ML20151M567
| ML20151M567 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 12/02/1985 |
| From: | Berger J OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | Thomas R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 26166, NUDOCS 8601020608 | |
| Download: ML20151M567 (6) | |
Text
{{#Wiki_filter:- n s i. w -,.~. 'e /i r.4[ RETURN TO 396-SS FK j, wh ~ Oak Ridge Manpower Education, ' Associated Post Office Box 117 Research. and Training Universities Oak Ridge. Tennessee 37831-0117 Dvscr. December 2, 1985 ~ N /* RECEIVED Mr. R. D. Thomas, Chief Nuclear Materials Safety Section /_ [ U.S. Nuclear Regulatory Commission B; DEC 131985 > '3 Region V
- 0. S. NUCLEG REGULATCRf 1450 Maria Lane, Suite 210 t
ccmsren d Walnut Creek, CA 94596-5368 l gQ 1- @l
Subject:
PROPOSED CONFIRMATORY SURVEY PLAN FOR PHASE I DECONTAMINATION - GA TECHNOLOGIES
Dear Mr. Thomas:
Enclosed is our proposed survey plan for confirmation of the Phase I decontamination at the GA Technologies site in San Diego, CA. As can be noted in this plan we anticipate initiating our survey activities on December 10, 1985. I hope we can complete our work by December 14; if not, we j will stay over and work into the next week. I've already touched base with Keith Asmussen and Frank Bold of the GA Technologies staff, and everything is "go" from their standpoint. Please provide any comments or suggestions relative to the d'ocument at your earliest convenience, so that appropriate modifications to our plan can be implemented. It may be reached at FTS 626-3305. Sincerely, James D. Berger Fi Program Manager j Radiological Site Assessm{edt PrQram g, t [ c: a i JDB:vol Z: m 5 (o 1 cc: J. Counts (NRC - EWS-305) A h 3 l C. Paugh (NRC - EWW-359) -{. g 2 M RC + w. u
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W. Crow (NRC) 8-DEC 131985 e,2 2 -9 3 %$i 8601020600 851202 Curctag /p PDR ADOCK 070***** C PDR T- [ g
s ,. +. 4 PROPOSED CONFIRMATORY SURVEY PLAN j FOR PHASE I 0F THE ^ FORiiER WASTE PROCESSING FACILITY ' AND SURROUNDING AREAS GA TECHNOLOGIES SAN DIEGO, CALIFORNIA I. Site History and Description In mid 1984, GA Technologies, Inc. (GA) of San Diego, California, initiated decontamination activities for e purpose of decommissioning portions ci,their f acilities. One of the ' major areas being decontaminated was a former Waste Processing Facility. Potential contaminants have been identified as enriched uranium, thorium, and_ longer half-life fission and activation products. Decontamination is being performed in two Phases. Phase north'of (above) the pc ads, I includes the Solar Evaporations Ponds, the area the canyon below the ponds, the canyon area below the Waste. Processing il Facility,' and adjacent land areas; Phase II areas a r'e the former Waste Processing Facility -itself, the incinerator site, and a small area where contaminated asphalt was previously buried. CA has contracted with AWC[ 'Inc. of Las Vegas, Nevada, to assist in these.decont3mination activities. ,1., s The Phase I area contains approximately 78 acu Only approximately 2 acres of this area were directly affected by previous operations and considered potentially contaminated. The remainder of the adj acent area includes' hillsides and canyons; much of the terrain is relatively steep and accessability is limited. l5 Phase I activities have been completed and a report was issued by GA Technologies and AWC on November 11, 1985. This report indicates that the LI post-decontamination radiological conditions satisfy the NRC guidelines for decommissioning. Region V of the Nuclear Regulatory Commission has requested thatl -the ORAU. Radiological Site Assessment Program perform a confirmatory radiological ' survey of areas associated with. the Phase I decontamination activities. 8 . a. Prepared by the Manpower Education, Research, and Training Division of Oak Ridge Associated Universities, Oak Ridge, TN under interagency agreement DOE No. 40-816-83, NRC Fin. No. 9076-3, between the Nuclear Regulatory Commission and the Department of Energy December 2,;1985, i s, \\ J
l i II. Purpose The purpos,e of the ORAU survey is to confirm the radiological data presented in the GA Technologies /AWC report and to provide information for i evaluation of the site status, relative to the NRC guidelines for release for unrestricted use. III. Responsibility u 8 i w Work described'.in this survey plan will be performed under the supervision of Mr. .f. D. Berger, Certified Health Physicist with the s s l Radiological Site Assessmeht Program of the Manpower Education, Research, and Training Division of Oak Ridge Associated Universities. i i j IV. Procedures \\, ? A. Gridding .I ~ ? s ( The 10 ft, grki, established by GA will be used by ORAU to reference measurement and sampling locations. This grid will be subdivided and/or extended to adjacent areas, if necessary, based or. findings as the survey progresses. Surveys in surrounding areas will be referenced to 'the gri
- system, surface features, or existing r
landmarks, as Qopt priate.j l B. Direct Measurements } s' a'< l. Walkover surface scans will be conducted over all accessible areas of the site using portable gamma scintillation detectors 5 i and ratemeters with a dible indicators. Traverses will be at 1-2 m intervals in he gridded areas, areas immediately adjacent .th the gridded portions,.danyon drainage pathways, and locations 9 > t s where' elevated direct raatation levels are noted. In other areas n the traverses will be at 5-10 m intervals. Locations of elevated contact, radiation will,be noted for further evaluation. l ? s E \\ '- ) A k i c I t.
2. Gamma-ray measurements will be made at the surf ace and 1 m above the surface at 30 f t. intervals throughout the gridded area; at locations of elevated direct radiation, identified by the walko-scans; at 50 ft. intervals along drainage pathways; and at c unimum of 50 additional locations throeThout the Phase 1 area. Portable gamma scintillation detectors, calibrated onsite against. a pressurized ionization c.< amber, will be used for tiiese measurements. 3. Residual contamination, identified by direct measurements, will be brought to the immediate attention of GA personnel. If ~~ additional cleanup is performed during the survey, ORAU will conduct followup sampling and measurements of the cleaned areas. C. Sampling 1. Surface (0-15 cm) soil samples will be collected at each location where direct measurements are performed. 2. Subsurface samples to 1-1.5 m deep will be obtained f rc.n 10-15 randomly selected locati'ons within the gridded area; 5-10 locations along major drainage pathways; and from locations (if any), identified by the surface scans as potential areas of residual contamination. The exact number, locations, and depth of these sac 7 es will be determined by findings as the survey 1 progresses. Sampling will be performed from holes drilled with portable motorized or hand augering equipment. 3. Samples of surface or subsurface water will be collected from the site as available. D. Background and Baseline Determinations Soil and water samples will be collected f rom 6-8 areas surrounding - the site, to provide baseline concentrations of radionuclides for comparison purposes. Direct background radiation levels will be j measured at locations where baseline soil samples are collected. 4
V. Samples Analysis and Interpretation of Results Samples and direct measurement data will be returned to the Oak Ridge, TN laboratory for analysis and interpretation. Soil will be analyzed by solid state gamma spectrometry. Radionuclides of primary interest are U-238, U-235, Th-232, Th-228, Co-60, and Cs-137; however, spectra will be reviewed for other identifiable photopeaks. Selected and composite samples will also be analyzed for isotopic uranium and Sr-90. Water will be analyzed for gross alpha and gross beta; isotopic anclysis will be performed if gross concentrations exceed 15 pCi/l or 50 pCi/1, respectively. Results will be compared to NRC criteria, established for decommissioning of this property. VI. Tentative Schedule Measurements and Sampling December 10-16, 1985 Sample Analysis January 6-31, 1986 1 Draft Report March 14,1986 l' b I 1 t
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