ML20247M591
| ML20247M591 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/31/1988 |
| From: | Deal W, Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8906050076 | |
| Download: ML20247M591 (912) | |
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- DUKE POWER GoMPAxy P,0, Dox 33180 CHARLOTTE, N.O. 28242 IIALILTUCKEH TELEPitONE
- vms rer.manent (7o4) 073-4531 Nt%LEAm PSUDUUTION 1
May 31, 1989 f Document Control Desk .
l '
U. S. Nuclear Regulatory Commission Washington, D. C.' 20555
Subject:
. Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Annual Radiological Environmental Operating Report Gentlemen: ,
1 Purs.uant to Catawba Nuclear Station Technical Specification 6.9.1.6, please find attached the Annual Radiological Environmental Operating Report covering the operation of Units 1 and 2 during the 1988 calendar year. Submittal of this report was delayed per my April 27, 1989 letter to the NRC Document Control Desk.
Very truly yours, e
jfV H. B. Tucker Attachment JGT/3/AREOR !
xc: (w/o Appendix E)
Mr. S. D. Ebneter, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 2 25 Mr. W. T. Orders ,,
NRC Resident Inspector Catawba Nuclear Station 8906050076'881231 PDR ADOCK 05000413 R PDC
.May 23,.1989
_74 -
kj' INTRASTATION LETTER CATAWBA NUCLEAR STATION TO:n+ICT Glohr 'I vasu,: .,
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SUBJECT:
Catawba Nuclear Station Annual Radiological Environmental Operating Report for 1988 File: CN-778.05 Pursuant'to Administrative Control 6.9.1.6 of Catawba Nuclear Station Technical Specifications, the subject report has been completed and enclosed. This report is normally required to be submitted to the Nuclear' Regulatory Commission prior to May 1, 1989. A letter from Mr. Tucker dated April 28, 1989 has been sent to the NRC stating that this report will be submitted on May 31, 1989.
Please forward this report to appropriate General Office personnel for transmittal to the NRC.
U.PL//sra W. P. Deal /
. Radiation Protection Manager BMC/slj cc: J. S. Forbes w/o Appendix E of Attachment R. M. Glover w/o Appendix E of Attachment M. L. Birch w/o Appendix E of Attachment M. D. Lane w/o Appendix E of Attachment P. G. LeRoy w/o Appendix E of Attachment F J. M. Stewart w/o Appendix E of Attachment t Attachment l
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J ANNUAL. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY:
CATAWBA NUCLEAR STATION UNITS 1 AND 2 v
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JANUARY 1, 1988 - DECEMBER 31, 1988 LO
TABLE OF CONTENTS 4 ; l]
SECTION 1 JEXECUTIVE
SUMMARY
SECTION 2 ' INTRODUCTION PART 2.1 Site Description and Sample Locations PART 2.2 Scope and Requirements of the Environmental Monitoring Program.
PART 2.3 Statistical and Calculational Methodology 2.3.1- Estimation of the Mean Value 2.3.2 Lower Limit'of Detection and Minimum Detectable Activity
. TABLE 2.A' Catawba Radiological Monitoring Program Sampling' Locations
.(TLD Locations)
TABLE 2.B Catawba Radiological Monitoring Program Sampling Locations (Other Sampling Locations)
FIGURE 2.C Map of. Radiological Monitoring Program Sampling Locations (Near to Catawba)
FIGURE 2.D Map of Radiological Monitoring Program Sampling Locations (Distant from Catawba)
FIGURE 2.E Map of Radiological Monitoring Program Sampling Locations (Location 208 Shoreline and Bottom Sediment Sampling Points)
SECTION 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - DISCUSSION, INTERPRETATION, AND TRENDING OF RESULTS PART 3.1 Airborne Radioiodines and Particulate i
3.1.1 Radioiodines 3.1.2 Particulate PART 3.2 Ground Water l
PART 3.3 Drinking Water
[ PART 3.4 Surface Water PART 3.5 Milk O
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TABLE OF CONTENTS
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PART 3.6 .Broadleaf Vegetation PART 3.7 Shoreline Sediment PART 3.8 Fish PART-3.9 Direct Gamma Radiation '(TLD)
PART 3.10 Land Use Census PART 3.11 Bottom Sediment TABLE 3.A' 1988 Catawba' Annual Land Use Census Results TABLE 3.B 1988 Maximum Calendar Quarter Average Percent of Reporting Levels TABLE 3.C- Radionuclides Detected During 1988 and not Listed in Technical Specifications TABLE 3.D Fraction and Percent of 1988 Nuclide Measurements Yielding Detectable Activity TABLE 3.E Fraction and Percent of 1987 Nuclide Measurements Yielding Detectable Activity TABLE 3.F Fraction and Percent of 1984 Nuclide Measurements Yielding Detectable Activity SECTION 4 EVALUATION OF DOSE FROM ENVIRONMENTAL MEASUREMENTS VERSUS ESTIMATED DOSE FROM RELEASES PART 4.1 Dose from Environmental Measurements PART 4.2 Estimated Dose fcom Releases PART 4.3 Comparison of Doses
. TABLE 4.A Dose Estimates Based on 1988 Environmental Airborne Particulate Sample Results.
TABLE 4.B Dose Estimates Based on 1988 Environmental Drinking Water Sample Results TABLE 4.C Dose Estimates Based on 1988 Environmental Milk Sample Results TABLE 4.D Dose Estimates Based on 1988 Environmental Broadleaf Vegetation Sample Results ii l L - - _ - - -- - - - . - . _ . - . _ - . - . - . - - - - _ - - _ - - _ _ - - - - - - - - _ - - - _ - - - _ _ _ - - _ - _ _ _ _ - - - _ _ _ _ _ _ _ _ _ - - - - _ _ - - - _ _ _ _ _ _ _
TABLE OF CONTENTS TABLE 4.E Dose Estimates Based on 1988 Environmental Shoreline Sediment Sample Results TABLE 4.F Dose Estimates Based on 1988 Environmental Fish Sample Results TABLE 4.G Dose Estimates Based on Limiting 1988 Environmental Sample Results TABLE 4.H 1988 Environmental and Effluent Dose Comparison for Liquid Release Pathways TABLE 4.I 1988 Environmental and Effluent Dose Comparison for Gaseous Release Pathways SECTION 5 QUALITY ASSURANCE PART 5.1 Duke Power Company's Environmental Laboratory l PART 5.2 Contractor Laboratory PART 5.3 EPA Interlaboratory Comparison Program PART 5.4 Duke Power Company's Dosimetry Laboratory SECTION 6 REFERENCES APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PRCGRAM
SUMMARY
OF ANALYSIS RESULTS APPENDIX C SAMPLING DEVIATIONS APPENDIX D ANALYTICAL DEVIATIONS APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANALYSIS RESULTS i 4 I 1 7'N i 111 l
SECTION 1 EXECUTIVE
SUMMARY
This Annual Radiological Environmental Operating Report describes the > Catawba Nuclear Station Radiological Environmental Monitoring Program and the results of the program for the 1988 calendar year. Included in the report are identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and preoperational environmental data, analysis of trends in environmental radioactivity levels, comparisons of doses calculated from environmental measurements and doses calculated from effluent data, all analysis results for the 1988 program, a summary of these results, discussion of the results, discussion of the quality assurance activities associated with the program, and identification of all deviations from program requirements. Sampling activities were conducted as prescribed by Technical Specifications. Required sample analyses were performed and detection capabilities met Technical Specification requirements for all samples except one. Radioactivity clearly attributable to the operation of Catawba was detected in the following media, all at the discharge canal: Surface water: H-3 increasing
/\ Fish: Co-58 increasing \- / Co-60 increasing Cs-137 increasing Shoreline Sediment: Mn-54 steady Co-58 steady Co-60 increasing Cs-134 steady Cs-137 steady Bottom Sediment: Mn-54 steady Co-58 steady Co-60 steady Cs-134 steady Cs-137 steady No other significant trends regarding environmental radioactivity levels were evident in the sampling results.
Dose estimates based on environmental measurements and estimates calculated i using effluent release data were compared. The estimates consistently agreed well. l Catawba's contribution to environmental radioactivity is small. All positive l indications of radioactivity due to plant operations were less than the 1 reporting levels imposed by Technical Specifications. Operation of the O Station has had no significant radiological impact upon the health and safety of the general public. 1-1 ! I
4 I l 1 SECTION 2 g) i v INTRODUCTION , l i { l 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS { 4 Duke Power Company's Catawba Nuclear Station (CNS) is a two-unit facility located on the shore of Lake Wylie in York County, South ] 1 Carolina. Each of the two essentially identical units employs a I pressurized water reactor Nuclear Steam Supply System furnished by Westinghouse Electric Corporation. Each generating unit is designed to produce a net electrical output of approximately 1145 MWe. Units , 1 and 2 achieved initial criticality on January 7, 1985 and May 8, 1986, respectively. Condenser cooling is accomplished utilizing a closed cycle system i
~ incorporating cooling towers, instead of utilizing lake water directly. ,
Liquid effluents are released into Lake Wylie via the station discharge l
' canal, and are not accompanied by the large additional dilution water I flow associated with "once-through" condenser cooling. This design i' difference results in greater radionuclides concentrations in the discharge canal given comparable liquid effluent source terms.
A map depicting the site and the area Oithin one mile of CNS can be found in Figure 2.C. An area map encompassing a ten mile radius from the plant can be found in Figure 2.D. The CNS Radiological Environmental Monitoring Program (REMP) sampling locations are summarized in Tables 2.A and 2.B. Table 2. A lists the environmental Thermoluminescent Dosimeter (TLD) locations. Table 2.B lists all other sampling locations. The REMP sampling and analysis procedures are summarized in Appendix A. Figures 2.C, 2.D, and 2.E are maps depicting the specific positions of all REMP sampling locations. The location numbers shown on these maps correspond to those listed in Tables 2.A and 2.B. Figure 2.C comprises all sample locations within one mile of CNS. Figure 2.D comprises all remaining locations. Figure 2.E identifies Location 208 (Discharge Canal) shoreline sediment (IS, 2S, and 3S) and bottom sediment (1M, 2M, and 3M) sampling points. Of these six sediment samples, only shoreline sediment at location 208-15 is required by CNS Technical Specifications; the remaining five are supplemental samples first collected during 1986. l O 2-1
2.2 SCOPE AND REQUIREMENTS OF THE ENVIRONMENTAL MONITORING PROGRAM (3 1 (') The Radiological Environmental Monitoring Program required by CNS Technical Specification 3/4.12.1 provides representative measurements j of radiation and radioactive materials in those exposure pathways j and for those radionuclides that lead to the highest potential radiation i exposures of members of the public resulting from plant operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of effluent measurements and modeling of environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental l Monitoring. The Annual Land Use Census required by CNS Technical Specification 3/4.12.2 is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if ! required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. The results of this census are required to be included in this Annual Radiological Environmental Operating Report by Technical Specification Administrative Control 6.9.1.6. Participation in an approved Interlaboratory Comparison Program as required by CNS Technical Specification 3/4.12.3 provides for independent (V'n checks on the precision and accuracy of REMF environmental radionuclides measurements. Such checks shall be performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. This Annual Radiological Environmental Operating Report is required by CNS Technical Specification Administrative Control 6.9.1.6. This report adheres to the content specifications of Control 6.9.1.6. CNS Technical Specification 3.12.1 (Table 3.12-1) specifies the conduct of the Radiological Environmental Mon'.toring Program. The Duke Power Company Offsite Dose Calculation Manual further defines the specific types, frequencies, and locations of sampling and measurement. Technical Specification Table 3.12-2 provides reporting levels, as a function of sample type and radionuclides. If sample radionuclides activity exceeds 100% of reporting level (when summed over all detected nuclides having a reporting level for the applicable sample type, and when the sums are averaged by location over the applicabic calendar quarter) a special report must be submitted to the Nuclear Regulatory Commission. When radionuclides other than those listed in Table 3.12-2 are detected, they shall be addressed in this annual report. l Not all radionuclides have a reporting level for a given sample type. (q j For example, there are no reporting levels for gross beta analysis of any sample type, and sediment samples have no reporting levels for any radionuclides. ! 2-2 f
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' Technic'al.' Specification Table 4.12-1 lists required Lower Limit of
.yy 41. Detection (LLD) capabilities for REMPl sample analyses, as a function i
t of sample typesand radionuclides. ' Refer to Section 2.3.2 for the definition of LLD and Minimum Detectable Activity (MDA). .Not all radionuclides have a required LLD for a given sample type. Any analyses
- i. for which the required LLDs were not achievable shall be discussed' in this annual report.
1 Technical. Specification. Tables 3.12-2 and 4.12-1 list thirteen radionuclides; H-3,!Ma-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb_-95, I-131,-Cs-134,. Cs-137, Ba-140,'and La-140. These thirteen radionuclides are collectively.
, referred.to throughout this annual report as " Radionuclides' Listed-in Technical Specifications".;
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. 2;3 STdTISTICALAND..CALCULATIONALMETHODOLOGY r 4
- .. 2.3.1' ' ESTIMATION'0F THE MEAN VALUE-There was one (1) basic statistical calculation performed.on'the raw data resulting from the environmental sample analysis l program. The calculation involved .the determination of the mean .l value for the . indicator and the control samples for. each' sample j medium. The mean (x) is a widely used statistic. This value was Jused .in the reduction of .the data generated by- the sampling and !
analysis of the .various media in the Environmental Monitoring j Program. The following equation was used to estimate the mean: 1 N: 4 r I x i = 1y (eq. 2-1). x = --------------- N Lwhere, i =. estimate of the.mean,. l K- -i = individual sample, N = total. number of samples.with a net activity (or concentration), Lxj = net activity (or concentration) for sample i. NOTE: " Net activity (or concentration)" is the activity .(or ! concentration) determined to be present in the sample. . No
- 1
" Minimum : Detectable Activity, " Lower Limit of Detection",
"Less Than Level", or negative activities or concentrations are included in the calculation of the mean.
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' 2. 3; 2" LOWER LEVEL OF_ DETECTION ~ AND MINIMIM DETECTABLE ACTIVITY h The Lower . Level of Detection -(LLD) and . Minimum Detectable Activity (MDA) are used throughout the Environmental Monitoring Program,' both in the Technical Specifications and in the implementation of the specifications.
The LLD, as defined in the Technical Specifications, is the smallest concentration of radioactive material in' a sample that will -yield a net count, above~ system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank _ observation represents a~ "real" signal. The LLD is.an a priorilower limit of detection. The actual LLD is dependent upon the standard deviation . of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield,' and the radioactive decay of? the sample between sample collection and counting. The " required" LLD's for.each sample medium and selected radionuclides'are given in the Technical Specifications. l The MDA may be thought of as an " actual" LLD for a 'particular - sample ' measurement remembering that the MDA is calculated 'using a sample background instead 'of a. system background.' In ~ gamma
, spectroscopy analyses, the sample background may be elevated above the ' system background due to the continuum produced by: higher
- energy gammas from other radionuclides (either man-made or' naturally produced). The continuum increases the smallest concen-tration of a particular radionuclides that could be positively identified in the sample.: Thereford, to insure that the " required"-
LLD is not exceeded for any radionuclides in a sample medium, the MJA is calculated based on the actual background in the area of . the identifying gamma energy.and is compared to.the " required" LLD. If the MDA exceeds the " required" LLD, the sample is counted for a-longer time period so that the standard deviation of the sample background is minimized. If the " required" LLD exceeds the MDA, then the. analysis of the sample meets the requirements for the detection capability for environmental sample analysis. For " gross" counters (such as alpha / beta proportional counters and liquid scintillation counters), the MDA is calculated using a batch background count. This MDA is then compared the_ " required" LLD. If the MDA exceeds the " required"' LLD, the sample is counted for a longer time period so that the standard deviation of the batch background is minimized. If the " required" LLD exceeds the MDA, then the' analysis of the sample meets the requirements for the detection capability for environmental sample analysis. O 2-5
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,- g SECTION 3 ,
O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - DISCUSSION, INTERPRETATION, AND TRENDING OF RESULTS GENERAL INFORMATION Before discussing each sample type specifically in Sections 3.1 - 3.11, the following general information is best discussed separately. Sections 2.1 and 2.2 describe the CNS site, REMP sample locations, and requirements of the environmental monitoring program. Appendix A summarizes the environmental sampling and analysis procedures, and discusses changes j in the procedures occurring during 1988. In addition to the " required" sampling and analyses described in Technical Specification Table 3.12-1, the following " supplemental" measures were taken during 1988. These supplemental measures were first adopted during 1986:
- 1) Shoreline sediment, requiring collection at only one point along the CNS Discharge Canal (Location 208-IS), was collected at three points (Locations 208-1S, 208-2S, and 208-3S).
- 2) Shoreline sediment, requiring collection semiannually, was collected quarterly. The first and third quarter samples from Locations IN- '208-1S,'210, and 215 were considered to be the required samples
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and all remaining samples were considered supplemental.
- 3) Fish, requiring collection from Locations 208 and 216 semiannually, were collected quarterly. The first and third quarter samples were considered to be the required samples and the second and fourth quarter samples were considered supplemental.
- 4) Bottom. sediment, not requiring collection at all, was collected quarterly at CNS Discharge Canal Locations 208-1M, 208-2M, and 208-3M. These were considered to be supplemental samples.
' All deviations from the sampling and the analytical requirements of Technical Specification Table 3.12-1 which occurred during 1988 are addressed in Appendices C and D, respectively. For all 1988 CNS REMP analyses performed, the LLD capability requirements of Technical Specification 4.12.1 were met for all samples except one. For all 1988 CNS REMP samples collected, the reporting level limitations of Technical Specification 3.12.1 were not exceeded.
The quality assurance programs associated with radiological environmental monitoring are summarized in Section 5. Section 5.3 includes the results of Duke Power Company's Environmental Radiological Laboratory's participation in the EPA Interlaboratory Comparison Program. All 1988 CNS REMP sample analysis results are submitted in Appendix E. O These include results for the " supplemental" samples described earlier. ( 3-1 1
I Summary tables covering 1988 for each REMP sample type, containing the information required by CNS Technical Specification Administrative Control ] () 6.9.1.6, can be found in Appendix B. These summary tables are based upon required sample results only, the supplemental sample results are not reflected in these tables. The mean values tabulated in these 1988 summary tables are based upon detectable measurements only, whereas the summaries submitted with the 1984, 1985, and 1986 CNS Annual Radiological Environmental Operating Reports contain mean values based upon net activities for all measurements, even for negative net activities and non-detectable measurements. A number of additional summaries were generated in order to facilitate thorough evaluation of 1988 REMP data; however, these additional summaries have not been included in this annual report. Section 4 contains an evaluation of estimated doses to members of the public based upon REMP sample results as compared to doses estimated using effluent release data. As mentioned in the 1987 annual report, the Nuclear Data ND6620 gamma spectroscopy system (which was used to analyze CNS REMP samples collected during 1984, 1985, 1986, and most of 1987) was replaced by the Nuclear Data ND9900 gamma spectroscopy system effective September 1, 1987. When the ND6620 system was used to analyze samples prior to September 1,1987, a small but steady percentage of most activation and fission radionuclides measurements (approximately 5%) yielded detectable low-level activity, even when the presence of such activity was highly unlikely as for control location samples and preoperational samples collected during 1984. This phenomenon has not occurred using the ND9900 system, thus ending this ('% trend and suggesting that the ND6620 system may have been vulnerable to
\ false positive results, possibly due to the method by which it estimated net activity even when its peak search routine failed to detect a peak.
Based on the best available evidence, it appears that the ND6620 system was probably vulnerable to a small but steady percentage of low-level false positive results, and that the ND9900 system is sufficiently sensitive to meet the LLD capability requirements of CNS Technical Specification 4.12.1. During 1984, the last completely preoperational year at CNS, H-3 and Cs-137 were detected with sufficient frequency to imply their existance as background radioactivity. Table 3.F summarizes the fraction and percent of nuclide measurements performed during 1984 which yielded detectable activity, as well as the predominant nuclides detected. These figures encompass measurements of the thirteen radionuclides listed in technical specifications, and do not reflect other nuclides which were detected (such as several nuclides which occur naturally). There appears to be no reliably discernable difference between the control and indicator locations (for a given sample type) in terms of the data incorporated in Table 3.F. Note that for ground water, drinking water, and surface water samples, H-3 was frequently detected (at levels of about 300 pCi/ liter), and I-131 was occasionally detected in surface water at all three locations when performing low-level radioiodine analysis (at levels ranging from 0.3 to 1.7 pCi/ liter). r l (-, 3-2 w--___-_________________-_
l For all sample types other than water, Cs-137 was detected occasionally I f3 during 1984. Note that for shoreline sediment, Cs-134 was detected at i'j all three locations in four of six samples at levels ranging from 24 to 39 pCi/ liter. For the reasons discussed earlier (ND6620 sensitivity phenomenon), l the predominant nuclides of Table 3.F are likely to be the only nuclides I listed in technical specifications that actually existed in these preoperational samples. ] All 1988 REMP analysis results were carefully reviewed in order to detect and identify any significant trends. Many sources of information were examined to accomplish this, and the resultant trending observations were included in Sections 3.1 - 3.11. Quarterly REMP verification reports were generated in order to track technical specification requirements, and these reports were also used to evaluate trends occurring during periods 1 4 shorter than a year. The 1988 Summary of Analysis Results tables from , Appendix B, as well as the analogous tables for 1984, 1985, 1986, and ; 1987, were reviewed. To aid in trending, additional summaries were generated for each individual i location for each sample type, as well as for key groups of locations for each sample type. These additional summaries were not included in this annual report. With exception of certain 1986 results affected by the Chernobyl accident, these summaries incorporated all REMP sample results, required as well as supplemental. These summaries contain the following three parameters for each radionuclides listed in technical specifications:
- 1) the average nuclide activity for all detectable measurements performed during a year, 2) the average nuclide activity for all measurements performed
/ during a year (with non-detectable measurements being averaged in as zero \ activity), and 3) the fraction and percentage of all measurements performed during a year that yielded detectable activity. These three parameters were denoted as to whether or not they exceeded the corresponding control location parameter. The highest parameter out of all indicator locations for a given sample type was specially denoted. These parameters were generated for 1986, 1987, and 1988 and parameter ratios between two successive years were calculated. Key parameters for 1988 were also compared to the analogous parameters for 1984 (the last preoperational year) for those nuclides predominantly detected during 1984 (see Table 3.F). Technical Specification 3.12.1 addresses the actions to be taken when nuclides other than the thirteen radionuclides listed in technical specifications are detected in REMP samples. If such nuclides are detected and are not the result of plant effluents, the condition shall be reported and described in this annual report. Table 3.C summarizes all such occurrences during 1988. The naturally occurring radionuclides of Table 3.C (Bi-214, K-40, and Be-7) were consic;ered to have resulted from natural background radioactivity, not plant effluents. This is supported by the frequency with which they were detected at both indicator and control locations, and during reoperation. The occurrences of Cr-51, Co-57, Ru-103, Sn-113, and Sb-125 in shoreline and bottom sediment samples (all in discharge canal samples), are assumed to have resulted from CNS liquid effluents which contained these nuclides. Detections of Ce-144 and Cr-51 in differing air filter paper samples collected on May 18, 1988 were not considered attributable to CNS operations, as n neither nuclide was detected in airborne effluents from CNS during the () second quarter of 1988. 3-3
l 1 I l An informative first overview of 1988 CNS REMP sample analysis results
,, can be found in Table 3.D. This overview can be compared to the analogous I
(") 1987 overview of Table 3.E and preoperational 1984 overview of Table 3.F. These three tables include statistics for measurements of only the thirteen radionuclides listed in technical specifications (for both required and supplemental samples). Note that nearly all nuclide detection frequencies for 1988 decreased from their 1987 levels (just as 1987 frequencies had decreased relative to 1986 and 1984 frequencies). More specifically, all 1988 nuclide detection frequencies were less than their 1987 and 1964 levels, with exception of frequencies for shoreline sediment, fish, and bottom sediment samples collected from indicator locations. These apparent I decreases in nuclide detection frequencies are attributable to the 1987 j upgrade of gamma spectroscopy systems and the associated sensitivity difference j l discussed earlier. Further decreases have resulted from additional laboratory l efforts during 1988 to reduce false positive results. When considering the above summary evidence, it is clear that 1988 shoreline sediment, fish, and bottom sediment samples contain radioactivity resulting from plant operation. In order to specifically determine how these samples were impacted, or if any other sample types were impacted, a more detailed examination of data has been performed and the conclusions submitted in Sections 3.1 - 3.11. I l Technical Specification Table 3.12-2 provides reporting levels, as a function of sample type and radionuclides. If sample radionuclides activity exceeds 100% of reporting level (when summed over all detected nuclides having a reporting level for the applicable sample type, and when the sums are averaged by location over the applicable calendar quarter) a special report O must be submitted to the Nuclear Regulatory Commission. Table 3.B contains V the maximum percent of reporting level (when averaged over a calendar quarter) reached during 1988 for each sample type and location combination. Note that no such values are listed for shoreline sediment or bottom sediment, as there are no corresponding technical specification reporting levels. Note that most of these maximum 1988 values are zero, whereas none of the maximum 1987 values were zero. With three exceptions, all of these maximum percent of reporting levels were less than 5.8%, well below the 100% action level. The highest value reached was 39%, for surface water collected during the third quarter at CNS Discharge Canal Location 208. Tritium accounted for all of this figure. The percent of reporting level values for surface water at Location 208 for the four calendar quarters of 1988 were 23%, 31%, 39%, and 33%, respectively. l l The following Sections 3.1 - 3.11 discuss 1988 REMP results for each sample ) type specifically. Unless otherwise noted, these discussions are based j on all REMP sample results, required as well as supplemental (with exception J of certain 1986 results affected by the Chernobyl accident). In order to properly interpret the following discussions, the reader must be comfortably familiar with Section 2, the general information of Section 3, and Tables 3.B, 3.D, 3.E, and 3.F. i O 3-4 I
L3.1: AIRBORNE RADIOIODINES AND PARTICULATE , r'\:
.( j 3.1.1 RADI0 IODINES
- The only radionuclides detecte'd;in any 1988 REMP air charcoal l cartridge samples were K-40 and'Be-7, both of which occur-naturally. - The absence of other nuclides represents a significant change from all previous years, and is explained by the ND6620
- sensitivity phenomenon discussed earlier. Apparently, the rate of l false-positive results has been reduced dramatically.
3.1.2'. PARTICULATE With three exceptions, the only radionuclides detected in any.1988' REMP air particulate filter samples were naturally-occurring nuclides. Three single detections of Mn-54, Ce-144, and Cr-51 at low levels did occur in three. separate indicator location samples. It'.is questionable whether these three nuclides actually existed in these samples, as Mn-54 was_a minor airborne effluent, and Ce-144 and Cr-51 were.not detected'as airborne effluents, from CNS during
-the sampling. quarter. As for'many other REMP' sample types, the 1988 detection frequency has decreased'significantly from previous years, apparently along with the false-positive rate.
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,;3.2 -GROUND' WATER.
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.The~ o'nly radionuclides; detected in the eight 1988 REMP ground water '
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' samples were naturally-occurring nuclides. -This represents'a relatively small reduction in. detection frequency from previous years.
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_~h _ y 3.3 ' DRINKING NATER x. 1.g) Four of the_nuclides listed.in technical specifications were detect'ed.in y drinking' water samples:from the: indicator locations,'none in control
. location samples. - I-131 (at Location 213), and Zn-65 and Cs-137.(at Location.214) were only detected once, and at low levels. H-3 was detected with 50% frequency at'both indicator Locations 213 and 214, at an average concentration of about 650 pCi/ liter at both locations. These H-3 results are relatively, consistent with 1984 and 1987-results, except that'the detection frequency for H-3. increased from an abnormal-low of 10% in 1987,'yet was lower than the 1984 rate of 92%. The maximum-quarterly percent of-reporting level'was.'3.85% (Location 214, third quarter), and was attributable mostly to H-3.
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3.4 -SURFACE WATER
,a , I Three of the nuclides listed in technical specifications were detected in surface water samples, with H-3 being predominant. I-131 and Co-58 were detected only once, at low levels and in only one sample (the first monthly 1988 sample from discharge canal Location 208). H-3 was detected J at all three locations, but only in significant level and frequency at i Location 208.
H-3 was detected at Location 208 with a frequency of 100% (4/4) and an average concentration of 6030 pCi/ liter. While this frequency was the ) same as in 1987 and 1986, the average concentration was 45% greater than the 1987 average of 4170 pCi/ liter, and 158% greater than the 1986 ] 1 average of 2340 pCi/ liter. In comparison, H-3 was detected with only 25% ( frequency (1/4) at control Location 215, with a single 607 pCi/ liter i measurement. H-3 was detected with 100% frequency (12/12) during 1984, I with the highest activity equal to 630 pCi/ liter. It is clear that CNS operations are affecting discharge canal surface l water H-3 concentrations, which are continuing to increase. The increase !' in H-3 over the past two years is not inconsistent with the increase of H-3 in liquid effluents. The percent of reporting level values for surface water at Location 208 for the four calender quarters of 1988 were 23%, 31%, 39%, and 33%, respectively. H-3 was responsible-for the vast majority of the reporting level activity. I l l r ( ( l l 3-8 1
e, P 3.5 MILK 73 j_ Q Four of thelnuclides listed in technical specification were detected in i milk' samples; however, only Cs-137 was detected with significant !. ~ frequency. Cs-137 was detected during 1988 with frequencies of 54.2% (1?/24), 16.7% (4/24), and 54.2% (13/24) at indicator Locations 209 and 219, and at control Location 221, respectively. .The respective average detectable Cs-137 concentrations were 3.11, 3.23, and 3.78 pCi/ liter. l While these values are roughly comparable to each other and to 1986'and 1987 values, control Location 221 yielded the highest frequency of detection and activity for Cs-137 during 1988 (as it also did during 1987). During 1984, Cs-137 was detected with 15.0%~ frequency (12/80). Based on this information,-Cs-137 activity in milk samples cannot reasonably be attributed to CNS operations. The maximum quarterly' percent of reporting leve' aas 4.92%; this occurred at control Location 221 during the first q'av.c and was attributable. solely to Cs-137 activities. O I o 3-9
'3.6 BROADLEAF VEGETATION
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Two of the nuclides listed in technical specifications were detected in
.broadleaf vegetation samples; however, only.Cs-137 was detected with significant frequency.- Cs-137 was detected during 1988:with frequencies of:0.0%.(0/12), 41.7% (5/12); 50.0% (6/12), and 33.3%-(4/12) at indicator .
Locations 200, 201, and 226, and at control Location 217, respectively. The: respective average detectable Cs-137 concentrations.were 0.0,-91.3, l-43.7, and 74.3 pCi/ wet-kilogram. During'1984, Cs-137 was' detected with 25.0% frequency-(9/36). No trend is apparent at any of the locations L when comparing 1988 and 1987 values. While. indicator Loc.ation 201 yielded a slightly higher detection frequency and. average detectable concentration for Cs-137 as compared to control Location 217, the difference is not significant enough to reasonably attribute this l Cs-137 activity to CNS operations. The maximum quarterly percent of-I reporting level was 4.31%; this occurred at indicator Location 201 during l the: fourth quarter and was attributable solely to Cs-137 activities. 1
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' (j Nine of the nuclides listed in technical specifications were detected in shoreline sediment samples; however, only Mn-54, Co-58, Co-60, Cs-134,
(: and Cs-137 were detected with predominant frequency, and only.at CNS discharge canal Locations 208-IS, 208-2S, and 208-3S. No reliably significant differences could be found among the three discharge canal locations, therefore, the following observations are based on the three locations collectively. During 1984, low levels of Cs-134 and Cs-137 were detected with 66.7% (4/6) and 33.3% (2/6) frequency, respectively. Considering the ND6620 sensitivity phenomenon, and the total absence of any.nuclides-listed in technical specifications (except for two occurrences.of Cs-137) at indicator Location 210 and control Location 215, occurrence of'these five nuclides (discussed below) at Location 208 is the result of CNS operations. The evidence below shows that' concentrations of these five nuclides at Location 208 have generally leveled off'and remain roughly comparable'to 1987 values, with exception of Co-60 concentrations. i" Mn-54 was detected at Location 208 with a frequency of 91.7% (11/12) and
, an average. detectable concentration of 116 pCi/ dry kilogram. Respective values.for 1987 results were 66.7% (8/12) and 88.3 pCi/ dry kilogram, roughly comparable to 1988.
Co-58 was detected at Location 208 with a frequency of 100% (12/12) and an average detectable concentration of 329 pCi/ dry kilogram. Respective.
. values for 1987 results were 83.3% (10/12) and 408 pCi/ dry kilogram, comparable to 1988. ;
Co-60 was detec'ted at Location 208 with a frequency of 91.7% (11/12) and ', an average detectable concentration of 287 pCi/ dry kilogram. Respective values for 1987 results were 100% (12/12) and 161 pCi/ dry kilogram. q Thus, detection frequency decreased slightly, but average detectable ; concentration increased by 78% from 1987 to 1988. I Cs-134 was. detected at Location 208 with a frequency of 50.0% (6/12) and an average' detectable concentration of 51.8 pCi/ dry kilogram. Respective values for 1987 results were 66.7% (8/12)'and 60.8 pCi/ dry kilogram, comparable to 1988. Cs-137 was detected at location 208 with a frequency of 100% (12/12) and an average detectable concentration of 107 pCi/ dry kilogram. Respective values for 1987 results were 91.7% (11/12) and 126 pCi/ dry kilogram, comparable to 1988. O V 1 l i 3-11 l l I
v 3.8 FISH m (~) Six of the nuclides listed in technical specifications were detected in fish samples at CNS discharge canal Location 208, and none were detected in fish collected from control Location 216. Three of these nuclides, Co-58, Co-60, and Cs-137 were predominant. Occurrence of these nuclides are clearly the result of CNS operations. REMP results were reviewed by type'of fish,'and the results show that nuclide detection frequencies and concentrations were higher for forager fish, and less for predatory fish, as compared to bottom feeding fish. This trend was not evident in 1987 results. However, due to the relatively small sample size, the following observations v.e based on all three types of fish collectively. During 1984, only Cs-137 was detected with significant frequency (16.7%, 2/12). Co-58 was detected at Location 208 with a frequency of 50.0% (6/12) and an average detectable concentration of 281 pCi/ wet kilogram. Respective values for 1987 results were 41.7% (5/12) and 182 pCi/ wet kilogram. Thus, detection frequency increased by 20%, and concentration increased by 54% from 1987 to 1988.
, Co-60 was detected at Location-208 with a frequency of 33.3% (4/12) and an average detectable concentration of 291 pCi/ wet kilogram. Respective values for 1987 results were 41.7% (5/12) and 115 pCi/ wet kilogram. Thus, detection frequency decreased by 20%, but concentration increased by 153%
from 1987 to 1988. Cs-137 was detected at Location 208 with a frequency of 91.7% (11/12) and N an average detectable concentration of 89.9 pCi/ wet kilogram. Respective IJ'
\- values for 1987 results were 83.3% (10/12) and 51.2 pCi/ wet kilogram.
Thus, detection frequency increased by 10%, and concentration increased by 76% from 1987 to 1988. The maximum quarterly percent of reporting level was 27.31%; this occurred for bottom feeding fish at discharge canal Location 208 during the fourth quarter. The quarterly percent of reporting level values for all three , fish types collected at Location 208 were significantly higher in the fourth quarter of 1988 than in any other quarter. Cs-137 accounted for the majority of the reporting level values. Y.-) 3-12
1 3.9 DIRECT GAMMA RADIATION (TLD) I l h . (~) Forty thermoluminescent dosimeters (TLDs) are located in the vicinity of CNS in order to monitor direct gamma (whole-body) radiation. The TLD locations can be divided into four major groups; three control locations (217, 247, and 251), sixteen site boundary ring locations (one in each meteorological sector), sixteen 4-5 mile radius ring locations (one in I each meteorological sector), and five special interest locations, d Review of 1984 - 1988 TLD results quickly reveals that natural background 1 levels vary considerably from location to location, and from year to j year. Furthermore, in order to conclude whether a sufficiently small net dose rate _above natural background is significant, average dose rates for groups of TLDs (not single TLDs) must be compared. In other words, the larger the number of locations which are averaged, the smaller the average dose rate difference which can be detected. Therefore, no reliable conclusions could be reached when individual locations were { evaluated, but the following observations could be made when comparing groups of TLD locations for 1984, 1985, 1986, 1987, and 1988. When considering all TLD locations collectively, the average annual 1988 exposure was 70.9 mR, 14% lower than for 1984 (reoperation), and 21% lower than for 1987. These percent differences in themselves obviously do not reflect CNS operations; TLD location subgroups must be compared in order to assess the impact of CNS operations. The difference in annual exposure from year to year is likely due to the same conditions which cause variation in exposure among calendar quarters. O V The average annual 1988 exposure for the three control TLD locations was 67.1 mR. The respective values for 1984, 1985, 1986, and 1987 were 79.3 mR, 108.9 mR, 94.4 mR, and 84.7 mR. The average 1988 exposure for the sixteen site boundary ring TLD locations was 74.6 mR, 11.2% greater than the control average. In j comparison, the average site boundary ring location exposure was 10.3%, 7.3%, 10.5%, and 14.5% greater than the control average during 1984, 1985, 1986, and 1987, respectively. Using 1984 as a basis, the net average exposure for the site boundary ring was -3.2 mR, 0.2 mR, 3.6 mR, and 0.6 mR during 1985, 1986, 1987, and 1988, respectively. These net average exposures do not differ from zero enough to conclude that a trend exists l or that site boundary ring TLDs were affected by CNS operations. The average annual 1988 exposure for the sixteen 4-5 mile ring TLD locations was 70.3 mR, 4.8% greater than the control average. In comparison, the average 4-5 mile ring location exposure was 4.2%, -0.2%, 4.3%, and 3.2% greater than the control average during 1984, 1985, 1986, and 1987, respectively. Using 1984 as a basis, the net average exposure for the 4-5 mile ring was -4.8 mR, 0.1 mR, -0.9 mR, and 0.4 mR, during 1985, 1986, 1987, and 1988, respectively. These net average exposures do not differ j from zero enough to conclude that 4-5 mile ring TLDs were affected by CNS l operations. ) l Q G 1 l I 3-13 l l 1
{ 1 i i I The average annual 1988 exposure for the five special interest TLD i 1 em:. locations was 63.1 mR, 6.0% less than the control average. In l (~f comparison, the average special interest location exposure was 10.2%, 9.5%, 9.2%, and 7.2% less than the control average during 1984, 1985, J 1986, and 1987, respectively. Using 1984 as a basis, the net average ) exposure for the special interest locations was 0.8 mR, 0.9 mR, 2.5 mR, l and 2.8 mR during 1985, 1986, 1987, and 1988, respectively. These net average exposures do not differ from zero enough to conclude that a trend exists or that special interest TLDs were affected by CNS operations. i l l
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.Y 3-14
l - l;; , t,. 3.10', LAND USE CENSUS
*i k~~ The 19'88 Annual Land Use Census'was conducted as described in Section A.10 of-Appendix'A. . Table 3.A summarizes the census results. 'No changes
.were madeJin the CNS Radiological Environmental Monitoring Program on the basis of the census results. Since no dairies'were located within:a five mile radius of CNS, it was conservatively assumed that any milk animal could also'be considered'a meat animal.
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3.11 BOTTOM SEDIMENT i (m., ( ,) Five of the nuclides listed in technical specifications were detected in bottom sediment samples with predominant frequency; Mn-54, Co-58, Co-60, Cs-134, and Cs-137. These five nuclides were predominant at all three bottom sediment sampling points (CNS discharge canal Locations 208-1M, 208-2M, and 208-3M). These same five nuclides were predominant in shoreline sediment, where average detectable activities were considerably lower. Nb-95, Co-57, and Sb-125 were also detected in bottom sediment, but with lower frequencies and not at all three locations. The following observations are based on all three sampling points collectively, because overall, no single location appeared to exhibit consistently higher nuclide detection frequencies or concentrations. Note that there is no bottom sediment control location, and that bottom sediment was first collected during 1986. Mn-54 was detected with a frequency of 100% (12/12) and an average detectable concentration of 578 pCi/ dry kilogram. Respective values for 1987 results were 77.8% (7/9) and 723 pCi/ dry kilogram, comparable to 1988. Co-58 was detected with a frequency of 91.7% (11/12) and an average detectable concentration of 1040 pCi/ dry kilogram. Respective values for 1987 results were 77.8% (7/9) and 1730 pCi/ dry kilogram, roughly comparable to 1988.
,, Co-60 was detected with a frequency of 100% (12/12) and an average
( detectable concentration of 3180 pCi/ dry kilogram. Respective values
\--} for 1987 results were 88.9% (8/9) and 2460 pCi/ dry kilogram, comparable to 1988.
Cs-134 was detected with a frequency of 58.3% (7/12) and an average detectable concentration of 211 pCi/ dry kilogram. Respective values for 1987 results were 66.7% (6/9) and 166 pCi/ dry kilogram, comparable to 1988. Cs-137 was detected with a frequency of 100.0% (12/12) and an average detectable concentration of 570 pCi/ dry kilogram. Respective values for 1987 results were 100.0% (9/9) and 403 pCi/ dry kilogram, roughly comparable to 1988. p U 3-16
TABLE 3.A 1988 CATAWBA ANNUAL LAND USE CENSUS RESULTS O Date(s) Performed 8/1-2/88 Distance Distance Sector (Miles) Sector (Miles) Nearest Residence .60 Nearest Residence .68 Nearest Meat Animal 4.6 Nearest Meat Animal 3.6 N Nearest Garden 2.0 S Nearest Garden .85 Nearest Cow 4.6 Nearest Cow 3.6 Nearest Goat -- Nearest Goat -- Nearest Residence .53 Nearest Residence .73 Nearest Meat Animal -- Nearest Heat Animal 3.4 NME Nearest Gsrden 2.4 SSW Nearest Garden 1.0 Nearest Cow -- Nearest Cow 3.4 Nearest Goat -- Nearest Goat -- Nearest Residence .58 Nearest Residence .62 Nearest Heat Animal -- Nearest Heat Animal 2.6 NE Nearest Garden 2.7 SW Nearest Garden 1.4 Nearest Cow -- Nearest Cow 2.6 Nearest Goat -- Nearest Goat - Nearest Residence .55 Nearest Residence .80 Nearest Meat Animal -- Nearest Meat Animal 3.0 ENE Nearest Garden .55 WSW Nearest Garden .80 Nearest cow -- Nearest Cow 3.0 Nearest Goat - Nearest ficat 3.0 Nearest Residence .60 Nearest Residence 1.05 Nearest Heat Animal 4.0 Nearest Heat Animal 3.6 E Nearest Garden 4.60 W Nearest Garden 1.5 Nearest Cow 4.0 Nearest Cow 3.6, Nearest Goat 4.0 Nearert Goat -- Nearest Residence .78 Nearest Residence 1.2 Nearest Meat Animal -- Nearest Meat Animal 1.4 ESE Nearest Garden .90 WNW Nearest Garden 1. '2 Nearest Cow -- Nearest Cow 1.6 Nearest Goat -- Nearest Goat 1.4 Nearest Residence 1.03 Nearest Residence 1.4 Nearest Meat Animal -- Nearest Meat Animal 1.2 SE Nearest Garden 1.4 NW Nearest Garden 1.3 Nearest Cow -- Nearest Cow 1.2 Nearest Goat -- Nearest Goat 1.4 Nearest Residence .76 . Nearest Residence 1.04 Nearest Meat Animal -- Nearest Meat Animal 2.5 SSE Nearest Garden 2.0 NNW Nearest Garden 2.0 Nearest Cow -- Nearest Cow 2.5 Nearest Goat -- Nearest Goat -- Census is completed and is accurate to the best of my knowledge: k d Y-igna ~re ' Pers P forming Census Census Reviewed by: 7V CR Superv o l Census Reviewed by: UM 2> h 1 taff Health Physicist
i g / 3 .. , TABLE 3.B
'Q Q 1988 MAXIMUM CALENDAR QUARTER: AVERAGE PERCENT.OF REPORTING LEVELS Sample. % Rpt.. Calendar Quarter Sample Type Location. Level Sampling Dates Air Radioiodines 200 0.00% 'All 201 0.00% All 205- 0.00%- All.
212 0.00% All 217 0.00% .All- Control Air Particulate 200 0.00% .All 201 0.00% All 205 0.00% All 212 0.00% All 217 0.00% All' Control
, ' Air Radioiodines + 200 0.00% -All Particulate 201 0.00% All -l
'205 0.00% All-212 0.00% All 217 0.00% All Control
. Ground Water 200 0.00% All l ): 252 0.00% All' Drinking Water: 213 3.73% 10/05/88-12/28/88 214 3.85% 07/13/88-10/05/88' 218 0.00%- All Control Surface Water 208 139.20% 07/13/88-10/05/88 211 5.79% 07/13/88-10/05/88 215 3.04% 04/20/88-07/13/88 Control Milk 209 3.12% 04/13/88-06/29/88 219 3.40% 04/13/88-06/29/88 221 4.92% 01/13/88-03/23/88 Control Broadleaf Vegetation 200 0.00% All 201 4.31% 10/05/88-12/07/88 217 3.33% 10/05/88-12/07/88 Control 226 1.48% 07/06/88-09/07/88 i
Fish (Predator.) 208 4.17% 10/05/88 216 0.00% ALL Control Fish (Forager) 208 21.91% '10/14/88 216 0.00% All Control
' f"'g . Fish (Bottom Feeder) 208 27.31% 10/14/88 gV' 216 0.00% All Control
L (- p- 1 y TABLE 3.C en-
" Ji RADIONUCLIDES DETECTED DURING 1988 AND NOT LISTED IN TECHNICAL SPECIFICATIONS Airborne-Particulate Ce-144. 2.491E-2 pCi/ cubic meter Location 200 5/11/88-5/18/88
.Cr-51 4.951E-2 pCi/ cubic meter Location 212 5/11/88-5/13/88 Ground Water
- l. Bi-214 666. pCi/ liter Location 200 3/25/88 Bi-214 171. pCi/ liter Location 252 3/23/88-l Shoreline Sediment Cr-51 1091 pCi/ dry'kg Location 208-1S 12/21/88 l Co-57' - 9.18 pCi/ dry kg . Location 208-1S 12/21/88 Ru-103 10.2 pCi/ dry kg Location 208-IS 12/21/88'
; ,, Sn-113 12.2 pCi/ dry kg Location 208-IS 12/21/88
-- Sb-125 '44.1 pCi/ dry kg Location 208-1S 12/21/88
- ! Cr-51 128. pCi/ dry kg Location 208-3S 12/21/88 Bottom Sediment Co-57 35.3 pCi/ dry kg Location 208-1M 02/9/88 Co-57 12.1 pCi/ dry kg Location 208-1M 11/10/88 Sb-125 133. pCi/ dry kg Location 208-1M 11/10/88 Co-57 20.3 pCi/ dry kg Location 208-2M 11/10/88 l Sb-125 230. pCi/ dry kg Location 208-2M 11/10/88 Sb-125 387. pCi/ dry kg Location 208-3M 05/13/88 Most Sample Types and Locations K-40 and Be-7 i
t .;- J TABLE 3.D I . FRACTION AND PTRCENT OF 1988 NUCLIDE MEASUREMENTS YIELDING . DETECTABLE ACTIVITY : L
, Sample Type Indicator Locations . Control Locations.
Airborne Radioiodines 0.0 % 0/2332 0/583- 0.0 % Airborne Particulate. 1/2332 0.0 % 0/583 0.0 %. Ground Water 0/104 0.0 % No Control Location Drinking Water 7/346 2.0 % 0/173 0.0 % Surface Water 8/346 2.3 % 1/173 0.6 %- Milk 19/576 3.3 % 14/288 4.9 % Broadleaf Vegetation' 12/396 3.0 % 4/132 '3.0 % Shoreline Sediment 60/176 34.1 % 1/44 2.3 %
- Fish 28/132 21.2 % 0/132- 0.0 % j Bottom Sediment 56/132 42.4 % No Control Location i(} All Sample Types 191/6872 2.8 % 20/2108 0.9'%
^
l 1 < 1 l 1
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i l I c.
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TABLE 3.E fy;- -; FRACTION AND PERCENT OF 1987 NUCLIDE MEASUREMENTS YIELDING DETECTABLE ' ACTIVITY i Sample Type Indicator Locations Control Locations 1- Airborne Radioiodines 67/2277 2.9 %- 14/572 2.4 %' l b Airborne Particulate. 76/2277 3.3'% 12/572 -2.1 % Ground Water; 4.8 % No Control Location-5/104- ] l Drinking Water- 10/348- 2.9 % 1/174 0.6 %
' Surface Water' 19/348 5.5 % ~4/174 2.3 %- _
y Milk 32/733 4.4 % 17/288 5.9 %' .
'Broadisaf V'egetation 32/396 8.1 % 11/132- 8.3 %
-]
Shoreline Sediment 55/176 31.3 % 5/44 11.4 %' Fish 29/132 22.0 % 12/132 .9.1 %'
, Bottom . Sediment 47/99 47.5 % No Control Location All Sample Types 372/6890 5.4 % 76/2088 3.6 %
L O
y 3 TABLE-3.F I.. y FRACT10N AND PERCENT OF 1984 NUCLIDE MEASUREMENTS YIELDING DETECTABLE ACTIVITY l. Sample Type' All-Locations Predominant Nuclides-Airborne Radioiodines '99/2068 4.8 % Cs-137 26/188 13.8 % Airborne Particulate 108/2717 4.0 % Cs-137 22/247 8.9.% Ground Water. 2/52 3.8 % H 2/4 50.0 %' !~ Drinking Water 35/465 7.5 % H-3 11/12 91.7 % Surface Water 30/454 6.6 % H-3 12/12 100.0 % e I-131/LL 5/24 20.8 % Milk 43/960 4.5 % Cs-137 12/80 15.0 % Broadleaf Vegetation 24/396 6.1 % Cs-137 9/36 25.0 % Shoreline Sediment 7/66 10.6 % Cs-134 4/6 66.7 % Cs-137 2/6. 33.3 %
. Fish 4/132- 3.0 % Cs-137 2/12 16.7 %
All. Sample Types - 352/7310 4.8 % 1 e O
SECTION 4
.Q EVALUATION OF DOSE FROM ENVIRONMENTAL MEASUREMENTS VERSUS ESTIMATED DOSE FROM RELEASES 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 1988 CNS REMP samples. The primary purpose of estimating doses based on REMP sample results was to compare them to effluent program dose estimates. Therefore, doses based on REMP sample results were conservatively calculated in a manner as equivalent as possible to effluent-based dose estimates, in order to allow for the most valid comparison.
Doses based on REMP sample results were calculated using the methodology and data presented in NRC Regulatory Guide 1.109. Measured radionuclides concentrations, averaged over the entire year (with nondetectable measurements averaged in as zero) for a specific nuclide, indicator location, and sample type, were used to calculate REMP-based doses, after subtracting the analogous average background concentration (as measured at the corresponding control location). Regulatory Guide 1.109 consumption rates for the maximum exposed individual were used in the calculations. When the guide listed "NO DATA" as the dose factor for a given radionuclides and organ, a dose factor of zero was assumed. There were three radionuclides (Co-57, Sn-113, and Sb-125 detected in REMP (~. T sediment samples) for which the guide listed no external dose factors.
'N For these nuclides, the highest total body and skin dose factor listed (for Na-24) was used.
The dose contributions from detectable concentrations of naturally-occurring radionuclides other than tritium which were discussed in Section 3 (K-60, Be-7, and Bi-214), were not included in REMP-based dose calculations. All other detected nuclides, including the ones not listed in Technical Specifications which were discussed in Section 3, were included in REMP-based dose calculations. Results for all 1988 REMP samples, required as well as supplemental, were included in the dose calculations. Maximum REMP-based dose estimates for airborne particulate, drinking water, milk, broadleaf vegetation, shoreline sediment, and fish pathways are reported in Tables 4.A through 4.F, respectively. For each sample type, organ doses were evaluated separately for each specific location and age group (adult, teen, child, and infant). For example, shoreline sediment pathway doses for Locations 208-1S, 208-2S, and 208-3S were evaluated separately, as were fish pathway doses for predatory, forager, and bottom feeding fish types. In this conservative manner, the maximum REMP-based dose estimates for each sample type have been reported in Tables 4.A through 4.F, and the critical age, critical location, and critical fish type have been identified as well. rs N_. 4-1
r3< f i L Note that REMP-based dose estimates.were not, reported for the airborne
;O radioiodine or ground water sample types, because no nuelides other than M naturally-occurring K-40, Be-7, and Bi-214 were detected in these-samples. Note also that_REMP-based dose estimates were not reported'for the surface water or bottom sediment sample types, as these media are not directly connected to man, because sampled surface water is not considered to be'a potable drinking water source and because sampled-bottom sediment is permanently submerged. Dose estimates based on REMP TLD results'are discussed in Section 3.9.
In addition to evaluating dose for each REMP sample type separately, these resnits were compared and the maximum dose to each organ from any single sample type (the " limiting" sample type) was determined and-reported in Table 4.G. For skin dose, the. limiting sample type was determined and. reported in Table 4.G. For skin dose, the limiting sample type was shoreline sediment collected at discharge canal Location 208-lS. 'For doses to all other organs, the limiting sample type'was. fish collected at discharge canal Location 208. .For dose to the thyroid and the GI-LLI, forager fish were determined to be -limiting. 'For dose to the bone, liver,. total body, kidney, and lung, bottom feeding fish were determined to be limiting. The maximum organ dose estimate for any single REMP sample type collected during 1988 was 0.696 mrem / year to the maximum exposed adult's thyroid gland from consuming forager fish caught at discharge canal Location 208. In order to generate REMP-based dose estimates which could be compared to reported effluent-based dose estimates, two additional evaluations
., were' performed. These evaluations are discussed in the following two paragraphs.
Maximum 1988 REMP-based doses for' drinking water, shoreline sediment, and fish were summed to determine the maximum total REMP-based dose for all sampled liquid release pathways. This summation was performed individually for all 32 combinations of organ and age group. The dose
-contribution from shoreline sediment to each organ other than the skin was assumed to equal the total body contribution. The resulting maximum total organ dose estimates for the critical age groups have been reported in Table 4.H. The maximum total organ dose estimate for all 11guid release pathways sampled during 1988 was 0.739 mrem / year to the maximum exposed adult's thyroid gland. The critical pathway was forager fish, which accounted for 0.696 mrem / year (94.2%) of this total thyroid dose. Drinking water and shoreline sediment accounted for 5.6% and 0.2%
-of the total thyroid dose, respectively.
t
/
b 4-2
Maximum 1988 REMP-based doses for airborne particulate, milk, and {
.g broadleaf vegetation were summed to determine the maximum total V '
REMP-based dose for all sampled gaseous release pathways. This summation was performed individually for all'28 combinations of organ and age group. The resulting maximum total organ dose estimates for.the critical age groups have.been reported-in Table 4.I. The maximum total organ. dose estimate for all gaseous release. pathways sampled during 1988 was 0.117 mrem / year to the maximum exposed infant's_ thyroid gland. The. critical pathway was milk,.which accounted for essentially 100% of this total thyroid dose. However, it should be noted that the majority of ! the calculated maximum total organ dose, for all organs other than the thyroid,'was attributable to detection'of Cs-137 in REMP Location'201 E broadleaf vegetation samples at an average concentration not significantly greater than for control Location 217.
.All REMP-based annual dose estimates were less than 1 mrem / year, and
~
,were typically orders of magnitude below this level. All REMP-based i annual dose estimates were less than the corresponding calendar year (and even calendar quarter) dose limits applicable to effluent-based.
dose calculations (these limits are listed in CNS Technical' Specifications 3.11.1.2 and 3.11.2.3). l l, 1.. 4-3
I 4.2 ESTIMATED DOSE FROM RELEASES
/x f(). Throughout the year, dose estimates were calculated based on actual 1988 liquid and gaseous effluent release data. These effluent-based dose estimates were calculated using the LADTAP and GASPAR computer programs, which employ the methodology and data presented in NRC Regulatory Guide 1.109. The 1988 CNS Annual Radioactive Effluent Release Report included such calendar year dose estimates for the maximum exposed individual j from liquid and gaseous effluent releases. These reported doses are i shown in Table 4.H (liquid releases) and Table 4.I (gaseous releases),
along with the corresponding REMP-based dose estimates. The effluent-based liquid release doses of Table 4.H are summations of dose contributions from the fish and shoreline sediment pathways (estimated for the discharge canal) as well as the drinking water pathway (estimated for the nearest downstream potable water intake). The effluent-based gaseous release doses of Table 4.I are reported separately for noble gas exposure than for iodine, particulate, and tritium exposure. For noble gas exposure, there is no critical age group, as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group. For iodine, particulate, and tritium exposure, the 1988 CNS Annual Radioactive Effluent Release Report listed the maximum total organ dose for the highest dose location (0.5 miles ENE), but did so only for the maximum organ (thyroid) for the critical age group (child). Therefore, effluent-based dose estimates for' organs other than the thyroid are not given in the iodine,
/) particulate, and tritium exposure summary of Table 4.I.
%/
s 4-4
I i i 4.3 COMPARISON OF DOSES ! q j V Tables 4.H-and 4.I allow for easy comparison of REMP-based versus effluent-based maximum dose estimates, critical ages, and critical , pathways, for the liquid and gaseous release pathways respectively. As i discussed in Section 4.1, the REMP-baced estimates have been calculated -! in such a manner as to be as analogous as possible to the corresponding effluent-based estimates. Therefore, the estimates can be compared directly with few qualifications. One difference is that all effluent-based dose estimates include pathway contributions from tritium contained in liquid and gaseous effluents. Although REMP-based dose estimates for the drinking water pathway include dose contributions from tritium (as all REMP water samples are analyzed for tritium content), dose estimates for the fish, air, milk, and broadleaf vegetation pathways do not include tritium dose contributions, as tritium analysis is not performed on these samples. This results in REMP-based dose estimates that are biased somewhat low, in comparison to effluent-based estimates. Also, no REMP airborne noble gas samples are collected as part of the REMP, preventing an analogous comparison of effluent-based noble gas exposure estimates. Comparison of the data in Table 4.H reveals excellent agr,eement between REMP and effluent-based maximum dose estimates for liquid release i pathways. Table 4.H gives ratios of the environmental / effluent dose estimates for each organ. Excluding the thyroid estimate, REMP-based dose estimates ranged tightly between 15% and 30% of the effluent-based estimates (comfortably below the effluent-based estimates, as would typically be expected). For the thyroid, the REMP-based estimate was 4.48 times higher than the effluent-based estimate, which is not unreasonable for this type of comparison. The vast majority of this REMP-based thyroid estimate was attributable to a single detection of I-131 (67.9 pCi/ wet kg) in the forager fish sample collected from the discharge canal during the fourth quarter. Had I-131 not been detected in this sample, the liquid release REMP-based maximum thyroid dose estimate would have been 0.0851 mren/ year (critical age = child, critical pathway = drinking water), which is 52% of the effluert-based estimate. In addition to the excellent agreement Letween the REMP and . effluent-based organ dose estimates, the associated critical ages and ! critical pathways agreed nearly perfectly. This overall agreement is partially attributable to the fact that REMP fish and shoreline sediment samples collected at the diacharge canal typically contain detectable quantities of the same key radionuclides predicted to be predominant by effluent-based calculations. 4-5
For iodine, particulate, and tritium exposure via gaseous release
,g pathways (Table 4.I), the maximum dose organ was determined to be the
( ,) thyroid by both REMP and effluent-based calculations (although both the critical age and critical pathway differed). The REMP-based thyroid estimate was 41% of the effluent-based estimate, but this comparison requires clarification. 70.24% of the effluent-based dose estimate was attributable to tritium, a radionuclides not accounted for in the REHP-based estimate. Therefore, the effluent-based thyroid dose estimate could be adjusted to 0.0845 mrem / year (to exclude the tritium contribution) before comparison with the 0.117 mrem / year REMP-based estimate (which would then be 38% higher). Furthermore, the REMP-based estimate was entirely attributable to a single detection of I-131 (0.611 pCi/ liter) in one of 24 milk samples collected from REMP Location 219. It is questionable that I-131 actually existed in this sample, as Location 219 is distantly located six miles from CNS. Overall, 1988 annual dose estimates based on REMP sample results compared very favorably to effluent program dose estimates. This is especially true considering the uncertainties inherent in comparing dose estimates based on extremely low levels of environmental radioactivity. The REMP-based estimates were consistently comparable to, and typically less than, the corresponding effluent-based estimates. This evidence indicates that the effluent program dose estimates are both valid and reasonably conservative, and that doses to members of the public attributable to the operation of CNS are being maintained well within regulatory guidelines. in t r l 1 l
'% /
4-6
i l l l TABLE 4.A
/~~'i 4 '(_,/ DOSE ESTIMATES BASED ON 1988 ENVIRONMENTAL j AIRBORNE PARTICULATE SAMPLE RESULTS i 1
l Dose Rate Critical Critical Organ (mrem / year) Age Pathway Location 1 i Bone 3.18E-3 Child Airborne Particulate 200 Liver 9.95E-4 Child Airborne Particulate 200 T. Body 1.70E-4 Child Airborne Particulate 200 Thyroid 7.98E-8 Child Airborne Particulate 212 Kidney 5.68E-4 Teen Airborne Particulate 200 Lung 6.28E-3 Teen Airborne Particulate 200 GI-LLI 4.06E-4 Teen Airborne Particulate 200 (~ n
%J
i I TABLE 4.B i
'~T, I
\ ,) DOSE ESTIMATES BASED ON 1988 ENVIRONMENTAL DRINKING WATER SAMPLE RESULTS j l
l Dose Rate Critical Critical i Organ (mrem / year) Age Pathway Location { Bone 1.64E-2 Child Drinking Water 214 Liver 5.90E-2 Infant Drinking Water 214 T. Body 4.11E-2 Child Drinking Water 214 Thyroid 8.51E-2 Infant Drinking Water 213 Kidney 4.34E-2 Child Drinking Water 214 Lung 3.48E-2 Child Drinking Water 214 GI-LLI 4.18E-2 Infant Drinking Water 214
~%
I l l l' (
%J 1
l I l-I' i TABLE 4.C
- 1. ,--~
G' DOSE ESTIMATES BASED ON 1988 ENVIRONMENTAL MILK SAMPLE RESULTS Dose Rate Critical Critical Organ (mrem / year) Age Pathway Location Bone 3.02E-4 Infant Milk- 219 Liver 3.56E-4 Infant Milk 219 T. Body 1.57E-4 Infant Milk 219 Thyroid 1.17E-1 Infant Milk 219 Kidney 4.16E-4 Infant Milk 219 Lung 0 N/A Milk N/A GI-LLI 1.63E-3 Teen Milk 209
,r"N,
(.) gs
4 TABLE 4.D DOSE ESTIMATES BASED ON 1988 ENVIRONMENTAL BROADLEAF VEGETATION SAMPLE RESULTS Dose Rate Critical' Critical
' Organ (mrem / year) Age Pathway Location
' Bone 1-13E-1
. Child Broadleaf Vegetat on 201.
' Liver 1.08E-1 . Child Broadleaf Vegetation 201
.T. Body f6.08E-2 Adult- Broadleaf Vegetation 201
. Thyroid 0 N/A- Broadleaf Vegetation N/A Kidney 3.53E-2 ' Child Broadleaf Vegetation' 201 Lung 1.27E-2 Child Broadleaf Vegetation 201 GI-LLI 2.'34E Adult Broadleaf Vegetation 201 0
i l \ 1 h' '
TABLE 4.E
, ~ , .
( 3
\_ / DOSE ESTIMATES BASED ON 1988 ENVIRONMENTAL SHORELINE SEDIMENT SAMPLE RESULTS Dose Rate Critical Critical Organ (mrem / year) Age Pathway Location Skin 8.01E-3 Teen Shoreline Sediment 208-1S T. Body 6.82E-3 Teen Shoreline Sediment 208-1S Ov l
l i i
.. i I
J I
?
\
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TABIE 4.F fS 4
j DOSE ESTIMATES BASED ON 1968 ENVIRONMENTAL FISH SAMPLE RESULTS Dose Rate Critical Critical Organ (mrem / year) Age Pathway Location Bone 3.32E-1 Child Fish (Bottom Feeder) 208 Liver 4.01E-1 Teen Fish (Bottom Feeder) 208 T. Body 2.73E-1 Adult Fish (Bottom Feeder) 208 Thyroid 6.96E-1 Adult Fish (Forager) 208 Kidney 1.34E-1 Teen Fish (Bottom Feeder) 208 Lung 5.18E-2 Teen Fish (Bottom Feeder) 208 GI-LLI 3.98E-1 Adult Fish (Forager) 208 ,-n
( f f n i l l 4 l (v) i l l E-
,[' ;
.- ' TABLE 4.G DOSE ESTIMATES BASED ON LIMITING 1988 ENVIRONMENTAL SAMPLE RESULTS
~ Dose Rate Critical Critical' Organ' (mrem / year)- Age Critical Pathway Location Skin 8.01E-3' Teen' Shoreline Sediment' 208-1S
- r ' Bone 3.32E-1 Child Fish (Ecttom Feeder) 208
. Liver 4.01E-1 Teen Fish (Bottom Feeder) 208 T. Body 2. 7 3E- 1-- Adult- Fish (Bottom Feeder) 208-Thyroid 6.96E-1 Adult Fish (Forager) 208 Kidney 1.34E-1 Teen Fish (Bottom Feeder) 208 Lung
'5.18E-2 Teen Fish (Bottom Feeder) 208
.GI-LLI '3.98E-1 Adult Fish (Forager) .208 O
O
, ./c r y N. TABLE 4.H hg. : 1988 ENVIRONMENTAL AND EFFLUENT DOSE -i l COMPARISON FOR LIQUID RELEASE PATHWAYS i l. Dose Rate- Critical
- Organ (mrem / year) Age Critical Pathway- '
i 1l l- Skin (Env.)- 8'. 01E Teen Shoreline Sediment h - Skin (Eff.)' '5.44E-2 Teen Shoreline Sediment Env/Eff.= 0.15:
.I Bone (Env.) .3.50E-l' Child Fish.(Bottom Feeder)
Bone (Eff.). 1.25E+0 Child Fish Env/Eff = 0.28 Liver.'(Env.) '4.36E-1 Teen -Fish (Bottom Feeder) .l Liver (Eff.) 1.57E+0 Teen- Fish 1 Env/Eff =-0.28 l T. Body (Env.) 3.06E-1. Adult Fish (Bottom Feeder) l. _ T. Body (Eff.) 1.09E+0 Adult Fish Env/Eff = 0.28 i [') Thyroid (Env.) 7.39E-1 Adult Fish (Forager)
'%'. Thyroid-(Eff.) .1.65E-1 Teen Fish Env/Eff = 4.48 Kidney (Env.) 1.64E-1 Teen Fish (Bottom Feeder)
Kidney (Eff.) 5.64E-1 Teen . Fish Env/Eff = 0.29 Lung (Env.) 7.74E-2 Child Fish (Bottom Feeder) Lung (Eff.) 2.62E-1 Teen Fish Env/Eff = 0.30 GI-LLI (Env.) 4.28E-1 Adult Fish (Forager) GI-LLI (Eff.) 1.82E+0 Adult Fish Env/Eff = 0.24 1 1 O l x___ _-__ - -_-- - _ _ _____-- ____ __ _ - i
l:< . f j
-)
( TABLE'4.I 1 /, - ._ 1
.N 1988 ENVIRONMENTAL AND EFFLUENT DOSE i COMPARISON FOR' GASEOUS RELEASE PATHWAYS Noble Gas-Exposure Summary {
l Dose Rate. Critical i
- j. Organ' (mrem / year) Age Critical Pathway.
Skin (Env.) N.G. Not Sampled N/A . N/A. Skin (Eff.) 2.04E+0 N/A Noble Gas Exposure-T. Body (Env.) N.G. Not Sampled ' N/A . N/A. T. Body (Eff.) .7.54E-1 N/A Noble Gas Exposure Iodine, Particulate, and Tritium Exposure Summary Dose Rate Critical Organ (mrem / year) Age Critical Pathway Bone (Env ) 1.16E-1 Child Broadleaf Vegetation Liver (Env.) 1.09E-1 Child Broadleaf Vegetation T. Body (Env.) 6.09E-2 Adult Broadleaf Vegetation Thyroid (Env.) 1.17E-1 Infant Milk Thyroid (Eff.) 2.84E-1 Child- Vegetation Env/Eff = 0.41 Kidney (Env.). 3.61E-2 Child Broadleaf Vegetation Lung (Env.) 1.83E-2 Child Broadleaf Vegetation CI-LLI (Env.) 4.08E-3 Adult Broadleaf Vegetation I
V(3 i SECTION 5. QUALITY ASSURANCE 5.1 DUKE POWER COMPANY'S ENVIRONMENTAL LABORATORY The Environmental Radiological Laboratory (ERL) participates in the' EPA Interlaboratory Comparison Program and the Duke Power corporate cross-check program. The EPA sample types include mixed gamma in water (2-3 times per year), mixed gamma in milk (1-2 times per year),. low-level iodine in milk (1-2 times per year), tritium in water (3 times per year) and alpha-beta in water (3-4 times per year). The ERL prepares and analyzes each sample as quickly as possible and performs and documents follow-up investigations should the data obtained by the ERL be out.of limits. The ERL code designation in the EPA program is "CP". The " "' corporate cross-check sample types-included mixed gamma in many forms (body-burden standards, Marinelli beakers, filters), alpha-beta on filters, and tritium in water. The frequency of each cross-check is variable. As with EPA checks, an investigation is performed and documented should the data not meet the acceptance criteria. In conjunction with the EPA and corporate quality assurance programs, the
.O' ERL has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily source checks ensure that the instruments are in proper working order and these checks are used to monitor instrument performance. Additionally, standards are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of limits.
f i To ensure that ERL data is accurate and reliable, two in-house assess-ments were performed in 1988 in order to demonstrate an ability and ) willingness to perform self-audits and also aid the ERL in performing its j duties. Additionally, a quality assurance audit was performed by Duke Power's Audit Division in 1988. A recommendation and unresolved item were identified and addressed by the ERL and corrective action was taken ) to enhance laboratory operation. l 5.2 CONTRACTOR LABORATORY
\
No contractor laboratories were used. l I 1 L l .D d 4 3RDH3102 5-1 l
g v 5.3 EPA INTERLABORATORY COMPARISON PROGRAM As described in Section 5.1, the ERL participates in the EPA Inter-laboratory Coinparison Program. The performance by the Laboratory is documented in Table 5.3-1. Of the thirty-nine analyses performed in 1988, three analyses were out of EPA limits (three normalized deviations). The missed analyses and actions-
-taken are described below.
5.3.1 Alpha / Beta in Water (Gross Beta on 1/22/88) Daily source checks were reviewed and were acceptable. Gross alpha results were acceptable. Data calculations were scruti - nized for errors with none detected. ' The procedure was repeated . , using the 1/22/88 cross-check and results yielded similar values I as originally reported. It was concluded that the ERL performed the analysis-as according to procedure, duplicating the incorrect gross beta results. Therefore, it is believed that an error may have occurred with' the EPA sample preparation. Three > other gross alpha / beta in water EPA cross-checks were conse-quently performed.in 1988, all'providing acceptable results for gross beta. 5.3.2 Low Level I-131 in Milk (2/26/88) O Instrument daily performance was reviewed and found to be acceptable. A detailed investigation was conducted and the ERL determined that due to required rounding of figures to whole - numbers, additional error was introduced. The acceptance range was unusually narrow, 0.69 pCi/L for 3-sigma, which is inap-propriate for low-level counting, known = 4 pCi/L. ERL has consistently performed well on intralaboratory low-level I-131 in milk with activities as low as 0.8 pCi/L. Thirty-five percent of reporting laboratories produced results greater than 3 sigma. 5.3.3 Gross Alpha / Beta Air Filter (3/25/88) Instrument daily performance was reviewed and found to be acceptable. Gross beta results were acceptable. Failed cross-checks were reanalyzed, yielding data consistent with original results. One other EPA filter was analyzed in 1988 yielcing acceptable results for gross alpha and gross beta. Since the alpha calibration filters were several years old, new gross alpha and gross beta filter calibration sources were requisitioned.' 1 O 3RDH3102 5-2
5.' 4 DUKE POWER COMPANY'S DOSIMETRY LABORATORY
\ Duke Power Company's Dosimetry Laboratory routinely participates in environmental dosimetry measurement programs with the State of North Carolina, and the United States Department of Energy (DOE). The Depart-ment of Human Resource's Radiation Protection Section conducts the state programs, while the federal program is conducted by the DOE Environmental Measurements Laboratory. Duke Power participated in the state program during 1988. State program results are found in Table 5.4-A. DOE program results from 1987 testing are found in Table 5.4-B. A brief description of the two programs follows:
North Carolina State Program - Conducted by the Radiation Protection Section of the Department of Human Resources every six to eight months for all nuclear facilities within the state. Environmental dosimeters are irradiated by the state, returned, and processed by the nuclear facilities, and results are compared to the estimated delivered exposure. DOE Program ' Sponsored by the DOE Environmental Measurements Laboratory every one to two years. Intercomparison program studies are international in scope, typically attracting 125 participants from thirty countries. The objective of these studies is to assess the state-of-the-art of environmental dosimetry as indicated by statistical analysis of the results. Participants compare their performance with the delivered exposures, and the performance of their counterparts in other laboratories. h The mini-intercomparison program for 1987 was a. departure from the regular intercomparison studies in that it evaluated observed differences between two calibration isotcpes routinely used in environmental dosimetry, Cobalt-60 and Cesium-137. Differences between these isotopes have been observed since the first intercomparison program (1974), with those calibrating with Cesium-137 reporting, on average, values approximately 6% below the delivered value. Those calibrating with Cobalt-60, though, report values in exact agreement with the delivered value. Participants having access to both isotopes were given the opportunity to compare dosimeters irradiations in a test environment. l l l 1RDH2107 5-3
I ,' ji ,! 1 l . Ii rrr
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iii I iiiii iiiiii iiiiii L; CCCCC CCCCCC CCCCCC C C CCC A ppppp pppppp pppppp p p ppp LM OG 73277 073677 370077 3 9 777 RI . . TS 86888 287488 386688 1 3 888 N 11 5 13 4 22 1 Y L O3 CMR C( NAE ER GGE AOH RT NP rrr O R eee INO ttt TOF lll CS E iii 1 EIS U LLLLL LLLLLL LLLLLL L L FFF
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3 OAL A iiiii iiiiii iiiiii i i iii 4 RPU V CCCCC CCCCCC CCCCCC C C CCC - 5 PMS ppppp pppppp pppppp p p ppp 5 OE N E L LCR A W O 94544 69069 251505 010922 151255 525521 5 6 7 600 125 B TYK N 1 3 11 2 11 7 A NRC K T EOE MTH NAC _ OR - ROS IBS 1 VAO 3 NLR 1 ERC - E I a
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l SECTION 6
) REFERENCES 6.1 Catawba Nuclear Station Units 1 and 2 Technical Specifications.
6.2 Duke Power Company Offsite Dose Calculation Manual. 6.3 Catawba Nuclear Station Final Safety Analysis Report. 6.4 Title 10, Code of Federal Regulations. 6.5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating
' Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.
6.6 Kocher, D.C., " Radioactive Decay Data Tables", 1981. 6.7 1988 Catawba Nuclear Station Annual Radioactive Effluent Release Report. O i I i O 6-1
l l APPENDIX A , ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at Catawba was required to ensure compliance to the , Station Technical . Specifications. Analytical procedures were employed to ensure that Technical Specification Detection capabilities were achieved. Environmental sampling and analyses were performed by the Duke Power Environmental Radiological Laboratory group. Starting at Appendix A.1 the remainder of this Appendix describes the environmental sampling and analysis procedures by media type. CHANGE OF ANALYSIS METHODS The Environmental Radiological Laboratory -(ERL) examined the calculational method for determining a sigma error associated with reporting tritium data. The new method incorporated for 1988 data is consistent with error reporting l methodology currently used for gamma spectroscopy. The previous method for reporting tritium error values was based on a linear regression extrapolation, while the new method uses a critical level calculation before performing a sigma error calculation. The change in methods will reflect ERL's attempt. to have similar reporting techniques, where applicable, for environmental' data. CHANGES TO CATAWBA SAMPLING PROGRAM-Groundwater - Due to the death of the owner, Mr. James Bolick, at groundwater site number 200, a replacement had to be found. The new site number 200 was changed to the residence of Mr. Robert Littlejohn which is in the same sector and approximate distance as Mr. Bolick. Sampling began at the Littlejohn's June 22, 1988. A.1 AIRBORNE PARTICULATE AND RADI0 IODINE Airborne particulate and radiciodine samples at each of 5 locations were composited continuously by means of continuous air samplers. Air particulate were collected on a particulate filter and radioiodines were collected in a charcoal certridge situated behind the filter in the Sdmpler. Filters and cartridges were collected weekly. A weekly gamma ; analysis and gross beta analysis was performed on eaQ filter and a j weekly gamma analysis was performed on each charcoal cartridge. l O 2RDH2156 A-1
l 1 l A.2 GROUND WATER
. ('q s-Ground water grab samples were collected quarterly f rom residential wells at 2 locations. A gamma analysis, low level I-131 analysis and tritium analysis was performed on each sample. One location had to be replaced in June (see explanation above).
A.3 DRINKING WATER l Drinking water composite samples were collected biweekly from each of 3 Drinking Water Treatment Plants. A low level I-131 analysis was performed on each biweekly sample. Two biweekly samples were composited to. form a monthly composite for each location and a gamma analysis and gross beta- analysis was performed on each monthly composite. Monthly composites were retained and composited quarterly for tritium analysis. A.4 SURFACE WATER Surface water composite samples were collected biweekly from each of 3 locations. A low level I-131 analysis was performed on each biweekly sample. Two biweekly samples were composited to form a monthly composite for each ' location and a gamma analysis was performed on each monthly composite. Monthly composites .were retained and composited quarterly for tritium analysis. A.5 MILK O b Milk grab samples were collected semimonthly. from 3 dairies. A low level I-131 analysis and a gamma analysis was performed on each sample. A.6 BROADLEAF VEGETATION Broadleaf vegetation samples were collected monthly from each of 4 locations. A gamma analysis was performed on each sample. A.7 SHORELINE SEDIMENT Shoreline sediment samples were collected semiannually from 3 locations. A gamma analysis was performed on each sample. A.8 FISH Three types of fish samples were collected semiannually from each of 2 locations. The types of fish collected represented a predatory fish, a i forage fish and a bottom feeder fish. A gamma analysis was performed on the edible portions of each sample. O 2RDH2156 A-2
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..... A.9 DIRECT RADIATION (TLD)'
"... 'Thermoluminescent dosimeters (TLD) were collected quarterly from each of 40 locations. The- TLDs were placed surrounding .the CNS site as follows:
Sixteen TLDs; were located in an inner ring, one TLD in -each' of. the
~
meteorological sectors, in the. general area of the site boundary. Sixteen 'TLDs were located in an outer ring, one TLD .in each of. the . meteorological sectors', at approximately 6 to 8 km from. the ' site boundary. .The remaining eight TLDs were placed in special . interest areas-
-(schools, recreation: areas) and control locations. A gamma dose and dose rate were reported quarterly for each location.
-A.10 ANNUAL' LAND USE CENSUS The 1988 ' CNS Annual Land 'Use. Census was conducted on August 1-5. The census - identified the ' location, within 8 km. of the station in each of -
the sixteen meteorological sectors, of the nearest residence, meat animal, I. cow, goat, and garden producing broadleaf' vegetation over an area greater than 50 square meters. The census included a visit to the nearest locations identified during
'the 1987 census. . For each sector, the areas between the 1987 locations and the site boundary were surveyed in order to ensure identification of
' the nearest current locations. Based upon the above findings' for each sector, the entire sector area within 8 km of the station was surveyed-whenever necessary. ,
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2RDH2156 A-3
w-4 1988'CNS ANNUAL RADIOLOGICAL ENVIRONMENTAL'0PERATING REPORT- Appendix B- ..
}i .Index
/d. Page l'of 1 APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF ANALYSIS RESULTS B.1 Airborne Radioiodines-and Particulate B.1.1 Radiciodines B.I.2' Particulate B.2 Ground Water B.3 Drinking. Water B.4 Surface Water B.5 Milk B.6 Broadleaf Vegetation: B.7 Shoreline Sedir.ent B.8- Fish B.9 Direct Gamma Radiation (TLD) 1. L a
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M v APPENDIX C rx CATAWBA NUCLEAR STATION l L SAMPLING DEVIATIONS Sample (location a) Date Reason
., A. Surface Water
- 1. (208) 1/13-1/27/88 Due to a blown fuse in' the water sampler, the composite holding tank was only 1/2 full.
Approximated actual sample dates were 1/13-1/20/88. Action: Fuse was replaced and an abbre-viated sample was obtained from the water available, e 2. (2161 5/4-5/18/88 A construction crew cut ()s the power line to the water sampler. The actual sample collection p6riod was 5/4-5/17/88. Action: An abbreviated sample was collected. CNS personnel were f notified to 'nitiate J repairs.
- 3. (208) 5/4-5/18/88 Due to a malfunction of the composite sampler, :
a composite sample ! could not be obtained. Actual sample date is 5/18/88. Action: A grab sample was obtained and the old sampler was replaced with a new one. l
]
-( )
C-1
- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ l
i
- 4. (215)- 11/16-11/30/88 No composite sample was X,rT collected during this I(,)J sampling period, due to power supply being terminated..The' actual sampling period was 11/16-11/28/88.
Action: An abbreviated sample was collected. An alternate means of power is being pursued.
- 5. (208) 11/30-12/14/88 Due to a blown' fuse a composite sample could not be obtained.
Actual sample date was 12/14/88. Action: Fuse was replaced and and sampler restored to use. A grab sample was collected.
- 6. (215) 11/30-12/14/88 No compositeJasmple could be collected due
) to lack of power.
Actual sample date was 12/14/88. Action: Grab sample obtained.
- 7. (215) 12/14-12/28/88 No composite sample could be obtained from this site. Power has been disconnected.
Actual sample date was 12/28/88. Action: Grab sample collected. B. Drinkino Water
- 1. (214) 12/30-1/13/88) Due to clogged and plugged tubing, a composite sample could not be obtained.
Actual sampling date
, was 1/13/88.
Action: Plugged end of tubing was removed. C-2 A grab sample was collected.
w;
- 2. '(218) 12/30-1/13/88 Due to clogged' tubing.,
a composite sample
- (~}f
\/ . % could not be obtained from.this site.
Actual sampling date was 1/13/88. Action: Clogged tub-ing.was removed and a grab sample was collected from th(s site.
- 3. (213) 1/13-1/27/88 Fort Mill water treatment facility requested the re-location of our sampling equipment to allow room for their new pumps to be in-stalled. The drinking water system was dis-connected on 1/18/88.
The actual sampling period was 1/13-1/18/88. () Action: An abbreviated sample was collected. Reconnection of the system is pending.
- 4. (213) 1/27-2/10/88 Relocation of the water sampler has not been completed. A new drain l line has not been in-stalled. Actual sample date was 2/10/38.
Action: Grab sample was.obtained. Comple-tion of work order is pending. l S. (213) 2/10-2/24/88 Relocation of water sampler has not been completed. A new drain is yet to be installed. l Actual sample date is 2/24/88. 1 C-3
Action: Grab sample r') taken. Completion of (_) work request is pending.
- 6. (213) 2/24-3/9/88 Relocation of water sampler has not been' completed. A new drain must be hooked up.
Actual sample date is 3/9/88. Action: A grab sample was obtained. Comple-tion of work order is pending.
- 7. (214) 2/24-3/9/88 Due to a weight slipping off the tubing, thus holding-the tubing in the airs no composite sample could be obtained. Actual.
sample date was 3/9/88. Action: Grab sample was taken at this
) location. Metal weight was replaced.
- 8. (213) 3/9-3/23/88. Relocation of water sampler has not been completed. New drain
~
needs to be hooked up. l:- Actual sample date was ! 3/23/88; [. ' Action: Grab sample obtained. Completion of work order pending.
- 9. (213) 3/23-4/6/88 Relocation of water sampler was completed on 3/31/88 with a new drain. Actual sample date was 4/6/86.
Action: Grab sample was taken from the incoming water line. Sampler was started at 13:00 on 4/6/88. 1 O C-4 s L a _______-- - ___-_ - - . _ _ _
- 10. (213) .4/6-4/20/88 The newly installed f'}
A_/ drain line fed into a meter pit. The sampler had to.be turned off at the request of'the-water plant manager. Actual sample date was, , 4/20/88. Action: Sampler was turned off at 13:30 on 4/7/88. A grab sample was collected on 4/20/88.
- 11. (218) 11/16-11/30/88 No composite sample was available, due to mal-function of pump head.
Actual sample date was 11/30/88. Action: Grab sample collected. Pump head and tygon tubing
, adjusted. Restarted
,-)g.
( sampler.
- 12. (214)' 11/30-12/14/88 No composite sample was available due to a blown fuse in the interval sampler.
Actual sample date was 12/14/88. Action: Replaced fuse and restarted sampler. Collected grab sample. C. Air Particulate and Radiolodine j l 1 (201) 6/8-6/15/88 Due to a blown fuse, j the sampler only ran i 99.2 hours. Actual 1 sampling period was 6/8-6/12/88. Action: The fuse was replaced and sampler restored to service. C-5 ! l I
mer - .
.'r jp I ,,
Anfabbreviated' sample-
- 2. :(205) 111/16-11/23/88
, : - .- wasLcollected due-to a b'<wn fuse. Sampler-e, .only ran for 123.5 h r s.
Actual sampliftg: period 1 was'11/16-11/21/88. I l Action: Replaced. fuse and restarted the sampler. j
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APPENDIX'C (continued) ]) f" -- CATAWBA NUCLEAR STATION- ! UNAVAILABLE' ANALYSES Some: unavailable analysis from the routine sampling and - analysis schedules occured during the year. .These unavailable analysesonre tabulated below: Samole'Clocation'#) Date Reason A. Environmental TLD
'1' . ( 22g )~ 3/17-6/16/88 TLD was. missing from the collection site.
Action: A new TLD was placed at the collection site.
- 2. ( 246 ) 3/17-6/16/88 TLD.was missing from the collection site.
Action: A new TLD was placed at-the collection site.
- 3. ( 234 ) 6/16-9/15/88. TLD-was missing from the collection site.
Action: A new TLD L was placed at the collection site.
- 4. C.235 ) 6/16-9/15/88 TLD was missing from the. collection site.
Action; A new TLD was placed at the collection site.
- 5. ( 251 ) 9/15-12/15/88 TLD was missing from regular collection site. The TLD had been j thrown away by the new tenant Action: TLD has been moved to the new Duke Power office in Clover, S.C., approximately 1 C-7 block away.
i APPENDIX D q v ANALYTICAL DEVIATIONS CATAWBA NUCLEAR STATION LOWER LIMITS OF DETECTION Two LLD's were' missed for all analyses performed at the Environmental Radiological Laboratory (ERL) in 1988 for the Catawba Nuclear. Station. At location 215, a surface water composite with a normal collection date of 4May-18May88, was a deviation that was not detected by the ERL. The actual collection period was 4May-17May88 at 1500 hours. The following two nuclides that exceeded their respective LLD's are listed below: NUCLIDE LLD REPORTED LLD REQUIRED Low-Level I-131 1.01 1.00 BaLa-140 15.6 15.0 Administrative methodology has been restructured by the ERL staff to alleviate any futher reoccurances of this type. A full year was incorporated with a new gamma analysis system, which became O
\~l operational! September 1, 1987, which will also continue to enhance ERL's analytical capabilities.
i O ! D-1 i
- - _ - _ - _ _ _ _ - = _ . __ _ _ _ , _ _ _ .
d1 f n a '1988'CNS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Appendix E
', /~' L " , Index 1 Page 1 of 3 9
1 APPENDIX E RADIOLOGICAL' ENVIRONMENTAL MONITORING PROGRAM ANALYSIS RESULTS E.1 Airborne Radioiodines and Particulate 4 E.1.1 'Radioiodines E.1.1.1 Location 200 E.1.1.21 Location 201 E.1.1.3 ' Location 205 E.1.1.4 Location 212-E.1.1.5 Location 217 E.1.2 Particulate [v f- E.1.2.1 Location 200 E.1.2.2 Location 201 E.1.2.3 Location 205 E.1.2.4 Location 212 i' E.1.2.5 Location 217 E.2 Ground Water E.2.1 Location 200 E.2.2 Location 252 E.3 -Drinking Water E.3.1 Location 213 E.3.2 Location 214 E.3.3 Location 218 E-1 I-
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j L. 1988 CNS ANNUAL' RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Appendix EJ 1 Index
-:f-'f;l i,
t .Page 2 of 3-E.4- Surface' Water ~
.E.4.1 Locat' ion 208
, E . 4~ . 2 Location 211 E i 4'. 3 . Location 215.
L . E.5 Milk E.5.1 Location 209-E.5.2 Location 219 E.5.3 Location 221-E.6 Broadleaf Vegetation E.6.1 ' Location 200-E.6.2 . Location 201 E.6.3 Location 217 E.6.4 Location 226
~
E.71 ' Shoreline Sediment-E.7.1 Location 208-IS E.7.2 Location 208-2S E.7.3 Location 208-35 i E.7.4 Location 210 l E.7.5 Location 215 E.8' Fish E.8.1 Location 208 ) E.8.2 Location 216 1 E.9 Direct Gamma Radiation (TLD) E-2
- -_---_-_-_____________________. 1
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. l i1988"CNS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Appendix E
<g(;_ 4 Index.
> c : 4 ,
-- Page 3 of 3:
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;jw APPLIED SCIENCE CENTER j j .
RADIOANALYSIS LABORATORYc _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _=_______________________- VAX/VMS Samole Analvsis- Reporti generated : 14-JUN-1988 14:35:03.
. P1' ant Name~ : CdS' Samole. Number V : 408
, Tyoe/ Location- : AIR RADIOIODINES / 200 Sample.Date .: ' 6-JAN-1988 12:01:00
- Acq. . Start Time 11-JAN-1988'1.:57:33 2 Sample.Quantit y : 576.000~M3
' Sample'ID s'30DEC.TO 6JAN88 Measurement Type : ROUTINE I
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma -MDA> Frac. of Nuclide Energy; (pCi/M3) Error req LLD Rpt. Level' 1 MN-54 834.83- < 1.351E-02 'O.OOOE+00 CO-58 810.76 < 1.360E-02 0.OOOE+00 FE-59 1099.22 < 2.685E-02 ^ 0.OOCE+00
- CO-60 1332.47' < 1.358E-02 0.OOOE+00
. - 2N-65 1115.52 < 3.534E 0.OOOE+00 .
.j ' NB 765.78 < 1.652E-02 0.OOOE+00 -
ZR-95 '756.72l < 2.713E-02 0.OOOE+00 I-131 364.48 < 1.493E-02 0.OOOE+00 CS-134 604.66 < B.440E-03 0.OOOE+00 CS-137 661.65 < 1.477E-02 0.OOCE+00 BALA-140 1596.49 < 2.17BE-02 0.OOOE+00 K-40 1460.75 0.344 0.118 Total Fraction of Reporting Leve'l O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than' si gn f or , gamma results means no peak was f ound and the zero error is not applicable., - Tritium. Alpha and Beta results are the best estimate of the actiYity and the less than sig#n indicates that the net activity is less than.the critical level, CL'. CL = 0.5 LLD 1 _ _ - - - ___-_____. =._ - . _ _ _ _ . =_______________________ Analyzedby_____jf$k__. __________,____ Approved by:_ M .A A_s.L. _ _____________ Date: _j_/_y_/pg____ ___________________m_____________..______________.___._________.m _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ _ _ _ _ _ __ . . _ _ _ _ _ _ _ _ _ _ .
. 1 /
I ' VAX/VMS~ Sampl eJ Analysis Report- generated 's 22-JAN-1988 "13: 32: Ou - q
.,Q ' Plant Name. : CNS Sample Number a 437 l Type / Location. : AIR RADIDIODINES / 200 Sample Date : 13-JAN-1988 11:45:00
~ Acq. Start .Ti me - : 18-JAN-1988-14:08:28 Sample Quantity : ,555.000 M3 Sample ID. : 6JANrTO 13JAN88-Measurement-Type. LROUTINE
--------------------------------- =-_-_ ----------------------_- _ -
c
***** Gamma-Spectroscopy Analysis'*****
Activity 1-Sigma . MDA > ~ Frac.'of V NuclideL Energy , (pCi/M3) Error- req LLD Rpt. Level MN-54 '834.83 < 1.099E-02 'O.OOOE+00 CO-58 810.76 < 1.283E-02 0.OOOE+00 FE-59 1099.22- < 8.126E-03 0.OOOE+00 i
-CO-60 1332.47 < l'.449E-02 0.OOOE+00
~ZN-65 1115.52 < 2.952E-02 0.OOOE+00 ,l NB-95. 765.78- <.1.250E-02 0.OOOE+00 2 2R-95' 756.72 <J3.OO1E-02 LO.OOOE+00
I-131. -364.48 < 1.293E-02 0.OOOE+00 i. CS-134 604.66- < 1.148E-02 0.OOOE+00
'CS-137 661.65 < 1.604E-02 0.COOE+00 BALA-140.
1596.49 < 2.268E-02 0.OOOE+00-g _--------- Total Fraction of Reporting Level 0.OOOE+00 l Anal yz ed ' by : _______ 2___ _____________
~ Approved by:_ _%[._ _______________ Date: _.j_/_.gg/__aglL__
S 4
Lib 7 > , l
I
____________________________________= ______-_ _--___________________ VAX/VMS Sample Analysis'Reportigenerat'ede: 25-JAN-1988 13:29:06 I
.- Ji 1 ($)' -- Plant'Namex CNS' .
SampleLNumber .
- 450 J'~ Type / Location : AIR RADIDIODINES'/L200 Sample,Date '
. : 20-JAN-1988 10:30:00
'Acq.' Start Time- : 25-JAN-1988.12:57:42' ,
Sample Quantity : :567.000 M3 Sample'ID~ .
- 13JAN TO 2OJAN88 L Measurement. Type :' ROUTINE g . ___________________________-- _______ - _ _ _ . _________________________
*****~ Gamma-Spectroscopy Analysis ~*****
Activity 1-Sigma' MDA>. Frac. of E ' Nuclide Energy (pCi/M3) LError req 1LLD;Rpt. Level MN-54 834.83L < '1.619E 0.OOOE+00
.CO-58 810.76 1< 1.529E-02 0.OOOE+00 FE-59 1099.22 <-3.741E-02 .O.OOOE+00 CO-60 1332.47 < 1.797E-02 0.OOOE+00 ZN-65 1115.52 < 3.738E 0.OOOE+00 NB-95 765.78 <18.367E-03 0.OOOE+00 2R-95 756.72 <'1.439E-02 0.OOOE+00
'I-131'. 364.48 < 1.'651E-02 0.OOOE+00 CS-134 604.66 <.1.196E-02 0.OOOE+00
-CS-137- 661.65 <:1.2OOE-02 0.OOOE+00
/T- BALA-140- '1596.49 "< 8.160E-03 0.OOOE+00 is-): K-40; 1460.75 0.171 7.887E-02 .
Total Fraction of Reporting Level 0.OOOE+00 l Analyzed by:__ __ ____ _________________ Approved by:__ g _[2 _ _____________ Date: __L /_gtE/_ m ._ _ 6
I, # [ ' ' e VAX/VMS Sample Analysis. Report generated s. ~2-FEB-1988.15:24:07 LP1 ant _ Name. : CNS Sample Number ' : 483 'i
' Type / Location : AIR-RADIOIODINES1/c200; l- l Sample Date : 27-JAN-1988 12:40:00 Acq.- Start-Time : ~
2-FEB-1988 14:52:23 4 Sample Quantity :. 648.000 M3 Sample ID : 2OJAN TO 27JAN88 j Measurement Type : ROUTINE i
***** Gamma-Spectroscopy-Analysis *****
a
~ Activity 1-Sigma MDA>- Frac..of ;
Nuclide- Energy .
-(pCi/M3) Error req-LLD Rpt. Level-MN-54 834.83 <.1.074E-02 0.OOOE+00 CO-58 810.76~ < 1.541E-02 0.000E+00 FE-59 l1099.22 <~3.305E-02 0.OOCE+00 1 CD-60 1332.47 < 1.208E-02 0.000E+00 ZN-65 .1115.52 < 3.096E-02 0.OOOE+00 -s NB-95 765.78 < 1.089E-02 0.000E+00
-2R-95 756.72 < 2.078E-02 0.OOOE+00 I-131 364.48 < 1.453E-02 0.000E+00 CS-134 604.66 < 1.104E-02 0.OOOE+00 CS-137- -661.65 :< 1.456E-02 0.000E+00 BALA-140 1596.49. < 7.533E-03 0.OOOE+00
- (} Total Fraction of. Reporting Level O.000E+00
~
r
.Analy::ed by:- _ _rf\ h _____
'l Approved by _ A L _ M 1 ___________
Date: __2_. / _.,s_ / _(9_ _ __
'I
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c-t .
-= -
7 - - - - - ;--- e .
= " .'VAX/VMSLScmple' Analysis R: port gsnaratsd - L .5-FEB-1988 11:40:37 L ;
k 1 Plant Name : CNS. .y . Sample Number r . : 497.. . ( l(y x)..
~ Type / Location " ' AIR RADIDIODINES / 200 M'o Sample'Date :- '3-FEB-1988.09:30 OO l - Acq. . Start: Time. '5-FEB-1988.11:09:41 E "
- Sample.~ Quanti ty- 1488.OOO'M3 Sample.ID . 27JAN TO 3FEBB8
-Measurement Type s ROUTINE-
. ;f ,
-***** . Gamma-SpectroscopyLAnalysis *****
Activity. 1-Sigma MDA> Frac. of. Nuclide. ' Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83. < 2.179E-02 'O.OOOE+00 CO-58 '810.76 < 2.214E-02 0.OOOE+00 FE-59 1099.22 <L5.032E-02 -0.OOOE+00 CO-60 1332.47 < 4.184E-02 0.OOOE+00 ZN-65 1115.52 < 6.180E-02 0.OOOE+00-NB-95 765.78 < 2.730E-02 O.OOOE+00 ZR-95 756.72 < 3.152E-02 0.OOOE+00 I-1314 364.48 . <11.705E-02 0.OOOE+00 CS-134 604.66 < 1.670E-02 0.OOOE+00
. CS-137 661.65 t< 1.925E-02 0.OOOE+00 BALA-140 1596.49 .< 3.027E-02 0.,000E+00 >
p - K-40 1460.75 0.528 0.122. Analyzed by:_Q _ _ w_ _ _ Approved by:___ M _[_ ____2__ ____ Date: _ _& / _f_ / _ _Lild __ t t o
m . s h!- "f. I e s e m
- j# ' t s,
VAX/VMS' Sample' Analysis Reoort generated?:"23-FEB-1988 07:58:5i s"%y .
-o Plant Na'me -s' CNS.
iSampie' Number: !517 Type / Location' : . AIR RAD 10 IODINES / 200 Sample-Date. s'10-FEB-1988 11:45:00-Acq. Start Time : 16-FEB-1988 09:28:01-
' Sampl e . Quantity- : 615.000 M3 Sample ~ID- .
- 3FEB TO 10FEB88
. Measurement Type : ROUTINE-
-_-------------_----- __ - -- - - - - - - - = - - - - - - - ----- ------------
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma. MDA> Frac. of-
, 'Nuclide Energy. .(pCi/M3) Error -- reg LLD Rpt. Level MN-54 834.83 < 1.268E-02 0.000E+00 CO 810.76 < 9.939E-03 0.000E+00 FE 1099.22 <-2.955E-02 0.000E+00 CD-60 1332.47 <'1.273E-02 0.000E+00 ZN-65 1115.52 < 2.744E-02 0.000E+00
'N9-05 '765,78 < 1,595E-02 0.000E+00 ZRi951 756.72 < 2.384E-02 0.OOOE+00
~I-131 364.48 < 1.646E-02 0.000E+00 CS-134 :604.66 < 1.149E-02 0.000E+00 C' CS 2 137 661.65 < 1.208E-02 0.000E+00-
-/"" .BALA-140 1596.49 < 2.138E-02 0.OOOE+00
\ ,K-40. 1460.75- 0.295 7.828E-02.
= _ _ --
Total Fraction of Reporting Level 0.000E+00 Analyzed bys____)hh_ _ _______ Approved by:_ M _f._ _ _ _ _ ____________ Date: _A _E / / __ste___ 1
4 . [f. -
- = _ _ - -
[VAX/VMSLSample_ Analysis Report generated t 24-FEB-1988 13:34:50' (r
'k T.
lr . . ..
- Plant Name:- z.CNS Sampie; Number -- : L534
( Type'/ Loc at i on : . AIR RADIDIODINES /'200 Sample Date', : 17-FEB-1988 10:30:00-Acq. . Start. Time _': 22-FEB-1988 14:47:06 Sample-Quantity- 460.000 M3_-
- Sample ID.... : .10FEB:TO:17FEB88 Measurement Type;_:. ROUTINE
=- _ _. _____________
***** Gamma-Spectroscopy Analysis *****
. Activity 1-Sigma MDA> Frac. of'
- Nuclide ' Energy - (pCi /M3)'. '
Error req LLD Rpt. Level
~MN-54J 834.83 <L2.614E-02 0.OOOE+00 CO 810.76!l<?1.846E-02 0.OOOE+00 FE-59' 1099.22 <-3.134E-02 0.OOOE+00 CO-60' . 1332.47 .<-2.746E-02 0.OOCE+00 ZN-65 1115.52 '< 5.172E 0.OOOE+00
- NB-95 765.78~ <'1.998E 0.OOOE+00
- ZR -75 ; 75f'. 73 C 4,.490E-0? O.OOOE+00 I-1314 364.48 .< 2.627E-02. O'OOOE+00 .
CS-134 604.66 < 1.473E-02 0.OOOE+00 CS-137. 661.65 < 2.814E-02. ~0.OOOE+00' f (' i ~BALA-140 1596.49- '< 4.934E-02 0.OOOE+00 3.F ' K-40 1460.75 0.645 0.129
, Total Fraction of Reporting Level O.OOOE+00 y - Analyzed by:_ % ________________
AP proved by: __ M _[__ . _ _________ Date: _2 / ,,,,gg / __gi__ 0
%A
__ ____m__.__________m._._
I ( _______________________________________________________ -______________j
, , .VAX/VMS Sample. Analycio R2 port gansrated : 3-MAR-1988 09:14:43" l
- /-C Plant Name- : CNS L( f. . Sample Number : 571
- AIR RADIDIODINES / 200
^
Type / Location ,
; Sample Date : 24-FEB-1988 10:55:OO l Acq. Start Time : 29-FEB-1988 13:38:55 Sample-Quantity 501.000 M3 , ,
Sample ID
- 17FEB TO 24FEB88 *
{
- 1 Measurement Type t.____________________'OUTINE .__________________________________________________
***** Gamraa-Spectroscopy Anal ysi s ***** l Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. . Level MN-54 834.83 < 2.057E-02 0.OOOE+00 CO-58 810.76. < 1.586E-02 0.OOOE+00 FE-59 1099.22 < 4.973E-02 0.OOOE+00 CO 1332.47 < 1,513E-02 0.OOOE+00 ZN-65 1115.52 '< 3."36E-02 0.OOOE+00 NB-95 765.78 < 1.725E-02 0.OOOE+00 ZR-95 756.72' < 2.370E-02 0.OOOE+00 .
I-131 364.48 < 1.896E-02 0.OOCE+00 CS-134 604.66 < 1.558E-02 0.OOOE+00 CS-137 661.65 < 1.869E-02 0.OOOE+00
' BALA-140 1596.49 < 2.488E-02 0.OOOE+00 K-40 1460.75 9.681E-02 9.639E-02
'( } Total Fraction of Reporting Level' O.COOE+00 Analyzed by: __ _ f _____ ___
Approved by:__ g _(_ - ________ Date: _1 / _3_/_dg___ b O l
, 1 sr; . ... ----------------------------------------------------------------------
E' - .VAX/VMS'Samplo.Ab'alysis Rsport gznrrated.a 9-MAR-1988 15:35:19 Plant'Name CNS a n' . Sample Number : 593
(,); Type / Location 's AIR RADIDIODINES / 200 Sample Date : 2-MAR-1988 10:00:00 Acq. Start Time :- 9-MAR-1988 15:04:05 -)
Sample Quantity . 603.000 M3 Sample ID 24FEB TO 2 MAR 88 : Measurement Type s' ROUTINE .,
***** Gamma-Spectroscopy. Analysis:*****
-l f
' Activity 1-Sigma MDA> ' Frac. of Nuclide. Energy- (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.184E-02 0.OOOE+00' CO-58 810.76 < 1.460E-02 0.OOOE+00 FE-59 1099.22 < 2.653E-02 0.OOOE+00 -
CO-60 1332.47- < 2.138E-02 0.OOOE+00
.ZN-65 '1115.52. < 2.733E-02 0.OOOE+00 NB-95 765.78 < 1.031E-02 0.OOOE+00
'ZR-95 756.72 < 1.747E-02 0.OOOE+00 I-131 364.48 < 1.969E-02 0.OOOE+00
~
CS-134 604.66 < 1.204E-02 0.OOOE+00 - CS-137- 661.65 < 1.410E-02 0.OOOE+00 BALA-140 1596.49 < 2.953E-02 0.OOOE+00 K-40 1460.75 0.375 8.185E-02 [~ Total Fraction of Reporting Level O.OOOE+00 I Analyzed by:____ G Approved by:_ M __[._ _ ____ Date: _,,,,,1/_2_/__@@__ / i l e i l 1
, j
M, .
- - - - - - - - - - - - - - - ------ - _ _-,--------------------= -------____
' "; .VAX/VMS' Sample Analysin ' Raport ' gsnarated : 18-MAR-1988 13:58: 11 Plant Name : CNS Sample Number - 613 ps_)p2
. Type / Location : AIR RADIDIODINES./ 200 Sample Date : _
9-MAR-1988 12:OO OO Acq. Start Time : 15-MAR-1988111:36:54 Sample Quantity- : 549.000 M3 Sample ID : 2 MAR TO 9MARBB Measurement Type : ROUTINE
----- .------ =- ------ ------. - - - - - - - -
'***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level-MN-54 834.83 < 1.692E-02 0.OOOE+00 CD-58 810.76- < 1.460E-02 0.OOOE+00. FE-59 1099.22 < 8.'245E-03 0.OOOE+00-CO-60 1332.47 < 2.254E-02 0.OOOE+00 ZN-65 1115.52- < 3.849E-02 0.OOOE+00 NB-95 '765.78 < 1.474E-02 0.OOOE+00 ZR-95 756.72 <'2.878E-02 0.OOOE+00 1-131 364.48 < 1.806E-02 0.OOOE+00 __
' CS-134 604.66 < 1.198E-02 0.OOOE+00
- CS-137 661.65 .< 1.697E-02 0.OOOE+00 BALA-140 1596.49 < 2.417E-02 0.OOOE+00 K-40 1460.75 'O.518 9.975E-02
( ; Total Fraction of Reporting Level O.00 +00-Anal y:ed ' by: _ _____ umyy_________ J Approved by:__ M _b_ __ _____ Date: __)_ / _ff_ / _33___ t 0
- t. < =
1 ,
~
=----- -------------------------. - - - -
i# '
- OUKE POWER COMPANY.
.. r4y APPLIED SCIENCE: CENTER.
{p }$_,1? RADIDANALYSIS LABORATORY
~ VAX/VMS : Samole Analysis Report generated. : H15-JUN-1988 09:01:54-Plant'Name : CNS g Sample Number : 633 '
Type / Location : AIR RADIDIODINES / 200
> < Sample Date : 16-MAR-1988 11:01:00
'Acq.-~ Start Time : 22-MAR-1988 11:58:23
- g. . Sample Quantity : 567.000 M3
- 9 MAR TO 16 MAR 88
'~
Sample'ID:
. Measurement-Type :. ROUTINE
..---------- - - - - - - - - - - - - - - - - - - - __ _ __. = _ = .
***** Gamma-Spectroscopy Anal ysi s *****
. Activity 1-Sigma MDA>. Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level
~MN-54 834.83. < 1.085E-02 'O.OOOE+00 CO-58 810.76 < 9.648E-03 0.OOOE+00 FE-59 1099.22 < 3.847E-02. 0.OOOE+00 L
CO-60' 1332.47 < 2.121E-02 ' O.OOOE+00 ZN-65 1115.52 .< 2.769E-02 0.OOOE+00 .
] ) NB-95 765.78 < 1.209E-02 0.OOOE+00 -
ZR-95 756.72 < 2.543E-02 0.OOOE+00 I-131 364.48- < 1.643E-02 0.OOOE+00 CS-134 604.66 < 6.755E-03 0.OOOE+00
.CS-137- 661.65 < 1.193E-02 0.OOOE+00 BALA-140 1596.49 < 2.017E-02 0.OOOE+00 Total Fraction of. Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec , LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the ero error is not applicable.
. Tritium, Alpha and Beta results are the best estimate of the n indicates that the net activity is less activity than theand critical the less level,thanCL. sig/ CL = 0.5 LLD Analyzed-bys__sf/(________________________
Approved by:__ & ,1 h_. & _________ ____ Dates _ _Q / LJ~_ / be _ _ _ _
" no, *
. =,( *
= - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ ___ .-
[VAX/VMS Sample Analysis Report generated 131'-MAR-1988'11:32:17 s. 7.. Plant'Name ' s'CNS Sample ~ Number, s.670
- t 7 Type / Location : ' AIR RADIDIODINES / 200 Sample Date- : 23-MAR-1988 13:00:00-Acq.'St' art TimeL : 30-MAR-1988 08:35:10' LSample Quantity ': 592.000-M3-Sampl e .ID. : 16 MAR TO 23 MAR 88
- -Measurement Type s' ROUTINE
*****-Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide. Energy (pCi/M3) Error ' reg LLD Rpt. - Level
.MN-54' 834.83- <. 1.205E-02 0.OOOE+00.
CO-58 810.76 < 1.346E-02 0.COOE+00.
.FE-59 1099.22 < 3.353E-02 0.OOOE+00' CO-60 1332.47. < 1.563E-02 0.OOOE+00 ZN-65 1115.52- < 3.107E-02 0.OOOE+00 NB-95 765.78 < 1.198E 0.OOOE+00 2R-95 756.72. < 1.991E-02 0.OOOE+00 I-131' 364.48 < 1.472E-02 0.OOOE+00 CS-134 604.66 <'1.138E-02 0.OOOE+00 CS-137 661.65 < 1.369E-02 0.OOOE+00 y"N BALA-140 =1596.49 < 2.273E-02 0.OOOE+00 y -_--------
O.OOOE+00
~
Total Fraction of Reporting Level 4 Analyzed by: _ _ 2 _ _'_ _ _ ___________ Approved by:__ M _[_ ___ ._________ Date: _ J_ / _3!_ / _#_8__ ,_ l l
s,
= ;( ,
y _________ __=___________________________________________________________
.VAX/VMS Sample Analysis Report : generated : 20-APR-1988 11:42:le-
<r J-. \[^ x-Plant Name : CNS ' Samole Number: : 720'
; Type /Locati on L : AIR RADIDIODINES /'200 Semple Date- :-30-MAR-1988 11:20:00' .
Acq. Start Time :- 5-APR-1988 12:52:25
' Sample Quantity : 565.000 M3
- Sample ID : 23 MAR TO 30 MAR 88
.MeasurementfTypel: ROUTINE.
***** Gamma-Spectroscopy. Analysis *****
Activity 1-Sigma MDA> Frac.fof-Nuclide' Energy' _ ( pCi/M3)' Error req LLD Rpt'. Level
- MN-54 834.83 < 1.255E-02 0.COOE+00-CO-58 810.76 < 1.420E-02 0.OOOE+00 FE-59 1099.22- < 4.205E-02 0.OOOE+00 0.OOCE+00 CO-60. 1332.49. < 2.190E-02 ZN-65 1115.52'=< 4.062E-02 0.OOOE+00 .
NB-95 ~765.79: .< 1.874E-02 0.OOGE+00 2R-95 756.72 < 2.343E-02 0.OOOE+00 I-131 364.40- < 2.170E-02 0.OOOE+00 CS-134 604.70 < 1.279E-02' O.OOOE+00 CS-137. 661.65- < 1.647E-02 0.OOOE+00 BALA-140- 537.32 < 5.404E-02, O.OOGE+00
}1 __________
Total Fraction of Reporting Leve11 0.OOOE+00 t m Analyzed by:___________ _. _______ p
- Approved by
- _____ sm IS _ ________________
Date: _f_/4q_/EE____ i i, l l
VAX/VMS Sample Analysis Report generated : 20-APR-1988 11:43:13 i ). LJ Plant Name : CNS ~ Sample Number : 740 Type / Location : AIR RADIDIODINES / 200 Sample Date : 6-APR-1988 09:05:00 Acq. Start Time : 8-APR-1988 11:57:13 Sample Quantity : 588.000 M3 Sample ID : 3OMAR TO 6APR88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1 --Si g ma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.315E-02 O.OOOE+00 CO-58 G10.76' < 7.928E-03 O.OOCE+00 FE-59 1699.22 < 2.363E-02 O.OOOE+00 CO-60 1332,49 " 2.102E-02
, O.OOGE+00 ZN-65 1115.52 < 2.640E-02 0.OOOE+00 NB-95 765.79 < 1.107E-02 0.OOOE+00 ZR-75 756.72 < 2.140E-02 0.OOOE+00 I-131 364.48 < 8.736E-03 0.OOOE+00 CS .134 604.70 s 9.128E-03 O.OOOE+00 A CS-13'7 661.65 < 1.119E-02 0.OOOE+00 kh BALA-140 K--4 0 537.32 < 2.734E-02 1460.81 O.303 0.OOOE+00 7.339E-02 Total Fraction of Reporting Level O.OOOE+00 Analyzed by:____________ _ _ _.g _ _ _ _ , , _ _ _
P Approved by:__ Date: _f_/.20,__4-r_ o q 1 l 1 l f
__ VAX/VMS Samo. le Analv. sis Reoort c. enerated : 20-APR-1989 07:48:L I 1
\.J Plant Name : CNS Samole Numoer : 768 Tvpe/ Loc ati on : AIR RADIOIODINES / 200 Samole Date : 13-APR-1988 11:32:00 Aca. Start Time : 19-APR-1988 15:32:45 Samole Quantitv : 593.000 M3 Sample ID : 6APR TO 13APR88 Measurement Tyoe : ROUTINE
***** Gamma-Spectroscopy Analvsis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rot. Level MN-54 834.83 < 1.647E-02 0.OOOE+00 CO-58 810.76 < 1.354E-02 0.COOE+00 FE-59 1099.22 < 2.614E-02 O.OOOE+00 CO-60 1332.49 < 1.594E-02 0.OOOE+00 ZN-65 1115.52 < 2.168E-02 0.OOOE+00 , NB-95 765.79 < 1.533E-02 0.COOE+00 ZR-95 756.72 < 1.928E-02 0.OOOE+00 I-131 364.48 < 1.519E-02 0.OOOE+00 l CS-134 604.70 < 8.883E-03 O.OOOE+00
/'} CS-137 661.65 < 9.465E-03 0.OOGE+00
\_/ BALA-140 537.32 < 3.678E-02 0.OOOE+00 '
K-40 1460.81 0.331 7.583E-02 Total Fraction of Repor-ting Level O.OOOE+00 Analvred by: _________ _. ____~_______ Approved by:____ M /_._ ._____ ___.________ Date: _/_ / .Ag_ / _f.jl_ _ _ ' 4 l 1 r~T l (/ )
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ = - - _ =___- ______= .________ _ . _ _ _
.VAX/VMS Scmplo Analycio Rnport gansratgd : 26-APR-1988 07:48:44 Plant Name : CNS
(~N, Sample Number : 790 A._) . Type / Loc at i on : AIR RADIOIODINES / 200 Sample Date : 20-APR-1988 09:39:00 Acq. Start Time : 25-APR-19BB 14:49: 29 Sample Quantity 536.000 M3 Sample ID : 13APR TO 20APR88 Measurement Type : ROUTINE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - _ _ _ _ _ _ _ _ - ___- ._____________
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac, of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 9.886E-03 0.OOGE+00 CD-58 810.76 < 8.130E-03 0.OOOE+00 .. FE-59 1099.22 < 7.236E-03 0.OOOE+00 CO-60 1332.49 < 1.262E-02 0.OOOE+00 ZN-65 1115.52 < 2.078E-02 0.OOOE+00 NB-95 765.79 < 1.578E-02 0 OOOE+00 ZR-95 756.72 < 2.497E-02 0.OOOE+00 I-131 364.48 < 1.366E-02 0.OOOE+00 CS-134 604.70 < 1.273E-02 0.OOOE+00 CS-137 661.65 < 1.129E-02 0.OOOE+00 BALA-140 537.32 < 5.446E-02 0.000E+00 K-40 1460.81 0.347 7.762E-02 () Total Fraction of Reporting Level O.OOOE+00 Analyzed by ___ _ Approved by:_ __ __ _ _______________ Date: _ /_4L/__!6__ 1 I l l
/^T V
- i. j l 1 OUKE POWER COMPANY !
- APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
)
mmmmm um .mmmmme e-__--mm-mme mummme mm__mmm-mmm =_. . VAX/VMS Samole Analysis Report gene ~ rated : 3-MAY-1988 12:47:15 j Plant Name : CNS Sample Number : 816 Type / Location : AIR RADIOIODINES / 200 Sample Date : 27-APR-1988 11:00:00 Acq. Start Time : 29-APR-1988 14:16:49 Sample Quantity : 575.000 M3 l Sample ID : 20APR TO 27APR88 i Measurement Type : ROUTINE j m-- m =___mm - _ = m__mem__mmm_mmmm____ _mem_m_m_
***** Gamma-Spectroscopy Analysis *****
Activity 1-Si gma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.470E-02 0.OOOE+00 CO-58 810.76 < 1.183E-02 0.COOE+00 FE-59 1099.22 < 2.935E-02 0.OOOE+00 CO-60 1332.49 < 2.317E-02 0.OOOE+00 2N-65 1115.52 < 3.224E-02 0.OOOE+00 h NB-95 765.79 < 1.357E-02 0.OOOE+00 ("J k- 2R-95 756.72 < 2.500E-02 0.OOOE+00 I-131 364.48 < 1.103E-02 0.OOOE+00 CS-134 604.70 < 9.681E-03 0.OOOE+00 CS-137 661.65 < 1.177E-02 0.OOOE+00 BALA-140 537.32 < 5.094E-02 0.OOOE+00 _m_m fotal Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma i f results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the l activity and the less than si gn indicates that the net activity is less) than the critical level, CL. CL = 0.5 LLD mmmmmmmmmmmmmmmmmmmmmmmm__mmmmmm m m m m m m m m m m m m m - -- - - - - - - - - "- "- - _ _ m sem em m_ m _ m Approved by: M_[_ __ _ _ _ _ _ _ _ _ _ Date: __S_/_[_/_fp___ n s-L- __ _ _ _
1 _____---- - = _ - - - - ____ _ _ - - _ - - _ _ - - - _ _ - - - - _ - _ - - _ - _- -____--_----_--__ OUKE POWER COMPANY
' APPLIED SCIENCE CENTER , ; RADIDANALYSIS LABORATORY V]. '
VAX/VMS Samole Analysis Report generated : 6-MAY-1988 14:51:30 Plant Name : CNS Samole Number : 826 Tyoe/ Location : AIR RADIOIODINES / 200 Sample Date : 4-MAY-1988 09:00:00 Acq. Start Time : 6-MAY-1988'12:56: 32 - Sample Quantity : 563.000 M3 Samole ID : 27APR TO 4MAYG8 Measurement Type : ROUTINE -
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rot. Level MN-54 834.83 < 1.441E-02 0.OOOE+00 CO-58 810.76 < 1.2OOE-02 0.OOOE+00 FE-59 1099.22 < 3.504E-02 0.OOOE+00 CO-60 1332.49 < 4.412E-03 0.OOOE+00 ZN-65 1115.52 < 3.307E-02 0.OOOE+00 r- NS-95 765.79 < 1.398E-02 0.OOOE+00 (_T ) ZR-95 756.72 < 2.138E-02 0.OOOE+00 I-131 364.48 < 6.863E-03 0.OOOE+00 CS-134 604.70 < 8.295E-03 0.OOOE+00 CS-137 661.65 < 1.543E-02 0.OOOE+00 BALA-140 537.32 < 2.491E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 \ Gamma results are listed as Less Than Levels using Tech Spec LLD ecuation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not aoplicable. Tritium, Aloha and Beta results are the best estimate of the activitv-and the less than sign indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD eup * .my _____m,_y Approved by:__m M j._ _____________ Date: _5_/_g_/__f@__ o o I i 1
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY fm ------------------------------------------------------------------------- As - VAX/VMS Samole Analysis Report generated : 18-MAY-1988 11:00:12 Plant Name- : CNS-Samole Number 854 Tyoe/ Location : AIR RADIGIODINES / 200 Sample Date : 11-MAY-1988 11:30:00 Aca. Start Time- : 17-MAY-1988 14:38:29 Sample Quantity : 651;O00 M3
-Samole ID i 4MAY TO 11MAY88 Measurement Type : ROUTINE
***** Gamma-Soectroscopv Analvsis *****
Activity . 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83--< 1.2OOE-02 0.OOOE+00 CO 810.76 < 7.430E 0.OOOE+00 FE-59 1099.22 < 2.759E-02 0.OOOE+00 CO-60 1332.49 < 4.229E-03 0.COOE+00 ZN-65 1115.52' < 3.391E-02 0.OOOE+00 NB-95 765.79 < 1.297E-02 0.OOOE+00 ZR-95 756.72 < 2.345E-02 0.OOOE+00 I-131 364.48 < 1.095E-02 0.OOOE+00 "O CS-134-CS-137 604.70 < 8.78BE-03 0.OOOE+00 661.65 < 1.191E-02 0.COOE+00 BALA-140 537.32 < 5.428E-02 0.OOOE+00 K-40 1460.81 0.301 6.910E-02 Total Fraction of Reporting Level O.COOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD t equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Aloha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD
.----------------- --- .---------- _- =_----------------------
1 _L l Analyzed o.y _____ ;____ __ -___ Approved by:__ M I- _______________ Date: _5_/lf_/_gf___ l (1) I 4 l i l _ - _ _ _ _ _ _ - _ _ . -- _ _ b
W 1 DUKE POWER COMPANY APPLIED' SCIENCE CENTER , RADIDANALYSIS LABORATORY 3
,f. VAX/VMS . Sample Analysis ; Report generated 3.31-MAY-1988 13:18:18 Plant Name : CNS .
Sample Number 876 Type / Location : AIR RADIDIODINES / 200 Sample Date '18-MAY-1988 10:05:00
.Acq., Start Time : 24-MAY-1988 11:50:43 Sample Quantity : 602.000 M3 Sample.ID. : 11MAY TO 18MAY88
-Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> . Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.754E-02 0.OOOE+00 CO-58 810.76 < 1.673E-02 0.OOOE+00 FE-59 1099.22 < 3.116E-02 0.OOOE+00 CO-60 1332.49 < 3.162E-02 0.OOOE+00 ZN-65 1115.52 < 4.830E-02 0.OOOE+00 NS-98 765.79 < 1.511E-02 0.OOOE+00 ZR-95 756.72 < 3.349E-02 0.OOCE+00 1-131 364.48 < 2.210E-02 0.OOOE+00 () .CS-134 CS-137 604.70 661.65 1.392E-02 2.012E-02 0.OOOE+00 0.OOOE+00 BALA-140 537.32 < 6.829E-02 0.OOOE+00 K-40 1460.81 0.729- 0.146 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. r Tritium, Alpha and Beta results are the best estimate of the f' activity and the less than sign indicates that the net activity is less ! than the critical level, CL. CL = 0.5 LLD l l Analyzed by:_C t% _ _ I p % ________ Approved by:___ M k _ ______________ Date: _f_/_f_/_@S___ L l O 1 L. 1 _ _ _ _ _ - _ _ _ - - _ . _ _ _ . _ :.. 1
- 7"I4 *
".________.r_:.=____'__
l DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY gr - ____ - -______________________ _____ ____-_________________________
\ VAX/VMS Sample Analysis Report generated 6-JUN-1988 13:13:16 Plant Name : CNS _
Sample Number : 896 Type / Location : AIR RADIOIODINES / 200 Sample Date : 25-MAY-1988 10:50:00 Acq. Start Time 1-JUN-1988 09:05:12 Sample'Ouantity 2 501.000 M3 Sample ID : 18MAY TO 25MAY88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi /M3) Error req LLD Rpt. Level MN-54 834.83 < 1.427E-02 0.OOOE+00 CO-58 810.76 <'1.228E-02 0.OOOE+00 FE-59 1099.22 < 2.481E-02 0 OOOE+00 CO-60 1332.49 < 1.887E-02 0.OOOE+00 2N-65 1115.52 < 4.185E-02 0.OOOE+00 NB-95 765.79 < 2sO95E-02 0.OOOE+00 2R-95 756.72 < 2.294E-02 0.OOOE+00 . I-131 364.48 < 1.878E-02 0.OOOE+00 (r'T) CS-134 604.70 < 1.106E-02 0.OOOE+00 CS-137 661.65 < 1.796E-02 0.OOOE+00 BALA-140 537.32 < 7.497E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 i Gamma results are. listed as Less Than Levels using Tech Spec LLD l equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. 1 l Tritium, Alpha and Beta results are the best estimate of the j activity and the less than sign indicates that the net activity is less l than the critical level, CL. CL = 0.5 LLD _ - _ _ _ _ _ - - - _ _ _ _ _ _ - - - _____________-----=-- _______________ l Analyzed bys__ ___ _ __ ________ __ j Approved by: M__I . _ ;________________ Date: _4_/_f_/__L___ SS l l i O 9 ---m_-_
OUKE POWER COMPANY ' APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY l ()~ AX/ MS Sanole Analysis Report oenerated 9 JUN 1988 10 05 17 Plant Name : CNS _ Sample. Number : 916 Type / Location : AIR RADIGIODINES / 200 Sample Date : 1-JUN-1988 09: 35: 00 l Acq. Start Time : 8-JUN-1988 09:46:31 Sample Quantity 637.000 M3 i Sample ID : 25MAY TO 1JUN88 Measurement Type : ROUTINE _ _ _ _ - - - _ _ _ _ _ _ _ _ - - - _ _ _ = - .
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 7.526E-03 0.OOOE+00 CO-58 810.76 < 1.120E-02 0.OOOE+00 FE-59 1099.22 < 7.181E-03 0.OOOE+00 CO-60 1332.49 < 1.721E-02 0.COOE+00 ZN-65 1115.52 < 3.158E-02 0.OOOE+00 NB-95 765.79 < 1.523E-02 0.OOOE+00 ZR-95 ~756.72 < 2.440E-02 ' O.OOOE+00 I-131 364.48 < 1.334E-02 0.OOCE+00
/ CS-134 604.70 < 1.199E-02 0.OOOE+00
\ CS-137 .661.65 < 1.046E-02 0.OOCE+00 BALA-140 537.32 < 4.308E-02 0.OOOE+00 K-40 1460.81 0.356 7.598E-02 Total Fraction of Reporting Level O.OOCE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD g
equation. LLD = 4.66 SQRT B/t. Presence of less than sign'for gamma results means no peak was found and the zero error is not applicable.
, Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
______________________________j__y'_______===== _________________
- 8 Analyzed by _ _ ______ _______________
Approved by:__ M _b_ _____ _ Date: __c_/_f_/__%___ l - O _ _____-.__m
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY O' VAX/VMS Samole Analysis Report generated 20-JUN-1988 13:22:04 Plant Name : CNS Sample Number : 940 Type / Location : AIR RADIGIODINES / 200 Sample Date : 8-JUN-1988 09:00:00 Acq. Start Time : 17-JUN-1988 09:58:02 Sample Quantity : 637.000 M3 Sample ID : 1JUN TO BJUNB8 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.105E-02 0.OOCE+00 ' m.__ ,
~
CO-58 810.76 < 1.278E-02 0.OOOE+00 FE-59 1099.22 < 2.937E-02 0.OOOE+00 CO-60 1332.49 < 1.743E-02 0.OOOE+00 2N-65 1115.52 < 2.963E-02 NB-95 765.79 < 7.211E-03 , O.OOOE+00 0.OOOE+00 fs ZR-95 756.72 < 2.097E-02 0.OOOE+00 ( l I-131 364.48 < 1.653E-02 0.OOOE+00 CS-134 604.70 < 9.256E-03 0.OOOE+00 CS-137 661.65 < 7.738E-03 0.OOOE+00 BALA-140 537.32 < 5.309E-02 0.OOOE+00 K-40 1460.81 0.361 7.702E-02 l Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD l _ _ - _ _ . ----= = _ _ - _ - - _____________________________ _-____-__- _ _ _ em _ elus _ _ em aum Approved by:__ M [. _____,,_____,____ Date: _f,,_/_4_t_/_Jf___ l O L i l l
j DUKE POWER COMPANYL APPLIED SCIENCE CENTER: RADIDANALYSIS LABORATORY 7 VAX/VMS Sample Analysis Report generated : 21-JUN-19BB 13:53:23 l
'i Plant Name : CNS Sample Number : 964 Type / Location : AIR RADIDIODINES / 200 -
Sample Date : 15-JUN-1988 12:02:00 Acq.-Start. Time : 21-JUN-1988 13:04:37 Sample Quantity : 508.000 M3 Sample ID.. : 8JUN TO 15JUN88
-Measurement Type : ROUTINE i
_ = - - - - _ _ _ _ _ _ _ _ _ _ _ . - - - - - - - _ _ _ _ _ _ _ - -
---q
- _ = - - - = - - - - -
***** Gamma-Spectroscopy Analysis *****
I Activity 1-Sigma MDA> Frac. of 1 Nuclide' Energy (pCi/M3) Error. reg LLD Rpt. Level l MN-54 834.83 < 1.188E-02 0.OOOE+00 CO-58 810.76 < 1.413E-02 0.OOOE+00 - " "- . FE 1099.22' < 2.995E-02 0.OOOE+00 CO-60 1332.49 < 2.407E-02 0.OOOE+00 ZN-65 1115.52 < 3.338E-02 0.OOOE+00 NB-95 765.79 < 1.874E-02 0.OOOE+00 2R-95 756.72. < 2.55BE-02 0.OOOE+00 p-s I-131 364.48 < 2.021E-02 0.OOOE+00 CS-134 '604.70 < 1.226E-02 0.OOOE+00 CS-137 661.65 < 1.678E-02 0.OOOE+00 BALA-140 537.32 < 6.291E-02 0.OOOE+00 K-40 1460.81 0.244 7.036E-02 _ _ _ - - _ = _ Total Fraction of Reporting-Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign f or gamma L results means no peak was f ound and the zero error is not applicable. l l Tritium,' Alpha and Beta results are the best estimate of the
-activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - ________- - - - Analyzed by:_ > __ m h ________ AP proved by: _, D [_ __ Date: __g_ / _sA / _as_ _ __ l
)
' DUKE-POWER COMPANY
' APPLIED' SCIENCE CENTER-RADIOANALYSIS LABORATORY--
[}- .VAX/VMS Sample Analysis Report generated : 24-JUN-1988:15:33:15 l J ~ Plant'Name . : CNS L LSample Number- : 976 L -Type / Location' : AIR RADIOIODINES / 200-L Sample Date . : 22-JUN-1988.12:28:00 l Acq. Start Time : 24-JUN-1988:13:15:12 Sample' Quantity : '501.000'M3-Sample ID: :'15JUN'TO:22JUN88 Measurement Type :/ ROUTINE-
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA>. Frac. of ' Nuclide- Energy (pCi/M3) Error' req.LLD Rpt. Level MN-54 834.83- < 1.932E-02 0.000E+00 00-58 810 '. 76 ~ < 1.649E-02 0.000E+00'
~FE-59 1099.22' < 2.901E-02 0.000E+00
- CO-60 1332.49 <-1.884E-02
_ 0.000E+00 ZN-65 1115.52' < 2.529E 0.000E+00 NB-95 765.79 < 1.554E-02 0.000E+00 ZR-95 756.72' < 3.118E-02 0.000E+00 I-131 364.48 < 1.044E 0.000E+00 CS-134 604.70 < 1.449E O.000E+00' CS-137 '661.65 < 1.090E-02 0.000E+00 BALA-140 537.~32 < 4.444E-02 0.000E+00 K-40 1460.81 0.494 0.101 Total Fraction of Reporting Level 0.000E+00 Gamma'results are listed as Less Than Levels.using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error-is not applicable.
~ Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that-the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by: -
mmh
. Approved by: - DS b Date: c / z// 88 O
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY r~~T, .
! /
VAX/VMS Sample Analysis Report generated a 6-JUL-1988 10:23:59 Plant Name : CNS Sample Number : 1000 Type / Location : AIR RADIOIODINES / 200 Sample Date : 29-JUN-1988 10:23:00 Acq. Start Time : 6-JUL-1988 08:50:46 , Sample Quantity : 564.000 M3 Sample ID : 22JUN TO 29JUN88 Measurement Type : ROUTINE
-----= .==------------------------------- -------------------------
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.073E-02 0.OOOE+00 CO-58 810.76 < 1.537E-02 0.OOGE+00 FE-59 1099.22 < 3.224E-02 0.OOOE+00 CO-60 1332.49 < 4.883E-03 0.OOOE+00 2N-65 1115.52 < 3.718E-02 0.OOOE+00 NB-95 765.79 < 1.634E-02 0.OOOE+00 ZR-95 756.72 < 1.679E-02 0.OOOE+00
/N 1-131 364.48 < 1.584E-02 0.OOOE+00 O CS-134 604.70 < 1.059E-02 O.OOOE+00 CS-137 661.65 < 1.568E-02 0.OOOE+00 BALA-140- 537.32 < 5.897E-02 0.OOOE+00 K-40 1460.81 0.366 8.184E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
--_------_--_-_-- - - = - - - - - - - - _ _ _ _ - - - _ _ _ _ - - _ - - - _ _ - - - - _ - - - - - - - - - -
Analyzed by:_ _[ ,______ Approved by: c f.,_ _______._______ Date: _f_ / _0_ _ / ,;27_ _ _ _ ; g>
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~ APPLIED. SCIENCE CENTER.
RADIDANALYSIS LABORATORY (y . .
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VAX/VMS Sample Analysis Report generated : 13-JUL-1988 10:42:06 Plant Name : CNS Sample Number 1033
' Type / Location : AIR RADIDIODINES / 200 l Sample Date : 6-JUL-1988 10:20:00 l Acq. Start: Time : 12-JUL-1988 16:35:52
" -Sample Quantity : 571.000 M3 Sample ID- : 29JUN TO 6JUL88 Measurement Type.: ROUTINE
-------------------------------__ -== ----- --------------------
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> . Frac. of Nuclide- Energy (pCi /M3) Error req LLD Rpt. Level MN-54 834.~83 < 8.382E-03 0.OOOE+00 CO-58 810.76 < 1.680E-02 0.OOOE+00-FE-59 1099 22 < 3.492E-02 0.OOOE+00 CO-60 1332.49 < 4.822E-03 0.OOOE+00 ZN-65 1115.52 < 3.868E-02 0.OOOE+00 NB-95 765.79 < 1.698E-02 0.OOOE+00 ZR 756.72 <'2.308E-02 0.OOOE+00 0; I-131 CS-134 364.48 604.70
< 1.340E-02.
< 1.OO2E-02 O.OOOE+00 0.OOOE+00 CS-137- 661.65 <-1.566E-02 'O.OOOE+00 BALA-140 .537.32 < 5.656E-02 0.OOOE+00 K-40 1460.81 0.307 9.772E-02 Total Fraction of Reporting Level O.OOOE+00
, Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. i Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
- - - - - - - - - - - -_ -----------= __--- -----------------
gg _ _ . . ___ __ Approved by:__ M b_u A ______ Date: __;E,/ _gh / As_-__ O .
. ' x ____________________________________________________________
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
/~g y' _________________________________________________________________________
VAX/VMS Sample Analysis Report generated : 18-JUL-1988 11:11:09 i
' Plant Name : CNS i Sample Number : 1066
' Type / Location : AIR RADIDIODINES / 200 Sample Date : 13-JUL-1988 12:50:00 Acq. Start Time s'18-JUL-1988 10:30:57
. Sample Quantity : 550.000 M3 Sample _ID : 6JUL TO 13JUL88 Measurement Type : ROUTINE
____________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -_= _-- ==___________________________
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.680E-02 0.OOOE+00 CO-58 810.76 < 3.194E-03 0.OOOE+00 FE-59 1099.22 < 3.175E-02 0.OOGE+00 CD-60 1332.49 < i.344E-02 0.OOOE+00 2N-65 1115.52 < 3.397E-02 0.OOOE+00 NB-95 765.79 < 1.401E-02 0.OOOE+00 4 ZR-95 756.72 < 2.333E-02 0.OOOE+00 l' I-131 364.48 < 1.828E-02 0.OOOE+00 CS-134. 604.70 < 9.566E-03 0.OOOE+00 CS-137 661.65 < 1.479E-02 0.OOOE+00 BALA-140 537.32 < 4.333E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66-SQRT B/t. Presence of less than sign f or gamma results means no peak was found and th zero error is not applicable. ( Tritium, Alpha and Beta results are the best estimate of the activity and the less than signCLindicates than the critical level, CL. = 0.5 LLD that the net activity is less { _ WND _ _ _ GUP END _ _ _ _ Approved by:_ M l_ ________________ Date: _f_/ _!8 / _##___.
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,- APPLIED; SCIENCE CENTER-
,_fc > _ RADIDANALYSIG LABORATORY-T.
~V:
s ,
-VAX/VMS Sample Analysis Report generated s . 22--J UL--1988 ' 15: 47: 07. . , ,
tu Plant Name : CN5: Samp1e' Number 1078" .1
. Type / Location : - AIR RADIGIODINES / 200 Bampie Date : 20-JUL-1988 los15:00
'ficq. StartqTime -
22-JUL-1988 13:06:08 Gample Quantity _ 604.000 M3-Sample'ID : 13JUL TO 20JULG8 rienurement ' l ype : - ROUTINE'
***** Gamma-5 spectroscopy Analysis *****
Activitv 1-Si gma MDA:( Frac. of. Nuclide. Energy . (pCi/M3) Error' reg LLD Rpt. Level t' MN-54 834.83. < 1.'603E-02 0.000E+00 CO-58 810.76. <-9.716E-03 0.000E+00 FE-59 1099.22 < 2.410E-02 0.OOGE+00 ) P' CO-60 1332.49 < i.563E-02 0.000E+00 2N 1115.52 --< 3.425E-02 O.000E+00 NB-95 .765.79- < 1.479E-02 0.000E+00
.756.'72 < 1.594E-02 O.000E+00 A 2R-95 364.48 < 4.671E-03 0.000E+00 L/ I-131 6.000E+00 CS-134 604.70 < 1.148E-02 CS-137- 661.65 < 1.'194E-02 0.000E+00
- B AL. A- 140 537.32 < 3.984E-02 0.000E+00 K-40 1460.8.1 C.342 7.642E-02' Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less -Than Levels using Tech Spec LLD equation. L1.D = 4.66 SQRT B/t. - Presence of less than sign for gamma results means no peak was found and the zero error is not appl i c abl e.
Tritium, Alpha and Beta results are the best estimate of the acti vi ty and the less than sign indicates that the net ac t i vi ty is less than the critical level, CL. CL = 0.5 LLD
.g gl., e.e m. .ne. $ .D Approvec bys_.._ M _h_ _._____;.___ _
Dates f, / _A.T / jrs_ _ , l i
)
i _ _ _ _ _ _ _ . _ _ _ _ _ __ _ J
DUKE POWER COMPANY APPLIED. SCIENCE CENTER RADIDANALYSIS LABORATORY r~s _ _ _ _ _ _ - _ . _ _ _ _ . _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ . _ . . - _ _ _ . _ VAX/VMS- Sample Analysis Report l generated : 1-AUG-1998 15:17:12
~
Plant Name. CNS Sample Number : 1143 Tyne/ Location- s. AIR RADIGIODINES / 200
-Sample Date : 27-JUL-1998 11:49:00.
L
'Acq. Start Time 1-AUG-1988 14:13:26'
. Sample Quantity : 461.000 M3 '
Gample~~ID 2OJUL TO 27JUL90 Measurement Type : ROUTINE 1
***** Gamma-Spectroscopy Analysis *****
i Activity 1-Sigma MDA>' . Frac, of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.307E-02 0.000E+00 CO-58
.G10.76' < 1.991E-02 0.000E+00 FE-59 1099.22 <-2.621E-02 0.OOGE+00 CO-60 1332.49 < 2.641E-02 0.000E+00 1 I, 'ZN-65 1115.52- <'5.313E-02 0.000E+00 NB-951 '765.79 < 1.644E-02 0. CiO0E+00 H
ZR-95 756.72 < 3.488E-02 0.000E+00
'i 364.48 < 1.654E-02 0.000E+00
[V I-131 CS-134 CS-137 604.70 661.65
< 1.694E-02
< 1.635E-02 0.000E+00 0.000E+00 BALA-140 537.32 4 6. 999E--02 0.OOCE+00 Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the j activity and the less than sign indicates that the net activity is lessJ than the critical level, CL. CL = 0.5 LLD f l
. Analyzed by __ _ _____ _ ______________ j Approved bya _[2_ ._ _ _ _ _ _ _ _
'Date: _4._/_ u/_as___
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APPLIED SCIENCE CENTER , f."1
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.. I- VAX/VMS Sample Analysis Report generated 9-AUG-1980 13:24:13 c' N J t '
s Plant Name : CNS i- Sample Number 1157 Type / Location : AIR RADIOIODINES / 200 Sample Date : 3-AUG-1988 08:45:00 Aca. Start Time :: 8-AUG-1988 10:50:10 Sample Quantity : 595.000 M3 _
- Sample ID. : 27JUL TO 3AUGB8 Measurement Type s' ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac, of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.257E-02 0.OOOE+00 CO-58 810.76 < 7.588E-03 0.OOOE+00 FE-59 1099.22 < 2.233E-02 0.OOOE+00 - CO-60 1332.49 < 2.025E-02 0.OOOE+00 ZN-65 1115.52 < 2.357E-02 0.OOOE+00 NB-95 765.79 < 1.402E-02 0.OOOE+00 ZR-95 756.72 < 2.220E-02 0.OOOE+00
- I-131 364.48 < 1.030E-02 0.OOOE+00
("'
\-
CS-134 604.70 < 7.973E-03 0.OOOE+00 CS-137 661.65 < 9.074E-03 0.OOOE+00 i ' BALA-140 537.32 < 3.573E-02 0.OOOE+00 K-40 1460.81 0.217 7,974E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
' Tritium, Alpha and Beta results are the best estimate of the activity and the less than ' sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
--------- ---------------- _-- ==- - - ---------
Analyzedby:__k __~_,____________ Approved by:_ M [a_ [ _________ Date: _$_/ f_/_.fS.__ -
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' . DUKE POWER COMPANY
. APPLIED SCIENCE CENTER-l SADI0 ANALYSIS LABORATORY
(~'l VAX/VMS Sample Analysis Report generated : 18-AUG-1988 14:31:01 Plant.Name : CNS Sample Number : 1186 Type / Location : AIR RADIDIODINES / 200 Sample Date. : 10-AUG-1988'10 OO OO Acq. Start. Time : 18-AUG-1988 11:31:03-Sample Quantity 647.000 M3 Sample.ID : 3AUG TO 10AUG88 Measurement Type : ROUTINE
-----------------------.. _- - - - - - - - - - - - - = = _- __-------- ==-- __-
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.011E-02 0.OOOE+00 CO-58. 810.76 < 1.115E-02 0.OOOE+00 FE-59 1099.22 < 2.427E-02 0.OOOE+00 CO-60 1332.49 < 1.777E-02 0.OOOE+00 ZN-65 1115.52 < 2.914E-02 0.OOOE+00 NB-95 765.79. < 1.143E-02 0.OOOE+00 2R-95 756.72 < 2.052E-02 0.OOOE+00 (~s I-131 364.48 < 1.669E-02 0.OOOE+00
' (-) CS-134 604.70 < 9.536E-03 0.OOOE+00 CS-137 661.65 < 1.432E-02 0.OOOE+00 BALA-140 537.32 < 6.174E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity. is less than the critical level, CL. CL = 0.5 LLD Analyzedby:__[ _I_ m __________ Approved by:__ M _[__ - ________________ Date: __S_/_lp/_88____ l O> u-
- y. ' '
DUKE POWER' COMPANY' APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY f3 -
\- VAX/VMS Sample Analysis Report generated Ls . 23-AUG-1988 14:36:32 - ->
r Plant Name :-CNS ) Sample Number : 1203 -
]
Type / Location : AIR RADIDIODINES / 200 Sample Date : 17-AUG-1988 09:36:00 Acq.. Start Time : 23-AUG-1988 14:05:19' i Sample Quantity : 570.000 M3 I Sample ID : 10AUG TO 17AUG88 Measurement Type : ROUTINE j
------------_--_----------------------__ _ ----------_---_---- _--- 4 l
***** Gamma-Spectroscopy Analysi s ***** -
Activity 1-Sigma MDA> Frac. of j Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.609E-02 0.OOOE+00 CO-58 810.76 < 1.403E-02. O.OOOE+00 FE-59 1099.22 < 2,156E-02 0.OOOE+00
,CO-60 -1332.49 < 1.658E-02 0.OOOE+00 ZN-65 1115.52 < 8.267E-03 0.OOOE+00 NB-95 765.79 < 1.250E-02 0.OOOE+00 i ZR-9$ 756.72 < 3.016E-02 0.OOOE+00
[ -I-131 364.48 < 1.664E-02 0.OOOE+00 CS-134 604.70 < 1.288E-02 0.OOOE+00 CS-137 661.65 < 1.059E-02 0.OOOE+00 BALA-140 537.32 < 4.656E-02 0.OOOE+00 K-40 1460.81 0.326 0.115 Total Fraction of Reporting Level O.OOOE+00 4 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. I
'i Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzedbysk _;____________
Approved bys__[7%A /. _ _____ Date: _A_/_a4/__gE__ i
L I
. DUKE POWER COMPANY l o APPLIED SCIENCE' CENTER, j h
RADIDANALYSIS LABORATORY i l' -------_----------_------_-----------------_------------_---_-_--_--_-_-- i kJ VAX/VMS Sample Analysis Report generated : 29-AUG-1988 14:45:07 ) t. Plant'Name . CNS - Sample Number- : 1221-
' Type / Location : AIR RADIOIODINES / 200 Sample-Date : 24-AUG-1988 09:55:00 l Acq. Start' Time 's 29-AUG-1988 12:50:16 Sample Quantity : 643.000 M3 ]
Sample ID 17AUG TO 24AUG88 i Measurement Type : ROUTINE l
***** Gamma-Spectroscopy-Analysis ***** l i !
Activity 1-Sigma MDA> Frac. of: {
=Nuclide Energy (pCi/M3) Error req LLD Rpt. Level J MN-54 834.83 < 1.323E-02 0.OOOE+00 CO-58 810.76 < 1.440E-02 0.OOOE+00 )
. FE-59 1099.22 < 2.750E-02 0.OOOE+00 CO-60 1332.49 < 1.786E-02 0.OOOE+00 ZN-65 1115.52 < 3.424E-02 0.OOOE+00 NB-95 765.79' < 1.111E-02 0.OOOE+00 ZR-95 756.72 < 1.955E-02 0.OOOE+00
(~' I-131 364.48 < 1.434E-02 0.OOOE+00 3 CS-134 604.70 <-6.907E-03 0.OOOE+00 CS-137 661.65 < 1.206E-02 0.OOOE+00 BALA-140 537.32 < 4.140E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the ' activity and the less than sign . indicates that the net activity is less than the critical level, CL.- CL = 0.5 LLD J Analyzed bys_ _f __ _________ Approved by:_ M L. _________________ Date: _}_/ b_/ - _@___ O
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
/"T q_j -------------------------------------------------------------------------
VAX/VMS Sample Analysis Report generated 2-SEP-1988 13:25:21 Plant Name : CNS Sample Number 1236 Type / Location : AIR RADIOIODINES / 200 Sample Date : 31-AUG-1988 12:22:00 Acq. Start Time : 2-SEP-1988 12:54:05 Sample Quantity : 608.000 M3 Sample ID : 24AUG TO 31AUG88 Measurement Type ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level
. MN-54 834.83- <'1.188E-02 0.OOOE+00 CO-58 810.76 < 1.161E-02 0.OOOE+00 ,
FE-59 1099.22 < 2.499E-02 0.OOOE+00 CO-60 s 1332.49 < 1.662E-02 0.OOOE+00 ZN-6$ 1115.52 < 2.181E-02 0.OOOE+00 NB-95 765.79 < 1.239E-02 0.OOOE+00 fs ZR-95 756.72 < 1.326E-02 0.OOOE+00 ( I-131 364.48 < 9 668E-03 0.OOOE+00 CS-134 604.70 < 1.099E-02 0.OOOE+00 CS-137 661.65 < 1.106E-02 0.OOOE+00 BALA-140 537.32 < 3.766E-u2 0.OOOE+00 K-40 1460.81 0.345 7.913E-02
------ =
' Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 CORT B/t. Presence of less than sign for gamma results means no peak was 4ound and the zero error is not applicable.
I - Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:_c)s Q 81 w ___________ , Approved by:_ d _f2_ ______ ____ Date: 4_/_e_/__&___ 1 i________i___._______ . _ _ . _ _ _ _ .
DUKE POWER COMPANY . APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY L () ~UhN/VMS Sample Analysis Report generated a 9-SEP-1988 14:55:04
.]
l 1 L Plant Name : CNS H Sample Number - 1257 Type / Location : AIR RADIOIODINES / 200 j Sample Date : 7-SEP-1988 09:22:00 l Acq. Start Time : 9-SEP-1988 14:23:32 Sample Quantity a 588.000 M3 Sample ID- s'31AUG TO 75EP88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.437E-02 0.OOOE+00 CO-58 810.76 < 1.407E-02 0.OOOE+00 FE-59 1099.22 < 2.479E-02 0.OOOE+00 CO-60 1332.49 <.4.676E-03 0.OOOE+00 2N-65 1115.52 < 2.156E-02 0.OOOE+00 NB-95 765.79 < 1.608E-02 0.OOOE+00 ZR-95 756.72 r 2.OB3E-02 0.OOOE+00 r I-131 364.48 < 1.192E-02 0.OOOE+00
'( 'CS-134 604.70 < 9.695E-03 0.OOOE+00.
CS-137 661.65 < 1.318E-02 0.OOOE+00 BALA-140 537.32 < 4.685E-02 0.OOOE+00 K-40 1460.81 0.351 7.853E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by _ _ _
'S% _ _ _ _ _
Approved bys_ M f. _____. _ _ _ _ . _ _ . Date: _,f_/ jg_/_,fs
8
. :, 8
, DUKE POWER COMPANY:
APPLIED. SCIENCE CENTER
, , , RADIDANALYSIS LABORATORY' i 7i
!:VAX/VMS. Sample Analysis ~ Report generated:: 20-SEP-19BB.15:01:40
- ;c T ' Plant Name. : CNS~
t, ' Sample Number. s'1274'
.. Type /Locati on - : AIR RADIDIODINES / 2OO i
- Bample,Date' s,14-SEP-1988 12:33:00
'Acq.LStart1 Time : :20-SEP-1988 13:51:57
, Sample. Quantity; s' '654.000 M3.
+ 'Cample ID . D7BEP TO.14SEPBS Measurement Type z. ROUTINE
==_________________ _________.
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of. Nuclide , Energy (pCi/M3) Error: reg LLD Rpt. Level
.MN-54 834.83 <'B.475E-03 0.OOOE+00 CO-58 810.76 .<'1.400E 'O.OOOE+00 FE-59 1099.22. <.2.727E-02 -0.OOOE+00 CO-60' -1332.49- < 1.703E-02 0.OOOE+00'
- ZN 1115.52' <'2.84BE-02 0.OOOE+00 l --- -
NB-95 765.79- < 1.725E-02 0.OOOE+00 s 2R 756.72l <'5.216E-03 0.OOOE+00
.I-131 '364.48 : < 1. 661E-02 'O.OOOE+00 CS-134 '604.70 -<T1.180E-02 0.OOOE+00
.CS-137 661.65 < 7.151E-03 0.OOOE+00 BALA-140 -537.32- < 3.679E-02 0.OOOE+00' K 1460.81 0.306 0.102 1 Total Fraction of' Reporting Level' O.OOOE+00
' Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of lesn ' than sign f or gamma
,z results means no peak was f ound and the' zero error is' not applic,able.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by __ I
-Approved by:___ @ f. ,s;__- _, __ Dates _f_/_sf_/_,pe 10 .
l i ____________L_-_.____._-__ - _ - - _ _ - - - - _ - _ _ - - - - - - - - - - -
l L DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
'k/ VAX/VMS Sample Analysis Report generated : 23-SEP-1988 13:42:33 Plant Name : CNS Sample Number. : 1300' Type / Location .: AIR RADIOIODINES / 200 1 Sample Date : 21-SEP-1988 12: 25: 00 Acq.~ Start Time : 23-SEP-1988 13:11:23-p Sample Quantity : 642.000 M3 1 Sample ID : 14SEP TO 21SEP88 Measurement Type : ROUTINE l --__ __--__- _--------__ _ _ _ _ _ _ - _ ______-- -
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy . (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.103E-02 0.OOOE+00 CO-58 810.76 < 1.387E-02 0.OOOE+00 FE-59 1099.22 < 2.227E-02 0.OOOE+00 CO-60 1332.49 < 2.076E-02 0.OOOE+00 ZN-65 1115.52 < 2.887E-02 0.OOOE+00 NB-95 765.79 < 1.047E-02 0.OOOE+00-ZR-95 756.72' < 1.215E-02 0 OOOE+00 I-131 364.48 < 1.OO7E-02 0.OOOE+00 (")N
\_ CS-134 604.70 < 1.185E-02 0.OOOE+00 CS-137 661.65 < 1.119E-02 0.OOOE+00 BALA-140 537.32 < 2.947E-02 0.OOOE+00 K-40 1460.81 0.289 6.818E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Approved by:__ I._ ___ ___ Date: _f_ /_J4_ / pi O I 1
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY () , VAX/VMS Sample Analysis Report generated a 30-SEP-1988 12:05:41 Plant Name : CNS Sample Number : 1324 Type / Location : AIR RADIDIODINES / 200 Sample Date : 28-SEP-1988 11:23:00 Acq. Start Time : 30-SEP-1988 11:34:27 Sample Quantity :- 624.000 M3 Sample ID : 21SEP TO 2BSEP88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.288E-02 0.OOOE+00 CO-58 810.76 < 8.642E-03 0.OOOE+00 FE-59 1099.22 < 2.127E-02 0.OOOE+00 CO-60 1332.49 < 2.305E-02$ O.OOOE+00 ZN-65 1115.52, < 2.339E-02 0.OOOE+00 NB-95 765.79 < 1.350E-02 0.OOOE+00 ZR-95 756.72 < 1.OO4E-02 0.OOOE+00 I-131 364.48 < 1.052E-02 0.OOOE+00
' ) CS-134 CS-137 604.70 661.65 6.635E-03 1.276E-02 0.OOOE+00 0.OOOE+00 BALA-140 537.32 < 2.331E-02 0.OOOE+00 K-40 1460.81 0.413 0.113 Total Fraction of Reporting Level O.OOOE+00 Bamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
---- __ . - - - =------------ _= - ----------------- --
Analyzed by: _ m ,m / s) Approved by:__ y f. f. _ _ ______ __ Date: _2p_ /__J_ /.ap____ O m___________________________.._ .__ _
,.e f(V . .
DUKE. POWER COMPANY APPLIED' SCIENCE CENTER RADIDANALYSIS LABORATORY l ___-----________--__--------_----___------_____---____----_---_-_-----___ tVAX/VMS Salmple-Analysis Report generated ~ 10-DCT-1988 16:26:24 Plant Name s' 'CNS' Sample Number : 1348. Type / Location : AIR:RADIDIODINES / 200 Sample'Date - 5-DCT-1988.09:20:OO U Acq. Start Time : 10-DCT-1988 15:54 57'
' Sampl e - Quanti ty - : .634.000 M3
- Sample ID- 28SEP TO 50CTBS Measurement Type ROUTINE-
***** Gamma-Spectroscopy Analysi s ' *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy .pCi/M3) ( Error req LLD.Rpt. Level MN-54< 834.83 < 1.230E-02 0.OOOE+00 CO-58 810.76 < 1.087E-02 0.OOOE+00
-FE-59 1099.22 '< 1.911E-02 0.OOOE+00 CO-60 1332.49 < 1.490E-02 0.OOOE+00 ZN-65 1115.52' '< 2.545E-02 0.OOOE+00 NB-95 765.79 < 1.187E-02 0.OOOE+00' s- ,
, ZR-95 756.72 < 1.571E-02 0.OOOE+00
- I-131 364.48 < 1.164E-02 0.OOOE+00
'CS-134 604.70 < 7.393E-03 0.OOOE+00-CS-137' 661.65 < 1.102E-02 0.OOOE+00 BALA-140' 537.32 < 2.349E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD' equation. . LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the
, activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by: _
f ____ Approved by:M_/. _ r ___g________ Date: _gA/_1/_/- -80 0- _______.,____.______.m _ _ _ _ - - . . _ _ _ _ _ _ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ . .
- ---_-------- ---------------------_--- ----------- d E
. DUKE POWER COMPANY
, APPLIED SCIENCE CENTER
- RADIDANALYSIS LABORATORY
.' /~"I q, -------------------- ---------- ----- __ VAX/VMS Sample Analysis Report generated : 14-OCT-1988 15:28:18 d f 's
.. Plant Name' s CNS j E Sample Number i 1371-Type / Location : AIR RADIOIODINES / 200 l Sample Date : 12-OCT-1988 11:40:00 l Acq.-Start Time : 14-OCT-1988 14:56:37 l' Sample Quantity : 449.000 M3 Sample ID : SOCT TO.120CT88 Measurement Type : ROUTINE
-- ____ -- -- =--___--_-- -= --
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.551E-02 0.OOOE+00 CO-58 810.76 < 3.808E-03 0.OOOE+00 FE-59 1099.22 < 3.455E-02 0.OOOE+00 CO-60 1332.49 < 1.666E-02 0.OOOE+00 2N-65 1115.52' < 3.233E-02 0.OOOE+00 NB-95 765.79 < 1.592E-02 0.OOOE+00
-s ZR-95 756.72 < 2.472E-02 0.OOOE+00
< 1.391E-02 0.OOOE+00 l) 1-131 CS-134 364.49 604.70 < 9.036E-03 0.OOOE+00 CS-137 661.65 < 1.319E-02 0.OOOE+00 BALA-140 537.32 < 2.799E-02 0.OOOE+00 ,
K-40 1460.81 0.343 0.113 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD
-equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applic,able.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is lese than the critical l evel , CL. CL = 0.5 LLD ___--_== - - = _ _ Approved,by:__ M L _ _ _ _ r ________ Dates to_ /.jf_ / Ap____ o V
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
,-~ ---- ----_ ==----------------------------------------------- ------
k_) VAX/VMS Sample Analysis Report generated : 24-OCT-1988 14:08:23 Plant Name : CNS Sample Number : 1393 Type / Location : AIR RADIDIODINES / 200 SampleJDate : 19-DCT-1988 10:47:00 Acq. Start Time : 24-OCT-1988 12:50:35 Sample Quantity : 284.000 M3 Sample ID : 120CT TO 190CT88 Measurement Type : ROUTINE
-= - - = - _------- --------- - ------- = _ - - - - - - - ==-
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. cf Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.672E-02 0.OOOE+00 CO-58 810.76 < 2.482E-02 0.OOCE+00 FE-59 1099.22 < 1.524E-02 0.OOOE+00 CD-60 1332.49 < 2.603E-02 0.OOOE+00 ZN-65 1115.52 < 7.181E-02 0.OOOE+00- l NB-95 765.79 < 2.117E-02 0.OOOE+00 ! ZR-95 756.72 < 4.663E-02 0.OOOE+00 l I-131 364.48 < 2.570E-02 0.OOCE+00 f CS-134 604.70 < 1.977E-02 0.OOOE+00 CS-137 661.65 < 1.820E-02 0.OOOE+00 BALA-140 537.32 < 0.106 0.OOOE+00 ,
, l Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign f or gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the . ! attivity and the less than sign indicates that the net activity is less i than the critical level, CL. CL = 0.5 LLD I
--------- ___ =------------------- __ _-------- _ = - . ------
Analyzed by:_ f ___ Approved by: ____ % _/y 2________________ Date: _p_/_gf/_pg___ O e a-___.___.-___.__.__________ _ _ _ _ _ _ _ _ . . . . - _ _ _ . - _ _ _ . _ _ _ _ _ _ _ _ . . . _ _ . _ _ _
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY g
- ) ---------------=- - - - - - = = - - - - - - - - - - = _ _=------ -
VAX/VMS Sample Analysic Report generated : 28-OCT-1988 12:00:01 Plant Name : CNS Sample Number : 1410 Type / Location : AIR RADIOIODINES / 200 Sample Date : 26-DCT-1988 10:15:00 Acq. Start Time : 28-OCT-1988 11:28:10 Sample Quantity : 597.000 M3 Sample ID : 190CT TO 260CT88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Anal ysi s *****
Acti vi ty 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 9.148E-03 0.OOOE+00 CO-58 810.76 < 9.501E-03 0.OOOE+00 FE-59 1099.22- < 2.787E-02 0.OOOE+00 CO-60 1332.49 < 1.851E-02 0.OOOE+00 i ZN-65 111"-52 < 8.937E-03 0.OOOE+00 NB-95 765.79 < 1.519E-02 0.OOOE+00
.g ZR-95 756.72 < 2.489E-02 0.OOOE+00
('~'j I-131 364.48 < 1.158E-02 0.OOOE+00 CS-134 604.70 < 9.689E-03 0.OOOE+00 CS-137 661.65 < 1.154E-02 0.OOOE+00 BALA-140 537.32 < 2.982E-02 0.OOGE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. f Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less l than the critical level, CL. CL = 0.5 LLD Analy ed by:__ M _ __T 2st.________-- Approved by: _ Tt _ d________,________ Date: _ ;a_ / _zS_ / _ _ f s _ _ l l
/
-------------------------------------------------- - ==-----------
DUKE POWER COMPANY APPLIED SCIENCE. CENTER RADIDANALYSIS LABORATORY-r-Q ------------------------ --------------------------- --------- : ' - (-) VAX/VMS LSample Analysis Report generated's 7-NOV-1988.14:25:50 9h Plant' Name : CNS Sample _ Number : 1443-Type / Location : AIR RADIOIODINES / 200 Sample Date : 2-NOV-19BB 10:01:00 Acq.~ Start Time : 7-NOV-1988 13:12:53 Sample Quantity. : 645.000 M3 Sample ID : 260CT TO 2NOV88 Measurement Type : ROUTINE
=-----------------__________
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide- Energy . (pCi/M3) Error reg LLD Rpt. Level MN-54 ~ 834.83 < 9.090E-03 0.OOOE+00 CO-58 810.76 < 1.216E-02 0.OOOE+00 FE-59 1099.22 < 2.015E-02 0.OOOE+00 CO-60 1332.49 < 1.787E-02 0.OOOE+00 ZN-65 1115.52 < 2.047E-02 0.OOOE+00 ND-95 765.79 < 1.210E-02 0.OOOE+00 ZR-95 756.72 < 1.743E-02 0.OOOE+00 f 'I-131 364.48 < 1.392E-02 0.OOOE+00 CS-134 604.70 < 6.704E-03 0.OOOE+00 CS-137 661.65 < 1.131E-02 0.OOOE+00 BALA-140 537.32 < 4.712E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD
. equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less f than the critical level, CL, CL = 0.5 LLD
..- - - - - - - - - ---------__--- __--_-- -=------- - - - - _ -
Anal yz ed by: __ /" i
<f -
I _____ , ___ ____g________ l Approved by:_ 3 A,[_ =_______ Date: _jf_ / _.s_ / _gllts_ _ _ _ 1. 2 _.--_---_ _ _ _ - _
______________________-- ==______ DUKE POWER' COMPANY APPLIED SCIENCE CENTER
-RADIDANALYSIS LABORATORY f3 ds/
VAX/VMS Sample Analysis Report generated : 11-NOV-1988 15:05.33 Plant Name : CNS Sample Number -: 1459 Type / Location : AIR RADIDIODINES / 200 Sample Date : 9-NOV-1988 12:20:00 Acq. Start Time : 11-NOV-1988 14:34:10 Sample Quantity, : 608.000 M3 Sample'ID. : 2NOV TO 9NOV88 Measurement Type : ROUTINE
-.a_
. ***** Gamma-Spectroscopy Analysi s *****
Activity 1-Si gma MDA> Frac, of Nuclide ' Energy (pCi /M3) Error reg LLD Rpt. Level' MN-54 834.83 < 9.79BE-03 0.OOOE+00 CO-58 810.76. < 8.654E-03 0.OOOLeOO FE-59 1099.22 < 2.868E-02 0.OOOE+00 CO-60 1332.49 < 1.280E-02 0.OOOE+00 ZN-65 1115.52 < 7.922E-03 0.OOOE+00 NB-95 765.79 < 1.179E-02 0.OOOE+00 2R-95 756.72 < 2.394E-02 0.OOOE+00 I-131 364.48 < 8.181E-03 0.OOOE+00 .. CS-134 604.70 < 1.190E-02 0.OOOE+00 CS-137-661.65 < 9.038E-03 0.OOOE+00 BALA-140 537.32 < 4.235E-02 0.OOOE+00 K-40 1460.81 0.358 8.OO6E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less , than-the critical level, CL. CL = 0.5 LLD _ _ _ _ _ = = - -. Analyzed by:_s[ _____ '_ ___________ Approved by: 1775dg[2 _. ____________ Date: _g_/_9L/ _Je___ 1 0
- - _ - = -------
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY (~ ---------- --------. --------- ------------___ ------------------ k- - VAX/VMS Sample Analysis Report generated : 21-NOV-1988 12:38:16 Plant Name' : CNS-Sample Number s'1478 Type / Location : AIR RADIDIODINES / 200 Sample Date : 16-NOV-1988 09:50:00 Acq. Start Time : 21-NOV-1988 12: 06: 59 Sample Quantity : 618.000 M3 Sample ID : 9NOV TO 16NOV88 Measurement Type : ROUTINE ,
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma. MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 9.638E-03 0.OOOE+00 CO-58 810.76 < 1.670E-02 0.OOOE+00 FE-59 1099.22 < 2.199E-02 0.OOOE+00 CO-60 1332.49 < 1.196E-02 0.OOOE+00 ZN-65 1115.52 ,< 7.413E-03 0.OOOE+00 NB-95 765.79 < 1.242E-02 0.OOOE+00 ZR-95 756.72 < 1.595E-02 0.OOOE+00 (') (_/ 1-131 CS-134 364.48 604.70 1.301E-02 8.644E-03 0.OOOE+00 0.OOOE+00 CS-137 661.65 < 1.138E-02 0.OOOE+00 BALA-140 537.32 < 2.498E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma-results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD j
------------ . _ _ = = _ _ . _ - _ _ --- ==___ ------ ___
j Analyzed by: /Arrh4 M ___________ _ __ Approved by:__ M _b h ,_________ Date: _.g./_z_t / __mm___ O
pp DUKE.?OWER' COMPANY-n
. . APPLIED SCIENCE-CENTER RADIDANALYSIS~ LABORATORY s-g,q - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - - - _ - - - - - _ - - - - - - - - - - - - - - - - - - - - - _ - - - - -
*q ,){ < VAX/VMS Sample Analysi s Report generated ~ s . 28-NOV-1988 14: 16:28 IPla'nt'Name- 3.CNS F. Sample Number : 1495
' Type / Location : AIR RADIDIODINES / 200
- Sample Date . ~23-NOV-1988 10
- 55:00-1Acq. Start Time : 28-NOV-1988 13:31:18 Sample Quantity : 603'000. M3 Sample ID' : 16NOV TO 23NOV88'
- Measurement Type : ROUTINE
------------------ __--------------- = - - - - - - - - - - =----------------
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma 'MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level-MN-54 834.83 <:1.168E-02 0.OOCE+00
. CO-58 . 810.76 <'3.448E-03 0.OOOE+00 FE-59 1099.22 < 2.324E-02 0.OOOE+00 CO-60' 1332.49 < 2.101E-02 0.OOOE+00 ZN-65 1115.52 < 2.460E-02 0.OOOE+00
.NB-95 765.79- < 1.354E-02 0.OOOE+00 ZR-95 756.72- < 1.525E-02 0.OOOE+00 I-131- 364.48 < 1.013E-02 0.OOOE+00'
./ CS-134 604.70 < 1.147E-02 0.OOOE+00 d' CS-137 .661.65 < 1.358E-02 0.OOCE+00 BALA-140 537.32 < 4.348E-02 0.OOOE+00 K-40 1,460.81 0.387- 8.888E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed 'as Less Than Levels using Tech Spec LLD equation. LLD = 4.66.SQRT B/t. Presence of less than sign for gamma.
results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results' are the best estimate of the ! activity and.the less than sign indicates that the net activity is less-than the critical level, CL. CL = 0.5 LLD An al yz ed by': __M__( l Approved by:_ h . ma h e __________ Date: _ J.2_ / _,2 , / _B_(__ _
. \.)
i j mm___.____._____. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . . _ . _ _ _ . _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ . _ _ _ . _ . . . . .__ _ _ _ _ . _ _ . . . . . . _ . . _ _ . _ _
<_ 1 DUKE POWER COMPANY - APPLIED-SCIENCE CENTER RADIDANALYSIS LABORATORY- l
,, 3 l
(,f; ;VAX/VMS Sample Analysis Report generated .5-DEC-1988 11:44:11 i Plant Name- CNS Sample Number : 1532~
- Type / Location' s AIR RADIDIODINES / 200 Sample Date : 30-NOV-1988 10:07:00 Acq. Start Time 5-DEC-1988.11:12:27 Sample-Quantity : 583.000 M3 Sample ID: : 23NOV TO 3ONOV88
~ Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> . Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 -834.83 < 1.028E-02 0.OOOE+00 CO 810.76 < 1.290E-02 0.OOOE+00 FE-59 1099.22 < 3.402E-02 0.OOOE+00 CO-60 1332.49 < 1.382E-02 0.OOOE+00
'ZN-65 1115.52 < 7.857E-03 0.OOOE+00 NB-95 '765.79 < 1.455E-02 0.OOOE+00 ZR-95 756.72 < 5.113E-03 0.OOOE+00 I-131 364.48 < 1.089E-02 0.OOOE+00
_; 7-) CS-134 604.70 < 1.087E-02 0.OOOE+00 3" ' CS-137 661.65 < 8.864E-03 0.OOOE+00 BALA-140- 537;32 '< 5.390E-02 0.OOOE+00 2 = _ _ - ---- Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD
. equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than.the critical level, CL. CL = 0.5 LLD
------------------- -----------------. --------------=__. -
Analyzed by:_ h _h w__h_I_ m _ h _______ Approved by __ d __f. _____,_ __ Date: _ A / _$_ / _SS_ _ ("i G
\
__R_'_________________________________________________.___________________ DUKE POWER' COMPANY APPLIED. SCIENCE CENTER RADIDANALYSIS LABDRATDRY.
.. I g.
' (g)~
, ,VAX/VMS Sample Analysis Report generated : 15-DEC-1988 14:13:57 Plant:Name : CNS Sample Number : 1619 Type / Location : AIR RADIOIODINES / 200 Sample Date : 7-DEC-1988 09:35:00
'Acq. Start Time t'.13-DEC-1988 10:17:02 Sample Quantity : . 583.000 M3 ,
Sample ID : 3ONOV TO 7DEC88: Measurement Type : ROUTINE
- _ _ = _ - _____________________________ =__________________________
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level- !, MN 834.83 '< 1.306E-02 0.OOOE+00 CD-58 810.76 < 1.591E-02 0.OOOE+00
- - FE-59 1099.22 < 3.180E-02 0.OOOE+00 CO-60 1332.49 < 4.945E-03
- 0.OOOE+00 ZN-65 1115.52 < 2.273E-02 0.OOOE+00 NB-95 765.79 < 6.033E-03 0.COOE+00-ZR-95 756.72- < 2.049E-02 0.OOOE+00 I-131 364.48 < 1.488E-02 0.OOOE+00 1 CS-134 604.70 < 6.294E-03 0.OOOE+00 CS-137 ~661.65 < 1.087E-02 0.OOOE+00 BALA-140 1596.49 < 2.318E-02 0.OOOE+00 K-40 1460.81 0.299 9.339E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec. LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and.the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than.the critical level, CL. CL = 0.5 LLD Analyzed by: __ h M _,____________ Approved by:__ M ( / _ _ _ _ _ _ _ _ _ _ __ Date: _,g./fi /__se___ W 1 1
'DUKELPOWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY f
------------------------------------_ =-------------------------___-___
_, !(f -VAX/VMS~ Sample Analysis Report generated.s.-20-DE"~1988 13:22:54 ,.i'
' Plant'Name : CNS-Sample Number : 1640
-Type / Location : ' AIR RADIDIODINES / 200
' Sample Date : 14-DEC-1988 15:04:00 Aca.. Start Time : 20-DEC-1988 12:51:58 Sample Quantity : 633.000 M3 Sample'ID : 7DEC TO 14DEC88 Measurement Type ROUTINE
- - - = _.__ ------------------- _ _---------- - --------------
***** Gamma-Spectroscopy Analvsis *****
Activity 1-Sigma MDA> Frac. of
.Nuclide Energy (pCi/M3) Error rea LLD Rpt. Level MN-54 834.83 -< 1.301E-02 0.OOOE+00
. CO-58 ' 810.76 <-1.069E-02 0.OOOE+00 FE-59 1099.22. < 2.208E-02 0.OOOE+00 CO-60 1332.49 < 1.929E-02 0.OOOE+00
-ZN-65 1115.52 < 2.093E-02 0.OOOE+00 NB-95 765.79 <'1.187E 0.OOOE+00 2R-95 .756.72 '< 1.602E-02' O.OOOE+00
.- I-131 364.48 < 1.659E-02 0.OOOE+00 I( ) _
CS-134 CS-137 604.70 < 9.817E-03 661.65 < 8.683E-03
.O.OOOE+00 0.OOOE+00 BALA-140 1596.49 < 7.796E-03 0.OOOE+00
'K-40 1460.81 0.189 '5.702E-02 Total Fraction of Reporting Level O.OOOE+00 ,
Gamma results are listed as Less Than Levels using Tech. Spec'LLD equati on . LLD = 4.66 SQRT B/t. Presence.of less-than sign for gamma results means no peak was found and the zero error'is not applicable. Tritium. Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzedby:_b _ _s w e Approved by:__ M _(._ __.__ ________ Date: _;_/_(_/__q__ l
I DUKE-POWER COMPANY ) APPLIED SCIENCE' CENTER R RADI0 ANALYSIS LABORATORY
,M .
? %,f VAX/VMS Sample Analysis. Report generated': 28-DEC-1988'10:31:52 Plant Name : CNS Sample Number : 1692 ,
Type / Location : AIR RADIOIODINES / 200 j Sample Date : 21-DEC-1988 09:52:00 Acq. Start Time : 28-DEC-1988 10:00:42 Sample Quantity : 581.000 M3 is Sample ID : 14DEC TO 21DEC88 Measurement Type : ROUTINE AAAAA Gamma-Spectroscopy Analysis AAAAA Activity 1-Sigma HDA> Frac. of 1 Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.175E-02 0.000E+00 i CO-58 810.76 < 1.506E-02 0.000E+00 FE-59 1099.22 < 7.676E-03 0.000E+00 CO-60 1332.49 < 1.375E-02 0.000E+00 ZN-65 1115.52 < 3.498E-02 0.000E+00 NB-95 765.79 < 1.473E-02 0.000E+00
. ZR-95 756.72 < 2.086E-02 0.000E+00 1 I-131 364.48 < 1.645E-02 0.000E+00 CS-134 604.70 < 8.675E-03 0.000E+00 CS-137 661.65 < 1.027E-02 0.000E+00 BALA-140 1596.49 < 8.515E-03 0.000E+00 Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for samma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less l than the critical level, CL. CL = 0.5 LLD l M____________ Approved by:_ h ,.,u h ___________ Date: _.l_/_1/_f6____ a s ! L
D .
------------------------- ------ = _ - - . -------------------- . _ . .
~
DUKE POWER COMPANY APPLIED SCIENCE CENTER 1 1: RADIDANALYSIS LABORATORY ~ -
-jA :- .
s 4 LVAX/VMS Sample Analysis Report generated : 5-JAN-1989 15:59:17 Plant.Name _ a CNS. Sample. Number : 1728 Type / Location : . AIR RADIGIODINES / 200
. Sample Date 28-DEC-1988 10:50:00 Acq. Start Time ' 5-JAN-1989 15:10:57
' Sample Quantity.-: 574.OOO'M3 Sample ID : 21DEC TO 28DEC88
. Measurement Type : ROUTINE
_=_-----------------
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt.' Level MN-54 -834.83 < 3.259E-03 0.OOOE+00 ' CO-58 810.76 < 3.392E-03 0.OOOE+00 FE-59 ~1099.22- < 3.581E-02 _O.OOOE+00 CD-60 1332.49 < 4.893E-03 0.OOOE+00
'ZN-65 1115.52 < 2.450E-02 0.OOOE+00 Jps' 'NB-95 765.79 <17.857E-03 0.OOOE+00 1 ::ZR-95' 756.72 < 1.567E-02 0.OOOE+00 I-131 .364.48 < 1.339E-02 0.OOOE+00 CS-134 604.70 <-1.069E-02 0.OOOE+00 CS-137 661.65 < 1.189E-02 0.OOOE+00 BALA-140 1596.49 < 2.042E-02 0.OOOE+00 K-40 1460.81 0.331 9.064E-02 .
Total Fract' ion'of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net' activity _ is less than the critical level, CL. CL = 0.5 LLD Analyzed by ____ # Mad-- _- --_ -___
~
Approved by:_ b b _ $ m ____ ____ Date: __l_ / _(o_ /.dl.___
1 i 1 i DUKE POWER COMPANY. f APPLIED SCIENCE' CENTER. RADIDANALYSIS LABORATORY ( . { VAX/VMS Sample Analysis Report generated : 7-JAN-1989 15:10:55 1 i
, Plant Name : CNS Sample Number : 1744 Type / Location : AIR RADIOIODINES / 200 Sample Date : 4-JAN-1989 12:26:00 Acq. Start-Time :. 7-JAN-1989 14:39:34 Sample Quantity : 603.000 M3
-, Sample ID :-28DEC'TO 4JAN89 Measurement Type :- ROUTINE
____- ____- __ _______________----- =______________________
; ***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.388E-02 0.OOOE+00 CO-58 810.76 < 1.465E-02 0.OOOE+00 FE-59 1099.22 < 2.051E-02 0.OOOE+00 CO-60 1332.49 < 1.225E-02 0.OOOE+00 ZN-65' 1115.52 < 2.987E-02 0.OOOE+00 f] NB-95 765.79 < 2.791E-03 0.OOOE+00
\> _
ZR-95 756.72 < . 2.346E-02 0.OOOE+00 I-131 364.48 < 1.OO2E-02 0.OOOE+00 CS-134 604.70 < 1.160E-02 0.OOOE+00 CS-137 661.65 < 8.569E-03 0.OOOE+00 q BALA-140 1596.49 < 1.803E-02 0.OOOE+00 Total Fraction of Reporting' Level O.OOOE+00 Bamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD , ______-- = ________________- - = = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - Analyzed by:_ b_bl _ ______ Approvedby:_$hb[6_f_.__ ______________ Date: _J_/_gC/_!y___
.\
4 _ _ _ - _ _ - - - - i
DUKE POWER COMPANY APPLIED SCIENCE CENTER
'~h' /
RADIOANALYSIS LABORATORY-VAX/VMS Samole Analvsis Report' generated : 14-JUN-1988 14:35:18 Plant Name : CNS Sample Number a 409 EType/ Location : AIR RADIOIODINES-/ 201 Sample Date : 6-JAN-1988 11:35:00 Acq. Start Time : 11-JAN-1988 13:00:01 Sample Quantity : 574.000 M3 Samole ID 30DEC TO 6JAN88 Measurement Type : ROUTINE l
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rot. Level MN-54 834.83 < 1.420E-02 0.000E+00 CO-58 810.76 < 1.200E-02 0.000E+00 FE-59, 1099.22 < 3.075E-02 0.OOGE+00 CO-60 1332.47 < 1.487E-02 0.000E+00 ZN-65 1115.52 < 3.163E-02 0.000E+00 -ns NB-95 765.78 < 1.456E-02 0.000E+00 ( ) ZR-95 756.72 < 2.162E-02 0.000E+00
'I-131 '364.48 < 1.142E-02 0.000E+00 CS-134 604.66 < 8.157E-03 0.000E+00 CS-137 661.65 < 1.268E-02 0.000E+00 BALA-140 1596.49 < 1.889E-02 0.000E+00 K-40 1460.75 0.194 5.612E-02 Total Fraction of Reporting Level O.000E+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT 9/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tri ti um . Aloha and Beta results are the best estimate of the activity and the less than sigh indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD Analy:ed by:___ ________________________ Approsed by:__ @ _b @ ________________ Date: ___/zf_/R____ i (\_))
~
VAX/VMS Scmple Analycio R: port gsnarotsd.:' 18-JAN-1988 14:42:08
.,7 P1' ant Name- ~
.: 'CNS Sample. Number: 's-438.
-(~'E ; Type / Location : AIR RADIOIODINES / 201 -
- .~k / Sample Date ,a 13-JAN-1988 10:30:00 Acq. Start Time : 18-JAN-1988 14:11:03' Sample Quantity 539.000 M3 o . Sample 1IDf -6JAN TD-13JAN88 Measurement Type'_:'
ROUTINE
***** Gamma-Spectroscopy Anal ysi s * ****
. Activity 1-Sigma. MDA>- Frac. of Nuclide Energy (pCi/M3) Error req.LLD Rpt. Level MN-54 834.83 < 1.196E-02 0.000E+00-CO-58 810.76 < 1.396E-02 0.OOOE+00' FE-59 1099.22 < 3.193E-02 0.OOOE+00
.CO-60 1332.47 < 1.584E-02 0.OOOE+00 ZN-65 '1115.52 < 3.372E-02 0.OOOE+00 NB-95 765.78 < 1.355E-02 0.000E+00 2R-95 '756.72 *< 2.336E-02 0.OOOE+00 I-131 364.'48 < '1.146E-02 0.000E+00 CS-134 604.66 < 8.687E 0.000E+00 CS-137 661.65 < 1.428E-02 0.000E+00 BALA-140 1596.49 < 2.533E-02 .
0.OOOE+00 K-40 1460.75 0.397 0.101 ("'f
'(/
Total Fraction of Reporting Level O.OOCE+00
\
Anal yz ed by n _______ , _i _ _ - . _ _ _ _ Approved by:_ ~A/ b, __________________ Date: _.z_/_g/__gg__
- t VAX/VMS Sample Analysis Report generated : 26-JAN-1988 09:02:13 p.
_) Plant Name : CNS ! Sample Numbe'r : 451 Type / Location : AIR RADIOIODINES / 201 Sample Date : 20-JAN-1988 11:05:00 Acq. Start _ Time : 25-JAN-1988 13:00:42 Sample Quantity : 573.000 M3 Sample ID : 13JAN TO 2OJAN88 Measurement Type : ROUTINE
*****-Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.378E-02 0.OOOE+00 CO-58 810.76 < 1.057E-02 0.OOOE+00 FE-59 1099.22 < 3.OO6E-02 0.OOOE+00 CD-60 1332.47 < 1.670E-02 0.OOOE+00 ZN-65 1115.52 < 2.226E-02 0.OOOE+00 NS-95 765.78 < 1.154E-02 0.OOOE+00 ZR-95 756.72 < 2.476E-02 0.OOOE+00 1-131, 364.48 < 1.170E-02 0.OOOE+00 CS-134 604.66' < 1.025E-02 0.OOOE+00 CS-137 661.65 < 1.562E-02 0.000$+00 73 BALA-140 1596.49 < 2.492E-02 0.OOOE+00
) K-40 1460.75 0.530 9.833E-02 Total Fraction of Reporting Level O.OOOE+00 Analyzed by: . _ _ _, _a Approved by:__DL I.__ ________________
Date: _s_ / _ zt, / __es, __ i i 1 1 4 s
'w.J l
i l
i y .
.r
~
, VAX/VMS Sample: Analysis Report generated a 3-FEB-1988 10:12:16
}~x ^
. ](,) Plant Name : CNS Sample Number 484 Type / Location : AIR RADIDIODINES /~201.
Sample Date . : '27-JAN-1988 11:20:00 Acq. Start Time : 2-FEB-1988 14:54:53 Sample Quantity .: 597.000 M3 Sample ID : 2OJAN TO 27JANB8 _ , , Measurement Type : ROUTINE _--------------------==_ ---- .-------------
***** Gamma-Spectroscopy Analysis'*****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.194E-02 0.OOOE+00 CO-58 810.76 <L1.025E-02 0.000E+00 FE-59 1099.22 < 2.590E-02 0.OOOE+00 CO-60 1332.47 < 4.669E-03 0.000E+00
, ZN-65. 1115.52 < 3.139E-02 0.OOOE+00 NB-95. 765.78 < 1.040E-02 0.000E+00 ZR-95 756.72 < 1.960E-02 0.OOOE+00 I-131' 364.48 < 1.743E-02 0.OOOE+00
- CS-134 604.66 < B 712E-03 0.000E+00
. CS-137 661.65 < 1.413E-02 0.000E+00 BALA-140 1596.49 < 2.174E-02 0.OOOE+00
_fD K-40 1460.75 0.338 9.364E-02 bl ---------- Total Fraction of Reporting Level -
'O.000E+00 Analyzed by:_,
._,~_ $ n mg _
t
- )
Approved by:__e % _[_ ________________ Date: __4/_.;p_/_ M___ 4 l %). l m._____________--- - . . . - . _ -
. . VAX/VMS'Semplo Analysin Raport.gsnarstad- 5-FEB-1988'13:20:14 Plant Name~ CNS Sample' Number s.498
-I')!
Type / Location 31 AIR RADIOIODINES / 201
-V Sample Date :
3-FEB-1988 09:58:00
'Acq. . Start-Time : .5-FEB-1988 12:48:44 Sample Quantity :- 538.000 M3-
- Sample ID 27JAN TO 3FEB88-Measurement Type': ROUTINE
***** Gamma-Spectroscopy Analysis *****
. Activity 1-Sigma MDA> Frac. of Nuclide. Energy (pCi/M3) Error req LLD Rpt.' Level MN 834.83 -< 1.591E-02 'O.OOOE+00 CO-58 810.76 < 1.7?3E-02 0.OOCE+00 FE-59 1099.22 < 2.747E-02 0.OOOE+00 CO-60 1332.47 <.1.453E-02 0.OOOE+00 ZN 1115.52 < 3.501E 0.OOOE+00 NB-95 .765.78 < 8.312E-03 0.OOOE+00
, 2R-95 756.72 < 2.148E-02 0.OOOE+00 I-131- 364.48 < 1.309E-02 0.OOOE+00 CS-134. 604.66 < 1.181E-02 0.OOOE+00 CS-137 661.65 <'9.778E-03 0.OOOE+00 BALA-140 1596.49 < 7.316E-03 0.OOOE+00
__________ a Total Fraction of Reporting Level C.OOOE+00 O i Analyzed by: 2g m cw__________ J Approved by:__ h __I._[ _ _ _ _ _______ Date: __4 / _f_ / _@6_ __ . 6
1 I
)
_________________________________________________________________________q VAX/VMS Sample Analysis Report generated : 16-FEB-1988 10:01:10 )
. p 4 V I P1 ant Name : CNS f Sample Nuniber 518
. Type / Location : AIR RADIOIODINES / 201 Sample Date : 10-FEB-1988 12:27:00 Acq. Start Time : 16-FEB-1988 09:30:03 i Sample Quantity : 616.000 M3 j Sample ID : 3FEB TO 10FEB88 :
Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 9.782E-03 0.OOOE+00 CO-58 810.76 < 1.149E-02 O.OOOE+00 FE-59 1099.22 < 2.500E-02 0.OOOE+00 CO-60 1332.47 < 1.553E-02 0.GOOE+00 ZN-65 1115.52 < 3.280E-02 0.OOOE+00 NB-95 765.78 < 1.138E-02 O.OOOE+00 2R-95 756.72 < 2.670E-02 0.OOOE+00 I-131 364.48 < 1.490E-02 0.OOOE+00 CS-134 604.66 < 1.064E-02 O.OOOE+00
,r g CS-137 661.65 < 1.095E-02 0.OOOE+00 V BALA-140 1596.49 < 1.774E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Analyred by:__________________._ ______
w AP proved by:__ M _[ _ ______________ Date: __A./_ta.'_ @ .__ 9
f '-
==-------
VAX/VMS Sample Analysis Report generated : 22-FEB-1988 15:22:00 O
\/ Plant Name : CNS Sample Number 535-Type / Location : AIR RADIDIODINES / 201 Sample Date : 17-FEB-1988 10:55:00 Acq. Start Time : 22-FEB-1988 14:50:55 Sample Quantity :- 493.000 M3 Sample ID : 10FEB TO 17FEB88 Measurement Type : ROUTINE
__-------------------==_ _ - - - - - - - - - - - - = - - ------------------
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Si g ma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.233E-02 0.OOOE+00 CO-58 810.76 < 1.305E-02 0.OOOE+00 FE-59 1099.22 < 9.401E-03 0.OOOE+00 CO-60 1332.47 < 2.330E-02 0.OOOE+00 ZN-65 1115.52 < 3.409E-02 0 OOOE+00 NB-95 765.78 < 2.062E-02 0.OOOE+00 ZR-95 756.72 < 2.295E-02 0.OOOE+00 I-131 364.48 < 2.OO3E-02 0.OOOE+00 CS-134 604.66 < 1.614E-02 0.OOOE+00 CS-137 661.65 < 1.454E-02 0.OOOE+00 r~s BALA-140 1596.49 < 9.380E-03 0.OOOE+00 (_) K-40 1460.75 0.437 0.127 Total Fraction of Reporting Level O.OOOE+00 Anal yz ed by:,,_h_ _ _ _ _ _ _ _ _ _ _ , , _ Approved by:__ % _[2 _____________ Date: _!_/_ / A ___ 13 l l
__________________________________ -____L_____________________. IVAX/VMS\Samplo . A' nalysis-, R5 port 'gansrated_ _ _ _ - - L29-FEB-1988 14:21 53-3 ':. Plant'Name' : CNS-SampleLNumber. 3 572-
, < Type / Location'. xt AIR RADIDIODINES / 201
.f'VJ~y ' Sample Date : 24-FEB-1988 09:54:00' Acq.' Start. Time :-'29-FEB-1988 113:50:41-Sample Quantity : 568.000 M3 Sample ID- : 17FEB:TO 24FEB88 1 Measurement Type;: ROUTINE
***** Gamma-Spectroscopy Analysis'*****
Activity 1-Sigma .MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt.' Level MN-54 834.83. < 1.725E-02 0.OOOE+00 CO-58 810.76 <.1.685E-02 0.OOGE+00 FE-59 1099.22. < 3.111E-02 0.COOE+00 CO-60 1332.47 < 1.918E-02 0.OOOE+00 ZN-65 1115.52 < 3.919E-02 0.OOGE+00 NS-95 765.78 < 1.713E-02 0.OOGE+00 ZR 756.72 < 3.390E-02 0.OOOE+00 I-131 364.48 < 1.901E-02 0.OOOE+00 CS-134 604.66 .< 1.452E-02 0.OOOE+00
- CS-137 661.65 < 1.723E-02 0.OOOE+00 BALA-140 1596.49 < 2.446E-02 0.OOCE+00 K-40 1460.75 0.668 0.158 Total Fraction of Reporting Level .O.OOOE+00
. O.
Analyzed by:___ _ _ _ _ _ _ _ _ _ ______
/
Approved by:___ N _f,_ _
.__________ Date: _3_/__V __ff__
4 e 1 l l l l l .
c------------------------------------------------------------------------- W- ~ VAX/VMS Sample Analysie. Raport - gunsratsd 2. 9-MAR-1988n15:36:55 Plant Name- : _CNS
.. -Sample Number- : 594
[~
. Type / Location' s AIR RADIOIODINES / 201 Sample Date: :. '2-MAR-1988 09:55:00 Acq. . Start Time . : 9-MAR-1988 15:05:48 Sample Quantity : 573.000 M3 Sample ID 24FEB TO 2 MAR 88 Measurement Type : ROUTINE .
-------------------------------------- _=---------------------------- .
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide' Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.311E-02 0.OOOE+00 CO-58 810.76 < 1.339E-02 0.OOOE+00 , FE-59' 1099.22. < 2.445E-02 0.OOOE+00 - CO-60 1332.47 < 1.511E-02 0.OOOE+00 2N-65 1115.52 < 2.467E-02 0.OOOE+00 NB-95 765.78 < 1.328E-02 0.OOOE+00 2R-95 756.72: < :1. 592E-02 0.OOOE+00 I-131 364.48 < 1.272E-02 0.OOOE+00 CS-134 604.66 < 1.010E-02 0.OOOE+00 - CS-137- 661.65- < 1.281E-02 0.OOOE+00 BALA-140 .1596.49 < 3.112E-02 0.OOOE+00
. Total Fraction of Reporting Level O.COOE+00 Analyzed by: 4 Approved bys__ M __(_ u _ ____ _ _ _
Date: _J_ / _y/_ / _$___
?
I O 4 _ _ - _ _ _ _ _ _ _ _ __ _. _. l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -__________=- VAX/VMS Sample _Analysi's Rsport ggnaratadL: 15-MAR-1988 12:12:46: Plant Name: CNS EfN Sample. Number' ' ::614~ i f. Type / Location. -:' AIR RADIDIODINES /,201-
~
Sample Date .- 9-MAR-1988 12:20:00-Acq.- Start Time J: 15-MAR-1988 11:41:42 Sample Quantity . 573.OOO'M3
' Sample:ID- -2 MAR TG 9 MAR 88 Measurement Type. ; ROUTINE
***** Gamma-Spec troscopy Anal ysi s *****
Acti'vity 1-Sigma MDA> Frac. of-Nuclide Energy (pCi/M3) Error reg LLD'Rpt. Level MN 834.83. < 1.773E-02 0.OOOE+00 CO-58 810.76 < 2.289E 0.OOOE+00 . FE-59 1099.22 < 4.233E-02 0 OOOE+00
' CO 1332.47 < 2.889E-02 -0.OOOE+00 2N-65 1115.52 <.5.206E-02 0.OOOE+00 NB-95 765.78 <~1.804E-02. O.COOE+00
. ZR 756.72 < 3.577E-02 0.OOOE+00 I-131 364.48 < 2.271E-02 0.OOOE+00 , CS-134 604.66' < 1.400E-02 0.OOOE+00
. CS-137 661.65 <~1.892E-02 0.OOCE+00 BALA-140 '1596.49 .< 3.197E-02 0.OOOE+00 K-40 1460.75 0.787 0.128
=____
.( ,j . -
Total Fraction of Reporting Level O.OOOE+00 Anal yz ed ~ by: __ h h% _______ Approved by:__ M f._ _______. _ Date: _3_ / J6_ / __qLQ__ 4
l I ---- __---------. __-------.. -__- - ----------------------------..-- \ VAX/VMS Sample Analysis Report-generated : 29-MAR-1988 15:01:32 i I ( l y) Plant Name : CNS Sample Number 634 ( Type / Location : AIR RADIDIODINES / 201 Sample Dcte : 16-MAR-1988 10:22:00 Acq. Start Time : 22-MAR-1988 12:01:01 Sample Quantity : 564.000 M3 Sample ID : 9 MAR TO 16 MAR 88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD'Rpt.. Level MN-54 834.83 < 1.797E-02 0.OOOE+00 CO-58 810.76 < 1.778E-02 0.OOOE+00 FE-59 1099.22 < 3.895E-02 0.OOOE+00 CO-60 1332.47 < 2.775E-02 0.OOOE+00 ZN-65 1115.52 < 3.732E-02 0.OOOE+00 NB-95 765.78 < 1.808E-02 0.OOOE+00 ZR-95 756,72 < 2.278E-02 0.OOOE+00 I-131 364.48 < 1.630E-02 0.OOOE+00 CS-134 604.66 < 1.321E-02 0.OOGE+00 CS-137 661.65 < 1.677E-02 0.OOOE+00 7m BALA-140 1596.49 < 2.938E-02 0.OOOE+00
;'j __________
Total Fraction of Reporting Level O.OOOE+00 Analyzed by:________ 2_A o _ Approved by:_ 2 f_fm h ._ ___________ Date: _y_/ ac/_p>___
____,,__7-__-. f
- & y s
________________________-_-- - _ --=____ ________________ __
;VAX/VMS Sample: Analysis; Report generated 30-MAR-1988 09:09:51
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~
Plant Name : CNS Sample Number . 671-
- Type /Locati on : AIR RADIDIODINE91/ 201
, Sample Date : 23-MAR-1988 10:40:00 Acq.. Start Time : 30-MAR-1988 08:37:35:
' Sample Quantity. : 573.000 M3 Sampl e .' I D : 16 MAR TO 23 MAR 88 '-
Measurement Type : ROUTINE
.__________________________ _ -- ____________________________ = ______
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error. req LLD-Rpt. Level MN-54' 834.83 < 1.091E O.OOOE+00 CO-58 810.76 < 1.336E 0.OOOE+00 FE .1099.22 <:3.624E-02 0.OOOE+00 CO-60 1332.47 < 1.483E-02 0.COOE+00 N ~ ,a em s,.m , , ZN-65 1115.52 < 2.857E-02 0.OOOE+00 NB-95 ~765.78- <'1.232E-02 0.OOOE+00 ZR-95 756.72 < 4.622E 0.OOOE+00
-I-131" 364.48 :< 1.910E-02 0.OOOE+00 CS-134 604.66 < 8.446E-03 0.OOOE+00-
-CS-137 '661.65 '<il.169E-02 0.OOOE+00 BALA-140 1596.49 < 2.093E-02 .O.OOOE+00 L(_-f K-40 1460.75 0.227. 6.075E-02 Total Fraction of Reporting Level O.OOOE+00 Analyzed by:______ _;___ ___ .__
-Approved by:_ M _k ___- .___________
Date: __3_/_R /__fq__ L
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i
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J L- ' 1
VAX/VMS Sample Analysis Report generated 6-APR-1988 13:45:04 _) Plant Name : CNS Samole Number 721 Tvpe/Locati on : AIR RADIDIODINES / 201 Samole Date : 30-MAR-1988 11:40:00 Acq. Start Time : 5-APR-1988 12:54:47 Sample Quantity : 603.000 M3 Sample 1D : 23 MAR TO 30 MAR 88 Measurement Type : ROUTINE i
= _ _ _ _ _ _ _ _ _ _ _ - - ==_ ______
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rot. Level MN-54 834.83 < 1.847E-02 0.OOOE+00 CO-58 810.76 .< 1.721E-02 0.OOOE+00 FE-59 1099.22 < 3.225E-02 0.OOOE+00 CO-60 1332.49 < 2.095E-02 0.OOOE+00 ZN-65 1115.52 < 4.402E-02 0.OOGE+00 NB-95 765.79 < 1.823E-02 0.OOOE+00 ZR-95 756.72 < 2.829E-02 0.OOOE+00 I-131 364.48 < 1.739E-02 0.OOGE+00 CS-134 604.70 < 2.669E-02 0.OOGE+00 CS-137 661.65 < 2.OO6E-02 0.OOOE+00
,q , BALA-140 537.32 < 6.702E-02 0.OOOE+00
(,) .K-40 1460.81 0.589 0.155 Total Fraction of Reporting Level O.OOOE+00 Anal yz ed by: __Q}u _. h _______ Approved by:____ M _(,_ _2________________ Date: _ _[_ / _f _ / _ @ 8._ __
p VAX/VMS Sample Analysis Report generated : 20-APR-1988 11:43:07
,m i i LJ Plant Name : CNS Sample Number : 741 Type / Location : AIR RADIDIODINES / 201 Sample Date . : 6-AFR-1988 09:34:00-Acq. Start Time : 8-APP--1988 11:59:18 Sample Quanti':y : 589,000 M3 Sample ID : ~/> MAR TO 6APR88 Measurement Type' ROlJT INE
* * * ** Gamma--Spec troscopy Ane1ysie **+o Ar:1 i wi t v 1-Sigma MDA:r Frac. of Nuclide Energy tpC1 / M 3 ') Error reg LLD Rpt. Level MN-54 834.83 t 1.261E-02 0.OOOE+00 CO-58 810 ~76 1. 0.18E -02 0.COOE+00 FE-59 1099.22 -
?. 4 97E--02 0.OOOE+00 CO-60 1332.49 < 1.147E-02 O.OOOE+00 ZN-65 1115.52 2.365E-02 0.OOOE+00 NB-95 765.79 1.069E-02 0.OOOE+00 ZR-95 756.72 < 2.197E-02 O.OOOE+00 I-131 364.48 '
O.604E-07 0.OOOE+OO CS-134 604.70 ' 7.105E-03 O.OOOE+00 f.s CS-137 661.65 < 1.167E-02 0.OOOE+00 (')- BALA-140 K-40 537.32 1460.81 4.017E-02 O.253 O.OOOE+00 6.314E-02 Total Fraction of Reporting Level O.OOOE+00
\
\
- An al yz ed by
- ___ ____ _j.
W______.__., a l ' Ap p r o v e d e> y : _ _ _ mes~-__ _ _ _._ _ _ _ _ _ 0+te: _f_ ' .ao_ Mc . .. 1 I 1 l J
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. - - _ _ _ - _ _ _ . _ . _ _ . _ - - . _ _ _ _.. .n.
VAX/VMS Sample Analysis Report generated : 20-APR-1988 07: 48:22
?, ,
t l v Plant Name : CNS Samole Number : 769 Type / Location : AIR RADIDIODINES / 201 Samole Date : 13-APR-1988 10:44:00 Acq. Start Time : 19-APR-1988 15:34:30 Sample Quantity : 571.000 M3 Sample ID : 6APR TO 13APR88 Measurement Type : ROUTINE
* **** Gamma-Spectroscopy Anal vsi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 s 1.085E-02 O.OOGE+00 CO-58 810.76 < 1.296E-02 0.OOOE+00 FE-59 1099.22 , 2.710E-02 0.OOGE+00 CD-60 1332.49 ( 1.328E-02 0.OOOE+00 ZN-65 1115.52 4: 2.746E-02 0.OOOE+00 - NS-95 765.79 < 1. 4'-74E-0 2 0.OOOE+00 ZR-95 756.72 < 2.853E-02 O.GOOE+00 I-131 364.48 , 1.155E-02 0.OOOE+00 CS-134 604.70 , 1.254E-02 0.OOOE+00 CS-137 661.65 ; 1.396E-02 0.OOGE+00 (y) BALA-140 537.32 < 5.444E-02 O.GOOE+00 K-40 1460.81 0.239 0.101 Total Fraction of Reporting Level O.OOGE+00 An al vr ed by: _______ _,___-- ____________ Approved by:_ M _[. [_____,___________ Date: _ _/_2_/_
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VAX/VMS Samplo Anclysis Rzport _ gunsrated : 26-APR-1988 07:48:42-Plant Name : CNS Sample. Number : 789
](_/ - g. Type / Location. : AIR RADIDIODINES / 201 Sample Date : 20-APR-1988 09:56:00 Acq,' Start' Time s'25-APR-1988 14:43:42 Sample Quantity : 540.000 M3 Sample ID : 13APR TO 20APR88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. c'f Nuclide. Energy (pCi/M3). Error' reg LLD Rpt. Level-MN-54 834.83 <'i.523E-02 0.OOOE+00 CO-58 810.76 < 1.381E-02 0.OOOE+00 - FE-59 1099.22 < 3.820E-02
. 0.OOOE+00 CO-60 1332.49 < 2.070E-02 0.OOOE+00 ZN-65 1115.52 < 3.888E-02 0.OOOE+00 NB-95 765.79 < 1.826E 0.OOOE+00 LZR-95' 756.72 < 3.292E-02 0.OOOE+00 I-131 364.48 < 1.703E-02 0.OOOE+00 CS-134 604.70 < 1.404E-02 0.OOOE+00 CS-137 661.65 < 1.747E-02 0.OOOE+00 BALA1 140 537.32 < 5.533E-02 0.OOOE+00 K 1460.81 0.352 8.288E-02 I
) Total Fraction of Reporting-Level. O C OOE+00 Analv=ed by:___ If_ __ _ _ _ _ _ _ _ _ ___
Approved by:_ [ _ _ _ _ ;______________ Date: _ _ _ / ;4_ / _ J_S_ __ l 1 1
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- l. _ _ - -
-=-
= __-_- .---- --------------- --- _ ---- ----_--- ___ _ _ _
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
%,) ------------_--= _-_----------_---_-----_--------------------_-------_-
VAX/VMS Sample Analysis Report generated : 29-APR-1988 15:38:04 4 Plant Name : CNS Sample Number : 817 Type / Location : AIR RADIOIODINES / 201 Sample Date : 27-APR-1988 11:17:00 Acq. Start Time : 29-APR-1988 14:33:24 Sample Quantity : 561.000 M3 1 Sample ID : 20APR TO 27APR88 l Measurement Type : ROUTINE _ - - - = - _ = _ _ _ _ - _ . _ _ - _ _ . _ .-_ _ _ _ _ _ - _ _ - _ _ _ - - - - - - - - _ _ _ - _ . . _ _
***** Gamma-Spectroscopy Analysis ***** ,
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level l MN-54 834.83 < 8.443E-03 0.OOOE+00 CO-58 810.76 < 1.049E-02 0.OOOE+00 FE-59 1099.22 < 3.598E-02 0.OOOE+00 CO-60 1332.49 < 2.164E-02 0.OOOE+00 ZN-65 1115.52 < 4.020E-02 0.OOOE+00 NB-95 765.79 < 1.251E-02 0.OOGE+00 (~T ZR-95 756.72 < 2.779E-02 0.OOOE+00 (_) I-131 364.48 < 1.178E-02 -0.OOOE+00 CS-134 604.70 < 1.264E-02 0.OOOE+00 l CS-137 661.65 < 8.782E-03 0.OOOE+00 BALA-140 537.32 < 4.138E-02 0.OOOE+00 K-40 1460.81 0.184 7.968E-02 Total Fraction of Reporting Level O.OOOE+00 Samma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error i s not applicable. - Tritium, Alpha and Beta results are the best estimate of the 5 activity and the less than sign indicates that the net activity is less i than the critical level, CL. CL = 0.5 LLD I __--_--__ _ _ _ _ - _ _ _ _ _ _ _ _ =-- --- ____ ____--______--- Analyzed by:___ ______________ Approved by:_ M f _ ____ _____________ Date: _ _/_g_/_gq___ (~i I s_/ I l l' l ; i m_____. __ . _ _ _ _ _ _ _ i
- 4. . -
DUKE POWER COMPANY' APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
-- ; -== ____________________=- __________
VAX/VMS Samole Analysis Report generated : 6-MAY-1988 14:51:32-l L Plant Name : CNS Samole Number : 827 Tyoe/ Location : AIR RADIOIODINES / 201'
. Sample Date : 4-MAY-1988 09:20:00 Acq. Start Time : 6-MAY-1988'12:58:50 . - -
Sample Quantitv' : 564.000 M3 Sample'ID : 27APR TO 4MAY88 - Measurement Type : ROUTINE
===== -__- -_______
***** Gamma-Spectroscopy Analysis.*****
Activity Sigma MDA> Frac. of Nuclide Energy (pCi/M3) . Error -req LLD Rpt. Level H MN-54 834.83 < 1.391E-02 0.OOOE+00 CO-58 810.76 <'i. 866E-02 0.OOOE+00
. FE-59 1099.22 < 2.596E-02 0.OOOE+00 CO-60 1332.49' < 2.012E-02 0.OOOE+00 2N-65 1115.52 < 2.856E-02 0.OOOE+00 h
, - (,/
NB-95 ZR-95 765.79
- 756.72 1.738E-02 2.349E-02 0 OOOE+00 0.OOOE+00 I-131 364.48 < 1.555E-02 0.OOOE+00 CS-134 604.70 < 1.390E-02 0.OOOE+00 CS-137 661.65 < 1.650E-02 0.OOOE+00 BALA-140 537.32 < 5.226E-02 0.OOOE+00 K-40 1460.81 0.236 0.112
- l. Total Fraction of Reoortino Level O.OOOE+00 k
Gamma results are listed as Less Than Levels usino Tech Spec LLD ecuation. LLD ='4.66 SQRT B/t. Presence of less than sign for gamma F results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity i s - l ess than the critical level. CL. CL = 0.5 LLD _________________________________ - = _ _ _ _ _ _ _ _ _ _ - -
.=______
Analyzed by _ h w h _________ Approved by:_ 3 _b ___c____ _ _ _ _ Date: _1/ __f_ / __2,9___ O
. DUKE POWER COMPANY
- l. <
APPLIED SCIENCE CENTER-RADIDANALYSIS LABORATORY
;-q ________________________________________________________________ - - - - _ _ _
i f' VAX/VMS Samole Analysis Report generated : 18-MAY-1988 11:00:15 Plant Name : 'CNS
' Sample Number : 855 Type / Location : AIR RADIOIODINES / 201 Sample Date : 11-MAY-1988 11:45:00 Acq. Start Time : 17-MAY-1988 14:42:16 Sample Quantity' : 579.000 M3 Sample ID : 4MAY TO 11MAY88 Measurement Type : ROUTINE
_ _ _ _ _ _ _____________- - . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = = = = = _ - - - ___
***** Gamma-Spectroscopy Analysis ***** _!
Activity 1-Sigms MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Leve) MN-54 834.83 < 1.48BE-02 0.OOOE+00 CO-58 810.76 < 1.677E-02 0.OOOE+00 FE-59 1099.22 < 3.76BE-02 0.OOOE+00 CD-60 1332.49 < 1.597E-02 0.OOOE+00 ZN-65 1115.52 < 2.707E 0.OOGE+00 NB-95 765.79 < 7.489E-03 0.OOOE+00 2R-95 756.72 < 2.477E-02 0.OOOE+00 s: I-131 364.48 < 1.014E-02 0.OOOE+00 I g CS-134- 604.70 < 8.983E-03 0.OOOE+00 CS-137 661.65 < 1.3OOE-02 0.OOOE+00 BALA-140 537.32 < 4.462E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed oss Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD ______________ ____ t Analyzed by:_____________._J_ _ Approved by:_ _(_ _ _ _ _ _ _ _ _ _ _ ____ Date: _f_ / _/ g ___ O
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
,_, - - - _ ...- - _ - _ - _ _ _ = _ __-_---____--_-_-_--________---_-___-_-_____-_________
l ) VAX/VMS Sample Analysis Report generated 31-MAY-1988 13:18:21 x_/ Plant Name : CNS Sample Number 877 Type / Location : AIR RADIOIODINES / 201 i Sample Date : 18-MAY-1988 10:24:00 Acq. Start Time : 24-MAY-1988 11:52:43 Sample Quantity : 566.000 M3 Sample ID : 11MAY TO 18MAY88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis ***** !
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.471E-02 0.OOOE+00 CO-58 810.76 < 1.459E-02 0.OOOE+00 FE-59 1099.22 < 2.259E-02 0.OOOE+00 C0-60 1332.49 < 1.751E-02 0.OOOE+00 ZN-65 1113.52 < 8.670E-03 0.OOOE+00 NB-95 765.79 < 1.462E-02 0.OOOE+00 ZR-95 756.72 < 2.863E-02 0.OOOE+00 I-131 364.48 < 1.725E-02 0.OOOE+00 [ '; CS-134 604.70 < 1.014E-02 0.OOOE+00 N/ CS-137 661.65 < 1.663E-02 0.OOOE+00 BALA-140 537.32 < 5.482E-02 0.OOGE+00 K-40 1460.81 0.380 8.501E-02 Total Fraction of Reporting Level O.OOCE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma ' 4 results means no peak was found and the zero error is not applicable. j I Tritium, Alpha and Beta results are the best estimate of the l activity and the less than sign indicates that the net activity is less) than the critical level. CL. CL = 0.5 LLD l Analyzed by:_ h_ ' m __________ , Approved by:_ A _b_ - Date: __(./_f_/___BO__ l 73 N,] l l l l L___________________ _
(' ( , . ___ ,-. ~ ?^>V , ,
. DUKE: POWER COMPANY:
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. ;APPLIEDrSCIENCE'CENTERc H
~
RADIDANALYSIS LABORATORY.
- +: ,
c .c x) yAX/VMS, Sample. Analysis' Report' generated.. 1-JUN-1988 10s.03:59'
~
l IPlant[Name CNS- _ Sample Number 897 . .
' Type,/ Loc ati on 's : AIR RADIDIODINES / - 201 3 Sample.Date' MAY-1988410:15:OO 1
'Acq.sStart Time : 1-JUN-1988 09:07:48 ~t
/ s -Sample'Ouantity s' 599.000 M3
.Samp1'e..ID~ .
311BMAY TO 25MAY88-
= Measurement Type s. ROUTINE.
, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _____=_ _ ____
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA>. . Frac. of Nuclide, Energy .(pCi/M3) Error. reg LLD Rpt. Level MN-54' -834.83 < 1.169E-02 0.OOOE+00
- CO 810.76 < 1'3OOE-02
. 0.OOOE+00' "FE-59 1099.22 < 3.030E-02 0.OOOE+00 -
CO-60 ;1332.49 < 1.59BE-02 0.OOOE+00 ZN-65: 1115.52 :< 4.058E-02 0.OOOE+00-
.NB-95 765.79 <'1.352E-02 O.OOOE+00
.ZR-95 756.72 < 2.213E-02 0.OOOE+00 .
I-131 364'.48 <.2.067E-02 0.OOOE+00
~ ' CS-134 604.70 < 1.328E-02 0.OOOE+00 CS-137 661.65 < 1.064E-02 0.OOOE+00 BALA-140 537.32 < 5.604E-02 0.OOOE+00 K-40 1460.81 0.373 0.101-Total' Fraction of Reporting Level O.OOOE+00
~
Gamma results~are 1isted as Less Than Levels using Tech Spec LLD equation. LLD ='4.66 SORT B/t. Presence of less than sign for gamma results means no peak'was found and the zero error.is not applicable.-- Tritium, Alpha and Beta results are the best estimate of'the-
. activity and the less than sign indicates that the net activity is less-than-the critical level, CL. CL = 0.5 LLD
_______________________q._________________________________________ j
~ Anal yz ed by s _______ ,# _______ ___ _ ___
. Approved by __ M _[.__ >
________ ___ Date: _A /_g_/_p3___ i i V = _ _ _ _ _ - ._
DUKE POWER COMPANY-l APPLIED SCIENCE CENTER l RADIDANALYSIS LABORATORY
./~T VAX/VMS Sample. Analysis Report generated : 8-JUN-1988 11:56:10 K) .
Plant.Name' : CNS Sample Number 917 l Type / Location : ' AIR RADIGIODINES / 201 Sample Date : 1-JUN-1988 09: 50: 00 i Acq. Start Time : 8-JUN-1988 09:48:51 Sample Quantity- : 597.000 M3 Sample ID. '25MAY TO 1JUN88 Measurement. Type ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83. < 1.012E-02 0.OOOE+00
.CO 810.76 < 6.092E-03 0.OOOE+00 FE-59 '1099.22 < 3.700E-02.. O.OOOE+00 CO-60 1332.49 < 1.550E-02'- 'O.OOOE+00 ZN-65 1.115.52 < 3.016E 0.OOOE+00 NB-95 765.79 < 1.028E-02 0.OOOE+00 ZR-95 756.72 < 1.991E-O'2 ' O.OOOE+00 I-131 364.48 < 1.708E-02 0.OOOE+00 fs CS-134 604.70 < 9.579E-03 0.OOOE+00 -
-( CS-137 661.65 < 1.068E-02 0.OOO'E+00 .
BALA-140 537.32 < 4.670E-02 0.OOOE+00 K-40 1460.81 0.245 6.559E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66.SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD j ---------------------------- Analyzed by:____ N Approved by:____%[Cdkjh _ ____,__________ Date: __&_/__L/_29___ i k l 4
t l-L. 1 l r~j. t
\-
DUKE POWER COMPANY AFPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY ____________________________________________________________-- -=_______ VAX/VMS Sample Analysis Report generated : 17-JUN-1988 11:59:20 l
. Plant Name : CNS Sample Number : 943 Type / Location : AIR RADIDIODINES / 201 Sample Date : 8-JUN-1988 09:25:00 Acq. Start Time : 17-JUN-1988 10:54:20 Sample Quantity : 567.000 M3 Sample ID : 1JUN TO 8JUN88 Measurement Type : ROUTINE
==. -- ________=- __________=
***** Gamma-Spectroscopy Anal ysi s *****, .. ,. ,
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN 834.83 < 7.469E-03 , O.OOOE+00 CO-58 810.76 < 8.015E-03 0.OOOE+00 FE-59' 1099.22 < 2.890E-02 0.OOOE+00 I' CO-60 1332.49 < 2.290E-02 0.OOOE+00 (- ZN-65 1115.52 < 1.986E-02 0.OOOE+00 NB-95 765.79 < 1.279E-02 0.OOOE+00 ZR-95 756.72 < 2.594E-02 0.OOOE+00 I-131 364.48 < 2.038E-02 0.OOOE+00 CS-134 604.70 < 1.036E-02 0.OOOE+00 CS-137 661.65 < 1.068E-02 0.OOOE+00 BALA-140 537.32 < 5.393E-02 0.OOOE+00 K-40 1460,81 0.295 6.960E-02 g _____= ~ Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL, CL = 0.5 LLD _ _ _ _ _ _ - .- _ _ _ _ - ___________= __________________________ Analyzed by:_ _____________ Approved by:_. % k [:_ i _ Date.: _.s,,_ / _ a / _ me_ _ _ O
----------------= -----------------------------------------------------
DUKE POWER COMPANY APPLIED SCIENCE CENTER l RADIDANALYSIS LABORATORY
"' =_=_------= --------------------
1' VAX/VMS Sample Analysis Report generated : 21-JUN-1988 13:53:25 l Plant Name : CNS Sample Number 965 Type / Location : AIR RADIOIODINES / 201 Sample Date : 12-JUN-1988 11:38:00 Acq. Start Time : 21-JUN-1988 13:07:34 Sample Quantity : 337.000 M3 Sample ID : 8JUN TO 12JUN88 Measurement Type : ROUTINE
--- =----------------------
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 2.330E-02 0.OOOE+00 CO-58 810.76 < i.560E-02 0.OOOE+00 - "'~ - FE-59 1099.22 < 5.412E-02 0.OOOE+00 CO-60 1332.49 < 2.843E-02 0.OOOE+00 ZN-65 1115.52 < 3.839E-02 0.OOOE+00 NB-95 765.79 < 3.088E 0.OOOE+00 ZR-95 756.72 < 4.726E-02 0.OOOE+00 e') I-131 364.48 < 3.244E-02 0.OOOE+00 () CS-134 CS-137 604.70 661.65 1.473E-02 1.953E-02 0.OOOE+00 0.OOOE+00 BALA-140 537.32 < 0.114 0.OOOE+00 K-40 1460.01 0.528 0.128 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD s . Analyzed by:_ m_ m _______ Approved by:__ M _b _____________ ___ Date: _ A / .f_z_. /2EL - _ _ 5 SqN As dw$ k .le r ble.sn .,Gy . A $ $-zz-se j l n i i
b-o ;________________________________________________________________________"; DUKE POWER COMPANY APPLIED SCIENCE CENTER' RADIDANALYSIS LABORATORY. f(~j .________________________________________________________________________c 5' 'VAX/VMS Sample Analysis Report generated : '24-JUN-1988 14:07:49
' Plant Name. : CNS Sample Number 977 Type / Location s' AIR RADIOIODINES /'201 Sample Date : 22-JUN-1988 10:20:00 Acq. Start. Time : 24-JUN-1988 13:17:38 Sample Quantity 611.000 M3 Sample'ID :,15JUN TO 22JUN88 Measurement Type s' ROUTINE
_ _ _ _ _ _ _ _ - - - __________________- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - ______c
***** Gamma-Sp ectroscopy Anal ysi s *****
L Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt.. Level MN-54 834.83 <.1.471E-02 0.OOOE+00 i
.CO-58 810.76 < 2.805E-03 0.OOOE+00 j FE-59 1099.22 < 1.884E-02 0.OOOE+00 CO-60 1332.49 < 1.239E-02 0.OOCE+00 ZN-65 1115.52 < 3.029E-02 0.OOOE+00 NB-95 765.79 < 1.288E-02 .d.OOOE+00 2R-95 756.72 < 1.845E-02 0.OOCE+00 T I-131 364.48 < 9.735E-03 0.OOOE+00 CS-134 604.70 < 1.327E-02 0.OOOE+00 CS-137. 661.65 < 1.138E-02 0.OOCE+00 BALA-140 537.32 < 2.899E-02 0.OOOE+00
____ _== Total Fraction of Reporting Level O.COOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD . equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. - Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is les! than the critical level, CL, CL = 0.5 LLD __-- h
- t Analyzed by:_ h ._ m h ______
Approved by:_ 3 d [_._ _____ __ _ _ _ _ _ Date: __6_/_3f_/__b.jl__ D a
e -__-_______-__-__----___------_-------__ 1
---_-___--__----- _l !
1 DUKE POWER COMPANY j 1 APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY v r~-
,' N /g VAX/VMS Sample Analysis ' Report generated a '6-JUL-1988-10:24:06 i
Plant Name : CNS 1 Sample Number : 1001 ,
. Type / Location 1 AIR RADIOIODINES / 201 d
' Sample ~Date : JUN-1988-09:30:OO Acq. Start. Time : 6-JUL-1988'08:53:24 ,
' Sample Quantity :' 610.000 M3 - J Sample ID .22JUN TO 29JUN88 Measurement Type : ROUTINE
- Gamma-Spectroscopy Analysis ***** q Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN 834.83< 1.149E-02 0.OOOE+00 CO-58 810.76 < 2.946E-03 0.OOOE+00 FE-59 1099.22. < 3.262E-02 0.OOOE+00 CO-60 1332.49 <.1.244E-02 0.COOE+00 ZN-65 1115.52 < 2.653E-02 0.OOOE+00 NB-95' 765.79 < 1.395E-02 0.OOOE+00 ZR-95 756.72 < 1.332E-02 0.OOOE+00
^
I-131 364.48 < 1.570E-02 O.OOOE+00
. {s,g/ CS-134 604.70 < 1.274E-02 0.OOOE+00 CS-137 661.65 < 1.061E-02 0.COOE+00 BALA-140 537.32 < 4.564E-02 0.OOOE+00 K-40 1460.81 0.309 7.280E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT'B/t. Presence of less than sign for gamma results means. no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
- - _ _ _ - - _ _ - - --_-_--___-_______-_______-_______________=- _
Mm___ Analyzed Approved by:_,_ <;g_._4 by:_ h __ [k______ Date: __ ______ _'_7_ / e_r _ / _ ss_ _ _ 1 D (V
;___________________= ________________________
DUKE POWER COMPANY ' ' APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY
~ ') ________________ ____________________________________________________
,' VAX/VMS Sample Analysis Report generated : 12-JUL-1988 17: 27: 45 Plant Name : CNS Sample Number : 1034 Type / Location : AIR RADIOIODINES / 201 Sample Date : 6-JUL-1988 11:15:00 Acq. Start Time : 12-JUL-1988 16:39:07 Sample Ouantity : 598.000 M3 Sample ID : 29JUN TO 6JUL88 Measurement Type : ROUTINE
_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ - _ = - -_________-__-_____-___--___--__---_--__-
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.603E-02 0.OOOE+00 CD-58 810.76 < 1.187E-02 0.OOOE+00 FE-59 1099.22 < 3.829E-02 0.OOOE+00 CO-60 1332.49 < 1.268E-02 0.OOOE+00 ZN-65 1115.52 < 4.102E-02 0.OOOE+00 NB-95 765.79 < 1.541E-02 0.OOOE+00 ZR-95 756.72 < 2.883E-02 0.OOOE+00 (~'S I-131 364.48 < 1.603E-02 0.OOOE+00 (_) CS-134 604.70 < 8.18BE-03 0.OOOE+00 CS-137 661.65 < 8.355E-03 0.OOOE+00 BALA-140 537.32 < 5.431E-02 0.OOOE+00 K-40 1460.81 0.245 8.393E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the ! activity and the less than sign indicates that the net activity is less ) than the critical level, CL. CL = 0.5 LLD l _______--_____________- = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - -_ _-___-__--- Analyzed by ____ ______________ Approved bys___ M _C s______________ Date: _E _ / _9_ / _aE _ __
%)
~ DUKE POWER COMPANY.
APPLIED SCIENCE CENTER
.RADIDANALYSIS LABORATORY s __________-______________________________________________________________
\ VAX/VMS Sample Analysis Report generated : 18-JUL-1988 11:11:02 q 1
1 Plant Name : CNS Sample Number : 1062 Type / Location : AIR RADIOIODINES / 201 j Sample Date : 13-JUL-1988 11:16:00 ! Acq. Start Time : 18-JUL-1988 09:51:16 Sample Quantity 599.000 M3 Sample ID . : 6JUL-TO 13JUL88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level , MN-54 834.83 <:1.248E-02 0.OOOE+00 ' CO-58 810.76 < 1.148E-02 0.OOCE+00 FE-59 1099.22 < 3.125E-02 0.OOOE+00 CO-60. 1332.49 < 1.843E-02 0.OOOE+00 ZN-65 1115.52 < 1.858E-02 0.OOOE+00 ND-95 765.79 < 1.12SE-02 0.OOOE+00 ZR-95 756.72 < 2.506E-02 0.OOOE+00 e I-131 364.48 < 1.146E-02 0.OOOE+00 ( CS-134 604.70 < 7.816E-03 0.OOOE+00 CS-137 661.65 < 1.139E-02 0.OOOE+00 BALA-140 537.32 < 2.722E-02 0.OOOE+00 Total Fraction of Reporting Lev <el O.OOOE+00 Gamma results are listed as Less Than Level s using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma i results means no peak was f ound and the zero error i s not applicable. l o l Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD f 4
-_______--_----_-==_ _ = _ _ - _ _ _ _ _ _ . ________---___---_____--______
g A _ Approved by:_- 4_b ____ f _________ Datet _f_ / _/0 /__ M _ j l i I i ( l l 1 l
)
l E______________________________________ _ _ . _ _ _ _
y ' e DLikE. POWER COMPANY APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY ^
. . , ~ -
VAX/VMS Sample Analysis Report generated a'22-JUL-1988 15:47:58 v. Plant'Name : CNS Sample Number 1079 Type / Location : AIR RADIGIODINES / 201 Sample Date : 20-JUL-19BB 10:36:00
'Acq. Start Time
- - 22-JUL -1989 13: 08: 25 Sample Guantity' : 610.000 M3 Sample-ID . 13JUL TO 2OJULGG Measurement. Type : . ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD'Rpt. Level
'MN-54 834.G3 <-1.367E-02 0.000E+00 CO-58 810.76 < 1.10GE-02 0.000E+00 FE-59 1099.22 < 2.911E-02 O.000E+00 i CO-60 1332.49 < 1.679E-02 0.000E+00 ;
'ZN-65 1115.52 < 2.617E-02 0.QOOE+00 j NS-95 765.79 < 9.137E-03 0.000E+00 2R-95 756.72 < 2.371E-02 O.OOGE+00
) I-131 364.48 < 8.291E-03 0.000E+00 C5-134 604.70 < 1.119E-02 0.000E+00 CS-137. 661.65 < 9.923E-03 O.000E+00 B Al . A- 140 - 537.32 < 4.334E-02 O.OOOE+00 Total Fraction of Reporting Level 0.000E+00 Ga nma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 50RT B/t. Presence of less.than sign for gamma results means.no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the ectivity and the less'than sign indicates that.the net activity is less than the critical level, CL. CL := 0. 5 LLD t Analyzed by: _h im. mw__ ,_ _ _ Approved by:_ _(_ ,b ____._________ Date: _f / J_{/ _m __ i p V
DUKE POWER COMPANY.~ APPLIED. SCIENCE CENTER RADIDANALYSIS LABORATORY q g#j. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
'~
'VAX/VMS Sample Analysis Report generated 1-AUG-1988-15:17:14
~
Plant Name : CNS Sample Number 's 1144
' Type / Location : AIR RADIOIODINES / 201 Sampie Date : 27-JUL--1988 '09: 22: 00 Acq.-Start Time : 1-AUG-1988 14 18:06 Sample Quantity 's 595.000 M3 Sample ID : 2OJUL.TO 27JUL88 Measurement Type : ROUTINE
*****-Gamma-Spectroscopy' Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.290E-02 0.OOGE+00 CO-58 810.76 < 1.286E-02 0.000E+00 i FE-59 ~1099.22 < 2.968E-02 0.000E+00 ;
- CO-60 1332.49 < 2.080E-02 0.000E+00 ;
2N 1115.52 < 3.138E-02 0.OOOE+00 ;~ NB 765.79 < 1.'484E-02 -0.000E+00 ZR-95 756.72 < 2.386E-02 0.OOOE+00 [ I-131 364'.48 < 1.029E-02' O.000E+00-
\ .
CS-134 604.70 < 1.iO1E-02 0.OOOE+00 CS-137 661.65 < 2.412E-03 0.000E+00 BALA-140 537.32 < 4.731E-02 0.OOOE+00 K-40 1460.81 0.352 7.862E-02 Total Fraction of Reporting Level 0.000E+00 3 Gamma results are listed as Less Than Levels using Tech Spec LLD
, equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
e Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net-activity is'less than the critical level, CL. CL a 0.5 LLD L Analyzed by:___ __________ _____________ l Approved by:__ M _f._. _[ .________ Date: _g_/__g/_Je___ 1 (" ( i'
S ;
APPLIED SCIENCE CENTER m- +
RADIDANALYSIS LABORATORY s-() VAX/VMS Sample Analysis Report generated : 8-AUG-1988 14:29:31 Plant Name CNS Sample Number : 1161 Type / Location : AIR RADIOIODINES / 201 Sample Date : 3-AUG-1988 09:30:00
- Acq. Start Time : 8-AUG-1988 13:02:08 Sample Quantity : 607.000 M3
- 27JUL TO 3AUG88
. Sample ID Measurement Type : ROUTINE -
___________..___________________= _________-- =_- _______ =________
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.976E-02 0.OOCE+00 CO-58 810.76 < 1.623E-02 0.OOOE+00 FE-59 1099.22 < 2.856E-02 0.OOOE+00 - CO-60 1332.49 < 2.726E-02 0.OOOE+00 ZN-65 1115.52 < 4.219E-02 0.OOOE+00 N8-95 765.79 < 2.012E-02 0.OOOE+00 ZR-95 756.72 < 2.767E-02 0.OOOE+00 I-131 364.48 < 1.898E-02 0.OOOE+00
'N CS-134 604.70 < 1.399E-02 0.OOOE+00 (d
x CS-137 661.65 < 1.768E-02 0.OOOE+00 BALA-140 537.32 < 5.862E-02 0.OOOE+00 K-40 1460.81 0.489 0.117 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT D/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD _ _ _ _ _ _ _ _ _ _ _______ _ _ _ _ _ = _ - _ _ _ _ _=_ _____________ _me___sp__- _- _ Approved by:_ M _{_ _ _ =______ Date: _!_/_f__/__se__ O l - - - - _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ i
%h ;--C.3-d :--------------------------------- _- _=--------------------- __-_-_--
~
e > " % B'41MW:WA' TW .
/
DUKE POWER COMPANY APPLIED' SCIENCE CENTER RADIDANALYSIS LABORATORY s. je [ ---------------_----------------------_---------------------------------- T L "VAX/VMS.Samp,le Analysis Report generated : 18-AUG-1988 14:31:03' Plant Name : CNS Sample' Number : 1187 Type / Location : AIR RADIOIODINES / 201 Sample Date : 10-AUG-1988-12:25:00 .i Acq.LStart Time : 18-AUG-1988 11:33:43 I Sample Quantity' :: 639.000 M3 Sample ID. : 3AUG-TO 10AUG88 Measurement Type': ROUTINE
' ***** Gamma-Spectroscopy-Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide- Energy . (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 2.430E-03 0.000E+00 CO-58 810.76- < 6.791E-03 0.000E+00 FE 1099.22~.<~2.556E-02 0.000E+00 CO-60= 1332.49' < 3.895E-03 0.000E+00 ZN 1115.52 < 2.867E-02 0.000E+00 NB-95 765.79- < 1.111E-02 0.000E+00 ZR-95 756.72 '< 1.647E-02 'O.000E+00 I-131 , 364.48 < 1.569E-02 0.000E+00 1O . CS-134 604.70 < 7.347E-03 0.000E+00 "CS-137 661.65 < 1.297E-02 0.OOOE+00 BALA-140 537.32 < 3.962E-02 0.000E+00 K-40 1460.81 0.306 6.671E-02 Total Fraction of Reporting Level O.000E+00-Gamma results a're listed as Less Than Levels using . Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. , i 1 Tritium, Alpha and Beta results are the best estimate of the activity ~and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:__ ,__ f l Approvedby:__((((4a(_ ________________ Date: _JL/_fp/_f_8___ l l-- 4 l iE_______________________________~_____________
L:. . n. . DUKE POWER ~COMPA'NY' APPLIED BCIENCE. CENTER-RADIDANALYSIS LABORATORY t : '= v _________________________________________________________________________ 1 YAX/VMS' Sample Analysis Report generated si23-AUG-1988 15:05:06 p Plant Name : CNS-K . Sample Number : 1204 - f Type / Location : AIR RADIOIODINES /.201' Sample.Date : 17-AUG-1988 10:01:00
. Acq. Start Time 23-AUG-1988'14:34:05 Sample Quantity : 591.000 M3 Sample ID : 10AUG TO.17AUG88 Measurement Type ROUTINE p _________________________________________________________________________
' *****-Gamma-Spectroscopy Analysis *****-
1
-Activity 1-Sigma 'MDA> Frac. of Nuclide ' Energy (pCi/M3) Err or reg LLD Rpt. Level MN-54 834.83' < 1.790E-02 0,000E+00 CO-58 810.76. < 1.399E-02 0.000E+00 FE-59 1099.22 .< 4.436E-02 0.000E+00 CO-60 1332.49- < 1.985E-02 0.000E+00 2N-65 1115.52 < 2.647E-02 0.OOOE+00 NB-95 '765.79- < 1.154E-02 0.OOOE+00 ZR-95 -754.72 < 1.427E-02 0.OOOE+00 I-131 364.4G < 1.521E-02 0.000E+00 1 CS-134 -604.70 < 1.208E-02 0.OOOE+00 CS-137 661.65 <-1.288E-02 0.OOOE+00 BALA-140 537.32 < 3.854E-02 0.OOOE+00 Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. . LLD~= 4.66 SQRT B/t. Presence of less than sign for gamma .
results means no. peak was f ound and the zero error is not applicable. - ): Tritium,-Alpha and Beta results are the best estimate of the activity and the less than sign indicates _ that the net activity is less ) than the critical-level, CL. CL = 0.5 LLD Approved'bys__ M f b ____________ Date: __A/_1/_/___E__ 0 .
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY ff(-(/L LVAX/VMS _ Sample Analysis Report generated : 29-AUG-1988 14:45:09 Plant Name : CNS Sample Number 1222
. Type / Location : AIR RADIGIODINES / 201 Sample Date : 24-AUG-1988'09:OO:OO Acq.. Start Time : 29-AUG-1988 12:52:31
. Sample Quantity '
- 567.000 M3 p
Sam' le L ID: -. s 17AUG TO 24AUG88 Measurement Type:: ROUTINE ______________=_ _____________ ______ ___ _____-
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error- reg LLD Rpt. Level MN-54 834.83 < 1.487E-02 0.OOOE+00
. CO-58 810.76 < 1.116E-02 0.OOOE+00 FE-59 1099.22 < 3.793E-02 0.OOOE+00 CO-60 1332.49 < 1.822E-02 0.OOOE+00
'ZN-65 1115.52 < 2.360E-02 0.OOOE+00
-NB-95 765.79 < 1.718E-02 0.OOOE+00 ZR-95 756.72 < 2.402E-02 0.OOOE+00 I-131 364.48 < 1.'448E-02 0.OOOE+00 f CS-134 604.70 < 1.183E-02 0.OOOE+00 CS-137 661.65 < 1.204E-02 0.OOOE+00 I BALA-140 -537.32 < 6.066E-02 0.OOOE+00 K-40 1460.81 0.487 9.730E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. :LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the
. activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
___________________ ________- ____ =- - ---______ -- Analyzed.by:__ # l- __ _u_______
, Approved by:___ M __l;_ _ _________ Date: __1/ _Jir4 / _45____
O _ - - - __ x,. __.._---.__- _ - _ - - - - - -
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
.(-
/~) VAX/VMS Sample' Analysis Report generated 29-AUG-1988 14:45:09 Plant-Name : CNS Sample Number : 1222 Type / Location : AIR RADIOIODINES / 201 Sample Date : 24-AUG-1988 09: 00: 00 Acq. Start Time : 29-AUG-1988 12:52:31 Sample Quantity : 567.000 M3 Sample ID : 17AUG TO 24AUG88 Measurement Type : ROUTINE
_ _ - = - -
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.487E-02 0.OOOE+00 CO-58 810.76 < 1.116E-02 0.OOOE+00 FE-59 1099.22 < 3.793E-02 0.OOOE+00 ; CO-60 1332.49 < 1.822E-02 0.OOOE+00 ZN-65 1115.52 < 2.360E-02 0.OOOE+00 NB-95 '765.79 < 1.718E-02 0.OOOE+00
-ZR-95 756.72 < 2.402E-02 0.OOOE+00 I-131 364.48 < 1.448E-02 0.OOOE+00 t0 CS-134 CS-137 604.70 661.65 1.183E-02 1.204E-02 0.OOOE+00 0.OOOE+00
) BALA-140. 537.32 < 6.066E-02 0.OOOE+00 K-40 1460.81 0.487 9.730E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:__ # __ ___s________ Approved by:___ 3 h__/_._ ________________ Date: _ _ti / _& / _45____ O l ! L__________.__ _ _ _ _ _
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY ,
/~T 1 (m) . _________________________________________________________________________
VAX/VMS Sample Analysis Report generated 2-SEP-19BB 13:29:39 Plant Name : CNS Sample Number i 1238 j Type / Location : AIR RADIDIODINES / 201 Sample Date ]
- 31-AUG-1988 12:46:00 Acq. Start Time :. 2-SEP-1988 12:58:36 Sample Quantity : 598.000 M3 J Sample ID : 24AUG TO 31AUG88 t Measurement Type ROUTINE
______________________ = _ _ _ _ _ _ _ - - -_ =______________________________ {
***** Gamma-Spectroscopy Anal ysi s *****
i Activity 1-Sigma MDA> Frac. of , Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 8.798E-03 0.OOOE+00 CO-58 810.76 < 7.062E-03 0.OOOE+00
'FE-59 1099.22 < 3.426E-02 0.OOOE+00 CO-60, s 1332.49 < 4.153E-03 0.OOOE+00 ZN-65 1115.52 < 2.700E-02 0.OOOE+00 NB-95 765.79 < 1.063E-02 O.OOOE+00 rs 2R-95 756.72 < 1.423E-02 0.OOOE+00
( I-131 364.48 < 1.014E-02 0.OOOE+00 CS-134 604.70 < 9.511E-03 0.OOOE+00 CS-137 661.65 < 9.271E-03 0.OOOE+00 BALA-140 537.32 < 3.013E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD { equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
= __________ ___________________________________ _____ __
_______ sum ___ Approved byr__ W a f_f_ Date: _f_/_f_/_6E___ O
i s DUKE' POWER COMPANY APPLIED SCIENCE CENTER-RADIDANALYSIS LABORATORY
^%- VAX/VMS ' Sample. Analysis Report generated a 9-SEP-1988 14:56 56 Plant Name CNS Sample Number 1258 Type /Locati on : AIR RADIDIODINES / 201 Sample'Date : 7-SEP-1988 09:50:00
- Acq. Start. Time : 9-SEP-1988 14:25:19 Sample Quantity .529.000 M3 Sample ID- : 31AUB TO 75EPB8 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma- MDA> Frac. of Nuclide Energy .( pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 <-1.905E-02 0.OOOE+00 CD-58 810.76- < 6.020E-03 0.OOOE+00 FE-59 1099.22 < 8.390E-03 0.OOOE+00 CD-60 1332.49 <'1.910E-02 0.OOOE+00 7N-65 1115.52 < 4.094E-02 0.OOOE+00
- NB-95 765.79 < 1.tO5E-02 0.OOOE+00
. ZR-95 756.72 < 2.487E-02 0.OOOE+00
/ I-131 364.48 < 9.736E-03 0.OOOE+00 3 )T
% CS-134 604.70- < 1.557E-02 0.OOOE+00 CS-137 661.65 < 1.507E-02 0.OOOE+00
' BALA-140 .537.32 < 5.388E-02. O.OOOE+00 BE-7 477.59 5.810E-02 2.844E-02 K-40 1460.81 0.280 .9.612E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD _____--_---____---_= __ --_____
,----__--__- = --___-----__
L b o Approved bys__QChlf. ll- ____ _______ Date: _f_/_dL / _g&___
. ()
DUKE POWER COMPANY p APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY VAX/VMS Sample Analysis Report generated : 20-SEP-1988 15:25:32 Plant Name : CNS Sample Number : 1275 Type / Location : AIR RADIDIODINES / 201 . Sample Date : 14-SEP-1988 12:00:00 Acq. Start Time : 20-SEP-1988 14:39:52 Sample Quantity '607.000 M3 l Sample ID : 7SEP TO 14SEP88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level
'MN-54 834.83 <-1.340E-02 0.OOOE+00 CO-58 810.76 < 1.220E-02 0.OOOE+00 l FE-59 1291.56 < 1.196E-02 0.OOOE+00 CO-60 1332.49 < 1.321E-02 0.OOOE+00 ZN-65 1115.52- < 3.938E-02 0.OOOE+00 NB-95 765.79 < 1.580E-02 0.OOOE+00
-ZR-95 756.72 < 1.752E-02 0.OOOE+00 i I-131 364.48 < 1.294E-02 0.OOOE+00 CS-134 604.70 < 1.174E-02 0.OOOE+00 CS-137 661.65 < 9.915E-03 0.OOOE+00 BALA-140 537.32 < 5.340E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD l Analyzed by __ _f ____,____ Approved bys__ M b _ __ Date: _f_/_iL*_/_f5___ 1 I O
__________________________________________________________~_____==----___ DUKE POWER COMP NY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY j'~ - ___________ -___ ._________________________________ _______________
\_ VAX/VMS Sample Analysis Report . generated 23-SEP-1988 12:06:26 Plant Name : CNS Sample Number : 1294 Type / Location :. AIR RADIOIODINES / 201 Sample Date ~
- 21-SEP-1988 10:18:00 Acq. Start Time : 23-b7P-1988 11:35:00 Sample Quantity 565.000 M3 Sample ID : 14SEP TO 215EP88 Measurement Type ROUTINE
_ ________- ___________________ ==-- .___
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.434E-02 0.OOOE+00 CO-58 810.76 < 1.183E-02 0.OOOE+00 FE-59 1099.22 < 2.601E-02 0.OOGE+00 CO-60 1332.49' < 1.509E-02 0.OOOE+00 ZN-65 1115.52- < 2.465E-02 0.OOOE+00 NB-95 765.79 < 8.759E-03 0.OOOE+00 ZR-95 756.72 < 1.747E-02' O.OOOE+00
/~ I-131 364.48 < 7.168E-03 0.OOOE+00 T CS-134 604.70 < 1.092E-02 0.OOOE+00 CS-137 661.65 < 1.327E-02 0.OOOE+00 BALA-140 537.32 < 3.752E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD _____=- ___- __ _- __. ._ - _ _ _ _ _ _ _ _ _ - - ______ Analyzed by:__ _ __ __ _ _ _ _ _____ Approved by: j _b ,__________ Date: _g_/_gs_/_jd___
/
O l
-(_)
l _ _ - - _ _ - _ _ - _ _ _ - _ _ _ _ - - i
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY ( A / MS Sample Analysi Report generated 30 SEP-1988 11:38 38 Plant Name : CNS Sample Number 1320 Type / Location : AIR RADIDIODINES / 201 Sample Date : 28-SEP-1988 10:43:00 Acq. Start Time : 30-SEP-1988 11:06:14 Sample Quantity : 601.000 M3 Sample ID : 21SEP TO 28SEP88 Measurement Type : ROUTINE
---_-------------------------_ - - - . . = = _ -- __------------
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level t MN-54 834.83 < 1.291E-02 0.OOOE+00 I CO-58 810.76 < 1.359E-02 0.OOOE+00 FE-59 1099.22 < 1.916E-02 0.OOOE+00 CO-60 1332.49 < 1.570E-02 0.OOOE+00 2N-65 1115.52 < 3.273E-02 0.OOOE+00 NB-95 765.79 < 7.270E-03 0.OOOE+00
- 2R-95 756.72 < 1.795E-02 0.OOOE+00 I-131 364.48 < 7.950E-03 0.OOOE+00
() CS-134 CS-137 604.70 661.65 1.046E-02 1.126E-02 0.OOOE+00 0.OOOE+00 BALA-140 537.32 < 2.728E-02 0.OOOE+00 K-40 1460.81 0.292 7.078E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
== ----------- - - _ - _ - - _
_-------__- =- =------------ i l Analyzed by:_ h_ %) me _ ~- m _ Approved by:_(([)6._f. ____ _____ Date: _22 / .3_ / _29_ 1 l O __._.__________.._.__1_________ ._ _ _ . _
-------- - -. .--- = _-_ -------------_ _-- ._ ___
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY q q, ----- --------------------------------------- --- -------------- VAX/VMS Sample Analysis Report generated 10-OCT-1988 16:29:04 Plant Name CNS
' Sample Number : 1349 Type / Location : AIR RADIDIODINES / 201 Sample Date : 5-OCT-1988 09: 40: 00 Acq. Start Time : 10-DCT-1988 15:57:54 Sample Quantity : 567.000 M3 Sample ID : 28SEP TO 50CT88 Measurement Type : ROUTINE
-***** Gamma-Spectroscopy Analysis ***** I Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level -
MN-54 834.83 < 1.107E-02 0.OOOE+00 CO-58 810.76 < 1.295E-02 0.OOOE+00 FE-59 1099.22 < 2.233E-02 0.OOOE+00 CO-60 1332.49 < 2.069E-02 0.OOOE+00 2N-65' 1115.52 < 3.853E-02 0.OOOE+00 NB-95 765.79 < 1.520E-02 0.OOOE+00 2R-95 756.72 < 2.216E-02 0.OOOE+00 I-131 364.48 < 1.078E-02 0.OOOE+00 f^)- N- CS-134 604.70 < 9.697E-03 0.OOOE+00 ! CS-137 661.65 < 1.240E-02 0.OOOE+00 BALA-140 537.32 < 4.066E-02 0.OOOE+00 K-40 1460.81 0.525 0.101 Total Fraction of Reporting Level O.OOOE+00 i Gamma results are listed as Less Than Levels using Tech Spec LLD j equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. ] Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:_ _ _ __ _ ' I _ _ _ ___ ______ Approved by: _ **Titfef_.__ ______ _ Date: _2p_ / _ j]_ / JL __ O
--------------------- _- -------------------------=_. - - - - - - ---.
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY l t yj =-- __ ==-_ VAX/VMS Sample Analysis Repo.-t generated : 14-DCT-1988 15:45:36 Plant Name : CNS
. Sample Number : 1372 Type / Location : AIR RADIOIODINES / 201 Sample Date : 12-OCT-1988 11:17:00 Acq. Start Time : 14-DCT-1988 14:58:55 Sample Quantity 677.000 M3 Sample ID : 50CT TO 120CT88 Measurement Type : ROUTINE
--- . ---------== ------------- _ ------------- - - - - - - - - - - - - - - - - -
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.8s < 2.682E-03 0.OOOE+00 CO-58 810.76 < 1.174E-02 0.OOCE+00 FE-59 1099.22 < 2.249E-02 0.OOOE+00 CO-60 1332.49 < 1.183E-02 0.OOOE+00 2N-65 1115.52 < 1.959E-02 0.OOOE+00 NB-95 765.79 < 6.970E-03 0.OOOE+00 ZR-95 756.72 < 4.384E-03 0.OOOE+00 () 1-131 CS-134 364.48 604.70 1.088E-02 8.404E-03 0.OOOE+00 0.OOOE+00 CS-137 661.65 < 8.168E-03 0.OOOE+00 BALA-140 537.32 < 3.165E-02 0.000E+00 K-40 1460.81 0.160 7.209E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL, CL = 0.5 LLD Analyzed by: _ _ .
! j _________
_ _ _ _ /_ Approved by:_ M f_._ _ __, ____ Date: _ J e / J _ / _ _3_6_ _ _ I
DUKE POWER COMPANY APPLIED SCIENCE CENTER
'RADIDANALYSIS LABORATORY
,x . - - _ - - - - - - _ - - - - - _ - - - - - - - __--------_----__------_----------- _--------_ ,
f(_)- VAX/VMS Sample Analysis Report generated 24-OCT-1988 13:23:29 Plant Name : CNS
, Sample Number : 1394 Type / Location : AIR RADIDIODINES / 201
. Sample Date : 19-DCT-1988 11:10:00 Acq. Start Time : 24-OCT-1988 12:52:17 Sample Quantity- : 570.000 M3 Sample ID : 120CT TO'190CT88 Measurement Type : ROUTINE
_- -----= ---- _---- - _ _ = . __=--- . ------_---_--_--
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.693E-02 0.OOOE+00 CO-58 810.76 < 1.304E-02 0.OOOE+00 FE-59 1099.22 < 2.190E-02 0.OOOE+00 CO-60 1332.49 < 1.375E-02 0.OOOE+00 ZN-65 1115.52 < 2.318E-02 0.OOOE+00 NB-95 765,79 < 1.413E-02 0.OOOE+00 ZR-95 756.72 < 1.793E-02 0.OOOE+00 I-131 .364.48 < 1.340E-02 0.OOOE+00 O's CS-134' 604.70 < 1.411E-02 0.OOOE+00 CS-137 661.65 < 1.181E-02 0.OOOE+00 BALA-140 537.32 < 4.588E-02 0.OOOE+00 _ - =____ . Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equetion. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the - activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD _____-----__- - - = - - - . - _ .- _--- ----_-_______--___- Analyzed by jhd[ ___ _ I_ . __ Approved by:_ M __ _h_ __ _ _ __ __ 1 _ Date: _Lo_ / _ ag/__p.s___ (:) - - _ - - - - - - . . - _ _ - - - _ - _ - - - _ _ . - _ _ _ - _ _ . R
e, . .
; DUKE POWER COMPANY
' APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
- - - - - - - - - - - _ _ - = - - - - - - = - - - - _ - - - - -
= = _ - - - - - - _ - -
=-------------------
-VAX/VMC ; Sample ~ Anal ysi s_ Report . generated : 28-OCT-1988 12:03:44 Plant Name : CNS !
Sample Number- :-1411 Type / Location ' :" AIR RADIDIODINES / 201-Sample Date- : 26-OCT-1988 09:45:00 Acq. Start Timef : 28-OCT-1988 11:32:25 566.000 M3
~
. Sample Quantity' :
Sample ID. 190CT TOL260CT88-Measurement Type : ROUTINE
------------------------------ .-==_ =- ---------------------------- .
***** Gamma-Spectroscopy Anal ysi s *****
Activity. 1-Sigma MDA>- Frat. of _Nuclide Energy (pCi/M3) Error req LLD Rpt.- Level MN-54. 834.83 <- 1.027E-02 0.OOOE+00 CO-58 810.76 < 1.552E-02 0.COOE+00~ FE-59 1099.22 < 2.071E 0.OOOE+00 CO-60' 1332.49. < 1.700E-02 0.OOOE+00
- ZN-65 1115.52 '< 4.282E-02 0.OOOE+00 NS-95 765.79 <-1.204E-02' O.OOOE+00 ZR-95. 756.72 <t 1.877E-02 0.OOOE+00 j() - I-131 364.48 < '1.046E-02 0.COOE+00
'CS-134' 604.70 < 1.266E-02 0.OOCE+00 CS-137 661.65 < 1.396E-02 0.OOOE+00 BALA-140 537.32 < 3.084E-02 0.OOOE+00 K-40 1460.81 0.318 9.257E-02
------. =
Total Fraction of Reporting Level O.OOOE+00: .j Gamma results are listed . as Less Than Levels using Tech Spec LLD equation. .LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no- peak was found and the zero error is' not applicable. Tri tium , Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:__ y _______ __ ___4.___________ Approved by:_ M ft _b______- _ ______ ___ Date: _Lo_/_jj/_,W___
- ------__-.a--__-_.---.--.-.---.:---,------~--.--_-----._--- --,.,L,--- -.-- - - , - - - .- - - - .
1 _ _ _ _ _ _ = - --_________________________________________ _________________ DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
~) _ _ _ _ _ _ _ _ _ _ _ _ _ - _________________ _ _____________________________ i
(\ / ~ VAX/VMS Sample' Analysis ~ Report generated : 7-NOV-1988 13:46:03-Plant Name : CNS. 4 Sample Number. : 1444 l Type / Location _ : AIR RADIOIODINES / 201 Sample Date : 2-NOV-1988 10:30:00 Acq. Start' Time : 7-NOV-1988 13:14:37 - Sample Quantity _ 606.000 M3 Sample ID : 260CT TO 2NOV88 Measurement Type : ROUTINE _= - _ _ _ _ _ _ _ _ _ _ _ _ = - _ _ ----_____- ____- .____________________ i I
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of. Nuclide Energy . (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.433E-02 0.OOOE+00 CO-58 810.76 < 1.070E-02 0.OOOE+00 F.E-59 1099.22 < 2.028E-02' O.OOOE+00 CO-60 1332.49- < 1.589E-02 0.OOOE+00 2N-65 1115.52 < 3.818E-02 0.OOOE+00 NB-95 765.79 < 8.424E-03 0.OOOE+00 2R-95 756.72 < 1.812E-02 0.OOOE+00 I-131 364.48 < 1.381E-02 0.COOE+00 CS-134 s 604.70 < 9.876E-03 0.OOOE+00 CS-137 661.65 < 7.319E-03 0.COOE+00 BALA-140 537.32 < 4.146E-02 0.OOOE+00 K-40 1460.81 0.262 8.544E-02 Total Fraction of Reporting Level O. OOOE* 00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign f or gamma results means no~ peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD __________=- --= _________-_ a
. y L Analyzed by: __ ___ __#__ ___ _ _ _ _
Approved by: W _[. ... _____ __ _ _ _ _ __ Date: _j/_ / _ A_ / _se.___ O
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY
)
A /VMS Sample Analysis Report generated 11NOV-1b815:0755 Plant Name n'CNS Sample Number : 1460 Type / Location : AIR RADIDIODINES / 201 Sample Date : 9-NOV-1988 11:35:00 Acq. Start Time : 11-NOV-1988 14:36:45 Sample. Quantity : 632.000 M3 Sample ID : 2NOV TO 9NOV88 Measurement Type : ROUTINE ____________ ______ _ _ _ _ _ _ _ _ _ _ _ _ - - . --=-
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MdA> Frac. of. Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 9.118E-03
. 0.OOOE+00
. CO-58 810.76 <'5.574E-03 0.000E+00 FE-59 1099.22 < 2.600E-02 0.OOOE+00 CD-60 1332.49 < 1.040E-02 0.OOOE+00 2N-65 1115.52 < 6.361E-03 0.OOOE+00 NB-95 '765.79 < 1.094E-02 0.OOOE+00
'ZR-95 756.72 < 2.084E-02 0.OOCE+00 I-131 364.48 < 8.192E-03 0.OOOE+00
() CS-134 CS-137 604.70 661.65
< 9.194E-03
< 8.309E-03 0.OOOE+00 0.OOOE+00 BALA-140 537.32 < 2.378E-02 0.OOOE+00 K-40 1460.81 0.188. 5.224E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using. Tech Spec LLD l' equation.- LLD = 4.66 SORT B/t. Presence of less than nign for ga.mma results means no peak was f ound and the zero error is not applicable.
Tritium, 61pha and Leta results are the best estimate of the I activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:_ I Approvedby:_$2$def._ ________ _ ___ Date: _2L/_2 /_fe l l O l 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ . . . ]
--. __ ------------------- _ --------------= ----------------------_
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY Y' VAX/VMS Sample Analysis Report generated :.21-NOV-1988 13:47:42 Plant Name : CNS Sample Number 1486 Type / Location : AIR RADIOIODINES / 201 Sample Date : 16-NOV-1988 10:05:00 Acq. Start Time : 21-NOV-1988 13:16:13 Sample Quantity : 608.000 M3 Sample ID : 9NOV TO 16NOV88 - Measurement Type : ROUTINE ,
-----=_ .---== - _
=----=_ ----------
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.360E-02 0.OOOE+00 CD-58 810.76 < 1.498E-02 0.OOOE+00 FE-59 1099.22 < 3.474E-02 0.OOOE+00 CO-60 1332.49 < 1.627E-02 0.OOOE+00 ZN-65 1115.52 < 2.174E-02 0.OOOE+00 NB-95 765.79 < 8.320E-03 0.OOOE+00 ZR-95 756.72 < 9.583E-03 0.OOOE+00 I-131 364.48 < 8.255E-03 0.OOOE+00 (~)';
- k. CS-134 604.70 < 7.610E-03 0.OOOE+00 CS-137 661.65 < 1.399E-02 0.OOOE+00 BALA-140 537.32 < 4.612E-02 0.OOOE+00 K-40 1460.81 0.322 7.597E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Then Levels using Tech Spec LLD l equation. LLD = 4,66 SQRT B/t. Presence of ichs than. sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the acti vity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
---- - - - = - _ _ - _
Analyzed by:M on h _::_______ Approved by:__ $ _h _________________ Dcte: __1L / _ n /_es ___ c ( l l
DUKE ~ POWER COMPANY -
-APPLIED SCIENCE CENTER o
RADIDANALYSIS LABORATORY f
)< ~ ------------------------------------------------------------------------ 1
[(_)(7 VAX/VMSl Sample Analysis Report' generated : 28-NOV-1988f 14:18:24 I Plant'Name' : CNS Sample Number : 1496 Type / Location : AIR RADIOIODINES / 201 Sample Date : 23-NOV-1988 10:25:00 Acq. Start Time : 28-NOV-1988 13:33:07 Sample Quantity a 586.000 M3 Sample ID : 16NOV TO 23NOV88 Measurement Type : ROUTINE
-------= ---------------------- . ==. -------------- - _ _ -
***** Gamma-Spectroscopy Anal ysi s ***** .
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.088E-02 0.OOOE+00 CO-58 810.76 < 1.544E-02 0.OOOE+00 FE-59 1099.22 < 2.097E-02 0.OOOE+00 CO-60 1332.49 < 9.650E-03 0.OOOE+00 ZN-65 1115.52 < 2.501E-02 0.OOOE+00 NB-95 765.79 < 1.100E-02 0.OOOE+00 ZR-95 756.72 < 2.229E-02 0.OOOE+00 f-s 1-131 364.48 < 1.519E-02 0.OOOE+00 1 CS-134 604.70 < 7.851E-03 0.COOE+00 CS-137 661.65 < 1.267E-02 0.OOOE+00 BALA-140 537.32 < 5.560E-02 0.OOOE+00
.K-40 1460.81 0.235 6.505E-02 Total Fraction of Reporting Level O.OOOE+00 ,
Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT 5/t. Presence of legs than sign for gamma results means ne peak was found and the zero error is not applicable.- f i Tritium, Alpha and Eeta results are the best estimate of the I activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
- = . -------------------------.--------- -- -
-- -- - gun e sama--em - - h -- gue - .en Approved by:_ h h b m_ __ _ ____
Date: _g / _2_ / ff____ O l l
E- ______________________________________ __________ _________ _____ l L DUKE POWER COMPANY l APPLIED SCIENCE CENTER 1 RADIDANALYSIS LABORATORY amj ' _ _ _ _ _ _ - . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ __ - _____ . _ _ _ _ _ _ _ . _ _ _ _ _ _ . ___ VAX/VMS Sample Analysis Report generated : 5-DEC-1988 13:28:34 ) ,o Plant Name : CNS Sample Number : 1533 Type / Location : AIR RADIOIODINES / 201 Sample Date : 30-NOV-1988 09:20:00 Acq. Start Time : 5-DEC-1988 11:14:06 Sample Guantity : 596.000 M3 Sample ID : 23NOV TO 3ONOV88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.180E-02 0.OOOE+00 CO-58 810.76 < 6.679E-03 0.OOOE+00 FE-59 1099.22 < 7.700E-03 0.OOOE+00 CO-60 1332.49 < 1.315E-02 0.OOOE+00 ZN-65 1115.52 < 2.803E-02 0.OOOE+00 NB-95 765.79 < 1.316E-02 0.OOOE+00 ' ZR-95 756.72 < 1.352E-02 0.OOOE+00 e's I-131 364.48 < 1.155E-02 0.OOOE+00 (_) CS-134 604.70 < 1.048E-02 0.OOOE+00 CS-137 661.65 < 7.425E-03 0.OOOE+00 BALA-140 537.32 < 3.497E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta resuits are the best estimate of the ectivity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:_ _b' m w__________ Approved by:_ M _f_._ _1 ________ Date: _18_/_,p_/_ff___ s
DUKE POWER COMPANY APPLIED SCIENCE' CENTER RADIDANALYSIS LABORATORY f({)L____________________________________________________________ VAX/VMS Sample Analysis Report generated : 15-DEC-1988 14:14:04 Plant Name : CNS Sample Number :.1620 Type / Location : AIR RADIDIODINES / 201 Sample Date : 7-DEC-1988 10:12:00 Acq. Start Time : 13-DEC-1988 11:53:31 Sample Quantity : 603.000 M3 Sample ID : 30NOV TO 7DEC88 Measurement' Type : ROUTINE
*****. Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA>. Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level
. NN-54 834.83 < 1.132E-02 0.000E+00 CO-58 810.76 < 2.603E-03 0.000E+00 FE-59 1099.22 < 2.566E-02 0.000E+00 CD-60 1332.49 < 1.377E-02 0.000E+00 ZN-65 1115.52 < 1.780E-02 0.000E+00 NB-95' 765.79 < 1.240E-02 0.000E+00 ZR-95 756.72 < 1.498E-02 0.000E+00 I-131- .(,)~CS-134 364.48 < 1.229E-02' O.000E+00 604.70 < 8.925E-03 0.000E+00 CS-137 661.65 < 8.454E-03 0.000E+00 BALA-140 1596.49 < 2.389E-02 0.000E+00 K-40 1460.81 0.273 6.440E-02 Total Fraction of Reporting Level 0.000E+00 Gamma r esults are listad as Less Than Levels using Tech Spec LLD equa ti on . 1.LD = 4. ti6 SQRT Bit. Pr esence of lees than sign f or gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by __ r _______ ____ Approved by:_ 3 f _ 3_______ _______ Date: _er_/ _ 1_/_ E 6___ O , - __ - - 1
DUKE POWER COMPANY. APPLIED SCIENCE CENTER E RADIDANALYSIS LABORATORY
), VAX/VMS Samole Analys s Repo t generated 20-DEC-1988 13 24 57 Plant Name :-CNS Sample Number : 1641-Type / Location : AIR RADIOIODINES / 201.
Sample Date : 14-DEC-1988 12:00:00 Aca. Start Time : 20-DEC-1988 12:53:37 Sample Quantity .: 620.000 M3 Sample ID : 7DEC TO 14DEC88 Measurement Type : ROUTINE.
---. - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - . __-------------- = = -------
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> . Frac. of Nuclide Energy (DCi/M3) Error reg LLD Rot. Level MN-54 834.83 < 6.742E-03 0.OOOE+00
.- CO-58 '810.76 < 9.552E-03 0.OOOE+00 FE-59' 1099.22 < 2.444E-02 0.OOOE+00 CO-60 1332.49 < 1.682E-02 0.OOOE+00 2N-65 1115.52 < 6.557E-03 0.OOOE+00 NB-95 765.79 < 1.177E-02 0.OOOE+00 ZR-95 756.72 < 1.696E-02 0.OOOE+00 I-131 364.48 < 9.759E-03. O.OOOE+00
- () CS-134 CS-137 604.70 661.65 9.406E-03 1.098E-02 0.OOOE+00 0.OOOE+00 BALA-140 1596.49 < 6.756E-03 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD eauation. LLD.= 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tritium; Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
------------------------__ = -=-----------------------------. -- .
esa - -emup- - - - -emb Approved by: M[ _______________ Date: _1._ / _.e/_ / _ _ef_ _ _
.O
________--__-____________________a-_____________________________________. }. - DUKE' POWER COMPANY-
-APPLIED SCIENCE ~ CENTER RADI0 ANALYSIS LABORATORY fem { } .
(_) . ___________. VAX/VMS Sample Analysis' Report generated :;28-DEC-1988 10:56:23 a PlantiName ~: CNS
-Sample Number :.1693
' Type / Location : AIR RADIDIODINES / 201
. Sample'Date : 21-DEC-1988 10:21:00 Acq. Start Time. : 28-DEC-1988 10:02:17 Sample Quantity : 622.000 M3 LSample-ID : 14DEC TO 21DEC88 Measurement Type : ROUTINE L 1
~
AAAAA Gamma-Spectroscopy Analysis AAAAA Activity 1-Sigma MDA> ' Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level HN-54 834.83 < 8.680E-03 0.000E+00 CO-58 810.76 < 1.488E-02 0.000E+00 EE-59 1099.22' < 3.375E-02 0.000E+00 CO-60 1332.49 < 4.637E-03 0.000E+00 ZN-65 1115.52 < 2.136E-02 0.000E+00 NB-95' 765.79' < 1.348E-02 0.000E+00 f-c ZR-95 756.72 < 1.960E-02 0.000E+00 ; I-131 364.48 < 1.627E-02 0.000E+00 CS-134 604.70- < 8.760E-03 0.000E+00 CS-137 661.65. < 1.233E-02 0.000E+00 BALA-140 -1596.49 < 2.288E-02 0.000E+00 K-40 1460.81 0.200 8.404E-02 *
'i Total Eraction of. Reporting Level 0.000E+00.
I Gamma results are listed as Less Than Levels using Tech Spec LLD l equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma j results means no peak was found and the zero error is not applicable. l Tritium, Alpha and Beta results are tha best estimate of its activity and the less than sign indicates that the net activity is less. than the critical level, CL. CL = 0.5 LLD Analyzed by:_ _ I ,____________ Approved by: u _________ Date: _1_ / _ h / _d3_ _ _ O
______ - ______ =_____________- ________.._--- - - -
-_ =- __=_
E DUKE POWER COMPANY APPLIED SCIENCE CENTER [ RADIDANALYSIS LABORATORY . _________________ = _ _ _ _ _ _ _ - =_ _ ___________-- VAX/VMS Sample Analysis Report generated : 5-JAN-1989 15:59:19 Plant Name : CNS Sample Number : 1729 Type / Location : AIR RADIDIODINES / 201 Sample Date : 28-DEC-1988 10:00:00 Acq. Start Time : 5-JAN-1989 15:14:11 Sample Quantity 598.000 M3 Gample ID : 21DEC TO 28DEC88 Measurement Type : ROUTINE
=_______- =______
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < B.800E-03 0.OOOE+00 CO-58 810.76 < 1.131E-02 0.OOOE+00 I FE-59 1099.22 < 2.609E-02 0.OOOE+00 CO-60 1332.49 < 1.309E-02 0.OOOE+00 ZN-65 1115.52 < 3.045E-02 0.OOOE+00 f^y NB-95 765.79 < 1.338E-02 0.OOOE+00 (_) ZR-95 756.72 < 2.291E-02 0.OOOE+00 I-131 364.48 < 1.694E-02 0.OOOE+00 CS-134 604.70 < 8.085E-03 0.OOOE+00 CS-137 661.65 < 7.443E-03 0.OOOE+00 BALA-140 1596.49 < 2.857E-02 0.OOOE+00 Total Fraction of Reoorting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD aquation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritu,m, Alpha and Eata results are the best estinate of the j activity and the less than sign indicates that the net activity is less ' than the critical level, CL. CL = 0.5 LLD I = = :- _-_ ___ ___________. __. _______--_______ Analyzed by:___ _1 _ _ _ _ _ _ Approved by:__ h3 sq __ _______ Date: __L / _6_ / 3_9.___ rh 1 ()_ j 1
)
,------------------------------- - - - - = = _ - - - - -
DUKE POWER COMPANY r4 APPLIED SCIENCE CENTER
'(). , s RADIDANALYSIS LABORATORY -
VAX/VMS Sample Analysis Report generated : 7-JAN-1989 15:12:27 Plant Name : CNS Sample Number : 1745 Type / Location : AIR RADIOIODINES / 201 Sample Date : 4-JAN-1989.11:08:OO Acq. . Start' Time : 7-JAN-1989 14:41:25 Sample Quantity : 630.000 M3 Sample ID : 28DEC TO 4JAN89 Measurement. Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level' MN-54 834.83 < 9.219E-03 0.OOOE+00 CO-58 810.76 < 1.362E-02 0.OOOE+00 FE-59 1099.22' < 2.856E-02 0.OOOE+00
'CO-60 1332.49 < 4.571E-03 0.OOOE+00 ZN-65 1115.52 < 2.618E-02 0.OOOE+00
() NB-95 ZR-95 765.79 < 2.838E-03 756.72 < 1.689E-02 0.OOOE+00 0.OOOE+00 I-131 364.48 < 1.010E-02 0.OOOE+00 CS-134 604.70 < 1.143E-02 0.OOOE+00 CS-137 661.65 < 6.912E-03 0.OOOE+00 BALA-140 1596.49 < 2.257E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Preser ce of less than sign f or gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta r esul ts are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by: %u ___ Approved by:_ A__fi_ < ____________ Date: _,f_/__f_/_f[___ O i.
f' _________________= ==______ _- DUKE POWER COMPANY
', APPLIED SCIENCE CENTER
( ,I RADIDANALYSIS LABORATORY VAX/VMS Sample Analysis Report generated : 14-JUN-1988 14:35:51 Plant Name : CNS Sample Number : 410 Type / Location : AIR RADIGIODINES / 205 Sample Date : 6-JAN-1988 11:25:00 Acq. Start Time : 11-JAN-1988 13:04:16 Sample Quantity : 572.000 M3 Sample ID : 30DEC TO 6JANB8 Measurement Type : ROUTINE _ _ _ - _ = - =____________________________________ _________________________ j
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.954E-02 0.OOOE+00 CO-58 810.76 < 1.479E-02 0.OOOE+00 FE-59 1099.22 < 2.17BE O.OOOE+00 CO-60 1332.47 < 2.682E-02 0.OOOE+00
,_s ZN-65 1115.52 < 3.689E-02 0.OOOE+00 -
! NB-95 765.78 < 1.621E-02 0.OOOE+00
'-') 2R-95 756.72 < 2.913E-02 0.OOOE+00 I-131 364.48 < 1.604E-02 0.OOOE+00 CS-134 604.66 < 1.088E-02 0.OOGE+00 CS-137 661.65 < 1.490E-02 0.OOOE+00 BALA-140 1596.49 < 7.992E-03 0.OOOE+00 K-40 1460.75 0.424 8.836E-02 Total Fraction of Reporting Level O.000E+00 Gamma results are lished as Less Than Levels using Tech Spec LLD equetion. LLD = 4.66 SORT 5/t. Precence of less than sign for gamma results means no peak was f ound and the zero errer is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is lessj then the critical 19 vel, CL. CL = 0.5 LLD Analyzedby:___?(di______________________ Approved by:__ M _b_ h _________________ Date: __4_/_o-/ n____ r' 1
\_
n , , . a g' r s '.. c, Ca * '
>________________________________==-
, l
_=_____________________-- ___q VAX/VMS Sample Analysis Report generated:': 22-JAN-1988 i3:32i14'
~
- j
,) 'PlantiName; :: CNSJ Sample; Number' L: 439 ,
, fType/ Location AIR RADIDIODINES /c205. l]
SampleLDate1 : 13-JAN-1988 11:15:00 ) Acq..:StartoTime : 18-JAN-1988 14:13:16' - { Sample l Quantity : 599.OOO'M3 ' Sample-IDL 6JAN TO 13JAN88. j j Measurement Type :: ROUTINE _______=- _____________- = = = _ _ _ - ==_________________________________
.)
- n ***** . Gamma-Spectroscopy Analysis"*****
.s " ~
- i Activity 1-Sigma MDA> Frac. of-Nuclide- Energy (pCi/M3L , ' Error req!LLD Rpt. Level MN-54' 834.83- < 1.318E-02 -0.OOOE+00-
; cop 58 '810.76. < i.413E-02 0.OOOE+00
. FE 1099.22 <.3.730E-02 0.OOOE+00
'CO-60. - 1332.47 < 1.596E-02 0.OOOE+00
'ZN-65 1115.52 ~< 3.137E-02 0.OOOE+00 NB-95 , 765.78 <.1.923E . .O.OOOE+00 2R-95: =756.72: < 2.802E-02. 0;OOOE+00-I-131t 364.48 < 1.896E-02 .O.OOOE+00
, CS-134 604~.66 .< 1.119E-02 0.OOCE+00 CS-137 661.65<-1.534E-02 0.OOOE+00 BALA-140 1596.49 < 2.OS2E-02 0 OOOE+00
;(])i
'E Total' Fraction of, Reporting Level O.OOOE+00 I
G _ Anal'yzed by:_______ .1 _____;______ _u Approved by:_.,, M __(_ ;___;________ Date: __x,/_;5/_ A __ . t
= _ _ _ _ _ _ _ _ _ _ - - _ = _ _ _ _ _ - _ _ _ _ . -- -
-_-_____--____-_____---_--____-_-= _____________-______---_-_-__________
VAX/VMS Sample Analysis Report generated 25-JAN-1988 13:34:55 m 4 Plant Name : CNS Sample Number 452 Type / Location : AIR RADIDIODINES / 205 Sample Date : 20-JAN-1988 10:45:00 Acq. Start Time : 25-JAN-1988 13:03:17 Sample Quantity : 583.000 M3 Sample ID : 13JAN TO 2OJAN88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level . MN-54 834.83 < 1.188E-02 0.OOGE+00 CO-58 810.76 < 9.297E-03 0.000E+00 FE-59 1099.22 < 2.280E-02 0.OOOE+00 CO-60 1332.47 < 1.888E-02 0.000E+00 ZN-65 1115.52 < 2.553E-02 0.OOGE+00 NB-95 765.78 < 1.445E-02 0.000E+00 2R-95 756.72 < 7.606E-03 0.000E+00 1-131 364.48 < 1.452E-02 0.000E+00 CS-134 604.66 < 9.151E-03 0.OOGE+00 CS-137 661.65 < 1.139E-02 0.000E+00 r~s BALA-140 1596.49 < 1.864E-02 0.OOOE+00
$ j K-40 1460.75 0.271 6.577E-02 Total Fraction of Reporting Level 0.000E+00 4
Anal yzed by: _s _ ___ ____ Approved by _____ p , fa_ 2____________ Date: _2 _/ g( / _ _en __ l i
)
i 7,
. _ , l
)
i 9'E ' DUKE POWER COMPANY- ) APPLIED SCIENCE CENTER j RADIOANALYSIS LABORATORY l li
,l
.-($)-'*VAX/VMSSamplecAnr.lysisReportgenerateda 23-NOV-1988 15:44:32 l q
l
- Plant'Name. : CNS Sample Numbert : 485 -
f Type / Location' ~ s AIR RADIOIODINES / 205
, Sample Date 2.27-JAN-1988 12:10:00
;Acq. Start Time : 2-FEB-1988 14:56:57-Sample Quantity. :- 611.000-M3
. Sample.ID .
2OJAN TO 27JAN88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Anal ysi s - *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level-MN-54 834.83 < 1.146E-02 0.OOOE+00 CO-58 810.76 < 1.152E-02 0.OOOE+00 FE-59, 1099.22 < 2.670E-02 0.OOOE+00 CO-60. -1332.47 <-1.123E-0.2 0.OOOE+00 ZN-65 1115.52 <.2.306E-02 0.OOOE+00 NB-95 765.78 < 1.120E-02 0.OOOE+00
- ZR-95' 756.72 < 2.386E-02 0.OOOE+00
/~T I-131 364.48 < 1.021E-02 0.COOE+00
-( / CS-134 604.66 .< 7.314E-03. O.OOOE+00-CS-137 661.65 < 1.-333E-02 0.OOOE+00 BALA-140 1596.49 < 3.031E-02 0.OOOE+00 K-40 1460.75 0.244 6.091E-02 Total Fraction of Reporting Level .O.OOCE+00 s Gamma resultu are listed as Less Than Levels using Tech Spec LLD.
equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not ' applicable. F Tritiem, Alpha and Beta results are the best estimate of the activity than the.and the less critical than level, CL. signCLindicates
= 0.5 LLD that the net activity i s l ess j!
l\ . )N Analyzed by: q iy t__ tw_ - . _ - _ _ - Approved by ___ J ________________ Date: _p_/ftf_/,ht __ l 1
I 1(
- VAX/VMS' Samplo Analynf o Rsport gsnzrated a 5-FEB-1988 13:22:25
- Plant-Name s'CNS
- j. , Sample Number 499 Type / Location -: AIR RADIDIODINES / 205
,f
}. - Sample Date . : 3-FEB-2988 10:20:00 Acq. Start Time : 5-FEB-1988 12:51:14 Sample Quantity : 480.000 M3 Sample ID : 27JAN TO 3FEB88-Measurement Type : ROUTINE
***** Gainma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy . (pCi/M3) Error reg LLD-Rpt. Level
' MN-54 834.83 < 1.587E-02 0.OOOE+00 CO-58 810.76 <~1.421E-02 0.OOOE+00
~ FE-59 1099.22 <-3.025E-02 0.OOOE+00 CO-60 1332.47 < 1.991E-02 0.OOOE+00 ZN 1115.52 < 3.228E-02 0.OOOE+00 NB 765.78 < 1.172E-02 0.OOOE+00 2R-95 756.72 < 2.052E 0.OOOE+00 1-131 364.48 < 1.218E-02 0.OOGE+00 CS-134- 604.66 < 1.331E-02 0.OOOE+00
. CS-137 661.65 < 1.451E-02 0.OOOE+00 BALA-140 1596.49 < 2.741E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 0
Analyzed by:.. __ In h - Approved by:___ M _[_ _/ _________ Date: _,l_/_f_/_ff___ I l l' O V L E__ ___
VAX/VMS Sample Analysis Report generated : 16-FEB-1988 10:03:10
; ~,}
Q E Plant Name : CNS Sample Number : 519 Type / Location : AIR RADIOIODINES / 205 Sample Date : 10-FEB-1988 13:02:00 Acq. Start Time : 16-FEB-1988 09:32:05 Sample Quantity : 653.000 M3 Sample ID : 3FEB TO 10FEB88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis +++**
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.600E-02 O.OOOE+00 CO-58 810.76 < 1.270E-02 0.OOOE+00 FE-59 1099.22 < 2.753E-02 0.OOOE+00 CO-60 1332.47 < 1.698E-02 O.OOGE+00 ZN-65 1115.52 < 4.036E-02 0.OOOE+00 NB-95 765.78 < 1.671E-02 0.OOGE+00 ZR-95 756.72 < 2.082E-02 0.OOOE+00 I-13'1 364.48 < 1.555E-02 0.COOE+00 CS-134 604.66 < 7.466E-03 0.OOGE+00 CS-137 661.65 < 1.454E-02 0.OOGE+00 (7 )
.x BALA-140 1596.49 < 1.709E-02 O.OOOE+00 K-40 1460.75 0.404 8.072E-02 Total Fraction of Reporting Level O.OOOE+00
( An al yz ed by:_________ . a Approved by:__ M 1 ._ _._- ________ Date: __A/ _.!!/ _f_E__ (em) l { l l L -_-- _ _
i
' .i.
<________________________ _- _=_______________________________________
VAX/VMS Sample Analysis . Report generated 22-FEB-1988 16:08:09 f{ 1/ ~ P1 ant.Name' CNS
-Sample Number : 536 Type / Location : AIR RADIOIODINES / 205 q Sample'Date . : 17-FEB-1988 11:01:00 Acq.7 Start Time . : 22-FEB-1988'15:36:55 {
q
' Sample Quantity : 564.000 M3 s i- Sample ID. : 10FEB:TO 17FEB88 l F Measurement Type : ROUTINE
____=-_ _ _ _ _ . -- _ __ = ___=__ __- ______________
***** Gamma-Spectroscopy Analysis.*****
G Activity 1-Sigma MDA> Fr ac'. of Nuclide Energy. (pCi/M3) Error req LLD-Rpt. Level MN-54 '834.83- < 1.735E-02 0.OOOE+00 CO-58 810.76 < : 1. 252E-02 0.OOOE+00 FE-59 1099.22 < 8.OO8E-03 0.OOOE+00 CO-60 -1332.47 < 1.387E-02 0.OOOE+00 ZN-65 1115.52 -< 2.987E 0.OOOE+00 NB 765.78 < 1.583E-02 0.OOOE+00
'ZR 756.72 < 2.580E-02 0.OOOE+00 I-131 364.48 < 1.795E-02 0.OOOE+00
- CS-134 604.66 < 9.619E-03' O.OOOE+00
'CS-137 661.65 < 1.673E-02 0.OOOE+00 W ' BALA-140 1596.49 < 2.830E-02 O.OOOE+00
& Total Fraction of Reporting Level O.OOOE+00
=
-Analyzed..by:__ag n g #y, h _ _ _ _ _ _____________ ,
AP proved by:__ M _i_ h __ _________ Date: __t./_g/__86___ i O.
----------- _ --------= -- -
V~ VAX/VMS ' Sample Ana1Vei s . Report ganurstad : 29-FEB-1988.14:24s10 1' E Plant Name. : CNS i . Sample Number a 5731
- - /]- Type / Location _ -:-AIR RADIDIODINES'/ 205
(> Sample-Date, : 24-FEB-1988 10: 20: 00 r ' Acq. Start. Time- : 29-FEB-1988 13:53:06 Sample Quantity- : '483.000 M3-Sample.ID- : 17FEB TO'24FEB88 L Measurement Type : ROUTINE l
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 2.259E 0.OOOE+00 CO-58 810.76 < 2.OO3E-02 0.OOOE+00 FE-59 1099.22 < 3.294E-02 0.OOOE+00.
'CO-60 1332.47 < 2.080E-02 -0.OOOE+00 ZN-65 1115.52 < 4.500E-02 0.OOOE+00 NB-95 765.78 < 1.337E-02 0.OOCE+00 ZR-95 756.72 < 3.64BE-02 0.OOOE+00
.I-131 364.48 < 2.204E-02' O.OOOE+00 CS-134 604.66 < 1.144E-02 .O.OOOE+00 CS-137 661.65 < 2.226E-02 0.OOOE+00 BALA-140 1596.49 < 3.616E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 LO.
s Anal yz ed by: ___ _ __ __ _ _ _ _ _ _ ._ Approved by: ._ < M _(t_ d___________ Date:' _J./_1._/ 88___ i f f O
y; , . _________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ ____:
; ; VAX/VMS.. Simple Analysis ;Rsport ganaratdd : E 10-MAR-1988 -10: 00: 41
~
, Plant Name- 12CNS
-> ' i , Sampie Number- : .598
. Type / Location ~ :.' AIR RADIOIODINES / 205' i (/' 7 /.
- Sample Date?
^
2-MAR'-1988 10:50:00
' Acq. Start Time 'n':10-MAR-1988 09:29:32 Sample. Quantity 630.000 M3-Sample 11D; . .
24FEB TO: 2 MAR 88 -
~ Measurement: Type.: ROUTINE
( n
***** Gamma-Spectroscopy Analysis 1*****
Activity 1-Sigma. MDA> Frac. of Nuclide_ Energy . (pCi/M3) Error req LLD Rpt. Level
, MN-54 834.83 < 7.818E-03' O.OOOE+00 CO-58 810.76 < 1.793E-02 0.OOOE+00 FE-59 1099.22 < 2.036E-02 0.OOOE+00 .-
CD-60 1332.47 < .1.619E-02 0.OOOE+00 ZN-65 -1115.52 < 3.391E-02 0.OOOE+00 NB-95' 765.78 < 1.777E-02 0.OOOE+00 ZR-95: 756.72~ < 2.110E-02 0 OCOE+00 I-131 364.48 <'1.790E-02 'O.OOOE+00 CS-134 604.66 < 9.212E-03 0.OOOE+00 -- CS-137 661.65 < l'.080E-02' O.OOOE+00 BALA-140 1596.49 <12.920E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00. { N An al yz ed by: _____ _ __ _ _ _ . Approved by: _ M 8._ _ - __ __ _ _ _ _ _ _ _ Date: _ d,/_Z/_/_ & __ L k O 9
}' , .____
____-_-________---______:-_____---_______-_________________________j <l' < VAX/VMS Semplo Analycio Raport gansratsd's-15-MAR-1988 12:14:50 j g# A - Plant Name : CNS Sample Number a 615
.j f Type / Location- :- AIR RADIOIODINES '/ .205 ;;
.L' -@ Sample Date s.,9-MAR-1988'12:55:00
' Acqn Start Time 3.15-MAR-1988 11:43:48 Sample Quantity- :- 650.000 M3-Sample ID. 2 MAR TO 9MAROB. -
s
- a. Measurement Type : ROUTINE
---_-__-__--____ -_-_--___. _ _ = = - - . =_____ _______---______________
s
***** Gamma-Spectroscopy. Analysis *****
Activity' 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.091E-02 0.OOOE+00 CO-58 810.76 <'1.220E-02 - 0.OOOE+00' ,
' FE-59 1099.22 -< 2.873E-02 0.OOOE+00 CO-60 1332.47 '< 1.972E-02 0.OOOE+00 2N-65: .1115.52 < 3.OO4E-02 0.OOOE+00 NB-95 765.78 .< 1.271E-02 0.OOOE+00 ZR-95 756.72~ < 2.569E-02 0.OOOE+00 I-131 364.48 < 1.671E-02 0.OOOE+00 .
CS-134 604.66' < 8.827E-03 'O.OOOE+00 CS-137 661.65 <'1.295E-02 0.OOOE+00 BALA-140 1596.49- <-2.755E-02 0.OOOE+00 Total Fraction'of Reporting Level O.COOE+00-
' Analyzed by:__ _ 4 _________
Approved by:__ M _ft ________ . Date: J / /f_/ BS
- p. .
l' , m e lO'
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ = = - - - - - - - - - - - - - = . _ - - -
_VAX/VMS1 Sample Analysis Report generated.: 22-MAR-1988'12:33:50~
'AJ/7 Plant Name.
-CNS
. Sample Number : 635' Type / Location :' AIR RADIDIODINE9 / 205 Sample Date. 16-MAR-1988 10:41:00
~Acq. Start _ Time. : 22-MAR-1988.12:02:46-
-: Sample Ouantity : 563.000 M3
. Sample ID : 9 MAR TO 16 MARS 8 Measurement Type : ROUTINE 1
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac, of Nuclide Energy (pCi/M3) . Error reg LLD Rpt.. Level' MN 834.83 <.1.590E-02 0.OOOE+001 CO-58 810.76' <L2.322E-02 0.OOOE+00 FE-59 1099.22 < 3.542E-02 0.OOOE+00 CO-60 1332.47 < 3.308E-02 0.OOOE+00 ZN-65 1115.52~ < 4.182E-02 -0.OOOE+00 NB-95 765.78 < 2.175E-02 0.OOOE+00 ZR-95 756.72 < 3.54BE-02 0.OOOE+00 I-13,1 364.48 <: 2.396E-02 .O.OOOE+00 CS-134 604.66 < 1.397E-02' O.OOOE+00 CS-137 661.65 < 1.930E-02 0.000E+00
.BALA-140 1596.49 < 4.220E-02 0.OOOE+00
,( K-40 1460.75 0.611 0.113 Total Fraction of Reporting Level O.OOOE+00 Analyzed by: jf . _ _ .u_____
Approved by:____ d _[ , ______.__________ _ Date: _a_/_ g/__gS__ O
Q'
~
l'
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VAX/VMS Sample Analysis' Report generated 31-MAR-1988 11:32:22)
,}N'( ,
A/ ; P1' ant ' Name - : CNS
- Sample. Number-
- : 672-Type / Location : AIR RADIOIODINE9 /~205
- Sample Date- s.23-MAR-1988 11:50:00 Acq.EStart:Timei : 30-MAR-1988 08:39:50
; Sample Quantity- : . 603.000 M3 Sample ID. : 16 MAR TO-23 MAR 88
;/ Measurement ~ Type
_________ _c. ROUTINE
***** Gamma-Spectroscopy Analysis'*****
Activity 1-Sigma MDA> Frac. of ., _Nuclide . Energy (pCi/M3)- Errori reg LLD Rpt. Level ', 'MN-54 834.83 < 1.400E-02' O.OOOE+00 CO 810.76 g< 8.974E-03 0.OOOE+00 FE-59 1099.22: < 4.578E-02 0.OOOE+00 CO-60 L1332.47 < 1.642E-02 0.OOOE+00 ZN-65 1115.52- < 3.495E-02 0.OOOE+00 NB '765.78 < 1.306E-02 0.OOOE+00 ZR-95 1756.72- < 3.076E-02 0.OOOE+00
-I-131 364.48 < 1.773E-02 0.OOOE+00
- CS-134 604.66 < 1.237E-02 0.OOOE+00
-CS-137 661.65 < 1.723E-02 0.OOOE+00-L' .- BALA-140 1596.49 < 3.~326E-02 0.OOOE+00 L .K 1460.75 0.420 8.566E-02 Total-Fraction.of Reporting Level O.OOOE+00 1
An al yz ed . by: _______ __ _ . _ _ _ _ _ _ _ c. Approved by:___ M _(_v/ - Date: __.1/ _Al_ / _IS___ - 4
. 1
- s i d
____________________- ________________________________-- . = = = _ _ _ _ _ _ _ _ VAX/VMS Samole Analysis Reportfgenerated : 5-APR-1988' 13: 27: 34 1
;p 3 1i,
/. Plant Name. : lCNS-Sample Number : 722.
Type / Location AIR RADIOIODINES / 205 Sample Date- : 30-MAR-1988 11:50:00 Acq. Start Time : 5-APR-1988.12:56:41 Sample Quantity .:. 613.000 M3. a' l Sample ID : '23 MAR TO 30 MAR 88 Measurement Type : ' ROUTINE ___- ._______==-- _______________ ____________ -___------ ________
***** Gamma-Spectroscopy Analysi s *****1 Activity 1-Sigma MDA> Frac..of Nuclide . Energy- '(pCi/M3) Error req LLD Rpt. Level-MN-54' 834.83 < L1. 557E-02: 0.OOOE+00
-CO-58 810.76 '< 1.'140E-02 0.OOOE+00 FE 1099.22 .< 2.631E-02 0.OOOE+00. l CO-60 1332.'49 < 1.281E-02 0.OOOE+00 IN-65 1115.52 < 2.178E-02 0.OOOE+00' i NB-95 765.79. <'1'350E-02 . 0.OOCE+00 ZR-95' 756.72 < 2.694E-02 'O.OOOE+00 I-131 .364.48 < 1.495E-02: 0.OOOE+00
.CS-134' 604.70' < 1.237E-02 0.OOOE+00 CS-137 .661.65 < 1.286E-02 0.OOOE+00 j, BALA-140 537.32 < 4.99BE-02 0.OOOE+00
___<.==-- Total Fraction of Reporting Level .O.OOOE+00 Anal y:ed by: __ __ __ mg _ _ _ _ _
' Approved by:_ 3 _[.__ 4_______________ Date: _//__(/_Ie___ _
0: - L E w _ - - - _ _ _ - _ _ .- _
_n _- __. - ___- - - - - - _ - _ _ _ -- - - _ _ . - - _ _ _ _ - - - - _ - _ . . - - - _ _ _ - _ - _ - - t '4 .i t 9 1 s i y VAX/VMS' Sample Analysis Report generated i'20-APR-1988 11:43:02~
~
~P1' ant Name :: CNS y; :
SamplelNumber- : 742 .
- 4 Type / Location :. AIR'RADIDIODINES / 205~
LSample Date- : 6-APR-1980'10:35:OO " Acq.LStart Time .,. B-APR-1988 12:03:04' Sample Quantity : 592.000 M3. Semple ID _ 30 MAR TO 6APR88 Measurement. Type n. ROUTINE
***** Gamma-Spectroscopy. Analysis-*****
Activity 1-Sigma MDA> Frac. of-
'. Nuc l i d e - Energy (pCi/M3). Error. req LLD Rptv Level MN 834.93 .<'1.446E-02 O.OOOE+00-CO-58 810.76 .-1.562E-02
< 0.OOGE+00 FE-59 1099.22 <?3.751E-02 O.OOOE+00 CO-60 1332.49- <:1.871E-02 O.OOOE+00 ZN-65 1115.52 < 2.720E-02 0.OOOE+00 NB-95 765.79 < 1.248E-02.. O.OOOE+00 2R-95. 756.72- <~1.92BE-02 0.OOOE+00 I-131- 364.48 <-1.040E-02 0.OOGE+00 CS-134 .604.70 < 1.330E-02 0.OOOE+00
;p - CS-137 661.65 < 1.603E-02 O.OOOE+00
- g. BALA-140 537.32 < 4.323E-02 O.OOOE+00 Total Fraction'of Reporting Level 'O.OOOE+00-
\'
1
. An al yz ed by: ____, ____ _ y _ ______
Approved by:___ . h ___________ _ Date: _ p( /.M. _ / R_ _ _ lO L _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ - - - -_ - __ m
S, LVAX/VMS Sample' Analysis Report 1 generated : 20-APR-1988 07:48:24-
~
( - ' 1 't N. Plant Name.- 's:CNS-Gample Number- l: 770 LType/ Location : AIR-RADIDIODINES / 205 Samole'Date- .:'13-APR-1988.11:OO OO-Acq. Start Time : 19-APR-1988 15:36:20'
. 7 : Sample.Quantitv' : 572.000 M3 p_
- Sample ID . :-!6APR"TO.13APR88
' -Measurement Typec: ROUTINE-
***** Gamma-Spectroscopy Analysis *****-
Activity 1-Sigma MDA> Frac. of. Nuclide . Energy 7 ( pCi /M3)- Error. reg LLD Rpt. Level l, , MN-54 834.83 4 1.106E-02 0.OOOE+00-
! . 'CG-58 810.76 < 1.105E-02 0.OOOE+00 FE-59 =1099.22- < 1.873E-02 O.OOOE+00 CO-60' 1332.49 < 4.348E-03 0.OOCE+00 ZN-65 - 1115.52 < 2.152E-02 0.OOOE+00 ,
NB-95 765.79 < 7.519E-03 0.OOCE+00
'ZR-95 756.72 < 1.843E-02 0.OOOE+00 1-131 364.48 < 7.757E-03 0.OOOE+00 CS-134' 604.70 <'9.179E-03 0.OOOE+00 CS-137- 661.65 < 1.035E-02 0.OOOE+00
~
..'~
-BALA-140- 537.32 <'5.574E-02 0.OOOE+00 K-40 1460.01 0.423- 0.111 Total Fraction of Reporting Level O.OOOE+00 An al v ed by : ____________ _y _________
[' Approved by:___ M _b_. _____.__________ Date: _[_/_w_i__fj__ f l l l i _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ = _ _ _ . _ _ _ _ _ _ _ _ . _ . _ _ . _ _ _ . . _ _ . . . _ _ m .
VAX/VMS Scmplo Anelynic Report g;nsretcd 26-APR-1988 07:48:45 Plant Name : CNS l
,~
Sample Number : 791 ! Type / Location : AIR RADIDIODINES / 205
~) Sample Date : 20-APR-1988 10:25:00 Acq. Start Time : 25-APR-1988 15:06:11 Sample Quantity : 611.000 M3 Sample ID : 13APR TO 20APROB Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Si gma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.221E-02 0.OOOE+00 CO-58 810.76 < 1.254E-02 0.OOOE+00 - FE-59 1099.22 < 2.778E-02 0.OOOE+00 CO-60 1332.49 < 2.518E-02 0.OOOE+00 ZN-65 1115.52 < 3.160E-02 O.OOOE+00 NB-95 765.79 < 1.834E-02 0.OOOE+00 ZR-95 756.72 < 3.198E-02 0.OOOE+00 I-131 364.48 < 2.101E-02 0.OOOE+00 CS-134 604.70 < 1.225E-02 0.OOOE+00 CS-137 661.65 < 1.361E-02 0.OOOE+00 BALA-140 537.32 < 6.739E-02 0.OOOE+00 K-40 1460.81 0.399 0.147 ( ; Total Fraction of Reporting Level O.OOOE+00
-v Analyzed by:___ ___ _ _______________
Approved by:__ 7 /d._ _____.._________ Date: _ / _r_f_ / _gq _ __ ! . i l
?\
L-) i l - _ - _ _ _ _ _ _ _ _ _ - - _ _ s l
DUKE POWER COMPANY APPLIED SCIENCE CENTER 4 RADIDANALYSIS LABORATORY j
; ^
,) = - - ==_________________________________..________= _____- - _ - - ._
1 VAX/VMS Sample Analysis Report generated : 29-APR-1988 15:38:06 Plant Name : CNS Sample Number 818 Type / Location : AIR RADIDIODINES / 205 Sample Date : 27-APR-1988 11:30:00 Acq. Start Time : 29-APR-1988 14:38:08 Sample Quantity : 632.000 M3 Sample ID : 20APR TO 27APR88 Measurement Type : ROUTINE _. - _____- _-- =____ ______
***** Gamma-5 spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.265E-02 0.OOOE+00 CO-58 810.76 < 6.485E-03 0.OOOE+00 FE-59 1099.22 < 5.850E-03 0.OOOE+00 CO-60 1332.49 < 1.900E-02 0.OOOE+00 ZN-65 1115.52 < 2.555E-02 0.OOOE+00 NS-95 765.79 < 1.175E-02 0.OOOE+00
- ZR-95 756.72 < 1.744E-02 0.OOOE+00
-I ,) I-131 364.48 < 8.803E-03 0.OOOE+00 CS-134 604.70 < 8.065E-03 0.OOOE+00 CS-137 661.65 < 1.088E-02 0.OOOE+00 BALA-140 537.32 < 2.631E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are ' listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
= - - - = - = _ = - - - ___--- ____.._________________ -_______
Analyzed by:_____ _ ___________ Approved by:_ M [,_ d ______ _ __ _ _ ___ Date: __ / _y_/ _ ,re___ ] 1 N.] j l l l 1 m___
------------------------- __- ====-_
DUKE POWER COMPANY APPLIED SCIENCE CENTER
,~s RADIDANALYSIS LABORATORY r :
LJ
------- =----------_---- _=-___-- - - - - _ - - - - - - _ - - - = _ =
VAX/VMS Samole Analysis Report generated : 6-MAY-1988'14:51:33 Plant Name : CNS Somple Number : 828 Type / Location : AIR RADIDIODINES / 205 Sample Date : 4-MAY-1988 09:50:00
'Acq. Start Time : 6-MAY-1988 13:01:19 . _ .
Sample Quantity : 636.000 M3 Sample ID : 27APR TO 4MAY88 Measurement Type : ROUTINE -
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 . < 1.664E-02 0.OOOE+00 CO-58 810.76 < 8.588E-03 0.OOCE+00 FE-59 1099.22 < 5.158E-02 0.OOOE+00 CO-60 1332.49 < 2.416E-02 0.OOOE+00 ZN-65 1115.52 < 3.357E-02 0.OOOE+00
<x NB-95 765.79 < 1.659E-02 0.OOOE+00
( '
) ZR-95 756.72 < 1.962E-02 0.OOOE+00 I-131 364.48 < 1.480E-02 0.COOE+00 CS-134 604.70 < 1.439E-02 0.OOOE+00 CS-137 661.65 < 1.451E-02 0.OOOE+00 BALA-140 537.32 < 5.631E-02 0.OOOE+00 K-40 1460.81 0.615 0.107 Total Fraction of Reporting Level O.OOOE+00
\ u Gamma results are listed as Less Than Levels using Tech Spec LLD eauation. LLD = 4.66 SORT B/t. Presence of less than sign f or gamma I results means no peak was found and the zero error is not applicable. Tritium. Alnha and Beta results are the best estimate of the ' activity and the less than sign indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD Analyzed by:_ d W - _ s h _--_____ Approved by:___ @ _[._ _______________ Date: _g /__g/_f)___ a
,f*% ,
x> i l l I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .I
._- - ----- ~
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY j VAX/VMS Sample Analysis Report generated : 18-MAY-1988 11 : 00: 22 Plant Name : CNS Sample Number 858 Type / Location : AIR RADIOIODINES / 205 Sample Date : 11-MAY-1988 11:57:00 Acq. Start Time : 17-MAY-1988 14:49:25 Sample Quantity : 592.000 M3 Sample ID : 4MAY TO 11MAY88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
1 Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 8.829E-03 0.OOOE+00 CO-58 810.76 < 1.OO3E-02 0.OOOE+00 FE-59 1099.22 < 2.203E-02 0.OOOE+00 CO-60 1332.49 < 1.128E-02 0.OOOE+00 ZN-65 1115.52 < 2.076E-02 0.OOOE+00 NB-95 765.79 < 9.839E-03 0.OOOE+00 ZR-95 756.72 < 1.640E-02 0.OOOE+00
, ~s I-131 364.48 < 1.041E-02 0.OOOE+00 x ) CS-134 604.70 < 3.795E-03 0.OOOE+00 CS-137 661.65 < 8.713E-03 0.OOOE+00 BALA-140 537.32 < 3.748E-02 0.OOOE+00 K-40 1460.81 0.223 4.857E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD 1 equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error i s not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
--)_--_________--___---____- __-_---____
Analyzed by:________ _._ _ ____________ Approved by:___ M __/-_ ________ _________ Date: __s_/_/f_/__ay___
,~,
4
.,/
l DUKE POWER COMPANY I APPLIED SCIENCE CENTER- ! RADIDANALYSIS LABORATORY i i
-----_------__------_----_-- -_--------- -_----__------_ -_--- l
-i w.d
) VAX/VMS Sample Analysis Report generated a 31-MAY-1988 13:18:22' )
1
. 1 Plant Name : CNS ~
Sample Number : 878 j Type / Location : AIR RADIOIODINES / 205 j Sample Date 18-MAY-1988 11:05:00 ) Acq. Start Time : 24-MAY-1988 13:14:27 i Sample Quantity 568.000 M3 ( Sample ID : 11MAY TO 18MAY88 Measurement Type : ROUTINE _ _ _ _ _ _ _ _ - _ - - - - _ _ _ _ - - -- ==-____-_-__=_ __--____-_-__--_-__-_-_--- __
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.375E-02 0.OOCE+00 CO-58 810.76 < 1.098E-02 0.OOOE+00 FE-59 1099.22 < 2.160E-02 0.OOOE+00 CD-60 1332.49 < 1.302E-02 0.OOOE+00 ) ZN-65 1115.52 < 4.653E-02 0.OOOE+00 NB-95 765.79 < 1.091E-02 0.OOOE+00 ZR-95 756.72 < 1.712E-02 0.OOOE+00 I-131 364.48 < 1.670E-02 0.OOOE+00 ("T CS-134 604.70 < 1. OBOE-02 0.OOOE+00 (/ CS-137 661.65 < 1.548E-02 0.OOOE+00 i BALA-140 537.32 < 5.954E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 I Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. . Tritium- Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
-----------------____-------_----- . =.----__--_--_-_------_--- l Analyzed by:_ __ _________
Approved by __ M __h _ ________ ____ Date: _J_ / _(,_ / _ f6__- r~N 1
\.-)
h___---m_.___m-_m_.____m _ . _ _ _ _ _ _
V c A DUKE POWER COMPANYc
. APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY p
1,f'V -VAX/VMS Sample Analysis Report - generated 1-JUN-1988 10: 04 : 01- t L L(-[ . t
~PlantLName. CNS.
Sample,. Number 898 ~
> Type / Location- 3 AIR RADIDIODINES / 205
- . Sample'Date : 25-MAY-1988.10:25:OO Acq.' Start Time : 1-JUN-1980'09:10:19
- Sample' Quantity. 597.000 M3 J E
' Sample.ID . s.18MAYaTO'25MAY88
_ Measurement 1 Type' ' ROUTINE o ___________________________ _ _ __ _ _ _ -
~
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of
'Nuclide' Energy f(pCi/M3F . Error reg LLD Rpt. Level MN-54 834.83 <~1'.196E-02 .O.OOOE+00 CO-58 810.76' <'1.282E-02 'O.OOOE+00 FE-59' 1099.22. < 2.656E-02 0.OOOE+00
'CD-60. '1332.49 < 2.032E-02 0.OOOE+00 ZN 1115.52 < 3.676E-02 0.OOOE+00 L NB-95 -765.79~ < 1.044E-02 0.OOOE+00' 2R-95 o .756.72- < 2.570E-02 0.OOOE+00 .
I-131-- 364.48 < 1.417E-02 0.OOOE+00 L:*~L CS-134 604.70 < 1.191E-02 0.OOOE+00 4 CS-137; ~ '661.65 < 1.152E-02 0.OOOE+00 BALA-140 537.32 < 5.564E-02 0.OOOE+00 K-40 1460.81 0.'271 0.028E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than. Levels using Tech Spec LLD -
-equation. LLD = 4.66 SQRT B/t. Presence of'less than sign for-gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the ! activity 'and -the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD y____________________. _________ _______ LAnalyzed=bys____ J __ __ Approved'by:___ j N . _ ,._______ Date: _h_/_G_/_gB___ O i LL_-_---_-_L_-._---_------------- - - - - - - - -
y . ne g -~~ - -a= u a a- .; = = = .:.= = - : :- - .- - - :.= - = ;- == === ---- = ; . --- -- --------- = :. = g.~ L ' DUKE POWER COMPANY L L LAPPLIED SCIENCE. CENTER I L RADIDANALYSIS' LABORATORY- l
.I L' [~
s- - VAX/VMS Sample Analysis Report generated ' 8-JUN-1988 11:56:12 ] I' f i Plant Name CNS- ! Sample Number 918 Type / Location : AIR RADIGIODINES / 205
. Sample Date : 1-JUN-1988 10:25:00 Acq. Start Time : 8-JUN-1988 09:55:23 Sample Quantity. : 656.000 M3 ,
Sample ID' : 25MAY TO 1JUN88 Measurement Type : ROUTINE
---------------._ _ - .--------- _--==--=- _
***** Gamma-Spectroscopy Analysis *****
4 Activity 1-Sigma MDA> Frac. of -
.J Nuclide Energy- . (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.145E-02 0.OOOE+00 CO-58 810.76 '< 6.552E-03 0.OOOE+00-FE-59 1099.22- < 3.205E-02 O.OOOE+00 CD-60 1332.49 < 1.509E-02' 0.OOOE+00 ZN-65 1115.52 < 1.706E-02" O.OOOE+00 NB-95 765.79 < 1.061E-02 0.OOOE+00 2R-95 '756.72 < 1.933E-02 ' O.OOOE+00
.I-131 364.48 < 1.363E-02 0.OOOE+00 ,
. (') CS-134 604.70 ~< 7.889E-03 0.OOOEdOO -
\_/ CS-137 661.65 < 7.576E-03 0.OOOE+00
.BALA-140 537.32 < 3.919E-02' O.OOOE+00 l K-40 1460.81 0.118 6.498E-02 Total Fraction of Reporting Level O.OOOE+00 Bamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t.- Presence of less than sign for gamma results means no peak was found and. the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less, than the critical level, CL. CL = 0.5 LLD
,-)----=_ _==---------------------
o Analyzed by:____ _____________ Approved by:__ M _(_ Date: _4./__f_/_ g___
l l l c - o :.
' DUKE POWER COMPANY APPLIED SCIENCE CENTER PADIDANALYSIS LABORATORY VAX/VMS Sample Analysis Report generated : 17-JUN-1988 11:59:22 Plant Name : CNS Sample Number : 944 Type / Location : AIR RADIOIODINES / 205 Sample Date 8-JUN-1988 10:15:00
'Acq. Start Time : 17-JUN-1988 10:56:17
-Sample Quantity : 585.000 M3 Sample ID : 1JUN TO 8JUN88 Measurement Type : ROUTINE
_ _ _ _ _ _ _ _ _ _ _ _ = . -____________________-- ___ ____________________
, ** *** Gamma-Spectroscopy Anal ysi s *****, -w, Activity 1-Sigma MDA> . Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 6.569E-03 0.OOOE+00 CO-58 810.76 < 1.463E-02 0.OOOE+00 FE-59 1099.22 < 3.228E-02 0.OOOE+00
- CO-60 1332.49 < 2.118E-02 0.OOOE+00 2N-65 1115.52 < 4.404E-02 0.OOOE+00 NB-95 765.79 < 2.087E-02 0.OOOE+00 ZR 756.72 < 2.374E-02 0.OOOE+00 I-131 364.48 < 2.488E-02 0.OOOE+00 CS-134 604.70 < 1.285E-02 0.OOOE+00 CS-137 661.65 < 1.293E-02 ,0.OOOE+00 BALA-140 537.32 < 8.224E-02 0.OOOE+00 t K-40 1460.81 0.360 8.060E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD ____________________._.n,___....___________ - =_ _ --=- == =__- Analyzed by:___ ____________ Approved by:__ M _f_. , _ __________ Date: _f _ / _s:* / __8Le_ __ ()
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY-(~g -------..-------------- --------------------- --------- _ - - - - - - - - - - .A_) VAX/VMS Sample Analysis Report generated s .21-JUN-1988 13:53:26 Plant Name : CNS Sample Number 966; Type / Location : AIR RADICIODINES / 205 Sample Date. : 15-JUN-1988 11:20:00 Acq. Start Time : 21-JUN-1988 13:09:54 Sample Quantity : 646.000 M3 Sample.ID- : 8JUN TO 15JUNG8 Measurement Type : ROUTINE.
----------------------- =---= --- ------------ -------
*****. Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.24BE-02 0.OOOE+00 CO-58 810.76 < 8.637E-03 0.OOOE+00 - ~ ~ '- , i FE-59 1099.22 < 2.506E-02 0.OOOE+00 ' CD-60 1332.49 < 1.532E-02 0.OOOE+00 ZN 1115.52 < 2.181E-02 0.OOOE+00 NB-95 765.79 < 9.484E 0. OOOE+00 ZR-95. 756.72 < 1.596E-02 0.OOGE+00 I-131 364.48 < 1.383E-02 0.OOOE+00 f-) .(_j CS-134 604.70 < 1.010E-02 0.OOCE+00 CS-137 -661.65 < 1.077E-02 0.OOOE+00 BALA-140 537.32 < 2.783E-02 0.OOOE+00 K-40 1460.81 0.173 4.988E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.LL SQRT B/t. Presence of less than sign f or gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
-------- = - - - - - - - - = _ _ _ . =-- ..---------- _--------------
_ _ -__=--_ee-- Approved by:__ N .f_ __ Date: _c._ / _m / _AE:L___ nD
, ------------------------------- =_--------------------------------------
DUKE' POWER COMPANY i APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY n;, --------- ------------------------------------- _=------------------- VAX/VMS Sample' Analysis Report generated 24-JUN-1988 14:07:51 Plant Name' : CNS Sample. Number : 978 Type / Location s' AIR RADIOIODINES / 205 Sample Date' 22-JUN-1988 11:46:00
.Acq. Start Time : 24-JUN-1988 13:20:28 Sample Quantity : 501.000 M3 +
. Sample ID .
- 15JUN TO 22JUN88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA>~ Frac. of
;Nuclide Energy (pCi/M3) Error req LLD Rpt. Level.
MN-54 834.83 < 1.629E-02 'O.OOOE+00 CO-58 810.76 < 1.196E-02 0.OOOE+00 FE-59 1099.22 < 3.573E-02 0.OOOE+00 CO-60 1332.49 < ' 1.702E-02 0.COOE+00 ZN-65 ~1115.52 < 2.945E-02: 0.OOOE+00-NS-95 765.79 < 1.376E-02 0.COOE+00 ZR-95 756.72 < 1.750E-02 0.OOOE+00 1-131 364.48 0.COOE+00
- \--
[') CS-134 -604.70 1.131E-02 1.174E-02 0.OOOE+00 CS-137 661.65 < 8.555E-03 0.COOE+00 BALA-140 537.32 < 4.807E-02 0.OOCE+00 Total Fraction of Reporting Level O.OOCE+00 Gamma results are listed as' Less Than Levels using Tech Spec LLD equation, LLD = 4.66 SQRT B/t. Presence of less than sign-for gamma results means no peak'was found and the zero error is not applicabis. Tritium, Alpha and Beta results are the best estimate: of the activity and the less than sign indicates that the net activity is Ier than the critical level, CL. CL = 0.5 LLD Analy::ed by:_ h __ h w _________ Approvedby:)))ka(._ _ _______________ Date: _f_/_g_/_f9___ l i L ! 1 i 1
V ----------------------------------------------------------------- --- L L DUKE POWER COMPANY h , APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY. E
; f'y~ -------- --------------------------------------------------------_ _
\^ VAX/VMS Sample Analysis Report generated: 6-JUL-1988.10:24:12 s
Plant Name : CNS Sample. Number : 1002 Type / Location : AIR RADIDIODINES / 205 Sample Date : 29-JUN-1988 10:00:00 Acq.15 tart. Time : 6-JUL-1988 09:01:37-i Sample Quantity : 635.000 M3 Sample ID : 22JUN TO 29JUN83 Measurement. Type ROUTINE
._-_----- -=-----------------------
***** Gamma-Spectroscopy-Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.037E-02 0.OOOE+00 CO-58 810.76 < 1.683E-02 0.OOOE+00 FE-59 1099.22 < 3.213E-02 0.OOOE+00 CO-60 1332.49 < 1.924E-02 O.OOCE+00 2N-65 1115.52 < 2.033E-02 0.OOOE+00 NB-95 765.79 < 2.173E-02 0.'OOOE+00 ZR-95 756.72 < 2.198E-02 0.COOE+00 (~] 'I-131 364.48 < 1.928E-02 0.OOOE+00
.( _/ CS-134 604.70 < 9.442E-03 0 OOOE+00 CS-137 661.65 < 1.160E-02 0.OOOE+00 BALA-140 537.32 < 5.679E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error i s not applicable.
-Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less ,
than.the critical level, CL. CL = 0.5 LLD
----------- ---- =----------- -------------------------
Analyzed by _kp_ __ _ u____ Approved by: e_(._ _q_______,________ Date: _f_ / _4_ / _ff___ O I
l "N -------q[2----------___--_--__-_---_-----_-_------_----- -----_--__--__
. r DUKE POWER COMPANY ^~
APPLIED SCIENCE CENTER ' RADIDANALYSIS LABORATORY n . 9; , VAX/VMS Sample ' A'nalysis Report generated : 12-JUL-1988 17:27:47 , Plant Name ~ s CNS Sample Number 1035 Type / Location : AIR RADIDIODINES /.205
-Sample Date 6-JUL-1988 11 : 00: 00 Acq. Start Time : 12-JUL-1988 16:42:07 Sample'Ouantity : 603.000 M3 Sample ID : 29JUN TO 6JUL88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Si gma MDA> Frac, of Nuclide . Energy (pCi /M3) Error reg LLD Rpt. Level
'MN-54 834.83 < 1.450E-02 0.OOOE+00 CO-58 810.76 < 9.089E-03 0.OOOE+00 FE-59 1099 22 < 1.778E-02 0.OOOE+00
-CO-60 1332.49 < 1.832E-02 0.OOOE+00 2N-65 1115.52 < 3.024E-02 0.OOOE+00 NB-95 765.79 < 8.792E-03 0.OOOE+00 ZR-95 756.72 < 1.563E-02 0.OOOE+00
~T ' I -1~31 364.48 < 1.122E-02 0.OOOE+00
[d- CS-134 604.70 < 9.127E-03 0.OOOE+00 CS-137 661.65 < 1.180E-02 0.OOOE+00 BALA-140 537.32 < 3.369E-02 0.OOOE+00 K-40 1460.01 0.355 9.15BE-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzedby__sh$[_____ ________________ Approved by:__ 7 /s_(u _. ____,________ Date: _ _7_ / /2_ _ / __8L5__ _ I l l l l 1
DUKE POWER COMPANY ! APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY () N> VAX/VMS Sample Analysis Report generated : 18-JUL-19BB 11:11:04 __=---------------------- i
^
Plant Name : CNS Sample Number : 1063 Type / Location : AIR RADIDIODINES / 205 Sample Date : 13-JUL-1958 12:22:00 Acq. Start Time : 18-JUL-1988 09:53:24 Sample Quantity 590.000 M3 Sample ID : 6JUL TO 13JUL88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.571E-02 0.OOOE+00 CO-58 810.76 < 1.344E-02 0.OOOE+00 FE-59 1099.22 < 3.OO2E-02 O.OOOE+00 CO-60 1332.49 < 1.284E-02 0.OOCE+00 ZN-65 1115.52 < 2.746E-02 0.OOOE+00 NB-95 765.79 < 1.45BE-02 0.OOOE+00 ZR-95 756.72 < 2.429E-02 0.OOOE+00 (~3 I-131 364.48 '< 1.886E-02 0.OOOE+00 C/ CS-134 604.70 < 1.219E-02 0.OOGE+00 CS-137 661.65 < 1.191E-02 0.OOCE+00 BALA-140 537.32 < 5.173E-02 0.OOOE+00 K-40 1460.81 0.322 0.101 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD , equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma ' results means no peak was f our,d and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
--------------- ,---_-----__---____-___________----__------------_ j Analyzed by:_ _ m w __________
Approved by: M _[2__ ______________ Date: __t/_LB./__g6__
/7 I
L - -
DUKE POWER COMPANY
~ APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY y
- (:) VAX/VMS Sample. Analysis Report generated : 22-JUL-1988 15:48:13 Plant Name : CNS *
- 1084-
'.Type Sample / Location Number : AIR RADIDIODINES / 205 Sample Date : 20-JUL-1988 10:50:00 Acq. Start. Time : 22-JUL-1988 14:25:20 Sample Quantity : 580.000 M3 Sample ID s'13JUL TO 2OJUL88 Measurement Type : ROUTINE
-----=-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error . req LLD Rpt. Level MN-54 834.83 < 1.196E-02 0.OOCE+00 CO-50 810.76 < 1.429E-02 0.OOOE+00 ~ FE-59 1099.22 < 3.790E-02 0.OOOE+00 4 CO-60 1332.49 < i.604E-02 0.OOOE+00 i ZN-65 1115.52 < 2.185E-02 0.OOOE+00 } NB-95 765.'79 < 1.071E-02 0.OOGE+00 ZR-95 756.72 <'2.110E-02 0.OOOE+00 I-131 364.48 < 1.OO7E-02 0.OOOE+00 CS-134 604.70 < 1.131E-02 O.GOOE+00 CS-137 661.65 -< 0.265E-03 0.OOOE+00 BALA-140 537.32 < 3.863E-02 0.OOOE+00 K-40 1460.81 0.320 7.548E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech ' Spec LLD equation. LLD = 4.66 SORT D/t. Presence of less than sign for' gamma-resul ts means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
- t Analyzed by: _C\ _ t% _ _g w _____
Approved by:__ M __f_._ _h __ _ _ _________ Date: _f_ / zt_ / ss ___ p ..
DUKE POWER COMPANY APPLIED SCIENCE CENTER { RADIDANALYSIS LABORATORY ; f% l ( j ________________________ ____________ _____________ _____________________ VAX/VMS Sample Analysis Report generated 1-AUG-1988 15:17217 Plant Name " : CNS Sample Number 1145 Type / Location : AIR RADICIODINES / 205 Sample Date : 27-JUL-1988 11:30:00 z Acq. Start Time : 1-AUG-1988 14:20:39 ! I Sample Quantity : 602.000 M3 Sample ID : 20JUL TO 27JUL88 l Measurement Type : ROUTINE j
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.184E-02 0.OOOE+00 CO-58 810.76 < 1.026E-02 0.000E+00 FE-59 1099.22 < 1.842E-02 0.OOGE+00 . CO-60 1332.49 < 1.124E-02 0.000E+00 i ZN-65 1115.52 < 6.798E-03 0.OOOE+00 i NB-95 765.79 < 9.986E-03 0.000E+00 2R-95 756.72 < 1.765E-02 O.OOOE+00 h I-131 364.48 < 1.463E-02 0.000E+00 ("/ w CS-134 604.70 < 1.015E-02 0.OOOE+00 CS-137 66i 65 ( 1.254E-02 O.000E+00 BALA-140 537.32 < 4.158E-02 0.OOOE+00 K-40 1460.81 0.278 6.557E-02 Total Fraction of Reporting Level O.000E+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tr i t i um., Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less! than the critical level, CL. CL = 0.5 LLD l Analyzed by ________ _____ ___________ ! Approved by:_ M _f_, n____,_______ _ Date: _ 9_ _ / _ p / _ _4gS_ _ _ 1 I 1 fm t 1 k/
.yQy??i.S$6RONY2%CBM.X]Q&; j.f"
~
l g iMil: G ;;x X . gayNp e -
.c a JAPPLIED, SCIENCE' CENTER ~. -
' \ 'J l q~ . . '. RADI0 ANALYSIS LABORATORY n
[
----------------------------- d------_------------ _
[%),l. VAX/VMS Sample Analysis Report generated 9-AUG-1988 13:24:18 i Plant Name : CNS Sample Number : 1158 Type / Location : AIR RADIOIODINES / 205 Sample Date : 3-AUG-1988 09:15:00 Acq. Start Time a '8-AUG-1988 11:14:29 Gample Quantity : 563.000 M3
- 27JUL TO 3AUG88
~
Sample ID Measurement Type ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.93BE-02 0.000E+00 CO-58 810.76 < 1.477E-02 0.000E+00 FE-59' 1099.22 < 8.221E-03 0.OOOE+00 CO-60 1332.49 < 2.276E-02 0.000E+00 ZN-65 1115.52 < 3.459E-02 0.OOOE+00 NB-95 765.79 < 1.581E-02 0.OOOE+00 ZR-95 756.72 < 2.873E-02 0.OOOE+00 1-131 364.48 < 1.735E-02 0.000E+00 O) k/ CS-134 604.70 < 1.541E-02 0.OOOE+00 CS-137 661.~65 < 1.313E-02 0.000E+00 BALA-140 537.32 < 4.157E-02 0.000E+00 K-40 1460.81 0.287 7.404E-02 Total Fraction of Reporting Level O.000E+00 Gamma results are listed as Less Than Levels using ' Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed bys_)$ ,- ___________________ Approved by:_ M _b _ t__ _ _______ Date: _ a _ / _ _ / _ _83 _ _ _ O
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY (3 's_/ ' VAX/VMS Sample Analysis Report generated : 18-AUG-1988 14:31:05 Plant Name : CNS Sample Number : 1188 Type / Location : AIR RADIDIODINES / 205 il Sample Date : 10-AUG-1988 12:50:00 Acq. Start Time s'18-AUG-1988 11:38:09 Sample Guantity : 598.000 M3 [ Sample ID : 3AUG TO 10AUG88 ! Measurement Type : ROUTINE ___ =_________________________
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of l Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.548E-02 0.OOCE+00 CO-58 810.76 < 1.613E-02 0.OOOE+00 FE-59 1099.22 < 4.180E-02 0.OOOE+00 CO 1332.49 < 2.110E-02 0.OOOE+00 ZN-65 1115.52 < 4.150E-02 0.OOOE+00 NB-95 765.79 < 1.928E-02 0.OOOE+00 ZR-95 756.72 < 2.034E-02 0.OOOE+00 m I-131 CS-134 364.48 < 2.033E-02 0.OOOE+00 (,) 604.70 < 1.211E-02 0.OOOE+00 CS-137 661.65 < 1.387E-02 0.OOOE+00 BALA-140 537.32 < 6.295E-02 0.OOOE+00 K-40 1460.81 0.203 0.116 Total Fraction of Reporting Level O.OOOE+00 i Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. 1 J Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less i than the critical level, CL. CL = 0.5 LLD _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - ---__ _ ____._ _=___________________________ 1 Analy ed by:___ f _______ A PProved by:_ 3 _(_ _ Date: __A./_tf_/_tgr____ 1 0
DUKE POWER COMPANY
' APPLIED SCIENCE CENTER.
RADIDANALYSIS LABORATORY L I VAX/VMS Sample Analysis Report generated 23-AUG-1988 14:29:24
' Plant Name- : CNS Sample Number : 1200 Type / Location : AIR RADIDIODINES / 205 Sample Date : 17-AUG-1988 10:22:00 Acq. Start-Time : 23-AUG-1988 13:57:36 Sample Quantity :- 591.000 M3 Sample ID : 10AUG TO 17AUG88 Measurement Type.: ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac.'of Nuclide. Energy (pCi/M3) Error. reg LLD Rpt. Level MN-54 834.83 '< 1.268E-02 0.OOOE+00 CO-58. 810.76 < 1.297E-02 0.OOOE+00 FE-59 1099.22 < 2.331E-02 0.OOOE+00 CD-60 1332.49 < 4.209E-03 0.OOOE+00 ZN-65 1115.52 < 3.181E-02' O.OOOE+00 NB-95 765.79 < 1.149E-02 0.OOOE+00 2R-95 756.72 <.1.948E-02 0.OOOE+00
- Y I-131 364.48 < 1.700E-02 0.OOOE+00
, CS-134~ 604.70 < 7.931E-03 0.OOOE+00 CS-137 661.65 < 9.383E-03 0.OOOE+00 BALA-140 537.32 < 4.818E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD
' equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is.not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD i
- _=_________________ _____________________________-- =____
Analyzed by: MCdh__ n_ _ _ _ _ - _ _ _ _ _ _ , Approved bys__ M 2_[2_ ,__ ____________ Date: _ _8_ / _g_ / _ Je, __ _ 3 i o 1
< L DUKE POWER. COMPANY APPLIED SCIENCE CENTER
!RADI0 ANALYSIS LABORATORY
); sVAX/VMS Sample Analysis: Report generated 29-AUG-1988 13:25:34
. o i..
' Plant Name. : CNS Sample Number : 1223 Type / Location _ e AIR RADIDIDDINES / 205 '
, Sample Date . 24-AUG-1988 09:40:00 Acq. Start Time : 129-AUG-1988'12:54:29. Sample, Quantity - . -568.000 M3 Sample ID 17AUG TO 24AUG88 . Measurement Type : ROUTINE
.***** Gamma-Spectroscopy Analysis *****
v . Activity 1-Sigma MDA> Frac. of. Nuclide Energy . (pCi/M3) fError. reg LLD Rpt. . Level
.MN-54 834.83 < 1.230E-02 0.OOOE+00 CO-58 810.76 < 1.213E-02 .O.000E+00 FE-59 1099.22 <-3.306E-02 0.OOOE+00
.CO 1332.49 < 1.742E-02 0.000E+00 ZN-65 1115.52 < 1.453E-02 'O.OOOE+00 NB-95 765.79 < 7.237E-03 0.000E+00
- ZR-95 756.72 <-2.OO5E-02 0.OOOE+00 I-131 '364.48 .< 1.102E-02 0.OOCE+00 CS-134'
> .O' CS-137 604.70_ < 9.234E-03
.661.65 < 1.066E-02 0 OOOE+00 0.000E+00 BALA-140 537.32 < 4.691E-02 0.OOOE+00' K-40 1460.81 0.311 7.137E-02 Total. Fraction of Reporting. Level O.OOOE+00 Gamma results are. listed as Less'Than Levels using. Tech Spec'LLD equation. LLD = 4.66 SQRT'B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate.cf the activity and the less than sign indicates that. the net activity is less than the critical level, CL. CL = 0.5 LLD
. Analyzed by:__ _[___ _ ____
Approved'by:__ d , 6 ___ _ _ _ . _- Date: _8_ _ / ,k. / SS O- .
1 g ________________________________________________________________ ______ > DUKE POWER. COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY I (') i
%-) _________________________________________________________________________
VAX/VMS Sample Analysis Report generated : 2-SEP-1988 13:35:11 i Plant Name : CNS Sample Number : 1240 1 Type / Location : AIR RADIDIODINES / 205 Sample.Date- : 31-AUG-1988'13:04:00 Acq. Start Time : 2-SEP-1988.13:04:10 Sample Quantity : 597.000 M3 Sample ID : 24AUG TO 31AUG88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3)' Error reg LLD Rpt. Level MN-54 834.83 < 1.368E-02 0.OOOE+00 CO-58 810.76 < 1.063E-02 0.000E+00 FE 1099.22 < 3.288E-02 0.OOOE+00 !~ CD-60 s 1332.49 < 1.600E-02 0.OOOE+00 ZN-65 1115.52 < 3.124E-02 0.OOOE+00 NB-95 765.79 < 1.461E-02 0.OOOE+00 [-} (_/ ZR-95 I-131 756.72 364.48 1.748E-02 1.220E-02 0.OOOE+00 0.000E+00 1 CS-134 604.70 < 1.138E-02 0.000E+00 CS-137 661.65 < 1.299E-02 0.000E+00 BALA-140 537.32 < 5.114E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. t Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by: % [_ __________ Approved by: _W f_f. _ _________ ______ Date: _2_/_4_/_8_S____ i i
-_n__n__.__.___._.___ _ _ . _ l
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY r
-N
\- ' VAX/VMS. Sample Anal'ysis Report generated a 9-SEP-1988 14:13:50 Plant Name : CNS Sample; Number 1255 Type /Locati on : AIR RADIDIODINES / 205 Sample Date . : 7-SEP-1988 10:50:00 Acq.. Start Time - : 9-SEP-1988 13:42:20 Sample Quantity. :- 563.000 M3 Sample ID 31AUG TO 7SEP88 Measurement Type : ROUTINE E ***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA>. Frac. of. Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54' :834.83 < 8.094E-03 0.OOOE+00 CO-58 810.76 < 1.297E-02 0.OOOE+00 FE-59 1099.22 < 2.254E-02 0.OOOE+00 3 CD-60 1332.49 < 4.411E 0.OOOE+00 ZN-65 1115.52 < 1.961E-02 0.OOOE+00 NB-95 765.79 < 1.318E-02 0.OOOE+00. ZR-95 756.72- <ol.261E-02 0.OOOE+00 N I-131 364.48 < 1.041E-02 0.OOOE+00
. CS-134 604.70 < 7.737E-03 0.OOOE+00 CS-137 661.65 < 1.075E-02 0.OOOE+00 BALA-140 537.32 < 2.485E-02 0.OOOE+00 K-40 1460.81 0.264 6.610E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma-results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results.are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed bys_ h_ cc,_cw ______ Approved by:__s!gt f/k_______.___________t -_ Date: _J_/se_/_dD_-- l 1(()
a ,, <_________________________- ___________________________________________. DUKE POWER COMPANY l APPLIED SCIENCE CENTER
. RADIOANALYSIS LABORATORY j<'y ,______ __________________________________________ ___________ ____
VAX/VMS Sample Analysis Report generated a 20-SEP-1988 16:07:11. y Plant Name : CNS i Sample Number s 1276 Type / Location : AIR RADIDIODINES / 205 i Sample Date : 14-SEP-1988 12:12:00 Acq. Start Time : 20-SEP-1988 15:35:51 Sample Quantity :- 575.000 M3 ll Sample ID : 7SEP.TO 14SEP88 > Measurement Type : ROUTINE l l l ***** Gamma-Spectroscopy Analysis ***** 1 Activity 1-Sigma MDA> Frac. of
.Nuclide Energy .
.pCi/M3)
( Error req LLD.Rpt. Level MN-54 834.83 < 1.479E-02 0.OOOE+00 . CD-58 810.76 < 1.28BE-02 0.OOOE+00 f FE-59 1099.22- < 2.233E-02 0.OOOE+00 CD-60 1332.49 < 1.395E-02 0.OOOE+00 ZN-65 1115.52- < 2.BBOE-02 0.OOOE+00 NB-95 765.79' < 1.551E-02 0.OOOE+00
' . 'ZR 756.72 < 2.145E-02 0.OOOE+00 I-131 364.48 < 1.653E-02 0.OOOE+00 CS-134 604.70 < 1.308E-02 0.OOOE+00 CS-137 661.65 < 1.371E-02 0.OOOE+00 BALA-140 537.32 < 6.393E-02 0.OOOE+00 K-40 1460.81 0.403 8.792E-02 Total Fraction of Reporting Level O.OOOE+00
> Gamma results are listed as Less Than Levels using Tech Spec LLD i equation. LLD = 4.66 SQRT B/t. Presence of.less.than sign for gamma i results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the [ activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD ______________________________________________----- =____________ i Analyzed by:___ d e Y ,_________ Approved by:_ N ,f. ________________ Date: _f_/_%/__@,__ O
DUKE POWER COMPANY APPLIED SCIENCE CENTER ' RADIDANALYSIS LABORATORY l T'T _________________________________________________________________________ I ,VAX/VMS Sample Analysis Report generated : 23-SEP-1988 12:42:16 I Plant Name : CNS ; Sample Number i 1295 Type / Location : AIR RADIOIODINES / 205 l Sample Date : 21-SEP-1988 10:46:00-Acq. Start Time : 23-SEP-1988 11:36:43 Sample Quantity : 566.000 M3 Sample ID : 14SEP TO 21SEP88 Measurement Type : ROUTINE _ _ _ _ _ _ _ _ _ _ - __ _____ ____ _ _ - - -_________ _ _ _ _ = - - - _ _ _ _
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.618E-02 0.OOOE+00 CO-58 810.76 < 1.594E-02 0.OOOE+00 FE-59 1099.22 < 2.100E-02 0.OOOE+00 CD-60 1332.49 < 2.24BE-02 0.OOOE+00 ZN-65 1115.52 < 3.765E-02 0.OOOE+00 NB-95 765.79 < 1.462E-02
- 0.OOOE+00 2R-95 756.72 < 3.380E-02 O.OOOE+00
/ I-131 364.48 < 1.505E-02 0.OOOE+00
(_) CS-134 604.70 < 1.577E-02 0.OOOE+00 CS-137 661.65 < 1.508E-02 0.OOOE+00 BALA-140 537.32 < 3.560E-02 0.OOOE+00 K-40 1460.01 0.458 9.341E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:__ _ _ _ _ ?" _ ,_ ____ Approved by:_ M f2_ _ ________s_______ Date: _ _ / _gg_ / __sLs_ _ _ O 1 i i
DUKE, POWER COMPANY L APPLIED SCIENCE CENTERL F , RADIDANALYSIS LABORATORY ,
.q
~
(g ------------------------------------------------------------------------- 1s .. VAX/VMS Sample Analysis Report generated ' 30-SEP-1988 11:40:37 l Plant Name : CNS Sample-Number. : 1321 , Type / Location AIR RADIGIODINES /.205 Sample Date : 28-SEP-1988 11:00:00 l Acq.; Start Time : 30-SEP-1988 11:08:08 H ' Sample Quantity 643.OOO'M3 1 Sample.ID : 21SEP TO.28SEP88 Measurement Type : ROUTINE a I
***** Gamma-Spectroscopy Analysis *****
A Activity 1-Sigma MDA> Frac. of
-Nuclide Energy- (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 <'1.253E-02 0.OOOE+00
- ' CO-58 '810.76' < 1.106E-02 0.OOCE+00 FE-59 1099.22 < 2.658E-02 0.OOOE+00 CD-60 1332.49 < 4.578E-03 0.000E+00 ,
ZN-65 '1115.52. < 3.156E-02 0.000E+00
.NB-95 765.79 < 1.018E-02 0.000E+00' ZR-95 756.72 < 1.254E-02 0.000E+00 i I-131 .364.48 < 7.798E-03 0.000E+00
-CS-134- 604.70 < 6.372E-03 0.000E+00 CS-137 661.65 < 6.396E-03 0.OOOE+00 1
- BALA-140 537.32 < 3.436E-02 0.'OOOE+00 Total Fraction of Reporting Level 0.000E+00
. Gamma results are listed as Less Than Levels using Tech Spec LL D c
equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gammai results means no peak was found and the zero error is not applicable. Tritium,' Alpha and Beta results are the best estimate of the . e activity and the less than sign indicates that the ' net activity is 'less than the critical level, CL. CL = 0.5 LLD m __ , __ mm Approved by: M_[._ _____ __________ Dates .jp_ / ._g_ /.SfL--- -
<4 i
l 4 (:) ! 1 J
7 0
'c m: ,
o DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY [d' ) m VAX/VMS Sample Analysis Report generated : 10-OCT-1988 16:32:55 H EPlant'Name- CNS. H : Sample Number : 1350:
. Type / Location z. AIR RADIDIODINES / 205 H Sample Date a '5-DCT-1988 10:20:00-Acq. Start-Time' 10-OCT-1988 16:01:50 Sample Quantity' .
1583.000 M3 Sample lID- 28SEP_TD-50CT88 Measurement Type'_s ROUTINE ^ ___________________________ _________ _____ _______= - - _ - _ . ---_____.
- l. l I
.***** Gamma-Spectroscopy Analysi s *****
1 Activity 1-Sigma, MDA> Frac. of
~Nuclide- Energy l (pCi/M3) Error ' reg LLD Rpt. Level
~MN-54 834.83 ;< 7.202E-03 0.OOOE+00 CO-58 810.76 < 1.060E-02--
0.OOOE+00 FE-59? 1099.22 <- 1.810E-02' O.OOOE+00 CD-60 1332.49 < :1.482E-02 0.OOOE+00
'2N-65 1115.52- < 2.278E-02 0.OOOE+00 NB-95. :765.79 < 8.971E-03 0.OOOE+00 '
f' :
'ZR-95 756.72 < 1.612E-02 0.OOOE+00
; I-131 364.48 <'9.404E-03 0.OOOE+00 CS-134 604.70- <-8.033E-03 0.OOOE+00
~CS-137 661.65 <1 1.105E-02 0.OOOE+00 BALA-140 537.32 < 4.287E-02 0.OOOE+00 .
K-40 1460.81 0.185' 7.410E-02 Total Fraction of Reporting Level O.OOCE+00 Gamma' results are listed as Less Than Levels using Tech Spec LLD
' equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicab1'e.
Tritium.. Alpha and Beta results are the best estimate of the j activity. and the less than sign' indicates that the net activity is less than the, critical level,'CL. CL = 0.5 LLD 3 ____=- l
)
Analyzed'bys_ __ _' _I __. ______ l
. Approved by: j b _____ _ ,_________ Date: _a_/_tA / _gg___
1 s
.u
________m_.a_-- _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _
1 DUKE. POWER COMPANY j LAPPLIED SCIENCE-CENTER l~ RADIDANALYSIS LABORATORY'
;{j VAX/VMSl Sample' Analysis Report generated 14-OCT-1988 15:32:48
' Plant:Name; CNS 1 Sample Number - L1373!
- AIR RADIDIODINES / 205
= Type /Locati on Sample lDate- . ,a 12-OCT-1988;11:OO OO Acq.<--Start Time 3J14-OCT-1980'15:01:23
- 530.OOO.M3 iSample-Quantity.~
Sample-IDL .
's 50CT TO 120CT88 Measurement-Type : ROUTINE
***** Bamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA>. Frac.'of Nuclide Energy (pCi/M3) Error -req LLD Rpt. Level MN-54: 834.83 <:1.151E-02 0.OOOE+00 CO-58' 810.76 '< 9.907E-03' O.OOOE+00
, FE-59i 1099.22- < 3.447E-02 0.OOOE+00 CO-60: 1332.49. <.1.275E-02 0.OOOE+00 12N 1115.52' < 2.629E 0.OOOE+00 L ENB-95 ;765.79- <-1.188E-02 0.OOOE+00 2R-95' 756.72 < 1.609E-02 0.OOOE+00-l I-131 1364k48 .< 8.355E 0.OOCE+00 CS-134' .604.70 < 9.617E-03 0.OOOE+00 CS-137: 661.65 <.1.117E-02 0.OOOE+00 BALA-140 .537.32; '< 4.129E-02 0.OOCE+00' '
K-40. 1460.81 0.404 8.415E-02 Total Fraction of-Reporting Level 0.OOOE+00 Gamma results are listed ~ as Less Than Levels using , Tech Spec LLD.
~
equation. LLD =.4.66 SQRT'B/t. Presence of less than. sign for gamma results means no peak was'found and the zero error is not applicable. , Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less l than'the critical level..CL. CL = 0.5 LLD Analyzed by ____ Y ___________ 1 Approved 'by:_'_ - rsh _6 _____ __ Date: _c._/__12/__t8___ [f} ' . J
'J DUKE POWER COMPANY
' APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
/- ----------------------------------------------,--------------------------
-(- VAX/VMS' Sample Analysis Report generated a 24-DCT-1988 13:25:36 Plant Name 's CNS Sample Number : 1395 Type / Location : AIR'RADIDIODINES /-205 Sample Date : 19-OCT-1988'11:58:OO Acq. Start Time : 24-OCT-1988 12:54:28 Sample Quantity .: .631.000 M3 Sample ID. : 120CT TO 190CT88 Measurement Type : ROUTINE
------------------. _--- =- _ - - - - _ . __ - - - - - - - - - - - . ---- -- --
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 9.670E-03 0.OOOE+00
- CO-58 810.76 < 8.454E-03 0.OOOE+00 FE-59 1099.22 < 2.082E-02 0.OOOE+00 CO-60 1332.49 < 3.831E-03 0.OOOE+00 ZN-65 1115.52, < 2.356E-02 0.OOOE+00 NO-95 765.79 < 1.074E-02 0.OOOE+00 2R-95 756.72 < 1.585E-02 0.OOOE+00
364.48 I-131 < 7.760E-03 0.OOOE+00 1 CS-134 604.70 < 6.618E-03 0.OOOE+00 CS-137 661.65 < 1.143E-02 0.OOOE+00 BALA-140 537.32 < 3.819E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. 1 Tritium, Alpha and Beta results are the best estimate of the . 4 activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD g gg gg__ _.gg. __
Approved by: M I- _ _____,_______ Date: _ to_ / _ g 5 / _ _ m _ _ O 1
- i l
DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIOANALYSIS LABORATORY t ,
! ) - - - - - - - - - - - - - - - - - - - - - - .------------ _ - - - - - _ _-------------------------
VAX/VMS Sample Analysis Report generated : 28-OCT-1988 12:08:07 Plant Name : CNS
, Sample Number : 1412 Type / Location : . AIR RADIDIODINES / 205 Sample Date : 26-OCT-1988 09:30:00 Acq. Start Time : 28-OCT-1988 11:36:53 Sample Quantity : 562.000 M3 Sample ID : 190CT TO 260CT88 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level 1 MN-54 834.83 < 1.427E-02 0.OOOE+00 CO-58 810.76 < 2.686E-03 0.OOOE+00 FE-59 1099.22 < 1.769E-02 0.OOOE+00 CO-60 1332.49 < 1.475E-02 0.OOOE+00 ZN-65 1115.52 < 3.157E-02 0.OOOE+00 NB-95 765.79 < 8.842E-03 0.OOOE+00
.rs ZR-95 756.72 < 2.OO1E-02 0.OOOE+00
() '~ , I-131 CS-134 364.48 604.70
< 8.079E-03 0.OOOE+00
< 5.983E-03 0.OOOE+00 CS-137- 661.65 < 1.027E-02 0.OOOE+00 BALA-140 537.32 < 3.447E-02 0.OOOE+00 K-40 1460.81 0.212 5.874E-02 Total Fraction of Reporting Level O.COOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error i s not applicable. ;
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ==---------------------
pP Analyzed by _ __ ____ __ ___ _______ __ Approved by:_ M _[_, ________,________ Date: _e_ / _za. / _.Re__ _ t
\
u
/
l ( l l l L___
7 P cs DUKE' POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
,, ---------- ------ =--------------------------- ----------- __ ____-
j( /: , VAX/VMS Sample Analysis. Report generated a 7-NOV-1988-14:17:38 1 Plant' Name : CNS
' Sample Number 1445
- Type / Location : AIR RADIDIODINES / 205 Sample Date :- 2-NOV-1988 11:22:00 Acq. Start Time 7-NOV-1988 13:46:14
- Sample Quantity : 581.000 M3 Sample ID -
260CT TO 2NOV88 Measurement Type :-ROUTINE
***** Gamma-Spectroscopy . Analysi s *****
Acti vi ty 1-Sigma MDA> Frac, of Nuclide . Energy (pCi/M3) Error. req LLD Rpt. Level
;MN-54 834.83 < 1.032E-02 0.OOOE+00 CO-58 '810.76 <'3.049E-03 0.OOOE+00 FE-59 1099.22 < 2.027E-02 0.OOOE+00
-CO-60 1332.49' < 1.547E-02 -0.OOOE+00 ZN-65 1115. 52' <'3.127E-02 0.OOOE+00 NS-95 765.79 < 1.461E-02 0.OOOE+00 2R-95 756.72' .< 2.040E-02 0.OOOE+00 I-131 364.48 '< 1.321E-02 0.OOOE+00
- f-)
(, CS-134 604.70 < 1.105E-02 0.OOOE+00 CS-137 661.65 < 1.256E-02 0 OOOE+00 BALA-140 537.32- < 3.836E-02 0.OOOE+00
BE-7 477.59 7.992E-02 4.131E K-40 1460.81 0.339 0.106 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less ' than the critical level, CL. CL = 0.5 LLD Analyzed by:___ N __' Ym _______ Approved by:___ @ f. /_ ,__ ________________ Date: _g_/_J_/_afL__ T i O- ____m_________.____._ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ . _ _ - - _ _ - - _ - - - - -
._____________m
-DUKE POWER ~ COMPANY l-APPLIED SCIENCE CENTER' RADIDANALYSIS LABORATORY-
;(~ . ----------- = - - - - - - - - - - - .------ __----------------- _=---- -
fs,/ . VAX/VMS Sample Analysis Report. generated 4: 11-NOV-1988 15:09:36
. Plant Name : 'CNS
, . Sample Number : 1461
~- Type / Loc ati on ..: AIR RADIDIODINES / 205 Sample.Date- : 9-NOV-1988 12:02:00 Acq. Start ~ Time : 11-NOV-1988 14:38:26
-Sample-Quantity : 602.OOO M3 Sample ID 2NOV'TO 9NOV8B Measurement Type : ROUTINE
----------- L_-------------- 2------ -
' ***** Gamma-Spectroscopy Anal ysi s ***** -
" Activity 1-Sigma MDA> Frac. of
-Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 <-1.169E-02 0.OOOE+00 CO-58 810.76~ < 1. 018E- 52 0 OOCE+00 FE-59 '1099.22 < 2.494E-02 0.OOOE+00 CO-60 -1332.49 < 2.134E-02 0.OOOE+00 ZN-65 1115.52 <.2.914E-02 0.OOOE+00 NB-95 765.79 '< 9.187E-03 0.OOOE+00 2R-95 756.72 < 2.829E-02 0.OOOE+00 g- I-131. -364.48 < 8.533E-03 0.OOOE+00 l l CS-134 604.70. <.1.256E-02 0.OOOE+00 CS-137 661.65 < 1.026E-02 0.OOOE+00 BALA-140 537.32 <'3.986E-02 0.OOOE+00 K-40 1460.81 0.363 8.108E-02 l
-Total Fraction of Reporting Level O.COOE+00 Gamma 'results are : listed as Less Than Levels using Tech Spec LLD e equation;- LLD = 4.66.SQRT B/t. Presence of less than sign for gamma results means no peak was found and.the zero error is not applicable..
' I Tritium, Alpha-and Beta results are the best estimate of the activity and the less than sign indicates that the n6t activity is less than the critical level,' CL. CL = 0.5 LLD 1 ! Analyzed bys___ / _ i# .,2d_________ o i Approved by: $U)de_(._ ._c_______________ Date: _ x/_ / _ _ / _ ; e _ _ _ l O
__ _ ________________ _ _ _ _ _ _ _ _ - - - - - _==_________________________. DUKE' POWER' COMPANY APPLIED. SCIENCE CENTER RADIDANALYSIS LABORATORY y 7 s.
~
\_/ ~ VAX/VMS Sample Analysis Report generated : 21-NOV-1988 13:20:55;
.I
. Plant Name : CNS Sample Number : 1483 Type / Location. : AIR RADIDIODINES /'205 Sample Date : 16-NOV-1988 10:35:OO Acq. Start Time : 21-NOV-1988 12:09:26 Sample-Quantity :. 552.000 M3.
Sample ID .
- 9NOV TO 16NOV88 Measurement Type : ROUTINE ,
________________ _==- -.____________________ ___ - - - _ _ _ - - - ________
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma. MDA> . Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level e MN-54 834.83 < 1.233E-02 0.OOOE+00 CO-58 810.76 < 1.063E-02 0.OOOE+00 FE-59 1099.22 < 6.935E-03 0.OOOE+00 CO-60 1332.49 <-1.192E-02 0.OOOE+00 ZN-65 1115.52 < 7.344E-03 0.OOOE+00 NB-95' 765.79 <11.450E-02 0.OOOE+00 ZR-95 756.72 < 1.885E-02 0.OOOE+00 (~N I-131 364.48 < 1.295E-02 0.OOOE+00
.\ CS-134 604.70 < 1.3OOE-02 0.OOOE+00 CS-137 661.65 < 1.137E-02 0.OOOE+00 BALA-140 537.32 < 1.548E-02 0.OOOE+00 K-40 1460.81' .O.332 -7.420E-02 Total Fraction of Reporting' Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equ a t i'on . LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found and'the zero error is not applicable.
Tritium, Alpha.and Beta results are the best estimate of the j L activity and the less than sign indicates .that the net activity is less than the critical level, CL. CL = 0.5 LLD _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - === _____ -________ Analyred by:__ M h t.___=_-- Approved by: __@_f Ic________;_________ Date: _1/_ / _s s: /__et__ i , 4 l (~\ -
\_) 4 1<
l i DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY s rj -_----_----_-- ------_----- - - - - _----------------- ----------- ( I- VAX/VMS Sample Analysis Report generated : 29-NOV-1988 10!36:58 t-Plant Name : CNS I Sample Number : 1507 ] Type / Location : AIR RADIOIODINES / 205 1 Sample Date : 21-NOV-1988 14:10:00 ! Acq. Start Time : 29-NOV-1988 10:05:36 Sample Quantity : 420.000 M3 Sample ID : 16NOV'TO 21NOV88
' Measurement Type : ROUTINE l
l ***** Gamma-Spectroscopy Analysis ***** l Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error ' reg LLD Rpt. Level MN-54 834.83 < . 1.612E-02 0.OOOE+00 CO-58 810.76 < 2.100E-02 0.OOCE+00 FE-59 1099.22 < 4.281E-02 0.OOOE+00 CO-60 1332.49 < 6.477E-03 0.OOOE+00 ZN-65 1115.52' < 3.616E-02 0.OOOE+00 NB-95 765.79 < 2.222E-02 'O.OOOE+00 2R-95 756.72 < 2.605E-02 0.OOOE+00 p I-131 364.48 < 1.579E-02 0.OOOE+00 (,) CS-134 604.70 <: 1.682E-02 0.OOOE+00 CS-137 661.65 < 1.737E-02 0.OOOE+00 BALA-140 537.32 < 6.640E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the' zero- error is not applicable. Tritium, Alpha and Beta results are the best estima'.s of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed bys__ _ I ___e- - Approvedby:_[{])dk[_._ _____ ___ Date: _d_/ g&_/_SS___J 4lsSy<.o's* l bh'S & $ rou&a oss'fr s'.d a f njfs ggflgs Jq
&~ Ue s-pe l 6< .e. . s!,(-
1 i
- - - - _ _ - _ _ _ _ _ - - _ _ _ _ _ _ .--_ b
DUKE POWER COMPANY-APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY (j VAX/VMS. Sample Analysis Report generated .5-DEC-1988 15:27:18 Plant Name : CNS Sample Number : 1581-Type / Location : AIR RADIDIODINES / 205 Sample Date. : 30-NOV-1988 09:48:00 Acq. Start Time : 5-DEC-1988 13:26:22 Sample Quantity : .597.000 M3 Sample ID : 23NOV TO 3ONOV8B Measurement Type : ROUTINE
- ._-------------- -----------------= _--------==- =--------
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 4.493E-03 0.OOOE+00 CO-58 810.76 < 4.656E-03 0.OOOE+00 FE-59 1099.22 < 1.301E-02 0.OOOE+00
-CO-60 1332.49. < 6.877E-03 0.OOOE+00 ZN-65 1115.52 < 1.198E-02 0.OOOE+00 NB 765.79 < 6.039E-03 0.OOOE+00 ZR-95 756.72 < 6.899E-03 0.OOOE+00 l I-131 364.48 < 4.970E-03 0.OOOE+00
,]k - .CS-134 604.70 < 3.926E-03 0.OOOE+00 CS-137- '661.65 < 4.837E-03 0.OOOE+00 BALA-140 537.32 < 1.580E-02 0.OOOE+00 K-40 1460.81 0.243 4.371E-02 Total Fraction.of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign f or gamma results means no peak was f ound and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less' than the critical level, CL, CL = 0.5 LLD
- M eum - emp ese eup - -- eam -- - ets egh Approved by:__ M _?_ m _______ Date: _ a /_ _S_/_e.A6e.__
l d(N
(-; . , e--------------- - - - - - - - - - - - - - - - - - =---------------------------------- u DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY jY . . AJ VAX/VMS-Sample Analysis Report. generated : 15-DEC-1988 14:16:18 Plant Name .: CNS Sample Number : 1621-
. Type / Location : AIR RADIOIODINES / 205 Sample Date 7-DEC-1988 10:52:00
- Acq. Start Time : 13-DEC-1988 11:47:45 Sample Quantity : 609.000 M3
-Sample ID : 3ONOV TO'7DEC88 Measurement Type : ROUTINE.
--------------- _- ===----- --------------- == - ------ ----------
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy. (pCi/M3) Error. reg LLD Rpt. Level-MN-54 834.83 ~< 1.132E-02 0.OOOE+00 CD-58 810.76 <'1.535E-02 0.OOOE+00 FE-59 1099.22 <-3.038E-02' O.OOOE+00 CO 1332.49 < 2.261E-02 0.OOOE+00 ZN-65 1115.52 < 9.837E-03 0.OOOE+00 NB-95 765.79 < 3.031E-03 0.OOOE+00
,s 2R-95: 756.72 < 1.355E-02 0.OOOE+00 ,
364.48 < 1.417E-02 0.OOOE+00
.( J I-131 CS-134 604.70 < 1.OO4E-02 0.OOOE+00 d
1 CS-137 661.65 < 1.345E-02 0.OOOE+00 BALA-140 1596.49 < 2.326E-02 0.OOOE+00 K-40 1460.81 0.278 7.815E-02 Total Fraction of Reporting Level O.OOOE+00 j Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable. , i Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
-- --------- .- _--== --------------------------
Analyzedby:___h ______________ Approved by:__ M fs_ _ ____ ______ Date: A/ g./_ m __ O
~
~~
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~l DUKE; POWER. COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY-sy s[ ====-- -------------------------- ------------------- -
jm/g E VAX/VMS Samole: Analysis: Report- generated z 20-DEC-1988; 13: 54: 44
]
1 Plant Name : CNS 3 Samole Number: 3.1642: h Type / Location : AIR RADIDIODINES / 205 l Sample Date- 14-DEC-1988'12:36:OO l Acc. Start Time : 20-DEC-1988 13:23:33 1 Sample Quantity- :1 ~663.000 M3 j
, .Samp1'e ID .
- 7DEC TO 14DEC88 -1 Measurement Type :- ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity MDA> . Frac. of
~
3 1-Sigma Nuclide :Energ'. v . (pCi/M3) Error reg LLD Rat. Level MN 834.83 <.1.392E - 0.OOOE+00
+
CO 810.76 < 9.602E-03 O.OOOE+00 FE-59 1099.22 '<.2.442E-02 0.OOOE+00 CO =1332.49 < 1.940E-02 0.OOOE+00 ZN-65 1115.52 <.1.996E-02. O.OOOE+00 NB-95' 765.79 < 9.558E-03 0.OOOE+00 ZR-95 756.72 < 2.356E-02 0.OOOE+00
>I-131 L364.48 < 1.463E-02 0.OOOE+00-
- ('
~
CS-134 604.70' < 1.013E-02 .O.OOOE+00 CS-137 661.65 '< '1.135E-02 0.OOOE+00 BALA-140 1596.49 '< 2.563E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results'are listed as Less.Than Levels using Tech-Spec LLD [ equation. LLD = 4.'66 SQRT B/t. Presence of'less than sign for gamma results means no peak:was found and the zero error is.not applicable. Tritium, Alpha and Beta results are the best estimate of the j activity. and the' less . than sign indicates that the net activity is lest than the critical level. CL. CL = 0.5'LLD Approved by:__ M f2 __;________ _ Date: _f_/_f__/_ ___
g DUKE' POWER COMPANY-APPLIED SCIENCE CENTER [ L RADI0 ANALYSIS LABORATORY j j8 s ,; l .VAX/VMS Sample Analysis Report generated : 28-DEC-1988 10:34:55 Plant Name : CNS l Sample Number : 1694 L- Type / Location : AIR RADIOIODINES / 205 Sample Date : 21-DEC-1988 11:06:00 Acq. Start Time : 28-DEC-1988 10:03:57 Sample Guantity : 608.000 M3 l Sample ID : 14DEC TO 21DEC88 i Measurement Type : ROUTINE l AAAAA Gamma-Spectroscopy Analysis AAAAA Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level
. MN-54 834.83 < 0.694E-03 0.000E+00 CO-58 810.76 < 8.120E-03 0.000E+00 EE-59 1099.22 < 2.273E-02 0.000E+00 CO-60 1332.49 < 3.979tl,-03 0.000E+00 ZN-65 1115.52 < 2.637E-02 0.000E+00 NB-95 765.79 < 7.131E-03 0.000E+00 x ZR-95 756.72 < 1.507E-02 0.000E+00 1 I-131 364.48 < 1.076E-02 0.000E+00 CS-134 604.70 < 4.972E-03 0.000E+00 CS-137 661.65 < 8.296E-03 0.000E+00 BALA-140 159G.49 < 1.970E-02 0.000E+00 K-40 1460.81 0.346 7.220E-02 Total Eraction of Reporting Level 0.000E+00 Gamma results are listed as Less Than Levels using Tech Spec LLD '
equation. LLD ='4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:__ f_________________ Approved by:_ h k ' m _________ Date: _j_/_3./9_CL___
- ______________-_______________--_________________-----= .- 1 DUKE POWER COMPANY j APPLIED SCIENCE CENTER
. /'N RADIDANALYSIS LABORATORY -
kJ ~
._ ____________-__-_-_-- -_-_---__--_--- =------------_ -------___
VAX/VMS Sample Analysis Report generated : 5-JAN-1989 15:59:20-Plant Name : CNS Sample Number : 1730 Type / Location . AIR RADIOIODINES / 205 Sample Date : 28-DEC-1988 10:26:00 Acq. Start Time : 5-JAN-1989 15:15:22 Sample. Quantity : 597.000 M3 Sample ID : 21DEC TO 28DEC88 Measurement Type : ROUTINE ______-______--____________--_________________ - _ _ = _____________- -
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of { Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 9.953E-03 0.OOOE+00 CO-58 810.76 < 1.224E-02 0.OOOE+00 FE-59 1099.22 < 2.770E-02 0.OOOE+00 CO-60 1332.49 < 1.659E-02 0.OOOE+00 ZN-65 1115.52 < 3.979E-02 0.OOOE+00 NB-95 765.79 < 9.OO3E-03 0.OOOE+00 k'_")' ZR-95 756.72 < 2.180E-02 0.OOOE+00 I-131 -364.48 < 1.530E-02 0.OOOE+00 CS-134 604.70 < 7.921E-03 0.OOOE+00 CS-137 661.65 < 1.164E-02 0.OOOE+00 BALA-140 1596.49 < 2.546E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and.the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the ! activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD __--_____________a______________________-_________________- ____ Analyzed by:_____ M h ;__ _ _ _ _ f
., Approved by:_ hb __. _ _ _ _ _ __
Date: __L / _(c_ / B'L___ I n (_)- L_________-___--
l DUKE POWER COMPANY c - APPLIED SCIENCE CENTER. ( i"ji RADIDANALYSIS LABORATORY - VAX/VMS Sample Analysis Report generated : 7-JAN-1989 15:14:32 Plant Name : CNS Sample Number : 1746 Type / Location- : AIR.RADIDIODINES / 205 Sample Date .: 4-JAN-1989 11:56:00
'Acq. Start Time : 7-JAN-1989 14:43:31
' Sample Quantity : 634.000 M3 Sample ID .: 28DEC TD-4JANB9 Measurement Type :. ROUTINE'
=
***** Gamma-Spectroscopy Analysis *****
c . Activity 1-Sigma MDA> Frac. of Nuclide Energy _ (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.128E-02 0.OOOE+00 CO-58 810.76 < 8.283E-03 0.OOOE+00 FE-59 1099.22 < 2.839E-02 0.OOOE+00 CO-60 1332.49 < 1.037E-02 0.OOOE+00
. . ZN-65 1115.52 < 1.730E-02 0.OOOE+00
'( ) 'NB-95 ZR-95 765.79 <
756.72 < 6.338E-03 1.069E-02 0.OOOE+00 0.OOOE+00 I-131 364.48.'< 8.635E-03 0.OOOE+00 CS-134 604.70 < 6.951E-03 0.OOOE+00
. CS-137 661.65 < 9.243E-03 0.OOOE+00 BALA-140 1596.49 < 5.640E-03 0.OOOE+00 K-40 1460.81 O.247 7.854E-02 Total Fraction of Reporting Level O.OOOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma l
-results means no peak was f ound and the zero error is not applicable.
' Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
------------ =_--------------------- - _ _ = - - - - - ---------
k_ _ _ _ _ Approved by:_ M _f2_ g____________ Date: __f_/_g_/_ff__
~
us i
=
Am____.___-_m-__._m_m _____m.___- -
t DUKE POWER COMPANY
^^, APPLIED SCIENCE CENTER s ,/ RADIDANALYSIS LABORATORY VAX/VMS Sample Analysis Report generated : 14-JUN-1988 14:36:06 Plant Name : CNS Sample Number : 411 Type / Location : AIR RADIOIODINES / 212 Sample Date : 6-JAN-1988 12:35:00 Acq. Start Time : 11-JAN-1988 13:07:25 Sample Guantity : 637.000 M3 Sample ID : 30DEC TO 6JAN88 Measurement Tvpe : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activitv 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rot. Level MN-54 834.83 < 1.216E-02 0.OOOE+00 CO-58 810.76 < 1.601E-02 0.OOOE+00 FE-59 1099.22 < 4.417E-02 0.OOGE+00 CO-60 1332.47 < 2.598E-02 0.OOOE+00 ZN-65 1115.52 < 3.591E-02 0.OOOE+00 () NB-95 765.78 < 1.660E-02 0.OOOE+00 2R-95 756.72 < 3.313E-02 0.OOOE+00 I-131 364.48 < 1.876E-02 0.OOOE+00 CS-134 604.66 < 1.203E-02 0.OOOE+00
- CS-137 661.65 < 1.824E-02 0.OOOE+00 BALA-140 1596.49 < 2.721E-02 0.OOGE+00 K-40 1460.75 0.410 0.113 Total Fraction of Reporting Level O.OOOE+00 g
Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results e e the best estimate of the activity and the less than sig[n indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzedbys__)h____________________.____ Approved by:__ A @ 4 ________________ Date: __4._/_st / m____ (,/
i AYO V ' w m < _, , L - (3 - - - - - - - - - - - - - - - - - - = _ - =------------------------------------------------- Sh; . , 1 DUKE POWER. COMPANY. [ ' ges >
' APPL'IED SCIENCE CENTER d av. h , RADIDANALYSIS LABORATORY l r.
- +
g at' J VAX/VMS' Sample Analysi'sf Report generated 14-JUN-1988714:362.17 le , L ^ 'I Plant L Name : CNS l' ; Sample. Number: : 440 xType/ Location :.. AIR RADIOIODINES / 212
; Sample Date- : 13-JAN-1988 12:35:00,
.Acq.. Start Time -
- 18-J AN-1988 '14: 17: 19'
"- LSample Quantity ". 385.OOO'M3 Sample ID ..
- 6JAN TO 13JAN88.
Measurement ~ Type' . ROUTINE .
***** Gamma-Spectroscopy ' Anal ysi s *****
Activity 1-Siama MDA> Frac. of'
'NuclideL Energy '(pCi/M3) Error reg LLD;Rpt. Level
-MN-54 834.83 <'3.018E-02 0.000E+00 CO-58 810.76- '< 2.065E-02 0.000E+00 FE-59 - 1 Cr99. 22 < 5.692E 0.QOOE+00 >
CO-60 1332.47' < 3.995E-02 0.000E+00
, ZN-65 1115.52. < 6.326E-02 0.QOCE+00 *
.NB '765.78 < 2.787E-02 0.000E+00
-2R ,
756.72; < 4.869E-02 0.OOOE+00 I-131" 364.48 < . 2.626E-02 0.000E+00 _CS-134 604.66 < 2.334E-02 0.OOOE+00
;CS-137- 661.65 < 2.678E-02 0.000E+00 BALA-140= 1596.49 < 6.563E-02' LO.OOOE+00 K 1460.75- 'O.770 0.197' Total' Fraction of Reporting Level O.000E+00 1 Gamma results are listed as Less Than Levels using -Tech Spec LLD F ' eauati on . ' LLD = 4.66 SORT B/t. Presence of less than sign fer gamma
. .results means no peak was f ound and the zero error i s not applicable.
Tritium, Alpha and Beta results e e the best estimate of the activity and the less than sig[n indicates that the net ' activity is less than'the critical. level, CL. CL = 0.5 LLD. Ana19 zed bp:__ M ____________________ .______ _ _ _ _ Approved by: _ M p:@3.-________ _ _ _ Date: _h./ _eE_ / te_ ___ 1 Mmmmm.wa-- _w-.____.-a_ -w,_ _ . - _ - - - . _ - ~r_~ . _ - - -
I:) o: . VAX/VMS Sample' Analysis Reportfgenerated-t' 26-JAN-1988 09:02:00 , i ?~K: LQ
~~
Pl ant' Name CNS. Sample Number.. s.453 b : Type / Location : AIR RADIDIODINES / 212 L . Sample Date: : 20-JAN-1988~14:20:00: Acq.1 Start Time : 25-JAN-1988 13:06:03.. Sampl e: Quanti ty- : 577.000 M3' 1 Sample'IDF : '13JAN TO.2OJAN88 b >
, Measurement Type : ROUTINE L ; ***** Gamma-Spectroscopy' Analysis *****
l Activity 1-Sigma MDA>J Frac. of< Nuclide . Energy: (pCi/M3) Error req LLD Rpt. Level-MN-54: 834.83 < 1.291E-02 0.OOOE+00 CO-58 810.76 < 1.375E-02 0.OOOE+00 FE-59 1099.22 '<.4.048E-02 O.OOOE+00 ' CO-60~ .1332.47- < 1.921E-02 0.OOOE+00 , . , ZN-651 1115.52 < 2.233E-02 0.OOOE+00 L NB-95, .765.78. < 1.495E-02J 0.OOOE+00 I 2R-95 756.72 < 2.708E-02 0.OOOE+00 I-131 364.48 < 1.896E-02: 0.OOOE+00 CS-134' 604.66 < 1.326E-02 0.OOOE+00 CS-137- 661.65 '< 1.478E-02 0.000$+00
'(. 'BALA-140 11596.49 <-2.141E-02 Total Fraction of' Reporting Level 0.OOOE+00
.O.OOOE+00 Analyzed by:_____ ___________
Approved by:___ M __(_' {_______________ Date: _s_/_w /__eA__ i
'l u ;
1 I
I'4 _
'VAX/VMS Sample'Analyuis Report generated : 2-FEB-1988 15:30:46
! A
,?Q
.PlantJName. : CNS 4
. Sample Number' : 486-
~"
-Type / Location s cAIR RADIDIODINES / 212 ESample Date : 27-JAN-1988-13:30:00' L Acq. Start Time- : 2-FEB-1988 14:59:45-Sample Quantity : 568.000 M3
[
' Sample ID. :-2OJAN TO 27JAN88 c
c Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
H Activity 1-Sigma 'MDA> Frac.'of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level
~ MN-54 < 1.377E-02 0.OOOE+00 1834.83 CO-58 810.76 < 1.380E-02: 0.OOCE+00 FE-59-- 1099.22 < 3.543E-02 0.000E+00 CO-60 1332.47 < 2.558E-02 0.COOE+00 ZN 1115.52 < -3.531E-02 0.OOOE+00
- NB-95 765.78 < 1.797E-02' O.OOOE+00 ZR 756.72 < 2.883E-02 0.OOOE+00
'I-131 364.48- < 1.439E-02 0.'OOOE+00 CS-134 604.66 <- 1.449E-02 0.OOOE+00.
- CS-137 661.65 < 1.893E-02 0.OOOEv00
'BALA-140 1596.49 < 2.311E-02 0.OOOE+00
= _______
Total Fraction of Reporting Level. O.OOOE+00 nalyzed by:_ ___ _m h _____ Approved bys_ M _d_ f __ __ _____ Date: _A/ _ J_ / _fS_ __ W i' A
g , {; i; ,
,4 ,
-l DUKEEPOWER' COMPANY l.3 (< APPLIED} SCIENCE' CENTER.
RADIDANALYSIS LABORATORY
}(
1.VAX/VMS~ Sample Analysis Report. generated : 14-JUN-1988 14:36:31
. . Plant'Namel CNS Sample' Number- :- 500 L/ ': Type / Location' AIR-RADIDIODINES / 212
~ Sample Date: . 3-FEB-1988 11:30:00 LAcq.KStart' Times 3: 5-FEB-1988 12:53:03 Sampl e ' Quant i.t y .: 465.000 M3
. Sample ID : 127JAN-TO 3FEB88 Measurement Type : ROUTINE i
---------------------------. ---------------- . = - - - - - = = - - _-----
-l z***** = Gamma-Spectroscopy Anal ysis - ***** ;
Activity 1-Sigma MDA> Frac. of , Nuclide -Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 . < 1.379E-02 0.OOOE+00 CO-58. . 810.76 < 1.582E-02 0.OOOE+00 FE-59 '1099.22 < 2.780E-02 O.OOOE+00 CO-60 1332.47 <-1.834E-02 0.OOOE+00
- e 2N-65 1115.52 < 4.547E-02 0.OOOE+00
- l L NS-95 765.78 < 1.352E-02' O.OOOE+00
' ' 'ZR-95' 756.72' < 3.455E-02 0.OOOE+00 I-131' 364.48 <-8.512E-03 0.OOOE+00-CS-134 .604.66 < 7.133E-03 0.OOOE+00 CS2137 661.65 < l'.644E-02 0.OOOE+00 BALA-140 1596.49 < 7.285E-03 0.OOOE+00 Total Fraction of Reporting Level .O.OOOE+00 Gamma'results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign.for gamma results means no peak was found and the zero error is not applicable. - Tritium, Alpha and Beta results are the best estimate of the activity and the less than sigh indicates that the net activity is less i than the critical level. CL. j CL = 0.5 LLD Approved-by:___i g h g ______________ Date: -_t/_[_/R____ f l
1 J( ) , 1 I
_--._=-_7_ l h w ',- b
; /
(l l; [VAX/VMS SampleiAnalysisi,ReportTgenerated : FEB-1988 10:05:13 . 7; p
;u. '-
. P1 ant'iName" :! CNS' f! $w "t
eSamp1'e Number J :H 520 -
; Type /Locati on ; : AIR RADIDIODINES / 212 Gample Date".. -
.:. : 10-FEB-1988J13:00:00 tAcq. Statt Time: :-16-FhB-1988 09:34 12-Sample l Quantity- : . 576.000 M3-LSample ID . :J.:3FEB TO 10FEB88 Measurement;TypeL . ROUTINE'
.______________________________ _____________ _-_._= _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
i
. *****I Gamma-Spectroscopy Analysis ***** . '
Activity 1-Sigma MDA>' Frac. of. Nuclide Energy. ' (pCi/M3) : Error, reg LLD-Rpt. Level MN-54 834.83 '< 1.879E-02 0.000E+00 CO 810176 <-2.009E-02 0.000E+00 FE ;1099.22 .< 4.522E-02 . 0.000E+00 e,' CD-60i :1332.47 .< 2.873E-02 -O.000E+00-ZN-6"; '1115.52< 4.497E 0.OOOE+00- .
' NB-95 = 765.78 .< 1.712E-02 .0.000E+00 f '
'2R-95 --756.72. < 2.899E O.000E+00 I-131 -364.48 < 2.407E-02 'O.000E+00:
-CS-134 604l66- < l'.698E-02 0.000E+00 ,
.> . CS-137- 661.65 < 1.901E-02 0.000E+00 '
O LBALA-140 1596.49' < 9.206E-03 'O.'000E+00-M .. .K-40 ~1460.75 O.535 O.105. Total Fraction of Reporting Level . O.000E+00 l '
- (
- Anal yz ed by:.____
n h
. Approve'd by:_ p _I_ .
Date: __g/_&_/__E5__ i d -__a_m___m._._.__.___ . . . _ _ _ _
_ _ _ _ - _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ - = = - - - _ _ _ _ _ _ _ - - - - _ - _ - - - - _ _ _ _ _ _ _ _ _ _ _ _ - - - _ - - - - VAX/VMS. Sample Analysis Report generated :-22-FEB-1988 16:13:10
/ Plant Name. : CNS Sample' Number : 537 Type / Location : AIR RADIOIODINES / 212 Sample Date : ' 17-FEB-1988 09: 25: 00 Acq. Start Time : 22-FEB-1988 15:42:08 Sample _Ouantity : 549.000 M3 Sample ID : 10FEB TO 17FEB88 Measurement Type : ROUTINE
- --_------______-= __---_-____-______--____--___---------------
***** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error req LLD Rpt. Level MN-54 834.83 < 1.067E-02 0.OOOE+00 CO-58 810.76 < 8.757E-03 0.OOOE+00 FE-59 1099.22 < 3.220E-02 0.OOOE+00 CD-60 1332.47 < 1.743E-02 0.OOOE+00 ZN-65 1115.52 < 2.331E-02 0.OOOE+00 NB-95 765.78 <,1.360E-02 0.OOOE+00 . ZR-95 756.72 < 2.084E-02 0.OOOE+00 I-131 364.48 < 1.541E-02 0.OOOE+00 CS-134 604.66 < 1.295E-02 0.OOOE+00 CS-137 661.65 < 1.443E-02 0.OOOE+00 73 BALA-140 1596.49 < 2.254E-02 0.OOOE+00
) ,
. Total Fraction of Reporting Level O.OOOE+00 Analyzed by: h*_'________________- _
Approved by:_ M _(_
- ______________ Date: __n/_g/__E8__
ws/ ! I i ~~---_x--
- .a j , ._________________________________-_-__-----=______.__.__- _ _ = _ _ - - - -
fRif i VAX/VMSLSrmp1G Analysin'Reportigsnerated : 29-FEB-1988 15:08:15 y 1 1 K 3 . Plant" Name . : CNS- [ .~ Sample Number 9 574-E O\. - Type / Location : AIR RADIDIODINEST/ 212-
- [k/- - Sample Date
'Acq.. Start Time 24-FEB-1988 11:40:00 a l
s i
- 29-FEB-1988-14:36:57 ~!
j Sample. Quantity :. 506.000 M3
- Sample ID: : 17FEB TO:24FEBB8 Measurement Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA>. Frac. c'f Nuclide Energy (pCi/M3) Error . req-LLD Rpt. Level MN-54 834.83' < 1.533E-02 0.OOOE+00 CO-58 810.76 < 1.238E-02 0.OOOE+00
. FE-59 1C99.22 < 2.490E-02 0.OOOE+00
- CO-60' 1332.47 '< 1.958E-02 0.OOOE+00
, ZN-65 1115.52 < 2.631E-02 0.OOOE+00 NB-95 765.78 < 1.544E-02 0.OOOE+00 ZR-95 756.72- < 2.181E-02 0.OOOE+00 I-131 364.48 < 1.777E-02 0.OOOE+00 CS-134 604.66 '< 1.510E-02 0.OOOE+00 CS-137 661.65 < 1.753E-02 0.OOOE+00 BALA-140 1596.49 < 2.OO3E-02 0.OOOE+00 Total Fraction of Reporting Level O.OOOE+00
- / m ,
U Anal yz ed. by: ____ _ _ _ _ _______ Approved by:__ M _[:__ _ = _ _ _ _ _ _ _ _ _ , _ _ Date: _ _3 / _ n / _,g8___ 4
VAX/VMS Simplo Analycin-Rsport gsn'gretsd :
~
9-MAR-1988 15:41:41 Plant Name- LCNS'
-Sample-Number: . : 596- ' N/h- f-Type / Location Sample Date
- AIR RADIGIODINES./-212
- - 2-MAR-1988 11:30:00
'Acq.? Start. Time 9-MAR-1988 15:10:43 Sample Quantity : 428.000 M3 Sample ID. s'24FEB TO 2 MAR 88
-Measurement. Type ROUTINE-
***** Gamma-Spectroscopy Analysis *****
Activity Sigma MDA> Frac.. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 2.358E-02 0.OOOE+00 CO-58 .810.76 < 2.796E-02 0.OOOE+00
'FE-59 1099.22 < 7.419E-02 0.OOOE+00 -
CO-60 1332.47 < 4.119E-02 0.OOOE+00 ZN-65 1115.52 < 6.400E-02 0.OOOE+00 NB-95 765.78. < 2.698E-02 0.OOOE+00
-ZR-05 756.72 < 5.824E-02 0.OOOE+00 4-131. 364.48 < 2.839E-02 0.OOOE+00 CS-134 604.66 .< 1.662E-02. O.OOOE+00 --
CS-137 -661.65 .< 2.729E-02 0.COOE+00 BALA-140 1596.49 <'4.563E-02 0.OOOE+00 K-40. -1460.75 0.693 0.169 r"% Total Fraction of Reporting Level. O.OOOE+00 d-
\
Analyzed by: _ ___ _. Approved by:___ M f _ d ______________ l Date: _ _,3. / _/z_ / _S$_ __ y-G
/
V. l l l 1__1_____________..-..____..--
'~
- + .
~
' VAX/VMS-Simplo Analycio'R port gensrctcd 15-MAR-19"B 13:06: 32 4-
, . Plant Name - : CNS.
. : '616.
Sample Number
.['-<Il .
Type / Location' s AIR RADIDIODINES / 212
. Sample Date : 9-MAR-1988 16:00:00:
, , Acq. Start Time s 15-MAR-1988'12:35:25
, ~ Sample Quantity 586.000 M3 ,
Sample-ID : 2 MAR TO 9 MAR 88 l
- Measurement Type : ROUTINE -
* **** Gamma-Spectroscopy Anal ysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) . Error req LLD Rpt. Level MN-54 834.83 < 1.216E-02 0.OOOE+00 d CO-58 810.76 < 9.318E-03 0.OOOE+00 _ FE-59 1099.22 < 2.295E-02 0.OOOE+00 CD-60 1332.47 < 1'.144E-02 0.OOOE+00
- ZN-65 1115.52 < 2.399E-02 0.OOOE+00 NB-95 765.78 < 1.614E-02 0.OOOE+00 ZR-95 756.72 < 1.984E-02 0.OOOE+00 I-131 364.48 < 1.048E-02 0.OOOE+00 .
CS-134 604.66 < 8.564E-03 0.OOOE+00 CS-137 661.65 < 1.420E-02 0.OOOE+00 BALA-140 1596.49 < 2.438E-02 0.OOOE+00 K-40 1460.75 0.302. 6.921E-02 ;
/~T ' Total Fraction of Reporting Level O.OOOE+00
.V
~
Analyzed by:_ _ _ 6 .__ _ _ _ _ _ _ Approved by:_ M f. ___________ _______ Date: _3_/_8,/_f_{___ f e'
'/
A-- ! L R l e 1
.34 VAX/VMS Sampl e Analysi s. Report ' generated -: ' 2'2-MAR-1988 " 12: 35: 56 N
j'%f Plant Name- 3:CNS Sample Number. J636; g . Type / Location. : AIR RADIOIODINE9./ 212 Sample Date- : 16-MAR-1988.11:40 OO' LAcq. Start Time 22-MAR-1988'12:04:54
- Sample Quantity : 556.000 M3 Sample ID. '9 MAR TO-16 MAR 88 Measurement Type : ROUTINE
' *** ** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma. MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level
- MN-54 '834.83 < 1.151E-02 0.OOOE+00 CO-58 810.76 < 1.887E-02 0.000E+00 FE-59 1099.22 < 2.298E-02 0.OOOE+00 CO-60 '
- 1332.47 <-2.066E-02 0.000E+00 ZN-65 1115.52 <-3.512E-02 0.OOOE+00 NB-95 765.78 < 1.860E-02 0.000E+00 2R-95. 756.72 < 2.572E-02 0.OOOE+00 I-131 364.48 < 1.756E-02 0.000E+00 C5-134- 604.66 -< 1.181E-02 0.OOOE+00 CS-137 661.65 < 1.361E-02 0.000E+00
-- p-q
. 'BALA-140 1596.49 < 2.990E-02 0.OOOE+00
) ------_---
-Total Fraction of Reporting. Level 0.000E+00 Anal yzed by _ _ ,. ___________;L______
[ Approved by:_,__ @ I [_._ ______________ Date: __p_/_Af/_gp___ I 1 OL l 1 I 1
--_M .--,--_-__m--,----------a-_-a----.-- - - - - - - -- - _ - . , - - - - - - -
y;. .. V . . . VAX/VMS. Sample Analysis Report ~ generated : 30-MAR-1988 09:16:44 c l F'lant Name- : CNS Sample-Number ': 673 oType/ Location. .-AIR RADIOIODINES / 212 Sample.Date. - 23-MAR-1988:16:03:OO Acq. Start Time .: 30-MAR-1988 08:45:44 Sample Quantity: : .615.000 M3 Sample.ID : 16 MAR TO 23 MAR 88 Measurement-Type : ROUTINE ____________-- - =________________- _ _ _ _ _ _ _ _ _ _ _ _ . ===_________________
***** Gamma-Spectroscopy Analysi s *****
' Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3)' Error req LLD.Rpt. Level
_ . MN-54 834.83 < 1.957E-02 0.OOOE+00. CO-58 810.76 < 2.061E-02 .OOOE+00 FE-59 1099.22 < 3.739E-02 .O.OOOE+00 CO-60' 1332.47 <.3.029E 0.OOOE+00 ZN-65 1115.52 < 3.885E-02. O.OOOE+00 NB-95 765.78 < 2.032E-02; O.OOOE+00
'ZR-95 '756.72 < 3.391E-02 'O.OOOE+00 I-131 364.48' '< 2.142E-02 O.OOOE+00-CS-134 ~604.66 < 1.601E-02 0.OOOE+00 CS-137 661.65 '< 1.687E-02 0.OOOE+00 '
- - BALA -140 .1596.49 .< 3.098E-02 O.OOCE+00
-( K-40 1460.75- 0.539 0.164 Total Fraction of' Reporting Level O.OOOE+00 Analyzed.bys_____ __ _ _ _ _ ____ _
____________ i t-N Approved.by: %/s J____ __ _______ Date: _ J_ / _a / __gGL__ a I J
l , d
]
.'VAX/VMS Samole Analysis Report generated : 5-APR-1988.14:05:37-W J .. - 4 P ' //~Yl' j
(_); h Plant Name 3.CNS Sample Number, : 723 1 L Tyoe/ Location. : AIR RADIOIODINES / 212. Sample _Date ,: 30-MAR-1988 12:50:00
]
.Acq.. Start
- Time
- 5-APR-1988 13:34:45 l Sample Quantity- '_ : 630.000 M3 l Sample ID Ja-23 MAR TO 30 MAR 88
' Measurement-Type': ROUTINE
_________________________--- _______________________________== l
***** Gamma-Spectroscopy Analysis *****
. Activity. .1-Sigma MDA> Frac. of !
-Nuclide Energy. (pCi/M3) Error req LLD Rpt. Level
-MN-54 834.83 < 9.570E-03 0.OOOE+00 1 CO-58 -810.76 L< 9.703E-03 0.OOCE+00 i FE-59 1099.22 < 2.840E-02 0.OOOE+00 CD-60 1332.49- < 1.130E-02 0.OOOE+00
, ZN-65 1115.52 < 2.970E-02 0.OOOE+00 ] ;
NS-95 765.79 < 1.108E-02 0.OOOE+00 ] ZR-95 756.72 < 1.611E-02 0.OOOE+00. I-131. '364.48 < 1.057E-02 0.OOCE+00 CS-134 -604.70 < 9.332E-03 0.OOOE+00 CS-137 661.'65 <~6.199E-03 0.OOOE+00 BALA-140 537.32< 4.992E-02 0.OOOE+00
'.( ). __________
1 Total Fraction of Reporting Level O.OOOE+00 Analy::ed by: _ . m_ m_% ___________ Approved bys___ d _(_ 231______________ Date: _[/__(,/_4'js___ s B l J l ($1 ] ,
V~- . VAX/VMS Semole-'Analvais Rsoort canarate'd 12-APR-1988~06:35:17' Plant'Name. : CNS 4-. c Samole Number 745-
~(f,1 Type / Location Samole Date ,
- AIR RADIOIODINES / 212>
- s. 6-APR-1988 11:55:00 Acq. Start-Time- : 8-APR-1988 13: 48: 28 Samole-Quantity :. 593.000 M3 Samole ID~ . : 30 MAR TO 6APR88' Measurement Tyoe : ROUTINE
- - - - - - - - - - - - - - - - - - - - - - - - - = _ - - - - - - - - - - - - _ = - - - - - - - - = _
***** Gamma-Spectroscopy Analvsts *****
L Activity. Frac. cd
, 1-Sigma MDA>
Nuclide' Energy- .(pCi/M3) Error ' req LLD Rot. Level MN-54 834.83~'< 1.802E-02 0.OOOE+00 CO-58 810.76 < i.431E 0.OOOE+00 - FE-59 '1099.22 < 3.748E-02 0.OOOE+00 CD-60 1332.49 < 2.248E-02 0.OOCE+00 ! [- ZN-65 1115.52 <-3.861E-02 0.OOOE+00 NB-95 '765.79 < 1.730E 0.OOOE+00 l ZR-95 756.72 < 2.939E-02 0.OOOE+00 l 0.OOOE+00 I-131 364.48 < 1.467E-02 CS 134- 604.70 < 1.461E-02 0.OOOE+00 CS-137 661.65 < 2.099E-02 0.OOCE+00 BALA-140 -537.32 < 5.715E-02~ 0.OOOE+00 Total Fraction of Recorting Level O.OOOE+00 N.- '
'Analvred by: M,,i q _ M _.;_____
Approved by:__ M _(_ __ __________ Date: _g_/.f,g_/_pe_____ O i c . k q l i i
t, .: s 1
- i .h i , .,,
'j-
.~ .. ..
"' > n ,
-y' s L
(VAX/VMS Sample' Analysis Report! generated?:R20-APR-1988.07:48:25 y--j. M.. c Piant'Name, a CNS Sampl e : -Number; 2 771-l Type / Loc ati on' J-AIR-RADIDIODINES / 212-
, Sample Dete- : 13-APR-1988 12:50:00 ,
Acq.-Start Time ' : 19-APR-1988 :15: 38: 08 LSample Ouantitv: . : ^ 568.OOO M3' ... > Sampl e -; I D J 6APR:TO-.13APR88 " ~ Measurement? Type': ROUTINE-
# F
***** . Gamma-Spectroscopy?Analvsis *****
Activity }1-Sigma MDA>L Fr ac . n ofL ,
'. Nucl i de Energy- (pCi/M3) _ Error.. reg LLD Rpt. Levelt
- y. MN-54 834.83; ' <s i.138E-02 0.' OOOE + 00 .
~
1 CO -58 : .810.76 < .1'.455E-02L O.OOCE+00
-FE-59 1099.22 n< '3.870E-02 0.OOOE+00
'CO-60: 1332.49 < :1.952E-02 0.OOOE+00
- ZN-65; 1115.52: -<'4.044E-02 0.OOOE+00 -
NB-5 5 - 765.79 .< l '. 585E-02 0.OOOEtOO ZR-951 :756.72 < 2.370E-02 0.OOOE+00
. I-131 364.484 < 1 614E-02 0.OOOE+00
-CS-134 604.70' < 1.325E-02' O.OOOE+00 J/ % CS-137 . 661.65 .< 1.216E-02 0.OOOE+00 3 ? BALA- 140 537.32 ' l< 6.OO1E-02 L i.iOOE+00
' '~
LK-40 1460.81' O.357- 8. SO6E-02 .' ' , Total ^ Fraction of ' Reporting Level- 0.OOOE+00 s i Anal vr ed ' by: _______ __
' Approved by:_3Y_ _[_,_ _ _______._-_______
8 Date: _[,,, / _y_ / _J >_ _.
.O S
f
VAX/VMS Sample Analysis Report generated : 26-APR-1988 07:48:47 Plant Name : CNS Sample Number 792 () Type / Location Sample Date
- AIR RADIDIODINES / 212
- 20-APR-1988 12:21:00 Acq. Start Time : 25-APR-1988 15:13: 55 Sample Quantity : 567.000 M3 Sample ID : 13APR TO 20APR88 Measurement Type : ROUTINE
---------------- -- -----=== =-----= - --------------- =--- -
f
***** Gamma-Spectroscopy Analysi s *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/M3) Error reg LLD Rpt. Level - MN-54 834.83 < 1.306E-02 0.OOOE+00 CO-58 810.76 < 1.467E-02 0.OOOE+00 - FE-59 1099.22 < 2.921E-02 0.OOOE+00 I CO-60 1332.49 < 1.404E-02 0.OOOE+00 ZN-65 1115.52 < 3.752E-02 0.OOOE+00 NS-95 765.79 < 1.433E-02 0.OOOE+00 ZR-95 756.72 < 2.858E-02 0.OOOE+00 I-131 364.48 < 1.760E-02 0.OOOE+00 CS-134 604.70 < 1.127E-02 0.OOOE+00 CS-137 661.65 < 1.232E-02 0.OOOE+00 BALA-140 537.32 < 4.750E-02 0.OOOE+00 K-40 1460.61 0.380 0.114 Total Fraction of Reporting Level O.OOOE+00
}
Analy::ed by:____ _ _ _ _ _ _ _ _ _ _ . _ _ _ AP proved by:__ 3 _k_b __ _ ___ Date: _ _/_z[/_n___ 7-v I O
v7T b, :y1 H
?" DUKE' POWER COMPANY
' I
./5'. . APPLIED' SCIENCE CENTER..
EU " 1 RADIDANALYSIS LABORATORY s j(]); _________________________________________________________________________gl
,' VAX/VMS Sample Analysis Reportegenerated 29-APR-1988 15:38:07 Plant;Name : CNS- l O
l ' Sample. Number
- : 819 !
Type / Location : AIR RADIGIODINES / 212
' Sample Date s.27-APR-1988 13:40:00 ;
.Acq. Start ~ Time. : 29-APR-1988 14:42:18
; Sample' Quantity : 589.000 M3
- Sample.ID' .
8120APR TO 27APR88 Measurement Type s ROUTINE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -- _____= -_________________- = __.
'***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of- U
- Nuclide Energy .
(pCi /M3)- Error reg LLD Rpt. Level
, MN 834.83 < 1.696E-02 0.OOOE+00
- CO-58 810.76 < 1.645E-02 0.OOOE+00 FE 1099.22 < 1.966E-02 0.OOOE+00 CD-60 ~1332.49 < 1.285E-02 0.OOOE+00 ZN-65 1115.52- < 3.852E-02 0.OOOE+00 NB-95 .765.79 < 1.306E-02 0.OOOE+00 ZR-95 756.72 < 2.162E-02 0.OOOE+00
[, I-131' 364.48 < 1.048E-02 0.OOOE+00 CS-134
-604.70 < 1.435E-02 0.OOOE+00-CS-137 661.65 < 1.501E-02 0.OOOE+00 BALA-140 537.32 < 3.679E O.OOOE+00 K-40 1460.81 0.251 6.697E-02 Total Fraction of Reporting Level O.OOOE+00 k Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was f ound and the zero error is not applicable.
[.' Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD
= -- _______________________________- ____________________
Analy=ed by: = ________
. Approved by:____ M f_._ __ - __
Date: _[/__/_AG___ l~
DUKE POWER. COMPANY APPLIED SCIENCE CENTER 8 RADIDANALYSIS LABORATORY ' _________________________= ___________- - _ - _ - - _ _ _ _ _ _ __ _ _ _ _ . VAX/VMS Sample Analysis Report generated : 6-MAY-1988 14:51:35 l 1 Plant Name : CNS Sample' Number : 829
-Tyoe/ Location : AIR RADIDIODINES / 212 Sample Date : 4-MAY-1988 11:15:00 -
Acq. . Start Time' : 6-MAY-1988'13:04:44 . . . Sample Quantity s' 479.000 M3 Samole ID : 27APR TO 4MAYB8 ( Measurement Tvpe : ROUTINE - I
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . - - - _-. _ _ - -____ _ ___________a__ - - - -
***** Gamena-Spectroscopy Anal ysi s *** **
Activityi 1-Sigma MDA> Frac. of I Nuclide Energy (pCi/M3) , Error reg LLD Rpt. Level- . NN-54 .834.83 < 1.049E-02 0.OOOE+00 'l CO-58
- FE-59 810.76 1099.22 1.033E-02 3.670E-02 0.OOOE+00 0.OOOE+00 l
.i CD-60 1332.49 < 1.637E-02 0.OOOE+00 ZN-65 1115.52 < 5.217E-02 0.OOOE+00 ]
~
NB-95 765.79 < 1.899E-02 0.OOOE+00 s ZR-95 756.72 < 3.038E-02 0.OOOE+00 I-131 364.48 < 1.043E-02 0.OOOE+00 - CS-134 604.70 < 1.221E-02 0.OOOE+00 ' CS-137 661.65 < 1.531E-02 0.OOOE+00 l BALA-140. 337,32- < 5.424E-02 0.OOOE+00 Total Fraction of Reportino Level O.OOOE+00 l 1 Gamma results are listed as Less Than Levels usino Tech Spec LLD ecuation. LLD = 4.66 SQRT B/t.. Presence.of'less than sign for aamma results means no peak - was f ound and the zero error i s not applicable. Tritium. Aloha and Beta results are the'best estimate of the activity -and the less than sian indicates that the net' activity is less than the critical level. CL. CL = 0.5 LLD __________________ -__ =________ - __ -- _ _ _ _ _ ese age Approved by:_ __k ______________ Date: _,,S_/_7_/__.ti__ O I
>:b .
- DUKE POWER. COMPANY.
y APPLIED SCIENCE CENTER-
*^ RADIDANALYSIS LABORATORY
.I sVAX/VMS Sample ' Analysis ' Report generated 18-MAY-1988 11:00:18 Plant'~Name : CNS Sample. Number : 856 Type / Location- : AIR RADIOIODINES / 212-eSample Date. '
3 112 MAY-19BB 14:15:00 Acq.. Start Time '17-MAY-1988 14:51:46
- Sample' Quantity . : '595.OOO-M3 Sample,ID; 4MAY TO 11MAY88 Measurement; Type : ROUTINE
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide. Energy / (pCi/M3) Error' reg LLD Rpt. Level MN-54 834.83' < 1.385E-02 0.OOOE+00 CO-58 810.76 < 1.435E-02 0.OOOE+00' H FE-59' 1099.22 < 2.795E-02 'O.OOOE+00 CO-60 1332.49 < 2.120E-02 0.OOOE+00 ZN-65 1115.52- < 3.171E-02 'O.OOOE+00
.NB-95 765.79 < 1.394E-02 0.OOOE+00 ZR-95 756.72 < 2.439E-02 0.OOGE+00 I-131' 364.48 < 1.109E-02 0.OOOE+00
) CS-134 1604.70 <.1.200E-02 0.OOOE+00 CS-137 661.65. < 1.447E-02' O.COOE+00 BALA-140 537.32 -< 5.583E-02 0.OOOE+00 K-40 1460.81 .O.233 8.883E-02 Total Fraction of' Reporting Level 0.OOOE+00
- .. . Bamma results are listed as Less Than Levels using Tech Spec LLD F equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error'is not applicable.
j- Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less
'than the critical level, CL. CL = 0.5 LLD
___________________ __ ____________________________ =______ Analyzed by:_______ g w _________ Approved by:____ M _b_ __ __ Date: _ y_ / _1f_ / __@___
'O
w-- wm u w._ - . - . a.=- - .-- - --
- r ,
s' .
' DUKE. POWER. COMPANY'
~ APPLIED l SCIENCE CENTER
'RADIDANALYSIS LABORATORY j
~
I VAX/VMS Sample Analysis Report generated a 31-MAY-1988 13:18:24 ' Plant ~Name :CNS' _ Sample-Number l' 879 . iType/ Location AIR'RADIOIODINES / 212 .
. Sample Date? : 18-MAY-1988 13:50:00
~Acq. Start Time 's 24-MAY-1988 13:19:59
'Sampl e_ -Quanti ty -
570.000 M3 Sample.ID _
'n'11MAY..TO 18MAY88 Measurement Type ROUTINE
' ***** Gamma-Spectroscopy ' Anal ysi s '*****
-Activity 1-Sigma MDA> Frac.\of Nuclide Energy. ~(pCi/M3) Error req LLD Rpt. Level MN-54 , 834.83- < 1.249E-02 0.OOOE+00 CO-58 810;76 < 1.072E-02 0.OOOE+00
.FE 1099.22 < 2.705E 0.OOOE+00
,CO-60 1332.49. '< 2.046E-02 0.OOOE+00
.ZN-65 11'15.52. <.2.244E-02 .O.OOOE+00.
NB-95. .765.79 < 1.490E-02 .O.OOOE+00'
'ZR-95 756.72 <<'2.023E-02 0 OOOE+00 I-131 364.48 <'1.382E-02 0.OOOE+00 E CS-134 604.70. < 1.118E-02 0.OOOE+00 CS-137- 661.65 < 1.432E-02 0.OOOE+00 BALA-140 537.32 < 3.843E-02 0.OOOE+00-
.K-40 1460.81 0.222 9.714E-02 Total Fraction of Reporting Level 0.OOOE+00 Gamma result's are listed as Less Than' Levels using Tech Spec LLD;
. equation. LLD = 4.66 SORT B/t. Presence of less than. sign'for. gamma results,means no peak-was found and the zero error i s not applicable. j'- Tritium, Alpha and Beta results'are;the best estimate of the
. activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by:_ k % _ nh__ ____
Approved bys g__( _ ____________m___ Date: _g_/_f;_/_Ejk__ O
w , DUKE POWER COMPANY APPLIED SCIENCE CENTER T'T RADIDANALYSIS LABORATORY L) , VAX/VMS Sample Analysis Report generated : 14-SEP-1988 12:47:43 Plant Name s' CNS Sample Number. f. 899 Type / Location s. AIR RADICIODINES / 212 Sample Date 25-MAY-1988 11:20:00 Acq. Start-Time : .1-JUN-1988 09:13:40 Sample Quantity : 534.000 M3
. Sample ID .. : 18MAY TO 25MAY88 Measurement Type : ROUTINE-
________________________-_______- _________- =_________ ______-____
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac, of Nuclide Energy- (pCi/M3) Error req LLD Rpt. Level
>MN-54 .834.83 <.2.327E-02 .O.OOOE+00 CO-58. -810.76 < 2.033E-02 0.OOOE+00 FE-59 1099.22 < 2.952E-02 0.OOOE+00 CO-60 1332.49 < 2.077E-02 0.OOOE+00 2N-65 1115.52 < 3.051E-02 0.OOOE+00
(" NB-95 765.79 <'2.042E-02 0.OOOE+00 ( . ZR-95 756.72- < 3.956E-02 0.OOOE+00 I-131 364.48 <'2.109E-02 0.OOOE+00
-CS-134 604.70 < 1.594E-02 0.OOOE+00
'CS-137 661.65 < 1.580E-02 0.OOOE+00
'BALA-140 537.32 < 7.744E-02 0.OOOE+00 K-40 1460.81 0.316 O.105 Total Fraction of Reporting Level O.OOOE+00.
Gamma results are listed as Less Than. Levels using Tech Spec LLD f equation. LLD = 4.66 SQRT B/t. Presence of less than sign for
- gamma results_means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less .than sign indicates that the' net activity is less ' than the critical level, CL. CL = 0.5 LLD _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - . --__________==. ____-__= Analyzedbys____g/A________ __________ _ Approved by ___g ,1 1 Q _ _ _ _ _ _ _________ Date: __f_/r_f_/tc____ LO
DUKE POWER' COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY
' VAX/VMS Sample Analysis Report generated : 'B-JUN-1988 11:56:14
^ Plant Name : CNS ,
Sample Number 919 Type / Location : AIR RADIDIODINES / 212 Sample Date 1-JUN-1988 11:25:00 Acq. Start ~ Time . : 8-JUN-1988 10:06: 38-Sample Quantity- : 628.000 M3 Sample ID 25MAY TO 1JUN88 Measurement. Type : ROUTINE
=____________________ ==____________-
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy- (pCi/M3) Error reg LLD Rpt. Level MN-54 834.83 < 1.177E-02 0.OOOE+00 CO-58 810.76' < 1.335E-02 0.OOOE+00 FE-59 1099.22 < 3.814E-02 O.OOOE+00 CO-60 1332.49 < 4.439E-03' 'O.OOOE+00 ZN-65 1115.52 < 2.600E-02 0.OOOE+00 NB-95 765.79 < 1.600E-02 0.OOOE+00 ZR-95 756.72 < 2.824E-O'2 ' O.OOOE+00 I-131 364.48 < 1.885E-02 0.OOCE+00 CS-134 604.70 < 1.084E-02 0.OOOE+00 4 CS-137 661.65 < 1.549E-02 0.OOO'E+00 BALA-140 537.32 < 6.605E-02 0.OOOE+00 K-40 1460.81 0.336 7.508E-02 Total Fraction of Reporting Level O.COOE+00 Gamma results are listed as Less Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma L results means no peak was f ound and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the I activity and the11ess than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD _______=- _=____________________C , ____________________________ Analy:ed by:
-Approved bys__ M _b_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date: _.(_ / _t _ /_oE____
O
L 1 l l --------- ----------------------------- --- ------ .=----------- l 1 ,.m ( ) DUKE POWER COMPANY APPLIED SCIENCE CENTER RADIDANALYSIS LABORATORY ( --------. ------ .- ----- --------------- _ ----- j 1 VAX/VMS Sample Analysis Report generated 17-JUN-1988 11:59:16 Plant Name : CNS . Sample Number 941 Type / Location : AIR RADIOIODINES / 212 ! Sample Date : 8-JUN-1988 11:45:00 l Acq. Start Time : 17-JUN-1988 10:45:34 i Gample Quantity : 586.000 M3
- 1JUN TO BJUN88 Sample ID Measurement Type : ROUTINE
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