ML20096A729
| ML20096A729 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/30/1984 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| References | |
| NUDOCS 8408310229 | |
| Download: ML20096A729 (17) | |
Text
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WISCONSIN ELECTRIC SEMIANNUAL POWER COMPANY January 1,1984 through June 30,1984 POINT BEACH NUCLEAR PLANT UNIT NOS.1 AND 2 6
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U.S. Nuclear Regulatory Commission Docket Nos. 50-266 and 50-301 s 840s310229 840630 Facility Operating License Nos.
PDR ADOCK 05000266 R PDR DPR-24 and DPR-27
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TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Radioactive Liquid Releases 1 2.0 Radioactive Airborne Releases 6 ,
3.0 Radioactive Solid Waste Shipments 9 4.0 New and Spent Fuel Shipments and Receipts 10 5.0 Radiological Environmental Monitoring 11 6.0 Non-Radiological Environmental Monitoring Program 12 7.0 Non-Radioactive Chemical Releases 13 8.0 Circulating Water System Operations 14 -
9.0 Leak Testing of Radioactive Sources 14 e
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l 1.0 RADIOACTIVE LIQUID RELEASES i
-Radioactive liquid releases via the circulating water discharge are
! summarized for. total release and by individual source on a monthly basis in Table 1-1. An isotopic breakdown of the total radioactive liquid release is presented in Table 1-2.
The total radioactive liquid release excluding tritium for this reporting period was 0.3679 Curies which included 0.3479 Curies of processed radioactiv(Yiaste aid primary coolant system letdown, 0.0049 Curies of Unit 1 steam generator blowdown and 0.0151 Curies of Unit 2 steam generator blowdown.There was no detectable activity in retention pond effluent (other than tritium). The total tritium release for this reporting period was 1031.97 Curies, which included 1031.80 Curies of processed radioactive
- waste and priinary coolant system letdown, 0.000 Curies of Unit 1 steam generator-blowdown, 0.163 Curies of Unit 2 steam generator blowdown, and 0.007 CuriesTof reteition pend effluent.' All radioactive liquid releases to Lake Michigan were made through the circulating water discharge.
1.1 Additiens to Semiannual Monitor Report July 1, 1983 through December _.'A1, 1983 Oct Nov Dec Total (Ci),
Total Activity Released, Ci f Gross Alpha SMDA $MDA SMDA 2.81E-07 Average Diluted Discharge Concentration,~pCi/cc Gross Alpha 9tDA $MDA SMDA
%hPC' .
s -- -- --
The followira data which was not ava[lable at time of report preparation shocid be added to Table 1-2 of the Semiannual Monitoring Report July 1, 1983, Through December 31, 1983.
(6 Month
., Adjusted Oct Nov Dec Total (Ci)
Sr-89 1.37E-04 nifDA SMDA 2.36E-04 Sr-90 1.11E-05 1.65E-05 $MDA 9.98E-05 l
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TABLE 1-1 RADIOACTIVE LIQUID CIRCULATING WATER RELEASE SUfeARY PERIOD OF JANUARY 1. 1984 TO JUNE 30, 1984 Jan Feb March April g June Total Total Activity Released, (C1)
Camma Scan 1.90E-02 2.23E-01 3.18E-03 3.58E-02 2.22E-02 6.40E-02 3.67E-01 Cross Alpha 8. 54E- 06 1.94E-03 1.48E-05 (1) (1) (1) (1)
Tritium 6.75E+01 4.33E+02 9.04E+01 1.60E+02 1.75E+02 1.06E+02 1.03E+03 Total Volumes Released (Cat)
Processed Waste 9.98E+04 3.34E+05 7.60E+04 1.44E+05 1.07E+05 8.30E+04 8.44E+05 .
Steam Generator Blowdown, U1 IMDA 1.01E+03 SMDA 1.97E+06 2.67E+06 2.54E+06 7.18E+ 06 Steam Ge.vrator ,
Blowdown, U2 2.99E+06 2.41E+06 2.61E+06 2.56E+06 3.06E+06 3.05E+06 1.67E+07 Retention Pond 2.41E+05 3.08E+06 2.49E+06 2.85E+06 2.50E+06 2.20E+06 1.34E+C7 8.34E+06 7.87E+06 3.81E+07 y Total 3.33E+06 5.82E+06 5.18E+06 7.53E+06 Volume of Dilution Water. (cc) 3.46E+13 3.26E+13 3.39E+13 5.48E+13 5.16E+13 5.68E+13 2.64E+14 Average Diluted Discharge Concen-tar. tion (pCi/cc)-
Cross Camma 5.49E-10 6.85E-09 9.36E-11 6.53E-10 4.30E-10 1.13E-09
% MPC 6.82E-03 4.82E-01 6.55E-04 1.19E-02 3.77E-03 2.99E-02 Gross Alpha 2.47E-13 5.95E-11 4.37E-13 (1) (1) (1)
% MPC 8.24E-04 1.99E-01 1.46E-03 (1) (1) (1)
Tritium 1.95E-06 1.33E-05 2.67E-06 2.92E-06 3.39E-06 1.87E-06
% MPC 6.51E-02 4.44E-01 8.89E-02 9.71E-02 1.13E-01 6.21E-02 Maximun Discharge Concentration During Release Period, (pci/cc)
Cross Camma 1.10E-08 8.58E-08 6.87E-09 1.57E-08 6.47E-09 1.46E-08 Tritium 3.49E-05 9.47E-05 1.35E-04 1.26E-04 2.09E-04 6.83E-05 (1) Data unavailable at time of report.
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TABLE 1-2 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGES
- PERIOD OF JANUARY 1, 1984 TO JUNE 30, 1984 W
Nuclides Jan Feb March April May June Total D Released (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies)
Tritium 6.75E+01 4.33E+02 9.04E+01 1.60E+02 1.75E+02 1.06E+02 1.03E+03 E
- I-131 ShDA 20A SMDA 1.33E-04 1.15E-04 SMDA 2.48E-04 I-133- SMDA $NDA SMDA SMDA 3.00E-05 SMDA 3.00E-05
" Xe-133 SMDA SMDA SMDA 1.33E-02 8.73E-05 4.91E-04 1.39E-02 1.88E-06 SMDA 1.88E-06
[ Kr-85M Xe-135 SMDA 1MDA
$MDA SMDA SMDA SMDA SMDA 5.84E-04 2DA SMDA 5.84E-04 S SMDA 2.90E-04 Xe-135M 1MDA SMDA SMDA 2.90E-04 1MDA Kr-85 5MDA SOA 20A $MDA SMDA 4.82E-02 4.82E-02 -
K Co-57 SMDA SMDA SOA $MDA 4.97E-06 SMDA 4.97E-06 Ce-144 3.98E-05 6.54E-02 SMDA 2.79E-04 $MDA 2.61E-04 6.60E-02 Ce-141 SOA 7.77E-03 SOA SMDA SMDA SMDA 7.77E-03 -
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SMDA 1.43E-04 1.21E-02 w Cr-51 90A 1.20E-02 SMDA SMDA
' SOA SMDA SMDA '1.12E-02 E Sn-113 $MDA 1.12E-02 SMDA SOA SDA 3.58E-04 SMDA 4.78E-04 2.15E-03 e* Sb-125 1.3F #
F-18 3. 74& " $MDA SMDA SMDA SMDA SMDA 3.74E-05 Ru-103 SOA 8.64E-03 20A SMDA SMDA SMDA 8.64E-03 Y-91M 90/ 20A 20A SOA 9.40E-05 SMDA 9.40E-05 Cs-134 4.91E . 35E-03 1.13E-03 5.67E-03 7.16E-03 1.98E-03 2.52E-02 Ru-106 2CA 7,01E-02 SMDA 20A SMDA $NDA 3.01E-02 Ag-110M 4.72E-05 ? 31E-04 7.70E-06 2.07E-04 $MDA 1.81E-05 5.51E-04 Cs-137 8.31E-03 8.72E-03 1.60E-03 1.15E-02 1.35E-02 4.23E-03 4.86E-02 Zr-95 SMDA 5.92E-03 SMDA SMDA SMDA 7.15E-05 5.99E-03 Zr-97 SMDA 1.05E-03 SOA SMDA SMDA SMDA 1.05E-03 ,
Nb-95 GOA 1.05E-02 4.29E-06 1.36E-04 3.61E-05 1.68E-04 1.08E-02 a
_ Co-58 1.54E-03 1.80E-02 5.13E-05 6.37E-04 1.91E 3.47E-04 2.08E 02 Mn-54 5.57E-05 9.62E-04 5.45E-06 1.24E-04 1.56E-05 1.57E-04 1.32E-03
{
,- Co-60 2.24E-03 3.81E-02 1.68E-04 2.56E-03 9.77E-04 3.33E-03 4.74E-02 Na-24 DOA SOA SMDA SMDA SMDA 4.12E-03 4.12E-03 p
Nb-97 SOA 2.58E-04 8.12E-06 1.72E-05 SMDA 7.03E-06 2.90E-04 Sr-89 2.00E-05 1.32E-05 5.30E-06 (1) (1) (1) (1)
Sr-90 2.52E-05 1.9 E-05 2.91E-06 (1) (1) (1) (1) i TOTAL 1.90E-02 2.23E-01 3.18E-03 3.58E-02 2.22E-02 6.40E-02 3.67F-01 NOTE: (1) Data Unavailable at time of report.
1.3 Additions to the Semi-Annual Report, July 1 through December 31,
'1983.
The following data which was not available at the time of the report a preparation should be added to Table 1-3 in Section 1.0 of the Semi-Annual Monitoring Report covering the period July 1, 1983, through December 31,.1983.
TABLE 1-3 SUBSOIL SYSTEM DRAINS TRITIUM
SUMMARY
JULY 1, 1983 THROUGH DECEMBER 31, 1983 LOCATION S-1 5-3 S-9 S-10 TOTALS Third Quarter Hs (pCi/cc) 6.95E-07 1.17E-06 No Sample SMDA -
Aver. Flow, w d 7816 5458 No Flow 21037 -
Fourth Quarter Hs (pci/cc) 1.12E-06 1.73E-06 No Sample 2.70E-07 -
Aver. Floui y d 94648 56600 No Flow 417 -
Semiannual Totals Total Released, Ci. 3.24E-02 3.13E-02 No Sample 1.01E-03 6.47E-02 Total flow, gal 9.43E+06 5.71E+06 No Flow 1.97E+06 1.71E+07 TABLE 1-3 SUBSOIL SYSTEM DRAINS TRITIUM
SUMMARY
JANUARY THROUGH JUNE 1984 LOCATION S-1 S-3 S-9 S-10 TOTALS First Quarter
. H3 (pCi/cc) 1.61E-06 5.70E-07 $MDA 2.08E-06 -
l Aver. Flow, gpd 23895 5365 1470 6350 -
Second Quarter Hs (pCi/cc) (1) (1) (1) (1) -
Aver. Flow, gpd 4668 4150 1424 16727 -
Semiannual Totals Total Released, Ci (1) (1) (1) (1)
Total flow, gal 5.20E+06 1.73E+06 2.61E+05 4.20E-06 (1) Data unavailable at time of report.
2.0 RADIOACTIVE AIRBORNE RELEASES Radioactive airborne releases during normal plant operation are reported by total release in Table 2-1, and summarized by isotope in Table 2-2. The release paths contributing to radioactive airborne releases during this reporting period were the auxiliary building vent stack, Unit 1 containment purge stack, Unit 2 containment purge stack, drumming area vent stack, gas stripper building ventilation exhaust, combined air ejector decay exhaust and turbine building ventilation exhaust.
There were four decay tank releases during this report period.
2.1 Additions to the Semiannual Report, July 1, 1983, through December 31, 1983 The following data which was not available at the time of the report preparation should be added to Table 2-2 in Section 2.0 of the Semiannual Monitoring Report covering the period July 1, 1983, through December 31, 1983.
(6 Month Adjusted October November December Total, Ci Sr-89 $MDA 5%A SMDA SMDA Sr-90 SMDA SMDA SMDA SMDA l
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TABLE 2-1 RADIOACTIVE AIRBORNE RELEASE
SUMMARY
PERIOD OF JANUARY 1, 1984 TO JUNE 30, 1984 January February March April y M June Total Total Curies Released (Excluding Tritium) 3.94E+00 2.83E+00 6.51E+00 7.59E+00 1.52E+00 8.35E+00 3.07E401 Total Xe-133 Equivalent Curies Released (1) 4.13E+01 3.71E+01 5.38E+01 1.24E+02 1.54E+02 7.17E+01 4.82E+02 Average Release Rate (Curies /Second) (2) 1.54E-05 1.48E-05 2.01E-05 4.80E-05 5.75E-05 2.77E-05
=
Percent of Annual Technical Specifica-y tion Limits (3) 7.71E-03 7.41E-03 1.00E-02 2.40E-02 2.87E-02 1.38E-02 Maximum Hourly Average Release Rate (Curies /Second) (4) 3.54E-05 4.79E-04 5.08E-03 1.36E-03 2.30E-03 1.19E-04 Monthly Average Site Boundary Concentra-tion (pci/cc) (2) 2.31E-11 2.22E-11 3.01E-11 7.19E-11 8.62E-11 4.15E-11 (1) All gaseous particulate releases are converted to "Xe-133 equivalent" for calculational purposes using the ratio MPC(Xe-133)/MPC(i). MPC's for isotopes of iodine and particulate with half-lives longer than eight i I
days are reduced by a factor of 700.
(2) Averaged over one month and based on Xe-133 equivalent.
(3) Annual average Technical Specification limits are 0.2 Ci/sec, Xe-133 based on X/Q:1.5E-06 sec./m 3. Maximum Technical Specification limits are 2.0 Ci/sec. Xe-133 based on X/Q:1.5E-06 sec/m3 (4) Expressed as Xe-133 equivalent.
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TABLE 2-2 RADI0 ACTIVE AIRBORNE RELEASE
SUMMARY
PERIOD OF JANUARY 1, 1984 TO JUNE 30, 1984 -
Nuclides January February March April May June Total Released (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies)
Tritium 2.70E+01 2.79E+01 . 26E+02 1.75E+01 1.52E+01 7.63E+00 2.21E+02 Noble Gases Xe-133 1.33E+00 3.83E-01 4.66E-01 1.03E+00 4.76E-01 9.62E-01 4.65E+00 Kr-85M 1.44E-01 1.15E-01 1.98E-01 2.02E-01 3.19E-02 1.73E-01 8.64E-C1 !
Kr-88 2.70E-01 2.52E-01 3.99E-01 4.45E-01 6.26E-02 3.79E-61 1.81E+00 l Xe-133M 5.22E-02 3.41E-02 3.61E-02 6.82E-02 3.70E-02 5.65E-02 2.84E-01 Xe-135 8.71E-01 6.60E-01 1.05E+00 1.04E+03 1.92E-01 8.49E-01 4.66E+00 Xe-138 3.95E-01 5.86E-01 '
dE+00 1.50E+00 1.39E-01 1.34E+00 5.14E+00 Kr-87 1.49E-01 1.83E-01 2.84E-01 3.53E-01 4.78E-02 3.15E-01 1.33E+00 Xe-135M 2.32E-01 2.28E-01 3.69E-01 4.59E-01 4.65E-02 4.29E-01 1.76E+00
$' Ar-41 4.86E-02 4.19E-02 1.77E-01 2.82E-03 2.62E-02 8.63E-02 6.62E-01 Kr-85 4.54E-01 3.51E-01 2.36E+00 2.21E+00 4.63E-01 3.76E+00 9.60E+00 Particulates with half-lives less than eight days Rb-88 1.01E-06 $MDA $MDA SfDA SMDA SMDA 1.01E-06 Particulates with half-lives greater than eight days and iodines ,
I-131 7.76E-06 3.01E-06 2.93E-06 1.07E-05 4.26E-05 1.06E-05 7.76E-05 I-132 $MDA SMDA 2.55E-07 4.93E-05 3.86E-06 5MDA 5.34E-Of I-133 2.32E-06 6.44E-07 4.32E-06 1.70E-05 1.11E-04 1.19E-05 1.47E-04 Sr-89 SMDA SMDA SMDA (1) (1) (1) (1)
Sr-90 $MDA SMDA SMDA (1) (1) (1) (1)
Cd-109 SMDA SMDA SMDA 1.13E-09 1.27E-06 5.83E-05 5.96E-05 Sb-125 $MDA 4.14E-07 SMDA 6.95E-10 SMDA SMDA 4.14E-07 Ru-103 5.96E-08 SMDA SMDA SMDA 3.11E-08 SMDA 9.07E-08 Cs-134 5.09E-07 6.03E-08 2.06E-07 7.70E-08 3.91E-08 SMDA 8.91E-07 Cs-137 6.79E-06 1.09E-05 1.05E-05 1.09E-06 2.72E-07 2.61E-07 2.98E-05 Co-58 1.77E-06 2.23E-06 2.35E-06 7.64E-10 SMDA SMDA 6.35E-06 Mn-54 8.17E-08 2.54E-08 8.39E-08 SMDA SMDA SMDA 1.91E-07 Co-60 3.82E-06 9.80E-06 9.92E-06 1.05E-06 6.89E-07 5.13E-07 2.58E-05 Alpha 7.02E-11 4.04E-08 SMDA 3.17E-06 GIDA SIDA 3.21E-06 NOTE: (1) Data Unavailable at report time.
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k 3.0 ~ RADIOACTIVE SOLID WASTE SHIPMENTS L
Shipments offsite of solid waste for burial during this reporting period were as follows.
Date Volume (Fts) Total Activity (Ci) 01-09 195.0 20.000 D 01-11-84 84.0 98.300 (1) 01-13-84 1749.0 0.247 01-17-84 183.0 42.300 01-18-84 1265.0 0.139
( '01-21-84 183.0 162.600 01-26-84_ 1718.7 0.258 01-27-84 183.0 165.2 02-01-84 85.0 102.800 (1) 02-02-84 1797.0 0.271
, 02-10-84 1792.0 0.385 02-22-84 1212.0 0.433 03-02-84 2280.0 0.086
, 03-12-84 1698.0 0.643 03-14-84 1896.0 0.071 03-30-84 1530.5 0.129 05-17-84 1324.8 0.179 05-25-84 183.0 5.127 06-07-84 126.0 482.800 (1) 06-11-84 183.0 6.030 06-11-84 ~183.0 5.690 06-13-84 183.0 0.548 06-14-84 183.0 0.548 06-15-84 183.0 0.396
! 06-25-84 366.0 3.740 06-28-84 135.0 1.561 TOTALS: 20901.0 (ft3 ) 1100.481 (Ci)
(1) Involved spent resin.
4.0 NEW & SPENT FUEL SHIPMENTS AND RECEIPTS r During this reporting period, a total of 36 new fuel assemblies were received from Westinghouse Electric Corporation for Unit 1. The new fuel assemblies received for Unit I were used for the Spring, 1984, refueling.
There were 102 spent fuel assemblies received from the West Valley, New York and Morris, Illinois storage facilities during this reporting period.
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5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological environmental monitoring conducted by Point Beach Nuclear Plant from January 1, 1984, through June 30, 1984, consisted of air filters, gamma dose, vegetation, lake water, well water, milk, shoreline silt, soil, algae, and fish samples collected and analyzed in accordance with Technical Specification 15.4.10.
All measurements obtained during this period are within the normal range, and no unusual results or significant departures from normal were noted.
No. Sample Type Low Averaae* H_igt! Units TLDs 41 Quarterly 0.70 1.06 1 0.36 1.45 mR/wk Air Filters 3
149 Gross Beta 0.01 0.02 1 0.02 0.04 pCi/m 149 Radioiodine ---
all <0.03 ---
pCi/m 3
12 Gamma Scan ---
all <0.01 ---
pCi/m Milk 18 Radioiodine ---
all <0.5 ---
pCi/1 18 Sr-89 ---
all <5.0 ---
pCi/1 18 Sr-90 0.9 1.5 i 0.9 2.5 pCi/1 18 Gamma Scan ---
all <5 ---
pCi/1 Lake Water 30 Gross Beta 2.1 3.8 i 2.8 7.6 pCi/1 30 Gamma Scan ---
all <10 ---
pCi/1 10 Tritium <0.5 <0.6 i 0.4 1.02 pCi/ml 1 pCi/1 10 Sr-89 ---
all < ---
1 pCi/1 10 Sr-90 <1 <1.1 1 0.1 1.1 Well Water 2 Gross Beta <0.8 <2.9 5.0 pCi/1 2 Gamma Scan ---
both <10 ---
pCi/1 2 Tritium ---
both <0.5 ---
pCi/ml 2 Sr-89 ---
Both <5 ---
pCi/1 2 Sr-90 ---
both <1 ---
pCi/l Vegetation 8 Gross Beta 7.4 10.1 1 6.9 16.7 pC1/g (dry) 8 Gamma Scan ---
all <1 ---
pCi/g (dry)
No. Sample Type Low Averace* High Units Soll 8 Gross Beta 16.9 24.3 1 10.9 29.9 pCi/g (dry) 8 Gamma Scan:
Cs-137 ---
all <1 ---
pCi/g (dry)
Others ---
all <1 ---
pCi/g (dry)
Algae 2 Gross Beta 7.9 8.3 1 6.3 8.6 pCi/g (dry) 2 Gamma Scan ---
both <5 ---
pCi/g (dry)
Fish 6 Gross Beta 9.9 16.7 1 12.6 24.0 pCi/g (dry) 6 Gamma Scan ---
all <1 ---
pCi/g (dry)
Shoreline Sediment 5 Gross Beta 5.4 12.1 1 18.7 23.9 pCi/g (dry) 5 Gamma Scan --
all <1 ---
pCi/g (dry)
- 95% confidence internal given when applicable. Whenever samples below the detection limit are included in the computation of the average, the average is shown as a "less than" value.
1 0nly 5 analyses completed at this time.
6.0 NON-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM In accordance with Amendment Nos. 29 and 33 to Facility Operating Licenses DPR-24 and DPR-27, respectively, dated November 4, 1977, the Environmental Technical Specifications for the Point Beach Nuclear Plant, Units 1 and 2, were modified to allow temporary suspension of the non-radiological environmental monitoring program pending NRC review of the summary report of the five years of monitoring. As a result, the semiannual report specified by Item 16.6.2.a of the Technical Specification is not applicable.
7.0 NON-RADIOACTIVE CHEMICAL RELEASES 7.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system for the period of January 1, 1984, to June 30, 1984, included 5,156,100 gallons of neutralized clear water waste. The waste water contained 503 pounds of suspended solids and 302,586 pounds of dissolved solids.*
The concentration increases of chemical waste in the circulating water system during the period of chemical releases ranged from 0.018 to 19.41 ppa dissolved solids and from 0.000 to 0.038 ppm suspended solids.**
Plant chemical records indicated that the following amounts of chemicals were relcased in the form of neutralized waste:
Sodium 79,252 pounds Sulfate 202,546 pounds
- Chemical releases calculated are based upon each neutralized tank analysis prior to discharge.
- Based on calculations during times of actual discharges for-each individual neutralizing tank.
7.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases to the circulating water:
system from the retention pond for the period of January 1, 1984 to June 30, 1984, including 13,370,000 gallons of clear water waste. The waste water contained 828 pounds of suspended solids and 47,055 pounds of dissolved solids.*
Retention pond analysis and plant chemical records indicate that the following chemicals were released in the form of clear water waste from the retention pond.
Sodium 9,323 pounds Chloride 14,388 pounds Phosphate 306 pounds The balance of the dissolved solids were in the form of soluble calcium and magnesium compounds resulting from the plant makeup water cold lime softening process.
- Chemical release calculations are based on retention pond analyses during the period January 1, 1984 to June 30, 1984.
8.0 CIRCULATING WATER SYSTEM OPERATIONS The circulating water system operation during this reporting period for periods of plant operation is described in Table 8-1.
9.0 LEAK TESTING OF RADIOACTIVE SOURCES During the reporting period, all applicable sealed radioactive sources were leak tested according to Technical Specification requirement 15.4.12.
Leak test results were all <0.005 pCi.
TABLE 8-1 CIRCULATING WATER SYSTEM OPERATION January February March _Anril May June Average Volume Cooling UNIT 1 (1) (1) (1) 472.6(1) 509.8 347.1 Water Discharge, Million Gal / Day UNIT 2 294.7 269.9 288.2 482.2 450.9 331.9 Average Cooling Water UNIT 1 (1) (1) (1) 38.5(1) 42.1 49.6 Intake Temperature , .
Degrees F UNIT 2 37.7 36.1 35.4 37.5 42.0 49.7 0 Average Cooling Water UNIT 1 (1) . (1) (1) 55.3(1) 60.7 66.7 Y Discharge Temperature Degrees F UNIT 2 69.4 69.0 69.5 57.1 60.9 67.3 Average Ambient Lake UNIT 1 (2) (2) '2) (2) (2) (2)
Temeprature Degrees F UNIT 2 37.1 36.7 35.4 38.3 42.1 49.6 (1) Unit I shutdown for refueling and steam generator replacement from 10-01-83 to 04-08-84.
(2) Instrumentation out of service.
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ntsconsin Electnc macoumr 231 W. MICPlGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 August 24, 1984 Mr. H. 3. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555
Dear Mr. Denton:
DOCKET NOS. 50-266 AND 50-301 SEMIANNUAL MONITORING RE! ORT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Enclosed herewith is the Semiannual Monitoring Report for the Point Beach Nu; lear Plant, Units 1 and 2, for the period from January 1, 1984 to June 30, 1984. This report is submitted in accordance with Technical Specification 15.6.9.3.C and contains information regarding plant releases, new and spent fuel receipts, environmental radiological monitoring, and leak testing of sourcea during this reporting period. We have enclosed forty copies of this report for your use.
Very truly yours,
,h ct.d j Vice Pres dent-Nuclear Power C. W. Fay Enclosure Copy to NRC Resident Inspector
$,25 s6