ML20147D656

Semiannual Radiological Effluent Release Rept 6,Jul-Dec 1987

ML20147D656
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1987
From:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
WM-88-0046, WM-88-46, NUDOCS 8803040082
Download: ML20147D656 (34)

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ge Wolf Creek Generating Station Docket No: 50-482 Facility Operating License Not IPF-42 i

SEMIAbtElhL RADImmTCAL EFFIMNF REMASE REPORP Report No: 6 Reporting Period: July 1, 1987 through Decenber 31, 1987 Subnitted by:

Wolf Creek Nuclear Operating Corporation l

l 8803040082 871231 m

[9 PDR R

ADOCK 05000482 DCD /[

.;[ Attac,hment to WM 88-0046 g

INTRODUCTION

'Ihis Semiannual Radiological Effluent Release Report covers the period of July 1,1987,n through Decenter 31, 1987, and satisfies the requirements specified in Technical Specification 6.9.1.7.

Section I provides a sunmary of the quantities of radioactive liquid and gaseous effluents for this reporting perio3. The fornat is similar to that provided in Regulatory Guide 1.21, Revision 1. An elevated release pathway does not exist at Wolf Creek Generating Staticn. Therefore, all airborne releases are considered to be ground level releases. 'Ihe concurrent meteorological condition gaseous pathway dose determinat'cn is met by the Wolf Creek Offsite Dose Calculation Manual methodology on assigning all gaseous pathways to a hypothetical individual residing at the highest amual X/O and D/O location. 'Ihis results in a conservative estimate of dose to a Menber of the Public rather than determining each pathway dose for each release direction. A conservative error of thirty percent has been estimated in effluent data. There were four shipments of solid waste during this reporting period.

Section II provides Suppleaental Information as described in Regulatory Guide 1.21, Revisicn 1.

Section III provioes a sunmary of meteorological data for the period of January 1,1987, through December 31, 1987. This informaticn is also available cn site for review and inspection.  :

Secticn IV provides additional informaticn required by Technical Specification 6.9.1.7.

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SECTION I

' lear 1987 REPORT OF RADIOACTIVE EFFWEtfrS: LIQUID Quarter Quarter Unit 3 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci 2.44E-02 2.44E-01 ,

2. Average diluted concentration during period uCi/ml 3.68E-09 2.49E-07

3. Percent of Amlicable Limit  % 4.88E-01 4.88E+00 B. Tritium i

1. Total Release Ci '

l.02E+02 1.llE+01

2. Average diluted concentration during pericx1 uci/ml 1.58E-05 1.31E-05

3. Percent of Amlicable Limit ,

% 5.27E-01( }l 4.37E-01 C. Dissolved and Entrained Gases _

l. Total Release __Ci_ l. 8E+00 2.52E-01

2. Average diluted concentration during period uCi/ml 2.42E-67 2.72E-07

3. Percent of Applicable Limit  % 1.22E-01(3) 1.36E-01 D. Gross Alpha Radioactivity ,

1. Total Release Ci 0.00E+00 0.00E400 E. Voltane of waste released liters 5.03E+06 1.90E+06 l l F. Volume of dilution water used I liters 2.40E+10 3.21E+09

1. he applicable limit for the Wolf Creek Generating Staticn is five (5) curies per year.

l W e value printed here is derived by dividing the total release curies by 5 curies and then i nultiplying the result by 100.

2. his value is derived by the following forrtula:

(-  % aplicable limit = (Average diluted concentraticn) (100)

(IPC, Appendix B, Table II 100'R20)

3. 21s value is derived by the folloaing formulas

% applicable limit = (Average diluted concentration) (100)

(2E-4 frcan Technical Specification 3.11.1.1)

Page 1 of 31

, - 'n.

s Year 1987-LIQUID EFFUJINTS Continuous Fbde Batch Mode NUCLIDES Quarter 1 Quarter.. Quarter Quarter RELEASED Unit l 3 4 3 4 H-3 Ci 0.00E+00 0.00E+00 1.02E+02 1.11E+01 Na-24 Ci 0.00E+00 6.00E+N l 4.56E-05 1.30E-04 1

Cr-51 Ci '

O.00E+00 0.00E+00 0. 00E+fl0 4.56E-02 l \

Mn-54 Ci ,

0.00E+00 0.00E+N 2.10E-03 '

l.27E-02 Mn Ci '

O.00E+00 0.00E+N 6.85E-05 0. 00E+@

l Fe-55 Ci 0.00E+00 0.00E+00 1 6.94E-06 5.86E-04 l

Fe-59 Ci  ! 0.00E+00  ; 0.00E+00 1 1.42E-04 2. 23E-02 l

Co-58 Ci 1 0.00E H10 0.00E+N 2.80E-03 1.07E-01 Cr>-60 Ci l 0.00E+00 0.00E+@ 6.14E-03 9.83E-03 I

Zn-65 Ci 0.00E+00 0.00E+00 1.75E-04 5. 95F.-04 Rb-88 l Ci 1 0.00E+00 0.00E+N 8.25E-03 0.00E+N Zr-95 Ci 0.00E+00 0.00E+00 1.02E-04 i 7.62E-06

_ Nb-95 Ci l 0.00E+00 0.00E+N 2.47E-04 8.78E-04 Mo-99 Ci 0.00E+00- 0.00E+00 1.98E-03 3. %E-03 Tc-99M Ci 0.00E+00 0.00E+N 0.00E400 3.22E-05 l l I-131 Ci 0.00E+00 0.00E+00 1.44E-04 2.53E-04 I-133 Ci 0.00E+00 1 0.00E+00 2.40E-05 0.00E4W 1

Cs-134 Ci 0.00E+00 0.00E+G3 4.30E-05 7.72E-04 1

Cs-136 Ci l 0.00E+00 0.00E+00 0.00E+00 5.70E-05 Page 2 of 31

Year 1987 LIQUID EFEUJENTS Continuous Mode Batch bbde NUCLIDES Quarter Quarter ! Quarter Qual +.er RELEASED Unit 1 3 4 1 3 4 Cs-137 Ci 0.00E+00 0.00E+00 3.97E-05 1.54E-03 Cs-138 l Ci 0.00E+00 0.00E+00 1.09E-05 0.00E+W 1

La-140 Ci 0.00E+00 0.00E+N 0.00E+00 1.43E-05 l l Ce-141 Ci 0.00E+00 0.00E+00 8.80E-05 2.49E-04 Ce-144 Ci i 0.00E W 0.00E+00 1.88E-03 2.36E-03 Kr-85M Ci '

O.00E+00 l 0.00E+00 l 1.19E-03 0. 00E+@

Kr-85 Ci 1 0.00E+00 0.00E+W 8.84E-02 2.32E-01 l l Kr-87 Ci 0.00E+00 0.00E+W l 6.59E-05 0. 00E+@

l Kr-68 Ci 0.00E+PO 0.00E+00 l 1.00E-03 8.91E-05 l '

l Xe-131M Ci ,

0.00E+00 0.00E W I 1.06E-02 9.31E-03 1

Xe l33M Ci 1 0.00E+00 0.00E+00 1.33E-02 7.28E-04 l

_ Xe-133 Ci 0.00E+00 0.00E+00 i 1.02E+00 6.57E-03 Xe-135M Ci 0.00E+00 l 0.00E 6 l 0.00E W 3.03E-03 Xe-135 Ci 0.00E+00 0.00E400 4.45E-02 0.00E+00 l

_ Ar-41 Ci 0.00E+00 0.00E+00 l 2. 59E-M 0.00E+W Sr-90 Ci l 0.00E+00 0.00E+00 l 7.03E-08 5.93E-06 Sn-ll7M Ci 0.00E+00 0.00E+00 2.78E-05 2.71E-M 1

Sn-ll3 i Ci 0.00E 6 0.00E+N I 3.3PE-05 7. 66E-M l l Co-57 Ci l 0.00E+00 0.00E W j 7.02E-05 1.48E-M Page 3 of 31

Year 1987 LIQUID EFETJJENI'S Continuous Mode Batch Mode NUCLIDES Quarter Quarter i Quarter Quarter RELEASED , Unit l 3 4 l 3 4 l l 1 l Sb-124 Ci 0.00E+00 0.00E+00 0.00E+00 7.09E-03~

Sb-125 Ci 0.00E+00 , 0.00E+00 0.00E+63- 2.64E 1 Sb-126 Ci 0.00E+00 i 0.00E+N 0.00E+00 4.46E-04 l

Sr-89 Ci 0.00E+00 0. 00E4W <2.52E-04 <9.50E-05 Gross Alpha l Ci 0.00E+00 0.00E+00 <5.03E-04 <l.90E-04 l

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l l l l Note: Less than values are calculated using the lcuer limit of detection (LID) values obtained at the Wolf Creek Generating Station nultiplied by the volume of waste discharged during the respective quarter.

Page 4 of 31

Year 1987 IJOUID QMXATIVE DOSE SLMERY TABM 1 I

ODQ4 TECHNICAL CALCUIATED SPECIFICATION  % OF DOSE LIMIT . LIMIT LNIT 1, QUARTER l- OF 1987

'1UTAL DOSE (MRD4) . EOR BONE 4.32E-05 5.00E+00 8.65E-04.

'IUPAL DOSE (MRD4) EOR LIVER - 9.16E-03 5.00E+00 1.83E-01

'IUPAL DOSE (MRD4) EOR '1UTAL BODY 9.llE-03 1.50E+00 6.07E-01

'IUPAL DOSE (MRDi) EOR HIYROID 8.98E-03 5.00E+00 1.80E-01

'IUTAL DOSE (MRD4) FOR KIDNEY 9.04E-03 5.00E+00 1.81E-01

'IUTE DOSE (MRDi) EUR~ WNG 8.99E-03 5.00E+00 1.80E-01

'1UTAL DOSE - (MRD4) FOR GI-LLI 1.76E-02 5.00E+00 3.52E-01 LNIT 1, QUARTER 2 OF 1987

'IUTE DOSE (MRD4) FOR BONE 1.64E-04 5.00E+00 3.28E-03

'1 URAL DOSE (MRD4) EOR LIVER 8.%E-03 5.00E+00 1.79E-01

'1UTAL DOSE (MRD4) EOR 'IUTAL BODY 8.85E-03 1.50E+00 5.90E-01 IUPAL DOSE (MRD4) EOR HIYROID 8.57E-03 5.00E+00 1.71E-01

'IUTAL DOSE (MRD4) EOR KIDNEY 8.72E-03 5.00E+00 1.74E-01

'1UTAL DOSE (MREM) EOR WNG 8.59E-03 5.00E+00 1.72E-01

'1 URAL IDSE (MRD4) EOR GI-LLI 1.14E-02 5.00E+00 2.28E-01 UNIT 1, QUARTER 3 OF 1987

'1UTAL DOSE (MRD4) EOR DONE 2. 69E- 04 5.00E+00 5.38E-03 TorAL DOSE (MRD4) EOR LIVER 8 09E-03 5.00E+00 1.62E-01

'IUPAL DOSE (MRDi) EOR 'IUPAL BODY 7.88E-03 1.50E+00 5.25E-01

'IUTAL DCSE (M5M) EOR DIYROID 7.71E-03 5.00E+00 1.54E-01

'IUPAL IX)SE (MRD4) EOR KIINEY 7.68E-03 5.00E+00 1.54E-01

'IUTAL DOSE (MHD4) FOR WN3 7.48E 03 5.00E+00 1.50E-01

'IUTAL DOSE (MRD4) FOR GI-LLI 1.lSE-32 5.00E+00 2.30E-01 LNIT 1, QUARTER 4 OF 1987

'IUPAL DOSE (MREM) EOR DONE 1. 50E -01 5.00E+00 3.00E+00

'IUTAL DOSE (MRD4) EOR LIVER 2.61E-01 5.00E+00 5.22E+00

'IUTE DOSE (MRD4) EOR 'IUTAL IDDY 1.85E-01 1.50E+00 1.23E+01

'1 URAL DOSE (MRD4) EOR ElYROID 1.40E-02 5.00E+00 2.80E-01

'IUTAL DOSE (MRD4) ECR KIDEY 9.31E-02 5.00E+00 1.86E+00

'IUTAL DOSE (MRD4) EOR ENG 3.74E-02 5.00E400 7.48E-01 TOTAL DOSE (MRD4) EOR GI-LLI 2.03E-01 5.00E+00 4.06E+00 LNIT 1, 'IUPAIS FOR 1987

'IUPAL DOSE (MRD1) EOR DONE 1.50E-01 1.00E+01 1.50E+00

'IUTE DOSE (MPEM) EOR LIVER 2.87E-01 1.00E+01 2.87E+00

'IUPAL DOSE (MRD4) EOR 'IUPAL DODY 2.llE-01 3.00E+00 7.03E+00

'IUTAL DOSE (MRD4) FOR TiYROID 3.93E-02 1.00E+01 3.93E-01

'IUPAL DOSE (MRD4) EOR KIDNEY 1.19E-01 1.00E+01 1.19E+00

'IUTE IX)SE (MRD4) EOR WNG 6.25E-02 1.00E+01 6.25E-01

'IUPAL DOSE (MRD4) FOR GI-LLI 2.44E-01 1.00E+01 2.44E+00 1

Baaed 'on Technical Specification 3.11.1.2 which restricts dose to the Whole body to less than or equal to 1.5 mrem per quarter and 3.0 mrem per year. Dose restricticn to any organ is less than or equal to 5 mrem per quarter and 10 mrem per year.

Page 5 of 31

Year 1987 LIQUID CLNUIATIVE DOSE SlbNARY TABIE 2 A. Fission & Activation Products Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (rnt including H-3,

1. Total Release - gases, alpha) Ci 1.07E-02 1.05E-02 2.44E-02 2.44E-01 2.90E-01 l l

2. Maximxn Organ Dose (mrem) 9.55E-03 2.85E-03 3.75E-03 2.58E-01 2.59E-01

3. Organ Dose Limit (mrem) l 5.00E+00 5.00E+00 5.00E+00 L ME+00 1.00E+01 l l

4.  % of Limit 1.91E-01 5.70E-02 ll7.50E-02 ll5.16E+00 i 2.59E+00 B. Tritium

1. Total Release Ci 8.85E+01 1.15E+02 1.02E+02 1.llE+01 3.17E+02

2. Maximxn Organ Dose (mrem) i 8.05E-03 1 8.55E-03 i 7.75E-03 3.39E-03 2.77E-02

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

4.  % of Limit l1.61E-01 1.71E-01 1. 55E-01 16.78E-02 2.77E-01 Thic table is included to show the correlation between curies released and the associated calculated nuinn organ dose. Wolf Creek ODW methodology is used to calculate the maxinum organ dose which assumec that an individtul drinks the water aryl eats fish from the discharge point. Technical Specification 3.11.1.2 organ dose limits are used. ,

I Page 6 of 31

Year 1997

, - REPORT OF PADIOACTIVE EFF1UEtTTS: AIRBORNE Quarter Quarter Unit 3 4 A. Fission & Activation Gases

1. Total Release Ci 6.79E+01 1 7.46E+01

2. Average release rate for period l uCi/sec 2.66E+01 1.07E+01

3. Percent of Technical Specification Limits l  %- 3.92E-02 l 3.64E-02 B. Iodines i

1.. Total Iodine-131 l Ci 9.64E-06 1.06E-05

2. Average release rate for perio3 uCi/sec 1.21E-06 1.34E-06

3. Percent of Technical Specification Limits I  % l 9.64E-04 i 1.06E-03 C. ~ Particulates l

1. Particulates with half-lives > 8 days Ci 1.78E-06 6.55E-05

2. Average release rate for period uCi/sec 2.24E-07 8.24E-06

3. Percent of Technical Srxx:ification Limits  % 3.2tE-04 4.61E-04 1

4. Gross Alpha radioactivity Ci 0.00E+00 0.00E+W D. Tritium ..

1. Total Release Ci l 8.35E400 3.03E+00

2. Average release rate for pericd uCi/sec l 1.09E+00 4.llE-01 l

3. Percent of Tedmical Specificatica Limits  % 7.93E-02 2.88E-02

'Ihe percent of Technical Specification Limits for fission and activation cpses is calculated using the folicwin3 methodology:

% of Technical Specification Limit = (Quarterly 'Ibtal Gamna Airdose)(100) ,

5 mrad The percent of Technical Specificaticn Limits for Icxiine is calculated using the follcuing methodology:

% of Technical Specification Limit = (Total Curies of Iodine-131)(100) 1 curie Page 7 of 31

'Ibe percent of Technical Specification Limits for particulates is . calculated using the following methodology:

- % of Technical Specification Limit = (Highest Organ Dose due to Particulates)(100) 7.5 mrem

'IhA percent of Technical Specification Limits for tritium is calculated using the following methodolocff:

% of 'Ibchnical Specification Limit = (Highest Organ Ibse due to H-3)(100) 7.5 mrem This type of methodology is used sin the Wolf Creek Technical Specifications tie releases to doses rather than Curie release rates.

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Page 8 of 31 l

4 Year 1987 GASEOUS EFFWEtES Continuous Mode batch Mode NUCLIDES l Quarter l Quarter l Quarter Quarter RELEAS E Unit 3 1 4 3 4 1.- Fission and Activation Gases Ar-41 Ci~ 0.00E+00  ! 0.00E+N 2.llE-01 0.00E400 l

Kr-85 '

Ci 0.00E+00 0.00E+00 4.29E-05 1.12E-02 l \

Kr-85M Ci , 0.00E400 0.00E+N I 2.95E-03 ,

0.00E+N Kr-87 Ci l 0.00E+00 0.00E+00 '

O.00E+m 0.00E+N Kr-88 Ci 1 0.00E+00 l 0.00E+N 5.53E-04 0.00E 6 Xe-131M Ci i 0.00E400 0.00E+00 l 6.31E-03 l 6.11E-04

\ l Xe-133 Ci 1 5.97E+01 4.83E401 1 6.70E+00 2.63E+01 1

Xe-133M Ci i 0.00E+00 l 0. NE+00 4.60E-02 4.17E-03 Xe-135 Ci 1.14E+00 1 0.00E @  ! l.22E-01 5.50E-03 Xe-135M Ci  ! 0.002400 0.00E+00__ 0. 00E+ 00 0.00E 6 Xe-138 Ci l 0.00E+00 0.00E+00 0.00E+00 0.00E+N 1 1 \

Total Ci L 6.08E+01 4.83E+01 7.09E+00 2.63E+01

2. Halogens (Gaseous)

I ~7~

I-131 Ci l 9.64E-06 1.G2-05 l<5.51E-07 <3.91E-05 I-133 Ci 4.14E-06 <2.55E-02 l<5.51E-05 <3.91E-03 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Er-82 Ci  ! 0.00E400 O.00E+00 h 0.00E+00 0.00E+00 Total l' Ci 1.38E-05 1.06E-05 1 0.00E+00 0.00E+00 Note: Less than values are calculated usirg the loger limit of detectic.J (LID) values obtained at Wolf Creek Generating Station nultiplied by the volume of air discharged during the respec+.ive quarter.

Page 9 of 31

Year 1987 GASEQUS EFFIDDES Cbntinuous Fbde Batch Mode NUCLI l r l Quarter l Quarter Quarter

3. Particulates l 11 - 3 Ci 8.33E+00 2.22E+00 l 1.65E-02 8.05E-01 Co-58 Ci 0.00E+00 6.55E-05 0.00E 6 0.00E 6 1 l Co-60 Ci l 1.78E-06 l 0.00E 6 0.00E+00 0.00E 6 Mn-54 Ci <2.55E-03 <2.55E-03 <5.51E-06 <3.91E-04 Fe-59 l ~Ci i <2.55E-03 l <2.55E-03 l <5.51E-06 <3.91E-04 l l l Zn-65 l Ci 1 l- <2.55E-03l <2.55E-03 l <5.SlE-06 <3.91E-04 l l l lb-99 Ci <2.55E-03 <2.55E-03 ' <5.51E-06 <3.91E-04 Cs-134 Ci <2.55E-03 l<2.55E-03 <5.51E-06 <3.91E-04 l l Cs-137 Ci l <2.55E-03 <2.55E-03 1 <5.51E-06 <3.91E-04 _

Ce-141 Ci <2.55E-03 <2.$5E-03 <5.51E-06 <3.91E-04 l

Ce-144 j_ Ci _l <2.$5E-03 l l <2. 55E-03l <5.51E-06 'l <3.91E-04 l l l

Sr-89 l Ci <3.55E-03 l <2.55E-03 <5.51E-06 l <3.91E-04 l

l l Sr-90 l' Ci l <2.55E-03 i<2.55E-03 l <5.51E-06 l <3.91E-04 1

Gross Alpha Ci l <2.55E-03 [ <2.55E-03 l <5.51E-06 <3.91E-04 l l l l l l l l \ l l l l l l l l l l l l l l l l l l l l l l l

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Note Less than values are calculated using the lower limit of detecticn (IlD) values obtained at Wolf Creek Generating Station nultiplied by the volume of air discharged during the respective quarter.

Page 10 of 31

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Year 1987 GASEKXE CLMKJ&IVE DOSE SLBMME Table 1 TECHNICAL SPECIFICATION  % OF

. QUARTER 1 OF 1987 LIMIT LIMIT DOSE FROM RADIOIODINES, PARTICULATES, AND TRITILE AT CDNTROLLING IDCATION:

70rAL DOSE (MREN) FOR BONE 2.02E-04 7.50E+00 2.69E-03

'IUTE DOSE (MREN) FOR LIVER 1.20E-02 7.50E+00 1.60E-01 1UTAL DOSE (MREN) MR 7UTAL DODY 1.20E-02 7.50E+00 1.60E-01 TUTE DOSE (MREN) EUR THYROID 1.23E-02 7.50E+00 1.64E-01 7UTAL DOSE (MREN) FOR KIDNEY 1.20E-02 7.50E+00 .1.60E-01

'1UTE DOSE (MRD4) EUR WNG 1.20E-02 7.50E+00 1.60E-01 TUTAL DOSE (MREN) FOR GI-LLI 1.21E-02 7.50E+00 1.61E-01 QUARTER 2 OF 1987 EOSE FRCN RADIOIODINES, PARTICULATES, AND TRITILN AT OJNTROLLING IDCATION:

TUTAL DDSE (MREN) FOR BOtE 3.13E-05 7.50E+00 4.17E-04

'IUTAL DOSE (MRIN) EOR LIVER 3.35E-02 7.50E+00 4.47E-01 TUTAL DOSE (MREN) FOR TUTAL DODY 3.35E-02 7.50E+00 4.47E 'IUPAL DOSE (MREN) FOR THYROID 3.35E-02 7.50E+00 4.47E-01 7UTAL IDSE (MREN) EDR KIDNEY 3.35E-02 7.50E+00 4.47E-01 ,

TUTE DOSE (MREM) EOR LUNG 3.35E-02 7.50E+00 4.47E-01

'10rAL DOSE (MPH 4) EUR GI-LLI 3.35E-02 7.50E+00 4.47E-01 QUARTER 3 OF 1987 DOSE FRCH RADIOIODINES, PARTICULATES, AND TRITIlN AT CDNrFOLLING LOCATION:

TUfAL DDSB (MREN) FOR frM: 3.86E-05 7.50E+00 5.15E-M

. 7UTAL DOSE (MREM) FOR LIVER - 5.99E-03 7.50E+00 7.99E-02 *

IUPAL DOSE (MREN)' EUR 70rAL BODY 5.99E-03 7.5FC400 7.99E-02 -

'IUPAL DOSE (MP.EN) FOR 'nIYROID 1.15E-02 7.50E+00 1.53E-01 7UTAL DOSE (MREN) FOR KIDNEY 6.00E-03 7.50E400 -8.00E-02

'1UTE DOSE (MREN) EOR WNG 5.98E-03 7.50E400 7.97E-02 TUPAL DOSE (MREN) EOR GI-LLI 5. 9'3E-03 7.50E+00 7.97E-02 QUARTER 4 O? 1987 DOSE FROM RADIOIOCINES, PARTICULATES, AND TP.ITIlN AT CONTROLLING IDCATION:

TorAL DOSE (MRU4) EUR BONE 3.26E-05 7.50E+00 4.35E-04

'1UTE DOSE (MPB4) EOR LIVER 2.20E-03 7.50E+00 2.93E-02

'IUPAL DDSE (MREN) EDR 70rAL DODY 2.19E-03 7.50E+00 2.92E-02

'IUTE DOSE (MRD4) EOR 'IHYROID 8.25E-03 7.50E+00 1.10E-01 TUTAL DOSE (MRD1) EOR KIDNEY 2.20E-03 7.50E+00 2.93E-02 7UTAL DOSE (MRDi) FOR WNG 2.18E-03 7.50E+00 2.91C-02 TUTAL DOSE (MRD4) FOR GI-LLI 2.20E-03 7.50E+00 2.93E42 Page 11 of 31

' ' .l'16fAIS FOR 1987 -

DOSE FBQ4 RADIOIODINES, PARTICULATES, AND TRITIUM AT CotiflOLLING IDCATION:

- '10fAL DOSE (MREM) FOR BONE 3.04E-04 1.50E+01. 2.03E-03.

'IUPE DOSE ~ (MRD4) FOR LIVER 5.37E-02 1.50E+01 3.58E-01

'IUPE DOSE (MRD4) FOR '10fAL BODY 5.37E-02 1.50E+01- 3.58E . 'IUTE DOSE (MRD1) FOR 'IEYROID 6.55E-02 1.50E+01 4.37E-01

' 'IUPAL DOSE (MRD4) FOR KIDNEY 5.37E-02 1.50E+01 3.58E-01

- '1UPE DOSE (MREM) FOR LUNG 5.37E-02' l.50E+01_ 3.58E-01

'1UPAL DOSE (MRD4) FOR GI-LLI 5.37E-02 1.50E+01 -3.58E-01

- 1. ' Based on Wolf Creek Technical Specification 3.11.2.3 whi& restricts dose.during any.

calendar quarter to less than or equal to 7.5 mrem to any organ and during any calendar year to less than or equal to 15 mrem to any organ.

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Page 12 of 31

Year 3987 GASDJUS CUMUIATIVE IDSE SMRRY TABIE 2 A. Fission'& Activation Gases Quarter 1 Quarter 2 Quarter 3 uuarter 4 Total

1. Total Release (Ci) 1. 33E+01 1.75E+01 6.79E+01 7.46E+01 1.73E+02 l l l

2. Total Gantua Airdose (mrad) 4.74E-04 1.13E-03 1.%E-03 1.82E-03 5.38E-03

3. Ganina Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

4.  % of Limit l 9.48E-03 2.25E-02 l 3.92E-02 1 3.64E-02 1 5.38E-02 B. Particulates

1. Total Particulates (Ci) 1.14E-04 1.20E-05 1.78E-06 6.55E-05 1.93E-04

2. Maximum Organ Ibse (mrem) 2.54E-04 l 3.80E-05 2.46E-05 l 3.46E-05 3.51E-04'

3. Organ Dose Limit (mrem) 7.50E+00 l 7.50E+00 l 7.50E+00 l 7.508400 1.50E+01

4.  % of Limit 3.39E-03 5.07E-04 3.28E-04 4.61E-04 2.34E-03 C. Tritium

1. 'Ibtal Release (C1) 1.66E+01 4.69E+01 8.35E+00 3.03E+00 7.49E+01 l l l l

2. ,Maxiirun Organ Dt se (mrem) l 1.18E-02 3.34E-02 l 5.95E-03 l 2.16E-03 1 5.33E-02 l

3. Ortan Dxv3 Limit (mrom) 7.50E+;j0 7.50E H30 7.Sf)E+00 7.50E+00 1.50S+01

4.  % of, Limit i 1.57E-01 4.45E-m 7.93E-02 2.88E-02 3.55E-01 D. Iodine __

1. Total I-131 (Ci) 4.69E47 0.00E+00 9.64E-06 1.06E-05 2.07E-05 l l

2. Maxinum Organ Dose (mrem) 2.68E-04 0.00E+00 5.51E-03 6.06E-03 1.18E-02

3. Organ Ibse Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1. 5/'E+01

4.  % of Limit 1 3.57E-03 l 0.00E+00 l 7.35E-02 l 8.08E-02 7.87E-02 1

These values differs frcxn the "Report of Radioactive Effluents: Airborne" table since this value is based on dose and not one (1) curie.

This table is included to shcw the correlation between curies released and the associated calculated nnxinum organ dose. The maxirum organ dose is calculated using Wolf Creek ODQ4 nethodology Wich assumes that an individual actually resides at the release point. Technical Specification 3.11.2.3 organ dose limits are used.

Page 13 of 31

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2 SE"~rION II Supplemental Infornntion Facility: Wolf Creek Generating Station License Number: W F-42

1. Regulatory Limits A. For liquid waste effluents A.1 The concentration of radimetive nnterial released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained roble gases. For dissolved or entrained ny e ~

gases, the concentrstion shall be limited to 2 x 10 microcurie /mltotalactivity.

A.2 The dose or dose cannitment to a MEMBER OF 'HE PUBLIC fran radioactive nnterials in liquid effluents released, fran each unit, to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrens to the whole 1xdy and to less than or equal to 5 mrenu to any organ, and

b. Durino any caleMar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

B. For gaseous waste effluents B.1 '1he dose rate due to radicactive naterials released in gaseous effluents fran the site to areas at and toyond the SITE BOUNDARY shall be limited to the folicving

a. For noble gases: Less than or equal to 500 mrans/yr to the Whole body and less than or equal to 3000 mrans/yr to the skin, and

b. Fbr Iodine-131 aM 133, for tritium, and for all radionuclides in particulate fcrm with half-lives greater than 8 days: Less than or equal to 1500 mrans/yr to any organ.

B.2 The air dose due to noble gases released in gaseous effluents, fran each unit, to areas at and beyord the SITE DOUNDARY shall be limited to the follcwing:

a. During any calendar quarter: Less than or equal to 5 mrads for gamm radiaticn aM less than or equal to 10 mrads for beta radiation, and

b. During any caleMar yar: Less than or equal tc 10 mrads for gamna radiation and less than or equal to 20 mrads for beta radiaticn.

B.3 'Ihe dose fran Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 chys in gaseous effluents released, fran each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the follcuing:

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a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, arx1

b. During any calendar years Less than or equal to 15 mrens to any organ.

'2. Maxinum Permissible Concentrations Water - covered in section 1.A.

Air - covered in secticn 1.B.

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

4. Measurements and Approxinations of Total Radioactivity A. Liquid Effluents LIQUID RELEASE SMFLING MEM DD OF l TYPE OF ACTIVITY TYPE FREDUENCY ANMXSIS l A E YSIS I

l l l

1. Batch Waste  !

P .H. A. l Principal Gamn Release '

P l l Enmiters Tanks Each Batch '

l P.H.A. .

I-131

a. Waste l l Mcnitor l P l Dissolved and Tank ' One Batch /M l P.H.A. I Entrained Gases (Ganma Emitters)

b. Secondary I Liquid '

P l L.S. H-3 Waste l Each Batch l' l Monitor l G . F.P . I Gross Alpha Tank l P '

O.S.L. I Sr-89, Sr-90 Each Batch l O.S.L. 'l Fe-55 P = prior to each batch M = nonthly P.H.A. = gamn spectrum pulse height analysis using a liigh Purity Gen:nnium detector.

L.S. = liquid scintillation G.F.P. = Gas Flcw Proportioral omnting 0.S.L. = perforned by an Offsite Iaboratory There were no continuous radioactive waste effluents for this reporting period.

15 of 31

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4 B. Gaseous Waste Effluents e

l SAWLING l MIml0D OF TYPE OF GASEDUS, RELEASE TYPE l EREQUENCY AtRLYSIS '

ACPIVITY ANALYSIS l

P

, Eadi Tank 'lP.H.A. l Principal Ganma Waste Gas Decay Tan ['. I Grab Sanple Emitters l \'

P Principal Gama Con *ainment Purge or j Each Purge P.H.A. E Emitters Verst Grab Sanple % Bubbler and L.S. H-3 (oxide)

Principal Gama Unit Vent M P.H.A. Dnitters

. Grab Sanple uas uucoler and L.S. '

H-3 (oxide)

Radwaste Building l M 'P.H.A. Principal Ganma Vent i Grab Sarple l Emitters All Release Types as [ l I-131 listal alxwe .IContinuoua lP.H.A.

I-133 lP.H.A. i l l Continuous Particulate l Principal Ganma l Sanple Dnitters l l G.F.P.

Continuous l Particulate .i Gross Alpha C%rtposite l Sanple

.O.S.L. l l Catposite l Sr-89, Sr-90 Continuous Particulate Sanple Il C. A conservative error of +30% has been estimated. Wis includes voltzmtric neasiirement device, flow measurenent device and analytical errors.

5. Batch Releases There were thirty two (32) gaseous batch releases during the report pericr3. The icn3est gaseous batch release took 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, the shortest occurred over a ninty-six (%) minute interval. %e average release took 57.5 inirs wiU a total gaseous batch release time of 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br />.

%ere were 201 liquid batch releases during Ole report pericx1. We longest liquid batd1 release took 395 minutes while the shortest took cnly 30 minutes. %e average release time for the liquid batch relaises was 93.4 minutes. To':a1 release time for all 201 liquid batch releases was 312.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.

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~

6.'.- Atmomal' Releases s

a. - here were.two abnormal ligdid releases for this_ report period.

Section IV contains a description of these events.

+ -b. There were no abnomal gaseous releases for this report period.~.

4 1

5 4

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I!3TwENT NO WetE DITOGAL SEMIAltKRL 1GFORr (1987) soLlD wers anneurs A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOPAL (Not irradiated fuel) 1

1. Type of waste l Unit l 6-month Est. Total l l Period ' Error %

a. Spent resins, filter sludges,I m3* 1.55E+01 evaporator bottcms, etc. Ci 6.31E-01 2.50E+01

b. Dry cotipressible waste, m3" , 2.88E+01 contaminated equip. etc. Ci 8.36E-01 2.50E+01

c. Irradiated conponents, m3" 1 0.00E+00 control' rods, etc. Ci 1 0.00E+00 0.00E+00

c. Utner toescr10e) I m4" l J./bs+0U Mechanical Filters '

Ci l 3.93E+00 2.50E+01 m3* = cubic meters

2. Estimate of nnjor nuclide cotiposition (by type of waste)

a. Co-58  % 4.91E+00 H-J  % l 9.35E+01 Fe-55  % 1.54E+N C-14 '

% l 1.10E-01

b. Cr-51  % 1.77E-01 bh-54  % 1 7.84E+00 Fe-55  % 4.82E+01 Co-58 l  % 1 1.55E+01 Co-60 1  % 2.38E+01 N1-b3 )  % 4.68E+00 C-14  %  ! 8.97E-02 Nb-Vb i  % 1 1.77E C Fe-59  % 1.35E-Ol

c. None

d. Cr-51  % 3.23E+01 Mn-54  % 4.10E+00 Fe-55  % 3.44E-02 Co-b8 1  % 5.06E+01 Co-60  % 6. 44E+@

Fe-59 l  % 1 1.81E+00 Ni-63  % 3.28E-03 C-14 {  % l 7.36E-05 Zr-95 1  % 2.05E400 ND-Vb  % i 2.47E+00 Cs-137  % 3.842-02 18 of 31

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3. Solid waste Disposition Nmber of Shipnents Mode'of Transportation Destination 1 Truck Barnwell, South Carolina 3 Truck Beatty, Nevada

4. Class'of Solid Waste

a. Class A'

b. Class A

c. Not applicable

d. Class A

5. Type of container.

a. -LSA (Strong, tight)

b. LSA (Strong, tight)

c. Not applicable

d. ISA (Strong, tight)

6. Solidification Agent

a. Cement

b. Not applicable

c. Not applicable i d. Not applicable B.' IRRADIATED FUEL SHIPMENTS (Disposition)

There were rn irradiated fuel shipnents durirx3 this reporting pericx1.

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SKTim III IEEEE AT 501 WDE) WWID ABD DIRBCTIGi All gaseous releases at the Wolf Creek Generating Station are ground level releases. '1he meteorological data supplied in these tables omter the period fran January 1,1987, through Decenber 31, 1987, and indicate the number of

. hours at each wind speed and direction for each stability class. .

STABILITY CLASS: A E2VATION: GIWXND WIND SPEED (!fH) -

w1ND DIRECPION 1-3 4-7 8-12 1348 19-24 >24 MPAL N 0 10 16 1,8 4 0 48 NNE O 5 4- 0 0 0 9 NE O O O O O O O HE O O O O O O O ,

t E O O O O O O O ESE O O 1 0 0 0 1 SE 1 0 2 0 0 0 3 SSE O O 1 0 0 0 1 S 0 2 42 26 2 0 72 SSW 0 0 5 14 1 0 20

!M 0 0 0 0 0 0 0 W- 1 0 0 0 0 0 1 W- 1 0 -0 0 0 0 1 MM 0 1 0 0 0 0 1 NW 0 1 0 0 0 0 1 MM 0 5 13 6 0 0 24 WrAL 3 24 84 64 7 0 182 Periols of Calm (Hours): 0 1

20 of 31

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7;v STABILITY CUNSS: B- ELEVATION: GROL.ND WIND TEED (WH)

WIND

DIRECTION 1-3 4-7 8-12 13-18 19-24 =>24' '1 URAL N 1 3 9 5- 0 0 18 NNE . 0 6 2 0- 1 .0 .9

-0 3 0 0 0 0 3

~.NE ENE O O O 0- 0 0 0 E O O O O O 0 0 ESE O 1 0 1 0 'O 2 SE O 1 11 3 0 0- 15 SSE O 1 6 1 0 0 8 -

S 1 2 53 28 7 0- 91 SSW 0 1 15 24 4 0 44 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 l 0 0 0 0 -0 1-NW 0 1 0 0 0 0 1 IWW 0 3 11 7 0 -0 21

'IUPAL .

3 22 108 69 12 0 214 Pericxis of Calm (Iburs): O STABILITY C1 ASS: C EUNATION: GROLND WIND SPEED (WH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 'IUPAL N 0 6 21 12 1 1 41 NNE 1 2 5 1 5 0 14 IE O 1 3 2 0 0 6 ENE O O O O O O O ,

E O 1 0 0 0 0 1 ESE O 2 2 2 0 0 6 SE O 1 12 3 0 0 16 SSE O 2 4 7 2 0 15 ,

S 0 8 50 31 7 0  %

SSW 0 4 39 31 1 0 75 SW l 1 7 2 2 0 13 WSW 0 0 0 0 0 0 0 T

W 0 1 0 0 0 0 1 L

-WM 0 1 0 2 0 0 3 NW 0 1 0 0 0 0 1 -

RM 0 9 14 14 2 0 39

'1 URAL 2 40 157 107 20 1 327 Pericxis of Calm (Iburs): 0 21 of 31

7 - g.- s.o .

. " h 16 h,,

<lp, ,,( .

. . . M p: . .

3_

, STABILITY CLASS: D:

~

. EU! NATION: GROL2O

' ~

WIND W EED (W H)

'g DIRECTION 1-3 4-7: 8-12 -- 13-18 '19-24 >24 'IUPE ,

N- '

5' 38- 100 :74 33 7' 257-taE : 6 45: 124 124 37. .3 339 iNE 10 .194' -111' 34 :0' S -259 I!NE -3 35: 61 24 1- 0 124

': E' .l' 15 59 ', .48 .1 9. -124-ESE. -4 31 40- 19 0 0 ' 94 -

SE 17 39- 62 11 3 .0 122 SSE , 6 -- 69' :122- 83 - 0 293 S 14~ 110 249 '177 56 1 607- ,

ssw - 17 61- 217 111 31 0 437.

~SW 4 '43 45 - 18 7 0 117-WSW '6 37- 38 18 13 2 114

-W. 4 30 38 ~10 5 0. 87 M 3 20 37 '56 14 2 132 NW <

.4 22 .57. 97 ' 28 11 291 ItM =10' 33 115 104 31 5 298

'IUPE 104 . 732 . 1475 1008 273 31 3623 i

Periods of Calm-(Hours): 19 FrABILITY CLASS: E EI2VATION:' GROLND WIND SPEED (WH)

WIND

- DIRECTION 1-3 4-7 8-12 13-18 '19-24 >24 'IUTE N 3 45 33 15 2 1 99 l@E '7 46 33 10 0 0  %

NE 17 79 19 l' O 0 116-ENE 16 78 40 20 1 0 155 i

E '

E 12 49 47 41 2 1 152-l- ESE- 12 79 42 8 7 0 148 SE 14 67 45 22 4 0 152 SSE 6 114 150 77 17 0 364 S 5 80 205 119 55 4 468 SSW 7 66 125 41 5 0 244

~

Si- 7 61 41 3 2 0 114 NSW 10 45 17 5 0 0 77 l

W 7 25 32 4 3 0 71 l

l W 3 24 45 17 7 0  %

NW 11 18 44 22 3 0 98 ItM 9 37 44 28 5 0 123

! 'IUTE 146 913 %2 433 113 6 2573 Perials of Calm (Hours): 23 22 of 31 l.

p -

,( A ' o:

STABILITY CIASS: F ELEVATION: . GROUND WIND SPEED (WH)

WIND DIREUPION 1-3 4-7 8-12. 13-18 19-24 >24 mrAL ~

l N , 37 12 l' O O 53' NNE 7 :54 17 'O O O 78 NE 12 45 2 0 0 0 .59 ENE 4 48 6 0 0 0 58

,1:: 7 44 14 1 0 0 66 ESE 4 59- 26 1 0 0 90 SE 3 91 18 2 0 0 114 SSE 4 55 28 12 1 0 100 S 6 29 28 9 2 0 74 SSW 2 25 37 2 0 0 66 SW 5 15 15 1 0 0 36' WSW l 24 13 0 0 'O 38 W- 4 14 7 0 0 0 25

.WNW 6 17 17 0 0 0 40 NW 8 43 21 3 5 0 80 W 9 41 15 0 0 0 65 WrAL 85 641 276 32 8 0 1042 Pericris of Calm (Hours): 1 STABILITY CLASS: G ELEVATION: GROLND WIND SPEED (WH)

WIND DIREUPION 1-3 4-7 8-12 13-18 19-24 >24 MTAL N 1 11 4 0 0 0 16 NNE 2 17 7 0 0 0 26 NE O 11 1 0 0 0 12 ENE 2 16 2 0 0 0 20 E O 13 12 0 0 0 25 IEE 1 18 4 0 0 0 23 SE 2 28 1 4 0 0 35 SSE 1 39 6 0 0 0 46 S 3 15 11 0 0 0 29 SSW 0 8 3 0 0 0 11 Si 2 8 2 0 0 0 12 WSW 2 10 0 0 0 0 12 W 5 5 1 0 0 0 11 WNW 2 14 1 0 0 0 17 NW 3 32 7 0 0 0 42 M 4 18 13 0 0 0 35 WIAL 30 263 75 4 0 0 372 Perials of Calm (ikxtrs): 0 23 of 31

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-N STABILITY CLASS: All ELEVATION: GROLND fi:n WIND WIND SPEED (bPH)

DIRECTIO4 1-3 -

7 8-12 '13-18 19-24 >24 1 URAL ll[

iI N- 13 150 195 125 40 9 532 8 tt4E 23 175 192- 135 43 3 571 k NE- 39 243 136 37. 0 2.

0 0

455-jl ENE 25 177- 109 44 357 q -

~

E 20 122 132 90 3 1 368-ESE 21 ~190 115 31 7 0 364 L SE 27 227 151 45 7 0 457 SSE 17 280 317 '180 33 0 827 i - .

S 29 246 638 390 129 5 1437

- SSW 26- 165 441 223 42 0 897 SW 19 128 111 24 11 0 293 WSW 20 116 68 23 13 2 242 W 21 75 78 14 8 0 1%

• WrE 15 77 100 75 21 2- 290

!M 26 118 129 122 36 11 442 MM 32 146 225 159 38 5 605 1 URAL 373 2635 3137 1717 433 38 8333 Pericds of Calm (Hours): 43 lburs of Missing Data 384 The ocmputer that supplies the wind speed arx1 direction data for Wolf Creek Generating Statica does not report hourr unless tlwre are three 15 minute intervals of 90o3 data per hour. The 384 missing hours of data are due to i this criteria. In nost casca there is at least one good fiftest minute interval for each hour. This data is avullable for review at the Wolf Creek site.

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SEKTI0ti IV Additional Information

1. Unplanned Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .P age 26 '

2. Process Control Program. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Page 26

3. Offsite Dose Calculaticn Manua1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Page 27

4. Major Omnges ' to Radwaste Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Page 27

5. Land Use census . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Page 27 -

6. Radioactive Shipments............................................Page 27

.7. Inoperable Equipnent . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Page 27 C

23 of 31

. * :o SEFIGE IV JWklitional Infkmmation

1. Unplanned Releases

a. 'Ihe first unplanned release occurred on July 26, 1987 during.

an authorized release from Secondary Liquid Waste Monitor Tank (SIMfr) 'B' . 'Ihis occurrence was discovered on July 27, 1987, while obtaining routine tank logs, when it was noted' that SIMfP 'A' level had decreased from six percent to zero pircent during de time period of the SIJMP 'B' release. A sunple of the drain line on SIMfr 'A' was collected and analyzed.

Technical Specifications require that each Waste Monitor Tank be sartpled prior to release which had not been performed on SIM fr 'A'. A subsequent sanple en SIMfr 'A' drain line verified that site release limits had not been exceeded. The-release resulted in an estimated 6.01E-02 curies discharged and a maxinum organ dose of 4.06E-05 mrem. At no time did canditions develop that pased a threat to the health or safety of the public.

Further information concerning this unplanned release is contained in Wolf Creek Licensee Evert. Report (IER) 87-036-00.

b. A second unplanned release occurred on November 16, 1987. At 0758 hours0.00877 days <br />0.211 hours <br />0.00125 weeks <br />2.88419e-4 months <br /> en November 16, 1987, the Control Rocm received a High Alarm on Steam Generator Blowdown Radiation Monitor IN RE-52 which isolated steam generator drain-doan. Subsequent grab sanples of the bloadoen piping confirmed the presence of radioactive contamination. A liquid batch radioactive release permit was issued to cantinue the drain-doan of S/G

'A'. As the contents of S/G 'A' drained to the Wolf Creek cooling lake, the activity detected by IN RE-52 diminished to background levels. Investigation of this event determined the source of cantamination to be backficw frczn the normal radwaste discharge. With the blodcbwn system depresscrized during the refueling outage, the rurmal open position of valve BM IN-181 allcwed backf1w fran batch liquid release into the bloadoan piping. Procedure changes have been made to require BM IN-181 to be locked closed when the steam generator bloadcun path is not in use. At no time did conditions exist that posed a threat to the health or safety of the public.

Further information concerning this event is contained in Wolf Creek Event Report 87-76.

2. Process Control Program

'Ihere were no changes to the Wolf Creek Prccecs Control Program during this report period.

26 of 31 I

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3. Offsite Dose Calculation bbnual (OIn!)

he OCO1 was revised with Plant Safety Review Ccmnittee (PSRC) approval on 12-29-87. Wis was Revision 3 to the OD01. Dose factors for Co-57, Sb-124, Sb-125, and Sb-126 were included. These nuclides were not included in earlier revisions to the COO! because they are not included in Regulatcry Guide 1.109 and until 1987 did not represent a significant contribution to the liquid radaaste discharge. The dose factors for the four nuclides were obtainM frcm the reference naterial listed in Regulatory Guide 1.109. A copy of the four pages which reflect the additions are included with this report. Revisions are denoted by a revision bar in the right hand margin of each page.

4. Major Changes to Radaaste Systems There were no major changes to radwaste systems mado during this 3 report period. ,

5. Land Use Census ,

There were no new locations for dose calculations identified during this report period.

6. Radioactive Shipmnts There were four shipments of radioactive radwaste during this report b pericd. Three shipnents were to Beatty, Nevada, ard one shipmnt was to Barrraell, South Carolina.

7. Inoperable Equipnent There was no inoperable liquid or gaseous effluent monitoring instrumentation that was not corrected within the tine specifiM in Technical Specifications 3.3.3.10 or 3.3.3.11. There were no events leadire to liquid holdup tanks or gas storage tanks exceedirg the limits of Technical Specifications 3.11.1.4 or 3.11.2.6, respectively.

The following four pages are included with this report to reflect the addition of dose factors for (b-57, Sb-124, Sb-125, and Sb-126 to the ODO!.

Tb revisicns are denoted by a revisico bar in the right hard margin of each psgo.

27 of 31

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TABIE A.4-1 (cont'd)

SITE REIATED DOSE COPHI'IMENP FACIOR AIT MREN/IIR PER UCI/ML ADULT NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY Il1NG GI-LLI BA-140 1.88E+03 2.37E+00 1.23E+02 0.00000 8.05E-01 1.35E+00 3.88E+03 BA-141 4.37E+00 3.30E-03 1.48E-01 0.00E00 3.07E-03 1.87E-03 2.0GE-09 BA-142 1.98E+00 2.03E-03 1.24E-01 0.00E00 1.72E-03 1.15E-03 2.78E-18 IA-140 3.58E-01 1.80E-01 4.76E-02 0.00E00 0.00E00 0.00E00 1.32E+04 IA-142 1.83E-02 8.33E-03 2.07E-03 0.00E00 0.00E00 0.00E00 6.08E+01 CE-141 8.01E-01 5.42E-01 6.15E-02 0.00E00 2.52E-01 0.00E00 2.07E+03 CE-143 -1.41E-01 1.04E+02 1.16E-02 0.00E00 4.60E-02 0.00E00 3.90E+03 CE-144 4.18E+01 1.75E+01 2.24E+00 0.00E00 1.04E+01 0.00E00 1.41E+04 PR-143 1.32E+00 5.28E-01 6.52E-02 0.00E00 3.05E-01 0.00E00 5.77E+03 PR-144 4.31E-03 1.79E-03 2.19E-04 0.00E00 1.01E-03 0.00E00 6.19E-10 ND-147 9.00E-01 1.04E+00 6.22E-02 0.00E00 6.08E-01 0.00E00 4.99E+03 W-187 3.04E+02 2.55E+02 8.90E401 0.00000 0.00E00 0.00E00 8.34E+04 W-239 1.28E-01 1.25E-02 6.91E-03 0.00E00 3.91E-02 0.00E00 2.57E+03 Sb -124 2.40E+02 4.53E+00 9.50E+01 5.81E-01 0.00E00 1.87E+02 6.81E+03 l Sb-125 1.53E+02 1.71E+00 3.65E401 1.56E-01 0.00E00 1.10j' +02 1.69E+03 l 1

Sb-126 9.85E+01 2.00E+00 3.55E+01 6.03E-01 0.00E00 6.04E+01 8.05E+03 Co-57 0.00E00 3.55E401 5.90E+01 0.00E00 0.00E00 0.00E00 9.01E+02 [

l A-33 28 of 31

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TABIE A.4-2 (cont'd)

' SITE REIATED DOSE 00M4ITNENP FACIOR AIT MREM /HR PER UCI/ML tem

- NIETDE BONE LIVER T B00ft THYlOID KIDNEY IlJNG GI-ILI BA-140 1.86E+03 2.28E+00 1.20E+02 0.00E00 7.72E-01 1.53E+00 2.87E+03 BA-141 4.39E+00 3.28E-03 1.47E-01 0.00E00 3.04E-03 2.24E-03 9.36E-06 BA-142 1.%E+00 1.%E-03 1.20E-01 0.00000 1.66E-03 1.30E-03 6.01E-12 IA-140 3.61E-01 1.77E-01 4.72E-02 0.00E00 0.00E00 0.00E00 1.02E+04 IA-142 1.86E-02 8.25E-03 2.05E-03 0.00E00 0.00E00 0.00E00 2.51E+02 CE-141 7.98E41 5.32E-01 6.12E-02 0.00E00 2.51E-01 0.00E00 1.52E+03 CE-143 1.41E-01 1.03E+02 1.15E-02 0.00E00 4.60E-02 0.00E00 3.08E+03 l CE-144 4.17E+01 1.73E+01 2.24E+00 0.00E00 1.03E+01 0.00E00 1.05E+04 PR-143 1.36E+00 5.43E-01 6.76E-02 0.00E00 3.15E-01 0.00E00 4.47E+03 PR-144 4.46E-03 1.83E-03 2.26E-04 0.00E00 1.05E-03 0.00E00 4.92E-06 ND-147 9.73E-01 1.06E+00 6.34E-02 0.00E00 6.21E-01 0.00E00 3.82E+03 W-187 3.28E+02 2.67E402 9.37E+01 0.00E00 0.00E00 0.00E00 7.24E+04 IP-239 1.34E-01 1.27E-02 7.04E-03 0.00E00 3.98E-02 0.00000 2.04E+03 Sb-124 2.32E+02 4.28E+00 9.05E+01 5.26E-01 0.00E00 2.03E+02 4.68E+03 l Sb-125 1.49E+02 1.63E+00 3.48E+01 1.42E-01 0.00E00 1.31E+02 1.16E+03 l l

Sb-126 9.53E+01 1.95E+00 3.42E+01 5.39E-01 0.00E00 6.84E+01 5.64E+03 Co-57 0.00E00 3. 55E+01 5.%E+01 0.00E00 0.00E00 0.00E00 6.63E+02 l l

A-36 29 of 31

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TABIE A.4-3 (amt'd)

SITE REIATED DOSE O}MI'INEtTI' FACIOR AIT MREM /HR PER LEI /ML Gun NUCLIDE BONE LIVER T BODY '1HYRDID KIDNEY UJNG GI-LLI BA-140 5.09E+03 4.46E+00 2.97E+02 0.00E00 1.45E+00 2.66E+00 2.58E+03 BA-141 1.23E+01 6.86E-03 3.99E-01 0.00E00 5.94E-03 4.03E-02 6.99E+00 BA-142 5.36E+00 3.85E-03 2.99E-01 0.00E00 3.12E-03 2.27E-03 6.99E-02 IA-140 7.86E-01 2.75E-01 9.26E-02 0.00E00 0.00E00 0.00E00 7.66E+03 IA-142 4.08E-02 1.30E-02 4.07E-03 0.00E00 0.00E00 0.00E00 2.58E+03 G -141 2.34E-00 1.17E+00 1.73E-01 0.00E00 5.llE-01 0.00E00 1.46E+03 G-143 4.12E-01 2.23E+02 3.24E-02 0.00E00 9.37E-02 0.00E00 3.27E+03 G-144 1.23E+02 3.84E+01 6.54E+00 0.00E00 2.13E+01 0.00E00 1.00E+04 PR-143 3.06E+00 9.18E-01 1.52E-01 0.00E00 4.97E-01 0.00E00 3.30E+03 PR-144 1.00E-02 3.10E-03 5.05E-04 0.00E00 1.64E-03 0.00E00 6.68E+00 ND-147 2.17E400 1.76E+00 1.367- 01 0.00E00 9.65E-01 0.00E00 2.79E+03 W-187 4.30E+02 2.55E+02 1.14E+02 0.00E00 0.00E00 0.00E00 3.58E+04 tP-239 3.47E-01 2.49E-02 1.75E-02 0.00E00 7.91E-02 0.00E00 1.84E+03 l

Sb-124 6.54E+02 8.49E+00 2.29E+02 1.44E+00 0.00E00 3.63E+02 4.09E+03 Sb-125 4.22E+02 3.23E+00 8.84E+01 3.91E-01 0.00E00 2.35E+02 1. ole +03 l

Sb-126 2.59E+02 3.97E400 9.31E+01 1.52E+00 0.00E00 1.24E+02 5.23E+03 Cb-57 0.00E00 4.81E+01 9.73E+01 0.00E00 0.00E00 0.00E00 3.94E+02 l l

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30 of 31 L

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TABLE A.4-4 (cont'd)

SITE REATED DOSE CrMiITMENP FACIOR AIT MREM /HR PER UCI/ML INFANP NUCLIDE BONE LIVER T BODY 'IHYROID ' KIDNEY I11NG GI-LLI BA-140 6.43E+03 6.43E+00 3.31E+02 0.00E00 1.53E+00 3.95E+00 1.58E+03 BA-141 1.60E+01 1.09E-02 5.04E-01 0.00E00 6.58E-03 6.66E-03 1.95E+02 BA-142 6.92E+00 5.76E-03 3.41E-01 0.00E00 3.31E-03 3.48E-03 2.86E+01 1A-140 7.94E-01 3.13E-01 8.05E-02 0.00D00 0.00E00 0.00E00 3.68E+03 1A-142 4.14E-02 1.52E-02 3.64E-03 0.00E00 0.00E00 0.00E00 2.58E+03 CE-141 2.%E400 1.81E+00 2.13E-01 0.00E00 5.57E-01 0.00E00 9.33E+02 CE-143 5.57E-01 3.69E+02 4.21E-02 0.00E00 1.08E-01 0.00E00 2.16E+03 CE-144 1.12E+02 4.59E+01 6.28E+00 0.00E00 1.85E+01 0.00E00 6.43E+03 PR-143 3.06E+00 1.14E+00 1. 52E-01 0.00E00 4.25E-01 0.00E00 1.61E&O3 PR-144 1.03E-02 3.99E-03 5.19E-04 0.00E00 1.44E-03 0.00E00 1.85E+02 ND-147 2.03E+00 2.14E+00 1.31E-01 0.00E00 8.24E-01 0.00E00 1.35E+03 W-187 3.40E+01 2.36E+01 8.16E+00 0.00E00 0.00E00 0.00E03 1.39E+03 IP-239 4.18E-01 3.74E-02 2.llE-02 0.00E00 7.45E-02 0.00E00 1.08E+03 Sb-124 8.05E+02 1.19E+01 2.49E+02 2.14E+00 0.00E00 5.04E+02 2.48E+03 l Sb-125 4.63E+02 4.48E+00 9.52E+01 5.79E-01 0.00E00 2.90E+02 6.17E+02 l l

Sb-126 3.03E+02 5.94E+00 1.09E+02 2.33E+00 0.00E00 1.91E+02 3.14E+03 (b-57 0.00E00 4.33E+01 7.03E+01 0.00E00 0.00E00 0.00E00 1.47E+02 l l

A-42 31 of 31

W4) LF NUCLEAR CREEKOPERATING U $

Chsef Executive Omcor February 26, 1988 VM 88-0046 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washir6 ton, D. C. 20555

Subject:

Docket No. 50-482: Semiannual Radiological Effluent Release Report Gentlemen Attached is the Wolf Creek Generating Station Semiannual Rsdiological Effluent Release Report covering the period from July 1, 1987, through December 31, 1987. This report is submitted parsuant to section 6.9.1.7 of the Wolf Creek Generating Station, Unit No. 1, Technical Specifications.

Very truly yours, e -__2 Bart D. Withers Prasident and Chief Executive Officer BDV/11k Attachment oc B. L. Bartlett (NRC), w/a R. D. Msrtin (NRC), w/a P. V. O'Connor (NRC), 2 v/a l

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I PO. Box 411 I Burhngton, KS 66839 / Phone: (316) 364 8831 An EW opportunty Employw MMCVET l I

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