ML20085C204

Semiannual Radioactive Effluent Release Rept 13,Jan-June 1991

ML20085C204
Person / Time
Site:	Wolf Creek
Issue date:	06/30/1991
From:	Mike Williams WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20085C203	List: ML20085C199 ML20085C204 ML20085C208
References
NUDOCS 9109030183
Download: ML20085C204 (26)

Text

MLF CREEK NUCLFAR OPERATIIG CCRPORATION Nolf Creek Generating Station Docket No: 50-482 Facility Operating Li N e Not l@F-42 SFMINNUAL RADIOPCPIVE EFFIDENP RELFASE REIMP Report No: 13 Reporting Pericxt: January 1, 1991 thru gh June 30, 1991 Prepared by: Merlin G. Williams Approved by: ._ /

' D.'~D.'Bdy6r Director Plant Operations 9109030183 9108'27 PDR ADOCK 05000482 R PDR

'nible of Contiritas Pace Executive Sunnary i Section I Liquid Radimetive Effluents 1 Dose Sunnary 3 Aiatorne Radioactive Effluents 5 Dose Sunnary 7 Section II Offsite Dose Calculation Mcmual Limits 9 Maximum Ibanissible Concentrations 10 Noasuments and Approximations of 'Ibtal Radioactivity 11 Batch Releases 13 Conti.nuous Releases 13 Solid Waste Shipemts 14 Irradiated Fuel Shipnents 15 Section III Unplanned or Abnornal Relmses 16 Offsite Dose Calculation Manual 16 Major Changes to Liquid, Gaseous or Solid Radwaste Syst ms 16 Iand Use Census 17 Hadioactive Ship mnts 17 Inoperability of Airborne Effluent Monitoring Instrumentation 17 Storage Tanks 17 Liquid Effluent Changes to Report 12 Offsite Dose Calculation Manual

JgICTPIVE RMERY mo purpose of the Santiannual Radioactive Effluent Release Report is to report on the quantities of liquid and gaseous effluents and solid waste released frmt R>lf Creek Generating Station (WCGS). This report covers the period beginning on January 1, 1991, and ending on June 30, 1991.

Section I pmvides a sunnary of the quantities of radioactive liquid and gaseous effluents for this reporting period. The fornet is similar to that recmuended in Regulatory Guide 1.21, Revision 1. An elevatal release pathway does not exist at Nolf Creek Generating Station, therefore, all airborne releases are considered to be grourci level releases. 7ho concurrent meteorological condition gaseous pathway dose detarmination is net by the Walf Creek Offsite Ibse Calculation Manual nethetlogy of assigning all gaseous pathways to a hypothetical individual residing at the highest annual X/O and D/Q location. This Insults in a conservative ,

estimate of dose to a nunber of the public rather than detennining each pathway dose for each mloase condition. A conservative error of thirty percent has boon estimted in effluent data. Heteorological data for the period of January 1, 1991 through June 30, 1991, is available onsite for review and inspection.

Sections II and III provide additional infornation required by tar ulatry Guide 1.21, Revision 1 and 7bchnical Specification 6.9.1.7, reyn:tivM7 provides actual values to replace the estinated values for liquid effluents provided in Serniannual Radioactive Effluent Release Report

12. Analysis results for the Fourth Quarter of Report 12 were not empleted prior to subnisalon of the report. Actual results of Quarter 4 liquid effluents indicated the presence of Fe-55 in the liquid batch couposite.

The change decreases the total curies released and decreases the cumulative dose. Because analysis results for the Second Quarter of 1991 have not yet been cmpleted, Fe-55 activity and doses in liquid effluents is presented as an estinate.

Offsite Dose Calculation Manual (ODCH), Revision 7 was approved by the Plant Safety Review Cm mittee during this reporting period. This revision includes a relocation of the Radiological Effluent 7bchnical Specifications to the ODCM. Limits prwiously referred to as ibchnical Specification Limits in this report are now referred to as ODCM Limits. Actual values of these limits rmain unchanged. A cmplete copy of the ODCM is included as of this report.

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SECTION I REPORT OF RADI0 ACTIVE EFFLUENTS (1991): LIQUID Unit Quarter Quarter 1 2 A. Fission and Activation Products

1. Total Release (not including tritium, gasos, alpha) Ci 9.03E-02 3.81E-01'

2. Average Diluted Concentration During Period uCi/ml 4.68E-10 2.06E-09

3. Percent of Applicable Limit (1) 2 1.81E+00 7.62E+00 B. Tritium

1. Total Release Ci 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 A. 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-05 2.18E-02 D. _0ross 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. LVolume of dilution water used liters 1.93E+11 1.85E+11

- 1. The applicable limit for the Wolf Creek Generating Station is 5 Curles 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:

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

(MPC, Appendix B, Table II 10CFR20)

3. This value is ve,t ived by the following formula:

Z-of Applicabir Limit - (Aver?ge Diluted Concentration) (100)

(2E-4 from ODCM Section 2.1)

4. 2.20E-01 of the 3.81E-01 Curies in Quarter 2 are due to Fe-55 estimated from the Quarter 1 Composite results.

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LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit. 1 2 1 1 H-3 Ci 6.51E-02 1.67E-01 1.25E+02 3.57Et02 Cr-51 Ci 0.00E400 0.00E+00 8.59E-05 1.60E-04 Mn-54 Cl <1.73E-02 <2.71E-02 6.41E-04 7.01E-03 Fe-55 Ci <3.47E-02 <5.42E-02 7.98E-02 2.20E-01 Fe-59 Ci <1.73E-02 < 2 .1'1 E - 0 2 <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 Sr-89 Ci <1.73E-03 <2.71E-02 <1.90E-05 <5.23E-05 Sr-90 Ci <1.73E-03 <2.71E-02 3.46E-06 9.55E-06 Sr-92 Ci 0.00E400 0.00E+00 1.03E-05 1.01E-04 Nb-95 Ci 0.00E+00 0.00Et00 1.02E-04 8.30E-04 2r-95 Ci 0.00E+00 0.00E+00 4.50E-05 0.00E+00 2r-97 Ci 0.00Et00 0.00E+00 0.00E+00 1.90E-05 Mo-99 Ci <1.73E-03 <2.71E-02 <1.90E-04 <5.23E-04 Ag-110M Ci 0.00E+00 0.00E+00 1.40E-04 6.49E-03 Sn-113 Ci 0.00E+00 0.00Et00 0.00E+00 9.31E-05 Sn-117M Ci 0.00E+00 0.00E+00 0.00E+00 1.32E-05 Sb-125 Ci 0.00E+00 0.00E+00 1.41E-03 1.50E-02 I-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 Ci <1.73E-02 <2.71E-02 <1.90E-04 <5.23E-04 Ce-144 Ci <1.73E-02 <2.71E-02 <1.90E-04 <5.23E-04 Gross Alpha Ci <3.47E-03 <5.42E-03 <3.80E-05 <1.05E-04

Ar-41 Ci <3.47E-01 <5.42E-01 <3.80E-03 <1.05E-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 <5.42E-01 <3.80E-03 <1.05E-02 Kr-88 Ci <3.47E-01 <5.42E-01 <3.80E-03 <1.05E-02 Xe-131M Ci <3.47E-01 <5.42E-01 <3.80E-03 9.97E-02 l X9-133M C1 <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 I Xe-135 Ci <3.47E-01 <5.42E-01 <3.80E-03 3.38E-05 l

I NOTE: Less than values are calculated using the lower limit of detection (LLD)

-values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for the total release values.

The Fe-55 and Sr-90 values for the 2nd Quarter are based on the 1st Quarter Composite results.

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LIQUID CUMULATIVE DOSE EUlfMARY (1991)

. TABI.E 1 ODCM CALCULATED ODCM 2 0F DOSE ___ LIMIT LIM 11

QUARTER 10F 1991 TOTAL DOSE (mrem) FOR' BONE 3.3BE-03 5.00E+00 6.76E-02 TOTAL Dose (mrem) FOR LIVER 1.77E-02 5.00E+00 3.54E-01

,;-_70TAL DOSE (mrem) FOR TOTAL BODY 1.61E-02 -.50E+00 1.07E+00 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 '

TorAL DOSE (mrem) FOR GI-LLI 1.55E-02 5.00E+00 3.10E-01 QUARTER 2 0F 1991 .

TOTAL DOSE (mrem) FOR BCNE 5.31E-03 5.00E+00 1.06E-01 TOTAL DOSE (mrem) FOR LIVER 3.60E-02 5.00E+00 7.20E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 3.38E-02 1.50E+00 2.25E+00 TOTAL DOSE (mram) FOR THYROID 2.84E-02 5.00F+00 5.68E-01 TOTAL DOSE (mrem) FOR KIDNEY 3.04E-02 5.00E+00 6.08E-01 TOTAL DOSE (mrem) FOR LUNG 2.97E-02 5.00Et00 5.94E-01 TOTAL DOSE (mrem) FOR GI-LLI 4.97E-02 5.00E400 9.94E-01

-TOTAL FOR 1991 TOTAL DOSE (mrem) FOR BONE 8.69E-03 1.00E+0i 8.698-02 i TOTAL DOSE (mrem) FOR LIVER 5.37E-02 1.00E+01 5.37E-01 ,

TOTAL DOSE (mrem) FOR TOTAL BODY 4.99E-02 3.00E+00 1.66E+00 ;

-TOTAL DOSE (mrem) FOR THYROID 4.11E-02 1.00E+01 4.11E-01 TOTAL DOSE (mrem) FOR KIDNEY 4.46E-02 1.00E401 4.46E-01 TOTAL DOSE (mrem) FOR LUNG 4.32E-02 1,00E+C7 4.32E-01 TOTAL DOSE-(mrem) FOR GI-LLI 6.52E-02 1,00E+01 6.52E-01 Based on ODCM Section 2.2 which' restricts dose to the whole body " less than or equel to 1.5 mrem per quarter and 3.0 mrem ner year. Do.- ::PH etion to organ is less thare or +

equal ta 5 mrem per quarter and 10 mrem per year.

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LIQUID CUMULATIVE DOSE SUMHARY (1991)

TABLE 2

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

1. Total Release - (C1) 9.03E-02 3.81E-01 4.71E-01 2, Maximum Organ Dose (mrem) 5.00E-03 2.13E-02 2.63E-02

3. Organ Dose Limit (mrem) 5.00E+00 5.00E400 1.00E+01

-4. Percent of Limit 1.00E-01 4.26E-01 2.63E-01

.B. Tritium

1. Total Release (C1) 1.25E+02 3.57E+02 4.82E+02

2. Maximum Organ Dose (mrem) 1.27E-02 2.84E-02 4.11E-02 3, Orgaa Dose Limit (mrem) 5.00E+00 5.00E+00 1.00E+01

4. Percent of Limit 2.54E-01 5.6BE-01 4.11E-01 This table is in:1uded to show the correlation between Curies released ano the associated esiculated 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.

NOTE: The 2nd Quarter Category A values were calculated based on the Quarter 1 Fe-55 and Sr-90 concentrations.

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REPORT OF RADIOACTIVE EFFLUENTS (1991): AIRBORNE Quarter Quarter Unit 1 2 A. Fission and Activation Gases

1. Total Release Ci 5.36E+01 4.21E+02

2. Average Release Rate for Period uC1/sec 9.12E+00 5.86E+01

3. Percent of ODCM Limit (1) 2 7.10E-02 3.16E-01 B. Iodines

1. Total Iodine-131 C1 0.000+00 2.25E-06

2. Average Release Rate for Period uCi/sec 0.000+00 2.86E-07

3. Percent of Applicable Limit (2) 2 0.000+00 .2.25E-04 C. Particulates

1. . Particulates with Half-lives > 8 days Ci 4.12E-07 2.77E-06

2. Average Release Rate for Period uC1/sec 5.24E-08 3.52E-07

13. Percent of ODCM Limit (3) Z 1.51E-04 2.20E-03

4. Gross Alpha Radioactivity Ci 6.11E-08 1.65E-08 D. Tritium

1. Total Release Ci 4.12E+00 3.36E+00

2. Average Release Rate for Period uCi/sec 6.44E-01 1.20E+00

3. Percent of ODCM Limit (4)  % 3.91E-02 3.20E-02

-1. The percent of ODCM limit for fission and activation gases is calculated using the following msthodology:

2 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.

2. The percent of ODCM limit for lodine is calculated using the following methodology:

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

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

I of ODCM Limit = (Hinhest Organ Dose Due to Particulates)(100) 7.5 mrem

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

I of ODQi Limit = (Highest Organ Dose Due to H-3)(100)

, 7.5 mrem

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

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GASEOUS EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1 2 1 2

1. Pission and Activation Gases Ar-41 C1 1.37E+00 0.00E+00 2. 00E4 00 1,64E-01 Kr-85 Ci 0.00E400 0.00E+00 1.72E-02 0.00E+00 Kr-85M Ci 0.00E+00 2.84E-01 0.00E+00 0.00E+0C Kr-8' Ci <1.57E+01 <1.53E+01 <1.19E-01 <1.04E-02 Kr-88 Ci <1.37E+01 <1.33E+01 1.04E-01 (9.12E-03 Xe-131M Ci 0.00E+00 4.06E+00 0.00E+00 3.90E-03  :

Xe-133 Ci 4.86E+01 4.06E+02 3.66E-01 6.71E-01 Xe-133M Ci <4.26E+01 ( 56E+00 <3.22E-01 1.14E-03 Xe-135 Ci 1.21E+00 5.34E+00 <3.24E-02 3.94E-03 Xe-138 Ci <4.18E+01 <4.07E+01 <3.16E-01 <2.78E-02 Total Ci 5.12E+01 4.20E+02 2.38E+00 '8.44E-01

2. Halogens (Gaseous)

I-131 C1 <2.66E-04 2.25E-06 <2.01E-06 <1.77E-07 I-133 Ci <2.66E-02 <2.59E-02 <2.01E-04 <1.77E-05 Total Ci 0.00E+00 2.25E-06 0.00E+00 0.00E+00

3. Particulates and Tritium H-3 C1 3.97E+00 3.23E+00 1.50E-01 1.28E-01

, Mn-54 Ci <2.66E-03 <2.59E-03 <2.01E-05 <1.77E-06 j Fe-59 Ci <2.66E-03 <2.59E-03 <2.01E-05 <1.77E-06

_Co-58 Ci <2.66E-03 <2.59E-03 <2.01E-05 <1.7'E-06

Co-60 Ci <2.66E-03 <2.59E-03 <2.01E-05 <1.77E-06 Zn-65 Ci <2.65E-03 <2.59E-03 . <2.01E-05 <1.77E-06 4

Mo-99 Ci <2.66E-03 <2.59E-03 <2.01E-05 <1.77E-06 Cs-134 Ci <2.66E-03 <2.59E-03 <2.01E-05 <1.77E-06 Cs-137 Ci <2.66E-03 1.26E-06 <2.01E-05 <1.77E-06 Ce-141 Ci <2.66E-03 <2.59E-03 <2.01E-05 <1.77E-06 Ce-144 Ci <2.66E-03 <2.59E-03 <2.01E-05 <1.77F-06 Sr-89 Ci 3.51E-07 1.51E-06 <2.01E-05 <1.77E-06 Sr-90 Ci <2.6$E-03 <2.59E-03 <2.01E-05 <1.77E-06 Gross Alpha Ci 6.11E-08 1.65E-08 <2.01E-05 <1.77E-06

Total Ci 3.97E+00 3.23E+00 1.50E-01 1.28E-01 4

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.

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CASEOUS CtHlTI.ATIVE DOSE SIDMARY (3 ' 4)

Table 1 3

I ODCM CALCULATED 0101  ! 0F l QUARTER 1 OF 1991 DOBE LIMIT .b!MIT TOTAL Df*E (mrem) POR BONE 1.1*V-05 1.50E400 1.51E 04 '

T OT AL. '. /E (mrem) FOR LIVER E.916. 03 7.50E400 3.91E-02 TOTAL eSE (mrem) FOR TOTAL BODY 2.93E-03 7.50E+00 3.91E ',2 TOTAL 'OSE (mrem) FOR THYROID " 03E-03

. 7.50E+00 1.91E 02 TOTAL DOSE (mrem) FOR KIDNEY 2.93E-03 7.50E+00 3.91E-02  :

TOTAL DOSE (mrem) FOR LUNG 2,93E-03 7.50E+00 3.91E 02 TOTAL DOSE (mrem) POR GI-LLI i 93E-03 7.50E400 3.91E-02 ,

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QUARTER 2 0F 3991 '

?OTAL DO$E (mrem) FOR BONE  :.09E-04 7.50E400 2.25E-03 TOTAL DODE (mrem) FOR LIVFD 2.51E-03 1.50E400 3.35E-02 l TOTAL DOSE (mrem) FOR TOTAL BODY . 42E-03 7.50E400 3.23E-02  !

TOTAL DOSE'(mrem) POR Tl!YROID 3.69E-03 7.50E+00 4.92E-02  !

TOTAL DOSE (mrom) POR KIDNEY 2244E-03 7.50E400 3.25E-02  :

TOTAL D0fE (mrem) POR LUNG 2.41E-03 7.50E400 3.21E 02 l TOTAL DOSE (mrem) FOR GI-LLI 2.40E-03 7.50E400 3.20E-02 TOTALS FOR 1991 TOTAL D0bE (mrem) FOR BONE 1.00?.-04 1.50E+01 1.20E 03 ,

TOTAL DOSE (mrem) FOR LIVER 5.44E-03 1.50E401 3.63E-02  :

TOTAL DGSE (mrem) FOR T01AL BODY 5.35E-03 1.50E+01 3.57E-02 l TOTAL DOSE (mrom) FOR T!!YROID 6.62E-03 1.50E+01 4.41E-02 l TOTAL DOSE (mrem) POR KIDNEY 5.37E-03 1.50E+01 3.58E-02 i TOTAL DOSE (mrom) POR LUNO 5.34E-03 1.50E401 3.56E 02 '

TOTAL DOSE (mrom) FOR GI-LLI 5.33E 03 1.50E401 3 ' N-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 mram to any organ and during any calender year to less than or ,

equal to 15 mrem to any organ.

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GASEOLIS CUHilLATIVE DOSE SilHMARY (1991)

TABLE 2 Iluclides Released Quart er 1 Quarter 2 To a1 A. Fission and Activation Gases

1. Total Release (C1) 5.36E401 4.21E402 4.75E+02

2. Total Gamma Airdose (mrad) 3.55E-03 1.10E-02 1.46E-02

3. Gamma Airdose Limit (mrad) 5.00E+00 5 00E400 1.00E401

4. Percent of Oamma Airdose Limit 7.10E-02 2.20E-01 1.46E 01

5. Total Beta Airdose (mrad) 4.57E-03 3.16E-02 3.62E-02

6. Beta Airdose Limit (mrad) 1.00E401 1.00E401 2.00E401

7. Percent of Beta Airdose Limit (mrad) 4.57E 02 3.16E 01 1.81E 03 B. Particulater.

1. Total Particulates (C1) 4.12E-07 2.77E-06 3.18E-06

2. Maximum Organ Dose (mrem) 1.13E-05 1.65E-04 1.76E 04

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

4. Percent of Limit 1.51E 04 2.20E-03 1.17E-03 C. Tritium

1. Total Release (C1) 4.12 E4 00 3.36E+00 7.48E+00

2. Maximum Organ Dose (mrem) 2.93E-03 2.40E-03 5.33E-03

3. Organ Done Limit (mrem) 7. bOE4 00 7.50E+00 1.50E401

4. Percent of Limit 3.91E-02 3.20E-02 3.55E-02 D. lodine

1. Total 1-131. I-133 (C1) 0.00E400 2.25E-06 2.25E-06

2. Maximum Organ Dose (mrem) 0.00E400 1.29E-03 1.29E-03

3. Organ Dose Limit (mrem) 7.50E400 7.50E400 1.50E401 -

4. Percent of Limit 0.00E400 1.72E-02 8.60E-03 This table is incluced to show the correlation between Curies released and the associated calculated naximum organ dose. The maximum organ dose is calculated using Wolf Creek ODCM methodology which assumes that an individuni actually resides at the release point. ODCM Section 3.2.2 organ dose limits are used.

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IDC1'KH 11 lhi[plonantal Infunnitite Facility: } elf CmA Gonorntina StatioD Licenso Nunborn NPF-42

1. 0004 Limits A. For liquid kosto offluents A.1 'Iho concentration of radioactivo mitorial rolossod in liquid offluonts to U!RPSIllICTID AREAS shall be limitrd to the concentrations specificd in 10Cnt20, Apparxiix B, 7hblo II, Column 2, for radionuclidos other tJan dissolvod or entrainod noblo gasos. For dissolved or on shall bo limited to 2 x 10~grainod noblo gases, microCurlo/mi totalthe concentration activity.

A.2 Tho doso or doso ommitront to a MIEB121 OP 11tE PUllLIC ima radioactivo mstorials in liquid offluents roloasod, fmn cach unit, to (MtFSI1tICITD ARIE shall be limited:

a. During any calentar quarter to loss than or equal to 1.5 mrms to tho wholo inty arri to lesa Omn or cqual to 5 mmus to any organ, and

b. During any calendar year to loss tJan or oqual to 3 mmus to the wholo body and to less tJan or oqual to 10 mmas to any organ.

B. Ibr gaseous wasto offluonts B.1 Uho doso rato due to radioactive m*ttorials rolossed in gasoous offluents fmn the site to areas at and lxtyond the SITE DOUfMY shall be liraited to the folicwings

a. Ibr noble gasos: less tJan or equal to 500 mmns/yr to the whole txxty and less than or equal to 3000 mmas/yr to the ckin, arxi

b. For Iodino-131, Icdino-133, tritiun, and all radionuclidos in particulato form with half-lives greator than 8 days:

Inss than or equal to 1500 mmns/yr to any organ.

B.2 1ho air doso due to noble gases released in gasoons offluents, imn each unit, to areas at and beyond the SITE lY.XJNDMtY shall bo limited to the follcuings

a. During any calendar quarter: Insa than or equal to 5 mrads for ganms radiation and loss than or oqual to 10 mrada for tota radiation, and

b. During any calendar years Less than or cqual to 10 mrada for gannu radiation and less than or equal to 20 mrads for I; eta radiation.

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H.3 'iho dose fma Icdino-131, Iodine-133, tritium, arx! all radionuclidea in pirticulato fonn with half-lives gmster tJan 0 days in gamous offluents ruleasal to arms at arx1 tcyarvi the SITE InlimtY ehall to limited to the folicwings

a. Daring any calorriar quarter Inan than or winal to 7.5 mmta to any organ, arxi

b. During any calorriar yoar: Insa than or equal to 15 mrtun to any organ.

2. Maxinun Parmissiblo Concentratiana Wator - covered in Soction 1.A.

Air - covered in Section 1.B.

3. Averago anorgy of fission and activation gancous offluents is not applicable.

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4. Myisunnmts and lypnwimsticns of 7btal Itadioactivity A. Liquid Effluonts LIQUID R111%SB SAMPLI!U F.UMW OF SYPE OF /CI'1VITY TYPE 1RIUJDCY ANALYSIS ANALYSIS

1. lutch Wasto P.ll. A. Principal Gwin Release P ,__ D1Tnit.grn

'Ihnks Each lutdi P.ll. A. I-131

a. Wastn Monitor P Dissolvai arxi Tank Ono Ibtch/M P.ll. A. Entraincxl Gases (G3ntin Dnttters)

b. Socondary Liquid P L.S. 11- 3 wasta P22ch Ibtch Monitor S.A.C. _ Grosn Alrha Tank P O.S.L. Sr-89, Sr-90 Pach lutch 0.S.L. Fo-55

2. Continous P.l!. A. Principal Gwin Italoases thily Dnitturs Grab Sanplo P ll.A. 1-131

a. Steam M Dissolved and '

Generator Grab Sanple P .lf. A. Ihtrained Gases Blowdown _1G_ win Dnitters)

b. Turbino Ibily L4  !!-3 Duilding Grab Fanplo Sunp S.A.C. ._ _ Groan Alrha c . 1_im thily O.S.L. Sr-89, Sr-90 Sludge Grab Sanplo Pond Q1.L. Fe-55 P = prior to each hatch S.A.C. = scintillation alpha counter M = nonthly O.S.L. = rerfourrxl by an offsito laboratory L. S. = liquid scintillatian P.ll.A. = ganna spectnut pulso height analysis using a liigh Purity Germsnium detector.

Page 11 l

D. Cascous Wasto EffIuents SAMPLIIG M1311C D O F TYPE OF GASIDUS, R12 EASE TYPE FRII,U12CY N &lNSIS /CTIVITY ANALYSIS P

Each Tank P.ll. A. Principal Gsnma Wasto Gas Docay Tank Grab Sanplo thitters P Principal Ganni Containmnt Purgo or Each Punjo P.ll. A. ,_thitters Vent Orab Sanple Gas IAlbbler

_ . . , nnri L.S. 11-3 foxide)

Principal Ganna linit Vent .V P.ll. A. thitters

}&clSanple Gas Dubbler

,_ ,,,, and L.S. ,

FI-3 foxido)

Radwesto Duiluing M P.11. A. Principal Gannn Vent Grab Samlo lhtttr=ra Ibr linit Vent and I-131 Radwasto Duilding Cantinuous P.ll. A.

Vent release types 1-133 listed above. P.II.A.

Continuous Particulato Principal Ganms Samle Dnitters S.A.C.

Continuous Particulate Gross Alpha Conrosito Samle 0.S.L.

Ccuposite Sr-89, Sr-90 Continuous Particulato Samle Page 12

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S. Batch Iteleases  !

t 7 hem were 47 gaseous batch mioases during the mporting period. l The longest gaseous hitch relmso lasted 2,804 minutes, while the  !

shortest lastcd 90 minutes. 7he average ruloaso lastcx1475 minutos i with a total gaseous hstch release tim of 22,329 minutes.

r 3heru wuru 30 liquid batch ruloases during the reporting period. I sha longest 11guld batch release lasted 359 minutos, while the '

shortest lasted 46 minutos. The averago relonso lasted 104 minutos with a total liquid batch ruloaso tirn of 3,105 minutes.

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6. Cantinuous Italossos t i

7here were tw liquid releaso patheys designated as continuous j releases during this reporting period. They aru the Lirn Sitrige i Pand and 7brbino Building Sump. 'Ihcre worn tw gas releaso patliwayn ,

designated as continuous releases. 7hese aru the Unit Vent and  !

Itadeste Building Vent. l t

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_a . . _ _ _ __ ._.- ._. 1 __ - __ ,_ . _ _ - . _

ITFIllFNP NO Writ DIf110E SIMIMtKE R130ff (1991)

(KIJD Writ 12tilMlW1U A. SOLID WASTE SIIIPPED GTSITE 64bntli ITE Est.1RRIAL

'Ibtal Ut DISPO Unit Error %

1. Tyre of wasta Pericd m3* 2.25E401

a. Spent resins, f11 tor cludges, 4.00E402 2.50E+01 C1 evaporator bottcus, etc. m3+ 0.00E400

b. Dry ocupmssiblo wasta, 0.00E400 2.50E401 Ci cont 2uninat<xi equip. etc. m3+ 0.00E+00

c. Irradiated ccqnnents, Ci 0.00E4 00 0.00E400 contm1 rxis, etc. m3* 0.00E+00

d. Other 0.00E+00 0.00E+00 Ci m3* = cubic notors

2. Estianto of najor nuclide etqosition (by type of wasto)

a. Spent resins, filtnr sludgos, warcrator bottarn, otr.

Iwrcont Naclido Ahirrinnm pttrieli ikmn_ l 31.994% 1.20E+02 I Fo-55 9.56E+01 23.904%

N1-63 17.290% 6.91E+01 Co-60 0.306% 3.32E401 Cs-137 7.889% 3.15E+01 Co-50 6.947% 2. 78E+01 Cs-134 1.962% 7.84E+00 Mn-54 .709% 3.15E+00 C-34 .758% 3.03E+00 Stw125 .009% 3.55E-01 Zr-95 .031% 1.23E-01 Mb-95 .028% 1.11E-01 Zn-65 .009% 3.56E-02 11- 3

.004% 1.62E-02 Sr-90 .000% 8.96E-04 lb-7 .000% 3.87E-05 Ore-243/244 2.21E-05

.000%

Pu-239/240 .000% 9.92E-06 Pu-230 .000% 7.98E-06 Am-241

b. Dry ccupressible wasto, .ontaminated equirnent, etc.

none

c. Irradiatal ccqonants, control mis, etc.

none

d. Ot)xw nano Page 14 I

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3. Solid Wasto Disposition ibninr of Shirnents }trie of Transportation restinatioD 5 Truck Darnwell, South Carolina ,

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4. Class of Solid Wasto t I

a. Class A, Class 11

b. !bt applicable .

c. Ibt applicablo  !

d. Ibt applicablo ,

4

5. Type of Container  ;

a. ISA (Strong, tight)  :

b. Ibt applicable '

c. Ibt applicablo

d. Ibt applicablo

6. Solidifica+.lon Agent ,,

a. Ibt applicablo l

b. Ibt applicable l

c. Ibt applicable -

d. tbt applicable l B. IRRADIATED FUEL SilIPMDTTS (Disposition) ,

'1here waro no irradiated fuel shipnants during this reporting period. I i

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SICMCW III Additicral Infonmation

1. Unplanned or Abnonal Releases on January 1, 1991, a pressure drop of 6.4 psig in Waste Gas bocay Tank (m) #8 was identified at 1000 CST. mis release did not exaced Technical Specification limits. _ However, this situation ecnstituted a violation of Technical Specification 3.11.2.1, which requiral, in part, sanpling of a WGUr prior to its release. W e investigation by-Mechanical Maintenance pomel revealed that leakage had occurrod on the Catalytic Hydrogen Recombiner SHA01A rupturn disc.

Wis event resulted fra a snall misalignment between the faces of the disc f.lange. Although the misalignment rumined within specifications, it could still create a tear in the rupture disc. Decause there had not been any configuration work on this disc since initial installation, it appeared that this misalignment had been present since initial installation of the Waste Gas Systan. We rupture disc was replaced using enhanced techniques to avoid tearing the disc. 20 work instructions for rupture disc replacement have been changed to include a note of attention to the alignnent problan. We instructions include an enhanced technique to carefully install the disc without tearing it.

W ie event was reported in Licensee Event Report 482/91-001-01.

2. Offsite Dose _ Calculation Manual (ODCM)

Offsite Dose Calculation Manual, Revision 7, was approved this reporting period by the Plant Shfety Review Ccmmittee on March 21, 1991. We ODCM was revised la accordance with the guidance provided in Nuclear Regulatory Ccmnission Generic Letter 89-01. Generic letter 89-01, "Impleantation of Progranmatic Controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Ocntrols Section of the Technical Specifications and the Relocation of' Procedural Details of R US to the Offsite Dose Calculation Manual or to the Process Control-Program", provided, in part, guidance on the relocation of gucudural details, previously contained in the RETS, to tho ODCM. A cmplete copy of the entire CDCM is provided in Attachnent 2.

3. Major Changes to Radweste Treatnent Systans A tatporary nodification for the use of a vendor's portable radweste processing skid was reviewed and approved by the Plant Safety Rev1w Ccmmittee on Septmber 9,1987. Wis tmporary modification provides an optional nethod of processing liquid radweste through the use of either the originally installed waste evaporator package or a portable

- denineralizer skid. Althouah the portable skid r m ains as a t m porary modification to the plant configuration,-it is intended to be a primary l

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subsystun for the processing of 11guld radwasto ard therefom constitutes a nnjor change to the Liquid Radwnsto Treatment Systan.

Applicable adapters arxl mlatal equipent havo lxxtn pentanently installed and the use of the partable skid is currently ining incorporata3 into the Updatal Safety Analysis Relort (USAR). 'lhe analyses ruquired under the guidelines for this report am being finalized in conjunction with this pmcess of incorporation into the USAR. A ompleto discussion of this nodification will bo includod in the next subnittal of this rqort.

4. Iand Uso Census there mm no noa locations for dono calculations identiflod during this report period.

5. Radioactivo Shipants Uhem wra five shipents of radioactivo reidwusto durjag this rquit period. All five shipents wro to turnwall, South Carolina.

6. Inoperability of Effluent Monitoring Instnamtation them weru no events that involved inoperable liquid or gaseous effluent nonitoring instrununtation not being cormcted within the tinn sprifial in Ubchnical 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 excoading the limits of Technical Specifications 3.11.1.4 or 3.11.2.6.

Page 17

i ATIACIMINr 1 i

Attaciment 1 provides actual values to replaco the estinnted values for ,

lirpid offluents provided in Sami2innual Radioactive I:ffluont Ralosso Report 12. Ikw values are denotal by bold faco typo.

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SECTION I REPORT OF RADIDACTIVE KFFLUENTS (1990): LIQUID Unit Quarter Quarter ,

3 4 t A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) C1 1.92E-02 8.26E-03

2. Average Diluted Concentration During Period uCi/ml 6.62E-09 3.49E-09

3. Percent of Applicable LLnit (1)  ! 3.84E-01 1.65E-01 B. Tritium

1. Total Release C1 1.14E+02 1.61E402

2. Aver. age Diluted Concentration During Period uC1/ml 3.93E-05 6.80E-05 -

3. P;rcent of Applicable Limit (2) I 1.31E+00 2.27E+00 C. Dissolved and Entrained Gases ,

1. Total Release Ci 6.53E-05 1.40E-02

2. Average Diluted Concentration During Period uC1/ml 2.25E-11 5.91E-09

3. F;rcent of Applicable Limit (3) 2 1.12E-05 2.96E-03 D. Gross Alpha Radioactivity L

1. Total Release Ci 0.00E+00 0.00E+00  !

E. Volume of waste released (prior to dilution) liters 1.20E+06 7.69E407 i

F. Volume of dilution water used liters 2.90E409 2.29E409 i

1. Th2 applicable limit for the Wolf Creek Generating Station is 5 Curies per year.

(R0ference 10CFR50 Appendix 1 'Cuides On Design Objectives For Light-Water-Cooled Nuclear >

Power Reactors', paragraph A.2.) The value printed here is derived by dividing the total j release Curies by 5 Curies and then multiplying the result by 100. r

2. This value is derived by the following formula:

2 of Applicable Limit = (AverRRe Diluted Concentration) (100)

(HPC, Appendix B. Table II 10CFR20)

3. This value is derived by the following formulas  !

I of Applicable Limit - (Averane Diluted Concentration) (100) i (2E-4 from Technical Specification 3.11.1.1) i

_- _. _ _ = _ . - -- . . _ _ . . _ -_ _

LIQUID EFFLUENTS Continuous Mode Batch Hode NUCLIDES Quarter Quarter Quarter Quarter i l

RELEASED Unit 3 4 3 4 H-3 Ci 4.00E-03 1.47E-01 1.14E+02 1.61E+02 i Hn 54 C1 <2.48E-04 <3.81E-02 2.54E-04 1.93E-04 Fe-55 Ci <4.97E-04 <7.62E-02 6.99E-03 4.54E-03 Fe-59 Ci <2.48E-04 <3.81E-02 <3.49E-04 <3.44E-04 Co-57 Ci 0.00E+00 0.00E400 5.77E-06 8.68E-07 Co-58 Ci <2.48E-04 <3.81E-02 5.07E-03. 9.98E-04 Co-60 Ci <2.48E-04 <3.81E-02 3.38E-03 1.27E-03 Zn-65 Ci <2.48E-04 k3.81E-02 <3.49E-04 <3.44E-04 Sr-89 C1 <2.48E-05 <3.81E-03 <3.4VE-05 <3.44E-05 St-90 Ci <2.48E-05 <3.81E-03 <3.49E-05 <3.44E-05 Zr-95 Ci 0.00E+00 0.00E+00 2.30E-05 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00 8.11E-06 Ho-99 Ci <2.48E-04 <3.81E-02 <3.49E-04 <3.44E-04 Sn-117H Ci 0.00E+00 0.00E400 0.00E400 1.13E-06 Sb-124 Cl 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Sb-125 Ci 0.00E+00 0.00E+00 4.76E-04 3.89E-04 I-131 C1 <4.97E-04 <7.62E-02 <6.99E-04 <6.88E-04 Cs-134 C1 <2.48E-04 <3.81E-02 2.21E-03 3.34E-04 Cs-137 Ci <2.48E-04 <3.81E-02 2.83E-03 4.76E-04 Ce-141 Ci <2.48E-04 <3.81E-02 <3.49E-04 <3.44E-04 Ce-144 Ci <2.48E-04 <3.81E-02 <3.49E-04 <3.44E-04 Gross Alpha Ci <4.97E-05 <7.62E-03 <6.99E-05 <6.88E-05 Ar-41 Ci <4.97E-03 <7.62E-01 <6.99E-03 <6.88E-03 Kr-85H Ci <4.97E-03 <7.62E-01 <6.99E-03 <6.88E-0a Kr-85 C1 <4.97E-03 <7.62E-01 <6.99E-03 <6.88E-03 Kr-87 Ci <4.97E-03 <7.62E-01 <6.99E-03 <6.88E-03 Kr-88 Ci <4.97E-03 <7.62E-01 <6.99E-03 <6.88E-03 Xe-131H Ci <4.97E-03 47.62E-01 <6.99E-03 1.26E-04 Xe-133H Ci <4.97E-03 <7.62E-01 <6.99E-03 3.08E-04 Xe-133 Ci <4.97E-03 <7.62E-01 6.53E-05 1.38E-02 Xe-135H Ci <4.97E-03 <7.62E-01 <6.99E-03 <6.88E-03 Xe-135 C1 <4.97E-03 <7.62E-01 <6.99E-03 2.14E-05 NOTE: Less than values are calculated using the lower limit of detection (LLD) values listed in Table 4.11-1 of the Technical Specifications multiplied by the volume of waste discharged during the respective quarter. The less than values are not included in the summation for tne total release values.

1 The Fe-55 value for the 4th Quarter Batch Hode is based on the 3rd Quarter Composite re6ults. Estimated values for Quarter 4 have now been replaced with actual test results.

LIQUID CLDETLATIVE DOSE S199tARY (1990)

TABLE 1 ODCH TECHNICAL CALCULATED SPECIFICATION I 0F DOSE LIMIT LIMIT QUARTER 1 0F 1990 TOTAL DOSE (mrem) FOR BONE 2.30E-02 5.00E400 4.60E 01 TOTAL DOSE (mrom) FOR LIVER 9.33E-02 5.00E400 1.87E+00 TOTAL DOSE (arem) FOR TOTAL BODY 8.24E 02 1.50E+00 5.49E400 t TOTAL DOSE (mrom) FOR THYROID 5.61E-02 $.00E400 1.12E400 TOTAL DOSE (mrom) FOR KIDNEY 6.70E-02 5.00E+00 1.34E400 TOTAL DOSE (mrom) FOR LUNG 6.01E-02 5.00E400 1.20E400 TOTAL DOSE (arem) FOR GI-LLI 6.96E-02 5.00E+00 1.39E400 QUARTER 2 0F 1990 TOTAL DOSE-(mrem) FOR 8.96E-02 5.00E+00 1.79E400 TOTAL DOSE (mrem) FOR LIVER 1.89E-01 5.00E+00 3.78E400 TOTAL DOSE (mrom) FOR TOTAL BODY 1.49E-01 1.50E+00 9.93E400 TOTAL DOSE (mrem) FOR THYROID 3.34E-02 5.00E+00 6.68E-01 TOTAL-DOSE (mrom) FOR KIDNEY 8.41E-02 5.00E+00 1.68E+00 TOTAL DOSE (mrem) FOR LUNG 5.09E-02 5.00E+00 1.02E400 TOTAL DOSE (mrom) FOR GI-LLI 6.74E-02 5.00Ef00 1.35E+00 QUARTER 3 0F 1990  !

-TOTAL DOSE (mrom) FOR BONE 1.48E-02 5.00E400 2.96E 01 TOTAL DOSE (mrem) FOR LIVER 3.61E-02 5.00E+00 7.22E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 2.94E-02 1.50E+00 1.96E+00 i TOTAL DOSE (mrem) FOR THYROID 1.03E-02 5.00E+00 2.06E-01 ,

TOTAL DOSE (mrem) FOR KIDNEY 1.88E-02 5.00E+00 3.76E-01 TOTAL DOSE (mrom) FOR LUNG 1.31E-02 5.00E400 2.62E.01 TOTAL DOSE (mrom) FOR GI LLI 1.11E-02 5.00E+00 2.22E-01 QUARTER 4 0F 1990 TOTAL DOSE (mrem) POR BONE 3.13E-03 5.00E+00 6.26E-02 TOTAL DOSE (mrem) FOR LIVER 5.04E-02* 5.00E+00 1.01E+00*

TOTAL DOSE (mrom) FOR TOTAL BODY 4.90E-02* 1.50E+00 3.27E+00*

TOTAL DOSE (mrem) FOR THYROID 4.50E-02 5.00E+00 9.00E-01

' TOTAL DOSE (mrem) FOR KIDNEY 4.68E 02 5.00E+00 9.36E-01 TOTAL-DOSE (mrem) FOR LUNG 4.56E-02* 5.00E+00 9.12E-01*

TOTAL DOSE (mrem) FOR GI LLI 4.55E-02* 5.00E+00 9.10E-01*

TOTALS FOR 1990 TOTAL DOSE (mrom) POR BONE 1.31E-01* 1.00E+01 A.31E+00*

TOTAL DOSE (mrem) FOR LIVER 3.69E-01* 1.00E+01 3.69Ef00*

TOTAL DOSE (mrem) FOR TOTAL BODY 3.10E-01* 3.00E+00 1.03Ef01*

TOTAL DOSE (mrem) FOR THYROID 1.45E-01 1.00E+01 1.45E+00 '

TOTAL DOSE (mrem) FOR KIDNEY 2.17E-01 1.00E+01 2.17E+00 TOTAL DOSE (mrem) FOR LUNG 1.70E-01* 1.00E+01 1.70E400*

' TOTAL DOSE (mrem) FOR GI-LLI 1.94E-018- 1.00E+01 1.94E+00*

Based on Technical Specification 3.11.1.2 which restricts dose to the whole body to less than or squal to 1.5 mrem per quarter and 3.0 mrem per year. Dose restriction to any organ is less *

th:n or equal to 5 mrem per quarter and 10 mrem per year.

NOTE: The values for Quarter 2 of 1990 given above differ from the values reported in Semiannual Radioactive Effluent Release Report 11 due to adjustment for Fe-55 composite data.

• There was no significant change to these values and are therefore reported the same as the veeues in-Report 12.

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

LIQUID CLMULATIVE DOSE StDMARY (1990)

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

1. Total Release - (Cl) 1.19E-01 1.66E-01 1.92E-02 8.26E-03 3.12E-01

2. Maximum Organ Dose (nrem) 3.44E-02 1.53E-01 2.59E-02 7.50E-03* 2.21E-01*

3. Organ Dose Limit (mrem) 5.00E400 5.00E+00 5.00E+00 5.00E+00 1.00E+01

4. Percent of Limit 6.88E-01 3.06E+00 5.18E-01 1.46E-01* 2.21E+00*

B. Tritium

1. Total Release - (C1) 2.93E402 2.21E+01 1.14E+02 1.61E+02 5.90E+02

2. Maximum Organ Dose (mrem) 5.89E-02 5.56E-02 1.02E-02 4.31E-02 1.48E-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 1.18E+00 7.12E-01 2.04E-01 8.62E-01 1.48E+00 This table is included to show the correlation between Curles released and the associated calculated maximum organ dose. Wolf Creek ODCH methodology is used to calculate the maximum crgan dose vnich assumes that an individual drinks the water and eats fish from the discharge point. Technical Specification 3.11.1.2 organ dose limits are used.

NOTE: The Category A. Quarter 2 values differ from the values reported in Report 11 due to adjustment for Fe-55 composite data. The 4th Quarter Category A values were calculated based on the Quarter 3 Fe-5$ concentration. Estimated values for Quarter 4 have now been replaced with actual test results.

• There was no significant change to these values and are therefore being reported the same as the values found in Report 12.

.-J AA*-_4+--,& 4 - 41 -.J..4 RPEOMDir 2

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