ML20134N432
| ML20134N432 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/30/1985 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Martin R NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| KMLNRC-85-212, NUDOCS 8509050137 | |
| Download: ML20134N432 (19) | |
Text
.-
Wolf Creek Generating Station Docket No: SIN 50-482 Facility Operating License No: NPF-42 I
SIDED M U E RADIn tr:TCAL EETHENE IEEumSE REPORF Report No: 1 Reporting Period: January 1,1985 through June 30, 1985 Subnitted by:
Kansas Gas and Electric Company i
PDR ADOCK 05000482
>\\k
INTR)DUCTIOM W is Semiannual Radiological Effluent Release Report covers the period of January 1,1985, through June 30, 1985, and satisfies the requirements specified in Technical Specificaticn 6.9.1.7.
Facility Operatirg License NPF-32 was issued to Wolf Creek Generating Station on March 11, 1985, authorizing initial fuel loading ard physics testing up to five percent of full power. Initial criticality was achieved on May 22, 1985. Facility Operatirs License NPF-42 was issued on June 4,1985, authorizing further physics testing and full-power operation.
Section I provides a sunmary of the quantities of radioactive liquid ard
, gaseous effluents for this reporting period. We format is similar to that proiided in Regulatory Guide 1.21, Revision 4.
An elevated release pathway does not exist at Wolf Creek Generating Station. W erefore, all airborne releases are considered to be ground level releases. A conservative error of thirty percent has been estimated in effluent data. W ere was no shipment of solid waste durirg this reporting period. An assessment of radiation doses to the likely nest exposed member of the public for this reporting period will be provided in the next Semiannual Radiological Effluent Release Report.
Section II provides Supplemental Information as described in Regulatory Guide 1.21, Revision 4.
Section III provides a sunmary of Meterological Data for the period of May 1,1985, through June 30, 1985.
Section IV provides additional information required by Technical Specificaticn 6.9.1.7.
Page 1 of 17
SECTICN I Year 1985 REPORT OF RADIOACTIVE EFFIDENTS: LIQUID Quarter Quarter Unit 1
2 A.
Fissicn and Activation Products 1.
Total Release (not including trititn, gases, alIfla)
Ci 0.00E00 2.82E-04 2.
Average diluted concentration during period uCi/ml 0.00E00 6.09E-ll 3.
Percent of Applicable Limit 0.00E00 5.64E-03 B.
Tritium 1.
Total Release Ci 0.00E00
- 1. 37E-01 2.
Average diluted concentration during period uCi/ml 0.00E00 2.96E-08 3.
Percent of Arplicable Limit 0.00E00 1.05E-05 C.
Dissolved and Entrained Gases 1.
Total Release Ci 0.00E00 2.32E-04 2.
Average diluted concentration during period uCi/ml 0.00E00 5.02E-ll 3.
Percent of Applicable Limit 0.00E00 2.32E-08 D.
Gross Alpha Radioactivity 1
Total Release Ci 0.00E00 0.00E00 E.
Voltne of waste released liters 0.00E00 1.294E+06 F.
Voltrne of dilution water used liters 0.00E00 5.22E+09 Page 2 of 17
Year 1985 LIQUID EFFLUENIS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1
2 1
2 H-3 Ci 0.00E00 0.00E00 0.00E00 1.37E-01 Na-24 Ci 0.00E00 0.00E00 0.00E00 3.92E-05 Cr-51 Ci 0.00E00 0.00E00 0.00E00 8.42E-06 Co-58 Ci 0.00E00 0.00E00 0.00E00 1.34E-05 Tc-99M Ci 0.00E00 0.00E00 0.00E00 4.66E-05 I-131 Ci 0.00E00 0.00E00 0.00E00 3.45E-05 I-132 Ci 0.00E00 0.00E00 0.00E00 1.08E-06 I-133 Ci 0.00E00 0.00E00 0.00E00 7.99E-05 I-135 Ci 0.00E00 0.00E00 0.00E00 9.70E-06 Ba-140 Ci 0.00E00 0.00E00 0.00E00 1.50E La-140 Ci 0.00E00 0.00E00 0.00E00 8.72E-06 Ce-144 Ci 0.00E00 0.00E00 0.00E00 4.42E-06 W-187 Ci 0.00E00 0.00E00 0.00E00 2.72E-05 Xe-133 Ci 0.00E00 0.00E00 0.00E00
- 1. 35E-04 Xe-135 Ci 0.00E00 0.00E00 0.00E00 9.75E-05 Br-82 Ci 0.00E00 0.00E00 0.00E00 7.10E-06 Mn-54 Ci 0.00E00 0.00E00 0.00E00
<l.43E-05 Fe-59 Ci 0.00E00 0.00E00 0.00E00
<1.89E-05 Co-60 Ci 0.00E00 0.00E00 0.00E00
<l.26E-05 Page 3 of 17
Year 1985 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1
2 1
2 Zn-65 Ci 0.00E00 0.00E00 0.00E00
<3.0E-05 Mo-99 Ci 0.00E00 0.00E00 0.00E00
<6.14E-05 Cs-134 Ci 0.00E00 0.00E00 0.00E00
<3.07E-05 Cs-137 Ci 0.00E00 0.00E00 0.00E00
<1.36E-05 Ce-141 Ci
~
0.00E00
'0.00E00 0.00E00
<2.39E-05 Gross Alpha Ci 0.00E00 0.00E00 0.00E00
<2.36E-05 NOTE:
The data for the Nuclides Sr-89 and Sr-90 is not yet available from the off-site laboratory. This data will be reported in the next Semiannual Radioactive Effluent Release Report.
Page 4 of 17
9 Y:ar 1985 REPORP OF RADIOACTIVE EFFIDENTS: AIRBORNE Quarter
. Quarter Unit 1
2 A.
Fission & Activation Gases 1.
Total Release Ci 0.00E00 0.00E00 2.
Average release rate for period uCi/sec 0.00E00 0.00E00 3.
Percent of Tednical Specification Limits 0.00E00 0.00E00 B.
Iodines 1.
Total Iodine-131 Ci 0.00E00 0.00E00 2
Average release rate for period uCi/sec 0.00E00 0.00E00 3.
Percent of Tednical Specification Limits 0.00E00 0.00E00 C.
Particulates 1.
Particulates with half-lives > 8 days Ci 0.00E00 0.00E00 2.
Average release rate for period uCi/sec 0.00E00 0.00E00 3.
Percent of Technical Specification Limits 0.00E00 0.00E00 4.
Gross Al#1a radioactivity Ci 0.00E00 0.00E00 D.
Tritium 1.
Total Release Ci 0.00E00 2.47E-01 2
Average release rate for period uCi/sec 0.00E00 1.34E-01 3
Percent of Technical Specificaticn Limits 0.00E00 1.65E-05 Page 5 of 17
e Year 1985 GASEOUS EFFLUENTS Continuous Mode Batch Mode 10CLIDES Quarter Quarter Quarter Quarter RELEASID Unit 1
2 1
2 1.
Fission and Activatim Gases Ar-41 Ci 0.00E00 0.00E00 0.00E00 0.00E00
- KR-85 Ci 0.00E00 0.00E00 0.00E00 0.00E00 KR-85m Ci 0.00E00 0.00E00 0.00E00 0.00E00 KR-87 Ci 0.00E00
<1.08E02 0.00E00
<2.06E-01 KR-88 Ci 0.00E00
<1.13E02 0.00E00
<2.16E-01 Xe-131m Ci 0.00E00 0.00E00 0.00E00 0.00E00 Xe-133 Ci 0.00E00
<5.82E01 0.00E00
<1.12E-01 Xe-133m Ci 0.00E00
<2.46E02 0.00E00
<4.73E-01 Xe-135 Ci 0.00E00
<3.07E01 0.00E00
<5.89E-02 Xe-135m Ci 0.00E00 0.00E00 0.00E00 0.00E00 Xe-138 Ci 0.00E00
<2.19E02 0.00E00
<4.21E-01 Total Ci 0.00E00 0.00E00 0.00E00 0.00E00 2.
Halogens (Gaseous)
I-131 Ci 0.00E00
<3.76E-06 0.00E00 0.00E00 I-133 Ci 0.00E00
<6.17E-05 0.00E00 0.00E00 I-135 Ci 0.00E00 0.00E00 0.00E00 0.00E00 Br-82 Ci 0.00E00 0.00E00 0.00E00 0.00E00 Total Ci 0.00E00 0.00E00 0.00E00 0.00E00 Page 6 of 17
Year 1985 i
l GASEOUS EFFLUENTS Continuous Mode Batc!. Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1
2 1
2 3.
Particulates H-3 Ci 0.00E00 2.44E-01 0.00E00 2.66E-03 Mn-54 Ci 0.00E00
<8.38E-05 0.00E00 0.00E00 Fe-59 Ci 0.00E00
<1.61E-05 0.00E00 0.00E00 l-Co-58 Ci 0.00E00
<4.80E-06 0.00E00 0.00E00 Co-60 Ci 0.00E00
<7.21E-06 0.00E00 0.00E00
~ '.00E00'
<1.73E-05 0.00E00 0.00E00 0
Zn-65 Ci Mo-99 Ci 0.00E00
<8.38E-05 0.00E00 0.00E00 l
j
'Cs-137 Ci 0.00E00'
' 6.39E-06 0.00E00 0.00E00
~
~
Cs-134 Ci
'O.00E00
<1.19E-05 0.00E00 0.00E00 Ce-141 Ci 0.00E00
<8.19E-06 0.00E00 0.00E00
'Ce-144
'Ci
'0.00E00'
<3.25E-05 0.00E00 0.00E00
~
Gross Alpha ci 0.00E00
<9.75E-07 0.00E00 0.00E00 l
l NOTE:
The data for the Nuclides Sr-89 and Sr-90 is not yet available from the off-site laboratory. This data will be reported in the next Semiannual Radioactive Effluent Release Report.
Page 7 of 17
\\
..s SECTION II Supplemental Information i
Facility: Wolf Creek Generating Station License Neber: NPF-42 1.
Regulatory Limits A.
For liquid waste effluents A.1 'me concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in le CFR Part 29, Appendix B, Table II, Column 2, for radiornclides other than dissolved or entrained noble gases. Fordissolvedoragainednoblegases,theconcentration
- ~",m shall be limited to 2 x 19 microcurie /ml total activity.
A.2 The dose oc dose commitsent to a PeBER T '!HE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited:
During any calendar quarter to less than or equal to 1.5 mrens a.
to the W mle body and to less than or equal to 5 mrems to any organ, aM b.
During any calendar year to less than or equal to 3 mrems to the whole body a M to less than or equal to 19 mrems to any organ.
B.
For gaseous waste effluents B.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
a.
For noble gases: Imss than or equal to 500 mrans/yr to the whole body and less than or equal to 3999 mrems/yr to the skin, and b.
For Iodine-131 and 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: tass than or equal to.1500 mress/yr to any organ.
B.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE B00tOARY shall be limited to the following:
a.
During any calendar quarter: Less than or equal to 5 mrads for ganma radiation aM less than or equal to 10 mrads for beta radiation, and b.
During any calendar year: tess than or equal to le meads for gaans radiation aM less than or equal to 29 mrads for beta radiation.
Page 8 of 17
2.
Maximum Permissible Concentrations WATER - covered in section L.A.
I AIR - covered in section 1.B.
3.
Average energy of fission and activation gaseaus effluents is not applicable.
- 4.
- Measurements and Approximations of Total Radioactivity A.
Liquid Effluents LIQUID RELEASE SAMPLING METHOD OF TYPE OF ACTIVITY TYPE FREQUE!CY ANALYSIS ANALYSIS Principal Gama
- 1. Batch Waste P
P.H.A.
Emiters Release Each Batd1 Tanks P.H.A.
- a. Waste Monitor P
Dissolved and Tank One Batch /M P.H.A.
Entrained Gases (Gama Dnitters)
- b. Secondary P
Liquid Each Batch L.S.
H-3 Waste Moni-G.F.P.
Gross Alpha tor Tank P
Each Batch O.S.L.
Sr-89, Sr-90 0.S.L.
Fe-55 p = prior to each batch m = monthly P.H.A. = gama spectrum pulse height analysis using a High Purity Germanium detectcr.
L.S. = liquid scintillation G.P.P. = Gas Flow Proportional counting 0.S.L. = performed by an Offsite Laboratory l
There were no continuous radioactive waste effluents for this reporting period.
l l
Page 9 of 17
_.-.. - _ -.. -...=
1 B.
Gaseous Waste Effluents SAMPLING METHOD T TYPE T GASBOUS, REIEASE TYPE FREQUEICY ANALYSIS ACTIVITY ANALYSIS P
Waste Gas Decay Each Tank P.H.A.
Principal Gama Tank Grab Dnitters Sample P
Principal Gama
- Contairunent Purge Each PURGE P.H.A.
Emniters or Vent Grab Gas Bubbler Sample and L.S.
H-3 (oxide)
Principal Gama Unit Vent M
P.H.A.
Dnitters Grab Gas Bubbler Sample and L.S.
H-3 (oxide)
M l
Radweste Building Grab P.H.A Principal Gamna Vent Sanple Dnitters All Release Types Continuous P.H.A I-131 as listed above I-133 P.H.A.
Continuous Partilculate Principal Gama Sanple Emitters G.F.P.
Continuous Particulate Gross Alpha Camposite Sample 0.S.L.
Continuous Conposite Sr-89, Sr-90 Particulate Sample C.
A conservative error of + 30% has been estimated. This includes volumetric measurenent device, flow measurement device and analytical errors.
5.
Batch Releases The Wolf Creek Generating Station did not achieve initial criticality until May 22, 1985 at 7:45 a.m.
Therefore there were no radioactive effluent releases for the first quarter of 1985.
There were fourteen (14) gaseous batch releases during the second quarter of 1985. The longest gaseous batch release took 71 hours8.217593e-4 days <br />0.0197 hours <br />1.173942e-4 weeks <br />2.70155e-5 months <br />, the shortest occurred over an eleven (11) minutes interval. The average release took 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> with a total gaseous batch release time of 247 hours0.00286 days <br />0.0686 hours <br />4.083995e-4 weeks <br />9.39835e-5 months <br />.
Page 10 of 17 l
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-m.,-.w.~,,w,,,,,----.t., -, -. _ _
w-e,~,,-
r-.--.
,_.e.--
.u
..mmm..,,-_m-_~
l
(
'Ihere were sixty-eight (68) liquid batch releases daring the second quarter of 1985. The longest liquid batch release took 285 minutes while the shortest took only 32 minutes. 'Ihe average release time for the liquid batch releases was 59 minutes. Total release time for all sixty-eight (68) liquid batch releases was 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br />.
6.
Abnormal Releases
'Ihere were no abnormal liquid or gaseous releases for this report period.
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)
f Page 11 of 17 I
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SECTION III WIND SPEED AND DIRECTION TABLES All gaseous releases at the Wolf Creek Generating Station are ground level releases. The metrological data supplied in these tables cover the period from May 1, 1985 through June 30, 1985.
STABILITY CLASS:
A ELEVATION:
GROUND WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 M AL N
0 0
0 0
0 0
0 NNE 9
0 0
0 0
0 0
NE O
O O
O O
O O
ENE O
O O
O O
O O
E O
O O
O O
O O
ESE O
O 9
0 0
0 0
SE O
3 0
0 0
0 0
SSE O
O O
O O
O O
S 0
0 0
0 0
0 0
SSW 0
0 0
0 0
0 0
SW 0
0 0
0 0
0 0
WSW 0
0 0
0 0
0 0
W 0
0 0
0 0
0 0
NNW 0
0 0
0 0
0 0
NW 0
0 0
0 0
0 0
WW 0
0 0
0 0
0 0
i..
MAL 0
0 0
0 0
0 0
l I
i I
t i
f Page 12 of 17
STABILITY CLASS:
B ELEVATION:
GROUND WIND SPEED (MPH)
WIND 1-3 '
,4-7 8-12 13-18 19-24
>24 TOTAL DIRECTION N
O O
O O
O O
O NNE O
O O
O O
O O
NE O'
O O
O O
O O
ENE O
O O
O O
'O O
E O
O O \\
0 0
0 0
ESE O
O O
O O
O O
CE O
O O
O O
O O
SSE O
O O
O O
O O
S 0
0 0
0 0
0 0
SSW 0
0 0
7 0
0 7
SW 0
0 0
0 0
0 0
WSW 0
0 0-0 0
0 0
W 0
0 0
0 0
0 0
WNW 0
0 0
0 0
0 0
NW 9
0 0
0 0
0 0
t@lW -
0 0
0 0
0 0
0 MAL 0
0 0
7 0
0 7
STABILITY CIASS:
C.
ELEVATION:
GROUND wit 0 SPEED (MPH) y
. WIND DIRECTION 3 4-7 8-12 13-18 19-24
>24
, 'IOTAL N
O O
O O
'O
'O O
NNE e
e 0
g e
e 0
NE O
O O
O 0
0 ENE 0
0 0
J 0
0 0
E O
O O
O 9
0 0
ESE 9
0 0
0 0
0 0
SE -
0 0
0 0
0 0
0 SSE G
0 2
0 0
0 2
S 0
0 2
8 1
0 11 SSW 9
0 0
2 0
0 2~
SW G
0 0,
0 0
0 0
l WSW 0
0 0
0 0
0 0
W 0
0 0
0 0
0 0
WNW 9
0 0
O G
0 0
i.
NW 0
0 0
0 0
0 0
i telW 9
0 0
0 0
0 0
l f
MAL 0
0 4
10 1
0 15 l
i Page 13 of 17 i
e lTIABILITYCLASS:
D EIEVATION:
GROUND WIND SPEED (MPH)
WIND DIRECTION l-3 4-7 8-12 13-18 19-24
>24 TOTAL N
3 5
11 13 0
0 32 NNE O
10 23 10 3
0 46 NE 2
13 10 1
0 0
26 ENE~
l 21 21 1
0 0
44 E
2.
6 14 3
1 0
26
- ESE 1
5 9
4 1
0 20 SE O
6 15 7
0 0
28 SSE 2
10 18 16 0
0 46 S
1 4
8 54 18 2
87 SSW 0
4 5
37 14 3
63 SW 0
5 1
2 3
1 12 WSW 0
4 0
0 0
0 4
W 3
8 6
7 2
0 26 WNW 2
7 10 7
2 0
28 NW 2
6 15 18 11 0
52 NNW 0
7 16 21 1
0 45
'IUPAL 19 121 182 201 56 6
585 STABILITY CLASS:
E ELEVATION:
GROUND WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24
'IOTAL N
1 7
5 10 3
0 26 NNE 4
12 12 4
3 0
35 NE 5
19 11
-2 0
0 37 ENE 5
15 6
3 1
0 30 E
5 8
21 5
0 0
39 ESE O
16 18 3
1 0
38 SE 2
12 12 3
0 0
29 SSE O
18 49 14 5
0 86 S
1 13 47 41 22 2
126 SSW l
7 11 16 1
0 36 SW 2
8 2
0' O
O 12 WSW 2
9 4
1 0
0 16 W
0 4
4 2
0 0
10 WNW 2
4 3
1 0
0 10 NW 3
10 10 1
0 0
24 PNW 1
6 11 2
0 0
20
'IUTAL 34 168 226 108 36 2
574 Page 14 of 17
STABILITY CLASS:
F
~
ELEVATION:
GROUND WIND SPEED (MPH)
WIND DIRirTION 1-3 4-7 8-12 13-18 19-24
>24
'IvrAL N
O 10 7
0 0
0 17 NNE 1
13 8
1 0
0 23 NE O
8 0
0 0
0 8
ENE 1
12 7
0 0
0 20
- E O
10 1
0 0
0 11 ESE 1
13 0
0 1
0 15 SE O
7 0
0 0
0 7
SSE O
13 5
2 0
0 20 S
1 1
3 1
3 0
9 SSW 2
2 1
0 2
0 7
SW 0
3 0
0 0
0 3
WSW 0
3 0
0 0
0 3
W 1
4 0
0 0
0 5
WNW-0 2
1 0
0 0
3 NW 3
5 4
0 0
0 12 M
0 10 7
0 0
0 17
'IUPAL 10 116 44 4
6 0
180 STABILITY CLASS:
G ELEVATION:
GROUND WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24
'IOTAL N
0 5
1 0
0 0
6 NNE O
O 2
0 0
0 2
NE O
8 0
0 0
0 8
ENE 1
2 0
0 0
0 3
E O
O 2
1 0
0 3
ESE O
5 1
0 0
0 6
SE O
8 0
0 0
0 8
SSE O
1 1
0 0
0 2
S 0
0 0
0 0
0 0
SSW 0
0 0
0 0
0 0
SW 0
0 0
0 0
0 0
WSW 0
0 0
0 0
0 0
W 0
0 0
0 0
0 0
WNW 9
0 0
0 0
0 0
NW 0
4 3
0 0
0 7
M 0
3 0
0 0
0 3
'IUTAL 1
36 10 1
0 0
48 Page 15 of 17
--n a
STABILITY CLASS:
ALL ELEVATION:'
-GROUND WIND SPEED (MPH)
WIND DIRECTION
- 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
4 27 24 23 3
0 81 NNE 5
35 45 15 6
0 106 NE 7
48 21 3
0 0
79 ENE 8
50 34 4
1 0
97 E
7 24 38 9
1 0
79 ESE 2
39 28 7
3 0
79 l
SE 2
33 27 10 0
0 72 SSE 2
42 75 32 5
0 156 S
3 18 60 104 44 4
233 SSW 3
13 17 62 17 3
115 SW 2
16 3
2 3
1 27 WSW 2
16 4
1 0
0 23 W
4 16 10 9
2 0
41 WNW 4
13 14 8
2 0
41 NW 8
25 32 19 11 0
95 NNW l
26 34 23 1
0 85
'IUPAL 64-441 466 331 99 8
1409 Page 16 of 17' t
l e
SECTION IV Additional Information 1.
Unplanned: Releases There were no unplanned releases from the site to unrestricted areas of radioactive materials in gaseous or liquid effluents made during the reporting period.
2.
Process Control Program There were no changes to the Process Control Program during this reporting period.
3.
Offsite Dose Calculation Manual There were no changes to the Offsite Dose Calculation Manual made during this reporting period.
4 Major Changes to Liquid, Gaseous, or Solid Radwaste Systems These changes will be discussed in the next annual update of the Final Safety Analysis Report, as allowed by Technical Specification 6.1.5.
5.
Technical Specification Action Statement Information The liquid and gaseous effluent monitoring instrumentation time limits for inoperability, as listed in Technical Specifications 3.3.3.10 and' 3.3.3.11, were not exceeded during this reporting period.
The quantity of radioactive material contained in the liquid holdup tanks or gas storage tanks did not exceed the limits specified in Technical Specifications 3.11.1.4 or 3.11.2.6, respectively, during this reporting period.
6.
Land Use Census There were no new locations for dose calculations identified during this reporting period.
Page 17 of 17
KANSAS GAS AND ELECTRIC COMPANY THE ELECTFuC COMPANY GLENN L ROESTER i
voce p.a sioemt. nwctaan August 30, 1985 Document Control Desk U.S. Nuclear Regulatory Ca minaion Washington, D.C.
20555 Mr. R.D. Martin, Regional Administrator U.S. Nuclear Regulatory Comission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNBC 85-212 Re:
Docket No. SIN 50-482 Subj: Semiannual Radiological Effluent Release Report
Dear Mr. Martin:
Enclosed isthehalfCreek Generating Station Semiannual Radiological Effluent Release Report covering the period from January 1,
1985 through June 30, 1985.
This report is submitted pursuant to section 6.9.1.7 of the Wolf Creek Generating Station thit 1 Technical Specifications.
Yours very truly, G enn L. Koester Vice President, Nuclear GIK:see xc: P0'Connor (2), w/a JTaylor,w/a JCumins, w/a 9* s,
pnt N Marker - WrMn Kanens - Mnol Address PO Bar POR I Wirhorn Kansas 67201 - Telnohann-Aron Ovin ntns pnt.Ms1