ML080700339
| ML080700339 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/25/2008 |
| From: | Berg W Dairyland Power Cooperative |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| LAC-14028 | |
| Download: ML080700339 (68) | |
Text
WILLIAM 1. BERG President and CEO DAIRYLAND POWER CO0O0P E R AT I V E February 25, 2008 In reply, please refer to LAC-14028 DOCKET NO. 50-409 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Dairyland Power Cooperative La Crosse Boiling Water Reactor Possession-Only License No. DPR-45 Annual Radioactive Effluent Report and Radiological Environmental Monitoring Report
REFERENCES:
(1) NRC Letter, Keppler to Linder, dated August 12, 1983, Inspection Report 50-409/83-10 (DRMSP)
(2) LACBWR Technical Specifications 6.4.2, 6.5. 1.1Lc & d In accordance with 10 CFR 50.36a(a)(2), this letter serves to transmit to you the Radioactive Effluent Report and Radiological Enviromnmental Monitoring Report for the La Crosse Boiling Water Reactor (LACBWR) for 2007.
If you have any questions, please contact us.
Sincerely, DAII(YLANI) POWER COOPERATIVE William L. Berg, President & CEO WLB: LLN: two Enclosures cc/endl: Peter Lee, Ph.D., NRC Reg. III, Decommissioning Branch Kristina Banovac, NRC Project Manager Don Hendrikse, Wisc. Div. of Health A Touchstone Energy Cooperative
__Ilý 3200 East Ave. S. -
PO Box 817
- La Crosse, WI 54602-0817 - 608-787-1258
- 608-787-1469 fax www.dairynet.com
RADIOACTIVE EFFLUENT REPORT AND RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT FOR THE LA CROSSE BOILING WATER REACTOR (LACBWR)
(January 1 to December 31, 2007)
DAIRYLAND POWER COOPERATIVE 3200 EAST AVENUE SOUTH LA CROSSE WI 54602-0817
/
TABLE OF CONTENTS SECTION A: RADIOACTIVE EFFLUENT REPORT Section Title Pg 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.............................................................
6 6.0 Abnormal Releases........................................................
6 7.0 Estimated Total Analytical Error...........................................
6 8.0 Offsite Dose Calculation Summary and Conclusions...................
12 9.0 Offsite Dose Calculation Manual (ODCM) Review......................
13 10.0 Process Control Program (PCP) Review.................................
13 SECTION B: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Section Title Pg Introduction.................................................................
1 1.0 Sample Collection..........................................................*2 2.0 Results of the 2007 Radio-Environmental Monitoring Survey......
2 3.0 Conclusions.................................................................
4 4.0 Interlaboratory Comparison Program Results...........................
5
TABLE OF CONTENTS TABLES SECTION A: RADIOACTIVE EFFLUENT REPORT Table No.
Title P~a 1A Effluent and Waste Disposal - Gaseous Effluents Summation of All Releases................................................
7 1 B Effluent and Waste Disposal - Gaseous Effluents Elevated Release...........................................................
8 2A Effluent and Waste Disposal - Liquid Effluents Sumnmation of All Releases................................................
9 213 Effluent and Waste Disposal - Liquid Effluents.........................
10 3
Effluent and Waste Disposal Annual Report - 2007 Solid Waste and Irradiated Fuel Shipments............................................
11 SECTION B: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Table No.
Title Pag 5
Sample Frequency and Analysis of Radio Environmental Samples.
10 6
Permanent Environmental Monitoring Station Locations...............
11 7
Environmental TLD Locations.......I......................................
12 8
Rad io-Envi ron mental Samples Collected January-December 2007.
13
- 9.
Quarterly Thermoluminescent Dosimeter Dose Measurements in the LACBWR Vicinity....................................................
14 10 Weekly Gross Beta Air Particulates in the LACBWR Vicinity..........
15 11 Air Particulate Composite Results.........................................
18 12 Results of Analysis of Mississippi River Water in the Vicinity of LACBWR.................................................................
24 13 Results of Analysis of Mississippi River Sediment in the Vicinity of LACBWR...................................... I...........................
30 14 Fish Sample Activity in the Vicinity of LACBWR.........................
31 ii
TABLE OF CONTENTS FIGURES' Title No.
Page FIGURE 1 FIGURE 2 FIGURE 3 FIGURE 4 LACBWR Property Map............................................
Permanent Environmental Monitoring Station Location.........
LACBWR Environmental Dose Assessment Locations.........
LACBWR Environmental Dose Assessment Locations.........
6 7
8 9
iii
SECTION A RADIOACTIVE EFFLUENT REPORT
INTRODUCTION:
The La Crosse Boiling Water Reactor (LA CB WR), 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 is presently defueled and in a SAFSTOR mode. In August of 1987 a possession-only license was received.
In accordance with LACBWR Technical Specifications 6.5. 1. 1.d and in compliance with 10 CFR 50.36a(a)(2), this document is the Radioactive Effluent Report for the period January 1 through December 31, 2007.
1
EFFLUENT AND WASTE DISPOSAL REPORT (Supplemental Information)
FACILITY: La Crosse Boiling Water Reactor LICENSEE: Dairvland Power Cooperative DOCKET NO. 50-409 1.0 REGULATORY LIMITS
- a.
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, 3000 mRem/year to the skin from noble gases, and 1500 mRem/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 ODOM 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
IEFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
- b.
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.
For alpha emitting radionuclides, the concentration is limited to a total activity concentration of 4.9E-9 pCi/mI, based upon an actual alpha emitting radionuclide analysis performed on a representative water sample. The values reported in tables 2A and 2B, Liquid Effluents, are based on dilution with the combination of LACBWR and 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.
- c.
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.
3
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd) 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
- a.
Liquid Effluents Liquid effluent measurements for gross radioactivity are performed by HPGe gamma isotopic analysis of a representative sample from each tank discharged. In addition, each batch discharged tank is analyzed for alpha and tritium activity concentration. 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.
- b.
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 isokinetically samples and monitors 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 alpha activity. A quarterly composite of these filters is sent to a contractor for Sr-90 analysis.
4
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
- c.
Radioiodines Since the plant shutdown in April 1987, the 1-131/I-1 33 have decayed completely to stable elements. Amendment 66 to the LACBWR Technical Specifications, deleted the requirement for monitoring for iodine.
- d.
Fission and Activation Gases The concentration of radioactivity (pCi/cc) in gaseous releases from the stack is continuously monitored by two in line stack monitors. These gas concentrations (pCi/cc) are corrected for pressure loss in the sampling system and averaged by the monitors microprocessor. The results are used along with the stack flow rate to obtain the daily gaseous release from the plant. Since the plant shutdown in April 1987, gaseous releases have been immeasurable. All fission gases except Kr-85 have decayed to stable elements.
- e.
Tritium Tritium releases are determined by taking a grab sample of the stack atmosphere at the effluent of the stack monitor. Tritium, as tritiated water, is removed from the sample stream by condensation, using a cold trap. The condensed water vapor is then distilled and the distillate is analyzed for H-3 concentration (pCi/cc), by internal liquid scintillation spectrophotometry and the results are expressed in terms of tritium release rates. The tritium grab samples are obtained on at least a once/month basis unless the upper reactor cavity is flooded, at which time the sampling frequency is increased to at least once per 7 days.
5
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd) 5.0 BATCH RELEASES
- a.
Airborne All airborne effluent releases at LACBWR are from a single Continuous-Elevated Release Point.
- b.
Liquid All liquid effluent releases at LACBWR are batch releases. This is summarized as follows:
(1)
Number of Batch Releases:
17 (2)
Total Time Period for Batch Releases:
349.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (3)
Maximum Time Period for a Batch Release:
38.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (4)
Average Time Period for a Batch Release:
20.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (5)
Minimum Time Period for a Batch Release:
8.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> (6)
Average Stream Flow Rate During Periods of Release of Effluent into a Flowing Stream:
26100 ft3/sec 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%.
6
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
TABLE IA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES IUNIT QTR QTR QTR QTR TOTAL A.
FISSION & ACTIVATION GASES_______________________
- 1.
TOTAL RELEASE Ci 0.OOE+00 IO.0.0E+00 O.OOE+00 0.OOE+00 0.OOE+00
- 2.
AVERAGE RELEASE RATE FOR jj.CiI 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 L PERIOD jSec
_ I_
B.
IODINE 1-131 -
No longer analyzed for.
I ____
C.
PARTICULATES
- 1.
PARTICULATES WITH HALF-Ci 3.90E-06 6.11 E-06
- 1. 11 E-06 3.81E-07 1.15E-05 LIVES > 8 DAYS__
- 2.
AVERAGE RELEASE RATE FOR I.tCi/
5.01 E-07 7.77E-07 1.40E-07 4.79E-08 PERIOD Sec
- 3.
GROSS ALPHA RADIOACTIVITY Ci
- 1. 18E-06
,1.41 E-07 1.50E-07.
2.10E-08 1.49E-06 D.
- 1.
1TOTAL RELEASE Ci If3.20E-02 1.48E-02 9.39E-03 8.82E-03 6.50E-02
- 2.
AVERAGE RELEASE RATE FOR gCi/
4.12E-03 1.88E-03 1.18E-03
- 1. 11 E-03 PERIOD Sec E.
PERCENTAGE OF ODCM DOSE LIMITS FOR GASEOUSEFFLUENT RELEASES If QTR QTR QTR
.QTR
-YEARLY_
1.
INOBLE GAS RELEASE__________________
__GAMMA
%__ 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+O0
.OOE+00 BETA
%__ 0.OOE+00 I0.OOE+00 I.OOE+00 I0.OOE+00
.OOE+00
- 2.
H-3 AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8
__DAYS L IGAMMA (Highest Organ)
% I2.74E-04 17.70E-04 13.65E-04 I5.58E-05 I6.72E-04 7
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 GASEOUS EFFLUENTS - ELEVATED RELEASE ICONTINUOS MODE UNIT QTR QTR QTR QTR TOTAL NUCLIDES RELEASED
- 1.
FISSION GASES KRYPTON-85 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TOTAL FOR PERIOD Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 2.
IODINE 1-131 -
Analysis no longer required.
- 3.
PARTICULATES____
STRONTIUM-90 Ci 8.60E-08 4.50E-07 2.85E-07 CEIU-14Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE-'-O CESUM13 Ci 1.32E-06 5.02E-06 6.60E-07 O.OOE+OO 7.OOE-06 COBALT-60 Ci 2.49E-06 6.36E-07 1.67E-07 3.81 E-07 3.67E-06
~~Ci__
Ci CI Ci CI
~~Ci__
TOTALS Ci 13.90E-06 16.11 E-06
- 1. 11 E-06 4
4 th quarter Strontium-90 data is not yet available from Dairyland Power's contracted laboratory. This page will be resubmitted when data becomes available.
8
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
.TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES IUNIT QTR QTR QTR QTR TOTAL A
FISSION & ACTIVATION PRODUCTS
- 1.
TOTAL RELEASE (NOT INCL.
Ci 1.70E-02 1.56E-01 7.21 E-02 1.90E-02 2.64E-01 TRITIUM, GASES, ALPHA)
- 2.
AVERAGE DILUTED ptCiI 5.90E-09 3.65E-08 2.21 E-08 1.96E-8 CONCENTRATION DURING ml PERIOD B.TRITIUM
- 1.
TOTAL RELEASE Ci 9.31 E-03 3.26E-03 2.45E-03 1.10E-03 1.61 E-02 AVERAGE DILUTED jiCi/
3.23E-09 7.62E- -10 7.52E-10 1.13E-09
__ PERIOD C.
DISSOLVED AND ENTRAINED GAES
- 1.
TOTAL RELEASE Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 2.
AVERAGE DILUTED pCi!
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO PERIOD__
D. GROSS ALPHA RADIOACTIVITVY
- 1.
TOTAL RELEASE Ci 4.58E-05 I1.10E-04 J17.20E-05 15.72E-05 2.85E-04 E. VOLUME OF WASTE Liters 1.63E+05 8.38E+04 6.36E+04 2.23E+04 3.33E+05 RELEASED (PRIOR TO_
I _
__I_
DILUTION)__
F.
VOLUME OF DILUTION Liters 2.88E+09 4.29E+09 3.26E+09 9.3+81.14E+10 WATER USED DURING{97E8 PERIOD G. PERCENTAGE OF ODCM LIMITS FOR LIQUID RELEASES QTR QTR QTR TR YEARLY HIGHEST ORGAN
%__ 7.93 45.64 16.13 541 37.55 WHOLE BODY
___T_ -F16.7 95.82 33.91 1.34 78.89 9
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
TABLE 2B1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 LIQUID EFFLUENTS NUCLIDES RELEASED UNIT QTR QTR QTR QTR MANGANESE-54 Ci O.OOE+00 0.OOE+O0 O.OOE+00 0.OOE+00 IRON-55 Ci 0.OOE+00 8.33E-05 3.50E-05*
COBALT-60 Ci 1.64E-03 2.27E-03 1.04E-03 3.01 E-04 STRONTIUM-90 Ci 1.63E-04 5.83E-04 5.41 E-04*
CESIUM-i134 Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OQE+0O CESIUM-137 Ci 1.52E-02 1.53E-01 7.04E-02 1.87E-02 TOTAL FOR PERIOD Ci 1.70E-02 1.56E-01 7.21 E-02*
(ABOVE)
KRYPTON-85 Ci O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00
- 4 th quarter Strontium-90 data is not yet available from Dairytand Power's contracted laboratory. This page will be resubmitted when data becomes available.
10
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL (Not Irradiated Fuel)
UNIT 6-MONTH 6-MONTH TOTAL
- 1. TYPE OF WASTE PERIOD PERIOD
- a. SPENT RESINS, FILTER SLUDGES, m 3 10.23 0
10.23 EVAPORATOR BOTTOMS, ETC Ci 3.97E1 0
3.97E1
- b. DRY COMPRESSIBLE WASTE, m 3 68.65 182.22 250.87 CONTAMINATED EQUIPMENT, ETC Ci 5.69E-1 1.48E1 1.54E1 C. IRRADIATED COMPONENTS, CONTROL m3 97.13 0
97.13 RODS, ETC Ci 9.76E3 0
9.76E3
- d. OTHER (DESCRIBE) m 3 0
0 0
Ci 0
0
.0
- 2. ESTIMATE OF MAJOR NUCLIDE PERCENT
- 6-MONTH 6-MONTH COMPOSITION (BY TYPE OF WASTE)
OF TOTAL PERIOD PERIOD CURIES CURIES
- a. Spent Resin etc.
Co-60 0.8 3.18E-1 0
Cs-i 37 68.63 2.72E1 0
Fe-55 0.34 1.35E-1 0
Ni-63 27.58 1.09E1 0
Pu-241 0.99 3.93E-1 0
Sr-90 1.8 7.15E-1 0
ý2.3E-1 2.43E-2 Fe-55 13.75 7.82E-2 8.25E-3 Ni-63 42.00 2.39E-1 2.52E-2 Pu-241 2.7 1.54E-2 1.62E-3
~~I.
-I _______
11
EFFLUENT AND WASTE.DISPOSAL REPORT - (cont'd)
ESTIMATE OF MAJOR NUCLIDE
,PERCENT 6-MONTH 6-MONTH COMPOSITION (BY TYPE OF WASTE)
OF TOTAL PERIOD PERIOD CURIES CURIES
- b. Contaminated Equipment (Concrete)
Co-60 19.18 0
2.04E-1_
Fe-55 65.97 0
7.00E-1 Ni-63 8.43 0
8.95E-2 Pu-241 1.83 0
1.94E-2 H-3 3.44 0
3.65E-2
- b. Contaminated Equipment (FCIP Pipe)
Co-60 12.99 0
1.77 Fe-55 1.02 0
1.39E-1 Ni-63 81.77 0
1.12E1 Co-60 44.13 4.31 E3 0
Ni-59 0.5 4.88E1 0
Ni-63 45.66 4.46E3 0
Pu-241 0.01 9.76E-1 0
- 3.
SOLID WASTE DISPOSITION NO. OF SHIPMENTS MODE OF DESTINATION TRANSPORTATION 1
Rail Barnwell, SC 3
Truck Studvick, Erwin, TN 3
Truck Energy Solutions, Oak Ridge, TN 3
Rail Energy. Solutions, Clive UT 5
Truck Energy Solutions, Clive UT B.
IRRADIATED FUEL SHIPMENTS (DISPOSITION)
NO OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 12
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
- 8. 0 OFFSITE DOSE CALCULATIONS
SUMMARY
AND CONCLUSIONS:
- a.
Gaseous Effluent Releases The maximum quarterly offsite gamma dose due to noble gases was 0.00 mRad. The cumulative 2007 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 2007 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 5.77E-5 mRem. The cumulative 2007 annual maximum organ dose from these radionuclides was also approximately 1.01 E-4 mRem.
The highest historical annual average X/Q equal to 1.82 E-6 sec/in3 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.
- b.
Liguid Effluent Releases The maximum quarterly organ dose from liquid releases was approximately 2.28 mRem. The cumulative 2007 annual organ dose was approximately 3.76 mRem. The maximum quarterly total body dose for liquid releases was approximately 1.44 mRem, and the cumulative 2007 annual total body dose was approximately 2.37 mRem.
- c.
Conclusion All calculated offsite doses were below ODCM limits.
13
EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)
- 9. 0 OFFSITE DOSE CALCULATION MANUAL (ODOM) REVIEW The ODCM was reviewed in April 2007. A minor word change was submitted to change Containment Building to Reactor Building. The revised page is being submitted in this report for your review.
10.0 PROCESS CONTROL PROGRAM (PCP) REVIEW The PCP has been reviewed and updated in 2007. The revised PCP is being included in its entirety in this report for your review, as required by Technical Specifications.
The revision allowed for the handling of the reactor pressure vessel outside of the controlled area (page 4 of 5, attachment 1). All other pages were reformatted.
14
~>EXCLUSION AREA ca The EXCLUSION AREA is defined as the area within an 1109 ft. (338m) radius
> from the centerline of the Reactor Building. This was the area established per 10 CFR 100 as the EXCLUSION AREA for plant siting and operation.
O MAXIMUM PERMITTED CONCENTRATION (MPC)
Cuý The limiting liquid effluent concentration value 10 CFR 20, Appendix B, Table 2, ca Column 2.
MEMBER OF THE PUBLIC O
~MEMBER OF' THE PUBLIC shall mean an individual in a CONTROLLED or UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC
>.is during any period in which the individual receives an occupational dose.
OPERABLE-OPERABILITY
- a.
A system, subsystem, train, component or device shall be OPERABLE or have Wo OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, a normal or an emergency electrical Cu 0R cc0 power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).
(Dz WC/)
SOURCE CHECK
-J o z A SOURCE CHECK shall be the qualitative assessment of channel response
< when the channel sensor is exposed to a radioactive source.
ODCM 3
Rev. 9
LA CROSSE BOILING WATER REACTOR PROCESS CONTROL PROGRAM (PCP)
Prepared by:
no 4~4~Zi Y/3107 Date Health Physics Review:
Security Review:
QA Review:
ORC Approved:
Date Date Date Date(
-7 April 2007 (Revision 12)
Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54602
LACBWR PROCESS CONTROL PROGRAM (PCP)
- 1.
INTRODUCTION The purpose of the Process Control Program (PCP) is to describe the methodology and procedures used by the La Crosse Boiling Water Reactor (LACBWR)
Facility during SAFSTOR, to ensure that radioactive waste material processing, packaging, transportation and disposal will be accomplished in a manner that is in compliance with all applicable federal, state, and burial site regulations, and with the LACBWR Security Plan for Transportation of LACBWR Hazardous Materials (Attach-ment 1). The PCP will provide guidance for LACBWR's three basic waste streams:
(1) dry active waste (DAW), (2) wet radioactive waste (resin or filter media), or (3) irradiated material (Reactor vessel or Reactor vessel components).
NOTE:
If the methodology and/or procedures found in the PCP are being violated, all radioactive waste processing activities will be suspended until these violations can be investigated and corrected.
I1.
SPECIFICATION Technical Specifications state:
- a. "The PCP shall be maintained onsite and will be available for NRC review."
- b. "Lice nsee-i nitiated changes to the PCP shall be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:
N Information to support the rationale for the change; 0 A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and E Documentation of the fact that the change has been reviewed and found acceptable by the ORC."
PCP PCP Rev.
12
111.
WET RADIOACTIVE WASTE The PCP and Health and Safety Procedure (HSP) 4.1 establish the steps used to dewater and stabilize wet radioactive waste material from the process water treatment systems and the liquid waste system. These wastes will be transferred to the Waste Treatment Building (WTB) for storage and processing before its ultimate disposal.
The WTB is located to the northeast of the Reactor Building. The WTB contains facilities and equipment for the collection, processing, storage and handling of low level solid radioactive waste materials.
The grade floor of the WTB contains a shielded compartment which encloses a permanent 320 ft3 stainless steel Spent Resin Receiving Tank (SRRT) with associated resin receiving and transfer piping, SRRT recirculation piping, SRRT demnineralized water flush piping, SRRT dewatering piping, SRRT air sparger piping, valves, and a SRRT ultrasonic level indication assembly. This cubicle is in the southeast corner of the building and has nominal 2' 6" to 3' thick reinforced high density concrete shield walls on the outer sides.
Wet radioactive waste materials may typically be described as whole bead demnineralizer resins, mechanical cartridge filters, waste sludge, and inorganic particulate residues. When expended, these wet wastes are transferred to the SRRT or, in some cases, directly into a High Integrity Container (HIC) for processing. In the case of Class C wet radioactive waste, as an alternate method to transfer to -the SRRT, they may be transferred to a HIC inside a transportation cask and dewatered from the cask to the plant process liquid waste system, thus reducing radiation exposure to personnel involved in performing the necessary package handling operations. Samples of wet waste are analyzed for isotopic composition and for waste classification.
Expended demnineralizer 'resins and waste sludge material from sumps and tanks are transferred to the SRRT as described in the Operating Manual Volume VII.
From the SRRT, partially dewatered spent resins and/or sludge material, which have been sluiced from plant demnineralizers and/or tanks, are pumped at a low flow rate/pressure with a Roper-type screw pump to a HIC, located in the adjacent shielded cubicle as described in Operating Manual Volume VII. The wall between the SRRT and the disposal HIC and other walls surrounding the HIC are a nominal 2' thick high density concrete. Also located in this cubicle is an air-driven Sandpiper-type diaphragm HIC dewatering pump, the resin transfer and dewatering valves and hoses, and the disposal HIC level indication connecting cable. Once in the HIC, spent resins and sludge material PCP PCP Rev.
12
is dewatered to the SRRT which is subsequently dewatered through a dlewatering ion exchanger. A final dewatering is performed as described in Operating Manual Volume VII and Health and Safety Procedure (HSP) 4. 1.
The final dewatering will ensure that the contents of the HIC meets the requirements of 100CFR61.56(a)(3) and 100CFR61.56(b)(2) and burial site criteria for free-standing liquids. Stabilization of the dewatered wet waste is provided by the HIC as authorized by 100FR61.56(b)(1). The contractor which supplies the HIC will provide DPC with a copy of the Certificate of Compliance for the HIC which details specific limitations on the use of the HIC.
Once final dlewatering is completed, the HIC is inspected, sampled, and the HIC lid is sealed and closed. The HIC is surveyed, decontaminated, and loaded into an appropriate shipping cask. Dewatered spent mechanical cartridge filters may be added directly to a HIC containing spent resins, if necessary.
The shipping cask is prepared for shipment in accordance to contractor's procedures. The vehicle is inspected both upon arrival onsite and after it is loaded prior to departure in accordance with procedure.
Once properly prepared for shipment, the wet waste will be either sent directly to an approved disposal site for burial, or it will be sent to a licensed waste processor for volume reduction. Any material remaining after reprocessing will be sent to burial by the processor for DPC.
IV.
DRY ACTIVE WASTES The PCP and Health and Safety Procedure 4.2 establish the steps used to process, package and ship the Dry Active Wastes (DAW) from the plant, in accordance with 1 OCFR2O.2006. The Dry Active Waste materials may typic ally be described as paper, cloth, metal, wood, plastic, concrete and other items or components which have become contaminated with radioactive materials. The DAW is normally characterized and labeled as Class A Unstable, in accordance with 10CFR61.55 and.56.
DAW will either be processed at LACBWR for burial at an approved burial site, or it will be processed for shipment to a licensed reprocessing contractor.
PCP PCP Rev.
12
- a. DAW for direct burial.
These waste's processed for burial from LACBWR are normally compacted using a DAW compactor unit located in the WTB. They are packaged in DOT Spec 7A containers or Spec 17H drums. Sufficient absorbent material is added to each waste container to limit free standing and non-corrosive liquid to less than 1% of the volume. Some dry waste material may be plant components which had become activated by neutron irradiation. Represent-ative samples of DAW are analyzed for isotopic composition and for waste classification.
After packaging, these DAW wastes are transferred to the DAW storage building which is located southwest of the Turbine Building. It is used to store processed, packaged and sealed low level dry active waste materials, and sealed low level activity components until they are sent to burial. The building has the capacity for 500 DOTi 7H-55 gall on drums of waste.
- b. DAW for Reprocessing Containers supplied by the contractor will be strategically placed within the controlled area to allow for the most efficient loading of these containers. The container size will vary due to the application required. Once filled, the reprocessing contractor will be notified and shipping arrangements will be made. The containers will be sealed and surveyed before leaving LACBWR.
Any waste volume remaining after reprocessing will be sent to burial by the contractor for LACBWR.
V.
IRRADIATED MATERIAL During the dismantlement activities at LACBWR, the reactor vessel and other irradiated components that were once in the vessel (shroud cans, control rods, etc.) will be disposed of. This material will normally be characterized and labeled as Class B or C Stable, in accordance with 10 CFR 61.
All irradiated material packaging and shipping will be handled by a licensed contractor hired by Dairyland Power to perform each shipment as required. DPC employees will provide oversight of these shipments to ensure compliance.
PCP PCP Rev.
12
VI.
WASTE CLASSIFICATION LACBWR Wastes will be classified as Class A Stable or Unstable, Class B Stable, or Class C Stable to determine the acceptability for near-surface disposal and for the purpose of segregation at the disposal site. The waste class will be based on the concentration of certain radionuclides in the waste as outlined in 1 OCFR61.55.
Radionuclide concentrations will be determined based on the volume or weight of the final waste form as discussed in Section C.2 of the Branch Technical Position Paper on Waste Classification.
Of the four suggested methods for determining radionuclide concentration, the one most commonly used is the direct measurement of individual radionuclides (gamma emitters) and the use of scaling factors to determine the radionuclide concentration of difficult to measure radionuclides (normally non-gamma emitters). The use of the other suggested methods; material accountability, classification by source or gross radioactivity measurements may occur if the situation best fits the use of that methodology.
Plant procedures are used in the determination of radionuclide concentration for difficult to measure nuclides (normally non-gamma emitters) and for the classification of radioactive waste for near-surface burial in accordance to 10CFR61.56(a)(3) and Table 1 and Table 2.
VII. SHIPMENT MANIFEST Each shipment of solid radioactive waste to a licensed land disposal facility will be accompanied by a shipment manifest as required by 10CFR2O.2006 and described in NUREG/BR-0204. The manifest will contain the name, address, and telephone number of the waste generator. The manifest will also include the name, address, and telephone number or the name and EPA hazardous waste identification number of the person transporting the waste to the land disposal facility.
The manifest will also indicate to the extent practicable: a physical description of the waste; the volume; radionuclide identity and quantity; the total radioactivity; and the principal chemical form. The solidification agent, if applicable, will be identified.
Waste containing more than 0. 1% chelating agents by weight will be identified and the weight percentage of the chelating agent estimated. Waste classification, Class A, B, or C, will be clearly indicated on the manifest. The total quantity of the radio-PCP PCP Rev.
12
nuclides H-3, C-14, Tc-99, and 1-129 will be shown on the manifest. Source material mass, and the masses of U-233, U-235, Pu isotopes and total Special Nuclear Material will be calculated and shown on the manifest.
Each manifest will include a certification by DPC that the transported materials are properly classified, described, packaged, marked, and labeled, and are in proper condition for transportation according to the applicable regulations of the Department of Transportation and the NRC. A qualified individual will sign and date the manifest.
LACBWR procedures are used for the preparation of burial site radioactive shipping manifests.
LACBWR will maintain a manifest record-keeping and tracking system that meets the requirements of 1 QCFR2O.2006.
Each shipment of radioactive waste to a licensed reprocessing contractor will be accompanied by a shipment manifest that meets the requirements of that contractor's license.
VIII. ADMINISTRATIVE CONTROLS A. Training A training program will be conducted to ensure that waste processing will be performed according to plant procedures and the POIP. An individual's training record will be maintained for audit and inspection. The processing and shipment of radioactive material will be performed by qualified and trained personnel.
All plant personnel who handle, package, and prepare for shipment radioactive material will receive appropriate DOT Hazardous Material Training, in accordance with their duties, once every three (3) years.
B. Record Retention Records of processing data, test and analysis results, results of training, inspections and audits will be retained in accordance with LACBWR Quality Assurance requirements for record retention.
PCIP POP Rev.
12
C. Documentation Control DPC-initiated changes may be made to the PCP and procedures in accordance with Technical Specifications and shall become effective upon review and acceptance by the Operations Review Committee (ORC).
Radioactive waste that does not fall within previous waste processing experience will be evaluated and, if necessary, included in the PCP prior to final processing and disposal. Approved changes in the PCP will be reported to the NRC in the subsequent annual Radioactive Effluent Release Report.
D. Quality Assurance The provisions of the NRC-approved LACBWR Quality Assurance Program apply to all activities performed under the PCP, and solid radioactive waste processing procedures.
E. Voluntary Information Submittal If any of the following mishaps occur during the preparation of LLW waste for disposal, a voluntary submittal of information will be sent to the NRC. This will be a 30-day report to the NRC's Director of the Division of Low-Level Waste Management and Decommissioning and will also be sent to the designated State disposal-site regulatory authority.
(1)
Failure of the high-integrity containers used to ensure a stable waste form. Container failure can be evidenced by changed container dimensions, cracking, or damage resulting from mishandling (e.g.,
dropping or impacting against another object).
(2)
Misuse of high-integrity containers, evidenced by a quantity of free liquid greater than 1 percent of container volume, or by an excessive void space within the container. Such misuse is prohibited by 10CFR61.56.
(3)
Production of a solidified Class B or C waste form that has any of the following characteristics:
" Contains free liquid in quantities exceeding 0.5 percent of the volume of the waste.
" Contains waste with radionuclides in concentrations exceeding those considered during waste form qualification testing accepted by the regulatory agency, which could lead to errors in assessment of waste class.
PCP PCP Rev.
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" Contains a significantly different waste loading than that used in qualification testing accepted by the regulatory agency.
" Contains chemical ingredients not present in qualification testing accepted by the regulatory agency, and those quantities are sufficient to unacceptably degrade the waste product.
" Shows instability evidenced by crumbling, cracking, spalling, voids, softening, disintegration, non-homogeneity, or dimensional changes.
" Evidence of processing phenomena that exceed the limiting processing conditions identified in applicable topical reports on process control plans (e.g., foaming, temperature extremes, premature or slow hardening, and production of volatile material).
PCP Pop Rev.
12 To POP Security Plan for Transportation Of LACBWR Hazardous Materials The purpose of this plan is to establish guidelines and requirements for the secure transportation of hazardous materials (HM) from the La Crosse Boiling Water Reactor (LACBWR) in accordance with Hazardous Materials Regulations, 49 CER 172 Subpart 1.
This plan applies to hazardous material consisting of radioactive material, or radioactively contaminated material in packages, and/or shipments that require placarding.
Definitions DPC:
Dairyland Power Cooperative GET:
General Employee Training - annual program that provides site specific training for employees, of which security training is included.
LSA:
Low Specific Activity LSE:
LACBWR Site Enclosure - all area within the fence that surrounds the LACBWR facility.
SCO: Surface Contaminated Object References (1) 49 CER 171-180 (Hazardous Materials Regulations)
(2)
Physical Security Plan and Procedures for LACBWR (3)
TPP-7, General Employee Training (GET) Procedure (4)
La Crosse Boiling Water Reactor Process Control Program (POP)
(5)
Health & Safety Department Procedures - Section 4: Waste Disposal PCP 1 of 5 POP Iof 5Rev.
12 To PCP Responsibilities The following personnel and their respective areas of responsibility were reviewed to assist in determining if the key elements of 49 CFR 172, Subpart 1, are satisfied.
IDPC Security Supervisor: IDPC management responsibility for administration and implementation of security program. Responsible for day-to-day oversight of the security organization. (See Ref. 2.)
Contract Security Post Commander: Overall supervisory and training responsibility for the Contract Security Force. (See Ref. 2.)
IDPC Health and Safety Supervisor: Responsible for all processing, packaging and preparation of HM for transportation.
IDPC Human Resources: Responsible for screening and hiring all IDPC personnel.
Training Supervisor: Responsible for ensuring initial and annual training is performed for, all LACBWR personnel.
Risk Assessment The goal of the hazardous materials security requirement is to effectively prevent hazardous materials from being used as tools of mass destruction and terror. In general, the only hazardous materials that LACBWR offers for transport in commerce (or potentially transports in commerce), and therefore come under this security requirement, are shipments of radioactive LSA or SCO material that require placarding because of their radioactive content. These shipments typically consist of large volumes of dry active waste (DAW) such as paper, discarded equipment, valves, pipe, wood, rags, floor sweepings, used glassware, etc. The total radioactivity in these shipments is very small. Only one of the twenty-six shipments made from LACBWR between January 22, 1997, and April 22, 2003, contained more than 160 mCi of radioactivity. There is no credible way that these small amounts of radioactivity could be separated from the large volumes of waste, concentrated, and used as tools of mass destruction or terror, and therefore the security risk is very low..
12 To POP One shipment of spent resins and sludge made in October 1999 contained 40,900 mCi (40.9 Ci) of radioactivity. This shipment presents a higher security risk than the DAW shipments, but it was made in a heavily shielded Type B cask, certified by the N RC under 10 CER 71 regulations. However, the relatively low specific activity and large volume (5.35 cubic meters) of the contents of this shipment do not lend themselves to separation and concentration for use as a tool of mass destruction. The potential for sabotage or highjacking for terrorist purposes, warrants consideration.
In the coming years, the majority of our shipments will be LSA or SCO with characteristics similar to those described above. Some will contain higher concentrations of radioactivity, but. the security risks will be low because of the large volumes and low specific activities. All large volume LSAISCO shipments and Type B shipments use sole-use transportation systems, where the transport vehicle is loaded at LACBWR with our shipment and proceeds to the authorized recipient as expeditiously as possible.
At some time, we will make shipments of irradiated reactor fuel assemblies from LACBWR. This type of shipment is considered a relatively high security risk, and these shipments will be made under special security procedures developed at that time to meet then current NRC and DOT requirements. A 90-day prior notification must be made to the NRC before making a shipment of irradiated fuel.
Another type of radioactive material that is considered to have a greater security risk is small encapsulated radioactive sources. We have a number of this kind of sources that will need to be disposed of before license termination. Most have very small quantities of radioactive material and therefore should be considered of very low security risk. However, three of these (two Cs-i 37 and one PuBe) have higher activity. These will not be shipped until just prior to LACBWR's license termination. Their shipment and disposal will be handled on a case-by-case basis at that time.
PCIP 3 of 5 PCP 3of 5Rev.
12 To PCP Facility Security Essentially all LACBWR hazardous material offered for transportation. (radioactive HM) is produced, processed, stored, prepared for shipment, loaded on a transport vehicle, and turned over to a carrier, within the LSE*. The LSE area is controlled under the LACBWR Physical Security Plan (see Ref. 2) and is under continuous, round-the-clock surveillance.
Personnel Security All personnel admitted to the LSE are issued badges. Three types of badges, indicating different levels of security clearance, are used:
Type 1:
Unescorted access to all areas including the LACBWR Protected Area (PA),
Type 2:
Unescorted access to the LSE but not the PA, and Type 3:
Visitor, escort required in the LSE and the PA.
All personnel involved with handling and processing the HM, and preparing it for shipment, have been subjected to the LACBWR Physical Security Plan Screening Program.
A limited number of DPC personnel are issued Type 2 badges, authorizing unescorted access to the LSE. These personnel have been subjected to the routine security and background screening for all OPO hires and are not considered to be a security risk under this plan.
All personnel who have not been cleared for unescorted access to the LSE are considered visitors and are issued Type 3 badges before access to the LSE is granted. A person with a Type 3 badge will be under continuous escort by a person with a Type 1 or Type 2 badge, and their access to the HM will be limited by the escort.
- Some large items, for example the reactor pressure vessel, that will be transported by rail car may be moved to the rail siding at the North end of the DPC owner controlled area before final preparation for shipment, loading on the transport vehicle, and turning over to a carrier.
These operations will be performed under special procedures and DPC security surveillance as appropriate.
PCP 4 of 5 Pop 4of 5Rev.
12 To PCP En route Security All hazardous material under this security plan is packaged and prepared for shipment and the preparation and arrangements for offering to an authorized carrier for transport are performed according to the LACBWR Process Control Program (PCP) and detailed Health &
Safety Department Procedures (Ref's 4 and 5). Only authorized carriers of nuclear material possessing a transportation security plan will be used for transportation of LACBWR HM.
DPC will cooperate with the selected carrier to enhance, to the maximum extent possible, the security of the shipment from the origin to the destination. Appropriate checklists and requirements to document this interaction with the carrier and the carrier's drivers is included in the LACBWR PCP and/or Health & Safety Department Procedures.
Training Security plan training is accomplished as part of the annual GET training received by all LACBWR DPC and contract security employees. This training will provide an overview of this security plan and the security risks of transportation of LACBWR HM. It will cover LACBWR HM transportation security objectives, specific LACBWR security procedures, employee responsibilities, and actions to take in the event of a security breach.
Records Appropriate records production and retention are specified in the LACBWR POP, the Health & Safety Department Procedures, and/or the GET training procedure.
PCP 5 of 5 POP 5of 5Rev.
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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 CER 50 Appendix /. 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 environmental 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 (OD CM).
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.
1
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 1.0 SAMPLE COLLECTION Environmental samples are collected from the area surrounding LACBWR at the frequencies outlined in the ODCM. A series of figures and tables are included in this report to better show LACBWR's environmental program.
FIGURE 1 This map includes the plant boundary, roads, other generation plants, and the relationship of the plant to the nearest local community.
FIGURE 2 This map shows the location of LACBWR's permanent environmental monitoring stations.
FIGURES 3&4 These maps show the location of LACBWR's TLDs.
TABLE 5 This table shows the sampling frequency of the various environmental samples and the analyses performed on these samples TABLE 6 This table shows the permanent monitoring stations used in LACBWR's environmental program.
TABLE 7 This table shows the TLD locations.
TABLE 8 This table shows the number of various samples collected and analyzed during 2007.
2.0 RESULTS OF THE 2007 RADIO-E NVI RON MENTAL MONITORING SURVEYS During 2007, 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 thermo luminescent dosimeters consisting of four lithium fluoride (LiF) chips. These TLD's are changed on a quarterly basis and are sent to an outside contractor for reading. The TLD results for 2007 are shown on Table 9.
2
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd) 2.2 AIR PARTICULATE Air samples are collected continuously from various sites (see Table 6) around LACBWR. An air sampler is also located 18 miles north of the plant in La Crosse, Wisconsin, to act as a control station.
Particulate air samples are collected at the rate of approximately 30-60 1pm with a Gelman Air Sampler. The air filter consists of a glass fiber filter with an associated pore size of approximately 0.45 pm. The particulate filters are analyzed weekly for gross beta activity with an internal proportional counter, and the monthly particulate composites are gamma analyzed for individual isotopic concentration.
TABLE 10 This table shows the weekly gross beta gamma activity concentration from the air particulate filters.
TABLE 11 This table shows the composite air particulate isotopic analysis.
Comparison between the control station at La Crosse and the other stations near LACBWR indicate that there was no significant plant attributable airborne particulate activity.
2.3 RIVER WATER River water is collected monthly. River water samples above at, and below the plant site are collected and are gamma analyzed for isotopic concentration. The river water gamma isotopic analysis results are shown in Table 12. The results indicate that there was no significant plant attributable radionuclides in the river water.
3
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd) 2.4 SEDIMENT SAMPLES Sediment samples were collected twice per year above, at, and below the plant outfall. These samples were 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 radionuclide in this sediment declined significantly after plant shutdown. These amounts have remain relatively constant the last few years.
2.5 FISH Fish samples were collected quarterly above and below the plant discharge. The results of gamma spectral analysis o f edible portions of fish samples appear in Table 14. There has been no significant accumulation of plant-attributed radionuclides in fish in the vicinity of LACBWR.
3.0 CONCLUSION
S All environmental samples collected and analyzed during 2007 exhibited no significant contribution from LACBWR.
4
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd) 4.0 INTERILABORATORY COMPARISON PROGRAM RESULTS During 2007, 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.
ANLYISLACBWR CONTRACTORRAI ANALYSISRESULTS RESULTSRAO GROSS BETA 146 pCi 151 pCi 0.97 GROSS ALPHA 80.5 pCi 119 pCi 0.68 Ce-141 90 pCi 89.5 pCi 1.01 Cr-51 296 pCi 326 pCi 0.91 Cs-134 71 pCi 87.4 pCi 0.81 Cs-137 109 pCi 106 pCi 1.03 Co-58 106 pCi 111 pCi 0.96 Mn-54 128 pCi 121 pCi 1.06 Fe-59 99 pCi 94.4 pCi 1.05 Zn-65 158 pCi 149 pCi 1.06 Co-60 128 pCi 135 pCi 0.95 H-3 10100 pCi/it 9020 pCi/C 1.12 5
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)
LOCATION MAP 1000 50.0 0
1000 SCALE OF FEET OF T.HE 5th PM. -
JEFFERSON TOWNSHIP/
HOUSTON COU NTY,/
'LUSION BOUIMA:
1109 ft radiu!
M-678 INDICATES MILES ABlOVE MOUTH4 OF THE OHIO Rly k-NOTEISLAND 126 IS UNDER TI JURISDICTION OF UPPER MISSISSIPPI RIVER WILD TE LIFE AND FISH REFUGE.
FIGURE 1 - LACBWR PROPERTY MAP U ac osS e D-ivironnental
~
Sample
~i~t$(\\z~x'czVJA~3AiIIký-
Locations FIGURE 2 - PERMANENT ENVIRONMENTAL MONITORING STATION LOCATIONS (Refer to Table 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)
FIGURE 3 -LACBWR ENVIRONMENTALDOSE ASSESSMENT LOCATIONS RADIOLOGICAL ENVIRONMENTFIAL MONITORING REPORT - (cont'd) 0 FIGURE 4 - LACBWR EINVIRONMENTAL DOSE ASSESSMENT LOCATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)
TABLE 5 SAMPLE FREQUENCY AND ANALYSIS OF RADIO-ENVIRONMENTAL SAMPLES SAMPLE FREQUENCY ANALYSIS PERFORMED TLD (LiF) 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 Twice per year Gamma Spectroscopy Fish Quarterly Gamma Spectroscopy River Monthly Gamma isotopic analysis and tritium (Liquid Scintillation Analyzer)
Vegetation Obtain sample as directed if Gamma Spectroscopy abnormal stack particulate release occurs.
10
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)
TABLE 6 PERMANENT ENVIRONMENTAL MONITORING STATION LOCATIONS (Refer to Figure 2)
-LOCATION4
'AIR O.LOCATION, SAMPLE 1Radio Tower x
2 Dam No. 8 x
3 Trailer Court x
4 Crib House x
5 Main Office x
11
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)
TABLE 7 ENVIRONMENTAL TLD LOCATIONS LOCATION
...No..
LOCATION 1
LA CROSSE MAIN OFFICE AIR SAMPLER BOX 2
DAM #8 AIR SAMPLER BOX 3
RADIO TOWER BUILDING AT AIR SAMPLER 4
TRAILER COURT AIR SAMPLER BOX 5
CRIBHOUSE AIR SAMPLER BOX 6
G-3 CONTROL ROOM 7
SW GATEPOST AT END OF G-3 DIKE 8
ON FENCE N. SIDE OF FISHERMAN'S ROAD 9
SITE ENTRANCE GUARD AREA 10 ON FENCE AT NE CORNER OF THE SWITCHYARD 11 ON N. SITE AREA FENCE GATE 12 G-1 CRIBHOUSE 13 ON MOORING WALKWAY WEST OF LACBWR #2 WAREHOUSE 14 G-3 COAL UNLOADING CRANE 15 POWER POLE ON BLUFF SIDE EAST OF PLANT 16 RESTRICTED AREA FENCE N. SIDE 17 RESTRICTED AREA FENCE E. SIDE 18 RESTRICTED AREA FENCE S. SIDE 19 RESTRICTED AREA FENCE SW CORNER 20 RESTRICTED AREA FENCE W. SIDE 21 RESTRICTED AREA FENCE NW CORNER 12
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)
TABLE 8 RADIO-ENVIRONMENTAL SAMPLES COLLECTED JANUARY-DECEMBER 2007 TYPEOF SMPLENUMBER OF TYPEOF SMPLESAMPLES Penetrating Radiation (TLID's) 83 Air Particulate 256 River Water 36 Sediment 6
Fish 8
13
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)
TABLE 9 QUARTERLY THERMOLUMINESCENT DOSIMETER DOSE MEASUREMENTS IN THE LACBWR VICINITY JANUARY - DECEMBER 2007 BACKGROUND CORRECTED STATION 1 st QUARTER 2nd QUARTER 3rd QUARTER 4th QUARTER NO.
mRem mRem mRem mRem 1
0 0
0 0
2 0
0.2 0.9 1.3 3
0 0
0 Missing 4
4.2 0.8 6.3 0
5 14.4 19.4 10.6 5.2 6
0 0
0 0
7 0
0 1.9 0
8 0
0 2.4 0
9 1.2 5.9 3.6 0.5 10 0
0 1.2 0
11 0
4.5 6.5 0
12 2.6 3.2 7.8 3.2 13 0
0 1.5 0
14 0
0 0
0 15 4.0 10.4 12.2 0
16 19.0 36.1 21.3 42.8 17 29.0 81.1 20.7 28.5 18 35.3 0
35.3 25.6 19 10.3 11.9 20.3 14.7 20 10.7 0
9.5 0.6 21 24.8 53.4 39.4 27.3 Station #1 (La Crosse Main Office) located approximately is considered the Control TLD.
16 miles north of LA CB WR 14
TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)
COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER LA CROSSE DATE pCi/rn C/3PM3---
C/
3 CONTROL 01-03-07
.023+.003
.028+.005
.027+.004
.024+.002
.024+.002 01-09-07
.027+.003
.032+.005
.034+.004
.022+.002
.027+.003 01-17-07
.022 +.002
.025 +.004
.021 +.003
.018 +.002
.020 +.002 01-24-07
.036 +.003
.031 +.006
.028 +.004
.025 +.002
.032 +.003 01-30-07
.029 +.002
.024 +.004 No Sample
.023 +.002
.025 +.002 02-07-07
.027+.003
.015+.002
.018+.003
.017+.002
.030+.003 02-14-07
.027+.003
.022+.002
.026+.003
.018+.002
.025+.002 02-21-07
.029 +.003
.023 +.002
.027 +.003
.019+.002
.026 +.002 02-28-07
.019 +.002
.016 +.002
.012 +.003
.014+.002
.015 +.002 03-07-07
.019+.002
.018+.002
.018+.003
.013+.002
.016+.002 03-14-07
.024 +.002
.022 +.002
.026 +.003
.021 +.002
.022 +.002 03-21-07
.021 +.002
.019 +.002
.020 +.003
.017 +.002
.019 +.002 03-28-07
.024 +.002
.020 +.002
.024 +.003
.020 +.002
.021 +.002 04-04-07
.016+.002
.015+.002
.012+.003
.014+.002
.013+.002 04-10-07
.021 +.003
.018 +.002
.018 +.003
.015 +.002
.018 +.002 04-17-07
.022 +.002
.020 +.002
.021+.003
.021 +.002
.020 +.002 04-25-07
.021 +.002
.018+.002
.020+.003
.018+.002
.016+.002 05-02-07
.018 +.002
.015 +.002
.0161+.003
.017 +.002
.017 +.002 05-09-07
.022 +.002
.017 +.002
.021 +.003
.018+.002
.018 +.002 05-16-07
.022+.002
.018+.002
.028+.004
.019+.002
.020+.002 15
TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)
COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER LA CROSSE DATE pCi/rnPM3C/3 C/
3 CONTROL 05-23-07
.025 +.003
.020 +.002
.023 +.003
.024 +.002
.023 +.002 05-30-07
.022+.002
.017+.002
.019+.003
.019+.002
.019+.002 06-06-07
.016+.002
.016+.002
.016+.002
.016+.002
.017+.002 06-13-07
.023 +.003
.021 +.002
..017+.003
.024 +.002
.024 +.002 06-20-07
.026 +.002
.023 +.002
.021 +.003
.024 +.002
.024 +.002 06-27-07
.020 +.002
.049 +.004
.015 +.002
.022 +.002
.022 +.002 07-03-07
.012+.002
.012+.002
.011 +.002
.012+.002
.011+.002 07-10-07
.027 +.003
.025 +.002
.019 +.003
.027 +.002
.025 +.002 07-18-07
.017+.002
.017+.002
.020+.003
.016+.002
.016+.002 07-25-07
.022 +.002
.023 +.002
.017+.003
.023 +.002
.023 +.002 08-01-07
.026+.003
.024+.002
.016+.002
.029+.002 F
.023+.002 08-08-07
.028+.003
.027+.002
.018+.003
.027+.003
.026+.002 08-21-07
.027+.003
.028+.002
.014+.003
.025+.002
.023+.002 08-22-07
.018+.002
.015+.002
.022+.005
.014+.002
.015+.002 08-29-07
.023 +.002
.022 +.002
.017 +.003
.020 +.002
..023 +.002 09-05-07
.031 +.003
.025+.002
.028 +.003
.029 +.002
.032 +.003 091-7.017+.002
.018+.002
.025+.005
.015+.002
.016+.002 09-19-07
.022 +.002
.023 +.002
.020 +.004
.,014 +.002
.021 +.002 09-26-07
.026 +.003
.024 +.002
.017 +.003
.021 +.002
.023 +.002 10-03-07
.026 +.003
.023 +.002
.030 +.005
.023 +.002
.024 +.002 16
TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)
COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER LA CROSSE DATE pCi/rn3 C/3C/M irn 3
CONTROL 10-10-07
.020 +.002
.021 +.002
.032 +.005
.020 +.002
.020 +.002 10-17-07
.020 +.0,02
.017 +.002
.014+.004
.019+.002
.017+.002 10-24-07
.019+.002
.025+.003
.1+05.019+.002
.023+.002 10-31-07
.027 +.003
.2+.02.026
+.004
.021 +.002
.025 + 1.002 11-07-07
.016 +.002
.017 +.002
.017+.003
.016+.002
.019+.002 11-14-07
.032+.003
.030+.003
.029+.004
.024+.002
.029+.003 11-21-07
.0.22+.002
.025+.002
.023+.003
.017+.002
.022+.002 11-28-07
.025 +.003
.019 +.002
.018 +.003
.015 +.002
.020 +.002 12-05-07
.025 +.003
.022 +.002
.022 +.005
.017 +.002
.024+.002 12-12-07
.037+.003
.031 +.003
..023 +.004 No Sample
.049 +.004 12-19-07
.045+.003
.037 +.003
.031 +.004 No Sample
.045 +.004 12-26-07
.033+.003
.033 +.003
.028 +.003 No Sample
.034 +.003 17
TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/rn 3)
LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 1-03-07 1-03-07 1-03-07 1-03-07 1-03-07 END DATE 1-31-07 1-31-07 1-31-07 1-31-07 1-31-07 ISOTOPES/RL*
Cs-1 34/10
<2.52E-3
<3.30E-3
<7.50E-3
<6.1 1E-3
<2.45E-3 Cs-i 37/20
<2.38E-3
<3.04E-3
<78E3<6.04E-3
<2.57E-3
- RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 1-31-07 1-31-07 1-31-07 1-31-07 1-31-07 END DATE 2-28-07 2-28-07 2-28-07 2-28-07 2-28-07 ISOTOPES/RL*_______
Cs-1 34/10
<2.34E-3
<2.97E-3
<2.OOE-3
<4.06E-3
<2.61 E-3 Cs-i 37/20 1.50E-3 +/- 4.58E-4 2.48E-3 +/- 6.21 E-4
<1.40E-3
<2.35E-3 1.61 E-3 +/- 4.80E-4 i-i-
i
-i
- RL = REPORTING LEVEL 18
TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/rn3)
.LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 2-28-07 2-28-07 2-28-07 2-28-07 2-28-07 END DATE 3-28-07 3-28-07 3-28-07 3-28-07 3-28-07 ISOTOPES/RL*
Cs-1 34/10
<2.35E-3
<2.92E-3
<2.OOE-3
<4.42E-3
<2.33E-3 Cs-i 37/20
<2.42E-3
<3.08E-3
<2.07E-3
<4.66E-3
<2.45E-3
- RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 3-28-07 3-28-07 3-28-07 3-28-76 3-28-07 END DATE 05-02-07 5-02-07 5-02-07 5-02-07 5-02-07 ISOTOPES/RL*
Cs-134/10
<1.83E-3
<2.38E-3
<-1.55E-3
<3.58E-3
<1.88E-3 Cs-i 37/20
<1.96E-3
<2.41 E-3
<1.66E-3
<3.59E-3
<1.92E-3
- RL = REPORTING LEVEL 19
TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/M3)
LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 05-02-07 05-02-07 05-02-07 05-02-07 05-02-07 END DATE 5-30-07 5-30-07 5-30-07 5-30-07 5-30-07 ISOTOPES/RL*
Cs-i 34/10
<2.28E-3
<2.95E-3
<1.96E-3
<4.30E-3
<2.41 E-3 Cs-137/20
<2.45E-3
<3.29E-3
<2.04E-3
<4.45E-3
<2.49E-3
- RL =REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 5-30-07, 5-30-07 5-30-07 5-30-07 5-30-07 END DATE 6-27-07 6-27-07 6-27-07 6-27-07 6-27-07 ISOTOPES/RL*
Cs-1 34/10
<2.38E-3
<3.09E-3
<2.38E-3
<3.69E-3
<2.30E-3 Cs-1 37/20
<2.51 E-3
<3.13E-3
<2.46E-3
<3.84E-3
<2.39E-3
- RL = REPORTING LEVEL 20
TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/rn 3)
LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 6-27-07 6-27-07 6-27-07 6-27-07 6-27-07 END DATE 8-01-07 8-01-07 8-01-07 8-01-07 8-01-07 ISOTOPES/RL*
Cs-1 34/10
<1.92E-3
<1.70E-3
<1.66E-3
<3.29E-3
<1.81E-3 Cs-i 37/20
<1.99E-3
<1.77E-3
<1.80E-3
<3.49E-3
<1.89E-3
- RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 8-01-07 8-01-07 8-01-07 8-01-07 8-01-07 END DATE 8-29-07 8-29-07 8-29-07 8-29-07 8-29-07 ISOTOPES/RL*
Cs-1 34/10
<2.27E-3
<3.1 1E-3
<2.32E-3
<5.08E-3
<2.44E-3 Cs-137/20
<2.44E-3=
<3.24E-3
<2.43E-3
<5.46E-3
<2.58E-3
- RL = REPORTING LEVEL 21
TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/rn3)
LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 8-29-07.
8-29-07 8-29-07 8-29-07 8-29-07 END DATE 9-26-07 9-26-07 9-26-07 9-26-07 9-26-07 ISOTOPES/RL*
Cs-134/10
<2.35E-3
<3.04E-3
<2.33E-3
<5.21 E-3
<2.49E-3 Cs-137/20
<2.41 E-3
<3.20E-3
<2.51 E-3
<5.63E-3
<2.67E-3
- RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 9-26-07 9-26-07 9-26-07 9-26-07 9-26-07 END DATE 10-31-07 10-31-07 10-31-07 10-31-07 10-31-07 ISOTOPES/RL*
Cs-i 34/10
<1.77E-3
<2.70E-3
<2.05E-3
<6.35E-3
<2.1 5E-3 Cs-137/20
<1.90E-3
<2.66E-3
<2.23E-3
<6.31 E-3
<2.31 E-3
- RL = REPORTING LEVEL 22
TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/rn3)
LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 10-31-07 10-31-07 10-31-07 10-31-07 10-31-07 END DATE 11-28-07 11-28-07 11-28-07 11-28-07 11-28-07 ISOTOPES/RL*
Cs-1 34/10
<2.36E-3
<3.52E-3
<2.71 E-3
<5.84E-3
<2.89E-3 Cs-1 37/20
<2.41 E-3
<3.52E-3
<2.78E-3
<5.45E-3
<3.03E-3
- RL =REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 11-28-07 11-28-07 11-28-07 11-28-07 11-28-07 END DATE 1-02-08 1-02-08 1-02-08 1-02-08 1-02-08 ISOTOPES/RL*
Cs-I 34/10
<9.73E-3
<2.65E-3
<2.25E-3
<5.03E-3
<2.57E-3 Cs-1 37/20
<9.92E-3
<2.81 E-3
<2.37E-3
<4.88E-3
<2.63E-3 4
I-I-
I ________________________
L ________________________
I ________________________
C ________________________
C ________________________
- RL = REPORTING LEVEL 23
TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)
SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE:
01-09-07 01-09-07 01-09-07 2-13-07 2-13-07 2-13-07 SAMPLE LOCATION:
DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL*
<149
<149 156 +/-140
<173
<173
<173 Mn-54/l 000
<5.35
<5.31
<5.33
<5.22
<5.27
<5.30 Co-60/300
<5.58
<5.79
<5.70
<5.73
<5.70
<5.70 Zn-65/300
<12.1
<12.0
<12.3
<12.2
<12.2
<12.3 Cs-i 134/30
<5.82
<5.88
<5.82
<5.97
<5.75
<5.97 Cs-137/50
<5.97
<6.11
<6.01-
<2.85 6.03 +/- 1.33
<6.04 I-
.4 4
I-
-4 I.
.4 4
I-
- RL = REPORTING LEVEL 24
TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)
SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE:
3-12-07 3-12-07 3-12-07 4-10-07 4-10-07 4-10-07 SAMPLE LOCATION:
DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL*
<153
<153
<153
<157
<157
<157 Mn-54/11000
<5.38
<5.52
<5.62
<5.53
<5.57
<5.49 Co-60/300
<5.80
<5.95
<5.73
<5.84
<5.68
<5.85 Zn-65/300
<1 1.80
<1 1.80
<12.4
<12.4
<12.0
<12.0 Cs-i 34/30
<5.91
<5.87
<5.87
<5.84
<5.90
<5.78 Cs-1 37/50
<6.33 9.16 +/-2.12
<6.18 8.14 +/-1.43 3.56 +/-1.15
<4.33
- RL = REPORTING LEVEL 25
TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)
SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE:
5-14-07 5-14-07 5-14-07 6-07-07 6-07-07 6-07-07 SAMPLE LOCATION:
DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL*
<147
<147
<147
<149
<149
<149 Mn-54/1 000
<5.41
<5.38
<5.38
<5.42
<5.27
<5.32 Co-60/300
<5.68
<5.67
<5.84
<5.60
<5.66
<5.52 Zn-65/300
<12.3
<12.0
<12.0
<1 1.8
<1 1.6
<12.0 Cs-1 34/30
<5.81
<5.86
<5.76
<5.84
<ý5.85
<5.73 Cs-i 37/50
<6.16
<4.44
<5.93 9.48 +/-2.0
<6.28
<5.89
- RL = REPORTING LEVEL 26
TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)
SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE:
7-10-07 7-10-07 7-10-07 8-14-07 8-14-07 8-14-07 SAMPLE LOCATION:
DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL*
<158
<158
<158
<155
<155
<155 Mn-54/1000
<5.44
<5.42
<5.38
<5.33
<5.33
<5.52 Co-60/300
<5.79
<2.67
<5.65
<5.62
<5.85
<5.56 Zn-65/300
<12.2
<12.3
<12.1
<12.0
<12.0
<12.2 Cs-134/30
<5.86
<5.83
<5.86
<5.87
<5.88
<5.91 Cs-137/50
<6.14
<3.99
<6.19
<6.12
<6.15
<6.21
- RL = REPORTING LEVEL 27
TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)
SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE:
9-11-07 9-11-07
.9-11-07 10-09-07 10-09-07 10-09-07 SAMPLE LOCATION:
DAM 8 OUTFALL VICTORY
'DAM 8 OUTFALL VICTORY ISOTOPES/RL*
<146
<146
<146
<147
<147
<147 Mn-54/1 000
<5.52
<5.43
<5.22
<5.43
<5.38
<5.25 Co-60/300
<5.84
<5.72
<5.52
<5.62
<5.56
<5.75 Zn-65/300
<1 1.7
<1 1.8
<1 1.6
<1 1.9
<11.7
< 12.2 Cs-134/30
<5.91
<5.90
<5.85
<5.81
<5.84
<5.80 Cs-137/50
<4.01 3.17 +/- 1.13
<3.13
<6.01
<6.30
<6.12
- RL = REPORTING LEVEL 28
TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Liter)
SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE:
11-14-07 11-14-07 11-14-07 12-11-07 12-11-07 12-11-07 SAMPLE LOCATION:
DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL*
<162
<162
<162
<143
<143
<143 Mn-5411000
<5.49
<5.48
<5.45
<5.34
<5.51
<5.47 Co-60/300
<5.72
<5.59
<5.81
<5.65
<5.67
<5.66 Zn-651300
<12.0
<12.3
<1 1.9
<12.6
<12.1
<12.3 Cs-i 34/30
<5.77
<5.98
<5.82
<5.90
<5.89
<6.02 Cs-137150
<6.18
<6.17
<6.27
<6.19
<6.10
<5.94
- RL = REPORTING LEVEL 29
TABLE 13 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER SEDIMENT IN THE VICINITY OF LACBWR (Concentration in pCiIKg)
(Reporting Level = 10 times Control Value)
COLLECTION DATE SAMPLE # 1 SAMPLE # 2 SAMPLE # 3 SAMPLE # 1 SAMPLE # 2 SAMPLE # 3 SAMPLE LOCATION 6-20-07 6-20-07 6-20-07 9-25-07 9-25-07 9-25-07 UPSTREAM OUTFALL DOWNSTREAM UPSTREAM OUTFALL DOWNSTREAM ISOTOPES Cs-1 34
<8.78
<7.94
<17.6
<9.01
<7.86
<17.6 Cs-137
<5.12 897 +/-60.5 110 +/-8.80
<8.18 133 +/-9.61
< 15.2 Co-60 6.67 +/- 1.29
+
4 30
TABLE 14
.FISH SAMPLE ACTIVITY IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Kg)
SAMPLE #1 SAMPLE #2 SAMPLE #1 SAMPLE #2 SAMPLE #1 SAMPLE #2 COLLECTION DATE:
3-27-07 3-27-07 6-20-07 6-20-07 9-25-07 9-25-07 FISH SPECIES:
CARP WALLEYE BASS CARP CARP WALLEYE ISOTOPES/RL*
Mn-541/3E4
<10.8
<1 1.2
<10.7
<8.71
<8.89
<8.86 Co-60/1 E4
<12.1
<12.6
< 12.3
<10.0
<10.0
<9.99 Zn-651 2E4
<29.3
<27.4
<26.6
<21.6
<22.6
<22.1 Cs-134/ 1E3
<13.1
<1 1.2
<1 1.0
<8.75
<9.03
<8.57 Cs-1 37/ 2E3
<1 1.9
<12.2
<7.95
<9.27 8.37+2.00 12.7+2.18
- RL =REPORTING LEVEL 31
TABLE 14 FISH SAMPLE ACTIVITY IN THE VICINITY OF LACBWR (Report Concentrations in pCi/Kg)
SAMPLE #1 SAMPLE #2.
SAMPLE #1 SAMPLE #2 SAMPLE #1 SAMPLE #2 COLLECTION DATE:
11-01-07 11-01-07 FISH SPECIES:
CARP WALLEYE ISOTOPES/RL*
Mn-54/ 3E4
<12.0
<8.64 Co-60/1 E4
<13.5
<9.86 Zn-651 2E4
<30.2
<22.5 Cs-1 34/ 1 E3
<12.6
<8.47______
Cs-1 37/ 2E3 10.2 +/-3.5
<5.84
- RL =REPORTING LEVEL 32