ML081260528

From kanterella
Jump to navigation Jump to search
Annual Radioactive Effluent Release Report 31, for January-December 2007
ML081260528
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 04/29/2008
From: Flannigan R
Wolf Creek
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 08-0038
Download: ML081260528 (46)
v • d • e


Text

WLF CREEK wNUCLEAR OPERATING CORPORATION April 29, 2008 Richard D. Flannigan Manager Regulatory Affairs RA 08-0038 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 31 Gentlemen:

This letter transmits the enclosed Wolf Creek Generating Station (WCGS) Annual Radioactive Effluent Release Report. The report covers the period from January 1, 2007, through December 31, 2007. It is being submitted pursuant to Section 5.6.3 of the WCGS Technical Specifications. The report provides corrected pages from the 2006 Annual Radioactive Effluent Report - Report 30, and, Procedures AP 07B-003, "Offsite Dose Calculation Manual," AP 07B-004, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)," and AP 31A-100, "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.

No commitments are identified in this correspondence. If you have any questions concerning this matter, please contact me at (620) 364-4117, or Ms. Diane Hooper at (620) 364-4041.

Sincerely, Richard D. Flannigan RDF/rlt Enclosures cc: E. E. Collins (NRC), w/e V. G. Gaddy (NRC), we B. K. Singal (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 Facility Operating License No: NPF-42 Annual Radioactive Effluent Release Report Report No. 31 Reporting Period: January 1, 2007 - December 31, 2007

2 of 45 Table of Contents Pa-ge Executive Summary 4 Section I Report of 2007 Radioactive Effluents: Liquid 5 2007 Liquid Effluents 7 2007 Liquid Cumulative Dose Summary - Table 1 9 2007 Liquid Cumulative Dose Summary - Table 2 10 Report of 2007 Radioactive Effluents: Airborne 11 2007 Gaseous Effluents 13 2007 Gaseous Cumulative Dose Summary - Table 1 15 2007 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 2007 Effluent Concentration Limits 21 2007 Solid Waste Shipments 22 Irradiated Fuel Shipments 23 Section III Meteorological Data - Hours At Each Wind Speed and Direction 24 Section IV Unplanned or Abnormal Releases 33 Offsite Dose Calculation Manual 33 Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems 33 Land Use Census 33 Radwaste Shipments 35 Inoperability of Effluent Monitoring Instrumentation 35 Storage Tanks 35 NEI Groundwater Protection Industry Initiative 35 Corrected pages from 2006 Annual Report 41

3 of 45 Table of Contents Page Enclosures 45 Enclosure I - WCGS Procedure AP 07B-003, Revision 6, "Offsite Dose Calculation Manual" Enclosure II - WCGS Procedure AP 07B-004, Revision 13, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Enclosure III - WCGS Procedure AP 31A-1 00, Revision 6, "Solid Radwaste Process Control Program"

4 of 45 EXECUTIVE

SUMMARY

This Annual Radioactive Effluent Release Report (Report # 31) documents the quantities of liquid and gaseous effluents and solid waste released by Wolf Creek Generating Station (WCGS) from January 1, 2007 through December 31, 2007. 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, 111, 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 2007, 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 2007.

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 2007.

Section II --- Section II includes supplemental information on continuous and batch releases, calculated doses, and solid waste disposal. There were 56 gaseous batch releases in 2007 versus 68 in 2006. There were 35 liquid batch releases in 2007 versus 50 in 2006. WCGS released 0.005 curies in liquid releases during 2007 versus 0.010 curies in 2006, excluding gas and tritium. Continuous release pathways remained the same as previous years and all continuous releases were monitored.

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 2007.

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

Included in this section are corrected pages 6 through 9 of the 2006 Annual Report. There was a software problem where the gross alpha values did not update properly. Curies were listed in the 1 st, 3rd and 4th quarters. There were gross alpha curies in only the 2nd and the 4 th quarters.

5 of 45 SECTION I REPORT OF 2007 RADIOACTIVE EFFLUENTS: LIQUID Unit Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 1.45E-03 1.66E-03 alpha)
2. Average Diluted Concentration During gCi/ml 8.47E-12 6.18E-12 Period
3. Percent of Applicable Limit (1)  % 2.89E-02 3.31 E-02 B. Tritium
1. Total Release Ci 2.72E+01 8.99E+01
2. Average Diluted Concentration During pCi/mI 1.60E-07 3.36E-07 Period
3. Percent of Applicable Limit (2) (ECL)  % 1.60E-02 3.36E-02 C. Dissolved and Entrained Gases
1. Total Release Ci 1.32E-05 1.89E-05
2. Average Diluted Concentration During gCi/ml 7.71 E-14 7.05E-14 Period
3. Percent of Applicable Limit (3)  % 3.85E-08 3.53E-08 D. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 0.OOE+00 E. Volume of Waste Released (prior to Liters 8.62E+07 1.18E+08 dilution)

F. Volume of Dilution Water Used Liters 1.70E+1 1 2.68E+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)

6 of 45 REPORT OF 2007 RADIO. *.CTIVE EFFLUENTS: LIQUID Unit Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 1.16E-03 1.05E-03 alpha
2. Average Diluted Concentration During gCi/ml 4.27E-12 4.34E-1 2 Period
3. Percent of Applicable Limit (1)  % 2.31 E-02 2.1OE-02 B. Tritium
1. Total Release Ci 2.93E+02 4.13E+02
2. Average Diluted Concentration During pCi/mI 1.08E-06 1.71 E-06 Period
3. Percent of Applicable Limit (2) (ECL) 1.08E-01 1.71 E-01 C. Dissolved and Entrained Gases
1. Total Release Ci 3.98E-04 2.33E-03
2. Average Diluted Concentration During ltCi/ml 1.47E-12 9.62E-12 Period
3. Percent of Applicable Limit (3) 7.35E-07 4.81 E-06 D. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 0.00E+00 E. Volume of Waste Released (prior to liters 8.98E+07 8.18E+07 dilution)

F. Volume of Dilution Water Used liters 2.71 E+11 2.42E+11 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:

(100)

% of Applicable Limit = (Average Diluted Concentration)

(2E - 04 from ODCM Section 2.1)

7 of 45 2007 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Released H-3 Ci 1.37E+00 1.53E+00 2.59E+01 8.84E+01 Cr-51 Ci N/A N/A N/A N/A Mn-54 Ci <4.30E-02 <5.87E-02 <9.53E-05 7.59E-06 Fe-55 Ci <8.60E-02 <1.17E-01 <1.91 E-04 <4.22E-04 Fe-59 Ci <4.30E-02 <5.87E-02 <9.53E-05 <2.11 E-04 Co-57 Ci N/A N/A 2.25E-06 7.37E-06 Co-58 Ci <4.30E-02 <5.87E-02 1.15E-03 1.16E-03 Co-60 Ci <4.30E-02 <5.87E-02 3.53E-05 6.75E-05 Zn-65 Ci <4.30E-02 <5.87E-02 <9.53E-05 1.66E-06 Sr-89 Ci <4.30E-03 <5.87E-03 <9.53E-06 <2.11 E-05 Sr-90 Ci <4.30E-03 <5.87E-03 <9.53E-06 <2.11 E-05 Sr-91 Ci N/A N/A N/A N/A Mo-99 Ci <4.30E-02 <5.87E-02 <9.53E-05 <2.11 E-04 Sb-1 24 Ci N/A N/A 3.72E-06 1.89E-06 Sb-125 Ci N/A N/A 2.49E-04 3.91 E-04 1-131 Ci <8.60E-02 <1.17E-01 <1.91 E-04 <4.22E-04 1-133 Ci N/A N/A N/A N/A Cs-134 Ci <4.30E-02 <5.87E-02 <9.53E-05 <2.11 E-04 Cs-136 Ci N/A N/A N/A N/A Cs-1 37 Ci <4.30E-02 <5.87E-02 4.05E-06 2.08E-05 Ce-141 Ci <4.30E-02 <5.87E-02 <9.53E-05 <2.11 E-04 Ce-144 Ci <4.30E-02 <5.87E-02 <9.53E-05 <2.11 E-04 Na-24 Ci N/A N/A N/A N/A Rb-88 Ci N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A N/A Tc-99M Ci N/A N/A N/A N/A Sn-1 17M Ci N/A N/A 1.42E-06 N/A Sb-122 Ci N/A N/A N/A N/A Sb-126 Ci N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A Gross Alpha Ci <8.60E-03 <1.17E-02 <1.91 E-05 <4.22E-05 Ar-41 Ci <8.60E-01 <1.17E+00 <1.91 E-03 <4.22E-03 Kr-85M Ci <8.60E-01 <1.17E+00 <1.91 E-03 <4.22E-03 Kr-85 Ci <8.60E-01 <1.17E+00 <1.91 E-03 <4.22E-03 Kr-87 Ci <8.60E-01 <1.17E+00 <1.91 E-03 <4.22E-03 Kr-88 Ci <8.60E-01 <1.17E+00 <1.91E-03 <4.22E-03 Xe-131M Ci <8.60E-01 <1.17E+00 <1.91 E-03 <4.22E-03 Xe-133M Ci <8.60E-01 <1.17E+00 <1.91 E-03 <4.22E-03 Xe-133 Ci <8.60E-01 <1.17E+00 1.31 E-05 1.89E-05 Xe-135M Ci <8.60E-01 <1.17E+00 <11.91 E-03 <4.22E-03 Xe-135 Ci <8.60E-01 <1.17E+00 <11.91 E-03 <4.22E-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.

8 of 45 2007 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Released H-3 Ci 1.41 E+00 2.18E+01 2.92E+02 3.91E+02 Cr-51 Ci N/A N/A N/A N/A Mn-54 Ci <4.46E-02 <4.06E-02 1.47E-06 <2.93E-04 Fe-55 Ci <8.92E-02 <8.12E-02 <6.43E-04 <5.85E-04 Fe-59 Ci <4.46E-02 <4.06E-02 <3.21 E-04 <2.93E-04 Co-57 Ci N/A N/A 3.37E-06 3.47E-06 Co-58 Ci <4.46E-02 <4.06E-02 3.74E-04 1.98E-04 Co-60 Ci <4.46E-02 <4.06E-02 1.11E-04 9.51E-05 Zn-65 Ci <4.46E-02 <4.06E-02 <3.21 E-04 <2.93E-04 Rb-88 Ci N/A N/A N/A N/A Sr-89 Ci <4.46E-03 <4.06E-03 <3.21 E-05 <2.93E-05 Sr-90 Ci <4.46E-03 <4.06E-03 <3.21 E-05 <2.93E-05 Mo-99 Ci <4.46E-02 <4.06E-02 <3.21 E-04 <2.93E-04 Sn-1 17M Ci N/A N/A N/A <2.93E-04 Sb-124 Ci N/A N/A N/A <2.93E-04 Sb-125 Ci N/A N/A 5.96E-04 7.26E-04 1-131 Ci <8.92E-02 <8.12E-02 2.67E-05 5.93E-06 1-133 Ci N/A N/A N/A 1.34E-06 1-135 Ci N/A N/A N/A N/A Cs-134 Ci <4.46E-02 <4.06E-02 <3.21E-04 <2.93E-04 Cs-136 Ci N/A N/A <3.21 E-04 N/A Cs-137 Ci <4.46E-02 <4.06E-02 4.26E-05 1.23E-05 Ba-140 Ci N/A N/A N/A 6.62E-06 Ce-141 Ci <4.46E-02 <4.06E-02 <3.21 E-04 <2.93E-04 Ce-144 Ci <4.46E-02 <4.06E-02 <3.21 E-04 <2.93E-04 Sr-91 Ci N/A N/A N/A <2.93E-04 Nb-95 Ci N/A N/A N/A N/A W-187 Ci N/A N/A N/A N/A Gross Alpha Ci <8.92E-03 <8.12E-03 <6.43E-05 <5.85E-05 Ar-41 Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-03 Kr-85M Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-03 Kr-85 Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-03 Kr-87 Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-03 Kr-88 Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-03 Xe-131M Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-03 Xe-133M Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-03 Xe-133 Ci <8.92E-01 <8.12E-01 3.98E-04 2.33E-03 Xe-135M Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-03 Xe-135 Ci <8.92E-01 <8.12E-01 <6.43E-03 <5.85E-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 45 LIQUID CUMULATIVE DOSE

SUMMARY

(2007) TABLE 1 QUARTER 1 OF 2007 (mrem) ODCM CALCULATED ODCM LIMIT(1)  % OF LIMIT DOSE TOTAL DOSE FOR BONE 1.97E-05 5.O0E+00 3.94E-04 TOTAL DOSE FOR LIVER 8.83E-03 5.OOE+00 1.77E-01 TOTAL DOSE FOR TOTAL BODY 8.82E-03 1.50E+00 5.88E-01 TOTAL DOSE FOR THYROID 8.80E-03 5.OOE+00 1.76E-01 TOTAL DOSE FOR KIDNEY 8.81 E-03 5.OOE+00 1.76E-01 TOTAL DOSE FOR LUNG 8.80E-03 5.OOE+00 1.76E-01 TOTAL DOSE FOR GI-LLI 8.85E-03 5.00E+00 1.77E-01 QUARTER 2 OF 2007 (mrem)

TOTAL DOSE FOR BONE 7.97E-05 5.OOE+00 1.59E-03 TOTAL DOSE FOR LIVER 3.14E-02 5.OOE+00 6.27E-01 TOTAL DOSE FOR TOTAL BODY 3.13E-02 1.50E+00 2.09E+00 TOTAL DOSE FOR THYROID 3.12E-02 5.OOE+00 6.25E-01 TOTAL DOSE FOR KIDNEY 3.13E-02 5.OOE+00 6.26E-01 TOTAL DOSE FOR LUNG 3.13E-02 5.OOE+00 6.25E-01 TOTAL DOSE FOR GI-LLI 3.13E-02 5.OOE+00 6.26E-01 QUARTER 3 OF 2007 (mrem)

TOTAL DOSE FOR BONE 1.38E-04 5.OOE+00 2.76E-03 TOTAL DOSE FOR LIVER 3.19E-02 5.OOE+00 6.38E-01 TOTAL DOSE FOR TOTAL BODY 3.18E-02 1.50E+00 2.12E+00 TOTAL DOSE FOR THYROID 3.17E-02 5.OOE+00 6.35E-01 TOTAL DOSE FOR KIDNEY 3.18E-02 5.OOE+00 6.35E-01 TOTAL DOSE FOR LUNG 3.17E-02 5.OOE+00 6.34E-01 TOTAL DOSE FOR GI-LLI 3.17E-02 5.OOE+00 6.34E-01 QUARTER 4 OF 2007 (mrem)

TOTAL DOSE FOR BONE 4.37E-05 5.OOE+00 8.73E-04 TOTAL DOSE FOR LIVER 3.85E-02 5.OOE+00 7.69E-01 TOTAL DOSE FOR TOTAL BODY 3.84E-02 1.50E+00 2.56E+00 TOTAL DOSE FOR THYROID 3.84E-02 5.OOE+00 7.68E-01 TOTAL DOSE FOR KIDNEY 3.84E-02 5.OOE+00 7.68E-01 TOTAL DOSE FOR LUNG 3.84E-02 5.OOE+00 7.68E-01 TOTAL DOSE FOR GI-LLI 3.84E-02 5.OOE+00 7.68E-01 TOTALS FOR 2007 (mrem)

TOTAL DOSE FOR BONE 2.81 E-04 1.OOE+01 2.81 E-03 TOTAL DOSE FOR LIVER 1.11E-01 1.OOE+01 1.11 E+00 TOTAL DOSE FOR TOTAL BODY 1.10E-01 3.OOE+00 3.68E+00 TOTAL DOSE FOR THYROID 1.10E-01 1.OOE+01 1.10E+00 TOTAL DOSE FOR KIDNEY 1.10E-01 1.OOE+01 1.10E+00 TOTAL DOSE FOR LUNG 1.10E-01 1.OOE+01 1.10E+00 TOTAL DOSE FOR GI-LLI 1.10E-01 1.OOE+01 1.10E+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 45 LIQUID CUMULATIVE DOSE

SUMMARY

(2007) 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) 1.45E-03 1.65E-03 1.16E-03 1.05E-03 5.30E-03
2. Maximum Organ Dose (mRem) 5.54E-05 1.12E-04 1.89E-04 5.88E-05 3.88E-04
3. Organ Dose Limit (mRem) 5.O0E+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OE+01
4. Percent of Limit 1.11E-03 2.23E-03 3.78E-03 1.18E-03 3.88E-03 B. Tritium
1. Total Release - (Ci) 2.72E+01 8.99E+01 2.93E+02 4.13E+02 8.24E+02
2. Maximum Organ Dose (mRem) 8.80E-03 3.12E-02 3.17E-02 3.84E-02 1.10E-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 1.76E-01 6.25E-01 6.34E-01 7.68E-01 1.10E+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.

I I of 45 REPORT OF 2007 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 1 2 A. Fission and Activation Gases

1. Total Release Ci 2.69E-01 2.16E-01
2. Average Release Rate for Period pCi/sec 3.46E-02 2.75E-02
3. Percent of ODCM Limit (1)  % 3.35E-03 2.81 E-03 B. Iodine
1. Total Release Ci O.OOE+00 O.OOE+00
2. Average Release Rate for Period liCi/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 0Ci/sec 0.OOE+00 0.OOE+00
3. Percent of ODCM Limit (3)  % 0.OOE+00 O.OOE+00
4. Gross Alpha Radioactivity Ci 0.OOE+00 0.OOE+00 D. Tritium
1. Total Release Ci 5.02E+00 1.69E+01
2. Average Release Rate for Period pCi/sec 6.46E-01 2.15E+00
3. Percent of ODCM Limit (4)  % 5.05E-02 1.61 E-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:

% of ODCM Limit = (Total Curies of Iodine- 131)(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 ties release limits to doses rather than curie release rates.

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

H - 3)(100)

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

12 of 45 REPORT OF 2007 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 3 4 A. Fission and Activation Gases

1. Total Release Ci 1.86E-01 2.61 E-01
2. Average Release Rate for Period pCi/sec 2.34E-02 3.28E-02
3. Percent of ODCM Limit (1)  % 2.39E-03 3.04E-03 B. lodines
1. Total Iodine-131 Ci O.OOE+00 0.OOE+00
2. Average Release Rate for Period IlCi/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 0.OOE+00
2. Average Release Rate for Period pCi/sec 0.OOE+00 O.OOE+00
3. Percent of ODCM Limit (3)  % 0.OOE+00 O.OOE+00
4. Gross Alpha Radioactivity Ci 0.0OE+00 O.OOE+00 D. Tritium
1. Total Release Ci 1.51 E+01 6.11E+00
2. Average Release Rate for Period gCi/sec 1.91 E+00 7.68E-01
3. Percent of ODCM Limit (4)  % 1.40E-01 5.56E-02 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:

%of ODCM Limit = (Total Curies of Iodine -131)(100) 1Curie

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:

% of ODCM Limit = (Highest Organ Dose Due to H - 3)(100) 7.5 mrem

13 of 45 2007 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission and Activation Gases Ar-41 Ci N/A N/A 2.58E-01 2.16E-01 Kr-85 Ci N/A N/A 7.63E-03 N/A Kr-85M Ci N/A N/A 2.78E-05 N/A Kr-87 Ci <1.52E+01 <1.53E+01 5.19E-06 <1.27E-02 Kr-88 Ci <1.31E+01 <1.32E+01 3.39E-05 <1.09E-02 Xe-131M Ci N/A N/A N/A N/A Xe-133 Ci <1.11E+01 <1.12E+01 3.03E-03 <9.26E-03 Xe-1 33M Ci <2.26E+01 <2.28E+01 5.60E-05 <1.89E-02 Xe-135 Ci <3.71 E+00 <3.75E+00 6.06E-04 <3.11E-03 Xe-1 35M Ci N/A N/A N/A N/A Xe-138 Ci <5.56E+02 <5.62E+02 <5.69E-01 <4.66E-01 Total Ci O.OOE+00 O.OOE+00 2.69E-01 2.16E-01
2. Halogens (Gaseous) 1-131 Ci <2.58E-04 <2.61E-04 <2.64E-07 <2.16E-07 1-133 Ci <2.58E-02 <2.61E-02 <2.64E-05 <2.16E-05 Total Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
3. Particulates and Tritium H-3 Ci 4.88E+00 1.62E+01 1.38E-01 6.94E-01 Mn-54 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Fe-59 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Co-58 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Co-60 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Zn-65 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Mo-99 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Cs-1 34 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Cs-1 37 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Ce-141 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Ce-1 44 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Sr-89 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Sr-90 Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Gross Alpha Ci <2.58E-03 <2.61 E-03 <2.64E-06 <2.16E-06 Total Ci 4.88E+01 1.62E+01 1.38E-01 6.94E-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 45 2007 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission and Activiation Gases Ar-41 Ci N/A N/A 1.84E-01 2.28E-01 Kr-85 Ci N/A N/A 7.02E-04 7.52E-04 Kr-85M Ci N/A N/A N/A N/A Kr-87 Ci <1.54E+01 <1.54E+01 <1.09E-02 <1.16E-02 Kr-88 Ci <1.32E+01 <1.33E+01 <9.39E-03 <1.OOE-02 Xe-131M Ci N/A N/A N/A N/A Xe-133 Ci <1.12E+01 <1.12E+01 7.1OE-04 4.33E-04 Xe-1 33M Ci <2.29E+01 <2.29E+01 4.11E-06 4.49E-06 Xe-1 35 Ci <3.76E+00 3.22E-02 <2.67E-03 <2.85E-03 Xe-135M Ci N/A N/A N/A N/A Xe-1 38 Ci <5.64E+02 <5.64E+02 <4.OOE-01 <4.27E-01 Total Ci O.OOE+00 3.22E-02 1.86E-01 2.29E-01
2. Halogens (Gaseous) 1-131 Ci <2.62E-04 <2.62E-04 <1.85E-07 <1.98E-07 1-133 Ci <2.62E-02 <2.62E-02 <1.85E-05 <1.98E-05 Total Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
3. Particulates and Tritium H-3 Ci 1.42E+01 5.84E+00 9.14E-01 2.66E-01 Mn-54 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Fe-59 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Co-58 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Co-60 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Zn-65 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Mo-99 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Cs-134 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Cs-137 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Ce-141 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Ce-144 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Sr-89 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Sr-90 Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Gross Alpha Ci <2.62E-03 <2.62E-03 <1.85E-06 <1.98E-06 Total Ci 1.42E+01 5.84E+00 9.14E-01 2.66E-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.

15 of 45 GASEOUS CUMULATIVE DOSE

SUMMARY

(2007) TABLE 1 QUARTER 1 OF 2007 (mRem) ODCM CALCULATED ODCM LIMIT  % OF LIMIT DOSE (1)

TOTAL DOSE FOR BONE 0.00E+00 7.50E+00 0.00E+00 TOTAL DOSE FOR LIVER 3.55E-03 7.50E+00 4.73E-02 TOTAL DOSE FOR TOTAL BODY 3.55E-03 7.50E+00 4.73E-02 TOTAL DOSE FOR THYROID 3.55E-03 7.50E+00 4.73E-02 TOTAL DOSE FOR KIDNEY 3.55E-03 7.50E+00 4.73E-02 TOTAL DOSE FOR LUNG 3.55E-03 7.50E+00 4.73E-02 TOTAL DOSE FOR GI-LLI 3.55E-03 7.50E+00 4.73E-02 QUARTER 2 OF 2007 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 1.19E-02 7.50E+00 1.59E-01 TOTAL DOSE FOR TOTAL BODY 1.19E-02 7.50E+00 1.59E-01 TOTAL DOSE FOR THYROID 1.19E-02 7.50E+00 1.59E-01 TOTAL DOSE FOR KIDNEY 1.19E-02 7.50E+00 1.59E-01 TOTAL DOSE FOR LUNG 1.19E-02 7.50E+00 1.59E-01 TOTAL DOSE FOR GI-LLI 1.19E-02 7.50E+00 1.59E-01 QUARTER 3 OF 2007 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 1.07E-02 7.50E+00 1.43E-01 TOTAL DOSE FOR TOTAL BODY 1.07E-02 7.50E+00 1.43E-01 TOTAL DOSE FOR THYROID 1.07E-02 7.50E+00 1.43E-01 TOTAL DOSE FOR KIDNEY 1.07E-02 7.50E+00 1.43E-01 TOTAL DOSE FOR LUNG 1.07E-02 7.50E+00 1.43E-01 TOTAL DOSE FOR GI-LLI 1.07E-02 7.50E+00 1.43E-01 QUARTER 4 OF 2007 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 O.OOE+00 TOTAL DOSE FOR LIVER 4.32E-03 7.50E+00 5.76E-02 TOTAL DOSE FOR TOTAL BODY 4.32E-03 7.50E+00 5.76E-02 TOTAL DOSE FOR THYROID 4.32E-03 7.50E+00 5.76E-02 TOTAL DOSE FOR KIDNEY 4.32E-03 7.50E+00 5.76E-02 TOTAL DOSE FOR LUNG 4.32E-03 7.50E+00 5.76E-02 TOTAL DOSE FOR GI-LLI 4.32E-03 7.50E+00 5.76E-02 TOTALS FOR 2007 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 1.50E+01 0.OOE+00 TOTAL DOSE FOR LIVER 3.05E-02 1.50E+01 2.03E-01 TOTAL DOSE FOR TOTAL BODY 3.05E-02 1.50E+01 2.03E-01 TOTAL DOSE FOR THYROID 3.05E-02 1.50E+01 2.03E-01 TOTAL DOSE FOR KIDNEY 3.05E-02 1.50E+01 2.03E-01 TOTAL DOSE FOR LUNG 3.05E-02 1.50E+01 2.03E-01 TOTAL DOSE FOR GI-LLI 3.05E-02 1.50E+01 2.03E-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 45 GASEOUS CUMULATIVE DOSE

SUMMARY

(2007) TABLE 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A. Fission and Activation Gases

1. Total Release - (Ci) 2.69E-01 2.16E-01 1.86E-01 2.61 E-01 9.32E-01
2. Total Gamma Air dose (mRad) 1.67E-04 1.40E-04 1.20E-04 1.52E-04 5.79E-04
3. Gamma Air dose Limit (mRad) 5.O0E+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01
4. Percent of Gamma Air dose Limit 3.35E-03 2.81 E-03 2.39E-03 3.04E-03 5.79E-03
5. Total Beta Air dose (mRad) 6.04E-05 4.95E-05 4.23E-05 5.77E-05 2.1OE-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 6.04E-04 4.95E-04 4.23E-04 5.77E-04 1.05E-03 Limit (mRad)

B. Particulates

1. Total Particulates (Ci) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
2. Maximum Organ Dose (mRem) O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00
3. Organ Dose Limit (mRem) O.OOE+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01
4. Percent of Limit O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 C. Tritium
1. Total Release (Ci) 5.02E+00 1.69E+01 1.51 E+01 6.11E+00 4.32E+01
2. Maximum Organ Dose (mRem) 3.79E-03 1.20E-02 1.05E-02 4.17E-03 3.05E-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 5.05E-02 1.61 E-01 1.40E-01 5.56E-02 2.03E-01 D. Iodine
1. Total 1-131, 1-133 (Ci) 0.OOE+00 0.OOE+00 O.OQE+00 O.OOE+00 O.OOE+00
2. Maximum Organ Dose (mRem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.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 O.OOE+00 O.OOE+00 O.OOE+00 O.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 45 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 the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble -9ases. 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 area 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 lodine-131, lodine-133, 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 a radionuclide in particulate form with half-lives greater than 8 days in gaseous effluents released to area 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 45

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 Water Grab Sample Treatment S.A.C. Gross Alpha O.S.L. Sr-89, Sr-90
c. Lime Sludge Pond Daily 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 45 B. Gaseous Waste Effluents Gaseous, Release Sampling Frequency Method of Analysis Type of Activity Type Analysis P P.H.A. Principal Gamma Emitters Waste Gas Decay Tank Each Tank Grab Sample Containment Purge or P P.H.A. Principal Gamma Emitters Vent Each Purge Grab Sample Gas Bubbler and L.S. H-3 (oxide)

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

Radwaste Building M P.H.A Principal Gamma Emitters Vent Grab Sample 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 Emitters Particulate 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 45

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 56 gaseous batch releases during the reporting period. The longest gaseous batch release lasted 856 minutes, while the shortest lasted 79 minutes. The average release lasted 157 minutes with a total gaseous batch release time of 8,876 minutes.

There were 35 liquid batch releases during the reporting period. The longest liquid batch release lasted 196 minutes, while the shortest lasted 78 minutes. The average release lasted 126 minutes with a total liquid batch release time of 4,394 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 3.29E-01 mRem William Allen White Building Workers 7.24E-03 mRem Access Road Users 3.38E-03 mRem Lake Use 4.37E-02 mRem The plant delivery calculations were based on deliveries 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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 <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> per year. The dose to fishermen on the lake was based upon 3,648 hours0.0075 days <br />0.18 hours <br />0.00107 weeks <br />2.46564e-4 months <br /> (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> a day for 304 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.

21 of 45 2007 EFFLUENT CONCENTRATION LIMITS Nuclides Curies Average Diluted 10 CFR 20 ECL % of ECL Concentration (uCi/ml)

(LtCi/ml)

H-3 8.23E+02 8.66E-07 1.O0E-03 8.66E-02 Cr-51 N/A N/A 5.OOE-04 N/A Mn-54 9.06E-06 9.53E-15 3.OOE-05 3.18E-08 Mn-56 N/A N/A 7.OOE-05 N/A Co-57 1.65E-05 1.74E-14 6.OOE-05 2.90E-08 Co-58 2.88E-03 3.03E-12 2.OOE-05 1.52E-05 Fe-59 N/A N/A 1.OOE-05 N/A Co-60 3.09E-04 3.25E-13 3.OOE-06 1.08E-05 Sb-124 5.61 E-06 5.90E-15 7.OOE-06 8.43E-08 Sb-125 1.96E-03 2.06E-12 3.OOE-05 6.87E-06 1-131 3.26E-05 3.43E-14 1.OOE-06 3.43E-06 1-133 1.34E-06 1.41 E-15 7.OOE-06 2.01 E-08 1-135 N/A N/A 3.OOE-05 N/A Ce-141 N/A N/A 3.OOE-05 N/A Cs-134 N/A N/A 9.OOE-07 N/A Cs-136 N/A N/A 6.OOE-06 N/A Cs-137 7.98E-05 8.39E-14 1.OOE-06 8.39E-06 Nb-97 N/A N/A 3.OOE-04 N/A Ba-139 N/A N/A 2.OOE-04 N/A Ba-140 6.62E-06 6.96E- 15 8.OOE-06 8.70E-08 Rb-88 N/A N/A 4.OOE-04 N/A Sn-117M 1.42E-06 1.49E-15 1.00E-08 1.49E-05 Sb-122 N/A N/A 1.OOE-05 N/A Sb-126 N/A N/A 7.OOE-06 N/A Na-24 N/A N/A 5.OOE-05 N/A Nb-95 N/A N/A 3.OOE-05 N/A Tc-99M N/A N/A 1.OOE-03 N/A Sr-91 N/A N/A 2.OOE-05 N/A Zn-65 1.66E-06 1.75E-15 5.OOE-06 3.50E-08 W-187 N/A N/A 3.OOE-05 N/A Ar-41 N/A N/A 2.OOE-04 N/A Kr-85 N/A N/A 2.OOE-04 N/A Kr-85M N/A N/A 2.OOE-04 N/A Kr-88 N/A N/A 2.OOE-04 N/A Xe-131M N/A N/A 2.OOE-04 N/A Xe-133M N/A N/A 2.OOE-04 N/A Xe-133 2.76E-03 2.90E-12 2.OOE-04 1.45E-06 Xe-135 N/A N/A 2.OOE-04 N/A Xe-138 N/A N/A 2.OOE-04 N/A

22 of 45 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 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* 1.32E+01"*

evaporator bottoms, etc. Ci 1.63E+02 2.50E+01

b. Dry compressible waste, m3* 2.11 E+02**

contaminated equip. etc. Ci 1.37E+00 2.50E+01

c. Irradiated components, m3* O.OOE+00 control rods, etc. Ci 0.00E+00 2.50E+01
d. Other m3* 0.OOE+00 Ci 0.OOE+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 30 4.90E+01 Ni-63 39 6.35E+01 Co-58 17 2.77E+01

b. Dry compressible waste, contaminated equipment, etc.

Nuclide Percent Name Abundance Curies Fe-55 24 3.28E-01 Ni-63 20 2.70E-01 H-3 44 6.OOE-01 Steam Generator Blowdown resin shipped for DAW.

23 of 45

c. Irradiated components, control rods, etc. - None
d. Other-None
3. Solid Waste Disposition Number of Shipments Mode of Transwortation Destination 3 Truck (Hittman Transport Services) Energy Solutions, Oak Ridge, TN 4 Truck (Hittman Transport Services) Studsvik Processing Facility, LLC; Erwin, TN 1 Truck (Studsvik Logistics) RACE, LLC; Memphis, TN
4. Class of Solid Waste
a. Class A, Class B, Class C- Corresponding to 2a
b. Class A.- Corresponding to 2b
c. Not applicable
d. Not applicable
5. Type of Container
a. LSA (General Design), Type A, Type B - corresponding to 2a
b. LSA (General Design) - corresponding to 2b
c. Not applicable
d. Not applicable
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 2007 period.

24 of 45 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, 2007, through December 31, 2007, 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 Station did meet Regulatory Guide 1.23 requirement for data recovery and had a 90.90% meteorological data recovery for 2007.

25 of 45 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2007 STABILITY CLASS: A ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1.50 11.50 25.25 15.50 5.25 3.00 62.00 NNE 3.00 9.75 18.25 6.50 2.00 0.50 40.00 NE 3.25 14.25 16.50 0.25 0.00 0.00 34.25 ENE 1.50 14.25 9.50 1.50 0.00 0.00 26.75 E 0.25 11.00 18.75 1.50 0.00 0.00 31.50 ESE 1.25 8.50 17.00 1.75 0.00 0.00 28.50 SE 0.75 11.50 21.00 10.25 0.00 0.00 43.50 SSE 0.75 15.50 65.75 33.00 10.00 2.75 127.75 S 1.00 16.50 86.25 97.00 26.75 5.75 233.25 SSW 0.25 11.25 57.00 85.50 15.00 2.50 171.50 SW 1.25 10.75 38.50 13.50 0.75 0.25 65.00 WSW 2.00 11.00 22.25 6.25 0.00 0.75 42.25 W 0.75 15.75 14.50 18.75 0.25 0.00 50.00 WNW 1.00 13.50 17.75 10.50 4.50 8.25 55.50 NW 0.75 12.25 20.25 22.00 7.00 3.00 65.25 NNW 1.00 14.00 22.25 24.50 21.25 6.50 89.50 TOTAL 18.75 201.25 470.75 348.25 92.75 33.25 1166.50 PERIOD OF CALM (HOURS): 0

26 of 45 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31,2007 STABILITY CLASS: B ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0.00 6.25 13.00 7.50 4.25 0.50 31.50 NNE 2.00 8.75 10.75 2.25 1.00 0.00 24.75 NE 2.75 10.00 3.50 0.50 0.00 0.00 16.75 ENE 0.00 7.75 3.25 1.00 0.00 0.00 12.00 E 1.25 12.25 6.00 1.00 0.00 0.00 20.50 ESE 0.75 8.25 6.25 0.00 0.00 0.00 15.25 SE 1.00 6.25 8.75 1.00 0.00 0.25 17.25 SSE 0.25 14.50 17.00 6.50 2.50 0.50 41.25 S 1.00 16.75 34.75 19.75 6.75 2.00 81.00 SSW 0.75 6.25 19.75 17.75 4.00 0.50 49.00 SW 0.50 4.00 9.25 3.00 0.00 0.75 17.50 WSW 1.00 5.25 5.00 2.75 1.00 1.75 16.75 W 0.75 4.50 4.00 2.25 0.25 0.25 12.00 WNW 0.50 3.00 2.25 2.00 1.00 2.00 10.75 NW 0.50 2.50 9.50 2.25 3.00 0.50 18.25 NNW 1.25 4.00 10.50 5.00 4.75 0.00 25.50 TOTAL 14.25 120.25 163.50 74.50 28.50 9.00 410.00 PERIOD OF CALM (HOURS): 0

27 of 45 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2007 STABILITY CLASS: C ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1.25 6.75 10.75 6.75 4.00 1.25 30.75 NNE 2.50 8.50 10.25 6.25 0.50 0.00 28.00 NE 0.25 5.25 3.75 0.75 0.00 0.00 10.00 ENE 1.00 8.00 2.00 0.25 0.00 0.00 11.25 E 1.25 15.00 7.50 1.25 0.25 0.00 25.25 ESE 1.25 11.00 4.50 0.00 0.00 0.00 16.75 SE 1.50 8.50 7.00 1.25

  • 0.00 0.00 18.25 SSE 1.50 22.25 15.50 7.75 3.25 0.50 50.75 S 0.50 16.00 26.75 15.00 6.75 2.25 67.25 SSW 0.25 6.25 21.25 14.50 7.50 0.75 50.50 SW 0.50 6.00 6.00 1.75 1.00 0.25 15.50 WSW 1.25 3.75 4.50 3.50 1.50 0.50 15.00 W 0.50 2.50 3.50 1.50 0.00 0.00 8.00 WNW 2.00 2.50 2.50 3.25 2.00 1.25 13.50 NW 1.50 2.25 6.25 1.75 3.00 1.50 16.25 NNW 1.50 5.75 11.75 4.25 4.75 0.50 28.50 TOTAL 17.25 130.25 143.75 69.75 34.50 8.75 405.50 PERIOD OF CALM (HOURS): 0

/

28 of 45 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2007 STABILITY CLASS: D ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 8.00 47.25 78.50 76.75 22.25 5.50 238.25 NNE 10.00 47.75 38.50 19.75 2.25 0.75 119.00 NE 12.25 56.25 62.75 3.25 0.00 0.00 134.50 ENE 10.00 58.75 40.75 8.50 0.25 0.00 118.25 E 8.00 58.75 57.25 18.25 0.50 0.00 142.75 ESE 6.75 52.25 32.25 8.75 0.25 0.00 100.25 SE 9.25 48.00 74.00 21.50 1.00 0.00 153.75 SSE 9.25 62.50 126.75 64.75 29.50 2.75 295.50 S 7.50 57.25 183.00 149.50 39.25 12.00 448.50 SSW 5.00 34.25 97.75 69.50 16.25 3.75 226.50 SW 7.50 39.50 25.75 6.75 1.25 0.50 81.25 WSW 5.00 25.25 23.75 11.75 3.00 0.75 69.50 W 3.50 17.50 29.25 24.75 0.50 0.25 75.75 WNW 5.75 14.75 33.00 31.25 15.25 4.00 104.00 NW 5.50 21.00 76.75 41.75 7.50 5.00 157.50 NNW 8.75 40.75 76.75 92.75 17.75 5.00 241.75 TOTAL 114.00 681.75 1056.75 649.50 156.75 40.25 2707.00 PERIOD OF CALM (HOURS): 0.25

29 of 45 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2007 STABILITY CLASS: E ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 14.25 29.50 37.50 18.50 0.25 0.00 100.00 NNE 12.75 34.25 19.75 7.75 1.00 0.00 75.50 NE 23.00 33.00 10.50 1.50 0.00 0.00 68.00 ENE 7.75 40.00 31.00 3.75 0.00 0.00 82.50 E 14.50 67.25 25.25 9.50 0.00 0.00 116.50 ESE 16.75 79.00 29.25 8.75 0.00 0.00 133.75 SE 15.25 80.50 69.25 22.75 4.75 0.75 193.25 SSE 9.25 97.25 170.50 61.00 18.50 3.25 359.75 S 7.50 68.50 138.50 69.50 24.75 4.50 313.25 SSW 8.25 48.50 73.75 35.00 11.50 1.25 178.25 SW, 7.25 58.25 19.50 9.00 5.00 0.25 99.25 WSW 4.25 21.50 20.75 2.75 0.50 0.25 50.00 W 3.00 23.50 29.25 2.25 0.00 0.00 58.00 WNW 5.25 20.50 29.00 1.50 0.00 0.00 56.25 NW 3.50 48.25 43.00 11.50 0.50 0.00 106.75 NNW 9.00 37.25 39.25 13.25 0.75 0.00 99.50 TOTAL 147.25 787.00 786.00 278.25 67.50 10.25 2090.50 PERIOD OF CALM (HOURS): 1.75

30 of 45 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2007 STABILITY CLASS: F ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 12.75 30.50 16.00 0.00 0.00 0.00 59.25 NNE 22.25 26.75 5.25 0.00 0.00 0.00 54.25 NE 18.25 18.00 0.50 0.00 0.00 0.00 36.75 ENE 9.75 21.00 2.25 0.75 0.00 0.00 33.75 E 15.00 45.00 4.50 0.25 0.00 0.00 64.75 ESE 12.75 55.00 7.50 1.00 0.00 0.00 76.25 SE 13.00 85.50 8.50 1.25 0.00 0.00 108.25 SSE 6.00 57.50 27.50 3.00 0.00 0.00 94.00 S 5.75 23.00 28.50 2.75 0.25 0.00 60.25 SSW 5.25 14.75 9.25 1.75 0.25 0.00 31.25 SW 7.75 16.50 1.50 2.25 0.25 0.00 28.25 WSW 1.50 5.75 0.00 0.25 0.00 0.00 7.50 W 3.00 5.50 2.00 0.00 0.00 0.00 10.50 WNW 4.25 5.75 0.75 0.00 0.00 0.00 10.75 NW 4.25 21.00 2.75 0.00 0.00 0.00 28.00 NNW 6.50 30.25 .10.50 0.00 0.00 0.00 47.25 TOTAL 135.25 461.75 127.25 13.25 0.75 0.00 751.00 PERIOD OF CALM (HOURS): 2.25

31 of 45 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2007 STABILITY CLASS: G ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9.00 26.75 3.75 0.00 0.00 0.00 39.50 NNE 14.25 37.25 4.75 0.00 0.00 0.00 56.25 NE 16.00 24.75 0.00 0.00 0.00 0.00 40.75 ENE 7.25 23.75 0.50 0.00 0.00 0.00 31.50 E 8.50 37.25 0.25 0.00 0.00 0.00 46.00 ESE 9.25 44.50 4.75 0.00 0.00 0.00 58.50 SE 3.75 31.25 1.00 0.00 0.25 0.00 36.25 SSE 4.00 14.75 7.75 3.00 0.50 0.00 30.00 S 1.00 3.50 4.25 1.25 1.00 0.00 11.00 SSW 1.75 1.50 1.00 0.00 0.00 0.00 4.25 SW 3.50 4.25 3.00 0.00 0.00 0.00 10.75 WSW 2.00 2.25 0.00 0.00 0.00 0.00 4.25 W 1.75 0.50 0.25 0.00 0.00 0.00 2.50 WNW 2.75 2.00 0.75 0.00 0.00 0.00 5.50 NW 7.25 15.25 0.50 0.00 0.00 0.00 23.00 NNW 7.25 16.75 1.75 0.00 0.00 0.00 25.75 TOTAL 90.25 286.25 34.25 4.25 1.75 0.00 425.75 PERIOD OF CALM (HOURS): 2.00

32 of 45 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31,2007 STABILITY CLASS: ALL ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 46.75 158.50 184.75 125.00 36.00 10.25 561.25 NNE 66.75 173.00 107.50 42.50 6.75 1.25 397.75 NE 75.75 161.50 97.50 6.25 0.00 0.00 341.00 ENE 37.25 173.50 89.25 15.75 0.25 0.00 316.00 E 48.75 246.50 119.50 31.75 0.75 0.00 447.25 ESE 48.75 258.50 101.50 20.25 0.25 0.00 429.25 SE 44.50 271.50 189.50 58.00 6.00 1.00 570.50 SSE 31.00 284.25 430.75 179.00 64.25 9.75 999.00 S 24.25 201.50 502.00 354.75 105.50 26.50 1214.50 SSW 21.50 122.75 279.75 224.00 54.50 8.75 711.25 SW 28.25 139.25 103.50 36.25 8.25 2.00 317.50 WSW 17.00 74.75 76.25 27.25 6.00 4.00 205.25 W 13.25 69.75 82.75 49.50 1.00 0.50 216.75 WNW 21.50 62.00 86.00 48.50 22.75 15.50 256.25 NW 23.25 122.50 159.00 79.25 21.00 10.00 415.00 NNW 35.25 148.75 172.75 139.75 49.25 12.00 557.75 TOTAL 583.75 2668.50 2782.25 1437.75 382.50 101.50 7956.25 Hours of PERIOD OF CALM Missing (HOURS): 6.25 Data: 796.75

33 of 45 SECTION IV ADDITIONAL INFORMATION

1. Unplanned or Abnormal Releases No unplanned, unmonitored release occurred in 2007. See Section II, Additional Information.
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 6, is included with this report as Attachment I. The other procedure, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program),

AP 07B-004, Revision 14, is included with this report as Attachment I1.

3. Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems Change Package #10399, to replace the Waste Gas Hydrogen and Oxygen Analyzers in the Gaseous Radwaste System, was completed in 2007. One train of the new Hydrogen and Oxygen Analyzer Rack was installed in September 2006. The other train was installed in February 2007. The previous analyzers were not designed to compensate for the presence of Helium, which caused erroneously high readings. It was necessary for Radwaste Treatment Systems personnel to be in constant attendance during multiple evolutions. In addition the previous analyzers were obsolete to the point that vendor assistance was minimal and there were no parts available for repair. The new analyzers are able to discriminate between Helium and Hydrogen, making operation of the system easier and more efficient.

Change Package #12092, issued 2/23/2007, allowed removal of the internal bladder from the Waste Evaporator Condensate Tank. The modification is scheduled for implementation in 2008.

The bladder was found to be torn during an inspection and Engineering determined it was more cost effective to remove the bladder rather than replace it. The Waste Evaporator Condensate Tank previously stored recyclable water (Reactor Makeup Water grade) and the bladder was necessary to prevent oxygen intrusion into the water. The function of the Waste Evaporator Condensate Tank was later changed to store non-recyclable water (floor drain, waste hold-up tank, etc.). Thus the modification does not affect the capacity or handling of radioactive wastes of the Radwaste systems.

Two revisions to Change Package #9337, Liquid Radwaste Zero Filtration System, were issued in 2007. This change package previously installed the new filtration system for Liquid Radwaste.

Nothing has been changed with the method by which Liquid Radwaste is handled by these revisions, the two revisions were issued to provide guidance for a replacement obsolete valve and to eliminate an electrical circuit in an abandoned circuit panel.

No other modifications were made to the Solid, Liquid or Gaseous Radwaste Systems in 2007 that alter the capacity or handling of Radioactive Wastes or differ in the method of treatment.

4. Land Use Census There was 1 change to the nearest occupied residence in sector B and 5 changes for the nearest garden producing broadleaf vegetation (per AP 07B-004, Offsite Dose Calculation Manual [Radiological Environmental monitoring Program]).

34 of 45

5. Radwaste Shipments Seven shipments of radioactive waste occurred during this report period.Section II, Subsection 3, of this report contains specific details regarding each shipment's mode of transportation and destination.
6. Inoperability of Effluent Monitoring Instrumentation No events occurred that violated ODCM Requirements Tables 2-2 and 3-2, liquid or gaseous effluent monitoring instrumentation.
7. Storage Tanks At no time during the year 2007 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."

8. NEI Groundwater Protection Industry Initiative See attached 6 pages See attached 4 pages with corrected gross alpha information for the 2006 Annual report.

35 of 45 ONSITE GROUNDWATER MONITORING Basis The onsite groundwater 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.

Program Description In March of 2006, Wolf Creek Generating Station (WCGS) established an onsite groundwater monitoring program. This program was implemented via procedure Al 07-007, Onsite Groundwater Monitoring Program. The onsite groundwater samples were collected by the WCGS Environmental Management group and were analyzed by Environmental, Inc., Midwest Laboratory. The vendor lab participated in an interlaboratory comparison program. Onsite groundwater samples were analyzed by gamma isotopic analysis, radiochemical analysis for 1-131 and tritium analysis. Quarterly grab samples were obtained from three wells: ESW-W-NE, ESW-W-NW and AUX. The following tables describe the sample locations, the program required lower limits of detection and the reporting levels for radioactivity detected.

Sample Location Sample Location Description ESW-W-NE Essential Service Water Dewatering Well, West Group, Northeast, located south of the reactor ESW-W-NW Essential Service Water Dewatering Well, West Group, Northwest, located south of the reactor AUX Dewatering Well located near the Auxiliary Building, on West Side Onsite Groundwater Lower Limits of Detection Analysis (pCi/I) 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

36 of 45 Discussion of Results As expected, low levels of tritium were detected in all of the onsite groundwater samples. The location with the highest level of tritium detected was ESW-W-NE (1,418 +/- 123 pCi/L). The measured level is significantly lower than the tritium levels routinely detected in surface water collected from Coffey County Lake (2007 range was 8,262 to 12,910 pCi/L). The location with the lowest level of tritium detected was location ESW-W-NW (355 +/- 87 pCi/L). The tritium activity was the only activity detected in the onsite groundwater samples. Required lower limits of detection were met. The individual sample results follow.

Onsite Groundwater --3 Results 2000 1800 1600 1400 1200 1000

,8000-600

.400 200 0

Mar-06 Jun-06 Sep-06 Dec-06 Mar-07 Jun-07 Sep-07 Dec-07

- ESW-W-NE m-- SW-W-NW A AUX

37 of 45 Onsite Ground Water Results COLLECTION LOCATION DUPLICATE DATE NUCLIDE CONCENTRATION (pCi/L)

AUX 16-Feb-07 MN-54 < 2.6 AUX 16-Feb-07 CO-58 < 3.1 AUX 16-Feb-07 FE-59 < 5.8 AUX 16-Feb-07 CO-60 < 2.7 AUX 16-Feb-07 ZN-65 < 5.9 AUX 16-Feb-07 ZR-NB-95 < 1.7 AUX 16-Feb-07 CS- 134 < 3.3 AUX 16-Feb-07 CS- 137 < 3.6 AUX 16-Feb-07 BA-LA- 140 < 2.3 AUX 16-Feb-07 H-3 682 +/- 99 AUX 16-Feb-07 1-131 (CHEM) < 0.337 AUX 18-May-07 MN-54 < 4.4 AUX 18-May-07 CO-58 < 3.9 AUX 18-May-07 FE-59 < 7.8 AUX 18-May-07 CO-60 < 5.5 AUX 18-May-07 ZN-65 < 7.0 AUX 18-May-07 ZR-NB-95 < 6.5 AUX 18-May-07 CS- 134 < 4.3 AUX 18-May-07 CS- 137 < 4.1 AUX 18-May-07 BA-LA- 140 < 8.9 AUX 18-May-07 H-3 373 +/- 87 AUX 18-May-07 1-131 (CHEM) < 0.343 AUX 09-Aug-07 MN-54 < 3.4 AUX 09-Aug-07 CO-58 < 3.0 AUX 09-Aug-07 FE-59 < .4.6 AUX 09-Aug-07 CO-60 < 5.7 AUX 09-Aug-07 ZN-65 < 3.9 AUX 09-Aug-07 ZR-NB-95 < 4.4 AUX 09-Aug-07 CS- 134 < 4.0 AUX 09-Aug-07 CS- 137 < 2.0 AUX 09-Aug-07 BA-LA- 140 < 8.1 AUX 09-Aug-07 H-3 703 +/- 108 AUX 09-Aug-07 1- 131 (CHEM) < 0.43 AUX 14-Nov-07 MN-54 < 2.7 AUX 14-Nov-07 CO-58 < 2.5 AUX 14-Nov-07 FE-59 < 3.8 AUX 14-Nov-07 CO-60 < 1.9 AUX 14-Nov-07 ZN-65 < 3.3 AUX 14-Nov-07 ZR-NB-95 < 3.6 AUX 14-Nov-07 CS- 134 < 3.8

38 of 45 COLLECTION LOCATION DUPLICATE DATE NUCLIDE CONCENTRATION (pCi/L)

AUX 14-Nov-07 CS-137 < 2.7 AUX 14-Nov-07 BA-LA- 140 < 1.6 AUX 14-Nov-07 H-3 885 +/- 122 AUX 14-Nov-07 1-131 (CHEM) < 0.418 ESW-W-NE 16-Feb-07 MN-54 < 3.1 ESW-W-NE 16-Feb-07 CO-58 < 2.9 ESW-W-NE I 16-Feb-07 FE-59 < 6.3 ESW-W-NE 16-Feb-07 CO-60 < 2.7 ESW-W-NE 16-Feb-07 ZN-65 < 7.9 ESW-W-NE 16-Feb-07 ZR-NB-95 < 3.1 ESW-W-NE 16-Feb-07 CS- 134 < 4.0 ESW-W-NE 16-Feb-07 CS- 137 < 3.9 ESW-W-NE 16-Feb-07 BA-LA- 140 < 3.4 ESW-W-NE 16-Feb-07 H-3 1418 +/- 123 ESW-W-NE 16-Feb-07 1- 131 (CHEM) < 0.371 ESW-W-NE 18-May-07 MN-54 < 3.7 ESW-W-NE 18-May-07 CO-58 < 2.0 ESW-W-NE 18-May-07 FE-59 < 5.6 ESW-W-NE 18-May-07 CO-60 < 2.6 ESW-W-NE 18-May-07 ZN-65 < 5.3 ESW-W-NE 18-May-07 ZR-NB-95 < 4.0 ESW-W-NE 18-May-07 CS- 134 < 3.6 ESW-W-NE 18-May-07 CS- 137 < 2.5 ESW-W-NE 18-May-07 BA-LA- 140 < 2.7 ESW-W-NE 18-May-07 H-3 897 +/- 108 ESW-W-NE 18-May-07 1- 131 (CHEM) < 0.476 ESW-W-NE 09-Aug-07 MN-54 < 2.8 ESW-W-NE 09-Aug-07 CO-58 < 3.4 ESW-W-NE 09-Aug-07 FE-59 < 4.7 ESW-W-NE 09-Aug-07 CO-60 < 2.0 ESW-W-NE 09-Aug-07 ZN-65 < 2.8 ESW-W-NE 09-Aug-07 ZR-NB-95 < 2.3 ESW-W-NE 09-Aug-07 CS- 134 < 2.4 ESW-W-NE 09-Aug-07 CS- 137 < 2.4 ESW-W-NE 09-Aug-07 BA-LA- 140 < 3.6 ESW-W-NE 09-Aug-07 H-3 894 +/- 115 ESW-W-NE 09-Aug-07 1-131 (CHEM) < 0.458 ESW-W-NE 14-Nov-07 MN-54 <_1 4.0 ESW-W-NE 14-Nov-07 ICO-58 I < 2.7 ESW-W-NE 14-Nov-07 -E-59 I _< 5.1

39 of 45 COLLECTION LOCATION DUPLICATE DATE NUCLIDE CONCENTRATION (pCi/L)

ESW-W-NE 14-Nov-07 CO-60 < 3.6 ESW-W-NE 14-Nov-07 ZN-65 ,_< 3.4 ESW-W-NE 14-Nov-07 ZR-NB-95 < 3.8 ESW-W-NE 14-Nov-07 CS- 134 < 3.5 ESW-W-NE 14-Nov-07 CS-137 < 4.1 ESW-W-NE 14-Nov-07 BA-LA- 140 < 4.7 ESW-W-NE 14-Nov-07 H-3 816 +/- 120 ESW-W-NE 14-Nov-07 1-131 (CHEM) < 0.443 ESW-W-NW 16-Feb-07 MN-54 < 3.4 ESW-W-NW 16-Feb-07 CO-58 < 4.2 ESW-W-NW 16-Feb-07 FE-59 < 7.0 ESW-W-NW 16-Feb-07 CO-60 < 4.3 ESW-W-NW 16-Feb-07 ZN-65 < 4.0 ESW-W-NW 16-Feb-07 ZR-NB-95 < 4.8 ESW-W-NW- 16-Feb-07 CS- 134 < 5.3 ESW-W-NW 16-Feb-07 CS- 137 < 3.7 ESW-W-NW 16-Feb-07 BA-LA- 140 < 2.9 ESW-W-NW 16-Feb-07 H-3 985 +/- 110 ESW-W-NW 16-Feb-07 1-131 (CHEM) < 0.346 ESW-W-NW 18-May-07 MN-54 < 2.0 ESW-W-NW 18-May-07 CO-58 < 2.5 ESW-W-NW 18-May-07 FE-59 < 3.4 ESW-W-NW 18-May-07 CO-60 < 2.5 ESW-W-NW 18-May-07 ZN-65 < 3.8 ESW-W-NW 18-May-07 ZR-NB-95 < 2.6 ESW-W-NW 18-May-07 CS- 134 < 2.7 ESW-W-NW 18-May-07 CS- 137 < 2.9 ESW-W-NW 18-May-07 BA-LA- 140 < 2.2 ESW-W-NW 18-May-07 H-3 355 +/- 87 ESW-W-NW 18-May-07 1-131 (CHEM) < 0.318 ESW-W-NW Duplicate 09-Aug-07 MN-54 < 1.8 ESW-W-NW 09-Aug-07 MN-54 < 5.4 ESW-W-NW Duplicate 09-Aug-07 CO-58 < 2.5 ESW-W-NW 09-Aug-07 CO-58 < 4.0 ESW-W-NW Duplicate 09-Aug-07 FE-59 < 5.5 ESW-W-NW 09-Aug-07 FE-59 < 7.5 ESW-W-NW Duplicate 09-Aug-07 CO-60 < 1.8 ESW-W-NW 09-Aug-07 CO-60 <_3.6 ESW-W-NW Duplicate 09-Aug-07 ZN-65 < 3.6 ESW-W-NW I 09-Aug-07 ZN-65 < 6.6

40 of 45 COLLECTION LOCATION DUPLICATE DATE NUCLIDE CONCENTRATION (pCi/L)

ESW-W-NW Duplicate 09-Aug-07 ZR-NB-95 < 3.0 ESW-W-NW E 09-Aug-07 ZR-NB-95 < 3.4 ESW-W-NW Duplicate 09-Aug-07 CS- 134 < 2.6 ESW-W-NW 09-Aug-07 CS- 134 < 4.7 ESW-W-NW Duplicate 09-Aug-07 CS- 137 < 2.2 ESW-W-NW 09-Aug-07 CS- 137 < 4.3 ESW-W-NW Duplicate 09-Aug-07 BA-LA- 140 < 2.0 ESW-W-NW 09-Aug-07 BA-LA- 140 < 7.2 ESW-W-NW Duplicate 09-Aug-07 H-3 831 +1- 113 ESW-W-NW 09-Aug-07 H-3 644 +1- 106 ESW-W-NW Duplicate 09-Aug-07 1-131 (CHEM) < 0.472 ESW-W-NW 09-Aug-07 1-131 (CHEM) < 0.483 ESW-W-NW 14-Nov-07 MN-54 < 2.8 ESW-W-NW 14-Nov-07 CO-58 < 1.5 ESW-W-NW 14-Nov-07 FE-59 < 4.9 ESW-W-NW 14-Nov-07 CO-60 < 1.2 ESW-W-NW 14-Nov-07 ZN-65 < 3.9 ESW-W-NW 14-Nov-07 ZR-NB-95 < 2.3 ESW-W-NW 14-Nov-07 CS-134 < 2.4 ESW-W-NW 14-Nov-07 CS- 137 < 3.4 ESW-W-NW 14-Nov-07 BA-LA- 140 < 1.4 ESW-W-NW 14-Nov-07 H-3 872 +/- 121 ESW-W-NW 14-Nov-07 1-131 (CHEM) I _< 0.402

41 of 45 SECTION I REPORT OF 2006 RADIOACTIVE EFFLUENTS: LIQUID Unit Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, Ci 3.03E-04 5.44E-04 gases, alpha)
2. Average Diluted Concentration l.Ci/ml 3.99E-12 2.55E-12 During Period
3. Percent of Applicable Limit  % 6.05E-03 1.09E-02 (1)

B. Tritium

1. Total Release Ci 1.99E+02 5.53E+02
2. Average Diluted Concentration pCi/mI 2.62E-06 2.59E-06 During Period
3. Percent of Applicable Limit (2)  % 2.62E-01 2.59E-01 (ECL)

C. Dissolved and Entrained Gases

1. Total Release Ci 2.85E-04 1.86E-03
2. Average Diluted Concentration lpCi/mI 3.76E-12 8.70E-12 During Period
3. Percent of Applicable Limit  % 1.88E-06 4.35E-06 (3)

D. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 3.40E-06 E. Volume of Waste Released Liters 8.46E+07 1.21 E+08 (prior to dilution)

F. Volume of Dilution Water Used Liters 7.58E+10 2.13E+11 NOTES:

4) 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.

5) This value is derived by the following formula:

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

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

6) This value is derived by the following formula:

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

(2E - 04 from ODCM Section 2.1)

42 of 45 REPORT OF 2006 RADIOACTIVE EFFLUENTS: LIQUID Unit Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, Ci 4.92E-04 8.64E-03 gases, alpha
2. Average Diluted Concentration gCi/ml 1.83E-12 4.44E-11 During Period
3. Percent of Applicable Limit 9.84E-03 1.73E-01 (1)

B. Tritium

1. Total Release Ci 4.42E+02 1.88E+02
2. Average Diluted Concentration GCi/ml 1.64E-06 9.65E-07 During Period
3. Percent of Applicable Limit (2)  % 1.64E-01 9.65E-02 (ECL)

C. Dissolved and Entrained Gases

1. Total Release Ci 6.68E-03 9.73E-03
2. Average Diluted Concentration pCi/mI 2.48E-1 1 5.OOE-1 1 During Period
3. Percent of Applicable Limit  % 1.24E-05 2.50E-05 (3)

D. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 1.74E06 E. Volume of Waste Released liters 8.62E+07 8.41 E+07 (prior to dilution)

F. Volume of Dilution Water Used liters 2.69E+11 1.94E+11 NOTES:

4) 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.

5) This value is derived by the following formula:

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

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

6) This value is derived by the following formula:

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

(2E -04 from ODCM Section 2.1)

43 of 45 2006 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Released H-3 Ci 1.34E+00 1.21 E+00 1.97E+02 5.52E+02 Cr-51 Ci N/A N/A N/A N/A Mn-54 Ci <4.21 E-02 <6.04E-02 2.49E-06 8.57E-07 Fe-55 Ci <8.42E-02 <1.21E-01 <3.34E-04 <6.19E-04 Fe-59 Ci <4.21 E-02 <6.04E-02 2.17E-06 <3.09E-04 Co-57 Ci N/A N/A N/A N/A Co-58 Ci <4.21 E-02 <6.04E-02 2.20E-05 8.92E-05 Co-60 Ci <4.21 E-02 <6.04E-02 2.66E-05 4.37E-05 Zn-65 Ci <4.21 E-02 <6.04E-02 <1.67E-04 <3.09E-04 Sr-89 Ci <4.21 E-03 <6.04E-03 <1.67E-05 <3.09E-05 Sr-90 Ci <4.21 E-03 <6.04E-03 <1.67E-05 <3.09E-05 Sr-91 Ci N/A N/A N/A 2.42E-06 Mo-99 Ci <4.21 E-02 <6.04E-02 <1.67E-04 <3.09E-04 Sb-124 Ci N/A N/A N/A N/A Sb-1 25 Ci N/A N/A 2.32E-04 3.88E-04 1-131 Ci <8.42E-02 <1.21 E-01 <3.34E-04 <6.19E-04 1-133 Ci N/A N/A N/A N/A Cs-1 34 Ci <4.21 E-02 <6.04E-02 <1.67E-04 <3.09E-04 Cs-136 Ci N/A N/A 1.18E-06 N/A Cs-1 37 Ci <4.21 E-02 <6.04E-02 1.62E-05 1.92E-05 Ce-141 Ci <4.21E-02 <6.04E-02 <1.67E-04 <3.09E-04 Ce-144 Ci <4.21E-02 <6.04E-02 <1.67E-04 <3.09E-04 Na-24 Ci N/A N/A N/A N/A Rb-88 Ci N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A 6.47E-07 Tc-99M Ci N/A N/A N/A N/A Sb-122 Ci N/A N/A N/A N/A Sb-126 Ci N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A Gross Alpha Ci <8.42E-03 <1.21 E-02 <3.34e-05 3.40E-06 Ar-41 Ci <8.42E-01 <1.21E+00 <3.34E-03 <6.19E-03 Kr-85M Ci <8.42E-01 <1.21E+00 <3.34E-03 <6.19E-03 Kr-85 Ci <8.42E-01 <1.21E+00 .<3.34E-03 <6.19E-03 Kr-87 Ci <8.42E-01 <1.21E+00 <3.34E-03 <6.19E-03 Kr-88 Ci <8.42E-01 <1.21 E+00 <3.34E-03 <6.19E-03 Xe-131M Ci <8.42E-01 <1.21E+00 <3.34E-03 <6.19E-03 Xe-133M Ci <8.42E-01 <1.21E+00 <3.34E-03 7.90E-06 Xe-133 Ci <8.42E-01 <1.21 E+00 2.85E-04 1.85E-03 Xe-135M Ci <8.42E-01 <1.21 E+00 <3.34E-03 <6.19E-03 Xe-135 Ci <8.42E-01 <1.21 E+00 <3.34E-03 8.87E-07 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.

44 of 45 2006 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Released H-3 Ci 1.55E+00 1.12E+00 4.40E+02 1.87E+02 Cr-51 Ci N/A N/A N/A N/A Mn-54 Ci <4.28E-02 <4.16E-02 2.51 E-06 1.30E-05 Fe-55 Ci <8.56E-02 <8.31 E-02 <6.43E-04 <9.97E-04 Fe-59 Ci <4.28E-02 <4.16E-02 1.94E-06 6.57E-06 Co-57 Ci N/A N/A N/A 1.09E-05 Co-58 Ci <4.28E-02 <4.16E-02 5.58E-05 7.47E-03 Co-60 Ci <4.28E-02 <4.16E-02 6.35E-05 1.86E-04 Zn-65 Ci <4.28E-02 <4.16E-02 <3.21 E-04 <4.99E-04 Rb-88 Ci N/A N/A N/A 7.34E-05 Sr-89 Ci <4.28E-03 <4.16E-03 <3.21 E-05 <4.99E-05 Sr-90 Ci <4.28E-03 <4.16E-03 <3.21 E-05 <4.99E-05 Mo-99 Ci <4.28E-02 <4.16E-02 <3.21 E-04 <4.99E-04 Sn-117M Ci N/A N/A N/A 4.61 E-06 Sb-124 Ci N/A N/A N/A 3.21 E-06 Sb-1 25 Ci N/A N/A 3.46E-04 8.35E-04 1-131 Ci <8.56E-02 <8.31E-02 <6.43E-04 <9.97E-04 1-135 Ci N/A N/A N/A N/A Cs-1 34 Ci <4.28E-02 <4.16E-02 <3.21 E-04 <4.99E-04 Cs-136 Ci N/A N/A 7.53E-07 N/A Cs-137 Ci <4.28E-02 <4.16E-02 2.11E-05 3.21 E-05 Ce-141 Ci <4.28E-02 <4.16E-02 <3.21 E-04 <4.99E-04 Ce-144 Ci <4.28E-02 <4.16E-02 <3.21 E-04 <4.99E-04 Sr-91 Ci N/A N/A N/A 2.94E-06 Nb-95 Ci N/A N/A N/A N/A W-187 Ci N/A N/A N/A N/A Gross Alpha Ci <8.56E-03 <8.31 E-03 <6.43e-05 1.74e-06 Ar-41 Ci <8.56E-01 <8.31 E-01 <6.43E-03 3.93E-06 Kr-85M Ci <8.56E-01 <8.31 E-01 <6.43E-03 1.72E-05 Kr-85 Ci <8.56E-01 <8.31 E-01 <6.43E-03 <9.97E-03 Kr-87 Ci <8.56E-01 <8.31 E-01 <6.43E-03 <9.97E-03 Kr-88 Ci <8.56E-01 <8.31 E-01 <6.43E-03 <9.97E-03 Xe-131M Ci <8.56E-01 <8.31 E-01 <6.43E-03 <9.97E-03 Xe-133M Ci <8.56E-01 <8.31E-01 7.27E-05 2.OOE-04 Xe-133 Ci <8.56E-01 <8.31E-01 6.54E-03 8.31E-03 Xe-135M Ci <8.56E-01 <8.31 E-01 <6.43E-03 <9.97E-03 Xe-135 Ci <8.56E-01 <8.31E-01 3.77E-05 1.21E-03 Xe-138 Ci N/A N/A 3.14E-05 N/A 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.

45 of 45 ENCLOSURES TO WCGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -

REPORT 31 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 I is AP 07B-003, Revision 6, "Offsite Dose Calculation Manual" Enclosure II is AP 07B-004, Revision 13, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Enclosure III is AP 31A-100, Revision 6, "Solid Radwaste Process Control Program"

Retrieved from "https://kanterella.com/w/index.php?title=ML081260528&oldid=2157560"