ML051240339

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Annual Radioactive Effluent Release Report, Report 28, 01/01/2004 Through 12/31/2004
ML051240339
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/31/2004
From:
Wolf Creek
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051240339 (40)
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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. 28 Reporting Period: January 1, 2004 - December 31, 2004

2 of 40 Table of Contents Page Executive Summary 4 Section I 8 Report of 2004 Radioactive Effluents: Liquid 8 2004 Liquid Effluents 10 2004 Liquid Cumulative Dose Summary -Table 1 12 2004 Liquid Cumulative Dose Summary -Table 2 13 Report of 2004 Radioactive Effluents: Airborne 14 2004 Gaseous Effluents 16 2004 Gaseous Cumulative Dose Summary - Table 1 18 2004 Gaseous Cumulative Dose Summary - Table 2 19.

Section II 20 Offsite Dose Calculation Manual Limits 20 Effluent Concentration Limits (ECLs) 20 Average Energy 21 Measurements and Approximations of Total Radioactivity (Liquid and 21 Gaseous Effluents)

Batch Releases 23 Continuous Releases 23 Doses to a Member of the Public from Activities Inside the Site Boundary 23 Additional Information 23 2004 Effluent Concentration Limits 27 2004 Solid Waste Shipments 28 Irradiated Fuel Shipments 29 Section III 30 Meteorological Data - Hours At Each Wind Speed and Direction 30 Section IV 39 Unplanned or Abnormal Releases 39 Offsite Dose Calculation Manual 39 Major Changes to Liquid, Solid, or Gaseous Radioactive Waste 39 Treatment Treatment Systems 39 Land Use Census 39 Radwaste Shipments 39 Inoperability of Effluent Monitoring Instrumentation 39 Storage Tanks 39

3 of 40 Table of Contents Attachment I - WCGS Procedure AP 07B-003, Revision 5, uOffsite Dose Calculation Manual" Attachment II - WCGS Procedure AP 07B-004, Revision 8, UOffsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Attachment IlIl - WCGS Procedure AP 31A-1 00, Revision 5, "Solid Radwaste Process Control Program"

4 of 40 EXECUTIVE

SUMMARY

This Annual Radioactive Effluent Release Report (Report # 28) documents the quantities of liquid and gaseous effluents and solid waste released by Wolf Creek Generating Station (WCGS) from January 1, 2004 through December 31, 2004. The format and content of this report are in accordance with Regulatory Guide 1.21, Revision 1, 'Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants." Sections 1,11, III, and IV of this report provide information required by NRC Regulatory Guide 1.21 and Section 7.2 of AP 07B-003, UOffsite Dose Calculation Manual" (ODCM).

Section I - Section I contains, in detail, the quantities of radioactive liquid and gaseous effluents and cumulative dose summaries for 2004, 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 2004.

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 2004.

Section II - Section II includes supplemental information on continuous and batch releases, calculated doses, and solid waste disposal. There were 67 gaseous batch releases in 2004 versus 87 in 2003. There were 58 liquid batch releases in 2004 versus 76 in 2003. WCGS released 0.019 curies in liquid releases during 2004 versus 0.020 curies in 2003, 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 Performance Improvement Requests (PIRs):

-PIR 2003-2580 - This PIR is being included as a follow-up from the 2004 Annual Report.

Baseline results were sent to engineering for evaluation. Engineering made a request for additional blank filters to be sent off for comparison. The results of those filters showed that the establishment of a baseline was not feasible.

PIR 2003-3253 - This PIR is being included due to an omission from the 2004 Annual Report.

On 10-29-03, a Turbine Building Sump composite was prepared and analyzed based on calculations performed on the excel spreadsheet, AIF 07B-020-02. The calculations were performed incorrectly due to a change in daylight savings time not being included.

PIR 2004-0037 - Weekly composites for both Waste Water Treatment and Turbine Building Sump were completed without all required samples. Both instances resulted in improperly performed Offsite Dose Calculation Manual surveillances.

PIR 2004-0620 - The MET tower did not meet the 90% data recovery availability for 2003 required by Reg Guide 1.23, "Meteorological Programs in Support of Nuclear Power Plants."

Actual availability was 84.4%. Instrumentation has been replaced to improve availability.

5 of 40 PIR 2004-1096 - On April 16, 2004, while recircing Waste Gas Decay Tank #6, the tank pressure was noticed to be decreasing by Operations. After investigating, it was determined that the pressure loss was accounted for by an increase in Gas Decay Tank #8.

PIR 2004-1235 - During the Quick Hit Assessment (04-153) of high ammonia chemistry, it was discussed that there was no clear determination on the effect of the ZERO system if high concentrations of ETA water are found to be leaking into the Dirty Radwaste System (DRW) from the Blowdown system.

PIR 2004-1287 - While preparing a liquid release permit for Waste Monitor Tank A (THB07A) on May 6, 2004, it was discovered that radiation monitor HBRE-18 was inoperable. Chemistry had not been notified of the monitor inoperability. The Offsite Dose Calculation Manual requires at least two independent samples be analyzed and at least two qualified individuals verify release rates and valve lineup with an inoperable monitor.

PIR 2004-1410 - The ODCM contains a statement that information contained in appendix B of attachment A is "proprietary information provided by SAL." This is a concern because the Nuclear Regulatory Commission (NRC) cannot put information identified as proprietary in the public domain, and they cannot withhold the information without the appropriate documentation describing what is proprietary and why.

PIR 2004-2087 - On August 13, 2004, the channel checks for radiation monitors GTRE-31 and GTRE-32 were not performed as required by Surveillance Requirements between 1100 and 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />. This is considered a missed surveillance in accordance with Surveillance Requirement 3.0.3.

PIR 2004-3146 - A Steam Generator Blowdown composite sample was not obtained within the necessary time, including the 25% grace period. The composite sample is required by AP 07B-003, Offsite Dose Calculation Manual. The resuit was a missed ODCM surveillance.

PIR 2004-3374 - The Effluent Management Software (EMS) used for performing Offsite Dose Calculation Manual required effluent release permit calculations was found to be inoperable on December 12, 2004. The Information Services help desk was contacted to resolve the problem, but due to the software age, lack of IS knowledge and no support system set up for immediate vendor assistance, the problems have yet to be resolved.

Section III --- Section III documents WCGS meteorological data for wind speed, wind direction, and atmospheric stability. At the time of this report, MET data was not made available.

6 of 40 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 or abnormal releases that occurred in 2004.

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

7 of 40 ATTACHMENTS Attachment I - AP 07B-003, revision 5, uOffsite Dose Calculation Manual" Attachment II - AP 07B-004, revision 8, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Attachment IlIl - AP 31A-1 00, revision 5, uSolid Radwaste Process Control Program"

8 of 40 SECTION I REPORT OF 2004 RADIOA ,CTIVE EFFLUENTS: LIQUID Unit Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 4.53E-03 1.94E-03 alpha)
2. Average Diluted Concentration During PC'ml 3.74E-1 0 1.53E-1 0 Period
3. Percent of Applicable Limit (1)  % 9.06E-02 3.87E-02 B. Tritium
1. Total Release Ci 1.68E+01 7.66E+01
2. Average Diluted Concentration During PiGVml 1.39E-06 6.04E-06 Period
3. Percent of Applicable Limit (2) (ECL) 1.39E-01 6.04E-01 C. Dissolved and Entrained Gases
1. Total Release Ci 0.OOE+00 O.OQE+00
2. Average Diluted Concentration During jiCi/ml 0.OOE+00 O.QQE+00 Period
3. Percent of Applicable Limit (3) O.OOE+00 0.00E+00 D. Gross Alpha Radioactivity
1. Total Release Ci 5.97E-06 2.32E-06 E. Volume of Waste Released (prior to Liters 4.58E+07 7.98E+07 dilution)

F. Volume of Dilution Water Used Liters 1.20E+10 1.26E+10 NOTES:

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

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

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

3) This value is derived by the following formula:

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

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

9 of 40 REPORT OF 2004 RADIO; CTIVE EFFLUENTS: LIQUID Unit Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 5.60E-03 6.55E-03 alpha
2. Average Diluted Concentration During gCi/ml 4.09E-1 1 4.89E-1 1 Period
3. Percent of Applicable Limit (1)  % 1.12E-01 1.31 E-01 B. Tritium
1. Total Release Ci 5.52E+02 4.18E+02
2. Average Diluted Concentration During gCi/ml 4.03E-06 3.12E-06 Period
3. Percent of Applicable Limit (2) (ECL) 4.03E-01 3.12E-01 C. Dissolved and Entrained Gases
1. Total Release Ci 4.OOE-03 9.05E-03
2. Average Diluted Concentration During PiCVml 2.93E-1 1 6.76E-1 1 Period
3. Percent of Applicable Limit (3) 1.46E-05 3.38E-05 D. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+O0 O.OOE+00 E. Volume of Waste Released (prior to liters 9.80E+07 1.1 OE+08 dilution)

F. Volume of Dilution Water Used liters 1.37E+1 1 1.34E+1 1 NOTES:

1) The applicable limit for the WCGS is 5 Curies per year. (Reference 10 CFR 50, Appendix I, NGuides 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) (1 00)

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

10 of 40 2004 LIQUID EFFLUENTS ntinuo'us Mode Batch Mode Nuclides Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Released H-3 Ci 8.31 E-01 7.19E-01 1.60E+01 7.59E+01 Cr-51 Ci n/a n/a 8.39E-06 n/a Mn-54 Ci <2.26E-02 <3.96E-02 3.26E-06 6.17E-07 Fe-55 Ci <4.53E-02 <7.93E-02 <5.1 8E-04 <4.48E-04 Fe-59 Ci <2.26E-02 <3.96E-02 <2.59E-04 <2.24E-04 Co-57 Ci n/a n/a 1.24E-05 n/a Co-58 Ci <2.26E-02 <3.96E-02 3.45E-03 7.60E-04 Co-60 Ci <2.26E-02 <3.96E-02 1.70E-04 6.30E-05 Zn-65 Ci <2.26E-02 <3.96E-02 <2.59E-04 <2.24E-04 Sr-89 Ci <2.26E-03 <3.96E-03 <2.59E-05 <2.24E-05 Sr-90 Ci <2.26E-03 <3.96E-03 <2.59E-05 <2.24E-05 Mo-99 Ci <2.26E-02 <3.96E-02 <2.59E-04 <2.24E-04 Sb-1 24 Ci n/a n/a 6.62E-06 2.54E-06 Sb-125 Ci n/a n/a 8.31 E-04 1.07E-03 1-131 Ci <4.53E-02 <7.93E-02 <5.1 8E-04 <4.48E-04 1-133 Ci n/a n/a n/a Cs-1 34 Ci <2.26E-02 <3.96E-02 9.1 OE-06 6.69E-06 Cs-1 37 Ci <2.26E-02 <3.96E-02 4.20E-05 3.28E-05 Ce-1 41 Ci <2.26E-02 <3.96E-02 <2.59E-04 <2.24E-04 Ce-144 Ci <2.26E-02 <3.96E-02 <2.59E-04 <2.24E-04 Gross Alpha Ci <4.53E-03 <7.93E-03 5.97E-06 2.32E-06 Ar-41 Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Kr-85M Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Kr-85 Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Kr-87 Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Kr-88 Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Xe-131 M Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Xe-1 33M Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Xe-1 33 Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Xe-1 35M Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-03 Xe-135 Ci <4.53E-01 <7.93E-01 <5.1 8E-03 <4.48E-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.

11 of'40 2004 LIQUID EFFLUENTS itinuous Mode Batch Mode Nuclides Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Released H-3 Ci 1.78E+OO 1.64E+OO 5.50E+02 4.16E+02 Cr-51 Ci n/a n/a 2.53E-05 n/a Mn-54 Ci <4.86E-02 <5.44E-02 <3. 1E-04 <3.58E-04 Fe-55 Ci <9.73E-02 <1.09E-01 <6.22E-04 <7.17E-04 Fe-59 Ci <4.86E-02 <5.44E-02 <3.i1 E-04 <3.58E-04 Co-57 Ci n/a n/a 4.63E-06 n/a Co-58 Ci <4.86E-02 <5.44E-02 9.78E-04 2.88E-04 Co-60 Ci <4.86E-02 <5.44E-02 2.06E-04 1.04E-04 Zn-65 Ci <4.86E-02 <5.44E-02 <3.11 E-04 <3.58E-04 Sr-89 Ci <4.86E-03 <5.44E-03 <3.11 E-05 <3.58E-05 Sr-90 Ci <4.86E-03 <5.44E-03 <3.1 1E-05 <3.58E-05 Mo-99 Ci <4.86E-02 <5.44E-02 <3.11 E-04 <3.58E-04 Sb-124 Ci n/a n/a n/a n/a Sb-125 Ci n/a n/a 4.36E-03 6.11E-03 1-131 Ci <9.73E-02 <1.09E-01 <6.22E-04 2.52E-06 1-132 Ci n/a n/a n/a n/a 1-133 Ci n/a n/a n/a n/a Cs-1 34 Ci <4.86E-02 <5.44E-02 4.OOE-07 1.52E-06 Cs-1 37 Ci <4.86E-02 <5.44E-02 2.05E-05 4.1 OE-05 Ce-1 41 Ci <4.86E-02 <5.44E-02 2.35E-07 <3.58E-04 Ce-144 Ci <4.86E-02 <5.44E-02 <3.11 E-04 <3.58E-04 Rb-88 Ci n/a n/a n/a n/a Ba-139 Ci - n/a - n/a n/a n/a Mn-56 Ci n/a n/a n/a n/a Nb-97 Ci n/a n/a n/a n/a Sn-117m Ci n/a n/a n/a n/a Gross Alpha Ci <9.73E-03 <1.09E-02 <6.22E-05 <7.17E-05 Ar-41 Ci <9.73E-01 <1.09E+OO <6.22E-03 <7.17E-03 Kr-85M Ci <9.73E-01 <1.09E+OO <6.22E-03 <7.17E-03 Kr-85 Ci <9.73E-01 <1.09E+OO <6.22E-03 <7.17E-03 Kr-87 Ci <9.73E-01 <1.09E+OO <6.22E-03 <7.17E-03 Kr-88 Ci <9.73E-01 <1.09E+OO <6.22E-03 <7.17E-03 Xe-131M Ci <9.73E-01 <1.09E+OO <6.22E-03 <7.17E-03 Xe-1 33M Ci <9.73E-01 <1.09E+OO <6.22E-03 4.32E-05 Xe-133 Ci <9.73E-01 <1.09E+OO 4.OOE-03 8.98E-03 Xe-1 35M Ci <9.73E-01 <1.09E+OO <6.22E-03 <7.17E-03 Xe-135 Ci <9.73E-01 <1.09E+OO 3.42E-06 3.30E-05 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.

12 of 40 LIQUID CUMULATIVE DOSE

SUMMARY

(2004) TABLE 1 QUARTER 1 OF 2004 (mrem) ODCM CALCULATED ODCM LIMIT(1)  % OF LIMIT DOSE TOTAL DOSE FOR BONE 2.06E-04 5.OOE+00 4.12E-03 TOTAL DOSE FOR LIVER 2.53E-02 5.OOE+00 5.07E-01 TOTAL DOSE FOR TOTAL BODY 2.53E-02 1.50E+00 1.68E+00 TOTAL DOSE FOR THYROID 2.50E-02 5.OOE+00 5.01 E-01 TOTAL DOSE FOR KIDNEY 2.51 E-02 5.OOE+00 5.03E-01 TOTAL DOSE FOR LUNG 2.51 E-02 5.OOE+00 5.01 E-01 TOTAL DOSE FOR GI-LLI 2.52E-02 5.OOE+00 5.04E-01 QUARTER 2 OF 2004 (mrem)

TOTAL DOSE FOR BONE 1.23E-04 5.OOE+00 2.46E-03 TOTAL DOSE FOR LIVER 1.40E-02 5.OOE+00 2.81 E-01 TOTAL DOSE FOR TOTAL BODY 1.40E-02 1.50E+00 9.32E-01 TOTAL DOSE FOR THYROID 1.38E-02 5.OOE+00 2.77E-01 TOTAL DOSE FOR KIDNEY 1.39E-02 5.OOE+00 2.78E-01 TOTAL DOSE FOR LUNG 1.39E-02 5.OOE+00 2.77E-01 TOTAL DOSE FOR GI-LLI 1.39E-02 5.OOE+00 2.78E-01 QUARTER 3 OF 2004 (mrem)

TOTAL DOSE FOR BONE 7.27E-05 5.OOE+00 1.45E-03 TOTAL DOSE FOR LIVER 4.13E-02 5.OOE+00 8.26E-01 TOTAL DOSE FOR TOTAL BODY 4.13E-02 1.50E+00 2.75E+00 TOTAL DOSE FOR THYROID 4.12E-02 5.OOE+00 8.24E-01 TOTAL DOSE FOR KIDNEY 4.13E-02 5.OOE+00 8.25E-01 TOTAL DOSE FOR LUNG 4.12E-02 5.OOE+00 8.25E-01 TOTAL DOSE FOR GI-LLI 4.13E-02 5.OOE+00 8.27E-01 QUARTER 4 OF 2004 (mrem)

TOTAL DOSE FOR BONE 2.05E-04 5.OOE+00 4.1 OE-03 TOTAL DOSE FOR LIVER 3.68E-02 5.OOE+00 7.36E-01 TOTAL DOSE FOR TOTAL BODY 3.67E-02 1.50E+00 2.45E+00 TOTAL DOSE FOR THYROID 3.65E-02 5.OOE+00 7.30E-01 TOTAL DOSE FOR KIDNEY 3.66E-02 5.OOE+00 7.32E-01 TOTAL DOSE FOR LUNG 3.65E-02 5.OOE+00 7.31 E-01 TOTAL DOSE FOR GI-LLI 3.66E-02 5.OOE+00 7.33E-01 TOTALS FOR 2004 (mrem)

TOTAL DOSE FOR BONE 6.07E-04 1.OOE+01 6.07E-03 TOTAL DOSE FOR LIVER 1.1 7E-01 1.OOE+01 1.17E+00 TOTAL DOSE FOR TOTAL BODY 1.17E-01 3.OOE+00 3.91 E+00 TOTAL DOSE FOR THYROID 1.1 7E-01 1.OOE+01 1.17E+00 TOTAL DOSE FOR KIDNEY 1.1 7E-01 1.OOE+01 1.17E+00 TOTAL DOSE FOR LUNG 1.17E-01 1.OOE+01 1.17E+00 TOTAL DOSE FOR GI-LLI 1.17E-01 1.OOE+01 1.17E+00

1. Based on ODCM Section 2.2, which restricts dose to the whole body to s 1.5 mRem per quarter and 3.0 mRem per year. Dose restriction of any organ is 5 5.0 mRem per quarter and 10.0 mRem per year.

13 of 40 LIQUID CUMULATIVE DOSE

SUMMARY

(2004) 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) 4.53E-03 1.94E-03 5.60E-03 6.55E-03 1.86E-02
2. Maximum Organ Dose (mRem) 3.18E-04 1.84E-04 1.02E-04 2.74E-04 8.71 E-04
3. Organ Dose Limit (mRem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01
4. Percent of Limit 6.36E-03 3.69E-03 2.04E-03 5.48E-03 8.71 E-03 B. Tritium
1. Total Release - (Ci) 1.68E+01 7.66E+01 5.52E+02 4.18E+02 1.06E+03
2. Maximum Organ Dose (mRem) 2.50E-02 1.38E-02 4.12E-02 3.65E-02 1.17E-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 5.01 E-01 2.77E-01 8.24E-01 7.30E-01 1.17E+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.

14 of 40 REPORT OF 2004 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 1 2 A. Fission and Activation Gases

1. Total Release Ci 3.28E-01 4.07E-01
2. Average Release Rate for Period giCVsec 4.17E-02 5.1 8E-02
3. Percent of ODCM Limit (1)  % 4.25E-03 3.59E-03 B. Iodine
1. Total Release Ci O.OOE+00 O.OOE+00
2. Average Release Rate for Period igCi/sec O.OOE+00 O.QOE+00
3. Percent of Applicable Limit (2)  % O.OOE+00 O.OOE+00 C. Particulates
1. Particulates with Half-lives > 8days Ci 2.86E-07 O.OOE+00
2. Average Release Rate for Period ,iCi/sec 3.64E-08 O.OOE+00
3. Percent ofODCM Limit (3)  % 2.03E-06 O.OOE+00
4. Gross Alpha Radioactivity Ci O.OOE+00 O.OOE+00 D. Tritium
1. Total Release Ci 4.63E+00 1.02E+01
2. Average Release Rate for Period pCi/sec 5.89E-01 1.29E+00
3. Percent of ODCM Limit (4)  % 4.76E-02 1.OOE-01 NOTES:
1) The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

%of ODCMLimit= (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:

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

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)(l00) 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 iscalculated using the following methodology:

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

15 of 40 REPORT OF 2004 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 3 4 A. Fission and Activation Gases

1. Total Release Ci 3.04E-01 3.86E-01
2. Average Release Rate for Period pCVsec 3.83E-02 4.86E-02
3. Percent of ODCM Limit (1)  % 3.64E-03 4.08E-03 B. lodines
1. Total Iodine-131 Ci O.OOE+00 0.OOE+00
2. Average Release Rate for Period piCisec 0.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 pCiCsec 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 1.51 E+01 4.52E+00
2. Average Release Rate for Period iCilsec 1.90E+00 5.69E-01
3. Percent of ODCM Limit (4)  % 1.38E-01 3.91 E-02 NOTES:
1) The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

%of ODCM Lirnit= (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:

%of ODCM Limnit= (Total Curies of Iodine -131 )( 100)

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 methodologyis 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

16 of 40 2004 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 3.27E-01 2.77E-01 Kr-85 Ci n/a n/a n/a 1.25E-01 Kr-85M Ci n/a n/a n/a 1.55E-06 Kr-87. Ci <1.02E+01 <1.01 E+01 <1.35E-02 <1.14E-02 Kr-88 Ci <1.14E+01 <1.13E+01 <1.52E-02 <1.28E-02 Xe-131M Ci n/a n/a n/a n/a Xe-1 33 Ci <6.38E+00 <6.32E+00 5.56E-04 5.13E-03 Xe-1 33M Ci <2.63E+01 <2.60E+01 <3.50E-02 7.26E-05 Xe-1 35 Ci <2.75E+00 <2.72E+00 <3.66E-03 1.96E-04 Xe-1 38 Ci <2.96E+02 <2.93E+02 <3.93E-01 <3.32E-01 Total Ci O.OOE+00 0.OOE+00 3.28E-01 4.07E-01
2. Halogens (Gaseous) 1-131 Ci <2.64E-04 <2.61 E-04 <3.51 E-07 <2.96E-07 1-133 Ci <2.64E-02 <2.61 E-02 <3.51 E-05 <2.96E-05 Total Ci O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00
3. Particulates and Tritium H-3 Ci 4.49E+00 9.68E+00 1.43E-01 4.94E-01 Mn-54 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Fe-59 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Co-58 Ci 2.86E-07 <2.61 E-03 <3.51 E-06 <2.96E-06 Co-60 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Zn-65 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Mo-99 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Cs-1 34 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Cs-137 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Ce-141 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Ce-1 44 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Sr-89 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Sr-90 Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Gross Alpha Ci <2.64E-03 <2.61 E-03 <3.51 E-06 <2.96E-06 Total Ci 4.49E+00 9.68E+00 1.38E-01 4.94E-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.

17 of 40 2004 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 2.81 E-01 3.12E-01 Kr-85 Ci n/a n/a 1.83E-02 8.71 E-03 Kr-85M Ci n/a n/a n/a n/a Kr-87 Ci <1.03E+01 <1.01 E+01 <1.20E-02 <1.27E-02 Kr-88 Ci <1.16E+01 <1.14E+01 <1.35E-02 <1.43E-02 Xe-1 31 M Ci n/a n/a 2.61 E-04 n/a Xe-1 33 Ci <6.48E+00 6.27E-02 5.23E-03 2.36E-03 Xe-1 33M Ci <2.67E+01 <2.61 E+01 2.75E-05 1.80E-05 Xe-1 35 Ci <2.80E+00 <2.73E+O0 <3.24E-03 <3.44E-03 Xe-1 38 Ci <3.OOE+02 <2.93E+02 <3.48E-01 <3.70E-01 Total Ci O.OOE+OO 6.27E-02 3.04E-01 3.23E-01
2. Halogens (Gaseous) 1-131 Ci <2.68E-04 <2.62E-04 <3.11 E-07 <3.30E-07 1-133 Ci <2.68E-02 <2.62E-02 <3.11 E-05 <3.30E-05 Total Ci O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00
3. Particulates and Tritium H-3 Ci 1.41 E+01 4.14E+O0 1.OOE+00 3.82E-01 Mn-54 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Fe-59 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Co-58 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Co-60 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Zn-65 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Mo-99 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Cs-1 34 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Cs-1 37 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Ce-1 41 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Ce-144 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Sr-89 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Sr-90 Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Gross Alpha Ci <2.68E-03 <2.62E-03 <3.11 E-06 <3.30E-06 Total Ci 1.41 E+01 4.14E+O0 1.OOE+00 3.82E-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.

18 of 40 GASEOUS CUMULATIVE DOSE

SUMMARY

(2004) TABLE 1 QUARTER 1 OF 2004 (mRem) ODCM CALCULATED ODCM LIMIT  % OF LIMIT DOSE (1)

TOTAL DOSE FOR BONE 6.19E-08 7.50E+00 8.25E-07 TOTAL DOSE FOR LIVER 3.27E-03 7.50E+00 4.36E-02 TOTAL DOSE FOR TOTAL BODY 3.27E-03 7.50E+00 4.36E-02 TOTAL DOSE FOR THYROID 3.27E-03 7.50E+00 4.36E-02 TOTAL DOSE FOR KIDNEY 3.27E-03 7.50E+00 4.36E-02 TOTAL DOSE FOR LUNG 3.27E-03 7.50E+00 4.36E-02 TOTAL DOSE FOR GI-LLI 3.27E-03 7.50E+00 4.36E-02 QUARTER 2 OF 2004 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 7.19E-03 7.50E+00 9.59E-02 TOTAL DOSE FOR TOTAL BODY 7.19E-03 7.50E+00 9.59E-02 TOTAL DOSE FOR THYROID 7.19E-03 7.50E+00 9.59E-02 TOTAL DOSE FOR KIDNEY 7.19E-03 7.50E+00 9.59E-02 TOTAL DOSE FOR LUNG 7.19E-03 7.50E+00 9.59E-02 TOTAL DOSE FOR GI-LLI 7.19E-03 7.50E+00 9.59E-02 QUARTER 3 OF 2004 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 1.07E-02 7.50E+00 1.42E-01 TOTAL DOSE FOR TOTAL BODY 1.07E-02 7.50E+00 1.42E-01 TOTAL DOSE FOR THYROID 1.07E-02 7.50E+00 1.42E-01 TOTAL DOSE FOR KIDNEY 1.07E-02 7.50E+00 1.42E-01 TOTAL DOSE FOR LUNG 1.07E-02 7.50E+00 1.42E-01 TOTAL DOSE FOR GI-LLI 1.07E-02 7.50E+00 1.42E-01 QUARTER 4 OF 2004 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 3.20E-03 7.50E+00 4.26E-02 TOTAL DOSE FOR TOTAL BODY 3.20E-03 7.50E+00 4.26E-02 TOTAL DOSE FOR THYROID 3.20E-03 7.50E+00 4.26E-02 TOTAL DOSE FOR KIDNEY 3.20E-03 7.50E+00 4.26E-02 TOTAL DOSE FOR LUNG 3.20E-03 7.50E+00 4.26E-02 TOTAL DOSE FOR GI-LLI 3.20E-03 7.50E+00 4.26E-02 TOTALS FOR 2004 (mRem)

TOTAL DOSE FOR BONE 6.19E-08 1.50E+01 4.13E-07 TOTAL DOSE FOR LIVER 2.43E-02 1.50E+01 1.62E-01 TOTAL DOSE FOR TOTAL BODY 2.43E-02 1.50E+01 1.62E-01 TOTAL DOSE FOR THYROID 2.43E-02 1.50E+01 1.62E-01 TOTAL DOSE FOR KIDNEY 2.43E-02 1.50E+01 1.62E-01 TOTAL DOSE FOR LUNG 2.43E-02 1.50E+01 1.62E-01 TOTAL DOSE FOR GI-LLI 2.43E-02 1.50E+01 1.62E-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.

19 of 40 GASEOUS CUMULATIVE DOSE

SUMMARY

(2004) TABLE 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A. Fission and Activation Gases

1. Total Release - (Ci) 3.28E-01 4.07E-01 3.04E-01 3.86E-01 1.43E+00
2. Total Gamma Airdose (mRad) 2.12E-04 1.80E-04 1.82E-04 2.04E-04 7.78E-04
3. Gamma Airdose Limit (mRad) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01
4. Percent of Gamma Airdose Limit 4.25E-03 3.59E-03 3.64E-03 4.08E-03 7.78E-03
5. Total Beta Airdose (mRad) 7.49E-05 8.07E-05 6.70E-05 7.74E-05 3.OOE-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 7.49E-04 8.07E-04 6.70E-04 7.74E-04 1.50E-03 Limit (mRad)

B. Particulates

1. Total Particulates (Ci) 2.86E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.86E-07
2. Maximum Organ Dose (mRem) 1.52E-07 0.OOE+00 O.OE+00 O.OOE+00 1.52E-07
3. Organ Dose Limit (mRem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01
4. Percent of Limit 2.03E-06 O.OOE+00 O.OE+00 O.OOE+00 1.02E-06 C. Tritium
1. Total Release (Ci) 4.63E+00 1.02E+01 1.51 E+01 4.52E+00 3.44E+01
2. Maximum Organ Dose (mRem) 3.57E-03 7.50E-03 1.03E-02 2.93E-03 2.43E-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 4.76E-02 1.OOE-01 1.38E-01 3.91 E-02 1.62E-01 D. Iodine
1. Total 1-131,1-133 (Ci) O.OOE+00 O.OOE+00 O.OOE+00 O.OE+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.OE+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.

20 of 40 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 gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 microCuries/mi 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, 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 lodine-1 31, lodine-133, 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 l.A.

Air - covered in Section l.B.

S

21 of 40

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 BatchlM Gases (Gamma Emitters)
b. Secondary Liquid P LS. 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 SumplWaste 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

22 of 40 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

23 of 40

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 67 gaseous batch releases during the reporting period. The longest gaseous batch release lasted 522 minutes, while the shortest lasted 42 minutes. The average release lasted 178 minutes with a total gaseous batch release time of 11,899 minutes.

There were 58 liquid batch releases during the reporting period. The longest liquid batch release lasted 265 minutes, while the shortest lasted 29 minutes. The average release lasted 156 minutes with a total liquid batch release time of 8,981 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 restricted area, 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 2.63E-01 mRem William Allen White Building Workers 5.91 E-03 mRem Access Road Users 2.69E-03 mRem Lake Use 3.66E-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 3840 hours0.0444 days <br />1.067 hours <br />0.00635 weeks <br />0.00146 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 320 days, based on the number of days that the lake was open to fisherman). Pathways used in the calculation were gaseous inhalation, submersion, and ground plane. All calculations were performed in accordance with the methodology and parameters in the ODCM.

8. Additional Information PIR 2003-2580 - This PIR is being included as a follow-up from the 2004 Annual Report. Several months' filters were sent to Sherry Laboratories for vendor analysis of boron and iron to establish a baseline for results. All results were sent to engineering for evaluation. At the request of engineering, several new filters, all from different lots, were sent to the vendor for comparison. Following the return of these results from the vendor, engineering determined that the establishment of a baseline for boron and iron on sample

24 of 40 filters was not feasible. Engineering recommended that the iron and/or boron content of exposed radiation monitor filters not be used as a first indication for RCS leakage.

Instead, isotopic analyses should be used, considering both total activity and isotopes present. Changes were made to chemistry procedures AP 02-002, Chemistry Surveillance Program, and AP 02-003, Chemistry Specification Manual, to provide necessary guidance to ensure any potential RCS leakage be quickly assessed.

PIR 2003-3253 - This PIR is being included due to an omission from the 2004 Annual Report. On 10-29-03, a Turbine Building Sump composite was prepared and analyzed based on calculations performed on excel spreadsheet, AIF 07B-020-02. The spreadsheet did not account for the hour gain due to daylight savings time and incorrectly calculated the discharge volume. The composite volume for the Turbine Building Sump was corrected for the end of daylight savings time, and other composites were reviewed to ensure the program error did not occur with them. Not including the 60-minute difference had virtually no impact, as there was an insignificant difference

(<0.5%) in the volume used for the total composite volume. A change was made to chemistry procedure Al 07B-020, Instructions for Composite Preparation, informing the user that daylight savings corrections need to be performed manually.

PIR 2004-0037 - For the week of 11-5 through 11-11-03, the Turbine Building Sump (TBS) weekly composite did not contain a required sample. For the week of 11-12 through 11-18-03, the Waste Water Treatment (WWT) weekly composite did not contain a required sample. Both instances resulted in improperly performed Offsite Dose Calculation Manual (ODCM) surveillances. Both instances happened during Refueling Outage 13. The TBS miss occurred due to miscommunication about the "composite week". Discussions between technicians resulted in the daily composite, pulled 11 03, not being added to the weekly composite. The review of appropriate paperwork was done improperly and that daily composite remained on the shelf. The omission was questioned but not resolved. The WWT miss also occurred due to miscommunication between Chemistry and Operations, as well as within Chemistry itself. A sample of the B basin was pulled 11-11-03 and saved for composite. That basin was held for three days prior to release due to a circ water outage. There was confusion between groups as to which basin had actually been sampled, and information about that was apparently recorded incorrectly. The result was that the composite for B basin, pulled 11-11 and released 11-14-03, was not included in the weekly composite. The volumes for both weekly composites were corrected and corresponding release permits edited to correct discharge volumes and total curies released. Several procedure changes were made to address daily compositing, defining the composite week, and changing the composite review and verification process. In addition, the problems and resolutions identified in this PIR were reviewed with all technicians face to face.

PIR 2004-0620 - The MET tower did not meet the 90% data recovery availability for 2003 required by Reg Guide 1.23, "Meteorological Programs in Support of Nuclear Power Plants." The actual availability was 84.4 %. The lower availability was due to instrument malfunction or the computer or computer link/modem being unavailable. A change package (09882) was implemented to replace instrumentation on the MET tower.

Meteorological instrumentation was replaced by mid-August 2004 to improve availability.

2004-1096 - On April 16, 2004, while recircing Waste Gas Decay Tank (WGDT) #6, the tank pressure was noticed to be decreasing by Operations. After investigating, it was determined that the pressure loss was accounted for by an increase in WGDT #8. The

25 of 40 result of the pressure transfer did not affect any ongoing operations. During troubleshooting, it was determined that HA V-1 032F, Compensating Seal Make-up Valve solenoid, was not operating properly. That valve was replaced, tested, and found operating properly. However, a pressure change between #6 and #8 was still observed.

It was then determined that the transfer appeared to be a result of the Waste Gas Compressor B moisture separator relief valve leaking by the valve seat, which may have been a result of the previously bad solenoid valve. A workorder was issued to replace the moisture separator relief.

2004-1235 - During the Quick Hit Assessment (04-153) of high ammonia chemistry, it was discussed that there was no clear determination on the effect of the ZERO system if high concentrations of ethanolamine (ETA) water are found to be leaking into the Dirty Radwaste System (DRW) from the Blowdown system. Discussions were held with Diversified Technologies Services (DTS) chemical engineer, who was contacted for advice on processing liquid waste containing ammonia and/or ETA. The DTS position is that the SRO unit will reject the ETA, which will result in this chemical being concentrated in the reject waste stream. It will then be concentrated as a dry solid waste in the Drum Dryer prior to disposal. ETA concentrations should not impact the existing liquid waste processing systems.

2004-1287 - While preparing a liquid release permit for Waste Monitor Tank A (THB07A) on May 6, 2004, it was discovered that radiation monitor HBRE-18 was inoperable.

Chemistry had not been notified of the monitor inoperability. The ODCM requires at least two independent samples be analyzed and at least two qualified individuals verify release rates and valve lineup with an inoperable monitor. In addition Chemistry is required to initiate APF 02-007-01, HBRE-18 Operability. The inoperability was due to a loss of communication between the RM11 and HBRE-18. Upon investigation, it was reported that the monitor was functioning properly locally. Due to the fact that it was operating locally and there was no release actually in progress, the Control Room Supervisor did not consider the monitor inoperable and no actions were taken. After further investigation, it was recognized that notification should have been made. The miscommunication resulted in unnecessary delays in permit preparation and additional unscheduled work for Chemistry.

2004-1410 - The ODCM, submitted as an attachment to the 2003 Annual Effluent Report, contains a statement that information contained in appendix B of attachment A is "proprietary information provided by SAL" This is a concern because the Nuclear Regulatory Commission (NRC) cannot put information identified as proprietary in the public domain, and they cannot withhold the information without the appropriate documentation describing what is proprietary and why. This phrase has been included in the ODCM since revision 0 was released because the ODCM receives its own review as part of revision process and is only an attachment to the report. The statement is not appropriate and there is no concern with prior submittals, but the NRC requested that the 2004 report be corrected so it can be handled properly. Following investigation, it appeared that the statement may have been inappropriately "cut and pasted" along with the data in this appendix but is not proprietary to SAL. The conclusion was that the statement could be removed without violating any agreement or rights of SAL. AP 07B-003, ODCM, was revised to remove the "proprietary information" label from the document. It was released 9-29-04. In addition, letter RA 04-0119 was submitted to the NRC on 10-13-04 to provide them with the revised version of the Annual Report containing the revised ODCM.

26 of 40 2004-2087 - On August 13, 2004, the channel checks for Containment Atmosphere radiation monitors GTRE-31 and GTRE-32 were not performed as required by Surveillance Requirements between 1100 and 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />. This is considered to be a missed surveillance in accordance with Surveillance Requirement (SR) 3.0.3. The previous check had been completed satisfactorily at 0449. The subsequent check completed at 2206. As allowed by SR 3.0.3, the surveillance was performed satisfactorily within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the missed surveillance. A review of historical data for both monitors indicated that both channels remained operable during the time of the missed surveillance.

2004-3146 - On November 23, 2004, a Steam Generator Blowdown composite sample was not obtained within the necessary time, including the 25% grace period. The composite sample is required by AP 07B-003, ODCM. The sample on 11-22 was obtained at 0805. The sample on 11-23 was not obtained until 1455, after prompting from the Control Room. Based on the grace period allowance, the sample was required by 1405. The result was a missed ODCM surveillance. The consequences of this were minor due to the fact that the daily sample composite represents a larger volume that will be reflected when included in the weekly composite.

2004-3374 - The Effluent Management Software (EMS) used for performing ODCM required effluent release permit calculations was found to be inoperable on December 12, 2004. The Information Services help desk was contacted to resolve the problem, but due to the software age, lack of IS knowledge and no support system set up for immediate vendor assistance, the problems were slow to be resolved. Data had not been backed up on EMS since 11-23, so reentering all of the permit data would have been required prior to performing additional release calculations. The evolution was expected to take between 12 and 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> for entry and verification. Fortunately, the system recovered long enough to perform a backup. EMS had to be accessed on a backup server, designed for testing/development not production. The consequences of not having EMS accessible to perform release calculations were missing ODCM required surveillances and potentially causing containment pressure to exceed Technical Specification limits. This malfunction happened previously in 2003. Backups are being performed on a weekly basis. A purchase requisition has been issued to establish an annual maintenance agreement with Computer Associates, the database support vendor.

In addition, a request for funding new software has been approved for 2005.

27 of 40 2004 EFFLUENT CONCENTRATION LIMITS Nuclides Curies Average Diluted 10 CFR 20 ECL % of ECL Concentration (uCi/ml)

(uCi/ml)

H-3 1.06E+03 3.59E-06 1.OOE-03 3.59E-01 Cr-51 3.37E-05 1.14E-13 5.OOE-04 2.28E-08 Mn-54 3.87E-06 1.31 E-14 3.OOE-05 4.37E-08 Mn-56 n/a n/a 7.OOE-05 n/a Co-57 1.70E-05 5.76E-1 4 6.OOE-05 9.60E-08 Co-58 5.47E-03 1.85E-11 2.OOE-05 9.25E-05 Co-60 5.44E-04 1.84E-12 3.OOE-06 6.13E-05 Sb-1 25 1.24E-02 4.20E-1 1 3.OOE-05 1.40E-04 Sb-1 24 9.16E-06 3.1OE-14 7.OOE-06 4.43E-07 1-131 2.52E-06 8.53E-15 1.OOE-06 8.53E-07 1-132 n/a n/a 1.OOE-04 n/a 1-133 n/a n/a 7.OOE-06 n/a Ce-1 41 2.35E-07 7.96E-16 3.OOE-05 2.65E-09 Cs-1 34 1.77E-05 5.99E-14 9.OOE-07 6.66E-06 Cs-137 1.36E-04 4.60E-13 1.OOE-06 4.60E-05 Nb-97 n/a n/a 3.OOE-04 n/a Ba-139 n/a n/a 2.OOE-04 n/a Rb-88 n/a n/a 4.OOE-04 n/a Sn-1 17M n/a n/a 1.OOE-08 n/a Sb-124 n/a n/a 7.OOE-06 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 2.00E-04 n/a Xe-131M n/a n/a 2.O0E-04 n/a Xe-133M 4.32E-05 1.46E-13 2.OOE-04 7.30E-08 Xe-133 1.30E-02 4.40E-1 1 2.OOE-04 2.20E-05 Xe-135 3.64E-05 1.23E-13 2.OOE-04 6.15E-08

28 of 40 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2004 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* 3.37E+01 **

evaporator bottoms, etc. Ci 9.85E+01 2.50E+01

b. Dry compressible waste, m3* 2.76E+02**

contaminated equip. etc. Ci 4.43E+00 2.50E+01

c. Irradiated components, m3* 0.00E+00 control rods, etc. Ci O.00E+00 2.50E+01
d. Other m3* 0.OOE+00 Ci 0.OOE+00 2.50E+01
  • m3 = cubic meters ** This iis 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 25.733 2.68E+01 Co-58 10.083 1.01 E+01 Ni-63 47.900 4.56E+01

b. Dry compressible waste, contaminated equipment, etc.

Nuclide Percent Name Abundance Curies Fe-55 58.081 2.54E+00 Co-58 12.997 1.75E-01 Ni-63 15.644 7.60E-01

29 of 40

c. Irradiated components, control rods, etc. - None
d. Other -None
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Truck (Hittman Transport Services) Barnwell Waste Management Facility, Barnwell, SC 1 Truck (Hittman Transport Services) Envirocare of Utah, Inc; Clive UT 3 Truck (Hittman Transport Services) Studsvik Processing Facility, LLC; Columbia, SC 1 Truck (Interstate Freight) RACE, LLC; Memphis, TN 1 Truck (RACE Logistics, LLC) RACE, LLC; Memphis, TN 4 Truck (R&R Trucking) 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 (Strong, tight), Type A, Type B - corresponding to 2a
b. LSA (Strong, tight) - 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 2004 period.

30 of 40 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, 2004, through December 31, 2004, 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 not meet Regulatory Guide 1.23 requirement for having at least 90%

meteorological data recovery for 2004. As identified in PIR 2004-0620 problems with instrumentation or computer link were the cause of this problem and resulted in the replacement of the meteorological tower instruments.

A Meteorological Professor at the University of Kansas helped to establish the first set of criteria that is used to determine data availability and verification. This verification takes a look at the required instruments on the tower and compares the instrument output (meteorological value) against one another and against a set of criteria for the particular parameter being measured.

This method also flags data as bad anytime the communication link to the plant computer is down or the plant computer is down. This method is conservative and may flag data as bad even though the required Reg. Guide 1.23 instruments are still available. Data availability using this method is 85.2%, for the year 2004.

The Meteorological Tower Instruments were replaced in 2004 and the problem of unresponsive instruments and the computer being down have been greatly reduced. Since the new instruments were installed data availability has been meeting the 90% availability requirement.

The data availability for the Meteorological Data for the year 2004 as stated above is 85.2%. Part of the unavailability for the year 2004 came from the time that it took to replace the instruments that were causing the system downtime. Wolf Creek Engineering change package 09882 updated the meteorological instrumentation (over 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />). It was recognized that the tower would be out of service while this replacement was ongoing and during this time back-up, hand instruments were available (if needed by the E-Plan) but these instruments are not credited for collection of meteorological data. It is expected that the meteorological tower data will be considerably more reliable from this point forward due to the installation of the replacement instrumentation and the fact that the key parameters have "back-up" instruments installed with the replacements.

31 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2004 STABILITY CLASS: A ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1.75 23.75 25.75 31.00 4.25 0.50 87.00 NNE 5.75 28.00 25.25

  • 9.00 1.00 0.00 69.00 NE 6.50 24.00 11.75 0.00 0.00 0.00 42.25 ENE 2.50 13.50 17.50 4.25 0.00 0.25 38.00 E 0.75 10.25 7.00 0.50 0.00 0.00 18.50 ESE 1.00 5.00 9.25 1.75 0.00 0.00 17.00 SE 0.75 6.25 14.75
  • 4.50 0.00 0.00 26.25 SSE 2.25 19.25 31.00 23.50 0.25 0.00 76.25 S 3.00 16.25 47.50 57.50 17.75 0.50 142.50 SSW 2.25 13.25 15.50 13.75 3.25 0.00 48.00 SW 3.25 16.50 8.25 4.50 0.00 0.00 32.50 WSW 2.00 11.00 9.25 0.50 0.00 0.25 23.00 W 1.25 8.50 13.00 2.75 0.25 0.25 26.00 WNW 2.75 10.50 9.50 1.75 0.00 0.00 24.50 NW 1.75 7.25 12.25 7.00 0.00 0.50 28.75 NNW 1.50 12.50 22.75 18.50. 2.75 0.00 58.00 TOTAL 37.25 225.75 280.25. 180.75 29.50 2.25 757.50 PERIOD OF CALM (HOURS): 0.50

32 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31,2004 STABILITY CLASS: B ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0.50 2.50 7.75

  • 9.00 1.00 0.25 21.00 NNE 0.75 6.75 9.00 5.25 1.25 0.25 23.25 NE 0.50 5.50 9.50 0.25 0.00 0.00 15.75 ENE 1.25 3.75 3.75 1.00 0.00 0.00 9.75 E 0.50 5.50 4.00 0.25 0.00 0.25 10.50 ESE 0.25 2.50 5.25 0.25 0.00 0.00 8.25 SE 0.75 3.25 6.00 2.00 0.00 0.00 12.00 SSE 1.50 6.00 18.50 14.00 0.25 0.00 40.25 S 0.75 3.50 16.50 20.25 5.50 0.00 46.50 SSW
  • 0.00 2.25 11.00 10.50 1.75 0.00 25.50 SW 1.00 2.50 7.50 2.00 1.25 0.00 14.25 WSW 1.75 3.50 2.50 1.75 0.25 0.00 9.75 W 0.25 2.75 7.00 3.75 0.00 0.00 13.75 WNW 0.75 3.25 4.50 5.25 0.00 0.00 13.75 NW 0.25 2.75 7.00 8.75 0.00 0.00 18.75 NNW 0.50 2.25 9.25 9.00 3.50 0.00 24.50 TOTAL 10.75 58.50 129.00 93.25 14.75 0.75 307.50 PERIOD OF CALM (HOURS): 0.25

33 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2004 STABILITY CLASS: C ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1.00 4.75 6.25 11.25 0.25 0.25 23.75 NNE 1.00 6.75 12.00 9.50 1.25 0.75 31.25 NE 2.00 8.75 6.50 0.75 0.00 0.00 18.00 ENE 0.00 4.00 5.75 2.50 0.00 0.00 12.25 E 0.25 8.25 4.75 1.00 0.00 0.00 14.25 ESE 1.75 5.75 4.00 0.25 0.00 0.00 11.75 SE 1.25 5.25 10.25 2.00 0.00 0.00 18.75 SSE 0.75 11.25 21.75 12.50 0.00 0.00 46.25 S 0.75 9.00 17.00 19.50 10.75 0.00 57.00 SSW 0.75 5.00 13.00 12.50 2.75 0.00 34.00 SW 0.50 5.25 8.25 4.25 1.00 0.00 19.25 WSW 1.25 3.00 4.75 1.00 0.25 0.00 10.25 W 1.50 1.50 3.25 4.75 0.25 0.00 11.25 WNW 0.75 5.75 4.00 7.75 1.75 0.00 20.00 NW 0.25 3.25 11.75 9.50 3.25 0.25 28.25 NNW 0.50 2.75 10.25 18.00 2.25 0.00 33.75.

TOTAL 13.25 90.25 143.50 117.00 23.75 1.25 390.00 PERIOD OF CALM (HOURS): 0.00

34 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2004 STABILITY CLASS: D ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3.50 45.50 86.75 99.50 29.00 3.50 267.75 NNE 5.75 72.25 85.75 80.50 13.00. 2.00 259.25 NE 20.25 79.00 81.00 6.25 0.00 0.00 186.50 ENE 11.75 61.25 49.00 12.75 0.00 0.00 134.75 E 11.25 65.00 43.50 16.00 0.75 0.00 136.50 ESE 8.00 41.75 36.75 4.00 0.25 0.00 90.75 SE 7.50 48.25 48.50 15.25 1.00 0.00 120.50 SSE 8.75 53.00 112.75 101.25 15.00 0.50 291.25 S *7.25 51.50 133.25 162.00 55.50 4.00 413.50 SSW 6.75 48.75 106.25 107.75 34.25 10.50 314.25 SW 7.50 34.25 25.00 15.25 0.75 0.00 82.75 WSW 4.25 19.00 18.50 11.00 2.00 3.25 58.00 W 2.75 12.75 19.25 22.25 2.75 0.00 59.75 WNW 3.25 14.75 41.00 55.75 7.25 0.50 122.50 NW 3.00 27.50 104.00 73.75 27.50 2.00 237.75 NNW 3.50 28.50 66.75 49.00 15.75 2.50 166.00 TOTAL 111.50 703.00 1058.00 832.25 204.75 28.75 2941.75 PERIOD OF CALM (HOURS): 0.00

35 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2004 STABILITY CLASS: E ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5.25 35.75 55.00 18.25 5.50 0.25 120.00 NNE 10.75 29.50 31.75 9.25 0.00 0.00 81.25 NE 27.25 44.00 11.50 0.25 0.00 0.00 83.00 ENE 11.50 57.50 19.75 2.00 0.00 0.00 90.75 E 11.00 62.50 44.50 6.00 1.50 0.25 125.75 ESE 9.25 58.00 34.75 2.25 1.25 0.25 105.75 SE 6.00 77.25 100.50 21.00 3.25 0.25 208.25 SSE 6.75 66.50 201.25 115.25 25.75 7.75 423.25 S 4.00 48.25 161.75 257.00 79.75 24.25 575.00 SSW 8.75 52.75 71.25 42.00 11.75 5.25 191.75 SW 3.75 66.75 26.00 4.25 2.00 0.75 103.50 WSW 3.75 23.00 21.00 5.25 1.00 1.25 55.25 W 1.25 26.25 23.50 2.25 0.00 0.00 53.25 WNW 1.75 18.50 44.75 3.25 0.25 0.00 68.50 NW 3.75 37.50 64.75 11.50 0.75 0.00 118.25 NNW 2.00 32.25 41.50 19.25 3.25 0.25 98.50 TOTAL 111.50 736.25 953.50 519.00 136.00 40.50 2502.00 PERIOD OF CALM (HOURS): 1.25

36 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2004 STABILITY CLASS: F ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2.50 25.00 14.00 0.00 0.00 0.00 41.50 NNE 6.50 42.25 6.50 1.00 0.00 0.00 56.25 NE 17.00 40.75 1.75 0.00 0.00 0.00 59.50 ENE 9.00 45.00 2.50 0.00 0.00 0.00 56.50 E 5.25 38.25 10.00 0.00 0.00 0.00 53.50 ESE 12.50 67.25 7.75 0.25 0.00 0.00 87.75 SE 7.00 88.75 29.25 0.75 0.50 0.00 126.25 SSE 1.00 40.50 46.50 6.75 0.50 0.00 95.25 S *3.25 19.00 15.75 9.25 3.00 0.50 50.75 SSW 5.00 17.00 4.50 2.00 0.00 0.00 28.50 SW 7.50 22.25 2.25 0.00 0.00 0.00 32.00 WSW 3.50 7.00 3.00 0.25 0.00 0.00 13.75 W 2.25 5.25 0.75 0.00 0.00 0.00 8.25 WNW 3.75 8.25 1.75 0.25 0.00 0.00 14.00 NW 5.00 24.25 6.00 0.50 0.00 0.00 35.75 NNW 4.50 26.25 9.75 0.50 0.00 0.00 41.00 TOTAL 93.00 517.00 162.00 21.50 4.00 0.50 800.50 PERIOD OF CALM (HOURS): 0.50

37 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2004 STABILITY CLASS: G ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4.00 35.00 12.50 0.50 0.00 0.00 52.00 NNE 4.75 87.00 7.75 0.00 0.00 0.00 99.50 NE 22.25 43.50 0.25

  • 0.25 0.00 0.00 66.25 ENE 12.75 42.50 0.50 0.25 0.00 0.00 56.00 E 8.25 34.25 1.25 0.00 0.00 0.00 43.75 ESE 10.25 50.00 3.00 0.25 0.00 0.00 63.50 SE 4.75 50.75 2.25 0.00 1.25 0.25 59.25 SSE 2.00 21.25 6.75 0.50 0.75 0.00 31.25 S 1.25 6.50 8.25 0.75 0.00 0.00 16.75 SSW 1.50 0.75 0.25 0.25 0.00 0.00 2.75 SW 2.50 3.50 0.00 0.00 0.00 0.00 6.00 WSW 0.50 2.75 0.00 0.25 0.00 0.00 3.50 W 0.50 0.50 0.00 0.00 0.00 0.00 1.00 WNW 3.25 1.50 0.00 0.00 0.00 0.00 4.75 NW 5.75 17.25 2.25 0.00 0.00 0.00 25.25 NNW 5.50 29.75 2.50 0.00 0.00 0.00 37.75 TOTAL 85.75 426.75 47.50 3.00 2.00 0.25 569.25 PERIOD OF CALM (HOURS): 0.00

38 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31,2004 STABILITY CLASS: ALL ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 18.50 172.25 208.00 169.50 40.00 4.75 613.00 NNE 35.25 272.50 178.00 114.50 16.50 3.00 619.75 NE 95.75 245.50 122;25 7.75 0.00 0.00 471.25 ENE 48.75 227.50 98.75 22.75 0.00 0.25 398.00 E 37.25 224.00 115.00 23.75 2.25 0.50 402.75 ESE 43.00 230.25 100.75 9.00 1.50 0.25 384.75 SE 28.00 279.75 211.50 45.50 6.00 0.50 571.25 SSE 23.00 217.75 438.50 273.75 42.50 8.25 1003.75 S 20.25 154.00 400.00 526.25 172.25 29.25 1302.00 SSW 25.00 139.75 221.75 188.75 53.75 15.75 644.75 SW 26.00 151.00 77.25 30.25 5.00 0.75 290.25 WSW 17.00 69.25 59.00 20.00 3.50 4.75 173.50 W 9.75 57.50 66.75 35.75 3.25 0.25. 173.25 WNW 16.25 62.50 105.50 74.00 9.25 0.50 268.00 NW 19.75 119.75 208.00 111.00 31.50 2.75 492.75 NNW 18.00 134.25 162.75 114.25 27.50 2.75 459.50 TOTAL 481.50 2757.50 2773.75 . 1766.75 .414.75 74.25 8268.50 Hours of Calm (<1.0 Hours of Hours of mph):2.50 Missing Bad Data:

Data: 513 785

39 of 40 SECTION IV ADDITIONAL INFORMATION

1. Unplanned or Abnormal Releases There were no unplanned or abnormal releases that occurred in 2004.
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 5, is included with this report as Attachment I. The other procedure, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program),

AP 07B-004, Revision 8, is included with this report as Attachment II.

3. Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems Temporary Modification 04-002HB is in the design process as a result of CCP 9337 modifications. Previous changes to the Zero Filtration System in Radwaste resulted in possible line overpressure problems to the Drum Dryer, as well as drain problems from the sample sink.

After further testing, it was determined that over pressurization was not a problem; however, changes are being made to allow for the use of a TMP that will throttle flow to the Drum Dryer Holdup Tank to monitor the system pressure. To address the drain problems from the sample sink, a new vent line will be installed to the SRO (Spiral Reverse Osmosis unit) so that the SRO sample line will no longer be used as a continuous process vent. - This should improve the functioning of the sample sink drain by reducing the flow into the sink.

4. Land Use Census No new locations for dose calculation were identified during this report period.
5. Radwaste Shipments Twelve 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 2004 was there an event that lead 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."

40 of 40 ATTACHMENTS TO WCGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - REPORT 28 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 5, "Offsite Dose Calculation Manual" Attachment II is AP 07B-004, Revision 8, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Attachment IlIl is AP 31A-100, Revision 5, "Solid Radwaste Process Control Program"

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