Text

Radiological Environmental Monitoring Program, 2011 Annual Radiological Environmental Operating Report, January 1 to December 31, 2011
	ML12122A921
Person / Time
Site:	Salem, Hope Creek
Issue date:	05/31/2012
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	LR-N12-0121
	Download: ML12122A921 (139)
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM & HOPE CREEK GENERATING STATIONS 2011 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 TO DECEMBER 31,2011

n TABLE OF CONTENTS H

. Summary...........................................................................................................................

4 II. The Radiological Environmental Monitoring Program................................................

8 1

A. Objectives of the Operational REMP.............................................................

9 B. Implementation of the Objectives...............................

9 i1l. Program Description....................................................................................................

10 A. Data Interpretation.......................................................................................

10 B. Program Deviations.....................................................................................

11 C. Program Changes 11 D. Quality Assurance Program."......................................................................

12 E. Summary of Results - Inter-Laboratory Comparison Program.................... 12 lI IV. Results and Discussion.........................................................................................

15 A. Atmospheric..................................................................................................

15

1. Air Particulates...................................................................................

16 I

2. Air Iodine............................................................................................

17 B. Direct Radiation............................................................................................

17 C. Terrestrial......................................................................................................

18 I

1. Milk....................................................................................................

19

2. Well Water (Ground Water) 20

3. Potable W ater (Drinking W ater).........................................................

21

4. Vegetables...............................................................................................

23

5. Fodder Crops.....................................................................................

24

6. Soil....................................................................................................

25 D. Aquatic...............................................................................................................

25

1. Surface W ater."..............................

26

2. Fish....................................................................................................

28

3. Blue Crab...........................................................................................

29

4. Sediment.............................................................................................

30 E. Land Use Survey.........................................................................................

. 31 V. Annotations to Previous AREOR..............................................................................

32 VI. Hope Creek Technical Specification Limit for Primary Water Iodine Concentrations.. 33 VII. Conclusions...........................................................................................................

33 VIII. References.......................................

34 TABLE OF CONTENTS (cont'd)

Appendix A - Program Summary................................................................................

A-1 Appendix B - Sample Designation and Locations......................................................

B-1 Appendix C - Data Tables...........................................................................................

C-1 Appendix D - Summary of Results from Analytics, Environmental Resource Associates and DOE MAPEP Interlaboratory Comparison Programs....... D-1 Appendix E - Radiological Groundwater Protection Program.......................................... E-1 LIST OF TABLES Table B-1 Sampling Locations.....................................................................................

B-3 Table B-2 Salem and Hope Creek Generating Stations' Radiological Environmental Monitoring Program............................................................

B-5 LIST OF MAPS Map B-1 Salem and Hope Creek Generating Stations' Radiological Environmental Monitoring Program On-Site Sampling Locations........ B-10 Map B-2 Salem and Hope Creek Generating Stations' Radiological Environmental Monitoring Program Off-Site Sampling Locations........ B-i 1 LIST OF FIGURES Figure 1 Gross Beta Activity in Air Particulates 1990 through 2011 (Quarterly).................................................................

C-24 Figure 2 Ambient Radiation - Off-site vs Control Station 1990 through 2011 (Quarterly)................................................................

C-25 Figure 3 Iodine-1 31 Activity in Milk 1990 through 2011 (Quarterly).................................................................

C-26 Figure 4 Gross Beta Activity in Surface Water 1990 through 2011 (Quarterly).................................................................

C-27 Figure 5 Tritium Activity in Surface Water 1990 through 2011 (Quarterly).................................................................

C-28 Figure 6 Cesium-137 and Co-60 Activity in Aquatic Sediment 1990 through 2011 (Quarterly).................................................................

C-29 Figure 7 Cesium-137 Activity in Soil 1974 through 2011 (Triennial)......................

C-30

1. -Summary During normal operations of a nuclear power generating station there are releases of small amounts of radioactive material to the environment. To monitor and determine the effects of these releases a Radiological Environmental Monitoring Program (REMP) has been established for the environment around Artificial Island where the Salem Generating Station (SGS) and Hope Creek Generating Station (HCGS) are located. The results of the REMP are published annually, providing a summary and interpretation of the data collected [10].

Public Service Enterprise Group's (PSEG) Maplewood Testing Services (MTS) was responsible for the collection of environmental samples during 2011. Maplewood Testing Services was responsible for the analysis of environmental samples during the period of January 1, 2011, through March 7, 2011. Teledyne Brown Engineering (TBE) was responsible for the testing of environmental samples from March 8, 2011 through December 31, 2011. The results are discussed in this report. Landauer provided the dosimetry services for PSEG throughout the reporting year 2011.

The REMP was conducted in accordance with the SGS and HCGS Technical Specifications (TS) and Offsite Dose Calculation Manual (ODCM) [14, 15,17, 21].

The Lower Limit of Detection (LLD) values required by the Technical Specifications and ODCM were achieved for the 2011 reporting period. The REMP objectives were also met during this period. The data that was collected in 2011 assists in demonstrating that SGS and HCGS were operated in compliance with Technical Specifications and the ODCM.

Most of the radioactive materials noted in this report are normally present in the environment either naturally such as K-40, or as a result of non-nuclear generating station activity, such as nuclear weapons testing. Measurements made in the vicinity of SGS/HCGS were compared to background or control measurements and I

the preoperational REMP study performed before Salem Unit 1 became operational.

I On March 11,2011 an earthquake off the Japanese islands produced a massive I

tsunami that caused a nuclear accident at four of the six Fukushima Daiichi reactors. The resulting radioactive plume was first detected in the environs of Hope Creek and Salem Generating Stations on March 21, 2011. The final date of positive detection was April 11, 2011. The radionuclide identified was Iodine-131.

Maximum activity levels found by media were 82 E-3 pCi/m 3 for air iodine. Samples collected were compared to offsite control locations to verify that these positive detections were not attributable to licensed activities. All other radionuclides analyzed for were below MDC.

lI The radioactive half-life of 1-131 is about 8 days. This short half-life allowed the affects of this radioactive plume to subside over about 3 weeks. As of April 12, 2011 no further impacts from the Fukushima Daiichi accident was evident.

I On April 7, 2011, 1 pCi/L 1-131 was identified in the surface water control location.

The most likely cause of the 1-131 is effluent from a medical facility.

Samples of air particulates, air iodine, milk, surface, ground and potable (drinking) water, vegetables, fodder crops, fish, crabs and sediment were collected and analyzed. External radiation dose measurements were also made in the vicinity of SGS/HCGS using OSL dosimeters.

To demonstrate compliance with Technical Specifications and ODCM (Sections 3/4.12.1 & 6.8.4.h -1,2,3) [14,15], samples were analyzed for one or more of the following: gamma emitting isotopes, tritium (H-3), iodine-131 (1-131), gross alpha and gross beta. The results of these analyses were used to assess the environmental impact of SGS and HCGS operations, thereby demonstrating compliance with Technical Specifications and ODCM (Section 3/4.11) and applicable Federal and State regulations [19,20,21], and to verify the adequacy of radioactive effluent control systems.

The concentration of radioactive material in the environment that could be attributable to Salem and Hope Creek stations operations was only a small fraction of the concentration of naturally occurring and man-made radioactivity. Since these results were comparable to the results obtained during the preoperational phase of the program [7,8,9], and with historical results collected since commercial operation

[10], it can be concluded that the levels and fluctuations were as expected for an estuarine environment and the operation of SGS and HCGS had no significant radiological impact on the environment.

The results provided in this report for the REMP are summarized below:

There were a total of 1465 analyses on 1157 environmental samples during 2011.

Of the total number of analyses and environmental samples, direct radiation dose measurements were made using 204 sets of direct reading dosimeters In addition to the naturally - occurring isotopes (i.e. Be-7, K-40, Ra-Nat and Th-232),

Cs-1 37 was detected in one sediment sample at a concentration below the ODCM LLD value of 180 pCi/kg dry.

Dose measurements made with quarterly OSLs at offsite locations around the SGS/HCGS site averaged 59 milliroentgen for the year 2011. The average of the dose measurements at the control locations (background) was also 59 milliroentgen for the year. This was comparable to the levels prior to station operation which had an average of 55 milliroentgen per year for 1973 to 1976.

Appendix E contains the annual report on the status of the Radiological Groundwater Protection Program (RGPP) conducted at Salem and Hope Creek Stations. The RGPP was initiated by PSEG to determine whether groundwater at and in the vicinity of Salem and Hope Creek Stations had been adversely impacted by any release of radionuclides that was not previously identified. The RGPP is being implemented by PSEG in conjunction with a nuclear industry initiative and associated guidance. The I

results provided in Appendix E for the RGPP are summarized below:

Salem The 2011 results of the laboratory analysis indicated that H-3 was detected in 10 of the 13 RGPP monitoring wells at levels ranging from 260 to 4,090 pCi/L. The wells with H-3 results above the LLD (200 pCi/L) included AL, BA, BB, BC, BD, BE, BG, U, Y and Z.

I Hope Creek The 2011 results of the laboratory analysis indicated that H-3 was detected in seven of the 13 RGPP monitoring wells at levels ranging from 205 to 3,690 pCi/L. The wells with H-3 results above the LLD (200 pCi/L) included BH, BI, BJ, BK, BM, BN and BO.

I The results are shown in Appendix E, in Table 4. The H-3 concentrations measured in the onsite monitoring wells were below the U.S. Nuclear Regulatory Commission Reporting Level of 20,000 pCi/L.

I PSEG Nuclear is continuing remedial actions for H-3 identified in shallow groundwater at Salem Station, conducted in accordance with a Remedial Action Work Plan that was approved by the New Jersey Department of Environmental Protection - Bureau of Nuclear Engineering (NJDEP-BNE) in November 2004. The Groundwater Recovery System (GRS) is in operation, providing hydraulic control of the plume and effectively removing H-3 contaminated groundwater. The H-3 contaminated groundwater is disposed in accordance with Salem Station's liquid radioactive waste disposal program. There is no evidence or indication that H-3 contaminated water above Ground Water Quality Criteria (GWQC) levels [GWQC is <20,000 pCi/L] has migrated to the station boundary or the Delaware River.

II.

The Radiological Environmental Monitoring Program Lower Alloways Creek Township, Salem County, New Jersey is the site of Salem Generating Station (SGS) and Hope Creek Generating Station (HCGS). Salem Generating Station consists of two operating pressurized water nuclear power reactors. Salem Unit One has a net rating of 1180 megawatt electric (MWe) and Salem Unit Two has a net rating of 1178 MWe. The licensed core power for both units is 3460 megawatt thermal (MWt). Hope Creek Generating Station is a boiling water nuclear power reactor, which has a net rating of 1216 MWe (3840 MWt).

Salem Generating Station (SGS) and Hope Creek Generating Station (HCGS) are located on a man-made peninsula on the east bank of the Delaware River. It was created by the deposition of hydraulic fill from dredging operations. The environment surrounding SGS/HCGS is characterized mainly by the Delaware River Estuary and Bay, extensive tidal marshlands, and low-lying meadowlands. These land types make up approximately 85% of the land area within five miles of the site.

Most of the remaining land is used for agriculture [1,2]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Reports [1,2], Environmental Statements [3,4], and the Updated Final Safety Analysis Reports for SGS and HCGS [5,6].

Since 1968, a radiological environmental monitoring program (REMP) has been conducted at the SGS/HCGS Site [22]. Starting in December 1972, more extensive radiological monitoring programs were initiated [7,8,9]. The operational REMP was initiated in December 1976, when Salem Unit 1 achieved criticality.

An overview of the 2011 REMP is provided in Table 1, Salem and Hope Creek Generating Stations Radiological Environmental Monitoring Program.

Radioanalytical data from samples collected under this program were compared with results from the preoperational phase and historical results during operations.

Differences between these periods were examined statistically to determine the effects of station operations. This report presents the results from January 1 i

through December 31, 2011, for the SGS/HCGS REMP.

i A.

Objectives of the Operational REMP i

The objectives of the Operational REMP are to:

1.

To fulfill the requirements of the Radiological Surveillance sections of the Technical Specifications and ODCM for SGS/HCGS.

2.

To determine whether any significant increase occurred in the I

concentration of radionuclides in critical pathways.

3.

To determine if SGS or HCGS has caused an increase in the I

radioactive inventory of long-lived radionuclides.

4.

To detect any change in ambient gamma radiation levels.

I

5.

To verify that SGS and HCGS operations have no detrimental effects on the health and safety of the public or on the environment.

B.

Implementation of the Objectives

1.

In order to meet the objectives, an operational REMP was developed.

Samples of various media were selected for monitoring due to the radiological dose impact to human and other organisms. The selection of samples was based on:

i (a),

established critical pathways for the transfer of radionuclides through the environment to man, and i

(b) experience gained during the preoperational phase. Sampling locations were determined based on site meteorology, i

Delaware estuarine hydrology, local demography, and land uses.

2.

Sampling locations were divided into two classes, indicator and i

control. Indicator stations are those which are expected to manifest I

station effects. Control samples are collected at locations which are believed to be unaffected by station operations, usually at 15 to 30 kilometers (9.3 to 18.6 miles) distance. Fluctuations in the levels of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control stations. Indicator and control station data are also evaluated relative to preoperational data.

3.

Appendix A, Program Summary, describes and summarizes the analytical results in accordance with Section 6.9.1.7 of the Salem Technical Specifications and Section 6.9.1.6 of the Hope Creek Technical Specifications [25,26,27].

4.

Appendix B, Sample Designation, describes the coding system which identifies sample type and location. Table B-1 On-site Sampling Locations lists the station codes, locations, latitude, longitude, and the types of samples collected at each station.

5.

The sampling locations are indicated on Maps B-1, Onsite Sampling Locations and B-2, Offsite Sampling Locations.

II1.

Program Description A.

Data Interpretation Results of analyses are grouped according to sample type and presented in Appendix C, Data Tables. All results above the Lower Limit of Detection (LLD) are at a confidence level of +/- 2 sigma. This represents the range of values into which 95% of repeated analyses of the same sample should fall.

As defined in U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95%

probability, with only 5% probability of falsely concluding that a blank I

observation represents a "real signal". LLD is normally calculated as 4.66 I

times the standard deviation of the background counting rate, or of the blank sample count, as appropriate, divided by counting efficiency, sample size, 2.22 (dpm per picocurie), the radiochemical yield when applicable, the radioactive decay constant and the elapsed time between sample collection and time of counting.

The Minimum Detectable Concentration (MDC) is defined as the smallest concentration of radioactive material that can be detected at a given confidence level. The MDC differs from the LLD in that the MDC takes into consideration the interference caused by the presence of other nuclides while the LLD does not.

The grouped data were averaged and standard deviations calculated in accordance with Appendix B of Reference 16. Thus, the +/- 2 sigma deviations, of the averaged data represent sample and not analytical variability. For reporting and calculation of averages, any result occurring at or below the LLD is considered to be at that level.

3 B.

Program Exceptions

1. Week ending July 25, 2011, air particulate/air iodine station 5D1 was not collected.

2. Surface water station 1 F2 was collected August 22, 2011 rather than on August 1,2011.

3 C.

Program Changes

1. On March 8, 2011, Teledyne Brown Engineering (TBE) took over responsibility for the testing of environmental samples from Maplewood Testing Services.

2. Station 5S2 was added to the REMP program starting at week ending 05/25/11.

D.

Quality Assurance Program Maplewood Testind Services The quality of the results obtained by MTS is ensured by the implementation of the Quality Assurance Program as described in the Maplewood Testing Services Quality Assurance Manual [11 a], the Maplewood Testing Services Electrical Division Quality Assurance/Control Plan [11 b], and the Maplewood Testing Services Mechanical Division environmental/Radiological Group Procedure Manual [11 c].

Teledyne Brown Engineering The quality of the results obtained by TBE is ensured by the implementation of the Quality Assurance Program as described in the Teledyne Brown Engineering Quality Assurance Manual [1 ld] and the Teledyne Brown Engineering Procedure Manual [l1 e].

E.

Summary of Results - Inter-laboratory Comparison Program The testing laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices, as appropriate, for 18 analytes. (Appendix D, Tables D-1 through D-4)

The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following acceptance criteria:

1.

Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of reported result and Analytics' known value. Since flag values are not assigned by Analytics, TBE 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 =

3 "A"), Acceptable with Warning (flag = 'W"), and Not Acceptable (flag =

"N"). Performance is considered acceptable when a mean result for i

the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/-

1 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.

3 Maplewood Testing Services For the first quarter 2011, Maplewood Testing Services participated in the I

Environmental Resource Associate's (ERA) program. Seven out of eight analytes met the specified acceptance criteria. One analyte did not meet the I

specified acceptance criteria for the following reason:

1.

Maplewood Testing Services' ERA February 2011 Gross Alpha in water result of 78.0 pCi/L exceeded the upper control limit of 77.5 pCi/L. The alpha detector was found to be out of calibration and was taken out of service. Data that could have been affected by the failure were checked. It was determined that no data was affected by the failure.

Teledyne Brown Engineering For the TBE laboratory, 14 out of 18 analytes met the specified acceptance criteria. Four analytes (one sample each of Cr-51, Sr-89 and Sr-90 and two Gross Alpha samples) did not meet the specified acceptance criteria for the following reason:

1.

Teledyne Brown Engineering's Analytics March 2011 Cr-51 in milk result of 398 pCi/L was higher than the known value of 298 pCi/L, resulting in a found to known ratio of 1.34. NCR 11-13 was initiated to investigate this failure. There was a slightly high bias in all the gamma activities. The June gamma results in milk did not show a high bias.

No further action was required.

2.

Teledyne Brown Engineering's ERA May 2011 Gross Alpha in water result of 64.1 pCi/L was higher than the known value of 50.1 pCi/L, which exceeded the upper control limit of 62.9 pCi/L. NCR 11-08 was initiated to investigate this failure. The solids on the planchet exceeded 100 rmg, which was beyond the range of the efficiency curve.

3.

Teledyne Brown Engineering's MAPEP March 2011 Gross Alpha in air particulate result of 0.101 Bq/sample was lower than the known value of 0.659 Bq/sample, which exceeded the lower control limit of 0.198 Bq/sample. NCR 11-11 was initiated to investigate this failure. The i

air particulate filter was counted on the wrong side.

I

4.

Teledyne Brown Engineering's ERA November 2011 Sr-89 in water result of 81.0 pCi/L was higher than the known value of 69.7 pCi/L, which exceeded the upper control limit of 77.9 pCi/L.

Nonconformance report 11-16 was initiated to investigate this failure.

The TBE reported value to known ratio of 1.16 fell within the acceptable range of +/- 20%, which TBE considers acceptable.

5.

Teledyne Brown Engineering's MAPEP March 2011 Sr-90 in soil, air i

particulate and vegetation were non-reports that were evaluated as failed. NCR 11-11 was initiated to investigate these failures. MAPEP i

evaiuated the non-reports as failed due to not reporting a previously reported analyte.

I IV.

Results and Discussion The analytical results of the 2011 REMP samples are divided into categories based on exposure pathways: atmospheric, direct radiation, terrestrial, and aquatic. The analytical results for the 2011 REMP are summarized in Appendix A, Program Summary. The data for individual samples are presented in Appendix C, Data Tables. The data are compared to the formal pre-operational environmental monitoring program data (1973-1976) and to historical data during operations. The data collected demonstrates that the SGS and HCGS REMP was conducted in I

compliance with the Technical Specifications and ODCM.

The REMP for the SGS/HCGS Site has historically included samples and analyses I

not specifically required by the Stations' Technical Specifications and ODCM.

These analyses are referenced throughout the report as Management Audit samples. Maplewood Testing Services continues to collect these samples. The summary tables in this report include these additional samples and analyses.

A.

Atmospheric i

Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters 3

with low-volume air samplers.

Iodine was collected from the air by adsorption on triethylene-diamine (TEDA) impregnated charcoal cartridges connected in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters. The displayed volumes were corrected to standard temperature and pressure.

1.

Air Particulates Air particulate samples were collected weekly at six indicator locations and one control location. Each of the samples collected for the year were analyzed for gross beta. Quarterly composites of the weekly samples from each station were analyzed for specific gamma emitters.

Gross Beta Gross beta activity was detected in 294 of 295 of the indicator station samples collected at concentrations ranging from 2 to 42 E-3 pCi/m 3 with an average concentration of 16 E-3 pCi/m 3, and in 51 of 52 of the control station samples at concentrations ranging from 6 to 32 E-3 pCi/m 3 with an average of 17 E-3 pCi/m 3. The maximum preoperational level detected was 920 E-3 pCi/m 3 with an average concentration of 74 E-3 pCi/m 3. (Table C-2, Appendix C) [Figure 1 -

Results for gross beta analysis from 1990 to current year are plotted as quarterly averages, with an inset depicting the period 1973 to 2011.]

Gamma Spectrometry Gamma spectroscopy was performed on each of the 24 quarterly composite samples.

Beryllium-7, attributed to cosmic ray activity in the atmosphere, was I

detected in 22 of 23 indicator station composites at concentrations ranging from 47.6 E-3 to 405 E-3 pCi/m 3 with an average concentration of 124 E-3 pCi/m 3, and in the four control station composites ranging in concentration from 61 to 245 E-3 pCi/m 3 with an average concentration of 115 E-3 pCi/m3. The maximum preoperational level detected was 330 E-3 pCi/m3 with an average concentration of 109 E-3 pCi/m 3. (Table C-I, Appendix C)

All other gamma emitters were less than the LLD.

2.

Air Iodine Iodine in filtered air samples was collected weekly at seven locations.

Each of the samples collected for the year was analyzed for 1-131.

Iodine-131 Iodine-1 31 was detected in 12 of 295 indicator station samples at concentrations ranging from 34.2 to 82.2 E-3 pCi/m 3 and in two of 52 control station samples at concentrations ranging from 57.2 to 58.2 E-3 pCi/m 3. The 1-131 was detected the week ending 03/28/11 through 04/11/11 and is attributed to the Fukushima incident, not to licensed activities. The maximum preoperational level detected was 42 E-3 pCi/m 3. (Table C-3, Appendix C)

I B.

Direct Radiation Ambient radiation levels in the environs were measured with a pair of I

optically stimulated luminescent (OSL) dosimeter supplied and processed by Landauer. Packets containing OSLs for quarterly exposure were placed in I

the owner-controlled area and around the Site at various distances and in each land based meteorological sector. Emphasis was placed on special I

interest areas such as population centers, nearby residences, and schools. I

A total of 51 locations were monitored for direct radiation during 2011, including 14 on-site locations, 31 off-site locations within the 10 mile zone, and six control locations beyond 10 miles.

Each location has a set of three OSL dosimeters packaged together. The pair uses aluminum oxide technology.

The average dose rate for the 31 quarterly off-site and 14 quarterly on-site indicator OSL dose rate was 5.1 milliroentgen per standard month. The average control OSL dose rate was 4.9 milliroentgen per standard month.

The preoperational average for the quarterly TLD readings was 4.4 milliroentgen per standard month. The results of the direct radiation measurements for 2011 confirmed that the radiation levels in the vicinity of the Salem and Hope Creek Generating Stations were similar to previous years. (Table C-4, Appendix C) [Figure 2 - The quarterly average radiation levels of the off-site indicator stations versus the control stations are plotted for the period 1990 through 2011, with an inset graph depicting the period 1973 to 2011.]

C.

Terrestrial Terrestrial REMP sampling includes the collection of milk, well water, potable water, vegetation, fodder crop and soil samples.

Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture. Animals are considered on pasture from April to November of each year. Samples were collected in new polyethylene containers and transported in ice chests with no preservatives added to the milk.

One well water sample was collected monthly. Separate raw and treated I

potable water samples were composited daily at the City of Salem Water and Sewer Department. All samples were collected in new polyethylene containers.

Locally grown vegetable and fodder crops were collected at the time of harvest from Management Audit sample locations. Broad leaf cabbage and kale were collected from on-site gardens. Maplewood Testing Services I

personnel planted, maintained and harvested these broad leaf crops in the late summer and fall from three locations on site and one across the river. All samples were weighed, packed in plastic bags and shipped to TBE.

1.

Milk I

Milk samples were collected at four local dairy farms (two farms in NJ and two in Delaware). Each sample was analyzed for 1-131 and gamma emitters.

Iodine-131 Iodine-1 31 was not detected above minimum detectable concentration in any of the 80 samples analyzed. The maximum preoperational level detected was 65 pCi/L, which occurred following a period of atmospheric nuclear weapons tests. (Table C-5, Appendix C) [Figure 3 - Results from 1990 to 2011 are plotted as quarterly averages, with an inset graph depicting the period 1973 to 2011.]

Gamma Spectrometry Naturally occurring K-40 was detected in all 80 samples with concentrations for the 60 indicator station samples ranging from 1,100 to 1,540 pCi/L with an average concentration of 1,345 pCi/L, and the 20 control station sample concentrations ranging from 1,100 to 1,590 pCi/L, with an average concentration of 1,290 pCi/L. The maximum I

preoperational level detected was 2,000 pCi/L with an average concentration of 1,437 pCi/L. (Table C-5, Appendix C)

All other gamma emitters were less than the LLD.

2.

Well Water (Ground Water)

Although wells in the vicinity of SGS/HCGS are not directly affected by plant operations, water samples were collected monthly from one farm's well (3E1). This well is located up gradient of the stations aquifer. Samples from this well are considered Management Audit.

Gross Alpha Gross alpha activity was not detected above the minimum detectable concentration in any of the well water samples. The maximum preoperational level detected was 9.6 pCi/L. (Table C-6, Appendix C)

Gross Beta Gross beta activity was detected in two of 12 well water samples.

Concentrations for the samples ranged from 1.8 to 1.9 pCi/L with an average of 1.8 pCi/L. As with the 2010 gross beta results, the 201.1 results are lower than the preoperational results which ranged from

<2.1 to 38 pCi/L, with an average value of 9 pCi/L. The downward trend may be attributed to the REMP participant installing a water treatment system for this well in February, 2009. (Table C-6, Appendix C)

Tritium Tritium activity was not detected above the minimum detectable concentration in any of the well water samples. The maximum preoperational level detected was 380 pCi/L. (Table C-6, Appendix

~I C)

Gamma Spectrometry I

Potassium-40 was detected in two of the 12 well water samples at concentrations of 52 and 63 pCi/L with an average concentration of 57 pCi/L. The maximum preoperational level detected was 30 pCi/L.

Ra-Nat was detected in two of the 12 of the well water samples at concentrations of 101 and 173 pCi/L with an average of 137 pCi/L.

The maximum preoperational level detected was 2.0 pCi/L. The higher than preoperational results are due to a procedural change instituted in 1986 for water sample preparation. It is reasonable to conclude that values currently observed are typical for this region. [28]

(Table C-7, Appendix C)

All other gamma emitters were less than the LLD.

3.

Potable Water (Drinking Water)

Both raw and treated potable water samples were collected and composited by The City of Salem Water and Sewer Department personnel. Each sample consisted of daily aliquots composited into a monthly sample. The raw water source for this plant is Laurel LakeI and its adjacent wells. These are Management Audit samples as no liquid effluents discharged from SGS/HCGS directly affect this I

pathway.

Gross Alpha I

Gross alpha activity was detected in two of the 12 raw water samples at concentrations of 0.7 and 1.1 pCi/L. Gross alpha was not detected in any of the treated water samples. The maximum preoperational I I

level detected was 2.7 pCi/L. (Table C-8, Appendix C)

Gross Beta Gross beta activity was detected in eight of the 12 of the raw water samples and eight of the 12 treated water samples. The concentrations for the raw samples ranged from 1.2 to 6.6 pCi/L.

Concentrations for the treated water ranged from 2.0 to 5.8 pCi/L.

The average concentration for both raw and treated water was 3.8 pCi/L. The maximum preoperational level detected was 9.0 pCi/L with an average concentration of 4.2 pCi/L. (Table C-8, Appendix C)

Tritium Tritium activity was not detected in any of the raw or treated water samples. The maximum preoperational level detected was 350 pCi/L with an average of 179 pCi/L. (Table C-8, Appendix C)

Iodine-131 Iodine-131 measurements were performed to an LLD of 1.0 pCi/L.

Iodine-1 31 activity was not detected in any of the raw or treated water samples. No preoperational data is available for comparison since 1-131 was not analyzed as a specific nuclide until 1989. Since that time all results have been below the MDC. (Table C-9, Appendix C)

Gamma Spectrometry Naturally occurring K-40 was detected in two of the 12 raw water samples at concentrations of 47 and 55 pCi/L, and in two of the 12 treated water samples, each at a concentration of 48 pCi/L. The i

average for both raw and treated water samples was 49 pCi/L. No I

preoperational data is available for comparison.

Naturally occurring Ra-Nat was detected in two of the 12 raw water samples, each at concentrations of 4.5 and 4.8 pCi/L. It was not detected in any of the 12 treated water samples. The combined potable water average was 4.6 pCi/L. The maximum preoperational level detected was 1.4 pCi/L. The higher results are due to the 3

procedural change for sample preparation, as discussed in the Well Water section. (Table C-9, Appendix C)

All other gamma emitters were less than the LLD.

4.

Vegetables i

Although vegetables in the region are not irrigated with water into which liquid plant effluents have been discharged, a variety of food I

products grown in the area for human consumption were sampled.

I These vegetables from local farms are collected as Management Audit samples. In addition, cabbage and kale were grown from seed I

by MTS personnel and planted at three on site locations and one offsite location in Delaware at 3.9 miles SSW. These broad leaf n

vegetable samples are collected since there are no milk farms operating within the 5 km radius of SGS/HCGS. The closest milk farm (13E3) is located in Odessa, DE at 4.9 miles (7.88 km). All samples (vegetable and broadleaf) were analyzed for gamma emitters and included asparagus, cabbage, kale, sweet corn, peppers, and tomatoes. These samples were from eight indicator stations (16 n

samples) and four control stations (13 samples). The results for these samples are discussed below.

3 Gamma Spectrometry Naturally occurring Be-7, attributed to cosmic ray activity in the atmosphere, was detected in two of the 15 indicator station samples (all cabbage) at concentrations of 283 and 364 pCi/kg wet and an average concentration of 324 pCi/kg wet. It was not detected in any of the control locations. No preoperational data is available for comparison.

Naturally occurring K-40 was detected in all 15 indicator samples, with concentrations ranging from 1,360 to 15,000 pCi/kg wet with an average concentration of 3,346 pCi/kg wet, and in all 14 control station samples at concentrations ranging from 1,330 to 16,400 pCi/kg wet with an average concentration of 6,893 pCi/kg wet. The maximum preoperational level detected was 4,800 pCi/kg wet with an average concentration of 2,140 pCi/kg wet. (Table C-10, Appendix C).

All other gamma emitters were less than the LLD.

5.

Fodder Crops Although not required by the SGS or HCGS Technical Specifications and ODCM, four samples of silage normally used as cattle feed were collected from three indicator stations and one control station. It was determined that these products may be a significant element in the food-chain pathway. These fodder crops are collected as Management Audit samples and analyzed for gamma emitters. All four locations from which samples were collected are milk sampling stations.

Gamma Spectrometry I

Naturally occurring Be-7, attributed to cosmic ray activity in the atmosphere, was detected in all three indicator samples at 3

concentrations ranging from 248 to 3,150 pCi/kg wet with an average concentration of 1,766 pCi/kg wet, and in the control station sample at 3

1,500 pCi/kg wet. The maximum preoperational level detected for silage was 4,700 pCi/kg wet with an average concentration of 2,000 3

pCi/kg wet.

Naturally occurring K-40 was detected in all three indicator samples at concentrations ranging from 3,230 to 10,900 pCi/kg wet with an 3

average concentration of 5,933 pCi/kg wet, and in the control station sample at a concentration of 3,970 pCi/kg wet. Preoperational results 3

averaged 7,000 pCi/kg wet. (Table C-1 1, Appendix C)

I All other gamma emitters were less than the LLD.

I

6.

Soil Soil is sampled every three years at nine stations, and analyzed for gamma emitters. These Management Audit samples are collected at 3

each station in areas that have been relatively undisturbed since the last collection in order to determine any change in the radionuclide 3

inventory of the area. (Table C-12, Appendix C)

Soil was sampled in 2010 and will not be sampled again until 2013.

D.

Aquatic I

Environmental Consulting Services, Inc (ECSI) collected all aquatic samples I

(with the exception of the 6S2 shoreline sediment). This sample set includes I

edible fish, shoreline and riverbed sediment, surface water and crab.

Surface water samples were collected offshore. The technicians collect the samples in new polyethylene containers that are rinsed twice with the sample medium prior to collection. The surface water samples are transported to MTS for analysis.

Edible fish are taken by gill nets while crabs are caught in commercial traps.

These samples are then processed where the flesh is separated from the bone and shell. The flesh is placed in sealed containers and frozen before being transported in ice chests to TBE for analysis.

Sediment samples collected by ECSI were taken with a bottom grab sampler and frozen in sealed polyethylene containers before being transported in ice chests to TBE. For the river bottom sediment, a marine GPS locates the correct site and the sampling boat is maneuvered over the area until the correct amount of sample is obtained (grabbed) with the sediment dredge. Personnel from MTS collect and prepare location 6S2 shoreline sediment (an onsite location). For this location, a square area, measuring one meter on each side is staked out and then divided into a grid of nine smaller boxes, three per side. A one inch deep scoop from the center of each of the small grids is taken. All the aliquots are combined and the total sample transported in the ice chest to TBE.

1.

Surface Water Surface water samples were collected monthly at four indicator stations and one control station in the Delaware estuary. One location (11 Al) is at the outfall area (which is the area where liquid radioactive effluents from the Salem Station are discharged into the Delaware I

River), one is downstream from the outfall area (7E1), and one is I

directly west of the outfall area at the mouth of the Appoquinimink River (12C1). Two upstream locations are in the Delaware River (1 F2) and at the mouth of the Chesapeake and Delaware Canal (1 6F1), the latter being sampled when the flow is from the Canal into the river.

Station 12C1, directly west, at the mouth of the Appoquinimink River, serves as the operational control. Location 12C1 was chosen as the control location because the physical characteristics of this station more closely resemble those of the outfall area than do those at the farther upstream location (1 F2). As discussed in the pre-operational i

summary report, due to the tidal nature of this Delaware-River-Bay estuary, there are flow rate variations and variations in salinity levels.

These variations will account for differences in concentrations of potassium and associated gross beta from K-40.

Gross Beta Gross beta activity was detected in 44 of the 48 indicator station 3

samples with concentrations ranging from 3 to 305 pCi/L and an average concentration of 68 pCi/L, and in all 12 of the control station i

samples with concentrations ranging from 4 to 190 pCi/L and an average concentration of 60 pCi/L. The maximum preoperational level 3

detected was 110 pCi/L with an average concentration of 32 pCi/L.

(Table C-13, Appendix C) [Figure 4 - Quarterly results for all 3

locations are plotted for the years 1990 to 2011, with an inset graph depicting the current period 1973 to 2011.]

3 Tritium Tritium activity was not detected in any of the indicator or control samples. The maximum preoperational level detected was 600 pCi/L, with an average concentration of 210 pCi/L. (Table 0-14, Appendix C) [Figure 5 - Quarterly positive results from 1990 to 2011 are plotted, with an inset graph depicting the period 1973 to 2011.]

Gamma Spectrometry Naturally occurring K-40 was detected in 13 of the 48 indicator station samples at concentrations ranging from 50 to 175 pCi/L with an average concentration of 110 pCi/L, and in 2 of the 12 control station samples with concentrations of 80 and 83 pCi/L and an average of 82 pCi/L. The maximum preoperational level detected for K-40 was 200 pCi/L with an average concentration of 48 pCi/L.

Iodine-131 was detected in one of 12 control station samples at a concentration of 1 pCi/L. The 1-131 is attributed to effluent from a medical facility. (Table C-15, Appendix C)

All other gamma emitters were less than the LLD.

2.

Fish Edible species of fish were collected semi-annually at two indicator stations and one control station and analyzed for gamma emitters in edible flesh.

Samples included channel catfish, white catfish, bluefish, white perch, summer flounder, black drum and striped bass.

Gamma Spectrometry Naturally occurring K-40 was detected in all three indicator station samples at concentrations ranging from 3,700 to 4,660 pCi/kg wet with an average concentration of 4,150 pCi/kg wet, and both control station samples at concentrations of 3,050 and 3,950 pCi/kg wet with an average concentration of 3,500 pCi/kg wet. The maximum preoperational level detected was 13,000 pCi/kg wet with an average concentration of 2,900 pCi/kg wet. (Table C-16, Appendix C)

All other gamma emitters were less than the LLD.

3.

Blue Crab

!I Blue crab samples were collected twice during the season at one indicator and one control station. The edible portions were analyzed 3

for gamma emitters.

Gamma Spectroscopy I

Naturally occurring K-40 was detected in both indicator station samples at concentrations of 2,320 and 2,910 pCi/kg wet with an 3

average concentration of 2,615 pCi/kg wet, and in both control station samples at concentrations of 2,390 and 2,630 pCi/kg wet with an 3

average concentration of 2,510 pCi/kg wet. The maximum preoperational level detected was 12,000 pCi/kg wet with an average 5

concentration of 2,835 pCi/kg wet. (Table C-17, Appendix C)

I All other gamma emitters were less than the LLD.

4.

Sediment Sediment samples were collected semi-annually from six indicator stations and one control station. Location 6S2 is the only shoreline sediment and it is directly affected by tidal fluctuations.

Gamma Spectroscopy Cesium-1 37 was detected in one of the 12 indicator samples (7E1) at a concentration of 107 pCi/kg dry. It was not detected in the control station samples. The maximum preoperational level detected was 400 pCi/kg dry with an average concentration of 150 pCi/kg dry. The Cs-137 concentrations are attributed to the atomic bomb testing that starting in the 1940s. (Figure 6 - Semi-annual positive results from 1990 to 2011 are plotted, with an inset graph depicting the current period 1977 to 2011.)

Naturally occurring Be-7, attributed to cosmic ray activity in the atmosphere, was detected in one of the 12 indicator station samples at a concentration of 1,510 pCi/kg dry. The maximum preoperational level detected was 2,300 pCi/kg dry.

Naturally occurring K-40 was detected in all 12 indicator station samples at concentrations ranging from 3,560 to 22,800 pCi/kg dry, with an average concentration of 9,843 pCi/kg dry, and at both control stations samples at concentrations of 13,500 and 17,100 pCi/kg dry with an average concentration of 15,300 pCi/kg dry. The maximum preoperational level detected was 21,000 pCi/kg dry with an average concentration of 15,000 pCi/kg dry.

Naturally occurring Ra-Nat was detected in five of the 12 indicator station samples at concentrations ranging from 1,350 to 3,850 pCi/kg I

dry with an average concentration of 2,320 pCi/kg dry, and at.both control station samples at concentrations of 2,420 and 2,740 pCi/kg dry with an average concentration of 2,580 pCi/kg dry. The maximum pre-operational level detected was 1,200 pCi/kg dry with an average concentration of 760 pCi/kg dry.

Naturally occurring Th-232 was detected in all 12 indicator, station samples at concentrations ranging from 175 to 1,370 pCi/kg dry with an average concentration of 697 pCi/kg dry, and in both of the control 3

station samples at concentrations of 1,070 and 1,370 pCi/kg dry with an average concentration of 1,220 pCi/kg dry. The maximum pre-operational level detected was 1,300 pCi/kg dry with an average concentration of 840 pCi/kg dry. (Table C-18, Appendix C)

All other gamma emitters were less than the LLD.

3 E.

Land Use Survey 3

SYNOPSIS OF 2011 LAND USE CENSUS A land use census was conducted in each of the 16 meteorological sectors to identify, within a distance of 8 km (5 miles),. the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50m2 (500ft2) producing broad leaf vegetation. In accordance with Salem and Hope Creek ODCMs the census was performed using a door to door survey, visual survey, Google Earth and by consulting with local agricultural authorities.

3 I

Milk Animal Oct, 2011 Km (miles)

Nearest Residence Oct, 2011 Km (miles)

Vegetable Garden Oct, 2011 Km (miles)

Meteorological Sector N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW None None None None None None None None None None None None 8.0 (5.0)

None None None None 8.0 (5.0) 6.2 (3.9) 6.2 (3.9)

None None None None None 6.2 (3.9) 6.9 (4.3) 7.1 (4.4) 6.5(4.0) 5.5(3.4) 5.9 (3.7) 6.8 (4.2)

None None None None None None None None None None 7.3 (4.6) 7.1 (4.4)

None None None None The 2011 Land Use Census results are summarized in the above table. A comparison of the identified locations from the 2011 table with the 2010 table shows that no new nearest milk animal, nearest resident, or nearest vegetable garden (500 Ft2) with broadleaf vegetation were identified.

Therefore, no formal dose evaluation or changes to the ODCMs are required.

In 2010 the stations identified two meat animal farms within 5 miles of the site. These locations are located 4.2 mi NNE and located at 4.6 mi SW. The stations have documented these farms in the corrective action program for tracking and initial dose calculations have been performed. Initial dose calculations indicate that this is not a limiting dose pathway. Due to unavailability of meat samples from the meat farms for 2011, sample collections have been rescheduled for the 2012 reporting year.

V.

Annotations to Previous AREOR A new calculation for determining C-14 contribution to dose was performed in the 2011 Effluent report, which reflects the dose changes to the 2010 AREOR.

In the 2009 and 2010 Annual Radiological Environmental Operating Report, there was not a discussion of the positive gamma emitters that were found in the sediment samples. There were two isotopes identified: Manganese (Mn) 54 and Cesium (Cs) 137 at very low levels (27 pCi/L for Mn and 50 to 58 pCi/L for Cs). The manganese sample is from the permitted plant effluents, and the cesium samples 3

could be either from permitted plant effluents or from the early atomic bomb tests.

The latter is the most likely cause as the quantities mirror the bomb test data and 3

any cesium from plant effluents should be mixed with detectable quantities of cobalt (58 and 60), manganese and other isotopes.

VI.

Hope Creek Technical Specification Limit for Primary Water Iodine Concentrations The Hope Creek primary water chemistry results for 2011 were reviewed. The specific activity of the primary coolant did not exceed 0.2 microcuries per gram 3

Dose Equivalent 1-131. Therefore, the iodine concentrations in the primary coolant did not exceed the Tech Spec limit specified in section 3.4.5.

3 VII.

Conclusions The Radiological Environmental Monitoring Program for Salem and Hope Creek Generating Stations was conducted during 2011 in accordance with the SGS and 3

HCGS Technical Specifications and ODCM. The LLD values required by the Technical Specifications and ODCM were achieved for this reporting period (See 3

Appendix A and Appendix C). The objectives of the program were also met during this period. The data collected assists in demonstrating that SGS and HCGS were 3

operated in compliance with Technical Specifications and ODCM requirements.

I The concentration of radioactive material in the environment that could be attributable to Salem and Hope Creeks stations operations was only a small fraction 3

of the concentration of naturally occurring and man-made radioactivity. Since these I I

results were comparable to the results obtained during the preoperational phase of the program, which ran from 1973 to 1976, and with historical results collected since commercial operation, PSEG Nuclear Personnel have concluded that the operation of the Salem and Hope Creek Stations had no significant radiological impact on the environment.

From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment.

VIII.

References

[1]

Public Service Enterprise Group. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2". 1971.

[2]

Public Service Enterprise Group. "Environmental Report, Operating License Stage - Hope Creek Generating Station". 1983.

[3]

United States Atomic Energy Commission. "Final Environmental Statement -

Salem Nuclear Generating Station, Units 1 and 2". Docket No. 50-272 and 50-311. 1973.

[4]

United States Atomic Energy Commission. "Final Environmental Statement -

Hope Creek Generating Station", Docket No. 50-354. 1983.

[5]

Public Service Enterprise Group. "Updated Final Safety Analysis Report -

Salem Nuclear Generating Station, Units 1 and 2".

[6]

Public Service Enterprise Group. "Updated Final Safety Analysis Report -

Hope Creek Generating Station.

[7]

Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Annual Reports 1973 through 1982".

[8]

Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Preoperation Summary - 1973 through 1976". RMC-TR-77-03, 1978.

[9]

Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - December 11 to December 31, 1976".

RMC-TR-77-02, 1977.

I

[10]

Maplewood Testing Services. "Salem and Hope Creek Generating Stations' I

Radiological Environmental Monitoring Program - Annual Reports 1983 through 2010".

[11 a] Maplewood Testing Services. "Quality Assurance Manual." December 2009

[11 b] Maplewood Testing Services. Mechanical Division "Quality Assurance /

U Control Plan". December 2009.

[11 c] Maplewood Testing Services. Mechanical Division U

Environmental/Radiological Group "Procedures Manual". December 2011.

[11d] Teledyne Brown Engineering. "Quality Assurance Manual." November 2011

[1 le] Teledyne Brown Engineering "Procedure Manual 011312".

3

[12]

Public Service Enterprise Group. "Salem Nuclear Generating Station Technical Specifications", Appendix A to Operating License No. DPR-70, I

1976, Sections 6.8.4.h - 1,2,3 and 6.9.1.7.

[13]

Public Service Enterprise Group. "Hope Creek Generating Station 3

Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 6.8.4.h - 1,2,3 and 6.9.1.6.

[14]

Public Service Enterprise Group. "Offsite Dose Calculation Manual"- Salem Generating Station. Revision 25.

[15]

Public Service Enterprise Group. "Offsite Dose Calculation Manual"- Hope Creek Generating Station. Revision 25.

3

[16]

U.S. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water." EPA-600/4-80-032, August 1980.

[17]

U.S. Nuclear Regulatory Commission. "Environmental Technical Specifications For Nuclear Power Plants." Regulatory Guide 4.8, December 1975.

[18]

U.S. Nuclear Regulatory Commission : "NRC Inspection Manual". Inspection Procedure 84750, Issue Date 3/15/94.

[19]

U.S. Nuclear Regulatory Commission: Code of Federal Regulations, Title 10 1

Part 20.1301 Standards for Protection Against Radiation.

[20]

U.S. Nuclear Regulatory Commission: Code of Federal Regulations, Title 10 U

Part 50, Appendix A, General Design Criterion 64, Monitoring Radioactivity Releases.

[21]

U.S. Nuclear Regulatory Commission: Code of Federal Regulations, Title10, Part 50, Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operations to meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents".

[22]

U.S. Nuclear Regulatory Commission, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants: Regulatory Guide 4.1, Rev. 1.

[23]

U.S. Nuclear Regulatory Commission: Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Regulatory Guide 4.13, Rev. 1.

[24]

U.S. Nuclear Regulatory Commission: Quality Assurance for Radiological Monitoring Programs (Normal Operations) Effluent Streams and Environment, Regulatory Guide 4.15, Rev. 1.

[25]

U.S. Nuclear Regulatory Commission: Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, NUREG -1302, April 1991.

[26]

U.S. Nuclear Regulatory Commission: Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, NUREG-1301, April 1991.

[27]

U.S. Nuclear Regulatory Commission: Radiological Assessment Branch Technical Position, Revision 1, November 1979.

[28]

NJDEP : "A South Jersey Homeowner's Guide to Radioactivity in Drinking Water: Radium" Revised April 2004.

[29]

American Nuclear Standards Institute, ANSI N545-1975, Performance Testing and Procedural Specification for Thermoluminescent Dosimetry (Environmental).

Intentionally left blank U

I I

APPENDIX A PROGRAM

SUMMARY

Intentionally left blank

m mAmImOGCA m m

m m

m m -Gm m

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS I. AIRBORNE AIR PARTICULATE (10-3 PCI/CU.M.)

GR-B 347 10 16 (294/295)

(2/42) 124 (22/23)

(47.6/405) 14GI C.

11.8 MILES WNW 17(51/52)

(6/32) 143 (3/4)

(65.5/283) 17(51/52)

(6/32) 115 (4/4)

(61/245)

GAMMA BE-7 K-40 CS-134 CS-137 GAMMA 1-131 27 NA NA 60 50 IFI 5.8 MILES N

<LLD

<LLD 0

0 0

0 AIR IODINE (10-3 PCI/CU.M.)

347 70 56.6 (12/295)

(34.2/82.2) 5.1 (180/180)

(3.2/11.7) 16E1 4.1 MILES NNW 67.0 (2/52)

(51.8/82.2) 8.9 (4/4)

(7.8/10) 57.7 (2/52)

(57.2/58.2) 4.9 (24/24)

(3.5/6.3)

H. DIRECT DIRECT RADIATION (MRAD/STD. MONTH)

II. TERRESTRIAL MILK (PCI/L)

QUARTERLY BADGES 1-131 204 NA 80 16S2 0.6 MILES N 0

0

<LLD

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS MILK (cont'd)

(PCI/L)

GAMMA K-40 CS-134 CS-137 RA-226 WELL WATER (PCI/L)

GR-A GR-B 80 NA 15 18 NA 12 3

12 4

12 NA 12 NA 15 15 1345 (60/60)

(1100/1540) 14F4 7.6 MILES WNW

<LLD

<LLD 1357 (20/20)

(1100/1500) 1290 (20/20)

(1100/1590) 0 0

0 0

0 1.8 (2/12)

(1.8/1.9) 3EI 4.2 MILES NE 1.8 (2/12)

(1.8/1.9)

NA NA NA H-3 GAMMA K-40 MN-54 CO-58

<LLD 57 (2/12)

(52/63) 3EI 4.2 MILES NE 57(2/12)

(52/63)

<LLD

<LLD NA NA NA 0

0 0

M M

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS WELL WATER (cont'd)

(PCI/L)

POTABLE WATER (PCI/L)

FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALAI40 RA-226 30 15 30 15 15 18 NA NA 24 3

<LLD

<LLD NA NA NA NA NA NA NA NA NA NA 0

0 0

0 137 (2/12)

(101/173) 0.9 (2/24)

(0.7/1.1) 3EI 4.2 MILES NE 2F3 8.0 MILES NNE 137 (2/12)

(101/173) 0.9 (2/12)

(0.7/1.1)

GR-A

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS POTABLE WATER (cont'd)

(PCI/L)

GR-B 24 4

24 NA 3.8 (16/24)

(1.2/6.6) 2F3 8.0 MILES NNE 3.8 (8/12)

(1.2/6.6)

NA NA 0

0 H-3 GAMMA K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131

<LL) 24 NA 15 15 30 15 30 15 10 49 (4/24)

(47/55) 2F3 8.0 MILES NNE 51(2/12)

(47/55)

<LLD

<LLD NA NA NA NA NA NA NA NA MMMMmMmMMMm M MmMM M

MM MM MM

RADIOLOGI m

m m

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS POTABLE WATER (cont'd)

(PCI/L) 4GETATION (PCI/KG WET)

CS-134 CS-137 RA-226 GAMMA BE-7 K-40 1-131 CS-134 CS-137 RA-226 TH-232 15 18 NA

<LLD

<LLD NA NA NA 29 NA NA 60 60 80 NA 4.6 (2/24)

(4.5/4.8) 324 (2/15)

(283/364) 4257 (15/15)

(1360/15000) 0 0

0 2F3 8.0 MILES NNE IODI 3.9 MILES SSW 3G1 C 16.5 MILES NE 4.6 (2/12)

(4.5/4.8) 364 (1/1) 16400 (1/1)

<LLD 3129 (14/14)

(1330/16400)

<LLD

<LLD 0

0 0

0 NA

<LLD

<LLD 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS FODDER CROPS (PCI/KG WET)

GAMMA BE-7 4

K-40 1-131 CS-134 CS-137 RA-226 TH-232 GR-B H-3 GAMMA K-40 NA NA 60 60 80 NA NA 1766 (3/3)

(248/3150) 5933 (3/3)

(3230/10900) 2G3 11.8 MILES NNE 2G3 11.8 MILES NNE 3150 (1/I) 10900 (1/I) 1500 (l/l) 3970 (I/1)

<LLD

<LLD 0

0 0

IV. AQUATIC SURFACE WATER (PCI/L) 60 4

60 NA 60 NA 68 (44/48)

(3/305) 7EI 4.5 MILES SE 112(12/12)

(8/305) 60(12/12)

(4/190)

<LLD

<LLD 110(13/48)

(50/175) 7E1 4.5 MILES SE 131 (4/12)

(101/175) 82 (2/12)

(80/83) 0 m m m

m m

m M m

m m

m m M mm m m

mm

m m

mRm mm mm m

mOm m

m m

m mmNm m

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS SURFACE WATER (cont'd)

(PCI/L)

MN-54 CO-58 FE-59 CO-60 ZN-65 ZRNB-95 1-131 CS-134 CS-137 BALAI40 15 15 30 15 30 15 15 18

<LLD

<LLD NA NA NA NA NA NA 12C1 2.5 MILES WSW 1(1/12) 1(1/12)

NA NA 15

<LLD NA 0

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS BLUE CRABS (PCI/KG WET) 00 GAMMA K-40 MN-54 4

CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 RA-226 GAMMA K-40 NA 130 130 260 130 260 130 150 NA 2615 (2/2)

(2320/2910)

IIA1 0.2 MILES SW

<LLD

<LLD 2615 (2/2)

(2320/2910) 2510 (2/2)

(2390/2630)

FISH (PCI/KG WET) 5 NA 4150 (3/3)

(3700/4660) 2G3 11.8 MILES NNE 4660 (1/I) 3500 (2/2)

(3050/3950) 0 m

m m

M m

m m

M m

m m

m M m

m m

m-mOm m

m m

mO-,

m m

m RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS FISH (cont'd)

(PCI/KG WET)

MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 RA-226 GAMMA BE-7 130 130 260 130 260 130 150 NA

<LLD

<LLD SEDIMENT (PCI/KG DRY) 14 NA NA 1510 (1/12) 7EI 4.5 MILES SE 1510 (1/2)

<LLD 0

0 K-40 9843 (12/12) 16FI (3560/22800) 6.9 MILES NNW 19450 (2/2) 15300 (2/2)

(16100/22800)

(13500/17100)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY DOCKET NO. 50-272/-311 DOCKET NO. 50-354 January 1, 2011 to December 31, 2011 MEDIUM OR PATHWAY ANALYSIS AND LOWER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF SAMPLED TOTAL NUMBER LIMIT OF MEAN NAME MEAN MEAN NONROUTINE (UNIT OF MEASUREMENT)

OF ANALYSES DETECTION (RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

REPORTED PERFORMED (LLD)*

MEASUREMENTS SEDIMENT (cont'd)

(PCI/KG DRY)

CS-134 CS-137 RA-226 TH-232 150 180 NA NA

<LLD

<LLD 107 (1/12) 2320 (5/12)

(1350/3850) 697 (12/12)

(175/1370) 7EI 4.5 MILES SE 7EI 4.5 MILES SE 12CI 2.5 MILES WSW 107 (1/2) 3040 (2/2)

(2230/3850) 1220 (2/2)

(1070/1370)

<LLD 2580 (2/2)

(2420/2740) 1220 (2/2)

(1070/1370) 0 0

0 0

I.

LLD LISTED IS THE LOWER LIMIT OF DETECTION WHICH WE ENDEAVORED TO ACHIEVE DURING THIS REPORTING PERIOD.

- MEAN CALCULATED USING VALUES ABOVE LLD ONLY. FRACTION OF MEASUREMENTS ABOVE LLD ARE IN PARENTHESES.

M M

M

=

M M

M

=

M

APPENDIX B SAMPLE DESIGNATION AND LOCATIONS

Intentionally left blank

SAMPLE DESIGNATION The PSEG's Maplewood Testing Services identifies samples by a three part code. The first two letters are the program identification code. Because of the proximity of the Salem and Hope Creek Stations a common environmental surveillance program is being conducted. The identification code, "SA", has been applied to Salem and Hope Creek stations. The next three letters are for the media sampled.

AIO =

APT =

ECH =

ESF =

ESS =

FPL =

FPV =

GAM =

Air Iodine Air Particulate Hard Shell Blue Crab Edible Fish Sediment Green Leaf Vegetables Vegetables (Various)

Game (Muskrat)

IDM

=

MLK =

PWR PWT =

SOL =

SWA=

VGT =

WWA=

Immersion Dose (TLD)

Milk

=

Potable Water (Raw)

Potable Water (Treated)

Soil Surface Water Fodder Crops (Various)

Well Water The last four symbols are a location code based on direction and distance from a standard reference point. The reference point is located at the midpoint between the center of the Salem 1 and Salem 2 containments. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction as follows:

1=N 2=NNE 3=NE 4 = ENE 5=E 6= ESE 7=SE 8 = SSE 9=S 10 = SSW 11 =SW 12 = WSW 13=W 14 = WNW 15= NW 16 = NNW The next digit is a letter which represents the radial distance from the reference point:

S A

B C

D

= On-site location

= 0-1 miles off-site

= 1-2 miles off-site

= 2-3 miles off-site

= 3-4 miles off-site E

F 4-5 miles off-site 5-10 miles off-site 10-20 miles off-site

>20 miles off-site The last number is the station numerical designation within each sector and zone; e.g.,

1,2,3,...etc. For example, the designation SA-WWA-3E1 would indicate a sample in the Salem and Hope Creek program (SA), consisting of well water (WWA), which had been collected in sector number 3, centered at 45 degrees (north east) with respect to the midpoint between Salem 1 and 2 containments at a radial distance of 4 to 5 miles off-site, (therefore, radial distance E). The number 1 indicates that this is sampling station

1 in that particular sector.

B-1

TABLE B-1 SAMPLING LOCATIONS Specific information about the individual sampling locations are given in Table B-1. Maps B-1 and B-2 show the locations of sampling stations with respect to the Site. A Portable Global Positioning System (GPS) was used to provide the coordinates of sampling locations.

tz.

STATIONC ODE 181 2S2 2S4 3S1 4S1 5S1 6S2 7S1 10S1 11S1 15S1 15S2 16S1 16S2 11A1 11A1A 15A1 16A1 12C1 12C1A 4D2 5D1 101D1 14D1 0.57mi. N 0.4 mi. NNE; Lamp Pole 65 Near HC Switch Yard 0.6 mi. NNE 0.58 mi. NE 0.60 mi. ENE 0.86 mi. E; site access road 0.23mi. ESE; area around Helicopter Pad 0.12 mi. SE; station personnel gate 0.14 mi. SSW; inlet cooling water bldg.

0.09 mi. SW; service water inlet bldg.

0.57 mi. NW 0.61 mi. NNW 0.57 mi. NNW 0.60 mi. N 0.2 mi. SW; outfall area 0.15 mi. SE; Located at the plant barge slip 0.65 mi. NW; cooling tower blow down discharge line outfall 0.24 mi. NNW; south storm drain discharge line 2.5 mi. WSW; west bank of Delaware River 3.7 mi. WSW; Located at the tip of Augustine Beach Boat Ramp 3.7 mi. ENE; Alloway Creek Neck Road 3.5 mi. E; local farm 3.9 mi. SSW; Taylor's Bridge Spur 3.4 mi. WNW; Bay View, Delaware STATION LOCATION LATITUDINAL DEG. MIN. FT 39-28-260 39-28-98 39 110 39 140 39 023 39 668 39 719 39 720 39 700 39-27-719 39-28-161 39 12 39 215 39-28-16 39-27-59 39 41 39-27-67 39-28 -24 39 22 39 17 39 292 39 396 39-24-613 39 26 LONGITUDINAL DEG. MIN. FT 75 222 75 10 75 992 75 678 75-31 -544 75 187 75-31 -912 75 15 75 160 75 225 75 525 75 32 75 432 75 17 75-32-25 75-32-02 75 19 75-32-58 75 08 75-34-48 75 175 75 334 75 733 75-35-521 IDM,VGT IDM IDM IDM IDM AIOAPT,IDM IDM,SOL,ESS IDM IDM IDM IDM,VGT IDM IDM,VGT IDM ECH,ESF,ESS,SWA Alternate SWA ESS ESS ECH,ESFESS,SWA Alternate SWA IDM AIO,APT,IDM IDM,SOL,VGT IDM SAMPLE TYPE mMn M

mm M

n r

-m M

M M

M

m m--

-mmTm-m m

m m

m TABLE B-i (cont'd)

STATION CODE STATION LOCATION 15D1 2E1 3E1 7E1 7E1A 11E2 12E1 13E1 13E3 16E1 1F1 1F2 2F2 2F3 2F5 2F6 2F9 2F10 3F2 3F3 3F6 3F7 4F2 5F1 6F1 7F2 9F1 1 0F2 11F1 12F1 3.8 mi NW; Rt. 9, Augustine Beach 4.4 mi. NNE; local farm 4.2 mi. NE; local farm 4.5 mi. SE; 1 mi. W of Mad Horse Creek 8.87 mi. SE; Located at the end of Bayside Road 5.0 mi. SW; Rt. 9 4.4 mi. WSW; Thomas Landing 4.2 mi. W; Silver Run Road (Rt. 9) 5.0 mi. W; Local Farm, Odessa, DE 4.1 mi. NNW; Port Penn 5.8 mi. N; Fort Elfsborg 7.1 mi. N; midpoint of Delaware River 8.5 mi. NNE; Pole at Corner of 574

& Howell, Salem 8.0 mi. NNE; Salem Water Company 7.4 mi. NNE; Salem High School 7.3 mi. NNE; Southern Training Center 7.5 mi. NNE; Local Farm, Tilbury Rd, Salem 9.2 mi. NNE; Local Farm, South Broadway (Rt. 49) Pennsville 5.1 mi. NE;Hancocks Bridge Municipal Bid 8.6 mi. NE; Quinton Township School 6.5 mi. NE; Local Farm, Salem/Hancocks Bridge Road 7.2 mi. NE; Local Farm, Beasley Neck Road, RD#3 6.0 mi. ENE; Mays Lane, Harmersville 6.5 mi. E; Canton 6.4 mi. ESE; Stow Neck Road 9.1 mi. SE; Bayside, New Jersey 5.3 mi. S; D.P.A.L. 48912-30217 5.8 mi. SSW; Rt. 9 6.2 mi. SW; Taylor's Bridge Delaware 9.4 mi. WSW; Townsend Elementary School LATITUDINAL DEG. MIN. FT 39-30-125 39-31 -380 39 098 39-25-08 39-22-57 39 328 39 862 39 989 39-27-17 39-30-762 39-32-693 39-33-08 39 522 39 40 39-33-448 39-33-713 39 55 39-35-35 39-30-410 39 616 39-32-03 39-32-07 39-29-953 39-28-360 39 396 39 971 39 042 39 034 39-24-766 39 778 LONGITUDINAL DEG. MIN. FT 75-35-28 75 428 75 646 75-28-64 75-24-24 75 546 75-36-968 75 735 75 30 75 580 75-31 -124 75 54 75 120 75 18 75 514 75 819 75-29-30 75-29-35 75 578 75 735 75-28-00 75-25-46 75 076 75-25-031 75-25-148 75-24-261 75 95 75 152 75 632 75-41 -311 SAMPLE TYPE IDM IDM IDM,WWA ESF,ESS,SWA Alternate SWA IDM IDM IDM MLK,VGT,SOL AIO,APT,IDM,SOL AIO,APT,IDM SWA IDM PWR,PWT IDM AIO,APT,IDM FPV,FPL,SOL FPV,FPL IDM IDM FPV,FPL FPV,FPL IDM IDM,SOL IDM IDM IDM IDM IDM IDM

TABLE B-1 (cont'd)

STATION CODE 13F2 13F3 13F4 14F2 14F4 15F3 15F4 16F1 16F1A 16F2 1GI 1G3 2G2 2G3 2G4 3G1 9G1 9G2 10G1 14G1 16G1 3H1 3H5 STATION LOCATION 6.5 mi W; Odessa, Delaware 9.3 mi. W; Redding Middle School, Middletown, Delaware 9.8 mi. W; Middletown, Delaware 6.7 mi. WNW; Boyds Corner 7.6 mi. WNW; local farm 5.4 mi. NW 7.0 mi. NW; local farm; Port Penn Road; Delaware 6.9 mi. NNW; C&D Canal 6.84 mi. NNW; Located at the C&D Canal tip 8.1 mi. NNW; Delaware City Public School 10.9 mi. NNE; Rte. 49, South Broadway 19 mi. N; N. Church St. Wilmington, Del (Old Swedish Church Yard Park) 13.5 mi. NNE; Local Farm; Pointers Auburn Road (Rt. 540), Salem, NJ 08079 11.8 mi. NNE; Local Milk Farm, Corner of Routes 540 & 45, Mannington, NJ 11.3 mi. NNE; large family garden; Rt 45 & Welchville Rd,Mannington, NJ 16.5 mi. NE; Milk Farm; Daretown-Alloway Road, Woodstown 10.3 mi. S; Local Farm, Woodland Beach Rd., Smyrna, Delaware 10.7 mi. S; Local Farm, Woodland Beach Road, Smyrna, Delaware 12 mi. SSW; Smyrna, Delaware 11.8 mi. WNW; Rte. 286/Bethel Church Road; Delaware 15 mi. NNW; Across from Greater Wilmington Airport 32 mi. NE; National Park, New Jersey 25 mi. NE; Farm Market, Rt 77 LATITUDINAL DEG. MIN. FT 39-27-297 39-27-215 39-26-857 39-29-979 39-30-44 39-30-987 39-31 -21 39-33-55 39-33-34 39-34-314 39-37.-113 39-44-287 39-38-19 39-36-21 39-36-02 39-35-913 39-18-47 39-18 39-18-223 39-31-290 39-40-637 39-51 -599 39-41 -040 LONGITUDINAL DEG. MIN. FT 75-39-372 75-42-543 75-43-111 75-39-042 75-40-52 75 586 75-38-31 75-34-25 75-33-56 75-35-429 75-30-178 75-32-512 75-26-10 75-24-53 75-25-21 75-16-804 75-33-50 75-34-11 75 095 75-46-495 75-35-570 75-11-96 75-12-380 SAMPLE TYPE IDM 1DM 1DM 1DM MLK,VGT,SOL IDM FPV ESS,SWA Alternate SWA IDM FPV 1DM FPV MLK,FPV,VGT,SOL FPV IDM,MLK,VGT,SOL FPV FPV,FPL 1DM AIO,APT,IDM IDM IDM FPL,FPV NOTE: All station locations are referenced to the midpoint of the two Salem Units' Containments. The coordinates of this location are: Latitude N 390 - 27' - 46.5" and Longitude W 750 - 32' - 10.6".

All Vegetables (FPV & FPL) and Vegetation (VGT), are management audit samples. They are not required by the Salem & Hope Creek Stations' Tech Specs nor listed in the Station's ODCM. Vegetable samples are not always collected in consecutive years from the same farmer since they rotate the type of crop they grow.

Mm M m

m

-M m m

m mM m

m m

m

=

m m

mmmm mm m

m m

TABLE B-2 SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Program Overview)

EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND

- SAMPLING AND AND/OR SAMPLE SAMPLE LOCATIONS COLLECTION TYPE/FREQUENCY* OF FREQUENCY ANALYSIS

1. DIRECT RADIATION Fifty-one routine monitoring stations with two or Quarterly Gamma dose/ quarterly Thermoluminescent more dosimeters placed as follows:

Dosimeters An inner ring of stations, one in each land based meteorological sector (not bounded by water) in the general area of the site boundary: 1S1, 2S2, 2S4, 3S1, 4S1, 5S1, 6S2, 7S1, 1OS1, 11S1, 15S1, 15S2, 16S1,16S2.

An outer ring of stations, one in each land-based meteorological sector in the 5 - 11 km range (3.12 -

6.88 miles) from the site (not bounded by or over water): 4D2, 5D1, 1OD1, 14D1, 15D1, 2E1, 3E1, 11E2, 12E1, 13E1, 16E1, 1F1, 3F2, 4F2, 5F1, 6F1, 9F1, 10F2, 11F1, 13F2, 14F2, 15F3.

The balance of the stations to be placed in special interest areas such as population centers, nearby residences, and schools: 2F2, 2F5, 2F6, 3F3, 7F2, 12F1, 13F3, 13F4, 16F2, 1G3, 10G1, 16G1, 3H1.

and in two areas to serve as control stations: 3G1, 14G1.

TABLE B-2 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND AND/OR SAMPLE SAMPLE LOCATIONS COLLECTION TYPE/FREQUENCY* OF FREQUENCY ANALYSIS

2.

ATMOSPHERIC

a. Air Particulate

b.

Air Iodine

3. TERRESTRIAL

a. Milk Samples from 6 locations:

1 sample from close to the Site Boundary : 5S1 3 Samples in different land based sectors: 1 F1, 2F6, 5D1.

1 Sample from the vicinity of a community: 16E1.

1 Sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction:

14G1.

Samples from milking animals in 3 locations within 5 km distance. If there are none, then, 1 sample from milking animals in each of 3 areas between 5 - 8 km (3.12 - 5 miles) distant: 13E3, 14F4, 2G3. (1) 1 Sample from milking animals at a control location 15-30 km distant (9.38 - 18.75 miles): 3G1.

Continuous sampler operation with sample collection weekly or more frequently if required by dust loading Semi-monthly (when animals are on pasture)

Monthly (when animals are not on pasture)

Gross Beta / weekly Gamma isotopic analysis /

quarterly composite lodine-131 / weekly Gamma scan semi-monthly Iodine-131 / semi-monthly Gamma scan / monthly lodine-131 / monthly

b. Well Water (Ground)

Samples from one or two sources only if likely to be affected. (Although wells in the vicinity of SGS/HCGS are not directly affected by plant operations, 3E1 farm's well, is sampled as management audit sample)

Monthly Gamma Scan / monthly Gross alpha / monthly Gross beta / monthly Tritium / monthly M

M m

m m

m M

M m

m M

m m

m mm m m

m m

TABLE B-2 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND AND/OR SAMPLE SAMPLE LOCATIONS COLLECTION TYPE/FREQUENCY*

FREQUENCY OF ANALYSIS

c. Potable Water (Drinking Water)

d. Vegetables

e. Fodder Crops One sample of the nearest water supply affected by its discharge (No potable water samples are required as liquid effluents discharged from SGS/HCGS do not directly affect this pathway) However, for management audit samples, one raw and one treated sample from a public water supply (City of Salem Water and Sewer Department) is collected: 2F3 One sample of each principal class of food products from area that is irrigated by water in which liquid plant wastes have been discharged (The Delaware River at the location of SGS/HCGS is a brackish water source and is not used for irrigation of food products). Management audit samples are collected from various locations during harvest: 2F9, 2F10, 3F6, 3F7, 2G2, 9G1, 9G2, and 3H5. In addition, Broad leaf vegetation (cabbage and kale) was planted &

collected onsite (1S1, 15S1, 16S1) and across the river, 1OD1, in lieu of having a milk farm within 5 km of the Site (1)

Although not required by SGS/HCGS ODCM, a sample of crops normally used as cattle feed (silage) were collected from our milk farms as management audit samples: 14F4, 3G1, 2G3, 13E3.

Monthly (composited daily)

Annually (at harvest)

Gross alpha / monthly Gross beta / monthly Tritium / monthly Gamma scan / monthly lodine-131 / monthly Gamma scan/on collection Gamma scan/on collection

TABLE B-2 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND AND/OR SAMPLE SAMPLE LOCATIONS COLLECTION TYPE/FREQUENCY*

FREQUENCY OF ANALYSIS

f. Soil

4. AQUATIC ENVIRONMENT oc

a. Surface Water

b. Edible Fish Although not required by SGS/HCGS ODCM, samples of soil are collected as manaqement audit samples: 6S2, 2F9, 5F1, 1OD1, 16E1, 13E3, 14F4, 2G3, 3G1 (Samples were collected in 2010)

One sample upstream: 1 F2 One sample downstream: 7E1 One sample outfall: 11A1 One sample cross-stream (mouth of Appoquinimink River): 12C1 (2)

And an additional location in the Chesapeake & Delaware Canal: 16F1 One sample of each commercially and recreationally important species in vicinity of plant discharge area: 11 Al One sample of same species in area not influenced by plant discharge: 12C1 (2)

And an additional location downstream: 7E1 One sample of each commercially and recreationally important species in vicinity of plant discharge area: 1 1A1 One sample of same species in area not influenced by plant discharge: 12C1 (2)

Monthly Gross Beta/monthly Gamma scan/monthly Tritium/monthly**

Every 3 years (2010-2013-2016)

Gamma scan/on collection Semi-annually Gamma scan (flesh)/ on collection-

c. Blue Crabs Semi-annually Gamma scan (flesh)/ on collection M-mmm-

-l M

=

M

=

M

=1

m m

m

-m mmmnmm m

m m--m-m TABLE B-2 (cont'd)

SALEM AND HOPE CREEK GENERATING STATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND COLLECTION TYPE/FREQUENCY*

AND/OR SAMPLE SAMPLE LOCATIONS FREQUENCY-OF ANALYSIS

d. Sediment One sample from downstream area: 7E1 One sample from cross-stream area/One sample from a control location: 12C1(2)

One sample from outfall area: 11Al One sample from upstream, the C & D Canal: 16F1 One sample from shoreline area: 6S2 One sample from Cooling Tower Blowdown: 15A1 And an.

additional location of south storm drain discharge line: 16A1 Semi-annually Gamma scan/on collection

Except for TLDs, the quarterly analysis is performed on a composite of individual samples collected during the quarter.

Tech Specs and ODCM require quarterly analysis but due to the tritium leak at Salem, it was decided to analyze surface waters on a monthly basis for tritium.

(1) While these milk locations are not within the 5 km range, they are the closest farms in the Site vicinity.

Since broad leaf vegetation is acceptable in lieu of milk collections, MTS personnel planted and harvested cabbage and kale at three locations on Site (1S1, 15SI, 16S1) and one across the river in Delaware (10DI).

(2)Station 12C1 was made the operational control (1975) for aquatic samples since the physical characteristics of this station more closely resemble those of the outfall area than do those at the upstream location originally chosen. This is due to the distance from Liston Point, which is the boundary between the Delaware River and Delaware Bay. As discussed extensively in the SGS/HCGS Pre-operational reports, the sampling locations further upstream show significantly lower background levels due to estuarine tidal flow.

MAP B-1 SALEM AND HOPE CREEK GENERATING STATIONS' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ON-SITE SAMPLING LOCATIONS 2I 15 14 ros 4,_

.* ~

HOPE CREEK

}

GENERATING-STATION

"----TOWER 13 5

DELAWARE MRVR IoI 10 8

B-10

MAP B-2 SALEM AND HOPE CREEK GENERATING STATIONS' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM OFF-SITE SAMPLING LOCATIONS B-1I

I I

I Intentionally left blank I

I I

1 I

I I

I

APPENDIX C DATA TABLES

I I

I Inte tion lly eft lankI I

I I1 I

I I

I

TABLE C-1 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATES, 2011 RESULTS IN UNITS OF 10-3 PCI/M3 +/--2 SIGMA STC COLLECTION Be-7 K-40 Cs-134 Cs-137 PERIOD SA-APT-14G1 (C) 12/28/10 03/28/11 06/27/11 09/26/11

- 03/28/11

- 06/27/11

- 09/26/11

- 12/27/11 AVERAGE

245 +/- 127 88 +/- 21 61 +/- 17 67 +/- 19 115 +/- 175 305 +/- 154 82 +/- 27 94 +/- 30 63 +/- 16 136 +/- 227

< 167

< 30

< 26

< 24

< 10

<2

<7

<2

<1

<2 SA-APT-16E1 12/28/10 03/28/11 06/27/11 09/26/11

- 03/28/11

- 06/27/11

- 09/26/11 12/27/11

< 138

< 39

< 32

< 40

<12

<2

<5

<2

<2 AVERAGE

SA-APT-1 Fl 12/28/10 03/14/11 03/21/11 03/28/11 03/28/11 04/04/11 06/27/11 09/26/11

- 03/28/11

- 03/21/11

- 03/28/11

- 04/04/11

- 06/27/11

- 04/11/11

- 09/26/11

- 12/27/11 283 +/- 126

< 68

< 128

< 332 190 +/- 106

< 211 193 +/-92

< 281 81 +/-25

< 30 297 +/- 105

< 438 66 +/-19

< 8

< 17

< 27

<11

<18

< 26

< 21

<2

< 23

<2

<8

< 18

<19

<16

<2

< 30

<2

<2 AVERAGE

143 +/- 242 SA-APT-2F6 12/28/10 03/28/11 06/27/11 09/26/11 03/28/11 06/27/11 09/26/11 12/27/11 405 59 48 48

+/- 142

+/- 26

+/- 15

+/- 12

< 89

< 26

< 20

<19

<8

<2

<1

<8

<2

<1

<1 AVERAGE

140 +/- 354 SA-APT-5D1 12/28/10 03/14/11 03/21/11 03/28/11 03/28/11 04/04/11 06/27/11 09/26/11 03/28/11 03/21/11 03/28/11 04/04/11 06/27/11 04/11/11 09/26/11 12/27/11 260 +/- 123

< 127

< 188

< 247

< 128

< 116

< 161

< 440 93 +/-22

< 26 198 +/- 104

< 194 48 +/-23

< 26 60 +/-12

< 22

<7

< 23

<17

< 30

<2

< 21

<2

<1

<6

< 25

< 21

< 30

<2

< 22

<2

<2 AVERAGE

132 +/- 186

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT (C) CONTROL STATION C-1

TABLE C-1 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATES, 2011 RESULTS IN UNITS OF 10-3 PCI/M3 +/- 2 SIGMA STC COLLECTION Be-7 K-40 Cs-134 Cs-137 PERIOD SA-APT-5Sl 12/28/10 - 03/28/11 277 +/- 145

< 134

< 9

< 9 03/28/11

- 06/27/

06/27/11

- 09/26/

09/26/11

- 12/27/

/11

'11 76 64 66

+/- 26

+/- 20

+/- 12

< 26

< 32

< 28

<2

<1

<2

<1 AVERAGE

SA-APT-5S2 121 +/- 209 (1) 115 +/-49 59 +/- 18 73 +/- 21 (1)

(1)

(1) 04/18/11 06/27/11 09/26/11 06/27/11 09/26/11 12/27/11

< 27

< 23

< 33

<2

<1

<2 AVERAGE

82 +/- 58 1

I I

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-2

TABLE C-2 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES, 2011 RESULTS IN UNITS OF 10-3 PCI/M3

2 SIGMA COLLECTION PERIOD 12/27/10 - 01/03/11 01/03/11

- 01/10/11 01/10/11 - 01/17/11 01/17/11

- 01/24/11 01/24/11

- 01/31/11 01/31/11

- 02/07/11 02/07/11

- 02/14/11 02/14/11

- 02/21/11 02/21/11

- 02/28/11 02/28/11

- 03/07/11 03/07/11

- 03/14/11 03/14/11

- 03/21/11 03/21/11

- 03/28/11 03/28/11

- 04/04/11 04/04/11

- 04/11/11 04/11/11

- 04/18/i1 04/18/11

- 04/25/11 04/25/11

- 05/02/11 05/02/11

- 05/09/11 05/09/11

- 05/16/11 05/16/11

- 05/23/11 05/23/11

- 05/31/11 05/31/11

- 06/06/11 06/06/11

- 06/13/11 06/13/11

- 06/20/11 06/20/11

- 06/27/11 06/27/11

- 07105/11 07/05/11

- 07/11/11 07/11/11 - 07/18/11 07/18/11 - 07/25/11 07/25/11 - 08/01/11 08/01/11 - 08/08/11 08/08/11

- 08/15/11 08/15/11

- 08/22/11 08/22/11

- 08/29/11 08/29/11 - 09/06/11 09/06/11 - 09/12/11 09/12/11 - 09/19/11 09/19/11

- 09/26/11 09/26/11 - 10/03/11 10/03/11

- 10/10/11 10/10/11

- 10/17/11 10/17/11

- 10/24/11 10/24/11

- 10/31/11 10/31/11

- 11/07/11 11/07/11

- 11/14/11 11/14/11

- 11/21/11 11/21/11

- 11/28/11 11/28/11

- 12/05/11 12/05/11

- 12/12/11 12/12/11

- 12/19/11 12/19/11

- 12/27/11 CONTROL SA-APT-14G1 28 +/-3 32 +/-2 16 +/-2 21 +/- 2 15 +/- 2 16 +/- 2 18 +/- 2 21 +/- 2 18 +/- 2 18 +/-2 14 +/-3 11 +/-3 24 +/-4 25 +/-4 19 +/-4 14 +/-4 13 +/-3 6+/-3 11 +/-3 6+/-3 9+/-3 18+/- 3 18+/- 4 19+/- 3 13+/- 3 13+/- 3 17 +/-4 19 +/-4 14 +/-3 28 +/- 4 21 +/- 4 17 +/- 4 15 +/- 4 15 +/- 3 13 +/-3 15 +/- 3

<5 17 +/- 4 10 +/-3 6+/-3 15 +/-3 20 +/-4 10 +/- 3 17 +/-3 16 +/- 3 21 +/-3 18 +/- 4 18 +/- 4 14 +/- 3 12 +/- 3 27 +/- 4 17 +/- 3 SA-APT-1 Fl 30 +/-3 31 +/- 2 16 +/- 2 23 +/- 2 19 +/- 2 14 +/- 2 21 +/- 2 17 +/- 2 19 +/- 2 19 +/- 2 14 +/- 3 9 +/-3 31 +/-5 29 +/-5 17+/- 4 13 +/-4 11 +/-3 5+/-3 12+/- 3 7+/-3 13 +/-3 16+/- 3 18 +/-4 19+/- 3 13+/- 4 13+/- 3 16+/- 4 21 +/-4 14+/- 3 25 +/-4 17+/- 3 15 +/- 4 13 +/- 4 14+/- 3 13+/- 4 15+/- 3 10+/- 4 16+/- 3 8+/-3 7+/-3 15 +/- 3 23 +/- 4 13 +/- 3 17 +/- 3 12 +/- 3 20 +/- 3 19 +/- 4 16 +/- 4 11 +/-3 12 3

31 +/-4 15+/- 3 SA-APT-2F6 29 +/-3 35 +/- 2 18 +/- 2 18 +/- 2 19 +/- 2 15 +/- 2 20 +/- 2 20 +/- 2 19 +/- 2 18 +/- 2 11 +/-3 11 +/-3 30 +/-4 25 +/-4 20 +/-4 12 +/-3 16+/- 3 8 +/-3 10 +/-3 5 +/-2 9 +/-3 18 +/- 3 17+/- 4 21 +/-3 14+/- 4 12+/- 5 15+/- 3 19+/- 4 14+/- 3 26 +/-4 18+/- 3 17+/- 3 13+/- 3 14+/- 3 12+/- 3 17+/- 3 8+/-3 17+/- 3 7+/-3 7+/-3 16+/- 3 22 +/-4 14 +/- 3 18 +/- 3 10+/- 3 19+/- 3 16+/- 3 17+/- 4 11 +/-3 13+/- 3 24 +/-4 15+/- 3 GROUP I SA-APT-5 29 +/-3 37 +/- 2 19 +/- 2 22 +/- 2 17+/- 2 17+/- 2 19+/- 2 22 +/-2 15+/- 2 16+/- 2 12+/- 3 10+/- 3 27 +/-4 42 +/-5 17+/- 4 12+/- 3 14+/- 3 8+/-3 12+/- 3 5+/-2 7+/-3 16 +/- 3 20 +/- 4 16 +/- 3 11 +/-3 12+/- 3 17+/- 3 16+/- 3 12 +/-3 16+/- 3 18 +/-4 10 +/-4 14+/- 3 10 +/-3 14+/-3 7+/-4 18 +/-4 7+/-3 8+/-3 15+/- 3 20 +/-3 10+/- 3 19+/- 3 12+/- 3 19+/- 3 19+/- 3 15+/- 3 11 +/-3 14+/- 3 27 +/- 4 17 +/- 3 5D1 SA-APT-5S1 25 +/-2 34 +/- 2 16 +/- 2 20 +/- 2 13 +/- 2 17 +/- 2 22 +/- 2 17 +/- 2 20 +/- 2 18 +/- 2 15 +/- 3 13 +/- 3 25 +/-4 23 +/- 4 17+/-4 11 +/-3 15 +/-4 7+/-3 12 +/-3 4 +/-3 8+/-3 17+/-3 20 +/-4 20 +/-4 10 +/-4 14+/-3 17+/-4 14+/-4 13+/-3 (2) 23+/- 4 15+/-3 14+/-3 11 +/-3 10+/-3 11 +/-3 15+/-3 9+/-4 16+/-4 5 +/-3 7+/-3 14+/-3 19+/-3 12 +/-3 20 +/-3 13 +/- 3 19 +/- 3 19 +/- 3 17+/-4 9 +/-3 11 +/-3 27 +/-4 15 +/-3 SA-APT-5S2 SA-APT-16E1 (1) 31 +/-T3 34 +/-2 17+/-2 20 +/- 2 17 +/-2 16 +/-2 2 +/-2 20 +/-2 17 +/-2 18 +/-2 13 +/-3 15 +/-3 28 +/- 4 29 +/- 5 19 +/-4 10 +/-4 14 +/-3 14 +/-4 9+/-3 8 +/-4 14 +/-3 12 +/-3

<3 6+/-3 8+/-3 8+/-3 18 +/-3 18 +/-3 18 +/-3 15 +/-4 18 +/-3 23 +/-4 12 +/-3 15 +/-4 10 +/-3 12 +/-3 15 +/-3 16 +/-4 20 +/-3 20 +/-4 14 +/-3 12 +/-3 24 +/-4 25 +/-4 17 +/-3 18 +/-3 13 3

16 +/-4 12 +/-4 8 +/-3 10 +/-3 12 +/-3 11 +/-3 11 +/-3 12 +/-3 17 +/-3 8+/-4 7+/-4 21 +/-4 23 +/-4 7+/-3 8+/-3 9+/-3 8+/-3 16 +/-3 14 +/-3 21 4

22 +/-4 11 +/- 3 12 +/-3 14 +/-3 17 +/-3 10 +/-3 14 +/-3 18 +/-3 17 +/-3 20 +/-4 20 +/-4 16 +/-4 17 +/-4 11 +/-3 10 +/- 3 16 +/-4 13 +/-3 26 4

25 +/-4 14 +/-3 16 +/-3 AVERAGE

17 +/- 11 16 +/- 12 16 +/- 12 16 +/- 14 15 +/- 11 14 +/- 9 16 +/- 13

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION (2) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3

CONCENTRATIONS OF IODINE-131* IN FILTERED AIR, 2011 1

TABLE C-3 RESULTS IN UNITS OF 10-3 PCI/M3 +/- 2 SIGMA COLLECTION PERIOD 12/27/10 - 01/03/11 01/03/11

- 01/10/11 01/10/11

- 01/17/11 01/17/11

- 01/24/11 01/24/11

- 01/31/11 01/31/11

- 02/07/11 02/07/11

- 02/14/11 02/14/11

- 02/21/11 02/21/11

- 02/28/11 02/28/11

- 03/07/11 03/07/11

- 03/14/11 03/14/11

- 03/21/11 03/21/11

- 03/28/11 03/28/11

- 04/04/11 04/04/11

- 04/11/11 04/11/11

- 04/18/11 04/18/11

- 04/25/11 04/25/11

- 05/02/11 05/02/11

- 05/09/11 05/09/11

- 05/16/11 05/16/11

- 05/23/11 05/23/11

- 05/31/11 05/31/11

- 06/06/11 06/06/11 06/13/11 06/13/11

- 06/20/11 06/20/11

- 06/27/11 06/27/11

- 07/05/11 07/05/11

- 07/11/11 07/11/11

- 07/18/11 07/18/11

- 07/25/11 07/25/11

- 08/01/11 08/01/11

- 08/08/11 08/08/11

- 08/15/11 08/15/11

- 08/22/11 08/22/11

- 08/29/11 08/29/11

- 09/06/11 09/06/11

- 09/12/11 09/12/11

- 09/19/11 09/19/11

- 09/26/11 09/26/11

- 10/03/11 10/03/11

- 10/10/11 10/10/11

- 10/17/11 10/17/11

- 10/24/11 10/24/11

- 10/31/11 10/31/11

- 11/07/11 11/07/11

- 11/14/11 11/14/11

- 11/21/11 11/21/11

- 11/28/11 11/28/11 - 12/05/11 12/05/11

- 12/12/11 12/12/11

- 12/19/11 12/19/11

- 12/27/11

(*(*

(*

CONTROL SA-AIO-14G1

<4

<5

<4

<3

<2

<3

<4

<1

< 22

< 27

2) 57 17

2) 58 23

2) < 26

<15

< 23

<6

< 32

< 42

< 57

< 39

< 27

< 34

< 32

< 20

< 34

<11

< 33

<17

< 45

<3

< 38

< 30

< 25

< 20

< 14

< 23

<7

< 35

<15

< 29

< 26

< 24

< 26

< 33

< 38

< 42

<44

< 24

<17

<15 SA-AIO-1 F1

< 2

< 3.8

< 2.3

< 2.7

< 2.5

< 2.9

< 2.2

<2

< 3.1

< 2.5

<18

< 21 46 +/- 22 68 +/- 17 55 +/- 16

<21

< 22

< 4.3

< 30

< 35

< 60

< 69

< 24

< 27

< 21

< 26

< 63

< 37

<16

< 31

< 5.7

< 27

< 49

< 29

<16

< 33

<18

<19

< 42

< 18

<19

< 27

<13

< 24

< 35

< 40

< 33

< 28

< 21

< 23 U

SA-AIO-2F6

<3

< 3

<4

<5

<4

<5

<2

<3

<2

<16

< 21 40 +/- 16 68 +/- 19

< 25

<13

< 21

<4

< 28

< 42

< 59

< 65

< 23

< 25

< 35

< 32

< 49

< 38

<17

< 28

<3

< 23

< 42

< 20

<13

< 33

<18

< 20

< 45

< 19

<18

< 26

< 25

< 12

< 22

< 32

< 36

< 31

< 26

< 20

< 22 U

SA-A

<3

< 3

<4

<3

<1

<3

<4

< 20

< 23 4:

7' 3'

< 14

< 24

<5

< 31

< 39

< 56

< 36

< 24

< 36

< 34

< 21

< 31

< 33

< 46

<8

< 40

< 32

< 26

< 25

<14

< 23

<6

< 34

< 14

< 27

< 24

< 23

< 24

< 32

< 35

< 42

< 41

< 24

<16

<15 GO-5DPSA-AIO-5Sl SA-AIO-5S2 SA-AIO-16E1

<4

<3

<2

<3

<4

<3

<5

< 19

< 24 3

14 47 16 4

19 71 18 4

14

< 18

<13

<25 2

<5

< 32

< 36

< 65

< 67

< 26

< 27

< 29

< 21

< 26

< 65

< 43 (3)

< 17

< 29

<5

< 25

< 45

< 22

<14

< 36

< 20

< 44

<19

<18

< 26

< 25

<12

< 23

< 32

< 36

< 31

<26

< 20

< 21 (1)

< 21

<4

< 29

< 32

< 57

< 62

< 22

< 25

<18

< 22

53

< 35

<17

< 29

<5

< 25

< 46

< 22

<14

< 37

< 20

< 46

<ý 19

<18

< 27

<13

< 24

< 34"

< 39

< 33

< 28

< 21

< 22

<6

<5

<2

<1

<2

<4

<3

<4

<2

< 22

< 26 52 +/- 17 82 +/- 16

< 15

<14

< 28

<7

< 33

< 44

< 61

< 41

< 29

< 36

< 35

< 21

< 34

< 52

< 35

<18

< 45

<8

< 39

< 31

< 27

< 20

< 14

< 24

<7

< 36

<15

< 28

< 25

< 23

< 25

< 31

< 37

< 41

<44

< 24

<16

<15 GROUP I I

I I

I UI 67 +/- 65 1

AVERAGE

58 +/- 1.4 56 +/- 22 54 +/- 39 50 +/- 42 59 +/- 34 1-131 RESULTS ARE CORRECTED FOR DECAY TO STOP DATE OF COLLECTION PERIOD.

- THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION (2) POSITIVE 1-131 IS FROM THE FUKUSHIMA INCIDENT (3) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION I

I I

C-4

TABLE C-4 DIRECT RADIATION MEASUREMENTS - QUARTERLY OSL RESULTS*, 2011 RESULTS IN UNITS OF mR/STANDARD MONTH**

STATION CODE SA-IDM-1 Fl SA-IDM-lSl SA-IDM-2E1 SA-IDM-2F2 SA-IDM-2F5 SA-IDM-2F6 SA-IDM-2S2 SA-IDM-2S4 SA-IDM-3E1 SA-IDM-3F2 SA-IDM-3F3 SA-IDM-3S1 SA-IDM-4D2 SA-IDM-4F2 SA-IDM-4S1 SA-IDM-5D1 SA-IDM-5Fl SA-IDM-5S1 SA-IDM-6F1 SA-IDM-6S2 SA-IDM-7F2 SA-IDM-7Sl SA-IDM-9F1 SA-IDM-1OD1 SA-IDM-10F2 SA-IDM-1OS1 SA-IDM-1 1 E2 SA-IDM-11Fl SA-IDM-1 1SI SA-IDM-12E1 SA-IDM-12F1 SA-IDM-13E1 SA-IDM-13F2 SA-IDM-13F3 SA-IDM-13F4 SA-IDM-14D1 SA-IDM-14F2 SA-IDM-15D1 SA-IDM-15F3 SA-IDM-15S1 SA-IDM-15S2 SA-IDM-16E1 SA-IDM-16F2 SA-IDM-16S1 SA-IDM-16S2 SA-IDM-1G3 (C)

SA-IDM-3G1 (C)

SA-IDM-3H1 (C)

SA-IDM-10G1 (C)

SA-IDM-14G1 (C)

SA-IDM-16G1 (C) 6 8

5 4

4 4

5 4

4 4

4 6

4 4

5 4

5 5

4 4

5 4

4 5

5 4

5 5

5 3

4 5

4 4

8 5

5 5

4 5

4 AVERAGE 2 S.D.

.0 +/- 1.0

.8+/- 6.6 5.0 +/- 0.9

.4 +/- 1.4 5.0 +/- 1.2

.8 +/- 0.8 5.9 +/- 1.7

.9 + 1.6

.3 +/- 1.7

.4 +/- 1.6

.8 +/- 0.8

.3 +/- 0.8

.4 +/- 1.9

.6 +/- 1.3 5.2 +/- 1.6

.6 +/- 1.3

.3 +/- 0.6

.3 +/- 0.7

.0 +/- 1.0 6.2 +/- 1.3

.4 +/- 2.6

.5 +/- 0.6

.8 +/- 1.2

.9 +/- 1.5

.6 +/- 1.5

.2 +/- 1.4 5.4 +/- 1.0 5.4 +/- 1.7

.2 +/- 0.6

.9 +/- 1.7

.1 +/-2.0

.4 +/- 1.4

.7 +/- 1.4

.3+/- 2.7

.5 +/- 2.1

.9 +/- 1.6 5.3 +/- 1.4

.3+/- 1.2

.3 +/- 1.8 3.9 +/- 0.8

.7 +/- 0.9 5.2 +/- 1.2

.7 +/- 0.5

,6 +/- 2.0 1.9 +/- 2.4 5.2

0.6 5.3 +/- 0.7 5.0 +/- 1.8

.5 +/- 1.7

.3 +/- 1.4

.2 +/- 1.7 JAN - MAR APR - JUN JUL - SEP OCT - DEC b.7 5.7 5.1 5.1 4.1 4.5 6.9 5.4 4.4 4.8 4.8 4.1 5.4 4.8 6.0 3.8 4.5 4.5 4.1 6.6 4.1 6.3 5.7 5.4 6.0 4.8 5.4 6.0 4.5 4.5 6.0 4.1 4.8 6.0 4.1 5.4 5.7 5.7 5.7 3.5 4.8 5.1 4.8 4.5 7.8 5.4 5.1 4.8 5.1 5.4 3.8 6.3 6.3 5.3 4.4 5.0 4.7 5.0 4.1 3.5 3.8 5.3 4.7 4.1 4.7 4.4 4.7 4.7 4.1 4.1 5.9 6.3 6.3 4.4 5.6 5.6 4.4 5.9 5.6 4.4 4.1 5.9 4.4 5.0 4.1 5.6 4.1 5.9 4.7 4.7 3.8 5.3 5.6 5.0 5.3 7.8 5.3 5.3 6.3 4.1 5.0 3.5 t6.6 11.6 5.4 4.7 5.4 5.4 6.3 5.7 5.4 5.4 4.7 4.4 4.7 5.4 5.7 5.4 4.1 4.7 4.4 6.9 4.1 6.9 4.7 4.1 6.3 4.4 4.7 4.1 4.1 6.0 4.4 5.4 5.4 6.9 6.6 5.7 5.1 6.0 6.3 4.4 4.4 5.7 4.4 5.4 10.0 4.7 5.1 4.7 5.4 6.3 5.4 5.5 11.7 4.3 3.5 5.5 4.6 5.5 4.3 3.8 3.8 4.3 3.8 3.2 3.8 4.6 4.3 4.1 4.1 3.2 5.5 3.2 6.3

,4.3 4.3 4.6 3.2 5.5 5.8 3.8 5.2 4.1 3.8 3.8 4.3 5.8 4.3 4.3 4.9 4.3 3.8 4.3 4.3 4.6 3.2 9.7 5.2 5.8 4.1 3.5 4.6 4.1

QUARTERLY ELEMENT OSL RESULTS BY LANDAUER RESULTS ARE REPORTED IN MILLIROENTGEN (mR) WITH THE STANDARD MONTH = 30.4 DAYS (C) CONTROL STATION C-5

I TABLE C-5 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS IN MILK, 2011 RESULTS IN UNITS OF PCI/L + 2 SIGMA SAMPLING PERIOD GAMMA EMITTERS ----------

STATION ID START STOP 1-131 K-40 Cs-134 Cs-137 Ra-226 SA-MLK-13E3 01/02/11

- 01/03/11

< 0.3 1430 +/- 70.3

< 1

< 3 SA-MLK-14F4 01/02/11

- 01/03/11

< 0.2 1460 +/- 73.1

< 1

< 5 SA-MLK-2G3 01/02/11

- 01/03/11

< 2.4 1370 +/- 73.6

< 1

< 4 SA-MLK-3G1 (C) 01/02/11

- 01/03/11

< 0.3 1340 +/- 77.3

< 1

< 4

< 2 SA-MLK-13E3 02/06/11

- 02/07/11

< 0.2 1390 +/- 73

< 1

< 3 SA-MLK-14F4 02/06/11 02/07/11

< 0.2 1400 +/- 72.6

< 1

< 3 SA-MLK-2G3 02/06/11

- 02/07/11

< 0.3 1410 +/- 76.9

< 1

< 2

< 3 SA-MLK-3G1 (C) 02/06/11

- 02/07/11

< 0.3 1270 +/- 70.3

< 1

< 4

< 4 SA-MLK-13E3 03/06/11

- 03/07/11

< 0.2 1340 +/- 68.6

< 1

< 2

< 4 SA-MLK-14F4 03/06/11

- 03/07/11

< 0.3 1490 +/- 76.6

< 1

< 3 SA-MLK-2G3 03/06/11 03/07/11

< 0.3 1360 +/- 71.9

< 1

< 2

< 3 SA-MLK-3G1 (C) 03/06/11

- 03/07/11

< 0.5 1260 +/- 77.5

< 3

< 2

< 3 SA-MLK-13E3 04/03/11

- 04/04/11

< 0.6 1440 +/- 156

< 7

<7

< 167 SA-MLK-14F4 04/03/11

- 04/04/11

< 0.8 1310 +/- 129

< 6

< 5

< 119 SA-MLK-2G3 04/03/11

- 04/04/11

< 1.0 1370 +/- 144

< 6

< 159 SA-MLK-3G1 (C) 04/03/11

- 04/04/11

< 1.0 1350 +/- 138

< 6

< 146 SA-MLK-13E3 04/17/11

- 04/18/11

< 0.6 1410 +/- 177

< 7

< 8

< 164 SA-MLK-14F4 04/17/11

- 04/18/11

< 0.5 1330 +/- 151

< 6

< 148 SA-MLK-2G3 04/17/11

- 04/18/11

< 0.5 1360 +/- 157

< 6

< 7

< 164 SA-MLK-3G1 (C) 04/17/11

- 04/18/11

<.0.7 1590 +/- 176

< 5

< 7

< 170 SA-MLK-13E3 05/01/11

- 05/02/11

< 0.8 1220 +/- 117

< 4

< 5

< 117 SA-MLK-14F4 05/01/11

- 05/02/11

< 0.9 1350 +/- 142

< 5

< 134 SA-MLK-2G3 05/01/11 05/02/11

< 0.8 1150 +/- 142

< 5

< 7

< 135 SA-MLK-3G1 (C) 05/01/11

- 05/02/11

< 0.6 1120 +/- 125

< 5

< 139 SA-MLK-13E3 05/15/11

- 05/16/11

< 0.9 1300 +/- 127

< 6.

< 6

< 149 SA-MLK-14F4 05/15/11

- 05/16/11

< 0.8 1430 +/- 166

< 7

< 8

< 189 SA-MLK-2G3 05/15/11

- 05/16/11

< 0.9 1200 +/- 142

< 5

< 6

< 114 SA-MLK-3G1 (C) 05/15/11

- 05/16/11

< 0.7 1310 +/- 134

< 5

< 6

< 130 SA-MLK-13E3 06/05/11

- 06/06/11

< 1.0 1300 +/- 164

< 8

< 9

< 188 SA-MLK-14F4 06/05/11

- 06/06/11

< 0.9 1430 +/- 160

< 6

< 7

< 169 SA-MLK-2G3 06/05/11

- 06/06/11

< 0.8 1400 +/- 206

< 7

< 8

< 207 SA-MLK-3G1 (C) 06/05/11

- 06/06/11

< 0.9 1320 +/- 160

< 9

< 191 SA-MLK-13E3 06/19/11

- 06/20/11

< 0.5 1460 +/- 198

< 9

< 8

< 207 SA-MLK-14F4 06/19/11

- 06/20/11

< 0.6 1370 +/- 201

< 7

< 8

< 190 SA-MLK-2G3 06/19/11

- 06/20/11

< 0.5 1270 +/- 149

< 5

< 7

< 183 SA-MLK-3G1 (C) 06/19/11

- 06/20/11

< 0.5 1180 +/- 146

< 6

< 152 SA-MLK-13E3 07/04/11

- 07/05/11

< 0.8 1350 +/- 153

< 5

< 6

< 131 SA-MLK-14F4 07/04/11

- 07/05/11

< 0.8 1370 +/- 181

< 9

< 226 SA-MLK-2G3 07/04/11

- 07/05/11

< 1.0 1420 +/- 180

< 8

< 7

< 144 SA-MLK-3G1 (C) 07/04/11

- 07/05/11

< 0.9 1380 +/- 169

< 7

< 8

< 189 IODINE-131 RESULTS ARE CORRECTED FOR DECAY TO STOP DATE OF COLLECTION PERIOD AND ANALYZED TO AN LLD (C) CONTROL STATION C-6 I

I I

U I

I I

I

TABLE C-5 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS IN MILK, 2011 RESULTS IN UNITS OF PCI/L +/-2 SIGMA SAMPLING PERIOD GAMMA EMITTERS ----------

STATION ID START STOP 1-131 K-40 Cs-134 Cs-137 Ra-226 SA-MLK-13E3 07/17/11

- 07/18/11

< 1.0 1360 + 185

< 7

< 9

< 156 SA-MLK-14F4 07/17/11

- 07/18/11

< 0.7 1490 +/- 162

< 7

< 170 SA-MLK-2G3 07/17/11

- 07/18/11

< 1.0 1340 + 147

< 7

< 162 SA-MLK-3G1 (C) 07/17/11

- 07/18/11

< 0.9 1350 + 242

< 8

< 10

< 204 SA-MLK-13E3 08/07/11

- 08/08/11

< 0.9 1390 + 185

< 7

< 8

< 160 SA-MLK-14F4 08/07/11

- 08/08/11

< 0.9 1290 +/- 141

< 6

< 7

< 146 SA-MLK-2G3 08/07/11

- 08/08/11

< 0.8 1470 +/- 133

< 5

< 6

< 137 SA-MLK-3G1 (C) 08/07/11

- 08/08/11

< 0.8 1220 + 124

< 5

< 110 SA-MLK-13E3 08/21/11

- 08/22/11

< 0.6 1180 + 180

< 6

< 7

< 185 SA-MLK-14F4 08/21/11

- 08/22/11

< 0.6 1290 +/- 151

< 6

< 7

< 162 SA-MLK-2G3 08/21/11

- 08/22/11

< 0.6 1310 +/- 183

< 7

< 6

< 159 SA-MLK-3G1 (C) 08/21/11

- 08/22/11

< 0.6 1360 +/- 205

< 6

< 8

< 177 SA-MLK-13E3 09/05/11

- 09/06/11

< 0.8 1320 +/- 194

< 6

< 7

< 173 SA-MLK-14F4 09/05/11

- 09/06/11

< 0.8 1440 +/- 158

< 6

< 7

< 168 SA-MLK-2G3 09/05/11

- 09/06/11

< 0.7 1540 +/- 168

< 7

< 158 SA-MLK-3G1 (C) 09/05/11

- 09/06/11

< 0.7 1400 +/- 140

< 6

< 154 SA-MLK-13E3 09/18/11

- 09/19/11

< 0.6 1160 +/- 150

< 6

< 7

< 129 SA-MLK-2G3 09/18/11

- 09/19/11

< 0.5 1440 +/- 120

< 4

< 5

< 105 SA-MLK-3G1 (C) 09/18/11

- 09/19/11

< 0.5 1240 +/- 139

< 5

< 6

< 153 SA-MLK-14F4 09/25/11

- 09/26/11

< 0.7 1270 +/- 155

< 6

< 8

< 153 SA-MLK-13E3 10/02/11

- 10/03/11

< 0.8 1210 +/-160

< 5

< 9,

< 167 SA-MLK-14F4 10/02/11

- 10/03/11

< 0.7 1330 +/- 167

< 7

< 178 SA-MLK-2G3 10/02/11

- 10/03/11

< 0.8 1330 +/- 148

< 6

< 141 SA-MLK-3G1 (C) 10/02/11

- 10/03/11

< 0.8 1100 +/- 159

< 8

< 7

< 192 SA-MLK-13E3 10/09/11

- 10/10/11

< 0.5 1250 +/- 162

< 7

< 9

< 205 SA-MLK-14F4 10/09/11

- 10/10/11

< 0.6 1140 +/-160

< 7

< 8

< 186 SA-MLK-2G3 10/09/11

- 10/10/11

< 0.5 1240 +/- 167

< 7

< 6

< 149 SA-MLK-3G1 (C) 10/09/11

- 10/10/11

< 0.6 1280 +/- 161

< 7

< 161 SA-MLK-13E3 11/06/11

- 11/07/11

< 0.7 1390 +/- 117

< 5

< 124 SA-MLK-14F4 11/06/11

- 11/07/11

< 0.8 1100 +/- 110

< 4

< 6

< 131 SA-MLK-2G3 11/06/11

- 11/07/11

< 0.7 1190 +/- 109

< 4

< 106 SA-MLK-3G1 (C) 11/06/11

- 11/07/11

< 0.7 1250 +/- 128

< 5

< 148 SA-MLK-13E3 11/20/11

- 11/21/11

< 0.9 1330 +/- 170

< 7

< 186 SA-MLK-14F4 11/20/11

- 11/21/11

< 0.7 1350 +/- 190

< 7

< 10

< 197 SA-MLK-2G3 11/20/11

- 11/21/11

< 0.7 1360 +/- 190

< 7

< 9

< 183 SA-MLK-3G1 (C) 11/20/11

- 11/21/11

< 0.8 1150 +/- 146

< 6

< 160 SA-MLK-13E3 12/04/11

- 12/05/11

< 0.7 1390 +/- 133

< 4

< 6

< 126 SA-MLK-14F4 12/04/11 12/05/11

< 0.9 1500 +/- 142

< 5

< 7

< 125 SA-MLK-2G3 12/04/11 12/05/11

< 1.0 1430 +/- 170

< 6

< 162 SA-MLK-3G1 (C) 12/04/11

- 12/05/11

< 0.7 1320 +/- 137

< 4

< 5

< 131 ANNUAL AVERAGE 1331 +/- 206

IODINE-131 RESULTS ARE CORRECTED FOR DECAY TO STOP DATE OF COLLECTION PERIOD AND ANALYZED TO AN LLD (C) CONTROL STATION C-7

TABLE C-6 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS AND TRITIUM IN WELL WATER*, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 SA-WWA-3E1 COLLECTION GR-A GR-B H-3 PERIOD iý 01/31/11 - 01/31/11

< 1.5 1.9 +/- 0.8

< 143 02/22/11 03/30/11 04/25/11 05/31/11 06/29/11 07/25/11 08/29/11 09/28/11 10/24/11 11/28/11 12/19/11 02/22/11 03/30/11 04/25/11 05/31/11 06/29/11 07/25/11 08/29/11 09/28/11 10/24/11 11/28/11 12/19/11

< 1.7

< 2.9

< 2.5

< 1.5

< 1.9

< 1.8

< 1.1

< 2.4

< 0.7

< 1.8

< 2.3 1.8 +/- 0.9

< 3.7

< 2.5

< 3.3

< 2.2

< 1.7

< 2.3

< 1.3

< 2.6

< 3.0

< 142

< 175

< 169

< 177

< 174

< 167

< 173

< 177

< 181

< 178

< 197 AVERAGE **

1.8 +/- 0.1 I

I I

I MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM

- THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-8 I

m-m m

mm-m-m m

m m

TABLE C-7 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER*, 2011 RESULTS IN UNITS OF PCI/L +/- 2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 1-131 Cs-134 Cs-1 37 BaLa-1 40 Ra-226 PERIOD SA-WWA-3E1 01/31/11

- 01/31/11 52 +/- 17 <1

<1

<3

<1

<2

<3

< 1

<1

<7 101 +/-4 SA-WWA-3E1 02/22/11

- 02/22/11 63 +/- 16 <1

< 1

<1

<2

<1

<4 173 +/- 7 SA-WWA-3Ei 03/30/11 -03/30/11

<14

<1

<2

<3

<1

<3

<2

<1

<2

<4

<43 SA-WWA-3E1 04/25/11

- 04/25/11

< 82

< 5

< 10

< 5

< 9

< 5

< 1

< 4

< 5

< 9

< 127 SA-WWA-3E1 05/31/11

- 05/31/11

< 34

< 4

< 10

< 4

<7

< 4

< 1

< 3

<4

< 13

< 83 SA-WWA-3E1 06/29/11

- 06/29/11

< 36

< 4

< 8

< 4

< 7

< 5

< 1

< 4

< 7

< 116 SA-WWA-3E1 07/25/11

- 07/25/11

< 70

< 4

< 9

< 4

< 9

< 5

< 1

< 4

< 7

< 110 SA-WWA-3E1 08/29/11

- 08/29/11

< 55

< 6

< 11

< 5.

< 8

< 5

< 1

< 4

< 5

< 7

< 124 SA-WWA-3E1 09/28/11

- 09/28/11

< 57

< 5

< 10

< 4

< 10

< 6

< 1

< 4

<5

<8

< 145 SA-WWA-3E1 10/24/11 - 10/24/11

< 105

< 6

< 7

< 14

< 8

< 12

< 8

< 1

< 7

< 12

< 189 SA-WWA-3E1 11/28/11 - 11/28/11

< 108

< 6

< 14

< 6

< 14

< 6

< 1

< 7

< 6

< 13

< 154 SA-WWA-3E1 12/19/11 - 12/19/11

<37

<3

<4

<8

<3

<8

<5

< 1

<4

<8

<84 AVERAGE **

57 _ 15 137 + 102 MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM

- THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES

TABLE C-8 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS AND TRITIUM IN RAW AND TREATED POTABLE WATER (2F3), 2011 RESULTS IN UNITS OF PCI/L +/- 2 SIGMA STC COLLECTION GR-A GR-B H-3 PERIOD RAW 01/01/11

- 01/31/11

< 0.8 6.6 +/- 0.8

< 144 02/01/11 02/28/11 03/01/11

- 03/31/11 04/01/11

- 04/30/11 05/01/11

- 05/31/11 06/01/11

- 06/30/11 07/01/11

- 07/31/11 08/01/11

- 08/31/11 09/01/11

- 09/30/11 10/01/11 10/31/11 11/01/111 11/30/111 12/01/11

-12/31/11 1.1 +/- 0.8

< 1.4

< 0.6

< 0.9

< 2.1

< 1.8

< 1.3 0.7 +/- 0.3

< 0.4

< 2.1

< 1.5 4.0 +/- 0.7

< 2.8 3.1 +/- 1.3 3.0 +/- 1.4 4.8 +/- 1.9 3.7 +/- 1.8

< 2.4 3.8 +/- 0.7 1.2 +/- 0.6

< 2.9

< 2.7

< 144

< 181

< 173

< 176

< 173

< 198

< 171

< 189

< 173

< 165

< 185 AVERAGE

0.9 +/- 0.6 3.8 +/- 3.1 TREATED 01/01/11 02/01/11 03/01/11 04/01/11 05/01/11 06/01/11 07/01/11 08/01/11 09/01/11 10/01/11 11/01/11 12/01/11 01/31/11 02/28/11 03/31/11 04/30/11 05/31/11 06/30/11 07/31/11 08/31/11 09/30/11 10/31/11 11/30/11 12/31/11

< 0.8

< 1.0

< 2.6

< 0.7

< 1.9

< 0.6

< 0.7

< 2.3

< 1.6 4.9 +/- 0.7 2.8 +/- 0.6

< 3.4 2.0 +/- 1.2 3.3 +/- 2.0 5.8 +/- 1.9 3.3 +/- 1.8

< 2.8 3.4 +/- 0.8 4.4 +/- 0.9

< 2.9

< 2.8

< 144

< 143

< 179

< 175

< 178

< 173

< 197

< 171

< 189

< 176

< 164

< 182 I

I I

AVERAGE

3.7 +/- 2.4

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-10

=

m m

mm m

=

m m

TABLE C-9 2011 CONCENTRATIONS OF IODINE-131* AND GAMMA EMITTERS IN RAW AND TREATED POTABLE WATER (2F3), 2011 RESULTS IN UNITS OF PCI/L +/- 2 SIGMA SAMPLING PERIOD GAMMA EMITTERS ----------

STATION ID START STOP 1-131 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 Cs-134 Cs-137 Ra-226 RAW 01/01/11 01/31/11

< 0.2 55 + 16

<1

<2

<1

<1 5 +/- 2 TREATED RAW TREATED RAW TREATED RAW TREATED RAW TREATED RAW TREATED RAW TREATED RAW TREATED RAW TREATED RAW TREATED RAW TREATED RAW TREATED 01/01/11 01/31/11 02/01/11 02/28/11 02/01/11 02/28/11 03/01/11 - 03/31/11 03/01/11 - 03/31/11 04/01/11 - 04/30/11 04/01/11 - 04/30/11 05/01/11 - 05/31/11 05/01/11 - 05/31/11 06/01/11 - 06/30/11 06/01/11 - 06/30/11 07/01/11 - 07/31/11 07/01/11 - 07/31/11 08/01/11 - 08/31/11 08/01/11 - 08/31/11 09/01/11 - 09/30/11 09/01/11 -09/30/11 10/01/11 - 10/31/11 10/01/11 - 10/31/11 11/01/11 - 11/30/11 11/01/11 - 11/30/11 12/01/11 - 12/31/11 12/01/11 - 12/31/11 AVERAGE **

<0.1

< 0.3

< 0.2

< 0.6

< 0.7

< 0.8

< 0.5

< 0.6

< 0.7

< 0.6

< 0.5

< 0.6

< 0.7

< 0.5

< 0.6

< 0.6 48+/- 12 47+/- 11 48+/- 15

< 30

<17

<18

< 43

<44

<7

< 136

< 52

< 72

< 56

< 113

< 97

< 168

<43

< 39

< 40

< 21

< 28

<6

< 37 49 +/-8

<1

<2

<4

<1

<5

<6

<5

<4

<5

<9

<5

<4

<2

<3

<1

<2

<1

<2

<1

<2

<5

<1

<5

<7

<5

<3

<5

<9

<6

<5

<4

<3

<1

<2

<1

<3

<4

<5

<9

<2

<13

<10

<8

<10

<11

<16

<12

<9

<8

<6

<1

<4

<3

<0

<1

<2

<4

<1

<7

<5

<6

<3

<4

<6

<8

<5

<4

<2

<1

< 2

<2

<1

<2

<3

<4

<7

<1

<10

<9

<8

<19

<10

<8

<5

<1

<3

<1

<3

<2

<4

<1

<9

<7

<5

<6

<9

<8

<5

<3

<1

<2

<1

<2

<3

<1

<7

<4

<5

<4

<5

<9

<5

<3

<1

<2

<1

<2

<4

<1

<8

<6

<4

<5

<9

<6

<5

<4

<3

<1

<2

<2 5+/-2

<2

< 43

<44

< 45

< 43

< 85

<18

< 163

< 162

< 116

< 93

<114

< 124

< 245

< 161

< 104

< 110

< 65

< 82

<15

< 40 5+/-0 IODINE-131 RESULTS ARE CORRECTED FOR DECAY TO STOP DATE OF COLLECTION PERIOD AND ANALYZED TO AN LLD OF 1.0 pCi/L.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES

TABLE C-10 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETABLES*, 2011 Results in Units of pCi/kg (wet) +/- 2 sigma STC COLLECTION SAMPLE Be-7 K-40 1-131 Cs-134 Cs-137 Ra-226 Th-232 PERIOD TYPE SA-FPV-2F9 04/24/11 Asparagus

< 63 2270 + 134

< 41

< 6

< 7

< 128

< 26 AVERAGE SA-FPV-2F9 SA-FPV-2F9 SA-FPV-2F9 05/01/11 05/01/11 05/01/11 Asparagus Asparagus Asparagus

< 52

< 55

< 54 2270 +/- 0 2390 +/- 111 2750 +/- 121 2780 +/- 124 2640 +/- 434

< 20

< 22

< 35

<5

<6

<5

< 110

< 123

< 106

<18

< 20 AVERAGE SA-FPL-3H5 (C)

SA-FPV-3H5 (C)

_SA-FPL-3F6 (C)

SA-FPV-2G2 (C)

SA-FPV-2F9 SA-FPV-2F9 SA-FPV-15F4 SA-FPV-15F4 SA-FPV-15F4 SA-FPV-3F6 (C)

SA-FPV-3F6 (C)

SA-FPV-9G2 (C)

SA-FPV-9G2 (C) 06/29/11 Cabbage

< 107 06/29/11 Tomatoes

< 38 2330 +/- 382

< 42 1950 +/- 106

< 12 AVERAGE 07/05/11 07/05/11 07/05/11 07/05/11 07/11/11 07/11/11 07/21/11 07/21/11 07/21/11 07/21/11 07/21/11 07/21/11 07/21/11 AVERAGE

t Cabbage Corn Peppers Tomatoes Corn Tomatoes Corn Tomatoes Peppers Corn Tomatoes Corn Tomato

< 262

< 106

< 212

< 165

< 135

< 130

< 119

< 121

<44

< 101

< 189

< 124

< 140 2140 +/- 537 2450 +/- 534 2110 +/- 275 1950 +/- 411 3260 +/- 391 2290 +/- 380 1360 +/- 250 2340 +/- 282 2030 +/- 276 1700 +/- 260 1800 +/- 279 2070 +/- 355 1960 +/- 256 1570 +/- 270 2068 +/- 944

< 57

< 23

< 45

< 39

< 27

<-30

< 38

< 43

<16

< 37

< 57

< 38

< 47

<9

<4

< 25

<12

<18

<19

<16

<10

<13

<5

<13

<18

<10

<16

<4

< 25

<11

< 22

< 17

< 20

<16

<14

<13

<6

<12

< 22

<11

<17

< 322

< 100

< 685

< 347

< 523

< 525

< 412

< 335

< 280

< 344

< 124

< 313

< 527

< 267

< 391

< 48

<16

< 115

< 54

< 94

< 78

< 68

< 62

< 40

< 59

< 31

< 59

< 85

< 50

< 54 MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM

- THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (C) CONTROL STATION m

-M M

m m

m M

M m

m m

M M

=

m m =

m m

m m M mM -

m m =

m =

m TABLE C-10 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETABLES*, 2011 Results in Units of pCi/kg (wet) +/- 2 sigma STC COLLECTION SAMPLE Be-7 K-40 1-131 Cs-1 34 Cs-137 Ra-226 Th-232 PERIOD TYPE SA-FPV-1G1 (C)

SA-FPV-1G1 (C)

SA-FPL-10Di SA-FPL-15S1 SA-FPL-16S1 SA-FPL-1F1 SA-VGT-14F4 CSA-VGT-1 F1 W_*SA-VGT-3G1 (C) 08/01/11 08/01/11 08/01/11 AVERAGE 10/05/11 10/05/11 10/05/11 10/05/11 Corn Tomatoes Peppers Cabbage Cabbage Cabbage Cabbage soy beans soy beans soy beans

< 68

< 124 1890 +/- 189 1330 +/- 157 2740 +/- 301 1987 +/- 1420

<16

<12

< 24 364 +/- 111

< 195

< 215 283 +/- 86 324 +/- 115

< 289

< 240

< 204 4010 4430 3230 3980

+/- 328

+/- 507

+/- 439

+/- 324

< 21

< 22

< 29

< 19

< 52

< 43

< 59

<8

<7

<12

<15

<16

<12

< 28

< 21

< 20

<8

<13

<16

< 23

<18

<17

< 31

< 26

< 28

< 179

< 161

< 296

< 331

< 356

<.432

< 275

< 589

< 478

< 494

< 35

< 52

< 80

< 71

< 53

< 124

< 130

< 113 AVERAGE 3913 +/- 998 11/06/11 11/07/1,1 11/18/11 13300 15000 16400

+/- 1150

+/- 1020

+/- 1030 AVERAGE 14900 +/- 3105 3713 +/- 7925 GRAND AVERAGE **

MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM

- THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (C) CONTROL STATION

TABLE C-1 1 CONCENTRATIONS OF GAMMA EMITTERS IN FODDER CROPS*, 2011 RESULTS IN UNITS OF PCI/KG (WET)

2 SIGMA STATION ID SAMPLING SAMPLE TYPE Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Ra-226 Th-232 DATE SA-VGT-13E3 09/13/11 Silage 248 t 148 3670 +/- 326

< 34

<11

< 13

< 283

< 52 SA-VGT-14F4 09/16/11 SA-VGT-2G3 09/16/11 SA-VGT-3G1 (C) 09/16/11 Silage Silage Silage 1900 +/- 171 3150 +/- 268 1500 +/- 204 1700 +/- 2392 3230 +/- 267 10900 +/- 573 3970 +/- 419 5443 +/- 7302

< 27

< 41

< 30

<11

<19

<15

<11

< 20

<15

< 281

< 429

< 341

<44

< 78

< 63 AVERAGE

MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM (C) CONTROL STATION M1 m

m mmm

-mmm MIMI mm MIMI

TABLE C-12 CONCENTRATIONS OF GAMMA EMITTERS IN SOIL, 2011 Results in Units of pCi/kg (dry)

2 sigma Soil samples are collected every 3 years. Soil will be collected in 2013 C-15

TABLE C-13 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER, 2011 RESULTS IN UNITS OF PCI/L +2 SIGMA COLLECTION CONTROL PERIOD SA-SWA-1iAl SA-SWA-12C1 SA-SWA-16F1 SA-SWA-1F2 SA-SWA-7E1 01/03/11 02/04/11 03/08/11 04/07/11 05/06/11 06/06/11 07/05/11 08/01/11 09/06/11 10/05/11 11/09/11 12/06/11 01/03/11 02/04/11 03/08/11 04/07/11 05/06/11 06/06/11 07/05/11 08/01/11 09/06/11 10/05/11 11/09/11 12/06/11 198 + 23 169 +/-24 18+/- 5 19 3

9+/-3 49 +/- 13 100 +/- 24 160 + 14 10 +3 5+/-1 39 +/-11 58 +/-14 70 + 140 190 +/- 23 158 +/- 23 9+/-3 30 +/-9 4+/-2 37 +/-8 113 +/- 20 77 +/-8 7+/-3 4+/-1 61 +/-9 35 +6 60 +/- 126 111 +/- 16 140 +/- 21

<4 20 +/- 4 4+/-2 15 +/-7 78 +/-12 73 +8 7+/-3 3+/-1 25 +/-3 17+/- 4 45 +/- 96 84 +/- 14 89 +/- 17

<3 19 +/- 4

<3 24 +/- 7 52 +/- 9 10 +/- 4 9+/-3

<2 22 +/-3 7+/-3 35 +/- 65 305 +/- 27 290 +/- 30 30 +/- 6 21 +/- 13 26 +/- 11 111 +/- 24 155 +/- 32 190 +/- 14 8+/-3 27 +/-3 110 +/-17 71

+/-15 112 +/-208 AVERAGE

GRAND AVERAGE

66 +/- 144 I

I I

I U

I I

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-16

TABLE C-14 CONCENTRATIONS OF TRITIUM IN SURFACE WATER, 2011 RESULTS IN UNITS OF PCI/L +/- 2 SIGMA COLLECTION CONTROL PERIOD SA-SWA-11AI SA-SWA-12C1 SA-SWA-16F1 SA-SWA-1F2 SA-SWA-7E1 01/03/11 - 01/03/11

< 140

< 141

< 140

< 142 02/04/11

- 02/04/11 03/08/11

- 03/08/11 04/07/11

- 04/07/11 05/06/11

- 05/06/11 06/06/11

- 06/06/11 07/05/11

- 07/05/11 08/01/11

- 08/10/11 09/06/11 09/06/11 10/05/11

- 10/05/11 11/09/11

- 11/09/11 12/06/11

- 12/06/11

< 142

< 173

< 186

< 178

< 165

< 174

< 162

< 174

< 192

< 166

< 199

< 143

< 146

< 187

< 180

< 169

< 174

< 200

< 177

< 182

< 167

< 195

< 144

< 150

< 187

< 180

< 166

< 172

< 161

< 176

183

< 166

< 200

< 142

< 149

< 190

< 180

< 187

<170

< 167

< 177

< 183

< 164

199

< 144

< 149

< 190

< 181

< 194

< 173

< 200

< 190

< 181

< 167

< 197 AVERAGE C-17

TABLE C-15 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER, 2011 RESULTS IN UNITS OF PCI/L +/- 2 SIGMA STC COLLECTION K-40 Mn-54 0o-58 Fe-59 Co-60 Zn-65 ZrNb-95 1-131*

Cs-134 Cs-1 37 BaLa-1 40 PERIOD SA-SWA-1lAl 01/03/11 130 +/- 20

<1

<0.3

<1

<3

<2

<1

<3

<5 02/04/11 03/08/11 04/07/11 05/06/11 06/06/11 07/05/11 08/01/11 09/06/11 10/05/11 11/09/11 12/06/11 165 +/- 20

< 22

< 42

<17

< 42 55 +/- 34

< 101

< 109

<44 50 +/- 27

<44

<1

<3

<5

<2

<6

<3

<5

<6

<2

<5

<1

<3

<4

<2

<5

<3

<5

<6

<2

<6

<2

<6

<12

<5

<14

<6

<11

<14

<4

<11

<1

<2

<4

<2

<5

<2

<4

<6

<2

<5

<1

<5

<9

<4

<15

<4

<9

<10

<12

<3

<12

<2

<3

<5

<2

<6

<3

<5

<6

<8

<2

<6 AVERAGE

- 100 +/- 113

<1

<2

<4

<2

<7

<3

<5

<6

<2

<5

<1

<3

<5

<2

<7

<3

<4

<5

<6

<2

<5

<1

<3

<5

<2

<5

<2

<5

<8

<5

<2

<5

<6

<11

<7

<11

<6

<8

<14

<12

<4

<11

<5

<7

<15

<8

<11

<6

<10

<14

<11

<4 00 SA-SWA-12C1 (C) 01/03/11 02/04/11 03/08/11 04/07/11 05/06/11 06/06/11 07/05/1 1-08/01/11 09/06/11 10/05/11 11/09/11 12/06/11 80 +/- 20 83 +/- 18

< 56

< 40

< 22

< 112

< 21

<44

<73

< 96

< 31

< 135

<1

<3

<5

<2

<5

<2

<6

<2

<1

<3

<5

<2

<6

<2

<6

<8

<6

<2

<3

<1

<6

<9

<5

<13

<6

<11

<17

<11

<4

<1

<3

<4

<2

<5

<2

<6

<2

<5

<9

<4

<9

<4

<12

<13

<4

<1

<2

<3

<6

<2

<6

<3

<6

<9

<6

-<.2

<1

<3 1+/-1

<4

<2

<5

<2

<6

<7

<6

<2

<6

<18

<7

<10

<7

<1

<6

<15 AVERAGE 82 +/- 4 1+/-0 IODINE-131 RESULTS ARE CORRECTED FOR DECAY TO STOP DATE OF COLLECTION PERIOD AND ANALYZED TO AN LLD OF 1.0 pCi/L.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES IODINE-131 IS ATTRIBUTED TO EFFLUENT FROM A MEDICAL FACILITY.

(C) CONTROL STATION m

m m

m

-n m

m am m

m

m mmmminm m

mmmmmmm mimmm TABLE C-15 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER, 2011 RESULTS IN UNITS OF PCI/L +/-2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 1-131*

Cs-134 Cs-137 BaLa-140 PERIOD SA-SWA-16F1 01/03/11 95 +/- 18

< 1

< 3

< 0.4

< 2

< 1

< 2

< 1

< 0.4

< 7 02/04/11 03/08/11 04/07/11 05/06/11 06/06/11 07/05/11 08/01/11 09/06/11 10/05/11 11/09/11 12/06/11 105 +/- 17

< 29

< 45

<14

< 61

< 23

< 52

< 63

< 31

< 33

< 106

<1

<3

<4

<1

<7

<3

<4

<5

<2

<4

<6

<1

<4

<5

<1

<7

.<3

<4

<7

<2

<4

<6

<1

<8

<13

<2

<12

<6

<8

<12

<3

<8

<11

< 0.4

<3

<5

<1

<7

<3

<4

<7

<2

<3

<5

<1

<.7

<10

<1

<11

<5

<8

<10

<3

<9

<12

<1

<5

<1

<5

<3

<5

<6

<2

<4

<5

<1

,*)

AVERAGE 100 +/- 14

<1

<3

<4

<1

<5

<3

<4

<6

<2

<4

<6

<1

<3

<4

<2

<6

<3

<4

<6

<2

<4

<7

< 0.3

<4

<6

<1

<7

<3

<5

<6

<2

<4

<5

< 0.5

<1

<4

<2

<6

<3

<5

<6

<2

<4

<7

<3

.< 10

<11

<4

<11

<6

<7

< 14

<3

<11

<14

<5

<3

<8

< 14

<7

<12

<7

<8

<15

<4

<9

<8 SA-SWA-1 F2 01/03/11 02/04/11 03/08/11 04/07/11 05/06/11 06/06/11 07/05/11 08/22/11 09/06/11 10/05/11 11/09/11 12/06/11 78 +/- 18 123 +/- 20

< 86

< 37

<16

< 53

< 55

< 86

< 102

< 32 99 +/- 49

< 94

<1

<4

<2

<5

<3

<5

<7

<2

<5

<7

<1

<4

<5

<2

<6

<3

<4

<6

<2

<5

<7

<2

<10

<11

<5

<11

<7

<10

<14

<4

<11

< 17

<1

<2

<4

<2

<5

<3

<5

<2

<6

<7

<4

<1

<8

<4

<10

<6

<9

<13

<4

<9

<11

<2

<5

<2

<7

<3

<5

<7

<2

<6

<8

<2

<1

< 0.5

<1

<1 AVERAGE 100 +/- 45

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

TABLE C-15 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER, 2011 RESULTS IN UNITS OF PCI/L +/-2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 1-131*

Cs-134 Cs-1 37 BaLa-140 PERIOD SA-SWA-7E1 01/03/11 119 +/-22

< 1

<1

<2

<1

<2

<1

< 1

<2

<3 02/04/11 03/08/11 04/07/11 05/06/11 06/06/11 07/05/11 08/01/11 09/06/11 10/05/11 11/09/11 12/06/11 175 +/- 22

< 37

< 44

<19

< 69 129

+/- 39

< 52

< 62

<17

< 44 101 +/-66

<1

<4

<5

<2

<7

<3

<5

<4

<2

<6

<5

<1

<4

<5

<2

<7

<3

<5

<2

<5

<7

<1

<9

<11

<6

<15

<6

<10

<9

<4

<10

<14

<1

<4

<3

<2

<5

<3

<4

<2

<4

<6

<2

<8

<10

<4

<11

<5

<8

<9

<4

<9

<1

<5

<6

<2

<8

<3

<6

<5

<2

<6

<8

<1

<4

<5

<2

<6

<2

<4

<2

<5

<1

<4

<5

< 2

<7

<3

<5

<4

<2

<5

< 10

< 15

<9

<15

<6

<11

<4

<13

<11 AVERAGE

131 +/-63

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES m

m m

=m mmm

=m

==m mimmm==mm==m TABLE C-16 CONCENTRATIONS OF GAMMA EMITTERS IN EDIBLE FISH, 2011 RESULTS IN UNITS OF PCI/KG (WET) +/- 2 SIGMA STC SA-ESF-11 Al SA-ESF-12C1 (C)

SA-ESF-2G3 COLLECTION PERIOD 05/06/11 10/24/11 AVERAGE 05/06/11 10/24/11 AVERAGE 05/06/11 AVERAGE K-40 4090 +/- 970 3700 +/- 898 3895 +/- 552 3050 +/- 908 3950 +/- 915 3500 +/- 1273 4660 +/- 957 4660 +/- 0 Mn-54

< 65

< 61

< 64

< 48

< 57 Co-58

< 76

< 59

< 77

< 69

< 71 Fe-59

< 192

< 142

< 197

< 168

< 166 Co-60

< 60

< 58

< 46

< 57

< 68 Zn-65

<.141

< 90

< 131

< 132

< 115 Cs-1 34

< 75

< 50

< 69

< 45

< 46 Cs-137

< 59

< 54

< 57

< 53 Ra-226

< 1450

< 1140

< 1100

< 1010

< 1210 (C) CONTROL STATION

TABLE C-17 CONCENTRATIONS OF GAMMA EMITTERS IN CRABS, 2011 RESULTS IN UNITS OF PCI/KG (WET) +/- 2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 PERIOD SA-ECH-1lAl 06/27/11 2910 +/- 687

< 39

< 49

< 140

< 33

< 95

< 41

< 887 08/22/11 2320 +/- 829

< 61

< 67

< 95

< 65

< 152

< 66

< 73

< 1470 AVERAGE 2615 +/- 834 2630 +/- 519

< 32 2390 +/- 900

< 58 2510 +/- 339 SA-ECH-12C1 (C) 06/27/11 08/22/11 AVERAGE

< 37

<64

< 92

< 158

< 34

< 64

< 32

< 37

< 805

< 53

< 106

< 47

< 52

< 985 n-)

(C) CONTROL STATION mmmmmmmm mmm mmmmmminmm mm

=m

=m m

mm==m=mmmi=mm

=

TABLE C-18 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT RESULTS IN UNITS OF PCI/KG (DRY) +/- 2 SIGMA, 2011 n'

STC COLLECTION Be-7 K-40 Cs-134 PERIOD SA-ESS-11A1 06/23/11

< 916 9890 +/- 1650

< 71 11/21/11

< 404 5490 +/- 826

< 35 AVERAGE 7690 +/- 6223 SA-ESS-12C1 (C) 06/23/11

< 690 17100 +/- 1820.0

< 70 11/21/11

< 637 13500 +/- 1400.0

< 54 AVERAGE 15300 +/- 5091.2 SA-ESS-15Al 06/23/11

< 575 3560 +/- 682.0

< 40 11/21/11

< 403 6370 +/- 806.0

< 38 AVERAGE 4965 +/- 3973.9 SA-ESS-16A1 06/23/11

< 526 6280 +/- 1000.0

< 50 11/21/11

< 381 5320 +/- 672.0

< 29 AVERAGE 5800 +/- 1357.6 SA-ESS-16F1 06/23/11

< 1680 22800 +/- 3100.0

< 135 11/21/11

< 554 16100 +/- 1340.0

< 49 AVERAGE 19450 +/- 9475.2 SA-ESS-6S2 06/27/11

< 342 3670 +/- 653.0

< 37 11/28/11

< 205 4140 :t 432.0

< 19 AVERAGE 3905 - 664.7 SA-ESS-7E1 06/23/11

< 569 14100 +/- 1180.0

< 46 11/21/11 1510 +/- 852 20400 1890.0

< 73 AVERAGE 1510 +/- 0 17250 - 8909.5 GRAND AVERAGE

1510

+/- 0 10623 +/- 13926

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (C) CONTROL STATION Cs-137 82 54 Ra-226

< 2050

< 775 78 69 57 46 57 30 2740 +/- 1720 2420 +/- 1390 2580 +/- 453

< 1210 1350 +/- 820 1350 +/- 0

< 1390 2600 +/- 836 2600 +/- 0

< 3870 1570 +/- 965 1570 +/- 0

< 1030

< 428 Th-232 635 +/- 252 484 +/- 144 560 +/- 214 1070 +/- 247 1370 +/- 258 1220 +/- 424 346 +/- 157 492 +/- 126 419 +/- 206 606 +/- 199 1020 +/- 164 813 +/- 585 919 +/- 427 1090 +/- 187 1005 +/- 242 278 +/- 136 175 +/- 63 227 - 146 950 +/- 189 1370 +/- 339 1160 +/-594 772 - 752 171 60 40 21 54 107 +/- 71 107 +/-0 107 +/-0 2230 +/- 1370 3850 +/- 1510 3040 +/- 2291 2394 +/- 1649

FIGURE 1 GROSS BETA ACTIVITY IN AIR PARTICULATE 1990 THROUGH 2011 1000.0 GROSS BETA IN AIR PARTICULATE (1) (2)(3)(4) (5) 1973 THROUGH 2011 1000-100-A 10 100.0 1-1976 1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 2012 0

10.0 1-Weapons Test 1974 2-Weapons Test 1976 3-Weapons Test 1977 4-Weapons Test 1978 5-Weapons Test 1980 6-Chernobyl1986 I QUARTERLY AVERAGEI m

mm=

m =

m m

m

=

mm mm m

m m

m

m m

m-m m

FIGURE 2 AMBIENT RADIATION - OFFSITE vs CONTROL STATION 1990 THROUGH 2011 10.0 8.0 0E E.0 2.0 0.0 1-Weapons Test 1974 2-Weapons Test 1976 3-Weapons Test 1977 4-Weapons Test 1978 5-Weapons Test 1980 6-Chernobyl 1986 QUARTERLY AVERAGEI

FIGURE 3 IODINE - 131 ACTIVITY IN MILK 1990 THROUGH 2011 20 10 I0 0.

IODINE-131 ACTIVITY IN MILK IODINE-131 ACTIVITY IN MILK (1) (2) (3) (4) (5) 1973 THROUGH2011 11 1

(6)1 15.00 10.00 5.00 0.00

-5.00

-10.00 -

0

-10 pI I I sII I

I 2-ep n

sI I

1976 I

t111InseI I

I I

I I-h l

8I T

I 1 -Weapons Test 1974 2-Weapons Test 1976 3-Weapons Test 1977 4-Wespons Test 1978 5-Weapons Test 1980 6-Chernobyl 1986 1 n"ARTFRI V AV;FRAflI.

m m

m mm nm m

m m

m

m m--m m

mm m

mmmnm mm m

mm FIGURE 4 GROSS BETA ACTIVITY IN SURFACE WATER 1990 THROUGH 2011 10000 GROSS BETA ACTIVITY IN SURFACE WATER (1)(2)(3)(4) (5) 1973 THROUGH 2011 (6),

100 1000 vi 10 t 3100 10 1-Weapons Test 1974 2-Weapons Test 1976 3-Weapons Test 1977 4-Weapons Test 1978 5-Weapons Test 1980 6-Chernobyl 1986 QUARTERLY AVERAGE I

I

FIGURE 5 TRITIUM ACTIVITY IN SURFACE WATER 1990 THROUGH 2011 10000.00 1000.00 CL 00.

00 100.00 1 0.0 0 i

I I I I I I

I I

ý.

I I

ý I

ý I I

] I I

I I

I I I I

I I

t I

I I

I f

I I

1-Weapons TeOt 1974 2-Weapons Teot 1976 3-Weapons Test 1977 4-Weapons Test 1978 5-Weapons Test 1980 6-Chernobyl QUARTERLY AVERAGE 1986 m

m m

mmn m

m m

m

m m

=------

m m

=

m m

FIGURE 6 CESIUM-137 & COBALT-60 ACTIVITY IN AQUATIC SEDIMENT 1990 THROUGH 2011 10000 1000 100 10 cgp "jq g

ce cpb lb pro C

Ndlq NZ fý,

N K

K Nq f

co ef 1 -Weapons Test 1974 2-Weapons Test 1976 3-Weapons Test 1977 4-Weapons Test 1978 5-Weapons Test 1980 6-Chemobyl 1986 I SEMI-ANNUAL AVERAGE

FIGURE 7 CESIUM -137 ACTIVITY IN SOIL 1974 THROUGH 2010 (TRIENNIAL) 800.0 700.0 600.0 500.0 0

Weapons Test Weapons Test 1974 1978 Weapons Test 1976 Weapons Test 1977 Weapons Test 400.0 0I.

300.0 200.0 100.0 0.0 1974 1977 1980 1983 1986 1989 1992 1995 1998 2001 2004 2007 2010 Sm mm m

m m

=

m

=

m m

APPENDIX D

SUMMARY

OF RESULTS FROM ANALYTICS, ENVIRONMENTAL RESOURCE ASSOCIATES (ERA),

AND DEPARTMENT OF ENERGY (DOE) - MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

I I

.1!

I Intentionally left blank I

I I

I

TABLE D-1 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM MAPLEWOOD TESTING SERVICES, 2011 (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media

' Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)

January 2011 AB767 H769 Water Gr-A Gr-B Water H-3 pCi/L 78.0,

62.5 32.7 - 77.5\\

pCi/L 48.0 51.9 31.3 - 48.8 pCi/L 3523 3460 2930 - 3820 N (1)

A A

G768 Water Ba-1 33 pCi/L 52.9 52.3 43.1 - 57.9 Co-60 pCi/L 74.1 68.9 62.0 - 78.2 Cs-134 pCi/L 56 56.2 45.4-61.8 Cs-137 pCi/L 105.0 100.0 90.0- 112 Zn-65 pCi/L 165 153.0 138 - 180 (1) The detector was out of calibration on the high side (conservative). Associated samples were all non-detects.

(2) Sr-89 TBE to known ratio of 1.16 fell within acceptable range of1+/-20%. No action required. NCR 11-16 (a) Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.

A A

A D-1

TABLE D-2 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2011 E7460-396 E7461-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 98.8 97.4 pCi/L 15.2 15.8 1.01 0.96 A

A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 92.9 96.9 0.96 A

! not provided by Analytics for this study 398 298 1.34 N (1) 130 232 121 289 201 287 1861' 130 205 113 266 175 261 172 1.00 1.13 1.07 1.09 1.15 1.10 1.08 A

A A

June 2011 E7463-396 E7462-396 E7851-396 E7852-396 E7854-396 E7853-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi pCi pCi pCi pCi pCi pCi pCi pCi 243 85.0 168 89.2 171 129 159 132 215 94.2 148 81.8 192 126 189 124 pCi 96.5 96.3 pCi/L 96.7 103 pCi/L 13.8 15.6 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 not provided by Analytics for this study pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 110 68.1 186 164 140 141 136 128 263 189 49.9 95.6 104 83.8 90.7 74.5 62.0 140 119 103.0 79.9 206 190 138 152 138 123 261 195 42.9 110 102 74.0 81.3 73.9 66.1 140 104 1.13 0.90 1.14 1.09 0.89 1.02 0.84 1.06 1.00 0.94 0.88 1.07 0.85 0.90 0.86 1.01 0.93 0.99 1.04 1.01 0.97 1.16 0.87 1.02 1.13 1.12:

1.01 0.94 1.00 1.14 0.89 A

A A

I I

I AP Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi 76.2 86.1 D-2

TABLE D-2 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

September 2011 E8070-396 E8071-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 102 90.8 pCi/L 13.2 14.7 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 74.2 66.9 249 116 106 95.4 147 53.1 175 150 66.6 263 139 110 108 152 57.5 190 156 89.2 66.7 226 128 114 97.5 151 54.8 180 157 67.5 229 130 115 98.6 153 55.5 183 159 1.12 0.90 0.83 1.00 1.10 0.91 0.93 0.98 0.97 0.97 0.97 0.96 A

A A

A E8073-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi pCi pCi pCi pCi pCi pCi pCi pCi 0.99 1.15 1.07 0.96 1.10 0.99 1.04 1.04 0.98 0.96 E8072-396 pCi 77.6 80.6 pCi/L 93.3 93.1 pCi/L 12.7 15.4 December, 2011 E8230-396 E8231-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 82.5 90.2 not provided by 465 566 142 171 185 210 177 221 208 241 164 183 259 291 224 270 1.00 0.82 0.91 Analytics for 0.82 0.83 0.88 0.80 0.86 0.90 0.89 0.83 A

A A

this study A

A A

A E8233-396 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi not provided by Analytics for this study 344 368 0.93 A

105 111 0.95 A

129 137 0.94 A

145 144 1.01 A

137 157 0.87 A

119 119 1.00 A

145 190 0.76 W

168 176 0.95 A

D-3

TABLE D-2 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2011 E8232-396 Charcoal 1-131 pCi 100 89.5 1.12 A

I I

i I

I I

U I

I I

I i

(1)

(a)

(b)

(c)

(d)

Sample appears to be biased high. Corrective Action evaluated after the 2nd Quarter Analytics PE sample; no action required. NCR 11-13 Teledyne Brown Engineering reported result.

The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

Ratio of Teledyne Brown Engineering to Analytics results.

Analytics evaluation based on TBE internal OC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.

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TABLE D-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a)

Value (b)

Control Limits Evaluation (c)

May 2011 RAD-85 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3

.MRAD-i4 Filter Gr-A pCi/L 59.8 pCi/L 42.5 pCi/L 73.3 pCi/L 64.9 pCi/L 74.6 pCi/L 87.8 pCi/L 103 pCi/L 64.1 pCi/L 51.8 pCi/L 27.4 pCi/L 38.5 pCi/L 10057 pCi/filter 79.7 pCi/L 81.0 pCi/L 35.5 pCi/L 90.7 pCi/L 36.6 pCi/L 44.7 pCi/L 118.7 pCi/L 80.2 pCi/L.

34.2 pCi/L 39.3 pCi/L 22.9 pCi/L 46.8 pCi/L 15733 pCi/filter 44.6 63:2 42.5 75.3 72.9 77.0 88.8 98.9 50.1 49.8 27.5 39.8 10200 51.1 -71.2 31.3-48.8 63.0 - 82.8 59.5 - 80.2 69.3 - 87.4 79.9-100 89.0- 118 26.1 - 62.9 33.8 - 56.9 22.9 - 32.3 32.2 - 44.4 8870-11200 A

A A

N (1)

A A

AA 74.3 38.5-112 A

November 2011 RAD-87 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A 69.7 41.4 96.9 33.4 44.3 119 76.8 53.2 45.9 27.5 48.6 17400 56.9 - 77.9 30.2 - 47.2 81.8-106 26.3 - 36.7 39.4-51.7 107-133 68.9 - 92.5 27.8 - 66.6 30.9 - 53.1 22.9 - 32.3 39.4 - 54.0 15200- 19100 N (2)

A A

A MRAD-1 5 58.4 30.3 - 87.8 A

(1) The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve. NCR 11-08 (2) Sr-89 TBE to known ratio of 1.16 fell within acceptable range of + 20%. No action required. NCR 11-16 (a) Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.

D-5

TABLE D-4 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

IRange Evaluation (c)

March 2011 11 -MaW24 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B' 11-GrW24 11-MaS24 11-RdF24 Soil Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 11 -GrF24 11-RdV24 September 2011 11-MaW25 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Bq/L 19.1 21.5 Bq/L 29.0 29.4 Bq/L 0.139 Bq/L 23.9 24.6 Bq/L 265 243 Bq/L 31.8 31.6 Bq/L 94.8 91 Bq/L 9.64 8.72 Bq/L

-0.142 Bq/L 0.767 1.136 Bq/L 3.43 2.96 Bq/kg 612 680 Bq/kg 772 758 Bq/kg 910 927 Bq/kg 500 482 Bq/kg 0.607 Bq/kg 569 540 Bq/kg NR 160 Bq/kg 1497 1359 Bq/sample 3.26 3.49 Bq/sample 2.36 2.28 Bq/sample 3.30 3.33 Bq/sample 0.0765 Bq/sample 2.84 2.64 Bq/sample

'NR 1.36 Bq/sample 3.30 3.18 Bq/sample 0.101 0.659 Bq/sample 1.23 1.323 Bq/sample 4.97 5.50 Bq/sample 0.0356 Bq/sample 10.8 9.94 Bq/sample 4.89 4.91 Bq/sample 6.42 6.40 Bq/sample NR 2.46 Bq/sample 3.07 2.99 Bq/L 16.0 19.1 Bq/L 0.0043 Bq/L 33.1 36.6 Bq/L 26.9 29.3 Bq/L 1011 1014 Bq/L 23.2 25.0 Bq/L 147 156 Bq/L 15.8 14.2 Bq/L 27.3 28.5 15.1 -28.0 20.6 - 38.2 (1) 17.2-32.0 170-316 22.1 -41.1 64-118 6.10 - 11.34 (1) 0.341 - 1.931 1.48-4.44 476 - 884 531 - 985 649-1205 337 - 627 (1),

378 - 702 112-208 951 - 1767 2.44 - 4.54 1.60-2.96 2.33 - 4.33 (1) 1.85-3.43 0.95-1.77 2.23-4.13 0.198 - 1.120 0.662 - 1.985 3.85-7.15 (1) 6.96-12.92 3.44 - 6.38 4.48 - 8.32 1.72-3.20 2.09 - 3.89 13.4 - 24.8 (1) 25.6 - 47.6 20.5 - 38.1 710- 1318 17.5 - 32.5 109-203 9.9-18.5 20.0 - 37.1 A

A A

A N (2)

A A

N (2)

A N (3)

A A

N (2)

A A

I U

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I U

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I U

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I A

A A

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TABLE D-4 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

September 2011 11-GrW25 11-MaS25 September 2011 11-RdF25 Water Gr-A Gr-B Bq/L 0.894 0.866 0.260 - 1.472 Bq/L 5.87 4.81 2.41 - 7.22 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample

-0.213 1110 1290 731 987 753 276 1870

-0.043 3.09 5.36 3.41 0.067 1.84 5.17 979 1180 644 848 625 320 1560 (1) 685-1273 826-1534 451 -837 594-1102 438-813 224-416 1092-2028 11-GrF25 11-RdV25 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 (1) 2.60 1.82 - 3.38 5.09 3.56 - 6.62 3.20 2.24 - 4.16 (1) 1.67 1.17-2.17 4.11 2.88 - 5.34 A

A A

W A

A A

A W

A A

A Bq/sample 0.0058 Bq/sample

-0.01 (1)

(1)

Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 0.0081 4.94 0.0639 3.36 5.89 1.31 6.54 (1) 4.71 3.30 - 6.12 (1) 3.38 2.37 - 4.39 5.71 4.00 - 7.42 1.26 0.88 - 1.64 6.39 4.47 - 8.31 (1) False positive test.

(2) Evaluated as failed due to not reporting a previously reported analyte. NCR 11-11 (3) The filter for Gross Alpha was counted on the wrong side. Recounted on the correct side resulted in acceptable results. NCR 11-11 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetnc and/or volumetric measurements made during standard preparation.

(c) DOE/MAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

D-7

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APPENDIX E RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM (RGPP)

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2011 Radiological Groundwater Protection Program (RGPP)

Table of Contents I. INTRODUCTION..........

3 II. GROUNDWATER PATHWAYS...........................................................................

4 A. Objectives for the Radiological Groundwater Protection Program................. 5 III. LONG-TERM GROUND WATER SAMPLING PROGRAM DESCRIPTION......

6 A3 Sample Collection...........................................

6 B. Sam ple A nalysis.................................................................................................

7 C. D ata Evaluatio n.....................................................................................................

8 IV. RESULTS AND DISCUSSION...........................................................................

12 A. G roundw ater R esults............................................................................................

12 B. Investigatio ns...................................................................................................

18 C. RG PP 2011 Status.............................................................................................

19 D. Impacts to Groundwater: Past Spills and Leaks.............................................

19 V. R EFER EN C ES..................................................................................................

20 Tables 1 Hope Creek RGPP Monitoring Wells: Construction Details.................................... 21 2 Salem RGPP Monitoring Wells: Construction Details...........................................

22 3 Relevant Groundwater Evaluation Criteria: Salem and Hope Creek Generating SS tatio n s.....................................

2 3 4 Analytical Results for Tritium in Groundwater.......................................................

24 3

5 Salem and Hope Creek 10CFR 50.75(g) Data.....................................................

27 Figures 3

1 Hope Creek RGPP Monitoring Well Locations....................................................

28 2 Salem RGPP Monitoring Well Locations..............................................................

29 3

3 Hope Creek Tritium Trends........................................

30 4 Salem Tritium Trends..........................................................................................

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I.

Introduction This is the annual report on the status of the Radiological Groundwater Protection Program (RGPP) conducted at Salem and Hope Creek Generating Stations. This report covers the RGPP groundwater samples collected from the PSEG site in 2011. This report also describes any changes to this program and provides the radiochemical analysis results for groundwater samples collected during the 2011 reporting year. The 2006 PSEG Annual Radiological Environmental Operating Report (AREOR) was the first report that provided a description of the RGPP (PSEG, 2007). The 2006, 2007, 2008, 2009 and 2010 AREORs contained information and detailed descriptions of the RGPP in Appendix F (PSEG 2007, 2008, 2009, 2010, 2011). This report contains the results of the 2011 long-term groundwater-sampling program.

The RGPP was initiated by PSEG in 2006 to determine whether groundwater at and in the vicinity of Salem and Hope Creek Stations had been adversely impacted by any releases of radionuclides related to nuclear station operations, and to provide the mechanism to detect such releases if they occur in the future.

The RGPP is a voluntary program implemented by PSEG in conjunction with the nuclear industry initiatives and associated guidance (NEI, 2007). Although it is designed to be a separate program, the RGPP complements the existing Radiological Environmental Monitoring Program and Radioactive Effluent Technical Specification Program. The RGPP is a component of the Site Integrated Tritium Management Program. The long-term groundwater-sampling program is one of the key elements of the RGPP that provides for early leak detection. The other key elements that comprise the RGPP and contribute to public safety are spill/leak prevention, effective remediation of spills and leaks, and effective stakeholder communication.

In 2002, operations personnel at Salem Generating Station identified a release of E-3 3

I radioactive liquids from the Unit 1 Spent Fuel Pool to the environment. PSEG developed a Remedial Action Work Plan (RAWP). This RAWP was reviewed by the United States Regulatory Commission (USNRC) and approved by the New Jersey Department of Environmental Protection (NJDEP) Bureau of Nuclear 3

Engineering (NJDEP-BNE). In accordance with the RAWP, a Groundwater Recovery System (GRS) was installed and is in operation to remove the groundwater containing tritium. This system was designed to prevent the migration of the tritium plume towards the plant boundary. The GRS is fully discussed in the quarterly Remedial Action Progress Reports (RAPR) provided to the state and the U.S. Nuclear Regulatory Commission by PSEG. The I

information and data associated with the GRS is not included in the annual RGPP reports. It should be noted that five shared monitoring wells (Well IDs AL, I

T, U, Y and Z) are included in both the GRS monitoring and RGPP long-term sampling programs to ensure that the two programs are comprehensive and I

integrated.

Groundwater Pathways PSEG's Salem and Hope Creek Generating Stationls are located in a flat, largely I

undeveloped region of southern New Jersey. The Sites are bordered on the west and south by the Delaware River Estuary and on the east and north by extensive marshlands. Both of the stations obtain cooling water from the Delaware River Estuary and discharge it back to this Estuary.

The site is underlain by over 1,000 feet of inter-layered sand, silt and clay.

The Salem and Hope Creek sites derive potable and sanitary water from deep wells in the Potomac-Raritan-Magothy (PRM) formations, greater than 600 feet below the surface.

There are no potable wells off-site within at least one mile. The nearest potable supply well is located 3.65 miles away in the state of Delaware. In the vicinity of E-4

the site there are no public water supply wells or private wells that can be impacted by radionuclides associated with nuclear station operations.

A. Objectives for the Radiological Groundwater Protection Program The long-term sampling program objectives are as follows:

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment or potential drinking water sources can occur.

2. Understand the local hydro-geologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.

3. Evaluate systems, structures, components, and work practices which have the potential to allow a release of licensed radioactive material to the groundwater.

4. Perform routine water sampling from strategic locations and evaluate radiochemical analysis results.

5. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.

5. Regularly evaluate analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

E-5 5

Ill.

Long-term Groundwater Sampling Program Description A. Sample Collection This section describes the general sampling methodologies used to collect water samples from monitoring wells for the Salem and Hope Creek Generating Stations RGPP. In 2006, 26 RGPP monitoring wells (Tables 1 and 2, Monitoring Well Construction Details) were installed and developed for both Salem and Hope Creek as described in the Site Investigation Report (ARCADIS, 2006A and 2006B). In 2010 two; additional monitoring wells were installed at Hope Creek (Wells BY and BZ) as investigatory tools (PSEG, 2010) but are not part of the RGPP. Groundwater samples are collected from all RGPP monitoring wells at a minimum frequency of semi-annually, with additional monitoring conducted as appropriate. Test Engineers and Laboratory Technicians from PSEG Maplewood Testing Services (MTS) collect the groundwater samples. Sampling protocols are consistent with USEPA and NJDEP guidance; a modified low-flow sampling methodology is used. This methodology is consistent with protocols established for the Salem GRS investigation. In May 2006, after the Site Hydrological Investigation was completed, the long-term groundwater-sampling program was initiated. The program includes sampling all 26 wells at least semi-annually.

The Hope Creek RGPP monitoring wells are nominally sampled semi-annually (BL, BT, BO, BP, BR and BS), quarterly (BM, BN and BQ), and monthly (BH, BI, BJ, and BK). The Salem RGPP monitoring wells are nominally sampled semi-annually (BA, BB, BC, BD, BE, BF, BG and BU), quarterly (AL, T and U), and monthly (Y and Z). The sampling frequencies that are specified in the RGPP procedures may be modified by the PSEG RGPP Manager for purposes of adaptive management of the RGPP. However, sampling and analysis shall not occur less frequently than semi-annually.

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1.

Program Deviations PSEG procedures specify analysis of Strontium-90 on an annual basis. Due to miscommunication with the analytical laboratory Strontium analyses were not generally performed in 2011. The wells are scheduled for Strontium analysis in spring 2012.

2.

New Wells at Salem Generating Station As discussed in the 2010 REOR (PSEG, 2011), in November 2010 ten new wells were installed at Salem Generating Station in response to the Salem Unit 2 tritium release from the Plant Vent to the storm drain system, in an effort to better understand the hydrology associated with the subsurface cofferdam at Salem and potential impacts to groundwater. Wells DA, DB, DC, DD, DE, DF, DG, DH, DI, and DJ are located around Salem Unit 2 in areas surrounding the Fuel Handling Building, containment, and main steam mixing bottle. These wells have been incorporated into the Salem Unit 1 GRS Remedial Action Work Plan under the oversight of the NJDEP-BNE to integrate the investigatory activities.

B. Sample Analysis This section describes the general analytical methodologies used to analyze the water samples for radioactivity for the Salem and Hope Creek Generating Stations RGPP. Groundwater samples were analyzed for plant-related gamma emitting radionuclides (semi-annually) and tritium (every sample) by a radiochemical analytical laboratory. In order to achieve the stated RGPP objectives, the long-term groundwater-sampling program includes the following measurements and analyses:

Concentrations of gamma emitting radionuclides in water by gamma spectroscopy.

E-7 7

Concentrations of tritium in water by filtration/distillation and liquid scintillation.

The tritium analysis results reported in Table 4 were obtained from PSEG MTS laboratory located in Maplewood, NJ and Teledyne Brown Engineering (TBE)

Laboratory located in Knoxville, TN. The gamma spectroscopy analysis results I

are obtained from Teledyne Brown Engineering.

Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check 1

programs. The TBE laboratory participates in an inter-laboratory cross-check program.

I Station personnel review and evaluate all analytical data deliverables obtained I

from these laboratories upon receipt (typically within 30 days after the water samples are received by the laboratory). Since the second quarter of 2011, all I

tritium analyses are performed by TBE. The MTS laboratory is no longer performing RGPP tritium analyses.

C. Data Evaluation 3

This section describes the method used to evaluate the analytical results for RGPP samples obtained at the Salem and Hope Creek Generating Stations.

Analytical data results are reviewed for adverse trends or anomalous data.

Investigations and notification are made as required by RGPP program procedures. The radiological data for groundwater collected since inception of the RGPP program was statistically evaluated to develop a baseline with which current operational data are compared. Several factors are important inthe interpretation and evaluation of the radiological data:

3

1.

Lower Limit of Detection 3

The lower limit of detection (LLD) is specified by federal regulation as a minimum E-8 8

sensitivity value that must be achieved routinely by the analytical method. The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

The environmental LLD is specified for the detectablity of each isotope that may be produced by Salem or Hope Creek stations in the Offsite Dose Calculation Manual (ODCM). A fact of particular interest to the industry, state and public is the LLD of tritium of which the station ODCM LLD is 3,000 pCi/L in water. The station procedure was modeled after the ODCMs for environmental LLDs; however, for the RGPP tritium analyses are performed with the lower LLD of 200 pCi/L.

During 2011, 34 tritium samples were above the LLDs. Of these, only one was for a sample that was above the LLD and then by less than 5% (207 pCi/L). The remaining deviations from the defined RGPP tritium LLDs were the result of higher concentrations of tritium in the samples (above the LLD).

Deviations for sample analysis include the failure to meet LLDs on several analyses, primarily for Barium-Lanthium-1 40 (BA-LA-1 40) and Iodine-1 31 (1I-131).

The cause for the missed LLDs was an extended hold time between sample collection and analysis. The sample transfer will be expedited to meet the specified LLDs.

There is no regulatory impact, as the radiological ground water protection program is a voluntary industry initiative.

2.

Laboratory Measurements Uncertainty Statistically, the exact value of a measurement is expressed as a range with a E-9 9

I stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from the counting system measurement, 3

calibration standards, sample volume or weight measurements, sampling uncertainty and other factors.

3 Analytical uncertainties are reported at the 95% confidence level in this RGPP report to be consistent with the uncertainties reported in the AREOR for the REMP.

3.

Groundwater Data Quality Analysis I

Groundwater samples generally consist of at least four aliquots. One of the 3

groundwater sample aliquots is submitted to the respective station's onsite chemistry laboratory for tritium and gamma spectroscopy analysis. If these I

screening analyses indicated that tritium concentrations are below 10,000 pCi/L and no plant-related gamma emitters were present, then the samples are 3

released for shipment to the offsite environmental laboratory. The on-site Chemistry laboratory's screening analysis for all 2011 RGPP groundwater 3

samples were below 10,000 pCi/L for tritium and no plant-related gamma emitters were present above the associated effluent LLDs specified in the 3

ODCM.

The second sample aliquot is sent to the MTS or TBE Laboratory for tritium analysis. If gamma analysis is to be performed, the third sample aliquot is I

submitted to the TBE Laboratory for gamma spectroscopy analysis.

The fourth sample aliquot is held as a back-up sample until all the analytical results were received and determined to be valid. In the event that the results l

were believed to be questionable or sample results were lost, the back-up sample would be submitted for analysis. In addition, this back-up sample can be I

used to verify any elevated analytical result.

10 E-10

All radionuclide results are compared to the limitations within the RGPP:

Internal Administrative Control Limits are defined within the RGPP procedures. They are developed based on a statistical analysis of the historical baseline concentrations of tritium in each specific well and are used to identify tritium concentrations that warrant further investigation for that specific well. Exceeding Administrative Control Limits does not initiate any external reporting.

" Courtesy Communication Control Limit is a tritium concentration established below regulatory requirements based on agreements with NJDEP-BNE and/or USNRC and other stakeholders, to ensure the stakeholders are cognizant. PSEG has verbally agreed to provide a courtesy communication by telephone no later than the end of the next business day to NJDEP-BNE for any RGPP confirmed tritium result that exceeds 3,000 pCi/L. The NRC Site Resident is also informed. This is not a regulatory required communication.

Voluntary Communication Limits are established for concentrations of radionuclides that require voluntary communication and reporting to regulators and/or stakeholders based on NEI 07-07 and the ODCM.

" The Reporting Level is the concentration of plant produced radioactive material in an environmental sampling medium (averaged over any calendar quarter) from a specified location that requires a 30-day written report to the Nuclear Regulatory Commission and is identified in the ODCM.

IV.

Results and Discussion The locations of the RGPP monitoring wells are illustrated on the maps for Hope Creek and Salem in Figures 1 and 2, respectively. The Monitoring Well E-11 11

Construction Details for Hope Creek and Salem including monitoring interval below ground surface are provided in Table 1, Hope Creek RGPP Monitoring Wells, Construction Details and Table 2, Salem RGPP Monitoring Wells, Construction Details. The relevant radiological groundwater parameters used to evaluate the groundwater data are provided in Table 3, Relevant Groundwater Evaluation Criteria: Salem and Hope Creek Generating Stations.

The 2011 Groundwater Tritium Analytical Results for Salem and Hope Creek Generating Stations are shown in Table 4.

A.

Groundwater Results Samples were collected from RGPP monitoring wells during 2011 in accordance with the station and MTS procedures for the radiological groundwater protection program.

The Site Conceptual Model was revalidated and the Site Investigation Report was updated in 2011. No changes to the RGPP were appropriate based on these updates.

The MTS Laboratory in Maplewood, NJ analyzed the groundwater samples for tritium. The TBE Laboratory in Knoxville, TN analyzed the groundwater samples for tritium and plant-related gamma emitters. Analytical results and anomalies, if any, are discussed below. Since the second quarter of 2011, all tritium analyses are performed by'TBE.

1. Third Quarter 2011 Tritium Event From July through September 2011, tritium was detected at an increased concentration in most RGPP wells. Some of these concentrations exceeded the administrative limits and initiated both courtesy communications and E-12 12I

investigation. A series of hypotheses were developed and investigated. The contract hydrogeologist (Arcadis) performed an evaluation of the event. Based on their hypotheses analysis, the most likely cause of the increased tritium concentrations was the result of the accelerated precipitation recapture due to number and magnitude of rain events. During July 8, 2011, over a five hour period (1300-1800 hrs), 1.78 in of rainfall was measured. In August 2011, approximately 14.5 inches of precipitation accumulated at Artificial Island.

Normal August mean monthly precipitation (as recorded from 1895 through 2011 is 4.5 inches. During a 36-hour period from August 13 to August 14, 2011, approximately 6.9 inches of rain accumulated. Also, Hurricane Irene passed over Artificial Island from August. 27 to August 28, 2011 and, during a 36-hour period, approximately 5.3-inches of rain accumulated.

The nuclear industry and PSEG's recapture study have detected tritium in water vapor and rainwater around plants coincident with permitted gaseous releases of tritium. Through a number of evaluations the industry has identified that permitted gaseous releases of tritium can be recaptured from the atmosphere as water vapor and precipitation downwind. The potential pathways followed by tritium at the site were evaluated. Based on observed tritium exchange between atmospheric water vapor and liquid water it appears that tritium was routinely exchanged from the atmosphere into the liquid water in the vadose zone. During average precipitation accumulation timeframes, this rain water with elevated tritium concentrations would flow slowly down into the groundwater. During the abnormally high precipitation accumulation during the third quarter of 2011 and specifically during August 2011, the rain water with elevated tritium concentrations was flushed from the vadose zone and flowed rapidly through shallow groundwater and was detected in the Riverbed Deposits monitored by the RGPP wells. Subsequent sampling events detected tritium at the historical concentration ranges indicating tritium concentrations have returned to baseline and equilibrated in the subsurface.

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I

2. Tritium Concentrations at Hope Creek Generatinq Station I

The results of the laboratory analysis indicate that tritium was not detected, i.e.,

reported at a concentration below the RGPP LLD of 200 pCi/L, in five RGPP 3

monitoring wells at the Hope Creek site. The tritium concentrations measured at wells BP, BQ, BR, BS, and BT were all less than the LLD of 200 pCi/L during 3

2011 as shown on Table 4.

I

" Tritium was detected at well BH at a maximum of 2,030 pCi/L during the third quarter event and in the range of 223 pCi/L to 868 pCi/L during the remainder of the 2011 sampling period. Well BH is located down gradient of the Condensate Storage Tank (CST) near the southwest protected area I

boundary and is a perimeter well.

" Tritium was detected at well BI at a maximum of 1,630 pCi/L during the third quarter event and in the range of <200 pCi/L to 367 pCi/L during the remainder of the 2011 sampling period. Well BI is located due west of the reactor containment and is a sentinel (source) well for facilities and buried piping..

3

Tritium was detected at well BJ at a maximum of 1,680 pCi/L during the third quarter event and in the range of 411 pCi/L to 790 pCi/L during the I

remainder of the 2011 sampling period. Well BJ is also located down gradient of the CST and is a sentinel (source) well for the CST.

I

" Tritium was detected at well BK at a maximum of 3,690 pCi/L during the I

third quarter event and in the range of <200 pCi/L to 731 pCi/L during the remainder of the 2011 sampling period. Well BK is also located due west of the reactor containment and is a perimeter well.

Tritium was detected at well BM at a maximum of 2,380 pCi/L during the I

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third quarter event and in the range of <200 pCi/L to 371 pCi/L during the remainder of the 2011 sampling period. Well BM is located west of the abandoned Unit 2 reactor building and is a sentinel (source) well for facilities and buried piping.

" Tritium was detected at Well BN in the range of 205 pCi/L to 492 pCi/L.

Well BN is located northeast of the Materials Control Center and is a sentinel (source) well for the Auxiliary Boiler building and buried piping.

" Tritium was detected at well BO at a maximum of 2,370 pCi/L during the third quarter event and in the range of 342 pCi/L to 448 pCi/L during the remainder of the 2011 sampling period. Well BO is located northwest of the Materials Center and is a perimeter well.

In accordance with station procedures, a sample analysis result that is above the administrative limit is re-sampled for a confirmatory analysis. The administrative limits for all station wells were developed by statistical analysis of the historical well data.

These low concentrations of tritium were evaluated and determined to not be indicative of an adverse trend as shown in Figure 4 - Hope Creek Tritium Trends.

The third quarter August 2011 tritium event was investigated and determined to be caused by natural phenomena (excessive precipitation) impacting the recaptured tritium. With the exception of the third quarter tritium event, there were no analytical results for which a Courtesy Communication (greater than 3,000 pCi/L tritium) was required as part of the RGPP. The tritium concentrations in these wells are being monitored and trended and have since returned to their normal levels.

No plant-related gamma emitters were detected in any RGPP well sampled in 2011. Naturally occurring Potassium-40 was detected in several of the wells E-15 15

I sampled during 2011.

I

3. Tritium at Salem Generating Station I

The results of the laboratory analysis indicate that tritium was not detected, i.e.,

reported at a concentration below the RGPP LLD of 200 pCi/L, in three RGPP 3

monitoring wells at the Salem site. The tritium concentrations measured at wells T, BF, and BU were all less than the LLD of 200 pCi/L during 2011 as shown on U

Table 4.

" Tritium was detected at well AL at a maximum of 2,310 pCi/L during the third quarter event and in the range of 446 pCi/L to 545 pCi/L during the remainder of the 2011 sampling period. Well AL is located south of the Salem Unit 1 reactor building and is a sentinel (source) well.I

" Tritium was detected at well BA at a maximum of 355 pCi/L during the third quarter event and at <200 pCi/L during the remainder of the 2011 sampling period. Well BA is located south of the reactor buildings, near the main fuel oil tank and is a perimeter well.

3

Tritium was detected at well BB at a maximum of 4,090 pCi/L during the third quarter event and in the range of <200 pCi/L to 260 pCi/L during the remainder of the 2011 sampling period. Well BB is located along the I

shoreline just north of the Circulating Water Intake Structure and is a perimeter well.

I Tritium was detected at well BC at a maximum of 2,100 pCi/L during the U

third quarter event and in the range of 250 pCi/L to 846 pCi/L during the remainder of the 2011 sampling period. Well BC is a sentinel (source)/perimeter well located southwest of Facilities, Refueling Water E-16 16I

Storage Tank, Auxiliary Feedwater Storage Tank and Primary Water Storage Tank (RAP) tanks and piping.

Tritium was detected at well BD at a maximum of 897 pCi/L during the third quarter event and in the range of 320 pCi/L to 447 pCi/L during the remainder of the 2011 sampling period. Well BD is located to the west of Salem Unit 2 reactor building and is a sentinel (source) well for Facilities, RAP tanks, and piping.

" Tritium was detected at well BE at a maximum of 1,370 pCi/L during the third quarter event and in the range of <200 pCi/L to 452 pCi/L during the remainder of the 2011 sampling period. Well BE is located to the west of Salem Unit 2 reactor building and is a perimeter well.

" Tritium was detected at well BG at a maximum of 1,560 pCi/L during the third quarter event and in the range of 450 pCi/L to 791 pCi/L during the remainder of the 2011 sampling period. Well BG is located northwest of Salem Unit 2 reactor building and is a perimeter well.

" Tritium was detected at well U at a maximum of 307 pCi/L during the third quarter event and in the range of 223 pCi/L to 479 pCi/L during the remainder of the 2011 sampling period. Well U is located north of Salem Unit 2 reactor building and is a sentinel (source) well for the House Heating Boilers.

" Tritium was detected at well Y at a maximum of 3,210 pCi/L during the third quarter event and in the range of <200 pCi/L to 541 pCi/L during the remainder of the 2011 sampling period. Well Y is located west of Salem Units 1&2 reactor buildings and is a perimeter well.

Tritium was detected at well Z at a maximum of 3,820 pCi/L during the third quarter event and in the range of <200 pCi/L to 513 pCi/L during the E-17 17

remainder of the 2011 sampling period. Well Z is located west of Salem Units 1 &2 reactor buildings and is a perimeter well.

These low concentrations of tritium were evaluated and determined not to be 3

indicative of an adverse trend as shown in Figure 5 - Salem Tritium Trends.

The third quarter tritium event was investigated and determined to be caused by 3

natural phenomena (excessive precipitation) impacting the recaptured tritium.

With the exception of the third quarter tritium event, there were no analytical results for which Courtesy Communication (greater than 3,000 pCi/L tritium) was required as part of the RGPP. The tritium concentrations in these wells are i

being monitored and trended.

No plant-related gamma emitters were detected in any RGPP well sampled in 2011. Naturally occurring Potassium-40 was detected in several of the wells sampled during 2011.

B.

Investigations PSEG has implemented an evaluation of the potential for tritium recapture from permitted releases. The program is on-going. Several of the Hope Creek RGPP I

wells which were designed as vault (flush mounted wells) were converted to stick mount (above ground level) in December 2010. The rationale behind this is that the vault mounted wells in low lying areas may collect rainwater runoff. Some tritium, which is release as a permitted discharge via the Salem and Hope Creek plant vents, may be re-captured during rain events and then washed into the n

vaults of the RGPP wells. Conversion of these wells has removed the vaults and places the height of the well opening at approximately 3-4 feet above ground 3

surface, thus removing the potential pooling of rainwater in the vault and around the well shaft.

3 E-18 18I

C.

RGPP 2011 Status The RGPP long-term sampling program will be modified as required in 2012 to adaptively manage the program to meet the RGPP objectives. Baseline sampling and analysis of groundwater will continue on the following schedule:

" Tritium will be analyzed at least semi-annually each calendar year to an LLD of 200 pCi/L; Plant-related gamma emitters will be analyzed semi-annually to the Environmental LLDs specified in the ODCM;

" Programs will be enhanced in 2012 to ensure specified LLDs are met and all parameters identified in station procedures are analyzed at the appropriate frequency; Alignment has been initiated with TBE on alternative analytical protocols for 1-131 to meet the ODCM specified LLD;

" Strontium will be analyzed annually;

" RGPP monitoring well sample frequency will be adjusted based on analytical results, but in no event less than semi-annually.

D.

Impacts to Groundwater: Past Spills and Leaks Historical unplanned and unmonitored releases on site are listed in Table 5, Salem and Hope Creek 10CFR50.75 (g) Data. In addition, the Investigation section of this appendix summarizes the tritium investigations ongoing in 2011.

There are currently no known active releases into the groundwater at Salem or Hope Creek Stations.

E-19 19

I In conclusion, the operation of Salem and Hope Creek Stations has had minimal adverse radiological impact on the environment from unmonitored or unplanned releases of radionuclides.

I V.

References I

1.

ARCADIS, 2006A. Site Investigation Report July 2006. PSEG Nuclear LLC.

Hope Creek Generating Station, Hancock's Bridge, New Jersey.

I

2.

ARCADIS, 2006B. Site Investigation Report July 2006. PSEG Nuclear LLC.

Salem Generating Station, Hancock's Bridge, New Jersey.

I

3.

ARCADIS, 2011. Addendum to the 2006 Site Investigation Reports. PSEG Nuclear LLC. Salem and Hope Creek Generating Stations, Hancock's Bridge, I

New Jersey. December 201 i.

4.

NEI, 2007. NEI 07-07, Industry Groundwater Protection Initiative - Final Guidance Document, Nuclear Energy Institute, Washington, DC, June 2007.

5.

PSEG, 2007. 2006 Annual Radiological Environmental Operating Report, January 1 to December 31, 2006, Salem Generating Station Unit 1 and 2 and Hope Creek Generating Station, April 2007.

6.

PSEG, 2008. 2007 Annual Radiological Environmental Operating Report, January 1 to December 31, 2007, Salem Generating Station Unit 1 and 2 and Hope Creek Generating Station, April 2008.

7.

PSEG, 2009. 2008 Annual Radiological Environmental Operating Report, January 1 to December 31, 2008, Salem Generating Station Unit 1 and 2 and Hope Creek Generating Station, April 2009.

8.

PSEG, 2010. 2009 Annual Radiological Environmental Operating Report, January 1 to December 31, 2009, Salem Generating Station Unit 1 and 2 and Hope Creek Generating Station, April 2010.

3

9.

PSEG, 2011. 2010 Annual Radiological Environmental Operating Report, January 1 to December 31,2010, Salem Generating Station Unit 1 and 2 and Hope Creek Generating Station, April 2011.

I E-20 20

Table 1. Hope Creek RGPP Monitoring Wells: Construction Details Total Monitoring MP MP Monitoring Installation Construction Diameter Depth Interval Elevation Elevation Purpose Source Targets Well ID Date Details (Inches)

(feet bgs)

(feet RPD)

Well BH May-06 Sch-40 PVC 4

37.0 27 - 37 97.92 8

Perimeter NA Well Bl May-06 Sch-40 PVC 4

38.5 28.5 - 38.5 99.6 9.68 Source Facilities; Piping Well BJ May-06 Sch-40 PVC 4

38.0 28 -38 100.23 10.31 Source Condensate Storage &

W B

M 0c0 C32-100.23______

10.31___ _

SucTransfer; Facilities; Piping Well BK May-06 Sch-40 PVC 4

38.5 28.5-38.5 98.19 8.27 Perimeter NA Well BL May-06 Sch-40 PVC 4

35.0 25 - 35 99.71 9.79 Perimeter NA Well BM May-06 Sch-40 PVC 4

38.0 28 - 38 99.76 9.84 Source Facilities; Piping SourceAuxiliary Boiler Building; Well BN May-06 Sch-40 PVC 4

12.5 7.5-12.5 102.64 12.72 Source Piping Well BO May-06 Sch-40 PVC 4

36.0 26 - 36 97.98 8.06 Perimeter/Source Building Sewage Well BP May-06 Sch-40 PVC 4

38.0 28 - 38 99.06 9.14 Perimeter/Source Building Sewage Well BQ May-06 Sch-40 PVC 4

42.0 32-42 102.16 12.24 Source Auxiliary Boiler Building; Dry Cask Storage Building; Piping Well BR May-06 Sch-40 PVC 4

40.5 30.5 - 40.5 104.28 14.36 Perimeter/Source Piping; Dry Cask Storage I___I

__I Building Well BS May-06 Sch-40 PVC 4

35.0 25 - 35 100.55 10.63 Upgradient NA Well BT May-06 Sch-40 PVC 4

38.5 28.5 - 38.5 99.60 9.68 Upgradient NA Notes:

MP bgs RPD msl NA NAD 83 Measuring Point Below ground surface Relative to plant datum Relative to mean sea level (NAVD 1988)

Not applicable North American Datum 1983 E-21

Table 2. Salem RGPP Monitoring Wells: Construction Details Installation Construction Diameter Total Depth Monitoring MP MP Monitoring Source Targets Interval Elevation Elevation Purpose Well ID Date Details (inches)

(feet bgs)

(feet RPD)

Well T Jun-03 Sch-40 PVC 2

31.2 21.2-31.2 104.13 14.21 Source Facilities; House Heating Bir Well U May-03 Sch-40 PVC 2

32.2 27.2 - 32.2 98.57 8.65 Source Facilities; House Heating Bir Well Y Sep-03 Sch-40 PVC 2

37.0 27.0-35.0 101.81 11.89 Perimeter NA Well Z Sep-03 Sch-40 PVC 2

37.5 27.5-37.5 101.86 11.94 Perimeter NA Well AL Jan-04 Sch-40 PVC 2

25.3 15.3-25.3 99.13 9.21 Perimeter NA Well BA May-06 Sch-40 PVC 4

39.5 29.5-39.5 101.07 11.15 Perimeter NA Well BB May-06 Sch-40 PVC 4

47.0 37 - 47 99.38 9.46 Perimeter NA Well BC May-06 Sch-40 PVC 4

38.0 28 - 38 98.78 8.86 Source / Perimeter Facilities; RAP Tanks; Piping Well BD May-06 Sch-40 PVC 4

40.5 30.5 - 40.5 98.78 8.86 Source Facilities; RAP Tanks; Piping Well BE May-06 Sch-40 PVC 4

37.0 27 - 37 98.31 8.39 Perimeter NA Well BF May-06 Sch-40 PVC 4

42.5 32.5-42.5 99.11 9.19 Perimeter NA Well BG May-06 Sch-40 PVC 4

37.0 27-37 100 10.08 Perimeter NA Well BU May-06 Sch-40 PVC 4

36.0 26-36 100.16 10.24 Upgradient NA Notea:

MP bgs RPD msl NA NAD 83 Measuring Point Below ground surface Relative to plant datum Relative to mean sea level (NAVD 1988)

Not applicable North American Datum 1983 E-22 M

m m

M -

E m

m m

m M

m m

M M M m

m m

m M

m m

Table 3. Relevant Groundwater Evaluation Criteria: Salem and Hope Creek Generating Stations PSEG ODCM Isotope RGPP LLD (pCi/L)

Reporting Level (pCi/L)

Tritium 200 30,000 Total Strontium 2.0 8

Mn-54 15 1000 Fe-59 30 400 Co-60 15 300 Zn-65 30 300 Nb-95 15 400 Zr-95 15 200 Cs-134 15 30 Cs-137 18 50 Ba-1 40 60 200 La-1 40 15 200 E-23

Table 4. Analytical Results for Tritium in Groundwater Well ID Sample Date]

Result Units Well ID ýample Dat4 Result Units 06/13/11

<200 pCi/L 06/07/11 791 DCi/L WELL BA 08124111 355 pCi/L 08/05111 1560 pCi/L 10/07/1

<200 pCi/L WELL BG 08/24/11 1460 pCi/L 11/03/11'

<200 pCi/L 10/11/11 507 pCi/L 1

1 11/08/11 450 pCi/L 01/20/11 260 pCi/L 06113/11

<200 pCVL 01/25/11 836 pCi/L 08/24/11 1240 pCi/L 02/11/11 482 pCi/L 09/01/11 4150 pCi/L 03/17/11 333 DCi/L 10/07/11

<200 pCi/L 04/15/11 404 pCi/L 11/03/111

<200 pCi/L WELL BH 05/23/11 310 pCi/L W

B 06/21/11 224 pCi/L 01/21/11 846 pCi/L 07/25/11 907 pCVL 06107/11 250 pCi/L 08/30/11 20301 PCi/L 07/29/11 250 pCi/L 09/30/11 372 pCi/L WELL BC 09101/11 2100 223pCi/L 10/11/11 649 pCi/L 11/08/11 362 pCi/L 01/25/11

<200 pCi/L 12/28/11 383 pCi/L 02/11/11 231 pCi/L S1 03/17/11 367 pCi/L 01/21/11 320 pCi/L 04/15/11 342 pCi/L 06/07/11 354 pCi/L WELL BI 05/23/11 243 pCi/L WELL BD 08/24/11 897 pCi/L 07/25/11 1630 pCi/L 10/11/11 447 pCi/L 08/30/11 1420 pCi/L 11/08/11 414 pCi/L 09/30/11

<200 pCi/L I

1 1

11/08/111

<200 pCi/L 01/21/11 301 PCi/L I _

6/7/2011 270 DCi/L 01/25/11 790 pCi/L 08/05/11 1370 DCi/LI 02/11/11 600 pCi/L WELL BE 08/24/11 365 DCi/L 03/17/11 761 pCi/L I

10/11/11

<200 :Ci/L 04/15/11 467 CiV/L 11/08/11 347 DCi/L 05/23/11 425 Ci/L 12/28/11 452 DCi/L 06/21/11 411 pCi/L 07/25/11 1680 pCi/L 06/07/11

<200 :Ci/L 08/30/11 1600 pCi/L WELL BE 08/24/11

<200 :Ci/L 09/30/11 556 1Ci/L 10/11/11

<200 :Ci/L 11/08/11 449 1Ci/L 11/08/11

<200 DCi/L I

I I

I, I

E-24 24

Table 4. Analytical Results for Tritium in Groundwater. (cont'd)

Well ID Sample Date]

Result I Units I Well ID Oample Datý Result I Units

_ I I

I 01/25/11 731 pCi/L WELL BS 06/23/11

<2001 pCi/L 02/11/11 407 pCi/L W

11/15/111

<200 pCi/L 03/17/11 332 pCi/L 1 _

04/15/11 215 pCi/L WELL BT 06/23/11

<200 pCi/L WELL BK 05/23/11 184 pCi/L 1 11/15/111

<2001pCi/L 06/21/11 335 pCi/L 1_

07/25/11 3690 pCi/L 06/23/11

<200 pCi/L 08/30/11 1610 pCi/L 09/09/11

<200 pCi/L 09/30/11 410 pCi/L WELL BU 10/13/11

<200 pCi/L 1

11/08/11 370 pCi/L 11/15/11

<200 pCi/L 12/22/11

<200 pCiYL 02/11/11

<200 pCi/L WELL BL 05/23/11

<200 pCi/L 01/25/11 1480 pCi/L 11/08/11

<200 DCi/L 02/11/11 1340 pCi/L 03/17/11 996 pCi/L 02/11/11

<200 pCi/L 04/15/11 847 pCi/L 03/17/11 222 pCi/L WELL BY 05/23/11 882 pCi/L 05/23/11

<200 pCi/L 07/25/11 2190 Ci/L WELL BM 07/25/11 2260 pCi/L 08/30/11 1400 pCi/L 08/30/11 2380 pCi/L 09/30/11 1120 Ci/L 09/30/11 371 pCi/L 1

11/08/11 1630 Ci/L 11/08/11 261 pCi/L I

I 01/25/11 323 pCi/L 03/22/11 492 pCi/L 02/11/11 377 pCi/L WELL BN 05/26/11 253 pCi/L 03/17/11 611 )Ci/L 11/15/11 205 pCi/L 04/15/11 528 pCi/L I

WELL BZ 05/23/11 536 pCi/L 06/23/11 448 pCi/L 07/25/11 3320 pCi/L WELL BO 08/05/11 2370 pCi/L 08/30/11 2890 pCi/L 11/15/11 342 ECi/L 09/30/111 412 pCi/L 1

11/08/11 491 pCi/L 06/23/11

<200 pCi/L I

1 11/15/111

<200 LCi/L 01/20/11 448 pCi/L

__1 1

03/04/11 516 pCi/L 03/22/11

<200 DCi/L 06/13/11 476 pCi/L WELL BQ 05/26/11

<200 DCi/L 08/05/11 2310 pCi/L 11/08/11

<200 :Ci/L WELL AL 08/31/11 1480 pCi/L i _

09/10/11 466 pCi/L WELL BR 06/23/111

<200 [pCi/L 10/07/11 446 pCi/L 1

11/15/111

<2001pCi/L 11/17/11 479 pCi/L I

12/20/11 545 pCi/L E-25 25

Table 4. Analytical Results for Tritium in Groundwater (cont'd)

Well ID Sample Dater Result Units 01/13/11

<207 pCi/L 06/07/11

<200 pCi/L WELL T 09/10/11

<200 pCi/L 10/11/11

<200 pCi/L 11/08/111

<200 pCi/L 01/13/11 290 pCi/L 06/07/11 223 pCi/L 09/10/11 307 pCi/L 10/11/11 309 pCi/L 11/08/11 479 pCi/L 12/28/11 361 pCi/L 01/20/11

<200 pCi/L 02/18/11

<200 pCi/L 03/29/11

<200 pCi/L 04/27/11

<200 pCi/L 05/26/11

<200 pCi/L 06/13/11

<200 pCi/L 07/29/11

<200 pCi/L 08/31/11 3210 pCi/L 09/27/11 541 pCi/L 10/07/11

<200 pCi/L 11/03/11

<200 pCi/L 12/13/11

<200 pCi/L 01/20/11 446 pCi/L 02/18/11 346 pCi/L 03/29/11 326 pCi/L 04/27/11 288 pCi/L 05/26/11 263 pCi/L 06/13/11

<200 pCi/L WELL Z 07/29/11 385 pCi/L 08/31/11 3820 pCi/L 09/27/11 503 pCi/L 10/07/11 457 pCi/L 11/03/11 513 pCi/L 1

12/13/11 400 PCi/L I

I I

E-26 26

Table 5. Salem and Hope Creek 1 OCFR 50.75(g) Data Spill/Discharge Quantity Spilled /

Location of Description Discharged Spill/Discharge Apr-95

- 88 millicuries Hope Creek and Steam from the Decon Salem Solution Evaporator released from Hope Creek's South Plant Vent Jan-02 Unit 1 RWST Salem Unit 1 RWST Nozzle Leak Sep-02

-5 Ci Ground west of Unit Blockage of the Spent Fuel 1 Spent Fuel Pool liner's "tell-tales" Building caused backup of contaminated water through building seams Mar-04 Co-60 North Side of Salem Corroded Pipe Cracked Circulating Water House Jan-05 No discharge to the Hope Creek rooms Water from inside the environment 3133, 3135, 3129 Waste Sludge Phase and 5102 Separator Tank Room appeared to be leaking through the crack in the Nall July-05 5.2 microcuries Hope Creek 54' Overflow of plant system Diesel Building contained within the building.

Aug-06 Southside of Salem Leaking Valve House Heating Boiler May-07 2.8 microcuries of In front of Salem Burst site glass during Cs 137 Unit 2 condensate operation. Resin blown

olisher through wall into switchyard Nov-1 0

.3 microcuries of At the pedestal Attributed to Fallout Cs 137 teps Salem Unit 2 containment E-27 27

Figure 1 - Hope-Creek RGPP Monitoring Well Locations N,)

00 m

m m

Figure 2 - Salem RGPP Monitoring Well Locations ro Fels

(,

BARTLETT

....Irl III e t

Figure 3 - Hope Creek Tritium Trends 9000 8000 7000 6000 3.5000 U

0U54000 3000 2000 1000 0

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Figure 4 - Salem Tritium Trends 5000 4500 4000 3500 S3000 U

o2500 0

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LA Ar AA I--dr~4 a)

(D w

w r

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-u-Well BC Well Y Well BD

-*--Well Z E-31 31 9

ML12122A921

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SUMMARY

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SUMMARY

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