ML20056F808
| ML20056F808 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/30/1993 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20056F807 | List: |
| References | |
| NUDOCS 9308310127 | |
| Download: ML20056F808 (16) | |
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WISCONSIN ELECTRIC SEMIANNUAL MONITORING REPORT JANUARY,1993 through JUNE,1993 POWER COMPANY POINT BEACH NUCLE AR PL ANT UNIT NOS.1 AND 2 U.S. Nuclear Regulatory Commission Docket Nos. 50-266 and 50-301
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Facility Operating License Nos.
9308310127 930526 DPR-24 and DPR-27 PDR ADOCK 05000266 R PDR
PREFACE This Semiannual Monitoring Report for the period of January 1,1993, through June 30,1993, is submitted in accordance with Point Beach Nuclear Plant Unit Nos.1 and 2 Technical Specification 15.7.8.4 and filed under Docket Nos. 50 966 and 50-301 for Facility Operation License Nos. DPR-24 and DPR-27, respectively.
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TABLE OF CONTENTS Section Title Pace 1.0 Radioactive Liquid Releases 1 2.0 Radioactive Airborne Releases 5 3.0 Radioactive Solid Waste Shipments 8 4.0 New and Spent Fuel Shipments 8 1
5.0 Radiological Environmental Monitoring 8 6.0 Nonradioactive Chemical Releases 12 7.0 Circulating Water System Operation 12 8.0 Leak Testing of Radioactive Sources 13 9.0 Miscellaneous Reporting Requirements 13
SEMIArWAL MONITORING REPORT January 1, 1993 to June 30, 1993 1.0 RADIOACTIVE LIOUID RELEASES The total radioactive liquid release, excluding tritium for this reporting period, was 1.40E-01 curies. This included 5.75E-2 curies in processed radioactive waste and primary coolant system letdown, 1.91E-04 curies in Unit I steam generator blowdown, 8.22E-02 curies in Unit 2 steam generator blowdown and 1.9BE-04 curies in retention pond effluent.
The total tritium release for this reporting period was 2.09E+02 curies.
This included 2.05E+02 curies in processed radioactive waste and primary coolant system letdorn, 2.01E-02 curies in Unit 1 steam generator blowdown, 2.82E+00 curies in Unit 2 steam generator blowdown and 7.60E-01 curies in retention pond effluent.
1.1 Circulatina Water Radionuclide Release Summary 1.1.1 Releases During Current Reporting Period Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curie released on a monthly basis and presented in Table 1-1. Table 1-1 also contains the comparison between the annual Appendix I dose limits for liquid discharges and the corresponding highest doses calculated according to the ODCM using the semiannual isotopic composition of the liquid discharge listed in Table 1-2.
1.1.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of the previous report preparation and should be added to Table 1-1 of the Semiannual Monitoring Report for July 1, 1992, through December 31, 1992.
6-MONTH DEC TOTAL Total Activity Released (Ci)
Gross Alpha (MDA 9.4E-06 Strontium 5.4E-05 2.6E-04 Average Diluted Discharge Concentration (pCi/cc)
Gross Alpha (MDA Strontium 1.1E-14 1 .-
l TABLE 1-1 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGE JANUAPJ 1, 1993 THROUGH JUNE 30, 1993 JAN FEB PR APR MAY JUN TOTAL Total Activity Released (Ci)
Gamma Scan 9.97E-03 9.62E-03 6.92E-02 1.21E-02 1.95E-02 1.98E-02 1.40E-01 Gross Alpha 1.6 E-07 1.9 E-07 4.36E-06 <MDA (1) (1) (1) l Tritium 1.78E+01 3.83E+01 2.93E+01 9.63E+01 2.17E+01 5.33E+00 2.09E+02 Strontium 1.4 E-06 5.55E-06 1.1 E-06 (MDA (1) (1) (1)
Total Volumes Released (Gal)
Processed Waste 4.14E+04 6.21E+04 6.47E+04 1.64E+05 8.39E+04 3.69E+04 4.53E+05 (U1) Steam Generator Blowdown 3.57E+06 3.22E+06 3.19E+06 (2) 4.37E+06 3.45E+06 1.78E+07 (U2) Steam Generator Blowdown 3.55E+06 3.24E+06 3.62E+06 4.03E+06 3.84E+06 3.45E+06 2.17E+07 Retention Pond 2.83E+06 2.30E+06 2.bOE+06 2.93E+06 2.77E+06 2.48E+06 1.59E+07 Miscellaneous Releases 9.99E+03 9.99E+03 Total 9.99E+06 8.83E+06 9.47E+06 7.13E+06 1.11E+07 9.42E+06 5.59E+07 Volume of Dilution Water (Gal) 8.75E+09 7.90E+09 8.80E+09 1.04E+10 1.52E+10 1.47E+10 6.58E+10 Average Diluted Discharge Concentration (uCi/cc)
Gross Gamma 3.01E-10 3.22E-10 2.08E-09 3.09E-10 3.39E-10 3.56E-10 Gross Alpha 4.8 E-15 6.4 E-15 1.31E-13 <MDA (1) (1)
Tritium 5.38E-07 1.28E-06 8.80E-07 2.46E-06 3.75E-07 9.59E-08 Strontium 4.2 E-14 1.85E-13 3.3 E-14 <MDA (1) (1)
Maximum Discharge Concentration During Release Period (uCi/cc)
Gross Gamma 4.62E-10 6.29E-10 2.77E-08 7.80E-10 6.91E-10 1.43E-09 Tritium 3.91E-05 3.66E-05 5.05E-05 5.39E-05 2.2 E-05 3.88E-06 Comparison of semiannual effluent doses to annual Appendix I Highest dose limits Annual Limit Calculated Dose (mrem) (mrem) 6 whole body 7.61E-03 (adult) 20 any organ 1.01E-02 (teen liver)
(1) Information unavailable at time of report preparation.
(2) Unit i refueling shutdown from March 27, 1993 to May 6, 1993.
Note: Dissolved noble gases detected in liquid effluents are included in airborne release totals RETS = Radiological Effluent Technical Specifications.
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TABLE 1-2 ISOTOPIC CC.MPOSITION OF CIRCULATING WATER DISCHARGES JANUARY 1, 1993 THROUGH JUNE 30, 1993 NUCLIDES JAN FEB MAR APR MAY JUN TOTAL RELEASED (Curies) (Curies) (Curies) (Curies) (Cu ri ep_l, (Curies) (Curies)
Tritium 1.78E+01 3.82E+01 2.93E+01 9.63E+01 2.17E+01 5.33E+00 2.09E+02 I-131 9.71E-05 3.18E-04 6.67E-04 1.37E-04 4.75E-04 3.13E-04 2.01E-03 1-132 (MDA 1.09E-05 3.19E-04 3.63E-04 1.02E-03 6.04E-04 2.32E-03 I-133 1.58E-03 1.80E-03 2.38E-03 2.51E-03 3.22E-03 3.64E-03 1.51E-02 I-134 <MDA 2.60E-06 1.03E-04 1.11E-05 1.73E-04 1.54E-04 4.44E-04 I-135 <MDA 2.01E-05 9.46E-05 1.08E-04 6.05E-04 6.24E-04 1.45E-03 F-18 6.65E-03 5.82E-03 5.18E-03 6.27E-03 8.59E-03 7.02E-03 3.95E-02 Na-24 <MDA 3.09E-06 1.19E-04 2.43E-05 3.02E-04 2.09E-04 6.57E-04 Cr-51 <MDA <MDA 2.22E-03 <MDA 3.76E-05 <MDA 2.26E-03 MN-56 <MDA 5.51E-06 <MDA 6.64E-05 3.90E-05 2.27E-04 3.38E-04 Co-57 <MDA <MDA <MDA 3.84E-05 <MDA <MDA 3.84E-05 Co-58 3.21E-05 2.30E-05 7.48E-05 5.28E-05 5.37E-05 2.86E-05 2.65E-04 Co-60 6.11E-05 3.55E-05 1.69E-04 1.76E-04 1.28E-04 1.49E-04 7.19E-04 Zn-69m (MDA (MDA 4.82E-06 <MDA <MDA <MDA 4.82E-06 Sr-92 (MDA <MDA 5.17E-0G <MDA <MDA (MDA 5.17E-06 Tc-99m <MDA <MDA <MDA <MDA 2.42E-06 6.49E-05 6.73E-05 Zr-97 <MDA <MDA <MDA <MDA 8.08E-06 <MDA 8.08E-06 Ag-110m 7.02E-05 6.34E-05 1.93E-04 2.50E-04 2.68E-04 3.35E-04 1.18E-03 Sb-125 <MDA (MDA 5.29E-02 1.23E-05 <MDA <MDA 5.29E-02 Te-132 <MDA <MDA 1.21E-04 3.83E-06 <MDA <MDA 1.25E-04 Cs-134 2.38E-04 5.34E-04 1.98E-03 9.26E-04 2.09E-03 3.04E-03 8.81E-03 l Te-131m (MDA 1.82E-04 9.79E-05 (MDA <MDA <MDA 2.80E-04 Cs-137 1.24E-03 8.14E-04 2.58E-03 1.17E-03 2.55E-03 3.16E-03 1.15E-02 Cs-138 <MDA <MDA <MDA <MDA <MDA 4.94E-05 4.94E-05 Ce-141 <MDA <MDA <MDA <MDA <MDA 3.51E-05 3.51E-05 Ce-144 <MDA <MDA <MDA <MDA <MDA 2.00E-04 2.00E-04 Sr-89 (MDA 4.25E-06 <MDA <MDA (1) (1) (1)
Sr-90 1.4 E-06 1.3 E-06 1.1 E-06 <MDA (1) (1) (1)
(1) Information unavailable at time of report preparation.
Note: Dissolved noble gases detected in liquid effluents are included in airborne release totals.
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1.2 Isoto_ni_q Composition of Circulatina Water Discharoes 1.2.1 Releases During Current Reporting Period The isotopic composition of circulating water discharges during the current reporting period is presented in Table 1-2.
1.2.2 Additions to Previous Semiannual Monitoring Report The following infomation was not available at the time of report preparation and should be added to Table 1-2 of the Semiannual Monitoring Report for July 1, 1992, through Decerr.ber 31, 1992.
6 -MCITTH DEC TOTAL Sr-89 (Ci) <MDA 5.0E-05 Sr-90 (Ci) 5.4E-05 2.1E-04 1.3 Subsoil Drain System Peleases of Tritium 1.3.1 Releases During Current Reporting Period The releases of tritium via the subsoil drain system Laring the current reporting period is presented in Taba 1-3.
TABLE l-3 SUBSOIL SYSTEM DRAINS - TRITIUM
SUMMARY
January 1, 1993 through June 30, 1993 First Ouarter S-1 S-3 S -f_ S-10 Totals H-3 (yCi/cc) (MDA cMDA No Sample (FDA Ave. Flow (gpd) 1.49E+04 6.85E+03 No Flow 2.11E404 fic_gnd Ouarter H-3 (pCi/cc) <MDA (MDA <MDA cMDA Ave. Flow (gpd) 5.33E+04 2.13E+04 5.89E+03 1.75E+04 Semiannuni TpoJAI J Total Released (Ci) <MDA cMDA <!C A eMDA (MDA Total Flow (gals) 6.19E+06 2.55E+06 5.36E+05 3.49E+06 1.28E+07 1
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1.4 Land Application of Sewaoe Sludge Trace amounts of radionuclides may be land-applied with sewage sludges on various Department of Natural Resources approved Wisconsin Electric Power Company properties surrounding the Point Beach Nuclear Plant in accordance with approved methodologies pursuant to 10 CFR 20.302. No land application of sewage sludge took place between January 1, 1993 and June 30, 1993.
2.0 RADIOACTIVE AIRBORNE RELEASES 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 containment purge stack, combined air ejector decay duct exhaust and turbine building ventilation exhaust.
There was one gas decay tank released during this reporting period.
2.1 Radioactive Airborne Release Summary 2.1.1 Release During Current Reporting Period Radioactivity released in airborne effluent for the current reporting period are summarized in Table 2-1.
Table 2-1 also contains the comparison of the annual Appendix I dose limits for atmospheric effluents to the highest dose and the noble gas doses calculated using ODCM methodology and the isotopic composition of atmospheric releases identified in Table 2-2.
2.1.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of the last report preparation and should be added to Table 2-1 of the Semiannual Monitoring Report for July 1, 1992 through December 31, 1992.
Strontium (Ci)
October cMDA November cMDA December cMDA Total (MDA 2.2 Isotonic Airborne Releases 2.2. Releases During Current Reporting Period The monthly isotopic airborne releases for the current reporting period are presented in Table 2-2.
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TABLE 2-1 RADIOACTIVE AIRBORNE RELEASE
SUMMARY
JANUARY 1, 1993 THROUGH JUNE 30, 1993 JAN FEB MAR APR MAY JUN TOTAL Total Noble Gases (Ci) : (2) 8.69E-01 7.44E-01 6.69E-01 2.72E+00 1.34E+00 5.55E-01 6.90E+00 Total Radiciodines (C1). 1.71E-06 2.40E-07 4.54E-05 2.75E-05 1.57E-09 1.27E-06 7.61E-05 Total Particulates (Ci): 4.84E-06 4.49E-06 1.53E-04 3.58E-05 1.91E-05 9.02E-06 2.2GE-04 Alpha (Ci): 5.42E-09 3.52E-07 1.17E-07 1.02E-06 3.66E-07 7.17E-07 2.58E-06 Strontium (Ci)* (MDA <MDA <MDA (1) (1) (1) (1)
All Others (Ci) 4.83E-06 4.14E-06 1.53E-04 3.48E-05 1.87E-05 8.30E-06 2.24E-04 Total Tritium (Ci)- 8 58E+00 2.67E+01 1.76E+01 8.91E+00 7.46E+00 7.46E+00 7.67E+01 Maximum Hourly Average Release Rate (Curies /Second) 7.15E-07 8.60E-07 8.11E-07 5.14E-04 1.16E-05 7.36E-07 Comparison of semiannual effluent doses to annual Appendix I dose Highest limits Annual Dose Limit Calculated Dose particulate 30 mrem / organ 1.63E-02 (child liver) noble gas 40 mrad (p air) 8.74E-04 noble gas 20 mrad (y air dose) 1.66E-03 noble gas 30 mrem (skin) 1.10E-03 noble gas 10 mrem (whole body) 1.96E-03 s
(1) Information unavailable at time of report preparation, but values typically do not alter monthly totals.
(2) Includes noble gas contribution from liquid releaces.
i TABLE 2-2 RADIOACTIVE AIRBORNE RELEASE
SUMMARY
JANUARY 1, 1993 THROUGH JUNE 30, 1993 NUCLIDES JAN FE8 MAR APR MAY JUN TOTAL PELEASED (Curies) Kuries) (Curies) (Curies) (Curies) (Curies) (Curies)
Tritium 8.58E+00 2.67E+01 1.76E+01 8.91E+00 7.46E+00 7.46E+00 7.67E+01 l Xe-133 3.56E-01 3.18E-01 3.24E-01 4.51E-01 3.66E-01 3.16E-01 2.13E+00 Kr-85m 5.35E-03 1.43E-03 2.21E-03 7.93E-02 3.01E-02 4.32E-03 1.23E-01 '
Kr-88 1.28E-02 3.27E-03 5.24E-03 1.73E-01 6.84E-02 8.80E-03 2.72E-01 Xe-133m 8.45E-05 5.50E-05 9.28E-05 G.59E-03 1.96E-03 3.00E-03 1.18E-02 Xe-135 4.04E-02 2.31E-02 2.83E-02 5.19E-01 2.14E-01 3.03E-02 8.55E-01 Xe-138 4.61E-02 1.24E-02 1.99E-02 4.97E-01 2.05E-01 2.94E-02 8.10E-01 Kr-87 1.08E-02 2.84E-03 4.57E-03 1.29E-01 5.03E-02 7.01E-03 2.05E-01 Xe-135m 1.40E-02 3.97E-03 5.87E-03 2.43E-01 7.63E-02 9.45E-03 3.53E-01 Ar-41 3.83E-01 3.79E-01 2.79E-01 4.99E-01 2.78E-01 1.47E-01 1.97E+00 Kr-85 <MDA <MDA (MDA 1.21E-01 5.15E-02 <MDA 1.73E-01 Xe-131m <MDA <MDA <MDA <MDA (MDA 5.23E-03 5.23E-03 I-131 (MDA <MDA 1.29E-05 1.46E-06 1.57E-09 1.80E-09 1.44E-05 I-132 2.07E-07 (MDA 3.78E-06 2.55E-06 (MDA <MDA 6.54E-06 I-133 1.51E-06 2.40E-07 1.95E-05 1.11E-05 <MDA 1.26E-06 3.36E-01 I-135 (MDA (MDA 9.24E-06 1.24E-05 <MDA <MDA 2.16E-05 F-18 3.69E-06 1.75E-06 6.81E-06 1.38E-05 <MDA 4.62E-06 3.07E-05 Na-24 (MDA <MDA <MDA 1.22E-06 <MDA <MDA 1.22E-06 Mn-56 (MDA (MDA <MDA 1.03E-06 <MDA <MDA 1.03E-06 Co-57 <MDA <MDA <MDA 2.47E-07 <MDA <MDA 2.47E-07 Co-58 <MDA <MDA 1.91E-06 <MDA (MDA (MDA 1.91E-06 Rb-88 (MDA <MDA (MDA 1.52E-06 1.14E-05 2.09E-06 1.50E-05 Te-132 <MDA <MDA <MDA <MDA 4.20E-09 <MDA 4.20E-09 Cs-134 <MDA 2.13E-07 7.43E-05 4.95E-06 <MDA <MDA 7.95E-05 Cs-137 1.14E-06 2.17E-06 6.89E-05 1.20E-05 (MDA 1.22E-06 8.54E-05 Cs-138 <MDA <MDA <MDA <MDA 7.31E-06 3.73E-07 7.68E-06 Sr-89 <MDA (MDA <MDA (1) (1) (1) (1)
Sr-90 <MDA <MDA <MDA (1) (1) (1) (1)
Alpha 5.42E-09 3.52E-07 1.17E-06 1.02E-06 3.66E-07 7.17E-07 3.63E-6 (1) Information unavailable at time of report preparation, but values typically do not alter monthly totals reported in Table 2-1.
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2.2.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of previous report preparation and should be added to Table 2-2 of the Semiannual Monitoring Report, covering the period July 1, 1992, through December 31, 1992.
Sr-89 (Ci) Sr-90 (Ci)
October <MDA c.MDA November cMDA (MDA December <MDA (MDA Totals cMDA (MDA' 3.0 RADIOACTIVE SOLID WASTE SHIPMENTS Solid wastes shipped for burial during this reporting period were as follows:
DATE OF SHIPMENT VOLUME TOTAL ACTIVITY TO BURIAL (CUBIC FEET) (Curies) BURIAL SITE 2/22/93 2.60 (1,2) 1.30E-03 Barnwell, SC 3/12/93 73.27 (1,2) 7.62E-02 Barnwell, SC 5/17/93 77.00 (1,2) 1.57E-02 Barnwell, SC 5/25/93 86.00 (1,2) 4.64E-02 Barnwell, SC 5/20/93 69.61 (1,2) 1.10E-02 Barnwell, SC 5/25/93 15.00 (1,2) 1.20E-G3 Barnwell, SC 5/17/93 95.44 (1,2) 1.27E-02 Barnwell, SC i 5/25/93 7.50 (1,2) 1.0CE-04 Barnwell, SC 6/23/93 16.44 (1) 1.80E-03 Barnwell, SC l 6/16/93 13.80 (1,2) 8.00E-04 Barnwell, SC 6/16/93 23.10 (1,2) 2.10E-03 Barnwell, SC 6/24/93 102.87 (1,2) 2.00E-01 Barnwell, SC 6/24/93 103.35 (1,2) 7.82E-02 Barnwell, SC 6/16/93 12.10 (1,2) 7.00E-04 Barnwell, SC TOTAL 698.08 4.49E-01 (1) Dry Active Waste (2) Scrap Metal 4.0 NEW AND SPENT FUEL SHIPMENT 3 AND RECEIPTS During this reporting period, a total of'28 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 1993 refueling.
There were no spent fuel shipments made from Point Beach Nuclear Plant during this reporting period.
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Introduction The results in this Semiannual Report are presented in the new i format which was initiated with the January - June 1992 Report..
Results are reported directly as measured, including negative and ;
zero values. -This eliminates the distortion of the results and long-term trends which occurs when the LLD is used to censor results that are below the LLD. This reporting convention follows that recommended in Health Physics Society Committee l Report HPSR-1 (1980) released as document EPA 520/1-80-012.
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The REMP results are presented in Table 5.1. This table contains the following information:
Sample: the type of the sample medium
Description:
the type of measurement LLD: the a criori lower limit of detection N: the number of samples analyzed Low: the lowest measured value i its associated 2a counting error Average: the average value i the standard deviation of N samples High: the highest measured value i its associatcd 20 counting error Units: the units of measurement Additional information also is presented in Table 5.1. Not all of the results in Table 5.1 are required by the PBNP radiological effluent technical specifications (RETS). Non-RETS items and values are noted by an asterisk (*). For certain analyses, an LLD which is lower than that required by RETS is used. For these analysec, both LLDs are listed with the RETS LLD given in parentheses. Occasionally, anomalous results are obtained which lie well outside of the range of expected values. If, upon investigation, these values are found not to be the result of PBNP operations they will not be listed in the table. In this case, the highest reported value will be footnoted and the omitted value discussed in the narrative portion of this section.
Blank values have not been subtracted from the results presented in Table 5.1.
5.2 Discussion Radiological environmental monitoring conducted at the Point Beach Nuclear Plant from January 1, 1993 through June 30, 1993 consisted of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, vegetation, and TLDs.
All TLD results for the reporting period were within the normal range. Site E-12, located on the discharge flume pier continues l to exhibit some of the lowest values.
l The analyses for individual radionuclides in environmental samples does not reveal any unexpected results. Sr-90 continues to persist in milk and water. Cs-137 continues to persist in milk, water, sediment, fish, algae, vegetation, and soil. These .
radionuclides routinely occur in environmental samples collected around the world. The occurrence of these radionuclides in the environment is attributable to the large scale atmospheric weapons tests of the 1960's, less frequent testing in the 70's and 80's, and to the Chernobyl accident. Tritium concentrations continue to be low.
Measured concentrations of other radionuclides occur as positive and negative values scattered around zero. Although the positive values are usually smaller than their associated error, small, non-zero values (below the associated LLDs) occur for I-131 in milk (1 of 18 samples), I-131, Co-60, Fe-59, and Zr-Nb-95 in water (each 1 of 30 samples). Although the concentration of Zr-Nb-95 in the composite from the discharge flume appears to be a real positive value at 7.1 1 3.6 pCi/1, this value is is not statistically different from typical blank values for this analysis. Blank values for Zr-Nb-95 are 2.4115.02-and 1.50 3.17 pCi/1. Other values also are comparable to the values obtained for " blanks" so that there would be no statistical difference from zero if blank values were subtracted. Therefore, these results appear to be attributable to statistical variations.
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TABLE 5.1 RADIOLOGICAL Ef'VIRONMENTAL MONITORING RESULTS Sample Description LLD N Low Average High Units TLD Environmental Radiation (*) 54 0.40 1 0.03 0.73 t 0.11 1.02 t 0.03 mR/7 days Air Gross beta 0.01 154 0.004 0.002 0.020 1 0.009 0.048 1 0.004 pCi/m' Cs-137 0.01(0.06) 12 -0.000410.0007 0.000010.0002 0.000410.0005 pCi /m' Cs-134 0.05 12 -0.000310.0006 -0.000110.0002 0.000410.0006 pCi/m' I-131 0.03(0.07) 155 -0.017 1 0.021 0.000 i 0.005 0.015 0.015 pCi/m' Other gamma emitters (*) 0.1 ( * ) 12 -0.000310.0008 0.0002 0.0003 0.0005 0.0005 pCi/m' Milk I-131 0.5 18 -0.1010.13 0.08 0.09 0.24 2 0.25 pCi/1 Sr-89 (*) 5 (*) 18 -1.4 1.1 -0.14 1 0.55 0.7 1.1 pCi/1 Sr-90 (*) 1(*) 18 0.9 1 0.4 1.41 1 0.29 1.9 i 0.5 pCi/1 Cs-134 5(15) 18 -2.1 2.2 -0.68 1 1.05 0.3 1 1.8 pCi/1 Cs-137 5(18) 18 -1.2 2.4 1.17 1 0.97 2.7 1 2.4 pCi/1 Ba-La-140 5(15) 18 -3.2 1 2.5 -0.36 1.55 1.8 1 2.6 pCi/1 Other gamma emitters (*) 15 ( * ) 18 -1.8 2.9 0.29 1 1.15 2.2 t 2.6 pCi/1 Lake water Gross beta 4 30 1.6 1 0.5 2.92 1 1.19 7.9 i 0.8 pCi/1 I-131 0.5 (2) 30 -0.13 0.23 0.05 1 0.10 0.29 1 0.23 pCi/1 Mn-54 10(15) 30 -1.7 2.9 -0.05 i 1.02 2.7 1 2.7 pCi/1 Fe-59 30 30 -8.7 i 8.7 +0.95 1 3.38 6.5 i 8.8 pCi/1 Co-58 10 30 -1.7 1 2.5 -0.04 1 0.72 1.1 1 3.0 pCi/1 Co-60 10 30 -0.9 1 1.8 0.54 t 0.98 2.2 i 1.8 pCi/1 Zn-65 30 30 -5.1 1 4.6 -1.12 1 2.35 2.6 i 4.5 pCi/1 Zr-Nb-95 15 30 -4.9 5.2 +0.40 2.54 7.1 3.6 pCi/1 Cs-134 10(15) 30 -8,5 1 2.3 +0.95 i 1.79 1.7 i 2.6 pCi/1 Cs-137 10(18) 30 -1.3 1 1.8 1.07 1.74 7.7 1 2.5 pCi/1 Ba-La-140 15 30 -5.3 i 6.6 +0.59 2.81 6.7 1 6.5 pCi/1 Other gamma emitters (*) 30 (*) 30 -2.0 1 3.0 +0.27 1.12 3.1 1 3.0 pCi/1 H-3 500(3000) 10 102 i 93 I- 1 46 250 1 164 pCi/1 Sr-89 (*) 5 (*) 10 -0.8 1 0.8 -0 2 0.39 0.4 0.7 pCi/1 Sr-90 (*) 1(*) 10 0.3 t 0.3 0.5m + 0.13 0.7 1 0.4 pCi/1 Algae Gross beta 0.25 2 4.33 1 0.27 4.94 1 0.86 5.55 0.37 pCi/g Co-58 0.25 2 -0.02110.033 -0.007 i 0.021 0.008 1 0.028 pCi/g Co-60 0.25 2 +0.01210.030 0.017 i 0.007 0.022 1 0.029 pCi/g Cs-134 0.25 2 -0.05710.029 -0.039 i 0.026 -0.020 1 0.027 pCi/g Cs-137 0.25 2 0.028 0.030 0.042 1 0.020 0.056 0.031 pCi/g 10
i Sarple Description LLD N Low Average High Units Fish Gross beta (*) 0.5 (*) 3 0.30 0.01 1.25 0.89 2.04 1 0.05 pCi/g Mn-54 0.13 3 0.001 0.012 0.00410.004 0.009 0.011 pCi/g Fe-59 0.26 3 -0.018io.028 -0.00710.011 0.008 0.030 pCi/g Co-58 0.13 3 -0.007 0.014 -0.003 0.003 0.00010.011 pCi/g Co-60 0.13 3 0.003 0.011 0.011 0.006 0.01610.010 pCi/g Zn-65 0.26 3 -0.023 0.020 -0.00910.012 0.00210.021 pCi/g Cs-134 0.13 3 -0.013io.009 -0.00410.006 0.00110.007 pCi/g Cs-137 0.15 3 0.00210.010 0.01510.011 0.028 0.010 pCi/g Other gamma emitters (*) 0.5(*) 3 -0.00410.012 -0.00210.003 +0.00210.012 pC1/g
, Well water Gross beta 4 2 1.2 1.7 2.3 1.6 3.4 1 2.2 pCi/1 I-131 0.5 (2) 2 -0.15 i 0.15 -0.01 1 0.21 0.14 0.15 pCi/1 Mn-54 10(15) 2 0.1 2.6 -0.55 1 0.64 1.0 2.7 pCi/1 Fe-59 30 2 1.6 4.8 3.80 3.11 6.0 1 8.1 pCi/1 Co-58 10 2 -1.1 2.7 -0.85 1 2.76 2.8 1 3.1 pCi/1 Co-60 10 2 -0.7 1 3.1 0.60 i 1.84 1.9 1 2.2 pCi/1 Zn-65 30 2 -5.5 1 5.7 -3.75 2.47 -2.0 4.5 pCi/1 Zr-Nb-95 15 2 -3.3 i 3.4 1.45 i 6.72 6.2 5.2 pCi/1 Cs-134 10(15) 2 -4.7 i 2.5 -2.55 1 3.04 -0.4 1 2.3 pCi/1 Cs-137 10(18) 2 1.1 2.5 1.75 0.92 2.4 2.9 pCi/1 Ba-La-140 15 2 -2.4 1 3.6 -0.95 2.05 0.5 1 4.8 pC1/1 Other gamma emitters (*) 30 (*) 2 -0.5 1 2.8 -0.10 i 0.57 0.3 i 2.7 pCi/1 H-3 500 2 -21.4 83.5 -8.9 i 17.7 3.6 i 86.2 pCi/1 Sr-89 (*) 5 (*) 2 -0.1 1 0.4 -0.1 1 0.1 0.0 1 0.4 pCi/1 Sr-90(*) 1(*) 2 0.0 t 0.2 0.1 t 0.1 0.1 0.2 pCi/1 Soil ( *) Gross beta 2 8 13.12 1 2.29 23.94 i 5.92 32.21 3.13 pCi/g Cs-137 0.15 8 0.065 t 0.019 0.038 i 0.158 0.559 i 0.068 pCi/g Shoreline Gross beta 2 5 5.6 1.2 7.4 1 1.3 8.8 1 1.5 pCi/g sediment (*) Cs-137 0.15 5 0.028 i 0.010 0.047 0.017 0.068 1 0.007 pCi/g Vegetation Gross beta (*) 0.25 (*) 8 5.1 0.02 6.33 i 0.93 7.7 1 6.3 pCi/g Cs-134 0.06 8 -0.00310.009 0.001 0.002 0.005 0.008 pCi/g Cs-137 0.08 8 -0.001 0.010 0.013 1 0.029 0.084 1 0.017 pCi/g I-131 0.06 8 -0.006 0.013 0.002 + 0.004 0.005 i 0.024 pCi/g 11
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6.0 NONPADICACTIVE CHEMICAL PELEASES 6.1 Scheduled Chemical Waste Releases
- Scheduled chemical waste releases to the circulating water system from January 1, 1993, to June 30, 1993, included 5.65E+06 gallons cf neutralized wastewater. The wastewater contained 7.63E+02 pounds of suspended solids and 4.03E+05 pounds of dissolved solids.
- Scheduled chemical waste releases are based on the average analytical results obtained from sampling a representative number of neutralizing tanks.
6.2 Miscellaneous Chemical Waste Releases
- Miscellaneous chemical waste releases from the retention pond (based on effluent analyses) to the circulating water for January 1, 1993, to June 30, 1993, included 1.59E+07 gallons of clarified wastewater. The wastewater contained 1.59E+03 pounds of suspended solids.
- Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used for January 1, 1993, to June 30, 1993, included 8.40E+04 pounds of sodium bisulfite and 2.46E+04 pounds of sodium hypochlorite.
7.0 CIRCUIATING WATER SYSTEM CPERATION The circulating water system operation during this reporting period for periods of plant operation is described in Table 7-1.
TABLE 7-1 CIRCULATING WATER SYSTEM OPEPATION January 1, 1993 to June 30, 1993 JAN FU; PAR APR MAY JUN Average Volume Cooling U1 282.2 285. 2 274.7*
- 435.3* 489.6 Water Discharge (Million gal / day) ** U2 282.2 252.2 283.5 345.3 491.9 486.6 Average Cooling Water U1 37 37 36*
- 47* 49 Intake Temperature (Degrees F) U2 37 37 36 40 47 49 Average Cooling Water U1 70 70 67*
- 65* 68 Discharge Temperature (Degrees F) U2 72 72 69 67 67 70 Average Ambient Lake Temperature (Degrees F) 34 34 35 39 44 47
(* Unit I refueling shutdown from March 27, 1993 to May 6, 1993)
(**For days with cooling water discharge flow) 12
8.0 LFAY TESTING OF PADICACTIVE SOURCES During this reporting period, all applicable sealed radioactive sources were leak tested in accordance with Technical Specification 15.4.12.
Leak test resu ts were all <0.005 pCi.
9.0 L4ISCELLANEOUS REPORTING REOUIREMENTS 9.1 Fevisions to the PENP Office Dese Calculation Manual (ODCM) and Process Control Program (PCP)
No revisions were made to either the Environmental Manual or the PCP during this reporting period. The ODCM, which was revised and submitted to the NRC at the end of the last reporting period, took effect on January 1, 1993.
9.2 Interlaboratory Comparison Program The analytical laboratory contracted to perform the radioanalyses of the PENP environmental samples participated in the EPA Interlaboratory Comparison Program during this reporting period.
9.3 Deviations from Specified Environmental Samole Tvoes. Locations, and Freauencies Three air samples, two (2) particulate and one (1) iodine, were missed during this reporting period.
9.4 Summary of Unachievable SDecified Environmental LLDs All LLDs listed in Table 15.7.7-2 of the PBNP Technical Specifications were achieved during this sampling period.
9.5 Special Circumstances No special cirecmstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during this reporting period.
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