ratio Fail pCi/g pCi/g pCi/g Ce-141 0.174 .0110 0.168 .00280 60 1.04 Pass Cr-51 0.556 .0450 0.569 .00950 59.9 0.98 Pass Cs-134 0.271 .0110 0.322 .00580 55.5 0.84 Pass Cs-137 0.347 .0170 0.375 .00625 60 0.93 Pass Co-58 0.221 .0110 0.245 .00409 59.9 0.90 Pass Mn-54 0.357 .0100 0.379 .00633 59.9 0.94 Pass Fe-59 0.142 .00100 0.138 .00230 60 1.03 Pass Zn-65 0.423 .0350 0.454 .00758 59.9 0.93 Pass Co-60 0.361 .0180 0.395 .00659 59.9 0.91 Pass

Enclosure to 0CAN051201 Page 39 of 42 Table 9.1 (continued)

Sample Type: Interlaboratory Comparison Analysis: Tritium, Gamma Isotopic 4th Quarter dated Dec. 8, 2011 Analytics E7480-125 Gamma in Water Range of 0.80 to 1.25 RBS Ref Lab Ref Lab RBS 1-s RBS/Ref Pass/

Nuclide Mean Value uncertainty Resolution pCi/L Lab Ratio Fail pCi/L pCi/L pCi/L I-131 94.0 17.0 88.7 1.48 59.9 1.06 Pass Ce-141 n/a n/a n/a n/a n/a n/a n/a (2)

Cr-51 599 91.0 566 9.45 59.9 1.06 Pass Cs-134 164 11.0 171 2.86 59.8 0.96 Pass Cs-137 223 17.0 210 3.50 60 1.06 Pass Co-58 216 15.0 221 3.69 59.9 0.98 Pass Mn-54 255 13.0 241 4.02 60.0 1.06 Pass Fe-59 188 20.0 183 3.06 59.8 1.03 Pass Zn-65 309 29.0 291 4.87 59.8 1.06 Pass Co-60 284 16.0 270 4.51 59.9 1.05 Pass Analytics E7483-125 Gamma in Milk Range of 0.80 to 1.25 RBS Ref Lab Ref Lab RBS 1-s RBS/Ref Pass/

Nuclide Mean Value uncertainty Resolution pCi/L Lab Ratio Fail pCi/L pCi/L pCi/L I-131 91.0 16.0 90.2 1.51 59.7 1.01 Pass Ce-141 n/a n/a n/a n/a n/a n/a n/a (2)

Cr-51 532 76.0 566 9.45 59.9 0.94 Pass Cs-134 160 11.0 171 2.86 59.8 0.93 Pass Cs-137 216 10.0 210 3.50 60 1.03 Pass Co-58 206 13.0 221 3.69 59.9 0.93 Pass Mn-54 237 12.0 241 4.02 60.0 0.98 Pass Fe-59 192 18.0 183 3.06 59.8 1.05 Pass Zn-65 304 22.0 291 4.87 59.8 1.04 Pass Co-60 265 16.0 270 4.51 59.9 0.98 Pass

Enclosure to 0CAN051201 Page 40 of 42 Table 9.1 (continued)

Analytics E7482-125 I-131 cartridge Range of 0.80 to 1.25 RBS Ref Lab Ref Lab RBS 1-s RBS/Ref Pass/

Nuclide Mean Value uncertainty Resolution pCi/each Lab Ratio Fail pCi/each pCi/each pCi/each I-131 90.0 8.00 89.7 1.50 59.8 1.00 Pass (1) Analysis result for Gross Beta in Water, Environmental cross check E-7481-125, was outside the passing ratio of agreement in the performance of the 2011 Interlaboratory Comparison Program as determined on 2/29/12. The reference labs known value was 247 pCi/L with a passing ratio for agreement of 0.80 to 1.25 thus producing control limits of 197.6 to 308.8 pCi/L. The RBS average value was 156 pCi/L making the ratio of agreement 0.63. CR-RBS-2012-01845 was generated.

Preparation for reanalysis of the same source material was begun on 3/1/12. RBS results obtained on 3/12/12 indicate an average of 199 pCi/L, decay corrected to an assay date of 3/17/11. The same ratio of agreement applies (passing 0.80 - 1.25) therefore indicating a passing result for the reanalysis with a 0.80 ratio of agreement.

Although the reanalysis passed, the reference lab, Eckert & Ziegler/Analytics (EZA), was contacted to verify that other participants did not have similar issues indicating a low bias and/or possible source problems. EZA reported that none of the other participants experienced any problems.

The most probable cause of the low sample result was sample preparation error during mixing, transfer, or evaporation of the sample. Analytics was contacted to obtain a quote for a standard of known value (Gross Beta in Water) which the RBS lab will prepare and analyze along with future samples for the analyses of Gross Beta in Water. ESP-8-068 will be revised to reflect this change.

(2) Ce-141 was unavailable at the reference lab for the mixed gamma matrix for the 4th quarter milk and water.

Enclosure to 0CAN051201 Page 41 of 42 Table 9.1 (continued)

CHEMISTRY SURVEILLANCE PROGRAM RADIOCHEMISTRY QUALITY CONTROL ACCEPTANCE CRITERIA This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.

In these criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratorys value to its associated uncertainty. As that ratio, referred to in this program as Resolution, increases the acceptability of a licensees measurement should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decreases.

RESOLUTION(1) RATIO FOR AGREEMENT(2)

<4 No Comparison 4 to 7 0.5 to 2.0 8 to 15 0.6 to 1.66 16 to 50 0.75 to 1.33 51 to 200 0.80 to 1.25

> 200 0.85 to 1.18 (1)

Resolution = (NRC Reference Value/Reference Uncertainty)

(2)

Ratio = (Licensee Value/NRC Reference Value)

Enclosure to 0CAN051201 Page 42 of 42 Annual Radiological Environmental Operating Report for 2011 ATTACHMENT 3 SEDIMENT DOSE CALCULATIONS Sediment Sample Results Dose calculation for the discharge sediment was performed using generalized equation found in Regulatory Guide 1.109, Revision 1, Appendix A as follows:

R = (40) x (C) x (U) x (D) x (W)

R = Annual dose to skin or total body in mrem/year; 40 = Area-mass conversion factor given in Appendix A of Rg 1.109 in kg/m2; C = 2011 maximum radionuclide concentration in pCi/kg; U = Maximum exposure time given in Table E-5 of RG 1.109 (67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> for teenager);

D = External dose conversion factor for standing on contaminated ground given in Table E-6 of RG 1.109 in mrem/hr per pCi/m2, and W = Shore-width factor (0.1) given in Table A-2 of RG 1.109.

Conversion Conversion Total 2011 Maximum Total Skin Radionuclide Factor For Factor For Body Concentration Dose Skin Total Body Dose Cs-137* 661 4.90 E-09 8.68 E-04 4.20 E-09 7.44 E-04 TOTAL 8.68 E-04 7.44 E-04

  • Dose from Sediment in mrem/year
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