ML20215J781
| ML20215J781 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 10/14/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | David Brown NORTH CAROLINA, STATE OF |
| References | |
| NUDOCS 8610270183 | |
| Download: ML20215J781 (31) | |
Text
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s DUKE POWER GOMPANY P.O. BOX 33180 CHARLOTTE, N.C. 28242 HALB. TUCKER. Tzt.rrnown vaca remeronwy NUCS. EAR PRODUCTRON (7M) 37NMI October 14, 1986 Mr. Dayne H. Brown, Chief Radiation Protection Section North Carolina Department of Human Resources P O Box 12200 Raleigh, NC 27605-2200
Dear Mr. Brown:
Pursuant to the provision of 10 NANC 3G section .2516'03), Duke Power Company requested State approval for disposal of sewage sludge, contaminated with very low levels of radioactivity, from the McGuire sanitary waste treatment system as non-contaminated material. See the attached letter dated June 25, 1986. The generic application proposed removal of the sludge and disposal of it in a Publicly Owned Treatment Works (POTW).
It should be noted that, if the sediment were mixed with the sewage waste water and the total activity were seen as activity of the water-mixture effluent, this could be releasable to the environment as normal effluent releases as allowed by 10 CFR Part 20, Appendix B. But due to sanitary considerations associated with the material involved, release into area water systems is not feasible; nor is it legally allowable per state regulations.
Removal of this waste (sludge) is necessary for compliance with the State of North Carolina issued National Pollutant Discharge Elimination System (NPDES) Permit. This permit is needed for continuous operation of the McGuire sanitary waste treatment (sewage) system.
When Duke Power initially requested permission in June to dispose of this sludge, the waste water treatment system at McGuire did not contain the maximum amount of sludge allowed. However, it is now quickly approaching this limit. Therefore, Duke Power requests that the State review and approve this proposal expeditiously to avoid the possibility of interrupted operation of the McGuire Nuclear Station due to the loss of its waste treatment system.
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Page 2 October 14, 1986 Should you need further information, please contact Mary Birch at (704) 373-4504 or Changfuh Lan at (704) 373-5691.
Sincerely, R
I 1 B. Tucker JHS/pja.037 Attachments cc: Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II, 101 Marietta Street, NW Suite 2900 Atlanta, GA 30323 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station Mr. H. .R.__Denton Office ~of Muclehr Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 M. L. Birch J. W. Foster C. F. Lan N. A. Rutherford J. H. Schulte R. P. Michael R. T. Simril L. Lewis
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DUKE POWER GOMPANY P.O. Box 33189 CHAMLOTTE. N.C. 28242 HALH. TUCKER TELEFNONE vics ... ant (704) 373-4531 prUCLEAR P.ODUCTION June 25, 1986 Mr. Dayne H. Brown, Chief Radiation Protection Section North Carolina Dept. of Human Resources P O Box 12200 Raleigh, NC 27605-2200
Dear Mr. Brown:
Duke Power Company requests State approval for disposal of sewage sludge, contaminated at very low levels of radioactivity, from the McGuire sanitary waste treatment system as non-contaminated material. The attached generic application (Attachment 1) proposes removal of the sludge and disposal of it in a Publicly Owned Treatment Works (POTW).
Also attached is data on the first application of the generic disposal proposal. It should be noted that the small amount of radioactivity was found only in cells 3 and 4 of the water treatment system. A composite sample taken across the entire lagoon showed no activity. As shown in Attachment 2 the ~
estimated doses are well below the limits calculated in the generic application.
Duke Power Company requests that this application be considered part of the requested license, submitted to you on December 19, 1985. This is one of three very slightly contaminated waste .
streams that we are asking to be allowed to dispose of under the requested license. The three potential waste streams and means of disposal are summarized below:
WASTE STREAM DISPOSAL METHOD Landfarming
- 1) Water Treatment Sludge Landfarming
- 2) Contaminated Soil POTW
- 3) Sewage Sludge If approved under the State license, each time Duke Power Company plans to dispose of one of these slightly contaminated waste The streams a detailed radiological analysis will be performed.
results of this analysis will be' compared to the license dose limits to ensure compliance before disposal. Copies of all analyses and assessments will be sent to the State to keep you informed of our activities.
1 . Pago 2 June 25, 1986 Should you need further information for this application, please contact Mary Birch at (704) 373-4504 or Changfuh Lan at (704) 373-5691.
, Sincerely, 4
4 8 __
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Hal B. Tucker i JHS/pja.014 Attachments i
- cc
- Dr. J. Nelson Grace, Regional Administrator
, U. S. Nuclear Regulatory Commission
! Region II, 101 Marietta Street, NW, Suite 2900 Atlanta, GA 30323 4
Mr. W. T. Orders NRC Resident Inspector j McGuire Nuclear Station Mr. H. R. Denton
, Office of Nuclear Reactor Regulation
! U. S. Nuclear Regulatory Commission l Washington, DC 20555 -
1 i M. L. Birch J. W. Foster l C. E , N. A. Rutherford 4
J."H ".Lan Schulte R. P. Michael R. T. Simril L. Lewis
)
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Attachment 1 a
McGuire Nuclear Station Application for the Approval to Dispose 1
of Very Low-Level Radioactive Waste ,
1.0 Pu rpose
/
Pursuant to 10CFR 20 6 20.302 and 10CFR Part 150 Duke Power Company requests State approval of the proposed method of disposal of sewage sludge contaminated with very low-levels of radioactivity from the sanitary waste treatment system as non-radioactive material. Approval of the proposed method is requested for use during each year of the remaining plant life. The volume of waste being generated per year is projected to be 4,000 cubic feet. The frequency of sewage sludge removal is projected to be no more than once per year.
! 2.0 Description of Waste Source The McGuire Sewage Treatment Aeration Basin (lagoon) treats sewage through biological digestion, followed by disinfection in a chlorination chamber.
This system is designed under normal biological and hydraulic loading conditions to treat raw sewage such that the effluent from the system will meet the pollutant limits specified in the station's National Pollution Discharge Elimination System (NPDES) perait. Maintenance of the NPDES permit is required for the continuous operation of the station Sanitary Waste Treatment System.
Part of the Sewage Treatment Aeration Basin design requires periodic removal of sludge. Sludge buildup reduces retention, and therefore, sewage treatment time. This makes the basin more susceptible to effluent compliance problems with changes in biological and hydraulic loading.
The McGuire sanitary waste stream collects flow from three main sources: the j turbine and auxiliary buildings; the service building and the CMD area. These flows are gravity fed into the areated lagoon. This lagoon is a rectangular shaped basin with three operating depths: 5 feet (28,000 gal / day), 6 feet (40,000 gal / day), and 8 feet (57,000 gal / day). The lagoon is lined with a flexible synthetic material including a ventilation and underdrain system.
Leak detection is provided by inspection of a capped underdrain pipe.
The lagoon is divided into four cells by bioseparation curtains. These curtains have 12 inch by 12 inch openings in alternating ends of the curtains to. allow flow from one cell to the next. The lagoon has 9 floating aerators, four in cell 1, two in cell 2, two in cell 3, and one in cell 4. Cell I has a volume of 102,255 gallons and a retention time of two days at the normal operating level. Cells 2 and 3 have a volume of 56,520 gallons et h and a design retention time of one day. Cell 4 also has a retention time of one day and a volume of 45,735 gallons.
The effluent travels through a chjorine contact chamber to the Wastewater Collection Basin before final discharga to the Catawba River. Sludge, which builds up in all cells, must be removed periodically to maintain proper settling and retention of the wastewater. The volume of waste being generated per year is projected to be 4,000 cubic feet. Presently there is
approximately 4,000 cubic feet of sewage sludge that needs disposal from the McGuire Sanitary Waste System.
3.0 Health and Safety Concern The McGuire Sewage Treatment Aeration Basin (lagoon) system was installed in l March 1983. Sludge was removed in mid-1984 while the system was out of service for the installation of new aerators. Radioactivity was not present in the sludge during this removal. Analysis of the sludge that is currently in the system found activity present only in cells 3 and 4. A composite sample taken across the entire lagoon showed no activity.
Currently, the effluent from the Aerated Basin is in compliance with the National Pollutant Discharge Elimination System (NPDES) permit limitations, but pollutant levels cannot be considered stable. Adverse weather conditions, unusual biological growth, or heavy system demands could cause hydraulic or biological overloads of the sewage treatment system resulting in exceeding NPDES permit limitations. IF this permit governing the system for the McGuire Nuclear Station is not maintained, operation of the station sanitary waste treatment system could be suspended. Without the availability of this system, per OSHA Regulation 29 CFT 1910.141(c)(1)(i) Table J1, occupancy of the McGuire N2 clear Station could be prohibited.
4.0 Sam 1p ing and Counting Methods Composite sample (s) will be taken from each cell with a Kemmerer sampler (below surface sampler) and placed directly into a marinelli, taped and then sent to the Station Health Physics Count P.oom or Duke's Applied Science Center Environ- .
mental Laboratory for radiological analysis.
The counting equipment is a Nuclear Data 6600 Multichannel Analyzer with Geli detectors. The sample will be counted for 100 minutes. The radioactivity concentrations of the sludge will be determined and compared to the, proposed maximum permissible concentration levels (See Appendix I). When there is more than one isotope, the limit for the combination of isotopes will be derived using the sum of the ratios of the quantity present in the combination and the limit for each specific
, isotope. The sum of these ratios for all the isotopes in the combination may not be grater than "1" (i.e., " unity").
5.0 Proposed Disposal Method The sewage sludge to be removed will be pumped by vendor to a tanker truck which transports the sludge to a local Publicly Owned Treatment Works (POTW).
A GM survey instrument will be used during the pumping process to ensure that there is no hot spot in the sludge to be disposed of. The background radiation level in the general areas has been measured to be less than 0.02 mr/hr.
Fees and permits are generally handled by the vendor as part of the contract.
Generally sludge from POTWs is eventually landspread, although other disposal methods, such as incineration, are available.
5.1 Possible Disposal Methods by POTW Sludge, which will be pumped by a contracted vendor, will be transported by that vendor to a POTW (Publicly Owned Treatment Works) where it is to be added to the POTW treatment system as raw sewage (non-contaminated). Once the sludge is pumped into the vendor's transporting vehicle, Duke loses control of the material. Although the contract will require the vendor to dispose of the material in compliance with applicable environmental regulations, we have
, no means to assure that the vendor will dispose of the sludge properly. That is, it could potentially be illegally dumped, or accidentally spilled. Of course, the environmental and public health effects due to the biological activity and infectious constituents of such waste would far outweigh the concern due to radioactivity, which is detailed in Section C.
Properly disposed of material at the POTW would be introduced as raw sewage or as sludge, either to an anaerobic digester or directly to another aerated lagoon. In either case, it will be significantly diluted (typical dilution factors range from 100 to over 1000) and will recieve extended biological treatment. The sludge that the POTW obtained from McGuire will remain in the treatment basin or digester for as short as a few days to as long as several
- years.
Once this diluted, dispersed sludge is removed from the POTW it would be dried, and then placed and covered in a sanitary landfill. Use of the land upon which the material was landfilled would probably not be restricted.
There is the possibility that the land could become recreational, farming, housing, commercial, or industrial land. If requested, the diluted sludge is available from the POTW to area farmers to use as fertilizer for crops. .
l 5.2 Monitoring of Sludge " Hot Spots" A thin window GM survey instrument is the preferred monitoring method to be used during the pumping process to ensure that there are no hot spots in the sludge to be disposed of in the proposed manner. A sodium iodide detector could be used if it is felt that more sensitive analysis monitoring is needed. If activity is detected that is above the area background radiation level, the " hot" sludge will be transferred into 55 gallons drums to be disposed of as contaminated material.
6.0 Evaluation of Environmental Impact There will be no impact on topography, geology, meteorology, hydrology, and nearby facilities by the proposed method of disposal.
7.0 Evaluation of Radiological Impact 7.1 Analysis Study It has been determined that none of the area POTWs incinerate their sludge.
Therefore, since only area POTWs are being utilized, acquired dosage by means of incineration, inhalation, is not a potential source of activity.
Ways of receiving possible activity from the sludge include:
- 1. exposure to container storing diluted (100 to 1000 times) sludge material; i
- 2. ingestion dosage due to consumption of vegetation grown in diluted sludge fertilized soil and the activity (external dosage) received while periodically tending to this vegetation growth;
- 3. external dosage received while remaining in the center of an area where the diluted sludge material was spread, either covered with soil or left uncovered.
7.2 Annual Dose Rate Estimation Assuming the worst. case, an analysis was performed using the maximum yearly amount of undiluted sludge, with the maximum allowable concentrations for each isotope, spread on the ground to a depth of six inches without any soil covering. If there is a mixture of more than one radionuclide, then the concentrations shall be limited so that the sum of of the ratios between the quantity present in the specific radionuclide may not exceed "1" (i.e.,
" unity"). From this, the annual dose for the total body for a person occupying the area 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per year is calculated to be always less than 1 mrem.
This is equal to a dose rate of 1.0E-03 mrem / hour which is below the dose rate due to the background radiation of the general area measured at 2.0E-2 mrem / hour. The results of this analysis can be found in Appendix II. It should be noted that adjustments for realistic factors, such as dilution and actual occupation time in the critical location of the landspread/ landfill, would greatly decrease the analyzed dosage.
A second analysis was performed to estimate the dose to an individual from ingestion of food. The maximum radionuclide concentrations were again used and/or the ratio rules applied. The annual total body dose is calculated to always be less than 0.5 mrem. The total highest dose to any organ is calculated to always be less than 1 mrem. The calculation results can be found in Appendix III.
The estimated doses are a very small fraction of one year's exposure to natural background radiation (about 100 millirems for the State of North Carolina) 8.0 Evaluation of Overall Benefits This sludge (4,000 ft 3), if packaged and disposed of as radioactive waste, will cost approximately $300,000 without solidification, and will cost more than $460,000 if solidification is required depending on radioactive waste packaging and waste form requirements. The actual burial space will be more than 4,800 ft3 in a licensed radioactive. waste burial site. Considering the generation rate of this type of waste (4,000 f t3 per year), the total cost saving could range from $300,000 to $460,000 per year and save burial site space,of 4,800 cubic feet per year.
Appendices (I) Maximum Permissible Concentration for McGuire Sanitary Sludge (II) Estimated External Doses 4
(III) Estimated Internal Doses
APPENDIX I
. Maximum Permissible Concentration for McGuire Sanitary Sewage Sludge Radionuclide Concentration (pCi/cc)
Na-24 3.92E-01 Cr-51 4.54E+01 Mn-54 1.67E+00 Fe-59 1.24E+00 Co-58 1.41E+00 Co-60 5.00E-01 Zn-65 4.96E-01 Zr-95 1.99E+00 Zr-97 1.80E+00 Nb-95 1.96E+00 Ag-110m 5.52E-01 I-131 3.12E+00 I-133 2.63E+00 Cs-134 5.25E-01 Cs-137 1.19E+00 La-140 6.60E-01 Ce-141 1.80E+01 Ce-144 3.10E+01 NOTE: In any case where there is a mixture of more than one radionuclide, then the concentrations shall be limited so that the sum of the ratios between the quantity present in the mixture and the limit established above for the specific radionuclide may not exceed "1" (i.e., " unity").
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1 APPENDIX II ESTIMATED DOSES TO AN INDIVIDUAL FROM STANDING ABOVE THE UNC0VERED DRIED SLUDGE BOTTOMS
- Average Average External d
Nuclide Concentra- Surface Dose Dose Annual Dose e
tion pCi/cc Deposition Factor Rate mrem pCi/m 2 mrem /hr mrem /hr x Per pCi/m 2 Na-24 3.92E-01 3.92E+04- 2.50E-08 9.80E-04 9.80E-01 Cr-51 4.54E+01 4.54E+06 2.20E-10 9.99E-04 9.99E-01 Mn-54 1.67E+00 1.56E+05 5.80E-09 9.69E-04 9.69E-01 Fe-59 1.24E+00 1.24E+05 8.00E-09 9.92E-04 9.92E-01 Co-58 1.41E+00 1.41E+05 7.00E-09 9.87E-04 9.87E-01 Co-60 5.00E-01 5.00E+04 1.70E-08 8.50E-04 8.50E-01 Zn-65 4.96E-01 4.96E+04 4.00E-09 1.98E-04 1.98E-01 Zr-95 1.99E+00 1.99E+05 5.00E-09 9.95E-04 9.95E-01 Zr-97 1.80E+00 1.80E+05 5.50E-09 9.90E-04 9.90E-01 Nb-95 1.96E+00 1.96E+05 5.10E-09 9.99E-04 -9.99E-01 Ag-110m 5.52E-01 5.52E+04 1.80E-08 9.93E-04 9.93E-01 I-131 3.12E+00 3.12E+05 2.80E-09 8.73E-04 8.73E-01 I-133 2.63E+00 2.63E+05 3.70E-09 9.73E-04 9.73E-01 r Cs-134 5.25E-01 5.25E+04 1.20E-08 6.30E-04 6.30E-01 4
Cs-137 1.19E+00 1.19E+05 4.20E-09 4~.99E-04 4.99E-01 La-140 6.60E-01 6.60E+04 1.50E-08 9.90E-04 9.90E-01 Cc-141 1.80E+01 1.80E+06 5.50E-10 9.90E-04 9.90E-01 Cc-144 3.10E+01 3.10E+06 3.20E-10 9.92E-04 9.92E-01
" Exposure of workers from inhalation of radionuclides is estimated to be minimal due to the proposed soil covering.
b 4
The average surface deposition was estimated by assuming that all of the l activities in the top 10 cm of sludge were deposited on the surface, and that
- the average concentrations of radionuclides in the dried sludge were the same-as the measured concentrations (wet weight). These two assumptions tend to counterbalance each other.
c Does' factors were taken from Regulatory Guide 1.109, Rev. 1, pp. 41-42.
d In estimating the annual dose the following conservative assumptions have been made: (1) an exposure of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> / year; (2) no dilution of sludge j from other sources; and (3) no soil covering.
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APPENDIX III ESTIMATED DOSES TO AN INDIVIDUAL FROM INGESTION OF FOOD Element Average Ingestfon Average Transfer Concentra- Dose Annual Dose
- Nuclide Concentra- Data" tion pCi/ Factor, mrem pCi/cc Veg/ Soil Kg - Veg. mrem per PCI Na-24 3.92E-01 5.2E-02 2.04E+01 1.70E-06 2.00E-02 Cr-51 4.54E+01 2.5E-04 1.13E+01 2.66E-09 1.75E-05 Mn-54 1.67E+00 2.9E-02 4.85E+01 8.72E-07 2.45E-02 Fe-59 1.24E+00 6.6E-04 8.18E-01 3.91E-06 1.85E-03 Co-58 1.41E+00 9.4E-03 1.32E+01 1.67E-06 1.28E-02 Co-60 5.00E-01 9.4E-03 4.70E+00 4.72E-06 1.29E-02 Zn-65 4.96E-01 4.0E-01 1.98E+02 6.96E-06 8.01E-01 Zr-95 1.99E+00 4.0E-01 '7.96E+02 6.60E-09 3.05E-03 Zr-97 1.80E+00 1.7E-04 3.06E-01 1.55E-10 2.75E-08 Nb-95 1.96E+00 9.4E-03 1.84E+01 1.86E-09 1.98E-05 Ag-110m 5.52E-01 1.5E-01 8.28E+01 S.79E-08 4.22E-03 I-131 3.12E+00 2.0E-02 6.24E-01 3.41E-06 1.23E-01 I-133 2.63E+00 2.0E-02 5.26E+01 7.53E-07 2.30E-02 Cs-134 5.25E-01 1.0E-02 5.25E+00 1.21E-04 3.68E-01 Cs-137 1.19E+00 1.0E-02 1.19E+01 7.14E-05 4.93E-01 La-140 6.60E-01 2.5E-03 1.65E+00 3.33E-10 3.18E-07 Ce-141 1.80E+01 2.5E-03 4.50E+01 1.18E-10 3.08E-06 .
Ce-144 3.10E+01 2.5E-03 7.75E+01 2.62E-08 1.18E-03' Based on the transfer factors in Table E-1, p. 37 of Regulatory Guide 1.109, Rev. 1, and assuming no soil covering.
Based on an adult ingesting 580 Kg of fruits, vegetables and grain, and using the dose conversion factors in Regulatory Guide 1.109, Rev. 1, pp. 56, 57. Doses from ingesting milk or meat would be less than the doses from ingesting fruits, vegetables and grain.
Attachment 2 Page 1 of 20 1
ESTIMATED DOSES TO AN INDIVIDUAL FROM INGESTION OF FOOD Element Average ANNUAL DOSE mrem Average Concentra-Nuclide Concentra- Trans{er Data tion pCi/ Total Highest Dose tion pCi/cc Veg/ Soil Kg - Veg. Body to Any Organ MN-54 1.77E-02 2.9E-02 5.13E-01 4.97E-04 4.49E-03 CO-58 4.10E-02 9.4E-03 3.85E-01 3.73E-04 3.37E-03 CO-60 1.04E-01 9.4E-03 9.78E-01 2.68E-03 2.28E-02
" Based on the transfer factors in Table E-1, p. 37 of Regulatory Guide 1.109, Rev. 1, and assuming no soil covering.
b Based on an adult ingesting 580 Kg of fruits, vegetables and grain, and using the dose conversion factors in Regulatory Guide 1.109, Rev. 1, pp. 56, 57. Doses from ingesting milk or meat would be less than the doses from ingesting fruits, vegatables and grain.
Attachment 2 Page 2 of 20 ESTIMATED DOSES TO AN INDIVIDUAL FROM STANDING ABOVE THE UNCOVERED DRIED SLUDGE BOTTOMS" Average Average External d Nuclide Concentra- Surface b Dose Dose Annual Dose Factor c Rate mrem tion pCi/cc Deposit {on pCi/m mrem /hr mrem /hr Per2 pCi/m MN-54 1.77E-02 1.77E+03 5.80E-09 1.03E-05 1.03E-02 CO-58 4.10E-02 4.10E+03 7.00E-09 2.87E-05 2.87E-02 CO-60 1.04E-01 1.04E+04 1.70E-08 1.77E-04 1.77E-01 TOTAL 2.16E-01
^ Exposure of workers from inhalation of radionuclides is estimated to be minimal due to the proposed soil covering.
b The average surface deposition was estimated by assuming that all of the activities in the top 10 cm of sludge were deposited on the surface, and.
that the average concentrations of radionuclides in the dried sludge were the same as the measured concentrations (wet weight). These two assump-tions tend to counterbalance each other.
c Dose factors were taken from Regulatory Guide 1.109, Rev. 1, pp. 41-42.
d In estimating the annual dose the following conservative assumptions have been made: (1) an exposure of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> / year; (2) no dilution by slidge from other sources; and (3) no soil covering.
Attachment 2 Page 3 of 20 Summary of'MNS WT Lagoon Sludge Results All of the samples were taken by dragging a sampling device across the bottom of the lagoon. The samples were then transferred to a 3500 mi marinelli for counting. The results from the spectrums are summarized below.
Date Cell Nuclide uCi/ unit 5/28 4 Mn-54 1.77 x 10[8 Co-58 4.35 x 10_7 Co-60 1.10 x 10 5/28 4 Co-58 4.62 x 10"_8 Co-60 1.78 x 10
-8 5/28 4 Co-60 3.52 x 10 5/29 ** 4 Co-58 3.32 x 10_8 Co-60 1.23 x 10 6/2 1 ---- --------------
6/2 2 ---- --------------
-8 6/2 3 Co-60 7.16 x 10 6/6 1,2,3,4 ---- --------------
(composite)
- Recount of 5/28 sample showing Co-58 and Co-60 The composite sample (6/6) combined samples from cells 1,2,3, and 4 mixed in a 3500 ml marinelli.
1 If additional sampling is required, please contact R.E. Baker at 373-3819.
Attachment 2 Page 4 of 20 SAMPLE RESULTS
- 06-JUN-86 13:44:48 *****************
WT LAGOON COMPOSITE
/ '
SAMPLE DATE: 06-JUN-86 11:00:00 SAMPLE IDENTIFICATION: 86-14020/
TYPE OF SAMPLE: C/LI'O # /
SAMPLE QUANTITY: 3500.000 UNITS: ML SAMPLE GEOMETRY: MARINELLI[f EFFICIENCY FILE NAME: AEFF.A3500M,j , +
ACQUIRE DATE: 06-JUN-86 13:34:36 FWHM(1332) 2.037 PRESET TIME (LIVE): 600. SEC f* SENSITIVITY: 3.500 ELAPSED REAL TIME: 600. SEC/
- SHAPE PARAMETER : 15.0 % '
ELAPSED LIVE TIME: 600. SEC
- NBR ITERATIONS: 10.
DETECTOR: A-GERM 25-P-280B
- LIBRARY:NUCL. MASTER
/ /
CALIB DATE: 02-JUN-86 04p43:00
- ENERGY TOLERANCE: 1.500KV KEV /CHNL: 0.5006975
- HALF LIFE RATIO: 8.00 OFFSET: 0.0507097 KEV
- ABUNDANCE LIMIT: 80.00% -
G. COEFF. : -1.818E-07 KEV /C**2
- o*************************************************************
% DEAD TIME = 0.00 %
- REVIEWED BY:
o********************************************* ** * * ****
., ENERGY WINDOW 50.12 TO 03 .87 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC -% ERR ' FIT 1 0 124.55 11. 42. 1.99 248.68 244 13 1.85E-02 88.1 2 0 138.24 7. 52. 8.37 276.02 271 23 1.12E-02 ****
3 0 220.82 4. 29. 0.77 441.00 436 13 6.19E-03 ****
4 0 238.68 8. 70. 0.67 476.68 471 35 1.39E-02 ****
5 0 353.01 23. 5. 7.30 705.11 696 21 3.88E-02 24.9 6 0 609.41 8. 8. 1.09 1217.57 1209 16 1.35E-02 60.5 PEAK SEARCH COMPLETED (REV 11)
Page 5 of 20 NUCLIDE IDENTIFICATION SYSTEM (REV 5/80)
NUCLIDE LINE ACTIVITY REPORT PAGE 1 FISSION GAS NUCLIDE SBHR 11 ENERGY AREA BMGND %ABN %EFF UCI / UNIT XE-135 FG Ei 249.79 0. O. 89.90* 0.000E-01 0.000E O 608.19~ 0. 0t
- 8. 8. 2.90 5.568E-01 7.929E -7 4. 7' NATURAL PRODUCT NUCLIDE SBHR ENERGY 1i AREA BKGND %ABN %EFF UCI / UNIT PB-214 NP EF 295.21 0. O. 17.50. 0.000E-01 351.92 0.000E O 0. 0C
- 23. 5. 37.20* 8.464E-01 5.895E -6 BI-214' NP 609.31 1. 47
- 8. 8. 46.30 5.568E-01 1120.29 1.048E -5 6. 32
- 0. O. 15.10* 0.000E-01 0.000E O 0. 0C 1764.49 0. O. 15.80 0.000E-01 0.000E O 0.' OC e
e F
G
Page 6 of 20 NUCLIDE IDENTIFICATION SYSTEM (REV 5/80)
UNKNOWN LINE REPORT PAGE 2
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PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC Y. ERR %El 0 M 11. 42. 1.99 248.68 244 13 1.85E-02 g 1.43E 2 0 M 7. 52. 8.37 276.02 271 23 1.12E-02 4 .45E 1 3 0 E.30tH2 4. 29. O.77 441.00 436 13 6.19E-03 4 1.19E
,8 .
Q0 M8 70. O.67 476.68 471 35 1.39E-02 - 1.13E LINES NOT MEETING
SUMMARY
CRITERIA NONE -
6 e
D
Page 7 of 20
- 02-JUN-86 19:08:57 *****************
1 WT CELL 3 (RECOUNT)
SAMPLE DATE: 02-JUN-86 15:30:00 SAMPLE IDENTIFICATION: 86-13419 k\
TYPE OF SAMPLE: C/LIO SAMPLE QUANTITY: 3500.000 . UNITS: ML SAMPLE GEOMETRY: MARINELLI EFFICIENCY FILE NAME: BEFF.B3500M,,
ACQUIRE DATE: 02-JUN-86 18:58:46
- FWHM(1332) 2.217 PRESET TIME (LIVE): 600. SEC
- SENSITIVITY: 3.500 ELAPSED REAL TIME: 600. SEC
- SHAPE PARAMETER : 15.0 %
ELAPSED LIVE TIME: 600. SEC
- NBR ITERATIONS: 10.
DETECTOR: B GERM 24P1160B
- LIBRARY:NUCL. MASTER CALIB DATE: 02-JUN-86 17:43:08
- ENERGY TOLERANCE: 1.500KV KEV /CHNL: 0.5007359
- HALF LIFE RATIO: 8.00 OFFSET: -0.0283382 KEV
- ABUNDANCE LIMIT: 80.00%
Q. COEFF. : -1.870E-07 KEV /C**2 *
% DEAD TIME = 0.00'h
- REVIEWED BY:
- ...*.*.*..***....**..*.*..***..***.****.*****.*...*..*..**** 2039.86 ENERGY WINDOW 50.04 TO PK IT ENERGY , AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC 1 0 64.24 10. 36. 0.93 128.36 121 11 1.61E-0E 2 0 75.28 14. 66. 0.91 150.41 147 12 2.33E-0E 3 0 198.27 13. 16. 1.52 396.06 393 7 2.21E-0E 4 0 274.28 6. 45. 3.32 547.93 545 20 1.07E-0E l
5 0 312.58 19. 12. 9.43 624.44 615 23 3.20E-02 6 0 1173.20 18. O. 1.89 2345.06 2340 22 3.00E-02 7 0 1332.71 25. O. 2.71 2664.20 2658 14 4.17E-02 PEAK SEARCH COMPLETED (REV 11) l
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Page 8 of 20 NUCLIDE IDENTIFICATION SYSTEM (REV 5/80)
SUMMARY
OF NUCLIDE ACTIVITY pAGE 3 TOTAL LINES IN SPECTRUM 7 LINES NOT LISTED IN LIBRARY 4 IDENTIFIED IN
SUMMARY
REPORT 2 28.57%
ACTIVATION PRODUCT
' 1-SIGMA NUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR % ERR CO-60 AP 5.27Y 1.000 7.155E -8 1.431E -8 20.00 i.
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- 02-JUN-86 18:24:08 *****
- +++* ***********
WT LAGOON CELL #2 -
SAMPLE DATE: 02-JUN-86 15:15:00 SAMPLE IDENTIFICATION: 86-13417 Oh(
g TYPE OF SAMPLE: C LIO SAMPLE QUANTITY: 3500.000 UNITS: ML SAMPLE GEOMETRY: MARINELL7 EFFICIENCY FILE NAME: CEFF.C3500M ACCUIRE DATE: 02-JUN-86 18:13:57
- FWHM(1332) 1.940 PRESET TIME (LIVE): 600. SEC
- SENSITIVITY:
ELAPSED REAL TIME: 3.250 600. SEC
- SHAPE PARAMETER : 15.0 %
ELAPSED LIVE TIME: 600. SEC
- NBR ITERATIONS: 10.
DETECTOR: C GERM 24-P-1301
- LIBRARY:NUCL. MASTER CALIB DATE: 26-MAY-86 17:44:14 KEV /CHNL:
- ENERGY TOLERANCE: 1.500KV 0.4999270
- HALF LIFE RATIO: 8.00 OFFSET: 0.0775047 KEV
- 0. COEFF. :
- ABUNDANCE LIMIT: 80.00%
2.354E-08 KEV /C**2
- l
% DEAD TIME = 0.00 %
- REVIEWED
- BY: *** Ad. ***
ENERGY WINDOW 25.07 TO *7+ #4 9 025.17 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR 1 0 148.70' e 7. 29. 2.50 2 0 201.80 6. 21.
297.29 287 29 1.17E-02 ****
1.49 403.50 396 12 1.06E-02 ****
3 0 223.72 7. 5. 0.80 447.34 4
445 7 1.12E-02 61.8 0 281.54 3. 7.
5 0.71 563.00 558 10 5.54E-03 ****
0 349.54 5. O. 0.62 699.00 695 8 8.33E-03 44.7 PEAK SEARCH COMPLETED (REV 11) i
, m.
Page 10 of 20 NUCLIDE IDENTIFICATION SYSTEM (REV 5/80)
UNKNOWN LINE REPORT pAGE 2 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR %EFF 1 0 148.70 7. 29. 2.50 2 0 201.80 6. 21. 1.49 297.29 287 29 1.17E-02 **** 1.23E OC 403.50 396 12 1.06E-02 **** 1.11E OC h 3 0 223.72 7. 5. O.80 447.34 445 7 1. LEE-02 61.8 1. 05E OC 4 0 281.54 3. 7. 0.71 563.00 5 0 349.54 5. O.
558 10 5.54E-03 ***+ 9.03E-01 0.62 699.00 695 8 8.33E-03 44.7 7.70E-01 LINES NOT MEETING
SUMMARY
CRITERIA NONE 1
O 1
I
. . . . '. Page 11 of 20 oo************************************************************
oo*************** 02-JUN-86 18:46:06 *****************
oo************************************************************
WT LAGOON CELL #1 -
- SAMPLE DATE: 02-JUN-86 15:00:00 S{)
SAMPLE IDENTIFICATION: 86-13416 \(
TYPE OF SAMPLE: C LIG SAMPLE GUANTITY: 3500.000 UNITS: ML SAMPLE GEOMETRY: MARINELLI EFFICIENCY FILE NAME: CEFF.C3500M,,
co************************************************************
ACCUIRE DATE: 02-JUN-86 18:35:53
- FWHM(1332) 1.940 PRESET TIME (LIVE): 600. SEC
- SENSITIVITY: 3.250 ELAPSED REAL TIME: 600. SEC
- SHAPE PARAMETER : 15.0 %
ELAPSED LIVE TIME: 600. SEC
- NBR ITERATIONS: 10.
oo*****************************************************s******
DETECTOR: C GERM 24-P-1301
- LIBRARY:NUCL. MASTER CALIB DATE: 26-MAY-86 17:44:14
- ENERGY TOLERANCE: 1.500KV KEV /CHNL: 0.4999270
- HALF LIFE RATIO: 8.00 OFFSET: 0.0775047 KEV
- ABUNDANCE LIMIT: 80.00%
- 0. COEFF. : 2.354E-08 KEV /C**2
- oo************************************************************
% DEAD TIME = 0.00 %
- REVIEWED BY:
a.*..***.*...**.*.......**......*.........**. ..***Aw*...
ENERGY WINDOW 25.07 TO 202$.17 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1 0 123.56 *
- 4. 16. 1.22 247.00 243 9 7.08E-03 ****
PEAK SEARCH COMPLETED (REV 11)
^
0
, , , , Page 12 of 20 NUCLIDE IDENTIFICATION SYSTEM (REV 5/8e)
UNKNOWN LINE REPORT PAGE 2 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR %EFF
@ t' ,
e 102.5: -
- 4. 1s. i. ee e47.00 e43 s 7.e8E-e2 **.* 1.etE ee
~
LINES NOT MEETING
SUMMARY
CRITERIA NONE .
i
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4v7,*y+-w-~w--+-s--.- ----~--.--,=---r--,wy%-----e. --,-m,-~
.' Page 13 of 20 us+,.......++.+...+.....++++++++++..+..........................
.++...++......... 29-NcY-26 [1:1a:29 ... .............
....... ....++.......+.+..+ .+++...++. ..+.......+.......+....
W7 OL'JCGE (CELL 4) RECCUNT / 86-1 / 900EFE s' s EAF:LE OATE: 28-MAY-86 12:10:00 34M !.E IDENTIFICATION: SG-12628
TV?E CF SAMPLE: C/LIO ' - -
SAF' ELE CUANTITY: 3500.000 ' UNITS: NL GAMPLE GECMETRY: MARINELLI EF?!CIENCY FILE NAME: D E F F . D 3 5..0 0 MI9 -
4++++++++++++++.+++++++++++++++++++++++++++++++.4++++++++.+++.
+
ACQUIFE DATE: 29-MAY-86 11:04: 17 + FWHM(1332) 1.890 ~~
DRESET TIME (LIVE): 600. SEC + SEN5ITIVITY: 3.250 ~~
ELAP5ED REAL TIME: 600. SEC + SHAPE PARAMETER : 15.0 4 ELAPSED LIVE TIME: 600. SEC' + NBR ITERATION 5: 10.
~
++..++++++++++++++++++++++###+++..... ......... 4+...... ..+.4
+
DETECTOP: D-GEFM 23-P-67WB + LIBRARY:NUCL. MASTER '~~ ~~
CALIB DATE: 26-MAY-86 17:57:37 + ENERGY TOLERANCE: 1.500MV KEV /CHNL: G.4998840 ' + HALF LIFE RATIO: 8.00 - -
OFFSET: 0.1570974 MEV + ABUNDANCE LIMIT: 80.00%
Q. COEFF. : 2.399E-08 KEV /C++2 +
+
+e+. .<<++...+++++++++++++++++++++++++++++++++++++++++++++++++
/
. CEAD TIME = 0. 0 0 . + REVIEWED BY: (C
+. .......++....+++++++++++++++++++++++++++++++++ ++.,+++. .
ENERGY WINDOW 25.15 TO 2025.08 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 4 193.93 19. 1.34 355.62 381 2
1 4 195. 76 17.
5.
3.
33 3.16E-02 29.0 1 G2E c 1.17 391.20 381 23 2.85E-02 20.6
, 2 u 198.13 13. 4. 1.29 396.13 381 32 2.20E-02 24.5 i - 4 200.59 13. 3. 1.25 400.96 291 23 2.17E-02 24.3 5 A 242.85 9. 1. 0.73 485.49 482 4
29 1.50E-02 27.1 1.42E c 6 148.11 5. 5. 0.73 496.00 482 29 7.95E-03 77.8 7 0 274.60 5.
0
- 5. 0.77 549.00 546 7 8.75E-03 75.6 3 278.10 4. 11. 1.18 556.00 552 7 5.83E-03 +++.
?. 0 389.58 3. 15. 0.80 779.00 772 15 5.00E-03 **++
10 0 811.53 11. O. 1.25 1623.00 1617 13 1.83E-02 20.2
!! 0 1172.54 37. O. 1. 74 2347.05 2240 15 6.17E-02 16. 4 12 0 1222.0- 28. 0. 1.62 2666.04 2659 16 4.67E-02 18. 9 PEAK SEARCH CONrLETED (REV 11)
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Page 14 of 20
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3UMr14 C'. OF NUCLI:E aC7I'v IT , ;; 32 3 TOTAL ' Ii4E5 IN SPECTRUM 12 LINEi NC7 ISTED IN LIBRARY d IDEttTICIED IN
SUMMARY
REPCRT 2 25. 00 c.
~
'O TI'/ATICN PPCDUCT ,
f 1 - 3 !.3 M 4 -
NUCLIDE 55HR HLIFE DECAV UCI / UNIT ERCOP '.E F R CG-58 AP 70.80D 1.004 3.21GE -8 1.001E -8 30.15 C0-50 AP 5.27Y 1.000 1.222E -7 2.221E -8 la. 90
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................+ 29-r.tAY-66 10: 45:01 ' .................
..++-. ..++.+....++ ......+...++++.+ .............. ...........
AT GLUDGE (CELL 4)'
CAMPLE DATE: 28-MAY-86 16:00:00' 21.M .T_2 IDENTIFICATION: SEM .2 2 242699 '
TYPE CF CAMPLE: C/ SLUDGE" 5 AMPLE OLcN ITY: 3500.000 - UNITS: ML '
SA'*S'_E GECMETRY: MAFINELLI '
EFc!TIENCY FILE NAME: DEFF.D3500M,,'
..++.4++.++.+++++++++++++++++++++++++++++++++.+++.+.....+..+..
ACQUIRE DATE: 29-MAY-86 10:25: 44 '+.FWHM(1222) 1.890 '
PRESET TIME (LIVE): 600. SEC ,e SENSITIVITY: 2.250 ELAPSED REAL TIME: 600. SEC
- SHAPE PARAMETER : 15.0 %
ELAPSED LIVE TIME: 600. SEC
- NBR ITERATIONS: 10. .
.>.+.+++++.+.4+s.+<+.+..+.+.,+.+++++++++.++.. ++++..++.....+++
+
DETECTOR: D-GERM 23-P-67WB + LIBRARY:NUCL. MASTER -
CALIB DATE: 26-MA(-86 17:57:37
- ENERGY TOLEFANCE: 1.500KV VEV/CHNL: 0.4998840 -
- HALF LIFE RATIO: 8.00 -
CFFSET: 0.1570974 KEV + ABUNDANCE LIMIT: 80.00%
- 0. COEFF. : 2.399E-08 KEV /C++2 *
+
++, +.++++.+.+++++++.++++..++++++++++++++++++++++++++++++++++.
. DEAD TIME = 0.00 % . REVIEWED BY:
.................++.+++++++++++++++++++++++++++y.++. ..+ ++ ..
ENEPGY WINDOW 25.15 TO 2025.C 3.- :T ENERGY AREA EKGND FWHM CHANNEL LEFT PW CTS /SEC %ERP FIT 1 4 72.26 ! !, 4 0.77 144.45 142 12 1.87E-02 29.5 5.87E-e 1 4 75.10 11. 5. 0.61 149.92 142 12 1.S?E-02 40.5 2 0 E5. 6- 4 30. 1.18 171.00 166 10 6.56E-03 ++.+
. 0 143.59 20. 16. 2.22 296.91 292 9 2.26E-02 25.6 i 5 0 154.12 5. 27. 0.73 208.00 205 9 8.32E-02 ...+
c.
~
0 194 12 6. 33. 1.26 268.00 264 12 9.66E-02 +++.
0 1222.02 5. 4. 0.63 2666.00 2658 16 7.89E-03 75.4 PEAK SEARCH COMPLETED (REV 11) i e
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. Page 16 of 20 '
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NuCLICE IDENTIFICATION SYSTEM (PEV 5 /00:
UNKNOWN LINE REPORT cc u_
- - 3 PK IT ENERGY AREA BKGND FWHM CHANNEL LE:~7 cW CTS /SEC 4 ERR .Ere i 1 4 d 11. 4 144. <-5 142 12 1.37E-02 29.5 7.02q-e
! O 4 11. 5. 61 149.92 la2 12 't.e7E-02 M 7.a9E-c;
' 0 4.
g4 0
- 64 30. 1. l e 171.00 166 10 6.5GE-03 M .:.1-E-0*.
- 20. 16. 2.32 286.91 292 9 3.3GE-02 25 l! g[6 0M 6. 22. 1.26 266.00 364 12 9.60E-02 M. 1.31E 1.24EOC01 4
LINES NOT MEETING
SUMMARY
CRITERIA I NONE a.
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...,+..+.....++..+ +++++++++++++++++......+...+...............
............+++++
ES-MAY-86 19:10:13 ............... .
...,++... . .++++++++++++++++++++++.....+.....................
WT LAGCCN CELL 4 SLUDGE
.N 3AMcLE DATE: 28-MAY-86 16:00:00 3AMcLE IDENTIFICATION: 86-12699 7792 OF 3 AMPLE: C/LIO SAMPLE CUANTITY: 2500.000 -
UNITS: ML 5AMGLE GEOMETRY: MARINELLI EFCICIENCY FILE NAME: DEFF.D2500M,,
- ++++++++++++++++++++*******+++++++++++++++++++..+........++..
ACQUIRE DATE: 28-MAY-86 18:58:11
- FWHM(1222) 1.890 PRESET TIME (LIVE): 600. SEC
- SENSITIVITY: 2.250 ELAPSED REAL TIME: 600. SEC
- SHAPE PARAMETER : 1 5 . 0 */.
ELADSED LIVE TIME: 600. SEC + NBR ITERATIONS: 10.
- ~
....+.. ..+++ ...+++...+++++.+ . 4++.....+..+++++...++.......
DETECTOR: D-GERM 23-P-67WB + LIBRARY:NUCL. MASTER CALIB DATE: 26-MAY-86 17:57:27
- ENERGY TOLERANCE: 1.500KV KEV /CHNL: 0.4998840
- HALF LIFE RATIO: 8.00 .
OFFSET: 0.1570974 KEV
- ADUNDANCE LIMIT: 80.00%
- 0. COEFF. : 2.299E-08 KEV /C++2 +
t...++.++++++,+++++++++++++++++++++++.+++++++++++ +++++++++++++
% DEAD TIME = 0.00 % + REVIEWED BY: #
.....++....+++++.+++++++++++++++..++++++++++++++++++++++++++++
ENERGY WINDOW 25.15 TO 2025.08 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR F 1 0 84.14 4. 90. 1.25 168.00 164 20 7.21E-03 ++++
2 0 138.90 8. 11. 1.27 277.56 275 7 1.23E-02 67.2 2 0 1173.56 12. O. 1.25 2347.03 2237 16 2.17E-02 27.7 0 1323.27 8. O. 1.22 26E6.50 2662 11 1.22E-02 25.4 PEAK SEARCH COMPLETED (REV 11)
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Page 18 of 20 w -
WCr_IDE IDENTITICATIGN 5/5 TEM (CEV Tf-20'-
5JmMARY OF NUCLIDE ACT**/ITY ::C-E 2 TOTAL LINES IN SPECTRUM e
-.*>ES NOT LISTED IN LIBRARY 2 ICENTIFIED IN
SUMMARY
REPORT 2 50.00? _
ACTIVATIGN PRCDUCT 1-5IGMA NUCLIDE 594R HLIFE DECAY UCI / UNIT ERROR Y.E R T-CO-60 AP 5.27Y 1.000 3.524E -3 1.246E -9 25.36 o
9 P -
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Page 19 of 20
,.>.+9,+++ ,+++++++++++++++++++++++++++++++++++++++++++++++++++
.#.#.+[*+++++**++* 28-MAY-86 10:54: 58 +++++++++++++++++
- .*****.++++++++***++++++4*+++++++++++++.++++++++.++...+++.+
WT SLUDGE 44h eeN SAMPLE DATE: 28-MAY-86 09:30:00 SAMPLE IDENTIFICATION: 86-12608 TYPE OF SAMPLE: C/ LIQ SAMPLE QUANTITY: 3500.000 UNITS: ML SAMPLE GEOMETRY: MARINELLI EFFICIENCY FILE NAME: AEFF.A3500M,,
- +*****++**********+++++**********************+****
ACQUIRE DATE: 28-MAY-86 10:44:49
- FWHM(1332) 1.960 PRESET TIME (LIVE): 600. SEC
- SENSITIVITY: 3.500 ELAPSED REAL TIME: 600. SEC
- SHAPE PARAMETER : 15.0 %
ELAPSED LIVE TIME: 600. SEC
- NBR ITERATIONS: 10.
- ++****4+++++*****************************************++++++++
DETECTOR: A-GERM 25-P-28GB
- LIBRARY:NUCL. MASTER CALIB DATE: 26-MAY-86 17:51: 43
- ENERGY TOLERANCE: 1.500KV KEV /CHNL: 0.5005845
- HALF LIFE RATIO: 8.00 OFFSET: 0.0180236 KEV
- ABUNDANCE LIMIT: 80.00% ,
O. COEFF. : -1.625E-07 KEV /C**2 *
+++++++#4++**+++++++++****************************************
% DEAD TIME = 0.00 %
- REVIEWED BY: *
- * **+++ ***
ENERGY WINDOW 50.07 TO 2039.70 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR , FIT 1 0 185.35 11. 52. 1.31 370.28 368 23 1.89E-02 94.6
_ 2 0 238.49 13. 45. 1.19 476.46 473 30 2.21E-02 76.6 3 0 557.81 6. 40, 4.90 1114.68.1104 40 9.25E-03 ++++
- 0 608.67 12. 3. 1.88 1216.36 1213 11 2.05E-02 34.4 Co-Si5 0 810. 74 -- --- 15. _ 0. - 0.80 -1620.40 1616 11 2.50E-02 25.8
,6 0 835.54 - 6. T.-' 1.63~~1670.00 1666 - 9 1.00E-02 40.8 U"' 7 0 1173.39 - 24 O. - 1. 84 --2345. 79 2336 -18 4. 00E-02 20. 4 e 0 1332.73 26. O. 0.69 2664.62 2657 15 4.33E-02 19.6 PEAK SEARCH COMPLETED (REV 11) m.
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NUCLIDE IDErJTICICATION SYSTEM (REV L 80)
SUMMARY
CF NUCLIDE ACTIVITY PAGE 3 TOTAL LINES IN SPECTRUM 9 LINES NOT LISTED IN LIBRARY 3 IDENTIFIED IN
SUMMARY
REPORT 3 33.33".
54CTIVATION PRODUCT 1-SIGMA NUCLIDE SBHR HLIFE DECAY UCI / UNIT ERROR YERR CO-58 AP 70.80D 1.000 4.619E -8 1.72EE -8 37.38 CO-60 AP 5.27Y 1.000 1.778E -7 2.744E -8 15.43 e
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