ML20090A899

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Semiannual Radioactive Effluent Release Rept 14 for Jul Through Dec 1991
ML20090A899
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/31/1991
From: Henry S
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20090A885 List:
References
NUDOCS 9203030132
Download: ML20090A899 (38)
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Enclosure to NO 92-0067 Page 1 of 34 WOLF CREEK NUCLEAR OPERATING CORPORATION Wolf Creek Generating Station  ;

l-Docket No: 50-482 Facility Operating License Not NPF-42 i:

l SDf1 ANNUAL RADICACTIVE EFFLUENT RF1 EASE REPORT Report No 14 Reporting Period: July 1, 1991 through December 31. 1991 l

Prepared by: Steve A. Henry Steve G. Wideman

,7 Approved by: / IM- / ;"^ /8///V(

Otto L.*Ma'ynard' Director Plant Operations l:

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l 9203030132 911231 PDR ADOCK 05000482 R PDR

(. ~s Enclosure to NO 92-0067 Page 2 of 34 l EXECUTIVE SUM 'ARY 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 Volf Creek Generating Station (WCGS). This report covers the period beginning on July 1, 1991, and ending on December 31, 1991.

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 determination is met by the WCGS Offsite Dose Calculation Manual methodology of assign 4.; all gaseous pathways to a hypothetical individual residing at the high,st annual X/Q and D/Q location. This results in a conservative estimate cf dose to a member of the public rather than determining each pathway done for each release 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 Technical Specification 6.9.1.7.

Attachment 1 provides actual values to replace the estimated values for lignid effluents provided in Semiannual Radioactive Effluent Release Report No. 13. Analysis results for the Second Quarter of Report No. 13 were not c( mpleted prior _to submission of the report. Actual results of Quarter 2 liquid effluents indicated the presence of Fe-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 1991 have not yet been completed. Fe-55 activity and doses in liquid effluents are presented as an estimate.

Offsite Dose Calculation Manual (ODCM), Revision 8, was approved by the Plant Safety Review Committee during this reporting period. This revision includes a deletion of the requirements to obtain tritium grab samples of the ventilation exhaust from the spent fuel pool area. A complete copy of the ODCM is included as Attach:nent 2 of this report.

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Enclosure _to NO 92-0067 Page 3 of 34 Table of Contents Pane Section I 4 Liquid Radioactive Effluents 4 Dose Summary 7 Airborne Radioactive Effluents 9 Dose Summary 11 Section 11 13 Offsite Dose Calculation Manual Limits 13 Maximum Permissible Concentrations 14 Measurements and Approximations of Total Radioactivity 15 Batch Releases 17 Continuous Releases 17 Solid Waste Shipments 18 Irradiated Fuel Shipments 20 Section III 21

..eteorological Data 21 Section IV 29

-Unplanned _or Abnormal Releases 29 Offsite Dose Calculation Manual 29 Hajor Changes to Liquid, Gaseous or Solid Radwaste Systems 30 Land Use Census 34 Radioactive Shipments 34 Inoperability of Airborne Effluent Monitoring Instrumentation 34 Storage Tanks 34 Liquid Effluent Changes to Report 13 Offsite Dose Calculation Manual

Enclosure to NO 92-0067 Page 4 of 34 SECTION I REPORT OF RADIOACTIVE EFFLUENTS (1991): LIQUID Unit Quarter Quarter 3 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci 7.27E-01 9.78E-01
2. Average Diluted Concentratign During Period uCi/ml 1.69E-07 1.78E-07
3. Percent of Applicable Limit I 1.45E+01 1.96E+01 B. Tritium
1. Total Release Ci 1.84E+02 5.12E+01
2. Average Diluted Concentratign During Period uC1/ml 4.28E-05 9.33E-06
3. Percent of Applicable Limit 2 1.43E+00 3.11E-01 C. Dissolved and Entrained Gases
1. Total Release Ci 6.87E+00 6.66E+00
2. Average Diluted Concentratign During Period uCi/ml 1.60E-05 1.21E-06
3. Percent of Applicable Limit  : 8.00E-01 6.05E-01 D. Gross Alpha Radioactivity

, 1. Total Release C1 2.74E-05 1.84E-05

-E. Volume of waste released (prior to dilution) liters' 3.70E+06 1.90E+07 F. Volume of dilution water used liters 4.30E+09 5.47E+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.

This value is derived by the following formulas

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

(MPC, Appendix B. Table II 10CFR20)

This value is derived by the following formula:

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

(2E-4 from ODCM Section 2.1) 6.62E-01 of the 9.78E-01 Curies in !uarter 4 are due to Fe-55 estimated from the Quarter 3 Composite results.

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Enclosure to NO 92-0067 Page 5 of 34 I

L1 QUID KFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3 4 3 4 H-3 C1 1.66E-02 7.01E-02 1.84E+02 5.11E+01 Be-7 Ci 0.00E+00 0.00E+00 0.00E+00 2.75E-03 Na-24 Ci 0.00E+00 0.00E+00 0.00E+00 5.50E-04 Cr-51 Ci 0.00E+00 0.00E+00 4.97E-03 3.92E-02 Mn-54 Ci <1.21E-03 <8.71E-03 7.96E-03 2.30E-03 Fe-55 C1 <2.42E-03 <1,74E-02 5.27E-01 6.62E-01 Fe-d9 Ci <1.21E-03 <8.71E-03 2.60E-04 3.77E-03 Co-57 Ci 0.00E+00 0.00E+00 9.48E-04 1.16E-03 Co-58 Ci <1.21E-03 <8.71E-03 3.08E-02 5.45E-02 Co-60 Ci <1.21E-03 <8.71E-03 1.30E-01 6.98E-02 Zn-65 Ci <1.21E-03 <8.71E-03 9.61E-05 <8.07E-04 Sr-89 Ci <1.21E-04 <8.71E-04 9.12E-05 1.15E-04 Sr-90 Ci <1.21E-04 <8.71E-04 <6.42E-05 <8.07E-05 Sr-92 Ci 0.00E+00 0.00E+00 1.13E-04 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 7.36E-04 1.54E-03 Nb-97 Ci 0.00E+00 0.00F+00 2.023-06 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 4.61E-04 6.96E-04 Zr-97 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mo-99 Ci <1.21E-03 <8.71E.03 <6.42E-04 <8.07E-04 Tc-99M Ci 0.00E+00 0.00E+00 1.53E-04 2.08E-05 Ru-103 Ci 0.00E+00 0.00E+00 4.13E-04 5.65E-04 Ag-110M Ci 0.00E+00 0.00E+00 4.08E-03 1.76E-04 Sn-113 Ci 0.00E+00 0.00E+00 1.76E-04 8.53E-05 Sn-117M Ci 0.00E+00 0.00E+00 1.70E-04 2.77E-04 Sb-124 Ci 0.00E+00 0.00E+00 1.40E-03 8.65E-03 Sb-125 Ci 0.00E+00 0.00E+00 9.26E-03 2.84E-02 Sb-126 Ci 0.00E+00 0.00E+00 1.01E-04 1.44E-05 I-131 Ci <2.42E-03 <1.74E-02 9.56E-04 2.06E-03 Cs-134 Ci <1.21E-03 <8.71E-03 2.31E-03 4.58E-02 Cs-136 Ci 0.00E+00 0.00E+00 0.00E+00 1.91E-04 Cs-137 Ci <1.21E-03 <8.71E-03 3.4bE-03 4.96E-02 Ba-139 C1 0.00E+00 0.00E+00 8.71E-04 2.46E-03 La-140 Ci 0.00E+00 0.00E+00 1.08E-04 3.47E-04 Ce-141 Ci <1.21E-03 <8.71E-03 7.63E-05 2.99E-04 Ce-144 Ci <1.21E-03 <8.71E-03 3.49E-04 1.62E-04 Hf-181 Ci 0.00E+00 0.00E+00 0.00E+00 1.65E-05 Np-239 Ci 0.00E+00 0.00E+00 2.32E-05 0.00E+00 Gross Alpha Ci <2.42E-04 <1.74E-03 2.74E-05 1.84E-05 Ar-41 Ci <2.42E-02 <1.74E-01 <1.28E-02 <1.61E-02 Kr-85M Ci <2.42E-02 <1.74E-01 8.29E-05 <1.61E-02

- - - - - . _ _ - - - - - - - - - - - - - - - - - _ . __ _______a

Enclosure to NO 92-0067 Page 6 of 34 LIQUID EFFLUENTS CONTINUED Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3 4 3 4 Kr-85 Ci <2.42E-02 <1.74E-01 7.66E-01 1.89E-01 Kr-87 Ci <2.42E-02 <1.74E-01 <1.28E-02 <1.61E-02 Kr-88 Ci <2.42E-02 <1.74E-01 <1.28E-02 <1.61E-02 Xe-131M Ci <2.42E-02 <1.74E-01 1.21E-01 2.19E-01 Xe-133M Ci <2.42E-02 <1.74E-01 2.74E-02 8.51E-03 -

Xe-133 Ci <2.42E-02 <1.74E-01  ! 94E+00 6.24E400 Xe-135M Ci <2.42E-02 <1.74E-01 <1.28E-02 <1.61E-02 Xe-135 Ci <2.42E-02 <1.74E-01 6.90E-03 <1.61E-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 vaste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

The Fe-55 anri Sr-89 values for Quarter 4 are based on the Quarter 3 Composite results. -

Enclosure to NO 92-0067 Page'7 of 34 LIQUID CUMULATIVE DOSE SUMARY (1991)

TABLE 1 ODCM CALCULATED ODCM 2 OF DOSE LIMIT LIMIT QUARTER 1 0F 1991 TOTAL DOSE (mrem) FOR BONE 3.33E-03 5.00E+00 6.66E-02 TOTAL DOFE (mrem) FOR LIVER 1.77E-02 5.00E+00 3.54E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 1.61E-02 1.50E+00 1.07E+00 TOTAL DOSE (mrem) FOR THYROID 1.27E-02 5.00Et00 2.54E-01 TOTAL DOSE (mrem) FOR KIDNEY' 1.42E-02 5.00E+00 2.84E-01 TOTAL DOSE (mrem) FOR LUNG 1.35E-02 5.00E+00 2.70E-01

-TOTAL DOSE (mrem) FOR GI-LLI 1.55E-02 5.00E+00 3.10E-01 QUARTER 2 0F 1991 TOTAL DOSE (mrem) FOR BONE 7.79E-03 3.00E+00 1.56E-01 TOTAL DOSE (mrem) FOR LIVER 3.78E-02 5.00E+00 7.56E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 3.42E-02 1.50E+00 2.28E+00 TOTAL DOSE (mrem) FOR THYROID 2.84E-02 5.00E+00 5.68E-01 TOTAL DOSE (mrem) FOR KIDNEY 3.04E-02 5.00E+00 6.08E-01 TOTAL DOSE'(mrem) FOR LUNG 3.07E-02 5.00E+00 6.14E-01 TOTAL DOSE (mrem) FOR GI-LLI 5.07E-02 5.00E+00 1.01E+00

' QUARTER 3 0F 1991 TOTAL DOSE (mrem) FOR BONE 1.47E-01 5.00E400 2.94E+00 TOTAL DOSE (mrem) FOR LIVER 3.13E-01 5.00E+00 6.26E+00 TOTAL DOSE (mrem) FOR TOTAL BODY 2.46E-01 1.50E+00 1.64E+01 TOTAL DOSE (mrem) FOR THYROID 7.75E-02 5.00E+00 1.55E+00 TOTAL DOSE (mrem) FOR KIDNEY 1.45E-01 5.00E+00 2.90E+0p LTOTAL DOSE (mrem) FOR LUNG 9.26E-02 5.00E+00 1.85E+00 TOTAL DOSE--(mrem) FOR GI-LLI 1.87E-01 5.00E+00 3.74E+00 QUARTER 4 0F 1991 TOTAL DOSE (mrem) FOR BONE 5.36E-01 5.00E+00 1.07E+01 TOTAL DOSE (mrem) FOR LIVER 9.88E-01 5.00E+00 1.98E+01 TOTAL-DOSE (mrem) FOR TOTAL BODY 7.44E-01 1.50E+00 4.96E+01 TOTAL DOSE (mrem) FOR-THYROID 4.0$E-02 5.00E+00 8.10E-01 TOTAL DOSE (mrem) FOR KIDNEY 3.47E-01 5.00E+00 6.94E+00 TOTAL DOSE (mrem) FOR LUNG 1.41E-01 5.00E+00 2.82E+00 TOTAL DOSE (mrem) FOR GI LLI 1.38E-01 5.00E+00 2.76E+00 TOTAL'FOR 1991' TOTAL DOSE (mrem) FOR BONE 6.94E-01 1.00E+01 6.94E+00 TOTAL DOSE (mrem).FOR LIVER 1.36E+00 1.00E+01 1.36E+01 TOTAL DOSE (mrem) FOR TOTAL BODY 1.04E+00 3.00E+00 3.47E+01 TOTAL DOSE (mrem) FOR THYROID 1.59E-01 1.00E+01 1.59E+00 TOTAL DOSF-(mrem) FOR KIDNEY 5.37E-01 1.00E+01 5.37E+00 TOTAL DOSE (mrem) FOR LUNG 2.78E-01 1.00E+01 2.78E+00 TOTAL DOSE (mrem) FOR GI-LLI 3.91E-01 1.00E+01 3.91E+00 Based on ODCK 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.

NOTEt_ The values for Quarters 1 and 2 of 1991 given above differ from the values reported in Semiannual Radioactive Effluent Release Report No. 13 due to adjustment for Fe-55 and Sr-90 composite data.

l Enclosure to NO 92-0067 Page 8 of 34-LIQUID CUMULATIVE DOSE SU M ARY (1991)

TABLE 2 A. Fission and Ac'.ivation Pr(ducts Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (not including H-3 ,

gases, alpha)

1. Tntal Release - (Ci) 9.03E-02 7.17E-01 7.27E-01 9.78E-01 2.51E+00

-2. Maximum Organ Dose-(mrem) 5.00E-03 2.23E-02 2.39E-01 9.48E-01 1.21E+00

3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01
4. Percant of Limit 1.00E-01 4.46E-01 4.78E+00 1.90E+01 1.21E+01 B. Tritium
1. Total Release (C1) 1.25E+02 3.57E+02 1.84E+02 5,12E+01 7.17E+02
2. Maximum Organ Dose (mrem) 1.27E-02 2.84E-02 7.39E-02 4.04E-02 1.55E-01
3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01
4. Percent of Limit 2.54E-01 5.68E-01 1.48E+00 8.08E-01 1.55E+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 fish from the discharge point.

0DCM Section 2.2 organ dose limits are used.

NOTE: The Quarter 4 Category A values were calculated based on the Quarter 3 Fe-55 concentration.

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-Enclosure to NO 92-0067 Page 9 of 34 REPORT OF RADIOACTIVE EFFLUENTS (1991): AIRBORNE Quarter Quarter Unit 3 4 A. Fission and Activation Gases

1. Total Release Ci 8,40E+02 1.68E+03
2. AverageReleaseRate{orPeriod uCi/sec 1.04E+05 2,90E+02
3. Percent of ODCM Limit  ! 6.30E-01 1.28E+00 B. Iodines
1. Total Iodine-131 Ci 2.02E-03 3.73E-04
2. Average Release Rate for Pegiod uCi/sec 3.62E-04 4.70E-05
3. Percent of Applicable Limit I 2.02E-01 3.73E-02 C. Particulates
1. Particulates with Half-lives > 8 days Ci 3.46E-07 1.66E-06
2. AverageReleaseRate{orPeriod uC1/sec 4.36E-07 2.08E-07
3. Percent of ODCM Limit Z 2,44E-06 1.17E-05
4. Gross Alpha Radioactivity Ci 1.30E-08 0.00E+00 D. Tritium .
1. Total Rtlease C1 2.82E+00 4.71E+00
2. AverageReleaseRate{orPeriod uCi/sec 8.56E-01 5,98E-01
3. Percent of ODCM Limit  % 2.68E-02 4.48E-02 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 Z of ODCM Limit.

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

2 of ODCM Limit = (Total Curies of Iodine-131)(100) 1 Curie 3

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

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

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

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

-Encloaure to NO 92-0067 Page 10 of 34 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 4.49E-01 0.00E+00 Kr-85 Ci 0.00E400 0.00E+00 1.54E+01 7.29E+01 Kr-85H C1 3.20E-01 0.00E+00 1.02E-03 0.00E+00 Kr-87 Ci <4.57E+01 <4.53E+01 4.93E-06 <6.80E+00 Kr-88 Ci 6.14E-01 <3.41E+01 7,46E-05 <5.11E+00 Xe-131M Ci 8.21E-01 1.18E+01 7.70E+00 3.34E+01 Xe-133 Ci 3.67E+02 9.98E+01 4.38E+02 1.46E+03 Xe-133M Ci 1.93E+00 <5.08E+01 2.54E+00 5.51E+00 Xo-135 Ci 5.20E+00 <4.19E+00 3.76E-01 <6.29E-01 Xe-135M Ci 0.00E+00 0.00E+00 5.00E-04 0.00E+00 Xe-138 Ci <9.58E+01 <9.51E+01 <1.36E+00 <1.43E+01 Total C1 3.76E+02 1.12E+02 4.64E+02 1.57E+03
2. Falogens (Gaseous) 1-131 C1 1.93E-03 3.73E-04 9.15E-05 <3.93E-06 I-133 C1 1.27E-04 <2.62E-02 1.60E-09 <3.93E-04 Total C1 2.06E-03 3.73E-04 9.15E-05 0.00E+00
3. Particulates and Tritium H-3 Ci 2.39E+00 4.18E+00 4.27E-01 5.29E-01 Mn-54 Ci <2.64E-03 <2.62E-05 <3.76E-05 <3.93E-05 Fe-59 Ci <2.64E-03 <2.ee6-03 <3.76E-05 '<3.93E-05 Co-58 Ci <2.64E-03 1.66E-06 3.46E-07 <3.93E-05 Co-60 Ci <2.64E-03 <2.62E-03 <3.76E-05 <3.93E-05 Zn-65 Ci <2.64E-03 <2.62E-03 <3.76E-05 <3.93E-05 Mo-99 Ci <2.64E-03 <2.62E-03 <3.76E-05 <3.93E-05 Cs-134 Ci <2.64E-03 <2.62E-03 <3-.76E-05 <3.93E-05 Cs-137 Ci <2.64E-03 <2.62E-03 <3.76E-05 <3.93E-05 Ce-141 Ci <2.64E-03 <2.62E-03 <3.76E-05 <3.93E-05 Ce-144 Ci <2.64E-03 <2.62E-03 <3.76E-05 <3.93E-05 Sr-89 Ci <2.64E-03 <2.62E-03 <3.76E-05 <3.93E-05 Sr-90 Ci <2.64E-03 <2.62E-03 <3.76E-05 <3.93E-05 Gross Alpha Ci 1.30E-08 <2.62E-03 <3.76E-05 <3.93E-05 Total C1 2.39E+00 4.18E+00 4.27E-01 5.29E-01 NOTE: Less than values for Noble Gases are calculated using the lower limit of detection (LLD) valuec 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.

Enclosure-to NO 92-0067 ,

Page 11 of.34 GASEOUS CUMQ.AY1VE DOSE SUMHARY (1991)

Table 1 ODCH CALCULATED ODCM I 0F QUARTER 1 0F 1991 DOSE LIMIT LIMIT TOTAL DOSE (mrem) FOR BONE 1.13E-05 7.50E+00 1.51E-04 TOTAL DOSE (mrem)-FOR LIVER 2.93E-03 7.50E+00 3.91E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 2.93E-03 7.50E400 3.91E-02 TOTAL DOSE (mrem) FOR THYROID 2.93E-03 7.50E400 3.91E-02 TOTAL DOSE (mrem) FOR KIDNEY 2.93E-03 7.50E+00 3.91E-02 TOTAL DOSE terem) FOR LUNG 2.93E-03 7.50E+00 3.91E-02 TOTAL DOSE (mrem) FOR GI-LLI 2.93E-03 7.50E+00 3.91E-02 QUARTER 2 0F 1991 TOTAL DOSE (mrem) FOR BONE 1.69E-04 7.50E+00 2.25E-03 TOTAL DOSE (mrem) FOR LIVER 2.51E-03 7.50E+00 3.35E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 2.42E-03 7.50E+00 3.23E-02 TOTAL DOSE (mrem) FOR THYROID 3.69E-03 7.50E+00 4.92E-02 TOTAL DOSE (mrem) FOR KIDNEY 2.44E-03 7.50E+00 3.25E-02 TOTAL DOSE (mrem) FOR LUNG 2.41E-03 7.50E+00 3.21E-02 TOTAL DOSE (mrem) FOR GI-LLI 2.40E-03 7.50E+00 3.20E-02 QUARTER 3 0F 1991 TOTAL DOSE (mrem) FOR BONE 3.51E-03 7.50E+00 4.68E-02 TOTAL DOSE (mrem) FOR LIVER 5.12E-03 7.50E+00 6.83E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 3.60E-03 7.50E+00 4.80E-02 TOTAL DOSE (mrem) FOR THYROID 1.16E+00 7.50E+00 1.55E+01 TOTAL DOSE (mrem) FOR KIDNEY 7.37E-03 7.50E+00 9.83E-02 TOTAL DOSE (mrem) FOR LUNG 1.61E-03 7.50E+00 2.15E-02 TOTAL DOSE (mrem)~FOR GI-LLI 1.93E-03 7.50E+00 2.57E-02 QUARTER 4 0F 1991 TOTAL DOSE (mrem) FOR BONE 6.56E-04 7.50E400 8.75E-03 TOTAL DOSE (mrem) FOR LIVER 4.43E-03 7.50E+00 5.91E TOTAL DOSE (mrem) FOR TOTAL BODY- 4.15E-03 7.50E+00 5.53E TOTAL DOSE (mrem) FOR THYROID 2.17E-01 7.50E+00 2.89E+00 TOTAL DOSE (mrem) FOR KIDNEY 4.85E-03 7.50E+00 6.47E-02 ,

TOTAL' DOSE (mrem) FOR LUNG 3.76E-03 7.50E+00 5.01E-02 TOTAL DOSE (mrem) FOR GI-LLI 3.84E-03 7.50E+00 5.12E-02 TOTALS FOR-1997.

1 TOTAL DOSE (mremi FOR BONE 4.35E-03 -1.50E+01 2.90E-02 TOTAL DOSE (mrem, FOR LIVER 1.50E-02 1.50E+01 1.00E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 1.31E-02 1.50E+01 8.73E-02 I

TOTAL-DOSE (mrem) FOR THYROID 1.38E+00 1.50E+01 9.20E+00

, ~ TOTAL DOSE (mrem) FOR KIDNEY 1.76E-02 1.50E+01 1.17E-01 j TOTAL DOSE (mrem) FOR LUNG 1.07E-02 1.50E+01 7.13E-02 l TOTAL DOSE (mrem) FOR GI-LLI 1.11E-02 1.50E+01 7.40E-02 Based on 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.

~ -. - _ _- -. - .. - . -

Enclosure to NO 92-0067 Page 12 0F 34 GASEOUS CUMULATIVE DOSE

SUMMARY

(1991)

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

1. Total Release (C1) 5.36E+01 4.21E+02 8.40E+02 1.68E+03 2.99E+03
2. Total Gamma Airdose (mrad) 3.55E-03 1.10E-02 2.18E-02 3.90E-02 7.54E-02
3. Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01
4. Percent of Gamma .

Airdose Limit 7.10E-02 2.20E-01 4.36E-01 7.80E-01 7.54E-01

5. . Total Beta-Airdose (mrad) 4.57E-03 3.16E-02 6.30E-02 1.28E-01 2.27,E-01
6. Beta Airdose Limit (mrad) 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01
7. Percent of Beta Airdose Limit (mrad) 4.57E-02 3.16E-01 6.30E-01 1.28E+00 1.14E+00 B. Particulates
1. Total Particulates (C1) 4.12E-07 2,77E-06 3.46E-07 1.66E-06 5.19E-06
2. Maximum Organ Dose (mrem) 1.13E-05 1.65E-04 1.83E-07 8.77E-07 1.77E-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 1.51E-04 2.20E-03 2.44E-06 1.17E-05 1.18E-03

-C. -Tritium

-1. Total Release (C1) 4.12E+00 3.36E+00 2.82E+00 4.71E+00 1.50E+01

2. Maximum Organ Dose (mrem) 2.93E-03 2.40E-03 2.01E-03 3.36E-03 1.07E-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 3.91E-02 3.20E-02 2.68E-02 4.48E-02 7.13E _D. Iodine
1. Total I-131 I-133 (Ci) 0.00E+00 2.25E-06 2.15E-03 3.73E-04 2.53E-03
2. Maximum Orgar Dose (mrem) 0.00E+00 1.29E-03 1.16E+00 2.13E-01 -1.37E+00
3. Organ Dose L.mit (mrem). 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01
4. Percent of Limit 0.00E+00 1.72E-02 1.55E+01 2.84E+00 9.13E+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 ODCM methodology which assumes that an individual actually resides at the release point.

ODCM Section 3.2.2 organ dose limits are used.

i I

l _ _ .- _ __ -_ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _

Enclosure to NO 92-0067 Page 13 of 34 SECTION II Supplemental Information License Number NPP-42 Facility: Wolf Cr(sk Generatina Statfon

1. ODCH Limits A. For liquid waste effluents A.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20, Appsndix B. Table II, Column 2, for radionuclides other thani d dissolved or entrained noble gases, noble the concentration gases. For dissolved or en shall be limited to 2 x 10'gra nemicrocurie/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 materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY --

shall be limited to the following:

For noble gases: Less than or equal to 500 mrems/yr to the a.

whole body and less than or equal to 3000 mremslyr to the skin, and

b. For lodine-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 Less than or equal to 5 mrads

a. During any calendar quarteri for gamma radiation and less than or equal to 10 meads for beta radiation, and
b. During any calendar years Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

- - - - ~%

Enclosure to NO. 92-0067 Page 14 of 34 B.3 The dose from Iodine-131. Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than e-days in gaseous effluents released to areas at and beyond the SITE BOUNDARY shall be limited to the followings During any calendar' quarter: Less.than or equal to 7.5

a. . mrems to any organ, and
b. During any calendar years Less than or equal to 15 mrems to any organ.
2. . Maximum Permissible Concentrations Water - covered in.Section 1.A.

Air - covered in Section 1.B.

3. Average energy of fission and activation gaseous effluenes is not applicable.

Enclosure to NO 92-0067 Page 15 of 34

4. 'Heasurements and Approximations of Total Radioactivity A. Liquid Effluents LIQUID _ RELEASE ' SAMPLING METHOD OF TYPE OF ACTIVITY TYPE. FREQUENCY ANALYSIS ANALYSIS .j
1. Batch Waste P.H.A. Principal Gamma Release P Emmiters Tanks Each Batch P.H.A. 1-131
a. Vaste Monitor P Dissolved and Tank One Batch /M P.H.A. Entrained Gases (Gamma Emitters)

P

b. Secondary Liquid P L.S. H-3 Waste Each Batch Monitor S.A.C. Gross Alpha Tank P 0.S.L. Sr-89. Sr-90 Each Batch 0.S.L. Fe-55
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)
b. Turbine Daily L.S. H-3 Building Grab Sample Sump S.A.C.- Gross Alpha
c. Lime Daily 0.S.L. Sr-89, Sr-90 Sludge . Grab Sample Pond O.S.L. Fe P - prior to each batch S.A.C. = scintillation alpha counter M = monthly 0.S.L. - performed by an offsite laboratory

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

Enclosure to NO 92-0067 Page 16_of 34 B. Gaseous Waste Effluents SAMPLING METHOD OF TYPE OF GASEOUS,' RELEASE TYPE ~ FREQUENCY ANALYSIS ACTIVITY ANALYSIS P

Each Tank P.H.A. Principal Gamma i Waste Gas Decay Tank Grab Sample Emitters P Principal Gamma Containment Purge or. Each Purge P.H.A.

Emitters Vent Grab Sample Gas Bubbler and L.S. H-3 (oride)

Principal Gamma Unit Vent M P.H.A. Emitters Grab Sample Gas Bubbler and L.S. H-3 (oxide)

Radwaste Building M P.H.A. Principal Gamma Vent Grab Sample Emitters For Unit Vent and I-131 Radwaste Building Continuous P.H.A.

Vent release types I-133 listed above. P.H.A.

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

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

Composite Sr-89, Sr-90 Continuous Particulate Sample

Enclosure to NO 92-0067 Page 17 of 34

5. Batch Releases There were 44 gaseous batch releases during the reporting period. The longest gaseous batch t elease lasted 9,800 minutes, while the shortest lasted 20 minutes. The average release lasted 3085 minutes with a total gaseous batch release time of 135,748 minutes.

There were 83 liquid batch releases during the reporting period.

The longest liquid batch release lasted 175 minutes, while the shortest lasted 21 minutes. The average release lasted 115 minutes with a total liquid batch release time of 9,522 minutes.

Continuous Releases 6.

There were two liquid release pathways derignated as continuous releases during this reporting period. They were the Steam Generatot Blowdown and Turbine Building Sump. There were two gas release pathways designated as continuous releases. These were the Unit Vent and Radwaste Building Vent.

Enclosure to NO 92-0067 Page 18 of 34 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1991)

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

1. Type of waste Unit 6-Month Est. Total Period Error
a. Spent resins, filter sludges, m3* 4.70E+00 evaporator bottoms, etc. Ci 9.3BE+00 2.50E+01
b. Dry compressible vaste, m3* 5.67E+01 contaminated equip. etc. Ci 4.30E+00 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 Fe-55 38.2842 3.59E+00 Ni-63 23.124Z 2,17E+00 Co-60 17.6232 1.65E+00 Co-58 9.2332 8.66E-01 Cs-137 4.2322 3.97E-01 Cs-134 3.3872 3.18E-01 Mn-54 1.310Z 1.23E-01 Sb-125 1.2262 1.15E-01 H-3 .864% 8.10E-02 C-14 .7172 6.73E-02 r .242 .000% 0.00E+00 Pu-241 .000% 0.00E+00 I-129 .000% 0.00E+00 Tc-99 .0002 0.00E+00 Sr-90 .000% 0.00E+00 Nb-94 .000% 0.00E+00 Ni-59 .000% 0.00E+00

Enclosure to 110 92-0067 Page 19 of 34

b. Dry compressible waste, contaminated equipment, etc.

none 11uclid e Percent

_Name Abut 1d ance Curles Fe-55 61.4172 2.4<E400 Co-60 24.050! 1.03E400 Hi-63 7.6022 3.27E-01 Hb-9's 1.5561 6.69E-02 Co-58 1.5$4! 6.68E-02 Cs-137 1.4832 6.37E-02 Mn-54 1.3621 5.B5E-02 Cs-134 .9172 3.94E-02 H-3 .0531 2.28E-03 C-14 .007! 2.86E-04 Cm-242 .000% 0.00E400 Pu-241 .0002 0.00E+00 1-129 .0002 0.00E+00 Tc-99 .000% 0.00E400 Sr-90 .000% 0.00E+00 Nb-94 .0001 0.00E400 Hi-50 .000% 0.00E400

c. Irradiated components, conttel rods, etc.

none

d. Other none
3. Solid Vaste Disposition .

)) umber of Shipments Mode of Transportation De p t i na t i on 6 Truck Barnwell, South Carolina B Truck Richland, Washington 4 Class of Solid Waste

n. Class A
b. Class A
c. Not a,iplicable
d. Not applicable
5. Type of Container
a. LSA (Strong, tig'at)
b. LSA (Strong, tight)
c. dot applicable
d. Not applicable i

t Enclosure to NO 92 0067 ,

Page 20 of 34 s

b 6.-Solidification Agent -

a. Not applicable ,
b. Not applicable
c. Not applicable .
d. Not applicable -

B. IRRADIATED FUEL SHIIMENTS (Disposition)

There were no irradiated fuel shipments during this reporting period.

t a

4

...,-e e y -,mwr,.m.~..,.--,,,.c., e--y.,-. , v.__ w nw.7..---e -. , ,w e r . .-,.4.,,. ,_ , - ,, - . .. m..-#4 . . .._w.,, .- -........ , _ - . . . . , . ,~.--.-%. -. - . -. -. - .*_

i Enclosure to NO 92 0067 Page 21 of 34 SECTION III

!!OURS AT EACll WIND SPEED AND DIRECTION All gaseous releases at the Wolf Creek Generating Station are ground level releases. The meteorological data supplied in these tables cover the period l from January 1. 1991, through December 31, 1991, and indicate the number of '

hours at each wind speed and direction for each stability class. l STABILITY CLASS: A ELEVATION: 10 METERS WIND SPEED (!!PH)

WIND DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL N 0 0 0 0 0 0 0 NNE O O O O O O O NE O O O O O O O ENE 0 0 0 0 0 0 0 E O O O O O O O

. EFE O O O O O O O SE O O O O O D 0 SSE. 0 1 3 0 1 0 5 S 0 0 10 5 2 0 17 SSW 0 0 7 14 4 0 25 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 1 1 0 0 2 WN 0 0 O O I 1 2 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O 0....

TOTAL 0 1 22 21 7 0 51 Periods of Calm (lioure): 0 I

i

. - . . _ _ . . . - _ . . _ . . . . , _ _ . . - . , , . _ . . _ , - _ - . . _ - . . , . . ~ , . . , . . . . - . . .

r

- Enclosure to NO 82 0067  :

Page 22 of 34 t

i STABILITY CLASS B ELEVATION: 10 HETERS WIND SPEED (MPH)

WIND DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL l N 0 2 5 7 1 0 15 NNE O 1 1 3 0 0 $ .f NE O O O O O O O ENE O O O O O O 0 E O -0 0 0 0 0 0 t ESE O 1 2 0 0 0 3 SE O 3 1 0 0 0 4 SSE O 7 8 10 0 0 25 S 0 0 61 43 14 2 120 SSW 1 -2 39 39 10 1 92 SW 0 1 7 2 0 0 10 ,

WSW 0 0 4 8 0 0 12 L

-W 0 0 $ 1 0 0 6 WIN 0 0 1 9 5 1 16 IN 0 0 1 1 2 4 8 NIN 0 O 5 10 1 2 18 VARIABLE O O O O O O O TOTAL 1 17 140 133 33 10 334 Periods of Calm (Hours): 0 ,

T L

s

..__._,.......__-..,_..-......,.._,.,.,,.,..1,_, _._....,-...-=-__,,-_,.-...-,,...m,_..,.,,. . - - _ , _ , _ . - _ , - . - - - - _ - . , - ~ , , . . - , -

Enclosure to NO 92 0067 Page 23 of 34 i

STABILITY CLASS: C ELEVATION: 10 METERS  !

WIND SPEED (HPil)  :

WIND DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL N 0 0 1 1 0 0 2 NNE O 1 2 1 0 0 4

{

r HE O O O O O O O i ENE O O 2 0 0 0 2 E O O O O O O O ESE O O O O O O O SE .0 2 1 0 0 0 3 SSE -0 1 4 0 0 0 5 S 0 2 13 11 2 1 29 SSW 0 0 $ 2 2 0 9 SV 0 0 2 3 0 0 5 WSW- 0 0 0 0 1 0 1 V 0 0 0 1 1 0 2 WIN O O 1 5 1 1 8 HW 0 0 2- 1 0 2 5 NNW 0 0 5 3 0 0 8 VARIABT.E O O O O O O O TOTAL 0 6 33 28 7 4 83 Periods of Calm (Hours): 0 ,

i t

I i-(

i.-

l r-.- _ , _ . . .._. . . ~ . , __ . . ~ _ . . . . , _ . . _ . . . , _ , , . , . , , . , , _ . . _ . . _ , _ _ , . . , _ . _ _ , _ _ . _ , . _ _ _ . . . _ , _ _ . , , , _ . , _ _ _ . . _ . . . . . , , _ _

1 Enclosure to NO 92 0067 Page 24 of 34

}

STABILITY CLASS: D ELEVATION: 10 METERS WIND $ PEED (MPH) l VIND DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL N 3 29 67 40 3 1 143 !

NNE 1 29 40 14 3 1 88 i NE 1 25 13 7 0 0 46 ENE 1 8 12 3 1 0 25 E 1 9 31 7 0 0 48 ESE 4 13 37 4 0 0 $8 i SE 1 15 33 2 1 0 52 SSE O 21 89 20 1 2 133 S 1 32 287 124 40 4 488 SSW 3 26 98 37- 9 0 173 SW 2 8 -23 7 4 0 44 WSW 4 12 17 6 5 1 45 W 6 21 23 9 11 0 70 WNW 0 16 34 44 7 1 102 NW 1 6 26 29 6 3 71 NNW 0 17 35 46 17 0 115 VARIABLE O O O O O O O TOTAL 29 287 865 399 108 13 1701 Periods of Calm (Hours): 3 l

l

)

l

Enclosure to NO 92 0067 Page 25 of 34 STABILIT7 CLASS: E ELEVATION: 10 M5lTERS WIND SPEED (MPH)

VIND DIRECTION 13 47 8 12 13 18 19-24 - >24 TOTAL N 25 182 83 2 1 0 293 NNE 29 94 47 3 0 0 173 NE 45 84 12 0 0 0 141 ,

ENE 22 68 24 0 0 0 116  :

E 14 104 59 2 1 0 180 ESE 16 140 43 2 0 0 201 SE 23 100 57 2 0 0 182 SSE 27 205 164 39 6 4 445 c

S 19 313 339 76 15 4 766 SSW 9 164 138 6 1 0 318 .

SW 9 70 23 4 0 0 106 WSW 18 58 24 3 0 0 103 W 12 65 38 1 0 1 117 WIN 13 52 50 11 0 1 127 NW 4 76 75 10 4 0 169 NNW 22 150 90 11 0 0 273 VARIABLE O O O O O O O ,

TOTAL 307 1925 1268 172 28 10 3710 Periods of Calm (Hours):

119 r

+ ..M-=- v -g -+g-m,nawwy.a9we4 g.y,.99.,m.9 upq p y7, .g. g n,,q , , , , 9.,,. q, y,,9 p-__ g 3=mj g%g99..+r.,p. m ,,.qq,g.,y, m9 pe,. ep9 ygppy g. g m. g. w w si q. p yg p .y ,49e 9ipe-~ T

.~.---._.m..._ --

Enclosure to No 92 0067 Page 26 of 34 STABILITY CLASS: F ELEVATION: 10 METERS WIND SPEED (MPH)

WIND DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL N 40 70 9 0 1 0 120 HNE 35 48 2 0 0 0 85 NE 34 19 1 0 0 0 54 ENE 40 42 7 0 0 0 89 E 34 65 11 0 0 0 110 ESE 31 48 3 0 1 0 83 SE 20 50 4 0 0 0 74 SSE $$ 100 24 2 0 0 181 S 48 124 36 1 0 0 209 SSW 21 $9- 10 0 0 0 90 SW 24 17 3 0 0. 0 44 ,

I WSW 28 23 3 1 0 0 55 V 41 29 0 0 0 0 70 WNW 24 12 4 1 0 0 41 NW 18 33 7 0 0 0 $8 NNW 38 45 17 0 0 0 100 VARIt*'a: 0 0 0 0 0 0 0 TOTAL 531 784 141 5 2 0 1463 Periods of Calm (Hours): 18 t

1 .

. _ _ _ . _ - . . . _ . _ . ..._....._.- ~ ..__. , , _ . . __

i

Enclosure to NO 92 0067 Page 27 of 34 STABILITY CLASS: G ELEVATION: 10 METERS VIND SPEED (HPil)

VIND DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL N 22 27 3 0 0 1 $3 NNE 22 21 1 0 0 0 44 NE 14 7 1 0 0 0 22 ENE 2 22 4 0 0 0 28 E 13 27 3 0 0 0 43 ESE 6 13 2 0 0 0 21 SE 15 15 1 0 0- 0 31 SSE 44 32 1 0 0 0 77 S 41 28 1 0 0 0 70 SSW 9 17 1 0 0 0 27 SW 10 3 0 0 0 13 WSW 3 1 0 0 0 0 4 W 11 8 0 0 0 0 19 VNW 14 $ 0 0 0 0 19 NW 12 4 0 0 0 0 16 NNW 25 13 3 0 0 0 41 VARIABLE O O O O O O 0-TOTAL 263 243 21 0 0 1 $28-Periods of Calm (Hours): 9 l

l l

I I

f l

Enclosure to NO 92 0067 Page 28 of 34 il STABILITY CLASS: All ELEVATION: 10 METERS WIND SPEED (llPil)

VIND DIRECTION 13 47 8 12 13 18 19 24 >24 TOTAL N 90 310 168 50 6 2 626 NHE 87 194 93 21 3 1 399 HE 94 135 27 7 0 0 263 ENE - 65 140 51 3 1 0 260 I

E 62 205 104 9 1 0 381

- ESE $7 215 87 6 1 0 366 SE $9 185 97 4 1 0 946 I

SSE 126 367 293 71 8 6 871 I S 109 499 747 260 73 11 1699 SSW 43 268 298 98 26 1 734  ;

SW 45 99 38 16 4 0 222 WSW $3 94 48 18 6 1 220 W 70 123 67 13 12 1 286 WNW $1 85 91 71 13 4 315 NW 35 119 ill 41 12 9 327

, - NNW 85 225 155 70 18 2 555 VARIABLE O O O O O O O TOTAL 1131 3263 2495 758 185 38 7870 Periods of Calm (Hours): 149 Hours of Missing Data 741

, A plant computer changeout occurred in April 1991. The meteorological data could not be retrieved through the new system. The data being presented has been obtained through strip charts from April. December. The high number of .

missing hours has been attributed to the malfunctioning of the strip chart  !

recorders.

l l

A m wy'e$ af t y s*-=w't,+ng+ wi y g a . --ewsyw g g , yt ac 1='e-. phwwsrgg=p,=p mgypw -i-erm4Pmen.y.---wa.e -ww.mwy wwem, - m.e=-a *- ____mm-__w - A-.-- - - - - _ _ - - - - - - - - - --

Enclosure to NO 92-0067 Page 29 of 34 i

SECTION IV Additional Information

1. Unplanned or Abnormal Releases On July 9, 1991, an unplanned release from Waste Gas Decay Tanks 2 and 3 occurred during sampling for a Nuclear Regulatory Commission Radiochemistry Confirmation Measurement cross check. The gas was released inside the Radwaste Buildings however, because Radwaste Building Effluent Monitor GH RE-010B was out-of-service for calibration, the gas discharge was not monitored. Review of the indication on Gas >

Decay Tank Discharge Radioactivity Monitor GH RE-023 and the results of a grab sample, back calculations of gas activity, and ventilation flow rates, revealed that the gas discharged through the vent was well below specified release limits. This event resulted from the use of a poorly designed water trap consisting of a glass vacuum flask with a rubber stopper in the top. When the pressure became too great in the flask, the stopper was dislodged allowing the gas to escape. The water trap has been replaced.

On July 31, 1991, an unplanned release from Waste Gas Decay Tank 5 occurred while placing the "A" Hydrogen Recombiner in service.

Subsequent calculations revealed that the released dose rate was 13.3 percent of the instantaneous release dose rate limit. The leakage was identified as possibly occurring from a relief valve on the gas analyzer rack. When the Waste Gas System is run on recirculation with the rack on standby, a small leak is sometimes present from the relief valve.

This is not the case when the rack is lined up to the system. Actions have been initiated to repair the valve.

On September 26, 1991, a radion tive waste stream had been releasing for 21 minutes when it was discovered that the original dilution flow of 40,000 gallons per minute (gpm) was not available, only 20,000 gpm was available. The release was immediate1v suspended. It was later

' determined that the release, based on the dilution of 20,000 gpm, resulted in a maximum permissible concentration (t:PC) factor of 0.66 which is 66 percent of the limit of 1 MPC.

2. Offsite Do.u calculation Manual (ODCM)

Offsite Dose Calculation Manual. Revision 8, was approved this reporting period by the Plant Safety Review Committee (PSRC) with subsequent Director Plant Operations approval on December 4, 1991. The revision included the deletion of the requirement to obtain tritium grab samples of the ventilation exhaust from the spent fuel pool area. The sample is not necessary because the exhaust goes through the unit vent which- also requires a tritium grab sample but with greater frequency. As required by Technical Specification 6.14, a complete, legible copy of the entire ODCM is provided as Attachment-2.

Enclosure to NO 92 0067 page 30 of 34

,1 Major Changes to Radwaste Treatment Systems The following three changes were identified as being permanent changes which would alter the capacity of handling radioactive wastes or differ in the method of treatment. Therefore, these changes are considered major changes to Radwaste Treatment Systems. The information following each change description is required by ODCH Section 7.2.c which requires a justificution for the change, 10 CFR 50.59 summary, and a comparison of projected effluents and doses prior to and resulting from the change.

I. Updated Safety Analysis Report (USAR) Change Request 91-053 offsite Processing of Dry Wastes This U4AR Change Request provides for the option of collecting dry waste in a vendor's container-(e.g.. 8 foot x 8 foot x 20 foot sea van) with subsequent shipment offsite for processing and (isposal.-

a) Controls are used for the placement of wastes into the container.

performance of radution monitoring around the container, and inspection / surveillance of the container for possible leakage or deterioration. There -is no increase in the probability of occurrence- or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the USAR; there is no possibility -that an accident or malfunction of equipment important to safety of a different type than any evaluated previously in the USAR may.be created: and the margin of safety as defined in the basis for any Technical Specification is not reduced, b) Offsite processing of dry wastes la more efficient than the current practice of compacting dry wastes at Wolf Creek Generating Station (WCGS). The vendor has the capability of reducing waste volume by a factor of about 10 compared to onsite volume reduction by~a factor of approximately 5.

c) .This-option uses a Department of Transportation / Nuclear Regulatory Commission approved radwaste container. ~It is a non-safety related prefabricated steel container, coated 'with anti-rust peint. Two of these containers are stored outside the radwaste building, within the radiation control area, for a residence time from several days to a few months. Once a container is filled it is sealed -and transported to the appropriate offsite processing facility, d) The quantity of solid waste. leaving- the facility remains unchanged, e) Because of the nature of the vaste (dry, low-level contamination),

it represents a negligible radiological hazard, if any. The radiological releases to the environment during normal conditions including-anticipated normal occurrences, are expected to be negligible and within the limits of 10 CFR 20 and 10 CFR 50 Appendix I. No significant effects on air and water quality are expected.

~ _ . _ _ _ _ - . _ . _ . _ . _ . _ - , _ . . . . . . - . . . _ . _ _ . _ . . _ _ . ~ . - . _ _ . - - _ . _ _ .

Enclosure to NO 92-0067

_Page 31 of 34 f) The radiological releases to the environment during r.ormal condtions including anticipated normal occurrences, remain unchanged.

g) Routine operational practices for handling radioactive vaste in accordance with the Wolf Crc enerating Station Health Physics Program and procedures mai~,ain occupational exposures As Low As Ressonably Achievable (ALARA). No change to occupational exposures is expected.

b) USAR Change Request 91-053 (Safety Evaluation 91-0009) was reviewed and approved by the PSRC on August 20, 1991, meeting

  1. 486.

II. USAR' Change Request 90-082 Use of Portable Radwaste Processing Skid A temporary modification for the use of a vendor's portable radwaste

, processing skid was reviewed and approved by the PSRC on September 9. 1987. This temporary modification provided an optional method of processing liquid radwaste through the use of either the originally installed vaste evaporator package or a vendor-provided portable demineralizer skid. Although the portable skid has remained as a temporary modification to the plant configuration. It is intended to 'e a primary schrystem for the processing of liquid radwaste and therefore constitutes a major change to the Liquid Radwaste Treatment System. Because the portable radwaste processing skid has been in use

-since 1987.- the comparisons described hereafter include actual data after the change instead of projections.

I a) The use of this equipment in processing 11guld radwastes does not introduce or create a new release path to the environment.

Pressure integrity of the vendor's equipment maintains and does not_ weaken the pruasure boundary of the plant's permanent liquid radwaste piping systems. Isolation valves exist to isolate the vendors skid from the plants permanent piping.

A rupture of the boron recycle holdup tank, primary evaporators bottoms tank, and the refueling water storage tank is evaluated in the USAR. These evaluations encompass all 'possible accident consequences created by the use of the additional radwaste processing equipment.

The procedure governing liquid radwaste processing with the vendor equipment addresses-valve lineups, operator actions in controlling and monitoring tank levels, pressure drops across filters.- and operation _of pumps._ 'e procedure also addresses actions to be taken if there is a leak detected which includes suspension of processing, isolation of leakage, and utilizing cautions described in the VCGS~ Radiation Protection Manual.

i Enclosure to NO 92 0067 Page 32 of 43 Based on the evaluation completed for this modification There is no increase.in the probability of occurrence or the consequences '

of an accident or malfunction of equipment important to safety previously evaluated in the USAR: there is no possibility that an  ;

accident or malfunction of equipment important to safety of a different type than any evaluated previously in the USAR may be created: and the margin of safety as defined in the basis for any  ;

Technical Specification is not reduced.

b) Use of the portable radwaste processing skid stemmed from a concern over the large volume of solidified evaporator concentrates generated during the initial year of operation of WCGS. The use of portable demineralizers to clean up radwaste streams rather than the use of evaporators was found to be most.

effective in reducing the volume of solid radwaste generated. The solid radwaste from the Liquid Waste Processing System was

  • substantially reduced to 164 cubic feet of spent demineralizer resins per year, this is less than five percent of the waste-volume- of 3450 cubic feet of solidified evaporator concentrates per year prior to the change.

c) This modification consists of flanges installed at the feeder header of the waste evaporator package and one for return to the waste evaporator condensate demineralizer. The vendor-provided demineralizer skid consists of one 60 cubic foot filter tank, four 30 cubic foot demineralizer vessels, one booster pump and associated piping, d) The annual average activity of waste effluent released after the change was determined to be six times the estimated activity in the USAR. . Iron and cobalt. accounted for 70 percent of the activity of effluent after the change while the release in the USAR . estimate is predominated by cesium and iodine, nuclides of serious significance to offsite doses.

e) The radioactive materials in the liquid effluents after the change have not resulted in an increase in the cumulative doses to the individual's whole body and organs (except GI-bLI) at the UNRESTRICTED AREA compared to the previously estimated doses in the USAR, although'the activities of Tritium and nuclides of.

' corrosion and activation' products have increased. The dose-(0.8 mrem /yr) to the GI is 4.7 times ,that of the USAR estimate.

Additionally, the annual dose to the thyroid after the change is only five percent of the USAR estimate while the dose to the whole body and. other organs are 50 percent of the corresponding USAR dose, f) The annual average activity of waste etiluent. released after- the change is only 67 percent of the release activity prior to the change. The cumulative exposure doses after the change are higher than those prior to'the change. However, these doses are still a small percent of the 10 CFR 50, Appendix I limit (i.e. 12 percent ,

of the 3 mrem /yr whole body dose and 1 5 percent of the 10 mrem /yr j organ dose).

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Enclosure to NO 92-0067 Page 33 of 34 g) Exposure to plant operating personnel vent down considerably. For the full year prior to the change, exposures resulting from solidification of the evaporctor bottoms was 1.64 PERSON-REM. The first full year following the change resulting from the use of the 1 Duratek skid was 0.42 PERSON-REM with 0.08 PERSON-REM for each of the years after.

b) USAR Change Request 90-082 (Safety Evaluation 91-0038) was reviewed and approved by the PSRC on September 11 1991, meeting  !

$488. ,

111. Plant Hodification Request (PMR) 03484 Segmented Shield for Dewatering Resins This modification involves segregating different types of resin to i reduce the number of Type 'B' Radioactive Waste shipments and uses a ,

movable segmented shield for radiation protection of personnel during  !

dewatering of spent resins in the shipping casks.

a) In the event of a spill of resin slurring or decant water, existing curbs or temporary barriers will contain the liquid ,

release. Additionally, this change does not affect any equipment important to safety. There is no increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the USAR:

there is no possibility that an accident or malfunction of r equipment important to safety of a different type than any evaluated previously in the USAR may be created: and the margin of i safety as defined in the basis for any Technical Specification is not reduced.

b) Changes to 10 CFR 71 " Transportation and Packaging of Radioactive Material', will result in nearly doubling the number of Type "B' shipments which in turn results in exceeding the storage capacity of Type 'B' waste at Wolf Creek Generating Station (VCGS). The number of Type 'B' shipment can be reduced by segregating Chemical

& Volume control System (CVCS) resins from the less radioactive (Type "A") waste resins. Presently. WCGS's primary resins are made up of two main sources: radwaste liquid processing and the more radioactive CVCS. These two are both sluiced to the spent resin storage tank (SRST) where they decay awaiting shipment.

Segregation into separate storage tanks can result in a substantial cost savings (approximately $445.00 per cubic foot) and would allow WCGS to maintain adequate resin storage capacity.

c) WCGS's current storage capability for primary resin is approximately 292 cubic feet. The segmented shield provides an additional and separate storage location where resin could be sluiced directly. The shield is to be located in the Drum Storage Building. The shield weighs approximately 54,000 pounds.

Equipment used for current devatering operations remains unchanged and is subject to their original requirements.

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g ,.y- - , ,..w-.r,w-, . - . -ey.,..-,.-m.,, . . . . . , .. % ,,_2 . . _ _

_____,m m__.-w-a.._-._.i_.me--,we---.,,-- ,r- .,..-. ,,w.w*

Enclosure to NO 92-0067 Page 34 of 34 d) The quantity of solid waste remains the same, only segregation of the different types of resins is involved, e) Maximum exposures to a member of the public in the UNRESTRICTED AREA and to the general population remains unchanged.

f) The releases of radioactive materials remains the same, only segregation of these materials is involved, g) Use of the segmented shield reduces exposure to plant operating personnel.

h) PMR 3483, Revision 0, (Salety Evaluation 91-0083) was reviewed and approved by the PSRC on October 15, 1991, meeting 1492L.

4. Land Use Census There were no new locations for dose calculations identified during this report period.
5. Radioactive Shipments There were fourteen shipments of radioactive radwaste during this report period. Six shipments were to Barnwell, South Carolina, the remaining eight shipments were to Richland, Washington.
6. Inoperability of Effluent Monitoring Instrumentation There were no events that involved inoperable liquid or gaseous effluent monitoring instrumentation not being corrected within the time specified in ODCM Sections 2.4 or 3.4, respectively.
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.

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ATTACIU4ENT 1 Attachment 1 provides actual values to replace the estimated values for liquid effluente provided in Semlannual Radioactive Effluent Release Report No. 13. New values are denoted by bold face type.

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SECTION I l REPORT OF RADIOACTIVE EFFLUENTS (1991): LIQUID Unit Quarter Quarter 1 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) C1 9.03E-02 7.17E-01
2. Average Diluted Concentration During Period uCi/ml 4.68E-10 3.87E-09
3. Percent of Applicable Limit (1) I 1.81E+00 1.43Ef01 B. Tritium
1. Total Release C1 1.25E+02 3.57E+02
2. Average Diluted Concentration During Period uCi/ml 6.48E-07 1.93E-06
3. Percent of Applicable Limit (2) I 2.16E-02 6.43E-02 C. Dissolved and Entrained Gases
1. Total Release Ci 4.74E-03 8.07E+00
2. Average Diluted Concentration During Period uCi/ml 2.46E-11 4.36E-08
3. Percent of Applicable Limit (3) 2 1.23E 2.18E-02 D. Cross Alpha Radioactivity
1. Total Release Ci 0.00E+00 0.00E+00 E. Volume of waste released (prior to dilution) liters 3.51E+07 5.52E+07 F. Volume of dilution water used liters 1.93E+11 1.85E+11
1. The applicable limit for the Volf Creek Generating Station is 5 Curies per year.

(Reference 10 CFR 50, Appendix I, " Guides On Design Objectives For Light-Vater-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 = (Averane Diluted Concentration) (100)

(MPC, Appendix B. Table II 10CFR20)

3. This value is derived by the following formula:

I of Applicable Limit = (Average Diluted Concentration) (200)

(2E-4 from ODCM Section 2.1)

4. 5.56E-01 of the 7.17E-01 Curies in Quarter 2 are due to Fe-55.

- _ . - ~ _ . . . _ , . -. _ _ -._.-_._

_ _ _ _ . . - - . _ . _ _ _ _ . __ . - _ . _ _ _ _ _ _ . . ___m_ - _ _ . _ _ _ _ _ _ _ . . _ _

l LIQUID EFFLUENTS Continuous Mode latch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1 2 1 2 H-3 Ci 6.51E-02 1.67E-01 1.25E402 3.57E+02 Cr-51 Ci 0.00E+00 0.00E+00 8.59E-05 1.60E-04 Mn-54 Ci <1.73E-02 <2.71E-02 6.41E-04 7.01E-03 3

Fe-55 C1 <3.47E-02 <5.42E-02 7.98E-02 $.56E-01 Fe-59 Ci <1.73E-02 <2.71E-02 <1.90E-04 <5.23E-04 Co-57 Ci 0.00E+00 0.00E+00 5.52E-05 8.03E-04 Co-58 Ci <1.73E-02 <2.71E-02 2.26E-03 1.54E-02 Co-60 Ci <1.73E-02 <2.71E-02 5.07E-03 1.14E-01 2n-65 Ci <1.73E-02 <2.71E-02 <1.90E-04 2.18E-05

$r-89 Ci <1.73E-03 <2.71E-02 <1.90E-05 <5.23E-05 Sr-90 Ci <1.73E-03 <2.71E-02 <1.90E-05 <5.23E-05 Sr-92 Ci 0.00E+00 0.00E+00 1.03E-05 1.01E-04 Hb-95 Ci 0.00E+00 0.00E+00 1.02E-04 8.30E-04 2r-95 Ci 0.00E+00 0.00E+00 4.50E-05 0.00E+00 2r-97 Ci 0.00E400 0.00E+00 0.00E+00 1.90E-05 Mo-99 Ci <1.73E-03 <2.71E-02 <1.90E-04 <5.23E-04 As-110M Ci 0.00E400 0.00E+00 1.40E-04 6.49E-03 Sn-113 Ci 0.00E400 0.00E+00 0.00E+00 9.31E-05

-Sn-117M Ci 0.00E+00 0.00E+00 0.00E+00 1.32E-05 Sb-125 Ci 0.00E400 0.00E+00 1.41E-03 1.50E-02 1-131 Ci <3.47E-02 <5.42E-02 <3.80E-04 <1.05E-03 Cs-134 Ci <1.73E-02 <2.71E-02 2.65E-04 3.76E-04 Cs-137 Ci <1.73E-02 <2.71E-02 3.68E-04 7.82E-04 Ce-141 C1 <1.73E-02 <2.71E-02 <1.90E-04 <5.23E-04 Ce-144 C1 <1.73E-02 <2.71E-02 <1.90E-04 <5.23E-04 Gross Alpha Ci <3.47E-03 <5.42E-03 <3.80E-05 <1.0$E-04 Ar-41 Ci <3.47E-01 <5.42E-01 <3.80E-03 <1.0$E-02 Kr-85M Ci <3.47E-01 <5.42E-01 <3.80E-03 <1.05E-02 Kr-85 Ci <3.47E-01 <5.42E-01 <3.80E-03 6.10E-01 Kr-87 Ci <3.47E-01 <$.42E-01 <3.80E-03 <1.05E-02 Kr-88 Ci <3.47E-01 <5.42E-01 <3.80E-03 <1.0$E-02 Xe-131M Ci <3.47E-01 <5.42E-01 <3.80E-03 9.97E-02 Xe-133M Ci <3.47E-01 <5.42E-01 <3.80E-03 2.28E-02 Xe-133 Ci <3.47E-01 <5.42E-01 4.74E-03 7.33E+00 Xe-135M Ci <3.47E-01 <5.42E-01 <3.80E-03 <1.05E-02 Xe-135 Ci <3.47E-01 <5.42E-01 <3.80E-03 3.38E-05 NOTE: Less than values are calculated using the lower limit of detection (LLD) values listed in Table 2-1 of the ODCH 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.

The Fe-55 and Sr-90 values for the 2nd Quarter are based on the 1st Quarter Composite results. Estimated values for Quarter 2 have now been replaced with actual test l results. Additionally, note change to Sr-90 for Quarter 1 due to vendor results on a retent of sample received af ter Report No.13 was subudtted.

-..w. .w., ,, m ., ,, v. e..r..c.-- -

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LIQUID CUMUI.ATIVE DOSE SUHHARY (1991)

TABLE 1 ODCH CALCULATED ODCM  ! 0F DOS $___ LIMIT LIMIT QUARTER 1 0F 1991 TOTAL DOSE (mrem) FOR BONE 3.33E-03 5.00E+00 6.66E-02 TOTAL DOSE (mrem) FOR LIVER 1.77E-02 5.00E+00 3.54E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 1.61E-02* 1.50E+00 1.07Ef00* ,

TOTAL DOSE (mrem) FOR THYROID 1.27E 02 5.00E+00 2.54E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.42E-02 5.00E+00 2.84E-01 TOTAL DOSE (mrem) FOR LUNG 1.35E-02 5.00E+00 2.70E-01 TOTAL DOSE (mrem) FOR GI-LLI 1.55E-02* 5.00E+00 3.10E-01*

QUARTER 2 0F 1991 TOTAL DOSE (mrem) FOR BONE 7.79E-03 5.00E400 1.56E-01 TOTAL DOSE (mrem) FOR LIVER 3.78E-02 5.00E+00 7.56E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 3.42E-02 1.50E+00 2.2BE100 TOTAL DOSE (mrem) FOR THYROID 2.84E 02 5.00E+00 5.68E-01 TOTAL DOSE (mrem) FOR KIDNEY 3.04E-02 5.00E+00 6.08E-01 TOTAL DOSE (mrem) FOR LUNG 3.07E-02 5.00E+00 6.14E-01 TOTAL DOSE (mrem) FOR GI-LLI 5.07E-02 5.00E+00 1.01Ef00 TOTAL FOR 1991 TOTAL DOSE (mrem) FOR BONE 1.11E-02 1.00E+01 1.11E-01 TOTAL DOS 2 (mrem) FOR LIVER 5.55E-02 1.00E+01 5.55E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 5.03E-02 3.00E+00 1.60E400 TOIAL DOSE (mrem) FOR THYROID 4.11E-02 1.00E+01 4.11E-01 TOTAL DOSE (mrem) FOR KIDNEY 4.46E 02 1.00E+01 4.46E-01 TOTAL DOSE (mrem) FOR LUNG 4.42E-02 1.00E+01 4.42E-01 TOT /.L DOSE (mrem) FOR GI-LLI 6.62E-02 1.00Ef01 6.62E-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 equal to 5 mrem per quarter and 10 mrem per year.

  • There were no significant changes to these values and are therefore reported the same as the values in Report 13.

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LIQUID CilHULATIVE DOSE SIM ARY (1991)

TABLE 2 A. Fission and Activation Products Quarter 1 Quarter 2 Total

!_ (not including 11-3.

gases, alpha)

1. Total Release - (C1) 9.03E 02 7.17E-01 8.07E-01 >
2. Maximum Organ Dose (mrem) 5.00E-03 2.23E-02 2.73E-02
3. Organ Dose Limit (mrem) 5. 00E4 00 5.00E+00 1.00E+01 4 Percent of Limit 1.00E-01 4.46E-01 2.73E-01 B. Tritium
1. Total Release (C1) 1. 2 5E4 02 3.57E+02 4.82E+02
2. Maximum Organ Dose (mrem) 1.27E-02 2.04E-02 4.11E-02
3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 1.00E401
4. Percent of Limit 2.54E-01 5.68E-01 4.11E-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. ODCH Section 2.2 organ dose limits are used NOTE: The 2nd Quarter Category A values were calculated based on the Quarter 1 Fe-55 and Sr-90 concentrations. Estimated values for Quarter 2 have now been replaced with actual test results.

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