ML20029B112

From kanterella
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept 12,Jul-Dec 1990. W/910301 Ltr
ML20029B112
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/31/1990
From: Bailey J
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NO-91-0071, NO-91-71, NUDOCS 9103050440
Download: ML20029B112 (33)
v • d • e


Text

. ._ _ . - _ . . . . _ _ . _ . _ . . _ - _ _ _ . . _ . . _ _ _ _ _ _ -

s ,

s I

W4pLF CREEK NUCLEAR OPEFMTING CORPOF% TION i

John A Dailey a v.c. er .o.ni March 1.1991 NO 91-0071 l

U. S. Nuclear Regulatory Commission l ATTN: Document Control Desk Mail Station F1-137 Washington. D. C. 20$$$

Subject Docket No. $0-482: Semiannual tadioactive Effluent Release Report 4

Gentlemen v

Enclosed is the Wolf Creek Generating Station (WCGS) Radioactive Effluent Release Report covering the per ad from July 1 1990 to December 31, 1990.

This report is submitted pursuant to section 6.9.1.7 of the WCGS. Unit .No.

1. Technical Specifications.

Very truly yours.

John A. Lailey Vice President

.. Operations JAB /jra Enclosure cci A. T. Howell (NRC), w/a R..D. Martin (NRC), w/a D.-V. Pickett-(NRG). w/a-

-H. E. Skow (NRC), w/a 9103050440 001231 PDR ADOCK 05000482 {

R PDR PO Box 411/ Durhngton, KS 66839 i Phone- (316) 364 8831 f f

n

t77. 4 , 7 ,..;O. An rw opmeunny Employer M F HC' VET

s ,

I

~

l NOLF OtEEE !RCLIW1 OP!JtNI'IfG CG1101ATICN ,

l Walf Crook Generating Station Dxket 1b: 50-482 Facility Operating License Ibn !HT-42 SIMIMME ItADIOhC.TIVE E2'MUENP Ill2FRIH ItHIUff Report !bs 12 Reparting Period: July 1,1990 through Dranber 31, 1990 Prepmd by: Marlin G. Williams Ar p 'ad by: , M s ,_*

G. d.Mk g Plant Manager

  • , Enclosuro to NO 91-0071 Paga 2 of 26 I

HKICUI'IVE SGMARY h p1rpose of the Saniannual Radioactive Effluent Release Report is to report on the quantities of liquid and gaseous effluents and solid waste relcased frun Wolf Creek Generating Station (WO3S). This report covers the period beginning on July 1,1990, and erding at Decamber 31, 1990.

Section I provides a sutmary of the quantitles of radioactive liquid and gaseous effluents for this reporting period. h fornet is similar to that recamanded in Regulatory Guide 1.21, Revision 1. An elevated release pathway does not exist at Wolf Creek Generating Station, therefore, all airborne releases are considered to be ground level releases. h I concurrent noteorological condition gaseous pathway dose determination is l mt by the Wolf Creek Offsite Dose Calculation Manual mthodology of assigning all gaseous pathways to a hypathetical julividual residing at the highest annual X/O and D/0 location. This results in a conservative estimte of dose to a nunber of the pLlic rather than determining each psthway dose for each release condition. A conservative error of thirty percent has been estinated in affluent data.

Sections II and III provide additional infouration required by Regulatory Guide 1.21, Rrnision 1 and Technical Specification 6.9.1.7, respectively.

Attachment 1 provides actual values to replace the estinated values for l liquid effluents providcd in Santannual Radioactive Effluent Release Report I 11. Analysis results for the Second Quarter of Report 11 were not completed l prior to subnission of the report. Actual results of Quarter 2 liquid I

effluents indicated the presence of Fe-55 in the liquid batch ccqposite.

The change increases the total curies releascd and increases the cumulative dose. Because analysis results for the Fourth Quarter of 1990 have not yet been ccmpleted, Fe-55 activity and doses in liquid effluents is presented as an estinate.

l

Enclopuro to No 91 0071 l

1 Page 3 of 36 l

4 e

Tutdo of Ctntxrtta D.92 Soction I 4 Liquid Radicactive Effluents 4 Coso Sunitary 6 Airborno Radicactive Effluents 8 Dose Sumary 10 Section II 12 ibchnical Specification Lbnits 12 Maxbnam Ponnissible Concontrations 13 Monsurutents and Approxinations of 7btal Radioactivity 14 Batch Releases 16 Continuous Relonson 16 Solid Naste Ship ants 17 Irradiated Fuel Ship ants 10 Section III 19 Motoorological Enta 19 Section IV 24 Unplanned or Abnontal Releases 24 Process Control Program 25 Offsite Dose Calculation Manual 25 Major Changes to Liquid, Gasoous or Solid Radwnsta Systuna 25 land Use Consus 26 Radioactive Shipunto 26 Inoparability of Airborne Effluent Monitoring Instnmentation 26 Storage Tanks 26 Attachntmt 1 Liquid Effluent Changes to Rtport 11.

o Enclosuro to NO 91 0071 l'cgo 4 of 26 l SECTION I REPORT OF RADIDACTIVE EFFLifENTS (1990): LIQUID Unit Quarter Quarter 3 4 A. Fission and Activation Product 3

1. Total Release (not including tritium, gases, alpha) Ci 1.92E-02 1.06E-02
2. Average Diluted Concentration During Period uCi/ml 6.62E-09 4.47E-09
3. Percent of Applicable Limit (1) 2 3.84E-01 2.12E-01 B. Tritium
1. Total Release C1 1.14E+02 1.61E+02
2. Average Diluted Concentration During Period uCi/ml 3.93E-05 6.80E-05
3. Percent of Applicable Limit (2) 2 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. Percent of Applicable Limit (3) I 1.12E-05 2.96E-03 D. Gross Alpha Radioactivity
1. Tois1 Re' case C1 0.00E+00 0.00E400 E. Volume of waste released (prior to dilution) liters 1.20E+06 7.69E+07 F. Volume of dilution water used liters 2.90E+09 2.29E409
1. The applicable limit for the Wolf Creek Generating Station is 5 Curies per year.

(Reference 10CFR50, 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 = 1Averane Diluted Concentration) (100)

(HPC, Appendix B. Table II 10CFR20) l 3. This value is derived by the following formula 2 of Applicable Limit = (Average Diluted Concentration) (100)

(22-4 from Technical Specification 3.11.1.1) l

i ,

, Enclosure to NO 91-0071 Page 5 of 26 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3 4 3 4 H-3 C1 4.00E-03 1.47E-01 1.14E+02 1.61E+02 Mn-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 6.88E-03 Fe-59 Ci <2.48E-04 <3.81E-02 <3.49E-04 <3.44E-04 Co-57 Ci 0.00E+00 0.00E+00 5.77E-06 8.68E-07 Co-$8 Ci <2.48E-04 <3.81E-02 3.07E-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 <3.81E-02 <3.49E-04 <3.44E-04 Sr-89 Ci <2.48E-05 <3.81E-03 <3.49E-05 <3.44E-05 Sr-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-117M Ci 0.00EiOO 0.00E+00 0.00E+00 1.13E-06 Sb-124 Ci 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 Ci <4.97E-04 <7.62E-02 <6.99E-04 <6.88E-04 Cs-134 Ci <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-OL <3.81E-02 <3.49E-04 <3.44E-04 Ce-144 C1 <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-85M Ci <4.97E-03 <7.62E-01 <6.99E-03 <6.88E-03 Kr-85 Ci <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-131M Ci <4.97E-03 <7.62E-01 <6.99E-03 1.26E-04 Xe-133M Ci <4.97E-03 <7.62E-01 <6.99E-03 1.08E-04 Xe-133 Ci <4.97E-03 <7.62E-01 6.53E-05 1.38E-02 j' Xe-135M Ci <4.97E-03 <7.62E-01 <6.99E-03 <6.88E-03 Xe-155 Ci <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 the total release values.

1 The Fe-55 value for the 4th Quarter Batch Mode is based on the 3rd Quarter ,

Composite results. I

Enclosure to NO 91-0071

. Pago,6 of 26 l

. LIQUID CUMULATIVE DOSE SU1 MARY (1990)

TABLE 1 ODCH TECHNICAL CALCULATED SFF.CIFICATION  ! 0F  :

DOSE LIMIT LIMI1 l QUARTER 1 0F 1990

' TOTAL DOSE (mrem) FOR BONE 2.30E-02 5.00E+00 4.60E-01 TOTAL DOSE (mrem) FOR LIVER 9.33E-02 5.00E+00 1.87E+00 TOIAL DOSE (mrem) FOR TOTAL BODY 8.24E-02 1.50E+00 5.49E+00 TOTAL DOSE (mrem) FOR THYROID 5.61E-02 5.00E+00 1.12E+00 TOTAL DOSE (mren) FOR KIDNEY 6.70E-02 5.00E+00 1.34E+00 TOTAL DOSE (mrem) FOR LUNG 6.01E-02 5.00E+00 1.20E+00 TOTAL DOSE (mrem) FOR GI-LLI 6.96E-02 5.00E+00 1.39E+00 i QUARTER 2 0F 1990 l TOTAL DOSE (mrem) FOR BONE 8.96E-02 5.00E+00 1.79E+00 l TOTAL DOSE (mrem) FOR LIVER 1.89E-01 5.00E+00 3.78E+00 i TOTAL DOSE (mrem) FOR TOTAL BODY 1.49E-01 1.50E+00 9.93E+00 TOTAL DOSE (mrem) FOR THYROID 3.34E-02 5.00E+00 6.68E-01 TOTAL DOSE (mrem) POR KIDNEY 6.41E-02 5.00E+00 1.68E+00 TOTAL DOSE (mrem) FOR LUNG 5.09E-02 5.00E+00 1.02E+00 TOTAL DOSE (mrem) FOR GI-LLI 6.74E-02 5.00E+00 1.35E+00 QUARTER 3 0F 1990 TOTAL DOSE (mrem) POR BONE 1.48E-02 5.00E+00 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 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 (mrem) FOR LUNG 1.31E-02 5.00E+00 2.62E-01 TOTAL DOSE (mrem) F0F GI-LLI 1.11E-02 5.00E+00 2.22E-01 QUARTER 4 0F 1990 TOTAL DOSE (mrem) FOR BONE 3.15E-03 5.00E+00 6.30E-02 TOTAL DOSE (mrem) FOR LIVER 5.04E-02 5.00E+00 1.01E+00 TOTAL DOSE (mrem) 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 (wrem) 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 (mrem) FOR BONE 1.31E-01 1.00E+01 1.31E+00 TOTAL DOSE (mrem) FOR LIVER 3.69E-01 1.00E+01 3.69E+00 TOTAL DOSE (mrem) FOR TOTAL BODY 3.10E-01 3.00E+00 1.03E+01

, 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) POR LUNG 1.70E-01 1.00E+01 1.70E+00 TOTAL DOSE (mrem) FOR GI-LLI 1.94E-01 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 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.

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.

i .

Enclosura to NO 91-0071 Pago 7 of 26 LIQUID CUMULATIVE DOSE SLEEARY (1990)

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

1. Total Release - (C1) 1.19E-01 1.66E-01 1.92E-02 1.06E-02 3.15E-01
2. Maximum Organ Dose (mrem) 3.44E-02 1.53E-01 2.59E-02 7.30E-03 2.21E-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 6.8BE-01 3.06E+00 5.18E-01 1.46E-01 2.21E+00 B. Tritium
1. Total Release - (C1) 2.93E+02 2.21E+01 1.14E+02 1.61E+02 5.90E+02
2. Maximum Organ Dose (mrem) 5.89E-02 3.56E-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 1.4BE+00 This table is included to show the correlation between Curies released and tha associated calculated maximum organ dose. Wolf Creek ODCH methodology is used to ecleulate the maximum organ dose which 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 Te-55 concentration, i

1 Enclosurs to NO 91-0071

Pags E of 26 REPORT OF RADI0 ACTIVE KFFLUKNIS (1990)
AIRBORNX Quarter Quarter Unit 3 4 A. Fission and Activation Gases
1. Total Release C1 2.$6%-01 3.59E+01
2. Average Release Rate for Period uCi/sec 0.00F400 1.4$E+01 j
3. Percent of Technical Specification Limit (1) 2 3.06E.03 4.40E-02 '

B. Iodines

1. Total Iodine-131 Ci 0.00E400 0.00E400
2. Average Release Rate for Period uCi/sec 0.00E400 0.00E+00
3. Percent of Applicable Limit (t  ! 0.00E+00 0.00E+00 C. Particulates
1. Particulates with Half-lives > 8 days Ci 0.00E+00 0.00E+00
2. Average Release Rate for Period uCi/sec 0.00E+00 0.00E+00
3. Percent of Technical Specification Limit (3) 2 0.00E+00 0.00E+00
4. Gross Alpha Radioactivity C1 2.36E-08 2.97E 08 D. Tritium  ;

i

1. Total Release C1 3.47E+00 4.$0E+00 1
2. Average Release Rate for Period uCi/sec 1.46E+00 1. 2 0 E+ 00
3. Percent of Technical Specification Limit (4)  ! 3.29E-02 4.28E 02 i
1. The percent of Technical Specification limit for fission and activation gases is calculated using the following methodology:

I of Technical Specification Limit = (Quarterly Total Gamma Airdose)(100) 5 mead

2. The percent of Technical Specification limits for Iodine is calculated using the following methodologyi l

l 2 of Technical Specification Limit = (Total Curies of Iodine-111)(100) 1 Curie

3. The percent of Technical Specification limit for pcrticulates is calculated using the following methodology:

l  ! of Technical Specification Limit = (Hichest Orvan Dose Due t o Pattity16t es )(100) 7.5 mrem

4. The percent of Technical Specification limit for tritium is calculated using the following methodology:

! I of Technical Specification Limit = (Highest Ornan Dose Due to H-3)(100) 7.5 mrem NOTE: This type of methodology is used since the Wolf Creek Technical Specifications tie release limits to doses rather than Curie release rat es.

f . .

4 , Enclosure to NO 91 0071 Page 9 of 26 1

GASEQUS EFFLUENTS I

Continuous Mode Batch Hode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3 4 3 4 i

1. F16sion and Activation Cases Ar 41 Ci 0.00E+00 1.03E+00 2.36E 01 4.41E-01 i Kr 85 C1 0.00E+00 0.00E+00 1.98E-02 7.00E 03 Kr-85M C1 0.00E400 4.62E-01 0.00E+00 0.00E+00 Kr-87 Ci <1.59E+01 <1.59E+01 <1.10E-02 <2.00E-02 Kr-88 Ci <1.39E+01 <1.39E+01 <9.62E-03 <1.75E-02 Xe-133 Ci <1.31E+01 3.04E+01 2.79E-04 1.11E-01 Xe 133M Ci <4.32E+01 <4.32E401 <2.99E-02 <5.43E-02 Xe 135 Ci <4.3$E+'io 3.41E400 <3.01E 03 <5.46E-03 Xe-138 Ci <4.24E401 <4.24E+01 <2.93E 02 <5.33E 02 Total Ci 0.00E+00 3.53E401 2.SfE-01 5.59E 01
2. Halogent (Gaseous) 2-131 Ci <2.70E 04 <2.70E 04 <1.87E-07 <3.39E-07 I-133 C1 <2.70E-02 <2.70E 02 <1.87E-05 <3.39E-05 Total Ci 0.00E+00 0.00E+00 0.00E400 0.00E+00
3. Particulates and Tritium H-3 C1 3.30E+00 4.14E+00 1.66E-01 1.60E-01 C0-58 Ci <2.70E-03 <2.70E 03 <1.87E-06 <3.39E-06 Co-f0 Ci <2.70E-03 <2.70E-03 <1.87E 06 <3.39E-06 Hn-54 C1 <2.70E-03 <2.70E-03 <1.87E-06 <3.39E-06 Fe 59 Ci <2.70E-03 <2.70E-03 <1.87E-06 <3.39E 06 2n 65 Ci <2.70E-03 <2.70E-03 <1.87E-06 <3.39E-06 Mo-99 C1 <2.70E-03 <2.70E-03 <1.87E 06 <3.39E-06 Cs-134 C1 <2.70E-03 <2.70E-03 <1.87E-06 <3.39E 06 Cs-137 Ci <2.70E-03 <2.70E-03 <1.87E-06 <3.39E-06 Ce-141 C1 <2.70E-03 <2.70E-03 <1.87E-06 <3.39E-06 Ce-144 Ci <2.70E-03 <2.70E-03 <1.87E-06 <3.39E-06 Sr-89 Ci <2.70E-03 <2.70E-03 <1.87E-06 <3.39E-06 l Sr-90 Ci <2.70E-03 <2.70E-03 <1.87E-06 <3.39E-06 Gross Alpha Ci 2.36E-08 2.97E-0B <1.87E-06 <3.39E 06 t

Total C1 3.30E+00 4.34E+00 1.66E-01 1.60E-01 NOTE: Less than values for Noble Oases 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 Technical Specification LLD values are used.

l l

\

. _ _ . . - - . , ..-,-.____m

' Enclosure to NO 91-0071 Page 10 of 26 GASEOUS CUMULATIVE DOSE SIDHARY (1990)

Table 1 ODCH TECHNICAL CALCULATED SPECIFICATION  ! 0F QUARTER 1 0F 1990 DOSE LIMIT LIMIT TOTAL DOSE (mrem) FOR BONE 9.24E-05 7.50E+00 1.23E-03 TOTAL DOSE (mrem) FOR LIVER 1.03E 03 7.50E+00 1.37E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 9.92E-04 7.50E+00 1.32E-02 TOTAL DOSE (mrem) FOR THYROID 3.10E 02 7.50E+00 4.13E 01 TOTAL DOSE (mrem) FOR KIDNEY 1.09E 03 7.50E+00 1.45E 02 TOTAL DOSE (mrem) FOR LUNG 9.40E-04 7.50E+00 1.25E-02 TOTAL DOSE (mrem) FOR GI-LLI 9.49E 04 7.50E+00 1.26E-02 QUARTER 2 0F 1990 TOTAL DOSE (mrem) FOR BONE 9.83E-04 7.50E+00 1.31E-02 TOTAL DOSE (mrem) FOR LIVER 7.69E-03 7.50E+00 1.02E 01 TOTAL DOSE (mrem) FOR TOTAL BODY 7.71E-03 7.50E400 1.03E-01 TOTAL DOSE (mrem) FOR THYROID 2.60E 02 7.50E+00 3.47E-01 TOTAL DOSE (mrem) FOR KIDNEY 7.70E-03 7.50E+00 1.03E-01 TOTAL DOSE (mrem) FOR LUNG 7.65E-03 7.50E+00 1.02E 01 TOTAL DOSE (mrem) FOR GI-LLI 7.73E 03 7.50E+00 1.03E-01 QUARTER 3 0F 1990 TOTAL DOSE (mrem) FOR BONE 0.00E+00 7.50E+00 0.00E+00 TOTAL DOSE (mrem) FOR LIVER 2.47E-03 7.50E+00 3.29E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 2.47E-03 7.50E+00 3.29E-02 TOTAL DOSE (mrem) FOR THYROID 2.47E-03 7.50E+00 3.29E-02 TOTAL DOSE (mrem) POR KIDNEY 2.47E 03 7.50E+00 3.29E-02 TOTAL DOSE (mrem) FOR LUNG 2.47E-03 7.50E+00 3.29E-02 TOTAL DOSE (mrem) FOR GI-LLI 2.47E-03 7.50E+00 3.29E-02 QUARTER 4 0F 1990 TOTAL DOSE (mrem) FOR BONE 0.00E+00 7.50EiOO 0.00E+00 TOTAL DOSE (mrem) FOR LIVER 3.21E-03 7.50E+00 4.28E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 3.21E-03 7.50E+00 4.28E-02 TOTAL DOSE (mrem) FOR THYROID 3.21E-03 7.50E+00 4.28E-02 TOTAL DOSE (mrem) FOR KIDNEY 3.21E 03 7.50E+00 4.28E-02 TOTAL DOSE (mrem) FOR LUNO 3.21E-03 7.50E+00 4.2bE-02 TOTAL DOSE (mrem) FOR GI-LLI 3.21E-03 7.50E+00 4.28E-02 TOTALS FOR 1990 TOTAL DOSE (mrem) FOR BONE 1.08E-03 1.50E+01 7.20E-03 TOTAL DOSE (mrem) FOR LIVER 1.44E-02 1.50E+01 9.60E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 1.44E 02 1.50E+01 9.60E-02 TOTAL DOSE (mrem) FOR THYROID 6.27E-02 1.50E+01 4.18E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.45E-02 1.50E+01 9.67E-02 TOTAL DOSE (mrem) FOR LUNG 1.43E-02 1.50E+01 9.53E-02 TOTAL DOSE (mrem) FOR OI-LLI 1.44E-02 1.50E+01 9.60E-02

1. Based on Wolf Creek Technical Specification 3.11.2.3 which restricts dose during any calender or ter to less than or equal to 7.5 mrem to any organ and during any calender > .r to less than or equal to 15 mrem to any organ.

' Enclosure to NO 91-0071 Page 11 of 26 GASEOUS CIMULMIVE DOSE StBMARY (3 990)

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

1. Total Release (C1) 9.61E+02 1.51E+00 2.56E 01 3.59E+01 9.99E+02
2. Total Gamma Airdose (mrad) 2.54E-02 7.30E-05 1.53E-04 2.20E-03 2.78E-02
3. Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E401
6. Percent of Gamma Airdose Limit 5.08E-01 1.46E 03 3.06E-03 4.40E-02 2.78E-01
5. Total Beta Airdose (mrad) 7.21E-02 1.27E-04 5.67E 05 3.22E-03 7.55E-02
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) 7.21E-01 1.27E-03 5.67E-04 3.22E-04 3.78E-01 B. Particulates
1. Total Particulates (C1) 6.56E-06 7.98E-05 0.00E+00 0.00E+00 8.64E-05
3. Maximum Organ Dose (mrem) 3.44E-06 1.0$E-03 0.00E+00 0.00E+00 1.05E-03
3. Organ Dose Limit (mrem) 7.50E400 7.50E+00 7.50E+00 7.50E400 1.50E+01
4. Percent of Limit 4.59E-05 1.40E 02 0.00E+00 0.00E400 7.02E-03 C. Tritium
1. Total Release (C1) 1.31E+00 9.37E+00 3.47E+00 4.50E400 1.86E+01
2. Maximum Organ Dose (mrem) 9.34E-04 6.68E-03 2.47E-03 3.21E-03 1.33E-02
3. Organ Dose Limit (mrem) 7.50E400 7.50E+00 7.50E+00 7.50E+00 1.50E+01
4. Percent of Limit 1.25E-02 8.91E-02 3.29E-02 4.28E-02 8.87E-02 D. Iodine
1. Total I-131. I-133 (C1) 5.26E-05 3.22E-05 0.00E-00 0.00E+00 8.48E 05
2. Maximum Organ Dose (mrem) 3.01E-02 1.84E-02 0.00E-00 0.00E+00 4.85E-02
3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E400 1.50E+01
4. Percent of Limit 4.01E-01 2.45E-01 0.00E-00 0.00E+00 3.23E-01 This table is included to show the correlation between Curles released and the associated calculated maximum organ dose. The maximum organ dose is calculated using Wolf Creek ODCM methodology which assumes that an individual actually resides at the release point. Technical Specification 3.11.2.3 organ dose limite are used.

. Enclosure to NO 91 0071

,Page 12 of 26 SIC 1'ICN II Eknil antal Informtim Facility: Malf Creek Gonoratina Station Licenso ihmber NPF-42

1. 7bchnical Spocification Limits A. For liquid wasto offluonts A.1 The concentration of radionctivo natorial relcased in liquid offluents to URISIRICI7D ARPAS shall bo limited to the concentrations upocified in 10Cnt20, Appendix B, Tablo II, Co.'.tmn 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or en shall bo limited to 2 x 10 grainad noble gases, microcario/ml totalthe concentration activity.

A.2 The dose or dose cmmitannt to a MEMBIR OF 7HE PUBLIC frun radioactivo natorials in liquid offluents released, frun each unit, to QRESTRICHD AREAS shall be limited:

a. During any calendar quarter to loss than or oqual to 1.5 mruns to the wholo body and to less than or equal to 5 mruns to any organ, and
b. During any calendar year to less than or equal to 3 mruns to the whole body and to less tinn or equal to 10 mrme to any organ.

B. For gaseous waste offluents B.1 The doso rato due to radioactive natorials released in gaseous effluents frun the site to areas at and beyond the SITE 10010ARY shall be limited to the followings

a. For noble gases: Loss than or cqual to 500 mruns/yr to tho whole body and less than or equal to 3000 mrms/yr to the skin, and
b. For Iodine-131, Ioiino-133, tritium, and all radionuclides in particulato fonn with half-livos greater than 8 days:

Less than or equal to 1500 mrams/yr to any organ.

B.2 1he air dose due to noble gases released in gaseous offluents, l frun each unit, to areas at and beyond the SITE IOU 10ARY ahall to limited to the following: l

a. During any calendar quarter: Iess than or cqual to 5 mrads for garma radiation and less than or cqual to 10 mrada for beta radiation, and l
b. During any calendar year: Insa than or equal to 10 mrads i for ganna radiation and less han or equal to 20 mrads for beta radiation. l l

Enclosure to NO 91-0071

,Pogo 13 of 26 B.3 'Iho dose fmn Iodine-131, Iodine-133, tritium, ard all radionuclidos in particulato fonn with half-lives grtetor tJ an 8 days in gaseous offluents relcesod to areas at and h? yond the SITE IOUNEARY shall to limitad to the folltwing

a. During any calendar quartar Icss than or equal to 7.5 nauts to any organ, and
b. Daring any calendar year: lose than or nyn1 to 15 mnne to any organ.
2. Maxian Permissible Concentrations i Water - covered in Section 1.A.

Air - covemd in Eoction 1.B.

3. Average energy of fission ard activat. ion gaseous effluents is not applicable.

I 1

Enclosure to 140 91 0071

) 'Page 14. of :'6 l .

l

4. Measumtunte ard A;pmxinntions of 'Ibtal Radicactivity l A. Liquid Effluonts i

I SAMPLI!G MUIllOD OF TYPE OF /CI'IVITY LIQUID R12 EASE TYPE FRET.)LfDCY NUdNSIS MUdSSIS

1. Ibt.ch Wast.o P.H.A. Principl Cama Roltese P Dimiters Tanks Fach Ibtch I P.H.A. 1-131 4 ,-

l

a. Wasto l 1 Martitor P Dissolved and 1 Tank Che ibtch/M P.H.A. Patrained Casos (Gama Dnittofs) i b. Secondary Liquid P L.S. H-3 l Waste Each ibtch Monitor S.A.C Grosa Alnha Tank P O.S.L. Sr-09. Sr-90 Each Batch i O.S.L. Fo-55
2. Cant.inous P.H.A. Princi ful Gmma

'l Releases Daily Dnitters Grab Sample P.H.A. 1-131

a. Steam M Dissolved and Generator Grab Sample P.H.A. Entrained Coses Blowdown (Gamn Dnitters)
b. 'litrbine Daily L.S. H-3 Building Grab femple Sunp S.A.C. Gmsn Alpha
c. Line Daily O.S.L. Sr-89, Sr-90 Sludge Grab Sample Pond O.S.L. Fe-55 P = prior to each batch S.A.C. = scintillation alpha counter M = nonthly O.S.L. = perfoured by an offaite laboratory L. S. = iiquid scintillation P.H.A. = game spectrum pulse height analysis using a High Purity Gcrnanium detector.

. . - . . . . . , - . . . . .. ,r...- , . .,.._.._..-.,_m. _ _ , _ _ . _ _ . _ _ , , . . , - . . ._ ._ . ~ --

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

i Enclosure to NO 91 0071

] . Page 15 of 36 1

4 i

  • B. Gsscous Waste Effluents STMPLIIG MIml0D OF TYPE OF
GNSEOUS, RELI%SE 'IYPE FRIUJE!CY A!RINSIS ACTIVITY AIRLYSIS P

Each Tank P .11. A. Principal Ganna

Waste Gas Decay Tank Grab S,wplo Dnitters P Princip1 Gums 1

Conta1JUtent hirgO Or EaCh PutgO P.}I. A. Ihitters Vent Grab Sanple Ces Idbler and L.S. _!!-3 foxido)

Principal Guna Unit Vent M P.it. A. _ nnittern ,,

Grab Sanple Gas Idtler and L.S. 11-3 (oxide).

Radwasto Duilding M P.l!.A. Principal Gam ;

Vent fgeh Samle _ Dnittoys _

All Roloase Typed I-131 as listed abovo Continuous P.H.A.

I-133

'P.H. A.

Continuous Particuleto Principal Guna Sanolo Dnittern , __,

S.A.C.

Continuous Part.iculate Grose Al[ta Crnrosite Sanolo 0.S.L.

Camposito Sr-89, Sr-90 Continuous Particulate Tswlo _.

i l

l-

--.,y .-,p.+,.,, . ., ,,. ,,,y 9 ,_mw., ,m--  %, y. m -___--rr 4T-*- te 4 Wp-TNr - - *" ---'r'-

Enclosure to NO 91 0071 Pago .16 of 26

5. Intch Releases 4

There wru 39 gaseous tutch releases during the rurorting period. h longest gaseous totch rulease lastxd 664 minutos, while the stortest lastext 15 minutes. 7ho average release lastal 174.4 minutos with a total gaseous batch release tino of 6,802 mtnutos.

Thero wutv 29 liquid tatch ruloasos during the reporting period, h longest liquid tutch ruloase lasted 140 mtnutos, while the shortest releaso lasted 42 mtnutes. The average relonso lasted 101 ndnutes with a total liquid batch release tino of 2,93 minutes.

6. Cantinuous Releasos 7here wurn tw lignid reloaso rathways designated as continuous reloaees during this reportin9 Feriod. They are the Lime Sludge Ibnd and 7\chtno Duilding Sunp. 7heru wre tw gas ruloaso pathways designated as cantinucus Iuloases. h so are the Unit Vent and Radwaste Dullding Vent.

+..-.-.~ __ - -.- - -

Enclosure to NO 91 0071 I

. , Page. 17 of 36 ,

. 1

[ frFILE9ff AIO MMmt DIfnGAL SletIAlechL HitKNr (1990) )

l 9 1TD Wd mtIttiM e mi A. SCLID WASTE SHIPPID GTSITE ITR BURIAL m DISPOSAL (Not irradiatal fuel) i Est. 'Ibtal

1. Type of msto Unit 6-Month Period Error %
a. Spent resins, filter sitxiges, m3* 8.20E+00 evaporator tottoms, etc. C1 2.61E+01 2.50E+01-

! b. Dry empressibio esto, m3* 3.58E+01 contaminatext equip, etc. Ci 6.34E-01 2.50E+01

c. Irradiated empononts, m3* 0.00E+00 control ruis, etc. Ci 0.00E+00 0.00E+00
d. Other m3* 0.00E+00 Ci 0.00E+00 0.00E+00 e

m3* = cubic meters

2. Estimate of a jor nuclide cmgesition (by type of m ste)
a. Spent resins, filter altriges, ovaporator bottans, etc. '

Nuclide Percent Nane a undance Curles c

Fe-55 47.503 1.24E+01

! Co-58 19.938 5.21E+00 i Ni-63 12.813 3.35E+00 Co-60 8.074 2.11E+00 Cr-51 2.987 7.8tE-01 4

H-3 2.288 5.9c2-01 Zr-95 1.568 4.10E-03 Ag-110m 1.243 3.25E-01 Mn-54 1.155 3.02E-01 Nb-95 1.067 2.79E-01 Cs-137 .393 ~1.03E-01 C-14 .350 9.16E-02 Cs-134 .225 5.89E-02 Pu-241 .199 5.21E-02 Ce-144 .092 2.40E-02 I-131 .060- 1.56E-02 Pu-238 .027 7.07E-03 Am-241 .011 2.95E-03 Cm-243/44 .007 1.71E-03 Pu-239/40 .000 5.66E-05

b. Dry cmpressible mate, contaminated equipment, etc.

Nuclide Parcent Name Aburriance Curies Fe-55 76.454 4.84E-01 Co-60 12.260 7.77E-02 N1-63 7.373 4.67E-02 Cs-137 1.428 9.05E-03 Mn-54 1.381 8.75E-03 Co-58 .907 5.75E-03 H-3 .137 8.71E-04 Cr-51 .037 2.37E-04 C-14 .023 1.46E-04

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

Enclosure to NO 91-0071

,Page 18 ef 26

c. Irradiated ccuponents, control rods, etc.

none

d. Other none
3. Solid Waste Disposition

?bmber of Shirimnts Fbde of Transrertation DestinatioD 4 Truck Barnwell, South Carolina

4. Class of Solid Waste
a. Class A, Class C-
b. Class A
c. Ibt applicable
d. !bt applicable
5. Type of Cantainer
a. ISA (Strong, tight)
b. ISA (Strong, tight)
c. Ibt applicable
d. Ibt applicable
6. Solidification Agent
a. Ibt applicable
b. Ibt applicable
c. !bt applicable
d. tbt applicable B. IRfGDIATED FUEL SIIIINDIIS (Disposition)

'1here wore no irradiated fuel shipnants during this reparting period.

Enclosure to NO 91 0071

,Page 19 of 26 l l

1 SICI',fm III l

l II.UIS AT I;ACI! WDD SPl!!D MO DIJGCfICN I All gaseous releases at the Wolf Cnmh Generating Station are gInund level releases. 'Ihe neto3IVlogical data supplitd in those tables cover the period l frun January 1,1990, through Ibconbar 31, 1990, and indicate the number of hours at each wind spood and dirret. ion for each stability class.

STABILITY CLASS: A ILUVKfICH: GROU!O I

WIND SPEED ()UM)

WIlO DIRECTICN 1-3 47 0 12 13-10 19 24 >24 IUrAL N O 2 4 4 0 0 10

!NE O O O O O O 0 NE O O O O O O O DE O O O 0 0 0 0 E O O O 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 1 0 0 0 0 0 1 SSE 1 2 0 0 0 0 3 S 0 7 6 1 0 0 14 SSW 0 6 11 6 0 0 23 SW 0 0 6 1 0 0 7 WSW 1 4 0 0 0 0 5 W 0 1 1 0 0 0 2 WNW 0 1 0 3 1 1 6

!M 1 6 4 2 6 0 19 IWd 0 4 2 2 0 0 R

'IUrAL 4 33 34 19 7 1 98 Periods of Calm (flours): O r

- - - - . - - ,, n. ,

Enclosure to NO 91-0071

. Pcgs 20 of 26 9

STABILITY CIASS: B EIJNATICH: Gout 0 WD0 SPEED (MPH)

WIlo DIRDCTIOi 1-3 4-7 8-12 13-18 19-24 >24 IUrE N 0 0 4 3 3 0 10 141E O O O O 1 0 1 NE O O O O O O O ENE O O O 0 0 0 0 E O O O O O O O ESE O 0 0 0 0 0 0 SE O O O O O O O SSE O O O 1 0 0 1 S 0 1 6 4 0 0 11 SSW 0 1 4 6 0 0 11 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 1 1 WtM 0 0 0 0 0 0 0

!M 2 0 0 0 0 0 2 tem 0 0 2 4 0 9 6 .

i

'IUIE 2 2 16 18 4 1 43 Ponode of calm (Hours): 0 STABILITY CLASS: C ELEVATIClit GROUT 0 WIND SPEED (!@ll)

WIND DIRDCTION 1-3 4-7 8-12 13-18 19-24 >24 'IUrE N 1 0 4 10 1 0 16 NNE O 0 0 2 1 0 3 NE 0 0 0 0 0 0 0 ENE O 0 0 0 0 0 0 E O O O O 1 0 1 ESE O 0 0 0 0 0 0 SE O O O O O O O SSE 1 0 0 0 0 0 1

-S 0 1 12 2 0 0 15 SSW 0 0 3 3 0 0 6 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 1 0 1 W 0 0 0 1 0 0 1 WrM 0 0 0 0 2 0 2 IM 3 1 -- O 0 1 0 5

!aM 0 0 6 5 2 0 13

'IUPAL 5- 2 25 23 9 0 64 Periods of Calm (! burs): 0

.. -. ...-..~- - - -.-...-.- - -..--- -- - ..

Enclosure to NO 91-0071

. Ta p 21 of' 26 l

1 STABILITl Cl. ASS: D ELEVAT7CH GROU!O WI!O SPEED (!@ll)

WUD DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 1CIAL

--- . 4.-----.. -_ . . .-- . ... ...._.......__........

l N 24 8 40 36 10 1 119 1 INE 24 8 61 32 8 0 133 l NE il 35 57 28 0 0 124 ENE 15 21 17 6 0 0 59 E 1 20 28 17 2 0 68 ESE 3 19 29 19 3 0 73 l SE- 4 26 54 6 2 0 92 l SSE 1 38 57 41 2 0 139 i S 2 -35 102 126 29 2 296 i SSW 4 21 76 85 29 6 221 SW 2 24 25 10 1 0 62 WSW 1 17 25 11 2 0 56 W 4 23 35 23 5 1 91 NNW 12 13 26 40 24 0 115 NW 14 14 30 53 24 5 140 tam 19 18 54 37 19 7 154 10rAL 134 340 716 570 160 22 1942 Periods of Calm (flours): 0 STABILITY CU.SS: E ELDTATIQ4: CRoute  !

WI!O SPEID (MPil)

WIND DIRECTION 1-3 47 8-12 13 18 19 24 >24 1UTAL N 11 36 112 154 34 1 348 INE 30 3; 93 69 35 9 273 "

NE 13 59 70 18 2 0 162 i ENE 12 45 50 30 -0 0 117 E- 5 40 54 18 1 0 118 ESE 9 78 49 26 9 1 171 SE 9 72 96 45 5 0 227 SSE 6 96 -236 127 27 2 494 S 5 63 255 467 194 34 1018 SSW 8 50 161 221 57 17 514 SW 7 58 41 12 2 0 120 WSW 8 35 46 14 2 0 105 W 7 30 50 14 1 1 103 WrM 6 19 33 12 0 0 75 NW 5- 47 72 44 15 16 199 NtM 61 44 98 85 32 8 370 SUIAL 202 809 1520 1336 416 89 4372 Periods of Cahn (Hours): 1 4

- - - . . - . . .,--_,_--._-.n.,,,,,.--,,n - . . , - ,. --a, , . . , , . ,,.-,.------,n. - Ir' , y

Enclosure to NO 91 0071

'Pago 22 of 26 STABILI'IT CLASS: F 12LVATIO1: GROU!O WI!O SPEITc (MPil)

WI!O DIRIUTIQi 1-3 4-7 8-12 13: '.0

. 19-24 >24 1UrA1, N 7 50 30 1 1 0 89

!aE 6 44 18 3 ') 0 71 ,

[ im 12 39 6 1 1 0 59 DE '1.

33 8 4 0 0 56 E 12 38 16 0 0 0 66 ESE 11 57 25 5 1 0 99 SE 8 88 33 1 1 0 131 SSE l 81 145 12 1 0 246 S . 31 1~1 108 22 0 342

~

SSd 27 94 25 4 1 150 SW t -1 '

9 0 0 0 52 y e  ! 33 19 0 0 0 59 U 7 12 10 1 0 0 3V H!M 6 11 3 0 0 (* 20

!M 9 22 23 1 0 0 55 14 7 24 23 17 3 0 r! 67 70rAL b.' 630 630 165 31 1 1600 Pericls of ' aim (Mm): 0 SThDU L rY CIX>St G EIlV. ATION: GICJ10 WI!O SPEED (MPH)

WnO DIRECTIQi 1-3 4-7 8-12 13-18 3'-24 s >24 'KffAL

--- _ .... . .._.~ . ........ . -... ..... .. . _. .... ... --........ s N 5 27 9 0 0 0 41 NNE 9 28 .? 0 0 0 46 NE 3 27 1 0 0 0 31

, ENE 2 12 0 0 0 0 14 L . -. - c . ..,;.____... . .... .___ _________ .__.... ._________

E i 27 4 0 0 0 32 IT,E 4 34 4 0 0 0 42 FC 1 79 0 0 0 0 80 f!SE 5 76 J7 0 0 0 98

._,____.__....___,,.4,___..____.......__....___...._________...

E 1 20 30 0 0 0 51

(

SbY1 SW 1

0 16 9 3 3

0 0

0 0

0 0

13 19 WSH 0 4 1 0 0 0 5

[ W

! 2 > 0 0 0 3 MM 1 4 0 0 0 0 5 IM 5 25 2 0 .

0 32 lam 9 27 12 0 , 0 48

' URAL 48 407 105 0 0 0 560 Pericds of Calm (Hours): 0 a

_______=_-_-

(

Enclosure to NO 91-0071

, Pass,23 of 26 STABILI'IY CLASS All ELEVATIO4: GROUND WIND SPEED (Mi ?

WIND DIRECTIO4 1-3 4-7 8-12 13-18 19-24 >24 'IUPAL N 48 123 203 208 49 2 633 10 03 69 117 181 106 45 9 527 NE 32 160 134 47 3 0 376 ENE 40 111 75 20 0 0 246 E 19 125 102 35 4 0 285 ESE 27 188 106 50 13 1 385 SE 23 265 183 52 8 0 531 a SSE 21 283 465 181 30 2 982 S *b 158 585 708 245 36 1747 SSN 20 114 352 346 90 24 946 5"? 11 139 84 23 3 0 260 WSW 17 93 91 25 5 0 231 W 19 '6 s 96 39 6 3 231 NNW 25 48 67 55 27 1 223 NW 39 115 131 100 46 21 452 lam 113 d6 191 136 53 15 624

'IGTAL 538 2221 3046 2131 627 114 8679 Periods (.f Calm (11oure): 1 lburs of Misat.g nata: 80

'Ihe ccuputer that supplies the wind speed and dirvction data for Wolf Creek Generating Station does not report hours unless there are three 15-minute intervals of good data per hour. 'Ihe 80 missing hours of data are due to this criteria. In nest cases there is at least one good 15-minute interval for each hour. 'Ihis data is available ansite for twiew at Wolf Creek Generating Station.

1

. . _____o

1 F.nclosure to NO 91-0071 t P go 24 of 26 SECPIm IV Akilticral Inforuntion

1. Unplanned or Abnormal Releases
a. On July 29, 1990, it was discoverud that Waste Gas Decay Tank (VGUT)
  1. 3 had undergone an unexpected pressuru drop while Hochanical Maintenance personnel were cycling its drain valve follcwing planned naintenance on the valve's reach rod. We valve was open for approxbnately two attnutes.

When the dein valve ms opened, gas frun WCDP #3 was released through the drain line header to the connecting drain traps. The gas pressure blew through the traps and pressurizal the Gaseous fladwaste Drain Collection 'Ihnk. This tank is nornally vcnted to the Waste Gas Ccmpressor suction which was not running at the tine of the event. The pressure pushed the contents of the drain collection through the discharge of the Gas Decay Tank Drain Pump, to the dcunstream filter. After passing tlurugh the filter, the gas arrived at the Waste ibld-Up Tank (MUr), b1cwing the loop seal as it passed through. Since the MUr is vented constantly to the Ibating, Ventilation, & Ai.r Conditioning System; once the loop soal was blown, a release occurred.

! Uhis event was caused by a procedural inadequacy which resulted in -

! an insufficient water supply in the drain traps. In order to ensure an adcquate water supply is in the traps, a change to the Waste Gas Systcm Startup and Shutdown Procedure has been completed to provide instructions for filling the drain trape prior to Waste Gas Systan startup.

Calculations done by Chemistry personnel verified that no ibchnical Specification release limits were exceeded during this event.

Ilowever, this situation did constitute a violation of ibchatcal Specification 3.11.2.1, which requires, in part, sanpling of a NGDP prior to its release. This event was reporttd in Idcensee Event Report 482/90-017-00.

b On August 27, 1990, a portable sump pung was temporarily installed

% by the Electrical Maintenance work group in the Turbine Building Olly Waste Sump with the sump pump's discharge directed to the plant's storm drains, bypassing the Turbine Building Drain Monitor.

This is a violation of Ibchnical Specification 3.11.1.1 which requires, in part, grab samples at the initiation of effluent flcw for activity analysis for continuous releases of liquid effluents to unrestricted areas.

1

1

. = .

Enclosure to NO 91-0071

' ' Pags' 25 of 26 Upon the discovery of the effluent flow, the Shift Supervisor halted all activities associated with the oily mate sump ard contacted Chanistry personnel to obtain a sample for activity analysis.

Calculations based on the sample results showed that the 'Itchnical Specification limite were not exceeded during the mlease, twrefore, them ms no traxet to the health and safety of site personnel or the public. Wis event was reported in Licensee Event Report 482/90-020-00, c On Ibvanber 29, 1990, Mechanical Maintenance personnel wure performing naintenance on the relief valve to Wasto Gas Docay Tank

  1. 6. At approxinately 0845 CST, the Maintenanm personnel proceeded to bmak the seal on the relief valve to allcw eny ruraining gas trapped in the systan to escape. We rellei valve rmnined open a few minutes until a portable radiation nonitor indated an incmasing railation level in the area. We rulief ulve fitting was retightened ard the Control Room was contacted. %e Control Roan instructed the Maintenance personnel tc tighter. che fitting back to its proper torque and further stated that the job would be ccmpleted at a later date.

At 0848 CST, the Control Roan received a process radiation high alaan for the Radwaste Building Waste Gas Vent. Health Physics ms contacted and confi=d that the alarm was valid. We area was evacuated and air samples were taken to determine the airborne activity in the surrounding area. %e area was then posted for M rh,rne radioactivity.

Calculations done by Chanistry personnel verified that no Technical Specificatico release limits were exceeded during this event.

Hcwver, this situation did constitute a violation of 'Ibchnical Specification 3.11.2.1, which requires, in part, sampling of a NGDT prior to its release. mis event was reported in Licensee Event Report 482/90-024-00.

2. Process Control Program (PCP)

On October 3,1990, the Plant Safety Review Cmmittee approved a PCP revision and its incorporation into the Radiation Protection ynx:edures as RPP 07-102, Revision 0, " Solid Radwaste Process Control Prograin".

Revisions included updating the PCP to reflect current regulatory requirunents, operating practices, and deletion of descriptions of waste solidification processes and equipnent which are no longer utilized at Wolf Creek Generating Station. A copy of the revised PCP, along with a note detailed description of the changes nude during the reporting period, will be suhrJ.tted by }hrch 29, 1991.

3. Offsite Dose Calculation Manual (CDCM)

%ere were no changes to the 00CM during this report period.

~ .

Enclosure to NO 91-0071

i. Page 26 of 26
4. Major Changes to the Radwasto Systms Were wre no mjor changes to radmasto systes unde during this mport period.
5. Land Use Census Were wre no nc ; locations for dose calculations identified during this report period.

6, Radioactive Shipinnts mere were four shiptents of radioactive radwaste during this report period. All four chipients were to Barnwoll, South Carelina.

7. Inoperability of Effluent Ibnitoring Instrumentation W ere were no events that involved inoperable liquid or gaseous effluent nonitoring instrumentation not being conected within the tine specified  :

in Nhnical Specifications 3.3.3.10 or 3.3.3.11,

8. Storage Tanks mere were no events Imding to liquid noldup tanks or gts storage tard:s exceoding the limits of 'Ibchnical Specifications 3.11.1.4 or 3.11.2,6.

l l

1

7 o_-, .,

.t.

ATF10 MENT 1 Attachment 1 pan: wides actual values to replace the estinate:1 values for liquid effluents prwided in Semiannual Radioactive Effluent Release Report 11. New values are denoted by bold face type, l

6-l l

l' i

l' l.

Attachm:nt.1 Page 2-of 6 y ..

SECTION I REPORT OF RADI0 ACTIVE EFFLUENTS (1990): LIQUID Unit Quarter Quarter 1 2

'A.- Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) C1 1.19E-01 1.66E-01
2. . Average Diluted Concentration During Period uCi/ml 1.32E-08 1.50E-08
3. . Percent of Applicable Limit (1) I 2.38E+00 3.32Ef 00 B. Tritium
1. Total Release C1 2.43E+02 2.21E+01
2. Average Diluted Concentration During Period uCi/ml 3.26E-05 1.98E-06

-3. Percent of Applicable Limit (2) I 1.09E+00 6.63E-02 C. Dissolved and Entrained Gases

.1.-: Total Release C1 1.32E+01 6.47E-03

2. Average Diluted-Concentration During Period uC1/ml 1.47E-06 5.81E-10 3.- Percent of Applicable Limit- (3) I 7.35E-01 2.90E-04

-D. Gross Alpha Radioactivity l

1. . Total Release-. Ci 0.00E+00 0.00E+00 E.- Volume of waste released (prior to dilution) liters 6.92E+07 3.67E+07' I!

<F.- Volume of-dilution watertused -liters 8.93E+09 1.11E+10

. 1.: The applicable limit for the-Wolf Creek Generating Station is 5 Curies per year'.-

(Reference 10 CFR 50 AppendixtI, ' Guides On Design Objectives For Light-Water-cooled; Nuclear 1 Power. Reactors', paragraph A.2.)' -The value printed here is derived by dividing

-the total release < Curies by15-Curies and then multiplying the result by?100.

'23 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 derived by the following formulas -

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

(2E-4 from Technical. Specification 3.11.1.1)

L

Attachmint 1 Pag,o 3 of 6 LIQUID EFFLUENTS Continuous Mode Batch Hode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1 2 1 2 H-3 Ci 9.93E-02 4.51E-01 2.93E+02 2.16E+01 Na-24 Ci 0.00E+00 0.00E+00 6.19E-06 0.00E+00 Cr-51 Ci 0.00E+00 8.73E-05 1.12E-02 5.07E-03 Mn-54 Ci <1.44E-02 <9.22E-03 1.31E-03 1,56E-03 Fe-55 Ci <2.87E-02 <1.84E-02 4.14E-02 3.31E-02 Fe-59 Ci <1.44E-02 <9.22E-03 1.88E-03 4.55E-04 Co-57 Ci 0.00E+00 0.00E+00 3.26E-05 4.10E-04 Co-58 Ci <1.44E-02 2.73E-05 1.45E-02 7.36E-02 Co-60 Ci <1.44E-02 3.19E-05 1.13E-02 3.35E-02 2n-65 C1 <1.44E-02 <9.22E-03 <1.22E-03 <5.52E-04 Rb-88 Ci 0.00E+00 0.00E+00 2.85E-02 0.00E+00 St-89 Ci <1.44E-03 <9.22E-04 <1.22E-04 <5.52E-05 Sr-90 Ci <1.44E-03 <9.22E-04 <1.22E-04 <5.52E-05 Sr-92 Ci 0.00E+00 0.00E+00 5.57E-05 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 3.38E-05 2.22E-05 Nb-95 Ci 0.00E+00 0.00E+00 2.17E-04 1.42E-04 Nb-97 Ci 0.00E+00 0.00E+00 6.59E-05 3.42E-06 Mo-99 Ci <1.44E-02 <9.22E-03 <1.22E-03 <5.52E-04 Ag-310M Ci 0.00E+00 0.00E+00 1.47E-04 3.42E-05 Sn-113 C1 0.00E+00 0.00E+00 1.67E-05 6.46E-06 Sn-117M C1 0.00E+00 0.00E+00 3.92E-04 0.00E+00 Sb-124 Ci 0.00E+00 0.00E+00 6.16E-04 1.83E-03 Sb-125 Ci 0.00E+00 6.64E-05 4.56E-03 8.77E-03 Sb-126 C1 0.00E+00 0.00E+00 5.35E-06 3.26E-05 I-131 Ci <2.87E-02 1.03E-06 1.70E-04 7.90E-06 Cs-134 Ci <1.44E-02 1.52E-05 1.45E-03 3.06E-03 Cs-137 Ci <1.44E-02 1.09E-05 1.89E-03 3.68E-03 Ba-139 Ci 0.00E+00 0.00E+00 1.74E-04 0.00E+00 La-140 Ci 0.00E+00 0.00E+00 2.23E-05 0.00E+00 Co-141 Ci <1.44E-02 <9.22E-03 7.08E-05 <5.52E-04 Ce-144 Ci <1.44E-02 <9.22E-03 <1.22E-03 <5.52E-04 Gross Alpha Ci <2.87E-03 <1.84E-03 <2.43E-04 <1.10E-04 Ar-41 Ci <2.87E-01 <1.84E-01 2.09E-04 <1.10E-02 Kr-85M C1 <2.87E-01 <1.84E-01 4.16E-03 <1.10E-02 l

._._m . m._ . _ ,_-. .. _ . , _ _ _ . _ - . - _ - - _ _ . _ . - - . . - _ _ . .___ _ . _ _ . __,

.- ~- 7, Attachmsnt 1

'Page:4 of-6 5:

LIQUID EFFLUENTS Continuous Mode- Batch Mode .

NUCLIDES_ _ Quarter Quarter Quarter Quarter RELEASED: Unit. 1 2 1 2 Kr-85 Ci <2.87E <1~.84E-01 9.60E-02 <1.10E-02 Kr-87 =Ci <2.87E-01 <1.84E-01 1.43E-04 <1.10E-02 Kr-88 Ci <2.87E-01 <1.84E-01 2.96E-03 <1.10E-02 Xe-131M C1 <2.87E-01 <1.84E-01 1.48E-01 2.13E-04 Xe-133M Ci <2.87E-01 <1.84E-01 1.20E-01 <1.10E-02 Xe-133- C1 <2.87EJ01 1.83E-05 1.27E+01 6.19E-03 Xe-135M C1 <2.87E-01 <1.84E-01 <2.43E-02 <1.10E-02 Xe-135 Ci <2.87E-01 <1.84E-01 5.67E-02 4.68E-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 the total release values.

1 The Fe-55 value for the Second Quarter Batch Mode is_ based on the First Quarter Composite results. Estimated valuee ' for Quarter 2 have now been replaced with actual test results.

n 9

d l

L

, e e Attachment 1 q Fage 5 of 6 s

LIQUID CUMUI.ATIVE DOSE SUMARY (1990)

TABLE 1 ODCM TECHNICAL CALCULATED SPECIFICATION 2 0F DOSE LIMIT LIMIT QUARTER 1 0F 1990 TOTAL DOSE (mrem) FOR BONE 2.30E-02 5.00E+00 4.60E-01 TOTAL DOSE (mrem) POR LIVER 9.33E-02 5.00E+00 1.87E+00 TOTAL DOSE (crem) FOR TOTAL BODY 8.24E-02 1.50E+00 5.49E+00 TOTAL DOSE (mrem) FOR THYROID 5.61E-02 5.00E+00 1.12E+00 TOTAL DOSE (mrea) FOR KIDNEY 6.70E-02 5.00E+00 1.34E400 TOTAL DOSE (mrem) FOR LUNG 6.01E-02 5.00E+00 1.20E+00 TOTAL DOSE (mrem) FOR GI-LLI 6.96E-02 5.00E+00 1.39E+00 QUARTER ? 0F 1990 TOTAL DOSE (mrem) FOR BONE 8.96E-02, 5.00E+00 1.79E+00, TOTAL DOSE (mrem) FOR LIVER 1.89E-01, 5.00E+00 3.78E400, TOTAL DOSE (mrem) FOR TOTAL BODY 1.49E-01 1.50E+00 9.93E+00 TOTAL DOSE (mrem) FOR THYROID 3.34E-02 5.00E+00 6.68E-01 TOTAL DOSE (mrem) FOR KIDNEY 8.41E-02, 5.00E+00 1.68E+00, TOTAL DOSE (mrem) FOR LUNG 5.09E-02, 5.00E+00 1.02Et00, TOTAL DOSE (mrem) FOR GI-LLI 6.74E-02 5.00E+00 1.35E+00 TOTAL FOR 1990 TOTAL DOSE (mrem) FOR BONE 1.13E-01, 1.00E+01 1.13E-01, TOTAL DOSE (mrem) POR LIVER 2.82E-01, 1.00E+01 2.82E+00, TOTAL DOSE (mrem) FOR TOTAL BODY 2.31E-01 3.00E+00 7.70R+00 TOTAL DOSE (mrem) FOR THYROID 8.95E-02 1.00E+01 8.95E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.51E-01, 1.00E+01 1.51E+00, TOTAL DOS'; (mrem) FOR LUNG 1.11E-01, 1.00E+01 1.11E+00, TOTAL DOSE (mrem) FOR GI-LLI 1.37E-01 1.00E+01 1.37E400 Bheed on Technical Specification 3.11.1.2 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 was no significant change to these valuen and are therefore reported the same as the valuna found in Report 11.

I l

e a a g Attachment 1

, Page 6 of.6-e.

LIQUID CUMULATIVE DOSE Site (ARY (1990)

TABLE 2 lA. Fission-and Activation Products Quarter 1 Quarter 2 Total

.1. Total Release - (not including H-3) 3_

gases, alpha) C1 1.19E-01 1.66E-01, 2.85E-01,

2. Maximum Organ Dose (mrem) 3.44E-02 1.53E-01 1.87E-01
3. . Organ Dose Limit (mrem) 5.00E+00 5.00E+00, 1.00E+01,
4. . Percent of Limit 6.88E-01 3.06E+00 1.87E+00 B. Tritium ,
1. Total Release.C1 2.93E+02 2.21E+01 3.15E+02
2. Maximum Organ Dose (mrem) 5.89E-02 3.56E-02 9.45E-02
3. Organ Dose-Limit (mrem) 5.00E+00 5.00E+00 1.00E+01
4. Percent of Limit 1.18E+00 7.12E-01 9.45E-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. Technical Specification 3.11.1.2 organ dose limits are used.

-* There was no significant change to the values and are therefore being reported the same as the values found in Report AA.

-__- - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Retrieved from "https://kanterella.com/w/index.php?title=ML20029B112&oldid=2491895"