ML12088A043

La Crosse Boiling Water Reactor - Annual Radioactive Effluent Report and Radiological Environmental Monitoring Report

ML12088A043
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/09/2012
From:	Berg W L Dairyland Power Cooperative
To:	Document Control Desk, NRC/FSME
References
LAC-14213
Download: ML12088A043 (67)

Text

WILLIAM L. BERG President and CEO DAIRYLAND POWER COOP E RAT IV E March 9, 2012 In reply, please refer to LAC- 14213 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 (1) NRC Letter, Keppler to Linder, dated August 12, 1983, Inspection Report 50-409/83-10 (DRMSP)(2) LACBWR Technical Specifications 6.4.2, 6.5.1.1 .c & d

REFERENCES:

In accordance with 10 CFR 50.36a(a)(2), this letter serves to transmit to you the Radioactive Effluent Report and Radiological Environmental Monitoring Report for the La Crosse Boiling Water Reactor (LACBWR) for 2011.This report replaces the earlier 2011 Radioactive Effluent Report and Radiological Environmental Monitoring Report sent on March 1, 2012, as documented transmittal LAC-14213. Please replace the earlier report in its entirety.If you have any questions, please contact us.Sincerely, William L. Berg, President and CEO WLB:LLN:jkl Enclosures cc/encl: Peter Lee, Ph.D., NRC Reg. III, Decommissioning Branch John Hickman, NRC Project Manager Don Hendrikse, Wisc. Div. of Health A Touchstone Energy Cooperative 0 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, 2011)DAIRYLAND POWER COOPERATIVE 3200 EAST AVENUE SOUTH LA CROSSE WI 54602-0817 TABLE OF CONTENTS SECTION A: RADIOACTIVE EFFLUENT REPORT Section Title Page Intro d u ctio n ...............................................................................

..... 1 1.0 R egulatory Lim its .............................................................................

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

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

4 4.0 A nalytical M ethods ..........................................................................

4 5.0 B atch R eleases .............................................................................

5 6.0 A bnorm al 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 Page Intro d uctio n ...............................................................................

....... 1 1.0 S am ple C ollection

......................................................................

.... 2 2.0 Results of the 2011 Radio-Environmental Monitoring Survey ..........

2 3 .0 C onclusions

...............................................................................

.... .. 4 4.0 Interlaboratory Comparison Program Results ................................

5 TABLE OF CONTENTS TABLES SECTION A: RADIOACTIVE EFFLUENT REPORT Table No. Title Page 1A Effluent and Waste Disposal -Gaseous Effluents Sum m ation of All Releases ............................................................

7 1B Effluent and Waste Disposal -Gaseous Effluents E levated R elease ............................................................................

8 2A Effluent and Waste Disposal -Liquid Effluents Sum m ation of A ll Releases ............................................................

9 2B Effluent and Waste Disposal -Liquid Effluents

..............................

10 3 Effluent and Waste Disposal Annual Report -2011 Solid Waste and Irradiated Fuel Shipm ents ........................................................

11 SECTION B: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Table No. Title Page 5 Sample Frequency and Analysis of Radio Environmental Samples 10 6 Permanent Environmental Monitoring Station Locations

................

11 7 Environm ental TLD Locations

.........................................................

12 8 Radio-Environmental Samples Collected January-December 2011. 13 9 Quarterly Thermoluminescent Dosimeter Dose Measurements in the LA C BW R V icinity ..................................................................

14 10 Weekly Gross Beta Air Particulates in the LACBWR Vicinity ...........

15 11 Air Particulate Com posite Results ..................................................

19 12 Results of Analysis of Mississippi River Water in the Vicinity of LA C BW R ...............................................................................

..... 25 13 Results of Analysis of Mississippi River Sediment in the Vicinity of LA C B W R ...............................................................................

.... .3 1 14 Fish Sample Activity in the Vicinity of LACBWR .............................

32 ii TABLE OF CONTENTS FIGURES No.Title Page FIGURE 1 FIGURE 2 FIGURE 3 FIGURE 4 LAC BW R Property M ap ...........................................................

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 CBWR), also known as Genoa Station No. 2, is located on the east bank of the Mississippi River near Genoa, Vernon County, Wisconsin.

The plant was designed and constructed by the Allis-Chalmers Manufacturing Company. It was completed in 1967 and had a generation capacity of 50 MW (165 MW(th)). The reactor is owned by Dairyland Power Cooperative (DPC).The reactor went critical in July 1967 and first contributed electricity to DPC's system in April 1968. After completing full power tests in August 1969, the plant operated between 60% and 100% full power, with the exception of plant shutdowns for maintenance and repair.In April of 1987 plant operation was ceased. The reactor was defueled and placed in a SAFSTOR mode. In August of 1987 a possession-only license was received.

In 2007 the reactor vessel was removed from the site and buried at the Barnwell waste repository.

In 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, 2011.1 EFFLUENT AND WASTE DISPOSAL REPORT (Supplemental Information)

FACILITY:

La Crosse Boilinq Water Reactor LICENSEE:

Dairyland 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 (ODCM).Also, in accordance with 10 CFR 50, Appendix I, the ODCM limitations for gaseous effluent radioactive material limit the air dose to a member of the public from noble gases in areas beyond the Effluent Release Boundary to less than 5 mRad gamma and 10 mRad beta per calendar quarter, and less than 10 mRad gamma and 20 mRad beta per calendar year. The dose limits from H-3 and particulates with half-lives greater than 8 days are less than 7.5 mRem per calendar quarter, and less than 15 mRem per calendar year to any organ.Cumulative dose contributions from gaseous effluent releases are determined in accordance with the LACBWR Offsite Dose Calculations Manual.2 EFFLUENT 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/ml, 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 Iron-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.c. Radioiodines Since the plant shutdown in April 1987, the 1-131/I-133 have decayed completely to stable elements.

Amendment 66 to the LACBWR Technical Specifications, deleted 4 EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)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.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: 5 EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)(1)(2)(3)(4)(5)(6)Number of Batch Releases: Total Time Period for Batch Releases: Maximum Time Period for a Batch Release: Average Time Period for a Batch Release: Minimum Time Period for a Batch Release: Average-Stream Flow Rate During Periods of Release of Effluent into a Flowing Stream: 28 514.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 23.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 18.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 11.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> 98250 ft 3/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 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2011 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES UNIT QTR QTR QTR QTR TOTAL A. FISSION & ACTIVATION GASES 1. TOTAL RELEASE Ci O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 2. AVERAGE RELEASE RATE FOR pCi/ Sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 PERIOD B. IODINE 1-131 -No longer analyzed for.C. PARTICULATES

1. PARTICULATES WITH HALF- Ci 4.21 E-07 7.69E-07 8.21E-07 3.24E-07 2.34E-06 LIVES > 8 DAYS 2. AVERAGE RELEASE RATE FOR g.Ci/ Sec 5.41 E-08 9.78E-08 9.20E-08 4.08E-08 PERIOD 3. GROSS ALPHA RADIOACTIVITY Ci 0.00+00 5.90E-08 7.20E-08 4.80E-08 1.79E-07 D. TRITIUM 1. TOTAL RELEASE Ci 7.16E-03 6.40E-03 3.98E-03 8.OOE-03 2.55E-02 2. AVERAGE RELEASE RATE FOR p.Ci/Sec 9.21E-04 8.14E-04 5.01E-04 1.01E-03 PERIOD E. PERCENTAGE OF ODCM DOSE LIMITS FOR GASEOUS EFFLUENT RELEASES QTR QTR QTR QTR YEARLY 1. NOBLE GAS RELEASE GAMMA % 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BETA % 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 0.00E+00 2. H-3 AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS GAMMA (Highest Organ) % 5.14E-05 6.29E-05 5.85E-05 5.77E-05 1.18E-04 7 EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2011 GASEOUS EFFLUENTS

-ELEVATED RELEASE I CONTINUOS MODE UNIT QTR QTR QTR QTR TOTAL NUCLIDES RELEASED 1. FISSION GASES KRYPTON-85 Ci O.OOE+00 O.0OE+00 O.OOE+00 O.OOE+00 Q.OOE+00 TOTAL FOR PERIOD Ci O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 2. IODINE 1-131 -Analysis no longer required.3. PARTICULATES STRONTIUM-90 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CESIUM-134 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CESIUM-137 Ci 2.04E-07 7.69E-07 8.21E-07 3.24E-07 2.12E-06 COBALT-60 Ci 2.17E-07 O.OOE+00 O.0OE+00 O.OOE+00 2.17E-07 Ci Ci Ci Ci TOTALS Ci 4.21 E-07 7.69E-07 8.21E-07 3.24E-07 2.34E-06 8 EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2011 LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES UNIT QTR QTR QTR QTR TOTAL A FISSION & ACTIVATION PRODUCTS 1. TOTAL RELEASE (NOT INCL. Ci 7.79E-03 2.28E-02 8.33E-03 1.62E-03 4.06E-02 TRITIUM, GASES, ALPHA)2. AVERAGE DILUTED p.Ci/ ml 7.80E-09 2.85E-09 2.02E-09 2.06E-09 CONCENTRATION DURING PERIOD B. TRITIUM 1. TOTAL RELEASE Ci 1.93E-03 2.30E-03 2.88E-03 1.07E-03 8.18E-03 AVERAGE DILUTED p.Ci/ ml 1.93E-09 2.88E-10 7.60E-10 1.36E-09 CONCENTRATION DURING PERIOD C. DISSOLVED AND ENTRAINED GASES 1. TOTAL RELEASE Ci 0.OOE+00 0.OOE+00 0.Q0E+00 0.OOE+00 0.OOE+00 2. AVERAGE DILUTED _Ci/_ml 0.00E+00 0.00E+00 0,00E+00 0,00E+00 CONCENTRATION DURING PERIOD D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE Ci 6.97E-06 2.96E-05 1.20E-05 2.43E-06 5.10E-05 E. VOLUME OF WASTE Liters 4.75E+04 3.81 E+05 1.38E+05 3.87E+04 6.05E+05 RELEASED (PRIOR TO DILUTION)F. VOLUME OF DILUTION Liters 9.99E+08 8.01E+09 3.78E+09 7.87E+08 1.36E+10 WATER USED DURING PERIOD G. PERCENTAGE OF ODCM LIMITS FOR LIQUID RELEASES QTR QTR QTR QTR YEARLY HIGHEST ORGAN % 3.61 9.20 2.73 0.74 8.14 WHOLE BODY % 7.63 19.45 5.78 1.57 17.21 9 EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2011 LIQUID EFFLUENTS NUCLIDES RELEASED UNIT QTR QTR QTR QTR MANGANESE-54 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 IRON-55 Ci O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 COBALT-60 Ci 1.60E-04 8.07E-04 3.66E-04 7.20E-05 STRONTIUM-90 Ci 1.32E-04 4.73E-04 1.56E-04 4.53E-05 CESIUM-134 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CESIUM-137 Ci 7.49E-03 2.15E-02 7.81E-03 1.55E-03 TOTAL FOR PERIOD Ci 7.79E-03 2.28E-02 8.33E-03 1.67E-03 (ABOVE)KRYPTON-85 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 10 EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT -2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL (Not Irradiated Fuel)6.ONTH 6-MONTH 1. TYPE OF WASTE UNIT PERIOD, PERIOD.- :TOTAL a. SPENT RESINS, FILTER SLUDGES, m3 0 0 0 EVAPORATOR BOTTOMS, ETC Ci 0 0 0 b. DRY COMPRESSIBLE WASTE, m3 15 32.4 47.4 CONTAMINATED EQUIPMENT, ETC Ci 1 E-03 1.4E-02 1.5E-02 C. IRRADIATED COMPONENTS, CONTROL m 3 0 0 0 RODS, ETC Ci 0 0 0 d. OTHER (DESCRIBE) m3 0 0 0 Ci 0 0 0 ,'6-MONTH 6-MONTH 2. ESTIMATE OF MAJOR NUCLIDE PERCENT PERIOD PERIOD COMPOSITION (BY TYPE OF WASTE) OF TOTAL CURIES C URIES Co-60 32.7 3.3E-04 4.6E-03 Fe-55 6.7 6.7E-05 9.4E-04 Ni-63 56.1 5.6E-04 7.9E-03 Pu-241 3.2 3.2E-05 4.5E-04 3. SOLID WASTE DISPOSITION MODE OF NO. OF SHIPMENTS TRANSPORTATION DESTINATION 2 Sole Use OAK RIDGE, TN B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

NO OF SHIPMENTS NONE MODE OF TRANSPORTATION DESTINATION 11 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 2011 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 2011 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 5.19E-06 mRem. The cumulative 2011 annual maximum organ dose from these radionuclides was also approximately 1.78E-05 mRem.The highest historical annual average X/Q equal to 1.82 E-6 sec/m 3 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. Liquid Effluent Releases The maximum quarterly organ dose from liquid releases was approximately mRem. The cumulative 2011 annual organ dose was approximately 8.14E-01 mRem.The maximum quarterly total body dose for liquid releases was approximately 2.92E-01 mRem, and the cumulative 2011 annual total body dose was approximately 5.16E-01 mRem.c. Conclusion All calculated offsite doses were below ODCM limits.12 EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)9. 0 OFFSITE DOSE CALCULATION MANUAL (ODCM) REVIEW No changes were made to the ODCM in 2011.10.0 PROCESS CONTROL PROGRAM (PCP) REVIEW The PCP was reviewed in 2011. The PCP was numbered as HSP-04.0 and converted to the required format. No significant changes were made to the PCP. The PCP is included in its entirety.13 Page 0.1 HSP-04.0 La Crosse Boiling Water Reactor LACBWR HEALTH & SAFETY DEPARTMENT PROCEDURE PROCESS CONTROL PROGRAM (PCP)DAIRYIAD POWER COO P1 I AT 71V f A Tnwchfzo Energ,' Cbop~ratii

_0_RECORD AND CONTROL-OF INITIAL ISSUE, REVISIONS

& PERIODIC-REVIEWS PREPARED BY H & S OPERATIONS ENGINEERING APPROVED &OR R REVIEW EVIEW QA REVIEW ISSUED*ISSUE REVIEWED BY REVIEW REVIEW REVIEWDATE SIGNATURE DATE SIGNATURE DATE SIGNATURE DATE SIGNATURE DATE SIGNATURE DATE OF ISSUE 0_ _ ..i- ,"_J"_ -.__f* LACBWR PLANT MANAGER** H&S SUPERVISOR OR RAD.PROT. ENGINEER Page 0.2 HSP-04.0 LACBWR HEALTH AND SAFETY DEPARTMENT PROCEDURE PROCESS CONTROL PROGRAM (PCP)Issue Notice No. 0 Dated APR 6 8 .7011 INSTRUCTIONS Description of and Reason for Change New Procedure REMOVE AND INSERT ALL PAGES Number the PCP as HSP 4.0 and convert to ACP 7.1 format.Minor word corrections for clarity.Changes to this procedure does not require 50.59 screening.

This issue shall not become effective unless accompanied by a new cover sheet, properly signed off in the appropriate review/approval columns.

HSP-04.0 Issue 0 LACBWR HEALTH AND SAFETY DEPARTMENT PROCEDURE PROCESS CONTROL PROGRAM (PCP)1.0 PURPOSE 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.

2.0 REQUIREMENTS

2.1 Technical

Specifications 2.1.1 "The PCP shall be maintained onsite and will be available for NRC review." 2.1.2 "Licensee-initiated 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: " Information to support the rationale for the change;" A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and" Documentation of the fact that the change has been reviewed and found acceptable by the ORC." Page 1 of 13 HSP-04.0 Issue 0 2.2 Wet Radioactive Waste 2.2.1 These wastes will be transferred to the Waste Treatment Building (WTB) for storage before their ultimate disposal.2.2.2 The WTB is located to the northeast of the Reactor Building.

The WTB contains facilities and equipment for the collection, 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 ft 3 stainless steel Spent Resin Receiving Tank (SRRT) with associated resin receiving and -transfer piping, SRRT recirculation piping, SRRT demineralized 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.2.2.3 Wet radioactive waste materials may typically be described as whole bead demineralizer resins, mechanical cartridge filters and waste sludge. When expended, resins and sludge are transferred to the SRRT. The cartridge filters may be added directly to a HIC as indicated below.2.2.4 From the SRRT, partially dewatered spent resins and/or sludge material, are pumped at a low flow rate/pressure with a Roper-type screw pump to a High Integrity Liner (HIC), located in the adjacent shielded cubicle as described in Operating Manual Volume VII. The wall between the SRRT and the 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 is dewatered to the SRRT which is subsequently dewatered.

A final dewatering is performed as described in Operating Manual Volume VII.Samples of wet waste are analyzed for isotopic composition and for waste classification before disposal.Page 2 of 13 HSP-04.0 Issue 0 2.2.5 The final dewatering will ensure that the contents of the HIC meets the requirements of 10CFR61.56(a)(3) and the burial site criteria for free-standing liquids. Stabilization of the dewatered wet waste is provided by the HIC as authorized by 10CFR61.56(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.2.2.6 Once final dewatering is completed, the HIC is inspected and the lid will be closed and sealed. The HIC is surveyed, decontaminated, if needed, and loaded into an appropriate shipping cask.NOTE: Dewatered spent mechanical cartridge filters may be added directly to a HIC containing spent resins, if necessary.

2.2.7 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.

2.2.8 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.2.3 Dry Active Wastes 2.3.1 The PCP and Health and Safety Procedures in Section 4 establish the steps used to process, package and ship the Dry Active Wastes (DAW)from the plant, in accordance with 10CFR20.2006 and 49CFR Part 173.The Dry Active Waste materials may typically 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 .56.2.3.2 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.

Page 3 of 13 HSP-04.0 Issue 0 2.3.3 DAW for Direct Burial These wastes processed for direct burial from LACBWR are packaged in approved shipping containers as required by the burial site. Sufficient absorbent material is added to each waste container to limit free standing and non-corrosive liquid to less than 1% of the volume. Representative samples of DAW are analyzed for isotopic composition and for waste classification.

2.3.4 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.2.4 Irradiated Material 2.4.1 Irradiated material packaging and shipping may be handled by a licensed contractor hired by Dairyland Power to perform such shipments.

DPC employees will provide oversight of these shipments to ensure compliance.

2.5 Waste

Classification 2.5.1 Due to the closing of the Barnwell burial site in 2007, LACBWR engaged in a campaign to dispose of all Class B and C waste. Currently LACBWR has no known Class B or Class C waste. LACBWR waste will be classified as Class A stable or unstable.

Waste classification is based on the requirements of 10CFR61.55.

2.5.2 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.

Page 4 of 13 HSP-04.0 Issue 0 2.5.3 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.

2.5.4 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 10CF-R61.56(a)-(3) and Table 1 and Table 2.2.6 Shipment Manifest 2.6.1 Each shipment of solid radioactive waste to a licensed land disposal facility will be accompanied by a shipment manifest as required by 10CFR20.2006 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.2.6.2 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.

2.6.3 Waste

containing more than 0.1% chelating agents by weight will be identified and the weight percentage of the chelating agent estimated.

Waste classification will be clearly indicated on the manifest.

The total quantity of the radio-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.Page 5 of 13 HSP-04.0 Issue 0 2.6.4 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 2.6.5 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.

2.6.6 LACBWR

will maintain a manifest record-keeping and tracking system that meets the requirements of 10CFR20.2006.

2.6.7 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.2.7 Administrative Controls 2.7.1 Training A training program will be conducted to ensure that waste processing will be performed according to plant procedures and the PCP. 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.2.7.2 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.

Page 6 of 13 HSP-04.0 Issue 0 2.7.3 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.2.7.4 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.

2.7.5 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.

2.7.5.1 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).2.7.5.2 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.

2.7.5.3 Production of a solidified Class B or C waste form that has any of the following characteristics:

Page 7 of 13 HSP-04.0 Issue 0" 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.* 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).

Page 8 of 13 HSP-04.0 Issue 0 ATTACHMENT 1 SECURITY PLAN FOR TRANSPORTATION OF LACBWR HAZARDOUS MATERIALS 1.0 PURPOSE 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 CFR 172 Subpart I.This plan applies to hazardous material consisting of radioactive material, or radioactively contaminated material in packages, and/or shipments that require placarding.

2.0 DEFINITIONS

2.1 General

Employee Training (GET) -annual program that provides site specific training for employees, of which security training is included.2.2 LSA: Low Specific Activity -Class 7 material with limited specific activity which satisfies the description and limits set forth in 49 CFR 173.403 2.3: LSE: LACBWR Site Enclosure

-All area within the fence that surrounds the LACBWR facility.2.4: SCO: Surface Contaminated Object -A solid object which is not itself radioactive but which has radioactive material distributed on its surfaces.

3.0 REFERENCES

3.1 49 CFR 171-180 (Hazardous Materials Regulations)

3.2 Physical

Security Plan and Procedures for LACBWR 3.3 TPP-7, General Employee Training (GET) Procedure Page 9 of 13 HSP-04.0 Issue 0 Attachment 1 3.4 La Crosse Boiling Water Reactor Process Control Program (PCP)3.5 Health & Safety Department Procedures

-Section 4: Waste Disposal 4.0 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 I, are satisfied.

4.1 LACBWR

Plant Manager/Security Supervisor:

DPC management responsibility for administration and implementation of security program. Responsible for day-to-day oversight of the security organization. (See Ref. 2.)4.2 Contract Security Post Commander:

Overall supervisory and training responsibility for the Contract Security Force. (See Ref. 2.)4.3 DPC Health and Safety/Maintenance Supervisor:

Responsible for all processing, packaging and preparation of HM for transportation.

4.4 DPC Human Resources:

Responsible for screening and hiring all DPC personnel.

4.5 Traininq

Supervisor:

Responsible for ensuring initial and annual training is performed for all LACBWR personnel.

5.0 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 normally in the 1-10 mCi range. There is no Page 10 of 13 HSP-04.0 Issue 0 Attachment 1 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.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 NRC under 10 CFR 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 LSA/SCO 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-137 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.Page 11 of 13 HSP-04.0 Issue 0 Attachment 1 6.0 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.

7.0 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 DPC 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.Page 12 of 13 HSP-04.0 Issue 0 Attachment 1 8.0 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 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.

9.0 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.10.0 RECORDS Appropriate records production Are specified in the LACBWR PCP, the Health &Safety Department Procedures, and/or the GET training procedure.

All records generated using this plan will be maintained in accordance with ACP 18.1 Page 13 of 13 SECTION B ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT INTRODUCTION:

The Radiological Environmental Monitoring (REM) Program is conducted to comply with the requirements of the ODCM and in accordance with 10 CFR 50 Appendix I. 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 (ODCM).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 2011.2.0 RESULTS OF THE 2011 RADIO-ENVIRONMENTAL MONITORING SURVEYS During 2011, 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 2011 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 Ipm 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 were 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 remained 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 of 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 2011 exhibited no significant contribution from LACBWR.4 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT -(cont'd)4.0 INTERLABORATORY COMPARISON PROGRAM RESULTS During 2011, 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.

LAGBWR CONTRACTOR:

ANALYSIS ... "RATIO-....____ _ .RESULTS .RESULTS T GROSS BETA 216 pCi 235 pCi 0.92 GROSS ALPHA 82.4 pCi 89.7 pCi 0.92--1-131 1... _00_pCi/I

-88.7 pCi/l. 1.3.Cr-51 584 pCi/I 566 pCi/I 1.03 Cs-134 164 pCi/I 171 pCi/I 0.96 Cs-137 239 pCi/I 210 pCi/I 1.14 Co-58 235 pCi/I 221 pCi/I 1.06 Mn-54 273 pCi/I 241 pCi/I 1.13 Fe-59 216 pCi/I 183 pCi/I 1.18 Zn-65 337 pCi/I 291 pCi/I 1.16 Co-60 297 pCi/I 270 pCi/I 1.10 H-3 1.19E4 pCi/I 1.09E4 pCi/I 1.09 5

.L1}SiOit BOUNDli 1109 ft radifit 1000 500 ._ -_ 1000 SCALE OF FEET T.-joiN. , R3-W.OF THE 5th PM.-JEFFERSON TOWNSHIP HOUSTON COUNTY, MINNESOTA I SEC. 5 T"12-I-N'E- ISLAND 126 IS UNDER TH JURISDICTION OF UPPER MISSISSIPPF RIVER WILD LIFE AND FISH REFUGE.INDICATILS MILES ABOVE THlE MOUTH OF ISE 01110 RIVER.FIGURE 1 -LACBWR PROPERTY MAP 6 EhivirormientalLocations FIGURE 2 -PERMANENT ENVIRONMENTAL MONITORING STATION LOCATIONS (Refer to Table 6)7 FIGURE 3 -LACBWR ENVIRONMENTAL DOSE ASSESSMENT LOCATIONS 8 169 to SF7.I i II U FIGURE 4 -LACBWR ENVIRONMENTAL 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)LOATlION 'AIR~NO.ý LOAIN-MLE-1 Radio 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 LOCT ION 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 2011 NUMBER OF TYPE OF SAMPLE SAMPLES Penetrating Radiation (TLD's) 84.Air Particulate 253 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 2011 BACKGROUND CORRECTED STATION 1st QUARTER 2nd QUARTER 3rd QUARTER 4th QUARTER NO. mRem mRem mRem mRem 1 0 0 0 0 2 0 0 0 1.3 3 0 0 0 0 4 0.3 0 1.7 3.2 5 0 0 0 0 6 0 0 0 0 7 0 0 0 0 8 0 0 0 0 9 0 0 1.4 1.1 10 0 0 0 0 11 0 0 0 0.9 12 0.4 0.4 1.8 1.6 13 0 0 0 0 14 0 0 0 0 15 3.0 3.6 6.3 6 16 6.6 7.6 5.9 5.3 17 5.3 6.0 11.7 6 18 18.8 22.0 21.5 21.4 19 6.9 12.2 25.4 5.8 20 0 0 1.1 1.1 21 4.2 2.7 4.0 5.7 Station #1 (La Crosse Main Office) located approximately is considered the Control TLD.16 miles north of LACBWR 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/m 3 pCi/m 3 pCi/m 3 pCi/lm 3 CONTROL.1-5-2011 .028+.002

.025+.002

.011+.022

.030+.003

.057+.005 1-12-2011

.026+.002

.018+.002

.012+.002

.020+.002

.020+.002 1-19-2011

.028+.002

.025+.002

.011+.002

.025+.003

.027+.002 1-26-2011

.031+.002

.023+.002

.030+.003

.030+.003

.033+.002 2-2-2011 .022+.002

.021+.002

.008+.002

.025+.003

.020+.002 2-9-2011 .026+.002

.023+.002

.008+.002

.023+.003

.022+.002 2-23-2011

.020+.002

.012+.002

.003+.002

.012+.002

.014+.002 3-2-2011 .025+.002

.023+.002

.008+.002

.024+.002

.024+.002 3-9-2011 .020+.002

.020+.002

.022+.002

.021+.002

.021+.002 3-16-2011

.021+.002

.019+.002

.016+.002

.022+.002

.021+.002 3-23-2011

.023+.002

.022+.002

.022+.002

.028+003 .023+.002 3-30-2011

.029+.002

.028+.002

.026+.002

.030+.003

.028+.002 4-6-2011 .034+.002

.030+.002

.030+.002

.034+.003

.038+.002 4-13-2011

.017+.002

.020+.002

.018+.002

.018+.002

.016+.002 4-19-2011

.019+002 .022+.002

.022+.003

.017+.002

.021+.002 4-27-2011

.016+.002

.016+.002

.015+.002

.012+.002

.013+.001 5-5-2011 .011+.001

.012+.002

.013+.002

.011+.002

.011+.001 5-11-2011

.017+.002

.015+.002

.019+.002 No Sample .018+.002 5-18-2011

.015+.002

.013+.002

.014+.002

.016+.002

.014+.001 5-25-2011

.012+.002

.014+.002

.016+.002

.013+.002

.012+/-.001 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/m 3 pCi/m 3 pCi/m 3 pCi/m 3 CONTROL 6-1-2011 .017+.002

.014+.002

.016+.002

.017+.002

.014+.001 6-7-2011 .020+.002

.023+.002

.021+.003

.024+.002

.021+.002 6-15-2011

.016+.002

.016+.002

.010+.002

.016+.002

.013+.001 6-22-2011

.014+.002

.017+.002

.012+.002

.015+.002

.014+.001 6-29-2011

.011+.002

.015+.002

.014+.002

.015+.002

.013+.001 7-5-2011 .020+.002

.020+.002

.021+.003

.020+.002

.023+.001 7-13-2011

.021+.002

.021+.002

.022+.002

.022+.002

.019+.002 7-20-2011

.029+.002

.025+.002

.029+.003 I .027+.002

.023+.002 7-27-2011

.015+.002

.017+.002

.012+.002

.018+.002

.014+.001 8-3-2011 .028--.022

.026.002 .027+.003

.030+.002

.025+.002 8-10-2011

.024+.002

.023+.002

.023+.003

.024+.002

.022+.002 8-17-2011

.020+.002

.023+.002

.022+.003

.023+.002

.020+.002 8-25-2011

.019+.002

.018+.002

.019+.002

.023+.002

.017+.001 8-31-2011

.017+.002

.024+.002

.025+.003

.019+.002

.016+.002 9-7-2011 .021+.002

.022.+.002

.024+.003

.026+.002

.017+.002 9-15-2011

.025+.002

.021+.002

.022+.002

.021+.002

.022+.002 9-21-2011

.015+.002

.017+.002

.019+.003

.018+.002

.017+.002 9-28-2011

.012+.002

.013+.002

.013+.002

.012+.002

.011+.001 10-5-2011

.024+.002

.019+.002

.019+.002

.019+.002

.017+.002 10-13-2011

.020+.002

.019+.002

.019+.002

.017+.002

.014+.002 10-19-2011

.013+.002

.016+.002

.019+.002

.016+.002

.015+.002 10-19-201_.013+.00

.016+.002___

.09 .0 .016+.002_____

.015+.002__

TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)i COLLECTION..

LACBWRkPLANT TRAILER COURT DAM #8 RA'DIOI TOWER, LA CROSSE DATE pCir 3 pC3Ira 3 pCi/m 3.: '3'i/ , CONTROL 10-27-2011

.020+/-.002

.022+.002

.020+.002

.023+.002

.021+.002 11-2-2011

.025+.003

.025+.003

.030+.003

.029+.002

.028+.003 11-9-2011

.027+.003

.029+.003

.024+.003

.025+.002

.019+.002 11-16-2011

.030+.003

.029+.003

.029+.003

.032+.002 NO SAMPLE 11-23-2011

.019+.002

.020+/-.002

.022+/-.003

.019+.002

.026+.002 11-30-2011

.028+.002

.031+.003

.031+.003

.029+.002

.028+.002 12-7-2011

.025+.002

.029+.003

.020+.003

.022+.002

.022+.002 12-14-2011

.036+.003

.034+.003

.019+.003

.037+.003

.034+.003 12-21-2011

.038+.003

.030+.003

.022+.003

.035+.003

.032+.002 12-28-2011

.018+.002

.017+.002

.012+.002

.021+.002

.020+.002 TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m 3)LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 1-5-2011 1-5-2011 1-5-2011 1-5-2011 1-5-2011 END DATE 2-2-2011 2-2-2011 2-2-2011 2-2-2011 2-2-2011 ISOTOPES/RL*

Cs-134/10

<2.68E-03

<1.95E-03

<2.1OE-03

<2.15E-03

<1.95E-03 Cs-1 37/20 <2.80E-03

<1.94E-03

<2.18E-03

<2.32E-03

<2.08E-03*RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 2-2-2011 2-2-2011 2-2-2011 2-2-2011 2-2-2011 END DATE 3-2-2011 3-2-2011 3-2-2011 3-2-2011 3-2-2011 ISOTOPES/RL*

Cs-134/10

<2.97E-03

<2.33E-03

<2.46E-03

<2.93E-03

<2.04E-03 Cs-1 37/20 <3.12E-03

<2.55E-03

<2.63E-03

<2.92E-03

<2.18E-03*RL = REPORTING LEVEL TABLE 11 i AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m 3)LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 3-2-2011 3-2-2011 3-2-2011 3-2-2011 3-2-2011 END DATE 3-20-2011 3-20-2011 3-20-2011 3-20-2011 3-20-2011 ISOTOPES/RL*

Cs-134/10

<3.15E-03

<2.43E-03

<2.67E-03

<3.08E-03

<2.20E-03 Cs-137/20

<3.26E-03

<2.44E-03

<2.61 E-03 <3.21 E-03 <2.31 E-03*RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 3-30-2011 3-30-2011 3-30-2011 3-30-2011 3-30-2011 END DATE 4-27-2011 4-27-2011 4-27-2011 4-27-2011 4-27-2011 ISOTOPES/RL*

Cs-134/10

<2.86E-03

<2.50E-03

<2.60E-03

<3.037E-03

<1.87E-03 Cs-137/20 3.85E-03+

3.54E-03+

<2.87E-03

<3.06E-03

<1.97E-03 8.43E-04 7.30E-04*RL = REPORTING LEVEL TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m 3)LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 4-27-2011 4-27-2011 4-27-2011 4-27-2011 4-27-2011 END DATE 6-1-2011 6-1-2011 6-1-2011 6-1-2011 6-1-2011 ISOTOPES/RL*

Cs-1 34/10 <2.38E-03

<1.92E-03

<2.09E-03

<2.61 E-03 <1.44E-03 Cs-1 37/20 <2.48E-03 2.63E-03+

<2.1OE-03 3.07E-03+

1.74E-03+5.55E-04 7.29E-04 4.12E-04*RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 6-1-2011 6-1-2011 6-1-2011 6-1-2011 6-1-2011 END DATE 6-29-2011 6-29-2011 6-29-2011 6-29-2011 6-29-2011 ISOTOPES/RL*

Cs-134/10

<2.23E-03

<2.37E-03

<2.58E-03

<3.31 E-03 <1.80E-03 Cs-137/20 2.49E-03+

<2.47E-03

<2.71 E-03 <3.47E-03

<1.85E-03 6.15E-04*RL = REPORTING LEVEL TABLE 11 I AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m 3)LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 6-29-2011 6-29-2011 6-29-2011 6-29-2011 6-29-2011 END DATE 7-27-2011 7-27-2011 7-27-2011 7-27-2011 7-27-2011 ISOTOPES/RL*

Cs-134/10

<2.06E-03

<2.31 E-03 <2.55E-03

<3.55E-03

<1.84E-03 Cs-137/20

<2.11E-03

<2.33E-03

<2.66E-03

<3.57E-03

<1.86E-03*RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 7-27-2011 7-27-2011 7-27-2011 7-27-2011 7-27-2011 END DATE 8-31-2011 8-31-2011 8-31-2011 8-31-2011 8-31-2011 ISOTOPES/RL*

Cs-134/10

<1.66E-03

<1.95E-03

<2.08E-03

<2.97E-03

<1.47E-03 Cs-137/20

<1.81E-03

<2.08E-03

<2.23E-03

<3.22E-03

<1.60E-03 4 4- 4*RL = REPORTING LEVEL TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m 3)LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 8-31-2011 8-31-2011 8-31-2011 8-31-2011 8-31-2011 END DATE 9-28-2011 9-28-2011 9-28-2011 9-28-2011 9-28-2011 ISOTOPES/RL*

Cs-134/10

<2.21E-03

<2.48E-03

<2.70E-03

<3.54E-03

<1.96E-03 Cs-137/20

<2.29E-03

<2.68E-03

<2.39E-03 3.71 E-03+ <2.04E-03 9.87E-04*RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 9-28-2011 9-28-2011 9-28-2011 9-28-2011 9-28-2011 END DATE 11-2-2011 11-2-2011 11-2-2011 11-2-2011 11-2-2011 ISOTOPES/RL*

Cs-134/10

<1.74E-03

<2.27E-03

<2.26E-03

<2.89E-11

<1.88E-03 Cs- 137/20 <1.80E-03

<2.34E-03

<2.41 E-03 <3.OOE-11

<1.97E-03*RL = REPORTING LEVEL TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m 3)LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 11-2-2011 11-2-2011 11-2-2011 11-2-2011 11-2-2011 END DATE 11-30-2011 11-30-2011 11-30-2011 11-30-2011 11-30-2011 ISOTOPES/RL*

Cs-134/10

<2.40E-03

<2.81E-03

<3.12E-03

<3.48E-03

<3.15E-03 Cs-137/20

<2.49E-03

<2.84E-03

<3.20E-03 3.89E-03+

<3.28E-03 9.60E-04*RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 11-30-2011 11-30-2011 11-30-2011 11-30-2011 11-30-2011 END DATE 1-4-2012 1-4-2012 1-4-2012 1-4-2012 1-4-2012 ISOTOPES/RL*

Cs-134/10

<1.92E-03

<2.32E-03

<2.49E-03

<2.98E-03

<1.46E-03 Cs-137/20

<2.05E-03

<2.46E-03 3.02E-03+

<3.15E-03

<1.59E-03 6.85E-04*RL = REPORTING LEVEL TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Concentrations in pCi/Liter)

I SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 1-1.0-2011 1-10-2011 1-10-2011 2-8-2011 2-8-2011 2-8-2011 SAMPLE LOCATION:

DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 413+95 289+94 330+94 498-91 415+90 436+91 Mn-54/1000

<3.98 <4.03 <3.88 <3.95 <3.92 <4.13 Co-60/300

<4.45 <4.28 <4.41 <4.45 <4.11 <4.35 Zn-65/300

<9.24 <9.73 <8.68 <9.54 <9.58 <9.48 Cs-134/30

<4.63 <4.67 <4.49 <4.58 <4.61 <4.49 Cs-137/50

<3.66 <4.56 <4.81 <2.73 <2.49 <4.69* RL = REPORTING LEVEL TABLE 12 OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR RESULTS OF ANALYSIS (Concentrations in pCi/Liter)(Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 1 COLLECTION DATE: 3-14-2011 3-14-2011 3-14-2011 4-11 L2011 4-11-2011 4-11-2011 SAMPLE LOCATION:

DAM 8 OUTFALL VICTORY DA4M 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 123+91 226+93 144+91 268+93 268+93 289+93 Mn-54/1000

<4.1 <4.24 <3.97 <3.80 <3.69 <3.88 Co-60/300

<4.22 <4.31 <4.53 <4.31 <4.22 <4.29 Zn-65/300

<9.47 <8.99 <9.53 <9.48 <9.70 <9.51 Cs-1 34/30 <4.79 <4.71 <4.62 <4!.66 <4.60 <4.67 Cs-1 37/50 <4.63 <4.67 <4.76 <41.73 <4.56 <4.79* RL = REPORTING LEVEL TABLE 12 OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR RESULTS OF ANALYSIS (Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPF LE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 5-9-2011 5-9-2011 5-9-2011 6-1312011 6-13-2011 6-13-2011 SAMPLE LOCATION:

DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 <103 <103 <103 <96 <96 <96 Mn-54/1000

<4.06 <3.92 <4.14 <3.92 <4.08 <3.94 Co-60/300

<4.38 <4.39 <4.34 <3!.97 <4.30 <4.11 Zn-65/300

<9.66 <9.57 <9.50 <9! L66 <9.54 <9.29 Cs-134/30

<4.66 <4.75 <4.45 <4.60 <4.59 <4.48 Cs-137/50

<4.81 <4.74 <4.68 <4L88 <4.43 <4.60* RL = REPORTING LEVEL TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Concentrations in pCi/Liter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPFLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 9-12-2011 9-12-2011 9-12-2011 10-11-2011 10-11-2011 10-11-2011 SAMPLE LOCATION:

DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 288+92 247+91 206+91 311f+95 <175 <175 Mn-54/1000

<3.98 <3.95 <4.12 <4 .04 <3.99 <4.16 Co-60/300

<3.98 <4.05 <4.19 <41.15 <4.07 <4.35 Zn-65/300

<8.83 <9.04 <9.17 <91.03 <9.78 <9.49 Cs-134/30

<4.49 <4.54 <4.56 <4168 <4.61 <4.51 Cs-137/50

<4.47 <4.68 <4.75 <4175 <4.63 <4.53* RL = REPORTING LEVEL TABLE 12 OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR RESULTS OF ANALYSIS (Concentrations in pCi/Liter) i SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 7-5-2011 7-5-2011 7-5-2011 8-8-2011 8-8-2-11 8-8-2011 SAMPLE LOCATION:

DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 <96 <96 <96 <98 <98 <98 Mn-54/1 000 <3.97 <3.86 <4.03 <3.92 <3.89 <3.91 Co-60/300

<4.47 <4.18 <4.32 <4.41 <4.34 <4.06 Zn-65/300

<9.50 <9.14 <9.28 <91.50 <9.28 <9.63 Cs-1 34/30 <4.60 <4.66 <4.62 <4.58 <4.53 <4.66 Cs-137/50

<4.63 <4.62 <4.75 <4167 <4.71 <4.77* RL = REPORTING LEVEL TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Concentrations in pCi/Liter) i SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 11-8-2011 11-8-2011 11-8-2011 12-1212011 12-12-2011 12-12-2011 SAMPLE LOCATION:

DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY ISOTOPES/RL

• H-3 <101 <101 <101 489+97 575+98 465+96 Mn-54/1000

<4.17 <4.03 <3.97 <4.09 <3.88 <4.04 Co-60/300

<4.37 <4.22 <3.94 <4.21 <4.27 <4.29 Zn-65/300

<9.07 <9.26 <9.13 <9.114 <9.74 <9.63 Cs-134/30

<4.66 <4.65 <4.56 <4.70 <4.78 <4.60 Cs-137/50

<4.76 <4.78 <4.63 <4.75 <4.65 <4.62* RL = REPORTING LEVEL TABLE 13 I RESULTS OF ANALYSIS OF MISSISSIPPI RIVER SEDIMENT IN THE VICINITY OF LACBWR (Concentration in pCi/Kg)(Reporting Level = 10 times Control Value)COLLECTION DATE SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPF LE # SAMPLE # 2 SAMPLE # 3 SAMPLE LOCATION UPSTREAM DOWNSTREAM OUTFALL OUTALL DOWNSTREAM UPSTREAM 6-1-2011 6-1-2011 6-1-2011 8-10-2011 8-10-2011 8-10-2011 ISOTOPES Cs-134 <4.78 <4.16 <8.55 <5.25 <4.11 <8.71 Cs-137 5.27+1.09 115+4.94 58+3.47 4.3942.54 43.6+2.41 97.9+4.96 TABLE 14 FISH SAMPLE ACTIVITY IN THE VICINITY OF LACBWR (Concentrations in pCi/Kg)COLLECTION DATE: SAMPLE #1 SAMPLE #2 SAMPLE #1 SAMPLE #2 SAMPLE #1 SAMPLE #2 FISH SPECIES: Bass CARP CARP & BASS + CARP & BASS +SHEEPHEAD I WALLEYE SHEEPHEAD WALLEYE 3-21-2011 3-21-2011 6-1-2011 6-1-2011 8-10-2011 8-10-2011 ISOTOPES/RL*

_Mn-54/3E4

<6.93 <7.55 <7.01 <8!18 <5.58 <5.55 Co-60/1E4

<7.78 <8.59 <7.73 <8:82 <6.18 <6.36 Zn-65/2E4

<18.2 <20.2 <17.3 <21.3 <14.3 <14.7 Cs-1 34/1E3 <7.59 <6.34 <7.45 <8.182 <6.04 <5.96 Cs-137/2E3

<8.05 7.98+2.29

<7.82 <9.108 7.70+1.76

<5.19*RL =REPORTING LEVEL TABLE 14 FISH SAMPLE ACTIVITY IN THE VICINITY OF LACBWR (Concentrations in pCi/Kg)COLLECTION DATE: SAMPLE #1 SAMPLE #2 FISH SPECIES: NORTHERN CARP PIKE 10-17-2011 10-17-2011 ISOTOPES/RL*

_Mn-54/3E4

<6.45 <5.16 __Co-60/1E4

<9.18 <5.84 _Zn-65/2E4

<22.1 <12.7_Cs-134/1 E3 <9.21 <5.70 Cs-1 37/2E3 <9.67 <5.51*RL =REPORTING LEVEL