ML20245L259

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Semiannual Radioactive Effluent Release Rept 9 for Period Jan-June 1989
ML20245L259
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/30/1989
From: Bailey J, Boyer G
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NO-89-0151, NO-89-151, NUDOCS 8908220055
Download: ML20245L259 (25)
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  1. LF CREEK W@ NUCLEAR OPERATING Np^  ;. August 17, 1989 Nucteer operWW ~

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NO 89-0351' U.:S. Nuclear Regulatory Commission ATTN: ' Document Control Desk Mail' Station'P1-137

-Washington, D. C. 20555

Subject:

Docket.No.:50-482: Semiannual Radiological-Effluent Release

-Report Gentlemen:

Enclosed ' is' the Wolf Creek Generating Station (WCGS) Radiological Effluent

Release Report
covering the; period'from January 1, 1989 to June-30, 1989.

This report' is submitted pursuant to section 6.9.1.7 of the WCGS, Unit

.No.:1. Technical Specifications.

Very truly yours, M& .

. John A. Bailey Vice President Nuclear Operations JAB /aem

,> Enclosure cci- B. L. Bartlett (NRC), w/a

- E. J . Holler (NRC), w/a R..D. Martin (NRC), w/a D. V. Pickett (NRC), w/a 8908220055 890630 PDR ADOCK 05000482 R FDC 7

P.O. Ekm 411/ Burhngton. KS 96839 / Prone: (316) 364-8831

~ An Equal Opportunity Employer MHCVET

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Encicsurt to NO~ 89-0151-M/i: .:;pd f 1.of 24 NorE GEEK NUCLEAR OPERATIIG ONPORATICN Nblf Creek Generating Station Docket No: 50--482 Facility Operating Idcense Not NPF-42 SEMIAleKEL RADIOMTIVE EFFIIJENT RE2 HSE REBWT Report No: 9 Reporting Period: January 1, 1989 through June 30, 1989 Fx w ed by: Merlin G. Willi -

Approved by:

C. D f4yer' Plant Ihnager

' J . i, Enclo:;uro to NO 89-0151 Page 2 of 24 ErnrYFfIVE SWeGRY h purpose of the S miannual Radioactive Effluent Release Report is to report on the quantities of liquid and gaseous effluents and solid waste released from Wolf Creek Generating Station (NOGS). 'Ihis w3mi, covers the period beginning on January 1,1989, and ending on June 30, 1989.

Section I provides a sumary of the quantities of radimetive liquid and gaseous effluents for this reparting period.. h format is s12nilar to that r+>-- udad in Regulatory Guide 1.21, Revision 1. An elevated release pathway does not exist at Wolf Creek Generating Station, therefore, all aiv+mme releases are considered to be ground level releases. The concurrent meteorological condition gaseous pathway dose determination is met by the Wolf Creek Offsite Dose ('almlation Manual methodology of assigning all gamla pathways to a hypothetical individual residing at the highest annual X/O and D/Q location. 'lhis results in a conservative estimate of dose to a nw;ex of the public rather than determining each pathway dose for each release cmdition. A conservative errar of thirty percent has been estimated in effluent data. Meteorological data for the period of January 1, 1989 through June 30, 1989, is available ansite for review and inspection.

Section II provides Supplemental Information as described in Regulatory I Guide 1.21, Revision 1.

Section III provides additional information required by Technical Specification 6.9.1.7.

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SEn!.1"zuro to NO 89-0151 p Ks e fP gt 3 cf 24~

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'lhh1a of Cantah i

EDGE Section I w, . . .

4 Liquid Radioactive Effluents. 4

Dose Sunmary .

8-

- AisluuaRadirmctive Effluents 10 Dose Sumary 14 E Section II 16 Regulatory Limits 16 Maxinum Permissible Canoentrations _

17 Measurements and 4pmrinations of Total Radioactivity

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~ Batch Releases 20 Continuous Releases 20 Abnamal Releases 20 Solid Waste' 24,r=mts 21' Tmvitated Fuel Shipnents 22 i Section III 23 Unplanned Releases 23 Process Control Ec v cuu 23 Offsite Dose Palm 1ation Manual 23 Major Changes to Liquid, Gaseous or Solid Radwaste Syste s 23 Iand Use Census 23

' Radioactive Shipnents .

23 Innrv:n-mhility of Airborne Effluent Mcmitoring Instrumentation 23 Storage Tanks 23 i

1 cm_______________ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _]

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3- " Enclo:uro to'NO 89-0151 SPI T I Oi I E

Page 4 of 24 Year 1989 REFmT OF RADIOACTIVE EFFWENPS: LTOUID Unit Quarter Quarter 1 2 A. Fission and Activation Products a

1. 'Ibtal Release (not includim tritium, aases, alphai Ci 1.95E-01 5.48E-02 l .

l: 2 Averaae diluted canoentratim durino period uCi/ml 7.66E-08 1.70E-08 (1) 3 Percent of Apolicable Limit  % 3.90E+00 1.10E+00 B, Tritium

1. 'Ibtal Release Ci 9.23E+00 1.19E402
2. Averaae diluted concentration durina period uCi/ml 3.62E-06 3. 68E-0:. ..

(2)

,3 Percent of Apolicable Limit  % 1.21E-01 1.23E+00 C. Dissolved and Entrained Gases .

1 'Ibtal Release Ci 8.84E-04 5.46E-03

2. Averaae diluted concentration durim period uCi/ml 3.47E-10 1.69E-09 (3)
3. Percent of Aeolicable Limit  % 1.74E-04 8.45E-04 3 D. Gross Aloha Radioactivity

_l '. 'Ibtal Release ci 0.00E+00 0.00E+00 E. Voltme of waste released (prior to dilution) liters 6.25E+06 1.10E+07 F. Volume of dilution water used liters 2.54E+09 3.22E+09

1. The applicable limit for the Wolf Creek Generating Station is five (5) Curies per year.

(Reference 10CFR50, Appendix I, " Guides On Design Objectives Far 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. '1his value is derived by the following fomula:

% of Applicable Limit = (Averace diluted cmoentration) (100)

(MPC, Appendix B, Table II 10CFR20)

3. This value is derived by the following fomula:

% of Applicable Limit = (Averace diluted conmntration) (100)

(2E-4 frtxn Technical Specification 3.11.1.1)

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Enclosura to NO 89-0151 Year 1989 -

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! IJQLilD EFFIIINES Cbntinuous Mode Batch Mode E NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1 2 1' 2 H-3 Ci 5.48E-02 3.94E-01 9.18E+00 1.19E+02 Sr-92 Ci 0.00E+00 0.00E&OO 2.79E-05 1.10E-05' Cr-51 Ci 0.00E+00 0.00E+00 1.29E-03 0.00E+00 h 54 Ci <2.74E-03 c5.16E-03 6.93E-03 4.45E-04 Aa-110M Ci 0.00E+00 0.00E+00 1.33E-04 2.57E-05 NS5 Ci <5.48E-03 <1.03E-02 1.78E-02 3.43E-02 h 59 ~ Ci <2,74E-03 <5.16E-03 7.96E-04 2.70E-05 Co-58 Ci <2.74F-03 <5.16E-03 1.40E-01~ 1.27E-02 00-60 Ci <2.74E-03' <5.16E-03 1.86E-02 5.36E-03 Zn-65 Ci <2.74E-03 <5.16E-03 <3.93E-04 <3.37E-04 h 97 Ci 0.00E+00- 0.00E+00 9.98E-05 4.32E-05 1 Zr-95 Ci 0.00E+00 0.00E+00 1.60E-04 1.01E-05 h 95 Ci 0.00E+00 0.00E+00 4.31E-04 2.21E-05 h 99 Ci <2.74E-03 <5.16E-03 <3.93E-04 <3.37E-04 I-131 Ci <5.48E-03 <1.03E-02 <7.85E-04 2.06E-05 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 6.24E-05 Cs-134 Ci <2.74E-03 <5.10E-03 1.94E-03 1.69E-04

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Enclosuro to NO 89-0151 Year 1989 Page 6 of 24 LIQUID EFFIIIENIS 1

l Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1 2 1 2 Cs-137 Ci <2.74E-03 <5.16E-03 2.49E-03 2.29E-04 La-140 Ci 0.00E+00 0.00E+00 1. 97E--05 0.00E+00 Ce-141 Ci <2.74E-03 <5.16E-03 <3.93E-04 <3.37E-04 Ce-144 Ci <2.74E-03 <5.16E-03 <3.93E-04 <3.37E-04 Kr-85M Ci <5.48E-02 <1.03E-01 <7.85E-03 <6.74E-03 Kr-85 Ci <5.48E-02 <1.03E-01 <7.85E-03 <6.74E-03 Kr-87 Ci <5.48E-02 <1. 03E.-01 <7.85E-03 <6.74E-03 Kr-88 Ci <5.48E-02 <1.03E-01 <7.85E-03 <6.74E-03 Xo-131M Ci <5.48E-02 <1.03E-01 <7.85E-03 1.59E-04 Xe-133M Ci <5.48E-02 <1.03E-01 <7.85E-03 <6.74E-03 Xe-133 Ci <5.48E-02 <1.03E-01 8.46E-04 5.29E-03 3

Xe-135M Ci <5.48E-02 <1.03E-01 <7.85E-03 <6.74E-03 Xe-135 Ci <5.48E-02 <1.03E-01 3.79E-05 5.82E-06 Ar-41 Ci <5.48E-02 <1.03E-01 <7.85E-03 <6.74E-03 Sr-90 Ci <2.74E-04 <5.16E-04 <3.93E-05 <3.37E-05 Sr-89 Ci <2.74E-04 <5.16E-04 <3.93E-05 <3.37E-05 Sn-113 Ci 0.00E+00 0.00E+00 2.02E-05 0.00E+00 Co-57 Ci 0.00E+00 0.00E+00 5.10E-04 1.08E-04 1

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!.- Enc 10 sura to NO 89-0151 Year 1989 Page 7 of 24 LIQrJID EFFMENIS Continuous Mode Batch Mode NUCLTDES $

Quarter Quarter Quarter Quarter RELFASED Unit 1 2 1 2 Sb-124 Ci 0.00E+00 0.00E+00 2.27E-04 1.99E-05 Sb-125 Ci 0.00E+00 0.00E+00 3.63E-03 1.16E-03 Gross Aloha Ci <5.48E-04 <l.03E-03 <7.85E-05 <6.74E-05 5

Note: Inss than values are calculated using the lower limit of detection (ILD) values obtainod 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 strination for the total release values.

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.. Enclatura t3 NO.89-0151. Year 1989

- PJg3 8 of 24 LIGIID (IMHATIVE DOSE SGdMAIE

'mBW 1 ODCM TEO NICAL1 CAICUIATED SPECIFICATICH  % OF DOSE LIMIT LIMIT QUARTER 1 OF 1989 70 PAL DOSE (nrem) IM BONE 1.94E-02 5.00E+00 3.88E-01 70mL DOSE (nrem) POR LIVER 4.60E-02 5.00E+00 9.20E-01 torAL DOSE (nrem) POR YUmL BODY 3.73E-02 1.50E+00 2.49E+00 70mL DOSE (nran) FOR THYROID 1.16E-02 5.00E+00 3.32E-01

'10mL DOSE (nran) FOR KIONEY 2.28E-02 5.00E400 4.56E-01 SURL DOSE-(nran) FOR IDG 1.54E-02 5.00E+00 3.08E-01

,. 70mL DOSE '(nran) FOR GI-LLI 2.89E-02 5.00E+00 5.78E-01 QUARTER 2 OF 1989 .

70mL DOSE.(nran) PTR BONE 1.40E-03 5.00E+00 2.80E-02 20mL DO3E (nran) FOR LIVER 2.23E-02 5.00E+00 4.46E-01 TUML DOSE (mran) IIR TOBL h)DY -2.17E-02 1.50E+00 1.45E+00 TOTAL DOSE (mten) FTR 3HYROID 2.01E-02 5.00E+00- 4.02E-01, TOTAL DOSE (nrun) PCR KIDNEY 2.07E-02 5.00E+00 4.14E-01 somL DOSE (nran). FOR IDG 2.04E-02 5.00E+00 _4.08E-01 4.28E ~

70&L DOSE (mten) FOR GI-LLI 2.14E-02 5.00E+00 YEAR-70-DATE TURIS FOR 1989 TURL DOSE (nran) FOR BONE 2.08E-02 1.00E401 2.08E-01'

'IUmL DOSE .(nrem) FOR IJVER. 6.83E-02 1.00E+01 6.83E-01 20fAL DOSE (nrem) . FOR TOTAL BODY 5.90E-02 3.00E+00 1.97E+00 3.17E-02 1.00E+01 3.17E-01 N ' 70mL DOSE,(mran) PCR UHYROID 4.35E-02 1.00E401 4.35E-01 TUML DOSE (mtun) FCR KIDNEY

'IUTAL DOSE (mtun) FTR IDG 3.58E-02 1.00E+01 '3.58E-01

'IUTAL DOSE (mrun) FOR GI-LLI 5.03E-02 1.00E+01 5.03E-01

' l Based m hhnical Specification 3.11.1.2 which restricts dose to the whole body to less than or equal to 1.5 mran per quarter and 3.0 mten per year. Dose restriction ~to any organ is less than or equal to 5 mten per quarter and 10 mrem per year.

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. Enc 13sur3 to NO 89-0151 Year 1989 Page 9 of 24 LIQUID COMUIATIVE DOSE SCMWE

'lNLE 2 A, Fission & Activation Products Ouarter 1 Ouarter 2 ibtal (not including H-3,

1. Total Release - cases, alphai C1 1.95E-01 5.48E-02 2.50E-01
2. Maximum Oruan Dose (mtun) 3.44E-02 2.30E-03 3.67E-02
3. Ornan Dose Limit fmrm) 5.00E+00 5.00E+00 1.00E+01
4.  % of Limit 6.88E-01 4.60E-02 3.67E-01 B- Tritium
1. Total Release Ci 9.23E+00 1.19E+02 1.28E+02 2- Maximum Ornan Dose (mrm) 1.16E-02 2.00E-02 3.16E-02 3 Oruan Dose Limit (mrm) 5.00E+00 5.00E+00 1.00E+01
4.  % of Limit 2.32E-01 4.00E-01 3.16E-01 Yhi2 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.

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, Enc 1: sura to NO 89-0151 Year 1989 i Page 10 of 24

j. REPCRT OF RADIOACTIVE EFFwENTS: AIRIERNE

! Quarter Quarter ]

j Unit 1 2

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i' A. Fission & Activation Gases 1 Total Release Ci 5.71E+01 1.26E+02 ,

t 2 Averaae release rate for period uCi/sec 1.13E+02 1.30E+02 l (1)  ;

3- Percent of 'Ibchnical Specification Ilmit  % 4.26E-02 9.87E-02 B. Todines

1. Total Iodine-131 Ci 0.00E+00 0.00E400 24 Averaae release rate for period uCi/sec 0.00E+00 0.00E400 (2) 3- Percent of Arolicable Limit  % 0.00E+00 0.00E+00 C- Particulate
1. Particulate with half-lives > 8 days Ci 5.36E-06 0.00E+00 2 Averaae release rate for period uCi/sec 6.89E-07 0.00E+00 (3) 3 Percent of 'Ibchnical Specification Limit  % 9.88E-04 0.00E+00

_4. Gross Alpha radioactivity Ci 0.00E+00 0.00E+00

1. D. Trititun
1. Total Release Ci 8.02E+00 1.49E+01
2. Averace release rate for period uC1/sec 1.07E+00 2.34E+00 (4)
3. Percent of 'Ibchnical Specification Limit  % 7.63E-02 1.41E-01
1. The percent of Technical Specification Limit for fission and activation gases is calculated using the following methodology:

% of Technical Specification Limit = (Ouarterly total beta airdose)(100) 10 mrad

2. The percent of applicable limit for iodine is calculated using the following methcxlology:

% of Applicable Lixit = (Total Curies of Iodine-131)(100) 1 Curie (Reference 10CFR50, Appendix I, " Guides On Design Objectives For Light-Water-Cooled Nuclear P7Wer Reactors", paragraph C.2.)

j Encic;;uro to NO .89-0151.

Page 11'of 24

' .3 'Ihe percent of Technical: Specification limit' for particulate' is m1mlated using .the following metherblegy:

. e i % of Technical: Specification Limit = (Hichest oman dose due to particulate)(100) 7.5 mean 74'.. The percent of Technical Specification limit for tritium is calculated using the following methodology l ,

. '% 'of Technical Specification Limit = (Hiohest oman dose due to H-3)(100)

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7.5 mren

'Eis type of mili+lvis used since the Nblf Creek Technical WHications tie releases to thaaa rather than Curie release rates.

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. Encicsura to NO 89-0151 Year 1989 )

Page 12 of 24 i GASEDUS EFFIDENIS Continuous Node Batch Mode NUCLIDES Quarter Quarter Quarter Quarter REITASED thit 1 2 1 2

1. Fission and Activation Gases Ar-41 Ci 0.00E+00 1.16E+00 3.53E-01 8.91E-01 Kr-85 Ci 0.00E+00 0.00E+00 6.03E-02 1.75E-01 Kr-85M Ci 0.00E400 6.71E-02 9.80E-03 2.62E-02 Kr-87 Ci <1.23E+01 <1.36E+01 <1.60E-02 <3.84E-02 Kr-88 Ci <1.47E+01 <1.62E+01 <1.91E-02 2.65E-04 Xe-131M Ci 0.00E+00 0.00E+00 4.40E-02 8.48E-01 Xe-133 Ci 3.56E+01 8.02E+01 2.06E+01 3.99E+01 Xe-133M Ci <3.55E+01 <3.90E+01 2.55E-01 4.53E-01 Xe-135 Ci <4.35E+00 2.20E+00 1.59E-01 4.29E-01 Xe-138 Ci <3.65E+02 <4.02E+02 <4.74E-01 <1.14E400

'Ibtal Ci 3.56E+01 8.36E+01 2.15E+01 4.28E401 2 2. Halocens (Gaseous)

I-131 Ci <2.36E-04 <2.60E-04 <3.06E-07 <7.35E-07 I-133 Ci <2.36E-02 <2.60E-02 <3.06E-05 <7.35E-05 Total Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

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. . Enclcsura to NO 89-0151 Year 1989 Page 13 of 24 GASEUS EFEWERIS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter .

REITASED Unit 1 2 1 2

3. Particulate H-3 Ci 8.01E+00 1.47E+01 7.95E-03 2.01E-01 CO-58 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Cb-60 Ci 5.36E-06 <2.60E-03 <3.06E-06 <7.35E-06 Mn-54 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Fe-59 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Zn-65 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Mo-99 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Cs-134 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Cs-137 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Ce-141 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Ce-144 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06

) Sr-89 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Sr-90 Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 Gross Alpha Ci <2.36E-03 <2.60E-03 <3.06E-06 <7.35E-06 1

Note: less than values are calculated using the lower limit of detection (IZD) values obtained at Wolf Creek Generating Station maltiplied by the volume of air discharged during the respective quarter. The less than values are not included in the sumantion for the tctal release values.

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Enc 1x ura to CO 89-0151 Year 1989 Page 14 of 24 Table 1 e

TECHNICAL 1 srECIF1cATIm s Or QUARTER 1 OF 1989 LIMIT LIMIT DOSE FRCH RADIOIODINES, PARTICULATE, AND TRITIQi AT CON 1pmLTtG IOCATICE:

'IOTAL DOSE (mrun) FOR BCNE 6.58E-05 7.50E+00 -- 8.77E-04

'IOTAL DOSE (mtun) EUR LIVER 5.79E-03 7.50E+00 7.72E-02

'IOTAL DOSE (mrun) FOR 'IOTAL BODY 5.79E-03 7.50E+00 7.72E-02

'IUIAL DOSE (mrun) KR TkMOID 5.78E-03 7.50E+00 7.71E-02

'IOTAL DOSE (mtun) Em KIDNEY 5.78E-03 7.50E+00 7.71E-02

'IDIAL D3SE (mtun) KR LUG 5.79E-03 7.50E+00 7.72E-02

'IUPAL DOSE (mrun) FOR GI-LLI 5.79E-03 7.50E+00 7.72E-02 QUARTER 2 OF 1989

, DOSE FRCM RADIOIODINES, PARTICEATES, AND 'JRITRM AT OCNIBmLTIG IDCATION:

'IDIAL DOSE (mrun) KR BONE 0.00E+00 7.50E+00 0.00E+00

'IDIAL DOSE (mtun) KR LIVER 1.06E-02 7.50E+00 1.41E-01

'IUIAL DOSE (mran) KR 'IUIAL BODY 1.06E-02 7.50E+00 1.41E-01

'IUIAL DOSE (mren) EUR THYROID 1.06E-02 7.50E+00 1.41E-01

'IOTAL DOSE (mtun) KR KIDNEY 1.06E-02 7.50E+00 1.41E-01

'IUIAL DOSE (mren) FOR IIRG 1.06E-02 7.50E+00 1.41E-01

'IUfAL DOSE (mrun) IOR GI-LLI 1.06E-02 7.50E+00 1.41E-01 YEAR 'ID-DATE 'IDIALS FOR 1989 DOSE IRCH RADIOIODINES, PARTICEATES, AND 'IRITRE AT CONIpmLTIG IOCATION:

'IUfAL DOSE (mtun) FOR BONE 6.58E-05 1.50E401 4.39E-04

'IUIAL DOSE (mtun) FOR LIVER 1.64E-02 1.50E401 1.09E-01 4 'JOTAL DOSE (mrun) FOR 'IUIAL 10DY 1.64E-02 1.50E+01 1.09E-01

'IOTAL DOSE (mren) FOR 'JHYROID 1.64E-02 1.50E+01 1.09E-01

'IUIAL DOSE (mren) IUR KIDNEY 1.64E-02 1.50E+01 1.09E-01

'JUTAL DOSE (mran) EUR IIRG 1.64E-02 1.50E+01 1.09E-01

'IDIAL DOSE (mren) EOR GI-LLI 1.64E-02 1.50E+01 1.09E-01

1. Based cm Walf Creek 'Ibchnical Specification 3.11.2.3 which restricts dose during any calender quarter to less than or equal to 7.5 mtun to any ogan and during any calender year to less than or equal to 15 mran to any organ.
  1. Bac10 sura to NO ' 89-0151 L

,' "' .; Year 1989 L Page 15 of 24 GASBOUS C[BGATIVE DOSE StBE9dE TAB 2 2 tA.' Fission and Activiation Gases Ouarter 1 Ouarter 2 Total li Total Release (C1) 5.71E+01 1.26E+02 1.83E+02 2e Total Ganna Airdose (nradi- 1.64E-03' 4.67E-03 6.31E-03

3. Ganna Airdose Limit 5.00E+00 5.00E+00 1.00E+01
4.  % of Ganne Airdose Limit ' 3.28E-02 9.34E-02 6.31E-02
5. - Total Beta Airdose (mrad) 4.26E-03 9.87E-03 1.41E-02
6. Beta Airdose Limit (nrad) 1.00E401 1.00E+01 2.00E+01
7.  % of Beta Airdose Limit 4.26E-02 9.87E-02 7.07E-02' B. Particulate
l. Total Particulate (Ci)' 5.36E-06 0.00E+00 5.36E-06
2. Mart == Otuan Dose (mrun) 7.41E-05 0.00E+00 7.41E-05 3- Oruan Dose Limit (nrem) 7.50E+00 7.50E+00 1.50E+01
4.  % of Lbnit 9.88E-04 0.00E+00 4.94E-04 L C. Tritium
1. Total Release (C1) 8.02E+00 1.49E+01- 2.29E+01
2. Mari== Oruan Dose (nran) 5.72E-03 1.06E-02 1.63E-02
3. 'Oruan Dose Limit (mrun) 7.50E400 7.50E+00 1.50E401
4.  % of Limit' 7.63B-02 1.41E-01 1.09E-01 D- Iodine 1- ' Total I-131 (Ci) 0.00E+00 0.00E+00 0.00E+00 2 Maximza Otuan Dose (mrem) 0.00E400 0.00E+00 0.00E+00 3- - Oruan Dose Limit (mrun) 7.50E+00 0.00E+00 1.50E+01
4.  % of Limit 0.00E+00 0.00E+00 0.00E+00 This table is included to show the correlation between Curies releasal and the associated calculated neximum organ dose. h naximum organ dose is calculated using Wolf Creek ODCM methodology which assumes that an individual actually resides at the release point. Tcx:hnical /

Specification 3.11.2.3 organ dose limits are used.

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Enclosure to NO 89-0151 i Page 16 of 24 l SECTICN II i

Supplemental Informticn Facility: Wlf Creek Generatina Station Ilmnse Runber: NPF-42

1. Regulatory Ilmits A. . For liquid waste effluents A.1 %e cx:noentration of ruitmetive material released in liquid l effluents to UNRESIRICfED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Colum 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or enMimi e gases, the concentration shall be limited to 2 x 10p~

microcurie /ml total activity.

A.2 he dose or dose ccumitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, frm each unit, to UNRESIRICI'ED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and
b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 meams to any organ.

B. For gaseous waste effluents B.1 he dose rate due to radioactive naterials released in gaseous effluents frm the site to areas at and beyond the SITE DOUNDARY Enall be limited to the following:

a. For noble gases: Isss than or equal to 500 mrms/yr to the whole body and less than or equal to 3000 mrms/yr to the skin, and
b. For Iodine-131 and 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Iess than or equal to 1500 mrms/yr to any organ.

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

a. During any calendar quarter: Inss than or equal to 5 mrads for gamm radiativa and less than or equal to 10 mrads for beta radiation, and
b. r> ring any calendar year: Iess than or equal to 10 mrads for ganna radiation and less than or equal to 20 mrads for beta radiation.

I % ;

,- --Ac1csur3 ' ta NO 89-0151 Page 17 of:24 B.3 'Ihe dose from Iodine-131 and 133, tritium, and all radionuclides in particulate foam with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:'-

a. During any calendar quarter: Iess than or equal to 7.5 mrans to any organ, and
b. During any calendar year: Less than or equal to 15 means to _any organ.

- 2.- Mari== Permissible Concentrations Water - hai in section 1.A.

Air - umu.ai in section 1.B.

3.- Average energy of flamien and activation namm effluents is not

. applicable.

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. - Enc 1: sura to NO 89-0151 Page 18 of 24

4. Measurements and Approximations of 'Ibtal Radioactivity A. Liquid Effluents LIQUID RELEASE SAMPLDG M2 HOD OF TYPE OF AL nym TYPE FREQUENCY ANALYSIS ANALYSIS
1. Batch Waste P.H.A. Principal Gamra Release P Dmtiters Tanks Each Batch P.H.A. I-131
a. daste Monitor P Dissolved cnd Tank One Batch /M P.H.A. Enminari Gases (Gamna Emitters)
b. Secondary Liquid P L.S. H-3 Waste Each Batch Monitor S.A.C. Gross Alpha Tank P O.S.L. Sr-89, Sr-90 g Each Batch O.S.L. Fe-55
2. Continous P.H.A. Principal Gamma Releases Daily Emitters Grab Sample P.H.A. I-131
a. Steam M Dissolved and Generator Grab Sample P.H.A. Entrained Gases Blowdown (Gamma Emitters)
b. Turbine Daily L.S. H-3 nni1dNg Grab Sample Sump S.A.C. Gross Alpha
c. Lhre Daily O.S.L. Sr-89, Sr-90 Sludge Grab Sample Pond O.S.L. Fe-55 I

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

M = monthly O.S.L. = perforred by an Offsite Laboratory 1

P.H.A. = gasta spectrum pulse height analysis using a High Purity l Genranium detector. i f I I

L.S. = liquid scintillation w_ _ _ _ - _ _ _ __ - _ . _ _. _

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. , . Enclosura t3 NO 89-0151 i

Page 19 of 24 l

B. Gaseous Waste Effluents SN4PLIN3 MEITED OF 'IYPE OF GASEQUS, RELEASE 'ITPE MtEQUEICY ANALYSIS ACTIVITY ANALYSIS P

Each Tank P.H.A. Principal Ganun Waste Gas Decay Tank Grab Sangle Emitters P Principal Gamna Containment Purge or Each Purge P.H.A. Emitters Vent Grab Sample Gas Bubbler and L.S. H-3 (oxide)

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

Radwaste 9dirHng M P.H.A. Principal Gamin Vent Grab Sartole Emitters-All Release Types I-131 as listed above Continuous P.H.A.

I-133 y P.H.A.

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

Cantinuous Particulate Gross Alpha Camposite Sample O.S.L.

Campasite Sr-89, Sr-90 Cantinuous Particulate Sample

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+ . - Enclecura to NO 89-0151 4

4- :Page 20 of.24

' 5. Batch Releases.

'Ihere were thirty-four (34) gaseous batch releases during the report period. The longest gaseous batch release took 42.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the shortest L -

occurred over a sixty-eight (68) minute interval' ' The average release took 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> with a total gaseous batch release time of 203 hours0.00235 days <br />0.0564 hours <br />3.356481e-4 weeks <br />7.72415e-5 months <br />.

There were 31 liquid batch releases during the report =rieri. The'

longest liquid. batch release took 195 minutes while the shortest took cnly 40 minutes. ' The avmage release time for the liquid batch releases was 115 minutes. 'Ibtal release time for all 31 liquid batch releases was 59.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

l 6. Continuous Releases L

l

'Jhere were two release pathways designated as continuous releases during this report period. They are the Lime Sludge Pond and the Turbine '

hilding Sump. At no time during this report period was Steam Generator-Blowdown diverted to Wolf Cmek Cooling Iake (NCCL).

7. Almormal Releases

'Ihere were no abnormal liquid or gaseous releases for this wru.L period.

T..

. , . Enc 10 sura t3 NO 89-0151 Page 21 of 24 EFFIDENT MO NM71E DISIOSAL SDiIANNGE REKle (1989)

SOGID NASTE SEIIPMENIS A. SOLID WASTE SHIPPED OFFSITE KR BURIAL OR DISIOSAL (Not imdiated fue1)

1. Type of mate thit 6-month Est. Total Period Error %
a. Spent resins, filter sludges, m3* 2.33E+01 evapurat.cr le;Lium, etc. Ci 1.40E-01 2.50E+01
b. Dry compressible e ste, m3* 6,79E+01 contaminated eouin, etc. C1 1.32E+00 2.50E+01
c. Tmaiated canpanents, m3* 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00
d. Other (describe) m3* 0.00E+00 Ci 0.00E400 0.00E+00 m3* = cubic meters
2. Estinate of najor nuclide cmposition (by type of waste)
a. Fe-55  % 5.64E+01 Ni-63  % 3.94E+01 Co-60  % 2.14E+00 l Ru-106  % 9.22E-01 Mn-54  % 4.98E-01 Cs-137  % 3.05E-01 Cs-134  % 2.28E-01 Co-58  % 3.20E-02 Sb-125  % 1.80E-02 Co-57  % 7.00E-03 Zr-95  % 5.00E-03 Nb-95  % 5.00E-03 Sn-113  % 2.00E-03
b. Fe-55  % 3.04E+01 Co-58  % 2.38E+01 Co-60  % 2.05E+01 Ni-63  % 1.23E+01 Mn-54  % 4.39E+00 Co-57  % 1.99E+00 Sb-125  % 1.79E+00 Fe-59  % 1.35E+00 Cr-51  % 1.25E+00 Aa-110M  % 7.76E-01 Cs-134  % 5.27E-01 Zr-95  % 5.09E-01 Sn-113  % 3.84E-01 C-14  % 5.50E-02

k .., ,

. j

.E s_ " s Encibnuro to NO.89-0151-

. , ' P233 22 cf.24

c. none
d. none  !

l

'3. Solid Waste' Disposition Ntamber of Shirmnents Mode of Trenovutiation Destination 5- Truck Barnwell, South Carolina

4. Class of Solid Maste
a. Class A-
b. Class A-

~c. Not applicable

, -d. 'Not applicable'

5. Type of Container . .

-a. LSA (Strong, tight) b.- LSA (Strong, tight)'

c. Not applicable
d. Not applicable
6. Solidification Agent'

-a. Not applicable-

b. Not applicable
c. Not. applicable y d. Not applicable B. IRRADIATED FUEL SHIPMENTS (Disposition)-

'lhere were no 4rraMated fuel shipments during this repo ting period.

9 Encicsur] to NO 89-0151 gg Page 23 of 24

1. Unplanned Releases h ere were no unplanned releases during this report period.
2. Process Control F w cuu Were were no changes to the Process Control Program during this report period.
3. Offsite Dose Calculation Manual (ODCM) mere were no changes to the CDCM during this report period.
4. Major Changes to Liquid, Gaseous, or Solid Radwaste Systems here were no changes to Ligaid, Gaseous, or Solid Radwaste systes during this report period.
5. Iand Use Census here were no new locations for dose calculations identified durirg this report period.
6. Radioactive Rhimewits 3

%ere were five shipmnts of radioactive radwaste during this report period. All five shipnents were to Barnwell, South Carolina.

7. Inoperability of Airborne Effluent Monitoring Instrumentation mere was no intwvn ahle liquid or gaseous effluent nonitoring instrumentation that was not corrected within the tine specified in Technical Specification 3.3.3.10 and 3.3.3.11.
8. Storage Tanks

%ere were no events leading to liquid holdup tanks or gaseous storage tanks exceeding the limits of Technical Specifications 3.11.1.4 or 3.11.2.6.

However, en June 16, 1989, at approximately 1000 CDP, it was disoavered that Technical Specification (T/S) Surveillance Requirment 4.11.2.6 had not been not when the quantity of radioactive naterial was not detemined within seven days of an addition to the number 6 waste gas decay tank (GDP) that occurred on June 6,1989. Chemistry personnel were notified of the discovery ard the quantity of radioactive naterial was detemined to be below T/S 3.11.2.6 limits at approximately 1015 CL7f. We details of this occurrmce were reported to the NRC in Liconsee Event Report 89-010-00.

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  • Enclosura to NO 69-0151 Page 24 of 24

'Ihe root cause of this event has been attributed to inadequate s,cmuotic controls which allowed a pumumel error by non-licensed Operations personnel to result in this failure to meet T/S surveillance require mnt. To prevent recurrence of this event, all suc.uiures l Jnvolving additions to the GUrs will be revised to require Operations personnel to notify Chanistry when any additions are nede to the GDTs.

A radwaste turnover checklist is being developed which will runind the

! operators to notify Chenistry when any additions are reade to the GDTs.

An addition has been nede to pro dure ADM 04-020, "Chenistry Surveillance Prwy.cuu", to provide Chanistry personnel a mechanism for documenting the GDP number, the date and the time of any additions to the GDPs when information is received frcrn Operations p6u.ocaual.

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