Text

Annual Radioactive Effluent Release Report - Report 35
	ML12129A384
Person / Time
Site:	Wolf Creek
Issue date:	04/30/2012
From:	Sen G; Wolf Creek
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RA 12-0040
	Download: ML12129A384 (58)
	v • d • e

W0LF CREEK ?KNUCLEAR OPERATING CORPORATION Gautam Sen Manager Regulatory Affairs April 30, 2012 RA 12-0040 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482: Wolf Creek Generating Station Annual Radioactive Effluent Release Report - Report 35 Gentlemen:

The purpose of this letter is to transmit the enclosed Wolf Creek Generating Station (WCGS)

Annual Radioactive Effluent Release Report. The report covers the period from January 1, 2011, through December 31, 2011. It is being submitted pursuant to Section 5.6.3 of the WCGS Technical Specifications. The report provides procedures AP 07B-003, Revision 7, "Offsite Dose Calculation Manual," AP 07B-004, Revision 18, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)," and AP 31A-100, Revision 8, "Solid Radwaste Process Control Program" that are included as part of the report in accordance with Section 5.5.1 of the WCGS Technical Specifications. These procedures have the changes made during the reporting period marked as required.

This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4175, or Mr. William Muilenburg, at (620) 364-8831, ext. 4511.

Sincerely, Gautam Sen GS/rlt

Enclosure:

2011 Annual Radioactive Effluent Release Report - Report 35 cc: E. E. Collins (NRC), w/e J. R. Hall (NRC), w/e N. F. O'Keefe (NRC), w/e Senior Resident Inspector (NRC), w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET

Wolf Creek Nuclear Operating Corporation Wolf Creek Generating Station Docket No: 50-482 Renewed Facility Operating License No: NPF-42 Annual Radioactive Effluent Release Report Report No. 35 Reporting Period: January 1, 2011 - December 31, 2011

2 of 57 Table of Contents Paqe Executive Summary 4 Section I Report of 2011 Radioactive Effluents: Liquid 5 2011 Liquid Effluents 7 2011 Liquid Cumulative Dose Summary -Table 1 9 2011 Liquid Cumulative Dose Summary - Table 2 10 Report of 2011 Radioactive Effluents: Airborne 11 2011 Gaseous Effluents 13 2011 Gaseous Cumulative Dose Summary - Table 1 15 2011 Gaseous Cumulative Dose Summary - Table 2 16 Section II Offsite Dose Calculation Manual Limits 17 Effluent Concentration Limits (ECLs) 17 Average Energy 18 Measurements and Approximations of Total Radioactivity (Liquid and 18 Gaseous Effluents)

Batch Releases 20 Continuous Releases 20 Doses to a Member of the Public from Activities Inside the Site Boundary 20 Additional Information 20 2011 Effluent Concentration Limits 22 2011 Solid Waste Shipments 23 Irradiated Fuel Shipments 24 Section III Meteorological Data - Hours At Each Wind Speed and Direction 25 Section IV Unplanned or Abnormal Releases 34 Offsite Dose Calculation Manual 34 Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems 34 Land Use Census 34 Radwaste Shipments 34 Inoperability of Effluent Monitoring Instrumentation 34 Storage Tanks 34 NEI Groundwater Protection Industry Initiative 35

3 of 57 Table of Contents Page Enclosures 57 Enclosure I - WCGS Procedure AP 07B-003, Revision 7, "Offsite Dose Calculation Manual" Enclosure II - WCGS Procedure AP 07B-004, Revision 18, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Enclosure III - WCGS Procedure AP 31A-1 00, Revision 8, "Solid Radwaste Process Control Program"

4 of 57 EXECUTIVE

SUMMARY

This Annual Radioactive Effluent Release Report (Report # 35) documents the quantities of liquid and gaseous effluents and solid waste released by Wolf Creek Generating Station (WCGS) from January 1, 2011 through December 31, 2011. The format and content of this report are in accordance with Regulatory Guide 1.21, Revision 1, "Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants." Sections 1,11, III, and IV of this report provide information required by NRC Regulatory Guide 1.21 and Section 7.2 of AP 07B-003, "Offsite Dose Calculation Manual" (ODCM).

Section I --- Section I contains, in detail, the quantities of radioactive liquid and gaseous effluents and cumulative dose summaries for 2011, tabulated for each quarter and for yearly totals.

Specific ODCM effluent limits and dose limits are also listed in Section I, along with the percentage of the effluent limits actually released and the percentages of the dose limit actually received. No effluent or dose limits were exceeded during 2011.

An elevated release pathway does not exist at WCGS. All airborne releases are considered to be ground level releases. The gaseous pathway dose determination is met by the WCGS ODCM methodology of assigning all gaseous pathways to a hypothetical individual residing at the highest annual X/Q and D/Q location, as specified in the ODCM. This results in a conservative estimate of dose to a member of the public, rather than determining each pathway dose for each release condition. A conservative error of thirty percent has been estimated in the effluent data.

As stated above, no ODCM dose limits were exceeded in 2011.

Section II --- Section II includes supplemental information on continuous and batch releases, calculated doses, and solid waste disposal. There were 49 gaseous batch releases in 2011 versus 42 in 2010. There were 59 liquid batch releases in 2011 versus 42 in 2010. WCGS released 0.005 curies in liquid releases during 2011 versus 0.011 curies in 2010, excluding gas and tritium. Continuous release pathways remained the same as previous years and all continuous releases were monitored.

The report contains information on the following Condition Reports (CR):

CR-42403 - ODCM surveillance was late due to monthly composites being completed after the late date.

The report contains information on Carbon-14 evaluation.

The report contains information on Nickel-63 study.

Section III --- Section III documents WCGS meteorological data for wind speed, wind direction, and atmospheric stability.

Section IV --- Section IV documents unplanned and abnormal releases, changes to radwaste treatment systems, land use census, monitoring instruments, radwaste shipments, and storage tank quantities. There were no unplanned, unmonitored releases in 2011.

Changes to the land use census are noted. No changes or events occurred with monitoring instruments, radwaste shipments, and storage units.

5 of 57 SECTION I REPORT OF 2011 RADIOACTIVE EFFLUENTS: LIQUID Unit Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 7.82E-04 1.34E-03 alpha)

2. Average Diluted Concentration During pCi/ml 5.59E-1 2 1.89E-11 Period

3. Percent of Applicable Limit (1) 1.56E-02 2.67E-02 B. Tritium

1. Total Release Ci 5.1 OE+02 9.24E+01

2. Average Diluted Concentration During piCi/ml 3.65E-06 1.31 E-06 Period

3. Percent of Applicable Limit (2) (ECL) 3.65E-01 1.31 E-01 C. Dissolved and Entrained Gases

1. Total Release Ci 2.59E-02 9.69E-05

2. Average Diluted Concentration During gCi/ml 1.85E-10 1.37E-12 Period

3. Percent of Applicable Limit (3) 9.26E-05 6.84E-07 D. Gross Alpha Radioactivity

1. Total Release Ci 0.00E+00 0.OOE+00 E. Volume of Waste Released (prior to Liters 9.88E+07 2.72E+07 dilution)

F. Volume of Dilution Water Used Liters 1.40E+11 7.07E+10 NOTES:

1) The applicable limit for the WCGS is 5 Curies per year. (Reference 10 CFR 50, Appendix I, "Guides On Design Objectives For Light-Water Cooled Nuclear Power Reactors," Paragraph A.2.) The value is derived by dividing the total release Curies by 5 Curies and then multiplying the result by 100.

2) This value is derived by the following formula:

% of Applicable Limit = (Average Diluted Concentration) (100)

(MPC or ECL, Appendix B, Table 2,1 OCFR20)

3) This value is derived by the following formula:

%of Applicable Limit = (Average Diluted Concentration) (100)

(2E - 04 from ODCM Section 2.1)

6 of 57 REPORT OF 2011 RADIOW*,CTIVE EFFLUENTS: LIQUID Unit Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 2.OOE-03 4.21 E-04 alpha)

2. Average Diluted Concentration During pICi/ml 7.17E-12 1.74E-12 Period

3. Percent of Applicable Limit (1) % 3.99E-02 8.42E-03 B. Tritium

1. Total Release Ci 3.66E+01 4.97E+01

2. Average Diluted Concentration During p.Ci/ml 1.31 E-07 2.06E-07 Period

3. Percent of Applicable Limit (2) (ECL) 1.31 E-02 2.06E-02 C. Dissolved and Entrained Gases

1. Total Release Ci 2.86E-04 4.32E-06

2. Average Diluted Concentration During 1ICi/ml 1.03E-12 1.79E-14 Period

3. Percent of Applicable Limit (3) 5.14E-07 8.93E-09 D. Gross Alpha Radioactivity

1. Total Release Ci 0.00E+00 0.OOE+00 E. Volume of Waste Released (prior to liters 1.14E+08 1.66E+08 dilution)

F. Volume of Dilution Water Used liters 2.78E+1 1 2.41 E+1 1 NOTES:

1) The applicable limit for the WCGS is 5 Curies per year. (Reference 10 CFR 50, Appendix I, "Guides On Design Objectives For Light-Water Cooled Nuclear Power Reactors," Paragraph A.2.) The value is derived by dividing the total release Curies by 5 Curies and then multiplying the result by 100.

2) This value is derived by the following formula:

%of Applicable Limit = (Average Diluted Concentration) (100)

(MPC or ECL, Appendix B, Table 2, 10CFR20)

3) This value is derived by the following formula:

% of Applicable Limit = (Average Diluted Concentration) (100)

(2E - 04 from ODCM Section 2. 1)

7 of 57 2011 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Released H-3 Ci 1.28E+00 9.09E-01 5.08E+02 9.15E+01 Cr-51 Ci N/A N/A N/A N/A Mn-54 Ci <4.89E-02 <1.30E-02 1.35E-06 9.28E-07 Fe-55 Ci <9.78E-02 <2.60E-02 <1.10E-03 <1.17E-03 Fe-59 Ci <4.89E-02 <1.30E-02 <5.49E-04 <5.83E-04 Co-57 Ci N/A N/A N/A N/A Co-58 Ci 6.13E-05 <1.30E-02 1.73E-05 8.33E-04 Co-60 Ci <4.89E-02 <1.30E-02 4.02E-05 5.01E-05 Zn-65 Ci <4.89E-02 <1.30E-02 <5.49E-04 <5.83E-04 Sr-89 Ci <4.89E-03 <1.30E-03 <5.49E-05 <5.83E-05 Sr-90 Ci <4.89E-03 <1.30E-03 <5.49E-05 <5.83E-05 Sr-91 Ci N/A N/A N/A N/A Sr-92 Ci N/A N/A N/A N/A Mo-99 Ci <4.89E-02 <1.30E-02 <5.49E-04 <5.83E-04 Sb-1 24 Ci N/A N/A N/A N/A Sb-1 25 Ci N/A N/A 4.95E-04 1.83E-04 1-131 Ci <9.78E-02 <2.60E-02 <1.10E-03 <1.17E-03 1-133 Ci N/A N/A N/A N/A Cs-1 34 Ci <4.89E-02 <1.30E-02 <5.49E-04 <5.83E-04 Cs-1 36 Ci N/A N/A N/A N/A Cs-1 37 Ci <4.89E-02 <1.30E-02 1.71 E-05 6.30E-06 Ce-1 41 Ci <4.89E-02 <1.30E-02 <5.49E-04 <5.83E-04 Ce-144 Ci <4.89E-02 <1.30E-02 <5.49E-04 <5.83E-04 Na-24 Ci N/A N/A N/A N/A Rb-88 Ci N/A N/A 1.48E-04 N/A Nb-95 Ci N/A N/A N/A N/A Zr-95 Ci N/A N/A N/A N/A Tc-99M Ci N/A N/A N/A N/A Ag-i 1OM Ci N/A N/A 9.89E-07 Sn-117M Ci N/A N/A N/A N/A Sb-1 22 Ci N/A N/A N/A N/A Sb-1 26 Ci N/A N/A N/A N/A Te-125M Ci N/A N/A N/A 2.62E-04 1-135 Ci N/A N/A N/A N/A Gross Alpha Ci <9.78E-03 <2.60E-03 <1.10E-04 <1.17E-04 Ar-41 Ci <9.78E-01 <2.60E-01 1.47E-05 <1.17E-02 Kr-85M Ci <9.78E-01 <2.60E-01 2.87E-05 <1.17E-02 Kr-85 Ci <9.78E-01 <2.60E-01 <1.10E-02 <1.17E-02 Kr-87 Ci <9.78E-01 <2.60E-01 <1.10E-02 <1.17E-02 Kr-88 Ci <9.78E-01 <2.60E-01 1.66E-05 <1.17E-02 Xe-131M Ci <9.78E-01 <2.60E-01 <1.10E-02 <1.17E-02 Xe-133M Ci <9.78E-01 <2.60E-01 4.72E-04 <1.17E-02 Xe-1 33 Ci <9.78E-01 <2.60E-01 2.20E-02 8.90E-05 Xe-135M Ci <9.78E-01 <2.60E-01 <1.10E-02 <1.17E-02 Xe-135 Ci <9.78E-01 <2.60E-01 3.31E-03 7.88E-06 NOTE "Less than" values are calculated using the Lower Limit of Detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The "less than" values are not included in the summation for the total release values.

8 of 57 2011 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Released H-3 Ci 2.33E+00 1.36E+00 3.42E+01 4.84E+01 Cr-51 Ci N/A N/A N/A N/A Mn-54 Ci <5.70E-02 <8.26E-02 <2.04E-04 <1.01 E-04 Fe-55 Ci <1.14E-01 <1.65E-01 <4.08E-04 <2.01E-04 Fe-59 Ci <5.70E-02 <8.26E-02 <2.04E-04 <1.01 E-04 Co-57 Ci N/A N/A N/A N/A Co-58 Ci <5.70E-02 <8.26E-02 2.97E-04 4.83E-05 Co-60 Ci <5.70E-02 <8.26E-02 1.32E-05 9.35E-06 Zn-65 Ci <5.70E-02 <8.26E-02 <2.04E-04 <1.01 E-04 Rb-88 Ci N/A N/A N/A N/A Sr-89 Ci <5.70E-03 <8.26E-03 <2.04E-05 <1.01E-05 Sr-90 Ci <5.70E-03 <8.26E-03 <2.04E-05 <1.01 E-05 Mo-99 Ci <5.70E-02 <8.26E-02 <2.04E-04 <1.01 E-04 Sn-117M Ci N/A N/A N/A N/A Sb-1 24 Ci N/A N/A 3.66E-05 2.64E-06 Sb-1 25 Ci N/A N/A 1.65E-03 3.54E-04 1-131 Ci <1.14E-01 <1.65E-01 <4.08E-04 <2.01E-04 1-133 Ci N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A Cs-134 Ci <5.70E-02 <8.26E-02 <2.04E-04 <1.01 E-04 Cs-1 36 Ci N/A N/A N/A N/A Cs-1 37 Ci <5.70E-02 <8.26E-02 6.08E-07 6.96E-06 Cs-1 38 Ci N/A N/A N/A N/A Ba-1 40 Ci N/A N/A N/A N/A Ce-141 Ci <5.70E-02 <8.26E-02 <2.04E-04 <1.01 E-04 Ce-144 Ci <5.70E-02 <8.26E-02 <2.04E-04 <1.01 E-04 Sr-91 Ci N/A N/A N/A N/A Sr-92 Ci N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A N/A Zr-95 Ci N/A N/A N/A N/A Sb-1 22 Ci N/A N/A N/A N/A Sb-1 26 Ci N/A N/A N/A N/A Gross Alpha Ci <1.14E-02 <1.65E-02 <4.08E-05 <2.01E-05 Ar-41 Ci <1.14E+00 <1.65E+00 <4.08E-03 <2.01 E-03 Kr-85M Ci <1.14E+00 <1.65E+00 <4.08E-03 <2.01 E-03 Kr-85 Ci <1.14E+00 <1.65E+00 <4.08E-03 <2.01 E-03 Kr-87 Ci <1.14E+00 <1.65E+00 <4.08E-03 <2.01 E-03 Kr-88 Ci <1.14E+00 <1.65E+00 <4.08E-03 <2.01 E-03 Xe-131M Ci <1.14E+00 <1.65E+00 <4.08E-03 <2.01E-03 Xe-133M Ci <1.14E+00 <1.65E+00 <4.08E-03 <2.01 E-03 Xe-133 Ci <1.14E+00 <1.65E+00 2.54E-04 4.32E-06 Xe-135M Ci <1.14E+00 <1.65E+00 <4.08E-03 <2.01 E-03 Xe-135 Ci <1.14E+00 <1.65E+00 3.24E-05 <2.01E-03 NOTE "Less than" values are calculated using the Lower Limit of Detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The "less than" values are not included in the summation for the total release values.

9 of 57 LIQUID CUMULATIVE DOSE

SUMMARY

(2011) TABLE 1 QUARTER 1 OF 2011 (mrem) ODCM ODCM % OF LIMIT CALCULATED LIMIT(1)

DOSE TOTAL DOSE FOR BONE 9.07E-05 5.OOE+00 1.81E-03 TOTAL DOSE FOR LIVER 1.41E-01 5.OOE+00 2.82E+00 TOTAL DOSE FOR TOTAL BODY 1.41 E-01 1.50E+00 9.41 E+00 TOTAL DOSE FOR THYROID 1.41E-01 5.OOE+00 2.82E+00 TOTAL DOSE FOR KIDNEY 1.41 E-01 5.OOE+00 2.82E+00 TOTAL DOSE FOR LUNG 1.41 E-01 5.OOE+00 2.82E+00 TOTAL DOSE FOR GI-LLI 1.43E-01 5.OOE+00 2.85E+00 QUARTER 2 OF 2011 (mrem)

TOTAL DOSE FOR BONE 2.71E-05 5.OOE+00 5.42E-04 TOTAL DOSE FOR LIVER 6.82E-02 5.OOE+00 1.36E+00 TOTAL DOSE FOR TOTAL BODY 6.82E-02 1.50E+00 4.55E+00 TOTAL DOSE FOR THYROID 6.81 E-02 5.OOE+00 1.36E+00 TOTAL DOSE FOR KIDNEY 6.82E-02 5.OOE+00 1.36E+00 TOTAL DOSE FOR LUNG 6.81 E-02 5.OOE+00 1.36E+00 TOTAL DOSE FOR GI-LLI 6.83E-02 5.OOE+00 1.37E+00 QUARTER 3 OF 2011 (mrem)

TOTAL DOSE FOR BONE 4.12E-06 5.00E+00 8.25E-05 TOTAL DOSE FOR LIVER 3.86E-03 5.OOE+00 7.71E-02 TOTAL DOSE FOR TOTAL BODY 3.86E-03 1.50E+00 2.57E-01 TOTAL DOSE FOR THYROID 3.85E-03 5.OOE+00 7.71 E-02 TOTAL DOSE FOR KIDNEY 3.85E-03 5.OOE+00 7.71 E-02 TOTAL DOSE FOR LUNG 3.85E-03 5.OOE+00 7.71 E-02 TOTAL DOSE FOR GI-LLI 3.89E-03 5.OOE+00 7.77E-02 QUARTER 4 OF 2011 (mrem)

TOTAL DOSE FOR BONE 2.31 E-05 5.OOE+00 4.63E-04 TOTAL DOSE FOR LIVER 5.75E-03 5.OOE+00 1.15E-01 TOTAL DOSE FOR TOTAL BODY 5.74E-03 1.50E+00 3.83E-01 TOTAL DOSE FOR THYROID 5.72E-03 5.OOE+00 1.14E-01 TOTAL DOSE FOR KIDNEY 5.73E-03 5.OOE+00 1.15E-01 TOTAL DOSE FOR LUNG 5.72E-03 5.OOE+00 1.14E-01 TOTAL DOSE FOR GI-LLI 5.73E-03 5.OOE+00 1.15E-01 TOTALS FOR 2011 (mrem)

TOTAL DOSE FOR BONE 1.45E-04 1.OOE+01 1.45E-03 TOTAL DOSE FOR LIVER 2.19E-01 1.00E+01 2.19E+00 TOTAL DOSE FOR TOTAL BODY 2.19E-01 3.OOE+00 7.30E+00 TOTAL DOSE FOR THYROID 2.19E-01 1.OOE+01 2.19E+00 TOTAL DOSE FOR KIDNEY 2.19E-01 1.OOE+01 2.19E+00 TOTAL DOSE FOR LUNG 2.19E-01 1.00E+01 2.19E+00 TOTAL DOSE FOR GI-LLI 2.21E-01 1.OOE+01 2.21E+00

1. Based on ODCM Section 2.2, which restricts dose to the whole body to < 1.5 mRem per quarter and 3.0 mRem per year. Dose restriction of any organ is < 5.0 mRem per quarter and 10.0 mRem per year.

10 of 57 LIQUID CUMULATIVE DOSE

SUMMARY

(2011) TABLE 2 A. Fission and Activation Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Products (not including H-3, gases, alpha)

1. Total Release - (Ci) 7.82E-04 1.34E-03 2.OOE-03 4.21E-04 4.53E-03

2. Maximum Organ Dose (mRem) 1.68E-03 1.83E-04 3.37E-05 3.11E-05 1.90E-03

3. Organ Dose Limit (mRem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01

4. Percent of Limit 3.36E-02 3.66E-03 6.73E-04 6.21 E-04 1.90E-02 B. Tritium

1. Total Release - (Ci) 5.1OE+02 9.24E+01 3.66E+01 4.97E+01 6.88E+02

2. Maximum Organ Dose (mRem) 1.41E-01 6.81E-02 3.85E-03 5.72E-03 2.19E-01

3. Organ Dose Limit (mRem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01

4. Percent of Limit 2.82E+00 1.36E+00 7.71E-02 1.14E-01 2.19E+00 This table is included to show the correlation between Curies released and the associated calculated maximum organ dose. Wolf Creek ODCM methodology is used to calculate the maximum organ dose that assumes that an individual drinks the water and eats the fish from the discharge point. ODCM Section 2.2 organ dose limits are used. The less than values are not included in the summation for the total release values.

11 of 57 REPORT OF 2011 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 1 2 A. Fission and Activation Gases

1. Total Release Ci 4.89E-01 6.19E-06

2. Average Release Rate for Period ýtCi/sec 6.28E-02 7.88E-07

3. Percent of ODCM Limit (1) % 5.82E-03 4.53E-09 B. lodines

1. Total Release Ci 0.OOE+00 0.OOE+00

2. Average Release Rate for Period 0Ci/sec 0.OOE+00 O.OOE+00

3. Percent of Applicable Limit (2) % 0.OOE+00 0.OOE+00 C. Particulates

1. Particulates with Half-lives > 8 days Ci 0.OOE+00 0.OOE+00

2. Average Release Rate for Period pCi/sec 0.OOE+00 0.OOE+00

3. Percent of ODCM Limit (3) % 0.OOE+00 0.OOE+00

4. Gross Alpha Radioactivity Ci 0.OOE+00 0.OOE+00 D. Tritium

1. Total Release Ci 9.92E+00 1.76E+01

2. Average Release Rate for Period fCi/sec 1.28E+00 2.24E+00

3. Percent of ODCM Limit (4) % 1.01 E-01 1.67E-01 NOTES:

1) The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

% of ODCM Limit = (Qtrly Total Beta Airdose)(100)or (Qtrly Total Gamma Airdose)(100) 10 mrad 5 mrad The largest value calculated between Gamma and Beta air dose is listed as the % of ODCM Limit.

2) The percent of ODCM limit for iodine is calculated using the following methodology:

- 131)(100)

% of ODCM Limit - (Total Curies of Iodine 1 Curie

3) The percent of ODCM limit for particulates is calculated using the following methodology:

% of ODCM Limit - (Highest Organ Dose Due to Particulates)(100) 7.5 mrem This type of methodology is used since the Wolf Creek ODCM ties release limits to doses ratherthan curie release rates.

4) The percent of ODCM limit for tritium is calculated using the following methodology:

- 3)(100)

% of ODCM Limit= (Highest Organ Dose Due to H 7.5 mrem

12 of 57 REPORT OF 2011 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 3 4 A. Fission and Activation Gases

1. Total Release Ci 9.03E-02 9.OOE-02

2. Average Release Rate for Period pCi/sec 1.14E-02 1.13E-02

3. Percent of ODCM Limit (1) % 1.16E-03 1.17E-03 B. lodines

1. Total Release Ci O.OOE+00 0.OOE+00

2. Average Release Rate for Period ptCi/sec O.OOE+00 O.OOE+00

3. Percent of Applicable Limit (2) % O.OOE+00 O.OOE+00 C. Particulates

1. Particulates with Half-lives > 8 days Ci O.OOE+00 O.OOE+00

2. Average Release Rate for Period gCi/sec O.OOE+00 O.OOE+00

3. Percent of ODCM Limit (3) % O.OOE+00 O.OOE+00

4. Gross Alpha Radioactivity Ci O.OOE+00 O.OOE+00 D. Tritium

1. Total Release Ci 1.49E+01 8.31 E+00

2. Average Release Rate for Period ptCi/sec 1.87E+00 1.04E+00

3. Percent of ODCM Limit (4) % 1.38E-01 7.28E-02 NOTES:

1) The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

%of ODCM Limit= (QtrlyTotal Beta Airdose)(100) (QtrlyTotal Gamma Airdose)(100) 10 mrad 5 mrad The largest value calculated between Gamma and Beta air dose is listed as the % of ODCM Limit.

2) The percent of ODCM limit for iodine is calculated using the following methodology:

% of ODCM Limit = (Total Curies of Iodine - 13 1)(100) 1 Curie

3) The percent of ODCM limit for particulates is calculated using the following methodology:

% of ODCM Limit (Highest Organ Dose Due to Particulates)(100) 7.5 mrem This type of methodology is used since the Wolf Creek ODCM ties release limits to doses ratherthan curie release rates.

4) The percent of ODCM limit for tritium is calculated using the following methodology:

Due to H - 3)(100)

% of ODCM Limit = (Highest Organ Dose 7.5 mrem

13 of 57 2011 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission and Activation Gases Ar-41 N/A N/A 4.47E-01 N/A Kr-85 N/A N/A 8.42E-04 N/A Kr-85M N/A N/A N/A N/A Kr-87 <9.04E+00 <9.09E+00 <2.47E-01 <1.43E-01 Kr-88 <9.90E+00 <9.95E+00 <2.70E-01 <1.57E-01 Xe-1 31M N/A N/A N/A N/A Xe-133 <4.40E+00 <4.42E+00 4.05E-02 6.19E-06 Xe-133M <1.17E+01 <1.17E+01 3.36E-04 <1.85E-01 Xe-135 <1.70E+00 <1.71 E+00 2.OOE-05 <2.70E-02 Xe-135M N/A N/A N/A N/A Xe-138 <1.61E+02 <1.62E+02 <4.40E+00 <2.55E+00 Total O.OOE+00 0.OOE+00 4.88E-01 6.19E-06

2. Halogens (Gaseous) 1-131 <2.59E-04 <2.60E-04 <7.06E-06 <4.09E-06 1-133 <2.59E-02 <2.60E-02 <7.06E-04 <4.09E-04 Total O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

3. Particulates and Tritium H-3 7.03E+00 1.67E+01 2.89E+00 9.48E-01 Mn-54 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Fe-59 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Co-58 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Co-60 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Zn-65 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Mo-99 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Cs-134 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Cs-137 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Ce-141 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Ce- 144 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Sr-89 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Sr-90 <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Gross Alpha <2.59E-03 <2.60E-03 <7.06E-05 <4.09E-05 Total 7.03E+00 1.67E+01 2.89E+00 9.48E-01 NOTE "Less than" values for Noble Gases are calculated using the Lower Limit of Detection (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates, the ODCM LLD values are used.

14 of 57 2011 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission and Activation Gases Ar-41 Ci N/A N/A 8.93E-02 9.OOE-02 Kr-85 Ci N/A N/A 1.45E-04 N/A Kr-85M Ci N/A N/A N/A N/A Kr-87 Ci <9.08E+00 <9.11 E+00 <3.73E-03 <3.24E-03 Kr-88 Ci <9.94E+00 <9.97E+00 <4.09E-03 <3.54E-03 Xe-1 31M Ci N/A N/A N/A N/A Xe-133 Ci <4.41 E+00 <4.43E+00 9.17E-04 <1.57E-03 Xe-133M Ci <1.17E+01 <1.18E+01 1.04E-05 <4.18E-03 Xe-1 35 Ci <1.71E+00 <1.72E+00 <7.04E-04 <6.1 OE-04 Xe-135M Ci N/A N/A N/A N/A Xe-138 Ci <1.62E+02 <1.62E+02 <6.65E-02 <5.77E-02 Total Ci O.OOE+00 O.OE+00 9.03E-02 9.OOE-02

2. Halogens (Gaseous) 1-131 Ci <2.60E-04 <2.60E-04 <1.07E-07 <9.25E-08 1-133 Ci <2.60E-02 <2.60E-02 <1.07E-05 <9.25E-06 Total Ci O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00

3. Particulates and Tritium H-3 Ci 1.48E+01 8.27E+00 8.27E-02 3.99E-02 Mn-54 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Fe-59 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Co-58 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Co-60 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Zn-65 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Mo-99 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Cs-134 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Cs-1 37 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Ce-141 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Ce-1 44 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Sr-89 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Sr-90 Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Gross Alpha Ci <2.60E-03 <2.60E-03 <1.07E-06 <9.25E-07 Total Ci 1.48E+01 8.27E+00 8.27E-02 3.99E-02 NOTE "Less than" values for Noble Gases are calculated using the Lower Limit of Detection (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates, the ODCM LLD values are used.

15 of 57 GASEOUS CUMULATIVE DOSE

SUMMARY

(2011) TABLE 1 QUARTER 1 OF 2011 (mRem) ODCM CALCULATED ODCM LIMIT % OF LIMIT DOSE (1)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 7.01 E-03 7.50E+00 9.35E-02 TOTAL DOSE FOR TOTAL BODY 7.01 E-03 7.50E+00 9.35E-02 TOTAL DOSE FOR THYROID 7.01 E-03 7.50E+00 9.35E-02 TOTAL DOSE FOR KIDNEY 7.01 E-03 7.50E+00 9.35E-02 TOTAL DOSE FOR LUNG 7.01 E-03 7.50E+00 9.35E-02 TOTAL DOSE FOR GI-LLI 7.01 E-03 7.50E+00 9.35E-02 QUARTER 2 OF 2011 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 1.24E-02 7.50E+00 1.66E-01 TOTAL DOSE FOR TOTAL BODY 1.24E-02 7.50E+00 1.66E-01 TOTAL DOSE FOR THYROID 1.24E-02 7.50E+00 1.66E-01 TOTAL DOSE FOR KIDNEY 1.24E-02 7.50E+00 1.66E-01 TOTAL DOSE FOR LUNG 1.24E-02 7.50E+00 1.66E-01 TOTAL DOSE FOR GI-LLI 1.24E-02 7.50E+00 1.66E-01 QUARTER 3 OF 2011 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 1.05E-02 7.50E+00 1.40E-01 TOTAL DOSE FOR TOTAL BODY 1.05E-02 7.50E+00 1.40E-01 TOTAL DOSE FOR THYROID 1.05E-02 7.50E+00 1.40E-01 TOTAL DOSE FOR KIDNEY 1.05E-02 7.50E+00 1.40E-01 TOTAL DOSE FOR LUNG 1.05E-02 7.50E+00 1.40E-01 TOTAL DOSE FOR GI-LLI 1.05E-02 7.50E+00 1.40E-01 QUARTER 4 OF 2011 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 5.87E-03 7.50E+00 7.83E-02 TOTAL DOSE FOR TOTAL BODY 5.87E-03 7.50E+00 7.83E-02 TOTAL DOSE FOR THYROID 5.87E-03 7.50E+00 7.83E-02 TOTAL DOSE FOR KIDNEY 5.87E-03 7.50E+00 7.83E-02 TOTAL DOSE FOR LUNG 5.87E-03 7.50E+00 7.83E-02 TOTAL DOSE FOR GI-LLI 5.87E-03 7.50E+00 7.83E-02 TOTALS FOR 2011 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 1.50E+01 0.OOE+00 TOTAL DOSE FOR LIVER 3.59E-02 1.50E+01 2.39E-01 TOTAL DOSE FOR TOTAL BODY 3.59E-02 1.50E+01 2.39E-01 TOTAL DOSE FOR THYROID 3.59E-02 1.50E+01 2.39E-01 TOTAL DOSE FOR KIDNEY 3.59E-02 1.50E+01 2.39E-01 TOTAL DOSE FOR LUNG 3.59E-02 1.50E+01 2.39E-01 TOTAL DOSE FOR GI-LLI 3.59E-02 1.50E+01 2.39E-01

1. Based on Wolf Creek ODCM Section 3.2.2, which restricts dose during any calendar quarter to less than or equal to 7.5 mRem to any organ and during any calendar year to less than or equal to 15 mRem to any organ.

16 of 57 GASEOUS CUMULATIVE DOSE

SUMMARY

(2011)TABLE 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A. Fission and Activation Gases

1. Total Release - (Ci) 4.88E-01 6.19E-06 9.03E-02 9.OOE-02 6.69E-01

2. Total Gamma Air dose (mRad) 2.91 E-04 1.52E-10 5.79E-05 5.84E-05 4.07E-04

3. Gamma Air dose Limit (mRad) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01

4. Percent of Gamma Air dose Limit 5.82E-03 3.05E-09 1.1 6E-03 1.1 7E-03 4.07E-03

5. Total Beta Air dose (mRad) 1.05E-04 4.53E-10 2.05E-05 2.06E-05 1.46E-04

6. Beta Air dose Limit (mRad) 1.OOE+01 1.OOE+01 1.OOE+01 1.OOE+01 2.OOE+01

7. Percent of Beta Air dose 1.05E-03 4.53E-09 2.05E-04 2.06E-04 7.32E-04 Limit (mRad)

B. Particulates

1. Total Particulates (Ci) O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00

2. Maximum Organ Dose (mRem) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

3. Organ Dose Limit (mRem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

4. Percent of Limit 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 C. Tritium

1. Total Release (Ci) 9.92E+00 1.76E+01 1.49E+01 8.31E+00 5.07E+01

2. Maximum Organ Dose (mRem) 7.56E-03 1.25E-02 1.03E-02 5.46E-03 3.59E-02

3. Organ Dose Limit (mRem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

4. Percent of Limit 1.01E-01 1.67E-01 1.38E-01 7.28E-02 2.39E-01 D. Iodine

1. Total 1-131, 1-133 (Ci) 0.OOE+00 O.OOE+00 O.OOE+0O 0.OOE+00 0.OOE+00

2. Maximum Organ Dose (mRem) O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

3. Organ Dose Limit (mRem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

4. Percent of Limit O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 This table is included to show the correlation between Curies released and the associated calculated maximum organ dose. The maximum organ dose is calculated using Wolf Creek ODCM methodology, which assumes that an individual actually resides at the release point.

ODCM Section 3.2.2 organ dose limits are used.

17 of 57 SECTION II SUPPLEMENTAL INFORMATION

1. Offsite Dose Calculation Manual Limits A. For liquid waste effluents A.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to 10 times the limit specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 microCuries/ml total activity.

A.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

B. For gaseous waste effluents B.1 The dose rate due to radioactive material released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and

b. For Iodine-1 31, Iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

B.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

B.3 The dose from Iodine-1 31, Iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

2. Effluent Concentration Limits (ECLs)

Water - covered in Section I.A.

Air - covered in Section I.B.

18 of 57

3. Average Energy Average energy of fission and activation gaseous effluents is not applicable. See ODCM Section 3.1 for the methodology used in determining the release rate limits from noble gas releases.

4. Measurements and Approximations of Total Radioactivity A. Liquid Effluents Liquid Release Sampling Method of Analysis Type of Activity Type Frequency Analysis P

1. Batch Waste Each Batch P.H.A. Principal Gamma Emitters Release Tank P

Each Batch P.H.A. 1-131

a. Waste Monitor P P.H.A. Dissolved and Entrained Tank One Batch/M Gases (Gamma Emitters)

b. Secondary Liquid P L.S. H-3 Waste Monitor Each Batch S.A.C. Gross Alpha Tanks P O.S.L. Sr-89, Sr-90

2. Continuous Daily P.H.A. Principal Gamma Emitters Releases Grab Sample P.H.A. 1-131

a. Steam Generator M Dissolved and entrained Blowdown Grab Sample P.H.A. Gases (Gamma Emitters)

b. Turbine Building Daily L.S. H-3 Sump/Waste Grab Sample Water Treatment S.A.C. Gross Alpha O.S.L. Sr-89, Sr-90

c. Lime Sludge Daily Pond Grab Sample O.S.L. Fe-55 P = prior to each batch S.A.C. = scintillation alpha counter M = monthly O.S.L. = performed by an offsite laboratory L. S. = Liquid scintillation detector P.H.A. = gamma spectrum pulse height analysis using a High Purity Germanium detector

19 of 57 B. Gaseous Waste Effluents Gaseous, Release Sampling Frequency Method of Analysis Type of Activity Type Analysis P P.H.A. Principal Gamma Waste Gas Decay Each Tank Emitters Tank Grab Sample Principal Gamma Containment Purge or P P.H.A. Emitters Vent Each Purge Grab Sample Gas Bubbler and L.S. H-3 (oxide)

Principal Gamma Unit Vent M P.H.A. Emitters Grab Sample Gas Bubbler and L.S. H-3 (oxide)

Radwaste Building M P.H.A Principal Gamma Vent Grab Sample Emitters For Unit Vent and Continuous P.H.A. 1-131 Radwaste Building Vent release types 1-133 listed above Continuous P.H.A. Principal Gamma Particulate Emitters Sample Continuous S.A.C. Gross Alpha Composite Particulate Sample Continuous O.S.L. Sr-89, Sr-90 Composite Particulate Sample P = prior to each batch S.A.C. = scintillation alpha counter M = monthly O.S.L. = performed by an offsite laboratory L.S. = Liquid scintillation detector P.H.A. = gamma spectrum pulse height analysis using a High Purity Germanium detector

20 of 57

5. Batch Releases A batch release is the discontinuous release of gaseous or liquid effluents, which takes place over a finite period of time, usually hours or days.

There were 49 gaseous batch releases during the reporting period. The longest gaseous batch release lasted 9,108 minutes, while the shortest lasted 56 minutes. The average release lasted 587 minutes with a total gaseous batch release time of 28,775 minutes.

There were 59 liquid batch releases during the reporting period. The longest liquid batch release lasted 272 minutes, while the shortest lasted 55 minutes. The average release lasted 131 minutes with a total liquid batch release time of 7,741 minutes.

6. Continuous Releases A continuous release is a release of gaseous or liquid effluent, which is essentially uninterrupted for extended periods during normal operation of the facility. Four liquid release pathways were designated as continuous releases during this reporting period:

Steam Generator Blowdown, Turbine Building Sump, Waste Water Treatment, and Lime Sludge Pond. Two gas release pathways were designated as continuous releases: Unit Vent and Radwaste Building Vent.

7. Doses to a Member of the Public from Activities Inside the Site Boundary Four activities by members of the public were considered in this evaluation: personnel making deliveries to the plant, workers at the William Allen White Building located outside of the protected area boundary, the use of the access road south of the Radwaste Building, and public use of the cooling lake during times when fishing was allowed. The dose calculated for the maximum exposed individual for these four activities was as follows:

Plant Deliveries 3.86E-01 mRem William Allen White Building Workers 8.36E-03 mRem Access Road Users 3.96E-03 mRem Lake Use 4.96E-02 mRem The plant delivery calculations were based on deliveries 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months per week for 50 weeks per year. The William Allen White Building occupancy was based on normal working hours of 2000 per year. The usage factor for the access road south of the Radwaste Building was 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months per year. The dose to fishermen on the lake was based upon 3,504 hours0.00583 days 0.14 hours 8.333333e-4 weeks 1.91772e-4 months (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months a day for 292 days, based on the number of days that the lake was open to fisherman). Pathways used in the calculation were gaseous inhalation, submersion, and ground plane. All calculations were performed in accordance with the methodology and parameters in the ODCM.

8. Additional Information CR- 42403 - The July monthly liquid effluent composites were completed after the late date of August 7, 2011. Composites are due the 1st of each month, with a 25% grace period. All the necessary samples were available to make the composites, but there were no qualified technicians on site to perform the required calculations and preparations once it was recognized that composites were not done. Composites were completed satisfactorily on the next working day that qualified technicians were available, which was

21 of 57 August 8, 2011. This resulted in an Offsite Dose Calculation Manual surveillance being completed late. New surveillances were created and included in the site surveillance program to try to alleviate further instances of this happening.

Carbon-14 (CR 36059)

Regulation 10CFR50.36a requires nuclear power plants to report quantities of principal radionuclides in the annual radioactive effluent release report. In the early 1980s, the NRC decided that C-14 radionuclide would not be required to be reported because it would not make a significant contribution to dose. Since this time, technology has advanced both for effluent isotopic reduction and isotope detection and estimation. It is more likely the C-14 meets the definition of a principal radionuclide in accordance with the newly published Regulatory Guide 1.21 Revision 2 (June 2009).

The NRC allows the reporting of this isotope based on estimation methods. EPRI TR 1021106 developed an estimation method based on peer-reviewed research that incorporates parameters of Wolf Creek's reactor design to estimate the gross amount of C-14 produced annually. This value is fed into additional calculations, based on Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, to provide an estimation of annual dose. Based on the 2010 theoretical calculations and assuming the maximum percentage of inorganic C-14 compounds (30%),

Wolf Creek has estimated the annual release of C-14 to be 10.7 curies and to contribute maximum dose values of 1.30 mrem/yr child bone dose and 0.259 mrem/yr child total body. This is well below the 10CFR50, Appendix I, ALARA design objective of 15 mrem/yr. Additionally, this value is on par with the dose expected from naturally occurring radiocarbon.

Nickel-63 Study Regulation 10CFR50.36a requires nuclear power plants to report quantities of principal radionuclides in the annual radioactive effluent release report. To meet this requirement, periodic monitoring of potential isotopes in the waste streams is performed and any findings evaluated. Wolf Creek is not currently required by the ODCM to monitor for Ni-63 in the liquid effluents. However, to determine if Ni-63 is present in the liquid effluents, all 4 th quarter liquid composites were analyzed for the nuclide. The Batch composite resulted in positive values of Ni-63. The remaining composites, Steam Generator Blowdown to the Lake, Waste Water Treatment, Turbine Building Sump and Lime Sludge Pond, were all none detected.

Using the Ni-63 detected in the quarterly Batch composite, the amount released for the year was conservatively estimated using the total liquid batch volume released and the total release duration for the year. Based on these estimates, Wolf Creek would release approximately 4.5E-04 mRem/year adult bone dose, which was the highest organ affected. Compared to 2.2E-01 mRem/year, which is the dose due to the highest organ for the year (adult Gi-LLI), the estimated Ni-63 bone dose is a minimal contributor. This estimation is well below the 10CFR50, Appendix I limit of 10 mRem/year to any organ.

22 of 57 2011 EFFLUENT CONCENTRATION LIMITS Nuclides Curies Average Diluted 10 CFR 20 ECL % of ECL Concentration (VCi/ml)

(ýLCi/ml)

H-3 6.88E+02 9.42E-07 1.OOE-03 9.42E-02 Na-24 N/A N/A 5.OOE-05 N/A Cr-51 N/A N/A 5.OOE-04 N/A Mn-54 2.28E-06 3.12E-15 3.OOE-05 1.04E-08 Mn-56 N/A N/A 7.OOE-05 N/A Fe-55 N/A N/A 1.OOE-04 N/A Fe-59 N/A N/A 1.OOE-05 N/A Co-57 N/A N/A 6.OOE-05 N/A Co-58 1.26E-03 1.72E-12 2.OOE-05 8.60E-06 Co-60 1.13E-04 1.55E-13 3.OOE-06 5.17E-06 Ni-65 N/A N/A 1.OOE-04 N/A Zn-65 N/A N/A 5.O0E-06 N/A Rb-88 1.48E-04 2.03E-13 4.OOE-04 5.08E-08 Sr-91 N/A N/A 2.OOE-05 N/A Sr-92 N/A N/A 4.OOE-05 N/A Nb-95 N/A N/A 3.OOE-05 N/A Zr-95 N/A N/A 2.OOE-05 N/A Nb-97 N/A N/A 3.OOE-04 N/A Tc-99M N/A N/A 1.OOE-03 N/A Ag-110M 9.89E-07 1.35E-15 6.OOE-06 2.25E-08 Sn-1 17M N/A N/A 3.OOE-05 N/A Sb-122 N/A N/A 1.OOE-05 N/A Sb-124 3.92E-05 5.37E-1 4 7.OOE-06 7.67E-07 Sb-125 2.68E-03 3.67E-12 3.OOE-05 1.22E-05 Sb-126 N/A N/A 7.OOE-06 N/A 1-131 N/A N/A 1.OOE-06 N/A 1-133 N/A N/A 7.OOE-06 N/A 1-135 N/A N/A 3.OOE-05 N/A Te-125M 2.62E-04 3.59E-13 2.OOE-05 1.80E-06 Cs-134 N/A N/A 9.OOE-07 N/A Cs-136 N/A N/A 6.OOE-06 N/A Cs-137 3.1 OE-05 4.24E-1 4 1.OOE-06 4.24E-06 Cs-138 N/A N/A 4.OOE-04 N/A Ba-139 N/A N/A 2.OOE-04 N/A Ba-1 40 N/A N/A 8.OOE-06 N/A Ce-141 N/A N/A 3.OOE-05 N/A W-187 N/A N/A 3.OOE-05 N/A Ar-41 1.47E-05 2.01E-14 2.OOE-04 1.OOE-08 Kr-85 N/A N/A 2.OOE-04 N/A Kr-85M 2.87E-05 3.93E-1 4 2.OOE-04 1.96E-08 Kr-88 1.66E-05 2.27E-1 4 2.OOE-04 1.14E-08 Xe-1 31M N/A N/A 2.OOE-04 N/A Xe-133M 4.72E-04 6.46E- 13 2.OOE-04 3.23E-07 Xe-133 2.23E-02 3.05E-1 1 2.OOE-04 1.53E-05 Xe-135 3.35E-03 4.59E-1 2 2.OOE-04 2.30E-06 Xe-138 N/A N/A 2.OOE-04 N/A

23 of 57 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2011 SOLID WASTE SHIPMENTS A. SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste Unit 1- Year Est. Total Period Error %

a. Spent resins, filter sludges m3* 2.98E+01**

evaporator bottoms, etc. Ci 4.53E+02 2.50E+01

b. Dry compressible waste, m3* 5.69E+02**

contaminated equip. etc. Ci 2.21 E-01 2.50E+01

c. Irradiated components, m3* 0.00E+00 control rods, etc. Ci O.00E+00 2.50E+01

d. Other m3* 1.54E+00 Ci 1.16E+00 2.50E+01

m3 = cubic meters ** This is the volume sent offsite for volume reduction, prior to disposal.

2. Estimate of Major Nuclide Composition (by type of waste).

[Nuclides listed with % abundance greater than 10 %]

a. Spent resin, filter sludges, evaporator bottoms, etc.

Nuclide Percent Name Abundance Curies Fe-55 33.04 1.50E+02 Ni-63 56.48 2.56E+02

b. Dry compressible waste, contaminated equipment, etc.

Nuclide Percent Name Abundance Curies Co-58 38.00 8.26E-02 Nb-95 24.07 5.24E-02 Zr-95 17.21 3.74E-02

c. Irradiated components, control rods, etc. - None

d. Other - Polyvinyl alcohol garments (Orex)

Sealed Sources (Department of Energy Source Recovery Project (OSRP))

Nuclide Percent Name Abundance Curies Am-241 99.00 1.15E+00

24 of 57

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 Truck (Hittman Transport Services) Energy Solutions; Oak Ridge, TN (Bear Creek) 3 Truck (Hittman Transport Services) Studsvik Processing Facility, LLC; Erwin, TN 5 Truck (Hittman Transport Services) Energy Solutions; Oak Ridge, TN (Gallaher Road)

Truck (R&R Trucking) Studsvik Processing Facility, LLC; Memphis, TN 1 Toxco Materials Management; Truck (Hittman Transport Services)

Oak Ridge, TN 1

Truck (Tri-State Motor Transit) IMPACT Services; Oak Ridge, TN Truck (Eastern Technologies Inc (ETI)) ETI; Ashford, AL 1 Truck (Eastern Technologies Inc) IMPACT Services; Oak Ridge, TN 1 Truck (R&R Trucking) NSSI/Sources & Services; Houston, TX

4. Class of Solid Waste

a. Class B - Corresponding to 2a

b. Class A - Corresponding to 2b C. Not applicable

d. Waste Classification not determined for 2d

5. Type of Container

a. LSA (General Design), Type A - corresponding to 2a

b. LSA (General Design) - corresponding to 2b C. Not applicable

d. Type A - corresponding to 2d OSRP, LSA (General Design) - corresponding to 2d (Orex)

6. Solidification Agent

a. Not applicable

b. Not applicable C. Not applicable

d. Not applicable B. IRRADIATED FUEL SHIPMENTS (Disposition)

No irradiated fuel shipments occurred during the 2011 period.

25 of 57 SECTION III HOURS AT EACH WIND SPEED AND DIRECTION This section documents WCGS meteorological data for wind speed, wind direction, and atmospheric stability.

The meteorological data supplied in the following tables covers the period from January 1, 2011, through December 31, 2011, and indicates the number of hours at each wind speed and direction for each stability class. All gaseous releases at the WCGS are ground level releases.

Wolf Creek Generating Station met Regulatory Guide 1.23 requirement for data recovery, for all instruments. The 60 Meter Wind speed had 93.5% data recovery. The remaining instruments, both at 10 and 60 meters, met or exceeded a 95% meteorological data recovery for 2011.

26 of 57 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2011 STABILITY CLASS: A ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 0.50 5.00 16.00 9.25 5.00 1.25 37.00 NNE 0.25 19.75 21.00 10.75 3.25 0.50 55.50 NE 1.00 24.25 22.00 3.00 0.00 0.00 50.25 ENE 0.75 18.00 18.25 1.25 0.00 0.00 38.25 E 1.00 17.75 17.25 2.25 0.00 0.00 38.25 ESE 1.00 8.50 23.25 10.75 0.25 0.00 43.75 SE 1.25 16.00 36.25 11.25 2.00 0.00 66.75 SSE 0.75 16.25 72.00 27.75 9.25 2.75 128.75 S 0.50 10.50 70.00 87.25 44.25 6.50 219.00 SSW 0.50 6.75 34.75 40.25 7.75 2.00 92.00 SW 0.50 1.50 21.25 8.75 0.75 0.00 32.75 WSW 0.75 5.00 8.75 8.25 2.50 0.00 25.25 W 0.25 12.25 23.75 5.75 0.75 0.00 42.75 WNW 3.00 10.25 15.75 10.50 2.00 0.25 41.75 NW 0.75 10.75 21.50 26.75 7.00 1.00 67.75 NNW 0.50 6.50 17.50 23.75 11.25 2.50 62.00 TOTAL 12.75 189.00 439.25 287.50 96.00 16.75 1041.75 PERIOD OF CALM (HOURS): 9.75

27 of 57 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2011 STABILITY CLASS: B ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 0.50 3.25 10.50 9.25 3.25 0.50 27.25 NNE 0.75 11.75 8.50 2.50 0.00 0.00 23.50 NE 1.75 17.75 9.25 0.25 0.00 0.00 29.00 ENE 0.25 12.00 10.75 0.75 0.00 0.00 23.75 E 1.25 12.75 10.25 1.00 0.00 0.00 25.25 ESE 1.00 13.75 9.00 2.25 0.00 0.00 26.00 SE 1.50 12.50 11.25 4.00 0.50 0.00 29.75 SSE 1.00 12.25 13.75 5.50 3.00 0.50 36.00 S 1.75 6.25 17.00 15.50 9.75 4.75 55.00 SSW 0.25 5.50 15.50 14.50 1.00 1.50 38.25 SW 1.25 3.00 10.50 3.00 1.25 0.00 19.00 WSW 0.75 10.00 3.25 2.75 1.50 0.00 18.25 W 0.75 9.25 9.75 4.25 1.25 0.00 25.25 WNW 0.25 5.25 7.25 8.50 1.00 0.00 22.25 NW 0.75 7.50 13.00 7.25 4.25 0.25 33.00 NNW 0.00 8.50 14.75 46.00 3.00 0.75 73.00 TOTAL 13.25 151.25 174.25 127.25 29.75 8.25 504.50 PERIOD OF CALM (HOURS): 2.75

28 of 57 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2011 STABILITY CLASS: C ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 0.75 2.75 9.75 10.50 3.00 0.00 26.75 NNE 2.00 12.50 9.75 3.00 0.00 0.00 27.25 NE 1.50 13.25 11.25 0.25 0.00 0.00 26.25 ENE 2.25 7.00 11.25 0.75 0.00 0.00 21.25 E 1.75 11.00 12.25 0.50 0.00 0.00 25.50 ESE 2.50 11.00 9.50 2.75 0.00 0.00 25.75 SE 1.50 10.75 9.50 2.00 0.25 0.00 24.00 SSE 1.00 10.25 14.50 8.00 1.25 1.25 36.25 S 2.25 5.50 13.75 16.00 7.50 5.50 50.50 SSW 2.00 5.25 15.00 12.75 3.75 3.75 42.50 SW 1.75 4.00 4.00 1.00 1.50 0.00 12.25 WSW 1.00 9.00 3.25 1.25 0.25 0.25 15.00 W 0.75 7.75 6.50 1.75 0.25 0.00 17.00 WNW 2.00 4.50 6.50 3.50 1.25 0.25 18.00 NW 1.50 4.25 12.00 12.25 2.50 2.00 34.50 NNW 1.75 5.00 21.00 14.50 3.75 1.00 47.00 TOTAL 25.50 123.75 169.75 90.75 25.25 14.00 449.75 PERIOD OF CALM (HOURS): 3.75

29 of 57 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2011 STABILITY CLASS: D ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 8.50 36.00 102.75 119.00 30.25 2.75 299.25 NNE 14.00 83.00 122.50 57.00 1.75 0.25 278.50 NE 26.00 81.75 80.75 16.00 0.00 0.00 204.50 ENE 12.50 55.25 68.75 22.75 1.75 0.00 161.00 E 17.50 69.75 77.00 18.00 0.50 0.00 182.75 ESE 9.50 51.00 56.50 14.25 0.00 0.00 131.25 SE 11.25 29.75 60.00 17.75 2.25 2.50 123.50 SSE 7.25 42.75 95.50 48.75 11.50 2.00 207.75 S 6.75 29.75 81.50 99.75 59.50 34.75 312.00 SSW 4.75 31.00 76.00 48.25 16.25 11.75 188.00 SW 10.25 32.00 19.50 8.00 1.50 0.00 71.25 WSW 4.75 19.50 23.25 5.25 0.75 0.25 53.75 W 4.75 18.75 24.00 12.50 1.25 0.50 61.75 WNW 4.00 17.75 42.50 30.75 2.25 0.25 97.50 NW 2.50 22.25 73.25 60.50 13.25 12.25 184.00 NNW 6.50 30.25 87.25 117.25 43.50 5.75 290.50 TOTAL 142.25 650.50 1091.00 695.75 186.25 73.00 2847.25 PERIOD OF CALM (HOURS): 7.50

30 of 57 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2011 STABILITY CLASS: E ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 7.25 31.75 35.50 15.75 2.50 0.00 92.75 NNE 17.50 40.50 37.25 5.25 0.00 0.00 100.50 NE 18.00 46.25 15.00 5.00 0.00 0.00 84.25 ENE 5.75 54.00 28.25 1.00 0.00 0.00 89.00 E 17.00 82.75 40.75 2.00 0.00 0.00 142.50 ESE 14.00 75.00 62.00 3.50 0.50 0.00 155.00 SE 10.50 66.50 80.50 28.50 3.00 0.25 189.25 SSE 7.00 88.50 174.50 89.50 16.50 0.25 376.25 S 6.25 59.75 137.25 132.75 59.50 18.75 414.25 SSW 7.75 49.50 69.25 20.75 2.25 2.25 151.75 SW 13.00 59.75 15.50 2.50 0.50 0.00 91.25 WSW 6.25 37.50 11.50 2.00 0.00 0.00 57.25 W 3.00 35.75 30.50 4.25 0.00 0.00 73.50 WNW 4.25 34.25 32.50 4.75 0.00 0.00 75.75 NW 4.00 47.50 64.50 5.25 0.50 0.50 122.25 NNW 5.50 55.00 40.50 17.25 2.50 0.75 121.50 TOTAL 139.75 864.25 875.25 340.00 87.75 22.75 2337.00 PERIOD OF CALM (HOURS): 2.25

31 of 57 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2011 STABILITY CLASS: F ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 9.75 42.50 11.00 0.00 0.00 0.00 63.25 NNE 19.50 50.75 7.25 0.00 0.00 0.00 77.50 NE 18.25 27.50 1.00 0.00 0.00 0.00 46.75 ENE 6.25 36.50 3.75 0.00 0.00 0.00 46.50 E 8.25 68.25 3.75 0.00 0.00 0.00 80.25 ESE 9.75 64.00 4.50 0.25 0.00 0.00 78.50 SE 8.75 87.00 18.50 0.25 0.00 0.00 114.50 SSE 6.50 78.75 34.25 9.00 0.50 0.00 129.00 S 5.00 26.00 21.75 12.25 9.00 2.25 76.25 SSW 4.25 14.25 10.50 0.75 0.00 0.00 29.75 SW 7.00 30.50 0.75 0.00 0.25 0.00 38.50 WSW 9.25 16.25 2.00 0.25 0.00 0.00 27.75 W 4.75 9.25 3.00 0.00 0.00 0.00 17.00 WNW 3.50 8.00 1.00 0.00 0.00 0.00 12.50 NW 9.25 32.50 4.75 0.00 0.00 0.00 46.50 NNW 12.00 42.00 18.50 0.50 0.00 0.00 73.00 TOTAL 132.25 634.00 146.25 23.25 9.75 2.25 957.50 PERIOD OF CALM (HOURS): 1.25

32 of 57 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2011 STABILITY CLASS: G ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 11.75 24.25 3.25 0.00 0.00 0.00 39.25 NNE 25.75 46.25 3.50 0.25 0.00 0.00 75.75 NE 25.00 21.75 1.00 0.00 0.00 0.00 47.75 ENE 6.25 31.25 0.50 0.00 0.00 0.00 38.00 E 7.75 34.25 0.25 0.00 0.00 0.00 42.25 ESE 6.00 35.75 0.50 0.75 0.00 0.00 43.00 SE 4.25 41.25 1.25 0.25 0.00 0.00 47.00 SSE 3.75 24.50 3.75 1.00 0.50 0.00 33.50 S 2.50 8.50 4.00 0.25 0.00 0.00 15.25 SSW 1.75 5.50 2.50 0.00 0.00 0.00 9.75 SW 3.00 4.50 0.00 0.25 0.00 0.00 7.75 WSW 2.25 4.50 0.00 0.00 0.00 0.00 6.75 W 3.25 1.75 0.00 0.00 0.00 0.00 5.00 WNW 5.50 2.00 0.00 0.00 0.00 0.00 7.50 NW 8.00 12.75 1.75 0.00 0.00 0.00 22.50 NNW 14.50 34.25 5.50 0.00 0.00 0.00 54.25 TOTAL 119.50 333.00 27.75 2.75 0.50 0.00 495.25 PERIOD OF CALM (HOURS): 4.50

33 of 57 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2011 STABILITY CLASS: ALL ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 39.00 145.50 188.75 163.75 44.00 4.50 585.50 NNE 79.75 264.50 209.75 78.75 5.00 0.75 638.50 NE 91.50 232.50 140.25 24.50 0.00 0.00 488.75 ENE 34.00 214.00 141.50 26.50 1.75 0.00 417.75 E 54.50 296.50 161.50 23.75 0.50 0.00 536.75 ESE 43.75 259.00 165.25 34.50 0.75 0.00 503.25 SE 39.00 263.75 217.25 64.00 8.00 2.75 594.75 SSE 27.25 273.25 408.25 189.50 42.50 6.75 947.50 S 25.00 146.25 345.25 363.75 189.50 72.50 1142.25 SSW 21.25 117.75 223.50 137.25 31.00 21.25 552.00 SW 36.75 135.25 71.50 23.50 5.75 0.00 272.75 WSW 25.00 101.75 52.00 19.75 5.00 0.50 204.00 W 17.50 94.75 97.50 28.50 3.50 0.50 242.25 WNW 22.50 82.00 105.50 58.00 6.50 0.75 275.25 NW 26.75 137.50 190.75 112.00 27.50 16.00 510.50 NNW 40.75 181.50 205.00 219.25 64.00 10.75 721.25 TOTAL 624.25 2945.75 2923.50 1567.25 435.25 137.00 8633.00 Maximum Hours of PERIOD OF CALM Invalid (HOURS): 31.75 Data: 95.5

34 of 57 SECTION IV ADDITIONAL INFORMATION

1. Unplanned or Abnormal Releases No unplanned, unmonitored release occurred in 2011.

2. Offsite Dose Calculation Manual (ODCM)

The ODCM is in the form of two separate Wolf Creek Nuclear Operating Corporation (WCNOC) administrative procedures. One of these procedures, the WCNOC "Offsite Dose Calculation Manual", AP 07B-003, Revision 7, is included with this report as Enclosure I. The other procedure, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program),"

AP 071-004, Revision 18, is included with this report as Enclosure I1.

3. Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems No major modifications were made to the Solid, Liquid or Gaseous Radwaste Systems in 2011 that alter the capacity or handling of Radioactive Wastes or differ in the method of treatment.

4. Land Use Census There were 3 changes to the nearest occupied residence and 7 changes for the nearest garden producing broadleaf vegetation (per AP 07B-004, Offsite Dose Calculation Manual [Radiological Environmental Monitoring Program]).

5. Radwaste Shipments Nineteen shipments of radioactive waste occurred during this report period. Section II, Subsection 3 of this report (Solid Waste Shipments) contains specific details regarding each shipment's mode of transportation and destination.

6. Inoperability of Effluent Monitoring Instrumentation No events occurred that potentially violated ODCM Requirements Tables 2-2 and 3-2, liquid or gaseous effluent monitoring instrumentation.

7. Storage Tanks At no time during the year 2011 was there an event that led to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Requirements Manual Sections 3.10.1 or 3.10.3.

Technical Specification requirements for the program are now covered by Technical Requirements Manual Section 3.10, "Explosive Gas and Storage Tank Radioactivity Monitoring."

35 of 57

8. NEI Groundwater Protection Industry Initiative ONSITE GROUNDWATER PROTECTION PROGRAM MONITORING Objective The objective of onsite groundwater protection program monitoring is to detect potential leaks of radioactivity from systems, structures, or components to the groundwater. At the Wolf Creek Generating Station, some background tritium influences from lake water are normal and expected.

Basis The onsite groundwater protection program monitoring sample results are being reported in the Radioactive Effluent Release Report per guidance received in association with the Nuclear Energy Institute (NEI) Groundwater Protection Industry Initiative. The following information is also being reported in association with the NEI 07-07 Groundwater Protection Industry Initiative:

1. Describe any onsite licensed radioactive materials releases or spills that were voluntarily communicated to State/Local officials during the calendar year. - None

2. Describe any onsite groundwater sample results that exceeded the reporting thresholds that were voluntarily communicated to State/Local officials during the calendar year. - None Onsite Groundwater Protection Program Monitoring Description In March of 2006, Wolf Creek Generating Station (WCGS) established an onsite groundwater protection monitoring program. During 2008, thirteen monitoring wells were added to the onsite groundwater protection monitoring program. The onsite groundwater protection program monitoring is implemented via procedure Al 07-007, Onsite Groundwater Protection Program Monitoring. The onsite groundwater samples were collected by the WCGS Environmental Management group and were analyzed by Environmental, Inc., Midwest Laboratory. Onsite groundwater samples were collected quarterly and were analyzed by gamma isotopic analysis, radiochemical analysis for 1-131 and tritium analysis. The vendor lab participated in an interlaboratory comparison program. The following tables describe the sample locations, the lower limits of detection and the reporting levels for radioactivity detected.

36 of 57 Sample Location Sample Location Description AUX Dewatering Well located near the Auxiliary Building, on East Side EAST ESW-W Essential Service Water Dewatering Well, East Group, West well, located southeast of the reactor MW-01A Monitoring Well, shallow depth, located northeast of the reactor MW-01 B Monitoring Well, mid-range depth, located northeast of the reactor MW-01C Monitoring Well, deep depth, located northeast of the reactor MW-02A Monitoring Well, shallow depth, located northwest of the reactor MW-02B Monitoring Well, mid-range depth, located northwest of the reactor MW-03A Monitoring Well, shallow depth, located southwest of the reactor MW-03B Monitoring Well, mid-range depth, located southwest of the reactor MW-03C Monitoring Well, deep depth, located southwest of the reactor MW-04A Monitoring Well, shallow depth, located southwest of the reactor MW-04B Monitoring Well, mid-range depth, located southwest of the reactor MW-05A Monitoring Well, shallow depth, located south of the reactor MW-05B Monitoring Well, mid-range depth, located south of the reactor MW-05C Monitoring Well, deep depth, located south of the reactor WEST ESW-W Essential Service Water Dewatering Well, West Group, West well, located south of the reactor Onsite Groundwater Lower Limits of Detection Analysis (pCi/L) Analysis (pCi/L)

H-3 2,000 Zr-Nb-95 15 Mn-54 15 1-131 1 Co-58 15 Cs-134 15 Fe-59 30 Cs-137 18 Co-60 15 Ba-La-140 15 Zn-65 30 Reporting Levels for Radioactivity Detected in Onsite Groundwater Analysis (pCi/L) Analysis (pCi/L)

H-3 20,000 Zr-Nb-95 400 Mn-54 1,000 1-131 2 Co-58 1,000 Cs-134 30 Fe-59 400 Cs- 137 50 Co-60 300 Ba-La-140 200 Zn-65 300

37 of 57 Discussion of Results Low levels of tritium continue to be detected in the West Essential Service Water Dewatering Well and in the Dewatering Well located near the Auxiliary Building, all within areas of backfill during plant construction. This has been attributed to the Plant's reuse of tritiated lake water, and consistent with gaseous tritium deposition during normal operation. Lake water is used for plant cooling, which includes essential service water, and in the Fire Protection System. The location with the highest level of tritium detected was WEST ESW-W (2,097 +/- 154 pCi/L), which likely resulted from direct lake water inputs from an essential service water pipe leak. The leak has since been repaired. The measured tritium levels are significantly lower than the tritium levels routinely detected in surface water collected from Coffey County Lake (2011 range was 9,847 to 15,523 pCi/L). Tritium activity was not detected in any of the groundwater samples obtained from the onsite monitoring wells that were drilled in 2008, indicating no tritium infiltration to the natural geological strata.

The tritium activity was the only activity detected in the onsite groundwater samples. Lower limits of detection were met and sample analysis results were below the applicable reporting levels.

Subsurface Water Due to Industry Operating Experience, the Wolf Creek Generating Station started collecting and analyzing subsurface water during 2010. Subsurface water monitoring is a portion of the Groundwater Protection Program and is implemented via procedure Al 07-007, Onsite GroundwaterProtection ProgramMonitoring. The definitions for subsurface water include:

1. Water that is encountered below grade while excavating, trenching, or drilling outside of the Radiologically Controlled Area and within the area displayed in Figure 2 (of Al 07-007). This excludes recent rainfall build-up in open excavation trenches.

2. Water that is encountered below grade or water that needs to be removed that is outside of a building, outside of the Radiologically Controlled Area and within the area displayed in Figure 2 (of Al 07-007). Examples may include electrical vaults, piping vaults, valve pits, manholes, concrete pits, etc. Excludes removing water from powerblock sumps, sanitary sewers, spill containment berms or from within buildings.

The collection of subsurface water samples was coordinated by the WCGS Environmental Management group and the samples were analyzed by the WCGS Chemistry Laboratory. The subsurface water samples were analyzed for tritium. The following table identifies the sample dates, sample locations, and the analysis results.

38 of 57 Date Location Tritium (pCi/L) Notes 3/16/11 Essential Service Water (ESW) Vault, piping, 3,739 No Gamma West of Control Building Emitters Detected 4/30/11 Cable Pull Manhole 120, Between Turbine Less Than No Gamma Building and Shop Building, north end. Minimum Emitters Detectable Detected Activity 6/23/11 XMA01A, XMA01B, XMA01C & XMA02 <1,931 Transformer Discharge Vault 6/23/11 XMA01D Transformer Discharge Vault <1,913 6/23/11 XMR01 Transformer Discharge Vault 2,860 6/23/11 XPB03 & XPB04 Transformer Discharge Vault <1,936 6/23/11 XNB01 & XNB02 Transformer Discharge Vault <1,913 As expected, tritium activity was detected in two of the subsurface water samples. The sample from the ESW vault was also analyzed for gamma activity and gamma emitters were not detected. Again, the detected tritium activity is likely due to the Plant's reuse of tritiated lake water. Lake water is used for plant cooling, which includes essential service water, and in the Fire Protection System. The measured tritium levels from subsurface water monitoring are lower than the tritium levels routinely detected in surface water collected from Coffey County Lake (2011 range was 9,847 to 15,523 pCi/L).

Conclusion Based upon the results of the water samples that were analyzed in association with the Onsite Groundwater Protection Program, no potential leaks of radioactivity from systems, structures, or components were identified.

39 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR AUX 28-Feb-1 1 MN-54 < 2.7 AUX 28-Feb-11 CO-58 < 3.1 AUX 28-Feb-1 1 FE-59 < 3.7 AUX 28-Feb-1 1 CO-60 < 2.5 AUX 28-Feb-1 1 ZN-65 < 4.4 AUX 28-Feb-1 1 ZR-NB-95 < 2.7 AUX 28-Feb- 1 CS-134 < 2.8 AUX 28-Feb- 1l CS-137 < 3.0 AUX 28-Feb-11 BA-LA-140 < 2.1 AUX 28-Feb-1 1 H-3 679 +/- 106 AUX 28-Feb-11 1-131 (CHEM) < 0.450 AUX 21-May-11 MN-54 < 2.2 AUX 21i-May-11 CO-58 < 2.0 AUX 21-May-1l1 FE-59 < 4.8 AUX 21-May-11 CO-60 < 3.1 AUX 21-May-11 ZN-65 < 5.0 AUX 21-May-11 ZR-NB-95 < 2.5 AUX 21 -May- 1i CS-134 < 2.9 AUX 21 -May- 1i CS-137 < 3.2 AUX 21 -May- 11 BA-LA-140 < 3.1 AUX 21-May-11 H-3 1337 +/- 124 AUX 21-May-11 1-131 (CHEM) < 0.317 AUX 17-Aug-11 MN-54 < 2.8 AUX 17-Aug- 1i CO-58 < 3.3 AUX 17-Aug- 1i FE-59 < 3.4 AUX 17-Aug- 1l CO-60 < 2.3 AUX 17-Aug-11 ZN-65 < 4.0 AUX 17-Aug-11 ZR-NB-95 < 2.8 AUX 17-Aug-11 CS-134 < 3.3 AUX 17-Aug- 1 CS-137 < 2.8 AUX 17-Aug- 1i BA-LA-140 < 3.0 AUX 17-Aug-11 H-3 1999 +/- 141 AUX 17-Aug-11 1-131 (CHEM) < 0.421 AUX 9-Nov-11 MN-54 < 4.1 AUX 9-Nov-1 1 CO-58 < 4.4 AUX 9-Nov-1 1 FE-59 < 5.0 AUX 9-Nov-11 CO-60 < 4.1 AUX 9-Nov-11 ZN-65 < 3.1 AUX 9-Nov-1 1 ZR-NB-95 < 3.7 AUX 9-Nov-l 1 CS-134 < 3.7

40 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR AUX 9-Nov-1I CS-137 < 4.4 AUX 9-Nov-11 BA-LA-140 < 6.1 AUX 9-Nov-11 H-3 1915 +/- 144 AUX 9-Nov-11 1-131 (CHEM) < 0.463 EAST ESW-W 28-Feb-11 MN-54 < 2.5 EAST ESW-W 28-Feb-11 CO-58 < 1.8 EAST ESW-W 28-Feb-11 FE-59 < 7.3 EAST ESW-W 28-Feb-1 1 CO-60 < 2.9 EAST ESW-W 28-Feb-1 1 ZN-65 < 4.8 EAST ESW-W 28-Feb-1 1 ZR-NB-95 < 3.5 EAST ESW-W 28-Feb-11 CS-134 < 3.7 EAST ESW-W 28-Feb-11 CS-137 < 1.7 EAST ESW-W 28-Feb-11 BA-LA-1 40 < 3.1 EAST ESW-W 28-Feb-1 1 H-3 < 152 EAST ESW-W 28-Feb-11 1-131 (CHEM) < 0.448 EAST ESW-W 21-May-11 MN-54 < 3.2 EAST ESW-W 21-May-11 CO-58 < 3.9 EAST ESW-W 21-May-11 FE-59 < 6.1 EAST ESW-W 21-May-11 CO-60 < 2.0 EAST ESW-W 21-May-11 ZN-65 < 4.7 EAST ESW-W 21-May-11 ZR-NB-95 < 2.4 EAST ESW-W 21-May-11 CS-134 < 4.1 EAST ESW-W 21-May-11 CS-137 < 3.6 EAST ESW-W 21 -May-11 BA-LA-1 40 < 5.4 EAST ESW-W 21 -May-11 H-3 < 141 EAST ESW-W 21 -May-11 1-131 (CHEM) < 0.454 EAST ESW-W 17-Aug-11 MN-54 < 2.5 EAST ESW-W 17-Aug-11 CO-58 < 3.5 EAST ESW-W 17-Aug-11 FE-59 < 3.7 EAST ESW-W 17-Aug-11 CO-60 < 1.7 EAST ESW-W 17-Aug-11 ZN-65 < 3.7 EAST ESW-W 17-Aug-11 ZR-NB-95 < 3.7 EAST ESW-W 17-Aug-11 CS-134 < 2.6 EAST ESW-W 17-Aug-11 CS-137 < 2.4 EAST ESW-W 17-Aug-11 BA-LA-140 < 2.9 EAST ESW-W 17-Aug-1 1 H-3 < 139 EAST ESW-W 17-Aug-11 1-131 (CHEM) < 0.240 EAST ESW-W 9-Nov-1 1 MN-54 < 2.6 EAST ESW-W 9-Nov-1 1 CO-58 < 2.3 EAST ESW-W 9-Nov-1 1 FE-59 < 5.7 EAST ESW-W 9-Nov-1 1 CO-60 < 1 1.4

41 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR EAST ESW-W 9-Nov-1 1 ZN-65 < 6.2 EAST ESW-W 9-Nov-11 ZR-NB-95 < 4.1 EAST ESW-W 9-Nov-1 1 CS-134 < 3.2 EAST ESW-W 9-Nov-1 1 CS-137 < 3.2 EAST ESW-W 9-Nov-11 BA-LA-140 < 3.7 EAST ESW-W 9-Nov-11 H-3 < 147 EAST ESW-W 9-Nov-11 1-131 (CHEM) < 0.448 MW-01A 28-Feb-11 MN-54 < 5.5 MW-01A 28-Feb-11 CO-58 < 5.0 MW-01A 28-Feb-11 FE-59 < 9.5 MW-01A 28-Feb-1 1 CO-60 < 3.4 MW-01A 28-Feb-11 ZN-65 < 7.8 MW-01A 28-Feb-11 ZR-NB-95 < 4.3 MW-01A 28-Feb- 1i CS-134 < 4.7 MW-01A 28-Feb-11 CS-137 < 5.9 MW-01A 28-Feb- 1l BA-LA-140 < 6.9 MW-01A 28-Feb- 1l H-3 < 152 MW-01A 28-Feb-11 1-131 (CHEM) < 0.429 MW-01A 19-May- 1l MN-54 < 2.3 MW-01A 19-May-11 CO-58 < 1.8 MW-01A 19-May-11 FE-59 < 5.6 MW-01A 19-May-11 CO-60 < 2.3 MW-01A 19-May- 1l ZN-65 < 6.5 MW-01A 19-May-11 ZR-NB-95 < 2.8 MW-01A 19-May-11 CS-134 < 2.0 MW-01A 19-May- 1l CS-137 < 2.8 MW-01A 19-May- 1i BA-LA-140 < 3.9 MW-01A 19-May-11 H-3 < 141 MW-01A 19-May-11 1-131 (CHEM) < 0.416 MW-01A 29-Aug-11 MN-54 < 3.4 MW-01A 29-Aug-11 CO-58 < 1.7 MW-01A 29-Aug-11 FE-59 < 2.5 MW-01A 29-Aug-11 CO-60 < 1.7 MW-01A 29-Aug-11 ZN-65 < 7.2 MW-01A 29-Aug-11 ZR-NB-95 < 3.0 MW-01A 29-Aug- 1 CS-134 < 3.2 MW-01A 29-Aug- 1 CS-137 < 3.5 MW-01A 29-Aug- 1l BA-LA-140 < 2.9 MW-01A 29-Aug- 1i H-3 < 151 MW-01A 29-Aug-1i 1-131 (CHEM) < 0.265 MW-01A 9-Nov-11 MN-54 q2.1

42 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-01A 9-Nov-1 1 C0-58 < 3.3 MW-01A 9-Nov-11 FE-59 < 5.7 MW-01A 9-Nov-11 CO-60 < 2.0 MW-01A 9-Nov-1 1 ZN-65 < 5.0 MW-01A 9-Nov-11 ZR-NB-95 < 3.7 MW-01A 9-Nov- 1 CS-134 < 3.0 MW-01A 9-Nov- 1 CS-137 < 3.2 MW-01A 9-Nov-11 BA-LA-140 < 2.7 MW-01A 9-Nov-11 H-3 < 147 MW-01A 9-Nov-11 1-131 (CHEM) < 0.340 MW-01 B 28-Feb-11 MN-54 < 2.7 MW-01B 28-Feb-11 CO-58 < 1.7 MW-01B 28-Feb-11 FE-59 < 3.8 MW-01B 28-Feb-11 CO-60 < 2.8 MW-01 B 28-Feb-1 1 ZN-65 < 3.2 MW-01B 28-Feb-11 ZR-NB-95 < 2.6 MW-01 B 28-Feb-11 CS-134 < 2.6 MW-01 B 28-Feb-11 CS-137 < 2.8 MW-01B 28-Feb-11 BA-LA-140 < 2.5 MW-01B 28-Feb-11 H-3 < 161 MW-01B 28-Feb-11 1-131 (CHEM) < 0.384 MW-01B 19-May-11 MN-54 < 2.1 MW-01B 19-May-11 CO-58 < 2.2 MW-01B 19-May-11 FE-59 < 4.7 MW-01B 19-May-11 CO-60 < 1.8 MW-01B 19-May- 1i ZN-65 < 3.6 MW-01B 19-May-11 ZR-NB-95 < 2.7 MW-01B 19-May-11 CS-134 < 2.2 MW-01B 19-May-1i1 CS-137 < 2.7 MW-01B 19-May- 1i BA-LA-140 < 2.5 MW-01B 19-May-11 H-3 < 141 MW-01B 19-May-11 1-131 (CHEM) < 0.430 MW-01B 29-Aug-11 MN-54 < 2.1 MW-01 B 29-Aug-11 CO-58 < 3.0 MW-01B 29-Aug-11 FE-59 < 3.7 MW-01 B 29-Aug- 1l CO-60 < 1.5 MW-01 B 29-Aug-1 1 ZN-65 < 5.2 MW-01 B 29-Aug-1 1 ZR-NB-95 < 1.7 MW-01B 29-Aug-11 CS-134 < 2.9 MW-01B 29-Aug-11 CS-137 <1 2.5 MW-01B 29-Aug-11 BA-LA-140 II<1 2.4

43 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-01B 29-Aug-11 H-3 < 151 MW-01B 29-Aug-11 1-131 (CHEM) < 0.286 MW-01B 9-Nov- 1l MN-54 < 2.9 MW-01 B 9-Nov-1 1 CO-58 < 2.4 MW-01 B 9-Nov-1 1 FE-59 < 4.8 MW-01 B 9-Nov-1 1 CO-60 < 2.7 MW-01 B 9-Nov-1 1 ZN-65 < 5.8 MW-01B 9-Nov-11 ZR-NB-95 < 2.1 MW-01B 9-Nov-11 CS-134 < 2.8 MW-01B 9-Nov-11 CS-137 < 2.9 MW-01B 9-Nov-11 BA-LA-140 < 2.4 MW-01B 9-Nov-11 H-3 < 147 MW-01B 9-Nov-11 1-131 (CHEM) < 0.395 MW-01C 28-Feb- 1l MN-54 < 2.8 MW-01i 28-Feb-11 CO-58 < 1.9 MW-01C 28-Feb- 1l FE-59 < 3.0 MW-01C 28-Feb-11 CO-60 < 1.3 MW-01C 28-Feb- 1l ZN-65 < 2.3 MW-01C 28-Feb-11 ZR-NB-95 < 1.8 MW-01C 28-Feb- 1i CS-134 < 2.2 MW-01C 28-Feb-11 CS-137 < 2.8 MW-01C 28-Feb-11 BA-LA-140 < 2.1 MW-01C 28-Feb-11 H-3 < 161 MW-01C 28-Feb-11 1-131 (CHEM) < 0.354 MW-01C 19-May-11 MN-54 < 2.3 MW-01C 19-May- 1l CO-58 < 1.7 MW-01C 19-May- 1l FE-59 < 2.7 MW-01C 19-May- 1l CO-60 < 1.7 MW-01C 19-May- 1l ZN-65 < 3.2 MW-01C 19-May- 1l ZR-NB-95 < 2.6 MW-01C 19-May-11 CS-134 < 2.1 MW-01C 19-May- 1l CS-137 < 2.5 MW-01C 19-May- 1l BA-LA-140 < 1.4 MW-01C 19-May- 1l H-3 < 141 MW-01C 19-May-11 1-131 (CHEM) < 0.340 MW-01C 29-Aug- 1 MN-54 < 2.9 MW-01C 29-Aug-11 CO-58 < 2.1 MW-01C 29-Aug- 1i FE-59 < 2.5 MW-01C 29-Aug- 1 CO-60 < 2.7 MW-01C 29-Aug-11 ZN-65 < 3.7 MW-01C 29-Aug- 1l ZR-NB-95 < 2.5

44 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-01C 29-Aug-11 CS-134 < 3.0 MW-01C 29-Aug-11 CS-137 < 2.7 MW-01C 29-Aug- 1l BA-LA-140 < 2.6 MW-01C 29-Aug-11 H-3 < 149 MW-01C 29-Aug-11 1-131 (CHEM) < 0.253 MW-01C 9-Nov- 1l MN-54 < 2.7 MW-01C 9-Nov-11 CO-58 < 3.1 MW-01C 9-Nov- 1l FE-59 < 5.9 MW-01C 9-Nov- 1i CO-60 < 2.4 MW-01C 9-Nov- 1i ZN-65 < 2.8 MW-01C 9-Nov- 1i ZR-NB-95 < 2.6 MW-01C 9-Nov-11 CS-134 < 3.0 MW-01C 9-Nov-11 CS-137 < 4.1 MW-01C 9-Nov-11 BA-LA-140 < 2.1 MW-01C 9-Nov- 1l H-3 < 147 MW-01C 9-Nov-11 1-131 (CHEM) < 0.298 MW-02A 28-Feb-11 MN-54 < 2.5 MW-02A 28-Feb-1 1 CO-58 < 2.2 MW-02A 28-Feb-11 FE-59 < 6.1 MW-02A 28-Feb-1 1 CO-60 < 3.7 MW-02A 28-Feb-1 1 ZN-65 < 5.3 MW-02A 28-Feb-1 1 ZR-NB-95 < 3.0 MW-02A 28-Feb-11 CS-134 < 3.2 MW-02A 28-Feb-11 CS-137 < 3.1 MW-02A 28-Feb-1 1 BA-LA- 140 < 3.0 MW-02A 28-Feb-11 H-3 < 161 MW-02A 28-Feb-11 1-131 (CHEM) < 0.422 MW-02A 19-May- 1i MN-54 < 1.7 MW-02A 19-May- 1l CO-58 < 1.5 MW-02A 19-May-11 FE-59 < 4.5 MW-02A 19-May-11 CO-60 < 1.5 MW-02A 19-May-11 ZN-65 < 2.4 MW-02A 19-May-11 ZR-NB-95 < 2.9 MW-02A 19-May- 1i CS-134 < 3.2 MW-02A 19-May-11 CS-137 < 2.4 MW-02A 19-May-11 BA-LA-140 < 4.0 MW-02A 19-May- 1i H-3 < 141 MW-02A 19-May-11 1-131 (CHEM)- < 0.485 MW-02A 29-Aug-1 1 MN-54 < 3.2 MW-02A 29-Aug-i 1 CO-58 < 1.3 MW-02A 29-Aug-1 1 FE-59 < 4.9

45 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-02A 29-Aug-1 1 CO-60 < 2.9 MW-02A 29-Aug-1 1 ZN-65 < 5.2 MW-02A 29-Aug-1 1 ZR-NB-95 < 2.3 MW-02A 29-Aug- 1i CS-134 < 2.5 MW-02A 29-Aug-11 CS-137 < 3.1 MW-02A 29-Aug-i 1 BA-LA- 140 < 3.2 MW-02A 29-Aug- 1 H-3 < 151 MW-02A 29-Aug-11 1-131 (CHEM) < 0.264 MW-02A 9-Nov-1 1 MN-54 < 2.7 MW-02A 9-Nov-11 CO-58 < 2.1 MW-02A 9-Nov-1 1 FE-59 < 6.9 MW-02A 9-Nov-1 1 CO-60 < 3.5 MW-02A 9-Nov-1 1 ZN-65 < 3.7 MW-02A 9-Nov-1 1 ZR-NB-95 < 5.3 MW-02A 9-Nov-11 CS-134 < 3.0 MW-02A 9-Nov-1 1 CS-1 37 < 4.9 MW-02A 9-Nov-11 BA-LA-1 40 < 5.0 MW-02A 9-Nov-11 H-3 < 147 MW-02A 9-Nov-11 1-131 (CHEM) < 0.471 MW-02B 28-Feb-1 1 MN-54 < 5.6 MW-02B 28-Feb-1 1 CO-58 < 3.9 MW-02B 28-Feb-1 1 FE-59 < 8.7 MW-02B 28-Feb-1 1 CO-60 < 2.3 MW-02B 28-Feb-1 1 ZN-65 < 9.4 MW-02B 28-Feb-1 1 ZR-NB-95 < 2.7 MW-02B 28-Feb-11 CS-134 < 3.7 MW-02B 28-Feb-11 CS-137 < 3.8 MW-02B 28-Feb-11 BA-LA-140 < 4.5 MW-02B 28-Feb-11 H-3 < 161 MW-02B 28-Feb-11 1-131 (CHEM) < 0.464 MW-02B 19-May- 1i MN-54 2.9 MW-02B 19-May-1l1 CO-58 < 2.6 MW-02B 19-May- 1i FE-59 < 3.6 MW-02B 19-May-11 CO-60 < 1.5 MW-02B 19-May-11 ZN-65 < 2.8 MW-02B 19-May-11 ZR-NB-95 < 3.2 MW-02B 19-May- 1i CS-134 < 3.1 MW-02B 19-May- 1l CS-137 < 1.4 MW-02B 19-May-11 BA-LA-140 < 1.8 MW-02B 19-May-11 H-3 < 1 141 MW-02B 19-May-11 1-131 (CHEM) < 1 0.422

46 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-02B 29-Aug-1 1 MN-54 < 2.5 MW-02B 29-Aug-1 1 CO-58 < 1.2 MW-02B 29-Aug-1 1 FE-59 < 2.3 MW-02B 29-Aug-1 1 CO-60 < 2.4 MW-02B 29-Aug-1 1 ZN-65 < 6.4 MW-02B 29-Aug-1 1 ZR-NB-95 < 2.7 MW-02B 29-Aug-11 CS-134 < 2.1 MW-02B 29-Aug-11 CS-137 < 3.8 MW-02B 29-Aug-1i1 BA-LA-140 < 2.3 MW-02B 29-Aug- 1i H-3 < 151 MW-02B 29-Aug-11 1-131 (CHEM) < 0.233 MW-02B 9-Nov-1 1 MN-54 < 5.0 MW-02B 9-Nov-1 1 CO-58 < 2.2 MW-02B 9-Nov-1 1 FE-59 < 8.0 MW-02B 9-Nov-1 1 CO-60 < 4.6 MW-02B 9-Nov-1 1 ZN-65 < 7.4 MW-02B 9-Nov-1 1 ZR-NB-95 < 4.9 MW-02B 9-Nov- 1i CS-134 < 4.8 MW-02B 9-Nov- 1i CS-137 < 3.5 MW-02B 9-Nov-11 BA-LA-140 < 4.7 MW-02B 9-Nov-1 1 H-3 < 147 MW-02B 9-Nov-11 1-131 (CHEM) < 0.435 MW-03A 28-Feb-1 1 MN-54 < 2.7 MW-03A 28-Feb-1 1 CO-58 < 2.0 MW-03A 28-Feb-1 1 FE-59 < 4.4 MW-03A 28-Feb-1 1 CO-60 < 2.9 MW-03A 28-Feb-1 1 ZN-65 < 5.3 MW-03A 28-Feb-1 1 ZR-NB-95 < 2.4 MW-03A 28-Feb-i 1 CS-134 < 2.6 MW-03A 28-Feb- 1i CS-137 < 2.7 MW-03A 28-Feb-i 1 BA-LA- 140 < 2.8 MW-03A 28-Feb- 1l H-3 < 161 MW-03A 28-Feb-11 1-131 (CHEM) < 0.387 MW-03A 21-May-11 MN-54 < 4.0 MW-03A 21-May-11 CO-58 < 2.6 MW-03A 21-May-11 FE-59 < 3.6 MW-03A 21-May-11 CO-60 < 5.5 MW-03A 21-May-11 ZN-65 < 5.8 MW-03A 21 -May- 1l ZR-N B-95 < 4.2 MW-03A 21-May-11 CS-134 < 3.5 MW-03A 21-May-11 CS-137 < 3.9

47 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-03A 21 -May- 11 BA-LA-140 < 5.9 MW-03A 21-May-11 H-3 < 141 MW-03A 21-May-11 1-131 (CHEM) < 0.459 MW-03A 29-Aug-1 1 MN-54 < 2.7 MW-03A 29-Aug-1 1 CO-58 < 2.3 MW-03A 29-Aug-1 1 FE-59 < 3.3 MW-03A 29-Aug-1 1 CO-60 < 1.9 MW-03A 29-Aug-1 1 ZN-65 < 5.0 MW-03A 29-Aug-1 1 ZR-NB-95 < 2.9 MW-03A 29-Aug-i 1 CS-134 < 2.7 MW-03A 29-Aug-11 CS-137 < 2.5 MW-03A 29-Aug-11 BA-LA-1 40 < 3.0 MW-03A 29-Aug-i 1 H-3 < 151 MW-03A 29-Aug-11 1-131 (CHEM) < 0.262 MW-03A 9-Nov-1 1 MN-54 < 3.2 MW-03A 9-Nov-1 1 CO-58 < 3.3 MW-03A 9-Nov-1 1 FE-59 < 3.7 MW-03A 9-Nov-1 1 CO-60 < 3.3 MW-03A 9-Nov-1 1 ZN-65 < 2.9 MW-03A 9-Nov-1 1 ZR-NB-95 < 4.3 MW-03A 9-Nov- 11 CS-134 < 2.9 MW-03A 9-Nov-11 CS-137 < 3.3 MW-03A 9-Nov-11 BA-LA-140 < 1.7 MW-03A 9-Nov-1 1 H-3 < 147 MW-03A 9-Nov-11 1-131 (CHEM) < 0.419 MW-03B 28-Feb-1 1 MN-54 < 2.4 MW-03B 28-Feb-1 1 CO-58 < 2.4 MW-03B 28-Feb-11 FE-59 < 4.1 MW-03B 28-Feb-1 1 CO-60 < 2.3 MW-03B 28-Feb-1 1 ZN-65 < 2.6 MW-03B 28-Feb-1 1 ZR-NB-95 < 1.6 MW-03B 28-Feb-11 CS-134 < 2.3 MW-03B 28-Feb-11 CS-137 < 2.5 MW-03B 28-Feb-11 BA-LA-1 40 < 2.5 MW-03B 28-Feb-11 H-3 < 161 MW-03B 28-Feb-11 1-131 (CHEM) < 0.433 MW-03B 21-May-11 MN-54 < 1.8 MW-03B 21-May-11 CO-58 < 2.6 MW-03B 21-May-11 FE-59 < 5.5 MW-03B 21-May-11 CO-60 < 1.8 MW-03B 21-May-11 ZN-65 < 6.5

48 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-03B 21-May-11 ZR-NB-95 < 2.9 MW-03B 21-May-11 CS-134 < 3.0 MW-03B 21-May-11 CS-137 < 3.2 MW-03B 21 -May-11 BA-LA-140 < 2.9 MW-03B 21-May-11 H-3 < 141 MW-03B 21-May-11 1-131 (CHEM) < 0.468 MW-03B 29-Aug-1 1 MN-54 < 1.6 MW-03B 29-Aug-11 CO-58 < 2.1 MW-03B 29-Aug-1 1 FE-59 < 5.9 MW-03B 29-Aug-1 1 C0-60 < 1.6 MW-03B 29-Aug-1 1 ZN-65 < 3.3 MW-03B 29-Aug-i 1 ZR-N B-95 < 1.9 MW-03B 29-Aug- 1l CS-134 < 3.6 MW-03B 29-Aug-11 CS-137 < 3.4 MW-03B 29-Aug-11 BA-LA-140 < 1.4 MW-03B 29-Aug-1 1 H-3 < 151 MW-03B 29-Aug-11 1-131 (CHEM) < 0.245 MW-03B 9-Nov-1 1 MN-54 < 2.2 MW-03B 9-Nov-i1 00-58 < 2.9 MW-03B 9-Nov-11 FE-59 < 4.8 MW-03B 9-Nov-1 1 CO-60 < 1.2 MW-03B 9-Nov-1 1 ZN-65 < 4.0 MW-03B 9-Nov-1 1 ZR-NB-95 < 3.7 MW-03B 9-Nov-11 CS-134 < 3.0 MW-03B 9-Nov- 1i CS-137 < 3.0 MW-03B 9-Nov-11 BA-LA-140 < 2.7 MW-03B 9-Nov-11 H-3 < 147 MW-03B 9-Nov-11 1-131 (CHEM)- < 0.425 MW-03C 28-Feb-1 1 MN-54 < 3.9 MW-03C 28-Feb-1 1 CO-58 < 1.4 MW-03C 28-Feb-1 1 FE-59 < 6.6 MW-03C 28-Feb-1 1 CO-60 < 3.2 MW-03C 28-Feb-1 1 ZN-65 < 4.2 MW-03C 28-Feb-1 1 ZR-NB-95 < 3.7 MW-03C 28-Feb-1I CS-134 < 3.5 MW-03C 28-Feb-11 CS-137 < 3.6 MW-03C 28-Feb-11 BA-LA-140 < 3.3 MW-03C 28-Feb-11 H-3 < 161 MW-03C 28-Feb-11 1-131 (CHEM) < 0.422 MW-03C 21-May-11 MN-54 < 2.8 MW-03C 21-May-11 CO-58 < 2.4

49 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-03C 21-May-11 FE-59 < 3.8 MW-03C 21-May-11 CO-60 < 1.8 MW-03C 21-May- 1l ZN-65 < 3.0 MW-03C 21-May- 1l ZR-NB-95 < 2.5 MW-03C 21 -May- 11 CS-134 < 2.5 MW-03C 21 -May- 11 CS-137 < 3.4 MW-03C 21 -May-11 BA-LA- 140 < 3.8 MW-03C 21-May-11 H-3 < 141 MW-03C 21-May-11 1-131 (CHEM) < 0.410 MW-03C 29-Aug-1 1 MN-54 < 2.8 MW-03C 29-Aug-i 1 CO-58 < 1.6 MW-03C 29-Aug-1 1 FE-59 < 3.4 MW-03C 29-Aug-1 1 CO-60 < 1.5 MW-03C 29-Aug-11 ZN-65 < 4.3 MW-03C 29-Aug-11 ZR-NB-95 < 2.3 MW-03C 29-Aug-I 1 CS-134 < 3.2 MW-03C 29-Aug-11 CS-137 < 1.8 MW-03C 29-Aug-11 BA-LA-140 < 1.7 MW-03C 29-Aug-11 H-3 < 151 MW-03C 29-Aug-1l1 1-131 (CHEM) < 0.255 MW-03C 9-Nov-1 1 MN-54 < 2.5 MW-03C 9-Nov-1 1 CO-58 < 1.8 MW-03C 9-Nov-1 1 FE-59 < 4.6 MW-03C 9-Nov-1 1 CO-60 < 1.8 MW-03C 9-Nov-11 ZN-65 < 6.3 MW-03C 9-Nov-11 ZR-NB-95 < 3.1 MW-03C 9-Nov-11 CS-134 < 2.2 MW-03C 9-Nov-11 CS-137 < 3.1 MW-03C 9-Nov-11 BA-LA-140 < 2.8 MW-03C 9-Nov-11 H-3 < 147 MW-03C 9-Nov-11 1-131 (CHEM) < 0.425 MW-04A 28-Feb-1 1 MN-54 < 3.3 MW-04A 28-Feb-1 1 CO-58 < 1.6 MW-04A 28-Feb-1 1 FE-59 < 4.6 MW-04A 28-Feb-11 CO-60 < 3.1 MW-04A 28-Feb-1 1 ZN-65 < 5.9 MW-04A 28-Feb-11 ZR-NB-95 < 3.4 MW-04A 28-Feb-11 CS-134 < 3.6 MW-04A 28-Feb-11 CS-137 < 3.9 MW-04A 28-Feb-1 1 BA-LA- 140 < 1.9 MW-04A 28-Feb-11 H-3 < 1 161

50 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-04A 28-Feb-11 1-131 (CHEM) < 0.428 MW-04A 21-May-11 MN-54 < 2.3 MW-04A 21-May-11 CO-58 < 2.4 MW-04A 21-May- 1l FE-59 < 2.7 MW-04A 21-May-11 CO-60 < 1.7 MW-04A 21-May-11 ZN-65 < 4.8 MW-04A 21-May-1 1 ZR-NB-95 < 2.2 MW-04A 21-May-11 CS-134 < 2.6 MW-04A 21 -May- 11 CS-137 < 3.1 MW-04A 21 -May- 1i BA-LA-140 < 3.3 MW-04A 21 -May- 11 H-3 < 141 MW-04A 21-May-11 1-131 (CHEM) < 0.407 MW-04A 29-Aug-11 MN-54 < 5.1 MW-04A 29-Aug-1 1 CO-58 < 6.9 MW-04A 29-Aug-11 FE-59 < 12.5 MW-04A 29-Aug-11 CO-60 < 4.1 MW-04A 29-Aug-1 1 ZN-65 < 6.0 MW-04A 29-Aug-1 1 ZR-NB-95 < 3.7 MW-04A 29-Aug- 1i CS-134 < 5.9 MW-04A 29-Aug-11 CS-137 < 4.1 MW-04A 29-Aug-11 BA-LA-1 40 < 5.6 MW-04A 29-Aug-11 H-3 < 149 MW-04A 29-Aug-11 1-131 (CHEM) < 0.454 MW-04A 9-Nov-1 1 MN-54 < 2.9 MW-04A 9-Nov-1 1 CO-58 < 2.4 MW-04A 9-Nov-1 1 FE-59 < 5.4 MW-04A 9-Nov-1 1 CO-60 < 2.2 MW-04A 9-Nov-1 1 ZN-65 < 4.0 MW-04A 9-Nov-1 1 ZR-NB-95 < 2.5 MW-04A 9-Nov- 1i CS-134 < 3.3 MW-04A 9-Nov- 11 CS-137 < 3.3 MW-04A 9-Nov-11 BA-LA-140 < 1.8 MW-04A 9-Nov-11 H-3 < 147 MW-04A 9-Nov-11 1-131 (CHEM) < 0.411 MW-04B 28-Feb-1 1 MN-54 < 2.7 MW-04B 28-Feb-1 1 CO-58 < 2.8 MW-04B 28-Feb-1 1 FE-59 < 5.2 MW-04B 28-Feb-1 1 CO-60 < 1.8 MW-04B 28-Feb-1 1 ZN-65 < 5.8 MW-04B 28-Feb-11 ZR-NB-95 < 3.1

51 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-04B 28-Feb-11 CS-134 < 2.7 MW-04B 28-Feb-11 CS-137 < 3.1 MW-04B 28-Feb-11 BA-LA-1 40 < 2.1 MW-04B 28-Feb-11 H-3 < 161 MW-04B 28-Feb-11 1-131 (CHEM) < 0.423 MW-04B 21-May-11 MN-54 < 2.5 MW-04B Duplicate 21-May-11 MN-54 < 3.7 MW-04B 21-May-11 CO-58 < 3.1 MW-04B Duplicate 21-May-11 CO-58 < 3.8 MW-04B 21-May-11 FE-59 < 2.5 MW-04B Duplicate 21-May-11 FE-59 < 6.0 MW-04B 21-May-11 CO-60 < 2.6 MW-04B Duplicate 21-May- 1l CO-60 < 2.6 MW-04B 21-May-11 ZN-65 < 5.8 MW-04B Duplicate 21-May-11 ZN-65 < 5.4 MW-04B 21-May-11 ZR-NB-95 < 2.9 MW-04B Duplicate 21-May-11 ZR-NB-95 < 3.1 MW-04B 21-May-11 CS-134 < 3.7 MW-04B Duplicate 21 -May- 1l CS-134 < 3.8 MW-04B 21-May-11 CS-137 < 2.7 MW-04B Duplicate 21-May-11 CS-137 < 3.5 MW-04B 21 -May- 1i BA-LA-140 < 3.5 MW-04B Duplicate 21 -May- 1l BA-LA- 140 < 5.2 MW-04B 21 -May- 11 H-3 < 141 MW-04B Duplicate 21 -May- 11 H-3 < 141 MW-04B 21-May-11 1-131 (CHEM)- < 0.438 MW-04B Duplicate 21-May-11 1-131 (CHEM) < 0.495 MW-04B 29-Aug-1 1 MN-54 < 3.9 MW-04B 29-Aug-1 1 CO-58 < 4.6 MW-04B 29-Aug-1 1 FE-59 < 3.9 MW-04B 29-Aug-1 1 CO-60 < 2.2 MW-04B 29-Aug-1 1 ZN-65 < 4.7 MW-04B 29-Aug-1 1 ZR-NB-95 < 3.3 MW-04B 29-Aug-1 1 CS-1 34 < 4.6 MW-04B 29-Aug-1 1 CS-1 37 < 3.8 MW-04B 29-Aug-11 BA-LA-140 < 3.6 MW-04B 29-Aug-11 H-3 < 149 MW-04B 29-Aug-11 1-131 (CHEM) < 0.239 MW-04B 9-Nov-11 MN-54 < 2.1 MW-04B 9-Nov-1 1 CO-58 < 1.2 MW-04B 9-Nov-1 1 FE-59 < 4.8

52 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-04B 9-Nov-1 1 CO-60 < 2.3 MW-04B 9-Nov- 11 ZN-65 < 3.7 MW-04B 9-Nov-1 1 ZR-NB-95 < 3.2 MW-04B 9-Nov- 1l CS-134 < 2.6 MW-04B 9-Nov- 11 CS-137 < 3.5 MW-04B 9-Nov-1 1 BA-LA- 140 < 1.8 MW-04B 9-Nov-i 1 H-3 < 147 MW-04B 9-Nov-11 1-131 (CHEM) < 0.263 MW-05A 28-Feb-1 1 MN-54 < 4.0 MW-05A 28-Feb-1 1 CO-58 < 4.8 MW-05A 28-Feb-1 1 FE-59 < 7.8 MW-05A 28-Feb-1 1 CO-60 < 2.9 MW-05A 28-Feb-1 1 ZN-65 < 2.7 MW-05A 28-Feb-1 1 ZR-NB-95 < 5.6 MW-05A 28-Feb- 11 CS-134 < 4.4 MW-05A 28-Feb- 1i CS-137 < 2.7 MW-05A 28-Feb-11 BA-LA-140 < 4.9 MW-05A 28-Feb-11 H-3 < 161 MW-05A 28-Feb-11 1-131 (CHEM) < 0.435 MW-05A 21-May-11 MN-54 < 2.2 MW-05A 21-May- 11 CO-58 < 1.6 MW-05A 21-May-11 FE-59 < 4.6 MW-05A 21-May-11 CO-60 < 2.4 MW-05A 21-May-11 ZN-65 < 3.2 MW-05A 21-May-11 ZR-NB-95 < 3.4 MW-05A 21 -May- 1i CS-134 < 3.4 MW-05A 21 -May- 1l CS-137 < 3.2 MW-05A 21 -May- 11 BA-LA-1440 < 3.7 MW-05A 21 -May- 11 H-3 < 141 MW-05A 21-May-11 1-131 (CHEM) < 0.250 MW-05A 29-Aug-1 1 MN-54 -< 3.0 MW-05A 29-Aug-1 1 CO-58 < 1.6 MW-05A 29-Aug-1 1 FE-59 < 7.6 MW-05A 29-Aug-1 1 CO-60 < 3.0 MW-05A 29-Aug-1 1 ZN-65 < 2.5 MW-05A 29-Aug-1 1 ZR-NB-95 < 3.3 MW-05A 29-Aug-11 CS-134 < 3.2 MW-05A 29-Aug-11 CS-137 < 2.8 MW-05A 29-Aug-1 1 BA-LA- 140 < 1.5 MW-G5A 29-Aug- 1l H-3 < 149 MW-05A 29-Aug-11 1-131 (CHEM) < 0.223

53 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-05A 9-Nov-1 1 MN-54 < 2.2 MW-05A 9-Nov-1 1 CO-58 < 2.4 MW-05A 9-Nov-1 1 FE-59 < 2.3 MW-05A 9-Nov- 1l CO-60 < 2.1 MW-05A 9-Nov-1 1 ZN-65 < 2.1 MW-05A 9-Nov-11 ZR-NB-95 < 2.1 MW-05A 9-Nov-11 CS-134 < 3.1 MW-05A 9-Nov-11 CS-137 < 3.5 MW-05A 9-Nov-11 BA-LA-140 < 2.7 MW-05A 9-Nov- 11 H-3 < 147 MW-05A 9-Nov-11 1-131 (CHEM) < 0.380 MW-05B 28-Feb-1 1 MN-54 < 2.8 MW-05B 28-Feb-1 1 CO-58 < 1.6 MW-05B 28-Feb-1 1 FE-59 < 3.0 MW-05B 28-Feb-1 1 CO-60 < 3.5 MW-05B 28-Feb-1 1 ZN-65 < 5.9 MW-05B 28-Feb-1 1 ZR-NB-95 < 2.5 MW-05B 28-Feb-11 CS-134 < 2.7 MW-05B 28-Feb-11 CS-137 < 2.5 MW-05B 28-Feb-11 BA-LA-140 < 1.3 MW-05B 28-Feb-11 H-3 < 161 MW-05B 28-Feb-11 1-131 (CHEM) < 0.373 MW-05B 21-May-11 MN-54 < 1.8 MW-05B 21-May-11 CO-58 < 1.5 MW-05B 21-May-11 FE-59 < 1.9 MW-05B 21-May-11 CO-60 < 2.3 MW-05B 21-May-11 ZN-65 < 5.7 MW-05B 21 -May- 1l ZR-NB-95 < 3.2 MW-05B 21 -May- 1i CS-134 < 1.8 MW-05B 21-May-11 CS-137 < 3.0 MW-05B 21 -May- 11 BA-LA-140 < 2.6 MW-05B 21 -May- 11 H-3 < 141 MW-05B 21-May-11 1-131 (CHEM) < 0.379 MW-05B 29-Aug-1 1 MN-54 < 2.4 MW-05B 29-Aug-1 1 CO-58 < 2.5 MW-05B 29-Aug-i1 FE-59 <4.7 MW-05B 29-Aug-1 1 CO-60 < 2.0 MW-05B 29-Aug-1 1 ZN-65 < 3.5 MW-05B 29-Aug-1 1 ZR-NB-95 < 1.8 MW-05B 29-Aug- 1i CS-134 < 2.6 MW-05B 29-Aug-11 CS-137 < 2.5

54 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-05B 29-Aug-11 BA-LA-140 < 2.4 MW-05B 29-Aug-1 1 H-3 < 149 MW-05B 29-Aug-11 1-131 (CHEM)- < 0.244 MW-05B 9-Nov-1 1 MN-54 < 5.0 MW-05B 9-Nov-1 1 CO-58 < 1.5 MW-05B 9-Nov-1 1 FE-59 < 7.7 MW-05B 9-Nov-1 1 CO-60 < 5.0 MW-05B 9-Nov-1 1 ZN-65 < 2.4 MW-05B 9-Nov-1 1 ZR-NB-95 < 3.0 MW-05B 9-Nov- 1l CS-134 < 3.9 MW-05B 9-Nov- 11 CS-137 < 3.5 MW-05B 9-Nov-11 BA-LA-140 < 2.4 MW-05B 9-Nov-11 H-3 < 147 MW-05B 9-Nov-11 1-131 (CHEM) < 0.261 MW-05C 28-Feb-1 1 MN-54 < 1.9 MW-05C 28-Feb-1 1 CO-58 < 2.4 MW-05C 28-Feb-1 1 FE-59 < 2.9 MW-05C 28-Feb-1 1 CO-60 < 1.7 MW-05C 28-Feb-1 1 ZN-65 < 3.4 MW-05C 28-Feb-1 1 ZR-NB-95 < 3.5 MW-05C 28-Feb-11 CS-134 < 2.3 MW-05C 28-Feb- 1l CS-137 < 3.0 MW-05C 28-Feb-11 BA-LA-140 < 2.1 MW-05C 28-Feb-11 H-3 < 161 MW-05C 28-Feb-11 1-131 (CHEM) < 0.351 MW-05C 21-May-11 MN-54 < 1.7 MW-05C 21-May-11 CO-58 < 2.7 MW-05C 21-May- 1l FE-59 < 4.8 MW-05C 21-May-11 CO-60 < 1.9 MW-05C 21-May-11 ZN-65 < 3.7 MW-05C 21-May-11 ZR-NB-95 < 2.1 MW-05C 21 -May- 11 CS-134 < 2.6 MW-05C 21 -May- 11 CS-137 < 3.3 MW-05C 21 -May-11 BA-LA- 140 < 3.0 MW-05C 21 -May- 11 H-3 < 141 MW-05C 21-May-11 1-131 (CHEM) < 0.434 MW-05C 29-Aug-1 1 MN-54 < 2.3 MW-05C 29-Aug- 1l CO-58 < 2.1 MW-05C 29-Aug-1 1 FE-59 < 4.7 MW-05C 29-Aug-1 1 C0-60 < 2.2 MW-05C 29-Aug-1 1 ZN-65 < 6.3

55 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR MW-05C 29-Aug-1 1 ZR-NB-95 < 3.2 MW-05C 29-Aug- 1l CS-134 < 3.5 MW-05C 29-Aug-11 CS-137 < 3.1 MW-05C 29-Aug-11 BA-LA-1 40 < 2.8 MW-05C 29-Aug- 1i H-3 < 149 MW-05C 29-Aug-11 1-131 (CHEM) < 0.374 MW-05C 9-Nov-1 1 MN-54 < 2.2 MW-05C 9-Nov-1 1 CO-58 < 2.9 MW-05C 9-Nov- 1l FE-59 < 6.1 MW-05C 9-Nov-1 1 CO-60 < 1.4 MW-05C 9-Nov-1 1 ZN-65 < 2.3 MW-05C 9-Nov-1 1 ZR-NB-95 < 3.7 MW-05C 9-Nov-11 CS-134 < 2.6 MW-05C 9-Nov-11 CS-137 < 4.2 MW-05C 9-Nov-11 BA-LA-1 40 < 2.8 MW-05C 9-Nov-11 H-3 < 147 MW-05C 9-Nov-11 1-131 (CHEM) < 0.451 WEST ESW-W 28-Feb-1 1 MN-54 < 2.7 WEST ESW-W 28-Feb-1 1 CO-58 < 2.7 WEST ESW-W 28-Feb-1 1 FE-59 < 5.3 WEST ESW-W 28-Feb-1 1 CO-60 < 3.7 WEST ESW-W 28-Feb-1 1 ZN-65 < 4.9 WEST ESW-W 28-Feb-1 1 ZR-NB-95 < 2.2 WEST ESW-W 28-Feb-11 CS-134 < 3.6 WEST ESW-W 28-Feb-1 1 CS-1 37 < 4.2 WEST ESW-W 28-Feb-11 BA-LA-140 < 2.3 WEST ESW-W 28-Feb-1 1 H-3 2097 +/- 154 WEST ESW-W 28-Feb-11 1-131 (CHEM) < 0.402 WEST ESW-W 21-May-11 MN-54 < 2.5 WEST ESW-W 21-May-11 CO-58 < 3.1 WEST ESW-W 21-May-11 FE-59 < 4.1 WEST ESW-W 21-May-11 CO-60 < 1.5 WEST ESW-W 21-May-11 ZN-65 < 3.5 WEST ESW-W 21-May-11 ZR-NB-95 < 1.9 WEST ESW-W 21-May-11 CS-134 < 2.2 WEST ESW-W 21-May-11 CS-137 < 2.7 WEST ESW-W 21-May-11 BA-LA-140 < 1.9 WEST ESW-W 21-May-11 H-3 1298 +/- 123 WEST ESW-W 21-May-11 1-131 (CHEM) < 0.481 WEST ESW-W 17-Aug-11 MN-54 < 2.3 WEST ESW-W I 17-Aug-11 CO-58 I 1.7

56 of 57 Onsite Groundwater Results Concentration (pCi/L)

LOCATION DUPLICATE COLLECTION DATE NUCLIDE ACTIVITY SIGN ERROR WEST ESW-W 17-Aug-11 FE-59 < 5.1 WEST ESW-W 17-Aug-11 CO-60 < 1.1 WEST ESW-W 17-Aug-11 ZN-65 < 1.6 WEST ESW-W 17-Aug-11 ZR-NB-95 < 4.3 WEST ESW-W 17-Aug-11 CS-134 < 2.9 WEST ESW-W 17-Aug-11 CS-137 < 4.2 WEST ESW-W 17-Aug-11 BA-LA-140 < 3.0 WEST ESW-W 17-Aug-11 H-3 1037 +/- 113 WEST ESW-W 17-Aug-11 1-131 (CHEM) < 0.218 WEST ESW-W 9-Nov-1 1 MN-54 < 2.5 WEST ESW-W 9-Nov-1 1 CO-58 < 3.1 WEST ESW-W 9-Nov-1 1 FE-59 < 3.2 WEST ESW-W 9-Nov-1 1 CO-60 < 1.7 WEST ESW-W 9-Nov-1 1 ZN-65 < 6.2 WEST ESW-W 9-Nov-1 1 ZR-NB-95 < 2.6 WEST ESW-W 9-Nov-11 CS-134 < 2.3 WEST ESW-W 9-Nov-11 CS-137 < 2.3 WEST ESW-W 9-Nov-11 BA-LA-140 < 3.1 WEST ESW-W 9-Nov-11 H-3 1361 +/- 128 WEST ESW-W 9-Nov-11 1-131 (CHEM) < 0.469

57 of 57 ENCLOSURES TO WCGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - REPORT 35 Changes to the Wolf Creek Generating Station (WCGS) Offsite Dose Calculation Manual (ODCM) are submitted annually with the Annual Radioactive Effluent Release Report. The WCGS ODCM is divided into two administrative procedures: WCNOC procedure AP 07B-003, "Offsite Dose Calculation Manual" and WCNOC procedure AP 07B-004, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)".

Enclosure l is AP 07B-003, Revision 7, "Offsite Dose Calculation Manual" Enclosure II is AP 07B-004, Revision 18, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Enclosure III is AP 31A-100, Revision 8, "Solid Radwaste Process Control Program"

ML12129A384

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