Text

Annual Radioactive Effluent Report and Radiological Environmental Monitoring Report
	ML16067A121
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/01/2016
From:	Nick B; Dairyland Power Cooperative
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	LAC-14374
	Download: ML16067A121 (29)
	v • d • e

BARBARA A. NICK President and CEO DAIRYLAND POWER COOPERATIVE March 1, 2016 In reply, please refer to LAC-14374 DOCKET NO. 50-409 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 10 CFR 50.3 6a(a) (2)

SUBJECT:

Dairyland Power Cooperative La Crosse Boiling Water Reactor Possession-Only License No. DPR-45 Annual Radioactive Effluent Report and Radiologieal Environmental Monitoring, Renort

REFERENCES:

(1) NRC Letter, Keppler to Linder, dated August 12, 1983, Inspection Report 50-409/83-10 (DRMSP)

In accordance with 10 CFR 50.36a(a)(2), this letter serves to transmit to you the Radioactive Effluent Report and Radiological Environmental Monitoring Report for the La Crosse Boiling Water Reactor (LACBWR) for 2015.

If you have any questions, please contact Cheryl Olson at 608-689-4207.

Sincerely, Barbara A. Nick, President and CEO BAN:CLO:tco Enclosures cc/endl: Cynthia Pederson, NRC Reg. III Administrator Marlayna Vaaler, NRC Project Manager Jason Hunt, Wisc. Div. of Health A Touchstone Energy9 Cooperative *'

3200 East Ave. S.

P0 Box 817

La Crosse, WI 54602-0817

608-787-1258

608-787-1469 fax

www.dairynet.com Dair-yland Power Cooperative is an equal opportunity provider and employer.

RADIOACTIVE EFFLUENT REPORT AND RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT FOR THE LA CROSSE BOILING WATER REACTOR (LACBWR)

(January I to December 31, 2015)

DAIRYLAND POWER COOPERATIVE 3200 EAST AVENUE SOUTH LA CROSSE, WI 54602-0817

TABLE OF CONTENTS SECTION A: RADIOACTIVE EFFLUENT REPORT Section Title Pa Introduction............................................................

1 1.0 Regulatory Limits.....................................................

2 2.0 Effluent Release Concentration Limit................................

4 3.0 Average Energy......................................................

4 4.0 Analytical Methods....................................................

4 5.0 Batch Releases.......................................................

5 6.0 Abnormal Releases...................................................

5 7.0 Estimated Total Analytical Error.....................................

5 8.0 Offsite Dose Calculation Summary and Conclusions..............

12 9.0 Offsite Dose Calculation Manual (ODCM) Review.................

12 10.0 Process Control Program (PCP) Review............................

13 SECTION A: RADIOACTIVE EFFLUENT REPORT Table No.

Title Page 1A Effluent and Waste Disposal - Gaseous Effluents Summation of All Releases..........................................

6 I1B Effluent and Waste Disposal - Gaseous Effluents Elevated Release.....................................................

7 2A Effluent and Waste Disposal Annual Report - 2015 Solid Waste and Irradiated Fuel Shipments.......................................

8 2B Effluent and Waste Disposal Annual Report -2015 Solid Waste and Irradiated Fuel Shipments.......................................

10

TABLE OF CONTENTS SECTION B: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Section Title Page Introduction...............................................................

1.0 Sample Collection......................................................

2 2.0 Results of the 2015 Radio-Environmental Monitoring Survey..

2 3.0 Conclusions.............................................................

3 4.0 Interlaboratory Comparison Program Results.......................

4 SECTION B: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Table No.

Title Page 1

ISESI Environmental Direct Radiation Badge Locations......

5 2

Sample Frequency and Analysis of Radio Environmental Samples 6

3 Radio-Environmental Samples Collected January-December 2015 7

4 Results of Analysis of Mississippi River Water in the Vicinity of LACBWR................................................................

8 5

Results of Analysis of Mississippi River Sediment in the Vicinity of LACBWR................................................................

9 6 --

2015 Quarterly OSL Dosimeter Dose Measurements in the ISESI Vicinity.................................................

10 ii

SECTION A RADIOACTIVE EFFLUENT REPORT

INTRODUCTION The La Crosse Boiling Water Reactor (LACBWR), also known as Genoa Station No. 2, is located on the east bank of the Mississippi River near Genoa, Vernon County, Wisconsin. The plant was designed and constructed by the Allis-Chalmers Manufacturing Company. It was completed in 1967 and had a generation capacity of 50 MW (165 MW(th)). The reactor is owned by Dairyland Power Cooperative (DPC).

The reactor went critical in July 1967 and first contributed electricity to DPC's system in April 1968. After completing full power tests in August 1969, the plant operated between 60% and 100% full power, with the exception of plant shutdowns for maintenance and repair.

In April of 1987 plant operation was ceased. The reactor was defueled and placed in a SAFSTOR mode. In August of 1987 a possession-only license was received. In 2007 the reactor vessel was removed from the site and buried at the Barnwell waste repository. In 2012 all spent fuel was placed in dry storage and placed at the LACBWR ISFSI.

In accordance with LACBWR Appendix C Section 2 of the Quality Assurance Program Description (QAPD), this document is the Radioactive Effluent Report for the Period January 1 through December 31, 2015.

1

EFFLUENT AND WASTE DISPOSAL REPORT (Supplemental Information)

FACILITY: La Crosse Boilingq Water Reactor LICENSEE: Dairvland Power Cooperative DOCKET NO. 50-409 & 72-046 1.0 REGULATORY LIMITS 1.1 Gaseous Effluent Release Limits:

LACBWR's stack effluent release limitations for gaseous effluent releases of radioactive material limits the release rate of the sum of the individual radionuclides, so that the dose rates to members of the public beyond the Effluent Release Boundary do not exceed 500 mRem/year to the whole body and 1500 moRero/year to a critical organ from H-3 and particulates with half-lives greater than 8 days as per the requirements of the Offsite Dose Calculation Manual (ODOM).

Also, in accordance with 10 CFR 50, Appendix I, the ODCM limitations for gaseous effluent radioactive material limit the air dose to a member of the public from noble gases in areas beyond the Effluent Release Boundary to less than 5 mRad gamma and 10 mRad beta per calendar quarter, and less than 10 mRad gamma and 20 mRad beta per calendar year. The dose limits from H-3 and particulates with half-lives greater than 8 days are less than 7.5 mRem per calendar quarter, and less than 15 mRem per calendar year to any organ.

Cumulative dose contributions from gaseous effluent releases are determined in accordance with the LACBWR Offsite Dose Calculations Manual.

2

1.2 Liquid Effluent Release Limits:

LACBWR's liquid effluent release limitations for liquid effluent releases are those concentrations specified in 10 CFR 20 Appendix B, Table 2, Column 2. The values reported in tables 2A and 2B, Liquid Effluents, are based on dilution of the effluent with the Genoa Station No. 3 condenser cooling water flow prior to discharge to the Mississippi River. No credit is taken for further dilution in the mixing zone of the Mississippi River.

Also, in accordance with 10 CFR 50, Appendix I, the dose commitment to a member of the public from radioactive materials released in liquid effluents to areas beyond the Effluent Release Boundary are limited to less than 1.5 mRem whole body and 5.0 mRem organ dose per calendar quarter, and less than 3.0 mRem whole body and 10 mRem organ dose per calendar year via the critical ingestion pathway.

Cumulative quarterly and annual dose contributions from liquid effluent releases are determined for the adult fish ingestion pathway in accordance with the LACBWR Offsite Dose Calculation Manual.

1.3 Solid Radioactive Waste All solid radioactive wastes are handled in accordance with a Process Control Program as defined by LACBWR procedures in order to assure that all applicable transportation and burial site disposal requirements are met. An amended report for 2014 is included in this report.

3

2.0 EFFLUENT RELEASE CONCENTRATION LIMIT The Effluent Release Concentration used to calculate permissible release rates are obtained from 10 CFR 20, Appendix B, Table 2, Column 2.

3.0 AVERAGE ENERGY The release rate limits for LACBWR are not based on average energy.

4.0 ANALYTICAL METHODS 4.1 Liquid Effluents Liquid effluent measurements for gross radioactivity are performed by HPGe gamma isotopic analysis of a representative sample from each tank prior to discharge. In addition, each batch discharged tank sample is analyzed for alpha and tritium activity concentrations using an IPC. A composite sample is created by collecting representative aliquots from each tank batch discharged during a calendar quarter. This composite is analyzed for lron-55 and Strontium-90 by a contractor on a quarterly basis.

4.2 Airborne Particulates Airborne particulate releases are determined by HPGe gamma isotopic analysis.

This analysis is performed by analyzing a glass fiber filter paper, taken from the stack monitor which continuously samples from an isokinetic point monitoring the stack effluent. This filter is changed and analyzed on an approximate weekly basis and analyzed within 7 days after removal. This filter is also analyzed for alp ha activity. A quarterly composite of these filters is sent to a contractor for Sr-90 analysis. Results of the analysis is shown in Table 1A and IlB.

4

4.3 Fission and Activation Gases With the removal of spent fuel from the site no fission gases remain. In 2013 the monitoring for fission and activation gases was eliminated.

4.4 Tritium With the removal of the spent fuel from the site, no means to produce tritium exist. Therefore, this process was discontinued in August of 2014 with the approved changes to the ODCM.

5.0 BATCH RELEASES 5.1 Airborne All airborne effluent releases at LACBWR are from a single Continuous-Elevated Release Point. Results are shown in Table 1A.

5.2 Lqi

All liquid effluent releases at LACBWR are batch releases as described in the ODCM. There were no liquid releases in 2015.

6.0 ABNORMAL RELEASES There were no abnormal releases of radioactivity in plant effluents.

7.0 ESTIMATED TOTAL ANALYTICAL ERROR The reported analytical results contain the following estimated errors:

Counting Error 95% Confidence Level Sampling Volume Error + 5%.

5

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2015 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR QTR QTR QTR TOTAL A.

FISSION & ACTIVATION GASES - No longer analyzed B.

IODINE 1-131 - No longer analyzed C.

PARTICULATES

1.

PARTICULATES WITH HALF-LIVES > 8 DAYS Ci 2.00E-7 4.30E-7 4.81 E-6 1.05E-6 8.29E-6

2.

AVERAGE RELEASE RATE FOR PERIOD pLCi/Sec 1.92E+2 4.08E+2 4.52E+2 9.86E+-2

3.

GROSS ALPHA RADIOACTIVITY Ci

<MDA

<MDA 3.00E-8

<MDA D.

TRITIUM - No longer analyzed E.

PERCENTAGE OF ODCM DOSE LIMITS FOR GASEOUS EFFLUENT RELEASES QTR QTR QTR QTR YEARLY

1.

NOBLE GAS RELEASE - No longer analyzed for.

2.

H-3 AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES

__GREATER THAN 8 DAYS GAMMA (Highest Organ) 4.65E-6 2.02E-5 4.62E-5 4.44E-5 5.62 E-5 6

TABLE 1B GASEOUS EFFLUENTS - ELEVATED RELEASE I I CONTINUOUS MODE UNIT 1t QTR 2n QTR 3d QTR 4h QTR TOTAL NUCLIDES RELEASED

1.

FISSION GASES KRYPTON Analysis no longer required.

2.

IODINE 1-131 -Analysis no longer required.

3.

PARTICULATES STRONTIUM-90 Ci 2.28E-12

< MDA 2.03E-12

< MDA 4.31 E-12 CESIUM-134 Ci

< MDA

< MDA CESIUM-137 Ci

< MDA 4.30E-7 2.96E-6 8.90E-7 4.28E-6 COBALT-60 Ci 2.00E-7

< MDA 1.85E-6 1.60E-7 2.21 E-6 TOTALS Ci 2.00E-7 4.30E-7 4.81 E-6 1.05E-6 8.29E-6 I _______ I

__________ I

__________ [

I __________ I 7

TABLE 2A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2015 A.

SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL (Not Irradiated Fuel) 6-MONTH 6-MONTH

1. TYPE OF WASTE UNIT PERIOD PERIOD TOTAL

a. DRY COMPRESSIBLE WASTE, m3NA 34.82 34.82 CONTAMINATED EQUIPMENT, ETC Ci NA 0.16 0.16

b. BEAD RESIN m3 NA 5.89 5.89 Ci NA 7.00 7.00

c. SLUDGE m3 NA 5.15 5.15 Ci NA 0.04 0.04 6-MONTH 6-MONTH

2. ESTIMATE OF MAJOR NUCLIDE PERCENT PERIOD PERIOD COMPOSITION (BY TYPE OF WASTE)

OF TOTAL CURIES CURIES

a. DRY COMPRESSIBLE WASTE, CONTAMINATED EQUIPMENT, ETC_____

C-14 1

NA 0.0017 Co-60 8

NA 0.0135 Cs-137 77 NA 0.1255 Ni-63 11 NA 0.0184 Sr-90 2

NA 0.0029

b. BEAD RESIN Co-60 1

NA 0.0597 Cs-137 61 NA 4.26 Ni-63 14 NA 0.957 H-3 24 NA 1.7

c. SLUDGE Am-241 1

NA 0.0003 Co-60 26 NA 0.0103 Cs-I137 63 NA 0.0250 Fe-55 1

NA 0.0006 Ni-63 6

NA 0.0026 Sr-90 2

NA 0.0007 8

3.

SOLID WASTE DISPOSITION NO. OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 1

Sole use Clive, UT 2

Sole use Oak Ridge, TN B.

IRRADIATED FUEL SHIPMENTS (DISPOSITION) - None 9

TABLE 2B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS - 2014 amended A.

SOLID WASTE SHIPPED OFFSlTE FOR DISPOSAL (Not Irradiated Fuel) 6-MONTH 6-MONTH

1. TYPE OF WASTE UNIT PERIOD PERIOD TOTAL:

DRY COMPRESSIBLE WASTE, m3 232.4 353.3 585.7

a.

CONTAMINATED EQUIPMENT, Ci 0.096 1.96 2.056 METAL m3 30 37.45 67.45

b.

ASBESTOS Ci 0.002 0.029 0.031 ACTIVATED WASTE m30 32.85 32.85

c.

CONTROL ROD DRIVE MECHANISIM Ci 0

3.94 3.94 m30 5.26 5.26

d.

OIL Ci 0

0.0742 0.0742 m30 3.28 3.28

e.

LEAD Ci 0

0.0035 0.0035 PERCENT TOTAL CURIES

2. ESTIMATE OF MAJOR NUCLIDE jOF TOTAL COMPOSITION (BY TYPE OF WASTE)

(>1%)

a.

DRY COMPRESSIBLE WASTE, CONTAMINATED EQUIPMENT,METAL Co-60 12.6 0.260 Cs-137 8.9 0.182 Fe-55 1.5 0.030 H-3 2.4 0.049 Ni-63 69.9 1.438 Pu-241 2

0.041

b.

ASBESTOS Co-60 22.6 0.007 Fe-55 3.2 0.001 Ni-59 1

0.0002 Ni-63 69 0.0214 Pu-241 3.2 0.001 10

c.

ACTIVATED WASTE CONTROL ROD DRIVE MECHANISIM Co-60 39 2.36 H-3 2

0.104 Ni-63 24 1.47

d.

OIL Co-60 5.4 0.004 Cs-i137 10.8 0.008 H-3 2.7 0.002 N-63 79.5 0.059 Pu-241 1.3 0.001

e.

LEAD Co-60 22.8 0.008 Fe-55 2.9 0.001 Ni-59 1

0.0002 Ni-63 68.6 0.024 Pu-241 2.9 0.001

3.

SOLID WASTE DISPOSITION MODE OF NO. OF SHIPMENTS TRANSPORTATION DESTINATION 23 Sole use Oak Ridge, TN B.

IRRADIATED FUEL SHIPMENTS (DISPOSITION) - None 11

8.0 OFFSITE DOSE CALCULATIONS

SUMMARY

AND CONCLUSIONS:

8.1 Gaseous Effluent Releases The maximum quarterly offsite gamma dose due to noble gases was 0.00 mRad.

The cumulative 2015 annual offsite gamma dose due to noble gases was 0.00 mRad.

The maximum quarterly offsite beta dose due to noble gases was 0.00 mRad.

The cumulative 2015 annual offsite beta dose due to noble gases was 0.00 mRad.

The maximum quarterly offsite dose to any organ from the release of H-3 and all radionuclides in particulate form with half-lives greater than 8 days was approximately 3.47E-6 mRem. The cumulative 2015 annual maximum organ dose from these radionuclides was also approximately 8.43E-6 mRem.

The highest historical annual average X/Q equal to 1.82 E-6 sec/m3 for the period 1985-1987 for the worst case offsite receptor location, in accordance with the ODCM, was used to calculate these offsite dose values.

8.2 Liquid Effluent Releases There were no liquid releases and therefore no dose from liquid releases.

8.3 Conclusion All calculated offsite doses were below ODCM limits.

9.0 OFFSITE DOSE CALCULATION MANUAL (ODCM) REVIEW Revision 15 to the ODCM was issued in August of 2014. The majority of the changes were made to reflect the current status of the facility with respect to its calculated radionuclide inventory. The calculation confirms it is not possible to 12

either (a) exceed the annual dose limits, or (b) reach the current airborne effluent monitor instantaneous release rate setpoint of 1500 mrem/yr. The LACBWR facility discontinued the monitoring of main stack air, offsite particulate air, OSL quarterly (not including ISESI) monitoring as well as fish sampling from the Mississippi river.

10.0 PROCESS CONTROL PROGRAM The process control program was last revised in 2012.

13

SECTION B ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

INTRODUCTION:

The Radiological Environmental Monitoring (REM) Program is conducted to comply with the requirements of the ODCM and in accordance with 10 CFR 50 Appendix I and 10 CFR 72.104. The REM Program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which could potentially lead to radiation doses to Members of the Public resulting from plant effluents. Environmental samples are taken within the surrounding areas of the plant and in selected control or background locations.

The monitoring program at the LACBWR facility includes monitoring of liquid and gaseous releases from the plant, as well as environment~al samples of surface air, river water, river sediment, milk, fish, and penetrating radiation.

The REM program theory supplements the Radioactive Effluent analyses by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways using the methodology of the Offsite Dose Calculation Manual (ODOM).

An Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed.

I

1.0 SAMPLE COLLECTION Environmental samples are collected from the area surrounding LACBWR at the frequencies outlined in the ODCM. A series of tables are included in this report to better show LACBWR's environmental program.

TABLE 1 This table shows the OSL locations at the ISFSI.

TABLE 2 This table shows the sampling frequency of the various environmental samples and the analyses performed on these samples TABLE 3 This table shows the number of various samples collected and analyzed during 2015.

2.0 RESULTS OF THE 2015 RADIO-ENVIRONMENTAL MONITORING SURVEYS During 2015, activity levels in the local environment were normal, indicating no significant plant attributed radioactivity.

2.1 PENETRATING RADIATION The environmental penetrating radiation dose is measured by optically stimulated luminescent (OSL) dosimetry. These OSL's at the ISESI are changed on a quarterly basis. Table 60OSL results for 2015 are shown.

2.2 AIR PARTICULATE Air particulate samples were discontinued in August 2014 when the requirements of the ODCM were updated.

2.3 RIVER WATER River water was collected monthly and is now collected semi-annually. River water samples above at, and below the plant site are collected and are gamma 2

analyzed for isotopic concentration. The river water gamma isotopic analysis results are shown in Table 4. The results indicate that there were no significant plant attributable radionuclides in the river water.

2.4 SEDIMENT SAMPLES Sediment samples are collected twice per year above, at, and below the plant outfall. These samples are gamma analyzed and these results appear on Table

5. They indicated that small amounts of plant-attributed radionuclides have accumulated in river sediments near the outfall. The amount of radionuclides in this sediment declined significantly after plant shutdown. These amounts have remained relatively constant the last few years.

2.5 FISH Fish sampling has been eliminated as of August 2014 when the requirements of the ODCM were updated.

3.0 CONCLUSION

S All environmental samples collected and analyzed during 2015 exhibited no significant contribution from LACBWR.

3

4.0 INTERLABORATORY COMPARISON PROGRAM RESULTS During 2015, interlaboratory comparison samples were obtained from an outside contractor. The equipment used to analyze the environmental samples was tested against the contractors' results. The following is the result of this comparison. (results in pCi/L)

ANALYSIS LACBWR RESULTS CONTRACTOR RESULTS RATIO GROSS BETA 2.55E2 2.46E2 1.04 GROSS ALPHA 4.62E1 4.63E1 I

1-131 9.58E1 9.26E1 1.03 Cr-5I 2.68E2 2.44E2 1.10 Cs-134 1.24E2 1.39E2 0.89 Cs-137 1.09E2 9.95E 1 1.10 Co-58 1.03E2 9.56E 1 1.08 Mn-54 1.42E2 1.26E2 1.13 Fe-59 1.07E2 9.34E1 1.15 Zn-65 2.46E2 2.15E2 1.14 Co-60 1.92E2 1.85E2 1.04 H-3 9.48E3 8.50E3 1.12 4

TABLE 1 ISFSI ENVIRONMENTAL DIRECT RADIATION BADGE LOCATIONS LOCATION LOCATION NO.

1 ISFSI ADMINISTRATIVE BUILDING WEST 2

ISESl PROTECTED AREA NORTH EAST SIDE 3

ISESl NORTH WEST SIDE 4

ISESl SOUTH WEST SIDE 5

ISESI SOUTH EAST SIDE 6

ISESI OWNER CONTROL FENCE NORTH 7

ISFSI OWNER CONTROL FENCE WEST 8

ISESl OWNER CONTROL FENCE EAST 9

ISFSI OWNER CONTROL FENCE NORTH EAST BY HEAVY HALL PATH 10 ISFSl OWNER CONTROL FENCE WEST BY BOAT LANDING 5

TABLE 2 SAMPLE FREQUENCY AND ANALYSIS OF RADIO-ENVIRONMENTAL SAMPLES SAMPLE FREQUENCY ANALYSIS PERFORMED OSL Dosimeters Quarterly

Dose in mRem Particulate Air Glass Weekly **

Gross Beta and Gamma Fiber Filters Spectroscopy of Composites Monthly (HPGe-MCA)

Milk Obtain sample as directed if Gamma Spectroscopy abnormal stack particulate release occurs.

Sediment Semi-annually Gamma Spectroscopy Fish Quarterly **

Gamma Spectroscopy River Semi-annually Gamma isotopic analysis and tritium (Liquid Scintillation Analyzer)

Vegetation Obtain sample as directed if Gamma Spectroscopy abnormal stack particulate release occurs.

- LCBWR Plant Monitoring discontinued in August 2014. LACBWR ISFSI Monitoring continues.

- - Monitoring requirement eliminated in August 2014.

6

TABLE 3 RADIO-ENVIRONMENTAL SAMPLES COLLECTED JANUARY-DECEMBER 2015 NUMBER OF TYPE OF SAMPLE SAMPLES Penetrating Radiation (OSL's) 40 Air Particulate 0

River Water 6

Sediment 6

7

TABLE 4 OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR RESULTS OF ANALYSIS (Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE:

DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY SAMPLE LOCATION:

4/14/15 4/14/15 4/14/15 10/14/15 10/14/15 10/14/15 ISOTOPES/RL

H-3

<114

<746

<746 Mn-54/1 000

<3.97

<3.99

<3.96

<4.07

<3.97

<3.97 Co-60/300

<4.24

<4.17

<4.15

<4.49

<4.30

<4.22 Zn-65/300

<9.13

<9.06

<9.42

<9.36

<8.04

<9.48 Cs-I134/30

<4.49

<4.47

<4.60

<4.59

<4.48

<4.52 Cs-I 137/50

<4.68

<4.69

<4.67

<4.73

<4.59

<4.77

RL = REPORTING LEVEL 8

TABLE 5 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER SEDIMENT IN THE VICINITY OF LACBWR (Concentration in pCi/Kg)

SAMPLE LOCATION UPSTREAM OUTFALL DOWNSTREAM UPSTREAM OUTFALL DOWNSTREAM COLLECTION DATE ISOTOPES Cs-134

<6.53

<5.98

<8.39

<6.34

<5.82

<8.45 Cs-137

<5.99 1110 92.2

<5.69 240 62 Co-60

<6.35 12.9

< 10.4

<5.97 21.5

<8.01 9

TABLE 6 QUARTERLY OSL DOSIMETER DOSE MEASUREMENTS IN THE ISESI VICINITY BACKGROUND CORRECTED JANUARY-DECEMBER 2015 STATION NO.

1st QUARTER mRem 2nd QUARTER mRem 3rd QUARTER mRem 4th QUARTER mRem 1

0 0

2 36.1 37.2 39.9 31.5 3

11.1 122.6 111.1 88.2 4

17.7 21.8 20.6 16.5 5

38.8 35.6 43.9 32.0 6

0 0

7 0

0 0

0 8

0 0

9 1.4 1.1 0

0 10 1.0 1.1 1.8 0.3 10