ML042950086

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Report No. 27, Annual Radioactive Effluent Release Report, January 1, 2003 - December 31, 2003.
ML042950086
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/31/2003
From:
Wolf Creek
To:
Office of Nuclear Reactor Regulation
References
27
Download: ML042950086 (40)
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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. 27 Reporting Period: January 1, 2003 - December 31, 2003

2 of 40 Table of Contents Page Executive Summary 4 Section I 8 Report of 2003 Radioactive Effluents: Liquid 8 2003 Liquid Effluents 10 2003 Liquid Cumulative Dose Summary - Table 1 12 2003 Liquid Cumulative Dose Summary - Table 2 13 Report of 2003 Radioactive Effluents: Airborne 14 2003 Gaseous Effluents 16 2003 Gaseous Cumulative Dose Summary - Table 1 18 2003 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 Waste Effluents)

Batch Releases 23 Continuous Releases 23 Doses to a Member of the Public from Activities Inside the Site Boundary 23 Additional Information 23 2003 Effluent Concentration Limits 26 2003 Solid Waste Shipments 27 Irradiated Fuel Shipments 28 Section III 29 Meteorological Data - Hours At Each Wind Speed and Direction 29 Section IV 38 Unplanned or Abnormal Releases 38 Offsite Dose Calculation Manual 38 Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems 38 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 078-003, Revision 5, aOffsite Dose Calculation Manual" Attachment II - WCGS Procedure AP 078-004, Revision 5, uOffsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Attachment III - WCGS Procedure AP 31A-1 00, Revision 4, "Solid Radwaste Process Control Program"

4 of 40 EXECUTIVE

SUMMARY

This Annual Radioactive Effluent Release Report (Report # 27) documents the quantities of liquid and gaseous effluents and solid waste released by the Wolf Creek Generating Station (WCGS) from January 1, 2003, through December 31, 2003. 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, 1II, 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 2003, 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 2003.

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 DIQ 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 2003.

Section II --- Section II includes supplemental information on continuous and batch releases, calculated doses, and solid waste disposal. There were 87 gaseous batch releases in 2003 versus 77 in 2002. There were 76 liquid batch releases in 2003 versus 71 in 2002. WCGS released 0.020 curies in liquid releases during 2003 versus 0.018 curies in 2002, excluding gas and tritium. Continuous release pathways remained the same as previous years and all continuous releases were monitored. There was a missed surveillance as a result of a valve misalignment on the sample isolation valve for Gas Decay Tank #3. The event is further discussed in the Performance Improvement Request (PIR) report information.

The report contains information on the following PIRs.

PIR 2003-0173 - On 1-29-2003 the Balance of Plant Operator (BOP) in the Control Room taking log readings noted that monitor GHRE-10A was in accident isolation which switches sample suction from room air rather than the Radwaste Vent effluent stream. The sampling as required by ODCM Table 3-2 was not met for 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> since the sample air was coming from room air.

PIR 2003-0529 - Support Engineering incorrectly reported a previous flow rate of 4627 cfm for the containment mini-purge unit as the current flow to Operations and Chemistry. The correct current flow should have been reported as 4260 cfm.

PIR 2003-0848 - During the channel calibration portion of STS IC-474B, "Channel Calibration Unit Ventilation System Radiation Monitor GTRE21B," it was discovered that the pump diaphragm had a hole in it. The sample air passing by the detector was diluted due to the pump diaphragm hole being upstream of the pump and the detector being downstream of the pump. It is unknown how long the hole in the pump diaphragm was present before being discovered.

5 of 40 PIR 2003-1882 - Waste Gas Decay Tank (WGDT) #3 decreased in pressure-and WGDT #8 increased in pressure during a Volume Control Tank (VCT) Purge. The purge was secured and all reach rod valves that could cause a decrease in pressure in the gas decay tanks were verified closed. Work Order 03-253665 was generated to replace the relief valve.

PIR 2003-2158 - On 7-17-2003 the "A" waste gas compressor moisture separator tank relief valve was being replaced. When the relief valve flange was broken loose water commenced spraying from the flange area. The flange bolts were retightened. This relief valve discharges into WGDT #8 that contained - 5 psig pressure. WGDT #8 pressure decreased - 0.4 psig during this evolution.

PIR 2003-2580 - Containment Atmosphere Monitors GTRE3I and GTRE32 were changed 8 2003. The particulate filters were discolored. Gamma scans'performed on the filters indicated no gamma activity. The discoloration of the filters is not indicative of Reactor Coolant System (RCS) leakage. The filters were sent off for boron and iron analysis and the results were inconclusive.

PIR 2003-2805 - The sample isolation valve for WGDT #3 was found in the open position by a Chemistry technician on 9-22-2003. The chemistry technician was performing STS CH-009, Waste Gas Decay Tank Curie Content Surveillance. The last sample from WGDT #3 taken for STS CH-009 was on 9-5-2003. After WGDT #3 was sampled, a curie content sample was obtained from WGDT #8 the same day. It is probable that the sample obtained for WGDT #8 on 9-5-2003 was not representative of what was in that tank, but rather a composite of WGDT #3 and WGDT #8 since the sample isolation valve for WGDT #3 was still in the open position. Once the sample isolation valve for WGDT #3 was closed the total curie content surveillance for WGDT

  1. 8 was completed. The consequence of the valve alignment is a missed surveillance.

PIR 2003-3555 - The low setpoint for WGDT permit 2003165 was incorrect. The correct setpoint to use was 7.97E+02 pLCi/sec, but 8.83E+02 ptCi/sec was recorded. The calculated low setpoint was 7.97E+02 ptCi/sec. The low setpoint for the Radwaste Vent was 8.83E+02 pCi/sec. The release was performed using a less conservative setpoint, but the low setpoint was not compromised due to the built-in conservatism of the setpoint calculation.

PIR 2003-3591 - The high setpoint for containment purge permit 2003178 for GTRE-22 and GTRE-33 was recorded as 1.02E-02 ptCi/cc and the correct setpoint should have been recorded as 1.OOE-02 piCi/cc. This incorrect setpoint 'could have prevented the Control Room from receiving the Hi-Hi Process Radiation Alarm prior to the ESFAS (Engineering Safety Feature Actuation System) isolating the containment purge. The low setpoint was not jeopardized during the release.

Section III --- Section III documents WCGS meteorological data for wind speed, wind direction, and atmospheric stability. WCGS did not meet the Regulatory Guide 1.23, 'Meteorological Programs in Support of Nuclear Power Plants" requirement for having at least 90%

meteorological data recovery for 2003. PIR 2004-0620 has been written to address this and the resolution will be presented in the 2005 Annual Report.

6of40 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. PIR 2003-2158 documents the decrease of -0.4 psig in WGDT #8 during an evolution to replace the "A" waste gas compressor moisture separator tank relief valve. Water sprayed out when the flange was loosened causing the decrease in pressure. The subsequent increase in the GHRE-10B monitor reading was determined to be from Chemistry sampling activities. There was no uncontrolled or unmonitored release in either circumstance. No ODCM limits were exceeded.

No changes or 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 Il-AP 07B-004, revision 5, uOffsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Attachment I11-AP 31A-100, revision 4, 'Solid Radwaste Process Control Program"

8 of 40 SECTION I REPORT OF 2003 RADIOA CTIVE EFFLUENTS: LIQUID Unit Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 1.09E-03 1.87E-03 alpha)
2. Average Diluted Concentration During LCi/ml 6.69E-11 1.17E-10 Period
3. Percent of Applicable Limit (1)  % 2.17E-02 3.73E-02 B. Tritium
1. Total Release Ci 3.11 E+02 3.24E+02
2. Average Diluted Concentration During pCi/ml 1.91 E-05 2.03E-05 Period
3. Percent of Applicable Limit (2) (ECL) 1.91 E+00 2.03E+00 C. Dissolved and Entrained Gases
1. Total Release Ci 3.30E-03 3.54E-03
2. Average Diluted Concentration During pCi/ml 2.03E-1 0 2.22E-1 0 Period
3. Percent of Applicable Limit (3) 1.02E-04 1.11 E-04 D. Gross Alpha Radioactivity
1. Total Release Ci 4.23E-06 0.OOE+00 E. Volume of Waste Released (prior to Liters 4.52E+07 9.42E+07 dilution)

F. Volume of Dilution Water Used Liters 1.62E+10 1.59E+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:

(Average Diluted Concentration) (100)

% of Applicable Limit =

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

3) This value is derived by the following formula:

%of Applicable Limit - (AverageDiluted Concentration) (100)

(2E --04 from ODCM Section 2.1)

9 of 40 REPORT OF 2003 RADIO CTIVE EFFLUENTS: LIQUID Unit Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 4.75E-03 1.25E-02 alpha
2. Average Diluted Concentration During pCi/ml 1.88E-10 5.77E-1 0 Period
3. Percent of Applicable Limit (1)  % 9.50E-02 2.50E-01 B. Tritium
1. Total Release Ci 7.11 E+02 1.52E+02
2. Average Diluted Concentration During PCi/ml 2.82E-05 7.02E-06 Period
3. Percent of Applicable Limit (2) (ECL)  % 2.82E+00 7.02E-01 C. Dissolved and Entrained Gases
1. Total Release Ci 3.89E-02 2.32E-02
2. Average Diluted Concentration During pCi/ml 1.54E-09 1.07E-09 Period
3. Percent of Applicable Limit (3) 7.71 E-04 5.34E-04 D. Gross Alpha Radioactivity
1. Total Release Ci 8.88E-05 1.53E-05 E. Volume of Waste Released (prior to liters 3.53E+07 8.78E+07 dilution)

F. Volume of Dilution Water Used liters 2.52E+10 2.16E+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:

% f A L (Average Diluted Concentration) (100)

AppBicable L2mit P oof 1 (MPC or ECL, Appendix B, Table 2, l OCFR20)

3) This value is derived by the following formula:

(Average Diluted Concentration) (100)

(2E - 04 from ODCM Section 2.1)

10 of 40 2003 LIQUID EFFLUENTS ntinuous Mode Batch Mode Nuclides Unit Quarter I Quarter 2 Quarter I Quarter 2 Released H-3 Ci 1. 1E+00 7.55E-01 3.1 OE+02 3.23E+02 Mn-54 Ci <2.24E-02 <4.68E-02 <2.37E-04 <3.20E-04 Fe-55 Ci <4.47E-02 <9.35E-02 <4.74E-04 <6.39E-04 Fe-59 Ci <2.24E-02 <4.68E-02 <2.37E-04 <3.20E-04 Co-57 Ci n/a n/a n/a 1 .42E-06 Co-58 Ci <2.24E-02 <4.68E-02 1.82E-04 5.88E-05 Co-60 Ci <2.24E-02 <4.68E-02 1.1 7E-04 1.96E-04 Zn-65 Ci <2.24E-02 <4.68E-02 <2.37E-04 <3.20E-04 Sr-89 Ci <2.24E-03 <4.68E-03 <2.37E-05 <3.20E-05 Sr-90 Ci <2.24E-03 <4.68E-03 <2.37E-05 <3.20E-05 Mo-99 Ci <2.24E-02 <4.68E-02 <2.37E-04 <3.20E-04 Sb-126 Ci n/a n/a n/a 2.53E-06 Sb-125 Ci n/a n/a 7.54E-04 1.51 E-03 1-131 Ci <4.47E-02 <9.35E-02 <4.74E-04 <6.39E-04 1-133 Ci n/a n/a 1.30E-06 n/a Cs-1 34 Ci <2.24E-02 <4.68E-02 1.48E-06 2.24E-06 Cs-137 Ci <2.24E-02 <4.68E-02 3.14E-05 8.97E-05 Ce-141 Ci <2.24E-02 <4.68E-02 <2.37E-04 <3.20E-04 Ce-144 Ci <2.24E-02 <4.68E-02 <2.37E-04 <3.20E-04 Gross Alpha Ci <4.47E-03 <9.35E-03 4.23E-06 <6.39E-05 Ar-41 Ci <4.47E-01 <9.35E-01 <4.74E-03 <6.39E-03 Kr-85M Ci <4.47E-01 <9.35E-01 <4.74E-03 <6.39E-03 Kr-85 Ci <4.47E-01 <9.35E-01 <4.74E-03 7.44E-04 Kr-87 Ci <4.47E-01 <9.35E-01 <4.74E-03 <6.39E-03 Kr-88 Ci <4.47E-01 <9.35E-01 <4.74E-03 <6.39E-03 Xe-131M Ci <4.47E-01 <9.35E-01 <4.74E-03 <6.39E-03 Xe-1 33M Ci <4.47E-01 <9.35E-01 <4.74E-03 <6.39E-03 Xe-133 Ci <4.47E-01 <9.35E-01 3.30E-03 2.80E-03 Xe-1 35M Ci <4.47E-01 <9.35E-01 <4.74E-03 <6.39E-03 Xe-135 Ci <4.47E-01 <9.35E-01 <4.74E-03 <6.39E-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 2003 LIQUID EFFLUENTS itinuous Mode Batch Mode Nuclides Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Released H-3 Ci 5.43E-01 1.41 E+00 7.1 OE+02 1.51 E+02 Mn-54 Ci <1.70E-02 <4.33E-02 8.68E-06 7.52E-07 Fe-55 Ci <3.39E-02 <8.66E-02 <1.40E-03 -<1.19E-03 Fe-59 Ci <1.70E-02 <4.33E-02 <7.02E-04 <5.97E-04 Co-57 Ci n/a n/a n/a 1.34E-05 Co-58 Ci <1.70E-02 <4.33E-02 1.24E-05 5.01 E-03 Co-60 Ci <1.70E-02 <4.33E-02 4.30E-04 5.1 OE-04 Zn-65 Ci <1.70E-02 <4.33E-02 <7.02E-04 <5.97E-04 Sr-89 Ci <1.70E-03 <4.33E-03 <7.02E-05 <5.97E-05 Sr-90 Ci <1.70E-03 <4.33E-03 <7.02E-05 <5.97E-05 Mo-99 Ci <1.70E-02 <4.33E-02 <7.02E-04. <5.97E-04 Sb-1 24 Ci n/a n/a n/a 2.36E-05 Sb-1 25 Ci n/a n/a 3.65E-03 *6.19E-03 1-131 Ci <3.39E-02 <8.66E-02 2.13E-04 1.77E-04 1-132 Ci n/a n/a n/a 2.23E-06 1-133 Ci n/a n/a n/a 2.97E-05 Cs-1 34 Ci <1.70E-02 <4.33E-02 9.90E-06 8.46E-06 Cs-1 37 Ci <1.70E-02 <4.33E-02 5.84E-05 4.34E-05 Ce-141 Ci <1.70E-02 <4.33E-02 <7.02E-04 <5.97E-04 Ce-144 Ci <1.70E-02 <4.33E-02 <7.02E-04 <5.97E-04 Cr-51 Ci n/a n/a 3.65E-05 4.92E-04 Rb-88 Ci n/a n/a 3.27E-04 n/a Ba-1 39 Ci n/a n/a 7.OOE-06 n/a Mn-56 Ci n/a n/a n/a :3.66E-06 Nb-97 Ci n/a n/a n/a 7.39E-06 Sn-117m Ci n/a n/a n/a 6.83E-06 Gross Alpha Ci <3.39E-03 <8.66E-03 8.88E-05 1.53E-05 Ar-41 Ci <3.39E-01 <8.66E-01 <1.40E-02 <1.1 9E-02 Kr-85M Ci <3.39E-01 <8.66E-01 3.91 E-05 <1.1 9E-02 Kr-85 Ci <3.39E-01 <8.66E-01 <1.40E-02 <1.19E-02 Kr-87 Ci <3.39E-01 <8.66E-01 <1.40E-02 <1.19E-02 Kr-88 Ci <3.39E-01 <8.66E-01 4.48E-05 <1 .19E-02 Xe-131M Ci <3.39E-01 <8.66E-01 5.09E-05 <1.1 9E-02 Xe-1 33M Ci <3.39E-01 <8.66E-01 5.13E-04 3.84E-04 Xe-1 33 Ci <3.39E-01 <8.66E-01 3.62E-02 2.15E-02 Xe-1 35M Ci <3.39E-01 <8.66E-01 <1.40E-02 <1.19E-02 Xe-1 35 Ci <3.39E-01 <8.66E-01 2.08E-03 1.32E-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.

12 of 40 LIQUID CUMULATIVE DOSE

SUMMARY

(2003) TABLE I QUARTER I OF 2003 (mrem) ODCM CALCULATED ODCM LIMIT(1)  % OF LIMIT DOSE TOTAL DOSE FOR BONE 1.67E-04 5.00E+00 3.34E-03 TOTAL DOSE FOR LIVER 4.06E-02 5.00E+00 8.12E-01 TOTAL DOSE FOR TOTAL BODY 4.05E-02 1.50E+00 2.70E+00 TOTAL DOSE FOR THYROID 4.04E-02 5.00E+00 8.07E-01 TOTAL DOSE FOR KIDNEY 4.04E-02 5.00E+00 8.09E-01 TOTAL DOSE FOR LUNG 4.04E-02 5.OOE+00 8.08E-01 TOTAL DOSE FOR GI-LLI 4.04E-02 5.OOE+00 8.08E-01 QUARTER 2 OF 2003 (mrem)

TOTAL DOSE FOR BONE 2.96E-04 5.00E+00 5.92E-03 TOTAL DOSE FOR LIVER 3.06E-02 5.00E+00 6.12E-01 TOTAL DOSE FOR TOTAL BODY 3.04E-02 1.50E+00 2.03E+00.

TOTAL DOSE FOR THYROID 3.02E-02 5.00E+00 6.04E-01 TOTAL DOSE FOR KIDNEY 3.03E-02 5.OOE+00 6.06E-01 TOTAL DOSE FOR LUNG 3.02E-02 5.00E+00 6.04E-01 TOTAL DOSE FOR GI-LLI 3.02E-02 5.OOE+00 6.04E-01 QUARTER 3 OF 2003 (mrem)

TOTAL DOSE FOR BONE 2.18E-04 5.OOE+00 4.36E-03 TOTAL DOSE FOR LIVER 5.43E-02 5.00E+00 1.09E+00 TOTAL DOSE FOR TOTAL BODY 5.42E-02 1.50E+00 3.62E+00 TOTAL DOSE FOR THYROID 5.44E-02 5.OOE+00 1.09E+00 TOTAL DOSE FOR KIDNEY 5.41 E-02 5.OOE+00 1.08E+00 TOTAL DOSE FORLUNG 5.40E-02 5.OOE+00 1.08E+00 TOTAL DOSE FOR GI-LLI 5.41 E-02 5.00E+00 1.08E+00 QUARTER 4 OF 2003 (mrem)

TOTAL DOSE FOR BONE 2.78E-04 5.OOE+00 5.56E-03 TOTAL DOSE FOR LIVER 8.67E-02 5.OOE+00 1.73E+00 TOTAL DOSE FOR TOTAL BODY 8.66E-02 1.50E+00 5.77E+00 TOTAL DOSE FOR THYROID 8.73E-02 5.00E+00 1.75E+00 TOTAL DOSE FOR KIDNEY 8.64E-02 5.00E+00 1.73E+00 TOTAL DOSE FOR LUNG 8.63E-02 5.00E+00 1.73E+00 TOTAL DOSE FOR GI-LLI 8.67E-02 5.OOE+00 1.73E+00 TOTALS FOR 2003 (mrem)

TOTAL DOSE FOR BONE 9.59E-04 1.OOE+01 9.59E-03 TOTAL DOSE FOR LIVER 2.12E-01 1.00E+01 2.12E+00 TOTAL DOSE FOR TOTAL BODY 2.12E-01 3.OOE+00 7.06E+00 TOTAL DOSE FOR THYROID 2.12E-01 1.OOE+01 2.12E+00 TOTAL DOSE FOR KIDNEY 2.11 E-01 1.OOE+01 2.11 E+00 TOTAL DOSE FOR LUNG 2.11 E-01 1.OOE+01 2.11 E+00 TOTAL DOSE FOR GI-LLI 2.11 E-01 1.OOE+01 2.I1 E+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 s 5.0 mRem per quarter and 10.0 mRem per year.

13 of 40 LIQUID CUMULATIVE DOSE

SUMMARY

(2003) TABLE 2 A. Fission and Activation Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Products (not including H-3, gases, alpha)

1. Total Release -(Ci) 1.09E-03 1.86E-03 4.75E-03 1.25E 2.02E-02
2. Maximum Organ Dose (mRem) 2.34E-04 4.08E-04 4.1 OE-04 1.03E-03 1.45E-03
3. Organ Dose Limit (mRem) 5.OOE+O0 5.OOE+00 5.OOE+O0 5.OOE+00 1.OOE+01
4. Percent of Limit 4.68E-03 8.17E-03 8.20E-03 2.07E-02 1.45E-02 B. Tritium
1. Total Release - (Ci) 3.1IIE+02 3.24E+02 7.1IIE+02 1.52E+02 1.50E+03
2. Maximum Organ Dose (mRem) -4.04E-02 3.02E-02 I5.40E-02 8.62E-02 2.11 E-01
3. Organ Dose Limit (mRem) 5.OOE+00 5.OOE+O0 5.OOE+00 5.OOE+00 1.OOE+01
4. Percent of Limit 8.07E-01 6.04E-01 I1.08E+00 1.72E+O0 2.I1 E+O0 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 2003 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 1 2 A. Fission and Activation Gases

1. Total Release Ci 3.28E-01 7.72E-01
2. Average Release Rate for Period pCi/sec 4.21 E-02 9.82E-02
3. Percent of ODCM Limit (1)  % 4.14E-03 5.68E-03 B. Iodine
1. Total Release Ci O.OOE+00 O.OOE+00
2. Average Release Rate for Period pCi/sec O.OOE+00 O.OOE+00
3. Percent of Applicable Limit (2)  % O.OOE+00 O.OOE+00 C. Particulates
1. Particulates with Half-lives > 8 days Ci O.OOE+00 O.OOE+00
2. Average Release Rate for Period pCi/sec O.OOE+00 O.OOE+00
3. Percent of ODCM Limit (3)  % O.OOE+00 0.OOE+00
4. Gross Alpha Radioactivity Ci O.OOE+00 O.OQE+00 D. Tritium
1. Total Release Ci 9.76E+00 1.31 E+01
2. Average Release Rate for Period pCilsec 1.26E+00 1.66E+00
3. Percent of ODCM Limit (4)  % 9.25E-02 1.23E-01 NOTES:
1) The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

% f 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:

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

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

% ofODCM 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:

(Highest Organ Dose Due to H -3)(100)

%of ODCM Limit mr 7.5 rnrem

15 of40 REPORT OF 2003 RADIOACTIVE EFFLUENTS: AIRBORNI Quarter Quarter" Unit 3 .4 A. Fission and Activation Gases

1. Total Release Ci 1.44E+00 2.13E+00
2. Average Release Rate for Period pCi/sec 1.81 E-01 2.68E-01
3. Percent of ODCM Limit (1) 1.41 E-02 '4.38E-03 B. lodines
1. Total Iodine-131 Ci 0.OOE+00 0.OOE+00
2. Average Release Rate for Period pCi/sec 0.00E+00 0.00E+00
3. Percent of Applicable Limit (2) 0.OOE+00 0.OOE+00 C. Particulates
1. Particulates with Half-lives > 8 days Ci 0.OOE+00 3.72E-06
2. Average Release Rate for Period PCi/sec 0.OOE+00 *4.68E-07
3. Percent of ODCM Limit (3) 0.OOE+00 2.64E-05
4. Gross Alpha Radioactivity Ci 0..OOE+00
1. Total Release Ci I1.25E+01 9.27E+00
2. Average Release Rate for Period , pCi/sec I .58E+00 1.1 7E+00
3. Percent of ODCM Limit (4) I1.20E-01 8.73E-02 NOTES:
1) The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

% of ODCM Limit - (QtrlyTotal Beta Airdose)(100) or(Qtrly Total Gama 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:

%ofODCM Limit-=(Total Curies of lodine-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 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)(1 00) 7.5 mrem

16 of 40 2003 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission and Activation Gases Ar-41 Ci n/a n/a 3.1 OE-01 4.37E-01 Kr-85 Ci n/a n/a n/a 3.17E-01 Kr-85M Ci n/a n/a n/a n/a Kr-87 Ci <2.09E+01 <2.08E+01 1.35E-03 <3.25E-02 Kr-88 Ci <1.77E+01 <1.76E+01 <1.95E-02 <2.76E-02 Xe-1 31M Ci n/a n/a n/a n/a Xe-133 Ci <1.39E+01 <1.38E+01 8.07E-03 1.81 E-02 Xe-1 33M Ci <4.46E+01 <4.44E+01 <4.90E-02 6.54E-05 Xe-135 Ci <5.42E+00 <5.39E+00 <5.95E-03 1.21 E-05 Xe-1 38 Ci <4.28E+02 <4.26E+02 8.05E-03 <6.67E-01 Total Ci O.OOE+00 O.OOE+00 3.27E-01 7.72E-01
2. Halogens (Gaseous) 1-131 Ci <2.65E-04 <2.64E-04 <2.91 E-07 <4.13E-07 1-133 Ci <2.65E-02 <2.64E-02 <2.91 E-05 <4.13E-05 Total Ci 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00
3. Particulates and Tritium H-3 Ci 9.14E+00 1.08E+01 6.18E-01 2.25E+00 Mn-54 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Fe-59 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Co-58 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Co-60 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Zn-65 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Mo-99 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Cs-1 34 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Cs-1 37 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Ce-141 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Ce-1 44 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Sr-89 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Sr-90 Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Gross Alpha Ci <2.65E-03 <2.64E-03 <2.91 E-06 <4.13E-06 Total Ci 9.14E+00 1.08E+01 6.18E-01 2.25E+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.

17 of 40 2003 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission and Activation Gases Ar-41 Ci n/a n/a 1.07E+00' 2.58E-01 Kr-85 Ci n/a n/a i.06E-02 1.71 E-01 Kr-85M Ci n/a n/a n/a n/a Kr-87 Ci <2.14E+01 <2.19E+01 <7.38E-02 5.82E-03 Kr-88 Ci <1.82E+01 <1.86E+01 <6.27E-02 <1.51 E+00 Xe-131M Ci n/a n/a 1.56E-05 ' 2.91 E-04 Xe-133 Ci 3.54E-01 1.57E+00 7.28E-03 '6.61 E-02 Xe-1 33M Ci <4.57E+01 <4.68E+01 <1.58E-01 2.49E-04 Xe-1 35 Ci <5.55E+00 6.OOE-02 <1.92E-02 1.79E-04 Xe-1 38 Ci <4.39E+02 <4.49E+02 <1.52E+00 <3.66E+01 Total Ci 3.54E-01 1.63E+00 '1.09E+00 5.02E-01
2. Halogens (Gaseous) 1-131 Ci <2.27E-04 <2.78E-04 <9.38E-07 '.-<2.27E-05 1-133 Ci <2.27E-02 <2.78E-02 <9.38E-05 <2.27E-03 Total Ci O.OOE+00 O.OE+00 O.OOE+00 0.OOE+00
3. Particulates and Tritium H-3 Ci 9.59E+00 7.02E+00 2.95E+00. 2.25E+00 Mn-54 Ci <2.72E-03 <2.78E-03 <9.38E-06 ' <2.27E-04 Fe-59 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Co-58 Ci <2.72E-03 3.72E-06 <9.38E-06. <2.27E-04 Co-60 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Zn-65 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Mo-99 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Cs-1 34 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Cs-1 37 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Ce-141 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Ce-1 44 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Sr-89 Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Sr-90 Ci <2.72E-03 <2.78E-03 <9.38E-06 I<2.27E-04 Gross Alpha Ci <2.72E-03 <2.78E-03 <9.38E-06 <2.27E-04 Total Ci 9.59E+00 7.02E+00 2.95E+00 2.25E+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.

18 of 40 GASEOUS CUMULATIVE DOSE

SUMMARY

(2003) TABLE I QUARTER 1 OF 2003 (mRem) ODCM CALCULATED ODCM LIMIT  % OF LIMIT DOSE (1)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 6.91 E-03 7.50E+00 9.21 E-02 TOTAL DOSE FOR TOTAL BODY 6.91 E-03 7.50E+00 9.21 E-02 TOTAL DOSE FOR THYROID 6.91 E-03 7.50E+00 9.21 E-02 TOTAL DOSE FOR KIDNEY 6.91 E-03 7.50E+00 9.21 E-02 TOTAL DOSE FOR LUNG 6.91 E-03 7.50E+00 9.21 E-02 TOTAL DOSE FOR GI-LLI 6.91 E-03 7.50E+00 9.21 E-02 QUARTER 2 OF 2003 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.00E+00 TOTAL DOSE FOR LIVER 9.24E-03 7.50E+00 1.23E-01 TOTAL DOSE FOR TOTAL BODY 9.24E-03 7.50E+00 1.23E-01 TOTAL DOSE FOR THYROID 9.24E-03 7.50E+00 1.23E-01 TOTAL DOSE FOR KIDNEY 9.24E-03 7.50E+00 1.23E-01 TOTAL DOSE FOR LUNG 9.24E-03 7.50E+00 1.23E-01 TOTAL DOSE FOR GI-LLI 9.24E-03 7.50E+00 1.23E-01 QUARTER 3 OF 2003 (mRem)

TOTAL DOSE FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE FOR LIVER 8.87E-03 7.50E+00 1.18E-01 TOTAL DOSE FOR TOTAL BODY 8.87E-03 7.50E+00 1.18E-01 TOTAL DOSE FOR THYROID 8.87E-03 7.50E+00 1.18E-01 TOTAL DOSE FOR KIDNEY 8.87E-03 7.50E+00 1.18E-01 TOTAL DOSE FOR LUNG 8.87E-03 7.50E+00 1.18E-01 TOTAL DOSE FOR GI-LLI 8.87E-03 7.50E+00 1.18E-01 QUARTER 4 OF 2003 (mRem)

TOTAL DOSE FOR BONE 8.04E-07 7.50E+00 1.07E-05 TOTAL DOSE FOR LIVER 6.55E-03 7.50E+00 8.73E-02 TOTAL DOSE FOR TOTAL BODY 6.55E-03 7.50E+00 8.73E-02 TOTAL DOSE FOR THYROID 6.55E-03 7.50E+00 8.73E-02 TOTAL DOSE FOR KIDNEY 6.55E-03 7.50E+00 8.73E-02 TOTAL DOSE FOR LUNG 6.55E-03 7.50E+00 8.73E-02 TOTAL DOSE FOR GI-LLI 6.55E-03 7.50E+00 8.73E-02 TOTALS FOR 2003 (mRem)

TOTAL DOSE FOR BONE 8.04E-07 1.50E+01 5.36E-06 TOTAL DOSE FOR LIVER 3.16E-02 1.50E+01 2.11E-01 TOTAL DOSE FOR TOTAL BODY 3.16E-02 1.50E+01 2.11E-01 TOTAL DOSE FOR THYROID 3.16E-02 1.50E+01 2.11E-01 TOTAL DOSE FOR KIDNEY 3.16E-02 1.50E+01 2.11E-01 TOTAL DOSE FOR LUNG 3.16E-02 1.50E+01 2.11 E-01 TOTAL DOSE FOR GI-LLI 3.16E-02 1.50E+01 2.11 E-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

(2003) TABLE 2 Nuclides Released Quarter I Quarter 2 Quarter 3 Quarter 4 Total A. Fission and Activation Gases

1. Total Release - (Ci) 3.27E-01 7.72E-01 1.44E+00 2.1 3E+00 4.67E+00
2. Total Gamma Airdose (mRad) 2.07E-04 2.84E-04 7.03E-04
  • 2.19E-04 1.41 E-03
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 4.14E-03 5.68E-03 1.41 E-02 4.37E-03 1.41 E-02
5. Total Beta Airdose (mRad) 7.51 E-05 I1.44E-04 2.73E-04 2.17E-04 7.09E-04
6. Beta Airdose Limit (mRad) 1.OOE+01 I .OOE+01 1.OOE+01 1.00E+01 2.OOE+01
7. Percent of Beta Airdose 7.51 E-04 I1.44E-03 2.73E-03 2.17E-03 . 3.54E-03 Limit (mRad)

B. Particulates

1. Total Particulates (Ci) O.OOE+O0 0.OOE+00 O.OOE+00 3.72E-06 3.72E-06
2. Maximum Organ Dose (mRem) O.OOE+O0 O.OOE+O0 O.OOE+00 I..98E-06 1.98E-06
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+O0 O.OOE+O0 2.64E-05 1.32E-05 C. Tritium
1. Total Release (Ci) 9.76E+00 1.31 E+01 1.25E+01 9.27E+00 4.46E+01
2. Maximum Organ Dose (mRem) 6.94E-03 9.25E-03 8.87E-03 6.55E-03 3.16E-02
3. Organ Dose Limit (mRem) 7.50E.00 7.50E+00 7.50E+00 7.50E+0O 1.50E+01
4. Percent of Limit 9.25E-02 1.23E-01 1.18E-01 8.73E-02 2.11E-01 D. Iodine
1. Total 1-131, 1-133 (Ci) O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00
2. Maximum Organ Dose (mRem) O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00
3. Organ Dose Limit (mRem) 7.50E+00 7.50E+00 7.50E+00 7.50E+O0 1.50E+01
4. Percent of Limit 'O.OOE+00 O.OOE+00 O.OOE+00 . .O.OOE+00 O.OOE+00 This table is included to show the correlation between Curies released and the associated calculated maximum organ dose. The maximum organ dose is calculated using Wolf Creek ODCM methodology which assumes that an individual actually resides at the release point. ODCM Section 3.2.2 organ dose limits are used.

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/ml total activity.

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

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and
b. During any calendar year to less than or equal to 3 mrems, to the whole body and to less than or equal to 10 mrems to any organ.

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

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and
b. For lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

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

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

B.3 The dose from lodine-1 31, lodine-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 l.A.

Air - covered in Section l.B.

21 of 40

3. Average Energy Average energy of fission and activation gaseous effluents is not applicable. See ODCIVI 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 L.S. H-3 Waste Monitor Each Batch S.A.C. Gross Alpha Tanks P O.S.L. Sr-89. Sr-90
2. Continuous Daily P.H.A. Principal Gamma Emitters Releases Grab Sample

. P.H.A. 1-131

a. Steam Generator M Dissolved and entrained Blowdown Grab Sample P.H.A. Gases (Gamma Emitters)
b. Turbine Building Daily L.S. H-3 Sump/Waste Water Grab Sample Treatment S.A.C. Gross Alpha O.S.L. Sr-89, Sr-90
c. Lime Sludge Pond Daily Grab Sample O.S.L. Fe-55 P = prior to each batch S.A.C. = scintillation alpha counter M = monthly O.S.L. = performed by an offsite laboratory L. S. = Liquid scintillation detector P.H.A. = gamma spectrum pulse height analysis using a High Purity Germanium detector

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 87 gaseous batch releases during the reporting period. The longest gaseous batch release lasted 9,795 minutes, while the shortest lasted 58 minutes.. The average release lasted 734 minutes with a total gaseous batch release time of 63,828 minutes.

There were 76 liquid batch releases during the reporting period. The longest liquid batch release lasted 382 minutes, while the shortest lasted 51 minutes. The average release lasted 202 minutes with a total liquid batch release time of 15,350 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 3.41 E-01 mRem William Allen White Building Workers 7.86E-03 mRem Access Road Users 3.49E-03 mRem Lake Use 4.90E-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 3528 hours0.0408 days <br />0.98 hours <br />0.00583 weeks <br />0.00134 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 294 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 2003-0173 - On 1-29-03 the BOP Operator was taking log readings on the RM-1 1 and noticed monitor GHRE-1 OA was in accident isolation mode so the monitor was pulling sample from room air rather than from the Radwaste Vent effluent stream. The monitor was reset and flow was re-established through GHRE-10A. A review of the RM-11 showed that GHRE-10A went into the "purging" mode at 1-28-03/2129. I&C personnel were performing STS SP-010B, Channel Operability Test, on GHRE-10B from 1900 to -2300 on 1-28-03. The technicians were performing a database download on

24 of 40 GHRE-10B at a time when the detector counts were high. As part of the downloading process the GHRE-10B software enables the detection circuitry. When the detector circuitry was enabled with existing high counts, the GHRE-10B signal was at a sufficient level to actuate the 'alert" alarm. When GHRE-10B goes into "alert", GHRE-10A goes into "purge" mode. We did not have sampling as required by the ODCM Table 3-2 for

-6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> when the sampling air was being pulled from room air.

PIR 2003-0529 - The letter sent as a result of STS PE-003, Emergency Exhaust System Flow Rate and Combined Pressure Drop Test, contained incorrect flow rate data for the Containment Purge unit. It had a recorded value of 4627 cfm as opposed to the current value of 4260 cfm. This incorrect flow rate was used in the low setpoint calculation for containment purge permit 2003030. The higher flow rate used in the calculation lent itself to a more conservative setpoint. The low setpoint used on the permit was 3.87E-05 uCi/cc based on 4627 cfm. The correct low setpoint would have been 4.23E-05 uCi/cc using 4260 cfm.

PIR 2003-0848 - On 3-28-2003 during the channel calibration portion of STS IC-474B, Channel Calibration Unit Ventilation System Radiation Monitor GTRE21 B, it was discovered that the pump diaphragm had a hole in it. The last time a procedure was performed that would have detected a hole in the pump diaphragm was 2-25-2003.

Chemistry reads the flow from the local rotometer and this flow reading is used in the calculation that determines the total volume of sample that passed through the applicable filter. The rotometer is on the discharge side of the pump and registers all flow passing through it, including any dilution air. It is unknown when the hole in the diaphragm developed.

PIR 2003-1882 - On June 23, 2003 following a VCT purge and hydrogen recombining to GDT #3 it was noted that the pressure in GDT #8 increased and the pressure in GDT #3 decreased. The pressure in GDT #3 was 13 psig and the pressure in GDT #8 was 1.8 psig at 0830/6-23-2003. Once the waste gas system was secured readings were taken on the eight gas decay tanks and monitored during the shift. The readings remained stable and at 0600/6-24-2003 the reading was 11.4 psig on GDT #3 and 3.6 psig on GDT

  1. 8. It was determined that the waste gas compressor relief valve could have caused the increase in GDT #8 and the decrease in GDT #3. Work Order 03-253665 was generated to investigate a potential hardware failure of the waste gas compressor relief valve.

Troubleshooting determined the moisture separator tank relief valve for "A" compressor was intermittently leaking by based on gas decay tank pressure changes and the relief valve was changed.

PIR 2003-2580 - Containment Atmosphere filters were changed on GTRE31 and GTRE32 on 8-29-2003; The particulate filters were discolored with a "dirty tan" color. A gamma scan was performed on the particulate filter from GTRE-31 and there was no activity detected. Filters discolored with rust or boric acid may be an indication of RCS leakage. The discoloration on the filters is not indicative of RCS leakage. The unit tripped on 8-18-2003. On 8-23-2003 the unit reduced power to 80%. These events could have contributed to the color on the filters as well. The filters were sent to Sherry Laboratories for iron and boron analysis so a baseline could be established. We are to complete 3 months of baseline sampling during routine operation and then perform periodic analysis to ensure the baseline hasn't changed. We didn't use the filters from the outage as a part of our baseline study so this PIR is still open. The conclusion will be included in the 2005 Annual Radioactive Effluent Report.

25 of 40 PIR 2003-2805 - On 9-22-2003 a chemistry technician found the sample isolation valve open for Gas Decay Tank #3. This tank was last sampled 9-5-2003. Gas Decay Tank

  1. 8 was sampled following the sample for Gas Decay Tank #3 that was taken earlier in the day. The sample for Gas Decay Tank #8 may not have been a representative sample since the isolation valve for Gas Decay Tank #3 was still' open. The consequence of this valve misalignment is a missed Technical Requirements Manual surveillance. Technical Surveillance Requirement 3.10.3.1 is "required once per 7 days during addition of radioactive material to the tank, AND once within 7 days following addition of radioactive material to the tank". Upon discovery both WGDT #3 and #8 were sampled, analyzed and the curie content for each tank was determined." This missed surveillance is not reportable in the form of. a Reportability Evaluation Request or Licensee Event Report.

PIR 2003-3555 - Gas Decay Tank Release permit 2003165 was issued with an incorrect low setpoint. The low setpoint is calculated using AIF 07B-022-07, Skin Dose Rate, and AIF 07B-022-08, Whole Body Dose Rate. The lower of the two values calculated is the setpoint selected. If the calculated low setpoint is greater than the RWV (Radwaste Vent) low setpoint, then the low setpoint on the GDT permit is set equal to the low setpoint on the RWV permit. If the calculated low setpoint is lower'than the RWV low setpoint, than the calculated setpoint is used. The calculated low setpoint was 7.97E+02 pCi/sec. The low setpoint on the RWV permit was 8.83E+02 pCi/sec. The correct low setpoint to use on the permit was 7.97E+02 pCi/sec, but 8.83E+02 pCi/sec was recorded on the permit. The release was performed with a less conservative setpoint, but the low setpoint was not compromised due to the built-in conservatism of the setpoint calculation.

An expected monitor response is calculated which considers the rate of the release. The calculated monitor response is then doubled and this is the value that is compared to the low setpoint. If the expected monitor response indicates the low setpoint could be exceeded, then the expected monitor response calculation is performed again using a lower release rate to ensure the low setpoint is not breached. The expected monitor response on the permit was 7.81E+01 pCi/sec, and the monitor reading during the release was 2.98E+01 pCi/sec.

PIR 2003-3591 - Containment Purge Permit 2003178 had an incorrect value for the high setpoint for GTRE-22 and GTRE-33, Containment Air monitors. The setpoint on the permit was recorded as 1.02E-02 pCi/cc'and the setpoint should have been recorded as 1.OOE-02 pCi/cc. The use of the incorrect setpoint was discovered after the release occurred by the technician who retrieved the permit from the control room. Monitor setpoints are used to ensure compliance with 10CFR20. The ESFAS actually controls the actuation of a containment purge isolation signal, therefore the radiation monitor, via the ESFAS, would have terminated the purge prior to exceeding any 10 CFR dose limits.

26 of 40 2003 EFFLUENT CONCENTRATION LIMITS Nuclides Curies Average Diluted 10 CFR 20 ECL % of ECL Concentration (uiCi/ml)

(liCi/ml)

H-3 1.50E+03 1.90E-05 1.OOE-03 1.90E+00 Cr-51 5.29E-04 6.68E-12 5.OOE-04 1.34E-06 Mn-54 9.43E-06 1.19E-13 3.OOE-05 3.97E-07 Mn-56 3.66E-06 4.62E-14 7.00E-05 6.60E-08 Co-57 1.48E-05 1.87E-13 6.OOE-05 3.12E-07 Co-58 5.26E-03 6.65E-1 1 2.OOE-05 3.33E-04 Co-60 1.25E-03 1.58E-1 1 3.OOE-06 5.27E-04 Sb-125 9.84E-03 1.24E-10 3.OOE-05 4.13E-04 Sb-1 26 2.53E-06 3.20E-14 7.OOE-06 4.57E-07 1-131 3.90E-04 4.93E-12 1.OOE-06 4.93E-04 1-132 2.23E-06 2.82E-14 1.OOE-04 2.82E-08 1-133 3.1OE-05 3.92E-13 7.OOE-06 5.60E-06 Cs-134 2.21 E-05 2.79E-13 9.OOE-07 3.1 OE-05 Cs-137 2.23E-04 2.82E-12 1.OOE-06 2.82E-04 Nb-97 7.39E-06 9.34E-14 3.OOE-04 3.11E-08 Ba-1 39 7.OOE-06 8.84E-14 2.OOE-04 4.42E-08 Rb-88 3.27E-04 4.13E-12 4.OOE-04 1.03E-06 Sn-117M 6.83E-06 8.63E-14 1.OOE-08 8.63E-04 Sb-124 2.36E-05 2.98E-13 7.OOE-06 4.26E-06 Kr-85 7.44E-04 9.40E-12 2.OOE-04 4.70E-06 Kr-85M 3.91 E-05 4.94E-13 2.OOE-04 2.47E-07 Kr-88 4.48E-05 5.66E-13 2.OOE-04 2.83E-07 Xe-131 M 5.09E-05 6.43E-13 2.OOE-04 3.22E-07 Xe-133M 8.97E-04 1.13E-11 2.OOE-04 5.65E-06 Xe-1 33 6.38E-02 8.06E-10 2.OOE-04 4.03E-04 Xe-135 3.40E-03 4.30E-11 2.OOE-04 2.15E-05

27 of 40 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2003 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* 7.52E+01 **

evaporator bottoms, etc. Ci 4.32E+02. 2.50E+01

b. Dry compressible waste, m3* 8.48E+02**

contaminated equip. etc. Ci . 2.12E+00 2.50E+01

c. Irradiated compon ents, m3* 0.OOE+00 control rods, etc. Ci 0.OOE+00 2.50E+01
d. Other m3* 0.OOE+00 Ci 0.OOE+00 2.50E+01
  • m3 = cubic meters ** This is the volume sent offsite for volume reduction, prior to disposal.
2. Estimate of Major Nuclide Composition (bytype of waste).

[Nuclides listed with % abundance greater than 10 %]

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

Nuclide Percent Name Abundance Curies Fe-55 54.398 2.35E+02 Co-58 11.685 5.05E+01 Ni-63 15.417 6.66E+01

b. Dry compressible waste, contaminated equipment, etc.

Nuclide Percent Name

  • Abundance Curies Fe-55 36.688 7.79E-01 Co-58 10.216 2.17E-01 Ni-63 32.908 6.99E-01

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c. Irradiated components, control rods, etc. - None
d. Other - None
3. Solid Waste Disposition
  • Number of ShiDments Mode of Transportation Destination 2 Truck (Hittman Transport Services) Barnwell Waste Management Facility, Barnwell, SC 4 Truck (Hittman Transport Services) Duratek, Inc., Bear Creek, Oak Ridge, TN 2 Truck (Hittman Transport Services) Duratek Inc., Gallaher, Oak Ridge, TN

.2 Truck (Hittman Transport Services) Studsvik Processing Facility, LLC; Columbia, SC 4 Truck (TAG Transport) Studsvik Processing Facility, LLC; Columbia, SC 1 Truck (R&R Trucking) ALARON Corporation (Wampum, PA) 8 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, Class B, 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 2003 period.

29 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,'2003, through December 31, 2003, 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 2003. PIR 2004-0620 has been written'and the resolution will be presented in the 2005 Annual Report.)

A Meteorological Professor at the University of Kansas established the first set of criteria that is used to determine data availability and verification. This verification takes a look at all instruments on the tower and compares the instruments against one another to verify a parameter that is outside the normal meteorological parameters for this part of Kansas. The software then flags all parameters in that 15-minute period as bad data. Bad data is then accumulated assuming all parameters were unavailable. 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 84.4%.

A review of the data from the instruments reveal that approximately 12% of the missing/bad data is from data that was either 0, or the data did not change from one 15 minute average to the other. This is due to either instrument malfunction or the computer or computer link/modem being down. The Meteorological Tower Instruments will be replaced in 2004 and the problem of unresponsive instruments and the computer being down will be eliminated, or greatly reduced.

Therefore, it is reasonable assurance that when the new instruments get installed that the data availability will be greater than 90%. The data availability for the Meteorological Data for the year 2003 is 84.4%.

30 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY I THROUGH DECEMBER 31, 2003 STABILITY CLASS: A ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 12 28 6 1 48 NNE 0 15 36 13 1 1 66 NE 1 26 51 2 0 0 80

  • ENE 0 15 32 1 1 0 49 E 0 3 14 2 0 0 19 ESE 1 4 12 15 1 1 34 SE 2 5 23 13 4 0 47 SSE 0 20 43 25 10 0 98 S 2 27 56 98 47 .6 236 SSW o 9 37 84 22 6 158 SW 3 5 20 19 6 0 53 WSW 1 14 19 5 0 0 39 W 0 11 41 7 0 2 61 WNW 2 6 6 8 10 2 34 NW 0 4 6 17 17 0 44 NNW 0 1 8 33 14 0 56 TOTAL 12 166 416 370 139 19 1122 PERIOD OF CALM (HOURS): 0

31 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2003 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 2 5 10 4 0 .21 NNE 0 11 18 14 0 0 43 NE 1 12 11 0 0 0 . 24 ENE 1 9 8 1 0 0 19 E 0 2 4 2 0 0 . 8 ESE 0 0 11 3 1 0 15 SE. 1 4 10 3 1 0 19 SSE 0 7 17 7 1 1 33 S 0 5 22 .7 3 1 38 SSW 0 4 .16 13 6 1 40Q SW 2 0 11 4 0 0 17 WSW 1 3 8 0 1 0 13 W 0 7 6 2 1 0 16 WNW 0 0 2 6 3 0 11 NW 0 5 4 15 9 0 33 NNW 0 1 9 15 11 0 36 TOTAL 6 72 162 102 41 3 386.

PERIOD OF CALM (HOURS): 0

32 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2003 STABILITY CLASS: C ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 2 12 12 3 1 30 NNE 0 6 25 13 0 0 44 NE 1 13 10 2 0 0 26 ENE 0 14 6 0 0 0 20

  • E 1 5 5 1 0 0 12 ESE 1 5 11 5 0 0 22 SE 1 7 12 3 1 0 24 SSE 0 2 18 8 4 1 33 S 1 7 12 20 6 2 48 SSW 1 5 11 24 4 2 47 SW 0 7 5 4 1 0 17 WSW 1 1 8 1 0 0 11 W 0 2 4 3 0 0 9 WNW 0 1 6 8 5 0 20 NW 0 0 12 21 12 0 45 NNW 0 4 18 22 5 0 49 TOTAL 7 81 175 147 41 6 457 PERIOD OF CALM (HOURS): 0

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.HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2003 STABILITY CLASS: D ELEVATION: 10 METERS WIND SPEED (mph)

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

N 0 . 15 31 86 18 6 156 NNE 3 33 74 71 19 4 204 NE 9 76 40 16 0 0 .141 ENE 9 72 42 11 0 0 . 134 E 8 62 44 13 1 0 128 ESE 7 42 37 21 1 0 108.

SE 3 44 64 19 1 0 131 SSE 4 52 102 104 25 0 287 S 1 64 132 135 28 7 367 SSW 1 44 81 65 14 2 207 SW 1 46 40 13 5 0 105 WSW 1 26 29 14 3 0 73 W 0 17 32 13 0 0 62 WNW 0 12 42 40 4 0 98 NW 0 10 74 79 55 1 219 NNW 0 31 64 63 25 0 . 183 TOTAL 47 646 928 763 199 20 2603 PERIOD OF CALM (HOURS): 0

34 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31,2003 STABILITY CLASS: E ELEVATION: 10 METERS WIND SPEED (mph)

. WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 7 14 11 0 1 33

NNE 1 32 27 10 4 1 75 NE 10 59 9 *2 0 0 80 ENE 9 38 11 1 0 0 59 E 7 62 33 4 0 0 106
  • ESE 4 78 23 6 0 0 111 SE 6 62 71 5 0 0 144 SSE 3 55 128 42 8 1 237 S 6 67 87 94 57 1 312 SSW 4 40 61 21 5 0 131 SW 4 43 25 2 0 *0 74 WSW 4 31 25 4 0 0 64 W 2 20 10 2 0 0 34
  • WNW 5 28 19 I 0 0 53 NW 3 32 47 7 0 0 89 NNW 3 32 48 6 0 0 89 TOTAL 71 686 638 218 74 4 1691 PERIOD OF CALM (HOURS): 1

35 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2003 STABILITY CLASS: F ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 19 12 1 0 0 32 NNE 0 41 15 0 0 . 0 56 NE 8 42 2 0 0 0 52 ENE 2 39 3 1 0 0 45 E 7 52 16 .0 0 0 75 ESE 4 64 11 0 0 0 79 SE. 2 79 19 0 0 0 100 SSE 3 42 24 4 0 0 73 S 3 12 13 9 1 0 38 SSW 2 15 11 . 1 0 0 29 SW 1 23 . 13 0 0 0 37 WSW 5 9 4 0 0 0 18 W 0 3 0 0 0 0 3 WNW 3 7 3 0 0 0 13 NW 2 17 9 0 0 0 28 NNW 1 29 12 0 0 0 42 TOTAL 43 493 167 16 1 0 720 PERIOD OF CALM (HOURS): 0

36 of 40 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2003 STABILITY CLASS: G ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 8 4 0 0 0 12 NNE 1 41 17 1 0 0 60 NE 7 38 1 0 0 0 46 ENE 3 39 3 0 0 0 45 E 0 40 5 0 0 0 45 ESE 1 33 0 0 0 0 34 SE 1 44 4 0 0 0 49 SSE 2 24 4 0 0 0 30 S 3 12 8 0 0 0 23 SSW 1 3 0 0 0 0 4 SW 0 3 2 0 0 0 5 WSW 1 3 1 0 0 0 5 W 1 7 0 0 0 0 8 WNW 0 6 0 0 0 0 6 NW .. 1 17 3 0 0 0 21 NNW 0 15 6 0 0 0 21 TOTAL 22 333 58 1 0 0 414 PERIOD OF CALM (HOURS): 0

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.HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31, 2003 STABILITY CLASS: ALL ELEVATION: 10 METERS WIND SPEED (mph)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 54 90 148 31 .9 -332 NNE 5 179 212 122 24 6 548 NE 37 266 124 22 0 0 449 ENE 24 226 105 15 1 0* 371 E 23 226 121 22 0 . 393 ESE 18 226 105 50 3 1 403 SE . 16 245 203 43 7 0* *514 SSE 12 202 336 190 48 3 .791 S 16 194 .330 363 142 17' *1062 SSW 9 120 217 208 51 11

  • 616 SW 11 127 116 42 12 0 -308 WSW 14 87 94 24 4
  • 223 W 3 67 93 27. 1 .2 193 WNW 10 60 78 63 22 2 235 .

NW 6 85 155 139 93 I 479 NNW 4 113 165 139 55 0 476 TOTAL 208 2477 2544 1617 495 52 7393 PERIOD OF CALM (HOURS):0

38 of 40 SECTION IV ADDITIONAL INFORMATION

1. Unplanned or Abnormal Releases On 7-17-2003 workers were in the process of replacing the "A" waste gas compressor moisture separator tank relief valve. This work was being performed under work order 03-253665. When the relief valve flange was broken loose water commenced spraying from the flange area and the flange bolts were retightened. This relief valve discharges to Gas Decay Tank #8 that contained approximately 5 psig pressure. Gas Decay Tank #8 lost approximately 0.4 psig during this evolution. The radwaste vent gaseous effluent monitor channel GHE103 indicated an increase from 9.02 to 16.2 uCi/sec. The water released from the relief valve resulted in the area being contaminated and the area was decontaminated. Health Physics sampling for airborne contaminants did not show any radioactive particulates or iodine. Mechanical maintenance personnel exited the area and were not contaminated or gassed up. The increase of channel GHE103 appeared to be a result of chemistry sampling of the radwaste vent. A graph over the previous two months was reviewed and channel GHE103 increased each time chemistry sampling or filter changes were performed. There was no unplanned, unmonitored or uncontrolled release of radioactive material to areas accessible to the public. This event wasn't due to an equipment problem. The clearance order for the job was not adequate and maintenance personnel assumed the system was vented to atmosphere, but did not validate it.
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 5, was revised in 2003; it is included with this report as Attachment II.

3. Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems Temporary Modification 98-018HB that installed the TUF (tubular ultra filtration) skid is still in place. This Temporary Modification is being made permanent with the implementation of Design Change Package (DCP) 9337. The estimated implementation date of DCP 9337 is expected to be March of 2004. The DCP makes the DTS (Diversified Technologies) Zero Filtration System, along with the WPS Demineralizer System, the primary means of liquid waste processing at Wolf Creek. Permanent piping and power supply are being added to mobile liquid radwaste processing skids. The primary liquid radwaste evaporator will be permanently out of service and abandoned in place.

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4. Land Use Census No new locations for dose calculation were identified during this report period.
5. Radwaste Shipments Twenty-three 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 2003 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."

40 of 40 ATTACHMENTS TO WCGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - REPORT 27 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 5, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Attachment IlIl is AP 31A-1 00, Revision 4, "Solid Radwaste Process Control Program"

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