ML20059D246

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Semiannual Radioactive Effluent Release Rept for Jan-June 1990
ML20059D246
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/30/1990
From: Boyer G
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9009060172
Download: ML20059D246 (46)
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Text

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August 28,1990 NO 90-0237 i U. S. Nuclear Regulatory Comunission ATTN Document Control Desk Mail Station F1-137 l Washington, D.C. 20555 Subject Docket No. 50-482: Semiannual Radioactive Effluent i Release Report i ( Gentlemen Enclosed is the Wolf Creek Generating Station' (WCGS) Radioactive Effluent Release Report covering the period from January 1, 1990 through June 30, _1990. This report is submitted pursuant to section 6.9.1.7 of the WCGS, t i j Unit No. 1 Technical Specifications. l Very truly yours, l bL O. dL i / f I Q John A. Bailey Vice President l Nuclear Operations ( JABlaem cca R. D. Martin (NRC), w/a D. V. Pickett (NRC), w/a H. E. Skow (NRC), w/a J. S. Wiebe (NRC), w/a 000T3 L 9009060172 900630 PDR ADOCK OSO 4 2 R q'(, _,, _. s s _, s, _ An EW opporturuly Employer h4F4 CWT

s Year 1989 LIQUID N TIVE DOSE stb 84ARY TABLE 2 m. Fission and Activation Products Quarter 1 Ouarter 2 Ouarter 3 Ouarter 4 Total (not including H-3, 1. Total Release - nases, aloha) Ci 2.19E-01 4.14E-02 3.11E-01 6.51E-02 6.36E-01 2. Maximum Ornan Dose (mrem) 3.46E-02 2.20E-03 3.92E-02 4.65E-04 1.11E-01 3. Ornan Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 l 4. Percent of Limit 6.92E-01 A.aoE-02 7.84E-01 9.30E-01 1.21E+00 B. Tritium L.1. Total Release Ci 9.23E+00 1.19E+02 1_.86E+02 2.74E+02 5.88E+02 2. Maximum Ornan Dose (mrem) 1.16E-02 2s00E-02 1224X-QL_ 4.30E-02 1.04E-01 t. Ornan Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 4. Percent of Limit 2.32E-01 4.00E-01 5.8BE-01 S.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 OPQ3 methodology is used to calculate the maximum organ dose which assumes that an individual drinks the water and eats fish from the diacharge point. Technical Specification 3.11.1.2 organ dose limits are used. NOTE: For Category A.1 above (Total Release - not including H-3, gasee, 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. Estimated values for Quarter 4 have now been replaced with actual test results. I

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-) .i i n. ,J L ? 1 WOLF CREEK NUCLEAR OPERATING 00RPORATICH l lc . Wolf Creek Generatirg Station t o Docket No: 50-482 4 h* Facility Gperating Li.wwe Not NPF-42 t i SIBEDEWEBL RADRECTIVE EFFHERtr RELERSE REEUU t Report Nos= 11 I: 90 %W Periods. - January 1,1990 through June 30,199') h Ii 1 l Prepared by:. Merlin G. Williatra Approved by: Iwc5 /cA-64Av 3oyea G. D. Ibyer Plant Manager i i r; c i( ' l~ s' .f ?j 1l ':IM'i_W

u-n ~ Enclosure to NO 90-0237 Page 2 of 4% T M RR99RY '1he 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 Ge e ting Station (NOGS). This report covers the period beginning on January 1, 1990, and ending on June 30, 1990. Section I provides a swnary of the quantities of radioactive liquid and gaseous effluents for this reporting period. 'Ihe format is similar to tlat r+x++-ded in Regulatory Guide 1.21, Revision 1. An elevated release pathway does not exist at Wolf Creek Generating Station, therefore, all a airbnrne releases cae considered to be ground level releases, h 1 concurrent meteorological condition gaseous pathway dose determinaticm is i et by the Wolf Creek Offsite Dose Calculation Marual nethodology of assigning all gaseous pathways to a hypothetical individual residing at the highest annual X/Q and DfQ locaticm. 'Ihis resultr in a omservative estimate of dose to a menibar of the public rath than detern.ining each pathway dose for each release candition. A conservativs error of thirty percera has been ee, anated in effluent data. Meteorological data for the pari 4 of January 1, 1990 through June 30, 1990, is available ensite for r review and inspection. E Sections II and III provide additional infonmtion requLral by Regulatory Guide 1.21, Revision 1 and Technical Specification 6.9.1.7, respectively. I-Offsite Ibse Calculation Manual (C004), Pavision 6 was approved by the Plant Safety Review Comittee during this reporting period. A copy of the pages frun the 0004 that have been revised are incltded as Attachment 1 of this E report. provides actua values to replace the estimated values for 11guld effluents providec; II Semlannual Radioactive Effluent Release Report

10. Analysis results for tl e Fourth Quarter were not ccmpleted prior to subntission of the report. 1ctual results of Qaatter 4 liquid offluents 7

indicated Fe-55 in the liquid batch conposite and the Turbine Building simp L <m enaite. The change redJes the total curies released aad increases the cunulative dose, h incre.ase in Fe-55 was caused by the Turbine Bcilding s sunp discharge point being an undiluted waste systcm. Because analysis results for the secotrl quarter of 1990 h ve not been completed as yet, Eb-55 in liquid effluents is presented as an estimate. W

.~ _ r .*i sEnclosure to NO 90-0237-i 'P;go 3 cf 45 ., ~ r a v: a ble of Cantants L' M l I section I 4 ISpid Radioactive Effluents 4 J: Dose aranary 7 Airborne Radioactive Effluents 9 li~ Dose Stenary 11- \\ l. I:' Section II .13' k %chnical Specification Ihnits 13 Mui==. Permlasible Concentrations 14 Measurenants and Approxinaticms of Total Radioactivity 15' Batch Releases: 17 Continuoue Releness 17 Solid Naste Shipnents

18-l}

Tr=ilated Fuel Shipnents 19 i Section III.

20 thplanned or Abnomal Releases 20 3

O Process Control Pro; - 20 ~ Offsite Dose Calculation Manual 20 -.1 f' - Major Changes.to Liquid, Gaseous or Solid 'Radwaste Systans 21- ' Iand Use Census 21 ~Radf.oactive Shipnents. 21 y 'Inc. 4 rah 414ty of Airborne Effluent Manitoring Instranentation. 21 l. Stc rage Tanks 21 !i ' Attachment I t ~i Changes to Offsite Dose ?alculation Manual O L i[. - \\: i 4 7- {'l + ' -M- +

Enclosure to NO 90-0237--- I<= E -Pass.4 of=45 BBCTION I REP 0t? 0F RADIO &cTIVE EFFLUERTS (1990): LIQUID Unit > quarter-Quarter 1 -2 L A.' Fission and Activation Products .1. Total Release-(not including tritium, gases, alpha) C1 1.19E-01 ' 1.52E-01 '2. iAverage Diluted Concentration During Per o - uC1/ml 1.32E-08' 1.37E-08 id 3. Percent of Applicable Limit (1) 2 2.38E+00 - 3.04E+00-B. Tritium 11. 4 Total Release-C1

2. 93E4 02 2.21E+01:

2. Average Diluted Concentration During Period uCi/cl 3.26E-05 1.98E a - 3 Petcent of Applicabic Limit (2) I 1.09E+00-6.63E C.'- Dissolved and Entrained Gases 1. . Total Release C1 1.32E+01 6.47E-03 2. Average' Diluted Concentration During Period uCi/ml 1.47E-06 5.81E-10 - 3.: Percent-of Applicable Limit (3) 7.35E-01 2.90E-04 D. Gross Alpha Radioactivity '1'.-JTotal Release 'Ci 0.00E+00 0.00E+00 E. Volume of waste released'(prior to dilution) liters 6.92E+07 3.67E407 F.' Volume ofidilution' water used liters 8.93E+09. 1.11Et10

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

(Reference-10 CFR-50, Appendix-I " Guides On Design Objectives For Ligbt-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. 1This value is-derived by the following formula

.!'of Applicable-Limit =-(Average Diluted Concentration) (100) (HPC. Apsendix B. Table II 10CFR20) 3. This_value is derived by the following formular ir '2 of Applicable Limit = (Average Diluted Concentration) (100) (2E-4 from Technical Specification 3.11.1.1) i 4 18 s f

/ a. s' --Enclosuro to N0'90-0237-Pogs 5 of 45? e E 1.IQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES-Quarter Quarter Quarter Quarter-PRLEASED-Unit 1 2 1 2 H-3 Ci ,9.93E-02 4.51E-01 2.9as.-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 Hn-54. Ci <1.44E-02 <9.22E-03 1.31E-03 1.56E-03 1 t Fe-55 Ci <2.87E-02 <1.84E-02 4.14E-02 1.88E-02 Fe-59' Ci <1.44E-02 <9.22E-03 1.88E-03 4.55E-04 Co-57 C1 0.00E+00 0.00E+00 3.26E-05 4.10E-04 Co Ci <1.44E-02 2.73E-05 -1.45E-02 7.36E-02 i 'd$g Co-60 Ci <1.44E-02 3'19E-05 1.13E-02 3.35E-02 ) Zn-65 Ci <1.44E-02 <9.22E-03 <1.22E-03 <5.52E-04 Rb-88 Ci 0.00E+00 0.00E+00 2.85E-02 0.00E+00 Br-89 Ci <1.44E-03 <9.22E-04 <1.22E-04 <5.!2E-05 Sr-90 Ci <1.44E-03 <9.22E-O' <1.22E-04 <5.52E-05, Sr-52 Ci 0.00E+00 0.00E+' 5.57E-05 0.0u5+00 P,r-95 ~ Ci-0.00E+00 0.00E 3.38E-05 2.22E-05 t Nb-95 C1 0.00E+00 0.00E+0c 2.17E-04 1.42E-04 l Nb-97 Ci 0.00E+00 0.00E+00 6.59E-05 3.42E-06 Mo-99 Ci <1.44E-02 <9.22E-03 <1.22E-03 <5.52E-04 l Ag-110M Ci 0.00E+00 0.00E+00 1.47E-04 3.42E Sn-113 Ci 0.00E+00 0.00E+00 1.67E-05 6.46E-06 Sn-117M Cl-0.00E+00 0.00E+00 3.92E-04 0.00E+00 T Sb-124 Ci 0.00E+00 0.00E+00 6.16E-04 1.83E-03 Sb-125, Ci ' 00E+00 6.64E-05 4.56E-03 8.77E-03 l Sb-126 Ci 0.00B+00 0.00E+00 5.35E-06 3.26E-05 l I-131 Ci <2.87E-02 1.03E-06 '1.70E-04 7.90E-06 Cs-134-Ci <1.44E-02 1.52E-05 '1.45E-03 3.06E-03 Cs-137 Ci <1.44E-02 1.09E-05 1.89E-03 3.68E-03 Ba-139 Ci 0.00E+00 0.00E+00 1.74E-04 0.00E+00 La-140 Ci 0.00E+00 0.00E+00 2.23E-05 0.00E+00 i Ce-141' Ci <1.44E-02 <9.22E-03 7.08E-05 <5.52E-04 Ce-144 Ci <1.44E-02 <9.22E-03 <1.22E-03 <$.52E-04 Grosa 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 Ci <2.87E-01 <1.84E-01 4.16E-03 <1.10E-02 j + m

^ o 4 Enc'1coure to NO 90-0237 c. ca. .P g3 6 cf 45-e LIQUID EFFLUENTS i Continuous Mode Batch Mode g NUCL1 DES-Quarter ' Quarter Quarter Quarter RELEASED Unit 1 2 1- '2 Kr-85 Ci <2.87E-01 <1.84E-01 9.60E-02 <1.10E -Kr-87 Ci <2.87E-01 <1.84E-01 1.43E-04 <1.10E-02 .Kr-88 Ci <2.87E <1.84E-01 2.96E-03 <1.10E. Xe-131M Ci <2.87E-01 <1.84E-01 1.4SE-01 2.13E-04 Xe-133M Ci <2.87E-01 <1.84E-01 1.20E-01 <1.10E-02 Xe-133 C1 <2.87E-01 1.83E-05 1.27E+01 6.19E-03 Xe-135M C1 <2.87E-01 <1.84E-01' <2.43E-02 <1.10E 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. c 1 The Fe-55 value for the Second' Quarter Batch Mode is based'on/ he First Quarter t Composite results. 3 s (k l It I. l' .+ I 1; a V!

y Encic'euro-to NO 90-0237 M .- [F0337'cf45-L' LIQUID CERWLATIVE DOSE SIBSIARY (1990) TABLE 1-j ODCM TECHNICAL CALCULATED SPECIFICATION Z OF DOSE LIMIT Llgli ' QUARTER 1 0F_1990 1

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+00i,

TOTAL DOSE-(mrem) FOR TOTAL' BODY 8.24E-02 1.50E+00 5.49E+00 1
TOTAL DOSE (mrom) 70R THYROID-

'5.61E-02 5.00E+00-1.12E+00 TOTAL DOSE-(mrem) 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. LyTOTAL DOSE (mrem) FOR GI-LLI-6.96E-02 5.00E+00 1.39E+00-L iQUARTER 2 0F 1990 5.00E+00 1.79E+00 c TOTAL DOSE (mrem) FOR BONE 8.94E-02 J! TOTAL DOSE'(mrem) FOR LIVER-1.89E-01 5.00E+00-3.78E+00 t P. TOTAL DOSE (arem) FOR-TOTAL BODY-1.49E-01 1.50E+00 ' 9.93E+00 ~ TOTAL D^SE-(mrem) FOR-ThfROID 3.34E-02 5.00E+00 6.68E-01

TOTAL'D0dE>(mrem) FOR KIDNEY 8.41E-02

.5.00E+00 1.68E+00: 1 '10TAL DOSE (mram) FUR LUNG 5.08E-02 5.00E+00 l'.02E+00' -TOTAL: DOSE (mrem) FOR GI-LLI 6.73E-02 5.00E+00 1.35E+00-TOTAL:FOR-1990

3. TOTAL. DOSE (mrom) FOR BONE 1.12E-01 1.00E+01-1.12E+00 1

' TOTAL DOSE (mrem).FOR LIVER-2.82E-01 1.00E+01' 2.82E+00- -i

  • TOTAL DOSE-(mrem) FOR TOTAL BODY 2.31E-01 3.00E+00 7.70E+00

-TOTAL DOSE'(mrem) FOR THYROID. 8.95E-02 1.00E+01: 8.95E-01 l - TOTAL DOSE (mrem) FOR. KIDNEY. 1.51E-01 1.00E+01 1.51E+00 TOTAL DOSE (mvem) FOR LUNG 1,11E-01 1.00E+01 1.11E+00 !. TOTAL DOSE.(mrem) FOR GI-LLI 1.37E-01 ~1.00E+01 '1.~ 37E+00 -l B:scd on Technical. Specification 3.11.1.2 which restricts dose to thefwhole body _to less than L

cr squal to 1.5 mrem per quarter and 3.0 mrem per year,. Dose. restriction _to any organ is less-

) thnn or equal to 5 mrem per quarter and'10 mrem per yeau.' 'i 1 e l ..i q; f A

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7 ;;. i ~ '3 I Encicouro-to NO'90-0237' a. . p,. P go 8 cf'45 l.IQUID CIBIDLATIVE DOSE SIBSGARY (1990) ?u TABLE 2 j ni A. Fission and Activation Products-Quarter 1-Quarter 2 LTotal ] +

1. ' Td!si Release - (not including H-3) 1 gases, alpha) C1 1.19E-01 1.52E-01

2.71E-01 '12., Maximum Organ Dose-(mrem)4 3.44E-02 1.53E 1.87E-017 3.: Organ Dose Limit 1(mrem). 5.00E+00. 5.00E+00 1.00E+01 4.. Percent of: Limit' 6.8BE-01 .3.06E+00 1>.87E+00' t q. 8..' Tritium '1.': Total Release Ci: 2.93E+02 2.21E+01 3.15E+02-

2... Maximum Organ Dose (mram).

5.89E-02 3.56E 9.45E-02 3.5 Organ Dose Limit (mrem) 5.00E+00 5.00E+00 1.00E+01' l> ' - 4. ' Percent of' Limit' 1.18E+00 7.12E-01 9.45E-01 l "This t'able.is included to show the correlation between Curies released and the associated 5 calculated maximum organ dose. Wolf Creek ODCM methodology is'used to calculate the' maximum. Kergan dose which asoumes that an individual drinks the: water and eats. fish;from the discharge. - pointL Technical Specification 3.11.1.2 organ dose limits are used'. 1 s V I )- 1 l i 1 i 1.?t < s .i'. ,e

e Enclosure to NO 90-0237 = Papri'9 ofs 45-REPORT OF RADIO &CT1TE EFFLUENTS (1990): AIRBORNE Quarter -Quarter Unit-1 2 + JA.-. Fission end Activation Gases 1.:-Total Release. Cl-9.61E+02 1.51E+00 2. ~ Average Release Rate for Period. uCi/sec 4.40E+02 3.88E+00 3.. Percent of Technical Specification Limit (1) I 7.21E-01 1.27E-03 B. Iodines-c'1. Total Iodine-133-Ci 5.262 35-

3. 2.2E-05 2.

Average Release Rate for Period uC1/sec 6.79E-06 4.11E-06. 3.; Percent of Applicable Lindt (2) 5.26E-03 ,3.22E-03 J. :Particulates-C

1.

Particulates with Half-lives >' 8 dayo C1 '6.56E-06 7.98E-05 2. Average Release Rate for' Period uCi/sec 8.47E-07 1.02E-05 ' 3.~- Percent of' Technical Specification Limit (3) Z 4.59E-05 ,1.' 4 0E-02 4.; Gross Alpha Radioactivity Ci 4.90E-Od 0.00E+00 D.- Tritium 1 '. Total Release Ci 1.31E+00 9.37E+00 '2. Average Release Rate for Period uCi/sec 2.52E-01 1.22E+00 ' 3;- Percent'of Technical Specification Limit-(4) 2 1.25E-02 8.91E-02 1.2 The percent of Technical SpecificationElimit for fission and activation gases is calbulatsd-

using the following methodology

s I of Technical Specification Limit = (Ouarterly Total-Beta Airdose)(107) !~ 10 mrad '2. The percent of Technical Specification Limits for-icdine is calculated using the following methodology: ? of Technical Specification Limit - (Total Curies of Iodine-131)(100) 1 Curie a 3.1 The percent-of Technical Specification limit for particulates is calculated using.the I.' twing methodology: 1 of Technical Specification Limit = (Highest Organ Dose Due to Particulates)(100) 7.5 mrem 4.; The percent of Technical Specification limit for tritium is calculated using the following . methodology:. I-of Technical Gpecification Limit = (Highest Organ Dose Due to H-3)(100) 7.5 mrem " NOTER JThis type of methodology is used since the Wolf Creek Technical Specifications tie release limits to doses rather than Curie release rates, it th

? [ Enciteuro to NO 90 0237-j . P;ge-10 cf 45 ,'l GASEOUS EFFLUENTS Continuous Mode Batch Mode NUCLIDES' Quarter Quarter Quarter

Quarter, RELEASED Unit 1

2 1 2 ^ 1. Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 9.53E-01 6.15E-02 Kr-85 C1 0.00E+00 0.00E+00 .5.35E-02 1.09E-01 -Kr-85H Cl- -0.00E+00 0.00E+00 9.95E-02 0.00E+00 Kr-87 Ci <7.58E+00 <7.76E+00 <3.44E-01 <6.89E-01 Kr-88 C1 <S.97E+00 <1.02E401 5.53E-02 <9.07E-01 D Xe-131H Ci 0.00E+00 0.00E+00 1.43E+01 .8.30E-04 L4 Xe-133 C1 4.36E+01 5.68E-01 8.79E+02 7.71E-01 .1 l ' l -Xe-133H Ci <2.74E+01 <2.81E+01 1.15E+01 3.11E-04 ~ l Xe-135 Ci 1.353+00 <2.96E+00 1.05E+01 1<2.63E-01 Xe-138 Ci <2.14E+01 <2.19E+01 <9.72E-01 <1.95E+00 s Total C1 4.50E+01 5.68E-01 9.16E+02 9.43E-01 2. Halogens (Gaseous) I-131 Ci 5.26E-05 3.22E-05 <1.12E-05 ' <2.24E-05 3 I-133 Ci <2.47E-02 <2.53E-02 <1.12E-03 <2.24E-03' Total Ci 5.26E-05 3.22E-05 0.00E+00 0.00E+00 3. Particulates and Tritium H-3 C1 1.07E+00-9.24E+00 2.40E 1.36E-01 C0-58 Ci 6.52E-06 <2.53E-03 <1.12E-04 <2.24E-04. Co-60 Ci <2.47E-03' 7.53E <1.12E <2.24E-04 Hn-54 C1 <2.47E-03 4.50E-06 <1.12F-04 <2.24E-04 Fe-59 Ci <2.4'E-03 <2.53E-03 <1.12E <z.24E-04 2n-65 Ci <2.47E-03 <2.53E-03 <1.12E-04 <2.24E-04 Ho-99 Ci- <2.47E-03 <2.53E-03 <1.12E-04 <2.24E-04 Cs-134 Ci <2.47E-03 <2.53E-03 <1.12E-04 <2.24E-04. Cs-137 C1 <2.47E-03 <2.53E-03 <1.12E-04~ <2.24E-04 Co-141 C1 <2.47E-03 <2.53E-03 <1.12E-04 <2.24E-04 Ce-144 Ci <2.47E-03 <2.53E-03 <1.12E-04 <2.24E-04 Sr-89. Ci <2.47E-03 <2.53E-03 <1.12E-04 <2.24E-04 Sr-90 C1 <2.47E-03 <2.53E-03 <1.12E-04 <2.24E-04 Gross Alpha C1 4.90E-08 <2.53E-03 <1.12E-04 <2.24E-04 l Total C1 1.07E+00 9.24E+00 2.40E-01 1.36E-01 NOTE: Less than values for Noble Gases are calculated using the lower limit of, [ detection (LLD) values obtained at Wolf Creek Generating Station multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates the Technical Specification LLD values are used. l" l s i 4

Enclosure to NO 90-0237-

  • /

Pago=11 of 45f tb e GASEOUS CIBWIATIVE DOSE stb 04ARY (1990) Table 1 ODCH TECHNICAL CALCULATED SPECIFICATION. 2 0F' , QUARTER l'0F 1990_ DOSE LIMIT

ggI,

. TOTAL DOSEL(arem) FOR BONE 9.24E-05 7.50E+00 1.23E-03 TOTAL DOSE (arem)'FOR LIVER 1.03E-03 7.50E+00- -1.37E-02 TOTAL DOSE (arem) FOR' TOTAL BODY-9.92E 7.50E+00

1. 32E-02 -.

TOTAL DOSE (mrem) FOR THYROID 3.10E-02 7.50E+00 4.13E-01 TOTALfDOSE (mrem) FOR KIDNEY 1.09E-03 7.50L+00-1.45E g i;.T07 % DDSE (mrem) FOR LUNG 9.40E-04 7.50E+00 1.25E-02, .70t4 DOSE' (mrem) FOR GI-LLI 9.49E-04 7.50E+00 1.26E-02 QUAR'TER=2 0FL1990 ' TOTAL DOSE.(mrem) FOR BONE-9.83E-04 7.50E+00 l'.31E-02 TOTAL DOSE (mrom) FOR LIVER 7.69E-03 7.50E+00 1.02E-01 TOTAL DOSE (mram) FOR TOTAL BODY 7.71E-03 7.50E+00 1.03E-01' d TOTAL DOSE (arem) FOR, THYROID 2.60E-02 7.50E+00 '3.47E TOTAL DOSE (mrom) FOR KIDNEY-7.70E 7.50E+00 1.03E-01 TOTAL' DOSE:(mram) FOR LUNG, 7.65E 03 7.50E+00 1.02E-01t . TOTAL DOSE (mrem) FOR GI-LLI 7.73E-03 7.50E+00 1.03E-01 TOTALS =FOR 1990: 1 TOTAL DOSE (mrem) FOR BONE 1.08E-03 1;50E+01 7.20E-03 t, TOTAL DOSE.(mrem)'FOR LIVER 8.72E-03 1.50E+01' 5.81E-02 TOTAL DOSE:(mrem) FOR TOTAL BODY 8.70E-03 1.50E+01 5.80E-02 ,_ TOTAL DOSE _(mrem)_FOR THYROID 5.70E-02 1.50E+01 3.80E 01' 1 TOTAL DOSE (mrem) FOR KIDNEY 8.79E-03 1.50E+01 5.86E-02 -- TOTAL DOSE (mrem) FOR. LUNG 8.59E-03 1.50Et01 5.73E-02 JTOTAL DOSE (mrem) FOR GI-LLI 8.68E-03' 1.50E+01 '5.79E-02 t-1. Based 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- . calender year to less than or equal to 15 mrem to any organ. s I t .4 V y

' ' - Encicsura to NO 90-0237.. LPag1 12.of 43 GASEOUS CLEGULATIVE DOSE SIRt(ARY (1990) TABLE 2 Nuclides Released Quarter 1-Quarter 2 Total A.: Fission and Activation Gases 1. Total Release (C1) 9.61E+02 1.51E+00 9.63E+0? - t 2.H Yotal Gamma Airdose'(mrad) 2.54E-02 7.30E-05 2.551.-37 3. Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 -1.00E 01 4.- Percent.of Gamma 3 'Airdose Limit-5.08E-01 1.46E-03 2.55E-01 '5. Tota) Beta Airdose (mrad) 7.21E-02 1.27E-04 7.22E-02' 6~ . Beta Airdose Limit (mrad) 1.00E+01 1.00E+01 2.00E+01 7.- Percent of Beta Airdose Limit (mrad) -7.21E-01 1.27E-03 3.61E B. Particulates 1. Total Particulates (C1) 6.56E-06 7.98E-05 8.64E-05 2. Maximum Organ Dose (mrem) 3.44E-06 1.05E-03 1.05E-03 3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 1.50E+01 4. Percent of Limit 4.59E-05 1.40E-02 -7.00E-03 C. . Tritium f -1. Total Release (C1) 1.31E+00 9.37E+00 1.07E+01 2.- Maximum Organ Dose (mrem)' 9.34E-04 6.68E-03 7.61E-Ob'

3.

Organ Dose Limit (mrem) 7.50E+00 7.50E+00

1. 50Ei L1-

'4.= Percent of Limit-1.25E-02 8.91E-02 5.07E 02 s-D.= Iodine

1..' Total I-131, 1-133 (C1) 5.26E-05 3.22E-05 8.48E-05 g

-2 Maximum Organ-Dose.(mrem)- 3.01E-02 1.84E-02 4.85E-02

3.. Organ DoseJLimit (mrem) 7.50E+00 7.50E+00 1.50E401-4..

Percent of Limit 4.01E-01 2.45E-01 3.23E-01 iThis' 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 rathodology which assumes-that an individual actually resides at the release. point. Technical vsp cification 3.11.2.'3 organ dose limits are used. D l M w

m Enclosura to NO 90-0237. 4r i }o .Page 13 of 45. s siglaser.tal Infcemati:n l Facility : Wolf.CE90k Germatina Station Iiicense Nunber:' NPP-42 1. Technical Specificatica Limits-A. - For liquid waste eifluents l A.1 The ocncentration of radioactive naterial relecsed in liquid i s effluents to 12 IRES 7RICI'ED AREAS shall be limited to the-t' concentraticms specified in 10CFR20, Appectiix B,' Table II, Coltan gases. For dissolved or en 1 2, for radionuclides other than dissolved c.? entrained noble, i: L shall be limited to 2 x 10 p noble gases, the concentration microcurie /ml total activity _. u A.2 The dow or dose camitment to a MEMBER 07 THE PUBLIC frm - radicoctive naterials in liquid effluents released, frun each unit, to UNRESTRICTED AREAS shall be limitedt. a. During any. calendar quarter _to less than or equal to 1.5 arems to.the whole body and to less than or equal to 5 mrm s to any organ, ard b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems.to arc ( organ. ) B. For gaseous waste effluents t" 8.1 2he dose rate due to radioactive materials released in gaseous effluents frm the site to areas at and bs3md the SITE BOUNDARY shall be. limited to the following: a. For noble gases: Iass than or equal to 500 mrms/yr to the - whole body and less than or equal to 3000 mrems/yr-to the skin, and b. For Icxiine-131, Iodine-133, tritium, and al1' radionuclides in particulate form with half-lives greater than 8 days: Iass than or equal to 1500 mrms/yr to any organ. B.2 The air dose due to noble gases released in gaseous effluents, 3 frcm each unit, to areas' at ard beyond the SITE BOUNDARY shall be limited to the following: ) a. During any calendar quarter: Iess than or equal to 5 mrade, for'gama radiation and less than or equal.to 10 mradsefor . beta radiation, and L_ b. During any calendar year Iess than or equal to 10 mrads p-for gamna radiation and less than or equal to 20 mrads for l' beta radiation. 6 l$ 7 x

Encicsuri to'N0'90-j237 - P;ge.14 of 45. 'B.3 'the does fran Iodine-131, Iodine-133, tritium, 'and all radionuclirlan in particulate form with half-lives greater than 8 days in gaseous effluents released to' areas at and beyard the SITE BotNARY shall be limited to the followings, a. Dt' ring'any "alardar quarter: Less than or equal-to-7.5 nnd mrums to a- ~ a year Issa than or equal to 15 means b. During arrj 1 to any or, - 2.. Maxt== Permissible Ccmoentrations Nster - covered in Section 1.A.

Air

- covered in Section 1.B. ~t l -- l L - 3. Average energy of fission and activation gaseous effluents'is not applicable. i V l t { L l l i' Ni i i l$ I' + t a . i

'y Enc 1:suro.to NO 90-0237' l ~ ~ P;gs 15.of 45 i l lt

4..

Measuzunents and Approxinations of Total Radioactivity A. Liquid Effluents-M LIQUID RE 2ASE SAMPLIlG METHJD OF TYPE OF ACI'IVITY f TYPE PREQUENCY ANALYSIS ANALYSIS 's j e i J

1. Batch Naste P.H.A.

Principal Gamna Release P Entniters Tanks Each Batch P.H.A. I-131 L

a. Waste

) Monitor P Dissolved and i,, j; Tank One Eatch/M P.H. A. - Entrained Gases 'y (Ganna Bnitters)

b. Secondary Liquid

.P L.S. H-3 Waste Each Batch Manitor S.A.C. Gross Aloha Tank P O.S.L. Sr-89. Sr-90 L Each Batch l 0.S.L. Pe-55

2. Continous P.H.A.

Principal Gamma e L l' Releases Daily Dnitters Grab Sanple P.H.A. 'I-131 I

a. Steam M

Dissolved and Generator-Grab Sanple P.H.A. Entrained Gases Blowdown (Game Buitters) ,t c'1 i'

b. Turbine Daily L.S.

H-3 Building Grab Sanple Sunp S.A.C. Gross Aloha l D

c. Lime Daily O.S.L.

Sr-89, Sr-90 Sludge Grab Sanple Pond O.S.L. Fe-55

q l

P = prior to each batch S.A.C. = scintillaticn alpha counter l! M = nonthly O.S.L. = perform 3d by an offsite laboratory 1 L. S. = liquid scintillatica L P.H.A. = gamm spectrum pulse height analysis using a High Purity Germnium detector. t I ~> 3 b .l--...-- -A-

7- ~ J. p Enclcsure:to NO 90-0237 5 P;go 16 cf.45 I, B. - Gaseous Waste' Effluerite d i. 1 SAMPLDG M2If0D T TYPE OF 1 -; GASB00S, REL5iSE TYPE PREQUENCY ANALYSIO ACTIVITY Al& LYSIS P Each Tank P.H.A. Principal Gama Waste Gas Decay Tank Grab Sanple Buitters P Principal = Ganima l Containnent Purge or Each Purge P.H.A. Bnitters L Vent Grab Sanple ; Gas Bubbler and L.S. H-3 (oxide) r incipal Gemna l; . Unit Vent M P.H.A. J 'tters 4 Grab Sanple Gas Bubbler and L.S. H-3 (oxide)' i I ' Radweste 2dldLN M P.H.A. Principal Ganma Vent Gr4 Sarrole Bnitters { All Release Types I-131 as listed above Continuous P.H.A. L I-133 P.H.A. Continuous Particulate Principal Gauna Sanole Dnitters S.A.C. Continuous Particulate-Gross Alpha Cmoosite sanole ll O.S.L. l~ Cmposite Sr-89, Sr-90 m. Ccritinuous Particulate l-Sanole ~ 1 1 I, l' \\ 1 k L ? - i'? 'I [,

Enciesuro to NO 90-0237. 1 -P:ge 17 cf 45 4i J P., l ,5. Batch Relaaman 'there were 34 gaseous batch releases during the reportire pericd. T. 'Ihe longest gaseous batch release lasted S.931 minutes, while the shortest lasted 104 minutes. 'Jhe average release lasted 2,787 minutes with a M gaseous batch release time of 94,753 minutes. 'Ihere were 58 liquid batch releases during the reporting period. 'Ibe longest 11ould-batch release lasted 147 minutes, while tle shortest release lastad 43 minutes. 'the average release lastal 103.4 minutes with a total Quid batch release time of 5,998 minutes. 6. Continuous Releases 1J 'Ihere were three liquid release pathways designated as continuous - releases during this reporting period. 'Ihey are the Lime Sludge l-Pond, Turbine M1 ding Sump and Steam Geerator Blowdown. 'lhere were two gas release pathways designated'as continuous releases, these are. the Unit Vent and Radweste Building Vent. l f 2 i I' 1 Nw, 4 - (. ss ^

i- - Enclosure.to NO 90-0237 < Pago 18 of 45-T Ifyrruarr AIO MtBIE DIBFQDhL SIBEDROUIL RIRRr (1990) U nnt.Tn MigIn agIpgetIB A. SCLID WASTE SHIPPED OETSITE PCR B(RIAL CR DISPOSAL (Not irradiated fuel) .1. Type of '.aste Unit-6-Month Est. 'Ibtal Period Etzor %:

a. Spent resins, filter' sludges, m3*

3.40E+00 L evaporator bottms, etc. Ci 8.98E-01 2.50E+01

b. Dry ocmpressible waste, m3*

3.57E+01 e contaminated equip. etc. C1 4.07E+00 2.50E+01: -{

c. Irradiated emponents, m3*

0.00E+00 control rods,'etc. Ci 0.00E+00 0.00E+00

d. Other m3*

0.00E+00 o' Ci 0.00E+00 0.00E+00 m3* = cubic meters 1 l L

2. Estimate of major nuclide canposition (by type of wate)

] I ( a. Spent resins, filter sludges, evaporator bottczns,.etc. Waste Class A l e Fe-55 8.57E+01 i Co-60 8.91E+00 i Ni-63 2.23Ev00 1 H-3. 1.66E+00 l l Mn-54 1.27E+00 'l l C-14 2.51E-01' l a.

b. Dry cuus.essible waste, cantaminated equignant, etc.

Fe-55 7.60E+01 Co -% 1.04E+01 l Ni-63 7.11E+00 i l: Co-58 3.60E+00 s Mn-54 1.52E+00 j l~ Cs-137 1.37E+00 -j i C % 7.00E-03 1 I c. Irradinted cmponents, control rods, etc. none l =! d. Other none 3.-Solid Naste Disposition 1 _Nymber of Shinnents Mode of Transoortatlan Destination 2 Truck.

Barnwell, South Carolina

.l ,i.i 5.

? JM Endosure to NO 90-02)i !Page 19f'45 p9 SI Solid Haste 4 e uuss A ' b. Class A c. Not applicable 'd.- Not applicable s

5. Type of Cantainer a.'

IA (Strong, tight) b. IEA (Strong, tight) c. Not applicable d. Not applicable

6. Solidification kjent a.

Not applicable b. Not applicable c. Not' applicable d. Not applicable B. IRRADIATED FUEL SHIPMENIS (Disposition) '1here were no 12. radiated fuel shipments during this ivrting period. t) l -;s

+ Enclosure-to No (0-023'i Page 20._of 45 SE:5'Eull IV Actiitional Ip*wmatim 1. Unplanned or Abnomal~ Releases 'Ibers were no unplanned or abnormal releases dur!rg this repart period. 2. Process Contrcl Pm3uun (PCP) 'Ihere were no changes to the Process Cmtrol Program s+n 5g this report . period. 3. Offsite Dose Calculation Manual (0D04) Revision-6 to the ODCM was issued with Plant Safety Review Ccemittee approval m June 13, 1990. Revision 6 to the ODCM included the~ following changes: Pages 33, 38, 39, 42, B-4, B-5 and B-6: Correct numbering of tableu and figures. Pages 34, 36: Biltorial changes. Page 35: h sanple requirment for Rooted Iquatic Plant has been deleted. 'Ihis sample -is not a 'Dechnical Specification required sanple and has not been available-for the past year. h sanple will be used as a co-sanple with the State of Kansas when available. Deleted reference to sanple frm Wolf Creek Cooling lake (NCCL) at Main Dam Spillway (SP). 'Ihis sanple is not required by 'Ibchnical Specifications.. 'Ihis sanple will continue-to be included as a co-sanple with the State of Kansas. Page 37: Correction of direction for 'Ihentoluminescent Dosineter (TID) Station 38,' distances for TLD Station 40 and vegetation sanple S-4. Aquatic Vegetation was deleted for reasons stated in Page 35 justifications. Page 40: Deleted aquatic vegetatim and SP surfa;a water sanple location for reasons stated in Page 35 justifications. Page 41: Deleted milk frm map legend since no milk sanple locations appear on this map. \\'

R

. h itsure to NO-90-0237 iPage 21'of 45 Page A-3
;

Cvu.cfwd typngm hical error. ' Evaluation of Charges: s ParHation monitor. Atpoints and dose fran liquid and gaseous releases .] are based upon sanples obtained fran actual plant effluents. '1he dose attributed to these effluents is based upon a conservative approach. which assumes an individual resides at the 1200 noter boundary. All 'fr pathways to the individual are assumed to be present. '1herefore, changes to the radiological environmental nonitoring sup.mn will have no affect upon the ca]culation of doso or monitor setpoint p determinaticn. A copy of the pages fran the ODCM that have been revised are included l - with this report as Attachment 1. Revisions are denoted by a revision bar in the right margin of.each page. 1 v 4. Major Changes to the Radweste Systems j i 'Ihere were no major changes to radweste systems made during this wruct. l

period, 5.

Land Use Census 'Ihere were no new locations for dose calculations identified during this -

I report period.

6. Radioactive Shipnants 'Ihere were two shipnents of racloactive radwaste during this report period. Both shipnents were to Barnwell, South Carolina. l 7. Inoperability of Effluent Monitoring Listrumentation 'Ibere were no events in which inoperable liquid or gaseous effluent 4 monitoring instrumentation that was not corrected within the time j-specified in Tnchnical Specifications 3.3.3.10 cr 3.3.3.11. 8. Storage Tanks 'Ihere were no events leading to liquid holdup tanks or gas storagc tanks exceeding the limits of Technical Specifications 3.11.1.4 or 3.11.2.6. m

_ s, W,, 'lL r 't : s,.,,(.1., e & lcoure to ND 90-0237'- f; t< 'P 33 22 of.45-9 ['f' ' ;. e [ i 5 f ATDORENT 1 t, ' f 4'!!

l
s'i h

'Ii +'l -'fi,. k-c- .i }- !..' k \\c.,

p

' E ,_e c. , y 1i i; lk 4' ' k'r > e -1 i 1

1..

I a i ll l l j I t l 5.. r l,; \\ 4 Ir l l, t 't i :. !i.' + c ls j-A t is's. 1 -r, q r

v ,c. .> s k _. ' f. ~l a .? '\\ u '"i w,. .F.ncitsur0 to N0'90-0237

Page:23 ofl.4 5 -

l z. + ~OFFSITE DOSE CALCULATION MANUAL. for-t Wolf' Creek Nuclear Operating-Corporation-Wolf Creek-Generating Station it. ? Revision 6 r T-y, 1 i l 1 b s ( s [j.: ' > ( I, - -o i 1 tli. -m<, I . 1 '. i t .-M .(. t V

y y.

.) h APPROVED BY k-j DATE: I3 iO-3 4 ManagerlChemistry 7 'e i d '/ '

PSRC _ /gfh/) /

e 7h DATE: [-/MO c .-t;? APPROVED BY-p. h. 'o St.- 'l -re. 1,

t,

4-Oi i h I-%, l 5, . 't ',' s t 'U (, y 4 I'. i O. l 1. 2 1 .y j,! ( -' i .I 1 + t e I g f j-i,,

p, 7 4 k? U ! Enclosur0 to NO 90-0237 ' E'

j Page 242
of,.453 LIST OF TABLES
Table' Page 4-l' Radiologica1 Environmental Monitoring Program 34

+ '4-2 Sampling Location Numbers, Distance (miles) and Directions 37- . A.1 Bioaccumulation Factors to be Used in the Absence A-2: of Site; Specific Data A.1 Dose Factors for-Noble Gases and Daughters A-3 A.2-1 Inhalation-Dose Factors for Adults A-4 g A.2-2 Inhalation Dose Factors for Teenagers. A-7 ?A.2-3 Inhalation Dose Factors for. Child A-10 t 'A.2-4'-Inhalation Dose Factors for Infant A-13. s A.2-5 External Dose Factor for Standing on A-16c' Contaminated Ground L . Ingestion Dose Factor for Adultc-LA-18L* .A.3-l' q; .A.3-2 Ingestion Dose Factor'for Teenagers A-21 LA'.3-3 Ingestion, Dose Factor for Child A-244 4 .A.3-4 Ingestion Dose Factor for Infant .A-27

a

'A.3-5 St 'le Element Transfer Data A-30 A.4-1 Sitie Related Ingestion Dose Commitment for Adult: A-31 c,1 'A.4-2' Site Related Ingestion Dose Commitment Factor.for A-34 Teenager

A.4-3; Site Related Ingestion Dese Commitment' Factor for Child A.

A.4'-4 Site Related Ingestion Dose-Commitment Factor for; Infant .A-40 + A.5-1 Inhalation! Dose Parameter for the Child A-43: Y W A.5-2 Inhalation Pathway Factor for Adult (RI. Factor) '4-44 u A. 5'-3 Inhalation' Pathway Factor for Teenager (RI Factor) A-47

e..

'A.5-4 Inhalation Pathwif Factor for Child (RI Factor) A-50 A.5-5 Inhalation Pathway Factor for Infant (RI Factor) A-53 ' I c,_ g f.:p _ J-t< L.. &ltb.+.iO

t G.. 4 J Encicsuro.to NO 90-0237-Page-25 of 45 LIST OF TABLES ' Table Page A.5-6 Grass-Cow-Milk Pathway Factor Adult' (RI Factor) A-56 .L- 'of Site Specific Data A.5-7 Grass-Cow-Milk Pathway Factor Teen (RI Factor) A-59 o 4 LA.5-8 Gras; ~.ow-Milk Pathway Factor Child (RI Factor) A-62 r A.5-9 Grass-Cow-Milk Pathway Factor Infant (RI ? actor) A-65 -A.5-10 Grass-Cow-Meat Pathway Factor Adult (RI Factor) =A-68 A.5-11 Grass-Cow-Meati Pathway Factor Teen (RI Factor) .A. A.5-12 Grass-Cow-Meati. Pathway Factor Infant. (RI Factor) ' A-74 i i.A.5-13 Vegetation Pathway Factor Adult -(RI Factor) -A-77 z .A.5-14 Vegetation Pathuay Factor Teen (RI Factor) A-80 1 A.5-15 Vegetation Pathway Factor Child (RI Factor) A-83 A.5-16 Ground Plane Pathway Factor (RI' Factor) ~A-86 A.5-17 Grass-Goat-Milk Pathway Factor Adult (RI Factor) A-87. LA 5-18 Grass-Goat-Milk Pathway Factor Teen (RI Factor) A-90 A.5-19 Grass-Goat-Milk Pathway Factor Child (RI Factor) A-93 1s-5 A.5-20 Grass-Goat-Milk Pathway Factor Infant (RI Factcri A. LIST OF FIGURES. 4 4.1 Airborne Pathway. Sampling Locations 38 L 4 ~. 2 ~ Direct Radiation Pathway Sampling Locations 39 4.3 Waterborne Pathway Sampling Locations 40 \\! K 4.4 Ingestion Pathway. Sampling Locations 41 f 4.5 Distant Sampling Location 42 \\ B.1 Vertical Standard Deviation of Material in a Plume B <' Lv 'B. 2 Plume Travel Distance Versus Fraction Remaining in Plume B-5 (; B.3 Plume Travel Distance Versus Relative Deposition Rate B-6 Y iii l '/

B p* + + $ $ M $b ///p%g (f[+4 IMAGE EVAL.UATION \\xxN/o/7/ \\f gf# TEST TARGET (MT-3) e

  1. 4

\\ \\\\\\ pfjj- /// t4 $+9 %h t< 1.0 llDE BL4 I " @ RE E m He l-l t: l.25 1.4 1.6 150mm 4 l> 6" 4 4 %* %++4 ,a <e,a x-xxA pjyg7/(c w w (t4 # O i 4 U i 1 Cd

Enclosurs to NO 90-0237 b Page 26 of 45 l. 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4-1 gives specific Radiological Environmental sampling pathways, locations and frequencies corresponding to Table 3.12-1 of Wolf Creek Technical Specifications. Maps showing these locations in relation to the Wolf Creek site are shown in Figures 4.1 through 4.E; Table 4-2 lists. distances ~and directioiis from l the site to the sampling locations. 4.1 INTERLABORATORY r')MPARISON PROGRAM Analysis of WCNOC Radiological Environmental samples is presently performed by Teledyne Isotopes, which participates in the EPA Laboratory Intercomparison Program. Resul'. of intercomparisons are then provided to WCNOC in revisions to 'feledyne's Quality ,F Control Manual (IWL-0032-361) which is maintained at the WCNOC Wichita offices. 9 9 l l l ODCM 33

o 7 TABLE 4-1 Sheet 1 of 3 -.o n - i R* RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM-

  • o UE 3

Number of Samples . En. Exposure Pathway / and. Sample Type and Frequency Sample Type Sample Loce' ions Collection Frequency of Analys'is- "E 1. AIRBORNE FIGURE 4.5 ~ Radiciodine and Indicator locations Continuous operation Radiciodine canister.- 0 Particulates at station numbers 2, of sampler with sample -Analyze weekly for 3, 32 and 37; control collection as required I-131.. location at TLD by dust loading but at Station number 40. least weekly. . Analyze forfgross. beta radioactivity notLless than 24 hours following filter. change. Perform gamma isotopic analysis on each sample when gross . beta activity'is greater than 10 times'the yearly mean of control 1 samples. Perform gamma isotopic analysis on composita (by location)ionce per quarter. 2. DIRECT RADIATION FIGURES 4.2 and 4.5 38 TLD locations within Quarterly at each Gamma dose quarterly. 5-mile radius of site location and two offsite locations; two TLD Dosimeters at-each location. ODCM 34 e ..e w. -,.i., -y e pe-. y 4 y g. ,y g ,_,9 y. a y- ..m% y,

.m i l i .g l TABLE 4-1 (Con't.). Sheet.2 of 3' RADIOIDGICAL ENVIRONMENTAL. MONITORING PROGRAM gg-yg .g{ Number of Samples J Exposure Pathway / and Sample Type and Fri.quency Ee ~ e Sample Type Sample Lo.ations Collection Frequency of Analysis __ gy i 3. WATERBORNE FIGURE 4.3 o I:>

a. Surface Upstream sample at Monthly grab sample Monthly gamma isotopic

? location MUSH near the -analysis. Quarterly- 'O John Redmond Reservoir tritium analysis of spillway, samples from composite sample. Wolf Creek Cooling Lake at locations ~DC.

b. Ground Indicator locations at Quarterly Quarterly gamma iso-C-10, C-49, D-65; topic and tritium control location at B-12.

analysis. c. Drinking Municipal water Monthly composite

  • Monthly gross beta and supplies at Burlington gamma isotopic analysis.

(upstream location BW-15) Qtarterly tritium analysis and.Leroy (downstream of composite sample. location LW-40).

d. Sediment from One sample.from Wolf Semiannually Semiannual gamma iso-Shoreline Creek Cooling Lake topic' analysis, discharge cove.
  • Composite sampling shall be performed by collecting an aliquot at intervals not exceeding 2 hours.

35' ODCM

  • T

-i TABLE 4-1 (Con't.) Sheet 3 of 3- .g g ' ao RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM

  • 7 UE Number of Sadples

- P.,,, Exposure Pathway / .and . Sample Type and Frequency ,0 Sample Type Sample Locations Collection Frequency of Analysis O' $ - 4. INGESTION FIGURES 4.4 and 4.5 E-

a. Milk Control' sample from Semimonthly when Gamma isotopic and location S-3 (Currently animals are on

_I-131 analysis of no indicator sampling pasture; monthly each sample. locations exist.) at other times. b. Fish One sample from Wolf Semiannually Gamma isotopic analysis Creek Cooling Lake, on edible portions similar control sample from John Redmond Reservoir spillway c. Food Products Broad leaf vegetation Monthly during harvest Gamma isotopic and I-131* samples at locations analysis on edible G-1 and A 1 (location portions. R-1 maybe used as alternate) ; control sample at location S-4. One sample of crops At time of harvest Gamma isotopic'and I-131* irrigated with Neosho' analysis on edible River water from loca-portions tions downstream of the Neosho-Wolf Creek Con-fluence-(Locations will vary from year to. year).

  • If the I-131 LLD from Table 4.12-1 of Tech Specs is met with the Gamma Isotopic analydth,

~ a j separate I-131 analysis is not-required. [ ODCM 36 . ~ _ u

TABLE 4-2 SAMPLING LOCATION NUMBERS, DISTANCES (miles) AND DIRECTIONS TLD and Air Particulate og Location Distance / Location Distance / $ ocation. Distance / Location L Direction,(). Distance /c Number Direction Number Direction Number Direction Number o 1 1.4/N 11 1.6/E 21 3.8/S 31 3.0/WNW az 2 2.7/N 12 1.8/ESE 22 4.1/SSW 32 3.2/hNW ,o 3 3.0/NNE, 13 1.5/SE 23 4.5/SW 33 3.7/WNW 4 4.0/NNE 14 2.6/SE 24 4.1/WSW 34 4.0/NW o 5 4.0/NE 15 4.5/ESE 25 3.6/W 35 4.6/NNW-w 6 4.4/ENE 16 4.2/E 26 2.6/WSW 36 4.2/N 7 1.9/NE 17 3.6/SE 27 2.1/SW 37 2.1/NNW 8 1.6/NNE 13 3.2/SSE 28 2.8/SW 38 1.2/NW 9 2.0/ENE 19 4.0/SSE 29 2.6/SSW 39 13.0/N 10 2.4/ENE 20 3.3/S 30 2.2/W 40 >15.0/WNW Groundwater Drinking Water Surface Water B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/W C-10 2.8/W LW-40 10/SSE DC 0.6/WNW C-49 2.9/SW D-65 3.9/S Milk and Food Products A-1 1.4/N R-1 2.1/NNW j G-1 1.6/SE S-3 >15.0/WNW S-4 >15.0/WNW Fish Shoreline Sediments Irrigated Crops WCCL DC 0.6/WNW NR-D1 9.2/S, JRR 4/W NR-D2. >10/S. ODCM 37 m.

Enclosuro to NO 90 0237 Page 31 of 45 \\ )._ \\ 2_ RP% j%c ~ p" @4 9Vnhb & ~~ ~~ 4/l/0/1Xe 8 -i l I ~ O?slIO ll / c, c s ,s ~' ' h_ _ } ~~ ~~ k"_Alk 5 j Nf',) e f l y / g*C w ,s. /f '8 UR LINGTDN e o 1 .a C,LDk b J l[ l N AIRBORNE PATHWAY SAMPLING LOCATIONS

  • - AIRBORNE PARTICULATE AND RADIOIODINE Figure 4.1 1

OIC1 38

EnclosurO.to NO 90-0237 a \\ {A h "%/' "3' "\\h 'l ~~~ \\ l / d i MEf M ' 1 : WI, R /',N _ _ " _ _ ...n s w, p ,l arstma N L / p U N 6 2 l E 25 A '. ([ i_ I ,2,1 c _w ,2e i L. 2; $7-l is g 0 / bl d' v L ,~m u. xyx 2, t s e n..,, a s oc- ,I' -/ \\ ""* Nid k, / s \\ / ~/ .o, ) "s K b lf l -k h . DIRECT RADIATION PATHWAY SAMPLING LOCATIONS

  • -TLD LOCATIONS Pigure 4.2 OD31 39

\\ l ;'. Enclosure to NO 90-0237 Page 33-of 45 L \\ jA h / B ~~~ s \\ Qh ,~ [ c Q" Y V %%# W ~~ 4MO /1X ~~s ,..A 9,"3A's"f' 'l t. ~ ~~~ ~ ~ N 6 l~~ i ~"( m ix ~ =j l_ N \\ ) w Ff g ' i,"

  1. AF 3

N \\{;/N 1'p-': C i /*' ;; M4s !* L N / nu.u,.. / S g f l Q 'f c ],,, K j J !V~ i l WATERBORNE PATHWAY SAMPLING LOCATIONS ~

  • - DRINKING WATER A-SURFACE WATER m-GROUND WATER v-SHORELINE SEDIMENT Figure 4.3 OI D I 40

l .j m Enclosure to NU 90-0237 ,,...u aa l \\ )A h ""M/ ~ 8k 1 y C ~ j i i g" % 9'm%) & ~- &, &. / /" /1 X~i~ SE!!E l N JRR h { m o, c t i_ is ~' j i R I)J w Ff h / i g '/ 4A. l q_ j; y )y y \\ ( f,.. WAh ~~. t..f 7 ,J 't.,-{'"""~Q j 4,,,,, / \\ '~ ,j f q,, K j { 3 J i y'- l h-n INGESTION PATHWAY SAMPLING LOCATIONS m-FOOD PRODUCTS G-FISH (WCCL) A-FISH (JRR) Figure 4.4 0001 41 [. l-E -

u;.. + - 6Cs. nctautry, 6y WG,JG-Ot91-p g

y atf (31)

.i oto u.s. so 83 1 1. 10 WL E WAVER F AS 113 3 H418 SUMWT l [. s-4 { 5 wte 4ools I ras iss [ s-a h l A ? E li v1 - m E NEwy 'l d \\ m ( FAs so = rA o l e / i II E ~ E l-S- / NA-01 t Ab91 . MonourY LE W uR. DISTANT SAMPLING LOCATIONS

  • -TLD m-DRINKING WATER l

A-MILK

  • -BROADLEAF VEGETATION /

IRRIGATED CROPS Figure 4.5 ODCM 42

-a ~ TABLE A.1-2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS

  • Total Body a g-Gamma Air Beta Air:

wg. Dose Factor Skin Dose Factor Dose Factor -Dose Factor-1; K L M N-Lo~ 3 3 i 3 Radionuclide (mrem /yr per uCi/m ) .(arem/yr per uCi/m ) (mrad /yr per uCi/m ) g (mra'/yr per uCifm' I) ^ d Kr-83m 7.56E-02** wz 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 UE Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 E) Kr-87 5.92E+03 9.73E+03 6.17E+03-1.33E+04 $I Kr-88 1.47E+04 2.'37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04-1.06E+04. Kr-90 1.56E+04 7.29E+03 1,63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02-Xe-135 1.31E+03 1.86"+03 1.92E+03 2.46E+03 Xe-137 1.42E+03' 1.2io+04 1.51E+03 1.27E+04-Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 BasedonRegulatoryguide-1.109(Rev. 1).

    • 7.56E 7.56 x 10 A-3 c.

~ Encitsuro to NO 90-0237-i Page 37. of 45 Figure B11. 1 1 i 1000 i i i \\ / i i / / / / / . / / l ,/ / o, ) / / / r p l / / \\ / / / 1 / s A / / / / / -8 100 i / / / s ? / / / -/ / u ; / ~ / ~ / / / / / / / / / /- / / ./ / }' / ,/ / 1 j- / / / f/ / / o / / / Q l l,/ e/ ~ / 7 p / / l af 10 / / / / J / / / /.' t / / / \\ // / / /- ;,/ / / / s / / /, / / 1 0.1 1.0 10 100 P'.UME TRAVEL DISTANCE (KILOMETERS) Vertical Standard Deviation of Materialin a Plurne (Letters denote Pasquill Stability Class). NOTE: THESE ARE STANDARD RELATIONSillPS AND MAY tlAVE TO DE MOOlFIEO FOR CERTAIN TYPES OF TERRAIN ANO/OR CLIMATIC CONDITIONS (E.G., VALLEY, OESERT. OVER WA T ERL OLCM B-4 1; 1 l l

f 4

+

" ~ i.. - Encicsur] to NO 90-0237 Page-38' of 45 9 O, 8w a' 4 4 / d / o / / / / f P a x w bW Od O / d w / t M / n w / o m j 2 1 h / a . u_ tp Q m A J f 4 w ca 4 /- c H W2 - D 'J O. O I i / / / p / o O O, G. m, q m, in ,7 g g ~ o o o o 6 6 6 6 d xo i 9Wnld NI DNINIVW3U NOll3VHd o

t ' I L* Encitsura to NO 90-0237 -Page 39 of 45 Figure B.3-t 10-3 I 104 \\ x ' E , s wr ,N \\ \\s e W N n. G \\ r N s C N 5 10-5 \\ p 's x \\ O' _x a. I w s o A. LU ~ \\ P \\ \\- s w N N 10-6 x 10-7 0.1 1.0 10.0 100.0, 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) ODCM B-6 I

_ p < p. I inc1: sura to NO 90-0237 Pag 3 '40 of 45 I-}. l: ) ATDORENP 2 l l l provides actual values to replace tie estimated values for liquid effluents provided in Santannual Radioactive Effluent Release Report 10. New values are denoted by bold face type. l.- I' 4 i i l i l ^ l \\ B } !i i l t

  • f 6.

Encicsurs to NO 90-0237 P:ge 41 -cf 45 SECTION I .1 Year 1989 REPORT OF RADIOACTIVE EFFLUENTS: LIOUID j Unit Quarter Quarter 3 4 A. Fission and Activation Products i 1. Total Release (not including tritium. nases, alpha) Ci 3.11E-01 6.51E-02 2. Averane Diluted Concentration Durinn Period uC1/ml ___ 8.04E-08 2.63E-08 3. Percent of Applicable Limit (1) 6.22E+00 _12.30E+00 [ B. Tritium t 1. Total Release Ci 1.86E+02-2.74E+02 L 2. Averane Diluted Concentration During Period uCi/ml 4.81E-05 1.11E-04 3. Percent of Applicable Limit (2) I 1.60E+00 3.69E+00' C. Dissolved and Entrained Gases 1. Total Release Ci 3.87E-02 1.74E-01 l 2. Average Diluted Concentration Durina Period uCi/ml 1.00E-08 7.04E-08 3. Percent of Applicable Limit (3) 5.00E-03 3.52E-02 D. Gross Alpha Radioactivity 1. Total Release Ci 0.00E+00 0.00E+00= E. Volume of waste released (prior to dilution) liters 4.75E+07 2.37E+07 F. Volume of dilution water used liters 3.82E+09 2.45E+09 .1 1 1. - The applicable limit for the Wolf Creek Generating Station is 5 Curies per year. j; (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 'rslease Curies by 5 Curles and then multiplying the result by 100. 2. This value is derived by the following formula Z of Applicable Limit = (Average Diluted Concentration) (100) ( (MPC, Appendix B. Table II 10CFR20) 3. This value is derived by the following formula: % of Applicable Limit = (Average Diluted Concentration) (100) (2E-4 from Technical Specification 3.11.1.1) l

Enciteure ts NO 90-0237 7:g3 42 ci 45 3,* Year 1989 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter-RELEASED Unit 3 4 3 4 i H-3 Ci 1.07E-01 4.96E-02 1.86E+02 2.74E+02 l 5 Mn-54 Ci <2.34E-02 <1.14E-02 9.49E-04 4.72E-04' i Fe-55 Ci <4.67E-02 9.16E-04 1.48E-01 5.22E-02 -l Fe-59 Ci <2.34E-02 <1.14E-02 <3.89E-04 <3.96E-04 Co-57 Ci 0.00E+00 0.00E+00 1.45E-03 3.25E-05 i Co-58 Ci <2.34E-02 <1.14E-02 9.42E-02 1.21E-03 Co-60 Ci <2.34E-02 <1.14E-02 5.90E-02 5.53E-03 Nb-95 Ci 0.00E+00 0.00E+00 5.87E-05 0.00E+00,_. ( Nb-97 Ci 0.00E+00 0.00E+00 3.52E-05 2.36E-05 l Sr-92 Ci 0.00E+00 0.00E+00 1.14E-05 7.70E-06 Sr-89 C.i <2.34E-03 <1.14E-03 <3.89E-05 $3 96E-05 4 i Sr-90 C1 <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 -l l \\ l 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 l Ce-144 Ci <2.34E-02 <1.14E-02 <3.89E-04 <3.96E-04 l Sb-125 Ci 0.00E+00 0.00E+00 3.43E-04 1.58E-03 L l l-

'M ): av E'citsura.to NO 90-0237

o. -

t n Y'

Pass 43.,cf 45 l

l? h L Year ~ 1989 1 LIQUID CtBIDLATIVE DOSE SIRel&EY TABLE 1 ...............................,.........................................y.................... ODCM TECHNICAL CALCULATED SPECIFICATION I 0F = b DOSE LIMIT LIMIT s QUARTER 1 0F 1989 . 5.00E+00-3.92E 01-._ TOTAL DOSE (mrem) FOR littl 1.96E.02. -TOTAL DOSE (mrem) FOR L3fi

  • 4.62E-02 5.00E+00 9.24E-01 TOTAL DOSE (mrem) FOR TOsci BODY-3.73E.02 1.50E+00-2.49E+00 TOTAL DOSE (mrem) FOR THYkJ2D

-1.16E.02 5.00E+00 2.32E.01 TOTAL DOSE (mrem) FOR KIDNEY 2.28E.02 5.00E+00 4.56E.01-TOTAL DOSE (mrem) FOR LUNG 1.55E.02' 5.00E+00 3.10E.01. TOTAL DOSE (mrem) FOR.GI-LLI 2.90E-02 5.00E+00 5.80E-01. ~ QUARTER 2 0F 1989 ' 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 BODY 2.17E.02 1.50E+00 1.45E+00, 9 TOTAL DOSE (mrem) FOR THYROID 2.01E.02 5.00E+00 4.02E.01 TOTAL DOSE (mrem) FOR KIDNEY 2.07E-02 5.00E+00 '4.14E-01 TOTAL DOSE (mram).FOR LUNG 2.04E.02 5.00E+00 4.08E.01: TOTAL DOSE'(mrem) FOR GI.LLI 2.14E.02 5.00E+00. 4.28E.01 LQUARTER 3 0F 1989 ~ TOTAL DOSE (mrem) FOR BONE 2.17E-02 5.00E+00 d 34E.01 TOTAL DOSE (mrem) FOR LIVER 6.86E.02 5.00E+00 1.37E+00 TOTAL DOSE (mrem) FOR TOTAL BODY 5.90E.02 1.50E+00 3.93E+00' TOTAL DOSE (mrem) FOR THYROID 3.30E 5.00E+00 6.60E.01 TOTAL DOSE (mrem) FOR KIDNEY 4.45E.02 5.00E+00-8.90E.01 1 1 TOTAL DOSE (mrem) FOR LUNG 3.72E-02 5.00E+00 7.44E-01 TOTAL DOSE (mrem) FOR GI.LLI' 4.11E-02 5.00E+00 8.22E.01 . QUARTER 4 0F 1989 ' TOTAL' DOSE (mrem) FOR BONE 4.83E.02 5.00E+00 9.66E-01 rTOTAL DOSE (mrem)'FOR LIVER 8.95E-02 5.00E+00 1.79E+00 TOTAL DOSE (mrem) FOR: TOTAL BODY 6.49E-02 1.50E+00 4.33E+00 ' TOTAL DOSE (mrem) FOR-THYROID 4.35E.02 5.00E+00 8.70E.91 TOTAL DOSE (mrem) FOR KIDNEY 5.04E.02 5.00E+00 1.01E+00

TOTAL DOSE (mrem) FOR LUNG 5.98E-02 5.00E+00 1.20E+00

'. TOTAL DOSE (mrem) FOR GI.LLI 5.90E.02 5.00E+00 1.18E+00

~1 ~... 1 , 9$gj "' Enc 1bour3 to NO 90-0237 Page 44 of 45-LIQUID CtBSIDIATIVE DOSE StBed&RY ' .j TABLE 1 (continued) i e TOTALS FOR 2989 TOTAL DOSE (mrem) FOR BONE 9.09E-02 1.00E+01 9.095-01 TOTAL DOSE (mrem) FOR LIVER 2.27E-01 1.00E+01 2.27E+00-l TOTAL DOSE (mrem) FOR TOTAL BODY 1.83E-01 3.00E+00 6.10E+00 ' TOTAL DOSE (mrem) FOR THYROID 1.08E-01 1.00E+01 1.08E+00' TOTAL DOSE (mram) FOR KIDNEY 1.38E-01 1.00E+01 '1.38E+00 TOTAL DOSE (mrem) FOR LUNG 1.33E-01 1.00E+01 1.33E+00- -TOTAL DOSE (mrem).FOR GI-LLI 1.51E-01 1.00E+01 1.51R+00 s 1 'B: sed on Technical Specification 3.11.1.2 which restricts dose to the whcle body to less than or equal to 1.5 mrem per ~ quarter and 3.0 mrem per year. Dose restriction to any 1 crg:n is less than or equal to 5 mrem per quarter and 10 mrem per year. i 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 edjustment for Fe-55 composite data. I i i i i i .I i l l l lt ,}}

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