ML20034E164

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Semiannual Radioactive Effluent Release Rept for Jul-Dec 1992
ML20034E164
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/31/1992
From: Hagan R, Maynard O, Michel D
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NA-93-0041, NA-93-41, NUDOCS 9302250214
Download: ML20034E164 (37)
v • d • e


Text

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J LFCREEK WO'NUCLEAROPERATING CO Robert C. Hagar, Vce Presde nt Nuclear Assurance February 19, 1993 NA 93-0041 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station F1-137 Washington, D. C. 20555

Subject:

Docket No.

50-482:

Semiannual Radioactive Effluent Release Report Gentlemen:

Enclosed is the Wolf Creek Generating Station (WCGS) Radioactive Effluent Release Report covering the period from July 1, 1992 to December 31, 1992.

This report is submitted pursuant to section 6.9.1.7 of the

VCGS, Unit No. 1. Technical Specifications.

Very truly yours,

',(

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/,M tut.

W Robert C. Hagan Vice President Nuclear Assurance RCH/jan Enclosure cc:

J. L. Milhoan (NRC), v/a G. A. Pick (NRC), v/a W. D. Reckley (NRC), v/a T. F. Stetka (NRC), w/a

/302250214 921231 gDR ADOCK 05000482 PDR P.O. Box 411/ Budington KS 66839 / Phone. (316) 3644B31 e

Enclosure to NA 93-0041 Page 1 of 37 6

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4 WOLF CREEK NUCLEAR OPERATING CORPORATION i

Wolf Creek Generating Station i

l' Docket No: 50-482 Facility Operating License No NPF-42 5

SDfIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Report No:

16 Reporting Period: July 1, 1992 through December 31, 1992 Prepared by: Daniel C. Michel Steven A. Henry Jennif er B. Yunk Approved by: [ai r, n (Sc.

Af ri fr>A

  • f erre Vi,c[ePresidentPlantOperations-j Otto L. Maynard

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- Enclosure to NA 0041

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.Page 2 of 371 l

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Table of Contents t

Pace

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Section I 4

I Liquid Radioactive Effluents 4

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' Dose Summary 6

. Airborne. Radioactive Effluents 8

Dose Summary-10 l

I Section II 12 Offsite Dose Calculation Manual Limits

- 1'2.

f C

Maximum Permissible Concentrations 13 Measurements and Approximations of Total Radioactivity

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Batch Releases 16 Continuous Releases 16

'l Solid Waste Shipments 17-l Irradiated.uel Shipments 19 1

Section III

-q Meteorological Data 20 i

Section IV.

27.

1 Unplanned or Abnormal Releases 27_-

j offsite Dose Calculation Manual

.27

.l Major Changes to Liquid, Gaseous or Solid Radwaste Systems 27

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Land Use Census

.27

~j Radioactive Shipments

.27:

1 Inoperability of Airborne Effluent Monitoring Instrumentation.

27

'l Storage Tanks 27

-)

Full and Low Pressure-RCS Gas Samples 27

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-Attachment 1

if Liquid effluent changes to report.No. 15-

'2 8' l

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Enclosure to NA 93-0041 Page 3 of 37 EXECUTIVE SIM4ARY 5

The purpose of the Semiannual Radioactive Effluent Release Report is to report on the quantities of liquid and gaseous effluents and solid waste released from Wolf Creek Generating Station (WCGS).

This report covers the period beginning on July 1, 1992, and ending on December 31, 1992.

Section I provides a summary of the quantities of radioactive liquid _and gaseous effluents for this reporting period.

The format is similar to that recommended in Regulatory Guide 1.21 Revision 1.

An elevated. release pathway does not exist at WCGS, therefore, all airborne releases are considered to be ground level releases.

The concurrent meteorological condition gaseous pathway dose deteomination is met by the WCGS Offsite Dose

{

Calculation Manual methodology of assigning all gaseous pathways to a hypothetical individual residing at the highest annual X/Q and D/Q location.

This results in a conservative estimate of dose to a member of the public rather than determining each pathway dose for each release j

condition.

A conservative error of thirty percent has been estimated in effluent data.

Sections II, III and IV provide additional information required by Regulatory Guide 1.21. Revision 1 and ODCM 7.2.

' provides actual values to replace the estimated values for airborne and liquid effluents provided in Semiannual Radioactive Effluent i

Release Report No.

15.

Analysis results for the Second Quarter of Report No. 15 were not completed prior to submission of the report. Actual results-of the Second Quarter airborne effluent monthly filter composites indicated the presence of Sr-90 in the Radwaste vent.

The change increases the total particulate curies released, and increases the cumulative d o s e.~

Actual' f

results of the Second Quarter liquid effluents indicated the presence of Fe-j 55 in the liquid batch composite.

The change increases the total curies

released, and increases the cumulative dose.

Because analysis results for the Fourth Quarter of 1992 have not yet been completed, Fe-55, Sr-89 and Sr-90 activities and doses in the airborne and liquid effluents are presented l

as an estimate.

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I SECTION I REPORT OF RADI0 ACTIVE EFFLUENTS (1992): LIQUID Unit Quarter Quarter.

3-4 l

A.

Fission and Activation Products

~

1.

Total Release (not including tritium, gases, alpha)

Ci 8.51E-02 4.07E-021(4)

L 2.

Average Diluted Concentration During Period uCi/ml 2.05E-08 1.23E-08 l

3.

Percent of Applicab3e Limit (1) 1.70E400 B.14E-01 l

B.

Tritium i

1.

Total Release Ci 1.50E+02 1.70E+02~

2.

Average Diluted Concentration During Period uCi/ml 3.62E-05 5.13E-05 3.

Percent of Applicable Limit (2) 1.21E+00 1.71E+00 l

l C.

Dissolved and Entrained Gases l

1.

Total Release C1 1.63E-02 1.37E-01 2.

Average Diluted Concentration During Period uCi/ml 3.93E-09 4.14E 3.

Percent of Applicable Limit (3)

I 1.97E-03 2.70E-02 D.

Gross Alpha Radioactivity 1.

Total Release Ci 3.02E-05 9.89E ;

f E.

Volume of waste released (prior to dilution) liters 8.74E+05 1.38E+08' i

F.

Volume of dilution water used liters 4.15E+09 3.17E+09 L 1.

The applicable limit for the Wolf Creek Generating Station is 5 Curies per year.

j (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 j

the total release Curies by 5 Curies and then multiplying the result by 100.

L 2.

'This value ls derived by the following formula:

I of Applicable Limit = (AveraRe Diluted Concentration) (200}

(10CFR20, Appendix B, Table II, MPC)

-3.--

This value is derived by the following formulas.

I of Applicable Limit -

(Averane Diluted Concentration) (100) l (2E-4 from ODCM Section 2.1) l l

4.

Curies in Quarter 4 are based on the October composite Fe-55 value, and the 3rd Quarter.

-composite Sr-89 and SR-90 values.

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' Enclosure to NA 93-0041

.Page'.5 of 37 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCL1 DES Quarter Quarter Quarter Quarter RELEASED Unit 3

4 3

4 i

H-3 C1 1.40E-05 9.75E-03 1.50E402 1.70E+02 Cr-51 Ci 0.00E+0D 0.00E+00 0.00E400

_9.07E-05 1

Mn-54 C1 1.04E-07

<6.85E-02 7.35E-04 8.10E-04 Fe-55 Ci

<4.92E-06

<1.37E-01.

3.47E-02 1.21E-02(1)

Fe-59 Ci

<2.46E-06

<6.85E-02

<4.35E-04

<3.79E-04 Co-57 Ci 0.00E+00 0.00E+00 3.73E-04 9.44E-05 Co-58 Ci 3.56E-07

<6.85E-02 1.47E-02 1.34E Co-60 Ci 1.19E-06

<6.85E-02 1.79E-02 1.53E-02 Zn-65 Ci

<2.46E-06

<6.85E-02

<4.35E-04

<3.79E-04 Sr-89 Ci

<2.46E-07

<6.85E-03 1.65E-03 1.44E-03(1).

Sr-90 Ci

<2.46E-07

<6.85E-03 4.61E-05

<4~01E-05(1)

Nb-95 C1 1.17E-07 0.00E+00 2.55E-04 0.00E+00 Mo-99 Ci (2.46E-06

<6.85E-02

<4.35'-04

<3.79E-04 3

3 Tc-99m Ci 0.00E+00 0.00E+00 1.06E-04 0.00E+00 Ag-110M Ci 0.00E+00 0.00E+00 1.76E-04 2.06E-04 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 7.27E-06 Sb-124 Ci 0.00E+00 0.00E+00 2.98E-05 0.00E400 l

Sb-125 Ci 3.50E-07 0.00E+00 1.01E-02 7.09E-03 I-131 Ci

<4.92E-06

<1.37E-01

<8.69E-04 1.69E-04' Cs-134-Ci 3.23E-07

<6.85E-02 1.61E-03 6.82E-04 Cs-137.

Ci 3.12E-07

<6.85E-02 1.65E-03 6.70E-04 La-140 Ci 0.00E+00 0.00E+00 1.79E-04 0.00E+00

[

Ce-143 Ci

<2.46E-06

<6.85E-02

<4.35E-04

<3.79E-04 l

Ce-144 Ci 1.40E-07

<6.85E-02 9.09E-04 6.89E-04 5

Gross Alpha Ci

<4.92E-07

<1.37E-02 3.02E-05 9.89E-06 Ar-41 Ci

<4.92E-05

<1.37E+00

<8.69E-03

<7.57E-03 i

Kr-85 Ci

<4.92E-05

<1.37E+00

<8.69E-03 1.21E-01 Kr-85m Ci

<4.92E-05

<1.37E+00

<8.69E-03

<7.57E-03 Kr-87 Ci

<4.92E-05

<1.37EiOO

<8.69E-03

<7.57E-03 i

Kr-88 Ci

<4.92E-05

<1.37E+00

<8.69E-03

<7.57E-03 1

'l Xe-131m Ci

<4.92E-05

<1.37E+00

<8.69E-03 1.92E-03

)

Xe-133 Ci

<4.92E-05

<1.37E+00 1.62E-02 1.41E-02 Xe-133m Ci

<4.92E-05

<1.37E+00

<8.69E-03 4.42E-05 Xe-135 Ci

<4.92E-05

<1.37E+00 5.81E-05 7.34E-05 Xe-135m Ci

<4.92E-05

<1.37E+00

<8.69E-03

<7.57E-03 NOTE:

Less than values are calculated using the lower limit of detection (LLD) l values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter.

(1)

The Fe-55 value for the 4th Quarter is based on the October monthly composite value.

The Sr-89 and Sr-90 values for Quarter 4 are based on the Quarter 3 composite values.

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~ Enclosure.to NA 93-0041 Prg2.6 6F 37

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LIQUID CUMULATIVE DOSE SIDEARY (1992) 1ABLE 1 ODCM CALCULATED ODCM I UF DOSE LIMIT

' LIMIT

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i QUARTER 1 OF 1992 TOTAL DOSE (mrem) FOR BCNE 3.22E-02 5.00E+00 6.44E-01 F

TOTAL DOSE (mrem) FOR LIVER 7.46E-02 5.00E+00 1.49E+00 TOTAL DOSE (mrem) FOR TOTAL BODY 6.01E-02 1.53E+00 4.01E+00 TOTAL DOSE (mrem) FOR THYROID 1.68E-02 5.00E+00-3.36E-01 TOTAL DOSE (mrem) FOR KIDNEY 3.5BE-02 5.00E+00 7.16E-01 TOTAL DOSE (mrem) FOR LUNG 2.33E-02 5.00E400 4.66E-01 TOTAL DOSE (mrem) FOR GI-LLI 5.03E-02 5.00E+00 1.01E400 QUARTER 2 0F 1992 TOTAL DOSE (mrem) FOR BONE 3.91E-03 5.00E+00 7.82E-02 TOTAL DOSE (mrem) FOR LIVER 1.83E-02 5.00E+00 3.66E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 1.66E-02 1.50E+00 1.11E+00 TOTAL DOSE (mrem) FOR THYROID 1.16E-02 5.00E+00 2.32E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.38E-02

5. 00E4 00 2.76E-01 TOTAL DOSE (mrem) FOR LUNG 1.24E-02 5.00E+00 2.48E-01 TOTAL DOSE (mrem) FOR GI-LLI 1.34E-02 5.00E+00 2.68E-01 QUARTER 3 0F 1992

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TOTAL DOSE (mrem) FOR B 1.06E-02 5.00E+00 2.12E-01 TOTAL DOSE (mrem) FOR L. /ER 2.76E-02 5,00E+00 5.52E-01' TOTAL DOSE (mrem) FOR TOTAL BODY 2.35E-02

1. 50E4 00 1.57E+00 f

TOTAL DOSE (mrem) FOR THYROID 1.06E-02 5.00E+00 2.12E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.62E-02 5.00E+00 3.24E-01 TOTAL DOSE (mrem) FOR LUNG 1.26E-02 5.00E+00 2.52E-01 TOTAL DOSE (mrem) FOR GI-LLI 1.63E-02 5.00E+00 3.26E-01 QUARTER 4 of 1992 TOTAL DOSE (mrem) FOR BONE 5.64E-03 5.00E+00 1.13E-01 TOTAL DOSE (mrem) FOR LIVER 2.44E-02 5.00EA90 4.88E-01 TOTAL DOSE (mrem) FOR TOTAL EODY 2.25E-02 5.00E400 1.50E+00 TOTAL DOSE (mrem) FOR THYROID 1.65E-02 5.00E+00 3.30E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.88E-02 5.00E+00 3.76E TOTAL DOSE (mrem) FOR LUNG 1.70E-02 5.00E+00 3.40E-01 TOTAL DOSE (mrem) FOR GI-LLI 1.82E-02 5.00E+00 3.64E-01 TOTALS /OR 1992 TOTAL DOSE (mrem) FOR BONE 5.24E-02 1.00E+01 5.24E TOTAL DOSE (mrem) FOR LIVER 1.45E-01 1.00E+01 1.45E+00 TOTAL DOSE (mrem) FOR TOTAL BODY 1.23E-01 3.00E+00 4.10E+00 TOTAL DOSE (mrem) FOR THYROID 5.55E-02 1.00E+01 5.55E-01 TOTAL DOSE (mrem) FOR KIDNEY 8.46E-02 1.00E+01

'8.46E-01 TOTAL DOSE (mrem) FOR LUNG -

6.53E-02 1.00E+01 6.53E-01 TOTAL DOSE (mrem) FOR GI-LLI 9.82E-02 1.00E+01 9.82E-01 NOTES:

1 Based on ODOM 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 to any organ is less.than or equal to 5 mrem per quarter and 10 mrem per year.

2 The values for Quarter 2 of 1992 given above differ from the values reported in Semiannual Radioactive Effluent Release Report No. 15 due to adjustment for Fe-55, Sr-89, and Sr-90. composite data.

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3 The Calculated Doses for the Fourth Guarter of 1992 given above are based on the October Fe-55 composite result, and the Third Quarter Sr-89 and Sr-90 composite results.

Enclosure.to NA 93-0041 j

Page.7 69 37 LIQUID CUMULATIVE DOSE SIDEARY (1992)

TABLE 2 A.

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

Total Release - (C1) 1.19E-01 3.23E-02 8.51E-02 4.07E-02 2.77E-01 2.

Maximum Organ Dose (mrem) 5.78E-02 6.70E-03 1.69E-02 8.30E-02 8.98E-02 3.

Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

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4.

'ercent of Limit 1.16E+00 1.34E-C1 3.3BE-01 1.66E-01 8.98E-01 B.

Tritium 1.

Total Release (Ci) 1.01E+02 3.01E+01 1.50E+02 1.70E+02 4.51E+02 2.

Maximum Organ Dose (mrem) 1.68E-02 1.16E-02 1.07E-02 1.61E-02 5.52E-02 3.

Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00.

1.00E+01 4.

Percent of Limit 3.36E-01 2.32E-01 2.14E-01 3.22E-01 5.52E-01 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 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.

NOTE:

The Fourth Quarter Category A values were calculated based on the October Fe-55 composite result, and the Third Quarter Sr-89 and Sr-90 composite results. Also, the Second Quarter Category A values given above differ from the values reported in Semiannual Radioactive Effluent Release Report No. 15 due to adjustment for Fe-55, Sr-89, and Sr-90 composite data.

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Enclosure to NA 93-0041 i

P.tge 8 of 37 REPORT OF RADIOACTIVE EFFLUENTS (1992): AIRBORNE' Quarter.

Quarter Unit 3

4 A.

Fission and Activation Gases i

1.

Total Release Ci 2.35E+01' 4.93E+01 j

2.

Average Release Rate for Period uC1/sec 3.10E+02 3.99E+01 3.

Percent of ODCM Limit (1)

I 2.74E-02 4.70E-02 i

B.

Iodines 1.

Total lodine-131 Ci 0.00E+00 1.67E-05 2.

Average Release Rate for Period uCi/sec 0.00E+00 2.11E-06 3.

Percent of Applicable Limit (2)

I 0.00E+00 1.67E-03 C.

Particulates 1.

Particulates with Half-lives > 8 days Ci 9.25E-07

0. 00E+ 00 '

2.

Aversg+ Release Rate for Period uCi/sec 1.16E-07 0.00E+00 3.

Percent of ODCM Limit (3)

I 5.44E-03 0.00E+00 4.

Gross Alpha Radioactivity Ci 0.00E+00 0.00E+00 D.

Tritium

-1.

Total Release Ci 6.01E+00 3.47E+00 2.

Average Release Rate for Period uCi/sec 2.55E+00 9.00E-01 3.

Percent of ODCM Limit (4)

,Z 5.67E-02 3.27E-02 1.

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

I of ODCM Limit = (Otrly Total Beta Airdose)(100) or (Otrly Total Gamma Airdose)(100) 10 mrad 5 mrad The largest value calculated between Gamma and Beta airdose is listed as the 2 of ODCM Limit.

2..

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

I 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:

I of ODCM Limit - (Eichest Orcan Dose Due to Particulates)(100) 7.5 mrem 4.

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

I of ODCM Limit = (Hinhast Ornan 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.

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Enclosure to NA 93-0041 Page 9 of 37 GASEOUS EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3

4 3

4 1.

Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 8.95E-02 1.10E-01 Kr-85 Ci 0.00E+00 0.00E+00 1.12E+01 3.33E-01 Kr-85M Ci 0.00E+00 1.50E-01 0.00E+00 4.44E-05 Kr-87 Ci

<4.51E+01

<4.53E+01

<1.43E-02

<1.75E-02 Kr-88 Ci

<3.39E+01 5.46E-01

<1.07E-02

<1.31E-02 Xe-131M Ci 0.00E+00 0.00E+00 1.96E-03 8.78E-02 Xe-133 Ci 8.61E+00 4.01E+01 4.23E-01 3.16E+00 i

Xe-133M Ci

<5.06E+01 1.70E-01 6.42E-04 1.62E-02 Xe-135 Ci 3.12E+00 4.58E+00 4.12E-03 7.48E-03 Xe-138 Ci

<9.47E+01

<9.51E+r'

<3.00E-02

<3.66E-02 Total Ci 1.17E+01 4.55E+.

1.17E+01 3.71E+00 2.

Halogens (Gaseous) i 1-131 Ci

<2.61E-04 1.67E-05

<8.26E-08

<1.01E-07 I-133 Ci

<2.61E-02

<2.62E-02

<8.26E-06

<1.01E-05 Total Ci 0.00E+00 1.67E-05 0.00E+00

<0.00E+00 3.

Particulates and Tritium i

H-3 Ci 5.85E+00 3.42E+00 1.60E-01 5.11E-02 Mn-54 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Fe-59 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Co-58 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Co-60 C1 4.88E-07

<2.62E-03

<8.26E-07

<1.01E-06 2n-65 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Mo-99 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Cs-134 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Cs-137 Ci

<2.61E-03

<2.62E-03

<B.26E-07

<1.01E-06 Cc-141 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Ce-144 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Sr-89 Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Sr-90 Ci 4.37E-07

<2.62E-03

<8.26E-07

<1.01E-06 Gross Alpha Ci

<2.61E-03

<2.62E-03

<8.26E-07

<1.01E-06 Total Ci 5.85E+00 3.42E+00 1.60E 5.11E-02 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.

The less than i

values are not included in the summation for the total release values.

-Enc 40sute to NA 93-0041 Vege 10 of 37 CASEOUS CUMULATIVE DOSE

SUMMARY

(1992) l Table 1 j

3DCM CALCULATED ODQd I 0F QUARTER 1 0F 1992 DOSE LIMIT LIMIT TOTAL DOSE (mrem) FOR BONE 0.00E+00 7.50E+00 0.00E+00 TOTAL DOSE (mrem) FOR LIVER 2.66E-03 7.50E+00 3.55E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 2.66E-03 7.50E400 3.55E-02 TOTAL DOSE (mrem) FOR THYROID 2.66E-03 7.50E+00 3.53E-02 TOTAL DOSE (mrem) FOR KIDNEY 2.66E-03 7.50E+00 3.55E-02 TOTAL DOSE (mrem) FOR LUNG 2.66E-03 7.50E+00 3.55E-02 TOTAL DOSE (mrem) FOR GI-LLI 2.66E-03 7.50E400 3.55E-02 QUARTER 2 0F 1992 TOTAL DOSE (mrem) FOR BONE 7.84E-05 7.50E+00 1.05E-03 TOTAL DOSE (mrem) FOR LIVER 2.99E-03 7.50E+00 3.99E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 2.97E-03 7.50E+00 3.96E-02 TOTAL DOSE (mrem) FOR THYROID 2.95E-03 7.50E+00 3.93E-02 TOTAL DOSE (mrem) FOR KIDNEY 2.96E-03 7.50E+00 3.95E-02 TOTAL DOSE (mrem) FOR LUNG 2.96E-03 7.50E+00 3.95E-02 TOTAL DOSE (mrem) FOR GI-LLI 2.95E-03 7.50E+00 3.93E-02 QUARTER 3 OF 1992 TOTAL DOSE (mrem) FOR BONE 4.08E-04 7.50E+00 5.44E-03 TOTAL DOSE (mrem) FOR LIVER 4.26E-03 7.50E+00 5.68E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 4.36E-03 7.50E+00 5.81E-02 TOTAL DOSE (mrem) FOR THYROID 4.26E-03 7.50E+00 5.68E-02 TOTAL DOSE (mrem) FOR KIDNEY 4.26E-03 7.50E+00 5.68E-02 TOTAL DOSE (mrem) FOR. LUNG 4.26E-03 7.50E+00 5.68E-02 TOTAL DOSE (mrem) FOR GI-LLI 4.26E-03 7.50E+00 5.6BE-02 QUARTER 4 0F 1992 TOTAL DOSE (mrem) FOR BONE 2.91E-05 7.50E400 3.BBE-04 TOTAL DOSE (mrem) FOR LIVER 2.48E-03 7.50E+00 3.31E TOTAL DOSE (mrem) FOR TOTAL BODY 2.47E-03 7.50E+00 3.29E-02 TOTAL DOSE (mrem) FOR THYROID 1.21E-03 7.50E+00 1.61E-01 TOTAL DOSE (mrem) FOR KIDNEY 2.50E-03 7.50E+00

-3.33E-02 TOTAL DOSE (mrem) FOR LUNG 2.45E-03 7.50E+00 3.27E-02 TOTAL DOSE (mrem) FOR GI-LLI 2.45E-03 7.50E+00 3.27E-02 TOTALS FOR 1992 TOTAL DOSE (mrem) FOR BONE 5.16E-04 1.50E+01 3.44E-03 TOTAL DOSE (mrem) FOR IIVER 1.24E-02 1.50E+01 8.27E-02 i

TOTAL DOSE (mrem) FOR TOTAL BODY 1.25E-02 1.50E+01 8.33E-02 TOTAL DOSE (mrem) FOR THYROID 2.20E-02 1.50E+01 1.47E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.24E-02 1.50E401 8.27E-02 TOTAL DOSE (mrem) FOR LUNG 1.23E-02 1.50E+01 8.20E-02 TOTAL DOSE (mrem) FOR GI-LLI 1.23E-02 1.50E+01 8.20E-02 NOTES:

1.

Based on Volf Creek ODCM Section 3.2.2 which restricts dose during any calender quarter to less than or equal to 7.5 mrem to any organ and during any calender year to less than or equal to 15 mrem to any organ.

I 2.

Values for the Second Quarter of 1992 given above differ from the values reported in Semiannual Radioactive Effluent Release Report No. 15 due to adjustment for Sr-89 and Sr-90 composite data.

)

3.

The calculated Doses for the Fourth Quarter of 1992 given above are based on the October Sr-89 and Sr-90 composite results.

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l Enclosure to NA 93-0041 l Page 11 of 37-i I

GASEOUS CUMULATIVE DOSE SIDEARY (1992)

TABLE 2

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

Pission and Activation Gases 1.

Total Release (C1) 1.77E+02 5.90E401

.2.35E+01 4.93E+01 3.09E+02-2.

Total Gamma Airdose (naad) 5.29E-04 9.97E-04 7.13E-04 2.35E-03 4.59E-03 3.

Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01-i l

4.

Percent of Gamma Airdose Limit 1.06E-02 1.99E-02 1.43E-02 4.70E-02 4.59E-02 5.

Total Beta Airdose (mrad) 2.41E-02 7.00E-03 2.74E-03 4.18E-03 3.80E-02 6.

Beta Airdose Limit (mrad) 1.00E+01 1.00E401 1.00E+01 1.00E401 2.00E+01 l

7.

Percent of Beta Airdose Limit (mrad) 2.41E-01 7.00E-02 2.74E-02 4.18E-02 1.90E-Ol' I

B.

Particulates 1.

Total Particulates (C1) 0.00E+00 4.91E-07 9.25E-07 0.00E+00 1.42E-06 2.

Maximum Organ Dose (mrem) 0.00E+00 7.84E-05 4.08E-04 0.00E+00 4.86E-04 3.

Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 4.

Percent of Limit 0.00E+00 1.05E-03 5.44E-03 0.00E+00 3.24E-03

)

C.

Tritium 1.

Total Release (C1) 3.74E+00 4.13E+00 6.01E+00 3.47E+00 1.74E+01 L

2.

Maximum Organ Dose (mrem) 2.66E-03 2.95E-03 4.25E-03 2.45E-03 1.23E-02 l

3.

Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 4.

Percent of Limit 3.55E-02 3.93E-02 5.67E-02 3.27E-02 8.20E-02 i

D.

Iodine i

1.

Total I-131, I-133 (Ci) 0.00E+00 0.00E+00 0.00E+00 1.67E-05 1.67E-05 2.

Maximum Organ Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 9.61E-03 9.61E-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 0.00E+00 0.00E+00 0.00E+00 1.28E-01 6.41E r 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.

NOTE:

The values for the Second Quarter Category B differ from the values reported in Semiannual Radioactive Effluent Release Report No. 15 due to adjustment for Sr-89 and Sr-90 j

composite data.

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. Enclosure to NA 93-0041 Page 12 of 37 SECTION II i

Supplemental Information Facility: Wolf Creek Generatina Station License Number: NPF-42 1.

ODCM Limits A.

For licuid waste effluents A.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20, Appendix B. Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. Fordissolvedorengrainednoblegases,theconcentration shall be lLnited to 2 x 10 microcurie /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 casenus waste effluents B.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas 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 l

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 followings 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.

. Enclosure to WA-93-0041

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Page'13 of 37.

i4 B.3 The dose 1from Iodine-131, Iodine-133, tritium, and all.

.3 i

' radionuclides in particulate fonn with half-lives greater than 8 j

days in~ gaseous. effluents released to areas 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.

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2.

Maximum Penmissible Concentrations (MPC's)

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. Water - covered in Section 1.A.

' i Air

- covered in Section 1.B.

i 3.

Average energy of fission and activation gaseous effluents'is not applicable.

See ODQ4 section 3.1.2 for the methodology used 'in determining the release rate limits for noble gas releases.

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9 Enclosure to'NA 93-0041

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Page 14 of 37 i

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.i 4.

Measurements and Approximations of Total Radioactivity-l A.

Liquid Effluents

^!

LIQUID RELEASE SAMPLING METHOD OF TYPE OF ACTIVITY f

TYPE FREQUENCY ANALYSIS ANALYSIS i

1. Batch Waste P.H.A.

Principal Gamma Release P

Emmiters i

Tanks Each Batch P.H.A.

I-131 I

l

a. Waste

't Monitor P

Dissolved and i

Tank One Batch /M P.H.A.

Entrained Gases

{

(Gamna Emitters)

b. Secondary l

Liquid P

L.S.

H-3 Waste Each Batch

.j Monitor S.A.C.

Gross Alpha

'i Tank E

F O.S.L.

'Sr-89. Sr-90 Each Batch O.S.L.

Fe-55 l

2. Continous P H.A.

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

I-131'

]

a. Steam M

Dissolved and Generator Grab Sample P.H.A.

Entrained Gases Blowdown (Gamma Emitters) l

.I

b. Turbine Daily L.S.

H-3 Euilding Grab Sample Sump S.A.C.

Gross' Alpha

'j i

c. Lime Daily O.S.L.

Sr-89, Sr-90;

't Sludge Grab Sample Pond

.]

O.S.L.

Fe-55

.I P = prior to each batch S.A.C. = scintillation alpha counter M = monthly 0.S.L. = performed by an offsite' laboratory l

L. S. - liquid scintillation detector P.H.A. = gamma spectrum pulse height analysis using a High Purity _

Germanium detector.

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i Enclosure to NA'93-0041 4

Page 15 of 37 oJ..

.)

B.

Gaseous Waste Effluents

- f SNHPLING METHOD OF TYPE OF GASEOUS, RELEASE TYPE FREQUENCY ANALYSIS ACTIVITY ANALYSIS P.

{

Each Tank __

P.H.A.

Principal Gamma f

Waste Gas Decay Tank Grab Sample Emitters i

P Principal Gamma f

Containment Purge or Each Purge P.H.A.

Emitters Vent Grab Sample Gas Bubbler and L.S.

H-3 (oxide)

Principal Gamma Unit Vent M

P.H.A.

Emitters i

Grab Smmple Gas Bubbler and L.S.

H-3 (oxide) l Radwaste Building M

P.H.A.

Principal Gamma Vent Grab Sample Emitters-t For Unit Vent and I-131 i

Radwaste Building Continuous P.H.A.

i Vent release types I-333 listed above.

P.H.A.

Continuous Particulate Principal Gamma Sample Emitters i

S.A.C.

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

Composite Sr-89, Sr-90 Continuous Particulate

]

Sample P = prior to each batch S.A.C. = scintillation alpha counter l

M = monthly 0.S.L. = performed by an offsite laboratory L. S. = liquid scintillation detector P.H.A. = gamma spectrum pulse height analysis using a High Purity Germanium detector.

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Enclosure to NA 93-0041

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.Page'16 of 37 t

5.

Batch Releases A batch release is the discontinous release of gaseous or liquid effluent which takes place over a finite period of time usually hours l

or days.

There were 37 gaseous batch releases during tie reporting period. The longest gaseous batch release lasted 847. minutes, while the shortest'~

l lasted 74 minutes. The average release lasted 164 minutes with a i

total gaseous batch release time of 6,071 minutes.

There were 35 liquid batch releases during the reporting period.

The longest liquid batch release lasted 156 minutes, while the

'}

shortest lasted 35 minutes.

The average release lasted 105 minutes j

with a total liquid batch release time of 3,673 minutes.

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6.

Continuous Releases I

A continous release is a release of gaseous or liquid effluent which

~

is essentially uninterrupted for extended periods during normal i

operations of the facility.

There were three liquid release pathways' designated as continuous releases during this reporting period. They were the Steam Generator.

}

Blowdown. Turbine Building Sump, and Lime. Sludge Pond. -There were two' gas release pathways designated as continuous releases. 'These vere

l the Unit Vent and Radwaste Building Ven*

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Enclosure.to NA 93-0041 i

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1992)

SOLID WASTE SHIPMENTS A.

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

1. Type of waste Unit 6-Month Est. Total Period Error I
a. Spent resins, filter sludges, m3*

5.90E+00 evaporator bottoms, etc.

Ci 1.37E+02 2.50E+01

b. Dry compressible vaste -

m3*

2.27E+01 contaminated equip. etc.

Ci 1.02E+01 2.50E+01

c. Irradiated components, m3*

0.00E+00 control rods, etc.

Ci 0.00E+00 0.00E+00

d. Other m3*

0.00E+00 Ci 0.00E+00 0.00E+00 m3* - cubic meters

2. Estimate of major nuclide composition (by type of waste)

{

a.

Spent resins, filter sludges, evaporator bottoms, etc.

Nuclide Percent Name Abundance Curies Cs-134 40.918I 5.62E+01 i

Cs-137 37.933I 5.21E+01 Fe-55 6.468%

8.89E+00 Ni-63 6.120I 8.41E+00 Co-60 3.602I 4.95E+00 Be-7 2.991I 4.11E+00 Mn-54 1.019Z 1.40E+00 Co-58

.6667 9.15E-01 C-14

.125I 1.72E-01 Sr-90

.103I 1.42E-01 Ce-144

.029I 4.01E-02 Sb-125

.013I 1.78E-02 H-3

.010Z 1.35E-02 Tc-99

.003%

4.41E-03 Pu-238

.000%

1.81E-04 Cm243/44

.000Z 8.48E-05 Pu239/40

.000I 6.12E-05 Am-241

.000I 2.04E-05 Cm-242

.000Z 0.00E+00 Pu-241

.000%

0.00E+00 1-129

.000%

0.00E+00 Nb-94

.000I 0.00E+00 Ni-59

.000I 0.00E+00 l

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p-h

.93-0041.

Enclosure to NA J. 4.

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'Page 18 of 37 i

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b. Dry compressible waste, contaminated equipment, etc.

Nuclide Percent Name Abundance Curies l

.i Fe-55 60,103I 6.13E+00 Co-60 25.085 2.56E+00 Ni-63 7.558%

7.71E-01 l

Co-58 1.719I 1.75E-01 Nb-95 1.5962 1.63E-01 Cs-137 1.456I 1.49E-01 I

Mn-54 1.436I 1.47E-01 Cs-134 1.0222 1.04E-01 H-3

.021I 2.12E-03 i

C-14

.003I 3.45E-04 Cm-242

.000%

0.00E+00 Pu-241

.000%

0.00E+00 1r I-129

.000I 0.00E+00 Tc-99

.000%

0.00E+00 Sr-90

.000%

0.00E+00 Nb-94

.0001 0.00E+00 Ni-59

.000%

0.00E+00 c.

Irradiated components, control rods, etc.

none d.

Other none'

[

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

Truck

Barnwell, South Carolina 2

Truck Richland, Washington.

1 Truck Beatty, Nevada 7

4. Class of Solid Waste a.

Class A, Class B - corresponding to 2a

[

b.

Class A - corresponding to 2b c.

Not applicable d.

Not applicable

5. Type of Container a.

LSA (Strong, tight) - corresponding to 2a b.

LSA (Strong, tight) - corresponding to 2b c.

Not applicable d.

Not applicable l

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Page'19'of 37.-

6. Solidification Agent a..

Not applicable b.

Not-applicable c.

Not applicable d.

Not applicable B.

IRRADIATED FUEL SHIPMENTS (Disposition)

There vere no irradiated fuel shipments during this reporting period.'

1 Enclosure'to NA 93-0041 Page 20 of 37 i

SECTION III HOURS AT EACH WIND SPEED AND DIRECTION All gaseous releases at the Wolf Creek Generating Station are ground level releases.

The meterological data supplied in these tables covers the period from January 1, 1992 to December 31, 1992, and indicates the number of hours at each wind speed and direction for each stability class.

wCcP5 U ECH ei4D 5FEZD 'ND SIRECTIOrl

- c.

--F. :.P D :

_ rap p i

- ;c7MhER 31 1 *; _

1 2.-

I~

tit: '-.._ u; 5 :

a i_;__ h l._ C a n

-_. _ _. _ -.-._ _ _ _ _ _ _ l u _ :2 e t e t S. _ _ _ - -.. - _ - - - -. -.- - - _ _ -- -

a

.p c e - - FC H.

3 t.

1. a ei 0-24

-... ~ 4 101aL

. a:I 5 l

}

O O

O r;

4

,i f-O O

O i

3 o

O o-l e.

_)

O Q

Q O

t I I I.

0 0

0 0

0 o

o O

O l'

i y

4 O

O o

O O

C~

(

i h

Q C

i)

C 9

7,.,

C h

O h

i

-1 5

Au i

O 3

_ l.Y l'. id L k _

d - ~ - _ ---~ --

~~d

- --~ ~~N 0--~~~~~

U~

-~

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3'

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Enclosure to NA 93-0041-Paga 21 of'37

  1. dCURS AT EACH WIND #EED AND DIRECTION-P E T l O T.

OF RECORD:

J A!4UAFn 1 - DECEMBER 31 1992 c

~.,.IT.

. Lrsd:

a aire 2L v

ELEisIICU1______._____________1DJeters_____ ___________-_______________

Wind Wind Speed (MPH) at 10M Leve1 l

52 cent

_1:2

_s:Z S12 12:18 12:04

_124 ICIAL N

(+

0 0

7 4

O 11 i

NNE O

O 1

1 O

O 2

[

NE O

O 3

0 0

0 3

ENE O

O O

O O

O O

E O

O O

O O

O O

i E5E 0

1 O

O O

1 ME O

O O

1 O

O 1

1 m

c=E c)

~

u 5

0 0

0 1

2-0 3

55W O

O 3

6 0

0 9

5W O

2 O

O O

O 2

W2w 2

1 O

O O

1-4 W

O O

2 O

O O

2 WidW O

1 2

O O

O

-3 NW O

2 2

O O

O 4

NNW O

O 1

14 4

0 19 2ARisELE___0________Q________0________0________0________0________0____

TOTAL.

2 6

17 32 11 1

69 Feriod of calm (hour s) :

O

' Enclosure lto NA 93-0041 Pags 22 of 37-7:

,i,

+.

HOURS AT EACH WIND' SPEED AND DIRECTION PERIOD OF FECORD:

JANUAR< 1 - DECEMBER 31 1992 51AElt1TV CLASS:

C E L ES A 1 1 C U 1_ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _10 _ td e r e c s _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _._ _ _ _ _ _ _ __ _ _ _ _ _ _

W4.nd Wind Speed (MP4) at 10M Level D2nerl

_1:3

_4:2 2:12 13:18 12:24

_224 ICIAL N

O O

O 5

'3 0

8 NNE O

O 1

2 O

O 3

NE O

O 2

O O

O 2

ENE O

O 1

O O

O

'1 E

O O

1 O

O O

1 E5E O

O O

O O

O O

5 SE O.

O O

2 O

O 2

SSE O

1 3

1 O

O 5

-i i

5 O

O 4

4 O

O 8

SSW O

O 1

2 1

0 4

SW 1

0 2

O O

3 WSW O

O 1

0 1

0 2

W O

O O

1 0

2 3-WNW O

O O

O O

O O

NW O

O O

O O

O

.O-

+

NNW O

1 5

4-5 0

15 UARieDLE___0________0________Q________0______.._0________0________Q____

TOTAL 0

3 19 23 10 2

57 Period of calm (hour s) :

0 I

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Enclosure to NA 93-0041

, -Pega 23 of 37 3.,

-HOURS AT EACH WIND EPEED AND DIRECTION DECEMEER-31 1992 PERIOD 75 RECORD:

JANUARY 1 57AEILITY CLASS:

D ELEkaIIOL:_ __________.__ _ _10_&tecs_________________________________

Wind Wind Epeed (MPH) at 10M Level Direct

_1:2

_d:I 8:12 13:18 12:24

_22e ICIAL N

5 36 103 88 29 7

268 NNE 6

39 80 73 18 4

220 NE 5

53 59 9

0 0

126 ENE 5

31 82 7

0 0

125 E

2 29 63 13 0

0 107 EEE 40 57 17 1

0 116 SE 2

29 75 39 2

0 147 i

SSE 5

62 129 88 9

0 293 3

2 46 133 190 62 2

435 S5W o

30 77 75 16 0

207 SW 3

28 28 10 0

0 69 WSW 4

21 30 15 10 0

80 W

2 29 40 19 6

18 114 WNW 5

17 i:4 50 30 6

142 NW 5

22 o6 92 32 3_

220 NNW 2

46 123 73-35 6

285' i

2AEIABLE___0________0________0________0________Q________0________Q____

TOTAL 52 558 1170 858 250 46 2943 F e r i c. d of calm (hours):

0 1

)

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Enclosure to NA 93-0041 Pego 24 of 37 t

t b

HOURS AT-EACH WIND 5 FEED AND DIRECTION l

t _

PERIOD Gir'RECORE:

JANUARY 1 - DECEMEER 31 1902 STABILITY CLAES:

E I

E L E U a I I O :h _ _ _ _ _ _. _ _ _ __ _._ _ _.. _ _1 0 _ d c t e r s. _ _ _.. _

Wind-Wind Speed UT h > at 10M Level Direct

-_ 1 :3

_a:2 S:12 12:18 1E':24

_224 ICIAL N

14 41 12G 100 36 5

'324

[

NNE 8

47~

54 26 6

5 146 5

NE 31 77 20 10 0

0' 138 ENE 17 75 o?

16 0

1 178 E

10 50 72 35 O

O 167 4

ESE O

CO 107 25 1

0 231 i

EE 4

70 161 45 5

0 285 l

SSE o

69

'168 153 40 1

440 l

5 8

42 234 259 86 9

637' ESW e

41 100 68 28 4

247 SW 3

45 52 13 0

O-113 WEW 1

31 38 7

2 O

79 i

i i

i W

3 46 56 21 O

O 126 1

i l

WNW 1

13 47 10 2

O S2

.Ii I

. -l NW 7

37 74 33 9

1 161 l

1 NNW 7

47 96 39 18 0

207

^

___Q________Q________Q____

2ABIALLE___Q________0________Q TOTAL 115 821 1476 868 233 26 3539 Period of calm (hours)=

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Enclosure to NA 93-0041 I

Page-25 of-37 b

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M iP3 A T al. r m:0' TFEED AND DIFECTION

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--n L :

,aw y.Ri 1 -

.W CEMBEfi 31 19 2

- u-1:/, 0:

iz i - s-

' 'i -

_.L A 3 E :

F E d '. A f 1_ m _. _... _..._ _ _ _ _ _ _ __

_._1_...D

, a:: _ _ _ __ ___ __ u _ __._ _ _ --. -.__ _ _ _.-_ -

6 N>

d wind
2. c, e.:: e n-at 10M Levei 2unr t l:2

_4:2 0:1 2.ir18 11':24 224 ICIAL

(

N 4

74 15 5

0 0

56 ted 3

41

'7 1

O O

72 i

NE 25 3?

1 e;

O O

61 ErE '

~

53 0

0 0

'69 j

E S

48 17 4

0 0

74 i

1

.1

.;.,1 4

0 0

10 o,,-

t. _ _ _

IE a

71 37 4

O

- 0 116 1

1 1m.em ww r,

47

m. _

o-o.

c i

=

a.

.c 4 ac o

g.e o_.

ce

.e -

t

-? ? W 5

17 24 12 0

0 58 i

zw lo 10 1

0 0

33 i

WEW 2

21 1O O

O O

33 j

4 5

?

e WNW I

9 7

O O

O 17 i

Nu 7

25 15 0

0 0

47 e

I I

blI'..b -d h

!f

^^

h h

j 60 t

' ' a E l.@ L E _ _ _ 0_ _ _ _., _ _ _ O _ _ _ _ _.. _ C._ _ _ _ _ _.. _ _0_ _ _ _ _ _ O _ _ _ _ -. _ _0 _ _ _ _ _ _ _ _ Q _. _ _

$ ^^

._u, u.'

b.

l

,.: > r-, f_

..m-s.."0 ke t ' v i d

.I C S;. l rre (hndr s) :

O 8

E l

c 1

?

i

,. r--

,_y w

9

Enclosure to NA 93-0041 Page 26 of 37.

HOUFE AT EM H WIND CPEED AND DIRECTION DECEMEER 31 1992 CEhl.*

v~

HECORD:

.%NL%FV 1

. ' #, L I.T.,

w, r.,:a.

E L a, A ll D rn.

_ - _ _.., _ _ _ _._ _.... 10 _Id e l. e t I _ _ _ -- - ~ _.. _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ __ _ _ _ _ _ _

Wind Wind Speed I Mi" H )

at 10M Levei Direct

_1:3 4:I J.21 '_

1.3:18 12:24

_ :.2:a

-IGIAL-N 1

9 9

0 0

0

.15 NNE O

M

^C 1

O O

60 21 1

O O

O 39

-[

NE ENE 4

10 2

O O

O 22 c

to 4

0 0

0 26

-[

+

ESE 4

4e 5

O O

O 55 SE C

19 2

O O

O

-33 1

-i SEE 1

17 12 O

O O

30

.1 O

O._ '

O.

.~ n.

(

t EEa 0

5 4

3 0

0 12 2W O

9 O

O O

O 3

~

WW G

4 2

O O

O o

i W

2

?

1 0-0 0

6 WNW C

1 O

O O

9 i

NW 3

15 0

0 0

0 18-1 NNW 3

10 0

0 0

0 1A

[

i V A El e L LE _ _._0_ _ _ _ _._ _ Q _ _ _ _. _ _0_ _ _ _ _ _ _ O _ _ _ _ _ _ _ _0_ _ _ _ _ _ _ _ Q _ _ _ __ _ _ _01_ _ _

i

-1 "OTAL

??

253 70 4

0 0

369 t

t

$Et'4Qd G t' C ik l tD ( h C 11 *" ~a b I O

v 4

.a v

Enclosure to NA 93-0041

+

.Page'27.of;37 c

t

  1. cure-A7 EACM wiUD CPEEC AND DIRECTION
  1. EI th JANUARY 1 - DECEME:ER 01 1992-

'. t i v. i L _ -

_ A,_;

AL.L m

6 L E ' 'd Il O::.u _ _ _. _ _._ _ _ _-_. _ _ _ _.

_10_ t a i s c.;- _ _ _ - _ _ _ _ _ _ _. _ _. _ _ _ _ _._ __ _ _ _ _ _ _ _.;_

s F Wtnd w, r,d Speed (MPH)

L t 10M Leve1 22cect

_1:2

_s Z 3:12.

13:1S 12:24

_L2d ICIAL

.5 L

N 24 120 251 205 72 12

_684 j

NNC 1i 157 102 104 24 9

503 NE

,~

lo4'

e 21 0

0_

3c.?

I FNE 175 17o 23 0

1

-411 E

14e 157 52 0

0 375 4

EEE 17 247 201 46 2

0 511 7

SE 12 1*9 275 91 7

0 584-SSE 20 if:

370 252 50 1

' sos 3

lo 119 464 479 152 11 1241 t

?Iw 20 93 209 166 45

_ _4 537 1

EW

~

98 90 26 O'

.O 223 4W o

78 21 22 13 1

204 W

87 107 42 6

20 271-4e 91 69 32 6

253 l

  1. aw 1

NW 22 101 157 125 41 4

46c>

NNW 17 133 2G1 131 62 6

605 L'A C l a C L E _ _ _ 0 _ _... _ _ _ _._ u _ _ _ _ _ _ _._ D._ _ _ _ _ _ _ _ Q _ _ _ _ _ _ _ _ Q _ _ _ _ _ _ _ _ 0 _ _ _._ _ _ _ _ Q _ _ _ _

-j 1

TOTAL 12.5

,_1 ? 4 3170 1854 506 75

'9119 b ? t' '?j ITd C 6 I TG ( h ",' U F S I

  • h

+

1 l

1

l Enclosure to NA 93-0041 Page 28 of 37 l

'i i

i SECTION IV Additional Information 1.

Unplanned or Abnormal Releases There were no unplanned or abnormal releases during this time period.

2.

Offsite Dose Calculation Manual (ODCM) t There were no revisions to the ODCM during this time period.

l 3.

Major Changes to Radwaste Treatment Systems No plant modifications to the radwaste treatment systems are currently

[

reportable.

4.

Land Use Census There were no new locations for dose calculations identified during this t

report period.

5.

Radioactive Shipments f

There were nine shipments of radioactive radwaste during this report

[

period. Six shipments were to Barnwell, South Carolina, two were to Richland, Washington, and one went to Beatty, Nevada. All nine

[

shipments were by truck.

6.

Inoperability of Effluent Monitoring Instrumentation There were no events that involved inoperable liquid or gaseous effluent I

monitoring instrumentation not being corrected within the time specified in Technical Specifications 3.3.3.10 or 3.3.3.11.

7.

Storage Tanks There were no events leading-to liquid holdup tanks or gas storage tanks

[

exceeding the limits of Technical Specifications 3.11.1.4 or 3.11.2.6.

.[

i t

t b

. Enclosure to'NA 93-0041-Page-29'of 37..

ATTACHMENT 1 1

2 provides actual values to replace the estimated value's for

]

liquid. effluents lprovided in Semiannual Radioactive Effluent' Release-Report 15.

New values are denoted by bold face type.

-}

r I

.i

'I I

t

.' 6 i

e i

'I

.I

.I l

i

.h r

P P

Epslosene to NA 93-0041 Page 30 of 37 SECTION I REPORT OF RADTOACTIVE EFFLUENTS (1992): LIQUID Unit Quarter Quarter 1

2 A.

Fission and Activation Products f

1.

Total Release (not including tritium, gases, alpha)

Ci 1.19E-01 3.23E-02 2.

Average Diluted Concentration During Period uCi/ml 1.14E-08 1.38E-08 3.

Percent of Applicable Limit (1)

Z 2.38E+00 6.46E-01 B.

Tritium 1.

Total Release Ci 1.01E+02 3.01E+01 2.

Average Diluted Concentration During Period uCi/ml 9.67E-06 1.29E-05 3.

Percent of Applicable Limit (2)

I 3.22E-01 4.30E-01 C.

Dissolved and Entrained Gases 1.

Total Release Ci 8.36E-03 3.21E-04 2.

Average Diluted Concentration During Period uCi/ml 8.00E-10 1.37E-10 3.

Percent of Applicable Limit (3)

Z 4.00E-04 6.85E-05 D.

Gross Alpha Radioactivity 1.

Total Release C1 1.68E-05 9.56E-06 E.

Volume of vaste released (prior to dilution) liters 1.45E+08 6.03E+07-F.

Volume of dilution water used liters 1.03E+10 2.28E409 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:

( Averace Diluted Concent ration) (100)

I of Applicable Limit (MPC, Appendix B. Table II 10CFR20) 3.

This value is derived by the following formula:

I of Applicable Limit =

(Averane Diluted Concentration) (100)

(2E-4 from ODCM Section 2.1) 4.

Curies in Quarter 2 are based on April composite results for Fe-55 and 1st Quarter composite results for Sr-89 and Sr-90.

Estimated values for Quarter 2 have now been replaced with ccinal composite results.

Encloture.to NA 93-0041 Pagi 31 mf 37 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCL1 DES Quarter Quarter Quarter Quarter i

RELEASED Unit 1

2 1

2 H-3 Ci 3.61E-02 2.30E-01 1.01E+02 2.99E+01 Be-7 Ci 0.00E+00 0.00E+00 0.00E+00 3.98E-05 Cr-51 Ci 0.00E+00 0.00E+00 3.21E-03 5.86E-05 Mn-54 Ci

<7.18E-02

<2.99E-02 2.13E-03 5.12E-04 Fe-55 Ci

<1.44E-01

<5.98E-02 4.45E-02 1.41E-02

^

Fe-59 Ci

<7.18E-02

<2.99E-02 2.14E-04

<2.53E-04 Co-57 Ci 0.00E+00 0.00E+00

'2.39E-04 8.65E-05 Co-58 Ci

<7.18E-02

<2.99E-02 1.49E-02 4.54E-03 Co-60 Ci

<7.18E-02

<2.99E-02 2.85E-02 5.53E-03 Zn-65 Ci

<7.18E-02

<2.99E-02

<7.29E-04

<2.53E-04 Sr-89 Ci

<7.38E-03

<2.99E-03

<7.29E-05

<2.53E-05 Sr-90 Ci

<7.18E-03

<2.99E-03 7.59E-06 5.56E-06 Sr-92 Ci 0.00E+00 0.00E+00 5.3>E-05 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 1.65E-03 8.11E-05 2r-95 Ci 0.00E+00 0.00E+00 7.39E-04 4.29E-05 Mo-99 Ci

<7.18E-02

<2.99E-02

<7.29E-04

<2.53E-04 r

Tc-99m Ci 0.00E+00 0.00E+00 0.00E+00 9.80E-06 I

Ru-103 Ci 0.00E+00 0.00E+00 1.38E-04 0.00E+00 Ag-110M Ci 0.00E+00 0.00E+00 3.20E-04 1.50E-04 Sn-113 Ci 0.00E+00 0.00E+00 9.85E-05 0.00E+00 Sb-124 Ci 0.00Et00 0.00E+00 9.25E-04 9.02E-05 Sb-125 Ci 0.00E+00 0.00E+00 1.18E-02 5.50E-03 I-131 Ci

<1.44E-01

<5.98E-02

<1.46E-03 2.08E-06 Cs-134 Ci 6.89E-05

<2.99E-02 3.94E-03 6.39E-04 Cs-137 Ci 8.10E-05

<2.99E-02 3.97E-03 6.80E-04 i

Ce-141 Ci

<7.18E-02

<2.99E-02

<7.29E-04

<2.53E-04 Ce-144 Ci

<7.18E-02

<2.99E-02 1.11E-03 2.41E-04 t

Gross Alpha ci

<1.44E-02

<5.98E-03 1.68E 9.56E-06 Ar-41 Ci

<1.44E+00

<5.98E-01

<1.46E-02

<5.05E-03 Kr-85 Ci

<1.44E+00

<5.98E-01

<1.46E-02

<5.05E-03 Kr-85m Ci

<1.44E+00

<5.98E-01

<1.46E-02

<5.05E-03 i

Kr-87 Ci

<1.44E400

<5.98E-01

<1.46E-02

<5.05E-03 Kr-88 Ci

<1.44E+00

<5.98E-01

<1.46E-02

<5.05E-03 Xe-131m Ci

<1.44E+00

<S.98E-01

<1.46E-02

<5.05E-03 Xe-133 Ci

<1.44E+00

<5.98E-01 7.82E-03 3.18E-04 Xe-133m Ci

<1.44E+00

<5.98E-01

<1.46E-02

<5.05E-03 Xe-135 Ci

<1.44E+00

<5.98E-01 5.37E-04 3.08E-06 Xe-135m Ci

<1.44E+00

<5.98E-01

<1.46E-02

<5.05E-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 vaste discharged during the_ respective quarter. The less than values are not included in the summation for the total release values.

The Fe-55 value for;the 2nd Quarter is based on the April monthly composite value.

The Sr-89 and Sr-90 values for Quarter 2 are based on the Quarter 1 composite values.

Estimated values for Quarter 2 have now been replaced with actual composite results.

Enclo::ure to NA 93-0041 Flig2 32 aof 37 LIQUID CUMULATIVE DOSE

SUMMARY

(1992)

TABLE 1 ODCM CALCULATED ODCM I 0F DOSE LIMIT LIMIT QUARTER 1 0F 1992 TOTAL DOSE (mrem) FOR BONE 3.22E-02 5.00E+00 6.44E-01

. TOTAL DOSE (mrem) FOR LIVER 7.46E-02 5.00E+00-1.49E+00 TOTAL DOSE (mrem) FOR TOTAL BODY 6.01E-02 1.50E+00 4.01E+00 TOTAL DOSE (mrem) FOR THYROID 1.68E-02 5.00E+00-3.36E-01

, TOTAL DOSE (mrem) FOR KIDNEY 3.58E-02 5.00E+00 7.16E-01 TOTAL DOSE (mrem) FOR LUNG 2.33E-02 5.00E+00 4.66E TOTAL DOSE (mrem) FOR GI-LLI 5.03E-02 5.00E+00 1.01E+00 QUARTER 2 OF 1992

. TOTAL DOSE (mrem) FOR BONE 3.91E-03 5.00E+00 7.82E-02 TOTAL DOSE (mrem) FOR LIVER 1.83E-02*

5.00E400 3.66E-01*

TOTAL DOSE (mrem) FOR TOTAL BODY 1.66E-02*

1.50E+00 1.11E400*

TOTAL DOSE (mrem) FOR THYROID 1.16E-02 5.00E+00 2.32E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.38E-02 5.00E+00 2.76E-01 TOTAL DOSE (mrem) FOR LUNG 1.24E-02*

5.00E+00 2.48E-01*

TOTAL DOSE (mrem) FOR GI-LLI 1.34E-02*

5.00E+00 2.68E-01*

TOTAL FOR 1992 TOTAL DOSE (mrem) FOR BONE 3.61E-02 1.00E+01 3.61E-01 TOTAL DOSE (mrem) FOR LIVER 9.29E-02*

1.00E+01 9.29E-01*

TOTAL DOSE (mrem) FOR TOTAL BODY 7.67E-02*

3.00E+00 2.56E+00*

TOTAL DOSE (mrem) FOR THYROID 2.84E-02 1.00E+01 2.84E-01 TOTAL DOSE (mrem) FOR KIDNEY 4.96E-02 1.00E+01 4.96E-01 TOTAL DOSE (mrem) FOR LUNG 3.57E-02*

1.00E+01 3.57E-01*

TOTAL DOSE (mrem) FOR GI-LLI 6.37E-02*

1.00E+01' 6.37E-01*

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 to any organ is less than or j

equal to 5 mrem per quarter and 10 mrem per year, j

  • .There were no significant changes to these values and they are therefore reported the same as the values in Report 15.

NOTE: The values above have been adjusted to reflect actual composite data.

i

)

i

Enclosure to NA 93-0041 P.tge 33'*of 37 LIQUID CUMULATIVE DOSE SIMtARY. (1992)

TABLE 2 A.

Fission and Activation Products Quarter 1 Quarter 2 Total (not including B-3, gases, alpha) 1.

Total Release - (C1) 1.19E-01 3.23E-02 1.51E-01 2.

Maximum Organ Dose (mrem) 6.31E-02 6.70E-03 6.98E-02*

3.

Organ Dose Limit (mrem) 5.00E+00 5.00E+00 1.00E+01 4.

Percent of Limit 1.26E+00 1.34E-01 6.98E-01*

B.

Tritium 1.

Total Release (Ci) 1.01E+02 3.01E+01 1.31E+02 2.

Maximum Organ Dose (mrem) 1.16E-02 1.16E-02 2.32E-02 3.

Organ Dose Limit (mrem) 5.00E+00 5.00E+00 1.00E+01 4.

Percent of Limit 2.32E-01 2.32E-01 2.32E-01 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 maxin;um organ dose which assumes that an individual drinks the water and eats fish from the discharge point.

ODCM Section 2.2 organ dose limits are used.

NOTE: The 2nd Quarter Category A values were calculated based on the April Fe-55 composite results and First Quarter Sr-89 and Sr-90 composite results.

Estimated values for Quarter 2 have now been replaced with actual composite results.

  • There were no significant changes to these values and they are therefore reported that same as the values in Report 15.

t

?

[

Enclostfre to NA 93-0041 Page 34 of 37 REPORT OF RADIOACTIVE EFFLUENTS (1992): AIRBORNE Quarter Quarter Unit 1

2 A.

Fission and Activation Gases 1.

Total Release C1 1.77E+02 5.90E+01 2.

Average Release Rate for Period uC1/sec 2.71E+02 5.85E+02 3.

Percent of ODCM Limit (1) 2 2.41E-01 7.00E-02 B.

Iodines e

1.

Total Iodine-131 Ci 0.00E+00 0.00E+00 2.

Average Release Rate for Period uCi/sec 0.00E+00 0.00E+00 3.

Percent of Applicable Limit (2)

I 0.00E+00 0.00E+00 C.

Particulates 1.

Particulates with Half-lives > 8 days Ci 0.00E+00 4.91E-07 2.

Average Release Rate for Period uCi/sec 0.00E+00 6.25E-08.

3.

Percent of ODCM Limit (3)

I 0.00E+0C 1.05E-03 4

Oross Alpha Radioactivity Ci 0.00E+00 0.00E+00 D.

Tritium 1.

Total Release Ci 3.74E400 4.13E+00 2.

Average Release Rate for Period uCi/sec 5.09E-01 1.01E+00

.3.

Percent of ODCM Limit (4)

I 3.55E-02 3.93E 1.

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

I of ODCM Limit = (Otrly Total Beta Airdose)(100) or (Otrly Total Gamma Airdose)(100) 10 mrad 5 mrad

-i The largest value calculated between Gamma and Beta airdose is listed as the I of ODQH Limit.

2.

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

(Total Curies of Todine-131)(100)

I of ODCM Limit

=

1 Curie 3.

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

I of ODCM Limit = (Hithest Ornan Dose Due to Particulates)(100) 7.5 mrem 4.

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

I of ODCM Limit = (Hithest Orcan Dose Due to H-3)(100) 7.5 mrem This type of methodology is used since the Wolf Creek ODCM ties release. limits to doses NOTE:

rather than Curie release rates. Also, the values in Category C of Quarter 2 have been adjusted-to reflect actual Sr-90 composite data.

b

Epilosure to NA 93-0041

-P:ge 35 of 37

[

GASEOUS EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1

2 1

2 1.

Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 5.23E-02 1.22E-01 Kr-85 Ci 1.29E+02 0.00E+00 4.55E+01 3.74E+01 Kr-85M Ci 0.00E+00 7.63E-02 0.00E+00 0.00E+00 Kr-87 Ci

<4.42E+01

<4.47E+01

<8.28E-01

<1.99E-02 Kr-88 Ci 4.27E-02

<3.36E+01

<6.22E-01

<1.50E-02 Xe-131M Ci 0.00E+00 0.00E+00 3.55E-03 0.00E+00 Xe-133 Ci 1.99E-01 1.82E+01 2.28E-01 1.77E-02 Xe-133M Ci

<4.96E+01

<5.02E+01

<9.28E-01

<2.24E-02 Xe-135 C1 1.72E+00 3.13E+00

<7.66E-02 3.98E-04 Xe-138 Ci

<9.27E+01

<9.39E+01

<1.74E+00

<4.18E-02 Total Ci 1.31E+02 2.14E+01 4.58E+01 3.75E+01 2.

Halogens (Gaseous) i I

I-131 Ci

<2.55E-04

<2.59E-04

<4.78E-06

<1.15E-07 I-133 Ci

<2.55E-02

<2.59E-02

<4.78E-04

<1.15E-05 Total Ci

<2.58E-02

<2.62E-02

<4.83E-04

<1.16E-05 3.

Particulates and Tritium H-3 Ci 3.53E+00 4.07E+00 2.07E-01 5.37E-02 Mn-54 Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 Fe-59 Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 Co-58 Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 Co-60 Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 2n-65 Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 Mo-99 Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 Cs-134 Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 Cs-137 Ci

<2.55E-03 4.52E-07

<4.78E-05

<1.15E-06 Ce-141 Ci

<2.55E-03

<2.59E-03'

<4.78E-05

<1.15E-06 Ce-144 Ci

<2.55E-03

<2.59E-03'

<4.78E-05

<1.15E-06' Sr-89 Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 Sr-90 Ci

<2.55E-03 3.91E-08

<4.78E-05

<1.15E-06 Gross Alpha Ci

<2.55E-03

<2.59E-03

<4.78E-05

<1.15E-06 Total Ci 3.53E+00 4.07E+00*

2.07E-01 5.37E-02

[

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.

  • There was no significant change to this value and it is therefore reported the same as the value in Report 15.

Enclosure to NA 93-0041 F, age 30 of 37 GASEOUS CUMULATIVE DOSE

SUMMARY

(1992)

Table 1 ODCM CALCULATED ODCM I 0F QUARTER 1 0F 1992 DOSE LIMIT LIMIT TOTAL DOSE (mren) FOR BONE 0.00E400 7.50E+00 0.00E+00 TOTAL DOSE (mrem) FOR L1VER 2.66E-03 7.50E+00 ~

3.55E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 2.66E-03 7.50E+00 3.55E-02 TOTAL DOSE (mrem) FOR THYROID 2.66E-03 7.50E+00 3.55E-02 TOTAL DOSE (mrem) FOR KIDNEY 2.66E-03 7.50E+00 3.55E-02.

TOTAL DOSE (mrem) FOR LUNG 2.66E-03 7.50E+00 3.55E-02 TOTAL DOSE (mrem) FOR GI-LLI 2.66E-03 7.50E+00 3.55E-02 QUARTER 2 0F 1992 TOTAL DOSE (mrem) FOR BONE 7.84E-05 7.50E+00 1.05E-03 TOTAL DOSE (mrem) FOR LIVER 2.99E-03 7.50E+00 3.99E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 2.97E-03 7.50E+00.

3.96E-02 TOTAL DOSE (mrem) FOR THYROID 2.95E-03 7.50E+00 3.93E-02 TOTAL DOSE (mrem) FOR KIDNEY 2.96E-03 7.50E+00 3.95E-02 TOTAL DOSE (mrem) FOR LUNG 2.96E-03*

7.50E+00 3.95E-02*

TOTAL DOSE (mrem) FOR GI-LLI 2.95E-03*

7.50E+00 3.93E-02*

TOTALS FOR 1992 TOTAL DOSE (mrem) FOR BONE 7.84E-05 1.50E+01 3.23E-04 TOTAL DOSE (mrem) FOR LIVER 5.65E-03 1.50E+01 3.77E-02 i

TOTAL DOSE (mrem) FOR TOTAL BODY 5.63E-03 1.50E+01 3.75E-02*

TOTAL DOSE (mrem) FOR THYROID 5.61E-03 1.50E+01 3.74E-02 TOTAL DOSE (mrem) FOR KIDNEY 5.62E-03 1.50E+01 3.75E-02 TOTAL DOSE (mrem) FOR LUNG 5.62E-03*

1.50E+01 3.75E-02*

TOTAL DOSE (mrem) FOR GI-LLI 5.61E-03*

1.50E+01 3.74E-02*

1.

Based on Wolf Creek ODCM Section 3.2.2 which restricts dose during any calender quarter to less than or equal to 7.5 mrem to any organ and during any calender year to less than or equal to 15 mrem to any organ.

NOTE: The values above have been adjusted to reflect actual composite data.

  • There were no significant changes to these values and they are therefore reported the same as the values in Report 15.

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'P.ge 37 of 37 GASEOUS CUMULATIVE DOSE

SUMMARY

(1992)

TABLE 2 Nuclides Released Quarter 1 Quarter 2 Total A.

Fission and~ Activation Gases 1.

Total Release (Ci) 1.77E+02 5.90F+01 2.36E+02

.2.

Total Gamma Airdose (mrad) 5.29E-04 9.97E-04 1.53E-03 3.

Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 1.00E+01 4.

Percent of Gamma Airdose Limit 1.06E-02 1.99E-02 1.53E-02 5.

Total Beta Airdose (mrad) 2.41E-02 7.00E-03 3.11E-02 6.

Beta Airdose Limit (mrad) 1.00E+01 1.00E+01 2.00E+01 7.

Percent of Beta Airdose Limit (mrad) 2.41E-01 7.00E-02 1.56E-01 B.

Particulates 1.

Total Particulates (Ci) 0.00E+00 4.91E-07 4.91E-07 2.

Maximum Organ Dose (mrem) 0.00E+00 7.84E-05 7.84E-05 3.

Organ Dose Limit (mrem) 7.50E+00 7.50E+00 1.50E+01-4.

Percent of Limit 0.00E+00 1.05E-03 5.23E-04' C.

Tritium 1.

Total Release (Ci) 3.74E+00 4.13E+00 7.87E+00 2.

Maximum Organ Dose (mrem) 2.66E-03 2.95E 03 5.61E-03 3.

Organ Dose Limit (mrem) 7.50E+00 7.50E+00 1.50E+01 4.

Percent of Limit 3.55E-02 3.93E-02 3.74E-02 D.

Iodine i

1.

Total I-131, I-133 (Ci) 0.00E+00 0.00E+00 0.00E+00 2.

Maximum Organ Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 3.

Organ Dose Limit (mrem) 7.50E+00 7.50E+00 1.50E+01 4.

Percent of Limit 0.00E+00 0.00E+00 0.00E+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.

j NOTE: The values in category B of Quarter 2 have been adjusted to reflect acutal Sr-90 composite data.

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