ML20217P276
| ML20217P276 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/31/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20217P274 | List: |
| References | |
| NUDOCS 9805060189 | |
| Download: ML20217P276 (123) | |
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l ANNUAL MONITORING REPORT 1997
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f POINT BEACH NUCLEAR PLANT January 1,1997 through December 31,1997 9805060189 900430 6 PDR ADOCK 0500 R
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POINT BEACH NUCLEAR PLANT ,
January 1,1997 through December 31,1997 r
9005060189 990430 PDR ADOCK 05000266 R
i POINT BEACH NUCLEAR PLANT I ANNUAL MONITORING REPORT I
1997 Part A: EFFLUENT MONITORING Part 11: MISCELLANEOUS REPORTING REQUIREMENTS Part C: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM January 1,1997 through December 31,1997 f
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l PREFACE This Annual Monitoring Report for the period of January 1,1997, through December 31.1997, 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 License Nos. DPR-24 and DPR-27, respectively.
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TAllLE OF CONTENTS Executive Summary 1 Part A Effluent Monitoring 3 1.0 Basis 4 2.0 Radioactive Liquid Releases 4 3.0 Radioactive Airbome Releases 9 4.0 Radioactive Solid Waste Shipments 12 5.0 Nonradioactive Chemical Releases 14 6.0 Circulating Water System Operation 14 Part 11 Miscellaneous Reporting Requirements 16 7.0 New and Spent Fuel Shipments and Receipts 17 8.0 Leak Testing of Radioactive Sources 17 9.0 Additional Reporting Requirements
( 17 Part C Radiological Environmental Monitoring Program 18
- 10. Basis 19
- 11. Program Description 19
[ 12. Results 33
- 13. Discussion 36
- 14. Conclusion 40 Appendix 41 f
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l l TABLE OF TABLES Table 2-1 Summary of Circulating Water Discharges 6 Table 2-2 1sotopic Composition of Circulating Water Discharges 7 Table 2-3 Subsoil System Drains-Tritium Summary 8 Table 2-4 Comparison of 1997 Liquid Doses to Appendix 1 Dose Objectives 8 Table 3-1 Radioactive Airborne Release Summary 10 Table 3-2 Comparison of 1997 Airborne Doses to Appendix I Dose Objectives 10 l
Table 3-3 Isotopic Composition of Airborne Releases 11 Table 4-1 Quantities and Types of Waste Shipped from PBNP 12 Table 4-2 Estimated Solid Waste Major Radionuclide Composition 13 Table 6-1 Circulating Water System Operation for 1997 15 l Table I l-1 PBNP Radiological Environmental Sample Collection Frequency 22 Table Il-2 Radiological Environmental Sampling Locations 23 l Table Il-3 Recommended Minimum Sample Size 26 l Table I l-4 Sample Collection for the State of Wisconsin 26 l Table Il-5 PBNP Radiological Environmental Sample Analysis and Frequency 29 l Table 12-1 Radiological Environmenial Monitoring Results for 1997 34 l
TABLE OF FIGURES Figure Il-1 Point Beach Nuclear Plant Radiological Environmental Monitoring Program Sites 22 Figure I l-2 Site Map tbr Point Beach Nuclear Plant 23 Figure 11-3 Co-located PBNP and State of Wisconsin Sampling Site 25 Figure Il-4 Water Collection on the Lake Michigan Shoreline 28 Figure l 1-5 Quarterly Air Sampler Flow Rate Verification 29 Figure 13-1 1-131 Concentration Frequency Distribution 34 l
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APPENDIX INDIVIDUAL, SAMPLE RESULTS AND TELEDYNE QA/QC RESULTS i
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EXECUTIVE SUMMART l
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l Pursuant to Part 50.34a of Title 10 of the Code of Federal Regulations (10 CFR 50.34a), the operation of the Point Beach Nuclear Plant (PBNP) should be conducted so as to keep the levels of radioactive material in effluents to unrestricted areas as low as reasonabb achievable ~
( ALARA). Furthermore.10 CFP 20.1302 directs PBNP to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas and of the environs around PBNP. Therefore, in addition to monitoring effluents, PBNP has a Radiological Environmental hionitoring Program (REMP)in order to verify that the appropriate controls have been applied to effluents prior to release. This Annual Monitoring Report for the period of g January 1.1997, through December 31,1997, is submitted in accordance with Point Beach 3 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 License Nos. DPR-24 and DPR-27, respectively. The report presents the results of efRuent and environmental monitoring programs, solid waste I shipments. new fuel shipments. non-radioactive chemical releases, circulating water system operation. and leak testing of radioactive sources.
During 1997, liquids containing 172 curies of tritium and 0.242 curies of other radionuclides were released from PBnP. Airborne releases consisted of 149 curies of tritium,46.9 curies of I noble gases. and 1.97 microcuries of particulate radioactive material. For the purpose of regulatory compliance with the effluent dose objectives of Appendix I to 10 CFR 50, doses from efiluents are calculated for the hypothetical maximally exposed individual (MEI) and compared to the Appendix I limits. Doses less than or equal to the Appendix I values are considered to be evidence that PBNP releases are ALARA. As such, the radiation exposure to the MEI is maximized with respect to occupancy, food consumption, and other uses of this area so that the l MEl represents an individual with reasonable deviations from the average for the general population in the vicinity of PBNP. Doses are calculated for the adult, teen, child, and infant age groups. The maximum annual calculated doses are shown below and compared to the corresponding dose objectives of 10 CFR 50, Appendix 1 LIQUID RELEASES I Dose Categorv Calculated Dose Annendix I Dose g Whole body dose 0.00228 millirem 6 millirem
[ Organ dose 0.00335 millirem 20 millirem I
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ATMOSPHERIC RELEASES Dose Category Calculated Dose Annendix I Dose l Organ dose 0.0164 millirem 30 millirem l Noble gas dose to the skin 0.00774 millirem 30 millirem l Noble gas dose to the whole body 0.000490 millirem 10 millirem l Noble gas beta particle air dose 0.000253 millirad 40 millirad l Noble gas gamma ray air dose 0.000515 millirad 20 millirad l
The results show that during 1997, the doses from PBNP efiluents were a small fraction of the Appendix I dose objectives and therefore continue to be ALARA.
The 1997 REMP collected 786 samples for radiological analyses and 108 sets of l thermoluminescent dosimeters were used to measure ambient radiation in the vicinity of PBNP. .
Samples collected consisted oflake and well water, soil, vegetation, milk, soil, shoreline ;
sediments, algae, fish, as well as particulate and radioiodine air samples. l Air monitoring from six different sites showed only background radioactivity from naturally
! occurring radionuclides. Terrestrial monitoring consisting of soil, vegetation, and milk found no l influence from PBNP. Similarly, samples from the aquatic environment, lake and well water, fish. and algae, revealed no buildup of PBNP radionuclides released in liquid effluents.
l Ilowever, two lake water samples had higher than normal tritium concentrations. It was
- determined that. because of a scheduling conflict, these samples were obtained during the i discharge of a waste holdup tank. Although the tritium results from these samples were higher l than normal H-3 concentrations in the water, the results verified that the controls PBNP applies l to discharges, to keep the resulting effluent concentrations to a small fraction of the applicable 10
! CFR 20 limit, had been applied correctly. The measured concentration was at 0.3% of the l applicable limit. Fallout radionuclides from atmospheric weapons testing and from Chernobyl still are present at very low concentrations in some samples: Sr-90 in milk and Cs-137 in soil, vegetation, and fish. Therefbre, based on the REMP radioanalytical results, PBNP effluents had a minimal impact upon the environment during 1997.
In addition to collecting and analyzing environmental samples, a survey ofland use with respect to the location of dairy cattle was made pursuant to Technical Specification 15.7.7.D.I. As in previous years, no dairy cattle were found to be grazing at the site boundary. Themfore, the assumption used in the evaluation of dpses from PBNP effluents, that cattle graa at the site boundary, remains censervative.
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( effluent. In addition to monitoring the liquid prior to discharge, shoreline sediments, water, and fish are analyzed to verify that the appropriate controls have been applied to the discharge.
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1.0 llASIS The Point Beach Nuclear Plant's (PBNP) effluent monitoring program is designed to comply with Federal Regulations for ensuring the safe operation of PBNP with respect to releases of radioactive material to the environment and its subsequent impact on the public.10 CFR 50.34a states that operations should be conducted so as to keep the levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable
( ALARA). In 10 CFR 50, Appendix 1, the Nuclear Regulatory Commission (NRC) provides the numerical values for what it considers to be the appropriate ALARA dose objectives to which the licensee's calculated effluent doses may be compared. These doses are a small fraction of the dose limits specified by 10 CFR 20.1301 and lower than the Environmental Protection Agency (EPA) limit in 40 CFR 190.
10 CFR 20.1302 directs PBNP to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas. This monitoring requirement (
also found in General Design Criterion (GDC) 64 of Appendix A to 10 CFR 50 and in PBNP GDC 17) is implemented in order to control effluent releases as required by PBNP GDC 70 and GDC 60 of Appendix A to 10 CFR 50. PBNP GDC 70 and GDC 60 of Appendix A to 10 CFR 50 also address the need for control of solid waste material.
In order to accomplish the required monitoring, PBNP monitors liquid, airborne, and solid waste streams. Liquid wastes are monitored by inline radiation monitors as well as by isotopic analv es of samples of the waste stream prior to discharge from PBNP.
Airborne releasc., of radioactive wastes are monitored in a similar manner. Furthermore, for both liquid and atmospheric releases, the appropriate portions of the radwaste treatment systems are used as required to keep releases ALARA. Results ofisotopic analyses are used to adjust the release rate of discrete volumes ofliquid and atmospheric wastes (from liquid waste holdup tanks and from gas decay tanks) so that the concentrations of radioactive material in the air and water beyond PBNP are below the regulatory concentration limits in Appendix B to 10 CFR 20. Solid wastes are shipped offsite for disposal at an NRC licensed facility. The amount of radioactivity in the solid waste is determined prior to shipment so that the material will comply with the applicable Department of Transportation regulations as well as NRC regulations.
2.0 RADIOACTIVE LIQUID RELEASES The total radioactive liquid release, excluding tritium for this reporting period, was 2.42E-01 curies. This consisted entirely of processed radioactive waste. There were no detectable curies in either Unit I steam generator blowdown,in Unit 2 steam generator blowdown , or in retention pond effluent.
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The total tritium release for this reporting period was 1.72E+02 curies. This consisted j entirely of processed radioactive waste. There was no detectable tritium measured either I in Unit I steam generator blowdown,in Unit 2 steam generator blowdown, or in retention I pond effluent, j 2,1 1997 Circulating Water Radionuclide Release Summarv 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 2-1 l
2.2 1997 Isotonic Comnosition of Circulating Water Discharges The isotopic composition of circulating water discharges during the current l reporting period is presented in Table 2-2. I 2.3 Subsoil Drain System Releases of Tritium Table 2-3 indicates that there were no tritium releases via the subsoil drain system during 1997. ;
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SUMMARY
l January 1,1997 through December 31,1997 NI N3 N9 b-lo 5-7 ' 58' l utal
- I trst Ouarler ll 3tulucc) 000L+00 0 00L+00 0.00L+00 0 00L+00 Ave f low orpd> l.75L+04 1.71L+03 6.44 L+03 9.52 L+03 3.17L+06 ;
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Il-3(utvec) 0.00L+00 0 00L+00 - .
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As e. l-low (gpd) 9 41 L+03 2.50L+03 0 00L+00 0.00L+00 7.46L+03 0.00L+00 1.78L+06 l \nnual totals i Released (LO 0 00L+00 0110L+00 0.00L+00 0.00L+00 0.00L+00 0.00L+00 0.00L+00 i lowtual) 4 M I L+06 1.04 L+06 S.MOL+0S 857L+05 8.19L+0$ 0.00L+00 M llL+06 i Subsoil drains S-7 and S-8 were uncovered in September during beach work.
I - No sample to analyze because of zero flow.
, 2.4 Doses From Liauid Effluent l
- Doses from liquid effluent are ca!culated using the methodology of the Offsite l Dose Calculation Manual (ODCM). The ODCM methodology is based on the l guidance of Regulatory Guide 1.109, " Calculation of annual doses to man fmm routine releases of reactor efnuents for the purpose of evaluating compliance with 10 CFR Part 50, Appendix 1." For compliance with Appendix I, the annual dose is calculated to the hypothetical maximally exposed individual (MEI). The MEI is assumed to reside at the site boundary in the highest X/ Q sector and is maximized with respect to occupancy, food consumption, and other uses of this area. As such, the MEI represents an individual with reasonable deviations from l the average for the general population in the vicinity of PBNP. A comparison of the calculated doses to the 10 CFR 50, Appendix 1 dose objectives is presented in Table 2-4.
TAllLE 2-4 l COMI'ARISON OF 1997 LIQUID EFFLUENT DOSES TO APPENDIX I DOSE OILIECTIVES s unual 1.tnut lmrcen] January-Deccenber ilsghest intal Calculated Dose lrnrcinl % ul 10 (lit 50. Appendn 1. Dose Objectne 6 (w hole body) 2.28E-03 (adult) 3.SE-02 20 tany organ) 3.35E-03 (child liver) 1.7E-02 i
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i 2.5 Land Application of Sewage Sludge The Wisconsin Department of Natural Resources has upproved the disposal of PBNP sewage by land-application 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 by the NRC on January 13,1988, pursuant to 10 CFR 20.302(a). The approved methodology required analyses prior to every disposal. Based upon an investigation of the source of the radionuclides, a combination of engineering modifications and administrative controls have eliminated radiological inputs to the sewage system for all but naturally occurring radionuclides. This was verified by sludge analyses, using the environmental LLD criteria, which found no byproduct radionuclides in the sludge after the controls and modifications were completed. Currently, the sludge is routinely monitored and no radionuclides attributable to PBNP have been found. There were no disposals of sewage by land application during 1997.
3.0 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 I containment purge stack, Unit 2 containment purge stack, combined air ejector decay duct exhaust and turbine building ventilation exhaust.
There were ten gas decay tank releases during this reporting period: 1 in January,1 in April,2 in August,1 in September,3 in November, and 2 in December.
3.1 Radioactive AirborneIklease Summary Radioactivity released in airborne effluents for 1997 are summarized in Table 3-1.
3.2 Doses From Airborne Efauent Doses from airborne effluent are calculated for the MEI following the methodology of Regulatory Guide 1.109. In addition to the MEI doses, the energy deposited by beta particles and gamma rays in air also is calculated and compared to the corresponding Appendix I dose objectives. A comparison of the annual Appendix I dose limits for atmospheric ef0uents to the highest organ dose and the noble gas doses calculated using ODCM methodology is found in Table 3-2. The doses demonstrate the releases from PBNP to the atmosphere centinue to be ALARA.
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4.0 IRADIOACTIVE SOI.lD WASTE SIUPMENTS 4.1 Ivpe. vdume. and activity of shinned solid waste The following types, volumes, and activity of solid waste was shipped from PBNP for ofTsite disposal or burial during 1997. No irradiated fuel was shipped ofTsite. The volume, activity, and type of waste is listed in Table 4-1.
Table 4-1 QUANTITIES and TYPES of WASTE SillPPED from PBNP Tyne of waste Units Ouantity A. Spent resins, litter sludges, evaporator m'(ft') 3.42E+00 (1.21E+02) bottoms, etc. Ci 1.30E+02 B. Dry compressible waste, contaminated m'(if) 2.01E+01 (7.10E+02) equip, etc.' Ci 3.21 E-01 C. Irradiated components, control m' (ft') 1.64E+00 (5.79E+01) rods, etc. Ci 1.12E+03 D. Other(describe) None
' Volume after incineration or compaction 4.2 Maior nuclide composition (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 4-2 in decreasing order of activity.
4.3 Solid Waste Disnosition There were ten solid waste solid waste shipments from PBNP, Two were to Barnwell, SC via truck and eight shipments, via truck, went directly to a volume reduction facility. Shipments were made on the dates listed below.
Directly to Barnwell: 5/20/97 and 8/25/97.
To Scientific Ecology Group for volume reduction prior to shipment to Barnwell:
1/14/97,1/28/97,4/18/97,4/25/97,5/l/97,7/21/97,10/7/97, and 12/16/97.
12
TABLE 4-2 ESTIMATED SOLID WASTE MAJOR RADIONUCLIDE COMPOSITION Type A Type 13 Type C Snent Resins. Filter Sludges. Etc. Drv Comoressible Waste. Etc. Irradiated Comnonents. Etc.
Nuclide Percent Nuclide Percent Nuclide Percent Name Abundance Name Abundance Name Abundance Ni-63 3.23 E+01 Fe -55 3.41 E+01 Co-60 5.43 E+01 Co-60 3.18E+01 Ni-63 2.52 E+0 ] Fe -55 2.97 E+01 Co-58 1.95 E+0 i Co-60 1.99E+01 Ni-63 1.50E4 01 Fe-55 1.05 E+01 Cs-137 8.87E+00 11-3 7.75 E-01 Cs- 137 3.10E+00 Co-58 5.79E+00 Ni-59 1.33 E-01 Mn-54 1.21E+00 Sb-125 2.21 E+00 Mn-54 6.77E-02 Sb-125 4.89E-01 C-14 1.80E+00 C-14 1.89E-02 Co-57 2.79E-01 Ag-110m 1.11E+00 Nb-94 3.80E-04 C-14 2 29E-01 Pu-241 7.48 E-01 Tc-99 2.35 E-05 Ag- 110m 2.00E-01 Sr-90 9.90E-02 Pu-241 7.42 E-07 j Cs-134 1.66E-01 Nb-95 4.40E-02 Cm-242 8.70E-09 i Pu-241 6.00E-02 Am-241 3.60E-02 )
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4.4 Addendum to 1995 Annual Monitoring Renort The waste shipment dates were inadvertently omitted from the 1995 Annual Monitoring Report. The following are th <htes shipments were made to Barnwell, SC for disposal: 8/15,8/17, 9/5,9/18,9/26,10/19,10/31,11/9.I1/15.
I1/16,12/20, and 12/27. There were 17 separate shipments on 12 different days.
M Multiple shipments were made on 8/17,9/5, and 12/20. Five of the seventeen shipments were from PBNP directly to Barnwell. The other shipments to Bamwell were from waste treatment facilities that had received PBNP waste for waste minimization.
5.0 NONRADIOACTIVE CllEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, i 1997, to December 31,1997, included 5.30E+06 gallons of neutralized wastewater. The wastewater contained 2.50E+02 pounds of suspended solids and 4.27E+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 effluent analyses) to the circulating water for January 1,1997, to December 31,1997, included 5.48E+07 gallons of clarified wastewater. The wastewater contained 3.71E+03 pounds of suspended solids.
Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1,1997, to December 31,1997, included 1.73E+05 pounds of sodium bisulfite and 3.77E+04 pounds of sodium i hypochlorite.
l 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.
14
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Table 6-1 CIRCULATING WATER SYSTEM OPEliATION FOR 1997 UNIT JAN Fell MAR APR MAY JUN Average Volume Cooling i 296.6 292.2* 296.6* 289.0* O' 142.3*
Water Discharge [Mgal/ day]" 2 0* 261.3* 0* 284.6* 296.6* 294.8*
Average Cooling Water 1 35 33' 33 38'
- 44*
Intake Temperature ['F1 2 34'
- 40' 44' 49' Aserage Cooling Water 1 63 51* 33* 39'
- 44' Discharge Temperature [ F] 2
- 34'
- 40' O' 50*
Aserage Ambient Lake 33 33 33 3P 45 49 Temperature [ F]
Table 6-1(continued)
CIRCULATING WATER SYSTEM OPERATION FOR 1997 UNIT JUL AUG SEP OCT NOV DEC Aserage Volume Coolmg i 273.7* 251.7* O' 0* 264.0* 296.6 Water Discharge [Mgal/dayl" 2 283.5* 357.6* 383.3* 504.0 433.9* 0*
Aserage Cooling Water 48' 60* *
- 1 36* 38 Intake Temperature [*F] 2 56* 62* 58' 45 43*
- Aserage Coohng Water 1 48' 61* *
- 37' 65 Discharge Temperature [*F1 2 58' 74* 70* 64 58*
- Aserage Ambient Lake 53 61 59 44 41 38 Temperature [ F1
- Unit I shutdown from February 18.1997 to November 30,1997, with intermittent CW flow. Unit 2 shutdown from January l-August 15, September 6-22, and November 15-December 31,1997 with intermittent CW flow.
" For days with cooling water discharge flow.
l 15
l Part B Miscellaneous Reporting Requirements 1
l 16
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7.0 NEW AND SPENT FUEL SHIPMENTS AND RECEIPTS No new fuel assemblies were received at PBNP from Westinghouse Electric Corporation during 1997 due to the extended outages.
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r There were no spent fuel shipments made from Point Beach Nuclear Plant during this reporting period.
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8.0 LEAK TESTING OF RADIOACTIVE SOURCES
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During 1997, all applicable sealed radioactive sources were leak tested in accordance f with Technical Specification 15.4.12. Leak test results were all <0.005 pCi.
I 9.0 ADDITIONAL REPORTING REQUIREMENTS 9.1 Revisions to the PBNP Office Dose Calculation Manual (ODCM) and Process Control Program (PCP)
There were no revisions to either the Environmental Manual or the PCP during 1997. The ODCM was revised during 1997 and one complete copy of the revised f manual is supplied with the submittal of this Annual Monitoring Report. The revision addresses Modification 3 to the commitment made, pursuant to the 1988 ;
NRC approval under 10CFR20.302(a), to analyze sewage sludge prior to each !
disposal via land application. M. .~. 9 tion 3 is inserted as Appendix H to the original 10CFR20.302(a) application located at the end of the ODCM.
f 9.2 Interlaboratorv Comoarison Program The analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples participated in the EPA Interlaboratory Comparison Program during 1997.
'9.3 Soecial Circumstances No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 1997.
t 17
1 Part C RADIOLOGICAL ENVIRONMENTAL MONITORING
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Collecting air samples is an important part of the PBNP Radiological Environmental Monitoring Program. Air samples are collected at five sites close to PBNP and one background site some 17 miles away.
18
10.0 BASIS FOR RADIOLOGICAL ENVIRONMENTAL MONITORING The objective of the PBNP REMP is measure ambient radiation levels and to collect and analyze air, water, vegetation, fish, and soil samples for their radionuclide content in order to determine whether the operation of the PBNP has radiologically impacted the surrounding environment. These measurements also serve as a check on the efficacy of PBNP effluents controls. The REMP fulfills 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 I 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.
For the aquatic environment, 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 contrast, the filamentous algae periphyton are attached to shoreline rocks and concentrate nuclides from the water flowing by their point of attachment. Grab samples oflake water provide a snapshot of radionuclide concentrations at the time the sample is taken.
The terrestrial and atmospheric environments are united by the air-grass-cow-milk exposure pathway. This pathway is important because of the many dairy farms around PBNP. Therefore, the REMP includes samples of air, general grasses, and milk from the PBNP environs. An annual land use survey is made to determine whether the assumptions on the location of dairy cattle remains conservative with respect to dose calculations for PBNP effluents. The dose calculations assume that the dairy cattle are located at the south site boundary in the highest depositional sector. In addition, soil samples are collected and analyzed in order to monitor the potential for long-term buildup of radionuclides in the vicinity of PBNP.
For the measurement of the levels of ambient environmental radiation that may be affected by direct radiation from PBNP or by noble gas effluents, the REMP employs a series of TLDs which are situated around PBNP.
I 1.0 PROGRAM DESCRIPTION 11.1 Results Renortine Convention The PBNP REMP results in this Annual Report are reported directly as measured, whether positive, negative or zero. No results are reported as <LLD. The LLD or Lower Limit of Detection is an a priori concentration value that specifies the 19 l
1 performance capability of the counting system used in the analyses of the REMP I samples. The required LLDs are set forth in the PBNP Radiological Efiluent Technical Specifications (RETS). The parameters for the apriori LLD are chosen so that there is only a five percent chance of falsely concluding a specific I radionuclide is present when it is not present at the specified LLD. Based on detector efficiency and average background activity, the time needed to count the sample in order to achieve the desired LLD depends upon the sample size. Hence, the desired LLD may be achieved by adjusting various parameters. When a suite of radionuclides are required to be quantified in an environmental sample such as lake water, the counting time used is that required to achieve the LLD for the l radionuclide with the longest counting time. Therefore, in fulfilling the requirement for the most difficult to achieve radionuclide LLD, the probability of l detecting the other radionuclides is increased because the countine time used is longer than that required to achieve the remaining radionuclide LL Ds.
When the radionuclide ofinterest is not present in the sample, the statistical nature of radioactive decay will produce negative and positive results centered about zero. To exclude valid measured concentrations whether negative or as I small positive values below the LLD will artificially inflate the calculated average value. Therefore, all generated data are used to calculate the statistical parameters presented in this report.
This reporting convention follows the recommendation made in NUREG-0475 (1978)" Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities Task Force Report," and in Health Physics Society Committee Report HPSR-1 (1980)" Upgrading Environmental Radiation Data" released as document EPA 520/l-80-012 and in more recent documents such as ANSI N42.23-1996," Instrument Quality Assurance for Radioassay Laboratories;" ANSI N13.30-1996," Performance Criteria for Radiobioassey;"
I and DE91-013607, " Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance."
11.2 Samoling Parameters Samples are collected at the frequency indicated in Table Il-1 from the locations l described in Table Il-2.and shown in Figures Il-1 and Il-2. The minimum acceptable sample size is found in Table Il-3.
I 1.3 Deviations from Reauired Collection Freauency Deviations from the collection frequency given in Table 11-1 are allowed (TS I 15.7.7.A.2) because of hazardous conditions, automatic sampler malfunction, I
20
seasonal unavailability, and other legitimate reasons. The following deviations from the scheduled sampling and frequency occurred during 1997:
11.3.1 No air particulate or radioiodine samples were obtained at E-04 for the week ending 10/6/97 because the air sampling pump failed.
11.3.2 The lake water sample was not collected at E-06 in February because the I extremely icy conditions made collection too hazardous for personnel.
I 1.4 Assistance to the State of Wisconsin The Radiation Protection Unit of the Wisconsin Department ofIIealth and Family Services maintains a radiological environmental monitoring program in order to confirm the results from the Kewaunee Nuclear Power Plant and from PBNP REMPs. As a courtesy and a convenience to the State of Wisconsin, PBNP personnel also collect certain environmental samples (Table 11-4) for the State from sites which are near PBNP sampling sites or are co-located. A typical, co-located sampling site (E-04) where air particulate and iodine as well as vegetation I samples me collected is shown in Figure Il-3. This al ,is a site where precipitation samples are collected for the State. The results of the State monitoring program are available from the Radiation Protection Unit of the WI I Department ofliealth and Family Services.
I I
I I
I I
I I
21
1 TABLE 11 1 PilNI'llADIOLOGICAL ENVIRONMENTAL SAMPLE COLLECTION FitEQUENCY Samnie Tvoe Samnle Codes Collection Frecuencv Environmental Radiation Exposure E-01, -02, -03, -04, -05, Quarterly
-06,-07,-08,-09,-12,
-14,-15,-16, 17.-18, 20,-22,-23,-24,-25,
-26, -2 7, -2 8, -29, -3 0, 31,-12 Vegetation E-01,-02,-03,-04,-06, 3x/yr as available
- -08,-09,-20 Algae E-05,-12 3x/yr as available Fish E-13 3x/yr as available Well Water E-10 Quarterly Lake Water E-01,-05,-06,-09,-12 E-12 collected weekly for monthly composite. Others collected monthly.
Milk E-11,-19,-21 Monthly Air Filters E-01, -02, -03, -04, -07., Weekly particulate filters and charcoal
-20 canisters by continuous air sampler.
Soil E-01 -02,-03,-04,-06, 2x/yr
-08,-09,-20 Shoreline Sediment E-01,-05 -06,-09,-12 2x/yr L
[
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l TABLE Il-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Location Cods Location Descrintion E-01 Meteorologica! 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 1:-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 Southeast Corner of the Intersection of Hwy.163 and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-li Dairy Farm 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, a residence about 0.25 miles North of Nuclear Road E-17 North of Mishicot, Hwy.163 and Assman Road, Northeast Corner ofIntersection E-18 Northwest 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 ~
E-20 Reference Location,17 miles Southwest, at Silver Lake College
- ~ '
E-21 Local Dairy Farm just South of Site on Lakeshore and Irish Roads E-22 West Side of Hwy. 42, about 0.25 miles North of Johanek Road 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 imersection 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-2 7 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 Tower.
E-30 NE corner at intersection of Tapawingo and Lakeshore Roads.
E-3i On utility pole North 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-33 Lake Michigan shoreline accessed from the SE corner of KNPP parking lot. Sample S of creek.
E-TC Transportation Control; Reserved for TLDs 23
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24
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25
TABLE 11-3 RECOMMENDED MINIMUM SAMPLE SIZE Samnle Tyne Size Vegetation 100-1000 grams Lake Water 8 liters 3
Air Filters 250 m Well Water 8 liters Milk 8 liters Algae 100-1000 grams Fish (edible portions) 1000 grams Soil 500-1000 grams Shoreline Sediment 500-1000 grams TABLE 11-4 SAMPLES COLLECTED FOR STATE OF WISCONSIN Samnie Tyne Location Frequency
- 1. Lake Water E-12 Weekly, Composited Monthly E-05 Quarterly
- 2. Air Filters E-07 Weekly E-08 Bruechert Residence
- 3. Fish E-13 Quarterly As Available
- 4. Precipitation E-01 Twice a month, E-04 As Available E-07 E-08 26
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At Site E-04 PBNP collects air, soil, and vegetation samples. Note also the black plastic mesh TLD cage located on the power pole. The State of Wisconsin collects air, vegetation, and precipitation. The State also has a TLD site approximately 30 feet from this location.
27
11.5 &alvtical Parameters The types of analyses and their frequencies are given in Table 11-5. The LLDs for the various analyses are found in the Results section (12) of this report (Table 12-1) with the summary of the REMP results. All environmental LLDs listed in Table 15.7.7-2 of the PBNP RETS (and also in Table 12-1) were achieved during 1997.
I 1.6 Brief Descrintion of Analvtical Parameters in Table 11-5 11.6.1 Gamma isotopic analysis Gamma isotopic analysis consists of a computerized scan of the gamma ray spectrum from 80 kev to 2048 kev. Specifically included in the scan are Mn-54, Fe-59, Co-58, Co-60, Zr-95, Nb-95, Ru-103, Ru-106.1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. However, any other nuclear power plant produced radionuclides which are present also are noted. Naturally occurring radionuclides such as Ra-226, Bi-214, Pb-212, TI-208, Ac-228, Be-7, and K-40 are frequently detected in soil, sediment, and vegetation. All radionuclides detected by gamma isotopic analysis are decay corrected to the time of collection.
I1.6.2 Gross Beta Analysis Gross beta analysis is a non-specific analyses which consists of measuring the total beta activity of the sample. No individual radionuclides are identifiable by this method. Gross beta analysis is a quick roethod of surveying samples for the presence of elevated activity which may require additional, immediate analyses.
I1.6.3 Water Samples Water samples include both Lake Michigan and well water. The well is the on-site PBNP well. The Lake Michigan samples are collected along the shoreline (Figure 11-4) at five locations north and south of PBNP.
Gross beta and gamma isotopic analytical results for water are obtained by measurements on the solids remaining after evaporation of the unfiltered sample to dryness. Ilence the results are indicated as "on total solids" in Table 11-5.
28
l TABLE 11-5 PHNP RADIOLOGICAL ENVIRONMENTAL SAMPLE ANALYSIS AND FREQUENCY Samnie Tyne Samole Codes Analyses Frecuency Environmental Radiation E-01,-02,-03,-04,-05 TLD Quarterly Exposure -06,-07,-08,-09,-12
-14,-15, 16,-17,-18,
-20, -22, -23, -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 Sr-89,90,1 131 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 1-131 Monthly Gamma Isotopic Analysis Monthly (on total solids)
Milk E 11,-19,-21 Sr-89, 90 Monthly 1 131 Gamma Isotopic Analysis Air Filters E-01, -02, 03, -04, Gross Beta Weekly (particulate)
-08,-20 1 131 Weekly (charcoal)
Gamma Isotopic Analysis Quarterly (on composite particulate filters)
Soil ' E-Oi,-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
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- 4 30
11.6.4 Air Samples Particulate air filters are allowed to decay at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before gross beta measurements are made in order for naturally occurring radionuclides to become negligible part of the total activity. Gross beta measurements serve as a quick check for any unexpected activity that may require further, immediate investigation. The particulate air filters are composited quarterly for analyses oflong-lived radionuclides such as Cs-134 and Cs-137. Charcoal filters are counted with as soon as possible so that the I-131 will undergo only minimal delay prior to analyses. ,
1 In order to insure that the air sampling pumps are operating satisfactorily, a gross leak check is performed weekly. On a quarterly frequency, a reference flow meter is connected across the face of the sampling pump with the particulate and charcoal filter in place (Figure 11-5). As necessary, the pump's flow rate is adjusted to correspond to that of the flow meter. The pumps are changed out annually for calibration and maintenance beyond that which can be accomplished in the field.
11.6.5 Vegetation Vegetation samples consist predominantly of green, growing plant material (grasses and weeds most likely to be eaten by cattle if they were present at the sampling site). Care is taken not to include any dirt associated with roots by cutting the vegetation off above the soil line.
I1.6.6 Environmental Radiation Exposure Environmental radiation exposure measurements are made with thermoluminescent dosimeters (TLDs). Each TLD used in the PBNP REMP consists of three lithium fluoride chips sealed in black plastic. The TLDs absorb the energy deposited in them by gamma rays. The gamma rays may originate from PBNP produced radionuclides or from naturally occurring radionuclides. The TLDs remain at the monitoring site for roughly three months prior to analyses and the results are reported as mrem per 7 days. Because the TLDs are constantly bombarded by naturally occurring gamma radiation, even during shipment to and from PBNP, the amount of exposure during transportation is measured using transportation controls with each shipment of TLDs to and from. The dose recorded on the transportation controls are subtracted from the monitoring TLDs in order to obtain the net in situ dose.
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12.0 RESULTS Summary of 1997 REMP Results Radiological environmental monitoring conducted at the Point Beach Nuclear Plant from January 1,1997 through December 31,1997 consisted of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, vegetation, and TLDs. The results are summarized in Table 12-1. Table 12-1 contains the following information: Sample: the type of the sample medium
Description:
the type of measurement LLD: the apriorilower 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 High: the highest measured value its associated 2s counting error Units: the units of measurement Additional information also is presented in this table. Not all of the results in Table 12-1 are required by the PBNP radiological effluent technical specifications (RETS). Non-RETS items and values are noted by an asterisk (*). For example, soil is not a good indicator for assessing small incremental releases which might occur during routine operation of PBNP (Regulatory Guide 4.5). However, soil is satisfactory for establishing long-term trends. Because soil was part of the pre-operational monitoring program, soil collection and analyses has continued for use as a long-term indicator. 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 are discussed in the narrative portion of this section. Blank values have not been subtracted from the results presented in Table 12-1. A complete listing of all the individual results obtained from the contracted analytical laboratory and the laboratory's radioanalytical quality assurance results and EPA Interlaboratory Crosscheck Program results are presented in the Appendix. 33
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13.0 DISCUSSION 13.1 TLDs All TLD results for the reporting period were within the range of values recorded in previous years. Unlike the past several years, results from Site E-12, located on l the discharge fiume pier were not some of the lowest values obtaine i by the TLDs. Similarly, E-32, approximately 1 mile west of the plant, which typically I has the highest exposure for the quarter had values comparable to the rest of the TLD results; and, like 1996, the values at E-32 were not statistically different from many of the other high values observed during the year, including the I background site some 17 miles WSW of PBNP. The fact that the average TLD results for 1997,0.87 0.11, are statistically identical to the 1996 average, 0.85io.12, even though both units were down for a considerable time period I during 1997, indicates that the environmental doses measured by the TLDs are dominated by natural sources and not by PBNP efnuents. I 3.2 Milk Radionuclide concentrations in milk continue to be indistinguishable from zero except for Sr-90 and Cs-137. These two radionuclide, which are still cycling through the environments, are attributable to the large scale atmospheric weapons tests of the 1960's, to the less frequent testing in the 70's and 80's, and to the l Chernobyl accident. That these results are common throughout the Great Lakes region and North America. The PBNP average Sr-90 of1.2 0.5 pCi/l compares I favorably with the Canadian national average of 1.6 pCi/l [B.A. Ahler and B.L. Tracy (1995), Environ. Health Prosnect.103, Suppl. 9, pp. 89-101,
" Radionuclides in the Great Lakes Basin").
13.3 Air The 1997 gross beta results are similar to the 1996 results; the minimum and 3 average values are the same but the 1997 maximum is 0.007 pCi/m lower. The I-I 131 concentration distributions for 1997 also are similar to that of 1996 with both 3 averages being 0.000 pCi/m . Figure 13-1 shows that the 1997 frequency distribution for the measured 1-131 concentrations in air are symmetrical around , 3 zero with the highest frequency falling in the -2 to +2 pCi per 1000 m interval. As discussed in Section 11.1, this is type of distribution is expected, because of the statistical nature of radioactive decay, when there is no I-131 activity present. No I-131 was emitted from PBNP during 1997. As in 1996, no cesium isotopes 36 s
Figure 13-1 1-131 Concentration ( pCi per 1000 m') Frequency Distribution 1997 l-131 CCNCENTRATION IN AIR 90 . _. 80 - l 70
>. 60-
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IdFrequency l I } 30 20 10 0 U m-
" 9 1 y 3 9 S l?
l-131(pCi/1000 m 3 ) were found in the air sam;'les. Be-7 radionuclide produce in the air by the collision of cosmic rays and atoms of otyr.n r..c ogen, and carbon in the air was found in all of the air samples (see Appendix). About '.80,000 curies of Be-7 are produced in the air over I the State of Wisconsin each year 13.4 Lake Waux For the suite of RETS specified gamma emitting radionuclides, measured concentrations continue to occur as small negative and positive values scattered I around zero. Sr-90 still persists from radioactive fallout. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. Thirteen of the 20 II-3 results are sufficiently above background to be distinguishable from zero. Many of thi within the upper range of positive results obtained from watcr " blanks" in p years,148 101 pCill. Two of the analyses produced considerably higher results than the others: the first quarter for the sample from the discharge flume and the fourth quarter { from E-01 south of PBNP. As in the past, this type of result occurs when environmental sampling occurs concomitantly with the discharge of a waste holdup tank. Waste holdup tanks are discharged at a low rate in order to keep the { resulting concentrations in Lake Michigan to a low fraction of the maximum concentration allowed by 10 CFR 20, Appendix B. Because of the low rate used 37 m
l I l l to discharge waste holdup tanks, it is not always possible to wait the several days it takes to complete the discharge before collecting a scheduled Lake Michigan water sample. When the fourth quarter samples were reanalyzed by individual l 3 months (see the results tablea in the Appendix), the result from E-01 reveals that the maximum concentration occurred in the month of December and has a value of 3336 pCi/1. This is 0.3 % of the H-3 concentration limit in Appendix B of 10 CFR 20. 13.5 Algae Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water with concentration factor over a thousand for certain radionuclides. The algae obtained from the vicinity of the discharge flume, E-12, have minute concentrations of Cs-137, Co-60, and Co-58, all of which were discharged from PBNP during 1997. North of PBNP at E-05, the Co-60 values are barely above background and appear to be false positives resulting from counting statistics. Il Co-60 really were present, minute quantities of Co-58 which was released in amounts comparable to Co-60 also should have been present. Another reason supporting the conclusion of a false positive is that the predominant current is from north to south along the western shore of Lake Michigan. The presence of Cs-137 at 0.038 i 0.012 pCi/g is consistent with the I cycling of this radionuclide within the Great Lakes. Massive resuspension events due to wind stress redistributes Cs-137 throughout Lake Michigan and make the Cs-137 more available to the algae. These events are visible on satellite photographs of the Lake. In 1976 after a Chinese weapons test, Cs-137 concentrations in algae reached 1.2 pCi/g compared to the 1997 PBNP average result of 0.030 pCi/g. 13.6 Eish The only specified radionuclide statistically different from zero in fish is Cs-137. Cs-137 was identified at the low levels given in Table 12-1 in the edible portions of all eight analyzed. The highest value of 0.082 pCi/g is down significantly from the high of 2.8 pCi/g seen in the mid-1970s during the Chinese weapons tests. 13.7 Well Water All but one of the isotopic well water resultc are small positive and negative values indistinguishable from zero. The lone exception is Cs-134 at 2.4 1.3 pCi/l. Although, this result was verified by the analytical laboratory to be the measured value, this result has been determined :o be a false positive. If the Cs-134 were real, Cs-137 should also be present because they should move through 38
the ground water at the same rate. Also, because this is a sample of subsoil water. E if the Cs-134 were the result of PBNP contamination, H-3, another PBNP effluent radionuclide which moves more readily than Cs-134 through an aquifer should also be present. Because both H-3 and Cs-137 are not present,it is concluded that I the Cs-134 result is a false positive. 13.8 Seil Cs-137 from veapons testing and Chernobyl incident fallout continue to be present in soil aamples collected as part of the PBNP REMP. The highest values occur in the ca np ground area of Point Beach State Park where campfire wood ash containing 1960s fallout is spread out on the ground after the fire is put out. I The recyclirg of Cs-137 in wood ash in this manner is found throughout the United Sta'.es. 13.9 Shoreline Sediment Shoreline sediment consists of beach sand and other sediments washed up on the i Lake Michigan shore. As in soil samples, the only non-naturally occurring radionuclide found in these samples is Cs-137. 13.10 Vegetation Although the naturally occurring radionuclides Be-7 and K-40 are found in all of the vegetation samples, the only technically specified radionuclide found is Cs-137. Two false positive identifications were made for Cs-134. The conclusion that the two were false positive is based on the absence of Cs-137 in the same sample and the fact that the Cs-134 concentrations were barely above zero. The two occurrences of Cs-137 were from the campground area of Point Beach State Park. Fallout Cs-137 from the 1960s which had been incorporated in the trees l growing at that time period now is being recycled as the trees are being used in campfires and the ashes are scattered on the ground. The occurrence of Cs-137 in I wood ash has been reported in Wisconsin and other states. 13.11 Land Use Census In accordance with the requirements of Technical Specification 15.7.7.D a visual l verification of animals grazing in the vicinity of the Point Beach Nuclear Plant site boundary was completed on August 1,1997 to ensure that the milk sampling locations remain as conservative as practicable. No significant change in the use of pasture lands was noted. As noted in 1996, the size of the dairy herd on Irish t 39 ~
Road, site E-21 has increased. Ilowever, because the cows have not moved closer to the PBNP site boundary, the point the cows are assumed to exist for the purpose of dose calculations for Appendix 1 compliance, the existing milk sampling program continues to be acceptable.
14.0 CONCLUSION
Based on the analytical results from the 786 environmental samples and from 108 sets of TLDs that comprised the PBNP REMP for 1997, PBNP effluents had a minimal, if any, measurab!e affect on the PBNP environs. These results demonstrate that the control of ellluents from PBNP continues to be acceptab.le pursuant to the ALARA criteria of 10CFR50.34a. l 40
"#7TELEDYNE l Brown Engineering Environmental Services MIDWEST LABORATORY
. onNaS$.rtt$Ns m:.nw 1847) 3 44 o FAX .44*) $n, 41.7 1
MONTHLY PROGRESS REPORT TO WISCONSIN ELECTRIC POWER COMPANY l MILWAUKEE, WISCONSIN RADIOLOGIC AL ENVIRONMENTAL MONITORING PROGRAM (REMP) FOR THE POINT BEACH NUCLEAR PLANT TWO RIVERS, WISCONSIN PREPARED AND SUBMITTED BY TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES MIDWEST LABORATORY Project Number: 8006 Reporting Period: January - December,1997 I Reviewed and I Approved by [o /C Date O2-0-98 B ' rob Te i 11.ead ( Distribution: K. Johansen, WEPCo (4 copies) FEB 131998 t
POINT BEACH NUCT FAR PI_ ANT TABLE OF CONTENTS Section h List of Tables . . iii
1.0 INTRODUCTION
. .1 2.0 LISTING OF MISSED SAMPLES . .2 s Apoendices A Interlaboratory Comparison Program Results . . A-1 B Data Reporting Conventions . . B-1 C Sampling Program and Locations . .. C-1 kk
POINT BEACH NUCLEAR PLANT LIST OF TABLES
. .u.
Iltle Pme Airbome Particulates and Iodine-131 Location E-01, Nietrological Tower . .4 Location E-02, Site Boundary Control Certer . .5 Location E-03, West Boundary . .6 Location E-04, North Boundary 7 Location E-08, G. J. Francar Residence . .S Location E-20, Silver Lake . .9 Airbome Particulates, Camma Isotopic Analyses . .10 N! ilk . .11 Well Water . .17 Lake Water . IS Lake Water, Analyses on Quarterly Composites . .24 Fish . . 23 Shoreline Sediments . .28 Soil. .30 Vegetation . . 32 Aquatic Vegetation . . 33 l Gamma Radiation, as Measured by TLDs . .34 i 1 iii
POINT BEACH NUCLEAR PLANT
1.0 INTRODUCTION
The following constitutes the final,1997 Monthly Progress Report for the Environmental Radiological Monitoring Program conducted at the Point Beach Nuclear Plant, Two Rivers, Wisconsm. Results of completed analyses are presented in the attached tables. Data tables reflect sample analysis results for both Technical Specification requirements and Special Interest locations and samples are randomly selected within the Program monitoring area to provide additional data for cross-comparisons. Data obtained in the program are well within the ranges previously encountered in the program and to be expected in the environmental media sampled. For gamma isotopic analyses, the spectrum includes the range from 80 to 204S kev, and specifically Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb95, Ru-103, Ru-106,1-131, Ba-La 140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as K-40 and Ra daughters, are frequently detected in soil and sediment samples. Specific isotopes listed are K-40, TI-20S, Pb-212, Bi-214, Ra-226 and Ac-22S. Unless noted otherwise, the results reported under "Other Gammas" are for Co-60 and may be higher or lower for other radionuclides. All concentrations, except gross beta, are decay corrected to the time of collection. All samples were collected within the scheduled period unless noted otherwise in the 1.isting of Missed Samples. 1
I POINT BEACH Ni1 CLEAR PLANT 2.0 LISTING OF MISSED SAMPLFS Expected Collect:on Sample Type Location Date Reason LW E-6 Feb,1997 Sample not collected due to extremely icy conditions. AP/Al E-4 10/6/97 Equipment failure. NOTE: Page 3 is intentionally lef t out. 2
POINT BEACH NUCLEAR PLANT AIRBORNE IODINE-131 AND GROSS BETA IN AIR PARTICULATE FILTERS E-01 Meteorotocical Tower Date Volume Gross Beta Iodine-131 Date Volume Gross Beta Iodine-131 Collected (m') (pCi/m') (pCi/ m') Collected (m') 2 f oCi/ m ) t oCi / m') Recuired LLD Q_Q10 0 030 0 010 g 01-08-97 433 0.032 : 0.003 0.001 : 0.007 07-08-97 302 0.011 : 0.003 -0.012 : 0.012 01-14-97 274 0.026 : 0.003 0.003 : 0.012 07-15-97 302 0.017 : 0.003 0.005 : 0.012 01-21-97 325 0.031 t 0.003 -0.005 0.010 07-22-97 302 0.023 : 0.003 -0.004 : 0.012 01-23 97 306 0.027 0.003 0.010 0.010 07-29-97 301 0.01S : 0.003 0.014 : 0.011 02-05-97 351 0.044 0.003 0.004 : 0.00S 03-05-97 303 0.019 : 0.003 0.003 : 0.011 02 11-97 272 0.029 : 0.003 0.001 0.013 OS-12-97 304 0.01S 0.003 -0.014 : 0.013 02-18-97 320 0.033 0.003 0.004 t 0.009 08-19-97 302 0.014 : 0.003 0.003 : 0.011 02-25 97 314 0.030 0.003 0.005 0.010 OS-26-97 301 0.017 0.003 0.00S 0.013 03-04-97 249 0.023 0.003 -0.014 0.014 09-02-97 304 0.016 : 0.003 -0.002 : 0.011 03-11-97 249 0.017 0.003 0,00S 0.014 09-09-97 300 0.01S = 0.003 -0.016 0.014 03-1S-97 255 0.029 0.004 0.011 0.015 09 16-97 306 0.027 : 0.003 0.002 : 0.010 03-25 97 253 0.019 : 0 004 -0.006 0.016 09-23-97 302 0.024 0.003 -0.004 : 0.011 04-01-97 24S 0.021 0.003 0.000 0.000 09-30-97 303 0.020 : 0.003 -0.00S 0.011 1st Quarter 0.023 0.007 0.002 0.007 3rd Quarter 0.019 0.004 -0.002 : 0.009 04 08-97 251 0.024 : 0.003 -0.020 0.014 10-06-97 257 0.030 0.004 -0.001 t 0.010 04-15-97 293 0.02S 0.003 -0.00S 0.008 10-13-97 302 0.031 0.003 -0.003 : 0.00S 04 22-97 293 0.02S 0.004 0.003 0.013 10-21-97 345 0.021 0.003 -0.005 0.011 04-29-97 292 0.016 0.003 -0.010 : 0.013 10-2S-97 305 0.015 0.003 -0.004 : 0.012 05-06-97 302 0.016 0.003 -0.000 : 0.009 11-04-97 301 0.026 0.003 -0.005 : 0.00S 05-13-97 2S5 0.015 0.003 -0.009 : 0.014 11-11-97 302 0.011 0.003 -0.010 : 0.013 05-21-97 325 0.010 0.002 0.001 0.010 11-1S-97 302 0.019 0.003 -0.011 0.013 05-27-97 242 0.010 0.003 0.006 0.013 11-25-97 304 0.043 t 0.004 -0.000 0.011 06-03-97 285 0.016 0.003 -0.005 t 0.011 12-02-97 306 0.034 0.003 0.005 0.012 06-10-97 301 0.019 t 0.003 -0.001 0.013 12-09-97 300 0.012 0.003 0.001 t 0.011 06-17-97 303 0.016 0.003 0.001 : 0.013 12 16-97 301 0.022 : 0.003 0.001 : 0.011 06-24-97 311 0.018 0.003 0.000 0.011 12-22-97 260 0.025 0.004 0.003 : 0.010 07-01-97 312 0.019 0.003 0.0'15 0.016 12 29-97 302 0.027 0.003 0.003 t 0.009 2nd Quarter 0.018 0.006 -0.002 : 0.00S 4th Quarter 0.024 0.009 -0.002 : 0.005 4
I: l l POlbir BEACH NUCLEAR PLANT AIRBORNE IODINE-131 AND GROSS BETA IN AIR PARTICULATE FILTERS E-02 Site Boundary Control Center Date Volume Gross Beta Iodine-131 Date Volume Gross Beta Iodine-131 E m Collected (m') (pCi/m') (pCi/m') Collected (m') (oCi / m') (oCi / m') Reauired LLD qq1g qg,3g g g 07-08-97 302 0.013 : 0.003 0.003 : 0.013 01-08-97 395 0.032 0.003 0.008 0.007 01-14-97 254 0.023 0.003 -0.004 0.014 07-15-97 302 0.019 0.003 0.001 : 0.013 01-21-97 301 0.025 0.003 0.015 : 0.011 07-22-97 302 0 023 : 0.003 0.002 0.008 E 302 0.020 0.003 -0.002 0.011 07-29-97 301 0.020 : 0.003 0.007 : 0.011 g 01 28-97 02-05-97 347 0.035 0.003 0.004 0.009 08-05-97 303 0.022 0.003 0.004 : 0.012 02-11-97 259 0.022 0.003 0.011 0.015 08-12-97 303 0.020 : 0.003 -0.001 0.013 g 08-19-97 303 0.021 0.003 0.007 : 0.011 us 02-18-97 304 0.027 0.003 -0.002 0.011 02-25-97 302 0.025 0.003 -0.010 0.011 08-26-97 301 0.020 0.003 -0.003 0.014 03-04-97 301 0.017 0.003 -0.002 0.012 09-02-97 304 0.018 0.003 0.002 0.011 03-11-97 299 0.018 0.003 -0.010 0.013 09-09-97 300 0.020 0.003 -0.013: 0.013 03-18-97 307 0.024 0.003 0.003 0.012 09-16-97 304 0.029 0.004 -0.011 0.012 03-25-97 303 0.015 0.003 0.011 0.014 09-23-97 303 0.023 0.003 -0.001 0.011 04-01-97 301 0.019 0.003 0.000 0.000 09-30-97 303 0.020 0.003 0.007 0.012 3rd Quarter 0.021 0.004 0.001 : 0.007 1st Quarter 0.023 0.006 0.002 0.003 10-06-97 257 0.030 0.004 0.004 0.011 C E< 04-08-97 300 0.019 0.003 0.004 0.010 04-15-97 301 0.024 0.003 -0.002 0.009 10-13-97 301 0.030 : 0.003 -0.004 0.00S 04-22-97 302 0.029 0.004 0.011 0.011 10-21-97 345 0.018 0.003 0.004 0.010 04-29-97 300 0.016 0.003 0.001 0.013 10-23-97 305 0.015 0.003 -0.003 : 0.011 05-06-97 302 0.017 0.003 0.007 0.008 11-04-97 303 0.024 0.003 -0.007 0.017 05-13-97 303 0.012 0.002 -0.001 0.008 11-11-97 301 0.012 0.003 -0.023 0.013 05-21-97 345 0.010 0.002 -0.007 0.010 11-18-97 302 0.022 0.003 -0.003 0.012 05-27-97 258 0.010 t 0.003 0.004 0.018 11-25-97 303 0.044 0.004 0.001 0.012 06-03-97 305 0.017 0.003 -0.009 0.012 12-02-97 306 0.034 0.003 0.009 0.011 06-10-97 301 0.019 0.003 -0.007 0.011 12-09-97 299 0.008 : 0.002 -0.003 0.011 l 06-17-97 306 0.016 0.003 -0.001 0.012 12-16-97 301 0.025 0.003 -0.006 0.010 l 06-24-97 301 0.016 0.003 -0.007 0.013 12-22-97 259 0.025 0.004 0.002 t 0.010 07-01-97 302 0.013 : 0.002 0.005 0.017 12-29 97 302 0.026 0.003 0.001 : 0.008 2nd Quarter 0.017 0.005 -0.000 : 0.006 4th Quarter 0.024 0.010 -1002 0.008 I I 5 I
POINT BEACH NUCLEAR PLANT AIRBORNE IODINE-131 AND GROSS BETA IN AIR PARTICULATE FILTERS E-03 West Boundarv Date Volume Gross Beta Iodine-131 Date Volume Gross Beta todine 131 Collected (m') (pCi/m') (pCi/m') Collected (m') (oCi/ m') WCi / m'i Reauired LLD 0 010 m g g 01-0S-97 439 0.024 ! 0.002 0.002 : 0.007 07-08-97 320 0.009 : 0.003 0.012 : 0.012 01-14-97 252 0.024 0.003 0.004 0.012 07-15-97 309 0.01S : 0.003 0.009 : 0.011 01-21-97 301 0.024 : 0.003 -0.010 0.011 07-22-97 294 0.021 : 0.003 -0.016 : 0.014 01-2S-97 304 0.020 0.003 0.001 0.010 07-29-97 301 0.017 0.003 0.003 : 0.011 02-05-97 346 0.036 : 0.003 0.001 : 0.009 08-05-97 303 0.020 : 0.003 0.006 : 0.011 02 11-97 258 0.025 : 0.00' -0.007 0.014 03-12-97 303 0.017 : 0.003 0.007 : 0.012 02-1S-97 304 0.031 0.003 -0.005 : 0.011 08-19-97 303 0.023 : 0.003 0.002 : 0.011 02-25-97 303 0.027 0.003 0.002 : 0.010 08 26-97 301 0.020 : 0.003 0.011 : 0.013 03-04-97 302 0.020 : 0.003 -0.000 0.011 09-02 97 305 0.01S 0.003 -0.005 : 0.011 03-11-97 29S 0.01S : 0.003 -0.014 0.014 09-09-97 301 0.021 : 0.003 -0.010 : 0.012 03-10 97 307 0.022 : 0.003 0.005 t 0.011 09-16-97 304 0.031 0.004 -0.006 0.012 03-25-97 304 0.015 0.003 -0.003 : 0.010 09-23-97 302 0.022 0.003 -0.001 0.010 04-01-97 300 0.019 0.003 0.000 0.000 09-30-97 303 0.019 : 0.003 -0.006 : 0.013 1st Quarter 0.023 0.006 -0.002 : 0.006 3rd Quarter 0.020 : 0.005 0.000 1 0.009 04-08-97 306 0.018 0.003 0.004 0.011 10-06-97 257 0.031 : 0.004 0.006 0.012 04 15-97 298 0.025 : 0.003 0.002 : 0.008 10-13-97 30' O.032 2 0.003 -0.003 : 0.00S 04-22-97 '93 _ 0.021 0.003 -0.010 0.013 10-21-97 345 0.01S 0.003 -0.003 : 0.010 04-29-97 290 0.016 0.003 0.010 0.012 10-23-97 304 0.014 0.003 0.010 0.011 05-06-97 302 0.016 : 0.003 0.003 0.009 11-04-97 304 0.024 : 0.003 -0.005 : 0.011 05-13-97 303 0.011 0.002 0.002 0.012 11-11-97 301 0.011 0.003 0.003 0.011 05-21-97 346 0.011 0.002 -0.009 0.011 11-IS-97 302 0.023 : 0.003 0.009 0.011 05-27-97 257 0.010 0.003 -0.007 0.012 11-25 07 308 0.044 0.004 0.007 : 0.011 06-03-97 305 0.013 0.003 0.012 0.010 Iw97 322 0.035 : 0.003 -0.000 0.011 06-10 97 290 0.022 0.003 0.001 0.011 12 09-97 319 0.006 0.002 -0.001 : 0.010 06-17-97 295 0.017 0.003 0.003 0.011 12-16-97 301 0.029 : 0.003 0.003 0.011 06-24-97 302 0.014 : 0.t03 0.007 0.010 12-22-97 277 0.024 0.003 0.001 : 0.009 07-01 97 291 0.020 0.003 0.0'1 1 0.018 12 29-97 322 0.026 : 0.003 0.002 0.009 2nd Quarter 0.016 : 0.005 0.002 0.007 4th Quarter 0.025 : 0.010 0.002 : 0.005 6
~
l i l POINT BEACH NUCLEAR PLANT AIRBORNE IODINE-131 AND GROSS BETA IN AIR PARTICULATE FILTERS E-04 North Boundary Date Volume Gross Beta Iodine-131 Date Volume Gross Beta lodine-13 E Collected (m') (pCi/m') (pCi/m') _ Collected ( m'1 (pCi / m') (oCi/t r') W Recuired LLD g qq3g g g 01-08-97 426 0.029 0.003 -0.005 0.007 07-08-97 327 0.012 0.003 0.000 : 0.012 01-14-97 264 0.025 0.003 0.014 0.014 07-15-97 333 0.017 0.003 0.013 : 0.019 01-21-97 321 0.026 0.003 0.000 0.010 07-22-97 319 0.023 0.003 0.004 : 0.007 g 01-28-97 324 0 018 0.003 -0.001 0.011 07-29-97 301 0.022 0.003 0.006 : 0.013 3 08-05-97 32S 0.023 : 0.003 0.011 : 0.011 02-05-97 369 0.040 0.003 -0.004 : 0.008 02-11-97 275 0.025 0.003 0.005 0.015 08-12-97 327 0.019 0.003 0.005 : 0.012 g; 08-19-97 327 0.018 0.003 -0.013 : 0.012 5 02-18-97 324 0.026 : 0.003 0.009 t 0.010 02-25-97 338 0.026 0.003 0.003 0.009 08-26-97 3 25 0.017 0.002 -0.010 : 0.013 03-04-97 S2 0.019 0.003 0.000 0.011 09-02-97 329 0.018 2 0.003 -0.007 : 0.011 03-11-97 297 0.019 0.003 -0.001 0.013 09-09-97 325 0.016 0.003 -0.010 : 0.011 l l 03-18-97 307 0.026 0.003 0.004 0.013 09-16-97 32S 0.023 : 0.003 -0.005 0.011 03-25-97 301 0.019 0.003 0.005 : 0.011 09-23-97 326 0.023 0.003 -0.001 0.011 l 04-01-97 302 0.016 0.003 0.000 0.000 09-30-97 327 0.020 : 0.003 0.00S : 0.012 3rd Quarter 0.019 : 0.003 0.000 = 0.009 1st Quarter 0.024 0.006 0.000 = 0.006 04-08-97 290 0.021 0.003 0.011 0.012 10-06-97 ND' - - 04-15-97 299 0.021 0.003 0.003 0.003 10-13-97 306 0.027 0.003 0.006 0.009 04-22-97 288 0.026 0.004 0.004 0.012 10-21-97 356 0.015 0.002 0.007 0.009 04-29-97 275 0.015 0.003 -0.012 : 0.014 10-28-97 313 0.016 0.003 -0.005 0.012 g 05-06-97 282 0.018 0.003 -0001 0.010 11-04 97 313 0.023 0.003 -0.006 0.020 5 05-13-97 303 0.013 0.003 0.001 0.006 11-11-97 310 0.009 0.002 0.005 0.012 05-21-97 345 0.010 0.002 -0.003 0.010 11-18-97 311 0.017 0.003 0.001 0.012 ' 05-27-97 257 0.011 0.003 -0.004 0.013 11-25-97 312 0.038 0.004 -0.004 t 0.011 06-03-97 296 0.013 0.003 -0.001 0.012 12-02-97 316 0.033 0.003 -0.003 : 0.011 06-10-97 323 0.017 0.003 0.012 0.010 12-09-97 306 0.010 0.002 -0.000 : 0.010 06-17-97 341 0.016 0.003 0.011 0.011 12-16-97 302 0.024 : 0.003 0.003 : 0.012 06-24-97 342 0.016 0.003 -0.003 0.010 12-22-97 268 0.024 0.003 0.006 0.009 g 07-01-97 331 0.021 0.003 0.006 0.018 12-29-97 311 0.023 0.003 -0.001 0.009 g 0.002 0.007 4th Quarter 0.022 0.009 0.001 : 0.004 2nd Quarter 0.017 0.005 I
= =s - ata.e _ gie m1,s . o ,uig _ m 1u,e. I
_g g
POINT BEACH NUCLEAR PLANT AIRBORNE IODINF-131 AND GROSS BETA IN AIR PARf!CULATE FILTERS E-08 C. T. Francar Residence Date Volume Gross Beta Iodine-131 Date Volume Gross Beta lodine-131 Collected (m') (pCi/m') (pCi/m') Collected (mh (oCi/mh InCi / mh Reauired LLD g ggqg} g g I 01-0S-97 01-14-97 399 250 0.029 0.003 -0.001 0.007 0.021 0.003 -0.013 0.014 07-08-97 278 0.010 : 0.003 -0.002 : 0.013 07-15-97 279 0.020 : 0.003 0.004 : 0.021 01-21-97 291 0.024 0.003 -0.001 0.011 07-22-97 278 0.021 : 0.003 -0.001 : 0.009 L 1 01-2S-97 313 0.019 0.003 0.001 0.011 07-29-97 299 0.021 : 0.003 0.007 : 0.011 02-05-97 370 0.030 : 0.003 0.000 0.003 OS-05-97 277 0.023 : 0.004 0.001 : 0.012 02-11-97 275 0.021 0.003 -0.005 0.014 08-12-97 2S9 0.014 :0.003 -0.004 : 0.014 02-1S-97 323 0.025 : 0.003 0.012 : 0.009 08-19-97 237 0.015 : 0.003 -0.008 = 0.013 02-25-97 323 0.023 : 0.003 0.001 0.009 OS-26-97 277 0.019 0.003 0.013 : 0.013 I 03-04-97 03-11-97 302 297 0.016 i 0.003 -0.008 0.011 0.017 : 0.003 0.001 0.013 09-02-97 09-09-97 2SO 0.020 0.003 0.007 : 0.013 277 0.016 : 0.003 -0.003 : 0.014 03-18-97 307 0.026 0.003 0.007 0.012 09-16-97 2SO 0.022 : 0.003 -0.001 : 0.012 I 03-25-97 304 0.014 0.003 -0.002 0.012 09-23-97 278 0.022 : 0.003 -0.003 : 0.011 04-01-97 300 0.015 0.003 0.000 : 0.000 09-30-97 2SS 0.017 : 3.003 0.001 : 0.013 1st Quarter 0.022 : 0.005 -0.001 : 0.006 3rd Quarter 0.019 : 0.004 0.001 : 0.006 04-08-97 0.019 0.003 -0.012 0.013 10-06-97 241 0.029 : 0.004 0.004 : 0.012 I 04-15-97 305 301 0.022 : 0.003 -0.002 0.009 10-13-97 273 0.030 0.004 -0.002 : 0.010 04-22-97 301 0.019 0.003 -0.007 0.012 10-21-97 318 0.017 : 0.003 0.000 : 0.012 04-29-97 301 0.014 0.003 -0.002 0.012 10-23-97 2SO 0.015 : 0.003 -0.002 0.013 05-06-97 304 0.015 : 0.003 -0.009 0.009 11-04-97 2SO 0.023 0.003 0.003 0.009 05-13-97 290 0.014 0.003 0.006 0.016 11-11-97 278 0.014 0.003 0.016 0.013 05-21-97 345 0.009 0.002 0.006 0.009 11-18-97 277 0.022 0.003 0.010 0.012 05-27-97 257 0.010 0.003 -0.018 0.015 11 25-97 2S0 0.040 0.004 0.001 0.014 06-03-97 308 0.014 : 0.003 -0.001 : 0.011 12-02-97 2S2 0.031 : 0.003 -0.007 : 0.012 1 06-10-97 276 0.017 : 0.003 0.007 : 0.013 12-09-97 271 0.008 0.003 -0.004 0.014 06-17-97 2S2 0.01S 0.003 -0.004 0.012 12-16-97 279 0.025 : 0.003 0.003 : 0.012 06-24-97 278 0.016 t 0.003 -0.000 0.013 12-22-97 255 0.025 0.004 -0.003 : 0.011 07-01-97 277 0.022 0.003 -0.001 0.020 12-29-97 296 0.027 0.003 0.011 0.009 2nd Quarter 0.016 0.004 -0.003 : 0.007 4th Quarter 0.024 0.008 0.003 0.007 I I ~ 8
I POINT BEACH NUCLEAR PLANT AIRBORNE IODINE-131 AND GROSS BETA IN AIR PARTICULATE FILTERS E-20 Silver L A Date Volume Gross Beta Iodine-131 Date Volume Gross Beta lodine-131 Collected (m') (pCi/m') (pCi/m') Collected (m ) 3 (oCi / m') ( eCi / m') Recuired LLD g g g 01-08-97 395 0.030 0.003 0.002 0.007 07-08-97 304 0.010 0.003 -0.002 : 0.011 01-14-97 255 0.023 0.003 0.011 0.013 07-15-97 298 0.018 0.003 0.002 : 0.021 01-21-97 302 0.027 0.003 -0.000 0.011 07-22-97 308 0.022 : 0.003 -0.011 : 0.010 g 01-28-97 301 0.019 0.003 0.006 0.012 07-29-97 300 0.019 : 0.003 -0.006 : 0.012 3 02-05-97 347 0.030 0.003 0.002 : 0.009 08-05-97 307 0.023 0.003 -0.007 : 0.011 02-11-97 263 0.023 0.003 0.008 0.015 08-12 47 299 0.020 : 0.003 -0.016 0.015 02-18-97 29S 0.028 0.003 0.001 0.012 08-19-97 302 0.014 0.003 0.007 0.010 02-25-97 303 0.022 0.003 0.010 0.011 08-26-97 302 0.017 : 0.003 0.008 : 0 014 03-04-97 305 0.017 0.003 -0.012 0.012 09-02-97 302 0.016 : 0.003 -0.004 : 0.012 03-11-97 294 0.015 0.003 -0.014 0.016 09-09-97 302 0.022 0.003 -0.012 : 0.013 03-18-97 306 0.027 ! 0.004 0.006 0.012 09-16-97 302 0.023 : 0.003 -0.006 : 0.012 03-25-97 304 0.015 0.003 0.001 0.011 09-23-97 304 0.022 : 0.003 -0.006 : 0.012 04-01-97 303 0.017 0.003 0.000 0.000 09-30-97 312 0.017 : 0.003 -0.001 : 0.013 1st Quarter 0.023 0.006 0.002 2 0.008 3rd Quarter 0.019 2 0.004 -0.004 0.007 04-08-97 289 0.018 t 0.003 0.001 ! 0.013 10-06-97 254 0.037 0.004 0.001 0.013 04-15-97 304 0.022 0.003 0.002 0.008 10-13-97 297 0.032 0.003 0.004 0.010 04-22-97 303 0.024 0.003 0.002 0.011 10-21-97 348 0.017 0.003 -0.005 0.010 04-29-97 292 0.019 0.003 0.010 0.013 10-28-97 304 0.016 0.003 -0.005 0.010 05-06-97 303 0.019 0.003 0.010 0.009 11-04-97 303 0.023 0.003 0.001 : 0.020 05-13-97 298 0.012 0.002 0.002 0.008 11-11-97 302 0.015 0.003 -0.013 0.012 05-21-97 344 0.008 0.002 0.011 0.009 11-18-97 299 0.023 : 0.003 -0.000 0.012 05-27-97 260 0.011 0.003 -0.005 0.012 11-25-97 304 0.047 0.004 0.003 0.012 06-03-97 307 0.015 0.003 0.010 0.010 12-02-97 319 0.032 0.003 -0.011 0.011 06 10-97 299 0.019 0.003 -0.012 0.012 12-09-97 300 0.010 0.002 -0.008 : 0.013 06-17-97 303 0.015 0.003 0.005 0.013 12-16-97 298 0.024 0.003 0.002 0.011 06-24-97 302 0.017 0.003 -0.006 0.011 12-22-97 259 0.025 0.004 0.001 0.010 g 07-01-97 292 0.022 0.003 0.017 0.018 12-29-97 302 0.022 : 0.003 -0.002 0.010 3 2nd Quarter 0.017 0.005 0.004 0.008 4th Quarter 0.025 0.010 -0.003 0.005 I I 9 I
POINT BEACH NUCLEAR PL ANT l CAMMA EMITTERS IN QUARTERLY COMPOSITES OF h AIR PARTICULATE FILTERS l (Concentration pCi/m') Location Lab Code Be-7 Cs-134 Cs-137 Other Gammas' 1st Guarter 1Q47 E-01 EAP- 1992 0.080 0.009 0.0001 0.0001 0.0001 t 0.0004 0.0002 0.0002 l E-02 - 1993 0.088 : 0.014 -0.0001 : 0.0003 -0.0002 : 0.0004 0.0006 : 0.00ii ! E-03 - 1994,5 0.067 0.008 -0.0001 0.0008 -0.0002 : 0.0004 0.0000 : 0.0007 E-04 - 1996 0.070 0.015 -0.0007 : 0.0027 -0.0004 : 0.0007 0.0005 : 0.0023 E-08 - 1997 0.074 0.017 -0.0001 t 0.0015 0.0005 0.0007 0.0000 t 0.0000 E-20 1998 0.071 ! 0.010 0.0003 0.0005 0.0004 : 0.0004 0.0002 t 0.0005 2nd Ouarter.1997 l E-01 EAP- 4912 0.105 0.012 0.0000 0.0002 0.0000 0.0005 0.0003 0.0003 E-02 4913 0.100 0.013 0.0000 0.0001 0.0002 : 0.0004 0.0001 : 0.0001 E-03 4914 0.093 0.013 0.0001 0.0082 0.0001 0.0005 0.0001 : 0 0019 E-04 4915 0.100 0.012 0.0005 0.0007 0.0002 : 0.0004 0.0000 : 0.0000 E-08 4916 0.089 0.012 0.0002 0.0009 -0.0002 : 0.0005 0.0009 0.0006 E-20 4917 0.093 0.013 0.0002 : 0.0003 0.0005 0.0004 0.0002 0.0003 3rd Ouarter.1997 l E-01 EAP- 8029 0.088 0.017 0.0001 0.0001 0.0001 0.0006 0.0003 0.0002 E-02 8030 0.097 0.012 0.0009 0.0022 -0.0008 0.0006 0.0001 0.0002 E-03 8031 0.089 0.014 -0.0006 0.0006 0.0006 0.0005 0.0005 0.0320 E-04 8032 0.093 0.014 -0.0002 0.0003 0.0004 : 0.0005 0.0008 : 0.0130 E-08 8033 0.074 0.013 0.0004 0.0011 -0.0006 0.0005 0.0015 0.0080 E-20 8034 0.092 0.014 0.0005 t 0.0010 -0.0003 0.0005 -0.0001 0.0002 4th Ouarter.1997 E-01 EAP- 10170 0.060 0.011 -0.0002 0.0002 0.0000 t 0.0004 0.0001 : 0.0004 E-02 10171 0.068 0.009 0.0000 0.0001 -0.0001 2 0.0003 0.0002 0.0010 ) E-03 10172 0.058 0.015 0.0004 0.0005 -0.0003 : 0.0006 0.0004 : 0.0014 1 E-04 10173 0.060 0.008 0.0004 0.0003 0.0001 0.0003 0.0003 0.0012 E-08 10174 0.063 0.008 0.0001 0.0001 0.0002 0.0003 -0.0002 : 0.0005 E-20 10175 0.067 0.008 0.0000 0.0001 0.0000 : 0.0001 0.0002 0.0003
- See Introduction 10
l ( PONT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES 4, (Monthly Collections) Sample Description and Concentration (pCi/L) E-11 Funk Dairy Farm Required Collection Date 01-08-97 02-12-97 03-12-97 LLD Lab Code EMI-87 EMI-70S EMI-1255 Sr-89 -0.4 1.3 0.2 : 0.7 0.7 : 1.0 5.0
$r-90 1.6 0.4 0.9 0.3 0.5 0.3 1.0 I-131 -0.19 0.18 0.17 0.20 0.01 0.13 0.5 K-40 1360 70 1450 110 1500 90 Cs-134 -1.6 1.9 -0.7 1.2 0.9 1.6 5.0 Cs-l'47 1.6 1.8 1.0 t 2.5 1.9 : 2.1 5.0 Ba-La-140 0.6 1.7 -5.4 54.1 2.5 : 11.4 5.0 Other Gammas' O.5 2.2 0.3 12.5 0.2 : 0.3 15.0 Collection Date 04-09-97 05-14-97 06-04-97 Lab Code EMI-1844 EMI-3037 EMI-3715 St-89 0.2 1.3 -1.5 0.9 0.4 1.0 5.0 Sr-90 1.0 0.3 2. 0 0.4 0.8 0.3 1.0 1-131 -0.04 : 0.20 0.11 0.14 -0.04 = 0.17 0.5 K-40 1460 t 70 1490 : SO 1490 1220 Cs-134 0.1 0.1 1.5 1.8 -1.1 1.5 5.0 Cs-137 0.6 1.5 2.4 1.8 0.3 2.3 5.0 Ba-La-140 -1.0 8.5 -0.1 : 1.9 -0.3 : 0.4 5.0 Other Gammas' O.7 2.4 -0.6 2.8 1.9 5.2 15.0
' See Introduction.
11 l
I POINT BEACH NUCLEAR PLANT g RADIOACTIVITY IN MILK SAMPLES 5 ! (Monthly Collections) Sample Description and Concentration (pCi/L) E-11 Funk Dairy Farm Required Collection Date 07-09-97 08-13-97 09 10-97 LLD Lab Code EMI-4639 EMI-5819 EMI-6578 Sr-89 -0.9 1.2 0.8 1.0 -0.8 : 0.S 5.0 l St-90 1.4 0.4 0.8 0.3 0.5 : 0.3 1.0 1-131 0.00 0.13 0.14 0.14 0.01 : 0.14 0.5 K-40 1420 120 1440 90 1440 130 Cs-134 1.1 0.7 1.0 2.8 0.1 : 1.6 5.0 Cs-137 0.7 2.5 -0.6 1.9 -1.13.4 5.0 g Ba-La-140 -0.6 2.1 -0.5 7.9 -0.9 2.2 5.0 g Other Gammas' -2.6 4.2 1.9 3.2 0.6 1.1 15.0 Collection Date 10-01 97 11-05-97 12-10-97 Lab Code EMI-7512 EMI-8584 EMI-9525 St-89 -1.4 0.9 -0.2 1.2 -0.4 0.7 5.0 Sr-90 1.8 0.4 1.1 0.3 0.7 0.3 1.0 I-131 -0.13 0.16 0.03 0.11 0.14 0.19 0.5 K-40 1470 120 1470 70 1350 110 Cs-134 0.2 0.2 0.0 0.1 0.5 0.7 5.0 Cs-137 2.1 2.9 -0.1 1.5 1.0 : 2.7 5.0 g Ba-La-140 2.4 3.1 1.5 38.7 -2.2 : 4.7 5.0 W Other Gammas' 1.4 2.5 0.7 : 1.2 0.3 1.1 15.0
- See introduction.
I
-3 12
POINT BEACH NUCLEAR PLANT , l 1 % RADIOACTIVITY IN MILK SAMPLES (Monthly Collections) . l Sample Description and Concentration (pCi/ L) i E-lo Engelbrecht Dain-Required Collection Date 01-08-97 02-12-97 03-12-97 LLD Lab Code EMI-88 EMI-709 EMI-1256 l Sr-89 -1.4 1.2 0.5 0.8 -0.7 : 1.0 5.0
$r-90 1.7 : 0.4 1.40.4 1.S : 0.4 1.0 l
I-131 -0.13 0.18 -0.06 0.17 -0.02 t 0.14 0.5 K-40 1470 :70 1400 120 1630 100 Cs-134 -0.2 1.4 0.7 3.6 -0.8 5.3 5.0 Cs-137 2.1 1.5 2.7 2.6 -0.5 2.2 5.0 Ba-La-140 -1.0 1.3 1.7 2.5 -0.9 : 3.3 5.0 Other Gammas' O.3 : 1.9 3.0 : 6.9 0.6 :S 15.0 Collection Date 04-09-97 05-14-97 06-04-97 Lab Code EMI-1845,6 EMI-3038 EMI-3716 Sr-89 0.0 0.S 0.5 : 1.0 0.6 1.1 5.0 Sr-90 1.1 : 0.2 1.7 0.4 1.2 : 0.4 1.0 I-131 -0.17 0.16 -0.14 = 0.20 -0.06 0.14 0.5 K-40 1580 70 1500 120 1480 160 Cs-134 0.4 1.1 -1.7 8.5 -1.7 1.3 5.0 Cs-137 0.7 1.5 2.0 2.7 -1.8 : 33.7 5.0 Ba-La-140 0.3 6.0 0.9 3.3 0.21.0 5.0 Other Gammas' -0.9 : 11.2 -0.5 1.0 0.8 : 4.2 15.0
- See Introduction.
13
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections) Sample Description and Concentration (pCi/L) E-lo Engelbrecht Dairv Required Collection Date 07-09-97 08-13-97 09-10-97 LLD Lab Code EMI-4640 EMI-5820 EMI-6579 St-89 0.4 1.1 -1.4 1.5 -0.2 : 1.4 5.0 $r-90 1.4 0.4 2.1 0.5 1.7 : 0.4 1.0 1-131 -0.08 0.14 -0.08 0.13 0.03 ! 0.14 0.5 K-40 1445 96 1490 100 1430 ! 150 Cs-134 0.2 0.3 1.4 6.9 -2.9 9.5 5.0 Cs-137 1.0 2.1 0.3 2.0 -0.3 : 3.3 5.0 Ba-La-140 0.4 2.3 1.2 1.4 3.9 : 11.5 5.0 Other Gammas' O.6 2.5 1.6 : 6.3 1.6 3.1 15.0 Collection Date 10-01-97 11-05-97 12-10-97 Lab Code FMI-7517 EMI-8585 EMI-9526 Sr-89 0.4 0.8 0.5 1.2 0.6' O.8 5.0 Sr-90 1.0 0.3 1.3 0.3 1.3 : 0.3 1.0 1-131 -0.22 0.17 0.08 0.12 0.04 0.17 05 K-40 1400 110 1560 110 1450 110 Cs-134 -1.4 1.9 1.9 : 1.3 2.7 : 4.8 5.0 Cs-137 1.6 2.7 1.0 2.1 -0.9 2.3 5.0 Ba-La-140 2.4 43.5 -1.5 : 3.3 0.4 28.7 5.0 Other Gammas' -1.4 3.2 1.2 3.5 0.1 14.6 15.0
- See introduction.
I _g 14
POINT BEACH NUCLEAR PLANT d, RADIOACTIVITY IN MILK SAMPLES (Monthly Collections) Sample Description and Concentration (pCi/L) E-21 Strutz Dairv Farm kequired I Collection Date 01-08-97 02-12-97 03-12-97 LLD Lab Code EMI-89 EMI-710 EMI-1257 Sr-89 -2.2 : 1.7 -0.2 ! 0.7 -0.1 0.8 5.0 Sr-90 1.8 0.5 1.4 0.3 0.9 0.3 1.0 1-131 -0.17 0.16 -0.07 0.1S -0.09 0.12 0.5 i K-40 Cs-134 1550 : 50 0.4 1.1 1540 110 1.1 4.4 1450 : 100 1.3 : 2.0 5.0 Cs-137 -0.6 1.0 -1.1 2.4 -1.0 : 2.4 5.0 Ba-La-140 -0.5 0.9 -1.4 36.1 1.6 : 5.5 5.0 1 Other Gammas' -0.6 : 1.2 0.S 2.2 0.3 : 0.3 , 15.0 Collection Date 04-09-97 05-14-97 06-04-97 Lab Code EMI-1847 EMI-3039 EMI-3717 Sr-89 -0.9 1.0 -0.2 0.8 -1.6 0.7 5.0 Sr-90 1.3 0.3 1.0 0.3 0.9 0.3 1.0 I-131 -0.18 0.17 0.02 0.15 -0.15 = 0.16 0.5 K-40 1540 80 1640 100 1670 120 Cs-134 0.3 0.5 -0.1 0.2 1.527.1 5.0 Cs-137 0.3 1.8 0.5 2.3 2.3 : 2.5' 5.0 Ba-La 140 -0.8 3.5 0.8 1.3 -1.1 2.6 5.0 Other Gamrnas' -0.2 0.5 1.2 1.2 -0.3 0.9 15.0
- See Introduction.
- Corrected result.
L c L 15 r
I POINT BEACH NUCLEAR PLANT gI g ! l RADIOACTIVITY IN MILK SAMPLES i (Monthly Collections) Sample Description and Concentration (pCi/L) I E-21 Strutz Dairy Farm Required , Collection Date 07-09-97 08-13-97 09-10-97 LLD Lab Code EMI-4641 EMI-5821 EMI-65SO
-0.5 0.8 -0.7 1.0 -1.0 1 1.1 5.0 Sr-89 Sr-90 0.7 0.3 1.1 0.3 1.2 20.3 1.0 I-131 -0.06 0.14 0.00 0.13 0.06 0.14 0.5 K-40 1392 98 1.510 110 1530 ! 110 g Cs-134 1.6 21.2 -0.7 : 35.2 0.2 ! 0.2 5.0 g Cs-137 0.5 2.3 2.4 2.3 0.6 2.5 5.0 Ba-La-140 -0.2 0.5 1.2 2.7 0.9 : 5.4 5.0 Other Gammas' 1.6 4.5 -0.8 5.0 0.6 182 15.0
(- Collection Date 10-01-97 11-05-97 12-10-97 Lab Code EMI-7514 EMI-8586 EMI-9527 0.5 0.7 0.3 0.9 -0.1 1.2 5.0 Sr-89 St-90 0.5 0.3 0.3 0.3 1.0 0.5 1.0 I131 -0.10 t 0.17 0.13 0.16 -0.13 0.16 K-40 1570 110 1330 120 1440 : 100 g Cs-134 0.1 0.5 -0.6 3.2 0.7 1.4 5.0 g Cs-137 0.1 23 0.5 2.9 -1.3 2.1 5.0 1.3 2.6 Ba La-140 0.3 1.2 -0.9 2.1 5.0 Other Gammas' O.2 0.3 0.1 0.7 1.4 1.1 15.0 g
- See Introduction.
I
L I POINT BEACH NUCLEAR PI ANT RADIOACTIVITY IN WELL WATER SAMPLES, E 10 (Quarterly Collections) ist Quarter hd Quarter 3rd Quarter 4th Quarter Required f LLD Collection Date 01-08 97 04-01-97 08-13-97 10-06-97 f Lab Code EWW-183 EWW-1774 EWW-5S54 EWW-7452 Gross Beta 2.9 2.1 -0.2 1.9 3.0 1.8 3.S : 1.4 4.0 H-3 -14.3 79.4 -83.1 70.7 78.0 84.0 -96.S S0.4 500 St-S9 0.35 0.53 0.29 0.59 -0.7S 0.5S 1.19 1.25 3.0
$r-90 -0.01 : 0.19 -0.20 0.23 0.46 t 0.26 0.31 ::0.31 1.0 I-131 0.25 t 0.27 0.05 0.25 -0.04 0.12 -0.05 : 0.12 0.5 Mn-54 -0.7 3.3 -0.6 4.5 -1.7 3.1 -0.5 1.5 10.0 Fe-59 -2.5 t 6.0 1.2 5.6 -3.2 16.5 -0.4 0.9 30.0 Co-58 0.1 t 3.1 1.8 3.3 -1.4 3.5 -0.3 : 1.7 10.0 Co-60 1.6 3.1 -3.9 2.1 3.7 3.1 0.3 3.4 10.0 Zn-65 -3.8 6.3 -4.8 9.7 -2.2 t 7.0 -0.6 3.0 30.0 Zr-No 95 -2.3 3.8 2.524.3 -1.3 : 3.6 -0.1 : 2.0 15.0 Cs-134 0.4 3.5 0.3 0.2 -0.5 t 0.5 2.4 1.3 10.0 Cs-137 -0.1 3.4 0.3 4.5 0.5 3.3 0.1 1.6 10.0 Ba-La-140 -4.3 6.4 1.3 5.5 0.6 : 1.5 -3.2 12.2 15.0 Other Gammas' -1.9 4.1 -3.S 1.2 -0.S 0.7 -0.5 t 0.5 30.0
- Ru-103 17 I
l 1 1 POINT BEACH NUCLEAR PL ANT RADIOACTIVITY IN LAKE WATER SAMPLES (Monthly Collections) 1 (pCi/L)
-~
1997 E-01 E-05 E-06 E-33 E-12 Collection Met. Two Creeks Coast Guard Nature Unit-1 Period Tower Park Station Conservancv Discharge Flume' l 1 Gross Beta (Required LLD 4.0) 1 January 3.4 0.6 2.4 0.5 2.5 0.3 3.5 : 0.6 4.3 : 0.6 February 1.7 : 0.5 2.1 t 0.5 NS' 2.1 : 0.5 1.6 : 0.5 March 2.6 t 0.6 3.8 : 0.6 4.2 0.6 3.0 0.5 2.30.5 April 3.0 0.6 3.4 0.6 3.3 0.6 2.8 0.6 3.2 : 0.6 May 2.3 0.5 3.3 ! 0.6 2.8 ! 0.6 2.9 0.6 2.8 0.5 June 1.9 : 0.5 1.5 : 0.5 2.4 : 0.5 2.4 0.5 2.1 : 0.5 July 2.7 t 0.5 2.0 0.5 2.3 0.5 2.3 = 0.5 2.0 = 0.6 August 4.3 :1.0 2.4 0.8 2.6 0.5 2.4 0.6 2.6 0.6 September 3.8 0.7 4.6 : 0.7 3.4 0.7 6.5 : 0.8 2.3 : 0.5 October 2.4 0.6 . 3.1 0.9 3.5 0.9 2.320.9 2.3 0.8 November 1.9 : 0.8 2.3 0.6 1.1 0.S 2.4 t 0.6 2.4 :0.6 December 2.3 :1.2 3.4 0.7 4.110.7 3.2 0.7 3.2 = 0.6 Iodine-131 (Required LLD 0.5) January 0.13 = 0.22 -0.25 0.21 -0.01 : 0.24 0.23 0.25 -0.01 0.16 February 0.02 0.15 -0.07 0.15 NS' -0.05 0.15 0.07 10.17 March 0.00 0.17 0.07 0.19 0.01 0.18 -0.06 0.18 -0.2020.20 April -0.03 0.22 -0.01 0.23 0.05 0.22 0.01 0.21 -0.0S 0.22 May -0.08 0.18 -0.04 0.19 -0.10 0.16 -0.11 t 0,15 -0.03 : 0.22 June -0 20 i 0.17 -0.02 : 0.19 0.0L t 0.19 -0.2.2 t 0.19 -0.07 t 0.23 July -0.01 0.16 0.16 : 0.16 -0.10 : 0.14 0.04 = 0.17 0.05 0.28 August 0.05 0.18 -0.1920.19 -0.10 0.23 -0.16 : 0.18 -0.16 0.16 September -0.11 0.19 0.12 0.18 -0.02 0.18 0.00 : 0.18 -0.13 0.18 October -0.14 0.13 -0.01 0.15 -0.07 0.14 -0.12 0.14 0.16 0.17 November -0.19 0.21 0.02 0.20 0.08 0.21 0.21 0.23 -0.18 0.21 December -0.12 0.19 0.14 0.19 -0.06 0.16 0.1620.19 -0.02 0.20 E-12 Unit-1 Discharge Fiume is a monthly composite of weekly grab samples.
- NS = No se.mple; sample not collected due to extremely icy conditions.
l l f 1 18
I POINT BEACH NUCLEAR PLANT t RADIOACTIVITY IN LAKE WATER SAMPLES (Monthly Collections) (pCi/L) 1997 E-01 E-05 E-06 E-33 E-12 Collection Me t. Two Creeks Coast Guard Nature Unit-1 Period Tower Park Station Conservancy Discharge Flume' Mn-54 (Required LLD 10.0) January -0.3 2.8 0.1 : 3.2 -0.6 : 2.2 2.3 3.5 -0.4 t 2.S February 0.2 2.4 -0.1 2.5 NS* 2.5 : 2.7 0.1 : 1.3 March 0.8 3.0 0.1 . 2.3 0.5 : 3.5 -0.6 2.5 -1.S : 3.3 Aptil 0.1 2.0 0.3 2.5 -0.8 2.6 1.0 : 3.5 -1.0 : 2.1 May -0.4 2.8 -1.3 ! 2.2 -1.0 4.2 -1.6 : 2.3 0.7 : 3.4 June 0.0 1.7 0.3 2.1 -1.9 : 3.1 -0.9 : 2.5 -0.6 : 2.7 July 1.6 1.7 0.2 2.9 1.0 2.2 0.1 : 2.9 -0.6 : 0.9 l August -0.1 0.9 0.1 1.2 0.3 0.7 -1.0 1.1 -1.7 2.3 IN l September -0.5 2.9 -1.9 2.2 0.1 2.4 0.2 1.5 -0.5 2.7 October 0.2 2.4 0.2 ! 1.8 0.3 2.0 -1.4 = 2.5 1.8:35 g November -2.1 2.8 -0.21.8 0.5 : 1.8 2.5 2.8 -1.3 : 2.0 m December 0.3 7.6 1.0 1.9 -0.8 2.5 0.9 t 2.1 0.2 2.2 Fe-59 (Required LLD 30.0) . January -4.1 3.9 -0.5 9.6 -3.6 6.5 -2.7 2.6 1.9 2.0 February -0.9 11.2 -2.5 18.4 NS* 0.3 2.8 0.8 2.9 i March -3.3 4.2 -0.4 0.8 3.0 7.4 -5.8 25.7 -2.6 4.8 Aptil -1.4 4.9 -6.8 18.3 -0.2 0.8 -0.3 = 0.9 2.6 2.7 May 4.2 7.4 2.2 3.3 -12.2 9.9 2.0 9.5 -1.3 5.8 June -4.0 39.5 0.2 0.6 -0.93.3 3.3 3.8 3.2 4.9 July 0.622.5 3.1 t 7.5 5.5 14.0 0.7 : 1.2 -0.7 3.5
- August -1.8
- 4.0 1.4 1.8 -0.8 10.2 2.9 : 24.3 0.8 : 2.1 September -1.8 16.3 -0.3 0.5 0.4 1.6 -2.4 95 4.0 5.8 l
October 3.8 : 11.8 0.5 0.7 -0.2 0.4 1.1 2.8 3.1 6.5 November -1.0 2.1 -0.6 1.2 -0.8 0.9 -10.1 9.1 0.9 18.1 E December -3.5 7.6 -2.5 4.5 1.3 2.8 -4.4 ! 27.6 0.2 0.4 5
- E-12 Unit-1 Discharge Flume is a monthly composite of weekly grab samples. g
- NS = No sample; sample not collected due to extremely icy conditions. g I
I vg 19
= l j
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN LAKE WATER SAhtPLES (htonthly Collections) (pCi/L)
- 1997 E-01 E-05 E-06 E 33 E-12 Collection Niet. Two Creeks Coast Guard Nature L~ nit 1 Period Tower Park Station Conservancy Discharge Flume' Co-58 (Required LLD 10.0)
January 0.3 3.6 -0.8 3.7 -0.5 : 2.5 -1.5 : 4.4 -0.1 : 2.5 February -0.3 2.3 1.7 2.9 NS" 0 3 : 2.8 -0.S : 1.6 Ntarch 1.4 2.6 0.2 2.6 0.3 4.0 -1.2 2.S -0.7 3.6 Aptil -1.4 2.1 2.7 : 3.3 -1.3 : 2.7 -2.6 : 3.4 0.2 : 2.4 hIay -0.4 : 2.9 1.4 2.3 -2.2 4.3 -1.0 = 2.3 -0.5 : 2.9 June 0.8 1.7 -0.6 2.2 -2.2 2.9 0.2 : 2.7 1.1 : 2.6 July 1.6 2.2 0.7 2.8 0.32.6 1.7 2.7 0.01.0 August 0.4 1.1 -0.7 1.6 0.1 0.9 0.3 1.3 0.4 : 2.7 September 1.7 : 3.1 -0.9 2.2 -0.6 2.8 -0.5 : 1.7 0.7 : 3.2 October -3.1 2.7 0.3 : 2.5 -1.5 2.2 -0.6 2.7 -1.0 : 4.2 November -0.7 2.9 0.6 2.3 -1.1 2.3 -0.9 4.3 0.82.3 December -1.0 2.6 0.4 2.2 1.8 2.9 -0.S : 2.3 -1.02.1 Co-60 (Required LLD 10.0) January 0.4 1.8 -0.3 3.0 1.8 3.3 -0.7 5.1 1.2 1.8 February -1.6 : 14.9 -0.1 1.1 NS' 1.6 : 5.6 0.5 2.0 h! arch 0.6 0.5 1.5 7.5 0.7 2.4 0.4 4.6 -0.4 2.3 April 0.4 3.9 -1.5 3.5 2.2 4.7 4.9 6.4 0.1 6.5 Ntay -1.0 : 1.1 0.6 5.3 -0.5 : 1.6 -0.8 0.8 -0.4 : 5.8 June -0.5 t 1.3 0.1 1.1 -0.1 : 0.4 1.3 : 6.0 1.3 : 2.3 July 0.8 : 2.4 -1.7 2.8 0.3 0.7 -0.2 0.9 1.2 t 2.5 August 0.1 0.2 -0.2 0.2 0.6 2 1.0 1.2 5.8 0.8 6.6 September -1.8 1.8 0.9 1.0 1.0 5.0 -03 0.4 1.4 = 0.9 October 1.8 8.8 1.0 1.6 0.2 1.1 0.5 : 1.1 2.3 6.3 November 0.0 0.1 -0.320.7 -0.4 0.4 0.9 1.5 -0.1 0.4 December 1.6 t 2.2 0.6 0.8 2.4 8.0 -0.8 : 3.1 0.3 0.8
' E-12 Unit-1 Discharge Fiume is a monthly compostte of weekly grab samples.
- NS = No sample; sample not collected due to extremely icy conditions.
20
f E POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN LAKE WATER SAMPLES i @. (Monthly Collections) (pCi/L) 1997 E-01 E-05 E-06 E 33 E-12 i Collection Met. Two Creeks Coast Guard Nature Unit-1 Period Tower Park Station Conservancy Discharge Flume' Zn-65 (Required LLD 30.0) January 0.7 t 5.3 2.0 6.9 -0.2 4.4 -4.1 : S.5 2.7 : 6.5 February -1.314.0 -1.9 : 5.9 NS' O.9 : 5.5 -2.3 : 3.5 March -2.0 5.8 -1.5 3.7 -2.4 8.1 2.2 : 5.8 -3.S : 5.5 g , April -3.4 4.3 0.3 : 7.0 -7.2 : 7.0 6.7 : 8.2 -4.14.7 gl May 0.3 5.1 0.4 : 4.5 7.1 7.9 0.4 : 4.5 -1.S : 8.0 June 0.2 3.0 0.5 4.5 -1.2 6.4 -0.4 : 4.1 3.0 : 4.9 July 4.4 : 3.5 -2.8 5.9 -5.8 4.7 0.9 : 4.2 -0.4 1.S August -0.8 1.9 -3.2 : 2.6 -3.1 1.5 -0.2 : 2.5 -3.7 5.5 September 3.0 5.7 1.0 3.3 -1.7 : 6.9 -0.5 3.0 -6.2 6.2 October -1.6 4.8 -2.8 4.2 0.9 : 3.4 -2.1 : 4.1 -11.9 9.8 l November 2.4 6.2 -0.3 0.7 1.4 3.9 -0.76.1 -0.2 4.3 E December -3.8 4.3 -0.9 i 3.9 -3.3 6.3 0.6 : 4.3 1.0 4.6 Zr-Nb-95 (Required LLD 15.0) (~ January 0.2 4.3 2.5 4.1 -1.5 2.9 1.8 4.6 -3.0 3.3 g i February -0.1 2.5 2.9 ! 3.4 NS" 1.3 3.1 0.2 1.5 g March -0.6 3.3 -0.9 2.6 3.5 5.0 -3.6 3.5 -2.525.2 Aptil -1.7 2.8 -0.2 4.2 -1.5 3.8 2.8 : 4.9 0.4 3.3 May -1.4 4.9 -0.5 3.3 -1.5 : 5.3 1.6 3.2 0.4 4.3 June 0.3 2.4 -2.0 3.4 1.4 4.3 -0.3 3.8 -0.7 3.6 July -0.3 2.8 0.7 5.0 0.2 3.6 1.0 4.2 0.3 1.3 August -1.2 1.6 0.1. 2.0 -1.2 1.5 0.4 1.9 1.1 3.2 l
-0.6 -0.6 3.6 -1.5 : 4.3 2.0 2.4 1.5 3.9 E September 5.0 i October 1.0 4.2 0.2 2 3.2 1.4 : 2.7 -0.8 3.6 1.8 5.0 November 1.2 4.4 0.2 : 3.2 -2.6 3.0 2.3 : 4.9 -2.2 2.8 December 2.3 3.3 0.3 2.8 -1.6 : 4.0 -0.5 3.3 -0.3 2.3
- E-12 Unit-1 Discharge Fiume is a monthly compostte of weekly grab samples.
' NS = No sample; cample not collected due to extremely icy conditions.
l I I l 21
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN LAKE WATER SAMPLES (Monthly Collections) (pCi/L) 1997 E-01 E-05 E 06 E-33 E-12 Collection Met. Two Creeks Coast Guard Nature Unit-1 Period Tower Park Station Conservancy Discharge Flume Cs-134 (Required LLD 10.0) January 0.5 : 4.2 1.3 : 3.7 -1.2 ! 2.2 1.S : 1.5 3,5 : 13.4 February 1.4 : 23.4 0.9 : 17.6 NS' 3.3 5.2 -0.7 : 1.7 March - 1.5 13.2 0.2 0.4 0.1 1.6 1.6!55 0.3 : 9.3 i Aptil May 0.1 : 0.1 1.1 : 2.0 0.7 : 1.2 0.7 : 0.4
-2.4 : 4.5 0.9 : 2.2
-1.1 4.4 0.7 : S.5 0.7 : 0.4
-1.4 : 2.4 June 0.7 16.8 0.4 : LO -1.4 1.0 1.1 = 3.1 0.7 : 3.3 July -0.7 7.7 -1.1 1.4 0.2 1.8 -1.1 : 18.4 0.0 = 0.1 August 0.3 0.7 -0.4 :2.1 0.8 0.4 0.1 : 0.3 -0.7 : 2.3 September 0.8 : 0.9 -1.S 5.9 -0.4 : 15.6 1.5 : 2.7 0.2 0.2 October -0.9 7.7 -1.2 3.3 0.7 : 0.9 0.4 : 0.5 -0.3 : 0.2 November 1.6 3.8 0.1 : 0.2 0.S 16.1 1.4 : 3.7 -0.7 : 1.4 December 1.9 2.2 0.6 0.5 1.2 1.3 1.1 : 0.8 -0.7 : 4.2 Cs-137 (Required LLD 10.0)
January 1.5 t 3.3 1.8 3.8 0.2 2.4 -2.0 : 4.1 0.3 t 2.9 1 February 0.1 2.6 -1.5 2.9 NS" 0.8 2.3 1.0 : 1.7 March 0.1 : 3.1 1.5 2.3 -3.5 : 4.1 0.2 : 2.5 1.8 : 3.5 April 1.4 2.6 0.2 : 3.6 0.7 3.4 2.1 : 4.2 0.3 2.4 l May June 1.3 3.1 1.0 2.1 0.5 : 2.3 1.0 : 2.5 1.6 3.6 1.8 3.3 0.5 : 2.5 2.5 c 2.5 3.4 : 3.9 1.8 : 3.4 July 0.5 2.0 0.3 : 3.2 0.8 : 2.1 -1.7 3.0 0.2 1.0 August 0.3 0.7 0.7 1.3 1.0 0.8 1.0 1.2 0.6 : 2.7 September 0.9 2.9 -0.4 2.3 -1.0 : 3.0 1.5 : 1.6 0.9 3.1 October 1.5 = 2.5 1.0 2.0 1.3 : 2.2 1.4 2.6 -0.5 : 4.6 November -1.1 2.9 1.8 : 2.4 -0.6 : 2.2 1.2 : 3.2 0.6 2.6 I December 0.9 2.6 0.2 2.0 -1.4 ! 2.7 0.5 : 2.7 1.9 : 2.1 l B
- E-12 Unit-1 Discharge Flume ts a monthly composite of weekly grab samples.
' NS = No sample; sample not collected due to extremely icy conditions.
I I I u L 22
I POINT BEACH NUCLE AR PL ANT RADIOACTIVITY IN LAKE WATER SAMPLES " (Monthly Collections) (pCi/L) 1997 E-01 E-05 E-06 E-33 E-12 Collection Met. Two Creeks Coast Guard Nature Unit-1 Period Tower Park Station Conservancy Discharge Flume' Ba-La-140 (Required LLD 15.0) January 6.2 8.1 1.4 t 7.0 1.0 7.9 -0.8 t 1.5 0.3 : 0.9 February 1.0 2.0 -4.5 10.6 NS' -12.2 33.9 -0.522.1 March -1.8 31.4 -0.7 0.9 -3.3 : 3.0 -2.0 15.0 -0.6 : 7.2 April 0.9 ! 13.7 6.4 16.5 -0.41.2 13.3219.4 2.9 : 14.7 l 4.8 37.8 3.8 20.3 7.4 4.3 11.5 5.1 : 31.3 = May 9.1 June 2.7 : 13.6 -3.4 4.9 -7.0 10.4 4.6 28.0 1.222.3 July -5.5 76.8 -2.0 4.3 -8.9 49.2 -10.5 9S.8 -3.8 : 4.1 August -6.3 11.6 2.8 5.9 -2.2 3.2 -0.4 7.1 -6.8 22.1 September -0.7 t 3.1 1.0 1.7 2.6 : 12.6 -0.4 3.1 2.0 4.1 October -0.8 : 26.9 2.3 3.9 -6.1 151.0 -4.5 : 5.7 -8.9 66.4 g November -14.4 11.2 -9.2 65.9 -8.1 : 30.0 -1.7 2.5 0.5 1.4 g December -2.0 t 2.1 2.2 7.3 0.5 2.3 -5.6 9.2 -4.1 11.6 Other Gammas' (Required LLD 3,0.0) (
\
January -0.4 2.0 3.0 4.9 -0.7 0.6 3.6 6.9 -0.4 : 0.3 February 1.0 0.6 -1.5 2.8 NT -1.7 2.1 -0.2 1.7 March -0.3 : 1.1 -1.1 0.7 0.4 0.4 -1.4 16.7 -2.0 2.4 April 1.2 0.9 -0.5 3.9 -1.5 1.5 0.4 0.4 0.4 0.1 May -2.5 1.8 2.8 1.9 -1.8 31.4 -1.4 2.1 -3.0 22.9 l June -2.6 : 2.4 -1.4 1.2 0.8 1.2 -2.1 4.1 0.8 0.8 5 July -2.5 23.3 -1.6 3.6 -1.5 1.0 0.9 3.6 -0.7 0.4 August -0.8 0.3 0.3 0.2 0.4 0.1 -0.4 7.1 -1.1 1.4 g September 0.3 1.2 0.9 t 0.6 0.9 0.6 -1.0 0.3 0.4 0.2 E October -0.7 0.2 -0.1 0.3 -2.2 1.4 -0.9 0.3 2.8 t 1.4 November 0.5 0.2 -1.1 1.3 -1.3 0.8 -0.2 t 0.2 1.720.8 December 0.3 0.1 -0.5 0.2 -0.5 0.3 -1.2 0.6 -0.2 0.1 {
' E-12 Unit-1 Discharge Fiume is a monthly composite of weeldy grab samples. g
- Ru-103 g1 j
' NS = No sample; sample not collected d'ue to extremely icy conditions.
I I q n
I l l POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN LAKE WATER SAMPLES t (Monthly Collections) (pCi/L) i l 1997 E-01 E-05 E-06 E-33 E-12 i Collection Met. Two Creeks Coast Guard Nature Unit-1 f Period Tower Park Station Conservancy Discharge Flume
- Sr-89 (Required LLD 5.0) ;
1st Quarter -0.9 0.9 -1.4 1.2 -1.3 1.4 -0.3 1.0 -1.3 ! 1.2 2nd Quarter -0.30.9 -0.6 : 0.9 0.0 : 0.8 -03 :0.S 0.4 : 0.6 3rd Quarter -0.1 : 0.7 0.1 0.9 -1.1 : 0.9 -0.5 t 0.7 -0.9 : 1.0 i 4th Quarter -0.1 : 0.7 0.5 0.7 -0.5 0.8 0.310.7 -0.320.5 l Sr-90 (Required LLD 1.0) ; 1st Quarter 0.7 = 03 0.9 0.4 1.0 0.5 0.5 03 0.4 t ')3 2nd Quarter 0.4 = 03 0.7 03 0.5 t 03 0.4103 0.2 03 3rd Quarter 0.5 03 0.5 !03 0.7 0.4 0.5 03 0.6 0.4 4th Quarter 0.6 203 0.2 0.2 0.5 03 03 203 0.4 03 H-3 (Required LLD 500) 1st Quarter 161 83 200 84 207 85 126 81 1997 :139 2nd Quarter 43 82 93 85 36 : 82 14 81 86 S4 3rd Quarter 145 90 176 :91 101 88 61 86 93 t 91 4th Quarter 1296 il27* 12 82 294 94 75 :85 6 76
- E-12 Unit-1 Discharge Flume is a monthly composite of weekly grab samples.
- Analysis was repeated; Result of reanalysis 1122 123 pCi/L. The quarterly composbe was analyzed as separate monthly samples. The result of the analyses as follows:
October 38 95 pCi/L November 44 95 pCi/L December 3336 184 pCi/L 24
POINT BEAcht NUCLEAR PLANT RADIOACTIVITY IN FISH SAMPLES EDIBLE PORTIONS ONLY - COLLEu eD AT E-13 (Collected 3x / year) Sample Description and Concentration (pCi/g wet) Required LLD Collection Date 06-11-97 06-11-97 ^ ' ' '7 Lab Code EF-3927 EF-3928, 9 i Type Northern Pike Sucker .t Ratio (wet wt./ dry wt.) 2.93 5.29 Gross Beta 3.35 0.12 2.68 0.07 3.37 : 0.12 0.5 K-40 3.24 0.52 1.69 0.27 2.89 : 0.37 Mn-54 -0.003 2 0.104 0.002 0.008 -0.003 : 0.009 0.13 I Fe-59 -0.021 0.194 -0.011 : 0.044 -0.002 2 0.003 0.26 I Co-56 0.007 0.010 -0.006 : 0.008 -0.003 2 0.009 0.13 Co-60 0.012 0.016 0.001 : 0.006 -1005 : 0.013 0.13 Zn-65 0.014 0.032 -0.006 0.018 0.013 2 0.017 0.26 i Cs-134 0.007 0.023 0.001 0.00S -0.009 0.035 0.13 l Cs-137 0.035 0.015 0.082 0.018 0.050 0.019 0.15 l Other Gammas' O.003 0.003 0.002 0.003 0.001 0.002 0.5 Collection Date 08-13-97 08-13-97 Lab Code EF-5896 EF-5897 Type Sculpin Smelt Ratio (wet wt./ dry wt.) 5.38 5.51 Gross Beta 3.08 0.11 3.52 0.12 0.5 K-40 2.63 0.58 2.79 0.50 Mn-54 0.009 0.019 0.001 0.015 0.13 Fe-59 0.022 : 0.026 -0.008 0.830 0.26 Co-58 -0.005 0.022 -0.004 0.015 0.13 Co-60 0.003 0.01'6 -0.003 : 0.001 0.13 Zn-65 -0.019 0.051 0.022 ! 0.030 0.26 Cs-134 0.003 0.029 0.002 0.007 0.13 Cs-137 0.031 0.022 0.028 0.017 0.15 Oth' Gammas' -0.004 0.002 0.007 0.003 0.5 l
' Ru-103 25
POINT BEACH NUGJJR PLANT RADIOACTIVITY IN FISH SAMPLES EDIBLE PORTIONS ONLY - COLLECTED AT E-13 (Collected 3x / year) Sample Description and Concentration (pCi/g wet) Required g LLD g Collection Date 12-17-97 12-17-97 12-17-97 Lab Code EF-9752 EF-9753 EF-9754 Type Sheepshead L?.ke Trout Redhorse g Ratio (wet wt./ dry wt.) 3.46 3.04 4.8S g Cross Beta 3.46 0.17 3.00 0.09 2.94 : 0.10 0.5 K-40 3.11 0.42 2.8810.34 2.69 0.36 Mn-54 -0.002 0.010 0.000 0.007 0.000 0.010 0.13 Fe-59 0.012 0.190 -0.015 0.037 -0.014 0.014 0.26 Co-58 0.005 0.011 -0.006 0.008 0.004 10.011 0.13 Co-60 0.002 0.036 -0.005 20.009 0.004 0.019 0.13 Zn-65 -0.026 0.029 0.007 0.018 -0.009 =0.021 0.26 - Cs-134 0.002 0.009 -0.001 0.002 0.003 10.003 0.13 Cs-137 0.029 0.012 0.074 0.015 0.021 0.010 0.15 Other Gammas' O.008 0.083 0.009 0.066 0.038 0.085 0.5 Collection Date Lab Code Type Ratio (wet wt./ dry wt.) Gross Beta 0.5 K-40 Mn-54 0.13 l
=
Fe-59 0.26 Co-58 0.13 Co-60 0.13 Zn-65 0.26 Cs-134 0.13 Cs-137 0.15 Other Gammas
- O.5
' Ru 103 I Note: Page 27 is intentionally left out. , 26
I POINT BEACH NUCLEAR PLANT l t l RADIOACTIVITY IN SHORELINE SEDLMENT S AMPLES ) (Semiannual Colle:tions) l l I Sample Description and Concentration (pCi/g dry) ; 1 Collection Date 04-15-97 04-15-97 04 15-97 Required Lab Code ESS-2216 ESS-2217 ESS-221S LLD l Location E-01 E-05 E-06 Gross Beta 4.43 1.33 5.22 1.32 6.52 : 1.39 2.0 Be-7 0.039 0.066 0.044 ! 0.046 0.013 : 0.051 K-40 1.99 ! 0.28 2.92 0.24 5.73 0.33 - l Cs-137 0.062 0.015 0.049 0.017 0 034 0.014 0.15 T1-20S 0.140 t 0.016 0.082 0.016 0.042 2 0.013 - Pb-212 0.393 0.044 0.250 : 0.025 0.155 t 0.024 - Bi-214 0.338 0.036 0.248 0.025 0.157 0.033 - Ra-226 0.61 0.24 0.49 0.24 0.35 0.18 - Ac-228 0.406 0.060 0.299 0.047 0.134 : 0.057 - Collection Date 04-15-97 04-15-97 Lab Code ESS-2219 ESS-2220 Location E-12 E-33 Gross Beta 6.09 1.37 4.87 1.36 2.0 Be-7 0.031 0.050 -0.003 0.053 X-40 5.98 0.34 4.11 0.2S - Cs 137 0.038 0.015 0.031 0.015 0.15 TI .'.08 0.043 t 0.016 0.057 0.016 - Pb-212 0.106 : 0.024 0.172 0.023 - Bi-214 0.123 0.022 0.143 0.024 - Ra-226 0.33 0.13 0.38 0.16 - Ac-228 0.176 0.048 0.174 0.045 - l l 28
I POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SHORELINE SEDLMENT SAMPLES (Semiannual Collections) Sample Description and Concentration (pCi/g dry) Collection Date 10-01-97 10-01-97 10-01-97 Required Lab Code ESS-7464 ESS-7465 ESS-7466 LLD Location E-01 E-05 E-06 Gross Beta 2.92 1.25 3.67 1.20 6.59 : 1.96 2.0 Be-7 0.097 0.094 0.012 0.056 0.005 = 0.0S5 I K-40 2.58 0.22 3.59 0.23 3.62 0.27 - Cs-137 0.048 0.012 0.015 0.006 0.045 2 0.017 0.15 TI-208 0.13 0.016 0.039 0.012 0.16 : 0.021 - Pb-212 0.39 0.030 0.13 0.020 0.41 0.034 - Bi-214 0.39 0.028 0.12 0.020 0.29 0.036 - Ra-226 1.01 0.14 0.37 0.11 0.97 ! 0.29 - Ac-228 0.37 0.064 0.16 0.036 0.41 0.058 I Collection Date 10-01-97 10-01-97 Lab Code ESS-7467 ESS-7468 , Location E-12 E-33 I Gross Beta 6.04 1.52 5.26 1.79 2.0 Be-7 0.012 0.073 0.023 : 0.057 K-40 5.02 0.28 7.48 0.32 - Cs-137 0.043 0.014 0.028 0.011 0.15 l TI-208 0.071 0.016 0.056 0.012 - Pb-212 0.22 0.023 0.15 0.021 - Bi-214 0.18 0.022 0.18 0.037 - Ra-226 0.38 0.17 0.36 0.16 - Ac-228 0.23 0.043 0.19 0.050 - I I (.- 29
POINT BEACH NUCLEAR PLANT RADIOACTIVITYIN SOIL SAMPLES
' t. .
(Semiannual Collections) Sample Description and Concentration (pCi/g dry) Collection Date 05-07-97 05-07 97 05-07-97 05 07-97 Required Lab Code ESO-2902 ESO-2903 ESO-2904,3 ESO-2906 LLD Location E-01 E-02 E-03 E 04 Gross Beta 11.92 2.67 27.97 2.64 25.51 1.76 25.35 : 2.07 2.0 I Be-7 0.17 0.13 0.12 0.23 0.093 0.13 0.12 : 0.20 K-40 11.53 t 0.74 22.62 1.13 IS.99 : 0.67 1.00 : 1.09 - Cs-137 0.004 2 0.243 0.089 0.036 0.27 : 0.036 0.021 : 0.020 0.15 TI 208 0.080 0.021 0.23 0.034 0.15 : 0.019 0.17 : 0.031 - Pb-212 0.30 0.041 0.65 0.070 0.52 0.038 0.5S 0.063 - Bi 214 0.27 0.061 0.38 0.073 0.39 t 0.051 0.38 = 0.061 - Ra-226 0.49 0.26 0.85 0.48 0.94 0.28 1.15 : 0.430 - Ac-22S 0.37 0.090 0.75 : 0.16 0.51 : 0.091 0.61 : 0.160 - I Collection Date 05-07-97 05-07-97 05-07-97 05-07-97 Lab Code ESO-2907 ESO-2908 ESO-2909 ESO-2910 I Location E46 E-08 E-09 E-20 Gross Beta 18.75 2.75 15.04 : 2.09 24.95 : 2.38 23.71 ! 2.46 2.0 Be-7 0.041 0.18 -0.027 0.12 -0.029 0.14 0.10 0.19 i K-40 Cs 137 13.08 o 0.83 0.80 0.057 11.91 0.71 0.004 0.012 20.75 t 0.S6 0.20 = 0.039 16.18 t 0.94 0.30 0.053 0.15 T1-208 0.060 t 0.022 0.085 0.018 0.17 0.028 0.21 0.040 - Pb-212 0.17 ! 0.040 0.26 t 0.035 0.56 t 0.053 0.49 ! 0.05S - Bi-214 0.11 0.041 0.17 0.036 0.37 : 0.050 0.36 0.062 - Ra-226 0.45 0.31 0.33 : 0.23 0.89 0.37 1.01 t 0.53 - Ac-228 0.23 0.23 0.30 : 0.090 0.51 : 0.11 0.57 0.12 - l i 30 e
I PONT BEACH NUCLEAR PLANT RADIOACTIVITY IN SOIL SAMPLES (SemiannualCollections) Sample Description and Concentration (pCi/g dry) Collection Date 10-01-97 10-01-97 10-01-97 10-01-97 Required Lab Code ESO-7456 ESO-7457 ESO-745S ESO-7439 LLD Location E-01 E-02 E-03 E-04 Gross Beta 31.12 3.29 23.76 3.18 18.56 2.68 22.S9 2.91 2.0 Be-7 0.057 0.11 0.15 0.12 0.14 0.14 0.26 0.12 I K-40 16.28 0.60 21.62 0.65 12.73 2 0.61 18.92 0.63 - Cs-137 0.18 0.022 0.23 0.024 0.43 0.038 0.16 0.023 0.15 T1-208 0.16 0.022 0.22 0.025 0.13 0.02S 0.20 0.025 - Pb-212 0.56 t 0.041 0.76 0.045 0.46 0.044 0.64 0.043 - Bi-214 0.38 0.039 0.43 0.038 0.43 0.044 0.43 0.041 - Ra-226 1.01 0.31 1.08 0.27 1.01 0.29 1.05 0.29 - Ac-228 0.62 0.079 0.75 0.078 0.50 t 0.081 0.64 0.077 - f Collection Date 10-01-97 10-01-97 10-01-97 1C-01-97 ' Lab Code ESO-7460 ESO-7461 ESO-7462 ESO-7463 Location E-06 E-08 E-09 E-20 Gross Beta 13.81 2.45 17.75 2.55 29.13 3.21 28.92 3.05 2.0 Be-7 0.065 t0.089 0.052 0.11 0.045 t 0.12 0.25 0.14 K-40 11.98 0.45 14.64 0.51 21.61 t 0.66 19.89 t 0.67 - Cs-137 0.57 0.028 0.53 0.031 0.24 0.026 0.46 0.030 0.15 T1-208 0.082 0.021 0.094 0.019 0.21 t 0.026 0.22 0.029 - Pb-212 0.25 0.030 0.32 t 0.033 0.67 0.045 0.65 0.046 - Bi-214 0.21 0.029 0.28 1 0.032 0.54 0.042 0.46 0.042 - Ra-226 0.54 0.15 0.59 0.23 1.16 t 0.30 1.29 0.43 - Ac-228 0.28 0.053 0.37 0.067 0.66 0.09 0.72 0.10 - I I
. g 31
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN VEGETATION SAMPLES h (Tri AnnualCollections) (pCi/g wet) Ratio Collection Lab w.gl Cross Locatioi Da te Code drv Beta Be-7 Cs 134 Cs-137 i131 K-40 Other Eguired LLD 0 25 0.li 0_06 02.3 Ofd 0 25 0.25 E-01 05-07-97 EG -2373 4.17 6.41:0.19 1.62:0.32 -0.002_-0.002 0.003:0.014 0.009:0.027 6.78 0.60 0.00S:0.011 E-02 05-07-97 -2874 3.83 6.07:0.20 0.92:0.23 0.004:0.008 -0.003:1013 0.014:0.061 6.90:0 63 0.005:0 010 E 03 05-07 97 -2375 4.63 7.17:0.16 1.01:0.24 0.000:0.004 0.006:0 011 0.003:0 003 S.90:0 60 0.001:0.002 E 04 05-07-97 -2376 4.78 6.93 0.14 1.68:036 -0.007 0.010 0.003:0.016 0.007:0.022 7.5nd.74 0 003:0.005 E-06 05-08-97 2S77 235 4.68:0.17 3.5S:038 -0.007:0.009 0.13:0.033 0.007:0.011 4 23:0.33 0.014:0.04s E-08 05-07 97 2378 3.78 6.70:0.20 1.24:0.35 0.007:0.005 0.010:0.01S -0 008:0.022 6.W-0.73 -0.003:0.023 E-09 05-07-97 -2379,80 4.05 6.55:0.14 1.51:0.25 0.003:0.017 0.001:0.014 0.016:0.033 6.03:0.53 -0.008:0.12 E 20 05-08-97 -23S1 5.50 5.14:1.16 1.65:0 34 0.003:0.006 0.020:0.019 -0.019:3.42 3.31:0.74 0.007:0.004 E 01 07-10-.97 EG -4741 4.21 4.11t0.14 0.82 0.20 0.002+0.038 0.004+0.015 0.001-0.002 4.83 0.33 0.013 0.15 E 02 07 10-97 -4742 6.01 5.57:0.18 1.29:0.17 -0.001 0.001 0.000 0.008 -0.001:0.003 4.71:0 3S 0.002 0.005 E-03 07-10-97 -4743 2.S5 5.21:0.20 0.33:0.35 0.006 0.020 -0.002:0.019 -0.004:0.008 4.33:0.64 0.005:0.003 E 04 07 10-97 -4744 4.26 5.65r3.19 1.20 0.26 -0.002:0.004 0.001:0.014 0.009-0.037 4.S3:0.48 0.005:0.021 E-06 07-10-97 -4745,6 4.46 4.90:0.12 0.78:0.21 -0.004:0.052 0.010:0.013 0.007:0.014 436:0.42 -0.009:0.063 E 08 07 10-97 -4747 4.45 2.43:0.13 0.53:0.32 0.010:0.018 0.020:0.018 0.008:0.021 4.S9:0.63 -0.006:0.034 E 09 07 10-97 -4748 3.22 5.13:0.19 0.S1:0.25 0.000i0 002 0.004:0.013 -0.003:0.015 6.12:0.63 0.000:0.003 E 20 07-10-97 -4749 5.17 7.33:0.26 1.18 0.26 0.005 0.007 -0.003:0.013 0.003:0.008 7.66:0.38 ' 001 0.001 E-01 10-01-97 EG -7428 1.501139:0.461.86:0.23 0.001:0.002 0.003:0.015 0.00Sr1018 5.15:0.57 0.010:0.049 E-02 10 01-97 7429 3.86 639:0.22 2.56:0.14 0.001:0.001 0.009:0.006 -0.002_-0.019 6.4S 0.25 0.001!0.011 E 03 10-01-97 -7430 2.14 6.75t0.29 3.84 0.42 0.007 0.006 0.004:0.015 0.012:0.23 5.S4:0.60 0.006 0.044 E-04 10-01-97 7431 2.73 5.21:0.24 3.73:0.35 -0.001:0.001 0.013:0 015 0.015:0.042 5.46:0.53 0.006 0.016 E-06 10-01-97 -7432 3 4.05 535:0.15 1 31:0.20 0.003 0.006 0.085 0.016 0.009 0.24 4.73:034 0.006:0.013 E-08 10-01-97 7434 2.29 633:0.25 4.52:0.42 0.004:0.006 0.002:0.013 -0.013:0.023 6.17 0.59 0.001:0.004 E 09 10-01-97 -7435 3.93 10.13:0.41 2.80 0.41 0.001+0.001 0.002:0.016 -0.011-0.016 4.95 0.62 0.010:0.029 E 20 10-01-97 -7436 4.10 5.51:0.20 1.97:0 35 -0.002:0.002 0.007 0.014 0.009:034 7.66:0.64 -0.012:0.017 1
- See Introduction.
32
1 PONT BEACH NUCLEAR PLANT RADIOACTIVITY IN AQUATIC VEGETATION (SemiannualCollections) O
/
Sample Description and Concentration (pCi/g wet) Collection Date 06-10-97 11-11-97 Required Lab Code ESL-3926 ESL-8884 LLD Location E-5 E-5 Ratio (wet wt./ dry wt.) 6.77 2.52 Gross Beta 2.34 0.19 5.69 0.59 0.25 Be-7 0.40 0.24 0.38 0.49 - I K-40 1.33 0.55 8.64 0.86 - l Co-58 0.009 0.017 0.004 0.057 0.25
- Co-60 0.015 0.012 0.029 0.027 0.25 l Cs-134 0.005 0.017 0.008 0.018 0.25 Cs-137 0.030 0.020 0.050 0.054 0.25
[ Collection Date 06-03-97 08-19-97 09-30-97 Lab Code ESL-3718 ESL-6034,5 ESL-7372 Location E 12 E-12 E-12 Ratio (wet wt./ dry wt.) 9.91 6.95 2.24 Gross Beta 0.56 t 0.03 2.08 0.13 4.87 0.86 0.25 Be-7 0.11 0.19 4.18 0.10 0.07 0.10 - K-40 2.19 0.31 1.55 0.20 3.36 0.35 - Co-58 0.007 0.020 0.010 0.007 0.025 0.012 0.25 Co-60 0.026 0.050 0.017 0.130 0.078 0.019 0.25 Cs-134 0.012 0.014 0.003 0.012 0.004 0.001 0.25 Cs-137 0.015 0.022 0.015 2 0.007 0.038 0.012 0.25 I' I
-I 33
PONT BEACH NUCLEAR PLASTr AMBIENT GAMMA RADIATION (TLD) 1st. Quarter,1997 Date Annealed: 12-26-96 Days in the field 87 Date Placed: 01-07-97 Days from Annealing Date Removed: 04-04-97 to Readout: 107 Date Read: 04-12-97 Daystn Location Field Total mR Net mR Net mR per 7 days Indicator E-1 87 13.1 0.2 9.5 t 0.4 0.76 : 0.03 E2 87 16.S 0.4 13.2 0.5 1.C6 0.04 i E-3 87 13.7 0.1 10.1 : 0.3 0.81 : 0.02 E-4 87 13.5 0.3 9.9 0.4 0.80 0.03 1 E-5 E-6 87 87 14.6 0.3 13.2 0.4 11.0 : 0.4 0.89 : 0.03 9.6 : 0.5 0.77 : 0.04 E-7 87 14.1 0.6 10.5 : 0.7 0.S4 0.06 E-8 87 14.7 t 0.3 I 11.1 0.4 0.89 : 0.03 E-9 87 15.0 0.4 11.4 0.5 0.92 0.04 E 12 87 11.6 0.1 8.0 0.3 0.64 t 0.02 l E-14 87 14.3 0.2 10.7 0.4 0.86 0.03 B E-15 87 16.1 0.5 12.5 0.6 1.01 0.05 E-16 87 16.7 0.6 13.1 0.7 1.05 0.06 E-17 87 15.0 0.2 11.4 0.4 0.92 0.03 I E-18 87 16.3 0.4 12.7 0.5 1.0220.04 E-22 87 15.0 0.3 11.4 t 0.4 0.92 0.03 E-23 87 15.0 0.3 11.4 0.4 0.92 0.03 1 E-24 87 14.3 0.6 10.7 0.7 0.86 0.06 E-25 87 13.4 0.3 9.8 0.4 0.79 0.03 E-26 87 13.3 ! 0.3 9.7 : 0.4 0.78 : 0.03 E-27 87 13.620.2 10.0 0.4 0.80 0.03 E-28 87 13.2 0.3 9.6 0.4 0.77 0.03 E-29 87 14.0 0.9 10.4 0.9 0.84 0.07 E-30 57 13.3 0.4 9.7 : 0.5 0.78 0.04 E-31 87 14.8 0.4 11.2 0.5 0.90 0.04 E-32 87 13.3 : 0.2 9.7 0.4 0.78 0.03 Control I E-20 87 11.9 : 0.5 8.3 0.6 0.67 0.05 Mean S.D. 14.2 1.3 10.7 1.3 0.8520.10 In-Transit Emesure Date Annealed 12 26-96 03-28-97 Date Read 01-13-97 04-12-97 Total mR ( ITC-1 4.0 0.1 3.1 0.2 ITC-2 3.9 0.1 3.2 0.2 31
I POINT BEACH NUCLEAR PLANT AMBIENT GAMMA RADIATION (TLD) 2nd. Quarter,1997 Date Annealed: 03-28-97 Days in the field 97 Date Placed: 04-04-97 Days from Annealing Date Removed: 07-10-97 to Readout: 114 l W Date Read: 07-20-97 Days in l Location Field Total mR Net mR Net mR per 7 davs W Indicator E-1 E2 97 11.4 0.4 7.8 0.6 0.56 0.04 g 97 12.9 0.3 9.3 0.6 0.6720.04 5 E-3 97 15.9 0.3 12.3 0.6 0.89 0.04 E-4 97 14.3 ! 0.2 10.7 t 0.5 0.77 0.04 g E-5 97 13.9 0.4 10.3 0.6 0.7420.04 g E-6 97 12.6 0.3 9.0 : 0.6 0.65 0.04 E-7 97 14.7 0.4 11.1 0.6 0.80 0.04 E-8 97 15.1 0.4 11.5 0.6 0.83 0.04 E-9 97 14.3 0.2 . 10.7 0.5 0.77 : 0.04 E-12 97 14.3 0.2 10.7 0.5 0.77 0.04 E-14 97 14.9 0.4 11.320.6 0.82 0.04 E-15 97 17.4 0.5 13.8 0.7 1.00 0.05 l
. E-16 97 15.8 0.5 12.2 0.7 0.88 0.05
( E-17 E-18 97 97 14.4 0.2 16.2 0.5 10.8 0.5 12.6 t 0.7 0.78 0.04 0.91 0.05 ( _l'E E-22 97 14.4 0.2 10.8 0.5 0.78 t 0.04 E-23 97 18.4 0.4 14.8 0.6 1.07 0.04 g E-24 97 16.0 0.4 12.4 0.6 0.89 0.04 g E-25 97 14.5 0.3 10.9 0.6 0.79 t 0.04 E-26 97 15.0 0.5 11.4 0.7 0.82 0.05 g E 27 97 15.6 0.5 12.0 0.7 0.87 0.05 g E-28 97 16.4 0.5 12.8 0.7 0.92 0.05 E-29 97 14.7 0.4 11.1 0.6 0.80 0.04 E-30 97 15.9 0.6 12.3 0.8 0.89 0.06 E-31 97 15.7 0.3 12.1 0.6 0.87 0.04 E-32 97 17.4 0.5 13.8 0.7 1.00 0.05 Control E-20 97 14.7 0.3 11.1 0.6 0.80 0.04 Mean S.D. 15.1 1.5 11.5 1.5 0.83 0.09 l In-Transit Emosure l W l Date Anraaled 03-28-97 06-27-97 l Date Read 04-12-97 07-20-97 l Total mR j ITC 1 3.1 0.2 4.0 0.2 ITC-2 3.2 = 0.2 4.0 0.3 35
POINT BEACH NUCLEAR PL ANT AMBIENT GAMMA RADIATION (TLD) c. 3rd. Quarter,1997 Date Annealed: 07-03-97 Days m the field 97 , Date Placed: 07 09-97 Days from Annealing Date Removed: 10-14-97 to Readout: 110 Date Read: - 10-21-97 , Days in Location Field Total mR Net mR Net mR per 7 davs Indicator E-1 97 13.1 0.1 9.0 0.5 0.65 = 0.04 E-2 97 16.1 : 0.4 12.0 0.6 0.S7 0.04 E-3 97 16.5 0.4 12.4 0.6 0.S9 0.04 E-4 97 14.9 0.2 10.3 : 0.5 0.7S : 0.04 E-5 97 14.8 0.1 10.7 : 0.5 0.77 0.04 E-6 97 12.9 0.4 8.8 0.6 0.64 : 0.04 E-7 97 14.1 0.7 10.0 0.9 0.7210.06 E-8 97 16.3 0.3 12.2 t 0.6 0.S8 0.04 E-9 97 18.2 0.4 14.1 0.6 1.02 0.04 E-12 97 15.0 0.3 10.920.6 0.79 0.04 E-14 97 16.0 : 0.5 11.9 : 0.7 0.86 0.05 E-15 97 17.6 0.4 13.5 0.6 0.97 : 0.04 E-16 97 17.0 0.4 12.9 0.6 0.93 0.04 E-17 97 14.9 0.2 10.8 : 0.5 0.7S 0.04 E-13 97 18.0 0.5 13.9 0.7 1.00 0.05 E-22 97 16.4 0.5 12.3 t 0.7 0.S9 0.05 E-23 97 16.8 0.4 12.7 : 0.6 0.92 0.04 E-24 97 17.6 0.4 13.5 t 0.6 0.97 0.04 E-25 97 16.4 : 0.5 12.3 0.7 0.S9 t 0.05 E-26 97 14.9 0.2 10.S 0.5 0.78 t 0.04 E-27 97 14.7 i 0.3 10.6 0.6 0.76 t 0.04 E-28 97 15.4 0.3 11.3 0.6 0.82 t 0.04 E-29 97 15.5 0.6 11.4 0.S 0.S2 0.06 E-30 97 14.6 0.3 10.5 t 0.6 0.76 0.04 E-31 97 16.1 0.6 12.0 : 0.S 0.S7 0.06 E-32 97 18.5 0.6 14.4 : 0.8 1.04 0.06 Contrd E-20 97 14.9 0.1 10.8 0.5 0.78 0.04 Mean S.D. 15.S 1.5 11.8 1.5 0.85 0.10 In-Transit Emosure Date Annealed 06-27-97 10-08-97 Date Read 07-20-97 10-21-97 Total mR ITC-1 4.0 0.2 4.0 : 0.3 ITC-2 4.0 0.3 4.2 0.2 36
I POINT BEACH NUCLEAR PLANT AMBIENT GAMMA RADIATION (TLD) 4th. Quarter,1997 2' Date Annealed: 10-08-97 Days m the held 86 Date Placed: 10-14-97 Days from Annealing Date Removed: 01-08-98 to Readout: 103 Date Read: 01-19-98 Days in Location Field Total mR Net mR Net mR per 7 days l 3 Indicator E-1 86 14.0 0.2 10.9 0.4 0.89 0.03 g E-2 86 14.2 0.2 11.1 = 0.4 0.90 0.03 g E-3 86 15.7 0.4 12.6 : 0.6 1.03 0.05 E-4 86 14.0 0.4 10.9 : 0.6 0.89 : 0.05 E-5 86 15.4 0.4 12.3 : 0.6 1.00 : 0.05 E-6 86 12.5 0.2 9.4 0.4 0.77 0.03 E-7 86 12.0 0.6 8.9 = 0.7 0.72 0.06 E-8 86 15.7 0.5 12.6 = 0.6 1.03 0.05 E-9 86 14.0 0.2 10.9 0.4 0.89 0.03 E-12 86 13.9 0.6 10.820.7 0.88 0.06 E-14 E 15 86 14.8 0.5 11.7 : 0.6 0.95 : 0.05 g 86 15.o 0.6 12.710.7 1.03 0.06 5 E-16 86 14.3 0.2 11.2 = 0.4 0.91 0.03 E-17 E-18 86 13.3 0.7 16.0 0.5 10.2 : 0.8 0.83 0.07 _g 86 12.9 = 0.6 1.05 0.05 i g E-22 86 14.6 0.7 11.5 0.8 0.94 0.07
- E-23 86 16.0 0.5 12.9 0.6 1.05 0.05 g E-24 E-25 86 17.0 0.5 13.9 0.6 1.13 0.05 g 86 15.4 0.6 12.3 0.7 1.00 0.06 E-26 86 14.1 0.3 11.0 0.5 0.90 0.04 E-27 86 14.2 0.3 11.1 0.5 0.90 0.04 E-28 86 15.8 0.6 12.7 0.7 1.03 0.06 E-29 86 14.3 0.4 11.2 0.6 0.91 0.05 E-30 86 14.3 0.4 11.2 0.6 0.91 0.05 E-31 86 14.5 0.4 11.4 : 0.6 0.93 0.05 E-32 86 15.9 0.4 12.8 0.6 1.04 0.05 Control E-20 86 14.1 0.1 11.020.4 0.90 0.03 Mean S.D. 14.7 1.1 11.6 1.1 In-Transit Emosure 0.94 0.09 g g
Date Annealed 10-08-97 01-02 98 Date Read 10-21-97 01-19-98 g ITC-1 4.0 0.3 Total mR 2.1 0.1 g ITC-2 4.2 0.2 2.1 : 0.1 I
-g 37
APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS I NOTE: Teledyne's Midwest Laboratory participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. The results are reported in Appendix A. Also reported are results of InternationalIntercomparison and Teledyne testing of TLD's, as well as, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results. Appendix A la updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only. January,1997 through December,1997
l l l Accendix A
$} ~
Interlaboratorv Comoarison Program Results Teledyne Brown Engineering Environmental Services Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These program > are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuelides known to the issuing agency but not to participant laboratories. The purpo>e of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible ( problems. ( Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Severa! months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the ( controllimits indicate a need to check the instruments or procedures used. ( The results in Table A-1 were obtained through participation in the environmental sample crosscheck l program for milk, water and air filters during the past twelve months. Data for previous years is available upon request. ' This program is conducted by the U.S. Environmental Protection Agency Office of Research and Developement National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada. The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed. Table A-3 lists results of the analyses on in-house " spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request. ( Table A-4 lists results of the analyses on in-house " blank" samples for the past twelve months. Data for previous years available upon request. Table A-5 list results of the in house " duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request. The results in Table A 6 were obtained through participation in the mixed analyte performance evaluation program. The results in Table A-7 were obtained through participation in tbc Environmental Measurement Laboratory Quality Assessment Program. Attachment A lists acceptance criteria for " spiked" samples. Out-of-limit results are explained directly below the result. Al I i
' 12-31-97 ATTACHMENT A ACCEPTANCE CRITERIA FOR "$ PIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARK 's5 ANALYSES' One Standard Deviation I
Analysis Level for si.ngle determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter l >100 pCi/ liter or kg 5% of known value 5 5 to SO pCi/ liter or kg 5.0 pCi/ liter Strontium 89 i >50 pCi/ liter or kg 2 to 30 pCi/ liter or kg 10% of known value 5.0 pCi/ liter Strontium-90*
>30 pCi/ liter or kg 10% of known value
>0.1 g/ liter or kg 5% of known value Potassium-40 s20 pCi/ liter 5.0 pCi/ liter Gross alpha
>20 pCi/ liter 25% of known value s100 pCi/ liter 5.0 pCi/ liter i Gross beta
>100 pCi/ liter 5% of known value s4,000 pCi/ liter is = (pCi/ liter) =
Tritium i >4,000 pCi/ liter 169.85 x (known) 10% of known value Radium-226,-22S <0.1 pCi/ liter 15% of known value 0.1 pCi/ liter, gram, or sample 10% of known value Plutonium lodine-131, 155 pCi/ liter 6.0 pCi/ liter
>55 pCi/ liter 10% of known value Iodine-129*
Uranium-238, s35 pCi/ liter 6.0 pCi/ liter
>35 pCi/ liter 15% of known value Nickel-63*
- Technetium-99*
I Iron-55 50 to 100 pCi/ liter 10 pCi/ liter
>100 pCi/ liter 10% of known value Others' -
20% of known value From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004. Teledyne limit. A2 l L w
Table A 1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'. ~ Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result' Control Code Type Collected Analysis 22 Sigma
- 1s, N=1 Limits STW-782 WATER Jan,1997 Sr-89 9.7 i 0.6 12.0 : 5.0 3.3 - 20.7 STW-782 WATER Jan,1997 Ur-90 24.0 1.0 25.0 5.0 16.3 33.7 STW-783 WATER Jan,1997 Gr. Alpha 10.0 1.4 5.2 5.0 0.0 - 13.9 STW-7S3 WATER Jan,1997 Gr. Beta 15.8 2.0 14.7 : 5.0 6.0 - 23.4 STW-784 WATER Feb,1997 I-131 86.0 2.0 S6.0 : 9.0 70.4 - 101.6 STW-784 WATER Feb,1997 1-131 79.3 : 2.0 86.0 : 9.0 70.4 - 101.6 ST1 VW-786 WATER Feb,1997 Ra-226 6.7 0.2 5.9:0.9 4.3 - 7.5 STWW-786 WATER Feb,1997 Ra-228 8.4 1.1 S.2 : 2.1 4.6 - 11.8 STWW-786 WATER Feb,1997 Uranium 26.5 1.3 27.0 3.0 21.S - 32.3 STW-787 WATER Mar,1997 H-3 7,594.0 279.7 7,900.0 : 790.0 6,529.4 - 9,270.6 STW-794 WATER Apr,1997 Gr. Alpha 44.3 1.6 4S.0 : 12.0 27.2 - 6S.8 STW-794 WATER Apr,1997 Ra-226 10.7 : 0.9 13.0 : 2.0 9.5 - 16.5 STW-794 WATER Apr,1997 Ra-228 4.7 : 0.4 3.1 : 0.S 1.7-4.5 All raw data and calculations were reviewed for errors. The analysis was repeated with the technician observed by the lab supervisor; the result of the reanalysis 3.10.5 pCi/L. The suspected cause of the higher result was the lower than expected recovery of berium tracer. No further action is planned at this time.
STW-794 WATER Apr,1997 Uranium 26.S : 0.3 24 0 3.0 IS.S - 29.2 STW-795 WATER Apr,1997 Co-60 21.7 0.6 21.0 5.0 12.3 - 29.7 STW-795 WATER Apr,1997 Cs-134 27.3 : 1.2 31.0 : 5.0 22.3 - 39.7 STW-795 WATER Apr,1997 Cs-137 21.7 1.5 22.0 5.0 13.3 - 30.7 STW-795 WATER Apr,1997 Gr. Beta 98.2 2.1 102.1 15.3 75.6 - 123.6 STW-795 WATER Apt,1997 Sr-89 21.3 t 1.2 24.0 5.0 15.3 - 32.7 STW-795 WATER Apr,1997 Sr-90 12.7 0.6 13.0 5.0 4.3 - 21.7 STW-796 WATER Jun,1997 Ba-133 24.7 1.2 25.0 5.0 16.3 - 33.7 STW-796 WATER Jun,1997 Co-60 18.7 t 0.6 18.0 5.0 9.3 - 26.7 STW-796 WATER Jun,1997 Cs-134 19.7 0.6 22.0 5.0 13 3 - 30.7 STW-796 WATER Jun,1997 Cs-137 52.0 2.0 49.0 5.0 40.3 57.7 STW-796 WATER Jun,1997 Zn-65 101.0 2.0 100.0 10.0 82.7 - 117.3 STW-797 WATER Jun,1997 Ra-226 2.7 0.1 3.0 0.5 2.1 - 3.9 STW 797 WATER Jun,1997 Ra-22S 2.3 0.3 3.1 t 0.8 L7 - 4.5 STW-797 WATER Jun,1997 Uranium 33.1:1.0 40.3 4.0 33.4 - 47.2 STW-799 WATER Jul,1997 Sr-89 37.7 t 3.2 44.0 : 5.0 35.3 - 52.7 STW-799 WATER Jul,1997 St-90 16.0 1.0 16.0 : 5.0 7.3 - 24.7 STW-802 WATER Jul,1997 I-131 10.7 : 1.2 10.0 : 6.0 0.0 - 20.4 STW-800 WATER Jul,1997 Gr. Alpha 3.1 0.3 3.1:5.0 0.0 - 11.8 STW-800 WATER Jul,1997 Gr. Beta 13.9 0.2 15.1:5.0 6.4 - 23.8 STW-801 WATER Aug,1997 H-3 11,348.7 241.4 11,010.0 1,101.0 9,099.8 - 12,920.2 STW-303 WATER Sep,1997 Ra 226 20.0 t 0.8 20.0 3.0 14.8 - 25.2 Al 1
I Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's I
/P' Midwest Laboratory results'.
Concentration in pCi/ L* l Sample Date Teledyne Results EPA Result" Control Lab Type Collected Analysis 2 Sigma
- 1s, N=1 Limits Code 7.0z0.1 8.0 2.0 4.5 - 11.5 STW-803 WATER Sep,1997 Ra-22S E STW-803 WATER Sep,1997 Uranium 5.0 0.1 5.1 3.0 0.0 - 10.3 g WATER Nov,1997 Ba-133 97.3 5.0 99.0 10.0 St.7 116.3 STW-811 Nov,1997 Co-60 28.3 1.7 27.0 5.0 IS.3 - 35.7 STW-811 WATER E STW-811 WATER Nov,1997 Cs-134 9.7 : 1.0 10.0 : 5.0 1.3 - 18.7 3 STW-811 WATER Nov,1997 Cs-137 78.0 3.5 74.0 5.0 65.3 - 82.7 STW-811 WATER Nov,1997 Zn-65 76.7 2.1 75.0 8.0 61.1 - 8S.9
- Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercompanson and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. g Envirownental Protection Agency (EPA), Las Vegas, Nevada. 3
- All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L: air filter samples, which are in pCi/ Filter. g
- Unless otherwise indicated, the TBEESML results are given as the mean 2 standard c;eviations for three g determinations.
d USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and controllimits as defined by the EPA. I I I I Al-2 I
Table A 2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average :13igma Code TLD Type Date Measurement 2 Sigma Value 2 Siema ( All Particioants) 2nd Intemational Intercomcarison 115-2 CaF:: Mn Bulb Apr,1976 Field 17.0 1.9 17 ~ 16.4 : 7.7 115-2 CaF:: Mn Bulb Apr,1976 Lab 20.S : 4.1 2L3 IS.S : 7.6 second IntemationalIntercomparison of Environmental Dosimeters conducted it. April of 1976 by the Health and Safety Laboratory (HASL), New York, new York, and the School of Public Health of the University of Texas, Houston, Texas. 3rd Intemational Intercomcarison 115-3 CaF:: Mn Bulb Jun,1977 Field 30.7 3.2 ~4.9 : 4.S 31.5 : 3.0 115-3 CaF : Mn Bulb Jun,1977 2 Lab S9.6 6.4 91.7 : 14.6 S6.2 : 24.0 Third IntemationalIntercomparison of Environmental Dosimeters conducted in the summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas. 4th International Intercomoarison 115-4 CaF:: Mn Bulb Jun,1979 Field 14.1 1.1 14.1 : 1.4 16.0 9.0 115-4 CaF:: Mn Bulb Jun,1979 Lab, High 40.4 1.4 45.S : 9.2 43.9 13.2 115-4 CaF:: Mn Bulb Jun,1979 Lab, Low 9.S 1.3 12.2 : 2.4 12.0 7.4 Fourth IntemationalIntercomparison of Environmental Dosimeters conducted in the summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 5th Inte national Intercomoarison 115-5 A CaF:: Mn Bulb Oct,1980 Field 31.4 : 1.8 30.0 6.0 30.2 14.6 115-5 A CaF:: Mn Bulb Oct,19SO Lab,End 96.6 : 5.8 SS.4 : 8.8 90.7 31.2 115-5 A CaF:: Mn Bulb Oct,1950 Lab, Start 77.4 5.8 75.2 7.6 75.5 40.4 Fifth Intemational Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 5th Intemational Intercomoarison 115-5B LiF-100 Chips Oct,1980 Field 30.3 4.8 30.0 6.0 30.2 : 14.6 115-5B LiF-100 Chips Oct,1980 Lab,End 85.4 11.7 88.4 8.8 90.7 : 31.2 115-5B LiF-100 Chips Oct,1980 Lab, Start St.1 7.4 75.2 t 7.6 75.8 40.4 Fifth Intemational Intercomparison of Environmental Dosimeters conducted in the fall of 19S0 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 6th Intemational Intercomoarison 115-6 Teledyne did not participate in the Sixth Intemational Intercomparison of Environmental Dosimeters. 7th Intemational Intercomoarison 115-7A LiF-100 Chips Jun,19M Field 75.4 2.6 75.S 6.0 75.1 29.8 115-7A LiF-100 Chips Jun,19M Lab, Co-60 80.0 t 3.5 79.9 4.0 77.9 27.6 115-7A LiF-100 Chips Jun,19M Lab, Cs-137 66.6 2.5 75.0 3.8 73.0 22.2 A21
~
I Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). Teledyne Results Known mR Average :2 Sigma I Lab Value : 2 Siema ( All Participants) TLD Type Date Measurement 2 Siema Code Seventh 1nternationalIntercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. 7th International Intercomoarison Field 71.5 : 2.6 75.8 6.0 75.1 29.8 115-7B LiF-100 Chips Jun,19M 115-7B LiF 100 Chips Jun,19M Lab, Co-60 84.8 6.4 79.9 4.0 77.9 : 27.6 g' Lab, Cs-137 78.8 1.6 75.0 : 3.8 > 3.0 : 22.2 3 115-7B LiF-100 Chips Jun,1984 Seventh InternationalIntercomparison of Environmental Dosimeters conducted in the spring and summer of 3 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. g 7th International Intercomoarison Field 76.8 2.7 75.8 : 6.0 75.1 29.8 115-7C CaSO : Dy Jun,19M Cards Lab, Co-60 82.5 3.7 79.9 4.0 77.9 : 27.6 CaSO : Dy Jun,1984 115-7C Cards g Lab, Cs-137 '79.0 3.2 75.0 3.8 73.0 22.2 5 115-7C CaSO.: Dy Jun,1984 Cards Seventh InternationalIntercomparison of Environmental Dosimeters conducted in the spring and .3ummer of l ( 5 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. Sth International Intercomoarison = 29.5 1.4 29.7 1.5 28.9 : 12.4 115-8A LiF-100 Chips Jan,1986 Field, Site 1 11.3 0.8 10.4 0.5 10.1 9.1 115-8 A LiF-100 Chips Jan,1986 Field, Site 2 Lab, Ca-137 13.7 0.9 17.2 0.9 16.2 6.8 115-8 A LiF-100 Chips Jan,1986 Eighth InternationalIntercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1985 at New York, New York, and sponsored by the U.S. Department of Energy. 8th Intemational'Intercomparison LiF-100 Chips Jan,1986 Field, Site 1 32.3 1.2 29.7 1.5 28.9 : 12.4 115-8B LiF-100 Chips Jan,1986 Field, Site 2 9.0 1.0 10.4 0.5 10.1 9.0 115-8B Lab, Cs 137 15.8 0.9 17.2 0.9 16.2 6.8 115-8B LiF-100 Chips Jan,1986 Eighth IntemationalIntercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy. g 5 8th International Intercomoarison Jan,1986 Field, Site 1 32.2 0.7 29.7 ! 1.5 28.9 12.4 115-8C CaSO.: Dy Cards g 10.6 : 0.6 10.4 0.5 10.1 9.0 g 115-8C CaSO : Dy Jan,1986 Field, Site 2 Cards 115-8C CaSO.: Dy Jan,1986 Lab, Cs-137 18.1 0.8 17.2 0.9 16.2 6.8 g g Cards l
-I l
A2-2 j l l l l l
Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 2 Sigma Ccde TLD Type Date Measurement 2 Siema Value : 2 Siema ( All Participants) Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of i 19SS-1986 at New York, New York, and sponsored by the U.S. Department of Energy. 9th International Intercomoarison 115 9 The Ninth International Intercomparison of Environmental Dosimeters was not available to Teledyne's Midwest Laboratory. I jpth International Intercomoarison 11510A LiF-100 Chips Aug,1993 Field 25.7 1.4 27.0 : 1.6 26.4 : 10.2 I 115-10A LiF-100 Chips Aug,1993 Lab,1 22.7 t 1.6 25.9 1.3 25 0 9.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62 7 : 2.6 72.7 1.9 69.S t 20.3 The Tenth Intemational Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State I University and sponsored by the U.S. Department of Energy and the Idaho State University. 10th International Intercomoarison 11510B CaSO4 : Dy Aug,1993 Field 26.0 2.3 27.0 1.6 26.4 10.2 I Cards 115-10B CaSO : Dy 4 Aug,1993 Lab,1 24.1 1.7 25.9 : 1.3 25.0 9.4 Cards I 115-10B CaSO4 : Dy Aug,1993 Lab,2 69.2 3.0 72.7 : 1.9 69.S 20.3 Cards The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State I University and sponsored by the U.S. Department of Energy and the Idaho State University. 1]Jh International Intercomoarison 115-11 Apr,1997 The Eleventh IntemationalIntercomparison of Environmental Dosimeters was conducted in 1997 and was organized by the Department of Energy's Environmental Measurements Laboratory in collaboration with Brookhaven National Laboratory and the National Institute of Standards and Technology. Results for the Eleventh Intemational Intercomparison were originally reported in error; The results are being re-evaluated and will be reported in a later update. Teledyne Testing S91 LiF-100 Chips Sep,1989 Lab 21.0!0.4 22.4 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes,Inc., Westwood, New Jersey, in September,1989. Teledyne Testing 89 2 CaSO4 : Dy Nov,1989 Lab 20.9 1.0 20.3 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. A2-3
I Table A-2. Crosscheck program results; 7hermoluminescent Dosimeters. (TLDs). I.
. Og Lab Teledyne Results Known Average :2 Sigma Code TLD Type Date Measurement 2 Siema Value 2 Siema ( All Participants)
E Teledyne Testing g 90-1 CaSO4 : Dy Jun,1990 Lab 20.6 1.4 19.6 ND Cards g ND = No Data; Teledyne Testing was only performed by Teledyne. E Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. Teledvne Testing g 90-2 CaSO4 : Dy Jun,1990 Lab 100.8 4.3 100.0 ND " Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Dosimetry Asssociates, Inc., Northville, MI, in October,1990. Teledvne Testing 91-1 CaSO4 : Dy Oct,1990 Lab,1 33.4 2.0 32.0 ND Cards 91-1 CaSO4 : Dy Oct,1990 Lab,2 55.2 4.7 58.S ND Cards 91-1 CaSO4 : Dy Oct,1990 Lab,3 87.8 6.2 85.5 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in October,1991. Teledvne Testing 92-1 LiF-100 Chips Feb,1992 Lab,1 11.1 0.2 10.7 ND 92-1 LiF-100 Chips Feb,1992 Lab,2 25.6 0.5 25.4 ND 92-1 LiF-100 Chips Feb,1992 Lab,3 46.4 0.5 46.3 ND g ND = No Data; Teledyne Testing was only performed by Teledyne. E Chips were irradLud by Teledyne Isotopes, Inc., Westwood, New Jersey, in February,1992. Teledyne Testing 92-2 CaSO4 : Dy Apr,1992 Reader 1, #1 20.1 0.1 20.1 ND Cards 92-2 CaSO4 : Dy Apr,1992 Reader 1, #2 40.6 0.1 40.0 ND Cards 92-2 CaSO4 : Dy Apr,1992 Reader 1, #3 60.0 1.3 60.3 ND Cards 92-2 CaSO4 : Dy Apr,1992 Reader 2, #1 20.3 0.3 20.1 ND l W Cards 92-2 CaSO4 : Dy Apt,1992 Reader 2, #2 39.2 0.3 40.0 ND Cards 92-2 CaSO4 : Dy Apr,1992 Reader 2, #3 60.7 0.4 60.3 ND Cards vI A2-4
Table A-2. Crosscheck program results;1hermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average t 2 Sigma TLD Type Date Measurement 2 Sigma Value : 2 Siema ( All Particicants) _ Code ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in April,1992. Teledvne Testing 93 1 Teledyne Mar,1993 Lab,1 10.0 : 1.0 10.2 ND LiF-100 Chips Teledyne Mar,1993 Lab,2 25.2 2.2 25.5 ND I93-1 LiF-100 Chips 93-1 Teledvne Mar,1993 Lab,3 42.7 5.7 45.9 ND LiF-100 ' Chips ND = No Dea;Teledyrie Testing was only performed by Teledyne. Chips were irradiated by Toledyne Isotopes, Inc., Westwood, New Jersey, in March,1993. Due to a potential error of 10-12% when c trds where irradiated, results of the testing on the cards will not be published. Data is I available upon aquest. Teledvne Testing 94-1 Teledyne Nov,1994 Lab,1 15.620.4 14.9 ND [ LiF-100 Chips 94-1 Teledyne Nov,1994 Lab,2 30.2 0.4 29.S ND LiF-100 Chips 94-1 Teledyne Nov,1994 Lab,3 59.2 0.3 59.7 ND LiF-100 Chips 94 1 CaSOg Dy Nov,1994 Reader 1, #1 14.9 0.1 14.9 ND I Cards 94-1 CaSOg Dy Nov,1994 Reader 1, #2 30.8 0.1 29.8 ND Cards l 94-1 CaSOg Dy Nov,1994 Reader 1, #3 58.9:0.3 59.7 ND Cards 94-1 CaSOg Dy Nov,1994 Reader 2, #1 15.4 0.2 14.9 ND I Cards 94-1 CaSOg Dy Nov,1994 Reader 2, #2 31.4 0.2 29.S ND Cards l 941 CaSOp Dy Nov,1994 Reader 2, #3 60.1 0.3 59.7 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes,.inc., Westwood, New Jersey, in November,1994. l Teledyne Testing 95-1 LiF-100 Chips Mar,1995 Lab,1 16.1 0.2 15.7 95-1 LiF-100 Chips Mar,1995 Lab,2 31.7 0.1 32.3 7 95 1 LiF-100 Chips Mar,1995 Lab,3 59.710.6 60.S 95-1 CaSOg Dy Mar,1995 Reader 1, #1 16.4 0.1 15.7 ND Cards l A2-5
i Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). 1.ab Teledyne Results Known Average 2 Sigma l Date Measurement 2 Sigma Value : 2 Siema ( All Participants) Code TLD Tvoe 95 1 CaSO4 Dy Mar,1995 Reader 1, #2 34.9 t 0.1 32.3 ND Cards 95-1 CaSOg Dy Mar,1995 Reader 1, #3 64.4 1.5 60.S ND g Cards g ND = No Data; Teledyne Testing was only performed by Teledyne. Cards and Chips were irradiated by Teledyne Isotooes, Inc., Westwood, New Jersey, in March,1995. E g Ietedvne Testing CaSOg Dy Mar,1995 Reader 2, #1 16.4 0.2 15.7 ND 95 2 Cards 95-2 CaSOg Dy Mar,1995 Reader 2, #2 33.9 0.4 32.3 ND Cards 95-2 CaSOg Dy Mar,1995 Reader 2, #3 60.5 0.3 60.8 ND l W Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1995. Teledvne Testing 96-1 lit-100 Chips Mar,1996 Lab,1 15.9 0.3 15.4 96 1 LiF-100 Chips Mar,1996 Lab,2 29.4 0.3 30.8 . 96 1 LiF-100 Chips Mar,1996 Lab,3 62.5 1.3 62.5 96 1 CaSOg Dy Mar,1996 Reader 1, #1 14.4 0.1 15.4 ND Cards 96 1 CaSOg Dy Mar,1996 Reader 1, #2 31.8 0.1 30.8 ND Cards 96-1 CaSOg Dy Mar,1996 Reader 1, #3 64.7 0.4 62.5 ND Cards Teledyne Testing g 96-2 CaSOg Dy Mar,1996 Reader 2, #1 14.3 0.4 15.4 ND g Cards 96-2 CaSOp Dy Mar,1996 Reader 2, #2 31.8 0.1 30.8 ND g Cards g 96-2 CaSOg Dy Mar,1996 Reader 2, #3 68.6 0.1 62.5 ND l Cards 1 l ND = No Data; Telodyrve Testing was only performed by Teledyne. l Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1996. l Teledvne Testing l 97-1 LiF-100 Chips Mar,1997 Lab,1 13.4 1.4 15.0 97-1 LiF-100 Chips Mar,1997 Lab,2 29.8 0.6 30.1 97-1 LiF-100 Chips Mar,1997 Lab,3 63.4 0.9 60.2 l s._ l A2-6 I
Table A-2. Crosscheck prograrn results; Thermolurninescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 2 Sigma Code TLD Tvoe Date Measurement 2 Sigma Value : 2 Siema ( All Particioants) 97-1 CaSO4 : Dy Mar,1997 Reader 1, #1 15.5 0.1 15.0 ND Cards 97 1 CaSO : Dy 4 Mar,1997 Reader 1, #2 34.0 : 0.1 30.1 ND Cards 97-1 CaSO.: Dy Mar,1997 Reader 1, #3 6S.3 2.1 60.2 ND Cards Teledvne Testinc 97-2 CaSO : Dy Mar,1997 Reader 2, #1 16.8 0.3 15.0 ND Cards 97-2 CaSO4 : Dy Mar,1997 Reader 2, #2 36.2 0.2 J 0.1 ND Cards 97-2 CaSO4 : Dy Mar,1997 Reader 2, #3 69.6 0.2 60.2 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1997. A2-7
l Table A-3. In-house " spike" samples.
% ~
Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analysis 2s, n=1' Activity Limits SPW 844 WATER Jan,1997 Th 230 3.120 0.104 3.070 1.842 - 4.29S SPW-844 WATER Jan,1997 Th-232 3.355 0.108 3.070 1.S42 - 4.293 i SPW 54S SPMI-534 WATER MILK MILK Feb.1997 Gr. Beta Feb,1997 Cs-134 43.381 1.305 48.649 4.940 41.S60 36.400 31.860 - 51.S60 4o 400 - 66.400 SPMI-534 Feb,1997 Cs-137 54.700 S.450 52.300 42.300 - 62.300 MILK 49.849 7.940 l SPMI-533 SPMI 535 MILK Feb,1997 Sr-89 Feb,1997 Sr 90 4S.S56 1.740 40.030 30.300 30.030 - 50.030 40.240 - 60.360 SPW-536 WATER Feb,1997 H-3 27229.744 : 452.056 2S234.000 22557.200 - 33SSO S00 SPW-547 WATER Feb,1997 Co-60 65.219 S.790 62.950 52.950 72.950 SPW-547 WATER Feb,1997 Cs-134 52.996 ! 8.000 56.430 46.430 - 66.430 SPW-547 WATER Feb,1997 Cs-137 60.419 12.900 52.320 42.320 62.320 SPW-600 WATER Feb,1997 I-131 72.182 1.009 66.300 53.040 - 79.560 SPW 600 WATER Feb,1997 I 131(g) 6S.S16 : 14.S00 66.300 39.7SO - 76.300 SPCil-701 CHARCOAL Feb,1997 I-131(g) 1.171 0.023 1.080 0.648 - 1.512 i SPAP-704 SPW-S38 CANISTER AIR FILTER WATER Feb,1997 Gr. Beta Feb,1997 Ra-226 6.302 0.041 19.770 0.139 5.740 17.300 0.000 - 15.740 12.110 22.490 SPW S3S WATER Feb,1997 Ra 228 36.7S4 2.571 31.300 21.910 40.690 l SPW-S40 WATER Feb,1997 Sr-90 35.S22 2.020 33.520 26.316 - 40.224 SPW-841 WATER Feb,1997 I-129 15.525 0.854 14.942 2.942 - 26.942 SPW-S43 WATER Feb,1997 Fe-55 1.418 0.530 1.535 0.000 - 21.535 1 SPAP-2730 AIR FILTER Mar,1997 Cs-137 2.151 0.025 1.900 1.140 - 2.660 SPMI-1670 MILK Apr,1997 Cs-134 50.2S2 : 8.920 53.600 43.600 - 63.600
$PMI-1670 MILK Apr,1997 Cs-137 56.090 14.900 52.100 42.100 - 62.100 SPW-2073 WATER Apr,1997 Co-60 34.077 : 4.280 51.300 41.300 - 61.300 SPW-2073 WATER Apr,1997 Cs 134 47.636 4.150 53.200 43.200 - 63.200 SPW-2073 WATER Apt,1997 Cs-137 60.6S8 : 5.760 52.100 42.100 - 62.100 SPW-2075 WATER Apr,1997 Gr. A1pha 34.554 e 2.677 41.300 20.630 - 61.950 SPW-2075 WATER Apt,1997 Gr. Beta 38.729 : 1.658 41.700 31.700 - 51.700 SPW-2546 WATER Apr,1997 H-3 25445.478 42S.384 26257.000 21005.600 - 31508.400 SPF-3434 FISH May,1997 Cs-134 0.199 0.020 0.222 0.133 0.311 i
SPF 3434 FISH May,1997 Cs-137 0.234 : 0.037 0.227 0.136 - 0.318 SPW-3750 WATER Jun,1997 I-131 76.174 0.776 71.S00 57.440 - 86.160 l SPW-3750 WATER Jun,1997 I-131(g) 66.5S7 S.750 71.S00 43.0S0 - S1.S00 SPMI-3752 MILK Jun,1997 I-131 79.851 : 0.S33 71.S00 57.440 - 86.160 SPMI 3752 MILK Jun,1997 I-131(g) 78.887 : 7.250 71.800 43.080 - S1.800 SPCH-3754 CHARCOAL Jun,1997 I-131(g) 81.869 0.317 76.600 45.960 - S6.600 CANISTER SPMI-4216 MILK Jul,1997 Cs-134 38.265 5.450 39.500 29.500 - 49.5v0 I SPMI-4216 MILK Jul,1997 Cs 137 46.472 t 10.600 41.500 31.500 - 51.500 SPMI 4216 MILK Jul,1997 I-131 75.247 0.S31 S3.230 66.584 - 99.S76 SPMI 4216 MILK Jul,1997 I-131(g) S4.872 7.010 83.230 49.938 - 93.230 A3-1 F
I Table A-3. In-house " spike" samples. Concentration in pCi/ L' @ Lab Sample Date Teledyne Results Known Control' Code Type Collected Analysis 2s, n=1' Activity Limits SPMI-4216 MILK Jul,1997 Sr-90 33.610 1.430 33.210 26.563 39 S32 SPW-4420 WATER Jul,1997 Co-60 26.270 4.360 24.900 14.900 34.900 SPW-4420 WATER Jul,1997 Cs-134 36.591 5.040 39.540 29.540 - 49.540 g SPW-4420 WATER Jul,1997 Cs 137 45.552 7.770 41.4S0 31.480 - 31.4S0 E SPW-4420 WATER Jul,1997 I-131(g) 85.221 9.660 S3.230 49.93S - 93.230 SPW-4420 WATER Jul 1997 Sr-90 36.285 : 1.629 33.210 26.568 - 39.S52 g SPMI-4916 MllK Jul,1997 I-131(g) 84.870 7.010 03.230 49.938 - 93.230 5 SPW-5470 WATER Jul,1997 Fe-55 4.548 : 0.640 5.477 0.000 - 25.477 SPW-5472 WATER Jul,1997 H-3 41026.000 : 329.000 41573.000 33262.400 - 49S93.600 g WATER Jul,1997 Gr. Alpha 49.266 : 2.031 41.305 20.653 - 61.95S 5 SPW-5474 SPW-5474 WATER Jul,1997 Gr. Beta 44.450 1.334 41.406 31.406 - 51.4Cf SPF-5476 FISH Jul,1997 Cs-134 0.641 0.030 0.700 0.420 - 0.930 l
=
SPF-5476 FISH Jul 1997 Cs-137 0.632 0.042 0.527 0.316 - 0.738 SPW-7500 WATER Oct,1997 Co-60 30.424 7.530 33.642 23 642 - 43.642 SPW-7500 WATER Oct,1997 Cs-134 37.410 : 6.690 36.086 26.086 - 46.086 SPW-7500 WATER Oct,1997 Cs-137 52.845 : 11.300 41.221 31.221 - 51.221 The Cs-137 spike is suspect. No errors were found in the spectroscopy program and the Cs-134 and Co-60 test results on the same sample were very good. Sample results prepared with a new standard are ,-- l acceptable. I m SPW-7500 WATER Oct,1997 I-131 78.126 1.201 73.302 62.642 - 93.962 SPMI-7505 MILK Oct,1997 Cs-134 15.166 3.250 IS.043 S.043 - 2S.043 SPMI-7505 MILK Oct,1997 Cs-137 91.110 S.370 S2.440 72.440 - 92.440 l 5PMI-7505 MILK Oct,1997 I-131 73.529 1.253 78.302 62.642 - 93.962 SPMI-7505 MILK Oct,1997 I-131(g) 74.613 8.810 78.302 46.981 - 88.302 l SPMI-7506 MILK Oct,1997 Sr-89 31.281 4.601 39.490 29.490 - 49.490 m SPCH-7727 CHARCOAL Oct,1997 I-131(g) 0.450 0.050 0.440 0.264 - 0.616 CANISTER SPAP-7730 AIR FILTER Oct,1997 Gr. Beta 3.080 0.030 3.040 1.S24 - 4.236 (ss) SPF-8483 FISH Nov,1997 Cs-134 0.306 0.025 0.31S 0.191 - 0.445 SPF-8485 FISH Nov,1997 Cs-137 0.738 0.049 0.649 0.389 - 0.909 SPW 9315 WATER Nov,1997 Gr. Alpha 51.420 6.385 41.2SO 20.640 - 61.920 l l SPW-9315 WATER Nov,1997 Gr. Beta 48.938 3.735 43.164 33.164 - 53.164 i SPW-9706 WATER Dec,1997 Gr., Alpha 40.480 4.598 41.2SO 20.640 - 61.920 SPW-9853 WATER Dec,1997 Co-60 44.900 8.290 42.0SO 32.080 - 52.080 SPW-9353 WATER Dec,1997 Cs-134 40.010 7.010 37.850 27.850 47.850
' All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L.; air filter samples, which are in pCi/ Filter; and food products, which are in mg/kg.
' All samples are the results of single determinations. g
' Controllimits are based on Attachrr.ent A, page A2 of this report. 3 NOTE: For fish, Jello is used for the spike matrix. For vegetation, Sawdust is used for the spike matrix.
A3-2
l Table A-4. In-house " blank" samples.
"h Concentration pCi/ L.
Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Tvpe Date Analysis LLD Activity (4.66 Siema) SPW-845 WATER Jan 1997 Th-228 <0.9 -0.263 0.560 <1.000 SPW-845 WATER Jan 1997 Th-230 <0.2 0.191 0.236 <1.000 SPW-845 WATER Jan 1997 Th-232 <0.2 -0.01S = 0.145 < l.000 SPh!I-533 NIILK Feb l997 Cs-134 <2.7 -0.531 : 0.647 < 10.000 SPht!-333 MILK Yeb 1997 Cs-137 <5.5 0.526 3.380 < 10.000
$PW-2 WATER Feb 1997 Ra-226 < 0.1 0.000 : 0.034 <1.000 SPAII-533 NIILK Feb 1997 I-131 <0.5 -0.031 0.316 < 0.500 SPNII-533 NIILK Feb 1997 Sr-S9 <0.7 -0.994 0.952 <5.000 SPN!!-333 MILK Feb 1997 Sr 90 N/A 1.695 0.439 <1.000 Low level of St-90 concentration in milk (15 pCi/L) is not unusual.
I SPW-537 SFW-537 WATER WATER Feb 1997 Co-60 Feb 1997 Cs-134
< 3.1
<3.5 0.065 ? ; 179 C.905 :1.100
< 10.000
< 10.000 SPW-537 WATER Feb l997 Cs-137 < 1. 7 -1.430 1.S00 < 10.000 SPW-537 WATER Feb l997 Gr. Alpha <0.4 -0.109 = 0.21S <1.000 SPW-537 WATER Feb l997 Gr. Beta <0.9 -0.155 0.596 < 3.200 SP W-537 WATER Feb l997 I-131 <0.4 -0.275 0.235 <0.500 SPW-337 WATER Feb l997 Sr-S9 <0.S -0.167 0.557 < 5.000 0.099 0.239 I SPW 337 SPW- 42 WATER WATER Feb 1997 Sr 90 Feb 1997 Fe-35
<0.5
< 0. 7 -0.403 : 0.374
<1.000
< 1000.000 SPW-842 WATER Feb l997 I-129 <0.9 -0.129 0.442 <1.500 SPW-S42 WATER Feb 1997 Ra-226 <0.04 0.013 : 0.026 <1.000 SPAP-2731 AIR FILTER Mar 1997 Co-60 <2.5 0.000 0.000 < 10.000 SPAP-2731 AIR FILTER NIar 1997 Cs-134 < 2. 6 -0.000 0.000 < 10.000 I SPAP-2731 AIR FILTER Mar 1997 Cs-137 <2.9 0.000 t 0.001 < 10.000 SPht!-1669 MILK Apr 1997 Cs-134 <5.5 0.069 : 0.118 < 10.000 SPMI-1669 MILK Apr 1997 Cs 137 <3.8 0.717 : 2.4S0 < 10.000 SPW 2074 WATER Apr 1997 Co-60 <3.6 0.857 S.3SO < 10.000 SPW-2074 WATER Apr 1997 Cs-134 <4.7 1.610 : 10.200 < 10.000 I SPW-2074 WATER Apr1997 Cs-137 <5.0 1.S00 3.200 < 10.000 SPW-2074 WATER Apr1997 Cr. Alpha <0.5 0.119 0.307 <1.000 SPW 2074 WATER Apr 1997 Gr. Beta < 1. 3 0.464 0.720 < 3.200 SPW-2547 WATER Apr 1997 H3 < 150 12.822 : 75.126 < 200.000
$PW-5 WATER May 1997 Ra-226 <0.03 -0.053 0.025 <1.000 I SPF-3435 FISH May 1997 Cs 134 <0.015 -0.014 : 0.002 < 10.000
$PF-3435 FISH May 1997 Cs-137 <0.016 0.001 0.011 < 10.000
$PW-6 WATER Jun1997 Ra-226 <0.04 -0.044 1 0.027 <1.000 A4-1
I Table A-4. In-house " blank" samples. Concentration pCi/ L'. $ Teledyne Results Acceptance Lab Sample Sample (4.66 Sizma) Criteria Code Tvoe Date Analvsis LLD Activitv* (4.66 Siema) WATER <0.3 -0.127 : 0.145 <0.500 SPW-3751 Jun1997 I-131
<0.3 0.089 :0.167 <0.500 SPMI-3753 MILK Jun1997 I-131 SPCH-3755 CHARCOAL Jun1997 I-131(g) <0.017 0.010 : 0.009 < 9.600 l E
CANISTER Co-60 <4.8 -0.392 : 1.230 < 10.000 SPMI-4217 MILK Jul1997 Cs 134 <3.0 -0.S74 : 1.700 < 10.000 SPMI-4217 MI'LK Ju11997 Cs-137 <5.9 1.600 3 430 < 10.000 SPMI-4217 MILK Jul1997
<0.3 -0.049 : 0.171 < 0.500 SPMI-4217 MILK Jul1997 I-131 E WATER Jul1997 Co-60 < 1.9 -4.660 : 4.750 < 10.000 E SPW-4421 Cs-134 <4.7 -1.450 2 3.090 < 10.000 SPW-4421 WATER Jul1997 Cs 137 <6.7 0.739 : 4.550 < 10.000 SPW-4421 WATER Jul1997 Sr-S9 < 1. 5 -0.165 : 1.901 < 5.000 SPMI-4217 MILK Jul1997 Sr-90 N/A 1.677 : 0.418 <1.000 SPMI-4217 MILK Jul1997 Low level c f Sr-90 concentration in milk (15 pCi/ L) is not i.tnusual.
SPW-4421 WATER Jul1997 Sr-89 < 1.7 0.917 1.547 < 5.000 SPW-442 t WATER Jul1997 Sr-90 <0.6 0.341 0.332 <1.000 g
<733 43.157 : 443.317 < 1000.000 ( N SPW-5471 WATER Jul1997 Fe-55 H-3 <161 22.700 5S.200 < 200.000 SPW-5473 WATER Jul1997 Cr. Alpha <0.6 0.170 0.425 <1.000 SPW-5475 WATER Jul1997 Gr. Beta <0.5 0.173 : 0.473 < 3.200 SPW-5475 WATER Jul1997 SPF-5477 FISH Jul1997 Co-60 <0.011 -0.001 0.002 < 10.000 g FISH Jul1997 Cs-134 <0.015 0.005 : 0.00S < 10.000 E SPF-5477 SPF-5477 FISH Ju11997 Cs-137 <0.018 0.006 0.010 < 10.000 SPW-7501 WATER Oct 1997 I-131 <0.4 0.010 0.009 < 0.500 Oct 1997 Sr-S9 < 1.1 -0.650 0 0.800 <5.000 SPW-7504 WATER SPW-7504 WATER Oct 1997 Sr-90 <0.4 0.150 0.210 < 1.000 g MILK Oct 1997 Co-60 < 6.2 -1.190 1.620 < 10 000 g SPMI-7507 Oct 1997 C5134 < 4.9 1.710 1.950 < 10.000 SPMI-7507 MILK Oct 1997 Cs-137 <6.5 -0.232 3.740 < 10.000 SPMI 7507 MILK
<0.3 -0.022 0.157 < 0.500 SPMI-7507 MILK Oct 1997 I-131 Oct 1997 Sr-89 < 1.0 0.862 : 1.107 <5.000 SPMI-7507 MILK Oct 1997 Sr 90 N/A 1.031 0.319 <1.000 SPMI-7507 MILK Low level of St 90 concentration in milk (1-5 pCi/L)is not unusual.
Dec 1997 Ra-223 <0.7 0.134 0.31S <1.000 RA-W-11 WATER
<2.4 -1.600 9.460 < 10.000 SPW-9852 WATER Dec 1997 Co-60 Dec 1997 Cs 134 <5.7 -0.450 2.34 0 < 10.000 SPW-9852 WATER s
A4-2
Table A-4. In-house " blank" samples. I Concentration pCi/ L*. Teledyne Results Acceptance Lab Sample Sample (4.66 Siema) Criteria Code Tvoe Date Analvsis LLD Activitv' I4 66 Siema) SPW-9832 WATER Dec 1997 Cs-137 <6.0 2.190 = 3.550 < 10.000 Liquid sample results are reported in pCi/ Liter, air filter sample results are in pCi/ filter, charcoal sample results are in pCi/ charcoal, and solid sample results are in pCi/ kilogram.
- The activity reported is the net activity result.
A4-3
Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes' Date Analysis Result Result Result iW 42,43 Jan,1997 Cr. Beta 3.0753 0.9097 2.5036 t 0.SS19 2.7S94 0.6335 41-63,64 Jan,1997 Co-60 0.8960 2.5500 0.S290 1.4300 0.S625 1.4618 41- 63,64 Jan,1997 Cs-137 0.4480 2.0600 0.7240 1.3800 0.5S60 : 1.2393 MI - 19,20 Jan,1997 Co-60 2.7900 2.6200 1.4300 : 2.4700 2.1100 : 1.8004 MI - 19,20 Jan,1997 Cs-137 -0.8750 2.7600 2.3900 1.9100 0.7575 : 1.67S2 MI - 92,93 Jan,1997 I-131 0.0455 0.2124 0.1031 0.2405 0.0743 0.1604 MI - 92,93 Jan,1997 K-40 1,466.8000 129.0000 1,417.3000 163.0000 1,442.0500 t 103.9351 WW - 116,117 Jan,1997 I-131 0.1299 0.2579 -0.0824 : 0.2359 0.0237 : 0.1747 LW - 146,147 Jan,1997 Co-60 -0.1850 0.4500 1.9100 : 16.9000 0.S625 S.4530 LW - 146,147 Jan,1997 Cs-137 -0.8360 t 2.1600 0.2350 3.4500 -0.3005 : 2.0352 LW - 146,147 Jan,1997 Gr. Beta 6.9782 1.4082 7.S900 t 1.5599 7.4341 1.0507 LW - 224,225 Jan,1997 Co-60 1.8300 4.2500 -1.2200 0.9290 0.3050 2.1752 LW - 224, 225 Jan,1997 Cs-137 -0.9650 3.4000 1.4500 1.7100 0.2425 t 1.9029 LW - 224, 225 Jan,1997 Gr. Beta 6.2S89 1.3951 7.3610 t 1.5370 6.S250 1.0379 WW - 322,323 Jan,1997 H-3 -5.4270 80.6586 -14.4721 S0.2518 -9.9496 56.8906 CW - 355,356 Jan,1997 Gr. Beta 3.1262 1.42S1 2.05S9 1.4561 2.5926 1.0198 CW - 355,356 Jan,1997 Cr. Beta -0.3849 1.2993 0.4440 1.3725 0.0296 0.9450 CW - 299, 300 Jan,1997 Gr. Beta 2.4965 1.0877 2.7913 1.4707 2.6439 t 0.9146 CW - 299, 300 Jan,1997 Gr. Beta 0.2070 1.3507 0.7394 1.3967 0.4732 0.9715 SW 441,442 Jan,1997 Co-60 -0.2460 1.3100 0.3250 0.3190 0.0395 0.6741 SW 441,442 Jan,1997 Cs 137 0.0619 t 2.3900 3.0200 2.8400 1.5410 1.8559 SWU - 389, 390 Jan,1997 Gr. Beta 2.7555 0.5392 2.65S5 t 0.5182 2.7070 0.3739 SWU - 389, 390 Jan,1997 H-3 158.6398 : 94.8968 125.0455 93.5661 141.8427 66.6333 MI - 377,378 Jan,1997 I-131 0.1482 0.2260 0.0950 0.2541 0.1216 0.1700 MI - 377,376 Jan,1997 K-40 1,379.5000 122.0000 1,304.8000 : 113.0000 1,342.1500 83.1460 MI 377,378 Jan,1997 St-89 -0.4172 0.8436 -0.2671 : 0.7S27 -0.3421 0.5754 MI - 377,378 Jan,1997 Sr-90 0.9881 0.3785 1.0431 0.3340 1.0156 0.2524 CW - 416, 417 Jan,1997 Gr. Beta 3.7493 1.2558 4.5363 1.14S9 4.1428 0.8510 CW 416,417 Jan,1997 Gr. Beta 0.1479 1.3455 0.6807 1.3926 0.4143 0.9682 PW - 607, 608 Jan.1997 Co-60 -0.4870 C.6140 0.8310 2.4300 0.1720 t 1.2532 PW - 607, 608 Jan.1997 Cs 137 -0.7370 2.6100 0.2580 3.0900 -0.2395 t 2.0224 PW - 607, 608 Jan 1997 Gr. Beta 5.7315 1.8872 5.5786 t 1.7689 5.6550 1.2933 CW 846,847 Jan,1997 Gr. Alpha 0.04 S4 0.4520 0.6758 0.4786 0.3621 : 0.3292 CW - 846,847 Jan,1997 Gr. Beta 1.3287 0.5381 2.1250 0.5415 1.7268 0.3817 CW - 846,847 Jan,1997 H3 1,518.5023 131.0155 1,631.7608 134.0877 1,575.1316 93.7344 CW - 846,847 Jan,1997 Sr-89 0.3800 0.5210 0.7406 t 0.8976 0.5603 t 0.5189 CW - 846,847 Jan,1997 Sr-90 0.1424 0.2458 0.7292 0.3717 0.4358 0.2228 AS-1
1 I! , l Table A-5. In-house " duplicate" samples. l Concentration in pCi/ L' l h.u ; Lab Sample First Second Averaged I Date Analysis Result Result Result Codes
- WW - 576, 577 Feb,1997 H-3 150.9770 84.0813 241.2023 : S7.8687 196.0897 60.S033 MI - 486,487 Feb,1997 I-131 -0.0797 0.1694 -0.1161 0.1703 -0.0979 : 0.1201 MI - 486, 487 Feb,1997 K-40 1,278.2000 167.0000 1,316.5000 141.0000 1,297.3500 : 109.2S17 g
MI - 486,487 Feb,1997 Sr-89 -0.8027 0.9962 -0.4554 0.9484 -0.6290 0.63, < g M1 486,487 Feb,1997 Sr-90 1.8013 0.4825 1.4S92 0.4537 1.6453 : 0.3312 MI - 510,51? Feb,1997 Co-60 0.6S90 1.0200 -2.2000 4.1400 -0.7555 : 2.1319 MI 510,511 Feb,1997 Cs-137 0.7830 2.6300 2.2400 : 3.2800 1.5115 2.1021 MI - 510,511 Feb,1997 I-131 0.0764 0.2227 0.0373 0.2345 0.056S : 0.1617 Feb,1997 1-131 0.0368 0.1942 -0.0045 0.2095 0.0161 : 0.1429 MI- 53L 532 Feb,1997 K-40 1,300.3000 178.0000 1,438.5000 156.0000 1,394.4000 : 11S.3427 MI - 531,532 Feb,1997 Gr. Beta 3.6552 1.5170 2.7825 1.4922 3.21S9 : 1.0639 CW - 554. 555 CW - 554,555 Feb,1997 Gr. Beta 0.5033 1.0364 -0.236S 0.9931 0.1332 0.7177 Mi - 632,633 Feb,1997 I-131 -0.2709 0.2349 -0.1024 0.1676 -0.1867 : 0.1443 MI - 632,633 Feb 1997 K-40 1,408.0000 165.0000 1,243.1000 t 145.0000 1,325.5500 : 109.8294 M1 - 723,724 Feb,1997 I-131 -0.0581 0.2376 0.2433 ! 0.265S 0.0926 0.1783 MI - 723,724 Feb,1997 K-40 1,574.8000 218.0000 1,396.8000 162.0000 1,4S5.S000 135.S013 LW - 757,758 Feb,1997 Gr. Beta 3.7439 0.9482 4.0547 0.9711 3.S993 0.67S [ CW - 883,884 Feb,1997 Gr. Beta 1.2996 1.2901 2.3358 1.3877 1.S177 0.9474 DW - 1030,1031 Feb,1997 Gr. Beta 2.0791 0.4817 2.0596 0.509S 2.0694 0.3507 DW - 1030,1031 Feb,1997 I-131 -0.1816 0.3127 -0.1217 t 0.3071 -0.1517 0.2192 SWU - 929,930 Feb,1997 Gr. Beta 2.4729 0.6238 2.990S 0.6691 2.7319 0.4574 SWU - 929,930 Feb,1997 H-3 170.1477 84.5878 202.2735 S5.9328 186.2106 60.2900 WW - 979,980 Feb,1997 H-3 102.1168 92.0531 12.4533 88.3392 57.2850 63.7918 SW - 1370,1371 Feb,1997 H-3 50.6979 i 78.8916 -8.0656 76.2734 21.3161 54.8669 LW - 953,954 Mar,1997 Co-60 0.7490 1.7500 -1.3300 3.8800 -0.2905 2.1282 LW - 953,954 Mar,1997 Cs-137 -0.3220 2.2800 1.5500 2.7200 0.6140 1.7746 g LW - 953,954 Mar,1997 Gr. Beta 3.7343 1.0079 4.6558 0.9898 4.1951 0.7063 g SW - 1036,1037 Mar,1997 Gr. Beta 1.7736 0.7279 2.1268 0.7453 1.9502 ! 0.5209 SW - 1576,1577 Mar,1997 H-3 219.6612 84.0956 250.7943 85.3666 235.2277 59.9156 SW - 1576,1577 Mar,1997 Sr 89 -0.5258 : 1.1183 -0.6149 0.9822 -0.5704 0.7442 SW - 1576,1577 Mar,1997 Sr-90 0.6723 0.3462 0.7181 0.3074 0.6952 t 0.2315 MI-1055,1056 Mar,1997 I131 0.1081 0.1729 0.0400 0.1677 0.0741 0.1204 MI - 1055,1056 Mar,1997 K-40 1,452.9000 126.0000 1,530.3000 : 124.0000 1,491.6000 : 88.3912 LW - 1120,1121 Mar,1997 Gr. Beta 2.5963 0.6078 1.8604 0.6077 2.2283 : 0.4298 g 0.0473 0.1434 = MI- 1158,1159 Mar,1997 I-131 0.0239 0.2040 0.0708 0.2015 MI- 1158,1159 Mar,1997 K-40 1,523.5000 152.0000 1,418.5000 157.0000 1,471.0000 109.2' CW - 1187,1188 Mar,1997 Cr. Beta 4.8369 1.9131 3.4999 1.8196 4.1684 1.320N A5-2
Table A-5. In-house " duplicate" samples.
$ Concentration in pCi/L' Lab Sarnple First Second Averaged Codes
- Date Analysis Result Result Result CW - 1187,1188 Mar,1997 Cr. Beta 0.1481 1.5087 -0.0S88 : 1.4S96 0.0296 : 1.0601 LW - 1145,1146 Mar,1997 Co-60 1.5000 3.3300 3.6600 6.4500 2.5S00 3.S533 Mar,1997 Cs-137 1.6200 3.2500 -0.9330 4.1100 0.3435 2.6199 i LW - 1145,1146 LW - 1145,1146 Mar,1997 Gr. Beta 4.2278 1.2135 3.5675 : 1.2356 3.S976 : 0.8659 MI 1275,1276 Mar,1997 I-131 -0.0683 0.2309 0.3734 : 0.4565 0.1525 0.255S MI - 1275,1276 Mar,1997 K-40 1,491.1000 193.0000 1,754.0000 177.0000 1,622.5500 130.9370 W W -1309,1310 Mar,1997 H3 4,232.80S9 188.1304 4,034.4635 183.5207 4,15S.6362 :13L40S6 Mar,1997 Gr. Beta 2.5242 : 0.6065 2.0921 : 0.5S46 2.3032 0.4212 i SWT- 1519,1520Mar,1997 WW - 1539,1540 Gr. Beta 1.2S78 0.6803 1.8468 0.7043 1.5673 0.4896 WW - 1539,1540 Mar,1997 H-3 -34.4755 72.6445 41.3706 : 76.1590 3 4476 52.6246 DW - 1688,1689 Mar,1997 Gr. Beta 4.5141: L3660 4.6S86 1.2681 4.6013 0.9319 DW - 1688,1689 Mar,1997 I-131 -0.1688 0.3758 0.3183 : 0.3363 0.0748 : 0.2522 Mar,1997 H-3 62.0000 152.0000 112.0000 152.0000 87.0000 107.4802 i SW CW -- 1909,1910 2204,2205 Mar,1997 H-3 435.8375 96.4774 430.4271 96.2750 433.1323 : 68.14S3 LW - 1931,1932 Mar,1997 H-3 168.9801 83.1073 137.7304 81.7913 153.3552 58.3023 CW - 1599,1600 Mar,1997 Gr. Beta 3.4372 : 1.5949 3.4464 1.52S9 3.441S 1.1047 CW - 1599,1600 Mar,1997 Gr. Beta 1.0978 0.9656 1.0340 0.9528 1.0659 : 0.6783 Mar,1997 Co-60 -0.0006 0.0102 -0.0002 0.0002 -0.0004 c 0.0051 g AP-2372,2573 g AP - 2572,2573 Mar,1997 Cs-137 0.0008 0.0007 0.0000 0.0005 0.0004 0.0004 SWU - 2045, 2046 Mar,1997 Sr-89 -0.0237 0.7179 0.1072 0.6305 0.0417 0.4777 SWU - 2045, 2046 Mar,1997 Sr-90 0.3676 0.3471 0.1910 0.2933 0.2793 0.2272 MI - 1641,1642 Apr,1997 I-131 -0.6675 0.3099 -0.5511 0.3244 -0.6093 0.2243 MI - 1641,1642 Apr,1997 K-40 1,556.3000 111.0000 1,393.1000 160.0000 1,474.7000 97.3666 1 LW 1763,1764 Apt,1997 Gr. Beta 2.3656 0.8258 2.1732 0.8478 2.2694 0.5917 LW - 1763,1764 Apr,1997 H-3 97.1488 79.2640 160.3540 S2.0162 128.7514 57.0295 AP 1974,1975 Apr,1997 Sr-89 -0.0001 t 0.0006 -0.0005 0.0015 -0.0003 0.0008
. AP - 1974,1975 Apr,1997 St-90 0.0001 0.0002 0.0001 0.0004 0.0001 0.0002 AP 1994,1995 Apr,1997 Co-60 -0.0003 0.0013 0.0002 : 0.0007 0.0000 0.0007 AP - 1994,1995 Apr,1997 Cs-134 -0.0001 0.0006 -0.0001 0.0016 -0.0001 0.0008 AP - 1994,1995 Apr,1997 Cs-137 -0.0002 0.0005 -0.0001 0.0005 -0.0002 0.0004 AP 1994,1995 Apr.1997 I131(g) -0.0001 0.0002 0.0001 0.0002 0.0000 0.0001 AP - 1994,1995 Apr,1997 K-40 0.0306 0.0192 0.0114 0.0180 0.0210 0.0132 WW - 1665,1666 Apt,1997 I-131 -0.4430 0.2674 -0.0311 0.2626 -0.2370 0.1874 WW - 1708,1709 Apr,1997 Gr. Beta 1.2245 0.6161 1.2S58 0.6134 1 2551 0.4347 WW - 1785,1786 Apr,1997 Gr. Beta 2.9118 2.0703 0.3820 : 2.1095 1.6469 1.4779 WW - 1785,1786 Apr,1997 H-3 9.0365 73.7753 -74.4153 71.1298 -46.7259 51.2402 WW - 1785,1786 Apr,1997 Sr-89 0.6539 0.6546 -0.4951 0.5197 0.0794 0.4179 AS-3
Table A-5. In-house " duplicate" samples. Concentration in pCi/ L' hI Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result WW - 1785,1786 Apr,1997 Sr-90 -0.0023 0.2013 0.2468 0.2347 0.1223 0.1546 W W 1737,1738 Apr,1997 Gr. Beta 15.0355 1.5075 15.6924 1.6231 -
15.3640 1.1076 WW - 1737,1738 Apr,1997 H-3 13.8405 75.2790 -5.1902 74.3991 4.3251 : 52.9201 g LW - 2848, 2849 Apr,1997 Gr. Beta 2.4095 0.6377 1.7316 0.5601 2.0706 : 0.4244 m MI - 1845, IM6 Apr,1997 Co-60 0.0309 0.0778 -1.8500 22.4000 -0.9096 11.2001 MI 1845,IM6 Apr,1997 Cs-134 0.1600 0.1350 0.5860 2.2600 0.3730 : 1.1320 MI - 1845,1846 Apr,1997 Cs-137 0.7580 1.1500 0.6290 : 2.6700 0.6935 : 1.4536 MI - 1845,1846 Apr,1997 I-131 -0.2586 0.2297 -0.0829 0.2149 -0.170S : 0.1573
-0.3954 1.6417 E
g MI - 1845,1846 Apt,1997 I131(g) -0.0707 0.2970 -0.7200 : 3.2700 MI 1845,1846 Apr,1997 K-40 1,592.5000 52.5000 1,559.3000 127.0000 1,375.9000 68.711S MI - 1845,1846 Apr,1997 $r-89 0.2592 1.3259 -0.3095 : 0.8315 -0.0252 0.7825 MI - 1845,1846 Apr,1997 $r-90 1.3583 0.3573 0.8755 0.2294 1.1169 0.2123 F - 2175,2176 Apr,1997 Gr. Alpha 0.0245 0.0359 0.0672 0.0377 0.0458 0.0260 F - 2175,2176 Apr,1997 Gr. Beta 2.3387 0.2713 1.7003 0.3684 2.0195 : 0.2288 F - 2175,2176 Apr,1997 K-40 2.5383 0.3610 2.5345 0.3640 2.5364 0.2563 F - 2175. 2176 Apr,1997 St-89 0.0003 0.0053 0.0021 : 0.0048 0.0012 0.0036 F - 2175,2176 Apr,1997 Sr-90 -0.0002 0.0018 -0.0003 0.0016 -0.0002 0.0014 l SWU - 2091,2092- Apt,1997 Gr. Beta 3.3295 0.6698 2.7374 0.6670 3.0334 0.4726 SWU - 2091,2092 Apr,1997 H-3 42.6019 76.2782 46.1034 76.4388 44.3526 53.9936 SWU - 2636,2637 Apr,1997 H-3 17.9011 75.4236 92.3927 78.7712 55.1469 : 54.5290 SL - 2432,2433 K-40 1.8447 0.4400 1.6811 0.5400 1.7629 0.3483 Apr,1997 5 E WW - 2462,2463 Apr,1997 Co-60 -0.5320 0.7550 0.4650 0.7810 -0.0335 0.5431 WW - 2462,2463 Apr,1997 Cs-137 0.6250 3.6500 -1.4600 3.4400 -0.4175 2.5078 WW - 2462, 2463 Apt,1997 H-3 19.6154 75.4335 -21.9230 73.5027 -1.1538 52.6613 F - 2412,2413 Apr,1997 K-40 3.0009 0.1660 3.0594 0.1470 3.0302 0.1109 i LW - 2550,2551 Apr,1997 Gr. Beta 2.0074 0.8317 3.6936 0.8973 2.8505 0.6117 g l LW - 2550,2551 Apr,1997 K-40 102.7800 55.6000 96.6520 54.9000 99.7160 39.0684 5 SP - 2806,2807 Apr,1997 Gr. Alpha 0.0245 0.3861 0.1365 0.3720 0.0805 0.2681 SP - 2806,2807 Apr,1997 Sr-89 -1.4194 t 6.8147 -5.6447 8.6109 -3.5321 5.4906 SP - 2806,2807 Apr,1997 Sr-90 2.6542 2.3158 7.1752 2.9780 4.9147 1.8862 PW - 2736,2737 0.1300 4.6800 -0.6250 9.8400 -0.2475 5.4481 Apr,1997 Co-60 g PW - 2736,2737 Apr,1997 Cs-137 -0.2740 4.2100 1.7400 3.3400 0.7330 2.6870 g PW - 2736,2737 Apr,1997 Gr. Beta 2.8037 t 1.5036 2.6658 1.4461 2.7348 1.0431 WW - 2712,2713 Apr,1997 H-3 1,482.0205 125.6515 1,596.1107 128.7524 1,539.0656 89.9520 SW - 2657,2658 May,1997 Gr. Beta 13.2739 i 1.3358 13.1663 1.2719 13.2201 0.9222 S O - 2677,2678 May,1997 Cs-137 0.1078 0.1000 0.2315 0.0507 0.1697 0.056] S O - 2677, 2678 May,1997 Gr. Alpha 5.5187 3.4094 8.3190 4.0540 6.9189 2 6486*' g g AS-4
Table A-5. in-house " duplicate" samples.
} Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result SO 2677,2678 May,1997 Gr. Beta 21.9926 2.7808 21.8461 3.0806 21.9193 : 2.0750 S O - 2677, 2678 May,1997 Sr-89 0.0075 0.0954 -0.0008 0.080S 0.0034 : 0.0625 S O 2677, 2678 May,1997 St-90 0.0713 0.0197 0.0642 0.0164 0.0677 :0.012S MI - 2764,2765 May,1997 Co-60 0.0636 0.0966 -1.5300 7.2300 -0.7332 3.6153 MI - 2764, 2765 May,1997 Cs-137 5.5000 5.2800 1.7700 4.9900 3.6350 3.6324 MI - 2764,2765 May,1997 I-131 -0.1635 0.1612 -0.0766 : 0.1452 -0.1201 : 0.1085 MI - 2S28, 2829 May,1997 I-131 -0.0153 0.2503 \
-0.0355 0.2257 -0.0504 0.I6S5 MI - 2S28,2829 May,1997 K-40 1,786.4000 126.0000 1,S97.0000 : 192.0000 1,S41.7000 : 114.8260 G - 2S79,2SSO May,1997 Co-60 0.0044 0.1100 -0.0207 : 0.2030 -0.00S1 0.1154 G - 2S79, 2SSO May,1997 Cs-134 0.0081 0.0305 -0.0030 0.0133 0.0025 : 0.0166 May,1997 Cs-137 0.0006 0.0234 0.0013 0.0166 I GG --2379,2SSO 2S79,2S80May,1997 Gr. Beta 0.0010 : 0.0143 6.4712 0.2029 6.6206 0.1927 6.5459 : 0.1399 G 2S79,2S80 May,1997 I-131(g) 0.0093 0.0456 0.0220 : 0.6620 0.0157 : 0.3313 G - 2S79,28S0 May,1997 K-40 6.2539 0.8340 5.7979 0.7160 6.0259 : 0.5496 S O - 2904,2905 May,1997 Co40 -0.0097 0.0201 -0.0021 0.0224 -0.0059 : 0.0150 May,1997 Cs-134 0.0348 0.0682 0.0208 0.1500 l SO - 2904,2905 0.0278 : 0.0324 0 - 2904, 2905 May,1997 Cs 137 0.2709 : 0.0541 0.276S 0.0463 0.273S 0.0356 S O - 2904, 2905 May,1997 Gr. Beta 24.4695 2.3915 26.5459 2.5962 25.5077 1.7649 S O - 2904,2905 May,1997 K-40 18.8100 1.0100 19.1610 0.8920 18.9355 t 0.6738 F - 2926, 2927 May,1997 Co-60 0.0071 0.0082 -0.0010 0.0015 0.0031 0.0042 F - 2926, 2927 May,1997 Cs-137 -0.0047 0.0122 -0.0029 0.0088 -0.0038 0.0075 I SW - 3008,3009May,1997 H-3 101.2957 91.5729 123.2634 92.4471 112.2795 65.0616
_ MI- 3050,3031 May,1997 Sr-89 -0.1527 : 0.9022 0.0234 0.8795 -0.0646 0.6300 MI- 3050,3051 May,1997 St-90 0.9779 0.3707 0.9427 0.3596 0.9603 0.2583 May,1997 Co-60 -0.0093 0.0979 0.0094 0.0303 [ F - 3070,3071 0.0000 0.0512
. F - 3070,3071 May,1997 Cs-137 0.0064 0.0113 -0.0003 0.0078 0.0030 0.0069 g G - 3090, 3091 May,1997 K-40 5.0649 0.2170 4.9752 o 0.2830 5.0201 0.1783 MI - 3116,3117 May,1997 I-131 -0.1346 0.1762 -0.0964 0.1650 -0.1155 : 0.1207 F - 3277,3278 May,1997 Gr. Beta 2.9487 0.1093 3.0022 0.1035 2.9755 0.0733 F - 3277,3278 May,1997 K-40 2.8485 0.2780 2.4647 0.3130 2.6566 0.2093 - MI 3232,3233 May,1997 I131 -0.1723 0.2021 -0.2680 0.2044 -0.2202 0.1437 MI - 3232,3233 May,1997 K-40 1,350.6000 121.0000 1,517.9000 141.0000 1,534 2500 92.9005
{ BS - 3311,3312 May,1997 Co-60 -0.0035 t 0.0348 -0.0044 0.0031 -0.0039 0.0175 BS - 3311, 3312 May,1997 Cs 137 0.0676 0.0334 0.0677 0.0297 0.0676 0.0223 F MS4,34S5 May,1997 K 40 2.4582 0.3320 [ 'W - 3533,3534 May,1997 H-3 -95.4129 90.4309 1.8380 0.2990
-117.7172 89.5093 2.1481 0.2234
-106.5650 63.6193 NW - 3395, 3396 May,1997 I-131 -0.1507 0.1S41
- -0.0473 0.2108 -0.0990 0.1399 6 s A5-5
I Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes' Date Analysis Result Result Result F 3720,3721 May,1997 K-40 2.6063 0.4030 2.6623 : 0.3390 2.6343 : 0.2633 LW - M64, 3465 May,1997 Co-60 -0.2860 1.2700 -0.0583 0.04S9 -0 1722 : 0.6335 LW - 3464, 3465 May,1997 Cs-137 2.4600 2.8100 1.5000 3.2400 1.9S00 : 2.1444 LW - 3464, 3465 g May,1997 Cr. Beta 3.3332 0.9801 3.7723 0.9839 3.562S : 0.6944 g! SW - 3883,3884 May,1997 H-3 -20.5031 87.7694 124.8827 93.7412 52.1893 : 64.20S4 MI 3513,3514 Jun,1997 I-131 -0.1592 0.1592 -0.1028 0.1714 -0.1310 : 0.1170 MI - 3513,3314 Jun,1997 K 40 1,560.3000 129.0000 1,521.9000 : 179.0000 1,541.1000 : 110.3200 P - 3794,3795 Jun,1997 H-3 109.9207 93.1034 24.2198 89.6079 67.0702 : 64.6100 F - 4049,4050 Jun,1997 K-40 2.8350 0.3980 3.0237 0.2420 2.9294 : 0.2329 MI - 3903,3904 Jun,1997 I-131 0.1550 0.1840 -0.1290 : 0.1587 0.0130 : 0.1215 MI - 3903,3904 Jun,1997 K-40 2,020.1000 142.0000 1,822.5000 18S.0000 1,921.3000 117.S007 VE - 3839,3840 Jun,1997 Cr. Alpha 0.2489 0.0857 0.1876 0.0693 0.2133 0.0553 VE - 3839,3S40 Jun,1997 Gr. Beta 4.4859 0.4451 4.1281 0.4123 4.3070 : 0.3034 VE - 3839,3840 Jun,1997 K-40 5.4016 0.3360 4.6783 0.4232 5.0400 : 0.2721 F - 3928,3929 Jun,1997 Co-60 -0.0025 0.0121 0.0045 : 0.0034 0.0010 : 0.0063 F - 3923,3929 Jun,1997 Cs-134 0.0050 0.0115 -0.0030 0.0114 0.0010 0.00S1 F - 3928,3929 Jun,1997 Cs-137 0.0841 0.0225 0.0796 0.02S6 0.0818 0.0182 F - 3928,3929 Jun,1997 Gr. Beta 2.7146 0.0950 2.6357 : 0.0977 2.6752 0.0631 F - 3928,3929 Jun,1997 I-131(g) 0.0206 0.0449 0.015S 0.0458 0.0182 0.0321 , F - 3928,3929 Jun,1997 K-40 1.8883 0.3970 1.4854 0.3780 1.6S69 0.2741 SWU - 3980,3981 Jun,1997 Cr. Beta 2.1443 0.6206 SWU - 3980,3981 2.3149 0.6407 2.2296 0.4460 g Jun,1997 H-3 221.0233 39.9165 105.6271 t 85.0852 163.3252 61.S960 E CW - 3948,3949 Jun,1997 Gr. Beta -0.4402 1.0747 -0.3764 1.1259 -0.4083 : 0.7782 SW - 4150, 4151 Jun,1997 H-3 30.4430 77.1886 56.0152 78.3895 43.2291 55.0068 MI - 4091,4092 Jun,1997 I-131 -0.0475 0.1439 -0.0071 0.1516 -0.0273 0.1045 SWT - 4240,4241 Jun,1997 Gr. Beta 2.1204 0.6338 2.8553 0.6330 2.4879 0.4479 SW - 5186, 5187 Jun,1997 H-3 190.3311 89.7491 g 192.1730 S9.8246 191.2521 63.4889 3 DW - 4280,4281 Jun,1997 Gr. Alpha -0.4934 0.7635 -0.4930 0.7640 -0.4932 0.5401 DW - 4280, 4281 Jun,1997 Gr. Beta 2.0633 0.8600 2.0630 0.8700 2.0631 0.6117 WW - 4811, 4812 Jun,1997 H-3 48.4888 S3.6998 50.3302 83.7808 49.4095 59.2133 CW - 5207,5208 Jun,1997 H-3 151.5810 88.1060 135.0114 87.4113 143.2962 62.0552 SW - 4364, 4365 Jun,1997 H-3 83.4415 83.9269 94.4046 84.4029 88.9230 59.5138 AP - 4983,4984 Jun,1997 Co-60 -0.0002 0.0009 0.0001 0.0007 -0.0000 0.0006 AP - 4983,4984 Jun,1997 Cs-137 0.0003 t 0.0004 -0.0001 0.0007 0.0001 0.0004 AP - 5004,5005 Jun,1997 Co-60 0.0002 0.0002 0.0003 0.0008 0.0002 0.0004 l AP - 50(M,5005 Jun,1997 Cs-137 -0.0002 0.0004 0.0002 0.0006 -0.0000 0!'004 DW - 4484, 4485 Jun,1997 Gr. Beta 2.0708 0.6272 1.9172 0.5805 1.9940 0.4273 ' AS-6
Table A 5. In-house " duplicate" samples.
.; Concentration in pCi/ L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result DW - 4484,4435 Jun,1997 H-3 39.2579 83.2425 66.8612 84.4541 53.0596 : 59.2913 SW - 4460,4461 Jul,1997 Gr. Beta 1.8471 0.76S5 2.2S01 0.778S 2.0636 0.5471 DW - 4510, 4511 Jul,1997 H-3 1.2216 80.7150 21.3772 : S1.6249 11.2994 : 57.3967 AP - 4917,491S Jul,1997 Co-60 0.0002 0.0003 0.0002 : 0.0006 0.0002 : 0.0003 AP - 4917,4918 Jul,1997 Cs-134 0.0002 0.0003 0.0002 : 0.0052 0.0002 : 0.0026 AP - 4917,4918 Jul,1997 Cs-137 0.0003 0.0004 0.0002 0.0004 0.0003 : 0.0003 AP - 4917,491S Jul,1997 I-131(g) -0.0009 : 0.0017 0.0022 : 0.0762 0.0006 0.03S1 AP - 4917,4918 Jul,1997 K-40 0.0239 0.0031 0.0305 0.0036 0.0272 : 0.0059 SP - 5024,5025 Jul,1997 Gr. Alpha 0.4224 0.9602 1.7S36 : 1.2429 1.1030 : 0.7853 SP - 5024,5025 Jul 1997 Sr-90 65.8931 7.2660 61.711S : 6.1959 63 S024 4.7745 Jul,1997 K-40 11.9570 0.5550 12.0610 0.5170 I BS - 4573,4574 12.0090 0.3792 WW - 4535, 4536 Jul,1997 Co-60 -0.0955 0.4620 1.0S00 1.3100 0.4923 0.7895 WW - 4535, 4536 Jul,1997 Cs-137 -0.7200 2.3500 0.1650 3.3100 -0.2775 2.0297 WW - 4535, 4536 Jul,1997 H-3 565.2121 103.8753 524.7523 : 102.4326 544.9322 72.9426 G - 4745,4746 Jul,1997 Co-60 -0.0147 0.1270 -0.0016 : 0.0036 -0.00S2 0.0635 Jul,1997 Cs-134 0.0055 0.0386 -0.0118 ! 0.0963 -0.0032 0.0519 i G-4745,4746 '3 -4745,4746 Jul,1997 Cs-137 0.0057 0.0186 0.0132 : 0.01S0 0.0095 0.0129 G - 4745,4746 Jul.1997 Gr. Beta 5.0148 0.1659 4.7792 : 0.1700 4.S970 0.11S8 G - 4745,4746 Jul,1997 I-131(g) 0.0040 i 0.0078 0.0104 c 0.0269 0.0072 0 0140 G - 4745,4746 Jul,1997 K-40 4.5596 0.5840 4.1530 0.6150 4.3563 0.4241 Jul,1997 Gr. Beta 2.7683 0.6756 3.4254 : 0.6591 3.0968 0.4719 I SWU LW - 4752,4733 - 4S32,4833 Jul,1997 Co-60 2.8200 20.3000 -1.9900 : 6.6500 0.4150 10.6307 LW 47S2,4783 Jul,1997 Cs-137 0.6730 3.2000 -0.6030 : 2.2500 0.0350 1.9559 LW 4782,4783 Jul,1997 Gr. Beta 4.0046 : 1.0458 3.5274 : 0.9990 3.7660 0.7232 MI - 4897,4898 Jul,1997 I-131 -0.0412 0.2132 0.0463 0.2335 0.0026 0.1593 MI 4897,4S93 Jul,1997 K-40 1,531.3000 123.0000 1,270.5000 : 152.0000 1,100.9000 97.7663 CW - 5150, 5151 Jul,1997 Gr. Beta 4.7218 1.5818 4.2648 t 1.6666 4.4933 1.1488 CW - 5150, 5151 Jul,1997 Gr. Beta -0.2253 1.0995 0.5464 1.2464 0.1605 0.8310 G - 5296,5297 Jul,1997 K-40 6.S000 0.6000 8.2000 0.S000 7.5000 0.5000 WW - 5369, 5370 Jul,1997 H-3 18,013.8557 373.4409 18,133.89SS : 374.6263 18,073 8773 264.4820 CW - 5321,5322 Jul,1997 Gr. Beta 1.5612 1.4170 1.3507 : 1.2764 1.4560 0.9535 CW 5321,5322 Jul,1997 Gr. Beta -0.6334 1.0849 0.5162 t 1.2191 -0.0586 0.8160
( WW - 534S,5349 Jul,1997 H-3 1,763.0308 139.9964 1,S13.1908 141.3214 1,7SS.1108 99.4620 MI 5464,5465 Jul,1997 I-131 -0.2555 0.2878 -0.3511 0.2946 -0.3033 : 0.2059 MI - 5464,5465 Jul,1997 K-40 1,282.9000 143.0000 1,380.0000 124.0000 1,331.4500 94.6375 VE - 5506,5507 Jul,1997 Cr. Beta 7.2756 0.2197 7.0057 0.2090 7.1407 0.1516 VE - 5506, 5507 Jul,1997 K-40 8.1566 0.3970 S.1817 0.4360 8.1692 0.2948 AS-7
l l Table A-5. In-house " duplicate" samples. ll Concentration in pCi/ L' Lab Sample First Second Ijl Averaged j Codes
- Date Analysis Result Result Result i WW - 5848, 5849 Jul.1997 H-3 51.6431 83.4870 10.4434 S2.9847 46.0433 : 53.8569 WW - 5529, 5530 Aug,1997 Gr. Beta 5.1545 2.1632 4.3564 : 1.9691 4.7555 : 1.4626 WW - 5529, 5530 Aug,1997 H-3 235.5502 91.5917 372.4741 : 97.6610 304.0122 : 66.9453 g
MI - 5606,5607 Aug,1997 I-131 -0.0759 0.3043 -0.1020 0.3423 -0.0889 02290 g SL 5563,5564 Aug,1997 Gr. Beta 1.C01 0.2206 2.0961 0.2125 2.0131 0.1531 SL - 5563, 5564 Aug,1997 K-40 1.1254 0.3530 1.3155 0.4050 1.2220 0.26S6 SL - 5563, 5564 Aug,1997 Sr-89 -0.0078 0.0216 0.0096 0.0196 0.0009 0.0146 SL - 5563,5564 Aug,1997 Sr-90 0.0097 0.0059 0.0031 t 0.004S 0.0064 : 0.0038 SW - 5584, 5585 Aug,1997 Gr. Beta 2.9875 0.7744 2.0205 : 1.0326 2.5040 0.6434 E 5 LW - 5678,5679 Aug,1997 Co-60 0.4180 1.2900 0.7270 : 1.4500 0.5725 : 0.9704 LW - 5678,5679 Aug,1997 Cs-134 0.8140 0.6510 0.8340 0.4840 0.S240 0 0.4056 LW - 5678,5679 Aug,1997 Cs-137 1.1400 1.1800 0.7750 : 1.1900 0.9575 : 0.8379 LW - 5678,5679 Aug,1997 Gr. Beta 2.6926 0.6727 2.4242 0.6023 2.55S4 : 0.4515 LW - 5678,5679 Aug,1997 I-131 -0.1036 0.3234 -0.0921 0.3371 -0.0979 0.2336 LW - 5678, 5679 Aug,1997 I-131(g) -10.1000 11.1000 -3.6000 5.8200 -6.3500 6.2666 LW - 5678,5679 Aug,1997 K-40 137.0000 16.5000 124.0000 17.3000 130.5000 11.9535 C - 5653,5634 Aug,1997 K-40 6.0419 0.5940 5.5554 0.5870 5.79S7 : 0.4176 ( CW - 5759,5760 Aug,1997 Gr. Beta 4.3051 1.5501 2.004S 1.4570 3.1550 1.0637 ' CW - 5759, 5760 Aug,1997 Gr. Beta -0.5860 1,1030 -0.0177 1.1407 -0.301S 0.7934 CW - 5708, 5709 Aug,1997 Gr. Beta 1.7190 1.4125 1.8843 1.4139 1.8017 0.9993 MI - 5891,5892 Aug,1997 I-131 0.0000 0.2400 0.1928 0.2253 0.0964 0.1646 MI - 5891,5892 Aug,1997 K-40 1,438.6000 131.0000 1,218.6000 175.0000 1,328.6000 109.3000 E 5 MI - 5926,5927 Aug,1997 I-131 -0.0311 0.1690 -0.1446 0.1748 -0.0879 0.1216 MI - 5926,5927 Aug,1997 K-40 1,577.8000 t 216.0000 1,429.9000 178.0000 1,503.8500 139.9464 SWU - 5972,5973 Aug,1997 H-3 274.7574 93.6817 157.2707 88.8812 216.0140 64.5681 CW - 6013,6014 Aug,1997 Gr. Beta 4.9801 1.3048 4.58S2 1.6114 4.7841 1.0367 g CW - 6013,6014 Aug,1997 Gr. Beta -0.5668 1.0528 -0.6145 1.1307 -0.5907 0.7725 E SL - 6034,6035 Aug,1997 Co-60 0.0183 0.0235 0.0159 t 0.2550 0.0171 0.1280 SL - 6034,6035 Aug,1997 Cs-134 0.0046 0.0136 0.0015 0.0020 0.0030 0.0069 SL - 6034, 6035 Aug,1997 Cs-137 '0.0118 0.0097 0.0175 0.0098 0.0147 0.0069 SL - 6034,6035 Aug,1997 Gr. Beta 2.1826 0.1949 1.9837 0.1773 2.0831 0.1317 SL - 6034, 6035 Aug,1997 I-131(g) -0.0039 0.0134 0.0013 0.0060 -0.0013 0.0073 SL - 6034,6035 Aug,1997 K-40 1.6231 0.2940 1.4676 0.2750 1.5454 0.2013 CW - 6172, 6173 Aug,1997 Gr. Beta 3.2828 1.0951 3.7336 1 1.6212 3.5082 0.9782 CW - 6172,6173 Aug,1997 Gr. Beta 1.2291 1.3108 0.0271 1.1175 0.6281 0.8612 CW - 6080,6081 Aug,1997 Gr. Beta 2.4263 1.5665 4.0378 1.5325 3.2321 1.0957. CW - 6080,6081 Aug,1997 Gr. Beta -0.0198 1.1927 0.9870 1.1701 0.4836 0.8354 D' A5-8
Table A-5. In-house " duplicate" samples.
". Concentration in pCi/L' Lab Sample First Second Averaged Codes' Date Analysis Result Result Result VE - 6106, 6107 Aug,1997 Co-60 0.0021 0.0173 0.0019 : 0.0087 0 0020 0.0097 VE 6106,6107 Aug,1997 Cs-137 0.0017 0.0057 -0.0005 : C.0072 0.0006 0.0046 VE - 6149, 6150 Aug,1997 Co-60 0.0043 0.1740 0.0004 : 0.0012 0.0024 : 0.0370 VE - 6149, 6150 Aug,1997 Cs-137 -0.0026 0.0056 0.0018 : 0.0060 -0.0004 : 0.0041 NII - 6203, 6204 Aug,1997 Co-60 2.3200 83.8000 0.7940 1.9700 1.5570 : 41.9116 MI - 6203, 6204 Aug,1997 Cs-137 0.5560 3.0200 1.2900 : 2.6500 0.9230 : 2.00S9 MI - 6203, 6204 Aug,1997 I-131 -0.2456 0.3252 -0.16SS : 0.3245 -0.2072 : 0.2297 VE - 6224, 6225 Aug,1997 Co-60 -0.0042 0.0160 0.0045 C.007S 0.0002 : 0.00S9 VE - 6224, 6225 Aug,1997 Cs-137 -0.0057 0.0131 0.0071 0.0047 0.0007 0.0070 VE - 6251, 6252 Aug,1997 Gr. Beta 3.4988 : 0.1337 3.5009 0 133S 3.4998 0.0946 VE - 62.51, 6252 Aug,1997 K-40 3.S744 0.5410 3.3980 ! 0.6150 3.6362 0.4095 Mi - 6335, 6336 Aug,1997 I-131 0.0196 0.2826 0.0564 0.269S 0.03S0 ! 0.1953 MI 6335,6336 Aug,1997 K-40 1,483.7000 12S.0000 1,53S.6000 : 116.0000 1,513.6500 S6.3713 SL 698'.,6983 Aug,1997 Co-60 0.0869 0.0110 0.0388 0.0135 0.0879 0.00S7 SL - 6982,6983 Aug,1997 Cs-137 0.0826 0.0110 0.0993 0.0165 0.0909 0.0099 Aug,1997 Cr. Beta -0.7733 0.1093 -0.69S8 0.09S9 0.7361 0.0737 i SL 6962,69S3 VW - 6312, 6313 4,401.6798 200.9023 Aug,1997 H-3 4,5S3.7685 204.3507 4,493.7241 143.2837 LW - 6560, 6561 Aug,1997 Gr. Alpha 0.4838 0.3347 0.7647 0.3421 0.6242 0.2574 LW - 6560, 6561 Aug,1997 Gr. Beta 1.6502 0.3609 1.6339 : 0.3320 1.6420 0.2452 LW - 6560, 6561 Aug,1997 H-3 164.1455 90.4249 131.5719 : S9.0337 147.S587 63.4501 Sep,1997 Gr. Beta 1.9762 0.5715 2.3786 0.62S4 2.1774 0.4247 i LW LW - -6520, 6520,6521 6521 Sep,1997 H-3 104.7304 87.8580 66.4144 86.1708 85.5724 61.5314
_ CW - 64S9,6490 Sep,1997 Gr. 3 eta 0.2448 1.3049 1.9046 1.3290 1.0747 0.9313 G - 6773,6774 Sep,1997 K-40 3.7979 0.2420 3.5568 0.3270 3.6774 0.2034 CW - 6796, 6797 Sep,1997 Gr. Beta 3.3658 1.5585 5.0139 1.1808 4.1899 0.9777 CW - 6796, 6797 Sep,1997 Gr. Beta -1.1040 1.0241 -0.7623 1.0723 -0.9332 0.7414 SWU - 7009, 7010 Sep,1997 Gr. Beta 3.2034 0.6793 3.2645 0.6681 3.2339 0.4764 SWU - 7009, 7010 Sep,1997 H-3 165.8491 90.5715 15v. v86 89.9273 158.2239 : 63.8164 C 6820,6821 Sep,1997 K-40 4.8113 0.4160 4.7307 0.5360 4.7710 : 0.3392 MI - 6886,6S87 Sep,1997 I-131 0.0177 0.1519 0.0180 0.1520 0.0179 0.1074 MI - 6886, 6887 Sep,1997 K-40 1,241.7000 155.0000 1,062.0000 156.0000 1,151.8500 109.9557 WW - 7031, 7032 Sep,1997 H-3 -38.0852 81.4466 -19.0426 82.3323 -28.5639 57.9054 CW - 6907, 6908 Fep,1997 Gr. Beta 3.8333 1.5682 4.5001 1.6814 4.1667 t 1.1496 CW - 6907, 6908 Sep,1997 Gr. Beta -0.0397 1.1726 -0.1621 1.1478 -0.1009 0.8204 F - 7221, 7222 Sep,1997 K-40 3.0101 0.3970 2.6722 0.4720 2.8412 0.5084 CW - 7177, 7178 Sep,1997 Gr. Beta 0.5864 0.9867 2.3794 1.4236 1.4829 0.8681 CW - 7177, 7178 Sep,1997 Gr. Beta -1.0971 1.0379 -0.1387 1.1507 -0.6179 0.7748 ~ A5-9
I Table A-5. In-house " duplicate" samples. Concentration in pCi/ L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result LW - 7198,71% Sep,1997 Gr. Beta 1.6523 0.6116 2.3619 : 0.6044 2.0071 : 0.4299 VE - 7141,7142 Sep,1997 Co-60 0.0012 0.0118 -0.0001 0.0004 0.0005 : 0.0059 VE - 7141,7142 Sep,1997 Cs-137 -0.0011 0.0090 0.0081 0.0103 SWU - 7364, 7365 Sep,1997 Gr. Beta 2.4372 0.6226 0.0035 : 0.006S g
2.7949 0.6153 2.6160 0.4377 g SWU - 7364, 7365 Sep,1997 H-3 245.3799 94.1721 269.0627 95.1596 257.2213 : 66.939S WW - 7408, 7409 Sep,1997 Co-60 0.4170 0.8010 2.0100 6.7100 1.2135 3.37S8 WW - 7408, 7409 Sep,1997 Cs-137 -0.2190 1.6500 0.8220 : 3.0600 0.3015 1.73S3 WW - 7408, 7409 Sep,1997 H-3 7,907.0011 264.0275 7,543.2790 : 25S.5239 7,725.1400 : 1S4.7601 LW - 7765,7766 Sep,1997 Gr. Alpha 0.2614 0.4857 0.3882 0.5450 0.324S 0.3650 LW - 7765,7766 Srj,1997 Gr. Beta 3.6490 : 0.5140 2.7232 : 0.4728 3.1861 ! 0.3492 LW - 7765, 7766 AP - 8208,8209 Sep,1997 H-3 3,168.6312 : 176.2295 3,030.6146 173.2010 3,099 6229 123.5470 g Sep,1997 Co-60 0.0002 0.0004 0.0004 : 0.0008 0.0003 0.0005
- AP - 8208,8209 Sep,1997 Cs-137 0.0003 0.0005 -0.0004 : 0.0006 -0.0000 0.0004 G 7244,7245 Oct,1997 Gr. Beta 9.0000 0.3000 8.4000 0.3000 S.7000 0.2121 G - 7244,7245 Oct,199; K-40 4.8853 0.7960 9.1594 0.7550 9.0224 0.54S6 Oct,1997 -0.0058 0.0181 G - 7244. 7245 G - 7244, 7245 Oct,1997 Sr-S9 -0.0056 0.0097 -0.0057 0.0103 g Sr-90 0.0053 0.0052 0.0017 0.0029 0.0035 G - 7265,7266 Oct,1997 0.0029 f 5 K-40 6.5763 0.5250 6.0640 0.6540 6.3202 0.4193 "
SW - 7313, 7314 Oct,1997 Gr. Eeta 24.5727 2.0773 21.9706 2.0623 23.2717 1.4636 SW - 7313, 7314 Oct,1997 K-40 114.6700 : 41.9000 90.9920 : 37.6000 102.S310 28.14S6 G -7432,7433 Oct,1997 Co-60 0.0073 0.0252 G - 7432,7433 Oct,1997 0.u0412 0.0059 0.0057 : 0.0129 g Cs-134 0.0057 0.0110 0.0009 0.0010 0.0033 0.0055 E G - 7432,7433 Oct,1997 Cs-137 0.0863 0.0217 0.0835 0.0247 0.0849 0.0164 G - 7432,7433 Oct,1997 Gr. Beta 5.3675 0.2025 5.3318 0.2123 5.3496 0.1467 G -7432,7433 Oct,1997 I-131(g) -0.0038 0.0069 0.0218 0.4830 0.0090 0.2415 G - 7432,7433 Oct,1997 K-40 4.4899 0.4020 4.9632 0.5470 4.7266 0.3394 CW - 7339,7340 Oct,1997 Gr. Beta 0.2969 1.2051 g
-0.2575 0.8630 0.0197 0.7411 g AP - 7537,7538 Oct,1997 Sr-89 0.0006 : 0.0008 -0.0001 0.0008 0.0002 0.0006 AP - 7537,7538 Oct,1997 Sr-90 -0.0001 0.0003 0.0001 0.0003 0.0000 : 0.0002 CW - 7560,7561 Oct,1997 Gr. Beta 3.7764 : 1.5058 3.7707 1.5155 3.7735 1.0692 C5N - 7560,7561 Oct,1997 Gr. Beta 0.4496 : 1.1864 0.3374 1.2009 0.3933 : 0.8440 F - 7474, 7475 Oct,1997 Co-60 -0.0010 0.0016 0.0020 0.0058 0.0005 0.0030 F - 7474,7475 Oct,1997 Cs-137 0.0071 0.0064 0.0001 0.0113 0.0036 0.0065 F - 7495,7496 Oct,1997 Co-60 F - 7495,7496 Oct,1997 0.0025 : 0.0076 0.0086 0.1430 0.0055 0.0716 g Cs-137 0.0078 0 0083 0.0044 0.0056 0.0061 0.0050 m F - 7626,7627 Oct,1997 K-40 2.2464 0.3120 1.5663 0.3760 1.9064 0.2443:
CW - 7669,7673 Oct,1997 Gr. Beta 5.7005 1.8448 3.6801 1.7132 4.6903 1.2588 U A5-10
Table A-5. In-house "duphcate" sarnples. g Concentration in pCi/L' e Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result CW - 7669, 7670 Oct,1997 Gr. Beta -0.0304 1.1674 0.1259 1.1344 0.047S : 0.S139 WW - 7648, 7649 Oct,1997 CW 38.3320 4.3000 31.7400 3.3600 35.0360 2.72S5 WW - 7643, 7649 Oct,1997 Cs 137 2.8800 2.3000 0.5180 : 1.9100 1.6990 : 1.494S WW - 7648, 7649 Oct,1997 H-3 241.3364 105.7031 265.5372 106.6226 253.436S 75.0692 MI - 7787,77SS Oct,1997 I-131 -0.0456 0.2490 0.0257 : 0.2696 -0.0099 : 0.1S35 MI - 7737, 778S Oct,1997 K-40 1,514.0000 : 114.0000 1,6S4.0000 102.0000 1,599.0000 : 76 4853 SO - 8010, S011 Oct,1997 Cs-137 0.?513 0.0712 0.3182 0.0693 0.3347 : 0.0497 S O - 8010, 3011 Oct,1997 K-40 22.4300 1.3200 22.0S30 1.2900 22.2565 : 0.922S SL - 8123,8124 Oct,1997 Cs-137 0.0368 0.0335 0.0242 0.0137 0.0305 : 0.01S1 SL - 8123, 8124 Oct,1997 K-40 2.8000 0.5510 2.5777 : 0.2960 2.6SS9 : 0.3127 F - 7915, 7916 Oct,1997 Cs-137 0.0072 0.0118 0.0031 0.00S5 0.0052 : 0.0073 MI - 7968, 7969 Oct,1997 I-131 -0.1451 : 0.3579 -0.4353 : 0.3455 -0.3152 : 0.2437 MI - 7968,7969 Oct,1997 K-40 1,324.1000 132.0000 1.313.0000 113.0000 1,31S 5500 : SS.5268 MI - 7968, 7969 Oct,1997 Sr-90 1.2S92 0.4152 1.2S92 : 0.7200 1.2892 : 0.4156 VE - 7934, 7935 Oct,1997 Co-60 0.0071 0.1160 -0.0029 0.0139 0.0021 0.0584 VE - 7934, 7935 Oct,1997 Cs-137 0.0022 0.0110 -0 0041 0.0099 -0.0010 0.0074 TWU - S946, 8947 Oct,1997 Gr. Beta 2.9772 0.6530 2.2SSS 0.5953 2.6330 0.4418
- iWU - S946, S947 Oct,1997 H-3 187.7210 97.36S2 125.5659 94.9331 156 6435 67.9943 CW - 8230, 8231 Oct,1997 Gr. Beta 3.6262 1.7126 4.9561 : 1.793S 4.2911 : 1.2400 CW - 8230, 8231 Oct,1997 Gr. Beta 1.7276 0.9533 0.1316 : 1.1929 0.9296 0.7635 CW - 8100,8101 Oct,1997 Gr. Beta 4.1481 1.6095 4.5744 1.5764 4.3612 1.1264 CW - 8100, 8101 Oct,1997 Gr. Beta -0.5655 : 0.8528 0.9791 1.2280 0.2068 0.7475 SS - 8501, 8502 Oct,1997 Cr. Alpha 7.95S0 3.4566 6.5709 3.1457 7.2645 2.3379
% - 8501, 8502 Oct,1997 Gr. Beta 19.4568 2.9472 17.6686 2.6664 18.5627 1.s872 SS - 8501, 8502 Oct,1997 K-40 12.4630 : 0.4450 13.4420 : 0.7910 12.9525 0.4538 CW - 8310, 8311 Oct,1997 Gr. Beta 2.1293 1.4423 2.1830 1.4550 2.1562 : 1.0243 CW - 8310,8311 Oct,1997 Gr. Beta 0.1798 : 1.1387 -0.0397 1.1504 0.0701 0.8093 CW - 8376, 8377 Oct,1997 Gr. Beta 4.7932 2.0194 7.3047 : 1.3637 6.0490 1.2184 CW - 8376,8377 Oct,1997 Gr. Beta 0.5653 1.8020 -0.0566 1.7632 0.2544 : 1.2606 MI - 8442,8443 Oct,1997 I-131 -0.0290 0.2689 0.1059 0.2666 0.0384 : 0.1893 MI - 8442, S443 Oct,1997 K-40 1,591.7000 178.0000 1,456.0000 116.0000 1,523.8500 : 106.2309 SWU - 8543, 8544 Oct,1997 Gr. Beta 2.2027 : 0.6193 2.1585 : 0.6134 2.1806 : 0.4358 SWU - 8543, 8544 Oct,1997 H-3 120.4712 87.0152 174.9557 : 89.2606 147.7134 : 62.3280 WW 6473,8474 Oct,1997 H-3 -28.9600 : 77.6404 27.1500 : 80.2139 -0.9050 55.8174 WW - 8566, 8567 Oct,1997 Co-60 0.4520 1.7400 0.3400 4.0500 0.3960 2.2040
'VW - 8566, 8567 Oct,1997 Cs-137 1.0300 2.2000 -0.7300 2.8600 0.1500 1.8041 _W - 8608,8609 Oct,1997 Gr. Beta 2.8483 0.6660 2.3035 0.6052 2.5759 0.4500 A5-11
I Table A-5. In-house " duplicate" sanples. Concentration in pCi/L' Lab Sampie First Second Averaged Codcs* Date Analysis Result Result Result Nov,1997 -0.0013 0.1396 MI- 8587,8588 I-131 0.0109 0.1350 0.004S : 0.0971 g MI- 8587,8588 Nov,1997 K-40 1441.6000 160.0000 1,499.6000 176.0000 1,470.6000 : 118.92S5 = WW - 8654, 8655 Nov,1997 Gr. Beta 0.6704 0.5213 0.8560 : 0.5226 0.7632 : 0.3691 WW - 8654, S655 Nov,1997 H-3 131.2268 87.3749 87.6861 : S5.5477 109.4565 : 61.1408 CW - 8753,8754 Nov,1997 Gr. Beta 5.4805 1.9992 4.3820 2.0409 4.9312 : 1.4255 CW - 8753, 8754 Nov,1997 Gr. Beta C.2S21 1.7806 0.1129 : 1.7701 0.1975 : 1.2554 g F - 9131, 9132 Nov,1997 Cs-137 0.0576 0.0192 0.0568 : 0.0171 0.0572 : 0.0129 5 F - 9131,9132 Nov,1997 Gr. Beta 2N445 0.0965 3.0473 : 0.0919 2.9959 : 0.0666 F - 9131,9132 Nov,1997 K-40 2.3452 0.3460 2.4680 0.3260 2.4066 0.2377 CW - 8854, 8855 Nov,1997 Gr. Beta 5.6218 1.7991 3.5028 : 1.6326 4.5618 : 1.2147 CW - 8854, SS55 Nov,1997 Gr. Beta 0.00C0 1.1731 0.6107 : 1.1604 0.3053 0.825 WW - 9087, 9083 Nov,1997 H-3 20.1989 81.0438 73.4489 S3.4219 46.S237 5S.1535 E g l WW - 9160, 9161 Nov,1997 Co-60 -0.9580 t 9.1800 -0.4340 4.2400 -0.6960 : 5.0559 WW - 9160, 9161 Nov,1997 Cs-137 -0.1440 : 2.3300 -0.5270 2.0700 -0.3355 : 1.55S3 SWT - 9341, 9342 Nov,1997 Gr. Beta 1.4657 0.7780 2.7123 0.8202 2.0S90 : 0.5652 l CW - 9410,9411 Dec,1997 Gr. Beta 3.2958 ' 5674
.. 4.2052 1.5722 3.7510 1.1100 CW - 9410, 9411 Dec,1997 Gr. Beta 0.6244 1 1948 -0.6229 1.0939 0.0007 : 0.8099 (
CW - 9466,9467 Dec,1997 Gr. Beta 1.6082 1M557 2.0375 1.6921 1.8228 1.1837 CW - 9466,9467 Dec,1997 Gr. Beta -0.0563 13639 -1.1838 1.6912 -0.6201 1.2218 WW - 9603, 9604 Dec,1997 Co-60 1.7300 1.7600 -0.6190 0.7560 0.5555 : 0.9577 l l WW - 9603, 9604 Dec,1997 Co-60 1.7300 1.7600 -0.0389 0.3420 0.8456 : 0.8965 WW - 9603, 9604 Dec,1997 Cs-137 0.4460 2.0800 0.0557 1.2900 0.2509 1.2238 LW - 9789,9790 Dec,1997 Co-60 0.1010 0.1050 0.1510 : 2.0300 0.1260 : 1.0164 LW - 9789, 9D0 Dec,1997 Cs-137 1.0000 2.1300 0.9130 t 2.0300 0.9565 1.4712 g LW - 97S9,9790 Dec,1997 Gr. Beta 5.6924 1.0951 4.5180 0.7757 5.1052 0.6711 W CW - 9947,9948 Dec,1997 Gr. Beta 0.9320 0.9447 1.5072 0.9762 1.2196 0.6792 AP - 10249,10250 Dec,1997 Co-60 0.0000 0.0001 0.0004 0.0016 0.0002 0.0008 AP - 10249,10250 Dec,1997 Cs-137 0.0005 0.0008 0.0002 0.0003 0.0004 0.0004
' All concentrations are reported in pCi/ liter, except solid samples, which are reported in pCi/ gram. g
- Lab codes are comprised of the sample media and the samp e numbers. Client codes have been eliminated to 3 protect client anonymity.
I I
'I A5-12
Tabis A-6. - Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP), comparison of MAPEP and Teledyne's Midwest Laboratory results for various sample media'. l Concentration" Lab Sample Date Teledyne Results MAPEP Result' Control I Code Type Collected Analysis Standard Deviation
- 1s, N=1 Limits STW-751 WATER Sep,1995 Am-241 1.370 0.120 1.320 : 0.070 1.056 1.5S4 STW-751 - WATER Sep,1995 Co-57 91.000 0.950 92.380 0.600 73.904 - 110.S56 STW 751 WATER - Sep,1995 Cs-137 55.000 0.500 58.770 : 0.730 47.016 - 70.524 STW 751 WATER Sep,1995 Mn-54 99.170 t L600 99.0SO t 1.000 79.264 - 11S.S96
- STW-751 WATER Sep,1995 Pu-238 1.700 0.040 1.S30 0.080 1.464 - 2.19U STW-751 . WATER Sep,1995 Pu-239 1.380 0.220 1.340 0.060 1.072 - 1.60S
' STW-751 WATER Sep,1995 S' M 13.730 0.950 15.690 0.300 12.552 - IS.82S STW-751 WATER Sep,1995 U-234 0.630 0.070 0.650 0.050 0.520 - 0.7SO STW-751 WATER Sep,1995 U-238 0.700 0.020 0.650 : 0.050 0.520 - 0.7S0 STSO-776 SOIL Sep,1996 Ara-241 27.000 23.700 : 2.830 20.900 37.310
. Standard deviation for three determinations not reported in Mixed Analyte Performance Evaluation Program Summary Report.
STSO-776 SOIL Sep,1996 Co-60 879.000 S12.000 S3.500 568.400 - 1,055.600 l STSO-776 SOIL Sep,1996 Cs-137 1,716.000 1,531.000 193.420 1,071.700 - 1,990.300 i STSO-776 SOIL Sep,1996 Pu-238 13.000 15.900 : 1.770 11.130 - 20.670 STSO-776 SOIL Sep,1996 Pu-239/240 18.000 19.700 1.960 13.790 - 25.610 4 STSO-776 SOIL Sep,1996 Sr 90 441.000 536.000 : 57.110 375.200 - 696.800 l STSO-776 SOIL Sep,1996 U-234/233 59.000 63.900 7.270 44.730 - S3.070 l STSO-776 SOIL Sep,1996 U-238 60.000 64.000 6.360 44.S00 - 83.200
- Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.
- All results are in Bq/kg or Bq/L as requested by the Department of Energy.
' Unless otherwise indicated, the TBEESML results are given as the mean 1 standard deviations for three determinations.
' MAPEP results are presented as the known values and expected laboratory precision (1 sigma,1 determination) and controllimits as defined by the MAPEP.
l l A6-1
Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML), comparison of EML and Teledyne's Midwest Laboratory results for various sample media'. Concentration in Bq/L' Lab Sample Date Control Code Type Collected An al v". 4 s Teledvne Result' EML Result' Limits' STW-755 WATER Mar,1996 Am-241 0.600 0.100 0.766 0.013 0.660 - 1.560 STW-755 WATER Mar,1996 Co-60 33.600 1.000 32.S00 0.5S0 0.S70 - 1.170 STW-755 WATER Mar,1996 Cs-137 42.S00 1.300 38.300 0.SS1 0.900 - 1.250 STW-755 WATER Mar,1996 Fe-53 109.000 21.700 83.000 3.440 0.270 - 1.620 STW-755 WATER Mar,1996 H-3 434.000 : 34.100 251.000 11.400 0.690 - 1.910 STW-755 WATER Mar,1996 Mn-54 4L900 1.400 38.400 1.160 0.SSO - 1.210 STW-755 WATER Mar,1996 Pu-238 0.900 0.100 0.982 : 0.074 0.680 - 1.330 STW-755 WATER Mar,1996 Pu-239 0.700 0.100 0.772 0.056 0.620 - 1.380 STW-755 WATER Mar,1996 Sr-90 2.200 0.700 1.450 0.034 0.730 - 1.650 STW-756 WATER Mar,1996 Gr. Alpha 2,180.000 53.500 1,S50.000 IS5.000 0.550 - 1.310 STW-756 WATER Mar,1996 Gr. Beta 872.000 27.000 744.000 74.000 0.750 - 1.650 STSO-757 SOIL Mar,1996 Am-241 6.230 2.8S0 3.690 : 0.454 0.520 - 2.410 STSO 757 SOIL Mar,1996 Cs-137 404.000 : 0.150 359.000 : 10.000 0.740 - 1.400 STSO-757 SOIL Mar,1996 K-40 525.000 23.300 465.000 t 30.000 0.700 - 1.590 STSO-757 SOIL Mar,1996 Pu-238 42.300 1.590 43.000 : 2.440 0.220 - 1.990 STSO-757 SOIL Mar,1996 Pu-239 9.000 0.700 9.230 0.346 0.620 - 1.990 STSO-757 SOIL Mar,1996 Sr-90 1,200.000 32.300 1,340.000 113.000 0.580 - 2.960 STSO-757 SOIL Mar,1996 Uranium 68.200 2.400 71.700 4.150 0.270 - 1.4S0 STVE-758 VEGETATION Mar,1996 Am-241 6.100 1.300 5.600 0.184 0.580 - 2.S60 STVE-758 VEGETATION Mar,1996 Cm-244 6.000 1.200 4.440 0.202 0.400 - 1.870 STVE-758 VEGETATION Mar,1996 Co-60 65.600 4.000 59.700 0.963 0.640 - 1.490 STVE-738 VEGETATION Mar,1996 Cs-137 1,100.000 12.600 944.000 16.200 0.750 - 1.480 STVE-758 VEGETATION Mar,1996 K-40 1,190.000 61.600 1,030.000 33.000 0.450 - 1.510 STVE-758 VEGETATION Mar,1996 Pu-239 9.200 1.300 9.820 1.220 0.600 - 1.980 STVE-758 VEGETATION Mar,1996 Sr-90 1,210.000 32.200 1,300.000 52.400 0.500 - 1.370 STAF-759 AIR FILTER Mar,1996 Am-241 0.270 0.040 0.189 0.007 0.620 - 1.930 STAF-739 AIR FILTER Mar,1996 Ce-144 23.200 1.020 33.300 3.300 0.610 - 1.310 STAF-759 AIR FILTER Mar,1996 Co-57 6.050 0.130 8.900 0.900 0.630 - 1.290 STAF-759 AIR FILTER Mar,1996 Co-60 26.500 0.430 29.500 2.900 0.740 - 1.250 STAF-759 AIR FILTER Mar,1996 Cs-134 12.900 0.280 14.700 1.460 0.700 - 1.210 STAF-759 AIR FILTER Mar,1996 Cs-137 6.200 0.900 6.640 0.700 0.720 - 1.320 STAF-759 AIR FILTER Mar,1996 Mn-54 3.270 0.350 3.440 0.380 0.760 - 1.330 STAF-759 AIR FILTER Mar,1996 Pu-238 0.080 0.020 0.096 0.002 0.610 - 1.550 STAF-759 AIR FILTER Mar,1996 Pu-239 0.090 0.020 0.093 0.003 0.670 - L5SO STAF-759 AIR FILTER Mar,1996 Ru-106 10.200 1.850 11.600 1.440 0.540 - 1.590 STAF-759 AIR FILTER Mar,1996 Sb-125 10.100 0.750 9.780 1.030 0.350 - 1.400 STAF-759 AIR FILTER Mar,1996 Sr-90 1.070 0.230 1.060 0.037 0.620 - 2.260 STAF-759 AIR FILTER Mar,1996 Uranium 0.118 i 0.020 0.107 0.003 0.790 - 2.880 A7-1
l l Environmental Measurements Laboratory Quality Assessment Program (EML), Table A-7. comparison of EML and Teledyne's Midwest Laboratory results for various sample l media'. . Concentration in Bq/L l Lab Sample Date Control Code Type Collected Analvsis Teledyne Result' EML Result' Limits
- STAF-760 STAF-760 AIR FILTER Mar,1996 Gr. Alpha AIR FILTER Mar,1996 Gr. Beta 2.210 0.050 1.950 t 0.040 1.620 0.150 1.770 0.150 0.820 - 1.580 0.750 - 1.940 E'
g STW-770 WATER Sep,1996 Am-241 1.300 0.200 1.080 0.040 0.640 - 1.730 STW-770 WATER Sep,1996 Co-60 65.000 2.210 61.100 0.730 0.920 - 1.180 g STW-770 WATER Sep,1996 Cs-137 96.100 3.010 89.500 1.360 0.900 - 1.250 m STW-770 WATER Sep,1996 Cr. Alpha 993.000 : 12.200 1,210.000 : 121.000 0.500 - 1.290 STW-770 WATER Sep,1996 Gr. Beta 579.000 8.070 488.000 34.600 540.000 54.000 0.600 - 1.640 5 W STW-770 WATER Sep,1996 H-3 587.000 : 58.000 0.650 - 1.910 STW-770 WATER Sep,1996 Mn-54 65.000 2.960 60.500 0.550 0.S70 - 1.220 STW-770 WATER Sep,1996 Pu-238 1.320 0.333 1.910 0.070 0.740 - 1.270 l An investigation was conducted. No errors in calculations or transcription were noted. The analysis was W repeated in duplicate under the observation of the Technical Lead. No discrepancies were noted in the performance of the procedure. The result of the reanalysis was 2.14:0.11 Bq/L. No further action is planned. g STW-770 WATER Sep,1996 Pu-239 0.698 : 0.247 0.540 0.030 0.780 - 1.420 3 STW-770 WATER Sep,1996 Sr-90 3.600 : 0.700 2.710 : 0.240 0.720 - 1.6o0 STW-770 WATER Sep,1996 U-234 0.517 : 0.196 0.480 0.040 0.770 - 1.530 , g STW-770 WATER Sep,1996 U-238 0.416 0.118 0.480 0.370 0.770 - 1.350 i 3 STSO-771 SOIL Sep,1996 Am-241 15.600 3.830 13.500 : 0.510 0.520 - 2.650 STSO-771 SOIL Sep,1996 Co-60 4.030 2.500 2.920 0.210 0.500 - 1.500 g STSO-771 SOIL Sep,1996 Cs-137 1,750.000 24.400 1,550.000 22.200 0.800 - 1.340 5 STSO-771 SOIL Sep,1996 K-40 369.000 59.500 300.000 25.000 0.730 - 1.670 STSO-771 SOIL Sep,1996 Pu-238 0.770 0.360 1.130 0.240 0.400 - 1.900 E STSO-771 SOIL Sep,1996 Pu-239 24.000 1.940 21.800 1.080 0.660 - 1.930 5 STSO-771 SOIL Sep,1996 Sr-90 63.600 3.950 69.900 5.100 0.460 - 2.840 STSO-771 SOIL Sep,1996 U-234 37.200 3.750 39.200 2.440 0.380 - 1.260 40.800 3.980 l W STSO-771 SOIL Sep,1996 U-238 41.600 0.610 0.350 - 1.550 STVE-772 VEGETATION Sep,1996 Am-241 1.530 0.884 1.230 0.410 0.680 - 2.780 STVE-772 VEGETATION Sep,1996 Cm-244 0.612 0.495 0.830 0.120 0.490 - 1.690 STVE-772 VEGETATION Sep,1996 Co-60 14.000 4.420 10.900 0.710 0.620 - 1.420 STVE-772 VEGETATION Sep,1996 Cs-137 219.000 10.100 190.000 6.680 0.S10 - 1.450 STVE-772 VEGETATION Sep,1996 K-40 1,160.000 99.400 992.000 29.000 0.790 - 1.500 STVE-772 VEGETATION Sep,1996 Sr-90 1,420.000 35.100 1,390.000 12.000 0.480 - 1.290 STAP-773 AIR FILTER Sep,1996 Co-57 11.800.t 0.296 14.800 0.814 0.620 - 1.220 STAP-773 AIR FILTER Sep,1996 Co-60 9.230 0.402 8.640 0.431 0.740 - 1.240 , STAP-773 AIR FILTER Sep,1996 Cs-134 9.620 0.376 10.800 0.392 0.720 - 1.210 l STAP-773 AIR FILTER Sep,1996 Cs-137 8.720 0.403 8.520 : 0.366 0.720 - 1.320 STAP-773 AIR FILTER Sep,1996 Gr. Alpha 0.731 0.037 1.150 0.110 0.830 - 1.550 An investigation was conducted and a transcription error while calculating the result was discovered. The recalculated value is 1.15 0.01Bq/ filter. No further action is planned. I A7-2 I
Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML), y comparison of EML and Teledyne's Midwest Laboratory results for various sample
~ "
media'. i Concentration in Bq/L' I Lab Code Sample Type Date Collected Analysis Teledvne Result' EML Result' Control Limits' STAP-773 AIR FILTER Sep,1996 Gr. Beta I STAP-773 STAP-773 AIR FILTER Sep,1996 Mn-54 AIR FILTER Sep,1996 Ru-106 0.540 0.037 7.060 0.4 72 11.500 3.190 0.500 0.050 6.350 0.270 10.S00 1.140 0.730 - 1.S40 0.750 - 1.270 0.5S0 - 1.300 STAP-773 AIR FILTER Sep,1996 Sb-125 I STW-7S8 STW-783 WATER WATER Mar,1997 Am-241 Mar,1997 Co-60 12.400 0.965 0.840 0.220 96.000 : 3.500 10.800 : 0.540 0.S37 0.02S 0.600 - 1.390 0.640 - 1.730 90.S50 L150 0.920 - 1.1S0 STW-788 WATER Mar,1997 Cs-137 77.000 3.500 I STW-7SS WATER Mar,1997 Fe-55 175.500 25.400 69.7S0 1 230 235.000 : 20.000 0.900 - 1.230 0.310 - 1.540 STW-7SS WATER Mar,1997 Gr. Alpha 1,04' 600 36.800 1,130.000 10.000 0.500 - 1.290 STW-788 WATER Mar,1997 Gr. Beta 591.400 23.300 744.000 10.000 0.600 - 1.640 STW-788 WATER Mar,1997 H3 272.000 29.700 250.300 : 4.200 0.650 - 1.910 STW-788 WATER Mar,1997 Mn-54 23.700 3.400 20.850 : 0.310 0.S70 - 1.220 Mar,1997 Pu 238 I STW-788 STW-7S8 WATER WATER Mar,1997 Pu-239 1.400 0.200 0.900 0.100 1.291 0.063 0.S50 : 0.050 0.740 - 1.270 0.780 - 1.420 STW-788 WATER Mar,1997 Sr-90 25 500 1.700 23.200 : 1.350 0.720 - 1.660 l STW-788 STSO-790 WATER SOIL Mar,1997 U Mar,1997 Am-241 L500 : 0.200 6.740 3.730 1.105 0.050 3.6S0 0.500 0.350 - 1.420 0.520 - 2.650 STSO-790 SOIL Mar,1997 Co-60 2.010 1.170 1.060 : 0.120 0.500 - 1.500 The sample size was too small for an accurate measurement. The activity error overlap the known value. 1 STSO-790 SOIL Mar,1997 Cs-137 918.640 8.400 825.500 14.100 0.800 - 1.340 STSO-790 SOIL Mar,1997 K-40 359.140 32.100 334.250 7.140 0.730 - 1.670 STSO-790 SOIL Mar,1997 Pu-238 0.300 0.200 0.530 0.110 0.400 - 1.900 STSO-790 SOIL Mar,1997 Pu-239 132.420 5.170 134.930 17.100 0.660 - 1.930 STSO-790 SOIL Mar,1997 St-90 38.830 5.770 40.310 0.420 0.460 - 2.840 STSO-790 SOIL Mar,1997 U 79.260 3.800 81 270 : 4.830 0.270 - 1.360 STVE-791 VEGETATION Mar,1997 Am-241 1.673 0.688 1.183 0.113 0.680 - 2.780 STVE-791 VEGETATION Mar,1997 Cm-244 0.688 0.468 0.900 0.050 0.490 - 1.690 STVE-791 VEGETATION Mar,1997 Co-60 16.914 3.5S0 12.500 0.320 0.620 - 1.420 [ STVE-791 STVE-791 VEGETATION Mar,1997 Cs-137 VEGETATION Mar,1997 Pu-239 216.667 ! 9.383 1.771 0.817 189.250 7.270 1.942 0.222 0.810 - 1.450 0.650 - 1.950 STVE-791 VEGETATION Mar,1997 Sr-90 361.130 19.715 361.000 : 43.300 0.480 - 1.290 STAP-792 AIR FILTER Mar,1997 Co-57 { STAP-792 AIR FILTER Mar,1997 Co-60 9.528 0.230 5.325 0.266 10.810 1.000 5.010 : 0.300 0.620 - 1.220 0.740 - 1.240 STAP-792 AIR FILTER Mar,1997 Cs-134 10.767 0.337 10.880 1.000 0.720 - 1.210 STAP-792 AIR FILTER Mar,1997 Cs-137 { STAP-792 AIR FILTER Mar,1997 Gr. Alpha 9.116 0.404 1.199 0.045 S.700 : 0.800 0.960 0.050 0.720 - 1.320 0.830 - 1.550 STAP-792 AIR FILTER Mar,1997 Gr. Beta 0.608 0.024 0.450 : 0.030 0.730 - 1.S40 STAP-792 AIR FILTER Mar,1997 Mn-54 8.494 0.429 7.620 0.600 0.750 - 1.270 l A7-3
I Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML), comparison of EML and Teledyne's Midwest Laboratory results for various sample g. media'. V. i g ll Concentration n Bq/L' Lab Sample Date Control , Code Type Collected Analysis Teledvne Result' EML Result' Lirnits' STAP-792 AIR FILTER Mar,1997 Pu-238 0.022 0.016 0.100 : 0.006 0.620 - 1.460 The cause of the deviation for the transuranic analysis (Pu-238, 239, U) is unknown. A dilution error is suspected The analysis is being repeated. STAP-792 AIR FILTER Mar,1997 Pu-239 0.031 0.010 0.119 0.006 0.500 - 1.500 STAP-792 AIR FILTER Mar,1997 Sb-125 14.118 1.099 12.330 : 1.000 0.600 - 1.390 i STAP-792 AIR FILTER Mar,1997 Sr-90 1.291 t 0.275 1.450 : 0.149 0.660 - 2.650 STAP-792 AIR FILTER M u,1997 U 0.150 0.020 0.211 : 0.00S 0.S03 - 3.360 STW-S05 WATER Sep,1997 Co-60 23.630 1.450 23.300 : 1.200 0.920 - 1.180 STW-805 WATER Sep,1997 Cs-134 63.500 2.600 66.000 : 2.600 0.500 1.500 STW-805 WATER Sep,1997 Cs-137 34.S80 2.430 34.300 : 1.700 0.900 - 1.2S0 STW-805 WATER Sep,1997 Fe-55 101.730. 33.530 115.000 10.000 0.310 - 1.540
$TW-805 WATER Sep,1997 Gr. Alpha 597.000 000 537.000 : 60.000 0.500 - 1.290 STW-803 WATER Sep,1997 Gr. Beta 985.000 a.000 712.000 70.000 0.600 - 1.640 STW-805 WATER Sep,1997 H-3 227.600 1.800 115.000 6.000 0.650 - 1.910 E
g The sample was acidic, causing a breakdown of resin in the tritium column. The sample was neutralized to pH 7 and reanalyzed. Results of reanalysis: 116.2 3.6 Bq/L. STW-S05 WATER Sep,1997 Mn-54 3S.480 t 3.230 37.S00 1.900 0.S70 - 1.220 : STW-805 WATER Sep,1997 St-90 3.460 0.690 2.940 0.180 0.720 - 1.660 STVE-806 VEGETATION Sep,1997 Co-60 32.330 5.560 32.400 1.600 0.620 - 1.420 g STVE-806 VEGETATION Sep,1997 Cs-137 627.330 16.670 624.000 31.000 0.S10 - 1.450 g STVE-806 VEGETATION Sep,1997 K-40 1,091.670 95.180 1,130.000 70.000 0.790 - 1.500 STVE-806 VEGETATION Sep,1997 Sr-90 1,335.000 32.000 1,434.000 75.000 0.480 - 1.290 g STSO-807 SOIL Sep,1997 Cs-137 1,239.440 22.460 810.000 : 40.000 0.800 - 1.340 g The sample size was not standard. The sample was reanalyzed using a different geometry. Results of reanalysis: Cs-137 - 813.1 9.0 Bq/kg; K 275.9 34.6 Bq/kg. STSO-807 SOIL Sep,1997 K-40 478.000 29.000 315.000 70.020 0.730 - 1.670 STSO-807 SOIL Sep,1997 Pu-239 10.800 0.400 10.160 0.370 0.660 - 1.930 STSO-807 SOIL Sep,1997 St-90 31.480 5.560 34.750 : 1.000 0.460 - 2.840 g STSO-807 SOIL Sep,1997 U 57.000 : 1.100 72.900 0.850 0.270 - 1.360 g STAP-808 AIR FILTER Sep,1997 Gr. Alpha 1.820 0.080 1.490 0.090 0.830 - 1.550 STAP-808 AIR FILTER Sep,1997 Gr. Beta 3.250 0.080 3.000 0.140 0.730 - 1.840 g STAP-808 AIR FILTER Sep,1997 Pu-2,38 0.230 0.100 0.210 0.007 0.620 - 1.460 g STAP-808 AIR FILTER Sep,1997 U 0.130 0.100 0.110 0.004 0.800 - 3.360 STAP-809 AIR FILTER Sep,1997 Ce-144 16.250 1.670 19.120 0.700 0.500 - 1.500 g STAP-809 AIR FILTER Sep,1997 Co-57 10.570 0.270 12.640 0.430 0.620 - 1.220 g l STAP-809 AIR FILTER Sep,1997 Co-60 9.820 0.270 10.730 t 10.900 0.740 - 1.240 STAP-809 AIR FILTER Sep,1997 Cs-134 24.700 0.490 28.170 0.730 C.720 - 1.210 E' STAP-809 AIR FILTER Sep,1997 Cs-137 7.240 0.370 7.310 0.250 0.720 - 1.320 5 i STAP-809 AIR FILTER Sep,1997 Mn-54 6.800 0.430 6.720 0.270 0.750 - 1.270 I A7-4 l L
Table A 7. Environmental Measurements Laboratory Quality Assessment Program (EML),
, comparison of EML and Teledyne's Midwest Laboratory results for various sample 4
media'. Concentration in Bq/ L" Lab Sample Date Control Code Tvoe Collected Analysis Teledyne Result' EML Result' Limits
- STAP-809 AIR FILTER Sep,1997 Sb-125 17.980 1.270 16.120 0.790 0.600 - 1.390 g
STAP-809 AlR FILTER Sep,1997 Sr-90 2.330 0.370 2.760 0.100 0.660 - 2.650
' The Environmental Measurements Laboratory provides the folhwing nuclear species : Air Filters, Soil, Tissue, Vegetation and Water. Teledyne does not participate in the Tissue program.
- Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/ Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg.
' Teledyne results are reported as the mean of three determinations: standard deviation.
d The EML result listed is the mean of replicate determmations for each nuclide:the standard error of the mean.
- The control !imits are reported by EML as the ratio of Reported Value / EML Value and are estabhshed from percentiles of historic data distributions (1982-1992). The evaluation of this historic data and the development of the controllimits is presented in DOE report EML-564.
A7-5
i I w I>. I I I I I APPENDIX B DATA REPORTING CONVENTIONS l . I I I I l 'l B-1 L
Data Reporting Conventions 1.0. All activities except gross alpha and gross beta are decay corrected to collection time or the end of the collection period. 2.0. Single Measurements Each single measurement is reported as follows: x s where x = value of the measurement; s = 20 counting uncertainty (corresponding to the 95% confidence level). In cases where the activity is found to be below the lower limit of detection L it is reported as
<L where L = the lower limit of detection based on 4.66o uncertainty for a background sample.
3.0. Duolicate analyses 3.1 IndLvidual results: x1 s1 x2 i s2 Reoorted result: x' s where x = (1/2) (x1 + x2) 2 s = (1/2) s+s! 3.2. Individual results: <Li
<L2 Reoorted result <L where L = lower of L1 and L2 3.3. Individual results: x s
<L i
x s if x 2 L; Reoorted result:
<L othenvise B-2 i ~
1 4.0. Comoutation of Averages and Standard Deviations 4.1 Averages and standard deviations. listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual E standard deviation would not be the average of quarterly standard deviations. 5 The average x and standard deviation s of a set of n numbers xi, x2. . . x n are defined as follows:
@g.
L' gi 1 x= Ex I (x- x)2 s= n-1 4.2 Values below the highest lower limit of detection are not included in the average. 4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported. 4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported. 4.5 In rounding off, the following rules are followed: 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44. 4.5.2. If the figure following those to be retained is equal to or greater than 5, the .- E figure is dropped and the last retained figure is raised by 1. As an ( 3 example,11.445 is rounded off to 1~.45. I I I I I, B-3 l l
POINT BEACH NUCI EAR PLANT i s APPENDIX C Sampling Program and Locations C1
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