Text

Annual Radioactive Effluent Release Report - Report 25
	ML021130490
Person / Time
Site:	Wolf Creek
Issue date:	04/17/2002
From:	Jacobs D; Wolf Creek
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	WO 02-0019 AP 07B-003, Rev 3, AP 07B-004, Rev 2
	Download: ML021130490 (88)
	v • d • e

W#*LF CREEK

'NUCLEAR OPERATING CORPORATION Donna Jacobs Plant Manager APR 1 712002 WO 02-0019 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555

Subject:

Docket No. 50-482: Wolf Creek Generating Station Annual Radioactive Effluent Release Report - Report 25 Gentlemen:

This letter transmits the enclosed Wolf Creek Generating Station (WCGS) Annual Radioactive Effluent Release Report.

The report covers the period from January 1, 2001, through December 31, 2001.

It is being submitted pursuant to Section 5.6.3 of the WCGS Technical Specifications. Two procedures are included as attachments to the enclosed report: AP 07B 003, "Offsite Dose Calculation Manual" and AP 07B-004, "Offsite Dose Calculation Manual, (Radiological Environmental Monitoring Program)."

No commitments are contained in this submittal.

If you should have any questions regarding this submittal, please contact me at (620) 364 4246, or Mr. Karl A. (Tony) Harris at (620) 364-4038.

Very truly yours, Don Jacobs DJ/pb Enclosure cc: J. N. Donohew (NRC), w/e D. N. Graves (NRC), w/e E. W. Merschoff (NRC), w/e Senior Resident Inspector (NRC), w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET

Enclosure to WO 02-0019 Page 1 of 36 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. 25 Reporting Period: January 1, 2001 - December 31, 2001

Enclosure to WO 02-0019 Page 2 of 36 Table of Contents Page Executive Summary 4

Section 1 6

Report of 2001 Radioactive Effluents Liquid 6

2001 Liquid Effluents 7

2001 Liquid Cumulative Dose Summary - Table 1 10 2001 Liquid Cumulative Dose Summary - Table 2 11 Report of 2001 Radioactive Effluents Airborne 12 2001 Gaseous Effluents 14 2001 Gaseous Cumulative Dose Summary - Table 1 16 2001 Gaseous Cumulative Dose Summary - Table 2 17 Section II 18 Offsite Dose Calculation Manual Limits 18 Effluent Concentration Limits (ECLs) 18 Average Energy 19 Measurements and Approximations of Total Radioactivity (Liquid and Gaseous Effluents) 19 Batch Releases 21 Continuous Releases 21 Doses to a Member of the Public from Activities Inside the Site Boundary 21 Additional Information 21 2001 Effluent Concentration Limits 23 2001 Solid Waste Shipments 24 Irradiated Fuel Shipments 25 Section III 26 Meteorological Data - Hours At Each Wind Speed and Direction 27 Section IV 35 Correction to the Annual Radioactive Release Reports Covering the Years 1993-2000 35 Section V 35 Unplanned or Abnormal Releases 35 Offsite Dose Calculation Manual 35 Major Changes to Liquid, Solid or Gaseous Radioactive Waste Treatment Systems 35 Land Use Census 36 Radioactive Shipments 36 Inoperability of Effluent Monitoring Instrumentation 36 Storage Tanks 36

Enclosure to WO 02-0019 Page 3 of 36 Table of Contents Attachment I - Corrected Pages from Annual Radioactive Release Reports Covering January 1, 1993 through December 31, 2000.

Attachment II - WCGS Procedure AP 07B-003, Revision 4, "Offsite Dose Calculation Manual" Attachment III - WCGS Procedure AP 07B-004, Revision 2, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)"

Enclosure to WO 02-0019 Page 4 of 36 EXECUTIVE

SUMMARY

This Annual Radioactive Effluent Release Report (Report 25) documents the quantities of liquid and gaseous effluents and solid waste released by the Wolf Creek Generating Station (WCGS) from January 1, 2001, through December 31, 2001. The format and content of this report is in accordance with Regulatory Guide 1.21, Revision 1. Sections I, II, Ill, 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 lists in detail the quantities of radioactive liquid and gaseous effluents and cumulative dose summaries for 2001, 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 2001.

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 2001.

Section II --- Section II includes supplemental information on continuous and batch releases, calculated doses, and solid waste disposal. The same number of gaseous batch releases occurred in 2001 and 2000 (75 for both years). There were fewer liquid batch releases in 2001 than there were in 2000 (51 versus 98).

WCGS released 0.0356 Curies in liquid releases during 2000, excluding gas and tritium. WCGS reduced this release amount in 2001, when 0.018 Curies, excluding gas and tritium, were released. Continuous release pathways remained the same as previous years and all continuous releases were monitored. Performance Improvement Request (PIR) 2001-3090 was written as a result of 3r quarter 2000 Lime Pond composite not meeting the Lower Limit of Detection (LLD) for Sr-89 due to the delay time in sending off the sample. PIR 2001-1599 was written previously to capture the fact that the Lime Pond composite was not sent off until July 2001. Maximum estimated doses to members of the public were approximately the same as in 2000 with the exception of the Coffey County Lake (Wolf Creek Lake, per USAR).

Dose assigned to fishermen who use the lake lowered to 5.58E-02 mRem in 2001, compared to 6.10E-02 mRem for 2000. This decrease can be contributed to the Coffey County Lake (Wolf Creek Lake) closure since September 11, 2001.

Section III --- Section III documents the WCGS meteorological data for wind speed, wind direction, and atmospheric stability. The quantity of missing hours of data for 2001 was 1110 hours0.0128 days 0.308 hours 0.00184 weeks 4.22355e-4 months . This corresponds to approximately 87.3% data availability. This lower availability was largely due to the unavailability of the computer and equipment for short periods of time.

PIR 2002-0576 was written to evaluate the fact that we did not meet the 90% availability goal as stated in Regulatory Guide 1.23.

Section IV ---Section IV contains corrected Annual Radioactive Effluent Release Reports covering the period January 1, 1993 through December 31, 2000. PIR 2000-0813 documents discrepancies found in the Effluent Management Software (EMS) Database. The Annual Reports submitted from 1993 to 1998 contained data inconsistent with true data. The EMS program was placed into service in 1993 to generate the release permits and associated reports. While performing the 1999 Annual Radioactive Effluent Report a problem was recognized where the values for Fe-55 were positive in Quarters 1 and 2. A comparison was made between the 1998 EMS Nuclide tables and the 1998 cumulative tables and several discrepancies were identified.

The values calculated in the cumulative tables are used to complete the Annual Radioactive Effluent Report. The Annual Reports submitted for 1993-1998 have been manually verified/validated and corrected as necessary. PIR 2001-1834 identifies that the volume released in 2000 was under-reported by 50,000 gallons. The 2000 Annual Report was corrected to include the 50,000 gallons. These corrections are being submitted as Attachment I to this report.

Section V --- Section V documents planned and unplanned releases; changes to radwaste treatment systems, land use census, monitoring instruments, radwaste shipments; and, storage tank quantities. An

Enclosure to WO 02-0019 Page 5 of 36 Section V --- Section V documents planned and unplanned releases; changes to radwaste treatment systems, land use census, monitoring instruments, radwaste shipments; and, storage tank quantities. An unplanned release on Gas Decay Tank #1 occurred on December 6, 2001, when Gas Decay Tank #1 was in re-circulation in support of STS IC-470A, "Gaseous Radwaste H2 and 02 Monitors HA Train "A"-Channel Calibration/ACOT." The tank pressure was 8.8 psig. During the performance of the procedure the Radwaste Vent Effluent monitor (GHN0103) release rate increased for a time period of two (2) hours.

After the procedure was completed the tank pressure was 7.6 psig. When the Waste Gas Compressor was secured, the tank pressure dropped to 5.2 psig. During this evolution, 3.6 psig was lost. This evolution resulted in 4.31E-02 Curies of Kr-85 and 5.90E-06 Curies of Xe-133 being released. PIR 2001-3064 was initiated to capture and evaluate the events. No ODCM limits were exceeded.

PIR 2001-1798 was initiated June 1, 2001, to document a missed surveillance.

The automatic isolation capability of the Mini-Purge valves was not verified quarterly as required by Section 3.4.2 and Table 3.3 of AP 07B-003, "Offsite Dose Calculation Manual." The last qualifying surveillance was performed on October 5, 2000.

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

ATTACHMENTS AP 07B-003, Revision 4, "Offsite Dose Calculation Manual" is included as Attachment II and AP 07B-004, Revision 2, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program)" is included as Attachment I11.

Enclosure to WO 02-0019 Page 6 of 36 SECTION I REPORT OF 2001 RADIOACTIVE EFFLUENTS: LIQUID Unit Quarter 1 Quarter 2 A.

Fission and Activation Products

1.

Total Release (not including tritium, gases, Ci 2.1OE-03 2.18E-03 alpha

2.

Average Diluted Concentration During PCi/ml 2.05E-10 1.23E-10 Period

3.

Percent of Applicable Limit (1) 4.20E-02 4.36E-02 B.

Tritium

1.

Total Release Ci 3.32E+01 2.04E+02

2. Average Diluted Concentration During PCi/ml 3.23E-06 9.10E-06 Period

3.

Percent of Applicable Limit (ECL) (2) 3.23E-01 9.10E-01 C.

Dissolved and Entrained Gases

1.

Total Release Ci O.OOE+00 3.06E-03

2. Average Diluted Concentration During PCi/ml O.OOE+00 1.37E-10 Period

3.

Percent of Applicable Limit (3)

O.OOE+00 6.85E-05 D.

Gross Alpha Radioactivity

1.

Total Release Ci 1.06E-05 O.OOE+00 E.

Volume of waste released (prior to liters 3.58E+07 4.93E+07 dilution)

F.

Volume of dilution water used liters 1.02E+10 2.23E+10 NOTES:

1) The applicable limit for the Wolf Creek Generating Station 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 printed here 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:

%l Limit =

(Average Diluted Concentration) (100)

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

3) This value is derived by the following formula:

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

(2E-4 from ODCM Section 2.1)

Enclosure to WO 02-0019 Page 7 of 36 REPORT OF 2001 RADIOS A.

Fission and Activation Products

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

2.

Average Diluted Concentration During Period

3. Percent of Applicable Limit (1)

B.

Tritium

1. Total Release

2.

Average Diluted Concentration During Period

3.

Percent of Applicable Limit (ECL) (2)

C.

Dissolved and Entrained Gases

1. Total Release

2.

Average Diluted Concentration During Period

3. Percent of Applicable Limit (3)

D.

Gross Alpha Radioactivity

1. Total Release E.

Volume of waste released (prior to dilution)

F.

Volume of dilution water used ACTIVE EFFLUENTS: LIQUID Unit Quarter 3 Ci 8.18E-03 pCi/ml 5.85E-10 1.64E-01 Ci pCi/ml Ci RCi/ml 2.16E+02 1.55E-05 1.55E+00 2.15E-04 1.54E-11 7.71 E-06 1.19E-05 8.03E+07 1.39E+10 Ci liters liters NOTES:

1) The applicable limit for the Wolf Creek Generating Station 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 printed here 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(Average Diluted Concentration) (100)

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

3)

This value is derived by the following formula:

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

(2E-4 from ODCM Section 2.1)

Quarter 4 5.50E-03 3.27E-10 1.10E-01 3.94E+02 2.34E-05 2.34E+00 5.38E-03 3.20E-1 0 1.60E-04 0.OOE+00 3.63E+07 1.63E+10

Enclosure to WO 02-0019 Page 8 of 36 2001 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 1 Quarter 2 Quarter I Quarter 2 Released H-3 Ci 7.04E-01 1.06E+00 3.25E+01 2.03E+02 Cr-51 Ci n/a n/a n/a n/a Mn-54 Ci

<1.77E-02

<2.45E-02

<1.83E-04 2.29E-05 Fe-55 Ci

<3.54E-02

<4.89E-02

<3.66E-04

<4.39E-04 Fe-59 Ci

<1.77E-02

<2.45E-02

<1.83E-04

<2.20E-04 Co-57 Ci n/a n/a 3.72E-06 n/a Co-58 Ci

<1.77E-02

<2.45E-02 1.19E-03 4.25E-04 Co-60 Ci

<1.77E-02

<2.45E-02 2.04E-04 4.72E-04 Zn-65 Ci

<1.77E-02

<2.45E-02

<1.83E-04

<2.20E-04 Sr-89 Ci

<1.77E-03

<2.45E-03

<1.83E-05

<2.20E-05 Sr-90 Ci

<1.77E-03

<2.45E-03

<1.83E-05

<2.20E-05 Sr-92 Ci n/a n/a n/a n/a Nb-95 Ci n/a n/a n/a n/a Zr-95 Ci n/a n/a n/a n/a Zr-97 Ci n/a n/a n/a n/a Mo-99 Ci

<1.77E-02

<2.45E-02

<1.83E-04

<2.20E-04 Ag-110M Ci n/a n/a n/a n/a Sn-113 Ci n/a n/a n/a n/a Sn-117M Ci n/a n/a n/a n/a Sb-124 Ci n/a n/a n/a n/a Sb-125 Ci n/a n/a 4.91 E-04 1.18E-03 1-131 Ci

<3.54E-02

<4.89E-02

<3.66E-04

<4.39E-04 Cs-134 Ci

<1.77E-02

<2.45E-02 8.06E-05 5.92E-06 Cs-1 37 Ci

<1.77E-02

<2.45E-02 1.28E-04 6.95E-05 Ce-141 Ci

<1.77E-02

<2.45E-02

<1.83E-04

<2.20E-04 Ce-144 Ci

<1.77E-02

<2.45E-02

<1.83E-04

<2.20E-04 Gross Alpha Ci

<3.54E-03

<4.89E-03 1.06E-05

<4.39E-05 Ar-41 Ci

<3.54E-01

<4.89E-01

<3.66E-03

<4.39E-03 Kr-85M Ci

<3.54E-01

<4.89E-01

<3.66E-03

<4.39E-03 Kr-85 Ci

<3.54E-01

<4.89E-01

<3.66E-03 2.64E-03 Kr-87 Ci

<3.54E-01

<4.89E-01

<3.66E-03

<4.39E-03 Kr-88 Ci

<3.54E-01

<4.89E-01

<3.66E-03

<4.39E-03 Xe-1 31M Ci

<3.54E-01

<4.89E-01

<3.66E-03

<4.39E-03 Xe-1 33M Ci

<3.54E-01

<4.89E-01

<3.66E-03

<4.39E-03 Xe-1 33 Ci

<3.54E-01

<4.89E-01

<3.66E-03 4.22E-04 Xe-1 35M Ci

<3.54E-01

<4.89E-01

<3.66E-03

<4.39E-03 Xe-1 35 Ci

<3.54E-01

<4.89E-01

<3.66E-03

<4.39E-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.

Enclosure to WO 02-0019 Page 9 of 36 2001 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Released H-3 Ci 4.37E-01 8.90E-01 2.16E+02 3.93E+02 Cr-51 Ci n/a n/a 6.68E-05 n/a Mn-54 Ci

<3.98E-02

<1.79E-02 2.07E-05

<3.21 E-04 Fe-55 Ci

<7.97E-02

<3.57E-02 1.59E-03

<6.42E-04 Fe-59 Ci

<3.98E-02

<1.79E-02

<3.18E-04

<3.21 E-04 Co-57 Ci n/a n/a 2.88E-05 1.89E-05 Co-58 Ci

<3.98E-02

<1.79E-02 7.71 E-04 4.88E-04 Co-60 Ci

<3.98E-02

<1.79E-02 7.18E-04 9.82E-04 Rb-88 Ci n/a n/a n/a n/a Zn-65 Ci

<3.98E-02

<1.79E-02

<3.18E-04

<3.21E-04 Sr-89 Ci

<3.98E-03

<1.79E-03

<3.18E-05

<3.21E-03 Sr-90 Ci

<3.98E-03

<1.79E-03

<3.18E-05

<3.21E-03 Sr-92 Ci n/a n/a n/a n/a Nb-95 Ci n/a n/a n/a n/a Ru-103 Ci n/a n/a n/a n/a Zr-95 Ci n/a n/a n/a n/a Zr-97 Ci n/a n/a n/a n/a Mo-99 Ci

<3.98E-02

<1.79E-02

<3.18E-04

<3.21E-04 Ag-110M Ci n/a n/a n/a n/a Sn-113 Ci n/a n/a n/a n/a Na-24 Ci n/a n/a n/a n/a Sb-125 Ci n/a n/a 4.59E-03 3.91E-03 1-131 Ci

<7.97E-02

<3.57E-02

<6.37E-04 5.11E-06 Cs-134 Ci

<3.98E-02

<1.79E-02 1.03E-04 1.71 E-05 Cs-137 Ci

<3.98E-02

<1.79E-02 2.77E-04 8.99E-05 Cs-138 Ci n/a n/a n/a n/a Ce-141 Ci

<3.98E-02

<1.79E-02

<3.11E-04

<3.21E-04 Ce-144 Ci

<3.98E-02

<1.79E-02

<3.18E-04

<3.21 E-04 Gross Alpha Ci

<7.97E-03

<3.57E-03 1.19E-05

<6.42E-05 Ar-41 Ci

<7.97E-01

<3.57E-01

<6.37E-03

<6.42E-03 Kr-85M Ci

<7.97E-01

<3.57E-01

<6.37E-03

<6.42E-03 Kr-85 Ci

<7.97E-01

<3.57E-01

<6.37E-03

<6.42E-03 Kr-87 Ci

<7.97E-01

<3.57E-01

<6.37E-03

<6.42E-03 Kr-88 Ci

<7.97E-01

<3.57E-01

<6.37E-03

<6.42E-03 Xe-1 31 M Ci

<7.97E-01

<3.57E-01

<6.37E-03

<6.42E-03 Xe-1 33M Ci

<7.97E-01

<3.57E-01

<6.37E-03

<6.42E-03 Xe-133 Ci

<7.97E-01

<3.57E-01 2.13E-04 5.38E-03 Xe-1 35M Ci

<7.97E-01

<3.57E-01

<6.37E-03

<6.42E-03 Xe-1 35 Ci

<7.97E-01

<3.57E-01 2.05E-06

<6.42E-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.

Enclosure to WO 02-0019 Page 10 of 36 2001 LIQUID CUMULATIVE DOSE

SUMMARY

TABLE I QUARTER 1 OF 2001 ODCM CALCULATED ODCM 1 LIMIT

% OF LIMIT DOSE TOTAL DOSE (mRem) FOR BONE 1.OOE-03 5.OOE+00 2.OOE-02 TOTAL DOSE (mRem) FOR LIVER 1.53E-02 5.OOE+00 3.06E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 1.49E-02 1.50E+00 9.90E-01 TOTAL DOSE (mRem) FOR THYROID 1.36E-02 5.OOE+00 2.72E-01 TOTAL DOSE (mRem) FOR KIDNEY 1.42E-02 5.OOE+00 2.83E-01 TOTAL DOSE (mRem) FOR LUNG 1.38E-02 5.OOE+00 2.76E-01 TOTAL DOSE (mRem) FOR GI-LLI 1.37E-02 5.OOE+00 2.74E-01 QUARTER 2 OF 2001 TOTAL DOSE (mRem) FOR BONE 2.79E-04 5.OOE+00 5.57E-03 TOTAL DOSE (mRem) FOR LIVER 3.19E-02 5.OOE+00 6.37E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 3.17E-02 1.50E+00 2.12E+00 TOTAL DOSE (mRem) FOR THYROID 3.15E-02 5.OOE+00 6.29E-01 TOTAL DOSE (mRem) FOR KIDNEY 3.16E-02 5.OOE+00 6.32E-01 TOTAL DOSE (mRem) FOR LUNG 3.15E-02 5.OOE+00 6.30E-01 TOTAL DOSE (mRem) FOR GI-LLI 3.15E-02 5.OOE+00 6.31 E-01 QUARTER 3 OF 2001 TOTAL DOSE (mRem) FOR BONE 1.15E-03 5.OOE+00 2.31 E-02 TOTAL DOSE (mRem) FOR LIVER 2.17E-02 5.OOE+00 4.34E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 2.12E-02 1.50E+00 1.41 E+00 TOTAL DOSE (mRem) FOR THYROID 1.99E-02 5.OOE+00 3.98E-01 TOTAL DOSE (mRem) FOR KIDNEY 2.05E-02 5.OOE+00 4.1OE-01 TOTAL DOSE (mRem) FOR LUNG 2.01 E-02 5.OOE+00 4.02E-01 TOTAL DOSE (mRem) FOR GI-LLI 2.01 E-02 5.OOE+00 4.01 E-01 QUARTER 4 OF 2001 TOTAL DOSE (mRem) FOR BONE 4.54E-04 5.OOE+00 9.09E-03 TOTAL DOSE (mRem) FOR LIVER 5.17E-02 5.OOE+00 1.03E+00 TOTAL DOSE (mRem) FOR TOTAL BODY 5.15E-02 1.50E+00 3.44E+00 TOTAL DOSE (mRem) FOR THYROID 5.11 E-02 5.OOE+00 1.02E+00 TOTAL DOSE (mRem) FOR KIDNEY 5.13E-02 5.OOE+00 1.03E+00 TOTAL DOSE (mRem) FOR LUNG 5.11E-02 5.OOE+00 1.02E+00 TOTAL DOSE (mRem) FOR GI-LLI 5.12E-02 5.OOE+00 1.02E+00 TOTALS FOR 2001 TOTAL DOSE (mRem) FOR BONE 2.89E-03 1.OOE+01 2.89E-02 TOTAL DOSE (mRem) FOR LIVER 1.21 E-01 1.OOE+01 1.21 E+00 TOTAL DOSE (mRem) FOR TOTAL BODY 1.19E-01 3.OOE+00 3.98E+00 TOTAL DOSE (mRem) FOR THYROID 1.16E-01 1.OOE+01 1.16E+00 TOTAL DOSE (mRem) FOR KIDNEY 1.18E-01 1.OOE+01 1.18E+00 TOTAL DOSE (mRem) FOR LUNG 1.17E-01 1.OOE+01 1.17E+00 TOTAL DOSE (mRem) 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 less than or equal to 1.5 mRem per quarter and 3.0 mRem per year. Dose restriction of any organ is less than or equal to 5 mRem per quarter and 10 mRem per year.

Enclosure to WO 02-0019 Page 11 of 36 2001 LIQUID CUMULATIVE DOSE

SUMMARY

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) 2.10E-03 2.18E-03 8.18E-03 5.50E-03 1.80E-02

2.

Maximum Organ Dose (mRem) 1.71E-03 3.94E-04 1.82E-03 6.83E-04 4.61E-03

3.

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

4.

Percent of Limit 3.41 E-02 7.88E-03 3.65E-02 1.37E-02 4.61 E-02 B.

Tritium

1.

Total Release - (Ci) 3.32E+01 2.04E+02 2.16E+02 3.94E+02 8.47E+02

2.

Maximum Organ Dose (mRem) 1.36E-02 3.15E-02 1.99E-02 5.1OE-02 1.16E-01

3.

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

4.

Percent of Limit 2.72E-01 6.29E-01 3.98E-01 1.02E+00 1.16E+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 which assumes that an individual drinks the water and eats the fish from the discharge point.

ODCM Section 2.2 organ dose limits are used.

Enclosure to WO 02-0019 Page 12 of 36 REPORT OF 2001 RADIOACTIVE EFFLUENTS: AIRBORNE Unit Quarter 1 Quarter 2 A. Fission and Activation Gases

1. Total Release Ci 8.54E-01 1.04E+00

2. Average Release Rate for Period

[tCi/sec 1.10E-01 1.32E-01

3. Percent of ODCM Limit (1) 4.31 E-03 5.12E-03 B. lodines

1. Total Iodine-131 Ci 0.00E+00 0.OOE+00

2. Average Release Rate for Period p.Ci/sec 0.00E+00 0.OOE+00

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

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

2. Average Release Rate for Period

ýtCi/sec 0.OOE+00 0.OOE+00

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

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

1. Total Release Ci 5.70E+00 1.19E+01

2. Average Release Rate for Period pCi/sec 7.33E-01 1.52E+00

3. Percent of ODCM Limit (4) 5.59E-02 1.14E-01 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 Gamma Airdose)(100) 10 mrad 5 mrad The largest value calculated between Gamma and Beta air dose is listed as the % of ODCM Limit.

2)

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

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

3)

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

% of ODCM Limit = (Highest Organ Dose Due to Particulates)(100) 7.5 mrem l

NOTE This type of methodology is used since the Wolf Creek ODCM ties release limits to doses rather than C Srates

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

Enclosure to WO 02-0019 Page 13 of 36 REPORT OF 2001 RADIOACTIVE EFFLUENTS: AIRBORNE Quarter Quarter Unit 3

4 A. Fission and Activation Gases

1. Total Release Ci 8.68E-01 1.88E+00

2. Average Release Rate for Period pCi/sec 1.09E-01 2.36E-01

3. Percent of ODCM Limit (1) 9.98E-03 9.28E-03 B. lodines

1. Total Iodine-131 Ci 0.OOE+00 O.OOE+00

2. Average Release Rate for Period liCi/sec 0.00E+00 0.OOE+00

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

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

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

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

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

1. Total Release Ci 1.96E+01 1.55E+01

2. Average Release Rate for Period plCi/sec 2.47E+00 1.95E+00

3. Percent of ODCM Limit (4) 1.83E-01 1.44E-01 NOTES:

1) The percent of ODCM limit for fission and activation gases is calculated using the following methodology: % of ODCM Limit = (Qtrly Total Beta Airdose)(100) or (Qtrly Total Gamma Airdose)(100) 10 mrad 5 mrad The largest value calculated between Gamma and Beta air dose is listed as the % of ODCM Limit.

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

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

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

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

4)

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

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

Enclosure to WO 02-0019 Page 14 of 36 2001 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 2.93E-01 3.59E-01 Kr-85 Ci n/a n/a 3.44E-01 2.09E-01 Kr-85M Ci n/a n/a n/a n/a Kr-87 Ci

<3.53E+01

<3.74E+01

<4.1OE-02

<5.27E-02 Kr-88 Ci

<4.52E+01

<4.79E+01

<5.26E-02

<6.75E-02 Xe-131M Ci n/a n/a n/a n/a Xe-133 Ci

<2.56E+01 3.29E-01 3.01E-02 3.99E-02 Xe-133M Ci

<7.94E+01

<8.41E+01

<9.26E-02

<1.19E-01 Xe-1 35 Ci 1.87E-01 1.04E-01

<1.36E-02 1.36E-04 Xe-138 Ci

<1.11E+03

<1.17E+03

<1.29E+00

<1.65E+00 Total Ci 1.87E-01 4.32E-01 6.67E-01 6.08E-01

2.

Halogens (Gaseous) 1-131 Ci

<2.44E-04

<2.58E-04

<2.84E-07

<3.65E-07 1-133 Ci

<2.44E-02

<2.58E-02

<2.84E-05

<3.65E-05 Total Ci O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00

3.

Particulates and Tritium H-3 Ci 5.41E+00 1.06E+01 2.89E-01 1.32E+00 Mn-54 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Fe-59 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Co-58 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Co-60 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Zn-65 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Mo-99 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Cs-I 34 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Cs-1 37 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Ce-141 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Ce-144 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Sr-89 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Sr-90 Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Gross Alpha Ci

<2.44E-03

<2.57E-03

<2.84E-06

<3.65E-06 Total Ci 5.41 E+00 1.06E+01 2.89E-01 1.32E+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.

Enclosure to WO 02-0019 Page 15 of 36 2001 GASEOUS EFFLUENTS (Continued)

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 7.65E-01 7.10E-01 Kr-85 Ci n/a n/a n/a 1.06E+00 Kr-85M Ci n/a n/a n/a n/a Kr-87 Ci

<3.85E+01

<3.86E+01

<9.20E-02

<1.04E-01 Kr-88 Ci

<4.93E+01

<4.95E+01

<1.18E-01

<1.33E-01 Xe-131M Ci n/a n/a n/a n/a Xe-133 Ci

<2.79E+01

<2.80E+01 1.02E-01 1.10E-01 Xe-133M Ci

<8.66E+01

<8.69E+01

<2.07E-01

<2.33E-01 Xe-135 Ci

<1.27E+01

<1.27E+01 2.67E-04

<6.09E-04 Xe-138 Ci

<1.21 E+03

<2.88E+00

<3.24E+00 Total Ci 0.OOE+00 O.OOE+00 8.68E-01 1.88E+00

2.

Halogens (Gaseous) 1-131 Ci

<2.66E-04

<2.67E-04

<6.36E-07

<7.16E-07 1-133 Ci

<2.66E-02

<2.67E-02

<6.36E-05

<7.16E-05 Total Ci 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00

3.

Particulates and Tritium H-3 Ci 1.59E+01 1.26E+01 3.71 E+00 2.83E+00 Mn-54 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Fe-59 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Co-58 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Co-60 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Zn-65 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Mo-99 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Cs-134 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Cs-137 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Ce-141 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Ce-144 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Sr-89 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Sr-90 Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Gross Alpha Ci

<2.66E-03

<2.67E-03

<6.36E-06

<7.16E-06 Total Ci 1.59E+01 1.26E+01 3.71E+00 2.83E+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.

Enclosure to WO 02-0019 Page 16 of 36 2001 GASEOUS CUMULATIVE DOSE

SUMMARY

TABLE 1 QUARTER 1 OF 2001 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR TOTAL BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI QUARTER 2 OF 2001 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR TOTAL BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI QUARTER 3 OF 2001 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR TOTAL BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI QUARTER 4 OF 2001 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR TOTAL BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI TOTALS FOR 2001 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR TOTAL BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI ODCM CALCULATED DOSE 0.OOE+00 4.03E-03 4.03E-03 4.03E-03 4.03E-03 4.03E-03 4.03E-03 0.OOE+00 8.44E-03 8.44E-03 8.44E-03 8.44E-03 8.44E-03 8.44E-03 0.OOE+00 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.39E-02 0.OOE+00 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 0.OOE+00 3.73E-02 3.73E-02 3.73E-02 3.73E-02 3.73E-02 3.73E-02 ODCM1 LIMIT 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01

% OF LIMIT O.OOE+00 5.37E-02 5.37E-02 5.37E-02 5.37E-02 5.37E-02 5.37E-02 0.OOE+00 1.13E-01 1.13E-01 1.13E-01 1.13E-01 1.13E-01 1.13E-01 0.OOE+00 1.85E-01 1.85E-01 1.85E-01 1.85E-01 1.85E-01 1.85E-01 0.OOE+00 1.46E-01 1.46E-01 1.46E-01 1.46E-01 1.46E-01 1.46E-01 0.OOE+00 2.49E-01 2.49E-01 2.49E-01 2.49E-01 2.49E-01 2.49E-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.

Enclosure to WO 02-0019 Page 17 of 36 2001 GASEOUS CUMULATIVE DOSE

SUMMARY

TABLE 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A.

Fission and Activation Gases

1.

Total Release - (Ci) 8.54E-01 1.04E+00 8.68E-01 1.88E+00 4.64E+00

2.

Total Gamma Airdose (mRad) 2.16E-04 2.56E-04 4.99E-04 4.64E-04 1.44E-03

3.

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

4.

Percent of Gamma Airdose Limit 4.33E-03 5.12E-03 9.98E-03 9.29E-03 1.44E-02

5.

Total Beta Airdose (mRad) 1.48E-04 1.55E-04 1.83E-04 3.14E-04 8.01 E-04

6.

Beta Airdose Limit (mRad) 1.OOE+01 1.OOE+01 1.OOE+01 1.00E+01 2.OOE+01

7.

Percent of Beta Airdose 1.48E-03 1.55E-03 1.83E-03 3.14E-03 4.OOE-03 Limit (mRad)

B.

Particulates

1.

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

2.

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

3.

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

4.

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

Tritium

1.

Total Release (Ci) 5.70E+00 1.19E+01 1.96E+01 1.55E+01 5.27E+01

2.

Maximum Organ Dose (mRern) 4.19E-03 8.54E-03 1.37E-02 1.08E-02 3.73E-02

3.

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

4.

Percent of Limit 5.59E-02 1.14E-01 1.83E-01 1.44E-01 2.49E-01 D.

Iodine

1.

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

2.

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

3.

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

4.

Percent of Limit 0.OOE+00 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.

Enclosure to WO 02-0019 Page 18 of 36 SECTION II SUPPLEMENTAL INFORMATION

1. Offsite Dose Calculation Manual Limits A. For liiuid 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 10-4 microCuries/ml total activity.

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

a.

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

b.

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

B.

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

a.

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

b.

For Iodine-131, Iodine-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-131, Iodine-1 33, tritium, and a radionuclide in particulate form with half-lives greater than 8 days in gaseous effluents released to area at and beyond the SITE BOUNDARY shall be limited to the following:

a.

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

b.

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

2.

Effluent Concentration Limits (ECLs)

Water - covered in Section 1.A.

Air - covered in Section 1.B.

Enclosure to WO 02-0019 Page 19 of 36

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

1. Batch Waste P

Release Tank Each Batch P.H.A.

Principal Gamma Emitters P

Each Batch P.H.A.

1-131

a. Waste Monitor Tank P

P.H.A.

Dissolved and Entrained One Batch/M Gases (Gamma Emitters)

b. Secondary Liquid P

L.S.

H-3 Waste Monitor Each Batch S.A.C.

Gross Alpha Tanks P

O.S.L.

Sr-89, Sr-90

2. Continuous Daily P.H.A.

Principal Gamma Emitters Releases Grab Sample P.H.A.

1-131

a. Steam Generator M

Dissolved and entrained Blowdown Grab Sample P.H.A.

Gases (Gamma Emitters)

b. Turbine Building Daily L.S.

H-3 Sump/Waste Water Grab Sample Treatment S.A.C.

Gross Alpha

c. Lime Sludge Pond Daily O.S.L.

Sr-89, Sr-90 Grab Sample O.S.L.

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

Enclosure to WO 02-0019 Page 20 of 36 B.

Gaseous Waste Effluents Gaseous, Release Sampling Frequency Method of Analysis Type of Activity Type Analysis P

P.H.A.

Principal Gamma Emitters Waste Gas Decay Tank Each Tank Grab Sample Containment Purge or P

P.H.A.

Principal Gamma Emitters Vent Each Purge Grab Sample Gas Bubbler and L.S.

H-3 (oxide)

Unit Vent M

P.H.A.

Principal Gamma Emitters Grab Sample Gas Bubbler and L.S.

H-3 (oxide)

Radwaste Building M

P.H.A Principal Gamma Emitters Vent Grab Sample For Unit Vent and Continuous P.H.A.

1-131 Radwaste Building Vent release types 1-133 listed above Continuous P.H.A.

Principal Gamma Emitters Particulate Sample Continuous S.A.C.

Gross Alpha Composite Particulate Sample Continuous O.S.L.

Sr-89, Sr-90 Composite Particulate Sample P = prior to each batch M = monthly L.S. = Liquid scintillation detector S.A.C. = scintillation alpha counter O.S.L. = performed by an offsite laboratory P.H.A. = gamma spectrum pulse height analysis using a High Purity Germanium detector

Enclosure to WO 02-0019 Page 21 of 36

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 75 gaseous batch releases during the reporting period.

The longest gaseous batch release lasted 2,240 minutes, while the shortest lasted 63 minutes. The average release lasted 230 minutes with a total gaseous batch release time of 16,992 minutes.

There were 51 liquid batch releases during the reporting period. The longest liquid batch release lasted 317 minutes, while the shortest lasted 48 minutes. The average release lasted 181 minutes with a total liquid batch release time of 8,793 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 personnel using the lake during times when fishing was allowed. The dose calculated for the maximum exposed individual for these four activities was as follows:

Plant Deliveries 4.02E-01 mRem William Allen White Building Workers 9.17E-03 mRem Access Road Users 4.12E-03 mRem Lake Use 5.58E-02 mRem The plant delivery calculations were based on deliveries 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months per week for 50 weeks per year.

The William Allen White Building occupancy was based on normal working hours of 2000 per year.

The usage factor for the access road south of the Radwaste Building was 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months per year. The dose to fishermen on the lake was based upon 3048 hours0.0353 days 0.847 hours 0.00504 weeks 0.00116 months (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months a day for 254 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 2001-1798 was written to document the fact that on June 1, 2001, Operations person identified that the automatic isolation capability of the Mini-Purge valves had not been verified quarterly, as required by Section 3.4.2 and Table 3.3 of AP 07B-003, ODCM. The last qualifying surveillance was performed on October 5, 2000. Licensee initiated changes to the ODCM must be documented and changes must be submitted to the NRC as part of or concurrent with the Annual Radioactive Effluent Release Report. Although Wolf Creek Nuclear Operating Corporation (WCNOC) did not change the ODCM document itself to remove the requirement for performing the subject surveillances, the elimination of the surveillance implementing the procedure, STN GT-004, Containment Purge Valves Actuation Test, constituted a change to the ODCM implementation program. Deletion of STN GT 004 was an inappropriate action and this procedure has since been incorporated into STS ST-201, Containment purge System In-service Valve Test.

PIR 2001-1599 was written June 20, 2001, and identified that the 3rd quarter, year 2000, Lime Pond sample was not sent off for Sr-89, Sr-90 and Fe-55 analysis as required by Table 2-1 of the ODCM.

The sample was located and sent to the offsite laboratory in July of 2001. The value for Sr-89 was

<5.8E-07 microcurie/ml. This did not meet the required LLD of 5E-08 due to the half-life of Sr-89 and the delay time in sending off the sample. We did not have enough remaining sample to meet the LLD.

Enclosure to WO 02-0019 Page 22 of 36 There has been no detectable Sr-89 and 90 in previous samples. There was no detectable gamma in the sample that failed to meet the LLD for Sr-89. Based on the absence of commonly found isotopes, it is logical that there would also be no Sr-89.

Enclosure to WO 02-0019 Page 23 of 36 2001 EFFLUENT CONCENTRATION LIMITS Liquid Effluents Average Diluted Concentration (uCi/ml) 1.35E-05 1.06E-12 6.93E-13 2.43E-1 1 8.17E-13 4.56E-1 I 3.78E-1 1 1.62E-10 8.12E-14 3.29E-1 2 8.97E-12 4.20E-1 1 9.57E-1 1 3.26E-14 10 CFR 20 ECL (uCi/ml) 1.OOE-03 5.OOE-04 3.OOE-05 1.OOE-04 6.OOE-05 2.OOE-05 3.OOE-06 3.OOE-05 1.O0E-06 9.OOE-07 1.OOE-06 2.OOE-04 2.OOE-04 2.00E-04 Nuclides H-3 Cr-51 Mn-54 Fe-55 Co-57 Co-58 Co-60 Sb-125 1-131 Cs-134 Cs-137 Kr-85 Xe-1 33 Xe-1 35 Curies 8.47E+02 6.68E-05 4.36E-05 1.59E-03 5.14E-05 2.87E-03 2.38E-03 1.02E-02 5.11 E-06 2.07E-04 5.64E-04 2.64E-03 6.02E-03 2.05E-06

% of ECL 1.35E+00 2.12E-07 2.31 E-06 2.43E-05 1.36E-06 2.28E-04 1.26E-03 5.40E-04 8.12E-06 3.66E-04 8.97E-04 2.1OE-05 4.78E-05 1.63E-08

Enclosure to WO 02-0019 Page 24 of 36 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2001 SOLID WASTE SHIPMENTS A.

SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste Unit

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

b. Dry compressible waste, contaminated equip. etc.

c. Irradiated components, control rods, etc.

d. Other m3*

Ci m3*

Ci 1-Year Period 1.32E+01"*

9.33E+2 2.71 E+02**

8.03E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

m3 = cubic meters

- 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.

Percent Abundance 24.289 32.856

b.

Dry compressible waste, contaminated equipment, etc.

Nuclide Percent Abundance 52.980 23.055 Curies 1.80E+02 2.40E+02 Curies 4.26E+00 1.85E+00 Est. Total Error %

2.50E+01 2.50E+01 2.50E+01 2.50E+01 Nuclide Name Fe-55 Ni-63 Name Be-7 Cs-1 37

Enclosure to WO 02-0019 Page 25 of 36

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

d. Other-None

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 6

Truck (Hittman Transport Services)

Barnwell Waste Management Facility, Barnwell, SC 5

Truck (Hittman Transport Services)

Duratek, Inc., Bear Creek, Oak Ridge, TN 3

2 1

Truck (Hittman Transport Services)

Truck (Kindrick Trucking)

Duratek Inc., Gallaher, Oak Ridge, TN Studsvik Processing Facility, LLC; Erwin, TN Studsvik Processing Facility, LLC; Erwin, 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 2001 period.

Enclosure to WO 02-0019 Page 26 of 36 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, 2001, through December 31, 2001, 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.

The quantity of missing hours in the following tables is 1110 hours0.0128 days 0.308 hours 0.00184 weeks 4.22355e-4 months . The lower availability (less than 90%)

was due to several factors: equipment out-of-service for a short period of time, short computer down time and the major factor of Wolf Creek's stringent method of calculating data availability.

Wolf Creek has approximately 20 different calculations that are used to calculate data availability; any one of these different calculations can cause a questionable data point.

All data points in question were discarded.

The missing/bad hours represent approximately 13% of the total; therefore, the meteorological tower was available approximately 87% of the time.

PIR 2002-0576 was written March 11, 2002, to evaluate the fact that we did not meet the 90% availability as stated in Regulatory Guide 1.23. The evaluation of the meteorological tower in PIR 2002-0576 is being performed in accordance with the corrective action program.

Enclosure to WO 02-0019 Page 27 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 2001 STABILITY CLASS:

ELEVATION:

WIND DIRECTION 1-3 N

1 NNE 0

NE 1

ENE 1

E 0

ESE 0

SE 1

SSE 4

S 2

SSW 1

SW 0

WSW 1

W 1

WNW 2

NW 3

NNW 0

TOTAL 14 A

10 METERS WIND SPEED (mph) 4-7 5

26 14 12 4

7 17 25 37 21 19 13 16 8

5 7

236 8-12 18 19 4

14 23 19 38 91 106 62 29 11 18 11 11 28 502 13-18 19-24

>24 37 9

0 0

8 8

13 29 139 97 12 3

13 21 11 53 453 11 4

0 0

0 1

3 3

30 23 2

1 2

10 7

5 102 0

1 0

0 0

3 3

3 0

0 0

1 1

0 12 PERIOD OF CALM (HOURS): 0 TOTAL 72 59 19 27 35 35 72 151 317 207 62 29 50 53 38 93 1319

Enclosure to WO 02-0019 Page 28 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 2001 STABILITY CLASS:

ELEVATION:

WIND DIRECTION 1-3 B

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

>24 TOTAL N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL PERIOD OF CALM (HOURS): 0 0

0 2

1 0

0 3

1 3

7 1

1 0

0 20 5

10 8

7 5

8 8

23 18 7

5 5

9 1

6 1

126 5

14 1

7 3

5 6

23 27 14 5

4 4

3 15 20 156 4

3 0

0 4

2 1

14 24 17 1

0 3

10 14 15 112 2

2 0

0 0

0 8

11 0

1 0

8 12 1

45 0

0 0

2 3

1 0

0 0

3 2

0 11 16 29 11 15 12 16 15 62 83 51 14 17 17 26 49 37 470

Enclosure to WO 02-0019 Page 29 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 STABILITY CLASS:

C ELEVATION:

10 METERS THROUGH DECEMBER 31 2001 WIND SPEED (mph)

WIND DIRECTION N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL PERIOD OF CALM (HOURS): 0 1-3 0

1 2

2 2

0 2

1 0

0 1

2 2

0 16 4-7 6

6 5

4 4

5 11 27 12 6

3 4

5 3

1 3

105 8-12 9

13 4

1 7

6 10 18 23 12 6

5 2

6 16 17 155 13-18 19-24 12 5

0 0

3 3

1 7

16 21 2

1 3

15 33 13 135 5

0 0

2 5

6 1

1 1

12 7

2 42

>24 0

0 0

1 2

1 0

0 1 1

1 0

7 TOTAL 32 25 11 7

16 14 24 56 58 47 12 11 13 39 60 35 460

Enclosure to WO 02-0019 Page 30 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 THROUGH DECEMBER 31 2001 STABILITY CLASS:

D ELEVATION:

10 METERS WIND SPEED (mph)

WIND DIRECTION N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL PERIOD OF CALM (HOURS): 0 1-3 4-7 8-12 13-18 19-24

>24 0

2 7

8 5

9 7

8 4

4 4

3 3

5 3

1 73 10 22 33 21 29 44 49 26 31 27 37 17 20 12 22 30 430 63 52 34 38 46 35 65 114 162 89 26 22 25 52 55 69 947 23 30 6

12 13 12 34 110 166 84 9

12 18 31 60 51 671 23 11 0

0 2

0 1

30 68 13 1

3 14 8

12 21 207 4

0 0

11 17 3

2 2

4 3

0 3

49 TOTAL 123 117 80 79 95 100 156 299 448 220 79 59 84 111 152 175 2377

Enclosure to WO 02-0019 Page 31 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: JANUARY 1 STABILITY CLASS:

E ELEVATION:

10 METERS THROUGH DECEMBER 31 2001 WIND SPEED (mph)

WIND DIRECTION N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL PERIOD OF CALM (HOURS): 1 1-3 4-7 0

4 20 7

6 8

5 5

8 5

3 3

1 3

0 6

84 8-12 26 22 34 34 40 40 49 67 64 44 18 43 18 12 14 42 73 618 26 4

14 33 36 53 185 175 63 14 12 18 20 43 40 758 13-18 19-24

>24 5

2 0

2 3

5 10 56 147 31 3

3 1

0 2

9 279 0

1 0

0 2

26 82 7

1 0

0 0

120 0

0 0

5 18 1

0 0

24 TOTAL 60 77 57 64 85 83 118 362 359 151 67 59 35 37 87 128 1883

Enclosure to WO 02-0019 Page 32 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

STABILITY CLASS:

ELEVATION:

WIND DIRECTION 1-3 N

2 NNE 7

NE 14 ENE 6

E I

ESE 7

SE 2

SSE 6

S 0

SSW 4

SW 2

WSW 5

W 1

WNW 3

NW 3

NNW 2

TOTAL 65 JANUARY 1 THROUGH DECEMBER 31 2001 F

10 METERS WIND SPEED (mph) 4-7 21 45 26 50 70 66 77 66 33 7

11 8

3 3

16 39 541 8-12 7

16 0

3 12 3

19 29 17 3

2 3

0 0

8 5

127 13-18 19-24 0

0 0

1 7

1 0

0 0

1 0

0 10

>24 0

0 0

TOTAL 30 68 40 59 83 76 98 102 57 15 15 16 4

7 27 46 743 PERIOD OF CALM (HOURS): 2

Enclosure to WO 02-0019 Page 33 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

STABILITY CLASS:

ELEVATION:

WIND DIRECTION 1-3 N

0 NNE 0

NE 18 ENE 6

E 2

ESE 5

SE 3

SSE 1

S 1

SSW 2

SW 0

WSW 1

W 0

WNW 0

NW 0

NNW 4

TOTAL 43 JANUARY 1 THROUGH DECEMBER 31 2001 G

10 METERS WIND SPEED (mph) 4-7 8-12 13-18 19-24 14 37 20 35 44 56 56 26 5

2 1

1 1

0 7

28 333 1

1 0

3 2

1 0

1 6

0 1

0 0

3 19 0

0 0

PERIOD OF CALM (HOURS): 0

>24 0

0 0

TOTAL 15 38 38 44 48 62 59 28 12 4

2 2

1 0

7 35 395

Enclosure to WO 02-0019 Page 34 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

STABILITY CLASS:

ELEVATION:

JANUARY 1 THROUGH DECEMBER 31 2001 ALL 10 METERS WIND SPEED WIND DIRECTION N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TOTAL PERIOD OF CALM (HOURS): 3 HOURS OF MISSING DATA: 1110 1-3 3

14 64 31 16 30 20 21 18 18 12 20 8

16 11 13 315 4-7 87 180 140 169 196 235 285 257 180 88 119 66 66 41 99 181 2389 8-12 125 141 47 80 126 105 191 461 516 243 83 57 67 92 148 182 2664 13-18 81 49 6

14 31 30 59 217 499 251 27 19 38 78 120 141 1660 (mph) 19-24 41 18 0

1 2

1 6

61 193 60 5

6 17 38 38 29 516

>24 4

1 0

0 0

22 43 9

2 2

5 8

4 3

103 TOTAL 341 403 257 295 371 401 561 1039 1449 669 248 170 201 273 420 549 7647

Enclosure to WO 02-0019 Page 35 of 36 SECTION IV This section contains corrected Annual Radioactive Effluent Release Reports covering the period January 1, 1993 through December 31, 2000.

PIR 2000-0813 documents discrepancies found in the Effluent Management Software (EMS) Database. The Annual Reports submitted from 1993 to 1998 contained data inconsistent with true data.

The EMS program was placed into service in 1993 to generate the release permits and associated reports.

While performing the 1999 Annual Effluent Report a problem was recognized where the values for Fe-55 were positive in Quarters 1 and 2. A comparison was made between the 1998 EMS nuclide tables and the 1998 cumulative tables and several discrepancies were found.

The values calculated in the cumulative tables are used to complete the Annual Radioactive Effluent Report.

The Annual Radioactive Effluent Reports submitted for 1993-1998 have been manually verified/validated and corrected as necessary. PIR 2001-1834 identifies that the volume released in 2000 was under-reported by 50,000 gallons. The 2000 Annual Radioactive Effluent Release Report was corrected to include the 50,000 gallons. These corrections are being submitted as Attachment I.

SECTION V ADDITIONAL INFORMATION

1. Unplanned or Abnormal Releases On December 6, 2001, Waste Gas Decay Tank #1 (THA01A) lost 3.6 psig during the performance of procedure STS IC-470A, "Gaseous Radwaste H2 and 02 Monitors HA Train "A"-Channel Calibration/ACOT."

The pressure at initiation was 8.8 psig.

During the performance of the procedure, GHN0103, Radwaste Vent Effluent Monitor release rate showed a slight increase for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . After the procedure was completed the tank pressure was 7.6 psig. The pressure had dropped to 5.2 psig when the Waste Gas Compressor was secured. PIR 2001-3064 was written to capture the events. 4.31E-02 curies of Kr-85 and 5.90E-06 curies of Xe-133 were released. This is captured on GRP 2001173. No ODCM limits were exceeded. The cause of this unplanned release was due to an inappropriate valve line-up, where the gas analyzer discharge to the waste gas compressor was open at the same time as the gas analyzer discharge to the Radwaste Building HVAC. Only one should have been open at a time. This provided a flow path so that any time the common downstream discharge to Radwaste HVAC valve was opened, a direct flow path from the Radwaste system to HVAC was opened. This inappropriate valve line up was because of a problem in the gas analyzer discharge valve configuration, which gave indications of the valve being closed when it was actually not fully seated. The gas analyzer discharge valves are located on top of the gas analyzer rack panel. The valve stem and hand wheel are on the front of the panel, while the valve body is behind the panel. The valve is not physically attached to the panel, rather the valve bonnet goes into a cutout in the panel, and is held in place by the gas tubing. Because of this configuration, there is very little to hold the valve from moving in or out of the panel. The as-found condition had the valve bonnets for two analyzers pushed back into the panel, so that the valve had dropped down. In this configuration, when the valve was taken to CLOSE, the hand wheel hit the panel before the valve vent closed. This gave the indication to the operator of the valve being closed when it was not. The valves in question have a work request written to provide support or relief of interference. This work request package is currently in the design phase.

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 4, was revised in 2001; it is included with this report as Attachment II. The other procedure, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program), AP 07B 004, Revision 2, was revised in 2001; it is included with this report as Attachment Ill.

3. Major Changes to Liquid, Solid, or Gaseous Radioactive Waste Treatment Systems

Enclosure to WO 02-0019 Page 36 of 36 As previously reported in the "1999 Annual Radioactive Effluent Release Report-Report 22", a state-of-the art filtration system was installed in 1998. Below is a summary of the improvements that were made to the system in 2001.

In July an Ozone (03) generation system was installed inline prior to the Tubular Ultrafiltration Unit (TUF) for treatment and destruction of organics, largely oil and grease. Since the installation of the 03 system, we have extended processing times and rates. This unit can treat the feed stream prior to the TUF, or clean the Reverse Osmosis membranes following a process that has degraded the unit flow to a minimum. With the 03 unit, TUF cleaning will typically recover the permeate flow to normal conditions within 12 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

This method is an improvement over using Sodium Hypochlorite (Bleach). The use of bleach resulted in aggressive corrosion to waste containers. This concentrated solution also reduced the concentration of the reject stream for activity since a high ratio was occupied by the chloride.

Ammonia intrusion has been a significant contributor to recent processing difficulties. The TUF continued to perform reliably, however the ammonia induced a chemical degradation of the Spiral Reverse Osmosis Unit membranes and downstream ion exchangers. New replacement membranes have restored the system performance. A new media was placed into the flow path with the WPS demineralizers to remove ammonia prior to the other operating demins. This media has performed well and has enabled WCNOC to regain our processing goal.

4. Land Use Census No new locations for dose calculation were identified during this report period.

5. Radwaste Shipments Seventeen 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 2001 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."

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 1 of 51 ATTACHMENT I Corrections to the Annual Radioactive Effluent Reports covering the reporting period from January 1, 1993, through December 31, 2000, are being submitted as Attachment I. Only the corrected pages are being submitted.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 2 of 51 1993 Annual Report This report was reviewed and no errors were identified.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 3 of 51 1994 Annual Report Liquid Effluents - 1994 Continuous Mode Nuclides Released H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Nb-95 Tc-99M Mo-99 Ag-110M Sn-113 Sn-117M Sb-125 1-131 1-133 Cs-1 34 Cs-1 37 La-1 40 Ce-141 Ce-144 Ar-41 Kr-85M Kr-85 Kr-87 Kr-88 Xe-131M Xe-1 33M Xe-133 Xe-135 Xe-138 G-ALPHA PERIOD TOTAL Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 1 4.55E-01 O.OOE+00

<5.36E-02

<1.07E-01

<5.36E-02 O.OOE+00 6.58E-07 2.74E-07

<5.36E-02

<5.36E-03

<5.36E-03 O.OOE+O0 O.OOE+0O

<5.36E-02 O.OOE+00 O.OOE+00 O.OOE+0O 7.33E-07

<1.07E-01 O.OOE+O0

<5.36E-02

<5.36E-02 O.OOE+O0

<5.36E-02

<1.07E+00

<1.07E-02 4.55E-01 Quarter 2 5.60E-01 O.OOE+00

<4.75E-02

<9.50E-02

<4.75E-02 0.OOE+00

<4.75E-02

<4.75E-03

<4.75E-03 O.OOE+00 0.00E+00

<4.75E-02 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00

<9.50E-02 O.OOE+00

<4.75E-02

<4.75E-02 0.OOE+00

<4.75E-02

<9.50E-01

<9.50E-03 5.60E-01 NOTE: Less than values are calculated using the lower limit Table 2-1 of the ODCM multiplied by the volume of waste Batch Mode Quarter 1 Quarter 2 4.54E+02 1.61 E+02 3.30E-05 0.OOE+00 2.34E-04 3.68E-04 6.05E-03 4.87E-03

<5.13E-04

<3.34E-04 1.33E-04 3.12E-05 5.02E-03 5.15E-04 5.73E-03 7.81 E-03

<5.13E-04

<3.34E-04

<5.13E-05

<3.34E-05

<5.13E-05 1.16E-05 7.76E-05 O.OOE+00 0.00E+00 3.66E-05

<5.13E-04

<3.34E-04 3.40E-06 5.49E-05 3.34E-06 0.00E+00 9.53E-06 O.OOE+00 4.86E-03 8.90E-04 4.97E-05 2.66E-04 6.1OE-06 1.30E-05 3.98E-04 4.21 E-04 5.23E-04 5.85E-04 0.OOE+00 6.40E-06

<5.13E-04

<3.34E-04

<5.13E-04 1.03E-04

<1.03E-02

<6.68E-03 1.05E-05

<6.68E-03

<1.03E-02 3.06E-03

<1.03E-02

<6.68E-03

<1.03E-02

<6.68E-03 1.15E-03 2.45E-03 1.10E-03 7.02E-04 1.18E-01 1.46E-01 1.26E-03 8.02E-05

<1.03E-02

<6.68E-03 5.52E-05 5.03E-06 4.54E+02 1.61E+02 of detection (LLD) values listed in discharged during the respective quarter. The less than values are not included in the summation for the total release values.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 4 of 51 LIQUID EFFLUENTS - 1994 Nuclides Released H-3 Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Rb-88 Sr-89 Sr-90 Sr-92 Zr-95 Mo-99 Nb-95 TC-99M Ru-1 03 Ag-110M Sn-113 Sn-1 17M Sb-1 24 Sb-1 25 Sb-126 1-131 1-132 1-133 1-135 Cs-134 Cs-137 La-1 40 Ce-141 Ce-144 Hf-181 Ar-41 Kr-85M Kr-85 Kr-87 Kr-88 Xe-131M Xe-133M Xe-1 33 Xe-135 Xe-138 G-ALPHA PERIOD TOTAL Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Continuous Mode Quarter 3 Quarter 4 1.54E-02 1.27E-02 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00

<1.35E-03

<4.23E-02

<2.70E-03

<8.47E-02

<1.35E-03

<4.23E-02 0.OOE+00 0.OOE+00

<1.35E-03

<4.23E-02

<1.35E-03

<4.23E-02

<1.35E-03

<4.23E-02 0.OOE+00 0.00E+00

<1.35E-04

<4.23E-03

<1.35E-04

<4.23E-03 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00

<1.35E-03

<4.23E-02 0.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00

<2.70E-03

<8.47E-02 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00

<1.35E-03

<4.23E-02

<1.35E-03

<4.23E-02 0.00E+00 0.OOE+00

<1.35E-03

<4.23E-02

<1.35E-03

<4.23E-02 0.OOE+00 0.OOE+00

<2.70E-02

<8.47E-01

<2.70E-02

<8.47E-01

<2.70E-02

<8.47E-01

<2.70E-02

<8.47E-01

<2.70E-02

<8.47E-01

<2.70E-02

<8.47E-01

<2.70E-02

<8.47E-01 5.03E-04 1.16E-03

<2.70E-02

<8.47E-01

<2.70E-02

<8.47E-01

<2.70E-04

<8.47E-03 1.59E-02 1.39E-02 Batch Mode Quarter 3 Quarter 4 3.30E+02 2.70E+01 4.02E-06 3.34E-05 4.88E-03 3.02E-02 1.07E-03 1.82E-03 1.61 E-02 9.48E-03 1.05E-03 3.19E-03 1.20E-04 2.50E-04 4.58E-02 7.09E-02 2.1OE-02 1.39E-02

<1.15E-03

<6.33E-04 5.49E-04 0.OOE+00

<1.15E-04

<6.33E-05

<1.15E-04

<6.33E-05 2.90E-06 O.OE+00 3.05E-04 3.96E-03

<1.15E-03

<6.33E-04 4.25E-04 6.81 E-03 7.56E-05 4.70E-05 1.OOE-04 6.34E-04 5.34E-05 0.OOE+00 5.11 E-05 6.08E-04 1.01 E-03 3.16E-05 1.49E-04 3.08E-03 6.16E-03 4.32E-02 0.00E+00 8.93E-05 6.85E-03 5.98E-03 0.00E+00 6.56E-05 4.51 E-05 4.25E-04 O.OOE+00 3.16E-05 1.84E-03 9.24E-04 2.47E-03 9.16E-04 1.58E-04 8.43E-05

<1.15E-03 5.14E-05 2.05E-04 2.83E-04 0.OOE+00 1.09E-04

<2.29E-02

<1.26E-02 1.84E-03

<1.26E-02 2.29E-01 2.50E-03

<2.29E-02

<1.26E-02 2.31 E-04

<1.26E-02 2.40E-01 4.17E-03 2.75E-01

<1.26E-02 2.62E+01 2.52E-02 1.83E-01 1.07E-04

<2.29E-02

<1.26E-02 2.98E-05 9.37E-06 3.57E+02 2.73E+01 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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 5 of 51 REPORT OF RADIOACTIVE EFFLUENT (1994) AIRBORNE Type of Effluent A. Fission and Activation Gases

1. Total Release

2. Average Release Rate for Period

3. Percent of ODCM Limit (1)

B. lodines (Iodine-131)

1. Total Release

2. Average Release Rate for Period

3. Percent of ODCM Limit (2)

C. Particulates (Half lives > 8 days)

1. Total Release

2. Average Release Rate for Period

3. Percent of ODCM Limit (3)

4. Gross Alpha Radioactivity D. Tritium

1. Total Release

2. Average Release Rate for Period

3. Percent of ODCM Limit (4)

Unit Ci JACi/sec Ci

ýiCi/sec Ci gCi/sec Ci Ci pCi/sec Quarter 1 1.33E+01 1.71 E+60 2.47E-02 Quarter 2 2.26E+01 2.87E+00 2.72E-02 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.00E+00 0.OOE+00 4.93E+00 6.56E-01 5.02E-02 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 6.67E+00 8.22E-01 6.49E-02 Quarter 3 Quarter 4 4.95E+02 4.06E+00 6.23E+01 5.11E-01 3.83E-01 1.64E-04 2.06E-05 1.64E-02 3.25E-03 1.72E-04 2.17E-05 1.72E-02 0.OOE+00 5.OOE-06 0.OOE+00 6.30E-07 0.OOE+00 3.55E-05 0.OOE+00 0.00E+00 6.42E+00 6.72E+00 8.08E-01 8.45E-01 6.12E-02 5.89E-02

1)

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

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

2)

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

% of ODCM Limit

=

(Total curies of Iodine-131)(100) 1 Curie

3)

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

% of ODCM Limit

=

(Highest Organ Dose due to Particulates)(1 00) 7.5 mrem

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 NOTE: This type of methodology is used since the Wolf Creek ODCM ties release limits to doses rather than Curie release rates.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 6 of 51 GASEOUS EFFLUENTS - 1994 Nuclides Released

1. Fission Gases Ar-41 Kr-85M Kr-85 Kr-87 Kr-88 Xe-131M Xe-1 33M Xe-1 33 Xe-1 35 Xe-1 38 Total for Period Continuous Mode Unit Quarter 1 Quarter 2 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.OOE+00 9.20E-02 0.OOE+00

<1.48E+01

<1.94E+01 0.OOE+00

<3.84E+01 4.67E+00 6.40E+00

<9.10E+01 Ci 1.13E+01 O.OOE+00 8.47E-02 0.OOE+00 1.05E-01 2.10E-01 0.OOE+00

<4.06E+01 1.47E+01 4.88E+00

<9.60E+01 2.OOE+01

2. lodines Ci Ci 1-131 1-133 Total for Period

3. Particulates

& Tritium H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 Cs-1 34 Cs-1 37 Ce-141 Ce-144 G-Alpha Total for Period

<2.53E-04

<2.67E-04

<4.81 E-07

<2.99E-07

<2.53E-02

<2.67E-03

<4.81 E-05

<2.99E-05 Ci 0.OOE+00 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 4.43E+00

<2.53E-03

<2.53E-03 Ci 4.43E+00 0.OOE+00 6.26E+00

<2.67E-03

<2.67E-03 5.49E-08 6.26E+00 0.OOE+00 4.98E-01

<4.81 E-06

<4.81 E-06 4.98E-01 0.OOE+00 4.06E-01

<2.99E-06

<2.99E-06 4.06E-01 NOTE: Less than values for Noble Gases are calculated using the lower limit of detection (LLD) values obtained at WCGS multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the ODCM LLD values are used. The less than values are not included in the summation for the total release values.

Batch Mode Quarter 1 3.75E-01 0.OOE+00 1.50E+00

<2.83E-02

<3.70E-02 0.00E+00 2.43E-04 8.40E-02 1.48E-03

<1.73E-01 1.96E+00 Quarter 2 3.08E-01 1.99E-05 2.21 E+00

<1.75E-02

<2.30E-02 1.48E-03 2.11 E-03 2.20E-01 6.75E-03

<1.08E-01 2.75E+00

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 7 of 51 GASEOUS CUMULATIVE DOSE

SUMMARY

1994 Table 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A. Fission and Activation

1. Total Release (Ci) 1.33E+01 2.26E+01 4.95E+02 4.06E+00 5.35E+02

2. Total Gamma Airdose (mrad) 1.24E-03 1.51 E-03 1.44E-02 1.58E-04 1.71 E-02

3. Gamma Airdose Limit (mrad) 5.OOE+00 5.O0E+00 5.OOE+00 5.OOE+00 1.OOE+01

4. Percent of Gamma Airdose Limit 2.47E-02 3.02E-02 2.88E-01 3.16E-03 1.71E-01

5. Total Beta Airdose (mrad) 1.77E-03 2.38E-03 3.83E-02 3.25E-04 4.28E-02

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 Limit 1.77E-02 2.38E-02 3.83E-01 3.25E-03 2.14E-01 (mrad)

B. Particulates

1. Total Particulates (Ci)

O.OOE+00 O.OOE+00 O.OOE+00 5.OOE-06 5.OOE-06

2. Maximum Organ Dose (mrem)

O.OOE+00 O.OOE+00 O.OOE+00 2.66E-06 2.66E-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+00 O.OOE+00 3.55E-05 1.77E-05 C. Tritium

1. Total Particulates (Ci) 4.93E+00 6.67E+00 6.42E+00 6.72E+00 2.47E+01

2. Maximum Organ Dose (mrem) 3.76E-03 4.86E-03 4.59E-03 4.42E-03 1.76E-02

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

4. Percent of Limit 5.02E-02 6.49E-02 6.12E-02 5.89E-02 1.17E-01 D. Iodine

1. Total 1-131, 1-133 (Ci)

O.OOE+00 O.OOE+O0 1.64E-04 1.72E-04 3.36E-04

2. Maximum Organ Dose (mrem)

O.OOE+00 O.OOE+00 1.67E-01 2.56E-02 1.93E-01

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 2.23E+00 3.41 E-01 1.28E+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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 8 of 51 1994 PERCENTAGE EFFLUENT CONCENTRATION LIMIT Nuclides Curies Average Diluted 10 CFR20

% of ECL Concentration ECL (jiCi/ml)

H-3 9.73E+02 1.62E-05 1 E-03 1.62E+00 Na-24 3.74E-05 6.22E-1 3 5E-05 1.24E-06 Cr-51 3.51 E-02 5.84E-1 0 5E-04 1.17E-04 Mn-54 3.49E-03 5.80E-1 1 3E-05 1.93E-04 Fe-55 6.21 E-02 1.03E-09 1 E-04 1.03E-03 Fe-59 4.24E-03 7.05E-1 1 1 E-05 7.05E-04 Co-57 5.34E-04 8.88E-12 6E-05 1.48E-05 Co-58 1.22E-01 2.03E-09 2E-05 1.02E-02 Co-60 4.84E-02 8.05E-10 3E-06 2.68E-02 Rb-88 5.49E-04 9.13E-12 4E-04 2.28E-06 Sr-90 1.16E-05 1.93E-13 5E-07 3.86E-05 Sr-92 2.90E-06 4.82E-14 4E-05 1.20E-07 Zr-95 4.26E-03 7.08E-1 1 2E-05 3.54E-06 Nb-95 7.31 E-03 1.22E-10 3E-05 4.07E-04 TC-99M 1.59E-04 2.64E-12 1E-03 2.64E-07 Ru-1 03 7.34E-04 1.22E-1 1 3E-05 4.07E-04 Ag-11OM 1.12E-04 1.86E-12 6E-06 3.1OE-05 Sn-113 7.74E-04 1.29E-11 3E-05 4.30E-05 Sn-1 17M 1.05E-03 1.75E-1 1 3E-05 5.83E-05 Sb-124 3.23E-03 5.37E-11 7E-06 7.67E-04 Sb-125 5.51E-02 9.16E-10 3E-05 3.05E-03 Sb-126 8.93E-05 1.48E-12 7E-06 2.11E-05 1-131 1.31 E-02 2.18E-10 1E-06 2.18E-02 1-132 6.56E-05 1.09E-1 2 1 E-04 1.09E-06 1-133 4.89E-04 8.13E-12 7E-06 1.16E-04 1-135 3.16E-05 5.25E-13 3E-05 1.75E-06 Cs-134 3.58E-03 5.95E-11 9E-07 6.61 E-04 Cs-1 37 4.49E-03 7.47E-1 1 1 E-06 7.47E-03 La-140 2.42E-04 4.02E-12 9E-06 4.47E-05 Ce-141 5.14E-05 8.55E-13 3E-05 2.85E-06 Ce-144 5.91 E-04 2.60E-12 3E-06 8.67E-05 Hf-181 1.09E-04 1.81E-12 2E-05 9.05E-06 Kr-85M 1.85E-03 8.13E-1 2 2E-04 4.07E-06 Kr-85 2.35E-01 3.91 E-09 2E-04 1.05E-05 Kr-88 2.31 E-04 3.84E-12 2E-04 1.92E-06 Xe-131M 2.48E-01 4.12E-09 2E-04 2.06E-03 Xe-1 33 2.65E+01 4.41 E-07 2E-04 2.20E-01 Xe-133M 2.77E-01 4.61E-09 2E-04 2.30E-03 Xe-135 4.61 E-01 7.66E-09 2E-04 3.83E-05

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 9 of 51 1995 Annual Report LIQUID EFFLUENTS - 1995 Nuclides Released H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Rb-88 Sr-89 Sr-90 Sr-92 Zr-95 Nb-95 Mo-99 Ru-1 03 Ag-110M Sn-113 Sn-1 17M Sb-125 1-131 Cs-1 34 Cs-1 37 La-140 Ce-141 Ce-144 Ar-41 Kr-85M Kr-85 Kr-87 Kr-88 Xe-131M Xe-1 31 Xe-133M Xe-133 Xe-135 Xe-138 G-ALPHA PERIOD TOTAL Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Continuous Mode Quarter 3 Quarter 4 1.77E-01 I.73E-O1 O.OOE+O0 O.OOE+00

<1.22E-02

<1.74E-02

<2.45E-02

<3.48E-02

<1.22E-02

<1.74E-02 O.OOE+00 O.OOE+00

<1.22E-02

<1.74E-02

<1.22E-02

<1.74E-02

<1.22E-02

<1.74E-02 O.OOE+00 O.OOE+00

<1.22E-03

<1.74E-03

<1.22E-03

<1.74E-03 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00

<1.22E-02

<1.74E-02 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

<2.45E-02

<3.48E-02

<1.22E-02

<1.74E-02

<1.22E-02

<1.74E-02 0.OOE+00 0.00E+00

<1.22E-02

<1.74E-02

<1.22E-02

<1.74E-02

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-01

<3.48E-01

<2.45E-03

<3.48E-03 1.77E-01 1.73E-01 Batch Mode Quarter 3 Quarter 4 2.86E+02 2.89E+02 2.41E-04 2.11E-04 1.04E-03 8.OOE-03 3.50E-02 1.34E-01 5.59E-05

<7.14E-04 5.61 E-05 5.78E-04 4.52E-03 1.55E-02 9.17E-03 1.04E-01

<4.39E-04

<7.14E-04 0.OOE+00 8.80E-04

<4.39E-05

<7.14E-05

<4.39E-05 2.71 E-05 0.O0E+00 2.56E-06 4.76E-04 1.37E-03 8.85E-04 3.64E-03

<4.39E-04

<7.14E-04 1.67E-06 0.00E+00 1.85E-04 2.28E-03 2.05E-04 7.61 E-04 0.OOE+00 2.50E-04 1.27E-02 3.13E-02

<8.78E-04

<1.43E-03 4.80E-04 2.37E-03 9.47E-04 3.90E-03 1.22E-06 0.OOE+00

<4.39E-04

<7.14E-04

<4.39E-04 6.83E-04

<8.78E-03

<1.43E-02

<8.78E-03 3.66E-04 5.30E-02 9.31 E-02

<8.78E-03

<1.43E-02

<8.78E-03 4.37E-05 2.71 E-02 7.43E-02

<8.78E-03

<1.43E-02 1.71 E-02 3.11E-02 2.15E+00 4.22E+00 3.34E-03 1.85E-02

<8.78E-03

<1.43E-02 1.72E-06 8.75E-05 2.88E+02 2.93E+02 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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 10 of 51 REPORT OF RADIOACTIVE EFFLUENT 1995 - AIRBORNE Type of Effluent A. Fission and Activation Gases

1. Total Release

2. Average Release Rate for Period

3. Percent of ODCM Limit (1)

B. lodines (Iodine-131)

1. Total Release

2. Average Release Rate for Period

3. Percent of ODCM Limit (2)

C. Particulates (Half lives > 8 days)

1. Total Release

2. Average Release Rate for Period

3. Percent of ODCM Limit (3)

4. Gross Alpha Radioactivity D. Tritium

1. Total Release

2. Average Release Rate for Period

3. Percent of ODCM Limit (4)

Unit Ci

ýt Ci/sec Ci 1iCi/sec Ci 1iCi/sec Ci Ci j.iCi/sec Quarter 1 3.36E+01 4.33E+00 4.62E-02 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 7.85E+00 1.01E+00 7.65E-02 Quarter 2 6.64E-01 8.45E-02 1.68E-03 Quarter 3 Quarter 4 2.1OE+01 2.31E+01 2.64E+00 2.91E+00 1.57E-02 1.71 E-02 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.03E-06 1.30E-07 O.OOE+00 0.OOE+00 1.90E-04 0.OOE+00 0.OOE+00 0.OOE+00 5.60E+00 6.61 E+00 3.89E+00 7.24E-01 8.32E-01 4.89E-01 5.23E-02 6.16E-02 3.58E-02

1.

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

% of ODCM Limit = (Qtrly Total Beta Airdose)(1 00) or (Qtrlv Total Gamma Airdose)(1 00) 10 mrad 5 mrad The largest value calculated between Gamma and Beta airdose 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 lodine-131)(100) 1 Curie

3.

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

% of ODCM Limit

=

(Highest Organ Dose due to Particulates)(100) 7.5 mrem

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 NOTE: This type of methodology is used since the Wolf Creek ODCM ties release limits to doses rather than Curie release rates.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 11 of 51 GASEOUS EFFLUENTS - 1995 Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Ar-41 Ci O.OOE+00 O.OOE+00 9.18E-02 1.02E-01 Kr-85M Ci O.OOE+00 6.45E-02 O.OOE+00 O.OOE+00 Kr-85 Ci 1.12E+01 O.OOE+00 2.12E+01 O.OOE+00 Kr-87 Ci

<1.95E+01

<1.93E+01

<6.72E-03

<6.39E-03 Kr-88 Ci

<2.26E+01

<2.24E+01

<7.79E-03

<7.41 E-03 Xe-131M Ci O.OOE+00 O.OOE+O0 7.81E-03 O.OOE+00 Xe-I 33M Ci

<4.28E+01

<4.23E+01

<1.47E-02

<1.40E-02 Xe-133 Ci

<1.25E+01 4.92E-01 7.59E-03 4.59E-03 Xe-135 Ci 9.76E-01

<5.14E+00 7.42E-05

<1.70E-03 Xe-1 38 Ci

<8.07E+02

<7.98E+02

<2.78E-01

<2.64E-01 Total for Period Ci 1.23E+01 5.56E-01 2.13E+01 1.07E-01

2. lodines 1-131 Ci

<2.71E-04

<2.68E-04

<9.32E-08

<8.86E-08 1-133 Ci

<2.71E-02

<2.68E-04

<9.32E-06

<8.86E-06 Total for Period Ci O.0OE+00 0.00E+00 0.OOE+00 O.OOE+00

3. Particulates

& Tritium H-3 Ci 7.75E+00 5.38E+00 8.76E-02 1.41 E-01 Mn-54 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Fe-59 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Co-58 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Co-60 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Zn-65 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Sr-89 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Sr-90 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Mo-99 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Cs-1 34 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Cs-I 37 Ci

<2.71E-03

<2.68E-03

<9.32E-07

<8.86E-07 Ce-141 Ci

<2.71E-03

<2.68E-03

<9.32E-07

<8.86E-07 Ce-144 Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 G-Alpha Ci

<2.71 E-03

<2.68E-03

<9.32E-07

<8.86E-07 Total for Period Ci 7.75E+00 5.38E+00 8.76E-02 1.41 E-01 NOTE: Less than values for Noble Gases are calculated using the lower limit of detection (LLD) values obtained at WCGS multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the ODCM LLD values are used.

The less than values are not included in the summation for the total release values.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 12 of 51 GASEOUS EFFLUENTS - 1995 Nuclides Released

1. Fission Gases Ar-41 Kr-85M Kr-85 Kr-87 Kr-88 Xe-131M Xe-i 33 Xe-1 33M Xe-1 35 Xe-1 38 Total for Period

2. lodines 1-131 1-133 Total for Period

3. Particulates and Tritium H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 Cs-1 34 Cs-1 37 Ce-1 41 Ce-144 G-Alpha Total for Period Unit Ci Ci Ci Ci Ci.

Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Continuous Mode Quarter 3 Quarter 4 0.00E+00 0.OOE+00 0.OOE+00

<1.92E+01

<2.22E+01 0.OOE+00 2.05E+01

<4.20E+01 1.67E-01

<7.92E+02 2.07E+01 0.OOE+00 0.OOE+00 0.OOE+00

<1.88E+01

<2.18E+01 O.OOE+00 2.26E+01

<4.13E+01 2.53E-02

<7.78E+02 2.27E+01 Batch Mode Quarter 3 Quarter 4 1.47E-01 0.OOE+00 0.OOE+00

<8.92E-03

<1.03E-02 0.OOE+00 1.36E-01

<1.96E-02 6.06E-04

<3.69E-01 2.83E-01 1.26E-01 0.OOE+00 0.OOE+00

<7.OOE-03

<8.12E-03 0.OOE+00 2.65E-01

<1.53E-02 8.07E-03

<2.89E-01 3.99E-01

<2.66E-04

<2.61E-04

<1.24E-07

<9.71E-08

<2.66E-02

<2.61E-02

<1.24E-05

<9.71E-06 O.OOE+O0 6.21 E+00

<2.66E-03

<2.66E-03 1.03E-06

<2.66E-03

<2.66E-03 6.21 E+00 0.OOE+00 3.82E+00

<2.61 E-03

<2.61 E-03 3.82E+00 0.O0E+00 3.78E-01

<1.24E-06

<1.24E-06 3.78E-01 0.OOE+00 6.85E-02

<9.71 E-07

<9.71 E-07 6.85E-02 NOTE: Less than values for Noble Gases are calculated using the LLD values obtained at WCGS multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the ODCM LLD values are used. The less than values are not included in the summation for the total release values.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 13 of 51 GASEOUS CUMULATIVE DOSE

SUMMARY

(1995)

Table 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A. Fission and Activation

1. Total Release (Ci) 3.36E+01 6.64E-01 2.10E+01 2.31E+01 7.84E+01

2. Total Gamma Airdose (mrad) 2.44E-04 8.43E-05 6.27E-04 6.50E-04 1.60E-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 4.88E-03 1.68E-03 1.25E-02 1.30E-02 1.60E-02

5. Total Beta Airdose (mrad) 4.62E-03 6.87E-05 1.57E-03 1.71 E-03 7.98E-03

6. Beta Airdose Limit (mrad) 1.OOE+01 1.OOE+01 1.OOE+01 1.OE+01 2.OOE+01

7. Percent of Beta Airdose Limit 4.62E-02 6.87E-04 1.57E-02 1.71 E-02 3.99E-02 (mrad)

B. Particulates

1. Total Particulates (Ci)

O.OOE+00 O.OOE+00 1.03E-06 0.00E+00 1.03E-06

2. Maximum Organ Dose (mrem)

O.OOE+00 O.OOE+00 1.42E-05 O.OOE+00 1.42E-05

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 1.90E-04 O.OOE+00 1.90E-04 C. Tritium

1. Total Particulates (Ci) 7.84E+00 5.60E+00 6.61E+00 3.89E+00 2.40E+01

2. Maximum Organ Dose (mrem) 5.74E-03 3.92E-03 4.62E-03 2.69E-03 1.69E-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 7.65E-02 5.23E-02 6.16E-02 3.58E-02 1.13E-01 D. Iodine

1. Total 1-131, 1-133 (Ci)

O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00

2. Maximum Organ Dose (mrem) 0.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 0.OOE+00 0.00E+00 Q.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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 14 of 51 1996 Annual Report REPORT OF RADIOACTIVE EFFLUENTS (1996) LIQUID Type of Effluent Unit Quarter 1 Quarter 2 A. Fission and Activation Products

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

Ci 8.10E-01 3.07E-01

2. Average Diluted Concentration During Period 1.Ci/ml 6.18E-08 6.65E-09

3. Percent of Applicable Limit (1) 1.62E+01 6.1 OE+00 B. Tritium

1. Total Release Ci 2.12E+02 7.57E+01

2. Average Diluted Concentration During Period p.Ci/ml 1.62E-05 1.64E-06

3. Percent of Applicable Limit (MPC)

(2) 1.62E+00 1.64E-01 (ECL) 5.40E-01 5.47E-02 C. Dissolved and Entrained Gases

1. Total Release Ci 9.75E+00 1.28E-02

2. Average Diluted Concentration During Period ICi/ml 7.44E-07 2.78E-10

3. Percent of Applicable Limit (3) 3.70E-01 1.39E-04 D. Gross Alpha Radioactivity

1. Total Release Ci 2.79E-03 7.98E-06 E. Volume of Waste Release (prior to dilution)

Liters 4.62E+07 8.25E+07 F. Volume of Dilution Water Used Liters 1.31 E+10 4.60E+10

1) The applicable limit for the Wolf Creek Generating Station 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 printed here 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)

(ECL, Appendix B, Table H / 2 10CFR20) 3)This value is derived by the following formula:

%ofApplicableLimit =(Average Diluted Concentration) (100)

(2E - 4 from ODCM Section 2.1)

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 15 of 51 REPORT OF RADIOACTIVE EFFLUENTS (1996) LIQUID Type of Effluent Unit Quarter 3 Quarter 4 A. Fission and Activation Products

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

Ci 4.91 E-02 2.11E-02

2. Average Diluted Concentration During Period

.Ci/ml 3.61 E-09 2.86E-09

3. Percent of Applicable Limit (1) 9.82E-01 4.22E-01 B. Tritium

1. Total Release Ci 1.69E+02 5.98E+01

2. Average Diluted Concentration During Period liCi/ml 1.24E-05 8.09E-06

3. Percent of Applicable Limit (MPC)

(2) 1.24E+00 8.09E-01 (ECL) 4.14E-01 2.70E-01 C. Dissolved and Entrained Gases

1. Total Release Ci 6.75E-03 5.94E-06

2. Average Diluted Concentration During Period p.Ci/ml 4.97E-10 8.04E-13

3. Percent of Applicable Limit (3) 2.48E-04 4.02E-07 D. Gross Alpha Radioactivity

1. Total Release Ci 8.92E-06 8.60E-06 E. Volume of Waste Release (prior to dilution)

Liters 2.79E+07 1.78E+07 F. Volume of Dilution Water Used Liters 1.36E+1 0 7.38E+09

1) The applicable limit for the Wolf Creek Generating Station 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 printed here is derived by dividing the total release Criies by 5 Curies and then multiplying the result by 100.

2) This value is derived by the following formula:

(Average Diluted Concentration) (100)

(ECL, Appendix B, Table I1 / 2 10CFR20)

3) This value is derived by the following formula:

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

(2E -4 from ODCM Section 2.1)

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 16 of 51 LIQUID EFFLUENTS 1996 Continuous Mode NUCLIDES RELEASED Sb-1 26 H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Hf-1 81 Nb-95 Zr-95 Mo-99 Ag-11 On Sn-113 Sn-1 17m Sb-1 25 1-131 Cs-134 Cs-1 37 Ce-141 Ce-144 Gross Alpha Ar-41 Kr-85m Kr-85 Kr-87 Kr-88 Xe-1 31 m Xe-1 33m Xe-133 Xe-135m Xe-1 35 Tc-99m Ru-1 03 Ru-106 Sb-124 Te-132 1-132 Ba-140 La-140 Np-239 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 1 n/a 2.79E-01 n/a

<1.69E-02

<3.38E-02

<1.69E-02 n/a 4.11 E-05 5.82E-05

<1.69E-02

<1.69E-03

<1.69E-03 n/a n/a n/a

<1.69E-02 n/a n/a n/a n/a 1.12E-05 3.61 E-05 3.01 E-05

<1.69E-02

<3.38E-03

<3.38E-01

<3.38E-01 1.17E-03

<3.38E-01

<3.38E-01 n/a n/a n/a n/a n/a n/a n/a n/a n/a Quarter 2 n/a 4.89E-01 n/a

<7.49E-02

<1.50E-01

<7.49E-02 n/a

<7.49E-02

<7.49E-03

<7.49E-03 n/a n/a n/a

<7.49E-03 n/a n/a n/a n/a

<1.50E-01

<7.49E-02

<1.50E-02

<1.50E+00

<1.50E+00 n/a n/a n/a n/a n/a n/a n/a n/a n/a Batch Mode Quarter 1 Quarter 2 2.61 E-05 n/a 2.12E+02 7.52E+01 7.83E-02 2.53E-02 2.31 E-02 4.83E-03 3.39E-01 1.09E-01 2.95E-03 3.12E-03 1.33E-03 3.53E-04 1.50E-01 5.76E-02 1.26E-01 2.59E-02

<3.64E-04

<3.05E-04

<3.64E-05

<3.05E-05 4.01 E-05

<3.05E-05 1.26E-04 n/a 1.32E-02 7.39E-03 9.54E-03 4.22E-03 5.82E-04

<3.05E-04 8.47E-04 1.22E-04 1.59E-03 3.64E-04 6.07E-04 n/a 5.38E-02 6.04E-02 2.44E-03

<3.05E-04 1.47E-03 9.33E-04 2.84E-03 9.73E-04 1.91E-04 6.11E-05 2.23E-03 9.26E-04 2.79E-03 7.98E-06

<7.28E-03

<6.11 E-03

<7.28E-03

<6.11 E-03 3.04E-01

<6.11 E-03

<7.28E-03

<6.11 E-03

<7.28E-03

<6.11 E-03 1.75E-01 1.16E-02 5.51 E-02

<6.11 E-03 9.21 E+00 9.65E-04

<7.28E-03

<6.11 E-03 9.73E-04 2.27E-04 5.36E-04 n/a 1.04E-03 9.36E-04 8.1 OE-04 n/a 1.34E-03 2.82E-03 8.91 E-05 n/a 1.28E-04 n/a 5.18E-04 n/a 1.29E-03 n/a 6.33E-04 n/a NOTE Less than values are calculated using the Lower Limit of Detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 17 of 51 LIQUID EFFLUENTS - 1996 NUCLIDES RELEASED H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Sr-92 Nb-95 Zr-95 Mo-99 Ag-11Om Sn-113 Sb-1 24 Sb-1 25 1-131 Cs-1 34 Cs-1 37 Ce-141 Ce-144 Gross Alpha Ar-41 Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-1 33m Xe-133 Xe-1 35m Xe-135 Na-24 Continuous Mode Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 3 2.17E-01 n/a

<1.62E-02

<1.78E-02

<1.62E-02 n/a

<1.62E-02

<1.62E-03

<1.62E-03 n/a n/a n/a

<1.62E-02 n/a n/a n/a n/a

<3.24E-02

<1.62E-02

<3.24E-03

<3.24E-01

<3.24E-01 n/a Quarter 4 1.75E-01 n/a

<8.88E-03

<2.34E-01

<8.88E-03 n/a

<8.88E-03

<8.88E-04

<8.88E-04 n/a n/a n/a

<8.88E-03 n/a n/a n/a n/a

<1.78E-02

<8.88E-03

<1.78E-03

<1.78E-01

<1.78E-01 n/a Batch Mode Quarter 3 1.69E+02 3.31 E-04 1.43E-03 1.31 E-02

<1.41 E-04 4.99E-05 3.97E-03 9.52E-03

<1.41 E-04

<1.41E-05

<1.41E-05 n/a 6.59E-04 2.88E-04

<1.41E-04 1.10E-05 5.88E-05 2.70E-05 8.02E-03 7.46E-05 6.31 E-03 4.75E-03

<1.41 E-04 3.18E-05 8.92E-06

<2.82E-03

<2.82E-03 5.63E-03

<2.82E-03

<2.82E-03 1.16E-03

<2.82E-03

<2.82E-03 n/a Quarter 4 5.98E+01 6.20E-04 7.93E-04 6.92E-03 3.03E-05 4.95E-05 4.98E-03 5.05E-03

<7.27E-05

<7.27E-06

<7.27E-06 2.11 E-06 1.39E-03 7.31 E-04

<7.27E-05 4.20E-05 1.31 E-04 3.25E-06 5.23E-03

<1.45E-04 9.83E-04 8.73E-04

<7.27E-05 1.98E-04 8.60E-06

<1.45E-03

<1.45E-03 5.94E-06

<1.45E-03

<1.45E-03 1.30E-06 NOTE Less than values are calculated using the Lower Limit of Detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 18 of 51 LIQUID CUMULATIVE DOSE

SUMMARY

1996 TABLE 1 ODCM ODCM 1 LIMIT

% OF LIMIT QUARTER 1 OF 1996 CALCULATED DOSE TOTAL DOSE (mRem) FOR BONE 3.50E-02 5.OOE+00 7.OOE-01 TOTAL DOSE (mRem) FOR LIVER 1.62E-01 5.OOE+00 3.24E+00 TOTAL DOSE (mRem) FOR TOTAL BODY 1.46E-01 1.50E+00 9.73E+00 TOTAL DOSE (mRem) FOR THYROID 1.13E-01 5.OOE+00 2.27E+00 TOTAL DOSE (mRem) FOR KIDNEY 1.22E-01 5.OOE+00 2.44E+00 TOTAL DOSE (mRem) FOR LUNG 1.08E-01 5.OOE+00 2.17E+00 TOTAL DOSE (mRem) FOR GI-LLI 5.56E-01 5.OOE+00 1.11E+01 QUARTER 2 OF 1996 TOTAL DOSE (mRem) FOR BONE 7.37E-03 5.OOE+00 1.47E+01 TOTAL DOSE (mRem) FOR LIVER 1.44E-01 5.OOE+00 2.89E+00 TOTAL DOSE (mRem) FOR TOTAL BODY 1.41 E-01 1.50E+00 9.40E+00 TOTAL DOSE (mRem) FOR THYROID 1.32E-01 5.OOE+00 2.64E+00 TOTAL DOSE (mRem) FOR KIDNEY 1.36E-01 5.OOE+00 2.72E+00 TOTAL DOSE (mRem) FOR LUNG 4.06E-02 5.OOE+00 8.12E-01 TOTAL DOSE (mRem) FOR GI-LLI 2.76E-01 5.OOE+00 5.52E+00 QUARTER 3 OF 1996 TOTAL DOSE (mRem) FOR BONE 3.22E-02 5.00E+00 6.44E-01 TOTAL DOSE (mRem) FOR LIVER 9.45E-02 5.O0E+00 1.89E+00 TOTAL DOSE (mRem) FOR TOTAL BODY 8.OOE-02 1.50E+00 5.33E+00 TOTAL DOSE (mRem) FOR THYROID 3.41 E-02 5.OOE+00 6.82E-01 TOTAL DOSE (mRem) FOR KIDNEY 5.39E-02 5.OOE+00 1.08E+00 TOTAL DOSE (mRem) FOR LUNG 1.31E-01 5.OOE+00 2.62E+00 TOTAL DOSE (mRem) FOR GI-LLI 4.47E-02 5.OOE+00 8.94E-01 QUARTER 4 OF 1996 TOTAL DOSE (mRem) FOR BONE 6.54E-03 5.OOE+00 1.31 E-01 TOTAL DOSE (mRem) FOR LIVER 1.62E-02 5.00E+00 3.24E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 1.33E-02 1.50E+00 8.87E-01 TOTAL DOSE (mRem) FOR THYROID 4.86E-03 5.OOE+00 9.72E-02 TOTAL DOSE (mRem) FOR KIDNEY 8.50E-03 5.OOE+00 1.70E-01 TOTAL DOSE (mRem) FOR LUNG 6.26E-03 5.OOE+00 1.25E-01 TOTAL DOSE (mRem) FOR GI-LLI 2.41 E-02 5.OOE+00 4.82E-01 TOTALS FOR 1996 TOTAL DOSE (mRem) FOR BONE 8.11E-02 1.OOE+01 8.11E-01 TOTAL DOSE (mRem) FOR LIVER 4.17E-01 1.OOE+01 4.17E+00 TOTAL DOSE (mRem) FOR TOTAL BODY 3.80E-01 3.OOE+00 1.27E+01 TOTAL DOSE (mRem) FOR THYROID 2.86E-01 1.OOE+01 2.86E+00 TOTAL DOSE (mRem) FOR KIDNEY 3.21 E-01 1.OOE+01 3.21 E+00 TOTAL DOSE (mRem) FOR LUNG 2.86E-01 1.OOE+01 2.86E+00 TOTAL DOSE (mRem) FOR GI-LLI 9.01E-01 1.OOE+01 9.01 E+00

1. Based on ODCM Section 2.2 which restricts dose to the whole body to less than or equal to 1.5 mRem per quarter and 3.0 mRem per year. Dose restriction of any organ is less than or equal to 5 mRem per quarter and 10 mRem per year.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 19 of 51 LIQUID CUMULATIVE DOSE

SUMMARY

1996 TABLE 2 A.

Fission and Activation Products (not including H-3, gases, alpha)

Total Release - (Ci)

Maximum Organ Dose (mRem)

Organ Dose Limit (mRem)

Percent of Limit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total 8.10E-01 3.07E-01 4.91E-02 2.11E-02 1.19E+00 4.71E-01 1.44E-01 6.1OE-02 2.70E-02 7.03E-01 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 9.43E+00 2.87E+00 1.22E+00 5.40E-01 1.41E+01 B.

Tritium Total Release - (Ci)

Maximum Organ Dose (mRem)

Organ Dose Limit (mRem)

Percent of Limit 2.12E+02 7.57E+01 1.69E+02 5.98E+01 5.17E+02 9.89E-02 1.32E-01 3.35E-02 5.81E-03 2.70E-01 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OE+01 1.98E+00 2.64E+00 6.70E-01 1.16E-01 5.41E+00 This table is included to show the correlation between Curies released and the associated calculated maximum organ dose. WCGS ODCM methodology is used to calculate the maximum organ dose which 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.

1.

2.

3.

4.

1.

2.

3.

4.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 20 of 51 REPORT OF RADIOACTIVE EFFLUENTS 1996 - AIRBORNE Unit Quarter 1 Quarter 2 A. Fission and Activation Gases

1. Total Release Ci 4.86E+02 7.45E+00

2. Average Release Rate for Period vCi/sec 6.24E+01 9.47E-01

3. Percent of ODCM Limit (1) 3.78E-01 1.011E-02 B. lodines

1. Total Iodine-131 Ci 5.54E-05 3.43E-05

2. Average Release Rate for Period VCi/sec 7.04E-06 4.36E-06

3. Percent of Applicable Limit (2) 5.5E-03 3.4E-03 C. Particulates

1. Particulates with Half-lives > 8 days Ci 6.88E-08 1.07E-06

2. Average Release Rate for Period VCi/sec 8.75E-09 1.36E-07

3. Percent of ODCM Limit (3) 1.72E-07 7.58E-06

4. Gross Alpha Radioactivity Ci 0.00E+00 0.OOE+00 D. Tritium 1 Total Release Ci 5.79E+00 7.35E+00 2 Average Release Rate for Period fiCi/sec 7.44E-01 9.35E-01 3 Percent of ODCM Limit (4) 5.48E-02 6.95E-02

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

(Qtrly Total Beta Airdose)(100)

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

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

(Total Curies of Iodine - 13 1)(100)

% of ODCM Limit =

ui 1 Curie

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

% of ODCM Limit (Highest Organ Dose Due to Particulates)(100) 7.5 mrem

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

% of ODCMLimit

=(Highest Organ Dose Due to H - 3)(100) 7.5 mrem NOTE This type of methodology is used since the WCGS ODCM ties release limits to doses rather than Curie release rates.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 21 of 51 REPORT OF RADIOACTIVE EFFLUENTS 1996 - AIRBORNE Unit Quarter 3 Quarter 4 A. Fission and Activation Gases

1. Total Release Ci 1.38E+00 9.33E+00

2. Average Release Rate for Period gCi/sec 1.73E-01 1.17E+00

3. Percent of ODCM Limit (1) 7.94E-03 1.27E-02 B. lodines

1. Total Iodine-131 Ci O.OOE+00 O.OOE+00

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

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

1. Particulates with Half-lives > 8 days Ci 0.00E+00 O.OOE+00

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

3. Percent of ODCM Limit (3)

O.OOE+00 O.OOE+00

4. Gross Alpha Radioactivity Ci O.OOE+00 O.OOE+00 D. Tritium 1 Total Release Ci 1.65E+01 1.08E+01 2 Average Release Rate for Period pCi/sec 2.08E+00 1.36E+00 3 Percent of ODCM Limit (4) 1.55E-01 1.01E-01

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

(Qtrly Total Beta Airdose)(100)

(Qtrly Total Gamma Airdose)(100)

% of ODCM Limit

=or 5ma 10 mrad 5 mrad The largest value calculated between Gamma and Beta airdose is listed as the % of ODCM Limit.

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

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

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

%of ODCM Limit = (Highest Organ Dose Due to Particulates)(100) 7.5 mrem

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 NOTE This type of methodology is used since the WCGS ODCM ties release limits to doses rather than Curie release rates.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 22 of 51 GASEOUS EFFLUENTS - 1996 NUCLIDES RELEASED Continuous Mode Batch Mode Unit Quarter I Quarter 2 Quarter 1 Quarter 2

1. Fission and Activation Gases Ar-41 Ci n/a n/a 4.23E-02 7.51 E-02 Kr-85 Ci n/a n/a 3.89E+01 7.23E+00 Kr-85m Ci n/a n/a n/a n/a Kr-87 Ci

<2.26E+01

<2.38E+01

<2.64E+00

<9.21 E-03 Kr-88 Ci

<1.97E+01

<2.08E+01

<2.30E+00

<8.02E-03 Xe-131m Ci 1.52E+00 n/a 1.31E+01 7.97E-02 Xe-1 33 Ci 1.41 E+02

<1.71 E+02 4.32E+02 5.85E-02 Xe-133m Ci

<3.74E+01

<3.95E+01 7.57E-01

<1.52E-02 Xe-1 35 Ci 1.29E+00

<3.64E+00 1.29E+00 O.OOE+00 Xe-138 Ci

<5.70E+02

<6.01E+02

<6.66E+01

<2.32E-01 Total for Period Ci 1.44E+02 0.OOE+00 4.86E+02 7.45E+00

2. Halogens (Gaseous) 1-131 Ci 5.54E-05 3.43E-05

<2.65E-05

<9.24E-08 1-133 Ci

<2.27E-02

<2.39E-02

<2.65E-03

<9.24E-06 Total for Period Ci 5.54E-05 3.43E-05 O.OOE+00 0.OOE+00

3. Particulates and Tritium H-3 Ci 4.39E+00 7.22E+00 1.40E+00 1.33E-01 Mn-54 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Fe-59 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Co-57 Ci 6.88E-08

<2.39E-03

<2.65E-04

<9.24E-07 Co-58 Ci n/a 1.07E-06 n/a n/a Co-60 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Zn-65 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Mo-99 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Cs-134 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Cs-1 37 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Ce-141 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Ce-144 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Sr-89 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Sr-90 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Gross Alpha Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Total for Period Ci 4.39E+00 7.22E+00 1.43E+00 1.33E-01 NOTE Less than values for Noble Gases are calculated using the Lower Limit of Detection (LLD) values obtained at WCGS multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the ODCM LLD values are used.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 23 of 51 GASEOUS EFFLUENTS 1996 NUCLIDES RELEASED Continuous Mode Batch Mode Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 1.Fisssion and Activation Gases Ar-41 Ci n/a n/a 5.37E-01 1.09E-01 Kr-85 Ci n/a n/a n/a 9.09E+00 Kr-85m Ci n/a n/a n/a n/a Kr-87 Ci

<2.52E+01

<2.78E+01

<6.72E-02

<1.19E-02 Kr-88 Ci

<2.19E+01

<2.42E+01

<5.85E-02

<1.03E-02 Xe-131m Ci n/a n/a n/a n/a Xe-133 Ci 5.10E-01 1.07E-01 6.65E-02 1.05E-02 Xe-133m Ci

<4.17E+01

<4.61E+01

<1.11E-01

<1.97E-02 Xe-1 35 Ci 2.64E-01 9.03E-03

<1.02E-02

<1.81 E-03 Xe-138 Ci

<6.34E+02

<7.01E+02

<1.69E+00

<2.99E-01 Total for Period Ci 7.74E-01 1.16E-01 6.04E-01 9.21E+00

2. Halogens (Gaseous) 1-131 Ci

<2.53E-04

<2.79E-04

<6.74E-07

<1.19E-07 1-133 Ci

<1.80E+02

<2.79E-02

<6.74E-05

<1.19E-05 Total for Period Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00

3. Particulates and Tritium H-3 Ci 1.28E+01 1.05E+01 3.71E+00 3.54E-01 Mn-54 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Fe-59 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Co-58 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Co-60 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Zn-65 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Mo-99 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Cs-1 34 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Cs-1 37 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Ce-141 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Ce-144 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Sr-89 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Sr-90 Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Gross Alpha Ci

<2.53E-03

<2.79E-03

<6.74E-06

<1.19E-06 Total for Period Ci 1.28E+01 1.05E+01 3.71 E+00 3.54E-01 NOTE Less than values for Noble Gases are calculated using the Lower Limit of Detection (LLD) values obtained at WCGS multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the ODCM LLD values are used.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 24 of 51 GASEOUS CUMULATIVE DOSE

SUMMARY

- 1996 Table I ODCM CALCULATED ODCM1

% OF LIMIT QUARTER 1 OF 1996 DOSE LIMIT TOTAL DOSE (mRem) FOR BONE 9.64E-05 7.50E+00 1.28E-03 TOTAL DOSE (toRerm) FOR LIVER 4.17E-03 7.50E+00 5.56E-02 TOTAL DOSE (mRem) FOR TOTAL BODY 4.13E-03 7.50E+00 5.51 E-02 TOTAL DOSE (mRern) FOR THYROID 3.59E-02 7.50E+00 4.79E-01 TOTAL DOSE (mRem) FOR KIDNEY 4.23E-03 7.50E+00 5.64E-02 TOTAL DOSE (mRem) FOR LUNG 4.07E-03 7.50E+00 5.43E-02 TOTAL DOSE (rnRem) FOR GI-LLI 4.08E-03 7.50E+00 5.44E-02 QUARTER 2 OF 1996 TOTAL DOSE (mRem) FOR BONE 5.99E-05 7.50E+00 7.99E-04 TOTAL DOSE (toRerm) FOR LIVER 5.19E-03 7.50E+00 6.92E-02 TOTAL DOSE (mRem) FOR TOTAL BODY 5.17E-03 7.50E+00 6.89E-02 TOTAL DOSE (toRerm) FOR THYROID 2.49E-02 7.50E+00 3.32E-01 TOTAL DOSE (mRem) FOR KIDNEY 5.23E-03 7.50E+00 6.97E-02 TOTAL DOSE (mRem) FOR LUNG 5.13E-03 7.50E+00 6.84E-02 TOTAL DOSE (mRem) FOR GI-LLI 5.14E-03 7.50E+00 6.85E-02 QUARTER 3 OF 1996 TOTAL DOSE (toRerm) FOR BONE O.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE (mRem) FOR LIVER 1.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 1.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mRem) FOR THYROID 1.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mRem) FOR KIDNEY 1.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mRem) FOR LUNG 1.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mRem) FOR GI-LLI 1.17E-02 7.50E+00 1.56E-01 QUARTER 4 OF 1996 TOTAL DOSE (mRem) FOR BONE O.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE (mRem) FOR LIVER 7.64E-03 7.50E+00 1.02E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 7.64E-03 7.50E+00 1.02E-01 TOTAL DOSE (mRem) FOR THYROID 7.64E-03 7.50E+00 1.02E-01 TOTAL DOSE (mRem) FOR KIDNEY 7.64E-03 7.50E+00 1.02E-01 TOTAL DOSE (mRem) FOR LUNG 7.64E-03 7.50E+00 1.02E-01 TOTAL DOSE (mRem) FOR GI-LLI 7.64E-03 7.50E+00 1.02E-01 TOTALS FOR 1996 TOTAL DOSE (mRem) FOR BONE 1.56E-04 1.50E+00 1.04E-03 TOTAL DOSE (mRem) FOR LIVER 2.87E-02 1.50E+00 1.91 E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 2.86E-02 1.50E+00 1.91 E-01 TOTAL DOSE (mRem) FOR THYROID 8.01 E-01 1.50E+00 5.34E-01 TOTAL DOSE (mRem) FOR KIDNEY 2.88E-02 1.50E+00 1.92E-01 TOTAL DOSE (mRem) FOR LUNG 2.85E-02 1.50E+00 1.90E-01 TOTAL DOSE (mRem) FOR GI-LLI 2.85E-02 1.50E+00 1.90E-01

1. Based on WCGS 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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 25 of 51 1996 Effluent Concentration Limits Curies Nuclides H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Sr-90 Sr-92 Zr-95 Nb-95 Ru-103 Ag-110M Sn-113 Sn-117M Sb-124 Sb-125 1-131 Cs-1 34 Cs-1 37 La-1 40 Ce-144 Hf-181 Kr-85 Xe-1 31 M Xe-133 Xe-1 33M Xe-135 Tc-99m Ru-1 06 Te-I32 1-132 Ba-140 Np-239 Na-24 Sb-126 Ce-141 Mo-99 5.17E+02 1.05E-01 3.02E-02 4.68E-01 6.1OE-03 1.78E-03 2.17E-01 1.66E-01 4.05E-05 2.11 E-06 1.50E-02 2.23E-02 1.96E-03 1.03E-03 2.1OE-03 6.07E-04 4.19E-03 1.29E-01 2.52E-03 9.69E-03 9.43E-03 1.29E-03 3.39E-03 1.26E-04 3.10E-01 1.87E-01 9.21 E+00 5.51 E-02 1.20E-03 5.36E-04 8.1 OE-04 8.91 E-05 1.28E-04 5.18E-04 6.33E-04 1.30E-06 2.61 E-05 2.52E-04 5.82E-04 Average Diluted Conc(mCi/ml) 6.45E-06 1.30E-09 3.77E-1 0 5.84E-09 7.58E-1 1 2.21 E-11 2.70E-09 2.07E-09 5.03E-13 2.62E-14 1.86E-10 2.78E-1 0 2.44E-11 1.28E-11 2.62E-1 1 7.54E-12 5.20E-1 1 1.60E-09 3.14E-1 1 1.21 E-10 1.18E-10 1.60E-11 4.23E-1 1 1.57E-1 2 3.85E-09 2.32E-09 1.14E-07 6.84E-1 0 1.50E-1 1 6.68E-12 1.01E-11 1.11E-12 1.59E-12 6.43E-1 2 7.89E-12 1.61E-14 3.25E-1 3 3.14E-12 7.26E-1 2 10 CFR20 ECL 1.OOE-03 5.00E-04 3.OOE-05 1.00E-04 1.O0E-05 6.OOE-05 2.OOE-05 3.OOE-06 5.OOE-07 4.OOE-05 2.OOE-05 3.OOE-05 3.OOE-05 6.00E-06 3.OOE-05 3.OOE-05 7.OOE-06 3.OOE-05 1.OOE-06 9.OOE-07 1.OOE-06 9.OOE-06 3.OOE-06 2.OOE-05 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 1.O0E-03 3.OOE-06 9.00E-06 1.OOE-04 8.OOE-06 2.OOE-05 5.00E-05 7.00E-06 3.OOE-05 2.00E-05

% of ECL 6.45E-01 2.61 E-04 1.27E-03 5.84E-03 7.58E-04 3.69E-05 1.35E-02 6.90E-02 1.01 E-04 6.55E-08 9.32E-04 9.27E-04 8.13E-05 2.13E-04 8.73E-05 2.51E-05 7.44E-04 5.34E-03 3.14E-03 1.37E-02 1.18E-02 1.78E-04 1.41 E-03 7.83E-06 1.93E-03 1.16E-03 5.72E-02 3.42E-04 7.50E-06 6.68E-07 3.35E-04 1.23E-05 1.59E-06 8.04E-05 3.95E-05 3.23E-08 4.64E-06 1.05E-05 3.63E-05

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 26 of 51 1997 Annual Report Section I REPORT OF RADIOACTIVE EFFLUENTS (1997) LIQUID Type of Effluent Unit Quarter 1 Quarter 2 A. Fission and Activation Products

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

Ci 1.01 E-02 3.92E-02

2. Average Diluted Concentration During Period fLCi/ml 6.33E-10 8.53E-10

3. Percent of Applicable Limit (1) 2.OOE-01 8.OOE-01 B. Tritium

1. Total Release Ci 2.1OE+02 7.12E+02

2. Average Diluted Concentration During Period pci/ml 1.32E-05 1.54E-05

3. Percent of Applicable Limit (MPC)

(2) 4.38E-01 5.14E-01 (ECL) 1.3E+00 1.5E+00 C. Dissolved and Entrained Gases

1. Total Release Ci 2.33E-04 8.83E-02

2. Average Diluted Concentration During Period pCi/ml 1.46E-1 1 1.91 E-09

3. Percent of Applicable Limit (3) 7.30E-06 9.56E-04 D. Gross Alpha Radioactivity

1. Total Release Ci 6.34E-06 2.80E-05 E. Volume of Waste Release (prior to dilution)

Liters 3.94E+07 3.60E+07 F. Volume of Dilution Water Used Liters 1.59E+10 4.61E+10

1) The applicable limit for the Wolf Creek Generating Station 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 printed here 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)

(ECL, Appendix B, Table 2 10CFR20)

3) This value is derived by the following formula:

(Average Diluted Concentration) (100)

%/o1 Applicable Limit =

(2E -4 from ODCM Section 2.1)

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 27 of 51 REPORT OF RADIOACTIVE EFFLUENTS (1997) LIQUID Type of Effluent Unit Quarter 3 Quarter 4 A. Fission and Activation Products

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

Cil 5.32E-02 6.41 E-02

2. Average Diluted Concentration During Period plCi/ml 2.21 E-09 1.47E-08

3. Percent of Applicable Limit (1) 1.06E+00 1.30E+00 B. Tritium

1. Total Release Ci 2.77E+02 1.29E+02

2. Average Diluted Concentration During Period

[LCi/ml 1.15E-05 2.96E-05

3. Percent of Applicable Limit (MPC)

(2) 3.84E-01 9.88E-01 (ECL) 1.2E+00 3.OE+00 C. Dissolved and Entrained Gases

1. Total Release Ci 1.50E-02 2.67E-02

2. Average Diluted Concentration During Period uCi/ml 6.24E-10 6.13E-09

3. Percent of Applicable Limit (3) 3.12E-04 3.07E-03 D. Gross Alpha Radioactivity

1. Total Release Ci 2.55E-05 7.53E-06 E. Volume of Waste Release (prior to dilution)

Liters 3.40E+07 7.84E+06 F. Volume of Dilution Water Used Liters 2.40E+10 4.35E+09

1) The applicable limit for the Wolf Creek Generating Station 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 printed here 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)

(ECL, Appendix B, Table 2 10CFR20)

3) This value is derived by the following formula:

%of ApplicableLimit = (Average Diluted Concentration) (100)

(2E - 4 from ODCM Section 2.1)

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 28 of 51 LIQUID EFFLUENTS 1997 NUCLIDE Continuous Mode Batch Mode RELEASED Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 H-3 Ci 4.79E-01 4.35E-01 2.10E+02 7.12E+02 Cr-51 Ci n/a n/a n/a n/a Mn-54 Ci

<1.95E-02

<1.75E-02 2.84E-05 9.69E-04 Fe-55 Ci

<3.91 E-02

<3.50E-02 1.80E-02 1.35E-02 Fe-59 Ci

<1.95E-02

<1.75E-02

<1.46E-04

<5.14E-04 Co-57 Ci n/a n/a n/a 6.68E-05 Co-58 Ci

<1.95E-02

<1.75E-02 2.68E-04 1.46E-03 Co-60 Ci

<1.95E-02

<1.75E-02 4.44E-03 1.49E-02 Zn-65 Ci

<1.95E-02

<1.75E-02

<1.46E-04

<5.14E-04 Sr-89 Ci

<1.95E-03

<1.75E-03

<1.46E-05

<5.14E-05 Sr-90 Ci

<1.95E-03

<1.75E-03

<1.46E-05 1.46E-05 Nb-95 Ci n/a n/a n/a 2.89E-04 Zr-95 Ci n/a n/a n/a 5.78E-05 Mo-99 Ci

<1.95E-02

<1.75E-02

<1.46E-04

<5.14E-04 Ag-110n Ci n/a n/a 2.01 E-06 n/a Sn-113 Ci n/a n/a 2.69E-05 1.31 E-04 Sn-117mn Ci n/a n/a n/a 1.26E-06 Sb-1 25 Ci n/a n/a 3.03E-03 5.48E-03 1-131 Ci

<3.91 E-02

<3.50E-02

<2.93E-04

<1.03E-03 Cs-134 Ci

<1.95E-02

<1.75E-02 3.20E-04 1.22E-03 Cs-1 37 Ci

<1.95E-02

<1.75E-02 4.40E-04 1.34E-03 Ce-141 Ci

<1.95E-02

<1.75E-02

<1.46E-04

<5.14E-04 Ce-144 Ci

<1.95E-02

<1.75E-02

<1.46E-04 4.41 E-05 Gross Alpha Ci

<3.91 E-03

<3.50E-03 6.34E-06 2.80E-05 Ar-41 Ci

<3.91 E-01

<3.50E-01

<2.93E-03

<1.03E-02 Kr-85m Ci

<3.91 E-01

<3.50E-01

<2.93E-03 2.38E-06 Kr-85 Ci

<3.91 E-01

<3.50E-01

<2.93E-03 6.25E-03 Kr-87 Ci

<3.91 E-01

<3.50E-01

<2.93E-03

<1.03E-02 Kr-88 Ci

<3.91 E-01

<3.50E-01

<2.93E-03

<1.03E-02 Xe-131m Ci

<3.91E-01

<3.50E-01

<2.93E-03 4.01E-05 Xe-133m Ci

<3.91 E-01

<3.50E-01

<2.93E-03 1.38E-04 Xe-133 Ci

<3.91 E-01

<3.50E-01 2.33E-04 8.18E-02 Xe-1 35m Ci

<3.91 E-01

<3.50E-01

<2.93E-03

<1.03E-02 Xe-135 Ci

<3.91 E-01

<3.50E-01

<2.93E-03 2.45E-05 Tc-99m Ci n/a n/a n/a n/a Ru-103 Ci n/a n/a n/a n/a Ru-106 Ci n/a n/a n/a n/a Sb-1 24 Ci n/a n/a n/a n/a Sb-1 26 Ci n/a n/a n/a 1.38E-06 Te-132 Ci n/a n/a n/a n/a 1-132 Ci n/a n/a n/a n/a NOTE Less than values are calculated using the Lower Limit of detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 29 of 51 LIQUID EFFLUENTS 1997 NUCLIDE RELEASED H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Sr-92 Nb-95 Zr-95 Mo-99 Tc-99M Ru-1 03 Ag-i 10m Sn-113 Sn-1 17m Sb-124 Sb-125 Sb-126 1-131 1-132 Te-132 Cs-134 Cs-137 Ce-141 Ce-144 Gross Alpha Ar-41 Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-1 35m Xe-135 Na-24 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Continuous Mode Quarter 3 Quarter 4 4.26E-01 1.20E-01 n/a n/a

<1.50E-02

<1.60E-02

<3.OOE-02

<3.20E-02

<1.50E-02

<1.60E-02 n/a n/a

<1.50E-02 1.12E-04

<1.50E-02

<1.60E-02

<1.50E-02

<1.60E-02

<1.50E-03

<1.60E-03

<1.50E-03

<1.60E-03 n/a n/a n/a n/a n/a n/a

<1.50E-02

<1.60E-02 n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

<3.OOE-02

<3.20E-02 n/a n/a n/a n/a

<1.50E-02 1.07E-04

<1.50E-02

<1.60E-02

<1.50E-02

<1.60E-02

<1.50E-02

<1.60E-02

<3.OOE-03

<3.20E-03

<3.OOE-01

<3.20E-01

<3.Q0E-01

<3.20E-01

<3.OOE-01

<3.20E-01

<3.OOE-01

<3.20E-01

<3.O0E-01

<3.20E-01

<3.OOE-01

<3.20E-01

<3.OOE-01

<3.20E-01

<3.OOE-01

<3.20E-01

<3.OOE-01

<3.20E-01

<3.OOE-01

<3.20E-01 n/a n/a Batch Mode Quarter 3 Quarter 4 2.77E+02 1.29E+02 8.53E-05 7.13E-03 6.59E-04 5.69E-04 1.60E-02 5.31 E-03

<4.07E-04 3.84E-04 1.18E-05 4.80E-05 4.54E-04 2.47E-02 1.13E-02 2.83E-03

<4.07E-04

<3.79E-04

<4.07E-05

<3.79E-05

<4.07E-05

<3.79E-05 n/a n/a 4.39E-05 1.14E-03 n/a 8.58E-04

<4.07E-04

<3.79E-04 n/a 1.05E-05 n/a 2.71 E-06 8.43E-06 n/a 3.39E-05 2.82E-05 n/a 1.15E-04 n/a 1.19E-03 2.16E-02 1.81E-02 n/a 4.86E-06 1.47E-06

<7.59E-04 n/a 6.83E-05 n/a 9.27E-06 1.71 E-03 7.90E-04 1.41 E-03 6.86E-04

<4.07E-04

<3.79E-04 6.57E-06

<3.79E-04 2.55E-05 7.53E-06

<8.14E-03

<7.59E-03 8.44E-06 6.73E-05

<8.14E-03

<7.59E-03

<8.14E-03

<7.59E-03

<8.14E-03

<7.59E-03

<8.14E-03

<7.59E-03 1.21 E-04 6.34E-04 1.48E-02 1.70E-02

<8.14E-03

<7.59E-03 1.06E-04 8.93E-03 n/a 1.32E-06 NOTE Less than values are calculated using the Lower Limit of detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 30 of 51 LIQUID CUMULATIVE DOSE

SUMMARY

(1997)

TABLE 2 A.

Fission and Activation Products(not including H-3, gases, alpha)

Total Release - (Ci)

Maximum Organ Dose (mRem)

Organ Dose Limit (mRem)

Percent of Limit Quarter 1 1.01 E-02 6.25E-03 5.00E+00 1.25E-01 Quarter 2 3.92E-02 1.34E-02 5.00E+00 2.69E-01 Quarter 3 5.32E-02 1.42E-02 5.00E+00 2.84E-01 Quarter 4 6.41 E-02 9.77E-02 5.00E+00 1.95E+00 B.

Tritium Total Release - (Ci)

Maximum Organ Dose (mRem)

Organ Dose Limit (mRem)

Percent of Limit 2.10 E+02 3.80E-02 5.OOE+00 7.60E-01 7.12E+02 6.45E-02 5.00E+00 1.29E+00 2.77E+02 2.73E-02 5.00E+00 5.45E-01 1.29E+02 7.76E-02 5.00E+00 1.55E+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 which assumes that an individual drinks the water and eats the fish from the discharge point. ODCM Section 2.2 organ dose limits are used.

1.

2.

3.

4.

1.

2.

3.

4.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 31 of 51 REPORT OF RADIOACTIVE EFFLUENTS (1997) AIRBORNE Unit Quarter 1 Quarter 2 A. Fission and Activation Gases

1. Total Release Ci 1.29E-01 4.52E-01

2. Average Release Rate for Period uCi/sec 1.67E-02 5.75E-02

3. Percent of ODCM Limit (1) 1.08E-03 7.82E-04 B. lodines

1. Total Iodine-131 Ci O.OOE+00 2.95E-06

2. Average Release Rate for Period

ýiCi/sec O.OOE+00 3.75E-07

3. Percent of Applicable Limit (2)

O.OOE+00 2.95E-04 C. Particulates

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

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

3. Percent of ODCM Limit (3)

O.OE+00 O.OOE+00

4. Gross Alpha Radioactivity Ci 6.18E-08 O.OOE+00 D. Tritium Total Release Ci 1.20E+01 2.58E+01 Average Release Rate for Period liCi/sec 1.61 E+00 3.28E+00 Percent of ODCM Limit (4) 1.19E-01 2.44E-01

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

Limit (Qtrly Total Beta Airdose)(100)

(Qtrly Total Gamma Aridose)(100)

% of ODCM Lmt=or 10 mrad 5 mrad The largest value calculated between Gamma and Beta airdose 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)(100) 7.5 mrem NOTE This type of methodology is used since the Wolf Creek ODCM ties release limits to doses rather than Curie rele

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

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

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 32 of 51 GASEOUS EFFLUENTS 1997 NUCLIDES RELEASED 1.Fission and Activation Gases Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-1 31 m Xe-1 33 Xe-1 33m Xe-1 35 Xe-138 Total

2. Halogens (Gaseous) 1-131 1-133 Total

3. Particulates and Tritium H-3 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Mo-99 Cs-1 34 Cs-1 37 Ce-141 Ce-144 Sr-89 Sr-90 Gross Alpha Total.

Continuous Mode Unit Quarter 1 Quarter 2 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci n/a n/a 4.39E-02

<2.03E+01

<1.51 E+01 n/a

<6.10E+00

<2.89E+01

<3.94E+00

<3.17E+02 4.39E-02

<1.88E-04

<1.88E-02 O.OE+00 1.17E+01

<1.88E-03

<2.27E-03 n/a

<1.88E-03

<1.88E-03 6.18E-08 1.17E+01 n/a n/a n/a

<2.34E+01

<1.75E+01 n/a 1.13E-01

<3.34E+01

<4.56E+00

<3.67E+02 1.13E-01 2.95E-06

<2.17E-02 2.95E-06 2.26E+01

<2.17E-03

<2.17E-03 n/a

<2.17E-03

<2.17E-03 2.26E+01 Batch Mode Quarter 1 Quarter 2 7.68E-02 n/a n/a

<8.19E-04

<6.11 E-04 n/a 8.76E-03

<1.17E-03 5.58E-05

<1.28E-02 8.56E-02

<7.59E-09

<7.59E-07 O.OOE+00 2.95E-01

<7.59E-08

<7.59E-08 n/a

<7.59E-08

<7.59E-08 2.95E-01 2.90E-01 n/a 2.67E-05

<3.90E-02

<2.91 E-02 n/a 4.90E-02

<5.56E-02

<7.58E-03

<6.10E-01 3.39E-01

<3.61 E-07

<3.61 E-05 O.OOE+00 3.25E+00

<3.61 E-06

<3.61 E-06 n/a

<3.61 E-06

<3.61 E-08 3.25E+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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 33 of 51 GASEOUS CUMULATIVE DOSE

SUMMARY

1997 TABLE 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A.

Fission and Activation Gases

1.

Total Release - (Ci) 1.29E-01 4.52E-01 1.22E+01 1.44E+00 1.42E+01

2.

Total Gamma Airdose (mRad) 5.38E-05 1.92E-04 1.71 E-03 3.02E-04 2.23E-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 1.08E-03 3.84E-03 3.42E-02 6.04E-03 2.26E-02

5.

Total Beta Airdose (mRad) 2.42E-05 7.82E-05 1.88E-03 1.75E-04 2.16E-03

6.

Beta Airdose Limit (mRad) 1.OOE+01 1.OOE+01 1.001E+01 1.OOE+01 2.OOE+01

7.

Percent of Beta Airdose 2.42E-04 7.82E-04 1.88E-02 1.75E-03 1.08E-02 Limit (mRad)

B.

Particulates

1.

Total Particulates (Ci) 0.OOE+00 0.00E+00 0.00E+00 1.27E-08 1.27E-08

2.

Maximum Organ Dose (mRem) 0.OOE+00 0.00E+00 0.OOE+00 1.08E-08 1.08E-08

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 1.44E-07 7.18E-08 C.

Tritium

1.

Total Release (Ci) 1.20E+01 2.58E+01 1.83E+01 2.83E+01 8.44E+01

2.

Maximum Organ Dose (mRem) 8.94E-03 1.83E-02 1.32E-02 1.97E-02 6.01 E-02

3.

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

4.

Percent of Limit 1.19E-01 2.44E-01 1.76E-01 2.62E-01 4.00E-01 D.

Iodine

1.

Total 1-131, 1-133 (Ci) 0.OOE+00 2.95E-06 2.27E-07 1.91 E-10 3.18E-06

2.

Maximum Organ Dose (mRem)

O.OOE+00 1.83E-03 0.O0E+00 1.10E-07 1.83E-03

3.

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

4.

Percent of Limit 0.OOE+00 2.44E-02 0.OOE+00 1.47E-06 1.22E-02 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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 34 of 51 1997 Effluent Concentration Limits Nuclides H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Sr-90 Zr-95 Nb-95 Ru-1 03 Ag-110M Sn-113 Sn-1 17M Sb-124 Sb-125 Sb-126 1-131 Cs-1 34 Cs-137 Ce-144 Kr-85 Kr-85M Xe-1 31 M Xe-i 33 Xe-1i33M Xe-135 Tc-99m Te-132 1-132 Na-24 Curies 1.33E+03 7.22E-03 2.22E-03 5.28E-02 3.84E-04 1.28E-04 2.70E-02 3.37E-02 1.46E-05 9.16E-04 1.47E-03 2.71 E-06 1.04E-05 2.20E-04 1.16E-04 1.19E-03 4.83E-02 6.24E-06 1.47E-06 4.13E-03 3.89E-03 5.07E-05 6.25E-03 7.81 E-05 4.01 E-05 1.15E-01 8.93E-04 9.08E-03 1.05E-05 9.27E-06 6.83E-05 1.32E-06 Average Diluted Concentration (mCi/ml) 1.47E-05 7.97E-1 1 2.45E-1 1 5.83E-10 4.24E-12 1.41 E-12 2.98E-1 0 3.70E-10 1.61 E-13 1.01 E-11 1.62E-1 1 2.99E-14 1.15E-03 2.43E-1 2 1.28E-1 2 1.31 E-11 5.33E-10 6.89E-1 4 1.62E-14 4.56E-11 4.27E-1 1 5.60E-1 3 6.90E-1 1 8.63E-1 3 4.43E-1 3 1.27E-09 9.86E-12 1.OOE-10 1.16E-13 1.02E-1 3 7.54E-1 3 1.46E-14 10 CFR 20 ECL 1.OOE-03 5.OOE-04 3.OOE-05 1.OOE-04 1.O0E-05 6.OOE-05 2.00E-05 3.OOE-06 5.OOE-07 2.OOE-05 3.OOE-05 3.OOE-05 6.OOE-06 3.OOE-05 3.00E-05 7.OOE-06 3.OOE-05 7.OOE-06 1.OOE-06 9.OOE-07 1.001E-06 3.OOE-06 2.0OE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 1.OOE-03 9.OOE-06 7.OOE-06 5.OOE-05

% of ECL 1.47E+00 1.59E-05 8.17E-05 5.83E-04 4.24E-05 2.36E-06 1.49E-03 1.23E-02 3.23E-05 5.05E-05 5.41 E-05 9.98E-08 1.91 E-06 8.10E-06 4.27E-06 1.88E-04 1.78E-03 9.85E-07 1.62E-06 5.07E-03 4.27E-03 1.87E-05 3.45E-05 4.31 E-07 2.21 E-07 6.35E-04 4.93E-06 5.OOE-05 1.16E-08 1.14E-06 1.08E-05 2.92E-08

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 35 of 51 GASEOUS EFFLUENTS 1997 NUCLIDES RELEASED

1. Fission and Activation Gases Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-1 33 Xe-1i33m Xe-1 35 Xe-1 38 Total

2. Halogens (Gaseous) 1-131 1-133 Total

3. Particulates and Tritium H-3 Cr-51 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Mo-99 Cs-1 34 Cs-1 37 Ce-141 Ce-144 Sr-89 Sr-90 Gross Alpha Total Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Continuous Mode Quarter 3 Quarter 4 n/a n/a n/a

<2.42E+01

<1.81 E+01 n/a 7.80E-02

<3.45E+01

<4.71 E+00

<3.79E+02 7.80E-02 2.27E-07

<2.24E-02 2.27E-07 1.28E+01 n/a

<2.24E-03

<2.24E-03 n/a n/a

<2.24E-03

<2.24E-03 1.28E+01 n/a n/a n/a 2.44E+01

<1.82E+01 n/a 7.96E-01

<3.48E+01 4.32E-02

<4.74E+00 8.39E-01

<2.24E-04

<2.26E-02 0.OOE+00 2.02E+01 n/a

<2.79E-03

<2.79E-03 n/a n/a

<2.79E-03

<2.79E-03 2.02E+01 Batch Mode Quarter 3 Quarter 4 2.61 E+00 9.25E+00 n/a

<2.78E-01

<2.08E-01 n/a 2.40E-01

<3.97E-01 5.97E-04

<4.35E+00 1.21E+01

<2.57E-06

<2.57E-04 0.00E+00 5.57E+00 n/a

<2.57E-05

<2.57E-05 n/a n/a

<2.57E-05

<2.57E-05 5.57E+00 4.19E-01 n/a n/a

<2.84E+00

<2.12E+00 n/a 1.79E-01

<4.06E+00

<5.53E-01

<4.45E+01 5.99E-01 1.91 E-10

<2.63E-03 1.91 E-10 8.11E+00 3.14E-09 2.07E-1 0

<2.63E-04 8.46E-09 3.77E-10

<2.63E-04 2.31 E-10 3.24E-10

<2.63E-04

<2.63E-04 8.11 E+00 NOTE Less than values for Noble Gases are calculated using the lower limit of detection (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the ODCM LLD rvalues are used.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 36 of 51 GASEOUS CUMULATIVE DOSE

SUMMARY

1997 Table 1 QUARTER 1 OF 1997 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR T-BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI QUARTER 2 OF 1997 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR T-BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI QUARTER 3 OF 1997 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR T-BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI QUARTER 4 OF 1997 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR T-BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI TOTALS FOR 1997 TOTAL DOSE (mRem) FOR BONE TOTAL DOSE (mRem) FOR LIVER TOTAL DOSE (mRem) FOR T-BODY TOTAL DOSE (mRem) FOR THYROID TOTAL DOSE (mRem) FOR KIDNEY TOTAL DOSE (mRem) FOR LUNG TOTAL DOSE (mRem) FOR GI-LLI 0DCM CALCULATED DOSE 0.00E+00 8.37E -03 8.37E-03 8.37E-03 8.37E-03 8.37E-03 8.37E-03 5.14E-06 1.82E-02 1.82E-02 1.99E-02 1.82E-02 1.82E-02 1.82E-02 3.87E-07 1.30E-02 1.30E-02 1.31 E-02 1.30E-02 1.30E-02 1.30E-02 7.02E-09 2.OOE-02 2.OOE-02 2.OOE-02 2.OOE-02 2.OOE-02 2.OOE-02 5.54E-06 5.96E-02 5.96E-02 6.14E-02 5.96E-02 5.96E-02 5.96E-02 ODCM1 LIMIT 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01

% OF LIMIT 0.OOE+00 1.12E-01 1.12E-01 1.12E-01 1.12E-01 1.12E-01 1.12E-01 6.85E-05 2.43E-01 2.43E-01 2.66E-01 2.43E-01 2.43E-01 2.43E-01 5.16E-06 1.73E-01 1.73E-01 1.75E-01 1.73E-01 1.73E-01 1.73E-01 9.37E-O8 2.67E-O1 2.67E-O1, 2.67E-01 2.67E-01 2.67E-01 2.67E-01 3.69E-05 3.97E-01 3.97E-01 4.09E-01 3.97E-01 3.97E-01 3.97E-01

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 37 of 51 1998 Annual Report SECTION I REPORT OF 1998 RADIOACTIVE EFFLUENTS LIQUID Unit Quarter 1 Quarter 2 A.

Fission and Activation Products

1.

Total Release (not including tritium, gases, Ci 1.47E-02 1.1 5E-02 alpha)

2.

Average Diluted Concentration During Period pCi/ml 4.58E-10 4.86E-10

3.

Percent of Applicable Limit (1) 0.29 0.23 B.

Tritium

1.

Total Release Ci 1.45E+01 5.01E+01

2.

Average Diluted Concentration During Period l.Ci/ml 4.51 E-07 2.12E-06

3.

Percent of Applicable Limit (MPC) 1.50E-02 7.08E-02 (ECL)

(2) 0.05 0.21 C.

Dissolved and Entrained Gases

1.

Total Release Ci 0.OOE+00 4.57E-04

2.

Average Diluted Concentration During Period

,Ci/ml 0.00E+00 1.94E-1 1

3.

Percent of Applicable Limit (3) 0.OOE+00 9.69E-06 D.

Gross Alpha Radioactivity

1.

Total Release Ci 1.92E-04 2.69E-04 E.

Volume of Waste Released (prior to dilution)

Liters 3.75E+07 1.08E+08 F.

Volume of dilution water used Liters 1.11E+10 2.37E+10

1) The applicable limit for the Wolf Creek Generating Station 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 printed here 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)

(ECL, Appendix B, Table 2 10CFR20)

3)

This value is derived by the following formula:

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

(2.Oe -04 from ODCM Section 2.1)

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 38 of 51 1998 RADIOACTIVE EFFLUENTS LIQUID Unit Quarter 3 Quarter 4 A.

Fission and Activation Products

1.

Total Release (not including tritium, gases, Ci 1.54E-02 2.51 E-02 alpha)

2.

Average Diluted Concentration During Period pICi/ml 6.66E-10 1.11E-09

3.

Percent of Applicable Limit (1) 0.31 0.50 B.

Tritium

1.

Total Release Ci 2.1OE+02 5.50E+02

2.

Average Diluted Concentration During Period

ýtCi/ml 9.11 E-06 2.43E-05

3.

Percent of Applicable Limit (MPC) 3.04E-01 8.10E-01 (ECL)

(2) 0.91 2.43 C.

Dissolved and Entrained Gases

1.

Total Release Ci 7.22E-03 1.29E-01

2.

Average Diluted Concentration During Period PLCi/ml 3.13E-10 5.71E-09

3.

Percent of Applicable Limit (3) 1.57E-04 2.85E-03 D.

Gross Alpha Radioactivity

1.

Total Release Ci 1.12E-03 0.OOE+00 E.

Volume of Waste Released (prior to dilution)

Liters 4.20E+07 1.37E+08 F.

Volume of dilution water used Liters 2.30E+10 2.24E+10

1) The applicable limit for the Wolf Creek Generating Station 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 printed here 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)

(ECL, Appendix B, Table 21 OCFR20)

3)

This value is derived by the following formula:

(Average Diluted Concentration) (100)

% of Applicable Limit = -(2E - 4 from ODCM Section 2.1)

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 39 of 51 1998 LIQUID EFFLUENTS Continuous Mode NUCLIDES RELEASED H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Sr-92 Nb-95 Zr-95 Zr-97 Mo-99 Ag-11Om Sn-113 Sn-117m Sb-1 24 Sb-125 1-131 Cs-1 34 Cs-137 Ce-141 Ce-144 Gross Alpha Ar-41 Kr-85M Kr-85 Kr-87 Kr-88 Xe-1 31M Xe-i 33M Xe-1 33 Xe-1 35M Xe-1 35 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci CI Ci Ci Ci Ci Quarter 1 2.61 E-01 n/a

<2.06E-02

<4.13E-02

<2.06E-02 n/a

<2.06E-02

<2.06E-03

<2.06E-03 n/a n/a n/a n/a

<2.06E-02 n/a n/a n/a n/a n/a

<4.13E-02

<2.06E-02

<2.06E-02 1.90E-04

<4.13E-01

<4.13E-01 Quarter 2 3.85E-01 n/a

<5.91 E-02

<1.18E-01

<5.91 E-02 n/a

<5.91 E-02

<5.91 E-03

<5.91 E-03 n/a n/a n/a n/a

<5.91 E-02 n/a n/a n/a n/a n/a

<1.18E-01

<5.91 E-02

<5.91 E-02 2.60E-04

<1.18E+00

<1.18E+OO

<1.65E-03

<1.18E+00

<1.18E+00 Batch Mode Quarter 1 1.42E+01 n/a 1.02E-04 1.65E-03

<8.24E-05 7.33E-05 8.82E-03 5.31 E-04

<8.24E-05

<8.24E-06

<8.24E-06 n/a 7.82E-05 3.38E-05 n/a

<8.24E-05 n/a 1.26E-05 n/a 1.54E-04 2.99E-03

<1.65E-04 1.19E-04 1.25E-04

<8.24E-05

<8.24E-05 1.42E-06

<1.65E-03

<1.65E-03 Quarter 2 4.95E+01 n/a 3.36E-04 2.44E-03

<1.58E-04 4.58E-05 3.33E-03 3.04E-03

<1.58E-04

<1.58E-05

<1.58E-05 n/a 1.01 E-04 2.98E-05 n/a

<1.58E-04 n/a n/a n/a 1.67E-05 1.86E-03

<3.17E-04 9.54E-05 1.85E-04

<1.58E-04

<1.58E-04 5.41 E-07

<3.17E-03

<3.17E-03 4.57E-04

<3.17E-03

<3.17E-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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 40 of 51 1998 LIQUID EFFLUENTS Continuous Mode NUCLIDES RELEASED H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Sr-92 Nb-95 Zr-95 Zr-97 Mo-99 Ag-11Om Sn-113 Sn-1 17m Sb-1 25 1-131 Cs-134 Cs-137 Ce-141 Ce-144 Gross Alpha Ar-41 Kr-85M Kr-85 Kr-87 Kr-88 Xe-1 31 M Xe-133M Xe-133 Xe-135M Xe-135 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Cl Ci Ci Ci Ci Quarter 3 6.54E-01 n/a

<2.08E-02

<4.16E-02

<2.08E-02 n/a

<2.08E-02

<2.08E-03

<2.08E-03 n/a n/a n/a n/a

<2.08E-02 n/a n/a n/a n/a

<4.16E-02

<2.08E-02

<2.08E-02 1.103E-03

<4.16E-01

<4.16E-01 Quarter 4 5.70E-01 Sn/a

<6.83E-02

<1.37E-01

<6.83E-02 n/a

<6.83E-02

<6.83E-03

<6.83E-03 n/a n/a n/a n/a

<6.83E-02 n/a n/a n/a n/a

<1.37E-01

<6.83E-02

<1.37E-02

<1.37E+00

<1.38E+00

<1.37E+00

<1.37E+00 Batch Mode Quarter 3 2.09E+02 3.44E-05 6.34E-04 2.97E-03

<2.29E-04 7.11E-05 3.35E-03 4.73E-03

<2.29E-04

<2.29E-05

<2.29E-05 n/a 2.60E-04 4.22E-05 n/a

<2.29E-04 n/a 1.53E-05 n/a 2.78E-03 8.64E-05 1.54E-04 2.33E-04

<2.29E-04

<2.29E-04 2.26E-05

<4.57E-03

<4.57E-03 7.22E-03

<4.57E-03

<4.57E-03 Quarter 4 5.49E+02 n/a 1.23E-03 6.63E-03

<3.99E-04 1.06E-04 4.14E-03 6.88E-03

<3.99E-04

<3.99E-05

<3.99E-05 n/a 2.45E-04 4.18E-05 n/a

<3.99E-04 n/a 2.20E-05 1.37E-05 5.20E-03 3.08E-05 2.30E-04 4.27E-04

<3.99E-04

<7.98E-05

<7.98E-03

<7.98E-03 1.31 E-02

<7.98E-03

<7.98E-0:

1.80E-03 3.37E-04 1.14E-01

<7.98E-03 1.25E-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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 41 of 51 1998 LIQUID CUMULATIVE DOSE

SUMMARY

TABLE 1 QUARTER 1 OF 1998 ODCM CALCULATED ODCM 1 LIMIT

% OF LIMIT DOSE TOTAL DOSE (mRem) FOR BONE 1.17E-03 5.OOE+00 2.34E-02 TOTAL DOSE (mRem) FOR LIVER 7.70E-03 5.OOE+00 1.54E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 7.19E-03 1.50E+00 4.79E-01 TOTAL DOSE (mRem) FOR THYROID 5.60E-03 5.00E+00 1.12E-01 TOTAL DOSE (mRem) FOR KIDNEY 6.28E-03 5.OOE+00 1.26E-01 TOTAL DOSE (mRem) FOR LUNG 5.84E-03 5.OOE+00 1.17E-01 TOTAL DOSE (mRem) FOR GI-LLI 7.75E-03 5.OOE+00 1.55E-01 QUARTER 2 OF 1998 TOTAL DOSE (mRem) FOR BONE 9.98E-04 5.OOE+00 2.00E-02 TOTAL DOSE (mRem) FOR LIVER 2.28E-02 5.OOE+00 4.56E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 2.23E-02 1.50E+00 1.49E+00 TOTAL DOSE (mRem) FOR THYROID 2.11 E-02 5.OOE+00 4.22E-01 TOTAL DOSE (mRem) FOR KIDNEY 2.17E-02 5.OOE+00 4.33E-01 TOTAL DOSE (mRem) FOR LUNG 2.13E-02 5.OOE+00 4.26E-01 TOTAL DOSE (mRem) FOR GI-LLI 2.28E-02 5.OOE+00 4.57E-01 QUARTER 3 OF 1998 TOTAL DOSE (mRem) FOR BONE 1.14E-03 5.OOE+00 2.28E-02 TOTAL DOSE (mRern) FOR LIVER 1.72E-02 5.OOE+00 3.44E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 1.67E-02 1.50E+00 1.11E+00 TOTAL DOSE (mRem) FOR THYROID 1.55E-02 5.O0E+00 3.10E-01 TOTAL DOSE (mRem) FOR KIDNEY 1.59E-02 5.OOE+00 3.18E-01 TOTAL DOSE (mRem) FOR LUNG 1.55E-02 5.OOE+00 3.10E-01 TOTAL DOSE (mRem) FOR GI-LLI 1.90E-02 5.00E+00 3.80E-01 QUARTER 4 OF 1998 TOTAL DOSE (mRem) FOR BONE 2.74E-03 5.OOE+00 5.49E-02 TOTAL DOSE (mRem) FOR LIVER 6.58E-02 5.00E+00 1.32E+00 TOTAL DOSE (mRem) FOR TOTAL BODY 6.45E-02 1.50E+00 4.30E+00 TOTAL DOSE (mRem) FOR THYROID 6.13E-02 5.OOE+00 1.23E+O0 TOTAL DOSE (mRem) FOR KIDNEY 6.27E-02 5.OOE+00 1.25E+00 TOTAL DOSE (mRem) FOR LUNG 6.17E-02 5.OOE+00 1.23E+00 TOTAL DOSE (mRem) FOR GI-LLI 6.51 E-02 5.00E+00 1.30E+00 TOTALS FOR 1998 TOTAL DOSE (mRem) FOR BONE 6.05E-03 1.OOE+01 6.05E-02 TOTAL DOSE (mRem) FOR LIVER 1.13E-01 1.00E+01 1.13E+00 TOTAL DOSE (mRem) FOR TOTAL BODY 1.11E-01 3.OOE+00 3.70E+00 TOTAL DOSE (mRem) FOR THYROID 1.03E-01 1.OOE+01 1.03E+00 TOTAL DOSE (mRem) FOR KIDNEY 1.07E-01 1.OOE+01 1.07E+00 TOTAL DOSE (mRem) FOR LUNG 1.04E-01 1.OOE+01 1.04E+00 TOTAL DOSE (mRem) FOR GI-LLI 1.15E-01 1.OOE+01 1.15E+00

1. Based on ODCM Section 2.2, which restricts dose to the whole body to less than or equal to 1.5 mRem per quarter and 3.0 mRem per year.

Dose restriction of any organ is less than or equal to 5 mRem per quarter and 10 mRem per year.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 42 of 51 1998 LIQUID CUMULATIVE DOSE

SUMMARY

TABLE 2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A.

Fission and Activation Products (not including H-3, gases, alpha)

1.

Total Release - (Ci) 1.47E-02 1.15E-02 1.54E-02 2.52E-02 6.68E-02

2.

Maximum Organ Dose (mRem) 2.15E-03 1.73E-03 5.80E-03 4.57E-03 1.42E-02

3.

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

4.

Percent of Limit 4.30E-02 3.47E-02 1.16E-01 9.15E-02 1.36E-01 B.

Tritium

1.

Total Release - (Ci) 1.45E+01 5.01 E+01 2.1 OE+02 5.50E+02 8.25E+02

2.

Maximum Organ Dose (mRem) 5.60E-03 2.11E-02 1.53E-02 6.12E-02 1.03E-01

3.

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

4.

Percent of Limit 1.12E-01 4.22E-01 3.05E-01 1.22E+00 1.03E+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 which assumes that an individual drinks the water and eats the fish from the discharge point. ODCM Section 2.2 organ dose limits are used.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 43 of 51 REPORT OF 1998 RADIOACTIVE EFFLUENTS: AIRBORNE Unit Quarter 1 Quarter 2 A. Fission and Activation Gases

1. Total Release Ci 2.63E-01 2.17E+00

2. Average Release Rate for Period tiCi/sec 3.39E-02 2.75E-01

3. Percent of ODCM Limit (1) 1.93E-03 2.22E-03 B. lodines

1. Total Iodine-131 Ci O.OOE+00 O.OOE+00

2. Average Release Rate for Period 1.Ci/sec O.OOE+00 0.OOE+0O

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

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

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

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

4. Gross Alpha Radioactivity Ci 1.37E-08 6.38E-08 D. Tritium Total Release Ci 9.03E+00 1.70E+01 Average Release Rate for Period pCi/sec 1.16E+00 2.16E+00 Percent of ODCM Limit (4) 8.51 E-02 1.61E-01

1)

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

(Qtrly Total Beta Airdose)(100)

(Qtrly Total Gamma Aridose)(100)

% of ODCM Limit =

or l0 mrad 5 mrad The largest value calculated between Gamma and Beta airdose is listed as the % of ODCM Limit.

2)

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

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

I Curie

3)

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

Limit(Highest Organ Dose Due to Particulates)(100)

% of ODCM Li.it 7.5 mirem NOTE 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:

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

% ofODCMLimit

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 44 of 51 REPORT OF 1998 RADIOACTIVE EFFLUENTS - AIRBORNE Unit Quarter 3 Quarter 4 A. Fission and Activation Gases

1. Total Release Ci 8.86E+00 1.01 E+01

2. Average Release Rate for Period LtCi/sec 1.12E+00 1.26E+00

3. Percent of ODCM Limit (1) 3.OOE-02 1.13E-02 B. lodines

1. Total Iodine-131 Ci O.OOE+00 0.OOE+00

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

3. Percent of Applicable Limit (2)

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

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

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

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

4. Gross Alpha Radioactivity Ci 1.11 E-08 1.28E-08 D. Tritium

1. Total Release Ci 3.54E+01 1.45E+01

2. Average Release Rate for Period uCi/sec 4.45E+00 1.82E+00

3. Percent of ODCM Limit (4) 3.32E-01 1.37E-01

1)

The percent of ODCM limit for fission and activation gases is calculated using the following (Qtrly Total Beta Airdose)(100)

(Qtrly Total Gamma Aridose)(100) methodology: % of ODCM Limit =

or 10 mrad 5 mrad The largest value calculated between Gamma and Beta airdose is listed as the % of ODCM Limit.

2)

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

(Total Curies of Iodine -131)(100)

% of ODCM Limit Curie

3)

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

(Highest Organ Dose Due to Particulates)(100)

% of ODCM Limit =

7.5 mrem

4)

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

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 45 of 51 1998 GASEOUS EFFLUENTS NUCLIDES RELEASED Continuous Mode Batch Mode Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 1.Fission and Activation Gases Ar-41 Ci n/a n/a 1.44E-01 4.09E-01 Kr-85 Ci n/a n/a n/a n/a Kr-85m Ci n/a n/a n/a n/a Kr-87 Ci

<2.76E+01

<2.87E+01

<1.55E-02

<4.47E-02 Kr-88 Ci

<2.06E+01

<2.14E+01

<1.15E-02

<3.33E-02 Xe-131m Ci n/a n/a n/a n/a Xe-133 Ci

<1.39E+01 1.16E+00 1.19E-01 5.98E-01 Xe-1 33m Ci

<3.93E+01

<4.09E+01

<2.20E-02

<6.37E-02 Xe-135 Ci

<5.36E+00

<5.58E+00 8.21 E-05 1.70E-03 Xe-1 38 Ci

<4.32E+02

<4.49E+02

<2.42E-01

<6.99E-01 Total Ci 0.OOE+00 1.16E+00 2.63E-01 1.01E+00

2. Halogens (Gaseous) 1-131 Ci

<2.55E-04

<2.66E-04

<1.43E-07

<4.13E-07 1-133 Ci

<2.55E-02

<2.66E-02

<1.43E-05

<4.13E-05 Total Ci O.0OE+00 O.OOE+O0 0.00E+00 O.Q0E+00

3. Particulates and Tritium H-3 Ci 8.96E+00 1.58E+01 7.18E-02 1.21 E+00 Mn-54 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Fe-59 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Co-58 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Co-60 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Zn-65 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Mo-99 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Cs-134 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Cs-1 37 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Ce-141 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Ce-144 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Sr-89 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Sr-90 Ci

<2.55E-03

<2.66E-03

<1.43E-06

<4.13E-06 Gross Alpha Ci

<2.55E-03 6.38E-08 1.37E-08

<4.13E-06 Total Ci 8.96E+00 1.58E+01 7.18E-02 1.21E+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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 46 of 51 1998 GASEOUS EFFLUENTS (Continued)

NUCLIDES RELEASED Continuous Mode Batch Mode Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 1.Fission and Activation Gases Ar-41 Ci 1.56E+00 n/a 4.97E-01 6.35E-01 Kr-85 Ci n/a n/a n/a 3.37E+00 Kr-85m Ci n/a 3.23E-02 n/a n/a Kr-87 Ci

<2.82E+01

<2.88E+01

<1.14E-01

<7.42E-02 Kr-88 Ci

<2.10E+01

<2.15E+01

<8.48E-02

<5.54E-02 Xe-131 m Ci n/a n/a n/a 6.16E-03 Xe-133 Ci 4.31 E+00 4.85E+00 2.48E+00 1.15E+00 Xe-133m Ci

<4.02E+01

<4.11E+01

<1.62E-01 4.45E-03 Xe-135 Ci

<5.48E+00

<5.61 E+00 2.55E-03

<1.44E-02 Xe-138 Ci

<4.41E+02

<4.51E+02

<1.78E+00

<1.16E+00 Total Ci 5.88E+00 4.88E+00 2.98E+00 5.17E+00

2. Halogens (Gaseous) 1-131 Ci

<2.61 E-04

<2.67E-04

<1.05E-06

<6.87E-07 1-133 Ci

<2.61 E-02

<2.67E0-02

<1.05E-04

<6.87E-05 Total Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

3. Particulates and Tritium H-3 Ci 2.48E+01 1.30E+01 1.06E+01 1.53E+00 Mn-54 Ci

<2.61 E-03

<2.67E-03

<1.05E-05

<6.87E-06 Fe-59 Ci

<2.61 E-03

<2.67E-03

<1.05E-05

<6.87E-06 Co-58 Ci

<2.61E-03

<2.67E-03

<1.05E-05

<6.87E-06 Co-60 Ci

<2.61 E-03

<2.67E-03

<1.05E-05

<6.87E-06 Zn-65 Ci

<2.61 E-03

<2.67E-03

<1.05E-05

<6.87E-06 Mo-99 Ci

<2.61 E-03

<2.67E-03

<1.05E-05

<6.87E-06 Cs-134 Ci

<2.61E-03

<2.67E-03

<1.05E-05

<6.87E-06 Cs-1 37 Ci

<2.61E-03

<2.67E-03

<1.05E-05

<6.87E-06 Ce-141 Ci

<2.61E-03

<2.67E-03

<1.05E-05

<6.87E-06 Ce-144 Ci

<2.61 E-03

<2.67E-03

<1.05E-05

<6.87E-06 Sr-89 Ci

<2.61 E-03

<2.67E-03

<1.05E-05

<6.87E-06 Sr-90 Ci

<2.61 E-03

<2.67E-03

<1.05E-05

<6.87E-06 Gross Alpha Ci 1.11E-08 1.28E-08

<1.05E-05

<6.87E-06 Total Ci 2.48E+01 1-30E+01 1.06E+01 1.53E+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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 47 of 51 1998 GASEOUS CUMULATIVE DOSE

SUMMARY

Table I QUARTER 1 OF 1998 ODCM CALCULATED ODCM1 LIMIT

% OF LIMIT DOSE TOTAL DOSE (mRem) FOR BONE 0.OOE+00 7.50E+00 O.OOE+00 TOTAL DOSE (mRem) FOR LIVER 6.37E-03 7.50E+00 8.50E-02 TOTAL DOSE (mRem) FOR TOTAL BODY 6.37E-03 7.50E+00 8.50E-02 TOTAL DOSE (mRem) FOR THYROID 6.37E-03 7.50E+00 8.50E-02 TOTAL DOSE (mRem) FOR KIDNEY 6.37E-03 7.50E+00 8.50E-02 TOTAL DOSE (mRem) FOR LUNG 6.37E-03 7.50E+00 8.50E-02 TOTAL DOSE (mRem) FOR GI-LLI 6.37E-03 7.50E+00 8.50E-02 QUARTER 2 OF 1998 TOTAL DOSE (mRem) FOR BONE O.OOE+00 7.50E+00 O.OOE+00 TOTAL DOSE (mRem) FOR LIVER 1.20E-02 7.50E+00 1.60E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 1.20E-02 7.50E+00 1.60E-01 TOTAL DOSE (mRem) FOR THYROID 1.20E-02 7.50E+00 1.60E-01 TOTAL DOSE (mRem) FOR KIDNEY 1.20E-02 7.50E+00 1.60E-01 TOTAL DOSE (mRem) FOR LUNG 1.20E-02 7.50E+00 1.60E-01 TOTAL DOSE (mRem) FOR GI-LLI 1.20E-02 7.50E+00 1.60E-01 QUARTER 3 OF 1998 TOTAL DOSE (mRem) FOR BONE 0.OOE+00 7.50E+00 0.OOE+00 TOTAL DOSE (mRem) FOR LIVER 2.50E-02 7.50E+00 3.34E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 2.50E-02 7.50E+00 3.34E-01 TOTAL DOSE (mRem) FOR THYROID 2.50E-02 7.50E+00 3.34E-01 TOTAL DOSE (mRem) FOR KIDNEY 2.50E-02 7.50E+00 3.34E-01 TOTAL DOSE (mRem) FOR LUNG 2.50E-02 7.50E+00 3.34E-01 TOTAL DOSE (mRem) FOR GI-LLI 2.50E-02 7.50E+00 3.34E-01 QUARTER 4 OF 1998 TOTAL DOSE (mRem) FOR BONE 0.OOE+00 7.50E+00 O.OOE+00 TOTAL DOSE (mRem) FOR LIVER 1.02E-02 7.50E+00 1.36E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 1.02E-02 7.50E+00 1.36E-O1 TOTAL DOSE (mRem) FOR THYROID 1.02E-02 7.50E+00 1.36E-01 TOTAL DOSE (mRem) FOR KIDNEY 1.02E-02 7.50E+00 1.36E-01 TOTAL DOSE (mRem) FOR LUNG 1.02E-02 7.50E+00 1.36E-01 TOTAL DOSE (mRem) FOR GI-LLI 1.02E-02 7.50E+00 1.36E-01 TOTALS FOR 1998 TOTAL DOSE (mRem) FOR BONE 0.OOE+00 1.50E+01 0.00E+00 TOTAL DOSE (mRem) FOR LIVER 5.36E-02 1.50E+01 3.57E-01 TOTAL DOSE (mRem) FOR TOTAL BODY 5.36E-02 1.50E+01 3.57E-01 TOTAL DOSE (mRem) FOR THYROID 5.36E-02 1.50E+01 3.57E-01 TOTAL DOSE (mRem) FOR KIDNEY 5.36E-02 1.50E+01 3.57E-01 TOTAL DOSE (mRem) FOR LUNG 5.36E-02 1.50E+01 3.57E-01 TOTAL DOSE (mRem) FOR GI-LLI 5.36E-02 1.50E+01 3.57E-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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 48 of 51 1998 GASEOUS CUMULATIVE DOSE

SUMMARY

TABLE 2 Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A.

Fission and Activation Gases

1.

Total Release - (Ci) 2.63E-01 2.17E+00 8.86E+00 1.OOE+01 2.13E+01

2.

Total Gamma Airdose (mRad) 9.65E-05 3.09E-04 1.50E-03 5.53E-04 2.46E-03

3.

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

4.

Percent of Gamma Airdose Limit 1.93E-03 6.17E-03 3.01 E-02 1.11E-02 2.46E-02

5.

Total Beta Airdose (mRad) 4.17E-05 2.22E-04 9.70E-04 1.01 E-03 2.24E-03

6.

Beta Airdose Limit (mRad) 1.00E+01 1.OOE+01 1.OOE+01 1.OOE+01 2.OOE+01

7.

Percent of Beta Airdose 4.17E-04 2.22E-03 9.70E-03 1.01 E-02 1.12E-02 Limit (mRad)

B.

Particulates

1.

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

2.

Maximum Organ Dose (mRem)

O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+O0

3.

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

4.

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

Tritium

1.

Total Release (Ci) 9.03E+00 1.70E+01 3.54E+01 1.45E+01 7.59E+01

2.

Maximum Organ Dose (mRem) 6.38E-03 1.21 E-02 2.49E-02 1.03E-02 5.37E-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 8.51 E-02 1.62E-01 3.32E-01 1.37E-01 3.58E-01 D.

Iodine

1.

Total 1-131, 1-133 (Ci)

O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+O0 0.OOE+00

2.

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

3.

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

4.

Percent of Limit 0.O0E+00 Q.OOE+00 O.OOE+00 0.O0E+00 O.OOE+O0 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.

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 49 of 51 1998 Effluent Concentration Limits Nuclides H-3 Cr-51 Mn-54 Fe-55 Co-57 Co-58 Co-60 Zr-95 Nb-95 Sn-113 Sn-117m Sb-124 Sb-1 25 1-131 Cs-1 34 Cs-137 Kr-85 Xe-131M Xe-i 33 Xe-1i33M Xe-1 35 Curies 8.24E+02 3.44E-05 2.30E-03 1.37E-02 2.96E-04 1.96E-02 1.52E-02 1.48E-04 6.84E-04 4.99E-05 1.37E-05 1.71 E-04 1.28E-02 1.1 7E-04 5.98E-04 9.70E-04 1.31 E-02 1.80E-03 1.22E-01 3.37E-04 1.25E-05 Average Diluted Concentration (uCilml) 1.30E-05 5.43E-1 3 3.63E-1 1 2.16E-10 4.67E-12 3.09E-10 2.40E-1 0 2.33E-1 2 1.08E-1 1 7.87E-13 2.16E-13 2.70E-1 2 2.02E-1 0 1.85E-12 9.43E-12 1.53E-11 2.07E-10 2.84E-1 1 1.92E-09 5.32E-12 1.97E-1 3 10CFR 20 ECL 1.OOE-03 5.OOE-04 3.OOE-05 1.OOE-04 6.OOE-05 2.OOE-05 3.OOE-06 2.OOE-05 3.OOE-05 3.OOE-05 3.OOE-05 7.00E-06 3.O0E-05 1.OOE-06 9.OOE-07 1.OOE-06 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04 2.OOE-04

% of ECL 1.30E+00 1.09E-07 1.21 E-04 2.16E-04 7.78E-06 1.55E-03 7.99E-03 1.17E-05 3.60E-05 2.62E-06 7.20E-07 3.85E-05 6.73E-04 1.85E-04 1.05E-03 1.53E-03 1.03E-04 1.42E-05 9.62E-04 2.66E-06 9.86E-08

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 50 of 51 2000 Annual Report SECTION I REPORT OF 2000 RADIOACTIVE EFFLUENTS: LIQUID Unit Quarter 1 Quarter 2 A.

Fission and Activation Products

1.

Total Release (not including tritium, gases, Ci 4.16E-03 1.66E-02 alpha)

2.

Average Diluted Concentration During Period jlCi/ml 3.49E-10 5.45E-10

3.

Percent of Applicable Limit (1) 8.33E-02 3.33E-01 B.

Tritium

1.

Total Release Ci 1.19E+02 7.44E+02

2.

Average Diluted Concentration During Period p.Ci/ml 9.98E-06 2.44E-05

3.

Percent of Applicable Limit (MPC) 9.98E-01 2.44E+00 (ECL)

(2)

C.

Dissolved and Entrained Gases

1.

Total Release Ci 1.32E-03 1.47E-01

2.

Average Diluted Concentration During Period t1Ci/ml 1.101E-10 4.81 E-09

3.

Percent of Applicable Limit (3) 5.54E-05 2.41 E-03 D.

Gross Alpha Radioactivity

1.

Total Release Ci 2.06E-04 5.55E-05 E.

Volume of Waste Released (prior to dilution)

Liters 4.50E+07 5.35E+07 F.

Volume of dilution water used Liters 1.19E+10 3.05E+10 NOTES:

1 )

The applicable limit for the Wolf Creek Generating Station 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 printed here 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)

(MPC or ECL, Appendix B, Table 21 OCFR20)

3)

This value is derived by the following formula:

% of (Average Diluted Concentration) (100)

(2E - 4 from ODCM Section 2.1)

Attachment I to the Wolf Creek Generating Station Annual Radioactive Effluent Release Report 25 Page 51 of 51 2000 GASEOUS EFFLUENTS NUCLIDES RELEASED 1 Fission and Activation Gases Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-1 31 m Xe-1 33 Xe-1 33m Xe-135 Xe-1 38 Total

2. Halogens (Gaseous) 1-131 1-133 Total

3. Particulates and Tritium H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-1 34 Cs-1 37 Ce-141 Ce-144 Sr-89 Sr-90 Gross Alpha Co-57 Total Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Continuous Mode Quarter 1 n/a n/a n/a

<4.24E+01

<5.09E+01 n/a

<3.49E+01

<9.97E+01 8.61 E-02

<1.12E+03 8.61 E-02

<2.58E-04

<2.58E-02 O.OOE+00 1.37E+01

<2.58E-03

<2.58E-03 n/a 1.37E+01 Quarter 2 n/a n/a n/a

<4.22E+01

<5.07E+01 n/a 1.42E+00

<9.93E+01

<1.23E+01

<1.12E+03 1.42E+00

<2.57E-04

<2.57E-02 O.OOE+O0 1.32E+01

<2.57E-03

<2.57E-03 n/a 1.32E+01 9

Quarter 1 Quarter 2 4.17E-01 2.31 E+00 n/a

<8.52E-02

<1.02E-01 n/a 9.70E-02

<2.01E-01 1.66E-04

<2.25E+00 2.82E+00

<5.20E-07

<5.20E-05 O.OOE+00 1.52E+00

<5.20E-06

<5.20E-06 n/a 1.52E+00 2.55E-01 1.03E+00 n/a

<3.98E-02

<4.78E-02 n/a 9.OOE-02

<9.37E-02 3.74E-04

<1.05E+00 1.38E+00

<2.43E-07

<2.43E-05 0.OOE+00 4.04E-01

<2.43E-06

<2.43E-06 n/a 4.04E-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.

WO 02-0019, Annual Radioactive Effluent Release Report - Report 25

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