ML071270038

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Annual Radioactive Effluent Release Report, Report No. 30 for 2006
ML071270038
Person / Time
Site: Wolf Creek 
(NPF-042)
Issue date: 12/31/2006
From:
Wolf Creek
To:
Office of Nuclear Reactor Regulation
References
RA 07-0046
Download: ML071270038 (46)
v • d • e


Text

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. 30 Reporting Period: January 1, 2006 - December 31, 2006

2 of 46 Table of Contents Page Executive Summary 4

Section I Report of 2006 Radioactive Effluents: Liquid 6

2006 Liquid Effluents 8

2006 Liquid Cumulative Dose Summary-Table 1 10 2006 Liquid Cumulative Dose Summary - Table 2 11 Report of 2006 Radioactive Effluents: Airborne 12 2006 Gaseous Effluents 14 2006 Gaseous Cumulative Dose Summary - Table 1 16 2006 Gaseous Cumulative Dose Summary - Table 2 17 Section II Offsite Dose Calculation Manual Limits 18, Effluent Concentration Limits (ECLs) 18 Average Energy 19 Measurements and Approximations of Total Radioactivity (Liquid and 19 Gaseous Effluents)

Batch Releases 21 Continuous Releases 21, Doses to a Member of the Public from Activities Inside the Site Boundary 21:

Additional Information 22 2006 Effluent Concentration Limits 231-2006 Solid Waste Shipments 24.'

Irradiated Fuel Shipments 25:

Section III Meteorological Data - Hours At Each Wind Speed and Direction 26 Section IV Unplanned or Abnormal Releases 35 Offsite Dose Calculation Manual 35 Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems 35 Land Use Census 35 Radwaste Shipments 35 Inoperability of Effluent Monitoring Instrumentation 35 Storage Tanks 35 NEI Groundwater Protection Industry Initiative 36

3 of 46 Table of Contents Paqe Attachments 46 Attachment I - WCGS Procedure AP 07B-003, Revision 6, "Offsite Dose Calculation Manual" Attachment II - WCGS Procedure AP 07B-004, Revision 13, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Attachment III - WCGS Procedure AP 31A-100, Revision 6, "Solid Radwaste Process Control Program"

4 of 46 EXECUTIVE

SUMMARY

This Annual Radioactive Effluent Release Report (Report # 30) documents the quantities of liquid and gaseous effluents and solid waste released by Wolf Creek Generating Station (WCGS) from January 1, 2006 through December 31, 2006. 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 2006, 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 2006.

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 2006.

Section II --- Section II includes supplemental information on continuous and batch releases, calculated doses, and solid waste disposal. There were 68 gaseous batch releases in 2006 versus 72 in 2005. There were 50 liquid batch releases in 2006 versus 62 in 2005. WCGS released 0.010 curies in liquid releases during 2006 versus 0.014 curies in 2005, 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 Report (CR):

CR 2006-0398 - While purging the Volume Control Tank (VCT) to Gas Decay Tank (GDT) #2, an attempt was made to remove water in a %Oxygen meter by opening HA-V0706. Opening the valve during the VCT purge process released radioactive gas, which resulted in an unplanned, monitored release.

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 was one unplanned, monitored release in 2006.

No changes to events occurred on the land use census, monitoring instruments, radwaste shipments, and storage units.

5 of46 ATTACHMENTS Attachment I - AP 07B-003, revision 6, "Offsite Dose Calculation Manual'"

Attachment II -

AP 07B-004, revision 13, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Attachment III-AP 31A-1 00, revision 6, "Solid Radwaste Process Control Program"

6 of 46 SECTION I REPORT OF 2006 RADIOACTIVE EFFLUENTS: LIQUID Unit Quarter 1 Quarter 2 A.

Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 3.03E-04 5.44.E-04 alpha)
2.

Average Diluted Concentration During

ýLCi/ml 3.99E-12 2.55E-12 Period

3.

Percent of Applicable Limit (1) 6.05E-03 1.09E-02 B.

Tritium

1. Total Release Ci 1.99E+02 5.53E+02
2.

Average Diluted Concentration During pCi/ml 2.62E-06 2.59E-06 Period

3.

Percent of Applicable Limit (2).(ECL) 2.62E-01 2.59E-01.

C.

Dissolved and Entrained Gases

1. Total Release Ci 2.85E-04 1.86E-03
2.

Average Diluted Concentration During JACi/ml 3.76E-12 8.70E-12 Period

3.

Percent of Applicable Limit (3) 1.88E-06 4.35E-06 D.

Gross Alpha Radioactivity

1. Total Release Ci 5.68E-14 O.OOE+00 E.

Volume of Waste Released (prior to Liters 8.46E+07 1.21 E+08 dilution)

F.

Volume of Dilution Water Used Liters 7.58E+10 2.13E+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 21 OCFR20)

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 46 REPORT OF 2006 RADIOA A.

Fission and Activation Products

1. Total Release (not including tritium, gases, alpha
2.

Average Diluted Concentration During Period

3.

Percent of Applicable Limit (1)

B.

Tritium

1. Total Release
2.

Average Diluted Concentration During Period

3.

Percent of Applicable Limit (2) (ECL)

C.

Dissolved and Entrained Gases

1. Total Release
2.

Average Diluted Concentration During Period

3.

Percent of Applicable Limit (3)

D.

Gross Alpha Radioactivity

1. Total Release, E.

Volume of Waste Released (prior to dilution)

,CTIVE EFFLUENTS: LIQUID Unit Quarter 3 Ci 4.92E-04 pCi/ml 1.83E-12 9.84E-03 Ci pCi/ml Ci pCi/ml 4.42E+02 1.64E-06 1.64E-01.

6.68E-03 2.48E-1 1 1.24E-05 1.04E-05 8.62E+07 Quarter 4 8.64E-03 4,44E-11 1.73E-01 1.88E+02 9.65E-07 9.65E-02

9. 73E-03 5.OOE-1 1 2.50E-05 1.62E-05 8.41 E+07 Ci liters F.

Volume of Dilution Water Used liters 2.69E+11 1.94E+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) Thisvalue 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)

8 of 46 2006 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Released H-3 Ci 1.34E+00

.1.21E+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

<4.21E-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

<4.21E-02

<6.04E-02

<1.67E-04

<3.09E-04 Sr-89 Ci

<4.21E-03

<6.04E-03

<1.67E-05

<3.09E-05 Sr-90 Ci

<4.21E-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

<4.21E-02

<6.04E-02

<1.67E-04

<3.09E-04 Sb-124 Ci N/A N/A N/A N/A Sb-125 Ci N/A N/A 2.32E-04 3.88E-04 1-131 Ci

<8.42E-02

<1.21E-01

<3.34E-04

<6.19E-04 1-133 Ci N/A N/A N/A N/A Cs-134 Ci

<4.21E-02

<6.04E-02

<1.67E-04

<3.09E-04 Cs-136 Ci N/A N/A 1.18E-06 N/A Cs-137 Ci

<4.21E-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

<1.21E-02 5.68E-14

<6.19E-04 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-O1

<1.21E+00

<3.34E-03

<6.19E-03 Kr-87 Ci

<8.42E-01

<1.21 E+00

<3.34E-03

<6.19E-03 Kr-88 Ci

<8.42E-01

<1.21 E+00

<3.34E-03

<6.19E-03 Xe-131 M Ci

<8.42E-01

<1.21 E+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

<1.21E+00 2.85E-04 1.85E-03 Xe-135M Ci

<8.42E-01

<1.21E+00

<3.34E-03

<6.19E-03 Xe-135 Ci

<8.42E-01

<1.21E+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.

9 of 46 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 2.51E-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

<3.21E-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

<3.21E-05

<4.99E-05 Sr-90 Ci

<4.28E-03

<4.16E-03

<3.21E-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 3.21E-06 Sb-125 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-134 Ci

<4.28E-02

<4.16E-02

<3.21E-04

<4.99E-04 Cs-1 36 Ci N/A N/A 7.53E-07 N/A Cs-137 Ci

<4.28E-02

<4.16E-02 2.11E-05 3.21E-05 Ce-141 Ci

<4.28E-02

<4.16E-02

<3.21E-04

<4.99E-04 Ce-144 Ci

<4.28E-02

<4.16E-02

<3.21E-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 1.04E-05 1.62E-05 Ar-41 Ci

<8.56E-01

<8.31E-01

<6.43E-03 3.93E-06 Kr-85M Ci

<8.56E-01

<8.31E-01

.<6.43E-03 1.72E-05 Kr-85 Ci

<8.56E-01

<8.31E-01

<6.43E-03

<9.97E-03 Kr-87 Ci

<8.56E-01

<8.31E-01

<6.43E-03

<9.97E-03 Kr-88 Ci

<8.56E-01

<8.31E-01

<6.43E-03

<9.97E-03 Xe-131M Ci

<8.56E-01

<8.31E-01

<6.43E-03

<9.97E-03 Xe-133M Ci

<8.56E-01

<8.31E-01 7.27E-05 2.OOE-04 Xe-1 33 Ci

<8.56E-01

<8.31E-01 6.54E-03 8.31 E-03 Xe-1 35M Ci

<856E-01

<8.31E-01

<6.43E-03

<9.97E-03 Xe-1 35 Ci

<8.56E-01

<8.31E-01 3.77E-05 1.21 E-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.

10 of 46 LIQUID CUMULATIVE DOSE

SUMMARY

(2006) TABLE 1 QUARTER 1 OF 2006 (mrem)

ODCM CALCULATED ODCM LIMIT(l)

% OF LIMIT DOSE TOTAL DOSE FOR BONE 7.50E-05 5.00E+00 1.50E-03 TOTAL DOSE FOR LIVER 2.29E-02 5.OOE+00 4.58E-01 TOTAL DOSE FOR TOTAL BODY 2.29E-02 1.50E+00 1.52E+00 TOTAL-DOSE FOR THYROID 2.28E-02 5.00E+00 4.56E-01 TOTAL DOSE FOR KIDNEY 2.28E-02 5.OOE+00 4.56E-01 TOTAL DOSE FOR LUNG 2.28E-02 5.00E+00 4.56E-01 TOTAL DOSE FOR GI-LLI 2.28E-02 5.OOE+00

  • 4.56E-01 QUARTER 2 OF 2006 (mrem)

TOTAL DOSE FOR BONE 6.25E-05 5.00E+00 1.25E-03 TOTAL DOSE FOR LIVER 4.38E-02 5*00E+00 8.77E-01 TOTAL DOSE FOR TOTAL BODY 4.38E-02 1.50E+00 2.92E+00 TOTAL DOSE FOR THYROID 4.38E-02 5.OOE+00 8.75E-01 TOTAL DOSE FOR KIDNEY 4.38E-02 5.00E+00 8.76E-01 TOTAL DOSE FOR LUNG 4.38E-02 5.00E+00 8.75E-01 TOTAL DOSE FOR GI-LLI 4.38E-02 5.OOE+00 8.76E-01 QUARTER 3 OF 2006 (mrem)

TOTAL DOSE FOR BONE 6.89E-05 5.OOE+00 1.38E-03 TOTAL DOSE FOR LIVER 3.57E-02 5.00E+00 7.13E-01 TOTAL DOSE FOR TOTAL BODY 3.56E-02 1.50E+00 2.37E+00 TOTAL DOSE FOR THYROID 3.56E-02 5.00E+00 7.11E-01 TOTAL DOSE FOR KIDNEY 3.56E-02 5.00E+00 7.12E-01 TOTAL DOSE FOR LUNG 3.56E-02 5.00E+00 7.11E-01 TOTAL DOSE FOR GI-LLI 3.56E-02 5.OOE+00 7.11E-01 QUARTER 4 OF 2006 (mrem)

TOTAL DOSE FOR BONE 1.84E-04 5.OOE+00 3.69E-03 TOTAL DOSE FOR LIVER 4.68E-02 5.OOE+00 9.35E-01 TOTAL DOSE FOR TOTAL BODY 4.67E-02 1.50E+00 3.11E+00 TOTAL DOSE FOR THYROID 4.65E-02 5.OOE+00 9.30E-01 TOTAL DOSE FOR KIDNEY 4.66E-02 5.OOE+00 9.31 E-01 TOTAL DOSE FOR LUNG 4.65E-02 5.OOE+00 9.30E-01 TOTAL DOSE FOR GI-LLI 4.68E-02 5.OOE+00 9.37E-01 TOTALS FOR 2006 (mrem)

TOTAL DOSE FOR BONE 3.91 E-04 1.OOE+01 3.91 E-03 TOTAL DOSE FOR LIVER 1.49E-01 1.OOE+01 1.49E+00 TOTAL DOSE FOR TOTAL BODY 1.49E-01 3.OOE+00 4.97E+00 TOTAL DOSE FOR THYROID 1.49E-01 1.OOE+01 1.49E+00 TOTAL DOSE FOR KIDNEY 1.49E-01 1.OOE+01 1.49E+00 TOTAL DOSE FOR LUNG 1.49E-01 1.OOE+01 1.49E+00 TOTAL DOSE FOR GI-LLI 1.49E-01 1.OOE+01 1.49E+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.

11 of 46 LIQUID CUMULATIVE DOSE

SUMMARY

(2006) 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) 3.03E-04 5.44E-04 4.92E-04 8.64E-03 9.98E-03

2.

Maximum Organ Dose (mRem) 1.03E-04 8.55E-05 9.46E-05 3.41 E-04 5.49E-04

3.

Organ Dose Limit (mRem) 5.OOE+00 5.O0E+00 5.O0E+00 5.OOE+00 1.OOE+01

4.

Percent of Limit

.2.07E-03 1.71 E-03 1.89E-03 6.82E-03 5.49E-03 B.

Tritium

1.

Total Release - (Ci) 1.99E+02 5.53E+02 4.41E+02 1.88E+02 1.38E+03

2.

Maximum Organ Dose (mRem) 2.28E-02 4.38E-02 3.56E-02 4.65E-02 1.49E-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 4.56E-01 8.75E-01 7.11E-01 9.30E-01 1.49E+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.

12 of 46 REPORT OF 2006 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 1

2 A. Fission and Activation Gases

1. Total Release Ci 3.01E-01 2.36E-01
2. Average Release Rate for Period pCi/sec 3.86E-02 3.OOE-02
3. Percent of ODCM Limit (1) 3.90E-03' 3.OOE-03 B. Iodine
1. Total Release Ci 0.OOE+00 0.OOE+00
2. Average Release Rate for Period pCi/sec 0.OOE+00 0.OOE+00
3. Percent of Applicable Limit (2)

O.OOE+00 0.OOE+00 C. Particulates

1. Particulates with Half-lives > 8 days Ci 0.OOE+00 0.O0E+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 O.OOE+00 D. Tritium
1. Total Release Ci 1.20E+01 1.56E+01
2. Average Release Rate for Period pCi/sec 1.55E+00 1.98E+00
3. Percent of ODCM Limit (4) 1.17E-01 1.49E-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 -1 31)(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:

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

13 of 46 REPORT OF 2006 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 3

ý4 A. Fission and Activation Gases

1. Total Release Ci 1.28E+00 2.47E-01
2. Average Release Rate for Period

[tCi/sec 1.61 E-01 3.11E-02

3. Percent of ODCM Limit (1) 5.70E-03 3.21E-03 B. lodines
1. Total Iodine-131 Ci 0.00E+00 O.OOE+00
2. Average Release Rate for Period

[tCi/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 0.00E+00
2. Average Release Rate for Period 1iCiisec O.OOE+00 O.OOE+00
3. Percent of ODCM Limit (3)

O.OOE+00 O.OOE+00

4. Gross Alpha Radioactivity Ci 0.OOE+00 O.OOE+00 D. Tritium
1. Total Release Ci 1.41E+01 1.17E+01
2. Average Release Rate for Period ptCi/sec 1.77E+00 1.47E+00
3. Percent of ODCM Limit (4) 1.29E-01 1.08E-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)

(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:

(Total Curies of Iodine -131)(100)

% of ODCM Limit =

I 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 rather than 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

14 of 46 2006 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1.

Fission and Activiation Gases Ar-41 Ci N/A N/A 3.01E-01 2.28E-01 Kr-85 Ci N/A N/A N/A 1.13E-03 Kr-85M Ci N/A N/A N/A 1.45E-04 Kr-87 Ci

<1.50E+01

<1.53E+01

<1.88E-02 3.45E-04 Kr-88 Ci

<1.11E+01

<1.14E+01

<1.40E-02 3.70E-04 Xe-131 M Ci N/A N/A N/A N/A Xe-133 Ci

<1.41 E+01

<1.45E+01

<1.77E-02 1.55E-03 Xe-133M Ci

<3.25E+01

<3.32E+01

<4.08E-02

<3.18E-02 Xe-135 Ci

<2.31E+00

<2.37E+00

<2.90E-03 1.52E-03 Xe-135M Ci N/A N/A N/A 6.41 E-04 Xe-138 Ci

<3.63E+02

<3.72E+02

<4.56E-01 1.63E-03 Total Ci 0.OOE+00 O.OOE+00 3.01E-01 2.35E-01

2.

Halogens (Gaseous) 1-131 Ci

<2.57E-04

<2.63E-04

<3.23E-07

<2.52E-07 1-133 Ci

<2.57E-02

<2.63E-02

<3.23E-05

<2.52E-05 Total Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

3.

Particulates and Tritium H-3 Ci 1.15E+01 1.48E+01 5.48E-01 7.55E-01 Mn-54 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Fe-59 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Co-58 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Co-60 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Zn-65 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Mo-99 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Cs-1 34 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Cs-1 37 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Ce-141 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Ce-144 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Sr-89 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Sr-90 Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Gross Alpha Ci

<2.57E-03

<2.63E-03

<3.23E-06

<2.52E-06 Total Ci 1.15E+01 1.48E+01 5.48E-01 7.55E-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 46 2006 GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter 3 Quarter 4 Nuclides Released

1.

Fission and Activiation Gases Ar-41 Kr-85 Kr-85M Kr-87 Kr-88 Xe-131M Xe-1 33 Xe-1 33M Xe-1 35 Xe-1 35M Xe-138 Total

2.

Halogens (Gaseous) 1-131 1-133 Total

3.

Particulates and Tritium H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144.

Sr-89 Sr-90 Gross Alpha Total Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 3 N/A N/A N/A

<1.56E+01

<1.16E+01 N/A 6.41E-01

<3.38E+01 2.16E-01 N/A

<3.78E+02 8.57E-01

<2.68E-04

<2.68E-02 0.00E+00 1.28E+01

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03

<2.68E-03 1.28E+01 Quarter 4 N/A N/A N/A

<1.63E+01

<1.21E+01 N/A

<1.54E+01

<3.53E+01

<2.51 E+00 N/A

<3.95E+02 0.OOE+00

<2.79E-04

<2.79E-02 0.OOE+00 8.60E+00

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03

<2.79E-03 8.60E+00 3.67E-01 3.59E-02 7.31E-06

<1.92E-02

<1.42E-02 7.21 E-05 1.31 E-02 2.06E-04 6.07E-04 8.80E-03

<4.65E-01 4.26E-01

<3.29E-07

<3.29E-05 0.OOE+00 1.28E+00

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06

<3.29E-06 1.28E+00 2.47E-01 N/A N/A

<1.04E+00

<7.74E-01 N/A

<9.84E-01

<2.26E+00

<1.61E-01 N/A

<2.53E+01 2.47E-01

<1.79E-05

<1.79E-03 0.OOE+00 3.11 E+00

<1.79E-04

<1.79E-04

<1.79E-04

<1.79E-04

<1.79E-04

<1.79E-04

<11.79E-04

<1.79E-04

<1.79E-04

<1 *79E-04

<1.79E-04

<1.79E-04

<1.79E-04 3.11 E+00 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.

16 of 46 GASEOUS CUMULATIVE DOSE

SUMMARY

(2006) TABLE 1 QUARTER 1 OF 2006 (mRem)

TOTAL DOSE TOTAL DOSE TOTAL DOSE TOTAL DOSE TOTAL DOSE TOTAL DOSE TOTAL DOSE FOR BONE FOR LIVER FOR TOTAL BODY FOR THYROID FOR KIDNEY FOR LUNG FOR GI-LLI ODCM CALCULATED DOSE 0.OOE+00 8.51 E-03 8.51 E-03 8.51 E-03 8.51 E-03 8.51 E-03 8.51 E-03 ODCM LIMIT (1) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 QUARTER 2 OF 2006 (mRem)

TOTAL DOSE FOR BONE TOTAL DOSE FOR LIVER TOTAL DOSE FOR TOTAL BODY TOTAL DOSE FOR THYROID TOTAL DOSE FOR KIDNEY TOTAL DOSE FOR LUNG TOTAL DOSE FOR GI-LLI QUARTER 3 OF 2006 (mRem)

TOTAL DOSE FOR BONE TOTAL DOSE FOR LIVER TOTAL DOSE FOR TOTAL BODY TOTAL DOSE FOR THYROID TOTAL DOSE FOR KIDNEY TOTAL DOSE FOR LUNG TOTAL DOSE FOR GI-LLI QUARTER 4 OF 2006 (mRem)

TOTAL DOSE FOR BONE TOTAL DOSE FOR LIVER TOTAL DOSE FOR TOTAL BODY TOTAL DOSE FOR THYROID TOTAL DOSE FOR KIDNEY TOTAL DOSE FOR LUNG TOTAL DOSE FOR GI-LLI TOTALS FOR 2006 (mRem)

TOTAL DOSE FOR BONE TOTAL DOSE FOR LIVER TOTAL DOSE FOR TOTAL BODY TOTAL DOSE FOR THYROID TOTAL DOSE FOR KIDNEY TOTAL DOSE FOR LUNG TOTAL DOSE FOR GI-LLI O.OOE+00 1.10E-02 1.10E-02 1.1OE-02 1.1OE-02 1.10E-02 1.1OE-02 O.OOE+00 9.95E-03 9.95E-03 9.95E-03 9.95E-03 9.95E-03 9.95E-03 O.OOE+00 8.28E-03 8.28E-03 8.28E-03 8.28E-03 8.28E-03 8.28E-03 O.OOE+00 3.77E-02 3.77E-02 3.77E-02 3.77E-02 3.77E-02 3.77E-02 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01

% OF LIMIT 0.OOE+00

1. 13E-01 1.13E-01 1.13E-01 1.13E-01 1.13E-01 1.13E-01 0.OOE+00 1.47E-01 1.47E-01 1.47E-01 1.47E-01 1.47E-01 1.47E-01 0.OOE+00 1.33E-01
  • 1.33E-01 1.33E-01 1.33E-01 1.33E-01 1.33E-01 0.OOE+00 1.10E-01 1.10E-01 1.10E-01 1.10E-01 1.10E-01 1.10E-01 0.OOE+00 2.52E-01 2.52E-01 2.52E-01 2.52E-01 2.52E-01 2.52E-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.

17 of 46 GASEOUS CUMULATIVE DOSE

SUMMARY

(2006) TABLE 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A.

Fission and Activation Gases

1.

Total Release - (Ci) 3.01E-01 2.36E-01 1.28E+00 2.47E-01 2.07E+00

2.

Total Gamma Airdose (mRad) 1.95E-04 1.50E-04 2.85E-04 1.60E-04 7.91 E-04

3.

Gamma Airdose Limit (mRad) 5.OOE+00 5.OOE+00 5.00E+00 5.OOE+00 1.OOE+01

4.

Percent of Gamma Airdose Limit 3.90E-03 3.OOE-03 5.70E-03 3.21 E-03 7.91 E-03

5.

Total Beta Airdose (mRad) 6.88E-05 5.37E-05 1.74E-04 5.66E-05 3.53E-04

6.

Beta Airdose Limit (mRad) 1.OOE+01 1.OOE+01 1.OOE+01 1.OOE+01 2.OOE+01

7.

Percent of Beta Airdose 6.88E-04 5.37E-04 1.74E-03 5.66E-04 1.77E-03 Limit (mRad)

B.

Particulates

1.

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

2.

Maximum Organ Dose (mRem) 0.o0E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00

3.

Organ Dose Limit (mRem) 0.OOE+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

4.

Percent of Limit 0.OOE+00 0.o0E+00 0.OOE+00 0.OOE+00 0.OOE+00 C.

Tritium

1.

Total Release (Ci) 1.20E+01 1.56E+01 1.41E+01 1.17E+01 5.34E+01

2.

Maximum Organ Dose (mRem) 8.77E-03 1.12E-02 9.71 E-03 8.09E-03 3.77E-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 1.17E-01 1.49E-01 1.29E-01 1.08E-01 2.52E-01 D.

Iodine

1.

Total 1-131, 1-133 (Ci) 0.OOE+00 O.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00

2.

Maximum Organ Dose (mRem) 0.OOE+00 O.OOE+00 0.OOE+00 0.O0E+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 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.

18 of 46 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 gaases. 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 Iodine-131, 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 lodine-131, 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.

19 of 46

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 M = monthly L. S. =Liquid scintillation detector S.A.C. = scintillation alpha counter O.S.L. = performed by an offsite laboratory P.H.A. = gamma spectrum pulse height analysis using a High Purity Germanium detector

20 of 46 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 M = monthly L.S. = Liquid scintillation detector S.A.C. = scintillation alpha counter O.S.L. = performed by an offsite laboratory P.H.A. - gamma spectrum pulse height analysis using a High Purity Germanium detector

21 of 46

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 68 gaseous batch releases during the reporting period. The longest gaseous batch release lasted 9399 minutes, while the shortest lasted 29 minutes. The average release lasted 682 minutes with a total gaseous batch release time of 48,501 minutes.

There were 50 liquid batch releases during the reporting period. The longest liquid batch release lasted 316 minutes, while the shortest lasted 65 minutes. The average release lasted 146 minutes with a total liquid batch release time of 7,069 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 4.07E-01 mRem William Allen White Building Workers 8.98E-03 mRem Access Road Users 4.17E-03 mRem Lake Use 5.45E-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 3756 hours0.0435 days <br />1.043 hours <br />0.00621 weeks <br />0.00143 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 313 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.

22 of 46

8. Additional Information CR 2006-000398 - While purging the Volume Control Tank (VCT) to Gas Decay Tank (GDT) #2, a Treatment Systems Operator (TSO) noticed water in the %Oxygen bypass flow meter on the 'A' Gas Analyzer Rack. The presence of water was interfering with waste gas operations. The VCT purge tripped due to excessive 02 in the recombiner outlet, but the waste gas compressor continued recirculating the contents of GDT #2. An attempt was made by the TSO to remove the water in-the %Oxygen meter by opening HA-V0706, 'A' Recombiner H2/O2 Analyzer Rad H20 drain. Opening HA-V0706 during the VCT purge process released radioactive gas, which resulted in an unplanned, monitored release of noble gases from the Radwaste Building Vent. No ODCM limits were exceeded. An estimated 7.44E-03 curies were released. This estimate was corrected for the Radwaste Vent flow rate and the amount of time the associated RM-1 1 readings remained elevated.

23 of 46 2006 EFFLUENT CONCENTRATION LIMITS Nuclides H-3 Cr-51 Mn-54 Mn-56 Co-57 Fe-59 Co-60 Sb-124 Sb-125 1-131 1-133 1-135 Ce-141 Cs-134 Cs-1 36 Cs-1 37 Nb-97 Ba-139 Rb-88 Sn-1 17M Sb-122 Sb-126 Na-24 Nb-95 Tc-99M Sr-91 Zn-65 W-187 Ar-41 Kr-85 Kr-85M Kr-88 Xe-131M Xe-133M Xe-133 Xe-135 Xe-138 Curies 1.38E+03 N/A 1.89E-05 N/A 1.09E-05 1.07E-05 3.20E-04 3.21 E-06 1.80E-03 N/A N/A N/A N/A N/A 1.93E-06 8.86E-05 N/A N/A 7.34E-05 4.61E-06 N/A N/A N/A 6.47E-07 N/A 5.36E-06 N/A N/A 3.93E-06 N/A 1.72E-05 N/A N/A 2.81 E-04 1.70E-02 1.25E-03 3.14E-05 Averaqie Diluted Concentration (4Ci/ml) 1.83E-06 N/A 2.51E-14 N/A 1.45E-14 1.42E-14 4.25E-13 4.26E-15 2.39E-12 N/A N/A N/A N/A N/A 2.56E-1 5 1.18E-13 N/A N/A 9.75E-14 6.12E-15 N/A N/A N/A 8.59E-1 6 N/A 7.12E-15 N/A N/A 5.22E-1 5 N/A 2.28E-14 N/A N/A 3.73E-13 2.26E-1 1 1.66E-12 4.17E-14 10 CFR 20 ECL (jiCi/ml) 1.OOE-03 5.OOE-04 3.OOE-05 7.OOE-05 6.OOE-05 1.OOE-05 3.OOE-06 7.OOE-06 3.OOE-05 1.OOE-06 7.OOE-06 3.00E-05 3.OOE-05 9.OOE-07 6.OOE-06 1.OOE-06 3.OOE-04 2.OOE-04 4.OOE-04 1.OOE-08 1.OOE-05 7.OOE-06 5.OOE-05 3.OOE-05 1.OOE-03 2.OOE-05 5.OOE-06 3.OOE-05 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04

% of ECL 1.83E-01

. N/A 8.37E-08 N/A.

2.42E-08 1.42E-07 1.42E-05 6.09E-08 7.97E-06 N/A N/A N/A N/A N/A 4.27E-08 1.18E-05 N/A N/A 2.44E-08 6.12E-05 N/A N/A N/A 2.86E-09 N/A 3.56E-08 N/A N/A 2.6tE-09 N/A 1.14E-08 N/A N/A 1.86E-07 1.13E-05 8.30E-07 2.08E-08

24 of 46 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2006 SOLID WASTE SHIPMENTS A. SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste
a. Spent resins, filter sludges evaporator bottoms, etc.
b. Dry compressible waste, contaminated equip. etc.
c. Irradiated components, control rods, etc.
d. Other
  • m3 = cubic meters
    • This disposal.

Unit m3*

Ci m3*

Ci m3*

Ci m3*

Ci 1-Year Period 3.15E+02**

2.50E+02 3.08E+02**

1.42E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Est. Total Error %

2.50E+01 2.50E+01 2.50E+01 2.50E+01 is the volume sent offsite for volume reduction, prior to

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 Name Be-7 Fe-55 Ni-63 Co-58 Percent Abundance 10 41 16 13 Curies 2.51 E+01 1.03E+02 4.09E+01 3.13E+01

b. Dry compressible waste, contaminated equipment, etc.

Nuclide Name Percent Abundance 33 16 26 Fe-55 Ni-63 H-3 Curies 4.72E-01 2.26E-01 3.69E-01

25 of 46

c. Irradiated components, control rods, etc. - None
d. Other-None
3. Solid Waste Disposition Number of Shipments 1

4 3

11 Mode of Transportation Truck (Hittman Transport Services)

Truck (Hittman Transport Services)

Truck (Hittman Transport Services)

Triad Transport Destination Barnwell Waste Management Facility, Barnwell; SC Duratek; Kingston, TN Studsvik Processing Facility, LLC; Erwin, TN 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 2006 period.

26 of 46 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, 2006, through December 31, 2006, 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 91.59% meteorological data recovery for 2006.

27 of 46 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

JANUARY 1 THROUGH DECEMBER 31, 2006 STABILITY CLASS:

A ELEVATION:

10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

2.00 12.75 29.25 30.00 6.75 0.75 81.50 NNE 13.75 11.00 24.50 10.25 0.25 0.00 59.75 NE 0.25 10.75 13.25 5.50 0.00 0.00 29.75 ENE 1.00 29.00 9.75 0.00 0.00 0.00 39.75 E

0.00 17.25 24.25 2.50 0.25 0.00 44.25 ESE 0.25 14.75 34.25 2.50 0.00 0.00 51.75 SE 2.25 20.75 27.00 20.75 1.00 0.25 72.00 SSE 1.50 24.75 94.00 51.25 23.75 2.50 197.75 S

1.75 21.50 76.00 118.75 53.25 4.00 275.25 SSW 2.75 13.75 47.00 46.00 14.75 2.00 126.25 SW 2.75 17.00 37.50 12.25 0.00 0.00 69.50 WSW 2.00 21.25 20.75 4.00 0.75 0.00 48.75 W

4.00 26.50 30.50 13.00 6.00 0.75 80.75 WNW 2.50 20.25 29.75 18.25 6.00 0.75 77.50 NW 1.75 18.00 28.25 15.50 5.75 0.00 69.25 NNW 1.25 14.25 42.25 49.00 7.00 1.00 114.75 TOTAL 37.75 293.50 568.25 399.50 125.50 12.00 PERIOD OF CALM (HOURS): 1.50

28 of 46 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

JANUARY 1 THROUGH DECEMBER 31, 2006 STABILITY CLASS:

B ELEVATION:

WIND DIRECTION 10 METERS WIND SPEED (mph) 1-3 4-7 8-12 13-18 19-24

>24 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL 0.75 1.25 1.25 0.50 0.75 0.00 1.00 1.25 0.25 0.25 1.25 1.00 0.75 0.75 1.75 1.00 13.00 5.75 4.00 8.50 5.25 4.75 3.00 4.00 9.50 10.00 2.75 5.25 8.00 9.25 5.75 6.00 5.00 96.75 10.50 7.25 4.75 4.25 8.75 4.25 7.75 15.00 17.50 14.75 5.50 3.00 6.00 4.75 8.50 14.75 137.25 7.50 5.00 1.75 0.25 0.25 1.50 5.50 10.00 15.75 7.25 1.00 0.75 3.50 3.25 9.25 18.75 91.25 1.75 0.25 0.00 0.00 0.00 0.00 1.25.

4.00 6.25 6.50 0.00 0.50 1.75 3.00 4.75 8.25 38.25 0.75 0.00 0.00 0.00 0.00 0.00 0.50 1.25 0.25 1.75 0.00 0.00 0.75 1.50 0.00 0.00 6.75 TOTAL 27.00 17.75 16.25 10.25 14.50 8.75 20.00 41.00 50.00 33.25 13.00 13.25 22.00 19.00 30.25 47.75 384.00 PERIOD OF CALM (HOURS): 0

29 of 46 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

JANUARY 1 THROUGH DECEMBER 31, 2006 STABILITY CLASS:

C ELEVATION:

10 METERS WIND SPEED (mph)

WIND DIRECTION N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL 1-3 1.00 0.75 2.50 0.00 0.50 0.50 0.00 1.25 1.50 0.25 1.25 0.75 1.00 0.75 1.50 0.50 13.00 4-7 5.75 5.75 148.75 8.50 6.50 6.00 5.25 8.00

  • 9.50 3.75 3.75 10.00 6.25 5.75 7.50 4.75 245.75 8-12 13-18 19-24

>24 14.00 11.00 2.75 3.75 6.00 6.75 4.25 15.50 15.50 10.75 2.75 4.75 5.75 3.75 10.75 12.50 130.50 9.00 8.50 1.25 0.75 3.00 2.75 6.00 12.50 15.50 7.75 1.75 1.50 3.75 3.00 8.00 15.25 100.25 1.75 0.50 0.25 0.00 1.00 0.75 0.25 4.50 4.75 7.00 0.00 0.25 0.75 2.25 3.75 7.75 35.50 0.50 0.00 0.00 0.00 0.50 0.75 0.50 1.00 0.25 2.75 0.00 0.00 0.75 0.50 1.00 0.50 9.00 TOTAL 32.00 26.50 155.50 13.00 17.50 17.50 16.25 42.75 47.00 32.25 9.50 17.25 18.25 16.00 32.50 41.25 535.00 PERIOD OF CALM (HOURS): 0

30 of46 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

JANUARY 1 THROUGH DECEMBER 31, 2006 STABILITY CLASS:

D ELEVATION:

10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL 4.00 6.50 18.00 13.25 12.75 6.25 4.00 4.75 5.25 3.50 6.50 3.00 3.00 3.00 3.00 5.50 98.25 4-7 23.50 34.75 37.25 36.75 31.50 31.25 32.25 28.75 23.00 19.50 34.00 16.00 18.75 16.00 20.25 29.50 433.00 8-12 13-18 19-24

>24 63.25 70.00 33.25 25.00 43.00 29.25 33.50 95.75 86.50 59.50 16.50 16.75 28.00 43.75 72.00 92.25 808.25 81.25 51.00 12.75 4.25 29.00 25.50 15.25 90.50 88.00 41.00 7.25 7.50 14.00 30.75 43.25 83.25 624.50 43.50 11.00 0.25 0.25 7.75 2.25 5.25 32.75 26.50

.20.00 0.75 0.50 2.25 5.25 22.00 39.00 219.25 8.75 1.00 0.00 0.25 2.25 0.75 2.50 9.50 2.50 3.00 0.00 0.00 1.75 1.50 4.50 3.25 41.50 TOTAL 224.25 174.25 101.50 79.75 126.25 95.25 92.75 262.00 231.75 146.50 65.00 43.75 67.75 100.25 165.00 252.75 2228.75 PERIOD OF CALM (HOURS): 1.25

31 of 46 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

JANUARY 1 THROUGH DECEMBER 31, 2006 STABILITY CLASS:

ELEVATION:

WIND DIRECTION 1-3 E

10 METERS WIND SPEED (mph)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL 7.25 8.25 14.25 16.50 9.25 8.00 6.25 10.00 4.75 4.00 6.50 2.25 3.25 4.25 3.00 3.75 104.25 4-7 32.25 27.25 14.00 42.00 37.00 39.25 52.25 92.00 35.00 27.00 46.00 20.00 20.00 27.00 44.50 39.00 594.50 8-12 13-18 19-24

>24 39.25 21.00 11.25 13.50 32.25 49.25 78.50 341.75 152.50 78.25 22.50 14.00 15.00 16.75 56.25 62.00 1004.00 14.75 5.50 0.25 0.50 13.25 4.75 17.50 250.50 144.50 28.25 1.00 4.00 5.00 3.00 12.75 21.00 526.50 1.25 0.00 0.00 0.00 0.50 1.50 4.00 20.25 30.75 4.00 0.00 2.50 0.25 0.00 0.00 0.75 65.75 0.00 0.00 0.00 0.00 0.00 1.25 1.50 4.50 6.00 0.50 0.00 1.00 1.50 0.00 0.00 0.00 16.25 TOTAL 94.75 62.00 39.75 72.50 92.25 104.00 160..00 719.00 373.50 142.00 76.00 43.75 45.00 51.00 116.50 126.50 2318.50 PERIOD OF CALM (HOURS): 1.25

32 of 46 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

JANUARY 1 THROUGH DECEMBER 31, 2006 STABILITY CLASS:

F ELEVATION:

10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

5.75 40.25 16.00 0.00 0.00 0.00 62.00 NNE 8.00 49.25 19.25 0.00 0.00 0..00 76.50 NE 16.25 23.25 1.00 0.00 0.00 0.00 40.50 ENE 10.00 50.00 3.25 0.00 0.00 0.00 63.25 E

11.00 55.00 4.25 0.00 0.00 0.00 70.25 ESE 6.75 56.50 10.25 0.00 0.00 0.00 73.50 SE 5.75 75.00 21.00 0.00 0.00.

0.00 101.75 S'SE 4.50 39.50 66.00 10.00 0.00 0.00 120.00 5

3.50 22.75 48.00 18.75 0.25 0.00 93.25 SSW 3.00 15.25 23.75 4.75 0.25 0.00 47.00 SW 8.75 21.25 1.75 0.25 0.00 0.00 32.00 WSW 6.75 11.50 2.00 0.00 0.25 0.0 20.50 W

5.00 8.50 2.50 1.25 0.00 0.00 17.25 WNW 6.25 15.00 2.25 0.00 0.00 0.00 23.50 NW 9.25 40.50 13.50 0.00 0.00 0.00 63.25 NNW 8.00 48.50 12.75 0.50 0.00 0.00 69.75 TOTAL 112.75 572.00 247.50 35.50 0.75 0.00 974.25 PERIOD OF CALM (HOURS): 1.75

33 of 46 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

JANUARY 1 THROUGH DECEMBER 31, 2006 STABILITY CLASS:

G ELEVATION:

10 METERS WIND DIRECTION N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL WIND SPEED (mph) 8-12 13-18 19-24 1-3 7.25 8.50 13.50 6.50 9.75 6.75 5.50 2.50 2.00 2.75 4.50 5.25 4.00 7.75 9.50 9.75 98.50 4-7 35.00 58.25 38.75 30.50 44.00 46.75 41.50 30.00 23.50 7.00 8.00 1.75 2.00 3.00 20.00 31.50 421.50

>24 TOTAL 1.25 7.00 0.75 1.00 3.50 1.25 3.25 9.50 12.50 5.25 0.50 0.00 1.00 0.75 1.00 3.25 51.75 0.75 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.50 0.00 0.00 0.75 0.00 0.00 0.50 2.50 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.25 0.00 0.00 0.00 0.00 0.00 0.00 0.25 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 44.25 7.3.75 53.00 38.00 57.25 54.75 50.25 42.00 38.00 15.75 13.00 7.00 7.75 11.50 30.50 45.00 581.75 PERIOD OF CALM (HOURS): 1.25

34 of 46 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

JANUARY 1 THROUGH DECEMBER 31, 2006 STABILITY CLASS:

ALL ELEVATION:

10 METERS WIND.

DIRECTION N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL WIND SPEED 8-12 13-18 (mph) 1-3 28.00 47.00 66.00 47.75 44.00 28.50 24.75 25.75 19.00 16.50 31.50 21.00 21.00 25.25 29.75 29.75 505.50 4-7 155.25 190.25 281.25 202.00 196.00 197.50 231.00 232.50 145.25 89.00 135.25 88.50 91.25 92.75 156.75 172.50 2657.00 173.50 160.00 67.00 60.50 122.00 135.25 175.25 637.50 408.50 239.25 87.00 61.25 88.75 101.75 190.25 239.75 2947.50 143.25 80.25 21.50 5.75 48.00 37.00 65.00 424.75 401.25 135.50 23.50 17.75 41.25 58.25 88.75 188.25 1780.00 19-24 55.00 12.00 0.50 0.25 9.50 4.50 11.75 85.25 121.75 52.75 0.75 4.75 11.00 16.50 36.25 62.75 485.25

>24

. TOTAL 10.75 1.00 0.00 0.25 2.75 2.75 5.25 18.75 13.00 10.00 0.00 1.00 5.50 4.25 5.50 4.75 85.50 565.75 490.50 436.25 316.50 422.25 405.50 513.00 1424.50 1108.75 543.00 278.00 194.25 258.75 298.75 507.25 697.75 8460.75 PERIOD OF CALM (HOURS): 7

35 of 46 SECTION IV ADDITIONAL INFORMATION

1. Unplanned or Abnormal Releases One unplanned, monitored release occurred in 2006. 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 13, is included with this report as Attachment II.

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 partially completed in 2006. One train of the new Hydrogen and Oxygen Analyzer Rack was installed in September.

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.

4. Land Use Census No new locations for dose calculation were identified during this report period.
5. Radwaste Shipments Nineteen 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 2006 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."

36 of 46

8.

NEI Groundwater Protection Industry Initiative See attached 9 pages

37 of 46 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 A] 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. During 2006, three other locations-were sampled once:

ESW-E-NW, LSP and OW-002. 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 ESW-E-NW Essential Service Water Dewatering Well, East Group, Northwest, located southeast of the reactor LSP Lime Sludge Pond, located northeast of the reactor OW-002 Oily Waste Outfall 002, located south of the reactor 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

38 of 46 Reporting Levels for Radioactivity Detected in Onsite Groundwater Analysis (pCi/I)

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 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 OW-002 (2,280 +/- 152 pCi/L). The measured level is significantly lower than the tritium levels routinely detected in surface water collected from Coffey County Lake (2006 range was 8,624 to 14,267 pCi/L). The location with the lowest level of tritium detected was location ESW-E-NW (197 +/- 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 H-3 Results 2000 1800.

1600 1400 1200 1000 800 600 40O0 200 0

Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 ESW-W-NE ESW-W-v N

A-AUX

39 of 46 EXPOSURE PATHWAY - WATERBORNE GROUND WATER LOCATION AUX Collection Date Nuclide Concentration (pCi/L) 28-MAR-06 MN-54

< 2.400 CO-58

< 2.400 FE-59

< 3.600 CO-60

< 2.200 ZN-65

-.< 3.400 ZR-NB-95

< 2.600 CS-134

< 1.900 CS-137

<2.400 BA-LA-140

<2.100 H-3 1687.000 +/- 136.000 1-131 (CHEM)

<0.310 10-MAY-06 MN-54

< 4.000 CO-58

<4.300 FE-59

< 7.800 CO-60

< 5.400 ZN-65

< 4.300 ZR-NB-95

< 3.000 CS-134

<4.500 CS-137

<4.200 BA-LA-140

< 5.700 H-3 532.000+/- 94.000 1-131 (CHEM)

< 0.339 30-AUG-06 MN-54

< 1.300 CO-58

<2.100 FE-59

< 5.100 CO-60

< 1.400 ZN-65

< 3.500 ZR-NB-95

< 1.800 CS-134

<2.800 CS-137

<2.600 BA-LA-140

< 3.200 H-3 831.000+/- 106.000 1-131 (CHEM)

<0.338 16-NOV-06 MN-54

< 2.100 CO-58

< 2.600 FE-59

< 4.100 CO-60

< 3.500 ZN-65

< 3.700 ZR-NB-95

< 2.500 CS-134

< 2.800 CS-137

< 3.000 BA-LA-140

< 2.500 H-3 768.000+/- 116.000 1-131 (CHEM)

< 0.446

40 of 46 EXPOSURE PATHWAY - WATERBORNE GROUND WATER LOCATION ESW-E-NW Collection Date Nuclide Concentration (pCi/L) 11-AUG-06 MN-54

< 3.700 CO-58

< 3.600 FE-59

< 6.400 CO-60

< 6.300 ZN-65

< 16.800 ZR-NB-95

< 5.700 1-131

<0.216 CS-134

< 6.400 CS-137

< 7.900 BA-LA-140

< 9.500 H-3 197.000+/- 87.000

41 of 46 EXPOSURE PATHWAY - WATERBORNE GROUND WATER LOCATION ESW-W-NE Collection Date Nuclide Concentration (pCi/L).

28-MAR-06 MN-54

< 3.000 CO-58

< 3.600 FE-59

< 4.600 CO-60

< 3.900 ZN-65

<5.400 ZR-NB-95

< 4.300 CS-134

< 3.300 CS-137

<2.500 BA-LA-140

< 3.000 H-3 1649.000+/- 135.000 1-131 (CHEM)

< 0.270 10-MAY-06 MN-54

< 3.600 MN-54-DUPLICATE

< 3.200 CO-58

<3.000 CO-58-DUPLICATE

< 3.000 FE-59

< 3.600 FE-59-DUPLICATE

< 5.100 CO-60

< 4.500 CO-60 DUPLICATE

< 1.500 ZN-65

< 3.200 ZN-65-DUPLICATE

< 4.800 ZR-NB-95

< 2.000 ZR-NB-95-DUPLICATE

< 4.100 CS-134

< 2.700 CS-134-DUPLICATE

< 4.000 CS-137

<2.800 CS-137-DUPLICATE

< 3.100 BA-LA-140

< 3.400 BA-LA-140-DUPLICATE

< 3.100 H-3 1339.000+/- 119.000 H-3-DUPLICATE 1463.000+/- 122.000 1-131 (CHEM)

< 0.480 1-131 (CHEM)-DUPLICATE

< 0.433 30-AUG-06 MN-54

< 4.700 CO-58

< 5.000 FE-59

< 9.000 CO-60

< 3.300 ZN-65

< 3.100 ZR-NB-95

< 7.400 CS-134

< 3.700 CS-137

< 3.800 BA-LA-140

< 6.700 H-3 1823.000+/- 136.000 1-131 (CHEM)

< 0.404

42 of 46 EXPOSURE PATHWAY - WATERBORNE GROUND WATER LOCATION ESW-W-NE (Cont'd)

Collection Date Nuclide Concentration (pCi/L) 16-NOV-06 MN-54

< 2.100 CO-58

< 3.500 FE-59

< 3.900 CO-60

< 2.600 ZN-65

< 3.900 ZR-NB-95

< 3.500 CS-134

<3.300 CS-137

<3.100 BA-LA-140

< 4.600 H-3 1542.000+/- 139.000 1-131 (CHEM)

< 0.520

43 of 46 EXPOSURE PATHWAY - WATERBORNE GROUND WATER LOCATION ESW-W-NW Collection Date Nuclide Concentration (pCi/L) 28-MAR-06 MN-54

< 7.100 CO-58

< 5.000 FE-59

< 11.400 CO-60

< 5.700, ZN-65

< 13.900 ZR-NB-95

< 6.100 CS-134

<6.800 CS-137

<3.100 BA-LA-140

< 8.200 H-3 1458.000+/- 130.000 1-131 (CHEM)

< 0.326 10-MAY-06 MN-54

< 4.000 CO-58

< 3.500 FE-59

< 9.700 CO-60

< 4.500 ZN-65

< 8.200 ZR-NB-95

< 5.100 CS-134

< 2.200 CS-137

< 3.500 BA-LA-140

< 4.600 H-3 256.000+/- 84.000 1-131 (CHEM)

< 0.296 30-AUG-06 MN-54

< 5.100 CO-58

<4.800 FE-59

< 9.500 CO-60

< 5.400 ZN-65

< 9.100 ZR-NB-95

< 5.100 CS-134

<4.100 CS-137

<4.500 BA-LA-140

< 3.700 H-3 1527.000+/- 128.000 1-131 (CHEM)

< 0.401 16-NOV-06 MN-54

< 3.500 CO-58

< 3.600 FE-59

< 5.900 CO-60

< 2.500 ZN-65

< 3.500 ZR-NB-95

< 3.500 CS-134

< 3.800 CS-137

< 3.900 BA-LA-140

< 2.900 H-3 1309.000+/- 132.000 1-131 (CHEM)

< 0.341

44 of 46 EXPOSURE PATHWAY - WATERBORNE GROUND WATER LOCATION LSP Collection Date Nuclide Concentration (pCi/L) 11 -AUG-06 MN-54

< 3.600 CO-58

< 4.200 FE-59

< 9.600 CO-60

< 4.000 ZN-65

< 6.500 ZR-NB-95

< 4.200 1-131

< 0.262 CS-134

< 6.000 CS-137

< 4.400 BA-LA-140

< 4.800 H-3 632.000+/- 104.000

45 of 46 EXPOSURE PATHWAY - WATERBORNE GROUND WATER LOCATION OW-002 Collection Date Nuclide Concentration (pCi/L) 11-AUG-06 MN-54

< 4.500 CO-58

< 4.100 FE-59

< 3.000 CO-60

< 4.700 ZN-65

<3.200 ZR-NB-95

< 4.400 1-131

<0.218 CS-134

< 5.900 CS-137

<4.000 BA-LA-140

< 2.800 H-3 2280.000+/- 152.000

46 of 46 ATTACHMENTS TO WCGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -

REPORT 30 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)".

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

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

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