ML20137Z755
| ML20137Z755 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/31/1985 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| CON-NRC-86-20 VPNPD-86-101, NUDOCS 8603130109 | |
| Download: ML20137Z755 (23) | |
Text
... .
l WISCONSIN ELECTRIC SEMIANNUAL POWER COMPANY JULY 1,1985 through DECEMBER 31,1985 POINT BE ACH NUCLE AR PL ANT UNIT NOS.1 AND 2 U.S. Nuclear Regulatory Commission 8603130109 051231 Docket Nos. 50-266 and 50-301 PDR ADOCK 05000266 Facility Operating License Nos.
l TABLE OF CONTENTS SECTION TITLE PAGE
- 1. 0 Radioactive Liquid Releases 1 2.0 Radioactive Airborne Releases 7 3.0 Radioactive Solid Waste Shipments 10 4.0 New and Spent Fuel Shipments 10 5.0 Radiological Environmental Monitoring 11 6.0 Non-Radioactive Chemical Releases 14 7.0 Circulating Water System Operations 15 8.0 Leak Testing of Radioactive Sources 15 9.0 Miscellaneous Reporting Requirements 17 10.0 Erratum for Previous Reports 18
1.0 RADI0 ACTIVE LIQUID RELEASES I
l Monthly radioactive liquid releases via the circulating water discharge are summarized by individual source, total activity, and equivalent Curie activity in Table 1-1. The isotopic composition of the total radioactivity released in liquid effluents is presented in Table 1-2. Table 1-3 summarizes subsoil tritium discharges.
The total radioactive liquid release excluding tritium for this reporting period was 0.6321 Curies. This included 0.0139 Curies of processed. radioactive waste and primary coolant system letdown, 0.0157 Curies of Unit 1 steam generator blowdown, 0.6025 Curies of Unit 2 steam generator blowdown. There was no detectable activity in the retention pond effluent other than tritium. The total tritium release for this reporting period was.406.774 Curies. This included 405.367 Curies of processed radioactive waste and primary coolant system letdown, 0.860 Curies of Unit l' steam generator blowdown, 0.495 Curies of Unit 2 steam generator blowdown, and 0.052 Curies in retention pond effluent. All radioactive liquid releases to Lake Michigan were made throcgh the circulating water discharge system.
1.1 Additions to Semiannual Monitoring Report January 1, 1985 through June 30, 1985.
The following data were not available at time of the last report preparation and should be added to Table 1-1 of the Semiannual Monitoring Report for January 1,1985 to June 30, 1985.
JAN FEB MAR APR MAY JUN
~~
10TAL Total Activity Released (Ci)
Gross Alpha <MDA 7.87E-06 3.62E-05 7.41E-06 <MDA 3.86E-05 9.01E-05 Average Oiluted Discharge Concentration (uci/cc)
Gross Alpha <MDA 2.49E-13 9.66E-13 1.18E-13 <MDA 5.93E-13
% MPC ---
8.30E-04 3.22E-03 3.93E-04 ---
1.98E-03 The following data were not available at time of the last report preparation and should be added to Table 1-2 of the Semiannual Monitoring Report for January 1, 1985 to June 30, 1985.
JAN FEB MAR APR MAY JUN TOTAL
- Sr-89 <MDA <MDA (MDA 2.19E-04 <MDA <MDA 2.19E-04 Sr-90 4.12E-07 1.27E-05 <MDA 3.73E-04 7.60E-04 8.18E-04 1.28E-03 Alpha <MDA 7.87E-06 3.62E-05 7.41E-06 sHOA 3.86E-05 9.01E-05
- Six month adjusted total Curies
The following data was not available at the time of the last report preparation, and should be added to the data of Table 1-3 of the January 1, 1985 to June 30, 1985 report.
TABLE 1-3 SUBS 0IL SYSTEM DRAINS - TRITIUM
SUMMARY
January 1, 1985 through June 30, 1985 LOCATION S-1 S-3 S-9 S-10 TOTALS First Quarter H-3 (uCi/cc) 4.60E-07 4.70E-07 <MDA <MDA -
Ave. Flow (gpd) 22752 2768 5376 13038 -
Second Quarter H-3 (tCi/cc) 8.80E-07 9.30E-07 No Sample 4.50E-07 -
Ave. Flow (gpd) 4115 2676 No Flow 8642 -
Semi-annual totals Total Released (Ci) 4.82E-03 1.30E-03 <MDA 1.34E-03 7.47E-03 Total Flow (gallons) 2.42E+06 4.93E+05 4.84E+05 1.96E+06 5.36E+06
TABLE 1-1
' RADIOACTIVE LIQUID CIRCULATING WATER RELEASE SUP98ARY-JULY 1, 1985 TO DECEMBER 31, 1985.
JUL AUG SEP OCT NOV DEC TOTAL Total Activity Released (Ci)
Gamma Scan 3.68E-02 5. 64 E 4.79E-01 6.38E-03 7.20E-03 4.61E-02 6.32E-01 Gross Alpha <MDA <MA (2) (2) (2) (2) (2) l Gross Beta (3) 8.45E-06 6.33E-07 (2) (2) (2) (2) (2) J Tritium 1.25E+02 8.70E+01 7.18E+01 5.78E+01 2.78E+01 3.63E+01 4.06E+02 Total Volumes Released (Gal)
Processed Waste 1.26E+05 1.20E+05 1.04E+05 4.30E+05 2.10E+05 6.88E+04 1.06E+06 Steam Generator .
Blowdown (U1) 2.68E+06 2.66E+06 2.54E+06 1.96E+06 2.63E+06 1.71E+06 1.42E+07 ,
Blowdown (U2) 2.54E+06 2.66E+06 3.29E+06 6.33E+05(1) 1.38E+06(1) 3.02E+06 1.35E+07 l e Retention Pond 2.15E+06 2.17E+06 2.36E+06 2.62E+06 3.22E+06 3.66E+06 1.62E+07 !
Condensor Hotwell !
(U2) 0 0 0 0 6.77E+05 0 6.77E+05 i Total Gallons 7.50E+05 7.61E+06 8.29E+06 5.64E+06 8.12E+06 8.46E+06 4.56E+07 l Volume of Dilution Water, (cc's) 6.74E+13 5.62E+13 6.64E+13 5.66E+13 5.49E+13 3.30E+13 3.35E+14 Average Oiluted Discharge Concentration (uCi/cc) l Gross Camma 5.45E-10 1.01E-09 7.21E-09 1.13E-10 1.31E-10 1.40E-09 !
Gross Alpha <MDA (MDA (2) (2) (2) (2) l Gross Beta (3) 1.25E-13 1.13E-14 (2) (2) (2) (2) l Tritium 1.85E-06 1.55E-06 1.08E-06 1.02E-06 5.05E-07 1.10E-06 i Maximus Discharge Concentration During Release Period (uCi/cc)
Gross Gamma 6.98E-09 1.62E-10 1.58E-10 1.09E-09 1.53E-09 1.99E-08 Tritium 5.24E-05 4.37E-05 6.82E-05 3.04E-05 1.87E-05 9.93E-05 l l
(1) Unit 2 refueling shutdown 10-06-85 to 11-25-85 (2) Data unavailable at time of report writing (3) Sr-89 and Sr-90 values only
TABLE 1-1 (Continued)
RADI0 ACTIVE LIQUID CIRCULATING WATER RELEASE SUMARY JULY 1, 1985 TO DECEMBER 31, 1985 JUL AUG SEP OCT NOV DEC TOTAL Total Equivalent Curies Released Co-60 Equivalent Curies 2.59E-02 8.87E-03 1.50E-01 2.05E-02 6.76E-02 3.20E-02 3.05E-01
% Annual RETS limit 2.74E-02 9.37E-03 1.58E-01 2.17E-02 7.14E-02 3.38EF02 3.22E-01 I-131 Equivalent curies 6.13E-03 9.89E-03 1.23E-02 7.91E-04 3.94E-04 1.33E-02 4.28E % Annual RETS limit 2.34E-02 3.78E-02 4.70E-01 3.02E-03 1.50E-03 5.08E-02 1.64E-01 Tritium Equivalent Curies 1.25E+02 8.70E+01 7.18E+01 5.78E+01 2.78E+01 3.63E+01 4.06E+02
% Annual RETS limit 6.38E-01 4.44E-01 3.66E-01 2.95E-01 1.42E-01 1.85E-01 2.07E+00 Note: Dissolved Noble Gasses detected in Radioactive Liquid Effluent discharges are included in Radioactive Airborne Release totals.
_- - _ . . _ _ - --. . . . - - . ~ _ - ._ - .- - .._ - _ , .__ . .-
i TABLE 1-2 I
ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGES JULY 1, 1985 TO DECEPEER 31, 1985
! NUCLIDES JUL AUG SEP DCT NOV DEC TOTAL 1 RELEASED (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies)
Tritium 1.25E+02 8.70E+01 7.18E+01 5.78E+01 2.78E+01 3.63E+01 4'.06E+02 i
1-131 1.67E-03 2.61E-03 3.29E-03 1.66E-04 < MDA 8.21E-03 1.60E-02 I-132 5.87E-03 9.46E-03 1.23E-02 1.11E-03 7.29E-04 7.72E-03 3.72E-02 I-133 1.27E-02 1.80E-02 2.25E-02 2.00E-03 1.60E-03 1.52E-02 7.20E-02 I-134 3.35E-03 4.89E-03 7.86E-03 5.28E-04 <MDA 3.20E-03 1.98E-02 I-135 9.82E-03 2.08E-02 2.48E-02 8.40E-04 <MDA 9.84E-03 6.61E-02
! Cs-137 1.30E-03 5.84E-04 2.47E-04 9.45E-04 3.29E-03 1.38E-03 7.75E-03 Co-60 7.02E-04 4.31E-05 9.59E-05 4.15E-04 7.64E-05 1.14E-04 1.45E-03' i
j Mn-54 1.27E-04 (MOA <MDA <MOA 2.32E-06 <MDA 1.29E-04 Co-58 5.52E-04 2.15E-05 1.04E-04 1.26E-04 3.95E-05 6.71E-05 9.10E-04 J ,
l y' Nb-95 9.15E-05 <MDA 3.00E-06 <MDA <MDA 6.49E-07 9.52E-05 '
j Sb-124 7.40E-05 <MDA <MDA <MDA <MDA <M0A 7.40E-05
] Cr-51 1.80E-04 <MDA <MDA <MDA 1.35E-05 <MDA 1.94E-04 Cs-134 2.05E-04 <MDA 4.56E-06 2.27E-04 6.93E-04 4.32E-04 1.56E-03
] 6.81E-05 <MDA (MDA <MDA <MDA 6.81E-05 i Sb-125 <MDA '
Zr-95 4.50E-05 <MDA <MDA <MDA <MDA <MDA 4.50E-05 i
Ag-110m 1.12E-05 <M3A <MDA <MDA <MDA <MDA 1.12E-05 j Ru-103 8.88E-06 (M)A <MDA <MDA <MDA <MDA 8.88E-06 i Te-132 <MDA 5.83E-07 <MDA <MDA <MDA <MDA 5.83E-07 1 Cs-138 <MDA <MDA 1.11E-03 <MDA <MDA <MDA 1.11E-03 Na-24 <MDA <MDA 4.06E-01 <MDA <MDA <MDA 4.06E-01 1 Tc-99m <MDA <MDA (MDA 1.75E-05 <MDA <MDA 1.75E-05 Ru-106 <MDA <MDA <MDA <MDA 7.56E-04 <MDA 7.56E-04
) <MDA <MDA <MDA 1.49E-06 <MDA 1.49E-06 i Co-57 <MDA 1 Sr-89 (MDA <MDA (1) (1) (1) (1) (1)
J Sr-90 8.45E-06 6.33E-07 (1) (1) (1) (1) (1)
TOTAL (2) 3.68E-02 5.64E-02 4.79E-01 6.38E-03 7.20E-03 4.61E-02 6.32E-01 (1) Data unavailable at time of report writing.
(2) Excluding tritium l
i
- Note
- Dissolved noble gases detected in radioactive liquid effluents are included in radioactive airborne release totals.
L
TABLE 1-3 SUBS 0ll SYSTEM DRAINS - TRITIUM
SUMMARY
July 1, 1985 to December 31, 1985 LOCATION ,
Third Quarter S-1 S-3 S-9 S-10 TOTALS H-3 (uCi/cc) (1) (1) (1) ~(1) -
Ave. Flow (gpd) 15990 2490 No Flow 10720 -
Fourth Quarter H-3 (uCi/cc) (1) (1) . (1) (1) -
Ave. Flow (gpd) 16540 580 'No Flow 16870 -
Semi-annual totals Total Released (Ci) (1) (1) (1) (1) (1)
Total Flow (gallons) 2.99E+06 2.82E+05 No Flow 2.54E+06 5.81E+06 (1) Data unavailable at time of report writing.
2.0 RADI0 ACTIVE AIRBORNE RELEASES Radioactive airborne releases are summarized by total Curies and equivalent Curies in Table 2-1. The isotopic composition of airborne releases is presented in Table 2-2.
The release paths contributing to radioactive airborne release totals during this reporting period were the auxiliary building vent stack, drumming area vent stack, gas stripper building vent stack, Unit 1 containment purge stack, Unit 2 contain-ment purge stack, combined air ejector decay duct exhaust, and turbine building ventilation exhaust.
There were three gas decay tank releases during this reporting period.
2.1 Additions to the Semiannual Report January 1, 1985 through June 30, 1985.
The following data was not available at time of the last report preparation and should be cdded to Table 2-2 in Section 2.0 of the Semiannual Monitoring Report covering the period January 1,1965 through June 30, 1985.
JAN FEB MAR APR MAY JUN TOTAL'(Ci)
Sr-89 <MCA <MDA <MDA <MDA <MDA <MDA <MDA Sr-90 <MDA <MDA <MDA <MDA <MDA <MDA <MDA TABLE 2-1 RADI0 ACTIVE AIRBORNE RELEASE SUPMARY PERIOD OF JiuLY 1,1985 TO DECEPEER 31, 1985 JUL A'JG SEP OCT NOV DEC TOTAL Total Noble Gases (Ci):(1) 3.75E+00 4.59E+00 3.28E+00 3.20E+01 2.45E-01 1.08E+01 5.47E+01 Total Radioiodines (Ci): 4.17E-05 1.05E-04 4.18E-04 3.67E-03 2.68E-05 2.50E-03 6.81E-03 Total Particulates (Ci): 5.77E-06 2.24E-06 1.44E-04 1.24E-05 4.94E-03 3.66E-04 .5.47E-03 Strontium (Ci): (2) (2) (2) (2) (2) (2) (2)-
Alpha (Ci): 8.54E-07 <MDA <MDA 3.55E-08 8.60E-07 1.27E-05 1.45E-05 All Others (Ci): 4.92E-06 2.24E-06 1.44E-04 1.24E-05 4.94E-03 3.53E-04 5.46E-03 Total Tritium (Ci): 1.53E+00 2.21E+00 1.38E+00 4.16E+00 1.80E+01 1.04E+00 2.83E+01 Total Equivalent.
Curies Released Xe-133 Equivalent Ci (1) 7.00E+01 9.49E+01 7.44E+01 5.65E+01 3.11E+00 2.06E+02 5.05E+02
% Annual RETS limit 6.73E-03 9.13E-03 7.15E-03 5.43E-03 2.99E-04 1.98E-02 4.85E-02 I-131 Equivalent Ci 1.94E-05 3.83E-05 1.62E-04 2.38E-04 2.23E-05 1.06E-03 1.55E-03
% Annual RETS limit 5.51E-03 1.09E-02 4.60E-02 6.76E-02 6.34E-03 3.01E-01 4.40E-01 Co-60 Equivalent Ci 2.60E-05 1.07E-05 9.32E-05 7.48E-05 5.60E-02 3.81E-03 6.00E-02
% Annual RETS limit 1.51E-03 6.22E-04 5.42E-03 4.35E-03 3.26E+00 2.19E-01 3.49E+00 Tritium Equivalent Ci 1.53E+00 2.21E+00 1.38E+00 4.16E+00 1.80E+01 1.04E+00 2.83E+01
% Annual RETS limit 5.28E-03 7.62E-03 4.76E-03 1.44E-02 6.24E-02 3.59E-03 9.81E-02 Maximum Hourly Average Release Rate (3)
(Curies /Second) 7.86E-07 1.42E-06 1.59E-05 9.93E-05 1.11E-04 6.01E-03 (1) Includes Nobel Gas contribution from liquid releases (2) Data not available at time of report (3) Expressed as Xe-133 equivalents
TABLE 2-2 ISOTOPIC COMPOSITION OF AIRBORNE RELEASES PERIOD OF JULY 1, 1985 TO DECEMBER 31, 1985 NUCLIOES JUL AUG SEP OCT NOV DEC TOTAL RELEASED (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Ceries)
Tritium 1.53E+00 2.21E+00 1.38E+00 4.16E+00 1.80E+01 '1.04E+00 2.83E+01 Xe-133 7.76E-02 8.46E-02 7.33E-02 1.92E+01 1.38E-01 1.20E+00 2.08E+01 Kr-85m 1.24E-01 1.86E-01 1.49E-01 3.16E-02 4.51E-04 4.27E-01 9.18E-01 Kr-88 3.32E-01 4.83E-01 3.83E-01 8.60E-02 1.15E-03 1.02E+00 2.31E+00 Xe-133m <MDA 1.17E-05 2.43E-04 1.84E-01 1.12E-05 1.77E 2.02E-01 Xe-135 5.80E-01 7.74E-01 6.27E-01 3.78E-01 9.19E-03 1.97E+00 4.34E+00 Xe-138 1.20E+00 1.65E+00 1.29E+00 8.15E-01 5.02E-03 3.32E+00 8.28E+00 Kr-87 2.88E-01 4.17E-01 3.38E-01 7.90E-02 1.07E-03 8.49E-01 1.97E+00 j3 Xe-135m 4.00E-01 4.82E-01 3.73E-01 2.19E-01 1.52E-03 1.06E+00 2.54E+00 Ar-41 1.01E-01 6.91E-02 4.55E-02 4.81E-02 8. 86E-02 4.07E-01 7.59E-01 Kr-85 6.47E-01 4.40E-01 3.27E-03 1.09E+01 9.76E-06 5.12E-01 1.25E+01 1-131 1.25E-05 2.28E-05 1.87E-05 1.92E-04 2.09E-05 8.45E-04 1.12E-03 I-132 <MDA <MDA <MDA 3.45E-03 <MDA 2.97E-04 3.75E-03 I-133 2.92E-05 6.10E-05 3.91E-04 2.61E-05 5.90E-06 7.97E-04 1.31E-03 1-134 <MDA <MDA <MDA (MDA <MDA 1.33E-05 1.33E-05 I-135 <MDA 2.12E-05 8.96E-06 <MDA <MDA 5.49E-04 5.79E-04 Co-58 3.64E-10 <MDA <MDA 1.63E-06 8.42E-05 5.40E-08 8.59E-05 Co-60 <MDA 1.43E-06 3.67E-06 4.44E-06 3.21E-05 3.55E-07 4.20E-05 Os-134 <MDA 1.25E-07 2.83E-07 2.64E-07 1.10E-03 7. 84E-05 1.18E-03 Cs-137 1.66E-06 6.83E-07 1.10E-06 5.92E-06 3.71E-03 2.49E-04 3.97E-03 Ra-88 2.09E-06 <MDA <MDA <MDA <MDA 2.51E-05 2.72E-05 Mn-54 <MDA <MDA 4.39E-08 7.35E-08 1.87E-06 <MDA 1.99E-06 Co-57 <MDA <MDA 2.06E-07 4.34E-09 <MDA <MDA 2.10E-07 Na-95 <MDA <MDA <MDA <MDA 2.50E-06 <MDA 2.50E-06
~.r-95 <MDA <MDA <M0A <MDA 1.31E-06 <MDA 1.31E-06 Sn-113 <MDA <MDA <MDA <MDA 2.15E-08 <MDA 2.15E-08 Sb-125 (MDA <MDA 3.79E-08 <MDA <MDA 4.55E-08 8.34E-08 Na-24 (MDA <MDA 1.39E-04 <MDA <MDA <MDA 1.39E-04 Ru-103 <MDA <MDA <MDA <MDA 1.28E-10 <MOA 1.28E-10 Ce-141 (MDA <MDA (M0A <M0A 8.48E-09 <MDA 8.48E-09 ALPHA 8.54E-07 <MOA <MDA 3.55E-08 8.60E-07 1.27E-05 1.45E-05
l l
l 3.0 RADI0 ACTIVE SOLID WASTE SHIPMENTS j Shipments offsite of solid waste for burial during this reporting period were as follows:
DATE OF VOLUME TOTAL ACTIVITY SHIPMENT (cubic feet) (Curies) 07-08-85 178.0 4.65 07-08-85 178.0 3.98 07-10-85 178.0 6.64 07-10-85 178.0 1.79 07-15-85 178.0 3.17 07-17-85 178.0 3.17 07-22-85 126.0 83.90 (1) 07-22-85 178.0 3.17 08-20-85 195.0 0.84 08-22-85 1204.5 0.28 11-14-85 1164.0 0.26 12-05-85 105.0 3.57 12-16-85 178.0 2.26 12-17-85 178.0 2.17 12-17-85 178.0 2.17 12-20-85 1297.0 0.21 12-20-85 390.0 0.83
. 12-26-85 178.0 2.08 (1) Involved spent resin.
4.0 NEW & SPENT FUEL SHIPMENTS AND RECEIPTS During this reporting period, a total of 28 new fuel assem' ulies were received from Westinghouse Electric Corporation for Unit 2. The new fuel assemblies received for Unit 2 were used for the Fall, 1985 refueling.
There were three spent fuel shipments made from Point 8each Nuclear Plant by the Department of Energy (00E).
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological environmental monitoring conducted by Point Beach Nuclear Plant from July 1, 1905 through December 31, 1985 consisted of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, vegetation, and TLDs. All sampling and analyses were accomplished in accordance with Technical Specification 15.7.7.
No results with significant deviations from normal, attributable to the operation of P8NP, were noted during this period.
No. Sample Type Low Average HM Units TLDs 42 Environmental Radiation 0.78 1.27 0.41 1.57 mR/7 days Air 3
156 Gross beta <0.01 <0.0210.02 0.07 pCi/m 156 Radioiodine all <0.03 pCi/m 3
12 Cs-137 a11 <0. 01 pCi/m 3
12 Cs-134 all <0.01 pCi/m 3
12 Other gamma emitters all <0.01 pCi/m Milk 18 Radioiodine all <0.5 pCi/1 18 Sr-89 all <5 pCi/1 18 Sr-90 1.2 2.111.7 3.7 pCi/1 18 Cs-134 all <5 pCi/l 18 Cs-137 all <5 pCi/1 18 Ba-La-140 all <5 pCi/l 18 Other gamma emitters all <5 pCi/l Lake Water 30 Gross Beta 1. 8 2.812.3 8.1 pCi/1 10 Tritium all <500 pCi/l 10 Sr-89 all <5 pCi/l 10 Sr-90 <1 <1.010.2 1.2 pCi/l 30 Radioiodine all <0.5 pCi/l 30 Mn-54 all <10 pCi/l 30 Fe-59 all <30 pCi/l 30 Co-58 all <10 pCi/1 30 Co-60 al1 <10 pCi/1 30 Zn-65 all <30 pCi/1 30 Zr-Nb-95 all <15 pCi/1 30 Cs-134 all <10 pCi/l 30 Cs-137 all <10 pCi/l 30 Ba-La-140 all <15 pCi/l 30 Other gamma emitters all <30 pCi/l 1
No. Sample Types Low Average High Units ,
Well Water 2 Gross Beta 2. 9 <3.511.6 < 4.0 pCi/1 2 H-3 all <500 pCi/1 2 Sr-89 all <5 pCi/1 2- Sr-90 all <1 pCi/1 2 I-131 all <0.5_ pCi/1 2 Mn-54 all <10 pCi/1
- 2 Fe-59 all <30 pCi/1 2 Co-58 all <10 pCi/1 2 Co o0 all <10 pCi/1.
2 Zn-65 all <30 pCi/1 2 Zr-Nb-95 all <15 pCi/1 l 2 Cs-134 all <10 pCi/1 2 Cs-137 all <10 pCi/1 2 Ba-La-140 .
all <15 pCi/1 2 Other Gamma Emitters all <30 pCi/1 Fish
- - 11 Gross Beta 0.4 2.411.9 3.8 pCi/g wet 11 Mn-54 all <0.13 pCi/g wet 11 Fe-59 all <0.26 pCi/g wet 11 Co-58 all <0.13 pCi/g wet i 1
11 Co-60 all <0.13 pCi/g wet .
l 11 Zn-65 all <0.26 pCi/g wet
- 11 Cs-134 all <0.13 pCi/g wet i 11 Cs-137 - <0.15 <0.1510.01 0.16 pCi/g wet 11 Other Gamma Emitters all <0.5 pCi/g wet Soil 8 Gross Beta 13.3 24.6115.4 34.7 pCi/g dry 8 Cs-137 <0.15 <0.2410.24 0.45 pCi/g dry 8 Other Gamma Emitters all <0.15 pCi/g dry Shoreline Sediment 5 Gross Beta 7.2 8.011.1 8.6 pCi/g dry 5 Cs-137 all <0.15 pCi/g dry l pCi/g dry 5 Other Gamma Emitters all <0.15 Vegetation '
i.
16 Gross Beta 3.4 5.613.2 9.2 pCi/g wet 16 Cs-137 all <0.08 pCi/g wet 16 Cs-134 all <0.06 pCi/g wet l l pCf/g wet 16 1-131 all <0.06 16 Other Gamma Emitters all <0.25 pCi/g wet i
, t I
No. Sample Types Low Average 'Hiah Units Algae 5 Gross Beta 0.8 1.913.9 5.4 pCi/g wet 5 C0-58 <0.25 <0.2510.02 0.27 pCi/g wet 5 Co-60 <0.25 <0.2610.06 0.32 pCi/g wet 5 Cs-134 all <0.25 pCi/g wet 5 Cs-137 all <0.25 pCi/g wat 5 Other Gamma Emitters all <0.25 pCi/g wet I
6.0 NON-RADI0 ACTIVE CHEMICAL RELEASES 6.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system for the period of July 1, 1985 to December 31, 1985 included 4,692,701 gallons of neutralized clear water waste. The waste water contained 776 pounds of suspended solids and 545,437 pounds of dissolved solids.*
The concentration increases of chemical waste in the circulating water system during the period of chemical releases ranged from 0.729 to 19.355 ppm dissolved solids and from 0.001 to 0.057 ppm of suspended solids.**
Plant chemical records indicated that the following amounts of chemicals were released in the form of neutralized waste:
Sodium : 170,317 pounds Sulfate : 276,907 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.
6.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases to the circulating water system from the retention pond for the period of July 1, 1985 to December 31, 1985, included 16,180,000 gallons of clear water waste. The wastewater contained 979 pounds of suspended solids and 69,169 pounds of dissolved solids.*
Retention pond analysis and sewage plant chemical records indicate.that the following chemicals were released in the form of clear wastewater from the retention pond.
Sodium : 486 pounds Chloride : 751 pounds Phosphate: 127 pounds The balance of the dissolved solids were in the form of soluble calcium and magnesium compounds resulting from the in plant makeup water cold lime softening process.
- Chemical release calculations are based on retention pond and sewage plant effluent analysis during the period July 1, 1985 to December 31, 1985.
7.0 CIRCULATING WATER SYSTEM OPERATION The circulating water system operation during this reporting period is described in Table 7-1.
8.0 LEAK TESTING OF RADI0 ACTIVE SOURCES During this reporting period, all applicable sealed radioactive sources were leak tested according to Technical Specification 15.4.12. Leak test results were all <0.005 uCi.
l
TABLE 7-1 CIRCULATING WATER SYSTEM OPERATION July 1, 1985 to December 31, 1985 JUL AUG SEP OCT NOV DEC ,
Average Volume Cooling UNIT 1: 476.1 469.9 467.5 484.5 -335.7 195.3 Water Discharge (Million gal / day) UNIT 2: 546.8 536.7 557.5 469.7* 43.3* 217.5 Average Cooling Water UNIT 1: 55.4 56.7 56.4 48.2 44.3 38.2 Intake Temperature (Degrees F) UNIT 2: 55.3 56.8 56.4' 45.2* 42.7* -37.9 ,
Average Cooling Water UNIT 1: 74.9 76.9 76.6 68.4 59.5 58.4
. Discharge Temperature 5; (Degrees F) UNIT 2: 74.3 76.0 75.7 60.7* 54.3* 59.3 Average Ambient Lake 55.4 56.8 56.4 47.3 41.1 33.7 Temperature '
(Degrees F)
(* = Unit 2 refueling shutdown from 10-06-85 to 11-25-85.) -
9.0 MISCELLANEOUS REPORTING REQUIREMENTS 9.1 Revisions to the PBNP ODCM and PCP
' Extensive changes to the Offsite 00se Calculation Manual (00CM), in-cluding changes to the Environmental Manual (EM) and the Process Control Program (PCP), were made during this reporting period in order to facili-tate the implementation of the PBNP Radiological Effluent Technical Specifications. Because these revisions are extensive and can not be effectively identified in this Semiannual Report, a complete copy of each revised document was forwarded to the Nuclear Regulatory Commission in a letter dated January 20, 1986.
9.2 Interlaboratory Comparison Program The analytical laboratory contracted to perform the radioanalyses of the environmental samples participated in the EPA Interlaboratory Comparison Program during this reporting period.
9.3 Deviations from Specified Environmental Sample Types, Locations, and Frequencies There were no deviations from the sampling types, frequencies, and locations specified in Technical Specification 15.7.7 during this reporting period.
9.4 Summary of Unachievable Specified Environmental LLDs All LLDs specified in Technical Specification 15.7.7 were accomplished.
L .
l-
- 10. ERRATUM TO PREVIOUS SEMIANNUAL REPORTS The following corrections should be made to Table 2-2 of the Se'miannual Report for January 1,1985 to June 30, 1985.
TABLE 2-2 4
CORRECTIONS .
I RADI0 ACTIVE AIRBORNE RELEASE
SUMMARY
JANUARY 1, 1985 TO JUNE 30, 1985 i 4 ,
Nuclides. June Total s
! Released (Ci) (Ci) ,/
, , j i Tritium 5.97E+00 3.88E+01 IN i Xe-133 3.66E-01 1.37E+01 ,
- Kr-85m 8.29E-02 1.75E+01
- Kr-88 2,05E-01 3.42E+00 t i Xe-133m 1.10E-02 1.28E-01 '
l Xe-135 5.43E-01 7.51E+00
- Xe-138 6.00E-01 8.25E+00 l Kr-87 1.73E-01 2.81E+00 1 Xe-135m 1.97E-01 - 3.22E+00 l Ar-41 6.17E-02' 5.15E-01 d i Kr-85 2.84E-02 4.24E+00 , \, '
t Xe-131m- <MDA 8.54E-02 t
! Zr-97 <MDA 2.97E-10 -[ .
! Cs-138 '<M0A 9.64E-07
) Rb-88 1.84C-07 1.91E-05
- I-131 3.00E-05 2.32E-03 ;
! I-132 <MDA 9.78E-09 I-133 7.06E-06 6.36E-05 I-135 <MDA 1.46E-08 Sr-89 <MDA ,y <MDA Sr-90 <MOA <MDA Cd-109 2.20E-06 8.92E-06 Sn-113 <MDA ' 6.95E-11 Sb-125 <MDA 4.14E-08 ,
A Ru-103 1.90E-08 1.90E-08 ' '
Cs-134 3.39E-07 4.80E-06 4 Cs-137 7.72E-06 4.67E-05 g Nb-95 2.92E-11 2.34E-08 Co-58 6.64E-05 7.15E-05 g Co-60 2.60E-05 3.74E-05 ,7 Alpha <MDA 9.73E-07 kl t
k J I g
The following corrections should be made to the radioiodine values in Table 2-2 for Semiannual Reports for the period January 1.1984 to June 30, 1985.
TABLE 2-2 CORRECTIONS RADI0 ACTIVE AIRBORNE RELEASE
SUMMARY
JANUARY 1, 1984 TO JUNE 30, 1984 Nuclides January February March April May June Total Released (Ci) (Ci) (Ci) (C1) (Ci) (Ci) (Ci)
I-131 7.76E-06 3.22E-06 4.63E-06 1.29E-05 4.26E-05 1.18E-05 8.29E-05 I-133 2.32E-06 1.31E-06 9.05E-06 1.82E-05 1.11E-04 1.36E-05 1.56E-04 TABLE 2-2 .
CORRECTIONS RADIOACTIVE AIRBORNE RELEASE
SUMMARY
JULY 1, 1984 TO DECEMBER 31, 1984 Nuclides July August September October November December Total Released (Ci) (Ci) (Ci) (Ci) {C_iji (Ci) (Ci)
I-131 4.63E-05 7.68E-05 1.24E-04 2.61E-04 1.34E-05 2.16E-05 5.43E-04 I-132 <MDA <MDA <MDA 2.27E-03 <MDA <MDA 2.27E-03 1-133 4.56E-06 1.66F-04 7.95E-05 1.84E-05 1.38E-05 2.51E-03 3.48E-04 TABLE 2-2 CORRECTIONS RADIOACTIVE AIRBORNE RELEASE
SUMMARY
JANUARY 1, 1985 TO JUNE 30, 1985 Nuclides January February March April May June Total Released (Ci) (C1) (Ci) (Ci) (Ci) {Cj,} (Ci)
I-131 2.09E-05 1.13E-05 1.14E-05 1.69E-03 5.57E-04 3.00E-05 2.32E-03 I-132 < EDA <MDA <MDA 9.78E-09 <MDA <MDA 9.78E-09 I-133 2.19E-05 9.65E-07 7.58E-06 7.78E-06 1.83E-05 7.06E-06 6.36E-05
.DM0 Wisconsin Electnc eom coupw 231 W. MICHIGAN.P.o BOX 2046, MILWAUKEE.Wl 53201 (414) 277-2345 VPNPD-86-101 NRC-86-20 February 28, 1986 Mr. J. G. Keppler, Regional Administrator Office of Inspection and Enforcement, Region III U. S. NUCLEAR REGULATORY COMMISSION 799 Roosevelt Road Glen Ellyn, II'dinois 60137
Dear Mr. Keppler:
DOCKET NOS. 50-266 AND 50-301 SEMIANNUAL MONITORING REPORT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Enclosed is the Semiannual Monitoring Report for the Point Beach Nuclear Plant, Units 1 and 2, for the period from July 1 through Deccmber 31, 1985. This report is submitted in accordance with Technical Specification 15.7.8.L A and contains information regarding plant releases, solid waste and new and spent fuel shipments, environmental monitoring, circulating water system operations, leak testing of sources, and other miscellaneous reportable items from this reporting period. Forty bound copies of this report are being forwarded to you under separate cover.
Very truly yours, bU C. W. Fay Vice President Nuclear Power Enclosure Copies to Director, Office of Inspection and Enforcemettt, USNRC NRC Resident Inspector MAR 5 tggg i.4 IEMS J