ML19056A195
| ML19056A195 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/21/2019 |
| From: | Gerard van Noordennen LaCrosseSolutions |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| LC-2019-0017 | |
| Download: ML19056A195 (59) | |
Text
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LACROSSESOLUTIONS 10.CFR 50.36(a)(2)
February 21, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 La Crosse Boiling Water Reactor Facility Operating License No. DPR-45 NRC Docket Nos. 50-409 and 72-046 LC-2019-0017
Subject:
La Crosse Boiling Water Reactor (LACBWR) Annual Radioactive Environmental Monitoring Report and Radioactive Effluent Release Report In accordance with Facility Operation License No. DPR-45, Quality Assurance Program Description (QAPD) Appendix C, Section 2.5.1, "Annual Radiological Environmental Monitoring Report," and Section 2.5.2, "Annual Radioactive Effluent Release Report," this letter submits these reports for the year 2018. The reports are required to be submitted prior to March 1 per QAPD Appendix C, Section 2.5 "Reporting Requirements," and are provided as enclosures to this letter.
The Radiological Effluent Release Report also contains changes to the Offsite Dose Calculation Manual (ODCM) per the requirements of QAPD Appendix C, Section 2.2, "Offsite Dose Calculation Manual." There were no changes to the Process Control Program for this reporting period. All revisions to the ODCM approved since the last report are provided as enclosures to this letter.
There are no new regulatory commitments in this submittal.
If you have any questions about this submittal please contact Mr. Joseph Jacobsen at (608) 689-4259.
Respectfully, G~"v'1h-.~
Gerard van Noordennen Vice President Regulatory Affairs S4601 State Highway 35, Genoa, WI 54632
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LaCrosseSolutions LC-2019-0007 Page 2 of2 Attachments:
- 2. LACBWR Offsite Dose Calculation Manual, Revision 5
- 3. LACBWR Offsite Dose Calculation Manual, Revision 6
- 4. LACBWR Offsite Dose Calculation Manual, Revision 7 cc:
Marlayna Vaaler, U.S. NRC Project Manager Regional Administrator, U.S. NRC, Region III Service List (Cover letter only, no attachments)
La Crosse Boiling Water Reactor Service List cc:
Ken Robuck President and CEO Energy Solutions 299 South Main Street, Suite 1700 Salt Lake City, UT 84111 John Sauger Executive VP and Chief Nuclear Officer ReactorD &D Energy Solutions 121 W. Trade Street, Suite 2700.
Charlotte, NC 28202 Joseph Nowak General Manager LaCrosseSolutions S4601 State Highway 3 5 Genoa, WI 54632-8846 Gerard van Noordennen VP Regulatory Affairs Energy Solutions 121 W. Trade Street, Suite 2700 Charlotte, NC 28202 Russ Workman General Counsel Energy Solutions 299 South Main Street, Suite 1700 Salt Lake City, UT 84111 Jerome Pedretti, Clerk Town of Genoa E860 Mundsack Road Genoa, WI 54632 Jeffery Kitsembel Division of Energy Regulation Wisconsin Public Service Commission P.O. Box 7854 Madison, WI 53707-7854 Paul Schmidt, Manager Radiation Protection Section Bureau of Environmental and Occupational Health Division of Public Health Wisconsin Department of Health Services P.O. Box 2659 Madison, WI 53701-2659 Barbara Nick President and CEO Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54602-0817 Cheryl Olson, ISFSI Manager La Crosse Boiling Water Reactor Dairyland Power Cooperative S4601 State Highway 35 P.O. Box 817 Genoa, WI54632-8846 Lane Peters La Crosse Boiling Water Reactor Dairyland Power Cooperative S4601 State Highway 35 Genoa, WI54632-8846 Thomas Zaremba Wheeler, Van Sickle and Anderson, S.C.
44 East Mifflin Street, Suite 1000 Madison, WI 53703 John E. Matthews Morgan, Lewis & Bockius LLP 1111 Pennsylvania A venue, NW Washington, DC 20004
(
LaCrosseSolutions LC-2019-0007: Attachments LACBWR Annual Radiological Environmental Operating Report
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR THE LA CROSSE BOILING WATER REACTOR (LACBWR)
(January 1 to December 31, 2018)
LACROSSESOLUT/ONS S4601 STATE HIGHWAY 35 GENOA, WI 54632 Page 1 of 55
TABLE OF CONTENTS SECTION A: RADIOACTIVE EFFLUENT REPORT Section Title Introduction.................................................................................
5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0
- Regulatory Limits........................................................................
Effluent Release Concentration Limit..........................................
Average Energy..........................................................................
Analytical Methods......................................................................
Releases.....................................................................................
Abnormal Releases....................................................................
Estimated Total Analytical Error..................................................
Offsite Dose Calculation Summary and Conclusions..................
Offsite Dose Ca1c*u1ation Manual (ODCM) Review......................
Process Control Program (PCP) Review......................,.............
Errata Data.................................................................................
SECTION A: RADIOACTIVE EFFLUENT REPORT 6
8 8
8 9
10 11
.16
- 17 20 20 Table No.
Title Page 1A Effluent and Waste Disposal -Airborne Particulate Effluents Summation of All Releases.........................................................
11 1 B Effluent and Waste Disposal - Airborne Particulate Effluents Ground Level Release................................................................
12 2A Effluent and Waste Disposal - Liquid Effluents Summation of All Releases.........................................................
13 28 Effluent and Waste Disposal - Liquid Effluents_..........................
14 3
Effluent and Waste Disposal 2018 Solid Waste and Irradiated Fuel Shipments...................................................................................
15 Page 2 of 55
SECTION B: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Section Title Introduction.................................................................................
22 1.0 2.0 3.0 4.0 -- -- _
Sample Collection.......................................................................
Results of the 2018 Environmental Monitoring Survey...............
Conclusions................................................................................
lnterlaboratory Comparison Program Results.............................
SECTION B: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 23 24 27 28 Table No.
Title Page 4
ISFSI Environmental TLD Locations.........................................
33 5
Sample Frequency and Analysis of Radio Environmental Samples 34 6
Low Volume Environmental Air Monitoring Station Locations 35 7
LACBWR Environmental TLD Locations......................................
36 8
Radiological Environmental Samples Collected 37 9
Quarterly Environmental TLD Results in LACBWR Vicinity........
38 1 O Bi-Weekly Gross Beta Environmental Air Sample Analysis Results 39 11 Bi-Weekly Gamma Spec Env. Air Sample Analysis Results.......
40 12 Semi Annual Mississippi River Water Analysis Results..............
53 13 14 Semi Annual Mississippi River Sediment Analysis Results.........
Quarterly Environmental TLD Results for ISFSI Area.................
SECTION B: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Figure No.
Title 1
2 3
4 LACBWR Property Map..............................................................
LACBWR Environmental Air Sampler Locations.........................
LACBWR RCA Fence Line Environmental TLD Locations.........
ISFSI Environmental TLD Locations..........................................
Page 3 of 55 54 55 29 30 31 32
SECTION A RADIOACTIVE EFFLUENT REPORT Page 4 of 55
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 the DPC 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 until 1987.
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 Independent Spent Fuel Storage Installation (ISFSI).
In June of 2016 DPC, working with the selected decommissioning contractor LaCrosseSolutions LLC, transferred their NRG License to LaCrosseSolutions LLC for the purposes of decommissioning the site to unconditional release criteria, per license termination plan criteria.
In accordance with LC-RP-PG-004 "Radiological Environmental Monitoring Program and Preparation of the Annual Radiological Environmental Operating Report", this document is the Annual Radiological Environmental Operating Report (AREOR) for the Period January 1 through December 31, 2018.
Page 5 of 55
Radioactive Effluent Report EFFLUENT AND WASTE DISPOSAL REPORT (Supplemental Information)
FACILITY: La Crosse Boiling Water Reactor LICENSEE: LaCrosseSolutions LICENSE NO. DPR-45 DOCKET NO. 50-409 & 72-046 1.0 REGULATORY LIMITS 1.1 Airborne Effluent Release Limits:
LACBWR airborne particulates, with half-lives greater than 8 days, released to areas beyond the Effluent Release Boundary shall be limited to</= 7.5 mRem to any organ per calendar quarter and</= to 15 mRem to any organ per calendar year(1 OCFR50 Appendix I). The cumulative dose contributions from airborne particulate effluent releases are determined in accordance with the LaCrosseSolutions, LLC Offsite Dose Calculational Manual (ODCM).
Additionally, for gaseous effluents of beta radiation in the form of tritium for beyond the Effluent Release Boundary shall be limited to 10 mRad per calendar quarter and 20 mRad per calendar year (10CFR50 Appendix l).The annual values for airborne effluent releases are reported in Table 1A and 1 B.
Also, in accordance with the provisions of 40 CFR 190, the restrictions for total dose to any member of the public from all LACBWR related sources and dose pathways are evaluated quarterly and on an annual basis.
1.2 Liquid Effluent Release Limits:
LACBWR's liquid effluent release limitations are those concentrations specified in 10 CFR 20 Appendix B, Table 2, Column 2. The values reported in Tables 2A and 28, 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.
Page 6 of 55
Radioactive Effluent Report 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. The cumulative dose contributions from liquid effluent releases are determined in accordance with the LaCrosseSolutions, LLC Offsite Dose Calculational Manual.
In accordance with the provisions of 40 CFR 190, the restrictions for total dose to any member of the public from all LACBWR related sources and dose pathways are evaluated quarterly and on an annual basis.
1.3 Solid Radioactive Waste All solid radioactive wastes are handled in accordance with a Process Control Program as defined by LaCrosseSolutions, LLC procedures, in order to assure that all applicable transportation and burial site disposal requirements are met.
Table 3 summarizes the annual solid radioactive waste shipment/ disposal statistics for the site.
Page 7 of 55
Radioactive Effluent Report 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 1 or 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 monitor tank prior to discharge. In addition, each batch monitor tank sample is.analyzed for gross beta and gross alpha as well as tritium activity concentrations. using site approved bench top af1alysis equipment. A composite sample is created_by collecting representative aliquots from e~ch tank batch discharged during a calendar quarter. This composite is analyzed for: lron-55, Strontium-90, Nickel-59, Nickel-63; Americium-241, Plutonium-238, Plutonium 239/240, and Plutonium
-241 by an off-site contractor on a quarterly basis.
4.2 Airborne Particulates Airborne particulate releases are determined by HPGe gamma isotopic analysis and gross beta and gross alpha analyses of glass fiber filter paper taken from low volume air samplers placed either in prevailing downwind locations or in representative sampling locations on HEPA exhaust systems. The filter paper is change out weekly and analyzed approximately a week.later.
Page 8 of 55
Radioactive Effluent Report 5.0 RELEASES 5.1 Airborne To demonstrate compliance with the limits in Section 1.1 dose contributions have been calculated using a bounding assessment as described in Regulatory Guide 1.21. This analysis is summarized in the current Offsite Dose Calculation Manual. Routine low volume air sampling is in place at four locations outside the RCA in the predominant typical downwind locations, to be used to demonstrate compliance with dose limits in Section 1.1. Any HEPA system exhausting to the outside environment has representative air sampling performed of the exhaust air following passing thru the HEPA system also for the purposes of demonstrating compliance with Section 1.1.
5.2 Liquid All liquid effluent releases at LACBWR are batch releases as described in the ODCM other than the summary below on the tritium release event to the shallow*
groundwater layer inside the posted RCA boundary and subsequently to the Mississippi River. The batch releases are summarized as follows:
(1)
Number of Batch Releases:
(2)
Total Time Period for Batch Releases:
193 hours0.00223 days <br />0.0536 hours <br />3.191138e-4 weeks <br />7.34365e-5 months <br /> (3)
Maximum Time Period for a Batch Release:
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (4)
Average Time Period for a Batch Release:
5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (5)
Minimum Time Period for a Batch Release:
2.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> (6)
Average Stream Flow Rate During Periods of 67,600 tt3/sec Release of Effluent into a Flowing Stream:
Discovery of a ground level surface water source of runoff water contaminated with elemental tritium and a pathway to the shallow groundwater layer in the RCA via an open excavation area was reported to the USNRC and Wisconsin Department of Natural Resources (WDNR) on March 14, 2018. The ground level surface water runoff source of tritium and the release pathway to the shallow groundwater layer was secured, and a hydro-geological contractor initiated an investigation to evaluate the extent of the elemental tritium release in the shallow groundwater layer including Page 9 of 55
Radioactive Effluent Report its movement to the Mississippi River outside of the RCA as well as vertical movement in the groundwater layers. The investigation has been completed and documented. The results of the investigation show no significant vertical movement of the elemental tritium thru the groundwater layers and an ultimate release estimated at approximately 920,000 gallons of water containing elemental tritium to the Mississippi River thru the shallow groundwater layer at an average activity level of 3000 pCi/Liter. The release period has been estimated as a time period of March 1, 2018 to the first week of December 2018 at which time the elemental tritium levels are now estimated to be at laboratory minimum detectable limits of 500 pCi/L. The calculated release dose of the estimated 920,000 gallons of water has been evaluated using the logic of the batch release but assuming no G-3 Coal Plant condenser cooling water dilution nor Mississippi River mixing zone dHution.
6.0 ABNORMAL RELEASES There were no abnormal releases of radioactivity in plant effluents which exceeded release limits.
Page 10 of 55
A.
- 1.
- 2.
- 3.
- 4.
B.
- 1.
Radioactive Effluent Report 7.0 ESTIMATED TOTAL ANALYTICAL ERROR The reported analytical results contain the following estimated errors:
Counting Error 95% Confidence Level Sampling Volume Error+/- 5%.
TABLE1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2018 AIRBORNE-PARTCULATE EFFLUENTS-SUMMATION OF ALL RELEASES UNIT QTR QTR QTR QTR TOTAL 1
2 3
4 PARTICULATES BETA-GAMMA PARTICULATES 1.082 1.082 7.21 2.885E-WITH HALF-LIVES-LIVES> 8 Ci E-04 E-04 3E-0 04 DAYS 05 AVERAGE RELEASE RA TE FOR
µCi/Sec 1.374 1.374 9.16 0
PERIOD E-05 E-05 E-06 GROSS ALPHA RADIOACTIVITY Ci 1.026 1.026 6.85 0
2.737E-E-07 E-07 E-08 07 TRITIUM Ci 2.495 2.495 1.66 0
6.652 2
PERCENTAGE OF ODCM DOSE LIMITS FOR PARTICULATE EFFLUENT RELEASES QTR I QTR I QTR QTR YEARLY ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8DAYS HIGHEST ORGAN % LIMIT 37% I 37%
I 25%
0 50%
NOTE: For tritium airborne releases averaged 3.15E-05 mRad/quarter and overall for the year released a total of 8.40E-05 mRad.
Page 11 of 55
Radioactive Effluent Report TABLE 18 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2018 AIRBORNE PARTICULATE EFFLUENTS-GROUND LEVEL RELEASE CONTINUOUS OR BATCH MODE UNIT QTR1 QTR2 QTR3 QTR4 TOTAL NUCLIDES RELEASED
- 1.
PARTICULATES Fe-55 Ci 1.350E-07 1.350E-07 8.900E-08 0
3.590E-07 Ni-59 Ci 1.265E-06 1.265E-06 8.430E-07 0
3.373E-06 Co-60 Ci 6.750E-06 6.750E-06 4.500E-06 0
1.800E-05 Ni-63 Ci 8.404E-06 8.404E-06 5.603E-06 0
2.241E-05.
Sr-90 Ci 8.450E-07 8.450E-07 5.640E-07 0
2.254E-06 Nb-~4 Ci 1.600E-08 1.600E-08 1.100E-08 0
4.300E-08 Tc-99 Ci 4.883E-09 4.883E-09 3.255E-09 0
1.302E-08 Cs-137 Ci 9.308E-06 9.308E-06 6.205E-06 0
2.482E-05 Eu-152 Ci 7.785E-05 7.785E-05 5.190E-05 0
2.076E-04 Eu-154 Ci 3.365E-06 3.365E-06 2.244E-06 0
8.974E-06 Eu-155 Ci 3.375E-08 3.375E-08 2.250E-08 0
9.000E-08 Np-237 Ci 3.741E-08 3.741E-08 2.493E-08 0
9.975E-08 Pu-238 Ci 1.265E-08 1.265E-08 8.433E-09 0
3.373E-08 Pu-239/240 Ci 1.181 E-08 1.181 E-08 7.8709E-09 0
3.149E-08 Pu-241 Ci 2.120E-07 2.120E-07 1.412E-07 0
5.652E-07 Am-241 Ci 3.593E-08 3.593E-08 2.395E-08 0
9.581 E-08 Am-243 Ci 2.148E-09 2.148E-09 1.433E-09 0
5.729E-09 Cm-243/244 Ci 2.693 E-09 2.693E-09 1.795E-09 0
7.181 E-09 Gases Tritium-Ci 2.495 2.495 1.662 0
6.652 TOTAL Ci 2.495 2.495 1.662 0
6.652 Page 12 of 55
A
- 1.
- 2.
B.
- 1.
C.
D.
- 1.
E.
F.
G.
Radioactive Effluent Report TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2018 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR1 QTR2 I QTR3 QTR4 FISSION & ACTIVATION PRODUCTS TOTAL RELEASE (NOT INCL.
Ci 4.43E-05 1.49E-03 1.37E-04 7.96E-06
- J"RITIUM,ALPHA)
~VERAGE DILUTED CONCENTRATION DURING
µCi/ml 1.33E-09 6.12E-09 2.68E-10 7.03E-12 PERIOD TRITIUM rT"OTAL RELEASE-batch releases Ci 2.98E-05 1.16E-01 1.12E-02 2.61E-03 onlv
~VERAGE DILUTED CONCENTRATION DURING
µCi/ml 8.97E-10 4.77E-07 2.20E-08 2.31E-09 PERIOD DISSOLVED AND ENTRAINED GASES-no releases - no longer analyzed for.
GROSS ALPHA RADIOACTIVITY TOT AL RELEASE Ci 1.90E-08 0
0 0
VOLUME OF WASTE RELEASED (PRIOR TO Liters 1.42E+04 2.31E+05 5.38E+05 1.26E+06 DILUTION)
VOLUME OF DILUTION WATER USED DURING Liters 3.32E+07 2.43E+08 5.12E+08 1.13E+09 PERIOD PERCENTAGE OF ODCM LIMITS FOR LIQUID RELEASES*
QTR QTR QTR QTR HIGHEST ORGAN 0.06%
1.54%
0.17%
0.03%
WHOLE BODY 0.13%
3.34%
0.39%
0.08%
- Includes direct release of groundwater with tritium to the river Page 13 of 55 TOTAL 1.68E-03 8.73E-10
- 1.30E-01 6.SOE-08 1.90E-08 2.04E+06 1.92E+09 YEARLY 0.90%
1.97%
Radioactive Effluent Report TABLE 28 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2018 LIQUID EFFLUENTS Fe-55 Ci 0.0 0.0 0.0 0.0 Ni-59 Ci 0.0 0.0 0.0 0.0 Co-60 Ci 0.0 0.0 0.0 0.0 Ni-63 Ci 0.0 1.69E-05 0.0 0.0 Sr-90 Ci 0.0 9.10E-05 1.73E-05 5.52E-06 Cs-137 Ci 4.43E-05 1.38E-03 1.20E-04 2.44E-06 Pu-238 Ci
. 0.0 0.0 0.0 0.0 Pu-239/240 Ci 5.81 E-09 0.0 0.0 0.0 Pu-241 Ci 0.0 0.0 0.0 0.0 Am-241 Ci 1.32E-08 0.0 0.0 0.0 Tritium-includes tritium directly released to river Ci 1.19E-03 1.19E-01 1.47E-02 4.63E-3E-03 b
roundwater TOTAL FOR PERIOD Ci 1.23E-03 1.20E-01 1.48E-02 4.632E-03 (ABOVE)
Page 14 of 55
Radioactive Effluent Report TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2018 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL (Not Irradiated Fuel)
- 1. TYPE OF WASTE
- a. Spent resins, filter sludges, evaporator bottoms, etc.
m3 0
0 0
- b. Dry compressible waste, contaminated equipment, etc.
- c. Irradiated components, control rods, etc.
- d. Other
- 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)
Cs-137 Fe-55 Ni-63 H-3 Pu-241 Co-60 C-14 Sr-90 Tc-99
- NOTE: showing all nuclides >1 % of total
- 3. SOLID WASTE DISPOSITION Ci m3 Ci m3 Ci m3 Ci 32.05%
11.66 26.79 7.18 4.07 13.12 1.72 1.49 1.09 MODE OF 0
9,676 203.602 0.00 0.00 0
0 65.84 23.95 54.02 14.77 8.32 26.19 3.54 3.05 2.21 NO. OF SHIPMENTS TRANSPORTATION 1425 Truck and Rail B.
IRRADIATED FUEL SHIPMENTS (DISPOSITION)
NO OF SHIPMENTS NONE MODE OF TRANSPORTATION Page 15 of 55 0
0 6,778 16454 2.028 205.630 0
0 0
0 0.00 0
0.00 0
0.07
+/- 10 0.02
+/- 10 1.07
+/- 10 0
+/- 10 0.05
+/- 10 0.79
+/- 10 0
+/- 10 0
+/-10 0.02
+/- 10 DESTINATION Clive, UT DESTINATION
Radioactive Effluent Report 8.0 OFFSITE DOSE CALCULATIONS
SUMMARY
AND CONCLUSIONS:
8.1 Particulate/Gaseous Effluent Releases The maximum quarterly offsite dose to any organ from the release of all radionuclides in particulate form with half-lives greater than 8 days was 2.78 mRem. The cumulative 2018 annual maximum organ dose from these radionuclides was also 7.50 mRem. The maximum quarterly offsite dose from gaseous beta emitters in the form of tritium is 3.15E-05 mRad/quarter and overall for the year released a total of 8.40E-05 mRad.
8.2 Liquid Effluent Releases The maximum quarterly organ dose from liquid releases was approximately 7.7E-02 mRem. The cumulative 2018 annual organ dose was approximately 9.0E-02 mRem. The maximum quarterly total body dose for liquid releases was approximately 5.0E-02 mRem, and the cumulative 2018 annual total body dose was approximately 5.91 E-02 mRem.
8.3 Conclusion All calculated offsite doses were below all ODCM limits for airborne, liquid, and ambient radiation.
Page 16 of 55
Radioactive Effluent Report 9.0 OFFSITE DOSE CALCULATION MANUAL {ODCM) REVIEW List of Changes to the ODCM In accordance with ODCM Section 4.6 the following is a summary of changes made to the ODCM thru the revision process during CY 2018 which verified that the level of radioactive effluent controls will be maintained as well as not adversely impact the accuracy or reliability of effluent, dose, or set point calculations.
- A summarized list of the changes is presented here, along with a complete copy of the affected ODCM revisions.
- 1. ODCM Revision 5 Page Section Change Summary Added revised bounding airborne release model details/
4 Summary results including for tritium. The bounding airborne release model follows Reg. Guide 1.21 requirements.
5 References Added 2.16 LC-RP-TSD-004 Rev 1 "La Crosse Bounding Airborne Release Assessment".
14 4.1.6 Clarified terms used in formula for the temporary ventilation units calculations.
15 4.2.1 and 4.2.3 Added tritium to the discussions.
Added tritium into discussions and Appendix I of 10 CFR 18-20 4.2.5 Part 50 release requirements for gaseous effluents of beta radiation.
21 4.2.5/B.2/3 Corrected average to weekly.
Updated this section to incorporate the tritium analyses performed in LC-RP-TSD-004 Rev 1as well as to 38-40 Appendix A incorporate the potential curie content release by nuclide and associated dose assessment analyses of adding a two week time interval to take down and remove the bio-shield wall in the Reactor Building.
Page 17 of 55
Radioactive Effluent Report
- 2. ODCM Revision 6 Page Section Change Summary 4
Summary Added requirements for the use of dewatering operations inside the RCA to remove rainwater and groundwater from open excavation areas by the use of a system of wells. The wells discharge would be directed to the Mississippi River normal liquids discharge NPDES location.
6 3.1-definitions Defined specifically the types of release: a batch release and dewatering operations release.
10-11 4.1 Introduced concepts of dewatering operations as it applies to release of groundwater from the RCA.
13 4.1.3 Added details to section to specify during dewatering operations that will obtain and analyze samples.
16 4.2.2 Specify that during dewatering operations will perform sampling and analysis of samples.
17-18 4.2.4.A.3 Added to address the specific daily type routine sampling requirements for dewatering operations including limits.
Gross alpha and Gross Beta limits set at 10% of the MPG values provided in ODCM for Am-241 and Sr-90 respectively.
19 4.2.4.B.4 Added to address the weekly sampling requirements for dewatering operations to verify that are less than 50% of the MPG concentrations specified in Appendix B, Table 2, Column 2 of 1 OCFR20 at the release point into the Mississippi River.
20 4.2.4.C.4 Added to provide details to the basis for the limits and methods used in Section 4.2.4.A.3 for dewatering operations.
36 Table 5.2 Clarified the table is to be used for batch releases.
Page 18 of 55
Radioactive Effluent Report
- 3. ODCM Revision 7 Page Section Description of change 4
Summary Added details to be able to run pump down operations where use a sump pump to pump out groundwater and rainwater intrusions from excavation areas inside the RCA to the temporary discharge piping to the NPDES release point in the Mississippi River.
7 3.1 Define Pump Down Operations 15 4.2.2 Define sampling requirements for pump down operations 16 4.2.4.A.2 Added pump down operations requirements for the presence of dilution flow from the G-3 Coal Plant condensate system as well as wastewater discharge flow limits 18 4.2.4.B.1 Added the specifications for the wastewater discharge pump to be used with pump down operations 18 4.2.4.B.2 and Specified minimum G-3 Coal Plant condensate dilution 4.2.4.B.3 flow requirements and sampling/ analyses/approval requirements for pump ~fown water prior to discharging pump down water to the Mississippi River NP DES release point area.
19 4.2.4.C.2 Specifies the conservative dilution factor to be applied when analyzing pump down water sampling data for compliant waste water release discharges.
The ODCM Revisions 5, 6, and 7 are attached with this report.
Page 19 of 55
Radioactive Effluent Report 10.0 PROCESS CONTROL PROGRAM (PCP) REVIEW The LaCrosseSolutions, LLC PCP was not revised in 2018.
11.0 Errata Data None.
Page 20 of 55
SECTION B ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Page 21 of 55
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 Part 50.36a 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 background locations.
The monitoring program at the LACBWR facility includes monitoring of liquid and airborne particulate releases from the plant, as well as collecting environmental samples of surface air, river water, river sediment, and ambient radiation.
The REM program therefore supplements the Radioactive Effluent ~nalyses 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 (ODCM).
An lnterlaboratory 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.
Page 22 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 1.0 SAMPLE COLLECTION Environmental samples are collected from the area surrounding LACBWR at the frequencies outlined in the ODCM and the Environmental Monitoring Program. A series of figures and tables are included in this report to explain the LACBWR environmental program.
FIGURE 1 FIGURE 2 FIGURE 3 FIGURE4 TABLE 4 TABLE 5 TABLE 6 TABLE 7 TABLE 8 TABLE 9 TABLE10 TABLE 11 This map includes the plant exclusion boundary, roads, other generation plants, and the relationship of the plant to the nearest local community.
This map shows the location of the LACBWR RCA Fence Line Area Environmental TLD Locations.
These maps show the location of environmental low volume air sampler locations.
This map shows the location of ISFSI environmehtalTLDs.
This table logs the environmental TLD locations at the ISFSI.
This table shows the sampling frequency of the various environmental samples and the analyses performed on these samples This table shows the environmental air monitoring stations used in LACBWR's environmental program.
This table logs the LACBWR environmental TLD locations.
This table shows the number of various samples collected and analyzed during 2018.
Quarterly Environmental TLD results for LACBWR Area Bi-Weekly Gross Beta Env. Air Sample Analysis Results for LACBWR Vicinity Bi-weekly Gamma Spec Env. Air Sample Analysis Results for LACBWR Vicinity Page 23 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 12 TABLE 13 TABLE 14 Semi Annual Mississippi River Water Analysis Results Semi Annual Mississippi River Sediment Analysis Results Quarterly Environmental TLD results for ISFSI Area 2.0 RESULTS OF THE 2018 ENVIRONMENTAL MONITORING SURVEYS During 2018, activity levels in the local environment were trending normal, indicating no significant plant attributed radioactivity.
Page 24 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 2.1 PENETRATING RADIATION The environmental penetrating radiation dose is measured by environmental TLDs.
2.1.1 LACBWR Plant - These environmental TLDs were changed on a quarterly basis. The results for the LACBWR Plant from 2018 are shown on Table 9.
2.1.2 ISFSI - These environmental TLDs are changed on a quarterly basis. Table 14 results for 2018 are shown. During CY 2018 TLD packet locations for #6 and #9 were reversed for the four quarterly changeouts. This was caused by a new changeout radiation protection technician using an incorrect ISFSI location figure from an operating procedure during the changeout operation to guide the changeout process in the field and as a result the #6 and #9 TLDs were reversed (based on the used ISFSI location figure). The operating procedure figure has been corrected and the CY 2019 first quarter TLDs are in there proper location. The impact tied to environmental dose consequences is insignificant as both TLD locations #6 and #9 routinely report on quarterly reads at or below background values.
Page 25 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 2.2 AIR PARTICULATE Air samples were collected continuously from various sites (see Figure 3) around LACBWR. Low volume particulate air samplers were used to co"llect air samples.
The air filter consists of a glass fiber filter with an associated pore size of approximately 0.45 µm. The particulate filters were analyzed bi-weekly for gross beta activity with an internal proportional counter, as well as analyzed by gamma spectroscopy for individual isotopic concentration.
TABLE 10 This table shows the bi-weekly gross beta gamma activity concentration from the air particulate filters.
TABLE 11 This table shows the individual air sample particulate isotopic analysis results.
Page 26 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 2.3 RIVER WATER River water is collected semi-annually. River water samples before the intake structure, at plant outfall, and below the plant outfall are collected and are gamma analyzed for isotopic concentration and tritium analysis. The river water gamma isotopic analysis results are shown in Table 12. The results indicate that there were no significant plant attributable radionuclides in the river water.
2.4 SEDIMENT SAMPLES Sediment samples are collected semi-annually before the intake structure, at plant outfall, and below the plant outfall. These samples are gamma analyzed and these results appear on Table 13. They indicated that small amounts of plant-attributed radionuclides have accumulated in river sediments near the outfall. The amount of radionuclides in the sediment has declined significantly
.after plant shutdown. These amounts have remained relatively constant the last few years.
3.0 CONCLUSION
S All environmental samples collected and analyzed during 2018 exhibited no significant contribution from LACBWR or ISFSI operations.
Page 27 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 4.0 INTERLABORATORY COMPARISON PROGRAM RESULTS During 2018, 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 are the results of these comparisons.
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GROSS BETA 204 pCi 210 pCi 0.97 GROSS ALPHA 34.6 pCi 39.6 pCi 0.87 1-131 90.1 pCi/1 80.4 pCi/1 1.12 Cr-51 295 pCi/1 278 pCi/1 1.06 Cs-134 153 pCi/1 160 pCi/1 0.96 Cs-137 128 pCi/1 113 pCi/1 1.14 Co-58 124 pCi/1 111 pCi/1 1.12 Mn-54.
170 pCi/1 144 pCi/1.
1.18 Fe-59
- 125 pCi/1 107 pCi/1-1.17 Zn-65 298_pCi/l 246 pCi/1 1.21 Co-60 214 pCi/1 198 pCi/1 1.08 H-3 18700 pCi/1 14500 pCi/1 1.29 Page 28 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
./
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ll*67S FIGURE 1 - LACBWR PROPERTY MAP LOCATION-MAP LOT 7 NOTt* ISLAND 126 IS UNDER THE
.rURISDICTION OF UPPER MISSISSIPPl RIVER WILD INlillCIIU.S J,llLES AIIOVE tttt UF'E AND FISH liEFUGE.
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MOU'lt! OF TttE 01110 RIVER.
Page 29 of 55 LOT~
29i2B 32 33 LOT i DCLUSION-BOUNDAI 1109 ft radiiu 1t WEll LIMITS T.-13-N., R.-7-W.
- l WELLS OF THE 4th P.M.
oTOWN OF GENO; 3 :_ VERNON COUNTY\\
'Ii LOT 4 WELL
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)
EJ FIGURE 2 - LACBWR RCA FENCELINE ENVIRONMENTAL TLD LOCATIONS 9
Page 30 of 55
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ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT FIGURE 3 - LACBWR ENVIRONMENTAL AIR SAMPLER LOCATIONS I I I
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-. I LOCATION-MAP 102!..,,;;,;90~~--~oo
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SCALE OF FEET T.*IOl*N., R:-3*W.
OF THE 5th P.M.
- JEFFERSON TOWNSHIP.
HOUSTON COUNTY, MINNESOTA SEC. 7 SEc..,e LOT 7 NOTE* ISLAND 126 IS UNDER TH£
.IURISOICTION OF UPPER Mlrui1SSIPPI RIVER WILD INGICULS MILES ABOVE Tttt llF'E AAO FISH REFUGE.
t,,;0Ult1 OF lttE OIIIG filVE.R.
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Page 31 of 55 f VILLAGE 06 r~.!~E-~~.J G(NOA LOT\\.
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- WELfs OF THE 4th P.M.
oTOWN OF GENOA VERNON COUNTY\\
WISCONSIN 1i LOT 4 WELL
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ill
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ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 4 ISFSI ENVIRONMENTAL TLD LOCATIONS 1
ISFSI ADMINISTRATIVE BUILDING WEST 2
ISFSI PROTECTED AREA NORTH EAST SIDE 3
ISFSI PROTECTED AREA NORTH WEST SIDE 4
ISFSI PROTECTED AREA SOUTH WEST SIDE 5
ISFSI PROTECTED AREA SOUTH EAST SIDE 6
ISFSI OWNER CONTROLLED FENCE NORTH 7
ISFSI OWNER CONTROLLED FENCE WEST 8
ISFSI OWNER CONTROLLED FENCE EAST 9
ISFSI OWNER CONTROLLED FENCE NORTH EAST BY HEAVY HAUL PATH 10 ISFSI OWNER CONTROLLED FENCE WEST BY BOAT LANDING Page 33 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 5 SAMPLE FREQUENCY AND ANALYSIS OF RADIOLOGICAL ENVIRONMENTAL SAMPLES Environmental Quarterly TLDs Particulate Air -
Bi-Weekly Glass Fiber Filters River Sediment Semi-annually River Water Semi-annually Page 34 of 55 Dose in mRem Gross Beta and Gamma Spectroscopy Gamma Spectroscopy Gamma Spectroscopy and Tritium (Liquid Scintillation Analyzer)
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 6 LOW VOLUME ENVIRONMENTAL AIR MONITORING STATION LOCATIONS (Refer to Figure 3) 1 Trailer Park 2
Coal Plant - North Side 3
North of Main Switch Yard 4
Lock and Dam #8 - North Side Page 35 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 7 LACBWR ENVIRONMENTAL TLD LOCATIONS 1
ADMINISTRATION BUILDING VAULT WEST END 2
RCA FENCE LINE NORTH 3
RCA FENCELINE SOUTHEAST 4
RCA FENCELINE SOUTH 5
RCA FENCE LINE SOUTHWEST 6
RCA FENCE LINE WEST G-3 Crib House Barge Wash Break Shack G-3 Control Room LACBWR Warehouse Modular Meeting Trailer-East of LACBWR Admin Building Page 36 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 8 RADIOLOGICAL ENVIRONMENTAL SAMPLES COLLECTED JANUARY-DECEMBER 2018 Penetrating Radiation(Environmental TLDs) 84 Air Particulate 104 River Water 6
River Sediment 6
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Page 37 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 9 QUARTERLY ENVIRONMENTAL TLD RESULTS IN THE LACBWR VICINITY JANUARY-DECEMBER 2018 1 (*)
BKG BKG
<0.10
<BKG 2(*)
<0.10
<0.10
<BKG
<BKG 3(*)
0.33 0.10
<BKG
<BKG 4(*)
<0.10
.BKG
<BKG
<BKG 5(*)
<BKG
<BKG
<BKG
<BKG 6(*)
<BKG
<BKG
<BKG
<BKG G-3 Crib House
<BKG
<BKG
<BKG
<BKG Barge Wash
<BKG
<BKG
<BKG
<BKG Break Shack G-3 *Control
<BKG
<BKG
<BKG
<BKG Room LACBWR
<BKG
<BKG
<BKG
<BKG Warehouse Modular *
<BKG
<BKG
<BKG
<BKG Meeting Trail~r-East of LACBWR Admin Building ALL BACKGROUND (BKG) CORRECTED RESULTS AND IF WITH (*) ON RCA FENCELINE HAD OCCUPANCY CORRECTION FACTOR APPLIED IF>
BACKGROUND TLD RESULTS Page 38 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE10 Bl-WEEKLY GROSS BETA ENVIRONMENTAL AIR SAMPLE RESULTS
- t~~lt~~~ i~t1~~1~~
- ~i~~;~~~~WJil~~~~~~t~~~i~l~
1-03-2018
.018 +/-.001
.023 +/-.001
.014 +/-.001
.020 +/-.001 1-17-2018
.019 +/-.001
.026 +/-.001
.017 +/-.001
.018 +/-.001 1-31-2018
.018+/-.001
.021 +/-.001
.017 +/-.001
.016 +/-.001 2-14-2018
.014 +/-.001
.021 +/-.001
.017 +/-.001
.015 +/-.001 2-28-2018
.015 +/-.001
.016 +/-.001
.019 +/-.001
.019 +/-.001 3-14-2018
.013 +/-.001
.014 +/-.001
.010 +/-.001
.013 +/-.001 3-28-2018
.013 +/-.002
.013 +/-.002
.014 +/-.002
.012 +/-.002 4-11-2018
.014 +/-.001
.014 +/-.001
.015 +/-.001
.017 +/-.002 4-25-2018
.017 +/-.002
.018 +/-.001
.017 +/-.001
.016 +/-.001 5-09-2018
.015 +/-.001
.017 +/-.001
.012 +/-.001
.014 +/-.001 5-23-201'8
.015 +/-.001
.014 +/-.001
.014 +/- :001
.014 +/-.001 6-06-201'8
.021 +/-.002
.022 +/-.002
.032 +/- :002
.017 +/-.001 6-20-2018
.016 +/-.001
.015 +/-.001
.014 +/-.001
.011 +/-.001 7-03-2018
.017 +/-.001
.014 +/-.001
.015+/-.001
.017 +/-.001 7-17-2018
.020 +/-.001
.028 +/-.001
.018 +/-.001
.014 +/-.001 8-01-2018
.016 +/-.001
.014 +/-.001
.015 +/-.001
.013 +/-.001 8-15-2018
.025 +/-.002
.025 +/-.002
.017 +/-.001
.020 +/-.001 8-29-2018
.023 +/-.001
.023 +/-.001
.016 +/-.002
.021 +/-.001 9-12-2018
.014 +/-.001
.014 +/-.001
.002 +/-.001
.001 +/-.001 9-26-2018
.018 +/-.002
.015 +/-.001
.015 +/--.002
.014 +/-.001 10-10-2018
.012+/-.001
.011 +/-.001
.001 +/-.001
.001 +/-.001 10-24-2018
.014 +/-.001
.011 +/-.001
.011 +/-.002
.012 +/-.001 11-07-2018
.013 +/-.001
.014 +/-.001
.013 +/-.001
.012 +/-.001 11-15-2018*
.017 +/-.002
.016 +/-.002
.013 +/-.001
.020 +/-.003 12-05-2018
.018 +/-.002
.017 +/-.002
.014 +/-.002
.017 +/-.001 12-19-2018
.032 +/-.002.
.035 +/-.002
.026 +/-.002
.028 +/-.002
- Air Samples pulled early due to site shutdown for holiday the next week
. Page 39 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 81-WEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN LOCATION SWITCHYARD pCi/m3 pCi/m3 pCi/m3 pCi/m3 START DATE 12-21-2017 12-21-20"17.
12-21-2017 12-21-2017 END DATE 1-03-2018 1-03-2018 1-03-2018 1-03-2018 ISOTOPES
- Cs-134
< 1.18 E-03
< 2.36 E-03
< 2.37 E-03
< 1.08 E-03 Cs-137
< 8.06E-04 2.19E-03 1.67E-03
< 8.86 E-04 Co-60
< 1.14 E-03
< 2.35 E-03
< 2.30 E-03
< 1.14 E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWITCHYARD START DATE 1-03-2018 1-03-2018 1-03-2018 1-03-2018 END DATE 1-17-2018 1-17-2018 1-17-2018 1-17-2018 ISOTOPES Cs-134
< 1.18 E-03
< 2.40 E-03
< 4.24 E-04
< 1.02 E-03 Cs-137
< 7.91 E-04 1.90 E-03
< 3.02 E-04 8.02E-04 Co-60
< 1.18 E-03
< 2.52 E-03
< 4.39 E-04
< 1.04 E-03 Page 40 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 Bl-WEEKLY GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT. LOCK AND DAM #8 SW MAIN SWITCHYARD START DATE 1-17-2018 1-17-2018 1-17-2018 1-17-2018 END DATE 1-31-2018 1-31-2018 1-31-2018 1-31-2018 ISOTOPES Cs-134
<1.11E-03
<2.53E-03
<2.40E-03
<1.00E-03 Cs-137 8.85E-04
<1.86E-03
<1.60E-03
<7.48E-04 Co-60
<1.13E-03
<2.43E-03
<2.40E-03
<1.07E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 1-31-2018 1-31-2018 1-31-2018 1-31-2018 END DATE 2-14-2018 2-14-2018 2-14-2018 2-14-2018 ISOTOPES Cs-134
<1.12E-03
<2.25E-03
<2.33E-03
<1.14E-03 Cs-137 1.03E-03 2.37E-03 2.10E-03 8.23E-04 Co-60
<1.0BE-03
<2.46E-03
<2.30E-03
<1.16E-03 Page 41 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 81-VVEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS' (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWITCHYARD START DATE 2-14-2018 2-14-2018 2-14-2018 2-14-2018 END DATE 2-28-2018.
2-28-2018 2-28-2018 2-28-2018 ISOTOPES Cs-134 *
<1.09E-03
<2.39E-03
<2.40E-03
<1.21E-03 Cs-137 1.36E-03 1.60E-03
<1.60E-03
<5.89E-04 Co-60
<1.13E-03
<2.39E-03
<2.40E-03
<1.22E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWITCHYARD START DATE 2-28-2018 2-28-2018 2-28-2018 2-28-2018 END DATE 3-14-2018 3-14-2018 3-14-2018 3-14-2018 ISOTOPES/RL
- Cs-134
<1.11 E-03
<2.63E-03
<2.32E-03
<1.01 E-03 Cs-137
<9.13E-04
<1.50E-03 :
<1.58E-03 8.20E-04 Co-60
<1.08E-03
<2.48E-03
<2.45E-03
<1.00E-03 Page 42 of 55
I i
I ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 81-WEEKL Y GAMMA SPEC ENV. AIR *SAMPLE ANALYSIS RESULTS (Con't)
I (Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWITCHYARD START DATE 3-14-2018 3-14-2018 3-14-2018 3-14-2018 END DATE 3-28-2018 3-28-2018 3-28-2018 3-28-2018 ISOTOPES Cs-134
<1.12E-03
<2.56E-03
<2.38E-03
<1.05E-03 Cs-137 1.20E-03
<1.44E-03 1.84E-03 7.31 E-04 Co-60
<1.11 E-03
<2.40E-03
<2.49E-03
<1.03E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM # 8 SW MAIN SWITCHYARD START DATE 3-28-2018 3-28-2018 3-28-2018 3-28-2018 END DATE 4-11-2018 4-11-2018 4-11-2018 4-11-2018 ISOTOPES Cs-134
<3.94E-03
<3.36E-03
<1.44E-03
<3.25E-03 Cs-137
<2.54E-03
<2.77E-03 1.25E-03 2.11 E-03 Co-60
<4.12E-03
<3.42E-03
<1.57E-03
<3.27E-03 Page 43 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11
- 81-WEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWITCHYARD START DATE 4-11-2018 4-11'."2018 4-1.1-2018 4-11-2018
- END DATE 4-25-2018 4-25-2018 4-25-2018 4-25-2018 ISOTOPES Cs-134
<3.95E-03
<3.36E-03
<1.43E-03
<3.18E-03 Cs-137
<4.14E-03
<3.53E-03
<1.53E-03
<3.23E-03 Co-60
<2.47E-03
<3.39E-03.
<9.01E-04
<3.22E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 4-25-2018 4-25-2018 4-25-2018 4-25-2018 END DATE
- 5-09-2018 5-09-2018 5-09-2018 5-09-2018 ISOTOPES Cs-134
<3.89E-03
<4.02E-03
<1.45E-03
<3.22E-03 Cs-137 4.94E-03
<2.55E-03 1.27E-03
<2.33E-03 Co-60
<4.10E-03
<4.21 E-03
<1.58E-03
<3.26E-03 Page 44 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 81-WEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 5-09-2018 5-09-2018 5-09-2018 5-09-2018 END DATE 5-23-2018 5-23-2018 5-23-2018 5-23-2018 ISOTOPES Cs-134
<3.84E-03
<3.22E-03
<1.48E-03
<3.22E-03 Cs-137 2.95E-03 2.52E-03 1.55E-03 2.52E-03 Co-60
<3.97E-03
<3.40E-03
<1.50E-03
<3.40E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 5-23-2018 5-23-2018 5-23-2018 5-23-2018 END DATE 6-06-2018 6-06-2018 6-06-2018 6-06-2018 ISOTOPES Cs-134
<3.97E-03
<3.34E-03
<1.65E-03
<3.21E-03 Cs-137
<3.25E-03 3.55E-03 4.69E-03
<2.64E-03 Co-60
<2.67E-03
<2.16E-03
<1.70E-03
<3.17E-03 Page 45 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 81-WEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS' (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 6-06-2018 6-06-2018 6-06-2018 6-06-2018 END DATE 6-20-2018 6-20-2018 6-20-2018 6-20-2018 ISOTOPES Cs-134
<4.00E-03
<3.43E-03
<1.55E-03
< 3.22E-03 Cs-137
<3.24E-03 1.99E-03 1.11E-03
<2.15E-03 Co-60
<4.09E-03
<3.56E-03
<1.57E-03
<3.20E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 6-20-201.8 6-20-2018.
6-20-2018 6-20-2018 END DATE 7-03-2018 7-03-2018 7-03-2018 7-03-2018 ISOTOPES Cs-134
<4.21E-03
<3.56E-03
<1.57E-03
<4.30E-03 Cs-137 3.43E-03
<2.74E-03
<1.67E-03 3.68E-03 Co-60
<4.46E-03
<3.78E-03
<1.72E-03
<2.33E-03 Page 46 of 55
I I
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 81-WEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESUL Ti (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 7-03-2018 7-03-2018 7-03-2018 7-03-2018 END DATE 7-17-2018 7-17-2018 7-17-2018 7-17-2018 ISOTOPES Cs-134
<3.98E-03
<3.20E-03
<2.16E-03
<2.78E-03 Cs-137
<4.03E-03
<3.24E-03
<1.84E-03
<2.43E-03 Co-60
<4.02E-03
<3.31 E-03
<2.13E-03
<2.77E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 7-17-2018 7-17-2018 7-17-2018 7-17-2018 END DATE 8-01-2018 8-01-2018 8-01-2018 8-01-2018 ISOTOPES Cs-134
<3.70E-03
<3.16E-03.
< 1.34E-03
<3.02E-03 Cs-137
<3.68E-03
<3.26E-03
<1.40E-03
<2.99E-03 Co-60
<3.72E-03
<3.19E-03
<1.14E-03
<2.99E-03 Page 47 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT I
TABLE 11
[
Bl-WEEKLY GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS. (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 8-01-2018 8-01-2018 8-01-2018 8-01-2018 END DATE 8-15-2018 8-15-2018 8-15-2018 8-15-2018 ISOTOPES Cs-134
<3.81 E-03
<3.30E-03
<1.43E-03
<3.24E-03 2.98E-03
<1.15E-03
<4.49E-03 Co-60
<3.97E-03
<3.51 E-03
<1.51E-03
<3.18E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 8-15-2018 8-15-2018 8-15-2018 8-15-2018 END DATE 8-29-2018 8-29-2018 8-29-2018 8-29-2018 ISOTOPES Cs-134
<3.87E-03
<3.39E-03
<1.50E-03
<3.16E-03 Cs-137 3.46E-03
<2.39E-03
- 8.75E-04
<2.37E-03 Co-60
<3.98E-03
<3.45E-03
<1.51E-03
<3.27E-03 Page 48 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 i
81-WEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 8-29-2018 8-29-2018 8-29-2018 8-29-2018 END DATE 9-12-2018 9-12-2018 9-12-2018 9-12-2018 ISOTOPES Cs-134
<3.86E-03
<3.30E-03
<1.47E-03
<3.23E-03 Cs-137 3.15E-03
<2.34E-03
<1.27E-03 2.50E-03 Co-60
<4.0BE-03
<3.35E-03
<1.51E-03
<3.44E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 9-12-2018 9-12-2018 9-12-2018 9-12-2018 END DATE 9-26-2018 9-26-2018 9-26-2018 9-26-2018 ISOTOPES Cs-134
<3.77E-03
<3.39E-03
<1.51E-03
<3.44E-03 Cs-137
<3.98E-03
<3.49E-03
<1.50E-03
<3.49E-03 Co-60
<3.95E-03
<3.35E-03
<1.49E-03
<3.48E-03 Page 49 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 81-WEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS: (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 9-26-2018 9-26-2018 9-26-2018 9-26-2018 END DATE 10-10-2018 10-10-2018 10-10-2018 10-10-2018 ISOTOPES Cs-134
<3.88E-03
<3.27E-03
<1.48E-03
<3.22E-03 Cs-137
<2.56E-03
<5.23E-03 1.04E-03 2.56E-03 Co-60
<3.94E-03
<3.37E-03
<1.47E-03
<3.24E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 10..:10-2018 10-10-2018 10-10-2018 10-10-2018 END DATE 10-24-2018 10..:24-2018 10-24-2018 10-24-2018 ISOTOPES Cs-134
<3.99E-03
,<3.55E-03
<1.49E-03
<3.27E-03 Cs-137
<3.95E-03
<3.27E-03
<1.54E-03
<3.43E-03 Co-60
<2.37 E-03.
<3.45E-03
<1.52E-03
<3.35E-03 Page 50 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 Bl-WEEKLY GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 10-24-2018 10-24-2018 10-24-2018 10-24-2018 END DATE 11-07-2018 11-07-2018 11-07-2018 11-07-2018 ISOTOPES Cs-134
<3.97E-03
<3.41 E-03 *
<1.48E-03
<3.18E-03 Cs-137
<3.42E-03
<2.84E-03
<9.66E-04.
1.93E-03 Co-60
<3.85E-03
<3.61 E-03
<1.57E-03
<3.30E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 11-07-2018 11-07-2018 11-07-2018 11-07-2018 END DATE 11-15-2018*
11-15-2018*
11-15-2018*
11-15-2018*
ISOTOPES Cs-134
<7.51 E-03
<6.19E-03
<2.85E-03
<6.04E-03 Cs-137
<7.22E-03
<3.41E-03
<1.53E-03
<4.33E-03 Co-60
<7.20E-03
<6.11E-03
<2.80E-03
<5.81E-03
- Air Samples pulled early due to site ~hutdown for holiday the next week Page 51 of 55
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 11 81-WEEKL Y GAMMA SPEC ENV. AIR SAMPLE ANALYSIS RESULTS (Con't)
(Concentrations in pCi/m3)
LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 11-15-2018 11-15-2018 11-15-2018 11-15-2018 END DATE 12-05-2018 12-05-2018 12-05-2018 12-05-2018 ISOTOPES Cs-134
<2.86E-03
<2.44E-03
<1.06E-03
<2.42E-03 Cs-137 1.65E-03 1.49E-03
<7.46E-04
<1.61 E-03 Co-60
<2.75E-03
<2.48E-03
<1.06E-03
<2.34 E-03 LOCATION COAL PLANT TRAILER COURT LOCK AND DAM #8 SW MAIN SWICHYARD START DATE 12-05-2018 12-05-2018 12-05-2018 12-05-2018 END DATE 12-19-2018 12-19-2018 12-19-2018 12-19-2018 ISOTOPES Cs-134
<4.21E-03
<3.51E-03
<1.63E-03
<3.35E-03 Cs-137
<2.55E-03
<3.46E-03
<1.54E-03
<1.88E-03 Co-60
<4.20E-03
<3.52E-03
<1.51E-03
<3.29E-03 Page 52 of 55
COLLECTION DATE:
SAMPLE LOCATION:
ISOTOPES/RL
- H-3/20000 Mn-54/1000 Co-60/300 Zn-65/300 Cs-134/30 Cs-137/50 RL = REPORTING LEVEL ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE12 SEMI ANNUAL MISSISSIPPI RIVER WATER ANALYSIS RESULTS (Concentrations in pCi/Liter)
SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE#1 SAMPLE#2 LOCK and LACBWR Dairyland LOCK and LACBWR DAM#8 OUTFALL.
Public River DAM#8 OUTFALL Access 4/17/2018 4/17/2018 4/17/2018 10/15/2018 10/15/2018 2550
</= 197
</=197
</=465
</=465
< 4.16
< 4.18
< 4.06
<4.05
< 4.12
< 4.32
< 4.18
< 4.20
< 4.49
<4.29
< 9.24
< 8.85
< 9.28
.< 8.86
< 9.33
<4.65
< 4.63
"< 4".67
< 4.47
<4.52
<4.75
< 4.71
<4.64
<4.62
< 4.73 Page 53 of 55 SAMPLE#3 Dairyland Public River Access 10/15/2018
</=465
< 4.01
< 4.12
< 9.05
< 4.51
< 4.48
SAMPLE LOCATION COLLECTION DATE ISOTOPES Cs-134 Cs-137 Co-60 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE13 SEMI ANNUAL MISSISSIPPI RIVER SEDIMENT ANALYSIS RES UL TS (Concentration in pCi/Kg)
UPSTREAM OUTFALL DOWNSTREAM UPSTREAM OUTFALL 04/24/2018 04/24/2018 04/24/2018 10/17/2018 10/17/2018
< 6.65
<5.17'
. < 11.90
< 5.23
< 5.01
<5.90 180.00 +/- 10.50 65.80 +/- 5.16
<4.11
<3.95
< 5.99
<4.90
< 10.90
<4.80
< 4.71 Page 54 of 55 DOWNSTREAM 10/17/2018
< 8.98 33.70 +/- 3.21
< 8.45
ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE14 QUARTERLY ENVIRONMENTAL TLD RESULTS FOR ISFSI AREA JANUARY-DECEMBER 2018 STATION NO.
1st QUARTER 2nd QUARTER 3rd QUARTER 4th QUARTER mRem mRem mRem mRem 1
1.0
<BKG
<BKG
<BKG 2
25.0 22.0 18.0 20.0 3
66.0 83.0 88.0 83.0 4
15.0 12.0 11.0 14.0 5
26.0 23.0 26.0 27.0 6 (*)
8KG
<BKG
<BKG
<BKG 7(*)
<0.1
<BKG
<BKG
<BKG 8 (*)
<0.10
<BKG
<BKG
<BKG 9 (*)
<BKG
<BKG
<BKG
<BKG 10 (*)
<0.10
<BKG
<BKG
<0.10 ALL BACKGROUND CORRECTED AND THOSE ON OWNER CONTROLLED AREA FENCE LINE IDENTIFIED WITH
(*) HAD OCCUPANCY FACTOR CORRECTION APPLIED IF> BACKGROUND TLD RESULTS Page 55 of 55