ML20138E037
| ML20138E037 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 12/31/1996 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20138E041 | List: |
| References | |
| NUDOCS 9705020021 | |
| Download: ML20138E037 (28) | |
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WISCONSIN ELECTRIC ANNUAL 4
MONITORING REPORT i
JANUARY 1996 through DECEMBER 1996 POWER COMPANY 4
i POINT BEACH NUCLEAR PLANT i
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,1 UNIT NOS.1 AND 2 j
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U.S. Nuclear Regulatory Commission Docket Nos. 50-266 and 50-301 4
Facility Operating License Nos.
pog50$oO!kosooo!66 DPR-24 and DPR-27 R
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k ANNUAL MONITORING REPORT i
January 1,1996 to December 31,1996 l
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i PREFACE l
This Annual Monitoring Report for the period of January 1,1996, through December 31,1996, is submitted in accordance with Point Beach Nuclear Plant Unit Nos. I and 2 Technical Specification 15.7.8.4 and filed under Docket Nos. 50 266 and 50-301 for Facility Operation 1,icense Nos. DPR 24 and DPR-27, respectively.
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TABLE OF CONTENTS 1.0 Radioactive Liquid Releases 3
2.0 Radioactive Airborne Releases 7
3.0 Radioactive Solid Waste Shipments 10 4.0 New and Spent Fuel Shipments and Receipts 11 5.0 Nonradioactive Chemical Releases 12 6.0 Circulating Water System Operation 12 7.0 Leak Testing of Radioactive Sources 13 8.0 Miscellaneous Reponing Requirements 13 9.0 Radiological Environmental Monitoring 13 TABLE OF TABLES Table 1-1 Summary of circulating water discharges 4
Table 1-2 Isotopic composition of circulating water discharges 5
Table 1-3 Subsoil system drains-Tritium Summary 6
Table 1-4 Sewage Sludge Land Application 6
Table 2-1 Radioactive Airborne Release Summary 8
Table 2-2 1sotopic Composition of Airborne Releases 9
Table 31 Quantities and Types of Waste Shipped from PBNP 10 Table 3 2 Estimated Solid Waste Major Radionuclide Composition i1 Table 6-1 Circulating Water System Operation for 1996 12 Table 9-1 PBNP Radiological Environmental Sample Collection Frequency 15 Table 9 2 Radiological Environmental Sampling Locations 16 Table 9-3 PBNP Radiological Environmental Sample Analysis and Frequency 19 Table 9-4 Corrected Radiological Environmental Monitoring Results for 1995 21 Table 9-5 Radiological Environmental Monitoring Results for 1996 25 TABLE OF FIGURES Figure 9-1 Point Beach Nuclear Plant Radiological Environmental Monitoring Program Sites 17 Figure 9-2 Site Map for Point Beach Nuclear Plant 18 2
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1.0 RADIOACTIVE LIQUID RELEASES The total radioactive liquid release, excluding tritium for this reporting period, was 4.82E-02 curies. This included 1.91E-03 curies in processed radioactive waste,1.31E-03 curies in Unit I steam generator blowdown,4.46E-02 curies in Unit 2 steam generator blowdown and 3.49E-04 curies in retention pond effluent.
The total tritium release for this reporting period was 4.19E+02 curies. This included 4.12E+02 curies in processed radioactive waste,1.09E-01 curies in Unit I steam generator blowdown,5.llE+00 curies in Unit 2 steam generator blowdown and 2.09E+00 curies in retention pond emuent.
1.1 Circulatine Water Radionuclide Release Summan-Releases During Current Reporting Period Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curies released on a monthly basis and presented in Table 1-1. Table 1-1 also contains the comparison between the annual Appendix 1 dose limits for liquid emuent and the corresponding highest doses calculated accord'ng to the ODCM using 'he annual isotopic composition of the liquid discharge.
1.2 harig.foapaition of Circulatmg Water Discharges Releases During Current Reporting Period The isotopic composition of circulating water discharges during the current reporting period is presented in Table 12.
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Table 1-1
SUMMARY
OF CIRCULATING WATER DISCHARGE JANUARY 1,1996 TliROUGII DECEMBER 31,1996 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Total Total Activity Released [Cil G-..e Scan plus Fe-55 5.49E-03 516E-03 5.37E-03 5.96E-03 6.59E-03 5.24E-03 3.84E-03 5.03E-03 3 36E-03 1.57E-03 3.90E-04 1.19E-04 4 81E-02 Gross Alpha 2.11 E-06 2.03E-06 3.00E-06 7.14E-06 Treum 5 99E+01 3.08E+01 6.19E+01 2.66E+01 429E+01 2.85E+01 7.55E+00 6.96E+01 3.30E+01 4.49E+01 5.10E+00 811E+00 4.19E+02 Strontium 3 05E-07 2.07E-07 6 07E-06 7.77E46 1.46E-07 3.50E-05 2.07E-06 5.16E-05 Toted Volume Released lgall rwsed Weste 6 21E+04 3.64E+04 1.18E+05 2.59E+05 7.46E+04 6 92E+04 2.96E+04 8 68E+04 4 71E+04 1.49E+0S 7.82E+04 4.3E+04 1.05E+06 U1 Steam Generator Blowdown 2.20E+06 2.09E+06 2.29E+06 8.58E+05 3.56E+06 2.96E+06 2.67E+06 2.68E+06 2.57E+06 2.68E+06 2.56E+06 2.68E+06 2.98E+07 U2 Steam Generator Blowdown 2.64E+06 2.51E+06 2.66E+06 2.58E+06 2.79E+06 2.93E+06 2.85E+06 2.68E+06 2.57E+06 4.21E+05 0.00E+00 0.00E+00 2 46E+07 I
Retenten Pond 2.68E+06 2.52E+06 2 66E+06 2.60E+06 3.88E+06 5.03E+06 4.05E+06 3.85E+06 3.50E+06 2.74E+06 2.14E+06 2.14E+06 3.78E+0i i
Total 7.58E+06 7.16E+06 7.73E+06 6.30E+06 1.03E+07 1.10E+07 9.60E+06 9.30E+06 8.69E+06 5.99E+06 4.78E+06 4.66E+06 9.33E+07
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Volume of Dieuten Water [cc) 3.31E+ 13 3.10E+13 3.31 E+13 3.96E+13 5 45E+13 5 56E+13 5 75E+13 5.75E+13 5.56E+13 5.88E+13 3.54E+13.
i+13 5.46E+14 i
Avg. Diluted Discharge Cone. luCi/cci 5
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G ume Scan plus Fe-55 1.66E-10 1.66E-10 1.62E-10 1.51 E-10 1.21 E-10 9.43E-11 6 67E-11 8.75E-11 6.04E-11 2.67E-11 1.10E-11 3.4 7E-12 8 81E-11 l
Gross Alpha 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.87E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.45E-14 8.4 7E-14 0.00E+00 1.31E-14 Treum 1.81 E-06 9 94E-07 1.87E-06 6.72E-07 7.87E-07 5.13E-07 1.31E-07 1.21 E-06 5.94E-07 7.64E-07 1.44E-07 2.37E-07 7.67E-07 Strontrum 9.21E-15 6 68E-15 1.83E-13 1.96E-13 0.00E+00 0 00E+00 2.54E-15 0.00E+00 0 00E+00 5.95E-13 5.85E-14 0.00E+00 9.45E-14 Men!.;-.. Discherge Conc. luCi/ccl
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Gross Gamma 2.49E-10 3 27E-10 2.02E-10 5.10E-10 2.22E-10 2.01E-10 1.47E-10 1.50E-10 1.99E-10 1.48E-10 1.10E-10 1.72E-10 f
f Trmum 3.79E-05 3.69E-05 4.04E-05 2.48E-05 3.56E-05 4.24E-05 6.15E-06 4.29E-05 ~3.26E-05 2.57E-05 4.10E-06 2.78E-05 Note: Dissolved noble gasses detected in liquid ellluents are included in airborne release totals t
COMPARISON OF 1996 LIQUID EFFLUENT DOSES TO ANNUAL APPENDIX 1 DOSE OBJECTIVES Armuel Limit [mrom]
January-December H6ghest Total Calculated Does [mrom]
% of 10 CFR 50. Appendix t, Dose Objective 6 (whole body) 3.27E-03 (infant) 5.5E-02 F
20 (any organ) 3.46E-03 (infant thyroid) 1.7E-02 t
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e Table I-2 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCIIARGES JANUARY 1,1996 TilROUGli DECEMBER 31,1996 Jan Feb Mar Apr May Jun j
Jul Aug Sep Oct Nov Dec Total isotope
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ H-3 5.99E+ 01 3 08E+01 6.19E+01 2.66E+01 4.29E+01 2.85E+01 7.55E+00 6.96E+01 3.30E+01 4.49E+01 5.10E+00 8.11E+00 4.19E+02 F-18 4.39E-03 4.03E-03 4.51E-03 4.40E-03 4 82E-03 3.97E-03 2.40E-03 3.28E-03 2.33E-03 3.17E-04 1.50E-04 3.46E-02 NA-24 7.52E-05 1.69E-04 1.87E-04 1.17E-04 5.48E-04 MN-54 2.07E-06 2.0 7E-06 CO-57 2.53E-06 1.52E-06 4.0$E-06 CO-58 1.61 E-05 1.07E-05 1.55E-05 1.41E-04 4 40E-05 2.69E-05 2.55E-05 1.72E-05 7.93E-05 5.90E45 2.13E-05 4.57E-04 CO-60 2.16E-05 2.10E-05 6.58E-05 1.37E-04 4.97E-05 1.03E-04 3.44E-05 2.85E-05 1.64E-05 3.16E-05 1.57E-05 5.25E-04 SR-89 1.48E-06 1.48E-06 SR-90 3 05E-07 2.07E-07 6.07E-06 7.77E-06 1.46E-07 3.50E-05 5.92E-07 5 01E-05 NS-97 1.11 E-05 104E-05 5.24E-06 4.97E-06 3.17E-05 ZR-97 4.67E-06 2.07E-06 6.74E-06 TC-99M 1.02E-06 1.02E-06 AG-110M 3.16E-05 6 98E-05 1.10E-05 1.16E-04 1.27E-05 1.46E-05 5.41E-06 8.52E-05 1.10E-04 2.55E-04 5.80E-05 7.95E-05 8.49E-04 SB-125 8.82E-05 7.33E-05 1.62E-04 TE-131 7.68E-05 6.38E-05 1.41E 04 TE-132 1.60E-06 160E-06 CS-137 8.36E-05 2.64E-04 7.53E-05 8 68E-06 3.54E-04 1.26E-05 5.32E-05 3.92E-04 2.80E-04 1.23E-04 2.08E-06 1.65E-03 1-131 1.09E-04 8.37E-05 6.56E-05 1.34E-04 3.92E-04 l-132 1.02E-04 1.02E-04 6-133 8.67E-04 6.50E-04 6.77E-04 9 60E-04 1.07E-03 9.23E-04 1.1eE-03 1.08E-03 8.82E-04 3 54E-04 8 64E-03 Note: Dissolved noble gasses detec:ed in liquid emuents are included in airborne release totals 5
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l 1.3 Subsoil Drain System Releases of Tritium Table 1-3 indicates that there were no tritium releases via the subsoil drain system during 1996.
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SUBSOIL SYSTEM DRAINS - TRITIUM
SUMMARY
hnuary 1,1996 through December 31,1996 I
S1 S3 S9 S10 Total 4
I' First Quarter l
H-3 [uCi/cc]
0.0E+00 0.0E+00 0.0E+00 0.0E+00 i
Ave. Flow [gpd]
4.8E+02 2.4 E+02 0.0E+00 1.3E+04 1.3E+06 second Quarter H-3 [uCi/cc]
0.0E+00 0.0E+00 0.0E+00 0.0E+00 Ave. Flow [gpd]
1.8E+04 3.0E+03 9 OE+01 8.8E+03 2.7E+06 Third Quarter H-3 [uCi/cc]
0.0E+00 0.0E+00 0.0E+00 0.0E+00 Ave. Flow [gpd]
2.2E+03 1.0E+03 4.8E+02 2.1 E+ 04 2.3E+06 Fourth Quarter H-3 [uCi/cc]
0.0E+00 0.0E+00 0.0E+00 0.0E +00 Ave. Flow [gpd]
1.0E+04 1.6E+03 0.0E+00 1.9E+04 2.9E+06 Annual Totals Released {Ci]
0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Flow [ gal]
2.8E+06 5.4E+05 5.2E+04 5.7E+06 9.1 E+06 1.4 I and Annlication of Sewage Sludge The Wisconsin Department of Natural Resources has approved the land-application of sewage sludges on various Wisconsin Electric Power Company properties surrounding the Point Beach Nuclear Plant. These sewage sludges, which may contain trace amounts of radionuclides, are applied in accordance with methodologies approved on January 13,1988, pursuant to 10 CER 20.302(a). The amounts discharged in the sewage during this reporting period are presented in Table 1-4.
TABLE l-4 SEWAGE SLUDGE LAND APPLICATIONS January 1,1996 through December 31,1996 Date of AnnlicaliQn Gallons Site Activity Released iCil June 28.1996 12,600 PB-02
<MDA October 1,1996 5,400 PB-02
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2.0 RADIOACTIVE AIRBORNE RELEASES The release paths contributing to radioactive airborne release totals during this reporting period were the l
auxiliary building vent stack, drumming area vent stack, gas stripper building vent stack, Unit I containment purge stack, Unit 2 containment 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 Radioactivs Airborne Release Summarv e
Radioactivity released in airborne effluents 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 i
atmospheric effluents to the highest organ dose and the noble gas doses calculated using ODCM methodology.
k 2.2 1sotonic Airborne Releases 1he monthly isotopic airborne releases for 1996 are preser.ted in Table 2.
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TABLE 2-1 RADIOACTIVE AIRBORNE RELEASE
SUMMARY
JANUARY 1,1996 TilROUGil DECEMBER 31,1996 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Total Total Noble Gemees [CQ [1]
1.05E-01 1.01E-01 1.41E-01 2.15E+00 2.12E-01 3.23E-01 1.52E-C1 1.41 E-01 3.80E-01 1.93E+00 5.90E-02 1.64E+00 7.33E+00 Total Radiolodines [CQ 0.00E+00 0 00E+00 8.60E-06 4 89E-06 9.58E-05 1.35E-05 1.28E-07 1.36E-06 0.00E+00 110E-04 0.00E+00 0.00E+00 2.54E-04 Total Particulates [CI) 5.78E-08 6 99E-07 3.47E-05 1.18E-06 1.84E-04 2.71E-08 8.52E-07 5.33E-06 1.10E-06 6 43E-08 3.31E-07 2.78E-07 2.28E-04 Alphe [CQ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.89E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.86E-09 3.2SE-09 2.78E-07 2.88E-07 Strontium [CQ 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.93E-06 2.46E-08 1.56E-08 0.00E+00 0.00E+00 0 00E+00 5.95E-08 All Others [CQ 5.78E-08 6 99E-07 3.4 7E-05 1.18E-0G 1.84E-04 2.71E-08 8.32E-07 5.31 E-06 1.08E-06 6.24E-08 3.28E-07 0.00E+00 2.28E-04 Total Tritium [CQ 4 80E+00 3 99E+00 7.05E+00 1.52E+01 3.71E+00 4.11E+00 3.44E+00 1.57E+00 4.22E+00 1.08E+01 5.54E+00 8.62E+00 7.31E+01 Max l0#.y Roteese [CWeec) 2.93E-09 7.12E-07 8 46E-07 2.00E-06 1.20E-05 1.18E-06 l 7.11E-07 1.04E-06 1.35E-06 4 67E-05 1.05E-05 1.11E-06 l
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[1] Includes noble gas contribution from liquid releases.
COMPARISON OF 1996 EFFLUENT DOSES TO APPENDIX I DOSE OBJECTIVES Ca;wi Amnest Appendet i Deee Obpective Jassary-Decessber Calculated Door lmresml Percent of Appendit i Dose Othective Particatete 30 mrem / organ iAIE-02 4.7E-02 Noble Gas 40 mrad (p air) 1.23E-03 3.I E-03 Noble Gas 20 mrad (y arr) 2.36E-03 1.2E-02 Noble Gas 30..
.- (skin) 1.57E-03 5.2E-02 Nebte Gas lo m sm (whole body) 2.86E-03 2.9E-02 i
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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Total W ope
[CQ
[CQ
[CQ (CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ
[CQ H-3 4 80E+00 3.99E+00 7.05E+00 1.52E+01
- 3. 71 E+00 4.11 E+00 3.44E+00 1.57E+00 4.22E+00 1.08E+01 5.54E+00 8.62E+00 7.31E+01 l
F-18 3.34E-05 1.89E-05 5.81 E-07 5 27E-06 5.82E-05 NA-24 4.03E-05 4.03E-05 CO-58 3 4/E-08 1.89E-08 6.05E-08 1.14E-07 CO-60 3 84E-07 1.08E-06 1.46E-06 BR-82 8.93E-10 6.62E-10 4.49E-10 9.82E 10 1.91 E-09 1.21 E-09 6.11E-09 SR-90 1.93E-06 2.46E-08 1.56E-08 5.95E-06 TC-99M 1.07E-06 3 27E-07 1.40E-06 CE-141 2.03E-07 2.03E-07 CE-144 2.51 E-07 2.51 E-07 TE-132 613E-08 6.13E-08 CS-137 5.78E-08 6 98E-07 2.42E-07 8.31 E-07 1.24E-04 3.85E-08 1.24E-07 1.26E-04 CS-138 2.64E-08 2.64E-08 l-131 4 89E-06 2.94E-05 1.02E-06 1.28E-07 5.21E-07 3 60E-05 i-132 6.37E-08 1.30E-04 1.30E-04 I
l-133 8 60E-06 6 63E-05 1.25E-05 8.40E-07 8.82E-05 AR-41 7.26E-02 6.98E-02 8 93E-02 6.43E-01 8.70E-02 1.46E-01 8.22E-02 7.95E-02 1.17E-01 2.31 E-01 3.83E-02 1.83E-01 1.84E+00 KR-85 0.00E+00 1.70E-02 1.94E-02 7.49E-03 1.55E-02 0.00E+00 1.75E-02 1.03E-02 7.34E-03 6.35E-03 3 63E-03 1.05E-01 I
KR-85M 1 84E-OS 1.73E-04 1.04E-03 5.00E-02 3.59E-03 6.31E-03 2.31E-03 6.27E-04 8.78E-03 5 06E-02 2.85E-09 6.26E-02 1.86E-01 KR-87 4.12E-05 4.16E-04 2.51 E-03 9.94E-02 8.23E-03 1.49E-02 4.23E-03 1.49E-03 2.11E-02 121E-01 6.87E-09 1.38E-01 4.11 E-01 KR-88 4.53E-05 4.19E-04 2.58E-03 1.05E-01 8 83E-03 1.59E-02 4.43E-03 1.55E-03 2.21 E-02 1.31E-01 7.06E-09 1.49E-01 4.41 E-01 XE-133 2.91E-02 1.03E-02 7.76E-03 3 97E-01 1.81 E-02 2.68E-02 2.30E-02 2.71E-02 3.40E-02 3.59E-01 1.43E-02 3.24E-02 9 79E-01 XE-133M 1.42E-03 6 01E-06 0.00E+00 1.00E-02 5.39E-03 8.47E-04 9.34E-05 7.16E-05 5.3d E-04 7.63E-04 5.80E-11 5.14 E-03 2.43E-02 XE-135 1.05E-03 7.94E-04 5.05E-03 2.25E-01 1.85E-02 2.97E-02 9.77E-03 4 69E43 4.17E-02 2.85E-01 1.31E-08 2.82E-01 9.03E-01 XE-135M 5 39E-05 5.48E-04 3.24E-03 1.57E-01 1.15E-02 1.95E-02 5.97E-03 1.93E-03 2.92E-02 1.72E-01 9.32E-09 1.84E-01 5.85E-01 XE-138 1.75E-04 1.70E-03 101E-02 4.57E-01 3.51 E-02 6.35E-02 2.03E-02 6.45E-03 9.51 E-02 5 68E-01 2.93E-08 5 99E-01 1.86E+00 1
3.0 RADIOACTIVE SOLID WASTE SIIIPMENTS 3.)
Tyne. volume. and activity of shinped solid waste The following types, volumes, and activity of solid waste was shipped from PBNP for offsite disposal or burial during 1996. No irradiated fuel was shipped offsite. The volume, activity, and type of waste is listed in Table 3-1.
Table 3-1 QUANTITIES and TYPES of WASTE SillPPED from PBNP Tyne of waste Units Ouantity A. Spent resins, filter sludges, evaporator m'(ft') 2.21E+01 (7.80E+02) bottoms, etc.
Ci 1.51 E+02 B. Dry compressible waste, contaminated m'(ft') 1.31E+01 (4.63E+02) equip, etc.'
Ci 1.16E+00.
C. Irradiated components, control None.
1 rods, etc.
D. Other(describe)
None.
' Volume after incineration or compaction 3.2 Maior nuclide compmition (by tvne of waste)
The major radionuclide content of the solid waste was determined by gamma isotopic analysis and by scaling to certain indicator radionuclides based on the measured isotopic content of representative waste stream samples. The estimated isotopic content is presented in Table 3-2 in decreasing order of activity.
3.3 Solid Waste Disnosition There were fourteen (14) solid waste solid waste shipments from PBNP to Barnwell, SC via truck.
Six shipments went directly to Barnwell. Eight were sent for compaction or other treatment prior to being shipped to Barnwell by the vendor. Shipments were made on the dates listed below.
Directly to Barnwell: 8/4/96,10/15/96,10/22/96, i1/5/96,12/19/96, and 12/20/96.
To Scientific Ecology Group for volume reduction prior to shipment to Barnwell: 4/10/96, 7/12/96,10/18/96,11/1/96, and 12/2/96.
To Frank W.11ake for scrap metal decontamination (only the contamination sent to Barnwell):
10/1/96,10/17/96, and i1/9/96.
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TABLE 3-2 ESTIMATED SOLID WASTE MAJOR RADIONUCLIDE COMPOSi ti N Type A Type B Snent resins. filter sludges etc.
Dry comnressible waste. etc.
Nuclide Percent Nuclide Percent Name Abundance Name Abundance Ni-63 2.77E+01 Fe -55 3.43E+01 Co-60 2.67E+01 Ni-63 2.54E+01 Fe-55 2.22E+01 Co-60 1.96E+01 Co-58 1.46E+01 Cs-137 9.56E+00 Cs-137 3.19E+00 Co 58 5.39E+00 Sb-125 1.85E+00 Sb-125 2.27E+00 Ag11Om 1.34E+00 C-14 1.67E400 Mn 54 1.15E+00 Ag 110m 1.20E+00 C-14 4.98E-01 Pu-241 5.44E-01 113 1.75E-01 Sr-90 6.70E-01 Co-57 1.65E-01 Nb-95 4.80E-02 Pu-241 1.57E-01 Am-241 2.50E-02 Nb-95 1.15E-01 Zr-95 2.40E-02 Zr-95 8.40E-02 Cm-243/244 1.30E-02 Sb-124 7.40E-02 Pu-239/240 1.00E-02 Sr-90 5.90E-02 Pu 238 9.00E-03 t
Sn-113 5.10E-02 Cs 134 8.00E-03 Nb-94 3.90E-02 11-3 6.00E-03 Cr-51 2.40E-02 Zn 65 3.00E-03 Zn-65 1.80E-02 Mn-54 3.00E-03 i
Ni-59 1.40E-02 Cm-242 1.00E-03 Cs-134 9.00E-03 Ce-144 1.00E-03 Ce-144 6.00E-03 Am 241 6.00E-03 Fe-59 5.00E-03 Cm-243/244 4.00E-03 Pu-238 3.00E-03 Pu-239/240 2.00E-03 Cm-242 1.00E-03 4.0 NEW AND SPENT FUEL SHIPMENTS AND RECEIPTS During 1996 a total of 52 new fuel assemblies were received from Westinghouse Electric Corporation.
Thirty-two (32) were received in March for the Unit I refueling and 20 were received in October for the Unit 2 refueling.
There were no spent abel shipments made from Point Beach Nuclear Plant during this reporting period.
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5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1,1996, to December 31,1996, included 8.19E+06 gallons of neutralized wastewater. The wastewater contained 3.05E+02 pounds of suspended solids and 6.89E+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.
5.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases from the retention pond (based on efiluent analyses) to the circulating water for January 1,1996, to December 31,1990, included 3.78E+07 gallons of clarified wastewater. The wastewater contained 1.95E+03 pounds of suspended solids.
Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1,1996, to December 31,1996, included 2.51E+05 pounds of sodium bisulfite and 7.32E+04 pounds of sodium hypc. chlorite.
6.0 CIRCULATING WATER SYSTEM OPERATION The circulating water system operation during this reporting period for periods of plant operation is described in Table 6-1.
Table 6-1 CIRCULATING WATER SYSTEM OPERATION FOR 1996 UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling i
282.2 282.2 282.2 268.0' 464.9 489.6 Water Discharge [Mgal/ day]'
2 282.2 279.2 282.2 348.1 459.4 486:6 Average Cooling Water 1
37 36 35 44' 45 49 Intake Temperature ['F]
2 37 36 35 40 45 49 Average Cooling Water 1
72 70 67 60' 66 69 Discharge Temperature ['F1 2
77 67 66 64 65 69 Average Ambient Lake 33 34 3$
39 44 48 Temperature ['F)
' Unit I refueling shutdown from April 1,1996 to April 22,1996
' For days with cooling water discharge flow 12
Table 6-1(continued)
CIRCULATING WATER SYSTEM OPERATION FOR 1996 UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling 1
489.6 490.1 489.6 501.3 311.0 291.8 Water Discharge [Mgal/ day]'
2 489.6 48'8.9 489.6 397.5' 0'
234.2' Average Cooling Water 1
52-56 62 47 37 35 Intake Temperature [*F]
2 52 56 62 47' 34' Average Cooling Water 1
72 76 82 65 67 65 Discharge Temperature ['F]
2 71 75 81 60' 34' Average Ambient Lake 50 54 61 46 37 35 Temperature ['F]
l Unit 2 refueling shutdown from October 7,1996 through December 31,1996 5 For days with cooling water discharge flow 7.0 LEAK TESTING OF RADIOACTIVE SOURCES During this reporting period, all applicable sealed radioactive sources were leak tested in accordance with Technical Specification 15.4.12. Leak test results were all <0.005 pCi.
8.0 MISCELLANEOUS REPORTING REQUIREMENTS 8,1 Revisions to the PBNP Office Dose Calculation Manual (ODCM) and Process Control Procram (PCP)
There were no revisions to either the Environmental Manual or the ODCM during 1996.
8.2 Interlaboratory Comnarison Procram The analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples participated in the EPA Interlaboratory Comparison Program during this reporting period.
8.3 Special Circum =tances No special circumstances repon regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 1996.
9.0 RADIOLOGICAL ENVIRONMENTAL-MONITORING PROGRAM (REMP) 9.1 Introduction
'Ihe REMP results in this Annual Report are presented in the new format which was initiated with the January - June 1992 Semiannual Monitoring Report. Results are reported directly as 13
1 l
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 Report HPSR 1 (1980) released as document EPA 520/1-80-012.
9.2 Obiective The objective of the PBNP REMP is to fulfill the requirements of 10 CFR 20.1302, PBNP General Design Criterion (GDC) 17, GDC 64 of Appendix A to 10 CFR 50, and Sections IV.B.2 and IV.B.3 of Appendix 1 to 10 CFR 50. Therefore, the REMP collects samples from various environmental media in order to provide data on measurable levels of radiation and radioactive materials in the principal pathways of environmental exposure.
t For the water exposure pathway, the samples include water as well as the biological integrators, fish and filamentous algae. Because of their migratory behavior, fish are wide area integrators. In l
contrast, the filamentous algae periphyton are attached to shoreline rocks and concentrate nuclides from the water flowing by their point of attachment.
De air-grass-cow-milk exposure pathway is important because of the many dairy farms around PBNP. Therefore, the REMP includes samples of air, general grasses, and milk in the PBNP environs.
For the measurement of the levels of ambient environmental radiation that may be afTected by direct radiation from PBNP, the REMP employs a series of TLDs which situated around PBNP.
9.3 Samnline Parameters Samples are collected at the frequency indicated in Table 9-1 from the locations described in Table 9-2 and shown in Figures 9-1 and 9-2. Because of weather and air sample pump malfunctions, the following deviations from the scheduled sampling and frequency occurred:
9.3.1 No particulate air samples or radioiodine samples were obtained because the air pumps were found inoperable in the field at E-01, E-02, E-03, and E-08 on 5/28,6/4,10/1, and 10/15, respectively.
9.3.2 The fourth quarter TLDs at E-3,-5,-9, 12,-22,-23, and -31 were lost in the field due to weather. New TLD holders have been obtained for fastening these monitors to poles and other structures.
9.4 Ansluical Parameters he types of analyses and their frequencies are given in Table 9-3. The LLDs for the various analyses are found in Table 9-5 with the summary of the REMP results. All LLDs listed in Table 15.7.7-2 of the PBNP Technical Specifications were achieved during 1996.
9.5 Correction to lo95 REMP Summary Results in the Annual Monitoring Report for 1995, the summary table from the July 1 - December 31,1994 Semiannual Monitoring Report was accidentally substituted for the January 1 December 31,1995 summary table (Table 9-4). The correct summary table is presented here in Table 9-4.
Also, the corresponding discussion is repeated from the 1995 Report for the sake of clarity.
14
-.~ -
I i
TABLE 9-1 PBNP RADIOLOGICAL ENVIRONMENTAL SAMPLE COLLECTION FREQUENCY j
Samnle Tyne Ramnle Codes Collection Frecuency Environmental Radiation Exposure E-01, -02, -03, -04, -05, Quarterly f
-06, -07, -08, -09, -12,
-14. 15, 16 17,-18, 20,-22. -23, -24, -25,
-26,-27. 28 29,-30,
-31. -32 Vegetation E-01, -02, -03, -04, -06, 3x/yr as available
-08,-09,-20 1
Algae E4)S, -12 3x/yr as available Fish E-13 3x/yr as available i
Well Water E-10 Quarterly Lake Water E-01, 06, -09, -12 E-12 collected weekly for monthly composite. Others collected
(
- monthly, l
J Milk E-11, -19, -21 Monthly i
Air Filters E-01, -02, -03, -04, -08, Weekly particulate filters and charcoal
-20 canisters by continuous air
- sampler, Soil E-01, 03, -04, -06, 2x/yr
-08,-09,-20 Shoreline Sediment E-01, -05, -06, -09, -12 2x/yr 4
0 15 l
a TABLE 9-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS I ev ntinn Code 11 ration Descrintion E-01 Meteorological Tower E-02 Site Boundary Control Center - East Side of Building E-03 Tapawingo Road, about 0.4 Miles West of Lakeshore Road E-04 North Boundary E-05 Two Creeks Park E-06 Point Beach State Park - Coast Guard Station E-07 WPSC Substation on County Rt. V, about 0.5 Miles West of Hwy. 42 E-08 G. J. Francar Property, at the Southeast Corner of the Intersection of Hwy 163 and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well
[
E-Il Dairy Farm (W. Funk), about 3.75 Miles West of Site E-12 Discharge Flume / Pier E-13 Pumphouse E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-15 Southwest Corner of Site E 16 WSW, Hwy. 42, Bishop Residence, about 0.25 miles North of Nuclear Road E-17 North of Mishicot, Hwy.163 and Assman Road, Northeast Corner of Intersection E-18 Nonhwest of Two Creeks at Zander and Tannery Roads E-19 Local Dairy Farm, about 0.2 miles West of Hwy. 42 on the North Side of Two Creeks Road (L. Engelbrecht)
E-20 Reference location,17 miles Southwest, at Silver lake College E-21 Local Dairy Farm just South of Site (L. Strutz) on Lakeshore and Irish Roads E-22 West Side of Hwy. 42, about 0.25 miles North of Johanek Road l
E-23 Greenfield Lane, about 4.5 Miles South of Site,0.5 Miles East of Hwy. 42 E-24 North Side of County Rt. V, near intersection of Saxonburg Road E-25 South Side of County Rt. BB, about 0.5 miles West of Norman Road E-26 804 Tapawingo Road, about 0.4 miles East of Hwy.163, North Side of Road E-27 Intersection of Saxonburg and Nuclear Roads, Southwest Corner, about 4 Miles WSW E-28 Nature Trail sign in parking lot on West side of EIC.
E-29 On tree on bluff overlooking Lake Michigan NE of Microwave Tower and due East of MET l
Tower.
E-30 NE corner at Intersection of Tapawingo and Lakeshore Roads.
E-31 On utility pole Nonh side of Tapawingo Road closest to the gate at the West property line.
E-32 On a tree located at the junction of property lines, as indicated by trees and shrubs, about 1000 feet east of the west gate on Tapawingo Road and about 1200 feet south of Tapawingo Road. The location is almost under the power lines between the blue and gray transmission towers.
E TC Transportation Control; Reserved for TLDs i
l 16
FIGURE 9-1 sac an e I ur 9' /
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POINT BEACH NUCLEAR PLANT
' La RADIOLOGICAL ENVIRONMENTAL
/r statu PONITORING PROGRAM SITES statt
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1j ENVIRONMENTAL MONITORING STATIONS 11
$ TLD
@ TLD 4 AIR A a OTHER ru. a c 18
I I
TABLE 9-3 PBNP RADIOLOGICAL ENVIRONMENTAL SAMPLE ANALYSIS AND FREQUENCY Ramnle Tyne Ramnle Codes Analyses Frecuency
~
Environmental Radiation E-01, -02, -03, -04, -05 TLD
. Quarterly -
Exposure
-06,-07,-08,-09,-12
-14, -15, -16, -17, -18, 1
-20, -22, 24,-25, 26,-27,-28,-29,-30,
-31, -32, -TC Vegetation E-01, -02, -03, -04, -06, Gross Beta 3x/yr as available
-08,-09,-20 Gamma Isotopic Analysis Algae E-05, -12 Gross Beta 3x/yr as available Gamma Isotopic Analysis Fish E-13 Gross Beta 3x/yr as available Gamma Isotopic Analysis (Analysis of edible portions only)
Well Water E-10 Gross Beta, H-3 Quarterly St-89, 90, I-131 Gamma Isotopic Analysis (on total solids)
Lake Water E-01, -05, -06, -09, Gross Beta Monthly
-12 H-3, Sr-89, 90 Quarterly composite of monthly collections I-131 Monthly Gamma Isotopic Analysis Monthly (on total solids)
Milk E-11, -19, -21 St-89, 90 Monthly 1-131 Gamma Isotopic Analysis l
Air Filters E-01, -02, -03, -04, Gross Beta Weekly (particulate)
-08,-20 I-131 Weekly (charcoal)
Gamma Isotopic Analysis Quarterly (on composite particulate filters)
Soil E41, -02, -03, -04, Gross Beta 2x/yr
-06,-08,-09, 20 Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -09, -12, Gross Beta 2x/yr
-33 Gamma Isotopic Analysis 19
_._._ 7 l
9.5.1 Sum==rv of 1995 REMP Reculte A summary of the REMP results for 1995 are presented in Table 9-4. The table contains the following information:
Sample: the type of the sample medium
==
Description:==
the type of measurement i
LLD:
the a priorilower limit ofdetection
)*
N:
the number of samples analyzed l
Low:
the lowest measured value
- its associated 2s counting error i
Average:
the average value
- the standard deviation of N samples High: the highest measured value
- its associated 2s counting error Units: the units of measurement l
Additional information also is presented in Table 9-4. Not all of the results in Table 9-4 l
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 analyses, 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. These results will be investigated I
and discussed in the narrative portion of this section. Blank values have not been subtracted from the results presented in Table 9-4.
9.5.2 Divn=cian for 1995 Recnin For the sake of continuity and clarity, the discussion for the 1995 results is repeated below to correspond to the insertion of the corrected summary table for the 1995 results.
Radiological environmental monitoring conducted at the Point Beach Nuclear Plant from January 1,1995 through December 31,1995 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 fiume pier continues to exhibit some of the lowest values whereas E-32, approximately 1 mile west of the plant, continues to exhibit some of the highest. The higher values at E-32 have been noted since TLDs were first located at this site. The reason for this result is not known and continues to be tracked. However, during 1995 the TLD results at E-32 have been lower than in the previous years. Herefore, the difTerences between TLD results from E-32 and from sites E-3 and E-31, located about 1200 feet north of E 32 at about the same distance from the plant, which typically have been 0.1 - 0.4 mR/ week, were only 0.1 - 0.2 mR/ week in 1995.
I ne analyses for individual radionuclides reveals that Sr-90 and Cs-137 continue to occur in environmental samples. Sr-90 continues to persist in milk and lakewater. Cs 137 occurs in shoreline sediment deposits, fish, algae, vegetation, and soil. These radionuclides routinely occur in environmental samples collected around the world and are attributable to the large scale atmospheric weapons tests of the 1960's and the less frequent testmg in the 70's and 80's, and as well as to the Chernobyl accident. The highest Cs-137 concentradons in soil occurs at E-06, the Point Beach State Forest. His occurs because campfire ashes, from trees which incorporated fallout Cs-137 in the 20 1
i I
..-7a-
TABLE 9-4 CORRECTED RADIOLOGICAL ENVIRONMENTAL MONITORING RESULTS FOR 1995 sample Description LLD N
Low Average Righ Units TLD Environmental Radiation
(*)
108 0.62 1 0.03 0.87 1 0.13 1.19 i 0.07 mR/7 days Air Gross beta 0.01 318 0.008 i 0.002 0.022 i 0.007 0.044 1 0.004 pCi/m' Cs-137 0.01(0.06) 24
-0.000810.0005
-0.000010.0003 0.000710.0006 pCi/m' Cs-134 0.05 24
-0.001010.0004
-0.000010.0004 0.000710.0008 pCi/m' I-131 0.03(0.07) 318
-0.023 1 0.017 0.000 1 0.007 0.019 i 0.015 pCi/m' Other gamma emitters (*)
0.1(*)
24
-0.0003to.0011 0.0002io.0002 0.000720.0004 pCi/m' Milk I-131 0.5 36
-0.1310.13 0.04 2 0.09 0.20 1 0.26 pCi/1 Sr-89 ( *)
5(*)
36
-2.1 1 1.0
-0.1 1 0.5 0.5 1 0.6 pCi/1 Sr-90 ( * )
1(*)
36 0.6 1 0.5 1.4 1 0.4 2.4 1 0.5 pCi/1 Cs+134 Sil5) 36
-2.4 i 2.6 0.2 i 1.0 2.1 2 2.8 pCi/1 Cs-137 5(18) 36
-1.9 i 2.8 0.4 i 1.1 3.4 i 2.8 pCi/1 Ba-La-140 5(15) 36
-3.9 i 3.8
-0.3 1 1.0 1.4 1 3.1 pCi/1 Other gamma emitters (*)
15(*)
36
-1.9 1 3.2 0.3 1 1.4 2.7 1 4.0 pC1/1 Lake water Gross beta 4
60 1.5 1 0.5 2.5 i 0.8 4.6 i 0.6 pCi/1 1-131 0.5 (2) 60
-0.3020.12 0.05 i 0.10 0.31 t 0.31 pCi/1 Mn-54 10(15) 60
-2.2 i 2.0
-0.0 2 0.9 2.9 i 3.2 pCi/1 Fe-59 30 60
-4.4 i 8.2 0.0 1 2.0 4.7 1 7.6 pCi/1 Co-58 10 60
-1.5 2 2.2 0.2 i 1.0 3.0 3.1 pCi/1 Co-60 10 60
-3.2 2 2.5 0.4 2 1.1 2.7 i 3.3 pC1/1 Zn-65 30 60
-8.1 i 6.5
-0.3 2 2.5 4.8 i 5.0 pCi/1 Zr-Nb-95 15 60
-4.2 i 5.7
-0.4 i 1.2 2.5 1 3.6 pCi/1 Cs-134 10(15) 60
-2.7 1 2.3 0.3 2 1.4 5.0 t 3.8 pCi/1 Cs-137 10(18) 60
-3.2 i 3.7 0.4 1 1.1 2.3 i 3.1 pCi/1 Ba-La-140 15 60
-16.9 i 20.2
-0.4 1 3.5 6.6 i 7.5 pCi/1 Other gamma emitters (*)
3 0 ( *)
60
-6.3 1 3.9
-0.6 i 1.5 4.1 i 4.3 pCi/1 H-3 500(3000) 20 66 i 78 543 i 1201 5450 1 210 pCi/1 Sr-89(*)
5(*)
20
-1.3 2 0.9
-0.3 2 0.5 0.3 i 0.8 pCi/1 Sr-90(*)
1(*)
20 0.3 1 0.3 0.9 i 1.2 1.641 0.5 pCi/1 Algae Gross beta 0.25 6
2.55 1 0.19 3.33 i 0.57 4.24 1 0.94 pC1/g Co-58 0.25 6
-0.00210.007 0.016 1 0.017 0.043 i 0.021 pCi/g Co-60 0.25 6
0.00410.010 0.013 2 0.010 0.029 i 0.028 pCi/g Cs-134 0.25 6
-0.00620.027 0.001 1 0.004 0.006 i 0.010 pCi/g Cs-137 0.25 6
0.01210.008 0.050 t 0.029 0.081 1 0.022 pC1/g 21
TABLE 9-4(continued)
CORRECTED RADIOLOGICAL ENVIRONMENTAL MONITORING RESULTS FOR 1995 Sample Description LLD N
Low Average High Unite Fish Gross beta (*)
0.5(*)
12 0.30 1 0.02 2.18 i 0.69 2.96 i 0.10 pCi/g Mn-54 0.13 12
-0.00810.006 0.00110.003 0.005t0.012 pCi/g Fe-59 0.26 12
-0.01110.023
-0.00010.008 0.01010.014 pCi/g Co-58 0.13 12
-0.00810.010 0.00210.003 0.002 0.013 pCi/g 1
Co-60 0.13 12
-0.005t0.012 0.00410.005 0.01310.017 pCi/g 2n-65 0.26 12
-0.02010.029 0.00410.009 0.01510.024 pCi/g Cs-134 0.13 12
-0.00210.006
-0.002io.003 0.007t0.008 pCi/g Cs-137 0.15 12 0.01010.014 0.05210.042 0.177 0.027 pCi/g 1
Other gamma emitters (*)
0.5(*)
12
-0.00510.015
-0.00010.003 0.00410.014 pCi/g Well water Cross beta 4
4
-1.3 1 1.9 1.6 t 2.3 4.1 i 1.6 pCi/1 1-131 0.5(2) 4 0.02 1 0.12 0.09 1 0.11 0.25 1 0.25 pCi/1 Mn-54 10(15) 4
-1.1 i 1.5
-0.0 i O.7 0.5 i 1.6 pCi/1 Fe-59 30 4
-2.3 1 4.4
-0.2 i 1.7 1.6 1 3.6 pCi/1 Co-58 10 4
-0.9 i 1.9 0.2 i 1.0 1.2 i 1.2 pCi/1 Co-60 10 4
0.1 i 1.4 0.6 1 0.7 1.6 i 1.9 pCi/1 Zn-65 30 4
-2.1 i 3.0
-0.7 i 1.1 0.6 i 3.4 pCi/1 Zr-Nb-95 15 4
-0.7 1 3.3 0.0 i 1.0 1.5 i 3.1 pC1/1 8
Cs-1?4 10(15) 4
-0.3 i 1.3 0.2 0.5 0.6 i 1.8 pCi/1 Cs-117 10(18) 4
-1.8 1 2.0
-0.4 i 1.3 1.1 i 1.8 pCi/1 Ba-La-150 15 4
-3.9 i 10.8
-0.7 1 2.3 1.0 t'2.3 pCi/1 other gamma er.itters (*)
30 (*)
4
-2.2 i 2.1
-0.7 i 1.2 0.6 i 1.4 PCi/1 H-3 500 4
-64.1 i 80.7
-10.2 i 46.1 39.9 i 75.9 pCi/1 Sr-89(*)
5(*)
4
-0.04 1 0.42 0.27 1 0.24 0.53 1 0.47 pCi/1 I
Sr-90(*)
1(*)
4 0.17 1 0.17 0.10 1 0.13 0.23 1 0.40 pCi/1 Soil (*)
Gross beta 2
16 11.7 i 2.2 18.9 i 4.9 26.8 i 3.0 pCi/g Cs-137 0.15 16 0.043 1 0.015 0.296 1 0.189 0.673 i 0.049 pCi/g Shoreline Gross beta 2
10 3.5 i 1.2 7.10 2 2.71 11.7 i 2.20 pCi/g I
sediment (*)
Cs-137 0.15 10 0.C26 1 0.013 0.037 1 0.006 0.045 1 0.014 pCi/g m
Vegetation Gross beta (*)
0.25(*)
24 3.111 0.11 5.32 i 1.24 8.60 1 0.29 pCi/g Cs-134 0.06 24
-0.01410.016 0.002 1 0.006 0.011 1 0.015 pCi/g f
Cs-137 0.08 24
-0.01310.015 0.009 i 0.025 0.119 1 0.024 pCi/g I-131 0.06 24
-0.013 0.027 0.003 1 0.009 0.020 t 0.024 pCi/g 1
1 D
b I
g f
22 i
[
i 1960s, is being scattered around various camp sites in the area. The occurrence of Cs-137 in tree ash has been observed in other areas of the United States.
Lake water tritium concentrations continue to be low. These samples are composited monthly for quarterly analysis. Most of the results are in the 100 - 250 pCi/l range.
Three of the H-3 results are in the 950 - 5500 pCi/l range. Two of these results were obtained approximately 1.7 and 4 miles north of PBNP with the highest concentration the furthest north. The predominant current along this side of Lake Michigan is from north to south which indicates that PBNP is not the likely source of these elevated H-3 concentrations. One composite result of 1348 pCi/l from the discharge canal, E-12, included a monthly sample taken at the same time as a holdup tank was being discharged in November. Analyses of the monthly samples showed that the October and December i
H-3 concentrations were less than 175 pCi/l whereas the November concentration from the discharge canal was 3900 pCill. Over the past two years, tritium blanks have yielded results in the range of-74.6 80.5 to 148
- 101 pCi/1. Only the H-3 results from E-01 for the tirst quarter of 1995 and from E-12 for the 4th quarter appear to be attributable to PBNP discharges. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a natually occurring radionuclide.
All of the isotopic well water results are small positive and negative values indistinguishable from zero. Only the gross beta results, which are attributable to naturally occurring radionuclides, are significantly positive.
For the remaining suite of RETS specified radionuclides, measured concentrations 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) whose *2s error does not overlap me occur for Co-58 and Co-60 in algae. These cobalt concentrations are low, two to four times lower than the Cs-137 concentrations which are the result of fallout which circulates through the Lake Michigan ecosystem.
The October Co-60 concentration is about two times the 2e counting error at E-05 (0.023 10.012), about 1.7 miles north of PBNP. This also occurs for Co-58 at the same site in both the August and October samples (0.017 i 0.011 and 0.043 i 0.021) and at E-12, near the PBNP discharge (0.029 2 0.012), in August. Both of these radionuclides were discharged by PBNP during 1995: Co-60 every month during 1995 and Co-58 from March - December. However, as previously discussed with regard to H-3, most of the positive results are obtained north of PBNP and not near the discharge as expected if PBNP were the primary source of these cobalt isotopes. Although no measurable Co-58 or Co-60 were found in the water samples from E-05 during the year, it is known that filamentous algae have cobalt bioaccumulation factors on the order of 250 to 2800.
Therefore, it is not surprising that the cobalt isotopes were found in the algae and not in the water. Freshwater fish have a t:ioaccumulation factor for Co-60 comparable to that of algae, about 1000. However, neither Co-58 nor Co-60 were observed in fish analyzed during the year. Therefore, it is possible that the algae results are false positives. Finally, it should be noted that the Co-58/60 levels found in the algae are at least ten times lower than the applicable LLDs and about 1000 times lower that the NRC notification levels.
23
5 I
i i
I 9.6 Summary of 1996 REMP Results i
A summary of the REMP results for 1996 are presented in Table 9-5. De table contains the I
following information:
\\
Sample:
the type of the sample medium
==
Description:==
the type of measurement LLD:
the a pnorilower limit of detection N:
the number of samples analyzed Low:
the lowest measured value
- its associated 2s counting error Average
- the average value
- the standard deviation of N samples liigh:
the highest measured value
- its associated 2s counting error Units:
the units ofmeasurement Additional information also is presented in Table 9-5. Not all of the results in Table 9-5 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 analyses, 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. Dese results will be investigated and discussed in the narrative portion of this section. Blank values have not been subtracted from the results presented in Table 9-5.
9.7 Discussion for 1996 Results Radiological environmental monitoring conducted at the Point Beach Nuclear Plant from January 1,1996 through December 31,1996 consisted of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, vegetation, and TLDs. De results are summarized in Table 9-5.
All TLD results for the reporting period were within the normal range. As in the past Site E-12, located on the discharge fiume pier continues to exhibit some of the lowest values whereas E-32, approximately I mile west of the plant, continues to exhibit some of the highest. The higher values at E-32 have been noted since TLDs were first located at this site. He reason for this result is not known and continues to be tracked. liowever, unlike previous years, during 1996 even the highest TLD results at E-32 were not statistically different from many of the other i
highest values observed during the year, including the background site some 17 miles WSW of
- PBNP, The analyses for individual radionuclides reveals that Sr-90 and Cs 137 continue to occur in environmental samples as they are cycled through the biosphere. Sr-90 continues to persist in milk and lakewater. Cs-137 occurs in shoreline sediment deposits, fish, algae, vegetation, and I
soil. These radionuclides routinely occur in environmental samples collected around the world and are attributable to the large scale atmospheric weapons tests of the 1960's and the less frequent testing in the 70's and 80's, and as well as to the Chernobyl accident.
Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. Lake water tritium concentrations continue to be low. These samples are l
composites of monthly samples for quarterly analysis. Most of the results are in the <100 - 250 pCi/l range. The highest result,862
- 124 pCi/1, occurred approximately 4 miles north of PBNP.
The predominant current along this side of Lake Michigan is from north to south which indicates 24
e TABLE 9-5 RADIOLOGICAL ENVIRONMENTAL MONITORING RESULTS FOR 1996 Sample Description LLD N
Low Average High Units TLD Environmental Radiation
(*)
101 0.63 1 0.06 0.83 1 0.12 1.13 1 0.05 mR/7 days Air Gross beta 0.01 308 0.008 i O.002 0.021 i 0.007 0.054 1 0.005 pCi/m' Cs-137 0.01(0.06) 24
-0.000310.0004 0.000010.0002 0.000310.0003 pCi/m' Cs-134 0.05 24
-0.002010.0004
-0.000010.0001 0.000410.0007 pCi/m' I-131 0.03(0.07) 308
-0.017 i O.012 0.000 1 0.007 0.019 i O.016 pCi/m' Other gamma emitters (*)
0.1(*)
24
-0.000510.0008 0.000210.0002 0.000610.0007 pCi/m' Milk I-131 0.5 36
-0.1810.14 0.08 1 0.11 0.28 i 0.28 pCi/1 Sr-89(*)
5(*)
36
-1.6 t 1.8
-0.2 1 0.8 1.1 i 1.2 pCi/1 Sr-90(*)
1(*)
36 0.6 i 0.3 1.1 1 0.4 1.1 1 0.4 pCi/1 Cs-134 5(15) 36
-2.0 1 2.7 0.2 1 0.8 1.9 i 3.4 pCi/1 Cs-137 5(18) 36
-1.4 i 3.7 0.6 i 1.0 3.1 i 2.5 pCi/1 Ba-La-140 5(15) 36
-2.4 1 1.7
-0.3 1 1.2 5.3 i 8.9 pCi/1 Other gamma emitters (*)
15(*)
36
-1.5 i 3.0 0.4 1 1.0 3.0 1 4.8 pCi/1 Lake water Gross beta 4
60 1.3 2 0.5 2.7 1 0.7 5.1 1 0.6 pC1/1 1-131 0.5 (2) 60
-0.2820.26 0.06 1 0.12 0.30 1 0.37 pCi/1 Mn-54 10(15) 60
-4.4 1 3.3 0.1 1 1.2 3.7 1 2.8 pC1/1 Fe-59 30 60
-6.3 1 6.3 0.1 i 2.4 8.5 i 6.9 pCi/1 Co-58 10 60
-3.8 i 3.0 0.1 i 1.1 1.8 i 4.1 pCi/1 Co-60 10 60
-3.2 i 2.3 0.7 1 1.4 4.1 1 2.3 pCi/1 Zn-65 30 60
-5.6 i 5.6
-0.9 i 2.1 4.9 i 6.0 pCi/1 Zr-Nb-95 15 60
-3.9 i 4.2
-0.3 i 1.5 3.1 i 5.9 pCi/1 Cs-134 10(15) 60
-3.5 2 3.0 0.0 2 1.1 2.6 1 3.0 pCi/1 Cs-137 10(18) 60
-2.9 1 2.9 0.4 i 1.2 3.1 1 2.1 pCi/1 Ba-La-140 15 60
-11.3 1 12.7
-1.0 i 3.4 8.4 1 14.7 pC1/1 Other gamma emitters (*)
30(*)
60
-4.2 2 3.8
-0.4 1 1.5 3.4 i 5.0 pCi/1 H-3 500(3000) 20 8 i 94 162 i 185 862 1 124 pCi/1 Sr-89(*)
5(*)
20
-1.4 i 1.0
-0.5 1 0.5 0.2 i 1.0 pCi/1 Sr-90 (*)
1(*)
20 0.3 1 0.2 0.7 0.2 1.1 1 0.4 pCi/1 Algae Gross beta 0.25 5
3.50 2 0.41 5.07 2 1.37 6.96 1 1.40 pCi/g Co-58 0.25 5
-0.01010.000
-0.001 1 0.006 0.003 1 0.010 pCi/g Co-60 0.25 5
0.00010.017 0.006 2 0.005 0.011 1 0.012 pCi/g Cs-134 0.25 5
0.00310.003 0.007 i 0.003 0.010 1 0.007 pCi/g Cs-137 0.25 5
0.02110.017 0.038 i 0.016 0.059 i 0.014 pCi/g 25
TABLE 9-5(continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING RESULTS FOR 1996 Sample Description LLD N
Low Average High Unite Fish Gross beta (*)
0.5(*)
9 1.38 i 0.06 2.50 t 0.76 3.54 1 0.07 pCi/g Mn-54 0.13 9
-0.00310.007 0.00110.003 0.00510.004 pCi/g Fe-59 0.26 9
-0.00610.017
-0.00110.009 0.01820.036 pCi/g Co-58 0.13 9
-0.00910.018
-0.00210.007 0.01520.021 pCi/g Co-60 0.13 9
-0.01730.022 0.00110.009 0.01610.020 pCi/g Zn-65 0.26 9
-0.051to.046
-0.00610.020 0.01910.036 pCi/g Cs-134 0.13 9
-0.003i0.021
-0.00510.003 0.00610.005 pCi/g Cs-137 0.15 9
0.015i0.008 0.04210.031 0.10410.018 pCi/g Other gamma emitters (*)
0.5(*)
9
-0.00110.009 0.00110.007 0.01910.034 pCi/g Well water Gross beta 4
4
-0.5 i 1.5 1.0 i 1.3 2.6 i 0.1 pC1/1 I-131 0.5 (2 )
4
-0.02 i 0.18 0.14 1 0.14 0.31t 0.31 pCi/1 Kn-54 10(15) 4
-0.3 i 1.6 0.4 2 0.5 0.8 i 2.1 pCi/1 Fe-59 30 4
-1.8 i 2.4 0.0 1 1.4 1.2 2 2.5 pCi/1 Co-58 10 4
-0.6 i 1.1 0.7 i 1.2 2.2 i 1.7 pCi/1 Co-60 10 4
-0.5 i 1.1 0.4 i 0.6 0.9 i 1.4 pCi/1 Zn-65 30 4
-3.5 1 4.4
-2.3 i 1.2
-1.0 1 2.1 pCi/1 Zr-Nb-95 15 4
-1.9 i 2.7
-0.3 i 1.1 0.5 t 2.2 pCi/1 Cs-134 10(15) 4
-0.5 i 2.3 0.3 1 0.6 0.9 i 1.2 pCi/1 Cs-137 10(18) 4
-0.6 i 2.4 0.7 i 1.0 1.7 i 1.2 pCi/1 Ba-La-140 15 4
-2.0 1 2.1 0.1 1 2.1 3.0 1 4.3 pCi/1 Other gamma emitters (*)
30(*)
4
-1.8 1 1.5
-1.2 1 0.5
-0.8 114 pC1/1 H-3 500 4
-27.0 t 76.0 21.3 1 36.6 49'.0 t 83.0 pCi/1 Sr-89 (*)
5(*)
4
-0.54 i 0.70 0.05 2 0.40 0.36 i 0.64 pCi/1 Sr-90 (*)
1(*)
4
-0.02 i 0.14 0.10 1 0.10 0.18 i 0.21 pCi/1 Soil ( * )
Gross beta 2
16 5.3 i 1.9 19.4 1 7.0 29.5 1 3.1 pCi/g Cs-137 0.15 16 0.020 1 0.018 0.201 i 0.202 0.807 i 0.041 pCi/g Shoreline Gross b9ta 2
10 4.40 i 1.12 6.92 1 1.44 8.41 i 1.12 pCi/g sediment (*)
Cs *.37 0.15 10 0.019 i 0.009 0.033 1 0.011 0.051 1 0.017 pCi/g Vegetation Gross beta (*)
0.25(*)
24 3.4 i 0.2 4.9 i 0.8 6.6 1 0.2 pCi/g Cs-134 0.06 24
-0.00410.013 0.003 i 0.005 0.018 i 0.019 pCi/g Cs-137 0.08 24 0.00510.011 0.012 1 0.030 0.150 i 0.035 pCi/g I-131 0.06 24
-0.01110.023
-0.000 i 0.007 0.016 i 0.032 pCi/g h
26
~*
Oe Q
w-m m
.m mm,...
,t..
i
\\
that PBNP is not the likely source of this elevated H-3 concentration. Of the remaining 19 composite samples, six are statistically equal to zero at the 95% confidence level. Over the past three years, tritium blanks have yielded results in the range of-101.3
- 70.2 to 148 101 pCUI.
An additional eight sample results fall within the range of these blanks..
For the remaining suite of RETS specified radionuclides, measured concentrations occur as l
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) whose *2s error does not overlap zero occur for Co-60, Mn 54, and Cs-137 in water. The Mn-54 (3.7 2.8 pCi/l) occurred in December. Hc. 'ever, the only measured PBNP Mn-54 discharge occurred in April suggesting that the lake water result is a false positive. The positive Cs-137 result is consistent with the know cycling of fallout in the Great Lakes. Five occurrences of minute quantities of Co-60 were found in lake water during the months of April, May, and August. If these results represen*ed actual lake water concentrations, the algae and fish (known to be long time integrators of these radionuclides with a bioaccumulation factors around 1000)in the same area should also have measurable Co-60. However, no Co-60 was detected in the algae or the fish. Note that the analyses of water " blanks" yield Co-60 results up to 1.711.6 pCi/1. Although the three occurrences in April correspond to the month with the maximum Co-60 discharge, the other two positive results (May and August) do not correspond to the second or third highest discharge months (March and May) when no Co-60 was detected in lake water. Therefo.;.hile it may be possible that the observed Co-60 is real, it is concluded that the Co-60 values are false positives. Assuming the highest measured concentration value of 4.li2.3 pCi/l to be real and consumed by the hypothetical maximumly exposed individual for one year, the resulting dose would be 9.2E-09 mrem which is orders of magnitude lower than the doses calculated for PBNP liquid releases for Appendix I compliance (Table 1 1).
All of the isotopic well water results are small positive and negative values in6stinguishable from zero 9.8 Land Use Census In accordance with the requirements of Technical Specification 15.7.7.D, a visual verification of animals grazing in the vicinity of the Point Beach Nuclear Plant site boundary was completed in July of 1996 to ensure that the milk sampling locations remain as conservative as practicable. No significant change in the use of pasture lands was noted. Although the size of the dairy herd at E-21 has increased, the cows have not move closer to the PBNP site boundary, the point the cows are assumed to exist for the purpose of dose calculations for Appendix 1 compliance. Therefore, the exis.bg milk sampling program continues to be acceptable, i
9.9 Conclusion Based on the results of the PBNP REMP for 1996, PBNP effluents had a minimal affect on the PBNP environs.
I 27
'