ML20012A234

Semiannual Radioactive Effluent Release Rept 10 for Jul-Dec 1989.

ML20012A234
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1989
From:	Boyer G, Mike Williams WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20012A161	List: ML20012A160 ML20012A234 ML20012A251
References
NUDOCS 9003090052
Download: ML20012A234 (32)

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i NOLF CREEK NUCLFAR OPERATI!G CORPORATION I I

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Wolf Creek Generating Staticri i

i Docket No 50-482  ;

Facility Operating License Not NPF-42 {

-l SIBRAIGERL RADIOKTIVE EFFillERE RE[JESE RERRP Report. No: 10  ;

Reporting Period: July 1,1989 through December 31, 1989  ;

i Prepared by: Nerlin G. Williams Approved by: M G. D. Boydb '

Plant Manager i

1 9003090052 900223 PDR ADOCK 05000402

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Encl sur3 t@ NO 90 0053 P0g3 2 cf 32 EEIKXFfIVE IKBROM The purpose of the Semiannual Radioactive Effluent Release Report is to report on the quantities of liquid and gaseous effluents and solid waste released from Wolf Creek Generating Statim (NOGS). This report covers the period beginning on July 1,1989, and ending cm December 31, 1989. l A sunmary of the quantities of radioactive liquid and gaseous offluents fer this reporting period is provided. The format is similar to that reocamanded in Regulatory Guide 1.21, Revision 1. An elevated release pathway does not exist at Wolf Creek Generating Station, therefore, all ah-i- < se relaaaam are considered to be ground level releases. The concurrent noteorological condition gaseous pathway dose dotarmination is met by the Wolf Creek offsite Dose Calculation Manual methodology of assigning all gaseous pathways to a hypothetical individual residing at the highest annual X/Q and D/Q location. '!his results in a conservative estinate of dose to a member of the public rather than determining each ,

pathway dose for each release candition. A conservative error of thirty

• percent has been estimated in effluent data.

This et also includes additional infomation required by Regulatory Guide 1.21, Revision 1 and hchnical Specification 6.9.1.7. Offsite Dose Calculation Manual (ODCM), Revision 5 was approved by the Plant Safety Review Ccamittee during this reporting period. A copy of ODN, Revision 5 is included in its entirety as Attachment 1 to this report.

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[ Enc 1;sure to NO 90 0053 P;ge 3 cf 32

'Innhia of Omtmits M

Section I 4 Liquid Radioactive Effluents 4 Dose Stamary 7 Airb.u.s Radioactive Effluents 10 Dose Stanary 14 Section II 16 Technical Specification Limits 16 Maximan Permissible Cmoentrations 17 Mansurements and Approxinatims of Tota. Radioactivity 18 Batch Releases 20 Continuous Releases 20 Solid Maste Shipnents 21 Irradiated Fuel Shipnents 23 Section III 24 Meteorological Data 24 Sectim IV 29 Unplanned or Abnomal Releases 29 Process Control Fr+== 30 Offsite Dose Calculation Manual 30 Major Changes to Liquid, Gaseous or Solid Radweste Systans 31 Land Use Census 31 Radioactive Shipnents 31 In-vahility of Effluent Monitoring Instrumentation 31 Storage Tanks 31 Attachment I p- Offsite Dose Calculation Manual L

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~ Br.clCs:r] t3 NO 90-0053 -

Pag 3 4 cf 32 I i

SECTION I Year 1989 j aro0RT OF RADIOACTIVE EFFLUENTS: LIOUID I Unit Quarter Quarter 3 4 A. Fission and Activation Products j i

1. Total Release (not including tritium, nases alpha) Ci 3.11rl-01 1.32E-01 ]

2. Averane Diluted Concentration Durina Period uCi/ml 8.04E-08 6.55E-08

3. Percent of Aeolicable Limit (1)  ! 6.22E+00 3.24E+00 l

B. Tritium j

1. Total Release C1 1.86E+02 2.74E+02 l

2. Averane Diluted Concentration Durine Period uCi/ml 4.83E-05 1.11E-04 j

3. ' Percent of Aeolicable 1.4=4t (2) 2 1.60E+00 3.69E+00 C. Dissolved and Entrained Cases

1. Total Release Ci 3.87E-02 .4E-01

2. Averane Diluted Concentration Durinn Period uCi/ml 1.00E-08 7.04E-08

3. Percent of Aeolicable Limit (3)  ! 5.00E-03 3.52E-02

_p. Gross Aloha Radioactivity

1. Total Release Ci 0.00E+00 0.00E+00 E. Volume of waste released (orior to dilution) liters 4.75E+07 2.37E+07 F. Volume of dilution water used liters 3.82E+09 2.45E+09

1. Th3 applicable limit for the Wolf Creek Generating Station is 5 Curles per year.

(Rsference 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 = (Averane Diluted Concentration) (100)

(MPC, Appendix B, Table II 10CFR20)

3. This value is derived by the following formula:

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

(2E-4 from Technical Specification 3.11.1.1)

Encicour] t3 NO 90 0053 Pag 3 5 of 32 Yer.r 1989 LIQUID EFFLUENTS ,

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

H-3 Ci 1.07E-01 4.96E-02 1.86E+02 2.74E+02 Hn-54 Ci <2.34E-02 <1.14E-02 9.49E-05 4.72E-04 i

Fe-55 Ci <4.67E-02 <2.29E-02 1.4BE-01 1.50E-01 Pe-59 Ci <2.34E-02 <1.14E-02 < 3 . 8 9 E ,0.4_ <3.96E-04 ,

Co-57 Ci 0.00E+00 0.000+00 1 1.45E-03 3.25E-2),__

Co-58 Ci <2.34E-02 <1.14E-02 9.42E-02 1 71E-03 -

Co-60 Ci <.t.34E-02 <1.14E-02 5.90E-02 5.53E-03 Nb-95 Ci _f.00E+00 0.00E+00 5.9?!-05 0.00E400 I i

Nb-97 Ci 0.00E+00 0.00E+00 3.52E-05 l 2.36E-05 Sr-92 Ci 0.00E+00 0.00E+00 1.14E-05 7.70E-06 Sr-89 Ci <2.34E-03 <1.14E-03 <3.89E-05 <3.96E-05 >

Sr-90 Ci <2.34E-03 <1.14E-03 <3.89E-05 <3.96E-05 Mo-99 Ci <2.34E-02 <1.14E-02 <3.89E-04 <3.96E-04 I-131 Ci <4.67E-02 <2.29E-02 4.95E-05 <7.91E-04 Cs-134 Ci <2.34E-02 <1.14E-02 2.58E-03 1.23E-03 Cs-137 Ci <2.34E-02 <1.14E-02 4.55E-03 1.59E-03 ,

Ce-141 Ci <2.34E-02 <1.14E-02 <3.89E-04 <3.96E-04 Ce-144 Ci <2.34E-02 <1.14E-02 <3.89E-04 <3.96E-04 , ,

Sb-125 Ci 0.00E+00 0.00E+00 3.43E-04 1.58E-03 1

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EnclCouro to NO 90 0053 P ge 6 cf 32 Year 1989 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 3 4 3 4 An-110M Ci 0.00E+00 0.00E+00 2.55E-05 3.70E-04 Gross Alpha Ci <4.67E-03 <2.29E-03 <7.79E-05 <7.91E-05 Kr-85M Ci <9.30E+00 <4.58E+00 <1.56E-01 <1.58E-01' Kr-85 Ci <9.30E+00 <4.58E+00 <1.56E-01 1.64E-02 Kr-87 Ci <9.30E+00 <4.58E+00 <1.56E-01 <1.58E-01 Kr-88 Ci <9.30E+00 <4.58E+00 <1.56E-01 <1.58E-01 Xe-131M C1 <9.30E+00 <4.58E+00 4.01E-04 5.77E-03 Xe-133M Ci <9.30E+00 <4.58E+00 3.78E-04 6.50E-04 Xo-133 C1 <9.30E+00 <4.58E+00 3.79E-02 1.51E-01 Xe-335M Ci <9.30E+00 <4.58E+00 <1.56E-01 <1.58E-01 Xe-135 Ci <9.30_E+00 <4.58E+00 6.48E-05 1.61E-05

_. Ar-41 Ci <9.30E+00 <4.58E+00 <1.56E-01 <1.58E-01 NOTE: Less than values are calculated using the lower limit of detection (LLD) values obtained at the Wolf Creek Generating Station 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.

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'Enciteure t3 No 90 0053 r .Fage 7'cf 32' j

_ Year _ 1989 LIQUID CtBIDLATIVE DOSE SUletARY TABLE 1  ;

ODCM TECHNICAL I 0*

CALCULATED SPECIFICATION 'I 0F.-

F^ . .

DOSE ,,

LIMIT M)RT, *

' QUARTER'1'0F 1989 i TOTAL DOSE (mrom) FOR BONE 1.96E.02 5.00E+00 3.92E.01 i

. TOTAL DOSE (mrom) FOR LIVER 4.62E-02 5.00E+00 9.24E.01 .

. TOTAL DOSE (mrem) FOR TOTAL. BODY 3.73E.02 1.50E+00 2.49E+00 TOTAL DOSE.(mrem) FOR THYROID 1.16E.02 5.00E+00 2.32E.01 TOTAL DOSE (mrem) FOR KIDNEY 2.2BE.02 5.00E+00 4.56E-01

-TOTAL DOSE (mrom) FOR LUNG 1.55E.02 5.00E+00 3.10E-01

' ;TOTAL 1 DOSE - (mrem) FOR GI-LLI 2.90E.02 5.00E+00 5.80E-01 '

l QUARTER 2 0F 1989 .

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- TOTAL DOSE (mrem) FOR BONE 1.30E.03 5.00E+00 2.60E.02 '

TOTAL DOSE (mrem) FOR LIVER 2.22E.02 5.00E+00 4.44E.01 <

TOTAL DOSE (mrem) FOR TOTAL PODY 2.17E-02 1.50E+00 1.45E+00 TOTAL DOSE (mrem) FOR' THYROID 2.01E-02 5.00E+00 4.02E.02 '

TOTAL DOSE (mrem) FOR KIDNEY 2.07E.02 5.00E+00 4.14E 01 TOTAL DOSE- (mrem) FOR LUNG 2.04E.02 5.00E+00 4.08E.01 l TOTAL DOSE (mrem) FOR GI.LLI 2.14E 02 5.00E+00 4.28E-01

' QUARTER 3'0F 1989 TOTAL DOSE (mrem) FOR BONE 2.17E-02 5.00E+00' 4.34E.01'

,-TOTAL DOSE (mrem) FOR' LIVER 6.86E-02 5.00E+00 1.37E+00 i TOTAL DOSE (mrem) FOR TOTAL BODY 5.90E-02 1.50E+00 3.93E+00

' TOTAL' DOSE (mrem) FOR THYROID 3.30E-02 5.00E+00 6.60E-01 l TOTAL DOSE (mrem) FOR KIDNEY 4.45E-02 5.00E+00 8.90E-01 L'-TOTAL DOSE (mrem) FOR LUNG 3.72E-02 5.00E+00 7.44E.01 L4 TOTAL DOSE (mrem) FOR GI.LLI 4.11E-02 5.00E+00 8.22E.01.

QUARTER 4 0F 1989' L TOTAL DOSE'(mrem) FOR BONE 1.35E.02 5.00E+00 2.70E.01 l;TOTALDOSE.(mrem)FORLIVER 6.55E.02 5.00E+00 1.31E+00 L1 TOTAL DOSE (mrem) FOR~ TOTAL BODY 5.93E.02 1.50E+00 3.95E+00

[jTOTAL DOSE (mrem)'FOR THYROID 4.35E.02 5.00E+00 8.70E.01

'1 TOTAL DOSE (mrem) FOR KIDNEY 5.04E-02 5.00E+00 1.01E+00

- TOTAL _ DOSE (mrem) FOR LUNG 4.64E-02 5.00E+00 9.28E-01

" TOTAL DOSE (mrem) FOR GI-LLI 4.52E.02 5.00E+00 9.04E-01 L

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., Enc 10s:ra to_NO 90-0053- l

.P ge'8 ef 32 1 y-i 1

a LIQUID CIRetULATIVE DOSE SIRetARY TABLE 1 (continued)

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'ITbTALSFOR1989 l

TOTAL DOSE (mrem) FOR BONE. 5.61E-02 1.00E+01 5.61E-01 i'

.70TAL DOSE'(mrem) FOR LIVER 2.03E-01 1.00E+01- 2.03E+00 l TOTAL DOSE-(mrem) FOR TOTAL BODY 1.77E-01 3.00E+00 5.90E+00 j

.-TOTAL DOSE (mrom) FOR T!iYROID 1.08E-01 1.00E+01 1.08E+00 TOTAL DOSE (mrem) FOR KIDNEY 1.38E-01 '1.00E+01 1.38E+00 TOTAL DOSE (mrem) FOR LUNO 1.20E-01 1.00E+01 '1.20E+00' 1.37E-01 TOTAL DOSE (mrem) FOR GI-L'A 1.00E+01 1.37E+00 t

L1: B: sed on Technical Specification 3.11.1.. aich restricts dose to the whole body-to less than or equal to 1.5 mrom per quarter and 3.0 mrem per year. Dose restriction to any L

crgan is less than or equal to 5 mrem per quarter and 10 mrem per year.

NOTE: The values for Quarter 1 and Quarter 2 of 1989 given'above differ from the values reported

'in Semiannual Radioactive Effluent Release Report Number'9 due to adjustment for Fe-55 composite' data. i h

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EnclCourf t NO 90-0053 P:ge 9 cf-32 q I

Year 1989 LIQUID CUMULATIVE DOSE SIRMARY TABLE 2 l

A.' Fission and Activation Products Quarter 1 Ouarter 2 Ouarter 3 Ouarter 4 Total (not including H-3,

1. Total Release - nases. aloha) C1 2.19E-01 4.14E-02 3.11E-01 1.62E-01 7.33E-01

2. Haximum Ornan Dose (mrem) 3.46E-02 2.20E-03 3.92E-02 2.25E-02 9.85E-02

3. Ornan Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 c

4. Percent of Limit 6.92E-01 4.40E-02 7.84E-01 4.50E-01 9.85E-01 B. Tritium

1. Total Release Ci 9.23E+00 1.19E+02 1.86E+02 2.74E+02 5.8BE+02 ,

2. ' Maximum Ornan Dose (mrem) 1.16E-02 2.00E-02 2.94E-02 4.30E-02 1.04E-01

3. ~Ornan Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 t

4. Percent of Limit 2.32E-01 4.00E-01 5.88E-01 8.60E-01 1.04E+00 This table is included to show the correlation between Curies released and the associated calculated maximum organ dose. Wolf Creek ODCM methodology is used to calculate the maximum t 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: For Category A.1 above (Total' Release - not including H-3, gases, alpha) Semiannual Radioactive Effluent Release Report Number 9 covering the reporting period of January 1, 1989.through June 30, 1989, indicated Quarter 1 to have released 1.95E-01 Curies and Quarter 2 to have released 5.48E-02 Curies. The values given above differ from the values reported in Report 9 due to adjustment for Fe-55 composite data. .The Quarter 4 value of 1.62E-01 Curies is an estimate based on Quarter 3 Fe-55 concentration.

L. Encitsur3 to NO 90-0053 Page 10 cf 32l Year 1989 REPORT OF manIOACTIVE EFFLUENTS: Avanneur Quarter Quarter Unit 3 4 Fission and Activation Gases

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1. Total Release Ci 8.99E+01 3.67E+02 l

2. Averane Release Rate for Period uCi/see 1.71E+02 2.28E+02

3. Percent of Technical Specification Limit (1)  ! 7.00E-02 2.82E-01 B .' Iodines

1. Total Iodine-131 C1 1.77E-05 0.00E+00

2. Average Release Rate for Period uCi/see 2.23E 0.00E+00

3. Percent of Aeolicable Limit (2) I 1.77E-03 0.00E+00 C. Particulates

( 1. 'Particulates with Half-lives > 8 days Cl 0.00E+00 0.00E+00 L.

2. Averane Release Rate for Period uCi/sec 0.00E+00 0.00E+00

3. Percent of Technical Soecification Limit (3) Z 0.00E+00 0.00E+00

4. Gross Aloha Radioactivity Ci 3.83E-08 0.00E+00 D. Tritium

, 1. Total Release Ci 5.15E+01 4.82E+01 i

l l' 2. -Averane Release Rate for Period uCi/sec 6.86E+00 6.53E+00 l

3. Percent of Technical Specification Limit (4)  ! 4.89E-01 4.59E-01

1. JThe percent of Technical Specification limit for fission and activation gases is calculated using the following methodology

I of Technical Specification Limit . (Ouarterly Total Beta Airdose)(100) 10 mrad

2. 'Ths applicable limit for the Wolf Creek Generating Station is 1 Curie per year. (Reference ,

10CFR50, Appendix I, " Guides on Design Objectives For Light-Water-Cooled Nuclear Power Rzectors", paragraph C.2.) The percent of applicable limit for iodine is calculated using the following methodology:

I of Applicable Limit = (Total Curies of Iodine-131)(100) 1 Curie

p p 'Encles:re to NO 90-0053~

P:ge 11'cf 32:

P z 3 '. 1Th3 percent of Technical Specification-limit for particulates is calculated using the

>following methodology:  ;

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'! of Technical. Specification Limit = (Hinhest Ornan Dose Due to Particulates)(1001- i 7.5 mrtm.

l4.:, ,The percent of Technical Specification limit for tritium is calculated using the following tathodology:

Z 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 releasee to doses rather than Curie release rates.

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Encicouro to NO 90 0053 lPago 12'of 32 Year 1989 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 9.25E-01 7.43E-01 1.85E+00-Kr-85 Ci 0.00E+00 0.00E+00 4.95E-02 0.00E+00 Kr-85M C1 3.67E-02 0.00E+00 1 91E-02 1.38E-01 Kr-87 Ci <1.39E+01 <1.29E+01 <3.04E-02 <7.80E-02 Kr-88 C1 <1.66E+01 <1.55E+01 4.52E-04 6.85E-02 Xe-131M- Ci 0.00E+00 0.00E+00 1.05E+00 2.10E+00 Xe-133 Ci 2.77E+01 1.98E+02 5.70E+01 1.54E+02 Xe-133M Ci <4.01E+01 <3.74E+01 4.71E-01 1.70E+00 Xe-135 Ci 2.48E+00 5.84E+00 3.13E-01 2.51E+00 Xe-138 Ci <4.12E+02 <3.84E+02 <9.02E-01 <2.32E+00 Total Ci 3.03E+01 2.05E+02 5.96E+01 1.62E+02

2. Halonens (Gaseous)

I-131 Ci 1.77E-05 <2.48E-04 <5.82E-07 <1.49E-06 I-133 Ci 4.29E-06 <2.48E-02 <5.82E-05~ <1.49E-04 Total Ci 2.20E-05 0.00E+00 0.00E+00 0.00E+00

EnciCouro.ts NO 90-0055

-Page 13 ef 32 Year 1989 GASEOUS EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter l RELEASED Unit 3 4 3 4 4

3. Particulates and Tritium i

H-3 Ci 5.14E+01 4.78E+01 1.42E-01 4.14E-01 CO-58 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 Co-60 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 Mn-54 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E Fe-59 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05  :!

Zn-65 Ci <2.66E-03 <2.4BE-03 <5.82E-06 <1.49E-05 Mo-99 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 ,

Cs-134 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 L .. Cs-137 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 _;

l Ce-141 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 Ce-144 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 1

Sr-89 Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 p i.

Ci <2.66E-03 <2.48E-03 <5.82E-06 <1.49E-05 Sr-90  ;

I Gross Aloha C1 3.83E-08 <2.48E-03 <5.82E-06 <1.49E-05 i

Total Ci 5.14E+01 4.78E+01 1.42E-01 4.14E-01  !

NOTES. Less than values are calculated using the lower limit of detection l (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter. The less than values are not included in the summation for the total release values.

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Sheleeura t1 No 90 0053  !

!Page 141Cf;52. ,

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Year 1989

-GASE0DS'CIBIOLATIVE DOSE SIRBIARY-Table 1 c......................................................................................... ,

ODCM ~ TECHNICAL 1 CALCULATED SPECIFICATION -! 0F 1 QUARTER 1 0F 1989 -DOSE- LIMIT- L1gli iTOTAL DOSE (mrom), FOR BONE- 6.58E-05. :7.50E+00 8.77E.04 TOTAL DOSE (mrom) FOR LIVER

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5.79E.03 7.50E+00 7.72E.021 l

TOTAL DOSE (mrom) FOR TOTAL-BODY 5.79E.03- 7.50E+00 7.72E.02_ [

.-TOTAL DOSE (mrem) FOR THYROID - 5.78E.03 7.50E+00 7.71E-02 TOTAL DOSE (mrem) FOR KIDNEY- 5.78E.03- 7.50E+00 7.71E.02 TOTAL' DOSE (mrem) FOR~ LUNG 5'79E.03

. 7.50E+00 7.72E-02~ g TOTAL DOSE-(mrem) FOR GI-LLI 5.79E.03 - 7.50E+00 '7.72E-02: J

. QUARTER 2 0F 1989~

TOTAL DOSE . (mrom) FOR BONE . 0.00E+00. 7.50E+00 0.00E+00 TOTAL DOSE (mrem) FOR LIVER 1.06E-02 7.50E+00 1.41E.01 TOTAL DOSE (mrem) FOR TOTAL BODY- 1.06E-02 7.50E+00 -1.41E-01 170TAL DOSE (mrem) FOR THYROID 1.06E-02 7.50E+00 1.41E.01-TOTAL DOSE (mrem) POR KIDNEY 1.065-02 7.50E+00~ 1.41E-01 TOTAL DOSE (mrem) FOR' LUNG 1.06E-02 7.50E+00 1.41E.01 -

TOTAL DOSE (mrem):FOR GI-LLI- 1.06E-02 7.50E+00 1.41E-01 QUARTER 3<0F.1989 TOTAL DOSE (mrem) FOR BONE 3.08E.05 7.50E+00 4.11E-04 '

' TOTAL DOSE (mrem), FOR LIVER 3.68E-02 7.50E+00 '4.91E " TOTAL DOSE (mrem)'FOR TOTAL BODY 3.67E.02 7.50E+00 4.89E ' TOTAL DOSE (mrem) FOR THYROID 4.69E.02 7.50E+00- 6.25E-01.

' TOTAL DOSE-(mrem)-FOR' KIDNEY 3.68E-02 7.50E+00 '4.91E-01 >

-TOTAL DOSE (mrem):FOR LUNG' 3.67E 7.50E+00 4.89E-01.

TOTAL DOSE (mrem) FOR'GI-LLI 3.67E.02 7.50E+00 4.89E-01 s QUARTER 450F 1989 . ,

TOTAL DOSE (mrem) FOR~ BONE 0.00E+00 7.50E+00 0.00E+00 L TOTAL' DOSE (mrem) FOR' LIVER 3.44E.02 7.50E+00- 4.59E-01

" TOTAL' DOSE (mrem)-FOR TOTAL BODY .3.44E.02 7.50E+00- 4.59E.01- ,

JTOTAL~ DOSE'(mrem) FOR THYROID 3.44E.02 7.50E+00 4.59E.01 *

. TOTAL DOSE (mrem) FOR KIDNEY 3.44E-02 7.50E+00 4.59E-01

TOTAL DOSE (mrem) FOR LUNG 3.44E-02 7.50E+00 4.59E-01 pLTOTALDOSE(mrem)'FORGI-LLI- 3.44E.02 7.50E+00 4.59E-01 iTOTALS FOR 1989 ,

b TOTAL DOSE (mrem) FOR BONE 9.66E-05 1~.50E+01 6.44E-04

TOTAL DOSE (mrem) FOR LIVER S.75E-02 1.50E+01 5.83E.01 TOTAL DOSE-(mrem) FOR1 TOTAL BODY 8.75E-02 1.50E+01 5.83E-01 L

TOTAL DOSE -(mrem) FOR THYROID 9.77E.02 1.50E+01 6.51E.01

" : TOTAL DOSE (mrem) FOR KIDNEY 8.75E-02 1.50E+01 5.83E-01 TOTAL: DOSE ~(mrem) FOR LUNG 8.75E.02 1.50E+01 5.83E.01

. TOTAL DOSE (mrem) FOR GI-LLI 8.75E.02 1.50E+01 5.83E-01 1.L B2 sed on' Wolf Creek Technical Specification 3.11.2.3 which restricts dose during any calender quarter to less'than or equal ~to 7.5 mrem to any organ and during any

:cslender year, to less than or equal to 15 mrem to any organ.

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R .EnclOstre to NO 90-0053 P:go 15 cf 32 Year 1989 GASEOUS CIMULATIVE DOSE SUtMARY TABLE 2 A. Fission and Activation Gases Quarter 1 Ouarter 2 Ouarter 3 Ouarter 4 Total

1. Total Release (Ci) 5.71E+01 1.26E+02 8.99E+01 3.67E+02 6.40E+02

2. Total Gm==a Airdose (mrad) 1.64E-03 4.67E-03 2.97E-03 1.17E-02 2.10E-02

3. Ga=== Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 Percent of Gamma

4. Airdose Limit 3.28E-02 9.34E-02 5.94E-02 2.34E-01 2.10E-01

5. Total Beta Airdose (mrad) 4.26E-03 9.87E-03 7.00E-03 2.82E-02 4.93E-02

6. Beta Airdose Limit (mrad) 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 l Percent of Beta

7. Airdose Limit (mrad) 4.26E-02 9.87E-02 7.00E-02 2.82E-01 2.47E-01 B. Particulates

1. Total Particulates (Ci) 5.36E-06 0.00E+00 0.00E+00 0.00E+00 5.36E-06

2. Maximum Organ Dose (mrem) 7.41E-05 0.00E+00 0,00E+00 0.00E+00 7.41E-05

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

4. Percent of' Limit 9.88E-04 0.00E+00 0.00E+00 0.00E+00 4.94E-04 C. Tritium

1. Total Release (C1) 8.02E+00 1.49E+01 5.15E+01 4.82E+01 1.23E+02

2. Maximum Organ Dose (mrem) 5.72E-03 1.06E-02 3.67E-02 3.44E-02 -8.74E-02 l

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

4. Percent of Limit 7.63E-02 1.41E-01 4.89E-01 4.59E-01 5.83E-01 l D. Iodine

1. Total I-131. I-133 (C1) 0.00E+00 0.00E+00 2.20E-05 0.00E+00 2.20E-05

2. Maximum Organ Dose (mrem) 0.00E+00 0.00E+00 1.02E-02 0.00E+00 1.02E-02

3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 i 4. Percent of Limit 0.00E+00 0.00E+00 1.36E-01 0.00E+00 6.80E-02 i

1 This table is included to show the correlation between Cur' s released and the associated calculated maximum organ dose. The maximum organ de- se calculated using Wolf Creek ODCM methodology which assumes that an individual actually resides at the release point. Technical Sp2cification 3.11.2.3 organ dose limits are used.

m -Encissurs ts NO 90-0053 .l l

Pago 16 ef 32 c

-7 l 5

SIK3'KBI II

, ' P n1  :*1 Infomation Facility: Wblf Creek Generatina Station License Number: NPF-42

1. Technical Specification Limits A. . For liquid waste effluents A.1 '1he concentration of radioactive material released in liquid effluents to UNRESTRICTED ARFAS shall be limited to the ocncentrations specified in 10CFR20, Appendix B, Table II, r Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained  ;

concentration shall be limited to 2 x 10 microcurie fe gases, the/ml total activity.

A.2 The dose or dose ocamitment to a MEMBER OF THE PUBLIC frun radioactive materials in licpid effluents released, from each unit, to ItlREERICPED AREAS shall be limited:

a. During any calendar quarter to less than or equal to L 1.5 mrums to the whole body and to less than or equal I to 5 mreme 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 mrums to any' organ.

B. For gaseous waste effluents B.1 The dose rate due to radioactive materials released in gaseous effluents fran the site to areas at and beyond the SITE -

~

BOUNDARY ahall be limited to the following:

a. For noble gases: Imss than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrums/yr to the skin, and i

b. For Iodine-131,-Iodine-133, tritium, and all radionuclides in particulate form with half-lives

! greater than 8 days: Iass than or equal to 1500 l mrems/yr to any organ.

B.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Issa than or equal to 5 mrads for ganma radiation and less than or equal to 10 l mrads for beta radiation, and

b. During any calendar year Isse than or equal to 10 mrads for ganma radiation and less than or equal to 20 mrads for beta radiation.

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h.' Enc 15suro-to-NO- 90-0053 s

'P:gt 17:ef 32 l B.3 ' '1he dose from Iodire-131; Iodine-133, tritium, and all radionuclirtaa in particulate fonn with half-lives greater than 8 days in gaseous affluents relaaw, fran each unit, to areas at l

and beyond the SITE BOCDIDhRY shall be limited to the following ,

a .' - During any oalendar quarter: Iass than or equal to l

=7.5 mrums-to any organ, and j b.: During any calendar year Imss than or equal to 15 1 mrems to any organ. _

2. Maxinum Permissible Concentrations i g Water - covered in Sectimi 1.A.

Air - covered in Section 1.B.  !

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

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Enciteure.to NO. 90-0053 Pago 18 cf'32=

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4. Measurements and Approxinations of 'Ibtal Radioactivity A'.; Liquid Effluents LIQUID RELEASE SAMPL11G METICD OF TYPE OF ACTIVITY TYPE PREQUENCY ANALYSIS ANALYSIS '

l. Batch Maste P.H.A. Principal Ganma '

Release P  !!hmiters i Tanks Each Batch P.H.A. I-131

a. Waste Monitor P Dissolved and Tank One Batch /M P.H.A. Entrained Gases (Ganma Emitters) <

b. Secondary  ;

Liquid P L.S. H-3 Naste Each Batch Monitor S.A.C. Gross Aloha ,

Tank '

P O.S.L. Sr-89. Sr-90 >

Each Batch O.S.L. Fe-55

2. Continous P.H. A. - Principal Ganma Releases Daily . Baltters - .

Grab Sanple P.H.A. I-131

a. Steam M Dissolved and Generator Grab Sample P.H.A. Entrained Gases Blowdown IGanma Emittersi

b. Turbine Daily L.S. H-3 Building Grab Sanple Sunp S.A.C. Gross Aloha

c. Lime 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. = performed by an offsite laboratory L. S. = liquid scintillation P.H.A. = ganma spectrum pulse height analysis using a High Purity Germanium detector.

': , Encicouro to NO 90-0053 P:go 19 cf 32.

t-B. Gaseous Waste Effluents bhMPLING MEHOD OF TYPE OF GASB00S, RELEASE TYPE PREQUENCY ANALYSIS ACTIVITY ANALYSIS' P

Each Tank P.H.A. Principal Ganna Naste Gas Decay ' Dank Grab Sanple Emitters ..l 1

P Principal Ganna Cantainment Purge or Each Purge P.H.A. ' Emitters  ;

Vent Grab Sanple Gas Bubbler  !

and L.S. H-3 (=lch)  !

l Principal Ganna Unit Vent .M P.H.A. Emitters' Grab Sanple Gas k hbler and L.S. H-3 (mithi-Radwaste Building M P.H.A. Principal Gamma Vent Grab Samole Emitters q All Release Types .

I-131 l as listed above Continuous P.H.A. j I-133 l P.H.A.

Continuous Particulate Principal Gamna l hle Emitters S.A.C.

Ccutinuous Particulate Gross Alpha' Ocmoosite Sanole i O.S.L. l l- Ocmposite Sr-89, Sr-90 1 l

' Continuous Particulate hie i

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Enciteuro t3 NO 90 0053-

,P2ge 20 cf 32, i 1

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5. Batch Releases

'Jhere were 30 gaseous batch releases during the report period. 'Ihe longest gaseous batch release took 2,468 minutes, the shortest occurred over a 102 minute interval. 'Ihe average release took 690 minutes with a total gaseous batch release time of 20,691 minutes.

'Ibers were 32 liquid batch releases during the report period.' The longest liquid batch release took 202 minutes while the shortest took only 40 minutes.- The average release time for the liquid batch releases l was 111 minutes. 'Ibtal release time for all 32 liquid batch releases  ;

was 3,543 minutes, i

6. Cbntinuous Releases

'Ibere were two release pathways designated as continuous releases during this report period. 'Ihey are the Line Sludge Pond and the Turbine Building Sunp. At no time during this report period was steam generator blowdown diverted to Wolf Creek Cooling Iake (NCCL).

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Y " .Encicour$ tD'NOL90-0053' P:g') 21 cf 32 1'

EFFILERFf JWE MBTE DISOSAL SieUJaeKmL Rmutr (1989)'

arr.m mars surnaeus L . A. SOLID WASTE SHIPPED OFFSITE PCR BLRIAL CR DISPOSAL (Not irradiated l

fuel) l'. Type of waste titit 6-Itmth Est. Total Period- Error %

a. Spent resins, filter sludges, m3* 1.85E+01 evaoorator bottans, etc. Ci 1.26E+03 2.50E+01

b. Dry ompressible waste, m3* 4.14E+01 contaminated sanin. etc. C1 2.041N 2.50E+01

c. Irradiated ocuponents, m3* 0.00E+00 centrol' rods, etc. Ci 0.00E+00 0.00E+00 1

d. Other (describe) m3* 0.00E+00 Ci 0.00E+00 0.00E+00 m3* = cubic meters I- 2. Estinate of najor nuclide conpositicn (by type of waste) i

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

Waste Class A Fe-55  %- 7.61E+01 Co  % 5.91E+00 j H-3  % 5.11E+00 1 Cr-51  % 4.92E+00 N1-63  % 3,83E+00 Fe-59  % 2,41E+00 _

Mn-54  % 6.63E-01 Co-58  % 3.20E-01 Sb-125  % 2.32E-01 l C-14  % 1.71E-01  ;

Cs-137  % 8.90E-02 i Nb-95  % 6.70E-02 Cs-134  % 6.10E-02 i Ru-106-  % 5.00E-02 Zr-95  % 3.60E-02 l Co-57  % 1.90E-02 4 Sr-89  % 4.00E-03 I i

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Enc 1:sure to NO,90-0053~-

.Page 22 cf 32 k

'Naste Class B Fe-55  % 7.12E+01 Co-60  % 5.59E+00 0o-58  % 5.59E+00 Cr-51  % 4.30E+00 Cs-137  % 3.52E+00 .

Cs-134  % 2.48E+00 Ni-63  % 2.27E+00

-Fe-59 -% 2.19E+00 Mn-54  % 1.39E+00 H-3  % 7.98E-01 Sr-89  % 1.69E-01 i C-14  % 1.52E-01 Co-57  %- 1.41E-01 St>-125  % 9.80E-02 It>-95  % 5.60E-02 Sr-90  % 6.00E-03 Sn-113  % 5.00E-03

b. Dry cwpassible mate, omtaminated equipnent, etc.

Fe-55  % 5.25E+01 Ni-63  % 2.33E+01 Co-60  % 1.67E+01 Co-58  % 3.62E+00 p Mn-54  % 2.58E+00 Sb-125  % 1.10E+00-Co-57  % 2.02E-01 Cr-51  % 3.20E-02 C-14  % 3.00E-02 Aa-110M  % -1.20E-02 Cs-134  % 1.10E-02 Cs-137  % 2.00E-03

c. IrmHated camponents, cmtrol rods, etc. <

L none

( d. Other I

none

3. Solid Naste Disposition Number of Shitznsnts Mode of Transportation Destination 6 Truck Barnwell, South Carolina i

1

-. a - ,-c

Encitsure tD NO.90-0053 P:g3-23 cf 32 j 1

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4. Class of Solid Waste

a. Class A and Class B

.b. Class A

c. Not applicable  ;

d. .Not applicable j

5. Type of Container

a. Type A ISA

b. LSA (Strong, tight) '

c. Not applicable

d. Not applicable

6. Solidification Agent i

a. Not applicable <

b.- Not applicable

c. . Not applicable

d. Not applicable ,

B. IRRADIATED FUEL SHIPMDTIS (Disposition)

'Ihere were no irradiated fuel shipents during this reporting period.

Enc 1*: sura to NO 90-0053 P:g) 24 cf 32. i l

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SIKTIN III 10GIS Jtr EROI WDD SPEID JGO DIRIKTIW l

All' gaseous releases at the Wolf Creek Generating Station are ground level }

. releases. 'Ihe meteorological data supplied in these tables cover the period ,

fran January 1,1989, through _%r 31, 1989, and indicate the number of hours at each wind speed and direction for each stability, class.

STABILITY CIASS: A ELEVATIW GROWD WIND SPEED (MPH)

WIND DIRECTI N 1-3 4 8-12 13-18 19-24 >24 'IUPAL N- 3 22 47 81 39 11 203 NNE O 15- 20 24' 3 0 62 NE O 1 3 3 0 0 7 ENE O O O 0 0 0 0 E O 0 0 0 0 0 0 ESE. 0 0 2 2 0 0 4 0

SE 1 5 4 0 0 10 SSE O 3 14 2 0 0 19 S 0 2 26 45 1 4 78 SSW 0 1 6 22 4 0 33 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0

'NW 0 0 0 1 0 0 1 NNW 4 7 17 25 12 3 68

'IUPAL 7 52 141 209 59 18 486 Periods of Calm (Hours): 3 L

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E

3Enciteur ts:NO 90-0053 e i: P:gi 25:cf-32.

L STABILITY CIASS: B EIAVATIW: GR0lRO WIND SPEED (MPH)

WIND i DIRECTIW. 1-3 4-7 8-12 13-18 19-24 >24 'IUIAL N 1 6 29 47 16 2 101 NNE l' 7 23 18 1 0 50-NE 2. 3 1 2 0 0 8 ENE O O O O 0- 0 ~0

.E 1 1 0 0 0 0 12 ESE O O 6 5 0 0 11 SE O 1 9 4 0 0 14 SSE- 0. 5 14 10 0 0 29 j S 3 4 43 43 6 1 100 SSW 0 3 10 11 7 -0 31 SW 0- 0 2 0 0 0 2 WSW 0 0 0 0 0 0 0 W. 0 0 0 0 0 0 0 141W 0 0 0 0 0 0 0 NW 0 0 1 0 1 0 2

.NNW 2 12 13 18 13 0 58 -

'IUEAL 10 42 151 158 44 3 408 Periods of Calm (Hours): 0 STABILITY CIASS: C- ELEVATIW: GROUND WI!O SPEED (MPH)-

WIND DIRECTION - 1-3 4-7 8-12 13-18 19-24 >24 'IUEAL >

N- 1 9 30 41 34 2 117 NNE 3 4 19 15 7 1 49 NE 1 4 9 1 0 0 15 ENE O 0 1 0 0 0 1 E- 0 0 0 0 0 0 0 ESE O 1 11 1 0 0 13

' SE 0 3 13 5 0 0 21 SSE 3 6 25 9 3 0 46 S 1 18- 42 52 6 1 120 SSW 0 4 26 28 15 0 73 SW 0 2 5 1 0 0 8 WSW 0 1 1 0 0 0 2 l

e W 0 1 0 0 0 0 1 NNW 0 2 0 0 0 0 2 NW 1 1 0 3 1 0 6 NNW 0 5 16 24 6 3 54

'1UIAL 10 61 198 180 72 7 528 g Periods of Calm (Hours): 1 1.

I

c Enc 1Cour3 to NO 90-0053 j., P233 26-cf 32' H STABILITY CLASS: D ELEVATICE: GROUND WIPO SPEED (MPH)

WIND DIRECPION- 1-3 4-7 8-12 13-18 19-24 >24- TOIAL N 4 36 90 89 45 4 268 IWE 7 25 85 49 17 8 191 1 NE- 12 70 73 6 1 0 162 ENE.- 8 60 31 5 0 0 104 E 7 37 70 10 0 0 124 ESE 8 52 89 18 0 0 167 SE 18 60 84 25 0 0 187 SSE 18 98 167 63 6 0 352 L S 17 91 189 270 67 7 641 l SSW 11 50 107 150 42 4 364 SW 3 37 50 14 3 0 107 NSW 0 26 37 19 1 0 83-i W 5 15 49 10 1 0 80 i IWW 1 21 48 20 6 8 104 i

NW- 4 17 60 77 43 9 210 i NNW 5 36 99 100 41 0 281 1 DIAL 128 731 1328 925 273 40 3425 Periods of Calm (Hours): 3 i

(

STABILITY CLASS: E ELEVATICH: GROUND l WIND SPEED (MPH) j

! WIND E DIRECTICN ~ 'l-3 4-7 8-12 13-18 19-24 >24 'IDIAL L

N 5 58 53 -7 0 0 123 .

NNE- '9 50 41 7 1 0 108 ~l NE 28 59 17 0- 0 0 104 ENE 29 113 49 7 0 0 198 l

l E 23 92 66 4- 0 0 185.

ESE 17 85 52 2 0 0 156 'l

.SE. 21 95 46 6 0 0 168

$ SSE 12 120 156 50 5 0 343 l

l S 6 42 137 146 47 1 379 SSW 3 48 95 19 0 0 165 SW 12 69 30 7 0 0 118 NSW 9 46 30 1 0 0 86 L W 1 32 34 12 0 0 79 L NNW 0 24 32 8 0 0 64 I

l NW 5 25 75 13 2 0 120 NNW 1 51 46 5 0 0 103 1UIAL 181 1009 959 294 55 1 2499 l Periods of Calm (Hours): 5

.Encicoura to NO 90-0053' tP:go 27.cf 32 S'IRBILITY CEASS: F ELEVATIW: GROLND WIND SPEED (MPH)

WIND I

DIRECTION 1-3' 4-7 8-12 13-18 19-24 >24 'IUIAL N 10 36 12 1 0 0 59  !

NNE 6 45 20 0 0 0 71 NE- 14 35 4 0 0 0 53

!!NE 14 34 4 0 0 0 52 E 8 63 13 0 0 0 84 BSE 12 63 5 1 0 0 81 SE 8 99. 9 0 0 0 116 SSE 2 56 28 2 0 0 88-

~

S 3 18 29 1 0 0 51 SSW 6 14 14 0 0 0 34 SW 8 26 t. 0 0 0 38 WSW 8 20 4 0 0 0 32 W 4- 8 5 0 0 0. 17 NNW 7 8 5 0 0 0 20 NW 10 18 14 0 0 0 42 NNW 4 25 16 0 0 0 45

'IUIAL 124 568 186 5 0 0 883 Periods of Calm (Iburs): 3

~

STABILITY CEASS: G ELEVATICN GROUND WIND SPEED (MPH)

WIND DIRECTIm 1-3 4-7 8-12 13-18 19-24 >24 'IUIAL o __ _ _ _ _ _ _ _ __________ _ _____

N- 4 8 0 0' 0 0 12 NNE 2 21 12 0 0 0 35 NE. 2 17 1 0 0 ~0 20 ENE 4 19 2 0 0 0 25 E 3 10 2 0 0 0 15 ESE 3- 25 2 0 0 0 30 l SE. 0 22 1 0 0 0 23 SSE 1- 15 10 0 0 0 26 S- 1 10 1 0 0 0 12 SSW 0 5 1 0 0 0 6 SW 5 5 0 0 0 0 10 WSW 2 7 1 0 0 0 10 W 0 2 0 0 0 0 2 NNW 2 4 1 0 0 0 7

. NW - 5 16 4 0 0 0 25 NNW 6 8 1 0 0 0 15

'IUIAL 40 194 39 0 0 0 273 Periods of Calm (Iburs): 0

Encicoura to NO 90-0053

.P:g3 28 cf 32

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STABILITY CIASS: All ELEVATICN: GROUND l :- WIND SPEED (MPH)

DIRECTICN 1-3 4-7 8-12 13-18 19-24 >24 'IUrAL N 28 175 261 266 134 19 883 NNE 28 167 220 113 29 9 566 NE 59- 189 108 12 1 0 369 ENE 55 226 87 12 0 0 380-E 42 203 151- 14 0 0 410 ESE 40 226 167 29 0 0 462 SE 47 281 167 44 0 0 539.

SSE 36 -303 414 136 14' 0 903 S 31 185 467 557 127 14 1381 i SSW 20 125 259 230 68 4 706  :

SW 28 139 92 22 3 0 284 )

NSW 19 100 73 20 1 0 213 W 10 58 88 22 1 0 179  ;

. NNW 10 59 86 28 6 8 197 i NW- 25 77 154 94 47 9 406-NNW 22 144 208 172 72- 6 624 i

'IUTAL 500 2657 3002 1771 503 69 8502 '!

Periods'of Calm (Hours): 15 j Hours of Missing Data: 243 i

The ccanputer that supplies the wind speed and direction data for Wolf Creek Generating Station does not report hours unless there are three.15-minute 1 intervals of good data per hour. 'Ihe 243 missing hours of data are due to l this criteria. In most cases there is at least one good 15-minute interval -i for each hour. 'Ihis data is available cmsite for review at Wolf Creek l Generating Station.  !

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Enc 1:sur3 to NO 90-0053 Pago 29.cf 32 o

SBerIm IV Additional Infannation

1. Unplanned or Abnomal Releases 1

a.- On July 17, 1989, it was ciiscovered that a violation of the aa=nling requimnants of Technical Specification 3.11.1.1 had occurred on July 16, 1989. 'Dechnical Specification 3.11.1.1 in part requires daily grab samples for activity analysis for ocntinuous releases of liquid effluents to unrestricted areas. Therefore, the following infannation is included in accordance with 'Nchnical Specification 6.9.1.7 requiranants.

On July 15, 1989, a valve lineup was perfonned to direct the discharge of several Turbine mildirg sumps to the Site Oil Separator. Later on July 15, a valve lineup error es mde when restoring the Turbine  !

Building sung discharge pathway to its nonnal configuration to the  !

Secondary Liquid Waste Oil Inta.cupw1. Uhis error resulted in six Turbine Building sunps still beirq discharged to the Site Oil Separator.

Unawere of this cxandition, Operations personnel informed Chemistry pm..cauel that the discharge had been tenninated and that no aa=nling -

was required. On July 17, 1989, the valve lineup error was discovered and prmptly corrected. Subsequent sampling and analysis by Chanistry 1 personnel covirnai that no releaso limits were excaadad. '

This event was the result of cognitive personnel error by utility licensed p=..c.usal. An oversight during Piping and Instrumentation Diapm review resulted in an inuu.sact valve lineup. ' The Licensee  !

Event Report (LER) was & to Operations Required Reac11ng to ensure -!'

other personnel are aware of this event and its consequences. The details of this occurrence were reported to the NRC in LER-482/89-015- j

00. '

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b. On Septanber 13, 1989, at approximately 1000 Car, the Containnent 1 minipurge damnara were open for 51 seconds during the perfonnance of the i 18-inch purge valve leakage surveillance test. This resulted in an i unplanned release of the Containment atmosphere to the env1xonment.

Samples of the Containment atmosphere were subsequently obtained and analyzed, and it was detennined that the release rates were not exceeded. A review of the installed radiation monitor trends showed no increase of activity during the 51-second release period. The radiation '

ntnitor's setpoint was set in accordance with the Offsite Dose Calculation Manual (00m) and would have initiated a Containment Purge Isolation had the setpoint been reached.

At the time of this occurrence, Containment Atmosphere Activity Monitor L

GT-RE-31 was out of service. All other radiation monitors in the l release pathway were in service. Technical Specification 3.3.3.1 requires one channel of Containnent atmosphere activity nonitors to be in service or the Containment purge valves are to be maintained closed.

Since Containment Atnosphere Activity Monitor GT-RE-32 was in service at the time of this occurrence, the requirments of Technical Specification 3.3.3.1 were satisified.

1 0

i Enc 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to NO: 90-0053 :

?P 33 30'cf 32

2. Process Control Program (PCP)  ;

Were were no changes to the Process Control Propcun during this report period.

3. Offsite Dose Calculation Manual (ODCN) I I

Revision 5 to the 000( ms issued with Plant Safety Review Ommittee approval on November 27,-1989. Revision 5 to the ODCM included the following changes:

Pages 14, 18 and 19:

Changed "FSAR" to "USAR" to reflect the appupciate title of the Updated Safety Analysis Report.

Pages 36, 37 and 41: 1 Changes on pages 36, 37 and 41 reflect the loss of two sanple locations, i F-1 and F-8, from the Radiological Envimmiinital Program. % ere are no ~!

milk sanpling locations available within five miles of Wolf Creek Generating Station. On page 37,. ground water sanple location D-65 inwcractly appeared as C-65 in revision 4 of the CDCM. This error was ,

corrected, i Page A-2:

Bioammilation factors for both silver and antbnony were added to Table ,

A.1-1. Since Revision 1 to Regulatory Guide 1.109 does not contain  !

bioaccunulation factors for these two elenant, the values were obtained -l fran revision 0 of Regulatory Guide 1.109.

.l Previous.to this addition, a bioam=ilation factor of zero es assuned for silver. Because Ag-110M does appear in liquid effluents at Wolf Creek, it is felt that using a bioam=ilation factor of. 2.3 fran the earlier revision of Regulatory Guide 1.109 m a more conservative than assuming no am=ilation of Ag-110M in fish flesh.  ;

-l When the ODCM, Revision 3 was issued it contained site-relate.1 dose  ;

cmmitment factors (AIT) for four additional nuclides, Sb-124, Sb-125,  !

Sb-126 and Co-57. A bioaccunulation factor of 1 for Antimony was used i to calculate the AIT values. Table A.1-1 was revised to reflect the

. bioaccunulation factor used in the calculation of the AIT values.

i L Pages A-20, A-23, A-26 and A-29:- l

l. As described in the paragraph above, revision 3 of the ODCM contained j

! AIT values-for four additional nuclides. In addition to the '

bioammilation factor, Ingestion factors for each age group were i utilized in mitmlating the AIT values. %e Ingestion Dose Factors for j Sb-124, Sb-125, Sb-126 and Co-57 were added to the Ingestion Dose Factor tables to clearly indicate the factors used to calculate the AIT values. j Pages A-32, A-35 and A-38:

Changing the bicaccumulation factor fran zero to 2.3 for silver results in higher AIT values for Ag-100M. %e tables on pages A-32, A-35 arri A-  ;

38 were updated to reflect this change for age groups Adult, Teen and Child. S e AIT values for Infant remain unchanged because infants are t not considered to consume fish flesh. i c '

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Enc 1cours to NO 90-0053' P g3 31 cf 32 '

According to the Wolf Creek Offsite Dose Calculation Manual nethodology all gaseous pathways are assigned a hypothetical individual residing at the boundary of the unrestricted area. %e' loss of milk sanpling locations F-1 i and F-8 fran the Radiological Environmental han1 Log Program will not reduce the accuracy or reliability of dose' calculations or setpoint determinations. % e dose calculations and setpoint calculations remain unchangal as a result of the loss of sanple locations F-1 and F-8.

- The change of the silver bioaccumulation factor fran zero to 2.3 will

. slightly increase the reported dose fran liquid effluents, however the J setpoint detennination will remain unchanged due to the fact the liquid .

nonitor setpoints are based upon MPCs not dose.

t I

The other changes rwyarding isotopes Sb-124, Sb-125,' Sb-126 and Co-57 i

support an earlier revision to the ODCM to include these isotopes in our program. %is change is a clarification to clearly indicate all values used J to calculate the AIT values. No change to dose calculations or setpoint determination results fran these additions. I A canplete copy of the ODN, Revision 5 is included with this report as l Attachment 1.-

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4. Majo- Changes to the Radwaste System l Sere were no major changes to radwaste systems made during this report period.

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S. Land Use Census here were no new locations for dose calculations identified during this l luru.i. period. 1

6. Radioactive Shipnents There were six shipnents of radioactive radwaste during this report period. All six shipnents were to Barnwell, South Carolina.

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7. Inoperability of Effluent Nonitoring Instrumentation l There was no inoperable liquid or gaseous effluent nonitoring instrumentation that was not corrected within the tine specified in Technical Specifications 3.3.3.10 or 3.3.3.11.

8. 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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