ML20154M309
| ML20154M309 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 02/19/1986 |
| From: | Barr K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 26522, NUDOCS 8603140034 | |
| Download: ML20154M309 (1) | |
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Sp at UNITE 3 STATES ,) ^h
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'o NUCLEAR REGULATORY COMMISSION y REGION ll ' ,
y j 101 MARIETTA STREET.N.W.
- ATLANTA. GEORGI A 30323
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g MEMORANDUM FOR: W. T. Crow, Acting. Chief ,
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Uranium Fuel Licensing Branch p Division of Fuel, Cycle and DocKETto q i Material Safety . _i . c usuc ~ ,
A Office of Nuclear' Materials > 2- C Safety and Safeguards C i FEB 2 71986 p . ,
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,, FROM: Kenneth P. Barr, Chief m Nuclear Materials Safety and D Cf" # '<
- FE8 2 71988 >
J4 ~ Safeguards Branch 't' Division of Radiation Safety 4 : g, -
d.s.huettmtww cc n n:a and Safeguards -
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SUBJECT:
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-RESULTS OF CONFIRMATORY RADIOLOGICAL SURVEY OF THE
.- 'Y l BABCOCK & WILC0X, LYNCHBURG RESEARCH CENTER (LRC), BUILDING C, PHASE I LYNCHBURG, VIRGINIA, DOCKET 70-824 Your memorandum of August 1, 1985, requested that we conduct a confirmatory
, radiological survey of the Phase I area of Building C at LRC and to transmit to l you the results of our survey and our recommendations.
On October 9-11 and November 18-21, 1985, Region II conducted the requested
,- closecut inspection ^ nd confirmatory survey. The results of that inspection are
- documented in Inspection Report No. 70-824/85-08, which is enclosed. As
- discussed in the inspection report, Region Il cannot at this time support LRC's request that Phase I of Building C be approved for release for unrestricted use.
We also understand that LRC is continuing with their decommissioning efforts on Phases II and III of Building C and that you have before you a request from them
! for an NRC Confirmatory Survey of Phase II of Building C. Since the concerns identified during the Phase I inspection also apply to the remaining phases, we feel that any further requests of Region II to perform confirmatory surveys should be deferred until NMSS has resolved with -the licensee the concerns identified during our initial closecut inspection. If NMSS concludes that Building C cannot'be released for unrestricted use, we do not believe it would be necessary or useful for Region II to conduct any further confirmatory surveys.
l As noted in the enclosed report, the samples obtained during the closeout
. inspection have been sent to RESL in Idaho for analysis. We will report those results to you when they become available.
J l Kenneth P. Barr
Enclosure:
Inspection Report No. 70-824/85-08 9603140034 e60219
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- ATLANTA.GEoMGI A 30323 f- g Babcock and Wilcox Company FEB .131986 ATTN: Dr. T. C. Engelder, Director Lynchburg Research Center Research and Development Division P. O. Box 11165 Lynchburg, VA 24506-11165 Gentlemen:
SUBJECT:
REPORT NO. 70-824/85-08 On October 9-11 and November 18-21, 1985, NRC inspected activities associated with your May 28, 1985 request to the Uranium Fuel Licensing Branch, Office of Nuclear Material Safety and Safeguards, that the NRC perform a confirmatory survey so that Phase I of your Butiding C may be released for unrestricted use.
At the conclusion of the inspection, the findings were discussed with those members of your staff identified in the enclosed inspection report.
Areas examined during the inspection are identified in the report. Within these areas, the in spectiori consisted of selective examinations of procedures and representative:raco.rds, interviews with personnel and performance of confirmatory
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( Within the scope of the inspection, no violations or deviations were identified.
Please note that the enclosed report details several specific open issues relating to your request that the Phase I area of Building C be released for unrestricted use. These issues include the location and continued use of your facility gaseous effluent stack, the scope of your release surveys and the background radiation levels in Building C due to other licensed activities. These issues
- will be reviewed with our Office of Nuclear Materials Safety and Safeguards, who will communicate directly with you.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," Part 2 Title 10, Code of Federal Regulation, a copy of this letter and the enclosures will be placed in the NRC's Public Document Room.
Should you have any question concerning this letter, please contact us.
Sincerely, J. hilip Stohr Director Division of Radiation Safety and Safeguards
Enclosure:
( Inspection Report No. 70-824/85-08
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e p ric UNIT ED STATES
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/, C EIlON 11 g .,j 101 MARIETT A STRE ET, N.W.
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, AT LANT A. GEORGI A 30323
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FEB 131996 Report No.: 70-824/85-08 Licensee: Babcock and Wilcox Company Lynchburg Research Center Lynchburg, VA 24505 Docket No.: 70-824 License No.: SNM 778 Facility Name: Lynchburg Research Center Inspection Condu ted: October 9-11 and November 18-21, 1985 Inspectors: k'd ft I!I R. E. $eddington f Date Signed
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B.JK. Revsin Da'te '51gned
/W.dB. hGloersenJ 0> r L ~ vzyss (Tate ' Signed Ado l Wad >* //,29 d S. S. Adamovitz v (Tate Sfgned Accompanying Personnel: W. E. Cline Approved by: M M C. M. Hosey', Section Ch' ef
//Nh Date Signed Di si n f Rad n iety and Safeguards
- x 9i. E.'Ilir4; TectTon Chief
/ pr f6 Date Signed Division of Radiation Safety and Safeguards SUMS.ARY Scope: This special, announced inspection entailed 143 inspector-hours onsite in the area of closeout inspection and confirmatory survey of the decommissioning of Building C, Phase I.
Results: No violations or deviations were identified.
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REPORT DETAILS
- 1. Persons Contacted Licensee Employees "R. Bennett, Manager, Safety and Licensing A. F. Olsen, Senior License Administrator
- G. Hoovier, Manager, Decommissioning
- H. Beasley, Chemist J. Hammonds, Decommissioning Foreman
' Attended exit interview
- 2. Exit Interview The inspection scope and findings were summarized on November 20-21, 1985, with those persons indicated in Paragraph 1. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
,- 3. Phase I, Building C Decommissioning (83890)
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- a. Background The licensee discontinued research and development activities with radioactive materials in Building C of their Lynchburg Research Center facility in 1982. Since no further use of radioactive material was planned for the building, the licensee formulated a decommissioning plan so that the building could be released for unrestricted use.
- b. Facility Description Building C is a single story building of concrete block construction with outside dimensions of 225 feet by 174 feet at its greatest width.
The building contains 24,000 square feet of laboratory, of fice and support space (Appendix A). The building decommissioning project was divided into three phases, with phase I consisting of the laboratories on the western end of the building and comprising approximately 10,000 square feet. Phase I includes laboratories 25, 26, 27, 43, 44, 50, 51, 52, 53 and 54. Also included are the offices and hallway along the front of the building that was once part of the Labs 43, 44, and 50, the western portion of Hallway 23, Old Central Stores area, and the basement and pit under Lab 50. The interior walls, ceilings and floors as well as the underlying soil were included in Phase I; however, the exterior walls and roof were not.
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- c. History of Operations in Phase I l
The first experiments performed in the original building were bench-scale experiments converting thorium nitrate to thorium oxide. An expansion in 1964 added pilot scale equipment for preparation of thorium-U233 nuclear fuel. Thorium fuel research and development was i
conducted in Laboratories 43, 44, 50, 53 and 54 and existing offices l
that used to be part of those laboratories. Research and development with plutonium-bearing fuels was initiated in new laboratories added in 1965. Uranium fuel projects involving work with uranium nitrate and uranium fluoride solutions and uranium fluoride, uranium chloride, and
! uranium oxide powders were initiated in Laboratories 27, 43, 44, 50, 53 and 54 at the conclusion of the plutonium work. Samples of beta gamma
. materials were occasionally analyzed in Laboratory 27 and sealed i containers of beta gamma contaminated materials from reactor sites were stored in the rear of Old Central Stores.
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- d. Communications l By letter dated March 28, 1983, the licensee forwarded for information purposes to the Uranium Fuel Licensing Branch, Nuclear Material Safety
- and Safeguards (NMSS) their plan for accomplishing the decommissioning of Building C. The plan included a discussion of how the facility i
- would be decontaminated, the surveys that would be performed and the release criteria for the facility.
By letter dated May 28, 1985, the licensee forwarded to the Uranium Fuel Licensing Branch, NMSS the final survey report for Phase 1 of Building C and requested that the NRC perform a confirmatory survey so that Phase I could be released for unrestricted use. The report also contained a more detailed statement of the release criteria that had been applied (Appendix B).
- 4. Closeout Inspection and Confirmatory Survey
- a. Procedures The inspectors reviewed selected portions of the following procedures:
LRC-TP-162, Calibration and Operating Procedures for NMC PC-5 Proportional Counter, February 28, 1984 LRC-TP-51, Calibration Procedure for PAC-4G, Gas Proportional Counter, June 13, 1984 LRC-TP-183, Revision 5, survey of Decontaminated Laboratory and Offices in Building C for Fixed and $mearable Contamination, November 13, 1985
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LRC-TP-197, Building C/A Soil Sampling Procedure, Rev. 5 June 17, 1985 LRC-TP-206, Decontamination Project Drum Sampling Procedure, Rev. 4, June 4, 1985 LRC-TP-207, Building C/A Core Sampling Procedure, Rev. 4, June 17, 1985 LRC-TP-208, Preparation of Soil Samples, Rev. 6, March 1, 1985 LRC-TP-210, Analysis of Radionuclides in Soil by Gamma Ray Spectroscopy, Rev. 4, February 6, 1985 LRC-TP-219, Efficiency Calibration for Gamma-Ray Spectroscopy System, Rev. O, February 28, 1984 LRC-TP-220, Gamma-Ray Spectrometry System-Count Reproducibility l
Control Chart, Rev. O, February 28, 1984 LRC-TP-221, Gamma-Ray Spectrometry System - Energy Calibration and
' ~ Periodic Checks of Activity and Energy Calibration, Rev. 1,
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July 29, 1985 LRC-TP-222, Gamma-Ray Spectrometry System-Background Checks, Rev. O, February 10, 1984 LRC-TP-223, Counting Procedure for Gamma Spectrometry Measurements of Health Physics Samples, Rev.1, July 1,1985 LRC-TP-267, Preparation of Soil Standards, Rev. O, February 25, 1985 LRC-1P-275, Analysis of Selected Radionuclides in Paint Chips by Gamma-Ray Spectroscopy, Rev.1, July 24,1985 The inspector verified that the procedures were consistent with the regulations, accepted industry practice and the licensee's decommissioning plan of March 28, 198S
- b. Records, Reports, Audits (1) The inspector reviewed licensee initial and final release survey records for fixed and loose alpha and beta gamma radioactivity in Phase I of Building C. The inspector determined that the records adequately documented the surveys performed and that the data in the records were consistent with the survey result summaries presented in the licensee's final survey report of March 28, 1985.
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l L (2) The inspectors reviewed several records, reports, and audits of Building C decontamination activities and a listing of those reviews are provided below:
(a) Audits i
- 1) Audit of Soil and Scrap Assay Procedures for Decommissioning Building C at the Lynchburg Research Center, Ronald A. Harlan and Associates, September 14, 1983.
- 2) Nuclear Data Audit Report, 0702C/0036C, Rev. O, September 19, 1983.
- 3) Audit of Final Report for Decontamination and Decommissioning of Phase 1 - Building C, Lynchburg Research Center, Source Technologies, letter dated l January 21, 1985, from Wahlig to Roberts.
! (b) Reports
( Comparison between Analyses of " Fines" and " Oversize,"
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October 31, 1983.
l-l 2) Memo from G. S. Hoovier (LRC) to R. L. Bennett (LRC),
Repacking and Recounting of Building C Soil Samples to Determine Packaging Variability, November 16, 1983.
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Statistical Analyses of Building C Soil Sample Measurements, December 6, 1983.
Estimation of Pu-239 from Am-241 in Building C Soil Samples, June 21, 1964.
- 5) Memo from H. L. Beazley (LRC) to N. Soltys (LRC), Site Background Soil Samples, December 3, 1984.
Americium-241 and Plutonium-241 Sum of Fractions, April 18, 1985. ,
l Evaluation of Pu-241/Am-241 Activities, May 14, 1985.
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! (. Pu-241/Am-241 Ratio, June 21, 1985.
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Comparison of Results from Samples Analyzed by Gamma Spectroscopy and Radiochemical Methods, October 30, 1985.
Estimates of Uncertainty for Soil Analyses, October 31, 1985.
(c) Records
- 1) Gamma Ray Analysis Results for Contaminated Drums #52-1962, PDPD 226-245, PDPD 485-504, and Core Background Samples.
- 2) Route Sheets for Building C Drum Samples - PDPD 1-150, PDPD 901-1200, PDPD 301-450.
- 3) Count Reproducibility Control Charts and Records, September 10, 1985 - November 19, 1985, for ORTEC Detectors 1, 2, and 3.
- 4) Efficiency Calibrations for ORTEC Detectors 1, 2, and 3 for the Following Geometries:
I liter marinelli - March 1, 1984
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- 11. petri dish - August 9, 1985 1
- 5) Gamma Source Calibration Certificates for the Following Geometries:
- 1. 1.0 liter solid (polymer) in 130G GA-mA Beaker - July 1, 1985
- 11. 1.0 liter soil (1516 grams) in 130G GA-mA Beaker - July 1, 1985
- c. Direct Survey Direct alpha and beta gamma radiation surveys were performed by the inspectors in a total of 259 grids in Phase I of Building C. Since the licensee had removed a significant amount of floor area to perform the excavations and some walls and ceilings had been torn down, the 259 grids surveyed represented approximately 10% of the remaining original grids. Contact measurements for alpha radiation were performed in three to nine random locations in each grid. All readings were less than the minimum detectable level for the instrument of approximately Approximately 50% of each grid was scanned for l 170 dpm/100 cm2 beta gamma radioactivity. All readings were less than 5000 dpm/200 ca r ; however, some areas could not be surveyed due to the background radiation levels. The location of the grids surveyed and results are shown in Appendix C.
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- d. Smear Survey Smear surveys were obtained by the inspectors from 32 locations in the Phase I area. The location of the surveys and results are shown in Appendix D. The smears were counted at the Region II office for gross alpha and beta radioactivity on a alpha-beta proportional counter and for gamma on an intrinsic germanium gamma spectroscopy system.
The only smear above the minimum detectable level for alpha contamination was on smear number 15 from the inside of a pipe penetrating the south wall of Lab 44 in grid 1292T which showed an activity of 1612 dpm. Since the surface area smeared was less than 100 cm2, this result indicates that the contamination levels in the pipe are in excess of the release criteria given in Appendix B. Gamma scan analysis of the smears identified only naturally occurring radioactive potassium (K-40).
- e. Gamma Radiation Survey Gamma radiation surveys were performed by the inspector in each labora-tory and office and around the outside of Building C in the phase I
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area. Measurements were made at each location at floor level, three feet above the floor and six feet above the floor. The survey results
'- are shown in Appendix E. A summary of the range of dose rates and the resulting exposure based on continuous occupancy for a year (8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />) and continuous occupancy during 50 work weeks of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> each (2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />) is shown in Appendix F. It was determined that the radiation levels observed were attributable to sources outside of Building C (i.e., radioactive waste storage in and around Building J and the hot cells in Building B).
- f. Special Samples The inspectors collected fifteen special samples as described in Appendix G. These samples included paint and concrete samples from several areas, wipes f rom inside ventilation ducts and samples of sludge from a sump in the pit under Lab 50. The samples were forwarded to a NRC contractor for analysis.
- 5. Soil Excavation (Trench) Sampling and Analysis During this phase of the inspection, the inspectors independently collected fourteen composited soil samples from the evacuated areas of Building C.
All fourteen samples were split with the licensee. The number of samples in each composite ranged from five to seven samples. Composite sample weights for each composite sample ranged from 500 to 800 grams. For each excavation location sampled, the sub-samples were composited, pulverized to some degree by field methods and mixed. The sample was then coned and subdivided into
( four equal sections. Samples were then taken from each section and placed into labeled containers. Details and descriptions of each composite sample can be found in Appendix H. Guidance on sample collection activities f
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including the number of soil samples to collect was obtained from the NRC's Office of Nuclear Material Safety and Safeguards.
Direct (gamma) radiation surveys were conducted in the fan room pit, old central stores pit, and lab #27 pit. Surveys were taken with a hand-held micro-Rem (uR) meter (NRC serial #013484) with all readings being taken with the instrument being held approximately one meter from the measured surface.
Surveys were made about the perimeter and diagonally across the fan room pit floor. Measurements were also made along the pit wall from the bottom of the pit to the top (original Building C ground floor). The measurements steadily increased from the 10 to 12 uR/ hour readings at the bottom to approximately 35 uR/ hour at the top of the pit. It appeared that high background levels in Building C contributed to the higher readings near the top of the pit. Survey results at the center of the pit in the lab #27 area ranged from 40 to 50 uR/ hour. The survey results for the floor of the pit beneath the old central stores areas ranged from 10 to 40 uR/ hour. The higher readings for the lab 27 area and old central stores area also appeared to be attributable to the high background in Building C.
The fourteen composited soil samples were sent to the Department of Energy's Radiological Environmental Sciences Laboratory (RESL) for analysis. The analytical technique used by RESL involves a radiochemical separation procedure. The licensee used a Nuclear Data high resolution gamma-ray I spectroscopy system to analyze the soil samples. Am-241, plutonium, thorium, and uranium concentrations were measured by analysis of gamma-ray energies with an energy range from about 50 kev to 2 MeV. Am-241 and U-235 concentrations were determined directly from their respective gamma-ray photopeaks. The plutonium concentrations were determined by multiplying the Am-241 concentration by an empirically determined ratio. The Pu-239/Am-241 ratio was determined by directly measuring the 375.02 and 413.69 kev photo-peaks of Pu-239 in samples containing nCi/gm quantities of the material and comparing these values with Am-241 concentrations measured in the same
, samples. The Th-232 concentration was determined indirectly from the 238.06 peak of Pb-212. The inspectors reviewed technical procedure LRC-TP-210
" Analysis of Radionuclides in Soil by Gamma-Ray Spectroscopy" which described the techniques used in the analyses referred to above. The NRC will include in its evaluation of the adequacy of the licensee's analytical technique on the comparison of the DOE /RESL results with B&W/LRC results.
The inspectors noted that LRC-TP-210 did not provide a means to check for the 'J-233 isotope. Apparently, some quantities of the material was used in the building at one time. The licensee explained that the U-233 had been used for a relatively short period of time and that all of the material had been accounted for, t
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- 6. Drum and Sampling and Analysis During this portion of the inspection, the inspectors collected a total of nine drum samples containing excavated soil. A core sample was obtained from each drum. The core was subdivided and samples were taken from each subdivided section and placed into labeled containers of approximately 500 ml. Details and descriptions of each sample can be found in Appendix I.
Six of the drums sampled were classified by the licensee as " releasable".
The inspectors r'eviewed several drum sampling analysis records and selected three drums of excavated soil with the highest plutonium activity and three drums which the licensee determined were below the minimum detectable activity (MDA). The six drum samples were sent to the DOE /RESL for analysis.
As part of confirming the licensee's ability to measure properly the radionuclides contained in the soil, the inspectors collected three drum samples that contained activity above the release limit and shipped them to DOF/RESL for analysis. These soil samples had been previously analyzed by the licensee. The adequacy of the licensee's analytical technique will include the comparison of the DOE /RESL results with the B&W/LRC results.
( 7. Findings As a result of the closecut inspection and confirmatory survey, the inspec-tors noted the following conditions relating to the release of Phase I, Building C for unrestricted use,
- a. The site gaseous effluent stack is located adjacent to the fan room in the south west portion of Phase I and penetrates though the building roof. The stack is still in service. The off gas ducting from Building B (hot cells) runs along the ceiling in Phase I to the stack.
Figure 2-4 of the licensee's May 28, 1985 final survey report (Appendix A) indicated that the stack was to be included in the area to be released under Phase I. The inspector stated that the off gas system and stack could not be released if it was still in service.
Additionally, releasing Building C for unrestricted use would cause the site gaseous ef fluent release point to be outside the restricted area boundary.
- b. The background gamma radiation levels from sources outside of Building C may cause unmonitored personnel occupying Phase I, if it were released, to receive an exposure in excess of 500 millirem in a year ( Appendix F). The licensee had not evaluated the occupancy time and potential exposures for future Building C occupants.
- c. The licensee did not perform any surveys in the fire equipment room (room with outside entrance in extreme south east corner of Phase I) on
( the basis that no licensed material had ever been in the room. The only surveys performed in the front portion of the Old Central Stores
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(currently ceramics area) were fif teen alpha contamination smears.
Beta gamma contamination and direct radiation surveys were performed only on the floor on the basis that the floor was the most likely place to have been contaminated in the event of a spill. However, Section 5.1.1 of the licensee's final survey report stated that, for the alpha surveys, 70% of the grids initially found above the release limit were on the walls,
- d. The licensee did not remove paint from surfaces containing the original coat of paint or in areas where special nuclear material had not been "
handled (Labs 25, 26, 27 and Old Central Stores). The inspector deterrained that this criteria failed to address the potential for contaminants leaching into the painted surfaces and being masked during ;
the scan surveys. Section 3.3 of the licensee's final survey report, in the third paragraph, stated that contamination had been found under i
- the original coat of epoxy paint on the floor and in the surface of the concrete in Lab 44 after the final release surveys had been performed.
The licensee did not sample other original painted areas as a result of '
this finding.
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- e. As discussed in paragraph 4.d of this report, a smear reading 16t2 dpm of alpha contamination was found on the inside of a pipe in Lab 44. ,
f' The possibility of residual contamination elsewhere in the pipe and its
( removal should be evaluated.
- f. Soil and concrete samples collected in the U-233 process area were not analyzed by the licensee for U-233 content.
! Appendixes:
A- Building C Floor Plan With Phase Boundaries B- Release Criteria C- Direct Survey Locations and Results l D- 3mear Survey Locations and Results l E- Building C, Phase I, Dose Rate Profile j F- Background Gamma Radiation Levels and Exposure Estimates
- G- Special Sample Locations and Descriptions i H- Trench Soil Sample Collection i I- Other Soil Sample Collection Data 1
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BUILDING C SOIL RELEASE LIMITS
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SUILDIES C EEEEBRAL BETA-SMOIA EEDOSURE LIMIT
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- Maximus Acceptable Limit :'
- For Unrestricted Use **
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Contamiamat i l
Th-22Pi with daughters i present and la equilibrium 10 pci/g soil ***
1 Natural Uraninen (U-238 + !
U-234) with daughters present and la equilibrium 10 pci/g soil
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l Depleted Wrani m or !
Natural Draninen that has been separated from its
- 1 daughters, eoluble or j insoluble 35 pci/g soil i
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i Soluble or insoluble 30 pci/g soil f plutonium (Y) or (W) I 1 compounds 25 pci/g soil ,
1 Americitas-241 (W)
- oospounds 30 pci/g soil l External Beta-emmaa
! Exposure mate 10uR/hr i
! O These limits are above background levels.
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) o* The individual ' soil limits given in this table apply to each Olement if it exists by itself. When they occur as a mixture, the I stan of the ratios of the elemental concentrations versus their limits
!, must be less than 1. Thus, for phase I,
) (An-241/30) + (pu/25) + (Th-232/5) + (U/30) <1 ,
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1 A limit of:5 pc1 Th-232/g soil has been adopted for this project.
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- ACCEPTA0LE StRFACE CONTNtIIIATim LEVELS h able b.e.f J .
b b f Nuclides" Averece .c.f huimum .d.f I
i u-net.- U-235. U-238, ed 8 1.000 dpm e/100 as:
l associated decay products 5.000 dpa e/100 cm8 15.000 dre e/100 cm Transuranics. Ra-226. Ra-228 !
Th-230. Th-228. Pa-231 2 20 dpm/100 cur8 Ac-227. 1-125. 1-129 100 dpm/100 cm8 300 dre/100 cm l l
Ra-223. Ra-224. U-232. 3.000 dps/100 cm* 200 dpm/100 ces 1-126. I-131. I-133 1.000 dpe/100 cm8 Beta-gesse emitters (nuclides t I with decay modes other than '
g alpha emission or spontaneous
- fission) except $r-90 and 15.000 dpm sy/100 cm8 1.000 dpm sy/100 cm8 N ethers noted above. 5.000 dpa sy/100 cm*
a Where surface contamination by both alpha- and beta-gasme emitting nuclides exists, the limits estob11shed for alpha and beta-gasse-emitting nuclides should apply independently.
b Asusedinthistable,dpa(disintegrationsperminute)meanstherateofserissionbyradioactivemeterial '
as determined by correcting the counts per minute observed by an appropriate detector for background.
efficiency, and geometric factors associated with the instementation.
For objects of c Measurements of average contaminant should not be averaged over more than 1 square meter.
less surface area, the average should be derived for each such object. ,
, 8 d The maximum contamination level applies to an area of not more then 100 cm .
8 of surface area should be deterurtned by wiping e The amount of removable radiesetive motorial per 100 cm that area with dry filter or soft absortent paper, applying sederste pressure, and assessing tihenthe amount removable of radioactive material on the wipe with an appropriate instrument of know efficiency.
contamination on objects of less surface area is detemined, the. pertinent levels should be reduced pro-portionally and the entire surface should be wiped.
f The average and maximum radiation levels associated with surface contamination resulting from beto-easse amitters should not exceed 0.2 ared/hr at 1 cm and 1.0 ared/hr at I cm. respectively, measured through ,.m l
% more than 7 m1111ecess per square contienter of *otal steerter.
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APPENDIX C DIRECT SURVEY LOCATIONS AND RESULTS Date: November 19 and 20, 1985 Instruments:
Eberline PAC-ISAGA, Serial No.197, with AC-3 probe, calibration due July 31, 1986 Foerline PAC-ISAGA, Serial No. 2244, with AC-3 probe, utibration due July 31,1%6 Eberlir.e RM-14, Serial No. 4726, with HP-210 probe, calibration due September 18, 1986 Survey Locations Indicated by Hash Marks Results:
Direct Alpha - All scans were <170 dpe/100 cm2 Direct Bete-Gama - All scans were <5000 dpe/100 cm2 l
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APPENDIX 0 SMEAR SURVEY LOCATIONS AND RESULTS Smear Results No. Date Location (gross alpha, cross beta) 1 11/19/85 Office 6, grid 240T, outside <2 dpm/100cm2, <3 dpm/100cm2 of duct and pipe 2 11/19/85 Office 6, grid Celling 8, <2 dpm/100cm2, <3 dpm/100cm2 top of I-beam 3 11/19/85 Office 5, grid Celling 1, <2 dpm/100cm2, <3 dpm/200cmr top of pipe 4 11/19/85 Office 5, grid Ceiling 4, <2 dpm/100cm2, <3 dpm/100cm2 5 11/19/85 Office 4, grid Ceiling 8, <2 dpm/200cm2, <3 dpm/200cm2 6 11/19/85 Office 4, grid 136T, top <2 dpe/100cm2, <3dpm/100cm2 of wall I 7 11/19/85 Office 3, grid 109T, top <211 dpm/100cm2, 212 dpe/100cm2 of pipe 8 11/19/85 Office 3, grid Celling 5, <2 dpm/100cm2, <212 dpm/100cm2 top of box 9 11/19/85 Office 2, grid Celling 7, 211 dpe/100cm2, 412 dpm/100cm2 top of conduit 10 11/19/85 Office 1, grid 25T, tops 411 dpm/100cm2, 211 dpm/100cm2 of pipes 11 11/19/85 Office 1, grid cefitng 5 211 dpm/100cm2, 211 dpm/100cm2 12 11/19/85 Lab 44, grid ceiling 17A 211 dpm/100cmt, <3 dpm/100cm2 13 11/19/85 Lab 44, grid ceiling 8A 211 dpm/100cm2, <3 dpm/100cm3 14 11/19/85 Lab 44, grid ceiling 3B, 311 dpm/100cmr , $11 dps/100cm2 ceiling and top of conduit 15 11/19/85 Lab 44, grid 1276T, 1612 dpm/ smear, 211 dpe/ smear inside pipe I
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Appendix D 2 t
Smear Results No. Date Location (aross alpha, cross beta) 16 11/19/85 Lab 44, grid 127CT, 211 dpm/100cm2, 212 dpm/100cm2 outside of sprinkler Pipe 17 11/19/85 Lab 44, grid 1259T, 211 dpm/100cm2, 212 dpa/100cm2 outside of conduit 11/20/85 Lab 43, grid ceiling 13E, 18 <2 dpm/100cm2, 212 dpm/100cm2 top of duct 19 11/20/85 Lab 43, grid ceiling 14A, 312 dpm/100cm2, 412 dpm/100cm2 inside duct 20 11/20/85 Lab 43, grid ceiling 14A, 411 dpm/ smear, 211 dpm/ smear 21 11/20/85 Lab 50, grids ceiling 9A 412 dpm/100cm2, 312 dpm/100cm2 and 98, top of conduit 22 11/20/85 Pit under Lab 50, grid 1777, 211 dpe/100cm2, 312 dpm/100cm2 floor 23 11/20/85 Pit under Lab 50, grid 1777, <2 dpm/100cm2, <3dpm/100cm2 floor 24 11/20/85 Lab 27, grid 1008, drain in <2 dpm/ smear, <3dpm/ smear floor 25 11/20/85 Lab 27, grid ceiling SA, top <2 dpm/ smear, <3 dpm/100cm2 of I-beam 26 11/20/85 Lab 27, grid ceiling 5A, <2 dpm/100cm2, <3 dpm/100cm2 top of girders 27 11/20/85 Hallway 23, by Lab 25, <2 dpm/100cm2, <3 dpm/100cm2 outside of off gas duct 28 11/20/85 Hallway 23, by Lab 25, <2 dpm/100cm2, 212 dpm/100cm2 outside of ventilation duct 29 11/20/85 Lab 25, grid 513, top <2 dpm/100cm2, <3 dpm/100cm2 ceiling 30 11/20/85 Lab 54, grid 1720T, <2 dpm/ smear, <3 dps/ smear hole in wall
- - - - ~ . - - _ . -
'k'pendix0 3
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h ar Results No. Date Location (gross alpha, gross beta) 31 11/20/85 Lab 53, grid 1673, hole <312 dpm/ smear, <3 dpm/ smear in floor 32 11/20/85 Lab 53, grid 16558, <2 dpm/ smear, 312 dpe/ smear inside pipe stub r
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APPINDI Xl CAMMA RADIATION l.EVEl.S AND EXPOStJRE ESTIMATFS Range of Dose Range of Exposures (MR) Average Dose Average Exposures (MR)
Loc _a_ tion fla_tes f uR/hrt $160 hr/yr* 2000 hr/yr* ftates f uR/hr) R160 hr/yr* 2900_ h r/yr*
Floor levei 15-80 131-701- 30-160 8:0.2 352 80 3 feet 20-120 175-1.051 40-240 52.2 457 104 6 feet 30-160 263-1,402 60-320 89.6 785 179
'8760 hr/yr based on continnotes occupancy (l.a., ?4 hr/d x 365 d/yr - 8760 hr/yr) 2000 hr/yr based on continuous occupancy during working hours for a year (l.e., tio hr/wk x 50 wk/yr = P000 hr/yr).
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{ i APPENDIX G SPECIAL SAMPLE LOCATIONS AND DESCRIPTIONS Sample No. Date Location Jescription 1 11/20/85 Pit under Lab 50, grid 1778 Sludge from pit sump 2 11/20/85 North wall of Lab 44 Paint from backside of electrical conduit 3 11/20/85 South ceiling of Lab 44 Faint from exterior of water pipe 4 11/21/85 Southeast corner of front Cloth wipe inside hallway of ventilation duct 5 11/21/85 Ventilation portal between Approximate 4" x 4" Labs 27 and 50 patch from furnace filter 6 11/21/85 West side of Lab 43 Cloth wipe inside j of ventilation duct 7 11/21/85 Ceiling of Lab 43 Sediment from dead-leg of sprinkler header - approxi-mately one pint of water filtered through a #41 filter 8 11/21/85 Front hallway wall east of Concrete and paint door 6, grid 377 9 11/21/85 Office 1, east wall, grid 11 Concrete and paint 10 11/21/85 Lab 43, north wall, east of Concrete and paint door grid 1059 11 11/21/85 Lab 44, south wall, east of Concrete and paint door, grid 1291 12 11/21/85 Lab 27, north wall, grid 832 Concrete and paint 13 11/21/85 Lab 25, north wall, grid 501 Concrete and paint 14 11/21/85 Lab 52, north wall, grid 1571 Concrete and paint
[' 15 11/21/85 Lab 53, floor, grid 1678 Concrete from around sump
- .t APPENDIX H TRENCH SOIL SAMPLE COLLECTION - B&W/LRC, BUILDING C - 11/19/85
- St.iples Composite in ea Sample # Location
- Composite Remarks **
1 Room 50 5 Samples collected at: (1) floor at grid 90, (2) floor near east wall, (3) grid 86, (5) 6' from floor east wall, (5) 6' from floor south wall 2 Room 51 5 Sample 'ocations: (1) floor on entry to Room 51, (2) middle of room on floor, (3) south wall, (4) west wall 3' from floor, (5) west wall l' from floor.
3 Lab 27, Leg #1 5 5 samples taken at ~ equal intervals along trench bottom; samples taken on trench bottom of each intersection.
[ 4 Lab 27, Leg #2 5 5 samples taken at ~ equal intervals along trench bottom; samples taken on trench bottom at each intersection.
5 Open Pit Area Lab 27 5 Samples taken at: (1) west end of pit (near leg #1) floor, (2) south end of pit floor, (3) north end of pit floor, (4) north wall in ~ 2' from floor; (5) east wall at floor level.
6 Drain Line #1 (under 6 6 samples taken on trench floor at labs 25, 26, & 27) approximate equal intervals starting from open pit room 27.
7 Drain Line #2 (under 6 6 samples taken on trench floor; samples labs 25, 26, & 27) were taken near each intersection. I 8 Drain Line under 5 5 samples taken on trench Lab #26 floor lab 26 at ap;,roximate equal intervals starting at intersection near north wall.
9 Lab 44 5 5 samples on trench floor taken at approximately equal intervals starting near north wall door.
i 10 Lab 43 7 Samples taken at: (1) one sample on trench floor at each diagonal inter-section; (2) near center of floor of deep l l
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. - , h pendix H 2
- Samples Composite in ea
( Sample # Location
- Composite Remarks **
pit at south east corner of room; (3) on trench floor near "L" at south door; (4) on trench floor along line at point where it enters hallway at south end of room.
11 Offices 1 & 2 6 For office #1 four samples taken on trench floor; samples were taken on trench floor near office door, at each trench intersection and near southwest corner wall. For office #2 two samples were taken on trench floor at mid point of the two trenches located in the office.
12 Offices 3 & 4 5 Samples taken on trench floor; 3 samples taken in offict 3 and 2 samples taken in office 4.
13 Floor beneath central 7 Samples collected as follows: (1) south stores area wall ~ 10' from floor; (2) west wall ~ 5' from floor; (3) west wall ~ 4' from
- floor; (4) floor at intersection with
( east will: (5) floor at intersection with north wall; (6) east wall ~ 3' from floor; (7) north wall ~
7' from floor.
14 "E" leg under lab #27 5 5 samples were all collected on floor of "E" shaped trench.
- Locations and descriptions of trench work are shown on Figure 3-2 entitled
" Phase 1 Excavation Location". The drain line number, trench " leg" number, and office numbers referred to above are marked on this figure which is provided as Appendix H-1.
- For each composite sample consisting of five sub-samples, the size of each ,
sub-sample was approximately 500 grams. For each composite consisting of six or .l more sub-samples, the size of each sub-sample was about 300-400 grams. For each ,
location sampled, the samples were composited, pulverized to some degree by field :
methods and mixed. The sample was then coned, subdivided into four sections. l Samples were taken from each section and placed in labeled containers identified for each sample location.
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APPENDIX 1 OTHER SOIL SAMPLE COLLECTION DATA FROM B&W/LRC, BUILDING C 11/19/85 Sample Sample Number Description Remarks Drum-1 PDPD 308 Releasable drum sample (high)
Drum-2 PDPD 383 ,,
_ Releasable drum samp1e.(high)
Drum-3 PDPD 542 .- ._ Releasable. drum'6 ample *(low)
Drum-4 PDPD 836
-Releasable crum's' ample }1ow)
'> La Drum-5 PDPD 1834 Releasable drum sample (low)
Drum-6 PDPD 1917 Releasable: drum sample (high)
Drum-7 PDPD 312 Drum' sample with activity above release linjt,-sample collectatd by B&W 4/28/883
[
s "and analyzed.
- Drum-8 PDPD 420 ~ ' Drum sample with" activity above release limit, sample collected by B&W 6/21/83 an analyzed.
~~^ ~~
Drum-9 PDPD 1173 Drum s'a'mpie with activity above release
-limit,- sample collected by B&W 12/12/83 and analyz,ed._ ,
Background-1 23-5-2 -_. . Soil. background collected by B&W 11/26/84 and analyzed.
Background-2 ~' Soil.tbackground ~ collected by NRC
"'11/19/85, 'we's t of Building C, approximately 50 feet from corner of parking lot.
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