LIC-94-0083, Radiological Environ Operating Rept TS 5.9.4.b Jan-Dec 1993
| ML20070N741 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/31/1993 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-94-0083, LIC-94-83, NUDOCS 9405090138 | |
| Download: ML20070N741 (52) | |
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, e 1 dgfg ' 1, g ggemag Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska E9102-2247 April 29, 1994 402/636-2000 LIC-94-0083 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, DC 20555
REFERENCE:
Docket flo. 50-285 Gentlemen:
SUBJECT:
Fort Calhoun Station 1993 Radiological Environmental Operating Report In accordance with Fort Calhoun Station Technical Specification 5.9.4.b, enclosed is the 1993 Radiological Environmental Operating Report for the period of January 1,1993 through December 31, 1993. Data was obtained in accordance with Technical Specification 5.9.4.b and the Offsite Dose Calculation Manual (ODCM). If you should have any questions, please contact me. Sincerely, 40 2M W. G. Gates Vice President WGG/mah Enclosure c: LeBoeuf, Lamb, Greene & MacRae (w/o enclosure) L. J. Callan, NRC Regional Administrator, Region IV S. D. Bloom, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector G. K. Samide, American Nuclear Insurers Supervisor - Radiochemistry Section, University of Iowa _mnnt n 9405090138 931231 , PDR ADOCK 05000285 / R PDR F c5 5124 Empoyment wth Eq+1; Opporturuty h g
e i , l l FORT CALHOUN STATION l RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TECHNICAL SPECIFICATION 5.9.4.b January 1, 1993 to December 31, 1993
i 1993 Annual Radioloaical Environmental Operatina Report In accordance with Technical Specification 5.9.4.b, attached is the Fort 1993 Annual Radiological Environmental Operating Report. Calhoun Station The materials (FCS)d are consistent with the objectives outlined in the provide Offsite Dose Calculation Manual (0DCM), and Sections IV.B.2, IV.B.3, and IV.C l of Appendix I of 10 CFR 50. Each segment of the report is presented in the following sequence: J
- 1) A discussion of FCS impact on the environment and program ,
observations relevant to the overall effectiveness of the Radiological Environmental Monitoring Program (Introduction).
- 2) The sample class, sample collection frequency, number of sample locations, and the number of samples collected this reporting period for each class are delineated in Table 1.0.
- 3) A statistical evaluation of program findings is summarized in Table 2.0 in accordance with Regulatory Guide 4.8, Table 1. For each type of sample medium and analysis, Table 2.0 exhibits separately all indicator locations, all control locations, and the location havir.g the highest annual mean result. For each of these classes, Table 2.0 specifies the following:
! A. The total number of analyses l l B. The fraction of analyses yielding detectable results
- (i.e., results above the highest lower limit of l detection (LLD) for this period).
l C. The maximum, minimum, and average results. The distance in miles and the direction relative to the FCS Reactor Containment Building (degrees azimuth) are specified for i the location with the highest annual mean.
- 4) Table 3.0 is a listing of missed samples and explanations.
- 5) Appendix A contains a description of the Vendor Interlaboratory Comparison Program results.
l 6) Appendix B describes the Vendor Data Reporting Conventions l utilized.
- 7) Appendix C reports the information required when primary coolant specific activity has exceeded the limits of Technical Specification 2.1.3.
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1 4 j a , h i f i INTRODUCTION l j 1993 Radioloaical Environmental Monitorina Proaram i ! constitutes the 1993 Annual Radiolo ical Environmental Operating i The followinhe Report for t Radiological Environmental Monitor $ng Proc ram (REMP) performed 1 for the Fort Calhoun Station (FCS). Results of completec, sample analyses are presented in the attached tables. Collection of sample media is performed by Omaha Public Power District (OPPD). Analyses and data are provided by contract vendor (Teledyne Brown Engineering--Northbrook, Illinois). ! The tables reflect samples collected to satisfy the requirements of the
- Technical Specifications and the Offsite Dose Calculation Manual (0DCM). Data obtained in the program were well within the ranges previously assessed in the j REMP. None of the media sampled contained radioactivity attributable to the
- operation of FCS. Deviations from the routine monitoring program were 1 performed as a result of various occurrences. Legitimate inconsistencies are i
allowed .in the REMP conditionally by the ODCM. However, all non-routine i functions must be included in the Annual Radiological Environmental Operating Report to the NRC. The following observations were determined to be j reportable: j (1) The intent of the program is to monitor the exposure pathway sequence for the potential of radioactive releases to the i environment. This is accomplished through the collection of fish,
- if available, in the order of the existing food chain. As a
] conservation measure, only one adult fish sufficient in size for
- representative analysis is routinely collected for each food chain '
4 class, defined by the procedure. However, due to the lack of specific target species in number and size for the insect feeding class it was necessary to collect several species and perform a ,
- composite analysis. Smallmouth Buffalo, Goldeye, and Freshwater i i Drum of varying size were collected for the composite. The fish
- species required by the REMP were collected as required at 1 Location 0-22, Missouri River mile marker 645.0.
- Results were all j < LLD for samples analyzed as defined in Table 2.0.
{ (2) 5.5 km or 3.4 miles, 0 j One 310*)milk was sample dropped location, from the REMP Flynndue Dairy, to t (he farm terminating operations on April 27, 1993. Two locations remain in the l sampling program and are sufficient to meet the requirements of
- the ODCM. One indicator location, Seltz Farm, is within 8.0 km of
', FCS (4.5 km, or 2.8 miles 0169*) and one control location, Japp Dairy, is between 8.0 km and 30.0 km of FCS (10.1 km or 6.3 miles, l i 0 219*). The effectiveness of the REMP has not been reduced by
- the closure of Flynn Dairy.
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t 5 l (3) Extreme flooding conditions occurred during July of 1993 in the i entire Missouri River valley drainage area including the FCS vicinity. As a result, it was necessary to alter the routine surface water sample Intake Structure, andlocations (downstream of the Raw Water 125' upstream of the F 0.5 miles discharge) in order to collect representative samples. Samples were collected at the nearest river access relative to FCS and the original sample sites. Boats could not be utilized during the flooding due to the river being closed by the U.S. Corps of Engineers. Substitute sample locations are given in the following chart. l I Approximately 5 miles l 300 feet Upstream 0.5 miles Downstream / Downstream of FCS near Date/ Time / Sample of FCS 0.125 miles west of FCS Fort Calhoun Stone Company l (-=- 7 7 93 /1545 / Up xxx 7/7 93 /1535 / Down xxx 714-93 /1610 / Up xxx l 7-14-93 /1630 / Down xxx 7 21-93 /1448 I Up xxx 7 2193 /1538 / Down xxx 7 28 93 /1411/ Up xxx 7-28-93 /1140 / Down xxx (4) Downtime for air sampling units was minimal as only five minor occurrences were documented. Four were maintenance related, and one was an inadvertent error as a result of the unit not being activated following filter Following unit maintenance, samplers were/ cartridge exchange.promptly returned to service Redundant samplers were in place at these locations as operated by the State of Nebraska Department of Radiological Health. Review of the State data indicated no environmental impact while OPPD units were inoperable. The effectiveness of the REMP has not been l reduced by failure of environmental air sampling units. l l l l l l
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i Table 1.0 Sample collection program. i I Number of Number of Samples Collection Sample Collected Sample Class Frequency Locations This Period . 1 Background Radiation (TLDs) Quarterly 11 44 Air Particulates Weekly 5 256 l Airborne Iodine Weekly 5 256 ; Milk Semimonthly 2 22 Surface Water Monthly 3 36 ; Fish Annually 2 5^ Mud and Silt Semiannually 1 2 I Food Crops Annually 4 JJ TOTAL 632 l i a Six species of fish were collected at location 0-22. Three were analyzed as a composite sample. l l l l l l i i 1
9 a Table 2.0 Radiological Environmental Monitoring Program Summary. l Name of Facility Fort Calhoun Nuclear Power Station - Unit i Docket No. 50-285 , Location of Facihty Washmgton, Nebraska Reporting Period January - December 1993 l (County, State) Indicator Location with liighest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLob hiean (F)C Mean (F)C Routine Mean (F)c (Units) Analyn d Range c Locationd Range c Range Results" l Background Gamma 44 0.5 1.4 (40/40) 0FA,Onsite Stn #1 1.6 (4 /4) 1.6 (4 /4) 0 Radiation (1.1 1.8) 0.5 mi.@ 293* (1.5-1.7) (1.5-1.7) (TLD) (mR/ week) OFJ,0.7 mi . @ 250* 1.6 (4 /4) (1.5-1.8) ! l Airborne GB 256 0.005I 0.020 (206/208) OAl, City of Blair 0.022 (51/51) 0.019 (48/48) 0 particulates (0.005-0.080) 3.0 mi @303* (0.010-0.080) (0.008-0.053) 1 (pCi/m3) I GS 20 Cs-134 0.001 <LLD - -
<LLD 0 Cs-137 0.001 <LLD - -
<LLD 0 Other 0.001 <LLD - -
<LLD 0 gammas Airbome I-131 256 0.7 <LLD - -
<LLD 0 kxtine (pCi/m3)
Milk, Fresh I-131 22 0.5 <LLD - -
<LLD 0 (pCi/L)
GS 22 K-40 150 1260 (11/11) 0-21, Japp Fann 1360 (11/11) 1360 (11/11) 0 l (1140-1460) 6.3 mi @ 219* (1190-1500) (1190-15(U) l Cs-134 15 <LLD - -
<LLD 0 l Cs-137 15 <LLD - -
<LLD 0 Other 15 <LLD - - <LLD 0 gammas surface Water GS 36 (pCi/L)
CS-134 15 <LLD - -
<LLD 0 i Cs-137 18 <LLD - -
<LLD 0 i
Other 15 <LLD - <LLD 0 gammas l l l H-3 12 300 (LLD - -
<LLD 0 )
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1 Table 2.0 Radiological Environmental Monitoring Program Summary. Name of Facility Fort Calhoun Nuclear Power Station - Unit 1 Docket No. 50-285 Ixcation of Facility Washington, Nebraska Reporting Period January - Den mber 1993 (County, State) Indicator Location with linghest Control Number i Sample Type and Locations Annual Mean Locations Non-l Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analyses" Range c Locationd Range t Range Results' hsh (pCi/g wet) CS 5 Mn-54 0.037 <LLD - - <LLD 0 Co-53 0.045 (LLD - - <tLD 0 Co-60 0.028 <LLD - -
<LLD 0 Zn-65 0.088 <LLD - - <LLD 0 1
Cs-134 Ohl8 <LLD - -
<LLD 0 Cs-137 0.022 <tLD - -
<LLD 0 1
Other 0 312 <LLD - - <LLD 0 ) I gammaSK Mud and Silt GS 2 (pCi/g dry) Cs-134 0.029 <LLD - <LLD 0 l Cs-137 0.023 <LLD - - <LLD 0 Other 0.026 <LLD - - <LLD 0 gammas Food Crops GS 11 (pCi/g wet) Mn-54 0.016 <tLD - - <LLD 0 Co-58 0.029 (LLD - -
<LLD 0 l l
Co-60 0.014 <LLD - - (LLD 0 Fe-59 Gol5 <LLD - - <LLD 0 Zn-65 0 315 <LLD - - (LLD 0 Zr-Nb-95 0.036 <LLD - -
<LLD 0 l
l Cs-134 0 312 (LLD - - <LLD 0 Cs-137 0.025 <LLD - - (LLD 0 Ba-La 140 0.013 <tLD - -
<LLD 0 a CB == gross beta, GS = gamma scan.
b LLD = nominallower limit of detection based on 95% confidence level. c Mean and range are based on detectable measurements only (i.e., <LLD). Fraction of detectable measurements at specified locations is indicated in parentheses (F). d Locations are specified: (1) by code, (2) by name, and (3) by distance and direction relative to Reactor Containment Building. e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten times the typical pre-operational value for the medium or location. I One value (<0.022) was eliminated from the LLD determination due to low volume. 8 Value given is for Ru-103. l l l
i i 1 l j TABLE 3.0 ! Listino of Missed Samples j
- Sample Type Date Location Reason Air Particulate / 01-13-93 OAJ-EOF Bldg. Sampler not activated i Charcoal Cartridge through North Omaha Power Station following filter j 01-20-93 (17.5 mi/157*) cartridge exchan/ge. l
.j Air Particulate 03-17-93 OAJ-EOF Bldg. Unit out of service
; Charcoal Cartridg/e through North Omaha Power Station for maintenance.
j i 03-24-93 (17.5 mi/157*) 1 lAirParticulate/ '08-16-93 OAI Sample not available. i ' Charcoal Cartridge through City of Blair, Nebraska Unit malfunction due j 08-18-93 (3.0 mi/303*) to blown fuse. I Air Particulate 10-27-93 OAJ-EOF Bldg. Unit out of service i Charcoal Cartridg/e through North Omaha Power Station for maintenance.
;. 11-03 93 (17.5 mi/157*)
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1 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS l l l 1 I > l
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i i 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 in-house spikes and blanks. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly 1 progress reports 6nly. Please refer to March, June, September and December progress reports for information. January,1990 through December,1993 March,1994
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l l l Appendix A l Interlaboratory Comparison Program Results l Teledyne's Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in , December 1971. These programs are operated by agencies which supply environmental type samples (e.g., i milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's i analytical procedures and to alert it to any possible problems, i l Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several 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 control limits 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 program for milk, water and air filters during the period 1990-1993. This program is conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada. The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), since 1976 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 imhouse " spiked" samples for the past twelve months. Data for previous years are 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 are available upon request. 1 I l Attachment A lists acceptance criteria for " spiked" samples, l 1 1 Out-of-limit results are explained directly below the result. ' 1 1 i A1
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l l December,1993 ATTACHMENT A l ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES l l LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES
- One Standard Deviation Analysis Level . for single determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium-89 6 5 to 50 pCi/ liter or kg 5.0 pCi/ liter l
>50 pCi/ liter or kg 10% of known value j Strontium-906 2 to 30 pCi/ liter or kg 5.0 pCi/ liter
>30 pCi/ liter or kg 10% of known value I Potassimn >0.1 g/ liter or kg 5% of known value Gross alpha s20 pCi/ liter 5.0 pCi/ liter
>20 pCi/ liter 25% of known value Gross beta $100 pCi/ liter 5.0 pCi/ liter
>100 pCi/ liter 5% of known value Tritium s4,000 pCi/ liter is = (pCi/ liter) =
169.85 x (known) ""
>4,000 pCi/ liter 10% of known value Radium-226,-228 <0.1 pCi/ liter
- 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value Iodine-131, s55 pCi/ liter 6.0 pCi/ liter Iodine-129b >55 pCi/ liter 10% of known value Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-645 >35 pCi/ liter 15% of known value Technetium-99 6 Iron-55, 50 to 100 pCi/ liter 10 pCi/ liter
>100 pCi/ liter 10% of known value Others6 -
20% of knmvn value
- From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year,1981-1982, EPA-600/4-81-004.
6 Teledyne limit. A2
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. , Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits I STW-589 WATER Jan,1990 Sr-89 22.7 i 5.0 25.0 i 5.0 16.3 - 33.7 l Sr-90 17.3 i 1.2 20.0 i 1.5 17.4 - 22.6 The sample was reanalyzed in triplicate for Sr-90; results of reanalyses were 18.811.5 pCi/L. No further action is planned. STW-591 WATER Jan,1990 Gr. Alpha 10.3 i 3.0 12.015.0 3.3 - 20.7 Gr. Beta 12.3i 1.2 12.015.0 3.3 - 20.7 STW-592 WATER Jan,1990 Ba-133 78.010.0 74.0 i 7.0 61.9 - 86.1 Co-60 14.7 i 2.3 15.0 i 5.0 6.3 - 23.7 Cs-134 17.3 i 1.2 18.0 i 5.0 9.3 - 26.7 Cs-137 19.3 i 1.2 18.015.0 9.3 - 26.7 Ru-106 133.3 i 13.4 139.0 i 14.0 114.8 - 163.2 Zn-65 135.016.9 - 139.0 i 14.0 114.8 - 163.2 STW-593 WATER Feb,1990 H-3 4827.0 t 83.0 4976.0 1 498.0 4113.0 - 5839.0 STW-594 WATER Mar,1990 Ra-226 5.010.2 4.910.7 4.1 - 5.7 Ra-228 13.510.7 12.7 i 1.9 9.4 - 16.0 STW-595 WATER Mar,1990 Uranium 4.0 0.0 4.0 i 6.0 0.0 - 14.4 STAF-596 AIR FILTER Mar,1990 Cs-137 9.3 i 1.2 10.0 i 5.0 1.3 - 18.7 Gr. Alpha 7.311.2 5.0 i 5.0 0.0 - 13.7 Gr. Beta 34.0 i 0.0 31.015.0 22.3 - 39.7 Sr-90 10.010.0 10.0 i 1.5 7.4 - 12.6 STW-597 WATER Apr,1990 Gr. A1pha 81.0 i 3.5 90.0.1 23.0 50.1 - 129.9 Ra-226 4.9 i 0.4 5.010.8 3.6 - 6.4 Ra-228 10.610.3 10.2 1.5 7.6 - 12.8 U 18.7 i 3.0 20.016.0 9.6 - 30.4 STW-598 WATER Apr,1990 Cs-134 16.010.0
- 15.015.0 6.3 - 23.7 Cs-137 19.0 i 2.0 15.0 i 5.0 6.3 - 21.7 Gross Beta 51.0 i 10.1 52.015.0 43.3 - 60.7 St-89 9.3 i 1.2 10.0 i 5.0 1.3 - 18.7 Al-1
l I I I Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
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l Concentrationin pCi/L6 l l Lab Sample Date Teledyne Results EPA Resultd Control ! Code Type Collected Analyses f2 Sigma' Is, N=1 Limits Sr-90 10.3 i 3.1 10.0 i 1.5 l 8.3 - 11.7 STM-599 MILK Apr,1990 Cs-137 26.0 6.0 24.0 i 5.0 15.3 - 32.7 I-131 98.7 i 1.2 99.0 i 10.0 81.7 - 116.3 I K 1300.0 1 69.2 1550.0 i 78.0 1414.7 - 1685.3 ' The K analysis was repeated in triplicate; result of reanalysis was 1421.7195.3 mg/L. No further action is planned. Sr-89 21.7 i 3.1 . 23.0 i 5.0 14.3 - 31.7 Sr-90 21.017.0 23.015.0 14.3 - 31.7 l STW-600 WATER May,1990 l Sr-89 6.0i 2.0 7.015.0 0.0 - 15.7 Sr-90 6.7i 1.2 7.0 i 5.0 0.0 - 15.7 STW-601 WATER May,1990 Gr. A1pha 11.0 i 2.0 22.0 i 6.0 11.6 - 32.4 Gross Alpha analysis was repeated in triplicate; results of reanalyses were 13.411.0 pCi/L. No further action is planned. Gr. Beta 12.3 i 1.2 15.0 i 5.0 6.3 - 23.7 STW-602 WATER Jun,1990 Ba-133 100.7 i 8.1 99.0110.0 81.7 - 116.3 I Co-60 25.3 i 2.3 24.0 i 5.0 15.3 - 32.7 Cs-134 23.711.2 24.015.0 18.2 - 29.8 Cs-137 27.713.1 25.015.0 16.3 - 33.7 Ru-106 202.7 i 17.2 210.0 1 21.0 173.6 - 246.4 Zn-65 155.0 i 10.6 148.0 i 15.0 130.6 - 165.4 STW-603 WATER Jun,1990 H-3 2927.0 i 306.0 2933.0 i 358.0 2312.0 - 3554.0 STW-604 WATER Jul,1990 . Ra-226 11.8 i 0.9 12.111.8 9.0 - 15.2 Ra-228 4.1 i 1.4 5.1i1.3 2.8 - 7.4 l STW-605 WATER Jul,1990 I U 20.3 i 1.7 20.8 i 3.0 15.6 - 26.0 STW-606 WATER Aug,1990 I-131 43.0i 1.2 39.0 i 6.0 28.6 - 49.4 STW-607 WATER Aug,1990 Pu-239 10.0 i 1.7 9.1 i 0.9 7.5 - 10.7 STAF-608 AIR FILTER Aug,1990 Cs-137 19.0 i 2.0 20.0 i 5.0 11.3 - 28.7 Al-2
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. l . l Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Result d Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits Gr. Alpha 14.010.0 10.0 i 5.0 1.3 - 18.7 l Gr. Beta 65.311.2 62.0 i 5.0 53.3 - 70.7 Sr-90 19.0 i 6.9 20.0 i 5.0 11.3 - 28.7 i j STW-609 WATER Sep,1990 l Sr 69 9.0 i 2.0 10.015.0 1.3 - 18.7 Sr-90 9.012.0 9.0 i 5.0 0.3 - 17.7 STW-610 WATER Sep,1990 Gr. Alpha 8.3 i 1.2 10.015.0 1.3 - 18.7 Gr. Deta 10.311.2 10.015.0 1.3 - 18.7 STM-611 MILK Sep,1990 Cs-137 20.0 i 2.0 20.0 i 5.0 11.3 - 28.7 I-131 63.0 i 6.0 58.0 i 6.0 47.6 - 68.4 K-40 1673.3 1 70.2 1700.0 1 85.0 1552.5 - 1847.5 Sr-89 11.7 i 3.1 16.0 i 5.0 7.3 - 24.7 Sr-90 15.0 i 0.0 20.015.0 11.3 - 28.7 l STW-612 WATER Oct,1990 -
- Ba-133 116.7 i 9.9 110.0 i 11.0 90.9 - 129.0 l Co-60 20.3 i 3.1 20.0 i 5.0 11.3 - 28.7 i
Cs-134 11.0 i 0.0 12.0 i 5.0 3.3 - 20.7 Cs-137 14.012.0 12.0 i 5.0 3.3 - 20.7 Ru-106 152.0 i 8.0 151.0 i 15.0 125.0 - 177.0 Zn-65 115.3 i 12.2 115.0 1 12.0 94.2 - 135.8 STW-613 WATER Oct,1990 H-3 7167.0 i 330.0 7203.0 1 720.0 5954.0 - 8452.0 STW-614 WATER Oct,1990 l Gr. Alpha 68.7 i 7.2 62.0116.0 34.2 - 89.8 l Ra-226 12.9 i 0.3 13.6 i 2.0 10.1 - 17.1 Ra-228 4.2 i 0.6 5.0 i 1.3 2.7 - 7.3 U 10.4 i 0.6 10.213.0 5.0 - 15.4 STW-615 WATER Oct,1990 Cs-134 9.0 i 1.7 7.015.0 0.0 - 15.7 Cs-137 7.711.2 5.0 i 5.0 0.0 - 13.7 Gross Beta 55.0 i 8.7 53.0 5.0 44.3 - 61.7 Sr-89 15.7 i 2.9 20.015.0 11.3 - 28.7 Sr-90 12.0 2.0 - 15.0 i 5.0 6.0 - 23.7 l l Al-3 I
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media *. Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits STW-616 WATER Nov,1990 Ra-226 6.8 i 1.0 7.4 i 1.1 5.5 - 9.3 Ra-228 5.311.7 7.7 i 1.9 4.4 - 11.0 STW-617 WATER Nov,1990 U 35.0 i 0.4 35.5 i 3.6 29.3 - 41.7 Sample was analyzed but the results were not submitted to the EPA because the deadline was missed (all data on file). STW-618 WATER Jan,1991 Sr-89 4.3 i 1.2 5.0 1 5.0 0.0 - 13.7 Sr-90 4.7i 1.2 5.015.0 0.0 - 13.7 STW-619 WATER Jan,1991 j Pu-239 3.6 i 0.2 3.3 i 0.3 2.8 - 3.8 ; STW-620 WATER Jan,1991 l Gr. Alpha 6.7i 3.0 5.0 i 5.0 0.0 - 13.7 1 G r. Beta 6.3 i 1.2 5.0 i 5.0 0.0 - 13.7 STW-621 WATER Feb,1991 Ba-133 85.7i 9.2 75.0 i 8.0 61.1 - 88.9 Co-60 41.3 i 8.4 40.0 i 5.0 31.3 - 48.7 Cs-134 9.0 i 2.0 8.015.0 0.0 - 16.7 Cs-137 9.7i 1.2 8.0i5.0 0.0- 16.7 Ru-106 209.71 18.6 186.0 i 19.0 153.0 - 219.0 Zn-65 166.71 19.7 149.0 1 15.0 123.0 - 175.0 STW-622 WATER Feb,1991 l I-131 81.3 i 6.1 75.0 i 8.0 61.1 - 88.9 j STW-623 WATER Feb,1991 H-3 4310.0 i 144.2 4418.0 1 442.0 3651.2 - 5184.8 ( STW-624 WATER Mar,1991
- Ra-226 31.4 i 3.2 31.8 i 4.8 23.5 - 40.1 l
Ra-228 21.1 i 5.3 11.9 - 30.3 No data for Ra-228 was reported; sample was lost during analysis. STW-625 WATER Mar,1991 U 6.7 i 0.4 7.6 i 3.0 2.4 - 12.8 STAF-626 AlR FILTER Mar,1991 Cs-137 33.7 i 4.2 40.0 i 5.0 31.3 - 48.7 ( Al-4 l w___-________. - . - - - -
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l i i i Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Tcledyne's l Midwest Laboratory results for various sample media'. ! l i Concentration in pCi/L6 Date Lab Sample Teledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma
- 1s, N=1 Limits Gr. Alpha 38.7 i 1.2 25.016.0 14.6 - 35.4 {
The cause of the high Gross Alpha result is the difference in geometry between the standard used in the TIML lab and the 1 EPA filter. Gr. Beta 130.0 i 4.0 124.016.0 113.6 - 134.4 St-90 35.7 i 1.2 40.015.0 31.3 - 48.7 STW-627 WATER Apr,1991 i } l
- Gr. AIpha 51.0 i 6.0 54.0 i 14.0 29.7 - 78.3 !
Ra-226 7.0 1 0.8 8.0 i 1.2 5.9 - 10.1 1 Ra-228 9.711.9 15.213.8 8.6 - 21.8 U 27.7 i 2.4 29.8 i 3.0 24.6 - 35.0 STW-628 WATER Apr,1991 1 Cs-134 27 3 i 1.2 24.0 i 5.0 15.3 - 32.7 Cs-137 29.012.0 25.015.0 16.3 - 33.7 Gross Beta 93.3 i 6.4 115.0 i 17.0 85.5 - 144.5 Sr-89 21.0 i 3.5 28.0 i 5.0 19.3 - 36.7 Sr-90 23.0 i 0.0 26.0 i 5.0 17.3 - 34.7 STM-629 MILK Apr,1991 Cs-137 54.7 i 11.0 49.0 i 5.0 40.3 - 57.7 I-131 65.3 i 14.7 60.0 i 6.0 49.6 - 70.4 K-40 1591.7 i 180.1 1650.0 i 83.0 1506.0 - 1794.0 Sr-89 24.0 i 8.7 32.0 i 5.0 23.3 - 40.7 Sr-90 28.0 i 2.0 32.015.0 23.3 - 40.7 STW-630 WATER May,1991 Sr-89 40.7 i 2.3 39.015.0 30.3 - 47.7
- Sr-90 23.711.2 24.0 i 5.0 15.3 - 32.7 STW-631 WATER May,1991 Gr. AIpha 27.7 i 5.8 24.0 i 6.0 13.6 - 34.4 Gr. Beta 46.010.0 46.015.0 37.3 - 54.7 STW-632 WATER Jun,1991 Ba-133 74.016.9 62.016.0 51.6 - 72.4 Sample was reanalyzed for Ba-133. Result of the reanalysis was 63.816.9 pCi/L; within the EPA controllimits.
Co-60 11.3 i 1.2 10.015.0 1.3 - 18.7 Cs-134 15.3 i 1.2 15.0 i 5.0 6.3 - 23.7 Cs-137 16.3 i 1.2 14.0 i 5.0 5.3 - 22.7 ) Ru-106 162.3 i 19.0 149.0 1 15.0 123.0 - 175.0 Al-5 w - e , , .* 7 -. ,., . -. g.- .. y, .-q- y , _3, q.c.% . - . .
O Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. l Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result d Control Code Type Collected Analyses i2 Sigma
- 1s, N=1 Limits Zn-65 119.3 i 16.3 108.0 i 11.0 88.9 - 127.1 STW-633 WATER Jun,1991 H-3 13470.0 385.8 12480.0 1 1248.0 10314.8 - 14645.2 STW-634 WATER Jul,1991 Ra-226 14.9 i 0.4 15.9 i 2.4 11.7 - 20.1 l Ra-228 17.6 i 1.8 16.7 i 4.2 9.4 - 24.0 STW-635 WATER Jul,1991 U 12.8 i 0.1 ,
14.2 i 3.0 9.0 - 19.4 STW-636 WATER Aug,1991 l I-131 19.3 i 1.2 20.0 i 6.0 9.6 - 30.4 STW-637 WATER Aug,1991 Pu-239 21.4 i 0.5 19.4 i 1.9 16.1 - 22.7 STAF-638 AIR FILTER Aug,1991 Cs-137 26.3 i 1.2 30.015.0 21.3 - 38.7 l Gr. Alpha 33.0 2.0 25.0 _.6.0 14.6 - 35.4 Gr. Beta 88.711.2 92.0 i 10.0 80.4 - 103.6 l Sr-90 27.014.0 30.0 i 5.0 21.3 - 38.7 STW-639 WATER Sep,1991 l Sr-89 47.0 i 10.4 49.0 i 5.0 40.3.- 57.7 Sr-90 24.012.0 25.0 i 5.0 16.3 - 33.7 STW-640 WATER Sep,1991 Gr. Alpha 12.0 i 4.0 10.015.0 1.3 - 18.7 Gr. Beta 20.311.2 20.0 i 5.0 11.3 - 28.7 STM-641 MILK Sep,1991 Cs-137 33.7 i 3.2 30.0 i 5.0 21.3 - 38.7 l I-131 130.7 i 16.8 108.0 i 11.0 88.9 - 127.1 l The cause of the high result for the I-131 analysis is unknown. ! An in-house spike sample was prepared with activity for I-131 of 68.316.8 pCi/L Result of TIML's analysis of the in-house j spike was 69.119.7 pCi/L. K 1743.3 i 340.8 1740.01 87.0 1589.1 - 1890.9 Sr-89 20.3 i 5.0 25.0 i 5.0 16.3 - 33.7 Sr-90 19.7 i 3.1 25.0 i 5.0 16.3 - 33.7 STW-642 WATER Oct,1991 Ba-133 94.713.1 98.0 i 10.0 80.7 - 115.3 Co-60 29.7 i 1.2 29.0 i 5.0 20.3 - 37.7 Cs-134 9.7i 1.2 10.015.0 1.3 - 18.7 Al-6 e -,w -- , - _ -e~,.. - - - - , .
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media *. Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits Cs-137 11.0 i 2.0 10.0 i 5.0 1.3 - 18.7 Ru-106 196.3 i 15.1 199.0 i 20.0 164.3 - 233.7 Zn-65 75.7 i 8.3 73.0 i 7.0 60.9 - 85.1 STW-643 WATER Oct,1991 H-3 2640.0 i 156.2 2454.0 i 352.0 1843.3 - 3064.7 STW-644 WATER Oct,1991 Gr. Alpha 73.0113.1 82.0 i 21.0 45.6 - 118.4 Ra-226 20.9 i 2.0 22.0 i 3.3 16.3 - 27.7 Ra-228 19.612.3 22.2 i 5.6 12.5 - 31.9 U 13.510.6 13.5 i 3.0 8.3 - 18.7 STW-645 WATER Oct,1991 j Co-60 20.3 i 1.2 20.0 i 5.0 11.3 - 28.7 i Cs-134 9.015.3 10.0 i 5.0 1.3 - 18.7 l Cs-137 14.7 i 5.0 11.0 i 5.0 2.3 - 19.7 I Gross Deta 55.313.1 65.0 i 10.0 47.7- 82.3 Sr-89 9.7 i 3.1 10.015.0 1.3 - 18.7 l St-90 8.7 i 1.2 10.0 i 5.0 1.3 - 18.7
]
STW-646 WATER Nov,1991 Ra-226 5.6 i 1.2 6.5i1.0 4.8 - 8.2 Ra-228 9.610.5 8.1i2.0 4.6 - 11.6 STW-647 WATER Nov,1991 U 24.7 i 2.3 24.9 i 3.0 19.7 - 30.1 STW-648 WATER Jan,1992 Sr-89 42.7i 6.4 51.0 i 5.0 42.3 - 59.7 Sr-90 18.3 i 3.1 20.0 i 5.0 11.3 - 28.7 STW-649 WATER Jan,1992 i Pu-239 16.110.8 16.8 i 1.7 13.9 - 19.7 STW-650 WATER Jan,1992 Gr. Alpha 23.7 i 9.2 30.018.0 16.1 - 43.9 Cr. Beta 27.7i 4.2 30.0 i 5.0 21.3 - 38.7 STW-651 WATER Feb,1992 1-131 60.314.2 59.0 i 6.0 48.6 - 69.4 STW-652 WATER Feb,1992 Ba-133 79.0 i 3.4 76.0 i 8.0 62.1 - 89.9 Co-60 40.3i 5.0 40.0 i 5.0 31.3 - 48.7 Cs-134 31.7 i 4.2 31.0 i 5.0 22.3 - 39.7 Al-7 l
I Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's -{ Midwest Laboratory results for various sample media'. Concentration in pCi/L6 l Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits Cs-137 51.0 i 3.4 49.0 i 5.0 40.3 - 57.7 Ru-106 188.7 i 28.8 203.0 i 20.0 168.3 - 237.7 Zn-65 148.0 1 15.0 150.7 i 6.1 122.0 - 174.0 STW-653 WATER Feb,1992 H-3 7714.0 i 119.6 7904.0 i 790.0 6533.4 - 9274.6 STW-654 WATER Mar,1992 Ra-226 9.010.4 10.1 i 1.5 7.5 - 12.7 Ra-228 18.8 i 0.6 15.513.9 8.7 - 22.3 STW-655 WATER Mar,1992 Rn-222 0.0 No Data; Special EPA testing. STW-656 WATER Mar,1992 U 25.1 i 1.9 25.313.0 20.1 - 30.5 STW-657 WATER Mar,1992 Rn-222 No Data is available; Special EPA testing. STAF-658 AIR FILTER Mar,1992
- Cs-137 10.0 i 0.0 10.0 i 5.0 1.3 - 18.7 Gr. Alpha 7.0 i 0.0 7.015.0 0.0 - 15.7 Gr. Beta 39.3 i 1.6 41.015.0 32.3 - 49.7 St-90 13.711.6 15.0 i 5.0 6.3 - 23.7 STW-659 WATER Apr,1992 Gr. A1pha 35.7 i 6.1 40.0 i 10.0 22.7 - 57.3 Ra-226 12.7 i 1.2 14.9 i 2.2 11.1 - 18.7 i Ra-228 14.5 i 2.1 14.0 i 3.5 7.9 - 20.1 U 3.9 i 0.2 4.013.0 0.0 - 9.2 l
STW-660 WATER Apr,1992 Co-60 61.0 i 4.0 56.0 i 5.0 47.3 - 64.7 Cs-134 24.3 i 1.2 24.015.0 15.3 32.7 j Cs-137 24.0 i 2.0 22.015.0 13.3 - 30.7 l l Gross Beta 113.0 i 7.2 140.0 1 21.0 103.6 - 176.4 l Sr-89 12.3 i 4.2 15.0 i 5.0 6.3 - 23.7 Sr-90 15.0 i 1.2 17.0 i 5.0 8.3 - 25.7 STM-661 MILK Apr,1992 l Cs-137 39.3 i 2.3 39.0 i 5.0 30.3 - 47.7 1-131 78.7 i 9.5 78.018.0 64.1 - 91.9 A1-8 l l
I l
. 1 Table A 1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's I Midwest Laboratory results for various sample media'.
l 6 Concentration in pCi/L I Lab Sample Date Teledyne Results EPA Resultd Control ; Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits K-40 1610.0 i 72.1 1710.0 i 86.0 1560.8 - 1859.2 Sr-89 25.3 i 7.6 38.015.0 29.3 - 46.7 The cause of the low Sr-89 results is unknown. Data were checked for errors. An in-house spike sample was prepared with activity for St-89 of 41.0110.0 pCi/L. Result of the analysis of the in-house spike sample for Sr-89 was 37.213.6 pCi/L Sr-90 24.3 i 3.1 29.0 i 5.0 20.3 - 37.7 STW-662 WATER May,1992 Sr-89 24.014.0 29.015.0 20.3 - 37.7 Sr-90 6.7 t 1.2 , 8.0 i 5.0 0.0 - 16.7 STW-663 WATER May,1992 Gr. Alpha 12.312.1 15.015.0 6.3 - 23.7 Gr. Beta 46.0i 5.0 44.0 5.0 35.3 - 52.7 STW-664 WATER Jun,1992 Ba-133 92.7 f 11.0 98.0 i 10.0 80.7 - 115.3 i Co-60 20.3 i 1.2 20.0 i 5.0 11.3 - 28.7 Cs-134 14.3 i 2.3 15.015.0 6.3 - 23.7 Cs-137 15.0 i 2.0 15.0 i 5.0 6.3 - 23.7 Ru-106 142.7 1 23.7 141.0 1 14.0 116.7 - 165.3 Zn-65 103.3 i 10.6 99.0 i 10.0 81.7 - 116.3 STW-665 WATER Jun,1992 H-3 2153.3 i 144.6 2125.0 1 347.0 1523.0 - 2727.0 STW-666 WATER Jul,1992 Ra-226 22.3 i 2.2 24.913.7 18.5 - 31.3 Ra-228 16.7 i 3.1 16.714.2 9.4 - 24.0 STW-667 WATER Jul,1992 Uranium 3.6i0.3 4.0 i 3.0 0.0 - 9.2 STW-668 WATER Aug,1992 1-131 47.0 i 3.5 . 45.0 i 6.0 34.6 - 55.4 STW-669 WATER Aug,1992 l Pu-239 8.5i0.9 9.0 1 0.9 7.4 - 10.6 j STAF-670 AIR FILTER Aug,1992 l A1pha 25.7 i 1.2 30.018.0 16.1 - 43.9 Beta 69.0 i 2.0 69.0 i 10.0 51.7 - 86.3 Cs-137 16.0 i 0.0 18.0 i 5.0 9.3 - 26.7 Sr-90 26.0 i 4.0 25.0 i 5.0 16.3 - 33.7 Al-9
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. Concentration in pCi/L 6 Lab Sample Date Teledyne Results EPA Result d Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits STW-671 WATER Sep,1992 Sr-89 16.0 i 4.0 20.0 i 5.0 11.3 - 28.7 Sr-90 14.3 i 3.1 15.0 i 5.0 6.3 - 23.7 STW-672 WATER Sep,1992 A1pha 43.0 i 13.1 45.0 i 11.0 25.9 - 64.1 ! Beta 41.3 i 18.6 50.0 i 5.0 14.3 - 58.7 STM-673 MILK Sep,1992 Cs-137 14.013.5 15.0 i 5.0 6.3 - 23.7 I-131(gamma 109.7 i 19.4 100.0 i 10.0 82.7 - 117.3 K 1540.0 i 103.9 1750.0 i 88.0 1597.3 - 1902.7 The K activity was calculated using the wrong volume (3.5 L), l instead of 3.25 L. Correction for volume resulted in a value of 1660.01110.1; within EPA controllimits. St-89 11.013.5 15.015.0 6.3 - 23.7 Sr-90 12.7 i 1.6 15.0 i 5.0 6.3 - 23.7 STW-674 WATER Oct,1992 Ba-133 80.319.0 74.017.0 61.9 - 86.1 j Co-60 11.3 i 2.3 10.0 i 5.0 1.3 - 18.7 Cs-134 9.7 i 2.3 8.015.0 0.0 - 16.7 l Cs-137 9.711.2 8.015.0 0.0 - 16.7 l Ru-106 170.7 i 2.3 175.0 i 18.0 143.8 - 206.2 Zn-65 169.7 i 25.0 148.0 i 15.0 122.0 - 174.0 STW-675 WATER Oct,1992 l H-3 5896.7 1 136.2 5962.0 i 596.0 4928.0 - 6996.0 STW-676 WATER Oct,1992 Gr. Alpha 24.7 i 5.0 29.017.0 16.9 - 41.1 l Ra-226 7.1 i 0.4 7.4 i 1.1 5.5 - 9.3 Ra-228 11.5 i 1.0 10.0 i 2.5 5.7 - 14.3 Uranium 9.710.5 10.2 i 3.0 5.0 - 15.4 STW-677 WATER Oct,1992 Co-60 15.0 i 2.0 15.015.0 6.3 - 23.7 Cs-134 5.7 i 1.2 5.015.0 0.0 - 13.7 l Cs-137 8.0i2.0 8.0i5.0 0.0 - 16.7 Gr. Beta 42.7 i 8.1 53.0 i 10.0 35.7 - 70.3 Sr-89 6.7i 1.2 8.0 i 5.0 0.0 - 16.7 Sr-90 10.0 i 2.0 110.0 i 5.0 1.3- 18.7 I Al-10 n ,- - , - . . - . . . - - , , , , . , - , , , . <
l l Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. l Concentration in pCi/L5 Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits STW-678 WATER Oct,1992 Ra-226 7.5 i 0.8 7.5i1.1 5.6 - 9.4 Ra-228 5.8 i 0.7 5.0 i 1.3 2.7 - 7.3 STW-679 WATER Nov,1992 Uranium 15.5 i 1.1 15.213.3 10.0 - 20.4 STW-680 WATER Jan,1993 Sr-89 15.0 i 2.0 15.0 i 5.0 6.3 - 23.7 Sr-90 10.3 i 1.2 10.015.0 1.3 - 18.7 i STW-681 WATER Jan,1993 Pu-239 17.5 i 1.6 20.0 i 2.0 16.5 - 23.5 l STW-682 WATER Jan,1993 A1pha 17.1 i 1.2 34.0 i 9.0 18.4 - 49.6 Gross Alpha analysis was repeated with similar results. An investigation of possible causes for the deviation from the EPA was conducted with no cause discovered. The sample was spiked with Th-230; so Alpha Spec Analysis for Th-230 was performed l in triplicate with results of 15.512.1,13.411.4, and 14.812.0. It should be noted that 66% of all participants failed this analysis with a grand average of 17.1. This coupled with the support of the Alpha Spec results leaves TIML cause to believe that there may have been 'a dilution error at the EPA. It should be noted that on the next Gross Alpha EPA check, TIML reported results that where exactly the known value. Since no apparent cause can be found, and TIML had outstanding results on the following sample, it is felt that no further investigation is needed. Beta 46.7 i 3.2 44.0 i 5.0 35.3 - 52.7 I STW-683 WATER Feb,1993 l I-131 106.0 i 10.0 100.0 1 10.0 82.7 - 117.3 STW-684 WATER Feb,1993 Uranium 7.2 1 0.5 7.6 i 3.0 2.4 - 12.8 STW-685 WATER Mar,1993 Ra-226 9.3 i 1.3 9.8 i 1.5 7.2 - 12.4 Ra-228 20.8 i 2.2 18.5 i 4.6 10.5 - 26.5 l STW-686 WATER Apr,1993 l l A1pha 88.3 i 8.1 95.0124.0 53.4 - 136.6 Ra-226 25.4 i 1.4 24.9 i 3.7 18.5 - 31.3 I Ra-228 17.4 i 1.2 19.0 i 4.8 10.7 - 27.3 Al-11
oi I Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses f2 Sigma' 1s, N=1 Limits Uranium 27.8 i 2.2 28.9 i 3.0 23.7 - 34.1 STW-687 WATER Apr,1993 Beta 141.719.0 177.0 1 27.0 130.2 - 223.8 Co-60 41.3 i 1.2 39.015.0 30.3 - 47.7 Cs-134 24.7 i 1.2 27.0 i 5.0 18.3 - 35.7 Cs-137 30.0 i 0.0 32.0 i 5.0 23.3 - 40.7 Sr-89 28.7 i 9.4 41.0 i 5.0 32.3 - 49.7 The EPA report was received 08-16-93. No cause for the low result for Sr-89 was found. The analyst has been observed performing this procedure with no noted descrepancies. Tcledyne will continue to monitor this procedure in the future. No further action is anticipated unless conditions warrant. Sr-90 28.0 i 3.5 29.0 i 5.0 20.3- 37.7 STW-688 WATER Jun,1993 H-3 9613.3 i 46.2 9844.0 i 984.0 8136.8 - 11551.2 STW-689 WATER Jun,1993
- Ba-133 101.7 i 10.3 99.0 i 10.0 81.7 - 116.3 Co-60 17.3 i 4.6 15.0 i 5.0 6.3 - 23.7 Cs-134 5.7i 1.2 5.0 i 5.0 0.0 - 13.7 Cs-137 6.0 i 2.0 5.015.0 0.0 13.7 Ru-106 108.018.0 119.0 1 12.0 98.2 - 139.8 Zn-65 114.0 i 13.2 103.0 i 10.0 85.7 - 120.3 STW-690 WATER Jul,1993 Sr-89 28.312.3 34.015.0 25.3 - 42.7 Sr-90 25.011.0 25.0 i 5.0 16.3 - 33.7
- STW-691 WATER Jul,1993
! AIpha 15.012.7 15.0 i 5.0 6.3 - 23.7 Beta 41.3 i 4.9 43.016.9 31.0 - 55.0 STW-692 WAT ER Aug,1993 Uranium 24.911.4 25.3 i 3.0 20.1 - 30.5 STAF-693 AIR FILTER Aug,1993 A1pha 17.0 i 1.0 19.0 i 5.0 10.3 - 27.7 Beta 47.3 i 0.6 47.0 i 5.0 38.3 - 55.7 i Cs-137 10.0i 1.0 9.015.0 0.3 - 17.7 Sr 90 19.3 i 0.6 19.0 i 5.0 10.3 - 27.7 STW-694 WATER Sep,1993 Ra-226 15.910.7 14.9 i 2.2 11.1 - 18.7 Al-12 l l l I
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media *. Concentrationin pCi/L6 Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits Ra-228 21.011.6 . 20.415.1 11.6 - 29.2 STM-695 MILK Sep,1993 Cs-137 49.013.0 49.0 i 5.0 40.3 - 57.7 I-131 125.3 i 4.5 120.0 i 12.0 99.2 - 140.8 K 1616.7 i 37.9 1679.0 i 84.0 1533.3 - 1824.7 Sr-89 19.3 i 1.5 30.0 i 5.0 21.3 - 38.7 Report was received 01-18-94; an investigation is underway as to the cause of the low Sr-89 fresults. In-house spikes have been prepared and the analysis is in progress (see SPM-4848 and SPM-4849 in future reports). There is no apparent cause of the low Sr-89 results. In-house spikes have been prepared and the analysis is in progress. The analyst has been observed performing this procedure with no discrepancies noted. No further action is planned unless the results of the in-house spikes show a problem. Sr-90 22.0 i 0.0 25.0 i 5.0 16.3 - 33.7 STW-696 WATER Oct,1993 I-131 116.7 i 2.3 117.0 1 12.0 96.2 - 137.8 STW-697 WATER Oct,1993 Gr. Alpha 39.7 t l.5 40.0! 10.0 22.7 - 57.3 Ra 226 10.6 i 0.5 , 9.9 i 1.5 7.3 - 12.5 Ra-228 13.2 i 1.5 12.5 i 3.1 7.1 - 17.9 Uranium 15.3 i 0.6 15.113.0 9.9 - 20.3 STW-698 WATER Oct,1993 Beta 52.0 i 1.0 58.0 i 10.0 40.7 - 75.3 Co-60 10.7 i 0.6 10.0 i 5.0 1.3 - 18.7 Cs-134 10.0 i 1.0 12.015.0 3.3 - 20.7 Cs-137 12.3 i 1.2 10.0 i 5.0 1.3 - 18.7
- Sr-89 11.3 i 0.6 15.0 i 5.0 6.3 - 23.7 Sr-90 11.010.0 10.0 i 5.0 1.3 - 18.7 l STW-699 WATER Oct,1993 A1pha 18.3 i 2.5 20.0 i 5.0 11.3 - 28.7 Beta 13.7 i 0.6 15.0 i 5.0 6.3 23.7 STW-700 WATER Nov,1993 H-3 7310.0 i 175.2 7398.0 i 740.0 6114.1 - 8681.9 STW-701 WATER Nov,1993 Ba-133 75.7 i 7.6 79.0 i 8.0 65.1 92.9 Co.60 30.7 i 2.1 30.0 i 5.0 21.3 - 38.7 A1-13 I
. . , - . . , . , . - . . - , - . - . . . - . - . - . . . . - . , . - - . - . . . _ . - , . . . - - ~ . . . - - . . . ~ - - . - , . - . . . . - -
i Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. Concentration in pCi/L' Lab Sample Date . Teledyne Results EPA Resultd Control Code Type Collected Analyses i2 Sigma
- 1s, N=1 Limits
' Cs-134 51.3 i 5.9 . 59.0 i 5.0 50.3 - 67.7 Cs-137 41.7 i 1.2 40.0 i 5.0 31.3 - 48.7 Ru-106 163.3 i 3.2 201.0 1 20.0 166.3 - 235.7 The report was received on 02-14 94; the cause of the low Ru-106 is under investigation. It should be noted that the grand average of all participants in this analysis was 175.2 pCi/L, with 54% of the participants outside oflimits.
'Zn-65 157.0 i 8.7 150.0 i 15.0 124.0 - 176.0
- Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
Environmental Protection Agency (EPA), Las Vegas, Neveda.
- 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.
- Unless otherwise indicated, the TUEESML results are given as the mean i 2 standard deviations for threc
, 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 e i l 1 i A1-14 l __ , _ _ - . . . _ , . ~ . , - . . _ . . ,.
Table A-2. Crosscheck program results;'Ihermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average i 2 Sigma i Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) ' 2ndlaternationaUntucom;urissa 115-2 CaF2 : Mn Bulb Apr,1976 Field 17.011.9 17.1 16.417.7 Lab 20.8 i 4.1 21.3 18.8 i 7.6 Second InternationalIntercomparison of Environmental Dosimeters conducted in April of 1'776 by the ficalth and Safety Laboratory (!IASL), New York, New York, and the School of Public Ifealth of :he University of Texas, IIouston, Texas. 3.rslin!crnMionallnicIcomImriEon 115-3 CaF2 : Mn Bulb Jun,1977 FieId 30.7 i 3.2 34.9 i 4.8 31.5 i 3.0 Lab 89.6 i 6.4 91.7114.6 86.2 i 24.0 Third International Intercomparison 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, Ilouston, Texas. 4th InternationaLintercomparison 115-4 CaF2 : Mn Bulb Jun,1979 Fieid 14.1 i 1.1 14.1 i 1.4 16.019.0 Lab, liigh 40.4 1.4 - 45.8 i 9.2 43.9113.2 Lab, Low 9.8 i 1.3 12.2 i 2.4 12.017.4 Fourth International Intercomparison of Erwironmental Dosimeters conducted in the summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 5thlniernationallatercomparison 115-5A CaF2 : Mn Bulb Oct,1980 FieId 31.411.8 30.0 i 6.0 30.2 i 14.6 Lab,End 96.615.8 88.4 i 8.8 90.7131.2 Lab, Start 77.4 i 5.8 75.2 i 7.6 75.8140.4 115-5B LiF 100 Chips Oct,1980 FieId 30.314.8 30.016.0 30.2114.6 Lab,End 85.4 i 11.7 88.4 i 8.8 90.7 i 31.2 Lab, Start 81.117.4 75.2 i 7.6 75.8 i 40.4 Fifth International Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public IIcalth of the University of Texas,Ilouston, Texas and Erwironmental Measurements laboratory, New York, New York, U.S. Department of Energy. ZthlaternationaLintercomparison 115-7A LiF-100 Chips Jun,1984 Fie1d 75.412.6 75.8 i 6.0 75.1129.8 i i A2-1 I l
9 l Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) Lab, Co-60 80.0.i 3.5 79.9 i 4.0 77.9 i 27.6 Lab, Cs-137 66.6 i 2.5 75.013.8 73.0122.2 115-7B CaF2 : Mn Bulb Jun,1984 FieId 71.5 t 2.6 75.816.0 75.1 i 29 8 Lab, Co-60 84.8 i 6.4 79.9 i 4.0 77.9 i 27.6 Lab, Cs-137 78.811.6 . 75.013.8 73.012.2.2 115-7C CaSO4 :Dy Jun,1984 i Cards 1 Fieid 76.8 i 2.7 75.8 i 6.0 75.1 i 29.8 Lab, Co-60 82.5 i 3.7 79.9 i 4.0 77.9 i 27.6 Lab, Cs-137 79.0 i 3.2 75.0 i 3.8 73.0122.2 Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of I 1984 at Las Vegas, Neveda, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory , Commission, and the U.S. Environmental Protection Agency. Teledyne did not participate in the Sixth ! InternationalIntercomparison of Environmental Dosimeters, j dih_ International Intercomparison 115-8 A LiF-100 Chips Jan,1986 Field, Site 1 29.5 i 1.4 29.7 i 1.5 28.9112.4 ; Field, Site 2 11.310.8 10.4 i 0.5 10.1 i 9.1 Lab, Cs-137 13.710.9 17.210.9 16.216.8 l 115-8 B CaF2 : Mn Bulb Jan,1986 Field, Site 1 32.311.2 29.7 t l.5 28.9112.4 Field, Site 2 9.011.0 . 10.410.5 10.119.0 Lab, Cs-137 15.8 i 0.9 17.2 i 0.9 16.216.8 l 115-8C CaSO.:Dy Jan,1986 Cards l l Field, Site 1 32.2 i 0.7 29.7 i 1.5 28.9 i 12.4 Field, Site 2 10.6 t 0.6 10.410.5 10.119.0 Lab, Cs-137 18.1 i 0.8 17.210.9 16.216.8 Eighth International Intercomparison 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. 10th.lniernallemal_In te rco m pa rison A 2-2
Table A-2. Crosscheck program results;1hermoluminescent Dosimeters. (TLDs). mR 1 Lab Teledyne Results. Known Average i 2 Sigma l Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) I 115-10A LiF-100 Chips Aug,1993 FieId 25.7 i 1.4 27.0 i 1.6 26.4 i 10.2 Lab 22.711.6 25.9 i 1.3 25.0 i 9.4 Lab 62.7 i 2.6 72.7 i 1.9 69.8 i 20.3 115-10B CaSOgDy Aug,1993 Cards Fie1d 26.0 2.3 27.0 i 1.6 26.4 i 10.2 Lab 24.111.7 25.9 i 1.3 25.019.4 Lab 69.2 i 3.0 72.7 1.9 69.8 i 20.3 Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State l University and sponsored by the U.S. Department of Energy and the Idaho State University. The Ninth l Intemational Intercomparison of Environmental Dosimeters was not available to Teledyne's Midwest j Laboratory. Ir.ledyBelesting 1 l 89-1 LiF-100 Chips Sep,1989 l Lab 21.0 i 0.4 22.4 ND ND = No Data; Teledyne Testing was only performed by Teledyne. ; Chips were irradiated by Teledyne Isotopes, Inc., Westwood NJ. in September,1989 89-2 Teledyne Nov,1989 { CaSOpDy
)
Cards Lab 20.9 i 1.0 20.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were itradiated by Teledyne Isotopes, Inc., Westwood NJ. in November,1989. 90-1 Teledyne Jun,1990 CaSogDy Cards Lab 20.6 i 1.4 19.6 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes,Inc., Westwood NJ. on June 19,1990. 90-2 Teledyne Sep,1990 CaSOgDy Cards Lab 100.814.3 100.0 ND ND = No Data; Teledyne Testing was only performed by Tcledyne. Cards were irradiated by Dosimetry Associates, Inc., Nortlwille, MI on October 30,1990. A2-3
Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs), mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Date Measurement i 2 Sigma Value12 Sigma (All Participants) 91-1 Teledyne Oct,1990 CaSO.:Dy Cards 12b 1 33.4 i 2.0 32.0 ND 12b 2 55.2 i 4.7 58.8 ND Lab 3 87.816.2 85.5 ND l ND = No Data; Teledyne Testing was only performed by Teledyne. l Cards were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on October 8,1991. 92-1 LiF-100 Chips Feb,1992 12b 1 11.110.2 10.7 ND 12b 2 25.610.5 25.4 ND 12b 3 46.4 i 0.5 46.3 ND ! ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on February 26,1992. 92-2 Teledyne Apr,1992 CaSO :Dy l Cards Reader 1, #1 20.1i 0.1 20.1 ND Reader 1, #2 40.6 i 0.1 40.0 ND Reader 1, #3 60.011.3 60.3 , ND Reader 2, #1 20.3 i 0.3 20.1 ND Reader 2, #2 39.2 i 0.3 40.0 ND Reader 2, #3 60.7 i 0.4 60.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne isotopes, Inc., Westwood NJ. on April 1,1992. 93-1 Teledyne Mar,1993 LiF-100 Chips lab 1 10.0 i 1.0 10.2 ND 12b 2 25.5 i 2.2 25.5 ND 12b 3 42.7i 5.7 45.9 ND ND = No Data; Teledyne Testing was only performed by Teledyne. - Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on March 10,1993. Due to a potential error of 10-12% when cards where irradiated, results of the testing on the cards will not be published. Data is available upon request. A2-4
-~ _
l l l , , 1 l Table A-3. In-house " spike" samples. l Concentration in pCi/11 Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits QCMI-26 MILK Jan,1990 i Cs-134 19.3 i 1.0 20.8 10.8 - 30.8 Cs-137 25.2 i 1.2 22.8 12.8 - 32.8 QCMI-27 MILK Feb,1990 Sr-90 18.011.6 18.8 8.8 - 28.8 l QCMI-28 MILK Mar,1990 1-131 63.8 i 2.2 62.6 50.1 - 75.1 QCMI-29 MILK Apr,1990 i Cs-134 18.3 i 1.0 . 19.7 9.7 - 29.7 Cs-137 20.3 i 1.0 18.2 8.2 - 28.2 ! I131 90.7 i 9.2 82.5 66.0 - 99.0 QCW-61 WATER Apr,1990 ! Sr-89 17.915.5 23.1 13.1 - 33.1 Sr-90 19.4 i 2.5 23.5 13.5 - 33.5 QCW-62 WATER Apr,1990 j Co40 8.7 0.4 9.4 0.0 - 19.4 Cs-134 20.0 i 0.2 19.7 9.7 - 29.7 i Cs-137 28.711.4 22.7 12.7 - 32.7 QCW-63 WATER Apr,1990 l I-131 63.5 i 8.0 66.0 52.8 - 79.2 QCW-64 WATER Apr,1990 H-3 1941.0 i 130.0 1826.0 1141.5 - 2510.5 QCW-65 WATER Jun,1990 Ra-226 6.4 1 0.2 6.9 4.8 - 9.0 QCW-66 WATER Jun,1990 Uranium 6.2 0.2 6.0 3.6 - 8.4 QCMI-30 MILK Jul,1990 Cs-134 46.011.3 49.0 39.0 - 59.0 Cs-137 27.611.3 25.3 15.3 - 35.3 Sr-89 12.8 i 0.4 18.4 8.4 - 28.4 Sr-90 18.2114 18.7 8.7 - 28.7 QCW-68 WATER Jul,1990 Gr. Alpha 9.8 i 0.3 10.6 0.6 - 20.6 Gr. Deta 11.4 i 0.6 11.3 1.3 - 21.3 QCMI-31 MILK Aug,1990 I-131 68.811.6 61.4 49.1 - 73.7 l I A3-1 l r- er m-+- 3 n ,- ,-Q ,- wme - 4 4 4 s- e-
Table A-3. In-house " spike" samples. Concentration in pCi/L' l l Lab Sample Date Teledyne Results Known Control' l Code Type Collected Analyses 2s, n=16 Activity Limits QCW-69 WATER Sep,1990 St-89 17.7i 1.6 19.2 9.2 - 29.2 l Sr-90 13.911.6 17.4 7.4 - 27.4 l QC M1-32 MILK Oct,1990 Cs-134 25.811.2 27.3 17.3 - 37.3 Cs-137 25.312.0 22.4 12.4 - 32.4 I-131 34.8 i 0.2 32.4 20.4 - 44.4 QCW-70 WATER Oct,1990 H-3 2355.0 i 59.0 2276.0 1577.3 2974.7 QCW-71 WATER Oct,1990 1-131 55.9 i 0.9 , 51.8 39.8 - 63.8 QCW-73 WATER Oct,1990 Co-60 18.312.7 16.8 6.8 - 26.8 Cs-134 28.3 i 2.3 27.0 17.0 - 37.0 Cs-137 22.7 i 1.3 22.4 12.4 - 32.4 ! QCW-74 WATER Dec,1990 Gr. Alpha 21.4 i 1.0 26.1 13.1 - 39.2 Gr. Beta 25.9 i 1.0 22.3 1P.3 - 32.3 QCMI-33 MILK Jan,1991 Cs-134 22.2 i 1.7 19.6 9.6 - 29.6 Cs-137 26.1 i 1.6 22.3 12.3 - 32.3 St-89 20.7 i 3.3 21.6 11.6 - 31.6 Sr-90 19.011.4 23.0 13.0 - 33.0 QCMI 34 MILK Feb,1991 1-131 40.7i 1.8 40.1 28.1 - 52.1 QCW-75 WATER Mar,1991 Sr-89 18.811.5 23.3 13.3 - 33.3 , QCMI-35 MILK Apr,1991
~
i Cs-134 19.2 i 2.0 22.6 12.6 - 32.6 l Cs-137 22.812.2 22.1 12.1 - 32.1 I-131 48.0 0.8 49.2 37.2 - 61.2 QCW-76 WATER Apr,1991 l I l-131 56.5 i 1.7 59.0 47.2 - 70.8 QCW.77 WATER Apr,1991 1 Co40 16.4 i 2.2 15.7 5.7 - 25.7 l i i A3-2 i
)
l Table A-3. In-house " spike" samples. t l l Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits Cs-134 23.8 i 2.5 22.6 12.6 - 32.6 Cs-137 25.0 i 2.4 21.1 11.1 - 31.1 ! QCW-78 WATER Apr,1991 l H-3 4027.0 i 188.0 4080.0 3264.0 - 4896.0 l QCW.79 WATER Jun,1991 Gr. Alpha 7.4i0.7 7.8 0.0 - 17.8 Gr. Beta 11.010.7 11.0 1.0 - 21.0 SPM-36 MILK Jul,1991 l Cs-137 34.3 i 3.0 35.1 25.1 - 45.1 I-131 14.4 i 1.9 18.3 6.3 - 30.3 Sr-89 28.1 i 2.1 34.0 24.0 - 44.0 St-90 11.610.7 11.5 1.5 - 21.5 QCMI-37 MILK Oct,1991 Cs-134 22.7 i 2.8 22.1 12.1 - 32.1 Cs-137 38.3 i 3.0 35.1 25.1 - 45.1 l I-131 23.6 i 3.2 25.8 13.8 - 37.8 ( QCW-80 WATER Oct,1991 ) St-89 27.4 i 6.9 24.4 14.4 - 34.4 St-90 11.7 i 1.4 14.1 4.1 - 24.1 QCW-81 WATER Oct,1991 1-131 19.110.7 20.6 8.6 - 32.6 I QCW-82 WATER Oct,1991 Co-60 22.6 i 2.7 22.1 12.1 - 32.1 Cs-134 15.511.8 17.6 7.6 - 27.6 Cs-137 ' 17.5 i 2.1 17.6 7.6 - 27.6 l QCW-83 WATER Oct,1991 l 1I-3 4639.0 i 137.0 4382.0 3505.6 - 5258.4 QCW-84 WATER Dec,1991 Gr. Alpha 6.2 i 6.0 7.8 0.0 - 17.8 l Gr. Beta 11.010.7 11.0 1.0 - 21.0 QCMI-39 MILK Jan,1992 - Cs-134 42.1 i 5.7 49.4 39.4 - 59.4 Cs-137 55.216.4 53.0 43.0 - 63.0 1-131 76.8 i 0.9 83.7 67.0 - 100.4 Sr-89 21.616.5 31.2 21.2 - 41.2 St-90 38.711.8 42.3 33.8 - 50.8 A3-3 _ _.~ - .._- . . _ -_ - - , _ . _ _ _--
Table A 3. In-house " spike" samples. Concentration in pCi/11 Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=1 6 ' Activity Limits QCW-85 WATER Mar,1992 Sr-89 26.213.1 32.0 22.0 - 42.0 Sr-90 24.4 i 1.4 28.0 18.0 - 38.0
. QCMI-40 MILK Apr,1992 Cs-134 58.012.6 55.9 45.9 - 65.9 Cs-137 43.7 i 3.0 38.9 28.9 - 48.9 QCMI-41 MILK Apr,1992 1-131 50.3 i 0.8 55.9 44.7 - 67.1 QCW-86 WATER Apr,1992 H-3 4080.0 i 190.0 4027.0 3221.6 - 4832.4 QCW-87 WATER Apr,1992 1-131 33.510.6 33.2 21.2 - 45.2 QCW-88 WATER Apr,1992 Co-60 17.5 i 2.7 19.7 9.7 - 29.7 Cs-134 28.9 i 2.5 33.5 23.5 - 43.5 Cs-137 41.013.0 38.9 28.9 - 48.9 QCW-89 WATER Jun,1992 Gr. Alpha 15.310.8 13.6 3.6 - 23.6 Gr. Beta 17.2 i 0.9 17.6 7.6- 27.6 QCMI-42 MILK Aug,1992 Cs-134 20.112.8 20.2 10.2 - 30.2 l
Cs-137 26.2 i 2.7 26.1 16.1 - 36.1 Sr-89 41.4 i 5.9 51.2 41.0 - 61.4 Sr-90 48.9 i 2.5 51.9 41.5 - 62.3 I 1 QCW-90 WATER Sep,1992 1 Sr-89 6.7 i 3.4 12.6 2.6 - 22.6 Sr-90 16.1 i 1.4 15.6 5.6 - 25.6 QCMI-43 MtLK Oct,1992 Cs-134 14.2 i 3.4 12.7 2.7 - 22.7. Cs-137 14.115.2 17.1 7.1 - 27.1 1-131 19.9 i 1.0 21.5 9.5 - 33.5 QCMI-44 MILK Oct,1992 Cs-134 28.2 i 4.0 25.4 15.4 - 35.4 Cs-137 38.8 i 5.1 34.2 24.2 - 44.2 1-131 36.1 i 1.2 43.0 31.0 - 55.0 l A3-4 1 1l
Table A-3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date Tcledyne Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits QCW-91 WATER Oct,1992 I-131 34.9 t 2.2 34.9 22.9 - 46.9 QCW-92 WATER Oct,1992 Co-60 11.4 i 1.9 9.2 0.0 - 19.2 Cs-134 18.7 i 2.3 14.3 4.3 - 24.3 Cs-137 14.111.8 15.0 5.0 - 25.0 QCW-93 WATER Oct,1992 H-3 3704.0 i 186.0 3904.0 3169.2 - 4638.8 QCW-94 WATER Oct,1992 H-3 14925.0 1 339.0 15616.0 12492.8 - 18739.2 QCW-95 WATER Oct,1992 I-131 64.2 i 2.7 67.2 53.8 - 80.6 QCW-36 WATER Dec,1992 A1pha 11.5 i 2.3 15.2 9.1 - 21.3 Beta 26.5 i 2.0 25.7 15.4 - 36.0 QCW-96 WATER Dec,1992 Gr. Alpha 8.3 i 0.6 10.4 0.4 - 20.4 Cr. Deta 19.8 i 1.5 20.6 10.6 - 30.6 SPM-3341 MILK Jan,1993 Cs-134 17.112.0 21.3 11.3 - 31.3 ! Cs-137 21.4 i 2.0 23.8 13.8 - 33.8 Sr-89 6.7 i 3.1 8.7 0.0 - 18.7 l St-90 20.0 i 1.2 19.2 9.2 - 29.2 SPM-3387 MILK Feb,1993 1-131 72.5 i 8.4 71.5 57.2 - 85.8 SPVE-3401 VEGETATION Feb,1993 ' (SAW DUST) I-131 994.5 i 53.2 953.7 763.0 - 1144.4 ) SPCH-3402 CHARCOAL Feb,1993 1-131 95.2 i 12.8 95.4 76.3 - 114.5 SPW-3434 WATER Apr,1993 Gr. Alpha 10.4 i 1.8 10.4 0.4 - 20.4 Gr. Beta 22.0 i 2.0 20.6 10.6 - 30.6 SPW-3556 WATER Apr,1993 Sr-89 18.2 i 5.0 22.2 12.2 - 32.2 Sr-90 20.1 i 1.8 17.0 7.0 - 27.0 A3-5 I --. - .--
Table A-3. In-house " spike" sarnples. Concentration in pCi/If Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=1 6 _ Activity Limits SPW 3597 WATER Apt,1993 H-3 5464.0 i 219.0 5428.0 4342.4 - 6513.6 SPW-3599 WATER Apr,1993 1-131 149.8 i 1.9 145.0 116.0 - 174.0 SPW-3606 WATER Apr,1993 Co-60 24.8 i 2.3 21.5 11.5 - 31.5 Cs-134 26.4 i 1.9 26.4 16.4 - 36.4 Cs-137 33.912.6 31.7 21.7 - 41.7 SPM-3631 MILK Apr,1993 Cs-.134 48.812.9 52.8 42.8 - 62.8 Cs-137 65.2 i 2.9 63.4 53.4 - 73.4 I-131 139.8 i 1.6 145.0 116.0 - 174.0 SPP-3681 FISH May,1993 (JELLO) Cs-137 68.217.7 67.6 57.6 77.6 Concentrations are in pCi/ Total Volume (550g). SPW-3842 WATER Jun,1993 Th-230 4.210.5 4.5 2.7 - 6.3 SPW-4160 WATER Jun,1993 Alpha 8.911.4 12.9 7.7 - 18.1 Beta 22.0 i 1.9 31.9 19.1 - 44.7 SPW-4232 WATER Aug,1993 Pe-55 1684.0 1 415.0 1420.0 1136.0 - 1704.0 SFW-4246 WATER Aug,1993 Sr-90 32.2 i 2.6 30.4 24.3 - 36.5 SPM-4247 MILK Aug,1993 Sr-89 29.1 i 4.9 35.4 25.4 - 45.4 St-90 18.3 i 1.3 19.2 9.2 - 29.2 SPW-4248 WATER Aug,1993 H-3 9910.0 t 300.0 10430.0 8344.0 - 12516.0 SPW-4250 WATER Aug,1993 Co-60 247.0 t 23.1 247.7 222.9 - 272.5 Cs-134 141/ 1 15.9 141.1 127.0 - 155.2 - l l i A3-6 1
Table A-3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=1' Activity Limits 1 Cs-137 283.5 i 27.8 247.2 222.5 - 271.9 l The cause of the high Cs 137 data is unknown. All data was l reviewed, no errors where found in the calculations. The I employee was observed performing this analysis and no l deviations from the procedure where observed. The employce's results have been good in the past; no further action is planned. I SPF-4251 FISH GELLO) Aug,1993 Cs-134 68.8 i 3.3 75.3 65.3 - 85.3 Cs-137 203.6 i 8.2 198.1 178.3 - 217.9 SPS-4262 SEDIMENT Aug,1993 (BOTTOM) Cs-134 74.1 i 9.9 71.0 61.0 81.0 Cs-137 212.4 i 14.8 197.8 178.0 - 217.6 l SPW-4377 WATER Sep,1993 l 1 1-131 39.0110.0 42.1 30.1 - 54.1 SPM-4378 MILK Sep,1993 l 1131 44.5 i 5.5 42.1 30.1 - 54.1 SPCII-4379 CHARCOAL Sep,1993 1-131 90.3 i 13.5 84.3 67.4 - 101.2 j SPVE-4380 VEGETATION Sep,1993
. (SAW DUST) "
1-131 193.2 1 20.0 170.2 136.2 - 204.2 SPW-4381 WATER Sep,1993 l Sr-89 21.914.0 28.8 18.8 - 38.8 Sr 90 19.511.8 19.0 9.0 - 29.0 l SPW-4382 WATER Sep,1993 1-129 18.1 i 1.0 18.6 6.6 - 30.6 SPW-4421 WATER Oct,1993 H3 16900.0 1 368.0 17380.0 13904.0 - 20856.0 SPW-4428 WATER Oct,1993 C&40 19.3 i 3.1 18.3 8.3 - 28.3 Cs-134 31.513.3 33.5 23.5 - 43.5 Cs-137 44.4 i 3.6 43.2 33.2 - 53.2 SPM-4426 MILK Oct,1993 Cs-134 30.8 i 4.5 33.0 23.0 - 43.0 Cs-137 43.4 i 6.0 43.2 33.2 - 53.2 1-131 49.718.6 44.5 32.5 - 56.5 A3-7
l l . l Table A 3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=16 Activity Limits SPW-4427 WATER Oct,1993 1-131 95.2110.6 88.9 71.1 106.7
- All results are in pCi/L, except elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/ Filter; charcoal which are in pCi/ charcoal; and food products which are in mg/kg.
- All samples prior to January 1991 are the results or three determinations; after January 1991, all determinations are single.
- Control Limits are based on EPA publication;" Environmental Radioactive Laboratory Intercomparison l
Studies Program", Fiscal Year 1981-1982, EPA-600/4-81-004 (see Attachment .A) or limits imposed by Teledyne's Midwest Laboratory. I i l l l l e A3-8
l Table A-4. In-house " blank" samples. l l Concentration pCi/L*. Teledyne Results Acceptance j lab Sample Sample (4.66 Sigma) Criteria j Code Type Date Analyses LLD Activitv6 (4.66 Sigma) SPW-8039 WATER Jan 1990 Ra-226 < 0.2 < 1.0 SPM-8040 MILK Jan 1990 fr-89 < 0.8 < 5.0 Si-90 < 1.0 < 1.0 j SPM-8208 MILK Jan 1990 Cs-134 < 3.6 < 10.0 Cs-137 < 4.7 < 10.0 Sr-89 < 0.8 < 5.0 Sr-90 N/A 1.6 1 0.5 < 1.0 ! Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusuat l SPM-8312 MILK Feb l990 Sr-89 < 0.3 < 5.0 Sr-90 N/A 1.210.3 < 1.0 Low level of St-90 concentration in milk (1-5 pCi/L) is not unusual. SPW-8312 WATER Feb 1990 Sr-89 < 0.6 < 5.0 Sr-90 < 0.7 < 1.0 SPM-8314 MILK Mar 1990 1-131 < 0.3 < 1.0 SPM-8510 MILK May 1990 Cs-134 < 4.6 < 10.0 Cs-137 < 4.8 < 10.0 1-131 < 0.2 < 1.0 SPW-8511 WATER May 1990 l H-3 < 200.0 < 300.0 SPM-8600 MILK Jul 1990 , Cs-134 < 5.0 < 10.0 t ! Cs-137 < 7.0 < 10.0 l 1-131 < 0.3 < 1.0 Sr-89 < 0.8 < 5.0 Sr-90 N/A 1.7 1 0.6 < 1.0 Low level of Sr-90 concentration in milk (15 pCi/L)is not unusual. A41
Table A-4. In-house " blank" samples. l l Concentration pCi/L*, Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Tvoe Date Analyses LLD Activity b (4.66 Sigma) SPM-8877 MILK Aug 1W0 , I131
< 0.2 <1.0 SPW-8925 WATER Aug 1990 H-3 < 200.0 < 300.0 SPW-8926 WATER Aug 1990 Gr. Alpha < 0.3 < 1.0 Gr. Beta < 0.7 < 5.0 SPW-8927 WATER Aug 1990 U-234 < 0.01 < 1.0 U-235 < 0.02 <1.0 U-238 < 0.01 < 1.0 SPW-8928 WATER Aug 1990 Co-58 < 4.1 < 10.0 Co-60 < 2.4 < 10.0 Cs-134 < 3.3 < 10.0 Cs-137 < 3.7 < 10.0 Mn-M < 4.0 < 10.0 SPW-8929 WATER Aug 1990 Sr-89 < 1.4 < 5.0 Sr-90 < 0.6 < 1.0 SPW-69 WATER Sep 1990 Sr-89 < 1.8 <5.0 Sr-90 < 0.8 < 1.0 SPW-106 WATER Oct 1990 H-3 < 180.0 < 300.0 1-131 < 0.3 < 1.0 SPM-107 MILK Oct 1990 Cs-134 < 3.3 < 10.0 Cs-137 < 4.3 < 10.0 1-121 < 0.4 < 1.0 SPW-370 WATER Oct 1990 Co-58 < 2.6 < 10.0 Co-60 < 1.6 < 10.0 Cs-134 < 1.7 < 10.0 Cs-137 <1.8 < 10.0 A4-2
Table A-4. In house " blank" samples. Concentration pCi/L*. [ Tcledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Code Criteria Type Date Analyses LLD Activitvb (4.66 Sigma) Mn41 < 1.7 < 10.0 SPW-372 WATER Dec 1990 Gr. Alpha < 0.3 < 1.0 Gr. Beta < 0.8 <5.0 SPM-406 MILK Jan 1991 Cs-134 < 3.7
< 10.0 Cs-137 <5.2 < 10.0 Sr-89 < 0.4 < 5.0 Sr-90 N/A 1.8 i 0.4 < 1.0 Low level of St-90 concentration in milk (1-5 pCi/L) is not unusual.
SPM-421 MILK Feb l991 1-131 < 0.3 < 1.0 SPM-451 MILK Feb 1991 Ra-226 < 0.1
< 1.0 Ra-228 < C.9
< 1.0 SPW-514 WATER Mar 1991 St-89 < 1.1
< 5.0 Sr-90 < 0.9
<1.0 SPW-586 WATER Apr 1991 Co-60 < 2.5 -
< 10.0 Cs-134 < 2.4
< 10.0 Cs-137 < 2.2
< 10.0 1-131 < 0.2
< 1.0 SPM-587 MILK Apr 1991 Cs-134 < 1.7
< 10.0 Cs-137 < 1.9
< 10.0 1-131 < 0.2 < 1.0 SPW-837 WATER Jun 1991 Gr. Alpha < 0.6
< 1.0 Gr. Beta < 1.1
< 5.0 SPM-953 MILK Jul1991 Cs-137 <4.9 < 10.0 I-131 <0.2 <1.0 Sr.89 < 0.7
< 5.0 A4-3
Table A-4. In-house " blank" samples. 4 Concentration pCi/L'. Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Tvoe Date Analyses LLD Activitv6 (4.66 Sigma) Sr-90 N/A 0.4 i O.3 < 1.0 Low level of Sr 90 concentration in milk (1-5 pCi/L)is not unusual. SPM-1236 MILK Oct 1991 Cs-134 < 3.7 < 10.0 Cs-137 <4.6 < 10.0 i I-131 < 0.2 < 1.0 SPW-1254 WATER Oct 1991 Sr-89
< 2.8 < 5.0 Sr90 < 0.7 < 1.0 SPW-1256 WATER Oct 1991 Co-60 < 3.6 < 10.0 Cs-134 < 4.0 < 10.0 Cs-137 < 3.0 < 10.0 I-131 < 0.4 < 1.0 7PW-1259 WATER Oct 1991 H-3 < 160.0 < 300.0 SPW-1444 WATER Dec 1991 Gr. Alpha < 0.4 < 1.0 Gr. Beta < 0.8 < 5.0 SPM-1578 MILK Jan 1992 i
Cs-134 <72 < 10.0 Cs-137 < 8.0 < 10.0
- 1-131 < 0.2 < 1.0 Sr-89 < 0.5 < 5.0 Sr-90 N/A 1.310.4 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L)is not unusual.
SPW-1860 WATER Mar 1992 Sr-89 < 0.6 < 5.0 St-90 < 0.4 < 1.0 SPW-2067 WATER Apr 1992 II-3 < 168.0 < 300.0 SPW-2114 WATER Apr 1992 C-14 < 1.0 < 200.0 A4-4
\ O 4 Table A-4. In-house " blank" samples. Concentration pCi/L'.
. Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analyses LLD Activityb (4.66 Sigma)
SPM-2119 MILK Apr 1992 Co-60 < 6.3 < 10.0 Cs-134 < 4.5 < 10.0 Cs-137 <5.4 < 10.0 SPW-2126 WATER Apr 1992 I-131 <0.2 < 1.0 SPM-2133 MILK Apr 1992 1-131 < 0.2 < 1.0 SPW-2220 WATER May 1992 Co-60 < 2.1 < 10.0 l Cs-134 < 2.1 < 10.0 Cs-137 < 2.3 < 10.0 ; SPW 2369 WATER Jun 1992 l Gr. Alpha < 0.4 <1.0 Gr. Beta < 0.8 <5.0 SPM-2500 MILK Aug 1992 I-131 < 0.4 < 1.0 Sr-89 <1.2 < 5.0 1 St-90 < 0.9 < 1.0 SPW-2666 WATER Sep 1992 ! Sr-89 <0.8 <5.0 Sr90 < 0.5 <1.0 SPW-2828 WATER Oct 1992 Co40 <4.8 < 10.0 Activity result is not available for this sample. Cs-134 < 6.0 < 10.0 Activity result is not available for this sample. Cs-137 < 6.1 < 10.0 Activity result is not available for this sample. H-3 < 177.0 < 300.0 I-131 <0.3 < 1.0 Activity result is not available for this sample. SPM-2829 MILK Oct 1992 Co-60 <9.3 < 10.0 Cs-134 <6.4 < 10.0 Cs-137 < 7.2 l
< 10.0 l
A4-5
l Table A-4. In-house " blank" samples. Concentration pCi/L*. Tcledyne Results Acceptance Lab Sample Sample . (4.66 Sigma) Criteria Code Type Date Analyses I.LD Activityb (4.66 Sigma) SPW-3212 WATER Oct 1992 Ra-228 < 1.0 < 1.0 SPW 3057 WATER Nov 1992 Ra-226 < 0.03 < 1.0 SPW-3294 WATER Dec 1992 Gr. Alpha < 0.4 < 1.0 Gr. Beta < 0.8 < 5.0 SPM-3342 MILK Jan 1993 Cs-134 <4.1 -0.9 i 2.6 < 10.0 Activity result is not available for this sample. Cs-137 < 3.9 0.812.2 < 10.0 Activity result is not available.for this sample. Sr-89 < 0.7 -0.911.1 < 5.0 Sr-90 N/A 1.6 i 0.5 < 1.0 i Low levels of Sr-90 concentration in milk (1-5 pCi/L) is not l unusual. SPM-3386 M1LK Feb 1993 I-131 < 0.2 0.1 i0.1 < 1.0 SPW-3557 WATER Mar 1993 St-89 < 0.5 0.310.5 < 5.0 Sr-90 < 0.5 0.1 i 0.2 < 1.0 ! SPW-3598 WATER Apr 1993 H-3 < 180.0 84.7194.2 < 300.0 SPW-3600 WATER Apr 1993 I-131 < 0.2 0.1 i 0.2 < 1.0 SPW-3601 WATER Apr 1993
- Co-60 <4.2 < 10.0 Activity result is not available for this sample.
Cs-134 < 4.4 < 10.0 Activity result is not available'for this sample. Cs-137 < 3.4 < 10.0 Activity result is not available for this sample. 1-131 < 0.4 0.310.9
< 1.0 SPM-3651 MILK May 1993 Cs-134 < 4.4 < 10.0 Activity result is not available for this sample, l
A4-6 i
3 Table A-4. In house " blank" samples. Concentration pCi/lf.
, Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Ccde Tyne Date Analyses LLD Activitv6 (4.66 Sigma)
Cs-137 < 6.3 < 10.0 Activity result is not available for this sample. 1-131 < 0.2 0.1 i 0.1 < 1.0 SPFP 3680 FOOD May 1993 Cs-137 <6.5 0.010.0 < '10.0 SPW-3844 WATER Jun 1993 Th-228 < 0.1 0.0 1 0.1 < 1.0 Th-230 <0.1 0.2 i 0.1 < 1.0 Th-232 <0.1 0.0 i 0.0 < 1.0 SPW-4234 WATER Jun 1993 Gr. Alpha < 0.3 0.010.2 < 1.0 i Gr. Beta <0.8 0.2 i 0.3 < 5.0 SPS-4059 SEDIMENT Jul1993 i (BOTTOM) j Cs-134 < S.0 0.0 1 0.0 < 10.0 i Cs-137 < 7.2 0.010.0 < 10.0
- SPVE-4060 VEGETATION Jul1993 (SAW DUST)
- Cs-134 <4.8 0.0 i 0.0 < 10.0 Cs 137 <6.4 0.010.0 < 10.0 1-131(g) < 13.5 0.0 1 0.0 < 20.0 i
SPM-4061 MILK Jul1993 Cs-134 <8.6 0.0 1 0.0 < 10.0 r C3-137 < 5.8 0.0 i 0.0 < 10.0 SPM-4062 MILK Jul 1993 Cs-134 < 3.8 1.5 i 1.5 1 < 10.0 q Cs-137 < 4.4 -1.613.3 < 10.0 SPW-4063 WATER Jul 1993 Co-60 <4.0 1.2 12.3
< 10.0 Cs-1M < 3.7 0.3 i l.2 < 10.0 Cs-137 <3.2 0.4 i 3.2 < 10.0 SPAP-4064 AIR FILTER Jul 1993 (COMPOSITE)
Cs-134 <2.1 0.0 1 0.0 < 10.0 Cs-137 <2.8 0.0 1 0.0 < 10.0 A4-7 .
.e , . . . . . . . , , . _ _ . - . . . , , , , , ,%.. ,._ . -
l l l Table A-4. In-house " blank" samples. ! l i Concentration pCi/L*. ! l Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Analyses Code Type Date LLD Activitv6 (4.66 Sigma) ' SPCH-406 CHARCOAL Jul1993 I131 < 0.1 0.0 1 0.0 < 1.0 Based on a volume of 300 m8 SPW-4233 WATER Aug 1993 Fe-55 < 506.0 0.0 i 0.3 < 1000.0 l i SPM-4235 MILK Aug 1993 i Cs-134 < 8.1' 1.6 i1.8 < 10.0 Cs-137 < 4.2 -1.7 i 3.4 < 10.0 1-131 < 0.1 0.0 1 0.2 < 1.0 St-89 < 0.8 -1.0 i 1.1 < 5.0 Sr-90 N/A 1.8 i 0.5 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L)is not unusual. SPW-4241 WATER Aug 1993 H-3 < 190.0 72.9 i 99.1 < 300.0 SPW-4243 WATER Aug 1993 , Co-60 < 7.0 0.413.1 < 10.0 l 2 Cs-134 < 7.6 0.8115.6 < 10.0 1 l Cs-137 <5.4 -0.7 i 4.2 < 10.0 ' l I-131 <0.5 0.0 i 0.1 < 1.0 4 Sr89 <1.1 -0.6 i 0.9 < 5.0 Sr-90 < 0.7 0.4 1 0.4 < 1.0 l SPW-4244 WATER Aug 1993 1 Pu-238 <1.0 0.410.7 < 1.0 s Pu-239/240 < 0.3 0.1 1 0.2 < 1.0 ~ Th-228 < 0.4 -0.1 i 0.3 < 1.0 Th-230 < 0.1 0.0 1 0.1 < 1.0 Th-232 < 0.1 0.0 1 0.0 < 1.0 U-233/234 < 0.1 0.1 i 0.1 < 1.0 U-235 < 0.1 0.0 1 0.1 < 1.0 U-238 < 0.1 0.1 1 0.1 < 1.0 SPW-4245 WATER Aug1993 * , Ra-226 < 0.1 0.0 1 0.0 < 1.0 Ra-228 < 0.8 -0.210.5 < 1.0 SPW-4422 WATER Oct 1993 H-3 < 180.0 -27.5 i 88.9 < 300.0 A4-8
4 Table A 4, In-house " blank" samples. Concentration pCi/L*. Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analyses LLD Activitv6 (4.66 Sigma) 6 All results are in pCi/L, except for air filter samples, which are in pCi/ Filter. Prior to 1993, results where reported as only an LLD, the activity reported is the net activity result. II I i 4 A4-9
l, I December,1993 ATTACHMENT _A ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES l LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' Analysis One Standard Deviation Level for single determinations Camma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium-896 5 to 50 pCi/ liter or kg 5.0 pCi/ liter
>50 pCi/ liter or kg 10% of known value Strontium-906 2 to 30 pCi/ liter or kg 5.0 pCi/ liter
>30 pCi/ liter or kg 10% of known value Potassium >0.1 g/ liter or kg 5% of known value l Gross alpha s20 pCi/ liter 5.0 pCi/ liter
>20 pCi/ liter 25% of known value <
l Cross beta s100 pCi/ liter 5.0 pCi/ liter
>100 pCi/ liter ;
5% of known value Tritium s4,000 pCi/ liter is = (pCi/ liter) = ,
>4,000 pCi/ liter 169.85 x (known)**2' l 10% of known value Radium-226,-228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value lodine-131, s55 pCi/ liter 6.0 pCi/ liter lodine-1296 >55 pCi/ liter 10% of known value Uranium-238, s35 pCi/ liter l 6.0 pCi/ liter Nickel-64 >35 pCi/ liter 15% of known value Technetium-996 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
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]
i l J I i d 1 j APPENDIX B 1 1 DATA REPORTING CONVENTIONS I s 6 i i N ? k l 1 d l, a 4 ( i 4 Y i a a B-1 4 4 i __--___m_ .___..,y. , . , , . , ,. . ,, ..m...y, _.- ,,.e._...,yy_,,. .7 ,-,..c- c - - . , ,
1 . *e , 1 Data Reporting Conventions I 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 l Each single measurement is reported as follows: l xis l where x = value of the measurement; I 1 s = 2a counting uncertainty (corresponding to the 95% confidence ! level). 1 In cases where the activity is found to be below the lower limit of detection L l it is reported as
<L i where L = the lower limit of detection based on 4.66a uncertainty for a background sample.
3.0 Duplicate analyses 3.1 Individual results: x1 1st x1 i s2 l l Reported result: x s where x = (1/2) (xi x2)
, ,~
s = (1/2) s{ + s2 3.2 Individual results: <L1
<L2 Reported result: <L where L = lower of L1 and L2 3.3 Individual results: xis
<L Reoorted result: x i s if x 2 L;
<L otherwise B-2
. 1 1
~ l l l 4.0. Computation 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 l example, an annual standard deviation would not be the average of l quarterly standard deviations. The average R and standard deviation (s) l of a set of n numbers x1, x2. . . xn are defined as follows: j i 1 l R=n Ex I(x - x,)* s= 1 n-1 l 4.2 Values below the highest lower limit of detection are not included in i 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. ; l 4.5.2. If the figure following those to be retained is greater than 5, the I figure is dropped and the last retained figure is raised by 1. As an example,11.446 is rounded off to 11.45. i l 4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure five is dropped, and the last-place figure retained is increased by one if it is an odd number or it is kept unchanged if an even number. As an example,11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42. B-3
O j . -, , 1 i a 1 APPENDIX C l i
- During the reporting period, the radioactivity of the primary coolant did not exceed the limits of Technical Specification 2.1.3.
4 1
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