ML032100648
| ML032100648 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 07/25/2003 |
| From: | Benneche P University of Virginia |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML032100648 (73) | |
Text
UNIVERSITY OF VIRGINIA NUCLEAR REACTOR FACILITY U.S. MAIL ADDRESS STREET ADDRES P.O. Box 400322 675 Old Reservoir Road Charlottesville, VA Charlottesville, VA 22903 229044322 Telephone: Ij543 ¢t4-982-5440 Fax: &ojqfA4-982-5473
-2S JulyX,2003 Docket 062 Document Control Desk United States Nudear Regulatory Commission Mail Stop 012-G13 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2783 Attention Mr. Daniel E. Hughes, Project Manager Operating Reactor Improvements Program Subject. Transmittal of University of Virginia Reactor Decormmissioning Project Continuing Characterization Summaries: Reactor Pool Soil Areas; Reactor Pool Interior; Plant Stack; Laboratory Rooms M008 and M005; Demineralizer Room; Hot Cell Room; Heat Exchanger Room; Source Room; Beamport Area; Impacted Drain Lines and Piping; Mezzanine Crawl Space; and Pond Sediment
References:
- 1. Amendment No. 26 to Amended Facility Operating License No. R-66 for the University of Virginia Research Reactor
- 2. Docket 50-62
- 3. Transmittal R. U. Mulder to D. E. Hughes, "Transmittal of the University of Virginia Reactor Decommissioning Project Master Final Status Plan, UVA-FS-002, Rev 0, March 2003- dated April 4,2003
Dear Mr. Hughes,
The referenced amendment which approves the decommissioning plan for the University of Virginia Research Reactor calls for the licensee to submit a report of any characterization surveys performed that were not part of the license amendment application. Appendix A -
Summary of Characterization Results from the University of Virginia Reactor Decommissioning Plan identified 15 locations or areas that required further investigation and evaluation to determine the appropriate decommissioning activities to be performed.
Those investigations are complete and documented by the summaries.
2,C)
Jul V Z2
_Luue-l2,2003 Page 2 We are pleased to transmit for your information three copies (enclosed) of the Continuing Characterization Summaries, prepared for the University of Virginia by CH2M HILL and its subcontractor, Safety and Ecology Corporation. They are: Reactor Pool Soil Areas; Reactor Pool Interior; Plant Stack; Laboratory Rooms M008 and M005; Demineralizer Room, Hot Cell Room; Heat Exchanger Room; Source Room; Beamport Area; Impacted Drain Lines and Piping; Mezzanine Crawl Space; and Pond Sediment This transmittal is the entire set of Characterization Summaries for the University of Virginia Decommissioning Plan.
The Table "Continuing Characterization Document Crosswalk" contains a crosswalk between the fifteen "areas" and the Characterization Summary describing the results of the investigations or other documents, indicated by (v), that will complete the resolution.
Table 1- Continuing Characterization Document Crosswalk Item Appendix A Summary No. "Area" Description or other document (v) 1 Reactor Room Wall & Floor Drains Reactor Pool Soil Areas + (v) Addendum 004: Interior Structure Surfaces 2 Reactor Pool Reactor Pool Interior 3 Reactor Stack Exhaust Reactor Plant Stack +(v) Addendum 006:
Exterior Structure Surfaces 4 Laboratory Sink Laboratory Rooms M08 and M005 5 Demineralizer Equipment surface Demineralizer Room 6 CAVALIER (v) Evaluation of Radiological Characterization Results Relative to Termination of NRC License R-123 7 Hot Cell surfaces Hot Cell Room 8 Heat Exchanger Sump Heat Exchanger Room 9 Ground Floor Walls Source Room +(v) Addendum 004: Interior Structure Surfaces 10 Beam Ports Beamport area 11 UST blockhouse (v) Addendum 001: Underground Waste Tank Excavation 12 Hot Cell Tank & Piping (v) Addenduhi 001: Underground Waste Tank Excavation 13 Pond Sediments Impacted Drain Lines and Piping Mezzanine Crawl Space
.Pond Sediment 14 Pond Bank (v) Addendum 001: Underground Waste Tank Excavation 15 Storm Drain Reactor Pool Soil (v) = documents that provide verification that the condition to be investigated is resolved.
If you have any questions regarding Htis transmittal please contact me at (434) 243-8821.
,8, 2003 Page 2 Sincerely, 1 d e lanp unAA p enicJQiy cOP f e'JtY +6. i-k fw~ei I Paul Benneche Reactor Supervisor University of Virginia July 26 ZOV3
Enclosures:
- 1. UVAP Continuing Characterization: Reactor Pool Soil Areas Summary
- 2. VWAP Continuing Characterization. Reactor Pool Interior Summary
- 3. UVAP Continuing Characterization: Reactor Plant Stack Summary
- 4. UVAP Continuing Characterization: Laboratory Rooms M008 and MO05 Summary
- 5. UVAP Continuing Characterization: Demnineralizer Room Summary
- 6. UVAP Continuing Characterization: Hot Cell Room Summary
- 7. UVAP Continuing Characterization: Heat Exchanger Room Summary
- 8. UVAP Continuing Characterization: Source Room Summary
- 9. UVAP Continuing Characterization: Beamport Area Summary
- 10. UVAP Continuing Characterization: Impacted Drain Lines and Piping Summary
- 11. UVAP Continuing Characterization: Mezzanine Crawl Space Summary
- 12. UVAP Continuing Characterization: Pond Sediment Summary c: Ralph Allen, Chair Reactor Decommissiornng Committee Stephen Holmes, NRC
UVAP Continuing Characterization:
Reactor Pool Soil Areas The Reactor Containment building housed the former UVA Research Reactor located on the first floor. The steel re-enforced concrete reactor pool is approximately four meters wide, ten meters long and nine meters in depth. The pool is separated into two halves by a concrete buttress that housed the reactor pool gate. The pool is oriented slightly off from true North to South. The Reactor Room floor elevation was near the top of the original pool structure, while the facility ground floor is about two feet above the bottom of the reactor pool. The space between the base of the pool and the Reactor Room floor and the Reactor Room sidewall was backfilled with site soil before the floor slab was poured. An exhaustive soil-sampling program was used to evaluate potential contamination levels in the materials used to backfill this space. Leakage from separated reactor room floor drain piping and other potential leakage paths from the reactor pool potentially affected some of these areas.
The soils around the reactor pool structure have been accessed at 36 locations. Nineteen bore holes were cored in the 8 inch thick concrete reactor room floor, seven bore holes were cored through the 18 inch thick reactor pool wall, seven bore holes cored through the 12 inch concrete reactor pool floor, one bore hole cored horizontally in the 12 inch thick concrete wall between the heat exchanger room and the reactor pool room and two horizontal bore holes cored in the 12 inch thick dernineralizer room wall (Figures 1, 2, and 3). All soil samples from these holes were below the DCGL of 3.8pCi/g for Co-60 and 11.0 pCi/g for Cs-137, with the exception of the "rI core and one reactor pool floor sample. See Tables 1 thru 8 for sample analyses results.
Reactor room "I" core (Figure 1) soil results (Table 1) ranged from non-detectable to 85.5 pCi/g Co-60. To determine the extent of the "r' core soil contamination, seven bore holes were cored in the reactor pool wall (Figure 2) to determine contamination migration from " r' core. Samples were obtained to a horizontal depth of 4.5-feet or refusal and showed no Co-60 activity. (Table 2). Three r,
boreholes were cored around " core. North "IC" and east "IB" of "r' at a distance of 10-feet, and to the south "IA" at a distance of 4-feet (Figure 1). Surface samples from these core holes indicated no Co-60 activity (Table 1, UVA-SL-050 thru 052). The activity in core bore 'T' was limited to an area of 1.5-foot across by 1.5-foot deep, and 3-feet in length adjacent to the pool south east wing wall and east pool wall. This soil was removed. Samples taken after soil remediation indicated soil results (Table 1, UVA-SL-126 thru 129) ranged from non-detectable to 1.4 pCi/g Co-60.
The initial through the pool floor core sample #9 (Figure 2) taken on 12/18/02 indicated activity of 4.72 pCi/g at a depth of 42 to 54 inches. This elevated activity is believed to have resulted from cross contamination, from the beam port concrete removal operation, which had been performed directly above the sample #9 location. The original 4-inch core was over cored with an 18-inch core for access. Two additional sample locations were selected adjacent to #9 sample and labeled PF1 and PF1A. Reactor pool core bore PF1 surface soil sample indicates activity for Co-60 at 3.7 pCi/gram.
Analysis of auger samples from PF1 and PF1A denotes no activity from licensed material above DCGL from the soil surface below the Reactor Room concrete floor to the depth of 90 inches. See Table 7 for results.
Soil samples were obtained from the west wall in the demineralizer room and heat exchanger area to a horizontal depth of 78-inches and 66-inches, respectively. These samples indicated no activity above DCGL's. See Tables 4 and 5 for results.
1
UVAP Continuing Characterization:
Reactor Pool Soil Areas Soil samples were obtained from twelve locations on the ground floor, from the heat exchanger room sump and though other concrete floor openings in the heat exchanger room and room G020 (Figure 3). All soil samples from these holes were below the DCGL of 3.8pCi/g for Co-60 and 11.0 pCi/g for Cs-137. See Table 6 for results.
Table 8 contains background sample results from Ragged Mountain Reservoir sediment samples, sediment on the UVAP site upstream from the pond bed sediment, UVAP site fill soil, and the UVAP rock face (in the upper parking lot) for comparison. The Ragged Mountain Reservoir is located approximately 5 miles west of the UVAP site and was designated as a background location in the GTS Characterization report. The Ragged Mountain reservoir rock formation is not the same geological formation as at UVAP, and contains rock with lower concentrations of naturally occurring radioactive elements.
Two samples from the floor core samples, UVA-PSL-002-5 and UVA-PSL-003-4 and a composite of the 4" concrete core samples, UVA-PCC-001 were sent to the offsite laboratory for Part 61 "hard to detect" isotope analysis. See Table 9 for results.
During Final Status Survey soil sampling, three 6-inch surface samples and one composite sample were found to be above DCGL criteria for Co-60. One sample from "lv' core area, UVA-SLFS-047 indicated activity of 9.7 pCi/g, Two samples from "B" core area, UVA-SLFS-032 and 052 indicated activity of 9.5 pCi/g and 18.8 pCi/g, respectively. The "M' core elevated area was delineated to a discreet location of 6-inches by 6-inches by 6-inches deep just under the piping junction of "L" pipe and the "M" core main floor drain header piping. This junction had been removed during D & D operations. This elevated soil was removed and follow-up samples were below DCGL criteria. The elevated area in "B" core was delineated and found to be limited to the "B" drain piping and the main floor drain header piping junction that was removed during D & D operations. This elevated soil was removed and follow-up samples were below DCGL criteria.
CONCLUSIONS:
Based on results of the initial surveys and surveys after D&D evolutions, no further remediation is required. The reactor pool soil areas are ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 1 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
2
LEGEND X 4 INCH SAMPLE CORE (SC)
D~ CLEAN OUT (CO) o FLOOR OR SINK DRAIN (FO OR SO) o ACCESS CORES (LETTERED)
SCALE ABR EOUALS 3 METERS ,,
(Uq DRAIN STANDPIPE ec-- (PLUGGED 5-12-03) 0 0
04 It cI 0
0 0--
N D OWN TO POND STANOPIPE PIPING REMOVED FROM -"
REACTOR ROOM TO HEAT EXCHANGER ROOM SUMP la 0 N
REMAINING PIPING SHOWN SOLID 0 DOTTED LINE SHOWS REMOVED PIPING INDICATES SEPARATED LINE LOCATION UVAR REACTOR ROOM FLOOR SHOWING REMAINING DRAIN PIPING
Rx pool Walls &Floor Concrete Cores I
N X iii ED 0
m02 RI-,
0 II I 0 I-1o'_Z 1.?1 a I I I 1 0
C -. - _ i -6 C)
I' I I __ I -- _Io -L -9
- s I _ II - __
f_
I I. I I.. I I I_ I ,
N 17
- Shilew Cmbr 0
0 Thlrmoto loslmbor II 9a 6/7/03
- I 4 - &I 4 - - - I - I -
s S'BOJ floS lood IO13,0"'I
- uonvzUjo4ov?.a~q SupinuuoD cdYAfl
UVAP Continuing Characterization:
Reactor Pool Soil Areas I""Core Soil Samples Table 1 (Onsite Lab Results)
Gamma Core Sample number Interval Loggin Scan Gamma Spectrosco z 44-2 44-9 K-40 Co-57 Co-60 Ag-108m Cs-137 Eu162 Pb-212 Pb-214 Inches CPM CPM pCi/gm pCi/gm pCVgm pCgrn pC~gm pC/gm pCigm pCigm UVA-SL-021 Surface N/A N/A 15.4 0.3 85.6 1.7 1.2 8.4 0.3 WVA-SL-031-1 0 to 6 N/A 92 13.3 Non-det 4.5 Non-det 0.2 Non-det 0.8 0.6 UVA-SL-031-2 6 to 18 N/A 103 14.5 Non-det 6.9 Non-det Non-det Non-det 1.2 0.5 UVA-SL-031-3 18 to 30 N/A 113 16.0 0.1 1.76 Non-det Non-det Non-det 1.3 0.7 UVA-SL-031-4 30 to 42 N/A 124 20.0 Non-det 2.5 Non-det Non-det Non-det 1.7 1.0 UVA-SL-031-5 42 to 54 NIA 123 20.1 Non-det 1.2 Non-det Non-det Non-det 1.8 1.2 UVA-SL-031-6 54 to 66 N/A 118 18.7 Non-det 3.7 Non-det Non-det Non-det 1.7 0.9 UVA-SL-038 Surface N/A N/A 22.5 0.6 45.6 1.1 1.0 3.5 1.4 UVA-SL-039 Surface N/A 112 12.7 Non-det Non-det Non-det Non-det Non-det 1.0 0.7 UVA-SL-040 Surface N/A 122 28.7 Non-det Non-det Non-det Non-det Non-det 2.5 1.8 UVA-SL-041 Surface N/A 110 23.3 Non-det Non-det Non-det Non-det Non-det 1.7 1.2 UVA-SL-050 Oto 6 11950 NMA 15.2 Non-det Non-det Non-det Non-det Non-det 0.8 0.4 UVA-SL-051 0 to 6 11818 N/A 14.4 Non-det Non-det Non-det Non-det Non-det 1.1 0.6 UVA-SL-052 0 to 6 11514 NIA 25.4 Non-det Non-det Non-det Non-det Non-det 1.6 1.1 UVA-SL-055 Surface N/A 132 18.3 Non-det 5.5 Non-det Non-det Non-det 1.3 0.7 UVA-SL-056 Oto 6 57943 140 22.4 0.2 19.2 0.4 0.3 3.0 1.4 0.7 UVA-SL-057 0 to 6 43712 179 16.7 Non-det 0.6 1.3 1.2 7.1 0.4 UVA-SL-058 0 to 6 25302 106 25.7 Non-det 1.0 Non-det Non-det Non-det 1.5 UVA-SL-113 Surface N/A 312 25.3 Non-det 8.9 50.1 Non-det Non-det 1.4 UVA-SL-113A Particle N/A N/A 22.0 Non-det 13.9 Non-det Non-det 0.7 1.6 1.3 UVA-SL-1 16 Oto 6 N/A 90 23.2 Non-det 2.9 Non-det Non-det Non-det 1.5 0.8 UVA-SL-1 19 0 to 6 N/A 69 18.8 Non-det 3.0 Non-det Non-det Non-det 1.3 0.7 UVA-SL-120 0 to 6 N/A 96 19A Non-det 0.4 Non-det Non-det Non-det 1.2 0.7 UVA-SL-121 Oto 6 N/A 143 16.7 Non-det 33.0 0.5 0.4 3.0 1.0 UVA-SL-130 B-25 Grab N/A N/A 16.1 Non-det 11.9 Non-det 0.3 Non-det 1.03 0.6 Soil Samples After "I" core soil decontamination WVA-SL-126 0 to 6 N/A N/A 10.5 Non-det 1.4 0.2 Non-det Non-det 0.7 0.5 UVA-SL-127 0 to 6 N/A N/A 18.0 Non-det Non-det Non-det Non-det Non-det 1.6 1.0 LVA-SL-128 Oto 6 N/A N/A 19.7 Non-det Non-det Non-det Non-det Non-det 1.2 0.7 UVA-SL-129 0 to 6 N/A N/A 20.4 Non-det Non-det Non-det Non-det Non-det 1.6 1.0 Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparation of sample for homogeneous mixture and drying.
6
UVAP Continuing Characterization:
Reactor Pool Soil Areas "I " Core Soil Samples, Pool East Wall Table 2 (Onsite Lab Results)
Gamma Core Sample number Interval Logging Scan GammaS o py Remarks 44-2 44-9 K-40 Cs-137 Co-60 Pb-212 Pb-214 Inches CPM CPM pCi/gm pC01gm pC0ggm pCtgm gm UVA-SL-043-1 0 to 18 NMA NJA 9.0 Non-det Non-det 0.6 0.6 Core #18 UVA-SL-043-2 18 to 30 NJA 76 19.1 Non-det Non-det 2.3 1.1 UVA-SL-043-3 30 to 36 N/A 88 18.8 Non-det Non-det 2.8 1.0 UVA-SL-044-1 0 to6 N/A 60 12.0 Non-det Non-det 1.5 1.0 Core #19 UVA-SL-044-2 6to 18 N/A 92 15.5 Non-det Non-det 1.7 1.1 UVA-SL-044-3 18 to 30 NJA 72 16.2 Non-det Non-det 1.8 0.9 UVA-SL-044-4 30 to 42 N/A 55 io.9 Non-det Non-det 1.7 1.0 UVA-SL-044-5 42 to 48 N/A 80 17.2 Non-det Non-det 2.0 1.1 UVA-SL-045-1 0 to 6 N/A 82 20.1 Non-det Non-det 1.6 1.0 Core #20 WVA-SL-045-2 6 to 18 N/A 93 20.8 Non-det Non-det 1.7 1.0 UVA-SL-045-3 18 to 30 N/A 71 19.7 Non-det Non-det 1.9 0.9 UVA-SL-045-4 30 to 42 N/A 70 20.8 Non-det Non-det 1.7 1.0 UVA-SL445-5 42 to 54 N/A 71 21.6 Non-det Non-det 1.6 0.8 UVA-SL-046-1 0 to 6 N/A 96 25.9 Non-det Non-det 1.9 1.4 Core #21 UVA-SL-046-2 6 to 18 N/A 110 27.6 Non-det Non-det 2.4 1.3 WA-SL-043 18 to 30 N/A 83 26.8 Non-det Non-det 2.4 1.4 WA-SL-046-4 30 to 42 N/A 105 30.0 Non-det Non-det 2.1 1.3 UVA-SL-046-5 42 to 54 N/A 86 23.9 Non-det Non-det 1.9 1.3 UVA-SL-047-1 0 to 6 N/A 102 24.0 Non-det Non-det 2.0 1.2 Core #22 UVA-SL-047-2 6 to 18 N/A 78 21.5 Non-det Non-det 2.0 1.1 WA-SL-047-3 18 to 30 N/A 96 22.7 Non-det Non-det 2.1 1.3 UVA-SL-047-4 30 to 42 N/A 86 20.0 Non-det Non-det 1.9 1.0 UVA-SL-047-5 42 to 54 N/A 82 23.4 Non-det Non-det 2.0 1.1 UVA-SL-048-1 0 to 6 N/A 95 16.0 Non-det Non-det 1.2 0.9 Core #23 LVA-SL-048-2 6 to 18 N/A 91 15.7 Non-det Non-det 1.2 0.7 WA-SL-048-3 18 to 30 N/A 87 22.1 Non-det Non-det 1.5 0.8 UVA-SL-048-4 30 to 42 N/A 105 26.3 Non-det Non-det 1.7 1.1 UVA-SL-048-5 42 to 54 N/A 103 25.4 Non-det Non-det 1.7 0.9 WA-SL-049-1 0 to 6 N/A 97 14.6 Non-det Non-det 1.0 0.6 Core #24 WA-SL-049-2 6 to 18 N/A 88 19.6 Non-det Non-det 1.5 0.9 WA-SL-049-3 18 to 30 N/A 79 25.8 Non-det Non-det 1.8 1.0 UVA-SL-049-4 30 to 42 N/A 100 25.5 Non-det Non-det 1.9 1.1 UVA-SL-049-5 42 to 64 NJA 80 21.7 Non-det Non-det 1.8 0.9 Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparation of sample for homogeneous mixture and drying.
7
UVAP Continuing Characterization:
Reactor Pool Soil Areas Reactor Room Core Soil Samples
_ __ Table 3 (Onsite Lab Results)
Gamma Core Sample number Interval Logging Scan Gamma S roscopY Remarks 44-2 44-9 K-40 Cs-137 Co-60 Pb-212 Pb-214 Inches CPM CPM pCigm pC/gm pCgm gm pC2gm __
UVA-SL-023 Grab NIA N/A 17.9 Non-det Non-det 0.3 0.5 Core H UVA-SL-023 Grab NIA N/A 19.5 Non-det 0.4 0.9 0.3 Core G UVA-SL-027-1 0 to 6 6652 87 20.0 Non-det Non-det 1.2 0.7 Core H UVA-SL-027-2 6 to 18 6435 112 20.0 Non-det Non-det 1.4 0.8 Core H UVA-SL-027-3 18 to 30 5806 128 20.0 Non-det Non-det 0.7 0.6 Core H UVA-SL-027-4 30 to 42 5367 89 22.4 Non-det Non-det 1.5 0.7 Core H UVA-SL-028-1 0 to 6 5241 98 16.0 Non-det Non-det 0.9 0.6 Core G UVA-SL-028-2 6 to 18 5858 86 22.0 Non-det Non-det 1.4 0.8 Core G UVA-SL-028-3 18 to 30 6001 102 21.0 Non-det Non-det 1.5 0.7 Core G UVA-SL-028-4 30 to 42 6357 117 23.3 Non-det Non-det 1.3 0.8 Core G UVA-SL-028-5 42 to 54 6750 124 26.0 Non-det Non-det 1.3 0.9 Core G UVA-SL-028-6 54 to 60 6300 98 21.8 Non-det Non-det 1.8 0.8 Core G UVA-SL-059-1 Surface N/A 95 24.6 Non-det Non-det 1.6 0.6 Core J UVA-SL-060-1 Surface N/A 98 21.0 Non-det Non-det 1.3 0.5 Core M UVA-SL-061-1 Surface N/A 97 18.4 Non-det Non-det 1.4 0.5 Core N UVA-SL-064 Grab N/A N/A 20.0 Non-det Non-det 1.4 0.8 Soil Removed From Core N UVA-SL-065 Grab N/A NIA 23.6 Non-det Non-det 1.2 0.7 Soil Removed From Core J UVA-SL-066 Grab N/A N/A 20.0 Non-det Non-det 1.1 0.7 Soil Removed From Core H UVA-SL-067 Grab NIA N/A 24.0 Non-det Non-det 1.6 0.9 Soil Removed From Core M UVA-SL-107 Grab NIA 86 23.0 Non-det Non-det 1.6 0.7 Soil Removed From Core E UVA-SL-108 Grab N/A 87 23.1 Non-det Non-det 1.3 0.6 Soil Removed From Core D UVA-SL-109 Grab N/A 85 19.2 Non-det Non-det 1.2 0.7 Soil Removed From Core R UVA-SL-110 Grab N/A 98 20.0 Non-det Non-det 1.3 0.8 Soil Removed From Core T UVA-SL-1 11 Grab N/A 81 22.4 Non-det Non-det 1.4 0.8 Soil Removed From Core B UVA-S-112 Grab N/A 103 27.0 Non-det Non-det 2.0 1.2 Soil Removed From Core L UVA-SL-114 0 to 6 N/A 105 23.7 Non-det Non-det 2.0 1.1 Core L Location A UYA-SL-1 15 0 to 6 N/A 96 24.2 Non-det Non-det 2.0 1.1 Core L Location B UVA-SL-123 0 to 6 N/A N/A 23.0 Non-det Non-det 2.0 1.0 Core L Location C UVA-SL-124 0 to 6 NIA N/A 26.0 Non-det Non-det 1.9 1.0 Core L Location D Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparation of sample for homogeneous mixture and drying.
8
UVAP Continuing Characterization:
Reactor Pool Soil Areas Demineralizer Room Wall Core Soil Samples Initial Table 4 (Onsite Lab Results)
Gamma re Sample number nterval Log anngScan Gam aSpe oscopY I Remarks 44-2 44-9 K-40 Cs-137 Co0 Pb-212 b-214 Inches PM PM CVgm pCVgm PCgm CVgm Ci/gm UVA-SL-012-1 0 to 6 N/A 87 26.6 Non-det Non-det 1.5 0.6 4-in core placed in UVA-SL-012-2 6 to 18 NIA 96 27.7 Non-det Non-det 1.7 0.7 West wall to access reactor UVA-SL-012-3 18 to 30 NIA 83 32.1 Non-det Non-det 1.8 0.7 Pool fill UVA-SL-012-4 30 to 42 N/A 87 28.0 Non-det Non-det 1.5 0.8 UVA-SL-012-5 42 to 54 N/A 78 27.7 Non-det Non-det 1.6 0.7 UVA-SL-012-6 64 to 66 N/A 94 26.8 Non-det Non-det 1.4 0.4 UVA-SL-012-7 66 to 78 N/A 100 26.0 Non-det Non-det 1.3 0.7 Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparation of sample for homogeneous mixture and drying.
Heat Exchanger Wall Core Soil Samples Table 5 (Onsite Lab Results)
Gamma Core Sample number Interval Logging Scan Gamma Spec scopy Remarks 44-2 44-9 K-40 Cs-1 37 Co-60 Pb-212 Pb-214 Inches CPM CPM pCi/gm pCirgm pClgm pC/gm pCVgm UVA-SL-011-1 0 to 6 N/A 78 31.0 Non-det Non-det 5.3 2.6 4-in core placed in UVA-SL-011-2 6 to 18 N/A 109 31.0 Non-det Non-det 4.0 1.5 West wall to access reactor UVA-SL-011-3 18 to 24 N/A 145 27.9 Non-det Non-det 2.0 0.9 Pool fill UVA-SL-011-4 24 to 30 N/A 74 24.8 Non-det Non-det 0.9 0.3 UVA-SL-011-5 30 to 42 N/A 92 26.0 Non-det Non-det 0.9 0.2 UVA-SL-011-6 42 to 64 N/A 93 26.2 Non-det Non-det 0.8 0.3 UVA-SL-011-7 54 to 66 N/A 81 21.2 Non-det Non-det 0.8 0.2 Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparation of sample for homogeneous mixture and drying.
9
UVAP Continuing Characterization:
Reactor Pool Soil Areas Ground Floor Core Hole Soil Samples Table 6 (Onsite Lab Results)
Gamma Core Sample number Interval Logging Scan Gamma Spect oy Remarks 44-10 44-9 K-40 Cs-137 Co-60 Pb-212 Pb-214 Inches CPM CPM pCi/gm pCilgm pCigm pC~gm _ _ _ __m UVA-SL-026 Grab NJA N/A 14.4 Non-det Non-det 1.2 0.5 Core A UVA-SL-030 Grab N/A N/A 7.0 Non-det Non-det Non-det Non-det Gravel, Heat exch. sump UVA-SL-032 Grab N/A N/A 33.9 Non-det Non-det 1.9 0.9 Soil, Heat exch. sump UVA-SL-034 Grab N/A N/A 5.3 Non-det Non-det Non-det Non-det Hot Cell Core UVA-SL-053-1 0 to 6 18934 61 6.7 Non-det Non-det 0.3 Non-det Core E Initial, Gravel UVA-SL-053-2 6 to 18 N/A 113 27.4 Non-det Non-det 2.2 0.8 Core E Initial, Soil UVA-SL-054-1 0 to 6 25296 120 24.7 Non-det Non-det 1.8 0.9 Hot cell, outside roadway UVA-SL-062-1 0 to 6 8795 72 7.0 Non-det N~on-det Non-det 0.2 Core E , Trackway UVA-SL-062-2 6 to 18 10021 142 31.5 Non-det Non-det 2.1 0.9 Excavation UVA-SL-062-3 18 to 30 10551 145 33.9 Non-det Non-det 2.3 0.7 UVA-SL-062-4 30 to 36 10832 133 31.3 Non-det Non-det 2.5 0.9 UVA-SL-063-1 0 to 6 N/A 84 8.6 Non-det Non-det 0.3 0.4 UVA-SL-063-2 6 to 18 N/A 125 32.4 Non-det Non-det 2.9 1.4 UVA-SL-063-3 18 to 30 N/A 120 33.1 Non-det Non-det 2.5 1.2 UVA-SL-063-4 30 to 34 N/A 140 30.7 Non-det Non-det 2.8 1.2 UVA-SL-064 Grab N/A 93 19.5 Non-det Non-det 1.4 0.8 UVA-SL-065 Grab N/A 101 23.6 Non-det Non-det 1.2 0.7 UVA-SL-066 Grab N/A 71 19.6 Non-det Non-det 1.1 0.7 Core E, Trackway UVA-SL-067 Grab N/A 122 24.0 Non-det Non-det 1.6 0.9 Soil Stock pile UVA-SL-068 Grab N/A 118 29.7 Non-det Non-det 2.2 0.9 P UVA-SL-069 Grab N/A 130 30.5 Non-det Non-det 2.2 1.0 UVA-SL-070 Grab N/A 112 29.3 Non-det Non-det 2.4 1.0 _
UVA-SL-071 Grab N/A 125 27.2 Non-det Non-det 2.1 0.9 UVA-SL-072 Grab N/A 108 30.5 Non-det Non-det 2.3 1.0 UVA-SL-073 Grab N/A 120 32.2 Non-det Non-det 2.2 0.9 UVA-SL-074 Grab N/A 135 30.8 Non-det Non-det 2.3 0.8 UVA-SL-075 Grab N/A 123 31.6 Non-det Non-det 2.5 1.0 UVA-SL-076 Grab N/A 86 10.9 Non-det Non-det 0.4 0.2 UVA-SL-077 0 to 6 N/A 112 33.1 1.0 Non-det 2.4 0.9 Trackway Excavation, UVA-SL-078 0 to 6 N/A 103 31.1 Non-det Non-det 2.1 0.8 Sampling refusal at 6 UVA-SL-079 0 to 6 103141 117 30.9 Non-det Non-det 2.2 1.0 Trackway Excavation UVA-SL-080 6 to 18 10823 121 28.5 Non-det Non-det 2.6 1.0 Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparation of sample for homogeneous mixture and drying.
10
UVAP Continuing Characterization:
Reactor Pool Soil Areas Ground Floor Core Hole Soil Samples Table 6 cont. (Onsite Lab Results)
Gamma Core Sample number Interval Logging Scan Gam maSpecsoop l Remarks 44-2 44-9 K-40 Cs-1 37 Co-60 Pb-212 Pb-214 Inches CPM CPM pCigm pCVgm pCi/gm pCi/gm pCigm UVA-SL-081 18 to 30 10516 137 33.0 Non-det Non-det 3.0 1.0 Trackway Excavation WA-SL-082 0 to 6 10721 121 23.4 Non-det Non-det 2.3 1.0 UVA-SL-83 6 to 18 10634 147 29.4 Non-det Non-det 2.6 1.0 WA-SL-084 18 to 30 11184 121 35.8 Non-det Non-det 3.0 1.0 U UVA-SL-085 0 to 6 10318 127 30.0 Non-det Non-det 2.1 0.7 U UVA-SL-086 6 to 18 10466 I 114 33.1 Non-det Non-det 2.4 0.9 UVA-SL-087 18 to 30 10214 141 34.9 Non-det Non-det 2.0 0.6 UVA-SL-088 Grab N/A N/A 24.0 Non-det Non-det 2.0 1.0 Hot cell outfall, soil pile UVA-SL-089 Grab NJA N/A 26.1 Non-det Non-det 2.1 0.8 Hot cell outfall, soil pile WA-SL-104 0 to 6 N/A N/A 16.6 Non-det Non-det 0.8 0.8 LWST Core WA-SL-105 0 to 6 N/A N/A 18.4 Non-det Non-det 0.9 0.6 LWST Core UVA-SL-106 0 to 6 N/A N/A 25.0 1.2 Non-det 2.3 0.9 Soil inside Terracotta pipe UNA-SL-117 Surface N/A 129 26.9 Non-det Non-det 2.3 1.1 Sanitary line core UVA-SL-118 Surface N/A 143 26.2 Non-det Non-det 2.4 1.0 A and B Header core WA-SL-122 Grab N/A 109 21.4 Non-det Non-det 1.4 0.6 Source room core UVA-SL-132 Surface NJA N/A 36.8 0.2 Non-det 3.7 1.9 Heat Exch. Suction line
=_______________
=_____ =====__ _______ Excavation Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparation of sample for homogeneous mixture and drying.
11
UVAP Continuing Characterization:
Reactor Pool Soil Areas Pool Floor Core Soil Samples Table 7 (Onsite Lab Results)
Gamma Core ample number nterval Loging Scan Gamma SetscoP Remarks 44-2 44-9 K-40 Cs-137 Co-60 Pb-212 Pb-214 Inches CPM CPM pCigm pCigm pCi/gm pCi/gm pCigm UVA-PSL-001-1 0 to 6 10985 75 28.6 Non-det Non-det 0.2 0.4 Pool Floor Core #6 UVA-PSL-001-2 6 to 18 13527 77 36.6 Non-det Non-det 3.0 1.3 UVA-PSL-001-3 18 to 30 14705 92 37.3 Non-det Non-det 2.7 1.2 UVA-PSL-001-4 30 to 42 13718 108 34.4 Non-det Non-det 4.2 1.6 UVA-PSL-001-5 42 to 54 14784 86 44.6 Non-det Non-det 3.9 1.7 UVA-PSL-002-1 Oto 6 9694 64 41.0 Non-det Non-det 1.7 0.8 Pool Floor Core #9 UVA-PSL-002-2 6 to 18 10241 78 45.1 Non-det Non-det 2.0 1.1 UVA-PSL-002-3 18 to 30 10401 52 42.3 Non-det Non-det 2.4 1.4 UVA-PSL-002-4 30 to 42 9948 67 41.0 Non-det Non-det 2.7 1.2 UVA-PSL-002-5 42 to 54 8813 117 38.8 Non-det 4.7 2.0 1.0 UVA-PSL-002-5A 42 to 54 N/A N/A 41.2 Non-det Non-det 2.0 1.2 Soil removal after collapse UVA-PSL-002-6 54 to 66 9691 71 40.0 Non-det Non-det 2.3 1.3 UVA-PSL-002-7 66 to 78 10213 84 40.4 Non-det Non-det 2.5 1.3 UVA-PSL-002-8 78 to 90 10321 61 37.6 Non-det Non-det 2.0 1.0 UVA-PSL-003-1 0 to 6 11529 60 32.0 Non-det Non-det 1.8 1.2 Pool Floor Core #8 UVA-PSL-003-2 6 to 18 13556 59 40.4 Non-det Non-det 3.2 1.7 UVA-PSL-003-3 18 to 30 23559 144 33.8 Non-det Non-det 8.2 3.4 UVA-PSL-003-4 30 to 42 21869 120 39.6 Non-det Non-det 8.1 3.5 UVA-PSL-003-5 42 to 54 17693 93 42.9 Non-det Non-det 4.6 2.1 UVA-PSL-004-1 0 to 6 20262 107 27.2 Non-det 0.9 2.8 1.4 Pool Floor Core #7 UVA-PSL-004-2 6 to 18 22437 70 36.1 Non-det Non-det 4.8 3.2 WVA-PSL-004-3 18 to 30 21510 131 38.2 Non-det Non-det 8.0 3.6 UVA-PSL-004-4 30 to 42 21048 78 34.7 Non-det Non-det 6.7 2.4 UVA-PSL-004-5 42 to 54 21552 145 37.7 Non-det Non-det 10.7 3.5 UVA-SL-029 surface N/A N/A 29.2 Non-det 3.7 0.6 0.2 Soil under 18" core # 9 UVA-SL-033-1 0 to 6 NWA 150 29.5 Non-det 1.7 1.4 0.5 Pool Floor Core # 9 UVA-SL-033-2 6 to 18 NJA 133 34.0 Non-det Non-det 1.9 0.8 To verify first sampling UVA-SL-033-3 18 to 30 N/A 159 30.9 Slon-det 1.1 1.9 0.8 Event after cutting 18" UVA-SL-033-4 30 to 42 N/A 143 33.2 on-dt on-det 1.7 0.9 Concrete core UVA-SL-033-5 42 to 54 N/A 176 31.0 on-det Non-det 2.0 0.8 Sample name PF1 UVA-SL-033-6 54 to 66 N/A 186 31.5 on-det on-det 2.2 1.1 UVA-SL-033-7 66 to 78 N/A 134 29.2 on-det -ondet 2.7 1.3 UVA-SL-035-1 0 to 6 NIA 121 28.9 on-det 1.5 2.9 1.1 Pool Floor Core # 9 UVA-SL-035-2 6 to 18 N/A 143 32.3 on-det 1.0 1.7 0.7 To verity first sampling UVA-SL-035-3 18 to 30 N/A 158 32.8 on-det on-det 2.9 1.5 Event after cutting 18 Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted Ina non-standard preparation of sample for homogeneous mixture and drying.
12
UVAP Continuing Characterization:
Reactor Pool Soil Areas Pool Floor Core Soil Samples Table 7 cont. (Onsite Lab Results)
Gamma Core Sample number Interval Logging Scan Gamma Spectroopy Remarks 44-2 44-9 K-40 Cs-137 Co-60 Pb-212 Pb-214 Inches CPM CPM pCi/gm pCi/gm pCgml pCi/gm UVA-SL-035-4 30 to 42 N/A 155 35.9 Non-det Non-det 2.0 1.2 Pool Floor Core # 9 UVA-SL-035-5 42 to 54 NIA 181 31.0 Non-det Non-det 2.1 1.4 Concrete second sample UVA-SL-035-6 54 to 66 N/A 143 33.2 Non-det 1.0 2.2 1.2 Sample name PFIA UVA-SL-035-7 66 to 78 N/A 169 30.1 Non-det Non-det 2.4 1.2 UVAOSL-035-8 78 to 90 N/A 147 32.7 Non-det Non-det 3.2 1.7 _
UVA-SL-036drain a Surface N/A N/A 25.9 Non-det Non-det Non-det Non-det Pool Floor Core # PF2 UVA-SL-037drain b Surface N/A N/A 28.1 Non-det Non-det 3.6 0.3 Pool Floor Core # PF3 Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparation of sample for homogeneous mixture and drying.
13
UVAP Continuing Characterization:
Reactor Pool Soil Areas Background soil sample results Table 8 (Onsite Lab Results)
Ragged Mountain Reservoir Sediment Samples Gamma Core Sample number Interval Loggin Scan Gamma Spectroscoy 44-2 44-9 K-40 Cs-I 37 Co-60 Pb-212 Pb-214 U-238 Th-232 Ac-228 Inches CPM CPM pCitgm pCi/gm pCVgm pC!g pCjgm pCigm pCi/m pC1gm UVA-RS-001-1 0 to 6 2031 10 17.4 1.0 Non-det 0.1 Non-det Non-det Non-det Non-det UVA-RS-001-2 6 to 18 2575 10 20.8 0.1 Non-det 0.3 0.2 0.3 Non-det Non-det UVA-RS-001-3 18 to 30 2626 10 22.3 0.1 Non-det 0.2 0.2 0.3 Non-det 0.2 UVA-RS-002-1 Oto 6 1906 10 21.5 0.6 Non-cet 0.3 0.1 Non-det Non-det UVA-RS-002-2 6 to 18 2618 10 20.7 Non-det 0.2 0.2 0.2 Non-det Non-det UVA-RS-003-1 0 to 6 2311 10 30.0 1.2 Non-det Non-det Non-det Non-det Non-det Non-det UVA-RS-003-2 6 to 18 3637 10 25.0 Non-det Non-det Non-det Non-det Non-dett Non-det Non-det LWVA-RS-003-3 18 to 30 3782 10 28.4 Non-det Non-det Non-det Non-det Non-det Non-det Non-det UVA-RS-004-1 0 to 6 1860 10 16.5 Nondet Non-det Non-det Non-det Non-et Non-et Nondet WIVA-RS-004-2 6 to 18 2471 15 18.8 Non det Non-det Non-et Nondet Nondet Non-et Nondet Upstream Creek Background UVA-BKGSL-001 0 to 6 N/A I N/A 19.0 INon-detjNon-detl 1.1 l 0.8 l 0.9 INon-detl 1.2 UVA-BKGSL-002 0 to 6 NtA I N/A 25.1 lNon-detjNon-detl 2.0 l 1.7 lNon-det Non-detl 2.0 Rock Face Background UVA-BKGSL-003-1 0 to 6 28253 111 45.0 Non-det Non-det 3.7 1.6 Non-det Non-det 3.4 UVA-BKGSL-003-2 6 to 18 N/A 119 54.4 jNon-det Non-det 3.2 1 1.2 4.4 Non-det 2.7 NVA-BKGSL-003-3 18 to 30 N/A 109 46.9 Non-det Non-det 3.4 0.8 Non-det Non-detl 3.4 Fill Dirt Background UVA-BKGSL-004-1 Oto 6 19214 96 32.4 Non-det Non-det 3.4 1.1 l Non-det Non-det 3.7 UVA-BKGSL-004-2 6to 18 N/A 130 35.3 Non-det Non-det 4.2 2.05 Non-det Non-det 4.5 UVA-BKGSL-004-3 18 to 30 N/A 127 39.6 Non-det Non-det 3.6 1.3 1.2 Non-det 4.0 Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a non-standard preparationof sample for homogeneous mixture and drying.
14
UVAP Continuing Characterization:
Reactor Pool Soil Areas Offsite Lab Results for Part-61 Analysis Table 9 Analysis Code Isotope Run Client Name Sample Type Client ID Report Units Result Uncertainty MDA AmNT AM-241 I Safety & Ecology Consultants LCS WCS PO~g 4.67 0.85 0.04 Am241 AM-241 1Safety & Ecology Consultants LCS LCS pCl/g 4.67 0.85 0.04 GLEPS AM-241 I Safety & Ecology Consultants LCS LCS pCI/g 3738.00 406.90 5.17 AmNT AM-241 1Safety & Ecology Consultants MBL BLANK pCi/g 0.01 0.03 0.06 Am241 AM-241 1Safety & Ecology Consultants MBL BLANK pCi/g 0.01 0.03 0.06 Am241 AM-241 I Safety & Ecology Consultants TRG UVA-PCC-001 PClIg 0.01 0.03 0.08 AmNT AM-241 1Safety & Ecology Consultants TRG UVA-PCC-001 pCilg 0.01 0.03 0.08 Am241 AM-241 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCilg 0.71 0.27 0.10 AmNT AM-241 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCiVg 0.88 0.44 0.07 Am241 AM-241 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 1.22 0.38 0.11 AmNT AM-241 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pClIg 1.88 0.74 0.08 AmNT AM-243 1Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.01 0.01 0.05 AmNT AM-243 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 0.75 0.29 0.07 AmNT AM-243 1Safety & Ecology Consultants TRG UVA-PSL-003-4 1.69 0.51 0.08 AmNT CM-244 1Safety & Ecology Consultants LCS LCS 5.79 1.02 0.08 pCI/g Am241 CM-244 I Safety & Ecology Consultants LCS LCS 5.79 1.02 0.08 AmNT CM-244 I Safety & Ecology Consultants MBL BLANK 0.01 0.03 0.08 pCi/g Am241 CM-244 I Safety & Ecology Consultants MBL BLANK 0.01 0.03 0.08 pCi/g AmNT CM-244 1Safety & Ecology Consultants TRG UVA-PCC-001 -0.01 0.01 0.09 Am241 CM-244 I Safety & Ecology Consultants TRG WA-PCC-001 -0.01 0.01 0.09 PCVg AmNT CM-244 1Safety & Ecology Consultants TRG UVA-PSL-002-5 0.18 0.22 0.07 Am241 CM-244 1Safety & Ecology Consultants TRG UVA-PSL-002-5 0.14 0.11 0.13 AmNT CM-244 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCl/g 0.66 0.37 0.09 Am241 CM-244 I Safety & Ecology Consultants TRG UVA-PSL-003-4 0.43 0.20 0.12 15
UVAP Continuing Characterization:
Reactor Pool Soil Areas Offsite Lab Results for Part61 Analysis Table 9 Analysis Code Isotope Run Client Name Sampfe Type Client ID Report Units Result Uncertainty MDA FeO55 CO-57 I Safety & Ecology Consultants LCS LCS pCi/g 3548.00 450.50 11.29 GLEPS CO-57 1Safety & Ecology Consultants LCS LCS pCvg 1396.00 189.60 4.17 GLEPS CO-57 1Safety & Ecology Consultants MBL BLANK pcilg 0.08 0.08 0.11 Gamma CO-57 I Safety & Ecology Consultants MBL BLANK pCi/g 0.00 0.01 0.02 Gamma CO-57 1Safety & Ecology Consultants TRG UVA-PCC-001 pCiIg 0.15 0.10 0.12 GLEPS CO-57 I Safety & Ecology Consultants TRG WA-PCC-001 M~/g 0.01 0.06 0.12 GLEPS CO-57 I Safety & Ecology Consultants TRG WA-PSL-002-5 pCYg -0.01 0.04 0.08 Gamma CO-57 1Safety & Ecology Consultants TRG WA-PSL-002-5 pCi1g 0.01 0.06 0.09 GLEPS CO-57 I Safety & Ecology Consultants TRG WA-PSL-003-4 pCilg -0.05 0.07 0.12 Gamma CO-57 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCl/g -0.09 0.11 0.14 Gamma CO-60 I Safety & Ecology Consultants LCS LCS pCi/g 262.40 19.50 1.19 Gamma CO-60 1Safety & Ecology Consultants MBL BLANK M/il -0.01 0.02 0.04 Gamma CO-60 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 29.81 2.22 0.34 Gamma CO-60 I Safety & Ecology Consultants TRG UVA-BKG-SL-001 pCi/g 0.14 0.13 0.27 Gamma CO-60 1Safety & Ecology Consultants TRG WA-PSL-002-5 pCl/g 16.26 1.21 0.21 Gamma CO-60 t Safety & Ecology Consultants TRG WA-PSL-003-4 pCilg -0.01 0.09 0.15 Gamma CS-137 I Safety & Ecology Consultants LCS LCS pCilg 156.90 16.66 1.03 Gamma CS-137 I Safety & Ecology Consultants MBL BLANK pCI/g 0.00 0.02 0.04 Gamma CS-137 1Safety & Ecology Consultants TRG WA-PCC-001 pCi/g 0.21 0.20 0.31 Gamma CS-137 I Safety & Ecology Consultants TRG WA-PSL-002-5 0.00 0.11 0.18 PCI/g Gamma CS-137 I Safety & Ecology Consultants TRG WA-PSL-003-4 0.03 0.10 0.18 Gamma EU-152 1Safety & Ecology Consultants MBL BLANK pCi/g 0.01 0.13 0.27 Gamma EU-152 I Safety & Ecology Consultants TRG WA-PCC-001 pCi/g 0.93 0.66 1.26 Gamma EU-152 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 0.33 0.55 0.84 16
UVAP Continuing Characterization:
Reactor Pool Soil Areas OfMsite Lab Results for Part-61 Analysis Table 9 Analysis Code Isotope Run Client Name Sample Type Client ID Report Units Result Uncertainty MDA Gamma EU-I52 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCVg 0.65 0.61 1.06 Gamma EU-154 1Safety & Ecology Consultants MBL BLANK pCIlg -0.02 0.05 0.10 Gamma EU-154 I Safety & Ecology Consultants TRG UVA-PCC-001 pC~g -0.03 0.36 0.60 Gamma EU-154 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 0.07 0.26 0.47 Gamma EU-154 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCYg -0.19 0.29 0.42 Gamma EU-155 I Safety & Ecology Consultants MBL BLANK PClvg 0.01 0.04 0.07 Gamma EU-155 I Safety & Ecology Consultants TRG UVA-PCC-001 pcifg 0.06 0.22 0.32 Gamma EU-155 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pcilg 0.31 0.17 0.27 Gamma EU-155 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pci/g 2.43 0.39 0.40 FeO55 FE-55 ISafety & Ecology Consultants MBL BLANK pci/g -0.75 1.16 1.94 Fe055 FE-55 I Safety & Ecology Consultants TRG UVA-PCC-001 pClIg -0.15 0.83 1.47 FeO55 FE-55 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g -0.27 0.75 1.29 FeO55 FE-55 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.20 0.87 1.54 H0003 H-3 I Safety & Ecology Consultants LCS LCS pCi/g 117.07 4.46 3.86 H0003 H-3 I Safety & Ecology Consultants MBL BLANK pCvg 1.89 2.19 3.67 H0003 H-3 1Safety & Ecology Consultants TRG UVA-PCC-001 pCIvg 1.70 1.97 3.30 H0003 H-3 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pC11g 1.68 1.94 3.26 H0003 H-3 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pC11g 0.00 1.92 3.29 GLEPS 1-129 I Safety & Ecology Consultants MBL BLANK pCi/g -0.17 0.36 0.68 GLEPS 1-129 I Safety & Ecology Consultants TRG UVA-PCC-001 pC1Ig -0.13 0.24 0.48 GLEPS 1-129 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g -0.06 0.25 0.47 GLEPS 1-129 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCivg 0.00 0.31 0.57 Gamma K-40 I Safety & Ecology Consultants MBL BLANK p~lvg 0.02 0.24 0.35 Gamma K-40 I Safety & Ecology Consultants TRG UVA-PCC-001 pCivg 12.45 2.60 1.46 17
UVAP Continuing Characterization:
Reactor Pool Soil Areas Offsite Lab Results for Part-61 Analysis Table 9 Analysis Code Isotope Run Client Name Sample TypO Client ID Report Units Result Uncertainty MDA Gamma K-40 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCl/g 43.60 5.11 1.00 Gamma K-40 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCI/g 43.65 5.16 1.01 NiO63 NI-63 1Safety & Ecology Consultants LCS LCS pci/g 938.22 11.90 5.07 N1063 NI-63 I Safety & Ecology Consultants MBL BLANK p~lIg 4.43 3.07 5.07 Nl063 NI-63 1Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 1.30 0.61 1.00 Ni083 NI-63 1Safety & Ecology Consultants TRG UVA-BKG-SL-001 pCi/g 0.00 0.58 1.00 N1063 NI-63 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCilg 0.00 0.58 1.00 NiO63 NI-63 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCilg 0.00 0.58 0.99 PuISO PU-238 1Safety & Ecology Consultants LCS LCS p0119 4.65 1.16 0.19 PulSO PU-238 1Safety & Ecology Consultants MBL BLANK pClfg 0.07 0.10 0.18 PulSO PU-238 I Safety & Ecology Consultants TRG UVA-PCC-001 pCiYg 0.01 0.02 0.06 PulSO PU-238 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCvg 0.00 0.00 0.03 PulSO PU-238 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pcilg 0.00 0.00 0.02 PulSO PU-238 I Safety & Ecology Consultants TRG Process Blank pCivg 0.00 0.00 0.04 PulSO PU-239 I Safety & Ecology Consultants LCS LCS pCVg 6.49 1.54 0.15 PulSO PU-239 I Safety & Ecology Consultants MBL BLANK pCVg 0.00 0.01 0.10 PulSO PU-239 I Safety & Ecology Consultants TRG UVA-PCC-001 pCilg 0.01 0.03 0.07 PuISO PU-239 I Safety & Ecology Consultants TRG WVA-PSL-002-5 pci/g 0.00 0.00 0.03 PulSO PU-239 I Safety & Ecology Consultants TRG UVA-PSL-003-4 0.01 0.02 0.02 pCivg PuISO PU-239 1Safety & Ecology Consultants TRG Process Blank 0.00 0.00 0.04 Pu241 PU-241 I Safety & Ecology Consultants LCS LCS 253.00 6.83 5.83 pCivg Pu241 PU-241 1Safety & Ecology Consultants MBL BLANK 1.17 0.64 1.05 Pu241 PU-241 I Safety & Ecology Consultants TRG UVA-PCC-001 pCilg 0.94 1.01 1.70 Pu241 PU-241 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCitg 1.23 0.67 1.10 18
UVAP Continuing Characterization:
Reactor Pool Soil Areas Offstte Lab Results for Part-61 Analysis Table 9 Analysis Code Isotope Run Client Name Sample Type Client ID Report Units Result Uncertainty MDA Pu241 PU-241 1Safety & Ecology Consultants TRG UVA-PSL-003-4 PCIig 1.73 0.64 1.04 Pu4ISO PU242 1Safety & Ecology Consultants LCS LCS pCi/g 4.28 0.85 0.07 Pu41SO PU242 1Safety & Ecology Consultants MBL BLANK pCiIg 0.06 0.07 0.09 Pu41SO PU242 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.02 0.03 0.03 PUMlSO PU242 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCilg 0.02 0.01 0.01 PU4ISO PU242 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.00 0.01 0.01 PU41SO PU-244 I Safety & Ecology Consultants MBL BLANK pCi/g 0.01 0.04 0.12 Pu41SO PU-244 1Safety & Ecology Consultants TRG UVA-PCC-001 pM/g 0.02 0.03 0.04 PU4ISO PU-244 1Safety & Ecology Consultants TRG UVA-PSL-002-5 PClfg 0.01 0.01 0.01 Pu41SO PU-244 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.02 0.02 0.01 Sr890...2C SR-89 I Safety & Ecology Consultants LCS LCS pCin -1.26 1.47 1.20 Sr89O-2C SR.-89 1Safety & Ecology Consultants MBL BLANK pCi/I 0.18 0.47 1.13 Sr89032C SR-89 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/I 0.13 0.11 0.22 Sr890..2C SR-89 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/I 0.03 0.10 0.23 Sr890-2C SR-89 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCI/I -0.08 0.10 0.23 Sr89O..2C SR-90 1Safety & Ecology Consultants LCS LCS pCI/1 12.72 0.49 0.91 Sr802 SR-90 1Safety & Ecology Consultants MBL BLANK pC/IA -0.30 0.09 0.89 Sr890-2C SR-90 I Safety & Ecology Consultants TRG WVA-PCC-001 pCiII -0.02 0.02 0.15 Sr890...2C SR-90 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/I 0.02 0.01 0.15 Sr890_2C SR-90 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/I 0.10 0.01 0.14 TC099 TC-99 I Safety & Ecology Consultants LCS LCS pCl/g 811.04 5.15 1.39 Tc099 TC-99 I Safety & Ecology Consultants MBL BLANK pCi/g 0.00 0.91 1.54 TC099 TC-99 I Safety & Ecology Consultants TRG UVA-PCC-I01 pCi/g -0.04 0.07 0.13 TC090 TC-99 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 0.11 0.09 0.15 19
UVAP Continuing Characterization:
Reactor Pool Soil Areas Offsite Lab Results for Part-61 Analysis Table 9 Analysis Code Isotope 1Run Client Name Sample Type Client ID Report Units Result Uncertainty MDA Tc099 TC-99 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/9 0.00 0.09 0.15 ThISO TH-228 1Safety & Ecology Consultants LCS LCS pCl/g 4.85 0.94 0.07 ThISO TH-228 I Safety & Ecology Consultants MBL BLANK pCi/g 0.05 0.05 0.03 ThISO TH-228 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.27 0.10 0.04 ThISO TH-228 i Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 2.59 0.48 0.03 ThISO TH-228 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCig 8.00 1.53 0.05 ThISO TH-230 I Safety & Ecology Consultants LCS LCS pCiIg 4.79 0.93 0.03 ThISO TH-230 I Safety & Ecology Consultants MBL BLANK pci0/ 0.85 0.25 0.03 ThISO TH-230 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.46 0.14 0.04 ThISO TH-230 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCVg 1.79 0.35 0.04 ThISO TH-230 I Safety & Ecology Consuttants TRG UVA-PSL-003-4 pCVg 5.95 1.16 0.02 ThISO TH-232 1Safety & Ecology Consultants LCS LCS pClg 4.90 0.95 0.06 ThISO TH-232 I Safety & Ecology Consultants MBL BLANK pCi/g 0.05 0.05 0.06 ThISO TH-232 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/9 0.29 0.10 0.04 ThISO TH-232 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCI/g 2.50 0.47 0.03 ThISO TH-232 I Safety & Ecology Consultants TRG WVA-PSL-003-4 pCi/g 7.01 1.35 0.06 Gamma TH-234 1Safety & Ecology Consultants MBL BLANK pCi/g -0.19 0.32 0.60 Gamma TH-234 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.35 2.25 2.43 Gamma TH-234 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pci/9 1.31 1.94 2.07 Gamma TH-234 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pClg 8.76 2.82 4.03 Sr890_2C TOTAL SR I Safety & Ecology Consultants LCS LCS pCi/I 11.46 0.98 0.78 Sr890_2C TOTAL SR 1Safety & Ecology Consultants MBL BLANK pCi/I -0.12 0.38 0.70 Sr890_2C TOTAL SR I Safety & Ecology Consultants TRG UVA-PCC-001 pCill 0.10 0.07 0.12 Sr890_2C TOTAL SR I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/i 0.05 0.08 0.13 20
UVAP Continuing Characterization:
Reactor Pool Soil Areas Offsite Lab Results for Part-61 Analysis Table 9 Analysis Code Isotope Run Client Name Sample Type Client ID Report Units Result Uncertainty MDA Sr890_2C TOTAL SR I Safety & Ecology Consultants TRG UVA-PSL-003-4 PCM/ 0.02 0.08 0.14 UUISO U-234 I Safety & Ecology Consultants LCS LCS pCilg 6.32 1.24 0.08 UUISO U-234 1Safety & Ecology Consultants MBL BLANK pCi/g 0.05 0.05 0.03 UUISO U-234 I Safety & Ecology Consultants TRG LUVA-PCC-001 pCilg 0.35 0.15 0.08 UUISO U-234 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pci/g 1.69 0.41 0.10 UUISO U-234 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCl/g 5.00 1.03 0.10 UUISO U-235 1Safety & Ecology Consultants LCS LCS PCIvg 0.32 0.17 0.06 UUISO U-235 I Safety & Ecology Consultants M8L BLANK pCvg 0.02 0.03 0.04 UUISO U-235 I Safety & Ecology Consultants TRG LUVA-PCC-001 pCIvg 0.02 0.04 0.05 UUISO U-235 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCVg 0.11 0.10 0.11 UUISO U-235 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pClvg 0.28 0.17 0.10 UUISO U-236 1Safety & Ecology Consultants MBL BLANK pCi/g 0.01 0.03 0.08 UUISO U-236 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.02 0.03 0.04 UUISO U-236 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 0.00 0.00 0.04 UUISO U-236 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCj/g 0.13 0.11 0.11 UUISO U-238 1Safety & Ecology Consultants *CS LCS pCiig 7.12 1.38 0.08 UU1SO U-238 I Safety & Ecology Consultants MEL BLANK pcitg 0.02 0.04 0.06 UUISO U-238 I Safety & Ecology Consultants TRG UVA-PCC-001 pCvg 0.49 0.18 0.04 UUISO U-238 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCivg 1.55 0.39 0.08 UUISO 11-238 1Safety & Ecology Consultants TRG LUVA-PSL-003-4 pCl/g 4.93 1.02 0.13 Gamma ZN-65 1Safety & Ecology Consultants M8L BLANK pClvg 0.05 0.04 0.07 Gamma ZN-85 1Safety & Ecology Consultants TRG UVA-PCC-001 pCVg -0.14 0.51 0.88 Gamma ZN-65 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g -0.15 0.33 0.50 Gamma ZN-65 I Safety & Ecology Consultants TRG UrVA-PSL-003-4 pCI/g -0.11 0.21 0.30 21
UVAP Continuing Characterization:
Reactor Pool Interior Summary The reactor pool structure is approximately four meters wide, ten meters long and nine meters in depth. The pool is separated into two halves by a concrete buttress that housed the reactor pool gate. The pool is oriented slightly off from true North to South. For the purpose of this survey, the pool structure interior surface has been referenced in two sections consisting of the north section and its three walls, and the south section and its three walls. Half of each buttress wall will be included in its adjoining wall and floor section. There are two beam ports located in the south section, on the west wall, approximately 2 meters off the pool floor. The north beam port (referred to as the hot beam port or #1 beam port) was activated by the reactor's neutron beam and has been removed along with the activated concrete surrounding the port. The second beam port area (referred to as the cold beam port or #2 beam port) was not used as extensively and only the first 18-inches was removed from the poolside with a portion of surrounding concrete. The pool surface paint was removed by means of a hydrolazer. The knee wall surrounding the pool was cut off flush to the reactor room floor and disposed of in accordance with Work Package 002, Radiological Surveys to Release Material for Unrestricted Use.
Five full width by 12 inches high sections were removed from the aluminum gate guide, to provide access that allowed the determination of the condition of the underlying concrete surface.
Co-60 has been determined to be the major facility related contaminate. The DecommissioningPlan provides a Derived Concentration Guideline Level (DCGL) for Co-60 of 7100-dpm/lOOcm total activity and 710-dpm/lOOcm 2 removable activity.
A reference Grid system was used for this survey. The grid was set at I-meter intervals with the grid starting location being the southwest corner of the room.
- 1. Surface Scan Surveys Portions of the pool floor were scanned for surface beta radioactivity, using a Ludlum Model 239-IF floor monitor with a Model 43-37 large-area (582 cm2 ) gas proportional detector, with a scan path of 0.44 m (1.44 ft) operated in the alpha-plus-beta detection mode. A Ludlum Model 2221 ratemeter/scaler was used to provide detector power and monitor the scan results.
Scans of wall surfaces were performed using a Ludlum Model 43-68 handheld 125 cm 2 gas proportional detector with a Ludlum Model 2221 ratemeter/scaler. Scanning was accomplished by moving the detector over the surface at a speed of approximately 10 cm per second (approximately 4 inches per second). The distance between the detector and the surface was maintained at a practical minimum, consistent with surface conditions.
Gamma scans were performed using a Ludlum Model 44-10 handheld sodium iodide detector with a Ludlum Model 2221 ratemeter/scaler. The scan was performed by moving the detector in a serpentine pattern, while advancing at a speed of approximately 0.5 m per second.
The distance between the detector and surface was maintained within 5 cm.
The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions. The observed lowest to highest range was recorded on the associated survey map.
1
UVAP Continuing Characterization:
Reactor Pool Interior Summary The beta/alpha scans ranged from 150 cpm to 2000 cpm with one measurement of 16,000 cpm utilizing the 43-68 probe and 1500 cpm to 4700 cpm with the 43-37 probe. The gamma scans ranged from 9000 cpm to 17000 cpm. Surveys UVAP- 0387, 0388, 0389, 0390, 0578, 0632, and 0712 are available in the UVAP files.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity were performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. Counts were integrated for a one-minute counting interval. Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e.,
with the detector face uncovered); this measurement included contributions from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm (Y2-inch thick). The detector response for this second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered (shielded) detector represents the level of beta activity. Measurements were performed at elevated locations as identified by scans and at locations representative of the general surface area. Direct integrated readings ranked from 293 dprn/lOOcm 2 to 17,632 dpm/l00cm 2 with one measurement of 56,000-dpm/100 cm . Surveys UVAP- 0387, 0388, 0389, 0390, 0578, 0632, and 0712 are available in the UVAP files.
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm 2 (15.5 in2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. Smear sample activity ranged from <MDA (22.99 dpm/lOOcm 2 ) to 101.3 dpm/lOOcm 2. Surveys UVAP- 0387, 0388, 0389, 0390, and 0578 are available in the UVAP files.
- 4. Drain Surveys Drains and piping associated with the reactor pool are addressed in the Impacted Drain Lines and Piping Summary.
2
UVAP Continuing Characterization:
Reactor Pool Interior Summary
- 5. Volumetric Sample Collection and Analysis Samples were taken from areas where the possibility of contamination was identified by elevated measurements. Twenty-four core samples were taken from the reactor pool floor and walls. See Figure 1 for locations. Eight samples, approximately 4" to 12" in depth were obtained for surface activity determination. The outer .25" (representing the pool wetted surface) of these samples were composited for offsite activity determination.
Fourteen borings were through the floor and wall to obtain soil samples from below the concrete surfaces. Soil from cores 18 through 23 was for soil migration determination from contaminated soil under "I" core in the reactor room. See Table 1 for results by onsite gamma spectroscopy. Core number 13 near the north 1beam port was obtained to a depth of 18" for concrete activation determination.
Initial pool floor core sample #9 taken on 12/18/02 indicated activity of 4.72 pCi/g at a depth of 42 to 54 inches. This elevated activity is believed to have resulted from cross contamination, from the beam port concrete removal operation. Two additional sample locations were selected adjacent to #9 sample location and labeled PF1 And PF1A. Reactor pool core bore PFI surface grab sample indicated activity for Co-60 at 3.7 pCi/gram. Auger samples from PFI and PFIA contained no activity from licensed material above DCGL levels to the depth of 90 inches.
Samples were submitted for onsite Gamma isotopic analyses. A composite sample of the pool 4-inch surface cores designated UVA-PCC-001 and two soil samples, one from core # 9 designated UVA-PSL-002-5 and core # 8 designated TVA-PSL-003-4 were managed under chain-of-custody procedures and submitted to the offsite laboratory, for radionuclide analyses.
See offsite lab report for results, Table 2.
- 6. Reactor Pool Gate Guides The reactor pool gate guides are included in the middle pool buttresses, on centerline, between the north half and south half of the pool. The area where the gate guide sides contact the concrete have separated and opened a void space from /8th of an inch to one inch in width. The aluminum gate guide is embedded in the interior faces of the east and west buttresses, and in the top face of the floor grade beam, forming a "UT" shape. The guide embedment consists of a 12-inch deep aluminum channel and an 8-inch deep aluminum channel. The 12-inch deep channel is embedded in the concrete with the toes of the channel flanges flush with the concrete surface, to form a gate guide channel in the concrete face. The 8-inch deep channel is welded to the backside of the 12-inch channel to act as an anchor for the 12-inch deep aluminum channel. The total depth of the embedment is approximately 11 inches. The length of the embedment is approximately 25 feet vertically in each of the two buttress interior faces, and approximately 7 feet horizontally in the top face of the floor beam.
A gamma scan with a L2221 and sodium iodide crystal was performed along the outer surface of the guide edge and concrete interface. A Beta scan with a L2221 and 43-68 probe was performed along the outer surface of the guide edge and concrete interface. Direct one minute integrated static measurements were performed at each elevated area of concern, as determined by the gamma or beta scans. Five locations were chosen to perform surveys on the unexposed 3
UVAP Continuing Characterization:
Reactor Pool Interior Summary surfaces of the gate guide. The two highest static count areas from each side, and one from the bottom guide area, were then removed and static counts performed on the exposed interface concrete surfaces. Each location had two; 2-inch core bores removed to a depth of 8-inches.
Surveys of these core bores, the 12-inch channel, the 8-inch channel and the concrete surfaces exposed were all less then the DCGL for Co-60. Surveys UVAP-0390, 0551, 0576, 0578, 0632 are available in the UVAP files.
- 7. Conclusions Based on results of the initial surveys and surveys after D&D evolutions, no further remediation is required. The reactor pool is ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 2 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
4
Reactor Pool Interior Walls &Floor Concrete Cores Figure 1 N-I N < l1l I
120Qd -
1 I I 1 X - I 14I 11 = = _ J6 _
-~~ _ ~~ A:::-:i$.
- - - -~~?~ i-X f -
17
- Shallow corc bom I
o Thtough to soD cor bore I
5 I I
UVAP Continuing Characterization:
Reactor Pool Interior Summary Reactor Pool Interior Walls & Floor Soil Results Table I Onsite Results Gamma Sample number Interval Logging Gamma S ectrosc Note 1 44-2 K-40 Cs-137 Co-60 Pb-212 Bi-214 Pb-214 Ra-226 Ac-228 U-238 Inches CPM pCgm pC0/gm pCpgrn pCi pCiiggm pCmm p pCilgm pCi/gm Pool core # 6 0 to 6 10985 28.6 Non-det Non-det 0.19 0.37 0.34 Non-det Non-det Non-det Pool core # 6 6 to 18 13527 36.6 Non-det Non-det 2.96 1.18 1.28 Non-det 2.78 Non-det Pool core # 6 18 to 30 14705 37.3 Non-det Non-det 2.69 1.24 1.19 2.14 2.69 1.73 Pool core # 6 30 to 42 13718 34.4 Non-det Non-det 4.21 1.69 1.65 5.11 4.09 Non-det Pool core # 6 42 to 54 14784 45.6 Non-det Non-det 3.94 1.89 1.72 4.07 3.34 Non-det Pool core # 7 0 to 6 20262 27.2 Non-det 0.90 2.85 1.24 1.40 2.49 Non-det Pool core # 7 6 to 18 22437 36.1 Non-det Non-det 4.80 3.09 3.19 7.49 4.87 4.50 Pool core # 7 18 to 30 21510 38.2 Non-det Non-det 7.96 2.90 3.62 8.66 8.17 Non-det Pool core # 7 30 to 42 21048 34.7 Non-det Non-det 6.68 2.10 2.42 5.05 5.98 Non-det Pool core # 7 42 to 54 21552 37.7 Non-det Non-det 10.7 2.84 3.50 8.24 10.6 Non-det Pool core#8 0 to 6 11529 32.1 Non-det Non-det 1.76 1.10 1.16 2.96 1.80 Non-det Pool core # 8 6 to 18 13556 40.4 Non-det Non-det 3.24 1.60 1.68 4.61 2.89 Non-det Pool core # 8 18 to 30 23559 33.8 Non-det Non-det 8.22 2.96 3.40 7.13 8.21 4.53 Pool core # 8 30 to 42 21869 39.6 Non-det Non-det 8.05 3.10 3.53 8.25 7.58 6.08 Pool core # 8 42 to 54 17693 42.9 Non-det Non-det 4.57 2.23 2.13 7.23 5.07 4.78 Pool core # 9 0 to 6 9694 41.0 Non-det Non-det 1.71 8.42 8.10 1.60 Non-det Pool core # 9 6 to 18 10241 45.1 Non-det Non-det 1.96 0.96 1.13 4.65 2.16 Non-det Pool core # 9 18 to 30 10401 42.3 Non-det Non-det 2.38 1.34 1.42 4.33 2.36 Non-det Pool core # 9 30 to 42 9948 41.0 Non-det Non-det 2.72 1.17 1.17 3.67 2.47 Non-det Pool core 9 42 to 64 8813 38.8 Non-det 4.72 2.03 1.02 0.97 1.89 Non Note 2 _ ___ __ __ _ Non-det Pool core #9 54 to 66 9691 41.2 Non-det Non-det 2.01 1.11 1.23 1.91 Non-det Pool core #9 66 to 78 10213 40.4 Non-det Non-det 2.48 1.14 1.32 2.64 2.42 Non-det Pool core #9 78 to 90 10321 37.6 Non-det Non-det 2.04 0.95 0.98 3.25 2.23 Non-det Pool core # 9A Surface N/A 29.2 Non-det 3.72 0.61 0.20 0.17 Non-det Non-det Non-det Pool core # 9A 0 to 6 N/A 29.5 Non-det 1.68 1.45 0.51 0.52 2.62 1.41 Non-det Pool core # 9A 6 to 18 N/A 34.0 Non-det Non-det 1.87 0.89 0.81 2.41 1.58 Non-det Pool core # 9A 18 to 30 N/A 30.9 Non-det 1.11 1.86 0.73 0.76 Non-det 2.01 Non-det Pool core # OA 30 to 42 N/A 33.2 Non-det Non-det 1.66 1.01 0.90 Non-det Non-det 1.62 Pool core # 9A 42 to 54 N1A 31.0 Non-det Non-det 1.96 0.86 0.78 2.84 2.19 Non-det Pool core # 9A 54 to 66 N/A 31.5 Non-det Non-det 2.16 1.00 1.10 2.76 2.01 1.13 Pool core # 9A 66 to 78 N/A 29.2 Non-det Non-det 2.71 1.15 1.32 Non-e 2.53 NonAAet on-det Denotes Non- Detectable ote 1: Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a Non-standard preparations of sample for homogeneous mixture and drying.
Mote 2: Two additional auger samples taken on both sides of the original sample to verify Co-60 activity at 42 to 54-Inch Depth. No activity noted In additional samples. Initial results believed due to cross contamination of sample.
6
UVAP Continuing Characterization:
Reactor Pool Interior Summary Reactor Pool Interior Walls & Floor Soil Results Table 1 Onsite Results cont.
Beta Sample number Interval Scan Gamma S ectrosooy Note I G
44-9 K-40 Cs-137 Co-60 Pb-212 Bi-214 Pb-214 Ra-226 Ac-228 U-238 Inches CPM pCjgm pCilgm pCigm pCigm pCil/gm pC/gm Pi/rgm pCi/lgm pC/gm Pool core # 9 O to 6 121 28.9 Non-det 1.48 2.87 1.17 1.07 Non-det 3.01 Non-det Pool core # 9B 6 to 18 143 32.3 Non-det 0.97 1.72 0.61 0.73 3.58 2.34 Non-det Pool core # 9B 18 to 30 158 32.8 Non-det Non-det 2.88 1.30 1.50 Non-det 2.40 0.94 Pool core # 9B 30 to 42 155 35.9 Non-det Non-det 2.04 1.48 1.26 Non-det 1.94 Non-det Pool core # 9B 42 to 54 131 31.0 Non-det Non-det 2.07 1.46 1.39 0.87 1.80 Non-det Pool core # 9B 54 to 66 143 33.2 Non-det 0.98 2.20 1.27 1.24 2.77 1.74 Non-det Pool core # 9B 66 to 78 169 30.1 Non-det Non-det 2.40 1.26 1.19 Non-det 2.27 Non-det Pool core # 9B 78 to 90 147 32.7 Non-det Non-det 3.16 1.73 1.72 2.94 3.35 1.57 Pool core # 1 0 to 6 N/A 25.9 Non-det Non-det 1.42 0.71 0.71 1.09 Non-det Non-det Pool core # 1 0 to 6 NIA 28.1 Non-det Non-det 0.36 0.43 0.33 Non-det Non-det Non-det Pool core # 18 0 to 18 NJA 9.04 Non-det Non-det 0.65 0.67 0.57 Non-det Non-det Non-det Pool core # 18 18 to 30 76 19.1 Non-det Non-det 2.34 1.32 1.01 2.20 2.31 Non-det Pool core # 18 30 to 36 88 18.8 Non-det Non-det 2.76 1.09 1.04 Non-det 2.94 1.12 Pool core # 19 0 to 6 60 12.0 Non-det Non-det 1.54 1.21 1.00 Non-det 1.56 Non-det Pool core # 19 6 to 18 92 15.5 Non-det Non-det 1.69 1.13 1.08 1.26 1.88 Non-det Pool core # 19 18 to 30 72 16.2 Non-det Non-det 1.80 0.96 0.91 2.16 2.00 Non-det Pool core # 19 30 to 42 55 10.8 Non-det Non-det 1.67 1.16 0.98 Non-det 1.54 Non-det Pool core # 19 42 to 48 80 17.2 Non-det Non-det 1.98 1.36 1.06 Non-det 1.84 0.42 Pool core # 20 0 to 6 82 20.2 Non-det Non-det 1.59 0.82 0.96 3.13 1.86 0.96 Pool core # 20 6 to 18 93 20.8 Non-det Non-det 1.69 1.01 0.95 1.85 1.32 Non-det Pool core # 20 18 to 30 71 19.7 Non-det Non-det 1.88 0.89 0.94 1.62 1.87 Non-det Pool core # 20 30 to 42 70 20.8 Non-det Non-det 1.69 0.88 1.03 1.77 Non-det 0.11 Pool core # 20 42 to 64 71 21.6 Non-det Non-det 1.65 0.97 0.79 Non-det 1.80 Non-det Pool core # 21 0 to 6 96 25.9 Non-det Non-det 1.93 1.32 1.39 2.97 2.48 1.57 Pool core # 21 6 to 18 110 27.8 Non-det Non-det 2.38 1.39 1.34 2.82 1.70 1.09 Pool core # 21 18 to 30 83 26.8 Non-det Non-det 2.41 1.34 1.42 3.54 2.21 Non-det Pool core # 21 30 to 42 105 30.0 Non-det Non-det 2.14 1.14 1.28 1.90 2.02 Non-det Pool core # 21 42 to 54 86 23.9 Non-det Non-det 1.89 0.93 1.31 Non-det 1.56 Non-det Pool core # 22 0 to 6 102 24.0 Non-det Non-det 1.96 1.37 1.23 2.16 1.89 Non-det Pool core # 22 6 to 18 78 21.5 Non-det Non-det 1.97 0.86 1.11 2.29 1.79 Non-dat Pool core # 22 18 to 30 96 22.7 Non-det Nondet 2.14 1.09 1.28 2.26 1.89 Non-et Pool core # 22 30 to 42 86 19.6 Non-det Non-det 1.87 1.20 0.97 2.96 1.86 Non-det Pool core # 22 42 to 54 82 23.4 Non-det Non-dt 2.03 1.24 1.07 2.52 2.01 Non-det N4on-det Denotes Non- Detectable NJote 1: Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a Non-standard preparations of sample for homogeneous mixture and drying.
7
IVAP Continuing Characterization:
Reactor Pool Interior Summary Reactor Pool Interior Walls & Floor Soil Results Table 1 Onsite Results cont.
Gamma Sample number Interval Logging _ Gamma S ectrosc py Note I K-40 Cs-137 Co-60 Pb-212 Bi-214 Pb-214 Ra-226 Ac-228 U-238
____________ Inches CPM pCigM m pC0ggm p0 p p011gmPC!/
m pC PO/gm p0i/gmr Pool core #23 0 to 6 95 16.0 Non-det Non-det 1.19 0.89 0.91 2.37 1.19 Non-det Pool core #23 6 to 18 91 15.7 Non-det Non-det 1.24 0.80 0.70 Non-det 1.27 Non-det Pool core # 23 18 to 30 87 22.1 Non-det Non-det 1.49 0.67 0.83 1.67 1.66 1.39 Pool core # 23 30 to 42 105 26.3 Non-det Non-det 1.76 0.98 1.08 Non-det 1.93 Non-det Pool core # 23 42 to 54 103 25.4 Non-det Non-det 1.65 0.98 0.91 3.31 2.01 0.45 Pool core # 24 Oto 6 97 14.6 Non-det Non-det 1.00 0.52 0.63 Non-det Non-det Non-det Pool core # 24 6 to 18 88 19.6 Non-det Non-det 1.54 0.84 0.87 2.86 1.62 0.02 Pool core # 24 18 to 30 79 25.8 Non-det Non-det 1.84 1.07 1.00 3.00 1.71 Non-det Pool core # 24 30 to 42 100 25.5 Non-det Non-det 1.88 1.15 1.12 2.95 1.73 Non-det Pool core # 24 42 to 64 80 21.7 Non-det Non-det 1.77 0.89 0.90 3.44 1.61 Non-det Non-det: Denotes Non- Detectable Note 1: Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a Non-standard preparations of sample for homogeneous mixture and drying.
8
UVAP Continuing Characterization:
Reactor Pool Interior Summary Table 2 Offsite Laboratory Report AnalysIsCode Isotope Run CllentName SampteType CllentlD ReportUnits Result Uncertainty MDA AmNT AM-241 1Safety & Ecology Consultants LCS WCS pCi~g 4.67 0.85 0.04 Am241 AM-241 I Safety & Ecology Consultants LCS LWS poifg 4.67 0.85 0.04 GLEPS AM-241 1Safety & Ecology Consultants LCS LCS pOilg 3738.00 406.90 5.17 AmNT AM-241 I Safety & Ecology Consultants MBL BLANK PCi/g 0.01 0.03 0.06 Am241 AM-241 I Safety & Ecology Consultants MBL BLANK pCifg 0.01 0.03 0.06 Am241 AM-241 I Safety & Ecology Consultants TRG UVA-PCC-001 170lg 0.01 0.03 0.08 AmNT AM-241 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.01 0.03 0.08 Am241 AM-241 I Safety & Ecology Consultants TRG UVA-PSL-002-5 poilg 0.71 0.27 0.10 AmNT AM-241 ISafety & Ecology Consultants TRG UVA-PSL-002-5 pCiVg 0.88 0.44 0.07 Am241 AM-241 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 1.22 0.38 0.11 AmNT AM-241 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pcl/g 1.88 0.74 0.08 AmNT AM-243 1Safety & Ecology Consultants TRG UVA-PCC-001 pQi/g 0.01 0.01 0.05 AmNT AM-243 1Safety & Ecology Consultants TRG UVA-PSL-002-5 PCiVg 0.75 0.29 0.07 AmNT AM-243 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCilg 1.69 0.51 0.08 AmNT CM-244 I Safety & Ecology Consultants LCS LCS pCl1g 5.79 1.02 0.08 Am241 CM-244 I Safety & Ecology Consultants LCS LCS PO/lg 5.79 1.02 0.08 AmNT CM-244 1Safety & Ecology Consultants MBL BLANK pCi~g 0.01 0.03 0.08 Am241 CM-244 I Safety & Ecology Consultants MBL BLANK pO/lg 0.01 0.03 0.08 AmNT CM-244 1Safety & Ecology Consultants TRG UVA-PCC-001 poi/g -0.01 0.01 0.09 Am241 CM-244 1Safety & Ecology Consultants TRG UVA-PCC-001 pCilg -0.01 0.01 0.09 AmNT CM-244 I Safety & Ecology Consultants TRG UVA-PSL-002-5 PCilg 0.18 0.22 0.07 Am241 CM-244 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 0.14 0.11 0.13 AmNT CM-244 I Safety & Ecology Consultants TRG WVA-PSL-003-4 pCiYg 0.66 0.37 0.09 Am241 CM-244 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.43 0.20 0.12 FeO55 CO-57 I Safety & Ecology Consultants LCS LCS pCiVg 3548.00 450.50 11.29 GLEPS CO-57 I Safety & Ecology Consultants LCS LCS pCi/g 1396.00 189.60 4.17 GLEPS CO-57 I Safety & Ecology Consultants MBL BLANK pCiwg 0.08 0.08 0.11 Gamma cO-57 I Safety & Ecology Consultants MBL BLANK PCVg 0.00 0.01 0.02 Gamma CO-57 I Safety & Ecology Consultants TRG UVA-PCC-001 POilg 0.15 0.10 0.12 GLEPS CO-57 I Safety & Ecology Consultants TRG UVA-PCC-001 pCvg 0.01 0.06 0.12 9
UVAP Continuing Characterization:
Reactor Pool Interior Summary Table 2 Offsite Laboratory Report Ana"IysCode Isotope Run CllentName SampleType CllentlD ReportUnIts Result Uncertainty MDA GLEPS C0-57 I Safety & Ecology ConsultantssTRG UVA-PSL-002-5 pCVg -0.01 0.04 0.08 Gamma CO-57 I Safety & Ecology ConsultantssTRG UVA-PSL-002-5 pulg 0.01 0.06 0.09 GLEPS CO-57 1Safety & Ecology ConsultantssTRG UVA-PSL-003-4 pCi/g -0.05 0.07 0.12 Gamma C0-57 I Safety & Ecology Consultants3TRG UVA-PSL-003-4 pCVg -0.09 0.11 0.14 Gamma C0-60 1Safety & Ecology ConsultantssLCS LCS pCilg 262.40 19.50 1.19 Gamma c0-60 I Safety & Ecology Consultants MBL BLANK pClg -0.01 0.02 0.04 Gamma co-o0 1Safety & Ecology ConsultantssTRG UVA-PCC-001 pCilg 29.81 2.22 0.34 Gamma C0-60 1Safety & Ecology ConsultantssTRG UVA-BKG-SL-001 pCIg 0.14 0.13 0.27 Gamma C0-60 1Safety & Ecology ConsultantssTRG UVA-PSL-002-5 pCi/g 16.26 1.21 0.21 Gamma CO-0 I Safety & Ecology ConsultantssTRG UVA-PSL-003-4 pClg -0.01 0.09 0.15 Gamma CS-137 I Safety & Ecology ConsultantssLCS LCS pCVg 156.90 16.66 1.03 Gamma CS-137 I Safety & Ecology ConsultantssMBL BLANK pCilg 0.00 0.02 0.04 Gamma CS-137 I Safety & Ecology ConsultantssTRG UVA-PCC-001 pCig 0.21 0.20 0.31 Gamma CS-137 1Safety & Ecology ConsultantssTRG UVA-PSL-002-5 pCig 0.00 0.11 0.18 Gamma CS-137 I Safety & Ecology ConsultantssTRG UVA-PSL-003-4 pCI/g 0.03 0.10 0.18 Gamma EU-152 I Safety & Ecology Consultants;MBL BLANK POClg 0.01 0.13 0.27 Gamma EU-152 I Safety & Ecology ConsultantssTRG UVA-PCC-001 pCvg 0.93 0.66 1.26 Gamma EU-152 1Safety & Ecology ConsultantssTRG UVA-PSL-002-5 pCilg 0.33 0.55 0.84 Gamma EU-152 I Safety & Ecology Consultants;TRG UVA-PSL-003-4 pClg 0.65 0.61 1.06 Gamma EU-154 I Safety & Ecology ConsultantsWMBL BLANK pCVg -0.02 0.05 0.10 Gamma EU-154 1Safety & Ecology Consultants3TRG UVA-PCC-001 pCilg -0.03 0.36 0.60 Gamma EU-154 I Safety & Ecology ConsultantssTRG UVA-PSL-002-5 pCilg 0.07 0.26 0.47 Gamma EU-154 1Safety & Ecology Consultants5TRG UVA-PSL-003-4 pCig -0.19 0.29 0.42 Gamma EU-155 I Safety & Ecology ConsultantsiMBL BLANK pCI/g 0.01 0.04 0.07 Gamma EU-155 I Safety & Ecology ConsultantsiTRG UVA-PCC-001 pCVg 0.06 0.22 0.32 Gamma EU-155 1Safety & Ecology ConsultantsJTRG UVA-PSL-002-5 pCVg 0.31 0.17 0.27 Gamma EU-155 I Safety & Ecology ConsultantssTRG UVA-PSL-003-4 pCilg 2.43 0.39 0.40 FeO55 FE-55 I Safety & Ecology ConsultantssMBL BLANK pClg -0.75 1.16 1.94 FeO55 FE-55 I Safety & Ecology ConsultantssTRG UVA-PCC-001 pCig -0.15 0.83 1.47 FeO55 FE-55 I Safety & Ecology ConsultantsiTRG UVA-PSL-002-5 pCVg -0.27 0.75 1.29 FeO55 FE-55 I Safety & Ecology ConsultantsiTRG UVA-PSL-003-4 pClg 0.20 0.87 1.54 10
UVAP Continuing Characterization:
Reactor Pool Interior Summary Table 2 Offsite Laboratory Report AnalysisCode isotope Run CllentName Sami pleType ClientlD RepoirtUnits Result Uncertainty MDA H0003 H-3 I Safety & Ecology Consultants LCS LCS pCi/9 117.07 4.46 3.86 H0003 H-3 I Safety & Ecology Consultants MBL BLANK pCilg 1.89 2.19 3.67 H0003 H-3 I Safety & Ecology Consultants TRG UVA-PCC-001 pCVg 1.70 1.97 3.30 H0003 H-3 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pC/g 1.68 1.94 3.26 H0003 H-3 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.00 1.92 3.29 GLEPS 1-129 1Safety & Ecology Consultants MBL BLANK pCi/g -0.17 0.36 0.68 GLEPS 1-129 1Safety & Ecology Consultants TRG UVA-PCC-001 pCVg -0.13 0.24 0.48 GLEPS 1-129 1Safety & Ecology Consultants TRG WVA-PSL-002-5 pC/g -0.06 0.25 0.47 GLEPS 1-129 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.00 0.31 0.57 Gamma K-40 I Safety & Ecology Consultants MBL BLANK pCig 0.02 0.24 0.35 Gamma K-40 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 12.45 2.60 1.46 Gamma K-40 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 43.60 5.11 1.00 Gamma K-40 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCig 43.65 5.16 1.01 NiO63 NI-63 I Safety & Ecology Consultants LCS LCS pCVg 938.22 11.90 5.07 N1063 NI-63 I Safety & Ecology Consultants MBL BLANK pCi/g 4.43 3.07 5.07 N1063 NI-63 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 1.30 0.61 1.00 Ni063 NM-3 I Safety & Ecology Consultants TRG UVA-BKG-SL-001 pCVg 0.00 0.58 1.00 Ni063 NI-63 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 0.00 0.58 1.00 NiO63 NI-63 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.00 0.58 0.99 PulSO PU-238 I Safety & Ecology Consultants LCS LCS pClg 4.65 1.16 0.19 PulSO PU-238 I Safety & Ecology Consultants MBL BLANK pCiug 0.07 0.10 0.18 PulSO PU-238 1Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.01 0.02 0.06 PuISO PU-238 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 0.00 0.00 0.03 PulSO PU-238 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.00 0.00 0.02 PulSO PU-238 I Safety & Ecology Consultants TRG Process Blank pCVg 0.00 0.00 0.04 PulSO PU-239 I Safety & Ecology Consultants LCS LCS pClg 6.49 1.54 0.15 PulSO PU-239 I Safety & Ecology Consultants MBL BLANK pCi/g 0.00 0.01 0.10 PulSO PU-239 I Safety & Ecology Consultants TRG UVA-PCC-001 pC/g 0.01 0.03 0.07 PulSO PU-239 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pC/g 0.00 0.00 0.03 PulSO PU-239 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.01 0.02 0.02 PulSO PU-239 I Safety & Ecology Consultants TRG Process Blank pClg 0.00 0.00 0.04 11
UVAP Continuing Characterization:
Reactor Pool Interior Summary Table 2 Offsite Laboratory Report Ane"yssCode Isotope Run CllentName SampleType ClientiD ReportUnits Result Uncertainty MDA Pu241 PU-241 I Safety & Ecology Consultants LCS LCS pCVg 253.00 6.83 5.83 Pu241 PU-241 I Safety & Ecology Consultants MBL BLANK pCVg 1.17 0.64 1.05 Pu241 PU-241 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.94 1.01 1.70 Pu241 PU-241 I Safety & Ecology Consultants sTRG UVA-PSL-002-5 pCi/g 1.23 0.67 1.10 Pu24l PU-241 I Safety & Ecology Consultants sTRG UVA-PSL-003-4 pCi/g 1.73 0.64 1.04 Pu4ISO PU242 I Safety & Ecology Consultants sCS LCS pCi/g 4.28 0.85 0.07 Pu4ISO PU242 I Safety & Ecology Consultants sMBL BLANK pCYg 0.06 0.07 0.09 Pu4IS0 PU242 I Safety & Ecology Consultants sTRG UVA-PCC-001 pCVg 0.02 0.03 0.03 Pu4ISO PU242 I Safety & Ecology Consultants sTRG UVA-PSL-002-5 pCi/g 0.02 0.01 0.01 Pu4ISO PU242 ISafety & Ecology Consultants sTRG UVA-PSL-003-4 pC/g 0.00 0.01 0.01 Pu4lSO PU-244 I Safety & Ecology Consultants sMBL BLANK pC/g 0.01 0.04 0.12 Pu4ISO PU-244 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.02 0.03 0.04 Pu4ISO PU-244 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCig 0.01 0.01 0.01 Pu4lSO PU-244 I Safety & Ecology Consultants sTRG UVA-PSL-003-4 pC/g 0.02 0.02 0.01 Sr89032C SR-89 I Safety & Ecology Consultants LCS LCS pCIA -1.26 1.47 1.20 Sr8903C SR-89 I Safety & Ecology Consultants MBL BLANK pCin 0.18 0.47 1.13 Sr890L2C SR-89 1Safety & Ecology Consultants TRG UVA-PCC-001 pCiL 0.13 0.11 0.22 Sr890_2C SR-89 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCaI 0.03 0.10 0.23 Sr890.2C SR-89 I Safety & Ecology Consultants sTRG UVA-PSL-003-4 pCIW -0.08 0.10 0.23 Sr89Q.2C SR-90 I Safety & Ecology Consultants sLCS LCS pun 12.72 0.49 0.91 Sr890..2C SR-90 I Safety & Ecology Consultants sMBL BLANK pCiA -0.30 0.09 0.89 Sr89OL2C SR-90 1 Safety & Ecology Consultants sTRG UVA-PCC-001 pCiA -0.02 0.02 0.15 Sr890..2C SR-90 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCIA 0.02 0.01 0.15 Sr8902C SR-90 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCI/l 0.10 0.01 0.14 Tc099 TC-99 1Safety & Ecology Consultants LCS LCS pCIg 811.04 5.15 1.39 Tc099 TC-99 I Safety & Ecology Consultants MBL BLANK pCi/g 0.00 0.91 1.54 TC099 TC-99 I Safety & Ecology Consultants sTRG UVA-PCC-001 pCVg -0.04 0.07 0.13 Tc099 TC-99 I Safety & Ecology Consultants sTRG UVA-PSL-002-5 pCVg 0.11 0.09 0.15 TCO99 TC-99 I Safety & Ecology Consultants sTRG UVA-PSL-003-4 pCVg 0.00 0.09 0.15 ThISO TH-228 I Safety & Ecology Consultants sLCS LCS pC/g 4.85 0.94 0.07 ml SO TH-228 1Safety & Ecology Consultants sMBL BLANK pCVg 0.05 0.05 0.03 12
UVAP Continuing Characterization:
Reactor Pool Interior Summary Table 2 Offsite Laboratory Report AnalysisCode Isotope Run ClientName SampleType CllentlD ReportUnIts Result Uncertainty MDA ThISO TH-228 I Safety & Ecology Consultants TRG UVA-PCC-001 pCI/g 0.27 0.10 0.04 ThISO TH-228 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 2.59 0.48 0.03 ThWSO TH-228 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 8.0c 1.53 0.05 ThISO TH-230 I Safety & Ecology Consultants LCS LCS PCI/g 4.75 0.93 0.03 ThISO TH-230 I Safety & Ecology Consultants MBL BLANK pClVg 0.85 0.25 0.03 ThISO TH-230 I Safety & Ecology Consultants TRG WNA-PCC-001 pCi/g 0.4f 0.14 0.04 ThISO TH-230 I Safety & Ecology Consultants TRG UVA-PSL-002-5 PCi/g 1.79 0.35 0.04 ThISO TH-230 I Safety & Ecology Consultants;TRG UVA-PSL-003-4 pCVg 5.95 1.16 0.02 ThISO TH-232 I Safety & Ecology Consultants LCS LCS PC1/g 4.9C 0.95 0.06 ThISO TH-232 I Safety & Ecology Consultants MBL BLANK pCI10 0.05 0.05 0.06 ThISO TH-232 I Safety & Ecology Consultants TRG UVA-PCC-001 pCilg 0.29 0.10 0.04 ThISO TH-232 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi1g 2.5C 0.47 0.03 ThISO TH-232 I Safety & Ecology Consultants TRG UVA-PSL-003-4 PCi/g 7.01 1.35 0.06 Gamma TH-234 I Safety & Ecology Consultants MBL BLANK PC1lg -0.19 0.32 0.60 Gamma TH-234 I Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.35 2.25 2.43 Gamma TH-234 I Safety & Ecology Consultants TRG WVA-PSL-002-5 pCiIg 1.31 1.94 2.07 Gamma TH-234 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi1g 8.7E 2.82 4.03 Sr890_2C TOTAL SR1 1Safety & Ecology Consultants LCS LCS PainI 11.4E 0.98 0.78 Sr890_2C TOTAL CSR I Safety & Ecology Consultants MBL BLANK PCan -0.12 0.38 0.70 Sr890_2C TOTAL ISR1 ISafety & Ecology Consultants TRG UVA-PCC-001 pCI/i . IC 0.07 0.12 Sr890_2C TOTALI S31R I Safety & Ecology Consultants TRG UVA-PSL-002-5 Pan/ o.os 0.08 0.13 Sr890_2C TOTAL fSR I Safety & Ecology Consultants TRG UVA-PSL-003-4 Pan/ 0.02 0.08 0.14 UUISO U-234 I Safety & Ecology Consultants LCS LCS PCi/g 6.32 1.24 0.08 UUISO U-234 I Safety & Ecology Consultants MBL BLANK pCI/g 0.05 0.05 0.03 UUISO U-234 I Safety & Ecology Consultants TRG UVA-PCC-001 pCVg 0.35 0.15 0.08 UUISO U-234 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCi/g 1.693 0.41 0.10 UUISO U-234 I Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 5.OC 1.03 0.10 UUISO U-235 1Safety & Ecology Consultants LCS LCS pCilg 0.32 0.17 0.06 UULSO U-235 1Safety & Ecology Consultants MBL BLANK pCVg 0.02 0.03 0.04 UUISO U-235 I Safety & Ecology Consultants TRG UVA-PCC-001 PC1lg 0.02 0.04 0.05 UUISO U-235 1Safety & Ecology Consultants TRG UVA-PSL-002-5 PCi/g 0.11 0.10 0.11 13
UVAP Continuing Characterization:
Reactor Pool Interior Summary Table 2 Offsite Laboratory Report AnalysisCode Isotope Run CllentNme SampleType ClientID ReportUnits Result UncertaInty MDA UUISO U-235 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCi/g 0.28 0.17 0.10 UUISO U-236 ISafety & Ecology Consultants MBL BLANK pCi/g 0.01 0.03 0.08 UUISO U-236 I Safety & Ecology Consultants TRG UVA-PCC-001 pCl/g 0.02 0.03 0.04 UUISO U-236 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCI/g 0.00 0.00 0.04 UUISO U-236 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pC/g 0.13 0.11 0.11 UUISO U-238 I Safety & Ecology Consultants LCS LCS pCi/g 7.12 1.38 0.08 UUISO U-238 I Safety & Ecology Consultants MBL BLANK pC/g 0.02 0.04 0.06 UUISO U-238 1Safety & Ecology Consultants TRG UVA-PCC-001 pCi/g 0.49 0.18 0.04 UUISO U-238 I Safety & Ecology Consultants TRG UVA-PSL-002-5 pCl/g 1.55 0.39 0.08 UUISO U-238 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pCilg 4.93 1.02 0.13 Gamma ZN-65 I Safety & Ecology Consultants MBL BLANK pCilg 0.05 0.04 0.07 Gamma ZN-65 1Safety & Ecology Consultants TRG UVA-PCC-001 pCVg -0.14 0.51 0.88 Gamma ZN-65 1Safety & Ecology Consultants TRG UVA-PSL-002-5 pCVg -0.15 0.33 0.50 Gamma ZN-65 1Safety & Ecology Consultants TRG UVA-PSL-003-4 pClg -0.11 0.21 0.30 14
UVAP Continuing Characterization:
Reactor Plant Stack Summary The University of Virginia Reactor (UVAR) Facility plant stack is located on the east side of the Reactor Confinement Building. The plant stack is 58-feet in total height running from the Mezzanine floor to 4-feet above the Confinement Building. The plant stack is made out of red brick and contains two duct liners; one 14-inch diameter made of transite and one 8-inch diameter made of terracotta. The 14-inch duct is the exhaust from the fume hoods in room MO1 9, the hot cell, the beam port closures, and the bulk access facility. The 8-inch duct is the exhaust flue from the boiler and was replaced in approximately 1992 with a new metal duct running along the outside of the plant stack. The plant stack also contains the air inlet and exhaust ducting to the reactor room.
The Characterization survey included the 14-inch duct, 8-inch duct, reactor room exhaust inlet, and top plenum area. A flue brush was used to obtain a volumetric sample from the interior of the 8-inch flue running the length of the plant stack. The HEPA filter and associated ducting, inline from the hot laboratory Room M019 fume hoods exhaust, was removed and discarded.
Co-60 has been determined to be the major facility related contaminant. The Decorniissioning Plan provides a Derived Concentration Guideline Level (DCGL) of 7100 dpm/lOOcm 2 total activity and 710 dpm/lOOcm 2 removable activity for Co-60.
- 1. Surface Scan Surveys Scans of surfaces at the inlet and exhaust of the each flue, reactor room exhaust inlet, and plenum area were performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector with a Ludlum Model 2221 ratemeter/scaler. Scanning was accomplished by moving the detector over the surface at a speed of approximately 10 cm per second (approximately 4 inches per second). The distance between the detector and the surface was maintained at a practical minimum, consistent with surface conditions.
Gamma scans were performed using a Ludlum Model 44-10 handheld sodium iodide detector with a Ludlum Model 2221 ratemeter/scaler. The scan was performed by moving the detector in a serpentine pattern, while advancing at a speed of approximately 0.5 m per second.
The distance between the detector and surface was maintained within 5 cm.
The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions and marked the location for activity determination by static count. The observed lowest to highest range was recorded on the associated survey map.
Survey UVAP-0400 and TVAP-0571 are available in the UVAP files. The betatalpha scans ranged from 263 cpm to 982 cpm. The gamma scans ranged from 7400 cpm to 17,800 cpm.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity was performed using a Ludlum Model 43-68 handheld 125 cm 2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. The expected alpha activity is minimal, <10% and all detected counts are considered to from beta activity. Counts were integrated for a one-minute counting interval.
Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e., with the detector face uncovered); this measurement included contributions 1
UVAP Continuing Characterization:
Reactor Plant Stack Summary from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm ('/ 2-inch thick). The detector response for this second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered (shielded) detector represents the level of beta activity. Measurements were performed at elevated locations as identified by scans and at locations representative of the general surface area. Direct integrated readings ranged from 136 dpm/lOOcm 2 to 3146 dpm/lOOcm 2.
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm2 (15.5 in2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. Smear sample activity ranged from <MDA (22.99 dpm/lOOcm 2) to 124 dpmlOOcm 2 .
- 4. Ducting Survey A volumetric sample was obtained utilizing a cleaning brush pulled through the S-inch boiler flue. Swabs were obtained from the inlet and outlets of both the 8 and 14-inch ducts.
These samples were submitted for onsite gamma isotopic analyses. Results from the swab obtained from the top of the 14-inch duct indicated the presence of U-238 at detectable levels.
All other samples indicated no reactor facility related isotopes. Gamma spectroscopy reports are attached. Samples were managed under chain-of-custody procedures and stored for additional counting or offsite analysis.
- 5. Conclusions Static surveys and the volumetric sample did not indicate facility related activity above the DCGL. Based on results of these surveys, no remediation is required. The plant stack and associated ventilation is ready for Final Status Survey. This survey satisfies the continuing characterization requirements of Area 3 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
2
UVAP Continuing Characterization:
Laboratory Rooms M008 and M005 Summary Laboratory rooms M008 and M005 are located on the mezzanine floor level, west end of the UVAR facility. M008 and M005 rooms are classified as a Class I area, floor, and lower walls with approximately 100-m2 floor area. Upper walls and ceiling are classified as a class 2 area.
The room contains painted block and poured concrete walls, a false drop panel ceiling and a prefab concrete floor covered in tile. The area contained laboratory soap stone counter tops, sinks, and fume hoods with HEPA filtered ventilation to the building exterior. New fume hoods and associated ventilation up to the HEPA filter housings were replaced in both rooms. Ni-63 was determined to be the contaminate of concern as denoted in Appendix A of the University of Virginia Reactor Decommissioning Plan and offsite lab report 03-04154 attached to survey UVAP-0663. Structure surface DCGL for Ni-63 is l.8E+06 cpm/l00 cm 2. Elevated areas were noted during surveys. Counter tops were decontaminated, the elevated floor tile, cabinet bottom, sink, sink drain, HEPA filters, and part of the ventilation systems were removed during D&D operations. Surveys UVAP-0509 and 0663 were performed with thin Mylar window Ludlum Model 43-68 handheld 125 cm 2 gas proportional detector with a Ludlum Model 2221 ratemeter/scaler calibrated to Ni-63.
A reference Grid system was not used for this survey.
- 1. Surface Scan Surveys Scans of walls, floors, counter tops and other surfaces were performed using a Ludlum Model 43-68 handheld 125 cm 2 gas proportional detector with a Ludlum Model 2221 ratemeter/scaler. Scanning was accomplished by moving the detector over the surface at a speed of approximately 10 cm per second (approximately 4 inches per second). The distance between the detector and the surface was maintained at a practical minimum, consistent with surface conditions.
The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions. The observed lowest to highest range was recorded on the associated survey map. Increases were noted above ambient levels during scans. Surveys UVAP-0301, 0303, 0304, 0509, and 0510 are available in the UVAP files.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity were performed using a Ludlum Model 43-68 handheld 125 cm 2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. The expected alpha activity is minimal, <10% and all detected counts are considered to be from beta activity. Counts were integrated for a one-minute counting interval.
Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e., with the detector face uncovered); this measurement included contributions from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm (X2-inch thick). The detector response for this second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered 1
UVAP Continuing Characterization:
Laboratory Rooms M008 and M005 Summary (shielded) detector represents the level of beta activity. Measurements were performed at elevated locations as identified by scans and at locations representative of the general surface area. Results for these static readings ranged from -11 dpmx/lOOcm 2to 81,439 dpm/lOOcm 2 .
Surveys UVAP-0301, 0303, 0304, 0409, 0509, 0510, and 0663 are available in the UVAP files.
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm2 (15.5 in2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. All smear results ranged from MDA for beta (22.99 or 28.26 dpm/lOOcm 2 pre or post instrument re-calibration) to 1060 dpm/lOOcm 2 and less than MDA for alpha (19.04 or 21.38 dpm/lOOcm 2 pre or post instrument re-calibration). Surveys UVAP-0301, 0303, 0304, 0409, 0509, 0510, and 0663 are available in the UVAP files.
- 4. Ventilation The old ventilation systems installed from the fume hoods in both rooms were surveyed.
Room M005 had a HEPA filter installed. The HEPA filter and housing were removed. In room M008, the blower wheel and housing was removed. Scans, integrated direct readings and smears were performed on the remaining ductworks. A water sample was obtained from the outside vent stack vertical cleanout. No elevated activity was detected in or on the remaining ventilation.
Surveys UVAP-0301, 0303, and 0304 are available in the UVAP files.
- 5. Drains Sink drain traps were removed from rooms M005 and M008 water residue was collected and analyzed by onsite gamma spectroscopy. The east sink drain was surveyed with the PSL2 pipe probe connected to a Ludlum Model 2221 ratemeter/scaler from room MOOS to the overhead piping in the Cavalier room. No elevated activity was noted. A smear indicated elevated activity at 1600 dpm/lOOcm 2 by using the onsite Tennelec counter. Subsequent, offsite lab analysis of the smear noted Ni-63 as the only contaminant. Survey UVAP-0663 is available in the UVAP files.
- 6. Conclusions Based on results of these surveys, no further remediation is required. Rooms M008 and M005 are ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 4 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
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UVAP Continuing Characterization:
Demineralizer Room Summary Demineralizer area, rooms M021 and M021A, are located on the mezzanine floor level, northeast corner of the UVAR facility. M021 and M02IA rooms are classified as a class I area, floor, walls, and ceiling, with approximately 100-m 2 floor area. The room contains painted block and poured concrete walls, painted precast concrete panel ceiling and poured concrete floor.
The area contained the reactor pool demineralizer system (resin and charcoal vessels, pumps and associated piping and equipment) and the associated regenerating equipment. All piping, motors, pumps, resin and charcoal vessels and associated materials were removed during D&D operations. The reactor room floor drain header runs vertically in the north west corner of room M021. The reactor room drain header piping will be addressed separately.
A reference Grid system was used for this survey. The grid was set at 1-meter intervals with the grid starting location being the southwest corner of the room.
- 1. Surface Scan Surveys Portions of the floor were scanned for surface beta radioactivity, using a Ludlum Model 239-IF floor monitor with a Model 43-37 large-area (582 cm2 ) gas proportional detector, with a scan path of 0.44 m (1.44 ft) operated in the alpha-plus-beta detection mode. A Ludlum Model 2221 ratemeter/scaler was used to provide detector power and monitor the scan results.
Scans of wall, overhead and other surfaces were performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector with a Ludlum Model 2221 ratemeter/scaler.
Scanning was accomplished by moving the detector over the surface at a speed of approximately 10 cm per second (approximately 4 inches per second). The distance between the detector and the surface was maintained at a practical minimum, consistent with surface conditions.
Gamma scans were performed using a Ludlum Model 44-10 handheld sodium iodide detector with a Ludlum Model 2221 ratemeter/scaler. The scan was performed by moving the detector in a serpentine pattern, while advancing at a speed of approximately 0.5 m per second.
The distance between the detector and surface was maintained within 5 cm.
The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions. The observed lowest to highest range was recorded on the associated survey map. No increases were noted above ambient levels during all scans.
Survey UVAP-0391 is available in the UVAP files.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity was performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. The expected alpha activity is minimal, <10% and all detected counts are considered to be from beta activity. Counts were integrated for a one-minute counting interval.
Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e., with the detector face uncovered); this measurement included contributions from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm (X2-inch thick). The detector response for this 1
UVAP Continuing Characterization:
Demineralizer Room Summary second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered (shielded) detector represents the level of beta activity. Measurements were performed at elevated locations as identified by scans and at locations representative of the general surface area. Results for these static readings ranged from 329 dpm/l 00cm2 to 2302 dpm/llOOcm 2. Survey LVAP-0391 is available in the UVAP files.
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm 2 (15.5 in 2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. All smear results were less han MDA for beta (22.99 dpm/lOOcm 2) and alpha (19.04 dpm/lOOcm 2). Survey UVAP-0391 is available in the UVAP files.
- 4. Conclusions Based on results of these surveys, no remediation is required. The demineralizer room is ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 5 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
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UVAP Continuing Characterization:
Hot Cell Room Summary Hot cell area, rooms G025, G026 and G027, are located on the ground floor level, southeast corner of the UVAR facility. G025, G026 and G027 rooms are classified as a Class 1 area, floor, walls, and ceiling, with approximately 70-m2 floor area. The room contains painted poured concrete walls, ceiling, and floor.
The area contained the hot cell interior, manipulator arms, lead glass window and mechanical hoist. Both manipulator arms and the lead glass window were removed during D&D operations.
Cs-137 activity was detected at six discreet locations on the floor and was the floor was decontaminated during D&D operations. The Cs-137 DCGL value of 2.8E4 dpm/l00cm2 was used as the screening level for structure surfaces in accordance with the UVAR decommissioning plan. The hot cell room drain and associated piping will be addressed separately.
A reference Grid system was used for this survey. The grid was set at 1-meter intervals with the grid starting location being the southwest comer of the room.
- 1. Surface Scan Surveys Portions of the floor were scanned for surface beta radioactivity, using a Ludlum Model 239-IF floor monitor with a Model 43-37 large-area (582 cm2) gas proportional detector, with a scan path of 0.44 m (1.44 ft) operated in the alpha-plus-beta detection mode. A Ludlum Model 2221 ratemeter/scaler was used to provide detector power and monitor the scan results.
The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions. The observed lowest to highest range was recorded on the associated survey map. Increases were noted above ambient levels during scans. Surveys UVAP-0275 and 0392 are available in the UVAP files.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity were performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. The expected alpha activity is minimal, <10% and all detected counts are considered to be from beta activity. Counts were integrated for a one-minute counting interval.
Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e., with the detector face uncovered); this measurement included contributions from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm (l/-inch thick). The detector response for this second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered (shielded) detector represents the level of beta activity. Measurements were performed at elevated locations as identified by scans and at locations representative of the general surface area. Results for these static readings ranged from 1484 dpm/nl Ocm2 to 34,831 dpm/ll00cm 2 .
Surveys UVAP-0275 and 0392 are available in the UVAP files.
1
UVAP Continuing Characterization:
Hot Cell Room Summary
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm2 (15.5 in2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. Smear results ranged from less than MDA for beta (22.99 dpm/lOOcm 2 ) to 79 dpm/lOOcm 2 and less than MDA for alpha (19.04 dpm/lOOcm 2). Surveys UVAP-0275 and 0392 are available in the UVAP files.
- 4. Volumetric sample A volumetric sample was obtained from the elevated floor concrete during decontamination effort in rooms 0026 and G027. This sample was analyzed by onsite gamma spectroscopy, retained and stored under chain of custody. The crane hook was analyzed by onsite gamma spectroscopy for isotopic determination. Reports JVA-CD-130 and MRS-00184 are available in the UVAP files.
- 5. Conclusions Based on results of these surveys and decontamination efforts, no further remediation is required. The hot cell room is ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 7 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
2
UVAP Continuing Characterization:
Heat Exchanger Room Summary Heat exchanger area, room G024, is located on the ground floor level, northeast corner of the UVAR facility. G024 room is classified as a Class 1 area, floor, walls, and ceiling, with approximately 100-m 2 floor area. The room contains painted block and poured concrete walls, painted precast concrete panel ceiling and poured concrete floor.
The area contained the reactor pool heat exchanger, primary and secondary side pumps and associated piping and equipment. All piping, motors, pumps, heat exchanger and associated materials were removed during D&D operations. A section of the primary suction and return piping was left in place inside the floor and wall and will be addressed separately. A valve-gallery sump is located along the middle of the south wall. It contained the valves for the reactor pool drains, heat exchanger primary suction piping drain, and a connection to the reactor room floor drain header for discharge to the pond. The sump is including in this summary, the drain piping will be addressed separately.
A reference Grid system was used for this survey. The grid was set at 1-meter intervals with the grid starting location being the southwest corner of the room.
- 1. Surface Scan Surveys Portions of the floor were scanned for surface beta radioactivity, using a Ludlum Model 239-IF floor monitor with a Model 43-37 large-area (582 cm2) gas proportional detector, with a scan path of 0.44 m (1.44 fit) operated in the alpha-plus-beta detection mode. A Ludlum Model 2221 ratemeter/scaler was used to provide detector power and monitor the scan results.
Scans of wall, overhead and other surfaces were performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector with a Ludlum Model 2221 ratemeter/scaler.
Scanning was accomplished by moving the detector over the surface at a speed of approximately 10 cm per second (approximately 4 inches per second). The distance between the detector and the surface was maintained at a practical minimum, consistent with surface conditions.
Gamma scans were performed using a Ludlum Model 44-10 handheld sodium iodide detector with a Ludlum Model 2221 ratemeter/scaler. The scan was performed by moving the detector in a serpentine pattern, while advancing at a speed of approximately 0.5 m per second.
The distance between the detector and surface was maintained within 5 cm.
The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions. The observed lowest to highest range was recorded on the associated survey map. No increases were noted above ambient levels during all scans.
Survey UVAP-0456 is available in the UVAP files.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity were performed using a Ludlum Model 43-68 handheld 125 cm 2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. The expected alpha activity is minimal, <10% and all detected counts are considered to be from beta activity. Counts were integrated for a one-minute counting interval.
Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e., with the detector face uncovered); this measurement included contributions 1
UVAP Continuing Characterization:
Heat Exchanger Room Summary from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm (Y2-inch thick). The detector response for this second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered (shielded) detector represents the level of beta activity. Measurements were performed at elevated locations as identified by scans and at locations representative of the general surface area. Results for these static readings ranged from 572 dpm/n 00cm 2 to 6078dpm/1 00cm2 . Survey UVAP-0456 is available in the UVAP files.
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm2 (15.5 in2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. All smear results ranged from MDA for beta (22.99 dpm/lOOcm2 ) to 153 dpm/lOOcm 2 and less than MDA for alpha (19.04 dpm/lOOcm 2). Survey UVAP-0456 is available in the UVAP files.
- 4. Volumetric Sample Collection and Analysis Soil samples were obtained from the concrete core hole located in bottom of the sump by hand auguring 0 to 6-inches in depth. Samples were submitted for onsite gamma isotopic analyses. No facility related activity was detected. The samples were logged on a chain of custody form and stored onsite.
- 5. Conclusions Based on results of these surveys, no remediation is required. The heat exchanger room is ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 8 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
2
UVAP Continuing Characterization:
Source Room Summary The Source room, G022 is located on the ground floor level, next to the biological shield, on the east side of the UVAR facility. The G022 room is classified as a Class 1 area, floor, walls, and ceiling, with approximately 30-m 2 floor area. The room contains painted block, ceramic and poured concrete walls, painted precast concrete panel ceiling and poured concrete floor. This room was originally a restroom and contains sanitary sewer piping that was used recently as a discharge point for treated and filtered radioactive liquids The original rest room was converted to store high-level radioactive materials. All associated materials were removed during D&D operations. The source room sanitary drain header piping will be addressed separately.
A reference grid system was used for this survey. The grid was set at 1-meter intervals with the grid starting location being the southwest corner of the room.
- 1. Surface Scan Surveys Scans of wall, overhead, floor and other surfaces were performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector with a Ludlum Model 2221 ratemeter/scaler.
Scanning was accomplished by moving the detector over the surface at a speed of approximately 10 cm per second (approximately 4 inches per second). The distance between the detector and the surface was maintained at a practical minimum, consistent with surface conditions.
Gamma scans were performed using a Ludlum Model 44-10 handheld sodium iodide detector with a Ludlum Model 2221 ratemeter/scaler. The scan was performed by moving the detector in a serpentine pattern, while advancing at a speed of approximately 0.5 m per second.
The distance between the detector and surface was maintained within 5 cm.
The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions. The observed lowest to highest range was recorded on the associated survey map. Increases were noted above ambient levels during scans. Three areas ranging froml839 cpm to 4271 cpm were decontaminated to below DCGL value for Co-60.
Survey IVAP-0696 is available in the UVAP files.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity were performed using a Ludlum Model 43-68 handheld 125 cm 2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. The expected alpha activity is minimal, <10% and all detected counts are considered to be from beta activity. Counts were integrated for a one-minute counting interval.
Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e., with the detector face uncovered); this measurement included contributions from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm (l/2-inch thick). The detector response for this second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered (shielded) detector represents the level of beta activity. Measurements were performed at I
UVAP Continuing Characterization:
Source Room Summary elevated locations as identified by scans and at locations representative of the general surface area. Results for these static readings ranged from I 1,111 dpm/l 00cm2 to 28,972 dpm/l 00cm2 .
Survey UVAP-0696 is available in the UVAP files.
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm2 (15.5 in2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. Smear results ranged from less than MDA for beta (28.26 dpm/lOOcm 2) to 852 dpm/lOOcm 2 and less than MDA for alpha (21.38 dpm/l00cm2 ). Survey UVAP-0696 is available in the UVAP files.
- 4. Volumetric sample A volumetric sample was obtained from the elevated tile during decontamination effort in room G022. This sample was analyzed by onsite gamma spectroscopy, retained and stored under chain of custody. Co-60 = 11.lpCig and Cs-137= 38.6 pCi/g Survey UVAP-0696 is available in the UVAP files.
- 5. Conclusions Based on results of this survey, no further remediation is required. The source room G022 is ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 9 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
2
UVAP Continuing Characterization:
Beamport Area Summary The neutron beamport area is located on the ground floor level, lower west side of the reactor pool in the biological shield through to the south west wall, approximately 2 meters off the pool floor. Two beam ports were located in this area. The north beam port (referred to as the hot beamport or No.1 beam port) was radioactively activated by the reactor's neutron beam and has been removed along with the activated concrete surrounding the port. The south beamport (referred to as the cold beam port or No. 2 beamport) was not used as extensively and only the first 18-inches of beam tube was removed from the pool wall with a portion of surrounding concrete. The beamport area is classified as a Class 1 area.
A reference grid system was not used for this survey.
- 1. Surface Scan Surveys Scans were performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector with a Ludlum Model 2221 ratemeter/scaler. Scanning was accomplished by moving the detector over the surface at a speed of approximately 10 cm per second (approximately 4 inches per second). The distance between the detector and the surface was maintained at a practical minimum, consistent with surface conditions.
Gamma dose rate determination was performed using an Eberline R020 handheld ion chamber detector. See attached surveys UVAP-0455 for results The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions. The observed lowest to highest range was recorded on the associated survey map. No increases were noted above ambient levels during all scans. Initial scans with a 43-68 detector ranged from 300 cpm to 17,700 cpm. After remediation scans with a 43-68 detector ranged from 334 cpm to 597cpm. Surveys UVAP-0474, 0633, 0688, and 0712 are available in the UVAP files.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity were performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. The expected alpha activity is minimal, less thanlo%, and all detected counts are considered to be from beta activity. Counts were integrated for a one-minute counting interval. Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e., with the detector face uncovered); this measurement included contributions from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm (l2-inch thick). The detector response for this second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered (shielded) detector represents the level of beta activity. Measurements were performed at elevated locations as identified by scans and at locations representative of the general surface area. Results forthese static readings ranged from -458 dpm/l00cm 2 to 23,229 dpm/lOOcm 2.
Surveys UVAP-0633, 0678, and 0688 are available in the UVAP files.
1
UVAP Continuing Characterization:
Beamport Area Summary
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm2 (15.5 in2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. Smear results ranged from less than MDA for beta (22.99 dpm/lOOcm 2) and alpha (19.04 dpm/lOOcm 2). Surveys UVAP-0455, 0633, and 0688 are available in the UVAP files.
- 4. Volumetric sample Two concrete samples were obtained from the beamport area. One sample was counted by onsite gamma spectroscopy. See attached report for results. A second beamport concrete sample UVA-CD-032 was managed under chain of custody and sent to the offsite lab for isotopic analysis. The STL Richland sample results are available in the UVAP files.
- 5. Conclusions Based on results of survey UVAP-0712, no further remediation is required. The beamport area is ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 10 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
2
UVAP Continuing Characterization:
Impacted Drain Lines and Piping Summary The University of Virginia Research Reactor facility utilized several systems to, handle, process, or dispose of potentially radioactive liquids and effluents. Among these systems were the Heat Exchanger systems, Reactor room drains that discharged to the pond, Reactor pool drains that could be directed to the pond or liquid waste tanks, sanitary system that discharged to the offsite sanitary facility, CAVALIER pit drain that discharged to the pond, hot cell floor drain that discharged to the hot cell liquid waste tank and the ground floor drains that discharged to the pond. These systems were surveyed and characterized during the D & D operations of the facility decommissioning.
The bulk of known potentially contaminated piping was removed from the UVAR Facility during remediation activities, but sections of radiologically impacted piping previously associated with the reactor coolant system and various drains from the reactor facility remain.
This remaining piping is embedded in concrete or buried beneath concrete or asphalt paving and soil. The piping is generally of small diameter (2 in to 4 in ID); however there are several short sections of larger diameter. Remaining piping includes:
- Heat exchanger lines: Stainless Steel (SS), 6 in ID x 22 ft and 6 in ID x 32 ft.
- Reactor pool drains: SS, 2 in ID x 32 ft and 2 in ID x 36 ft.
- Reactor Room floor drains: Cast Iron (CI), 2 in ID x -160 ft (multiple sections).
- Ground floor drain to Pond standpipe: CI, 2 in ID x 40 ft and 4 in ID x 140 ft.
- Reactor liquid drains to outside underground collection tanks: CI, 2 in ID x 75 ft.
- Hot Cell drain to outside underground collection tanks: PVC and Duriron (Fe+Si), 2 in ID x 55 ft.
- Ground floor drain to Pond hillside: CI,2 in ID x 40 ft and terra cotta, 4 in ID x8o ft.
In addition, the facility and property are serviced by storm and sanitary sewer services; drains for these services are located beneath the paved area, south of the building. Figures 1 through 3 illustrate the locations of the reactor facility piping.
Visual (boroscope) inspection of the internal surfaces of reactor piping revealed breaks or blockages in the floor drain piping system beneath the Reactor Room floor. This inspection also identified accumulations of scale and loose debris, concentrated on the bottom surfaces of the piping. Visual inspection of the sanitary system piping was performed and the lines appeared clean and free from scale. Visual inspection of the storm drain system was not conducted.
Broken or damaged areas of piping were accessed, and contaminated pieces of pipe and soil were identified and removed. Hydrolazing of reactor piping internal surfaces was performed to remove scale and loose debris. Piping access points have been created to enable final status survey and NRC confirmatory activities.
Direct and removable activity measurements were performed at exposed drain entries and on accessible internal piping surfaces. Swabs and water rinses were performed inside piping to determine loose surface activity. (See Tables 1 and 2 for results) Small diameters, fittings, bends, 1
IVAP Continuing Characterization:
Impacted Drain Lines and Piping Summary and other internal obstructions limited access to most other piping and accumulations of scale and debris prevented reliable quantification of surface activity levels. A soil sample was obtained from inside the French drain to assess the presence of activity. See table 3 for results.
Direct measurements at drain openings; swabs, and rinsate samples indicated low levels of contamination, but at levels below the Co-60 and Cs-137 criterion. Surveys UVAP-438, 515,615,618,622,626,634-636, 642, 644, 645, 653, 654, 695, 699, 700, 709, 711, 713-717 and 730 are available in the UVAP files.
The storm drain system was accessed at the 5 man ways in the paved area, south of the building. Gamma scans, Beta static 1-minute counts, and sludge samples were obtained from each access. No elevated activity above DCGL for Co-60 was detected. Surveys UVAP-0668 and 0069 are available in the UVAP files.
The sanitary system was accessed in the ground floor main header, the source room, and the outside man way. One elevated area was noted in the sanitary piping in the source room that was used as a discharge point for process liquids to the sanitary system. This section of piping was removed. Scan, one minute static counts, smears and sediment samples were performed in the remaining portions of the sanitary piping and man way. No elevated activity above DCGL for Co-60 was detected. Surveys UVA-0715 and UVA-0716 are available in the UVAP files.
Soil removed during excavation of the underground waste tanks, soil from the vicinity of piping breaks, debris collected from piping, and pieces of removed piping were analyzed by gamma spectroscopy. These analyses identified Co-60 as the primary potential contaminant in most of the remaining piping. Cs-137 is the major potential contaminant associated with the Hot Cell drain and was also present in other piping systems, but at lower levels than Co-60. Even smaller quantities of Co-57, Eu-152 and Ag-108m were identified in several of the samples.
Based on use history, visual inspections, and results of the limited scoping surveys, all remaining reactor-associated piping is considered potentially contaminated. With exception of the Hot Cell drain, which is predominantly contaminated with Cs-137, the contaminant in reactor facility piping is assumed to be Co-60; this is the most limiting of the identified potential contaminants and, in consideration of the limitations in performing such piping surveys, provides a level of conservative assurance that decommissioning is adequate. Criteria for FSS of reactor facility piping are therefore 28,000-dpm/100 cm 2 total activity for the Hot Cell piping and 7,100 dpm/100 cm total activity for other piping. Removable activity criteria are 10% of these total activity values
==
Conclusions:==
Based on results of the initial surveys and surveys after D&D evolutions, no further remediation is required. The reactor facility piping is ready for Final Status Survey. These surveys satisfy the continuing characterization requirements of Area 1, 11, 12, 14 and 15 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
2
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- 04 (PLUGGED 5-12-03) t: Q I-
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- N J DOWN TO POND STANDPIPE GE M
C, PIPING REMOVED FROM cm REACTOR ROOM TO HEAT EXCHANGER ROOM SUMP 5. M qU, IB a
IVp rsA 0 a,
REMAINING PIPING SHOWN SOLID 0 * @
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0
UVAP Continuing Characterization:
Impacted Drain Lines and Piping Summary II i
I I
I i
II I I L~~N ~ I I.
I v
I I
Figure 2-3 Ground Floor, external 5
06 N
LJ
UVAP Continuing Characterization:
Impacted Drain Lines and Piping Summary Drain line Swabs Table 1 (Onsite Lab Results)
Gamma Spectroscopy Sample number Detectable Isotopes Remarks Ag-Co-57 Co-60 108M Cs-137 Eu-152 Eu-154 UVA-CD-1 15 £Db clean out RF UVA-CD-120 _D' core to aM' core RF UVA-CD-125 'E" core to 5H" core RF UVA-CD-118 _ _ 'F drain to *H"core RF UVA-CD-067 _G' drain to OGO core RF UVA-CD-070 _G" core to 'H' core RF UVA-CD-119 X OH' core to *D'core RF WVA-CD-068 "Hw drain to OH" core RF UVA-CD-147 __H' core to V core RF UVA-CD-078 _*_ clean out to aIm core RF UVA-CD-077 "indrain to 8I' core RF UVA-CD-079 X X X X X X 8l' core to *N' core RF UVA-CD-075 _J' drain to 'I' core RF UVA-CD-074 _'Ke drain to OP" core RF UVA-CD-129 'Lo drain to 'M" core RF UVA-CD-127 _Mm core to or core RF UVA-CD-101 'N' core to demineralizer room core RF UVA-CD-130 _P' core to mr core RF UVA-CD-145 _r core to demineralizer room core RF UVA-CD-148 ____Sump clean out to sump GF UVA-CD-140 X 'Sump" core to TE excavation GF UVA-CD-142 __ _ excavation to Evaporation station well casing UVA-CD-143 _ Evaporation station well casing to pond GF UVA-CD-116 South pool drain to sump GF UVA-CD-117 X North pool drain to sump GF UVA-CD-062 _ Heat exchanger return line GF UVA-CD-134 X Heat exchanger suction line GF UVA-CD- 066 Heat exchanger suction linel-inch drain line GF Gamma Spectroscopy results is considered qualitative for screening purposes and isotopic identification.
Swabs performed Inside of drain piping to determine presence of facility related isotopes.
GF= Ground Floor RF= Reactor Room Floor 'E' excavation is the same as the Trackway Pit on Figure 2, 3 and 4 7
UVAP Continuing Characterization:
Impacted Drain Lines and Piping Summary Drain line Swabs Table I cont. (Onsite Lab Results)
Gamma Spectroscopy Sample number Detectable Isotopes Remarks
. . ~~~~~~~Ag-Co-57 Co-60 108M Cs-137 Eu-152 Eu-154 UVA-CD-085 A Bulk access core to A&B header GF UVA-CD-123 B Bulk access core to A&B header GF UVA-CD-122 A&B Bulk access header to sewer header GF UVA-CD-133 _A&B Bulk access header to outside man way GF UVA-CD-087 Hotcell drain pipe to outfall GF UVA-CD-137 Liquid waste tank drain line to outfall GF UVA-CD-115 Washing machine drain line Mezz. floor UVA-CD-105 Terracotta French drain at E6excavation GF UVA-CD-146 HX room PVC drain to Terracotta French drain WVA-CD-138 X RM GOI 8 sewer header to 90 degree elbow GF UVA-CD-139 . RM G01 8 sewer clean out to Trackway pit GF UVA-CD-144 X . Rm G022 shower/toilet drain to Trackway GF UVA-CD-149 Rm G022 sewer cleanout to Trackway GF Gamma Spectroscopy results is considered qualitative for screening purposes and isotopic identification.
Swabs performed inside of drain piping to determine presence of facility related isotopes.
GF= Ground Floor RF= Reactor Room Floor OE" excavation is the same as the Trackway Pit on Figure 2, 3 and 4 8
UVAP Continuing Characterization:
Impacted Drain Lines and Piping Summary Drain line Rinsate Table 2 (Onsite Lab Results)
Gamma Spectroscopy Sample number Detectable Isotopes Remarks Ag-Co-57 Co-60 108M Cs-137 Eu-152 Eu-154 UVA-WT-029 l X Hotcell drain line UVA-VT-037 _ Reactor room escape pit drain line UVA-WT-038 l X X Reactor room sink drain *B13 UVA-WT-039 . Reactor room floor drain *C" UVA-WT-040 . Reactor room floor drain OD' UVA-WT-041 X Reactor room floor drain TE UVA-WT-042 Reactor room floor drain TF UVA-WT-043 X Reactor room pool overflow drain M J UVA-WT-044 X X X X X Reactor room floor drain OIC UVA-WT-045 Reactor room composite from intact drain lines UVA-WrT-048 Bulk access A & B drain line UVA-WT-054 X G018 sink drain to sanitary sewer French Drain line Soil sample Table 3 (Onsite Lab Result;)
Gamma Spectroscopy Sample number Detectable Isotopes Remarks C Co-60 Ag-108M 13I Eu-1521 C Eu-164 UVA-SL-133 I X I French drain line was filled with soil Gamma Spectroscopy results is considered qualitative for screening purposes and isotopic identification.
Water rinse performed inside of drain piping to determine presence of facility related Isotopes.
GF= Ground Floor RF= Reactor Room Floor OE" excavation is the same as the Trackway Pit on Fiure 2, 3 and 4 9
UVAP Continuing Characterization:
Mezzanine Crawl Space Summary The Mezzanine Crawl Space is located on the mezzanine level of the UVAR facility.
Access to the area is located in the main stairwell. The room is classified as a class 2 area with approximately 100-m 2 surface area. The room contains concrete block walls, precast concrete panel ceiling with steel support beams and a dirt floor.
A reference Grid system was used for this survey. The grid was set at 1-meter intervals with the grid starting location being the southwest comer of the room.
- 1. Surface Scan Surveys Scans of wall, overhead and other surfaces were performed using a Ludlurn Model 43-68 handheld 125 cm2 gas proportional detector with a Ludlurn Model 2221 ratemeter/scaler.
Scanning was accomplished by moving the detector over the surface at a speed of approximately 10 cm per second (approximately 4 inches per second). The distance between the detector and the surface was maintained at a practical minimum, consistent with surface conditions.
Gamma scans were performed using a Ludlum Model 44-10 handheld sodium iodide detector with a Ludlum Model 2221 ratemeter/scaler. The scan was performed by moving the detector in a serpentine pattern, while advancing at a speed of approximately 0.5 m per second.
The distance between the detector and surface was maintained within 5 cm.
The count rate was monitored by means of the audible signal output, and when an increase in instrument response above the ambient level was noted, the surveyor paused for several seconds to confirm the conditions. The observed lowest to highest range was recorded on the associated survey map. Two slightly elevated reading were noted during the scan of the dirt floor and marked for soil sampling. No other increases were noted above ambient levels during all other scan. Surveys UVAP-0570, 0573 and 0574 are available in the UVAP files.
- 2. Integrated Direct Surface Beta Radioactivity Measurements Measurements of surface alpha-plus-beta radioactivity was performed using a Ludlum Model 43-68 handheld 125 cm2 gas proportional detector coupled to a Ludlum Model 2221 ratemeter/scaler. The expected alpha activity is minimal, <10% and all detected counts are considered to from beta activity. Counts were integrated for a one-minute counting interval.
Two measurements were performed. The first was a surface measurement, performed in the typical manner (i.e., with the detector face uncovered); this measurement included contributions from beta particles emitted from the surface and interactions of ambient gamma photons with the detector. The second measurement was performed at the same location with the detector face covered by a layer of wood approximately 1.27 cm (X/-inch thick). The detector response for this second measurement is representative of the contribution from gamma radiation only. The difference between measurements with an uncovered (unshielded) detector and covered (shielded) detector represents the level of beta activity. Measurements were performed at elevated locations as identified by scans and at locations representative of the general surface area. Results for these static readings ranged from 286 dpm/l0ocm2 to 2195 dpm/lOOcm 2 .
1
UVAP Continuing Characterization:
Mezzanine Crawl Space Summary
- 3. Smear Sample Collection and Analysis Smear samples for removable activity were collected by wiping a 5 cm (2-inch) diameter cloth disc over approximately 100 cm2 (15.5 in2) areas of the surface, while applying moderate pressure. Smear samples were obtained at each location of direct surface activity measurement.
Smear samples were counted for alpha and beta radioactivity on a Tennelec automatic gas proportional counter. All smear results were less than MDA for beta (22.99 dpm/lOOcm 2 ) and alpha (19.04 dpm/lOOcm 2 ).
- 4. Volumetric Sample Collection and Analysis Soil samples were obtained by hand auguring, at 9 locations in the dirt floor, 0 to 6-inches in depth. Samples were submitted for onsite gamma isotopic analyses. No facility related activity was detected. The samples were placed on a chain of custody and stored onsite. See Table 1 for results.
- 5. Conclusions Based on results of these surveys, no remediation is required. The mezzanine crawl space is ready for Final Status Survey.
2
UVAP Continuing Characterization:
Mezzanine Crawl Space Summary Mezzanine Crawl Space Soil Results (Onsite results)
Table 1 Gamma Sample number Interval Logging Gamm peoscopy 44-10 K-40 Cs-137 Co-60 Pb-212 Bi-214 Pb-214 Ra-226 Ac-228 U-238 Inches CPM pCigm pCigm pCOgm pCigm pCi/gm pCi/gm pCi/gm pCil/m pCi/gm MCS-001 Oto 6 30321 29.5 2.57 1.25 1.61 2.40 3.75 MCS-002 Oto6 24011 31.8 2.08 1.06 1.09 2.50 1.89 MCS-003 Oto 6 28003 28.4 2.24 1.26 1.30 5.08 1.92 1.88 MCS-004 Oto 6 27307 29.8 2.41 1.27 1.35 3.80 2.20 2.41 MCS-005 0 to 6 31210 26.9 4.83 1.58 2.10 4.81 4.70 2.36 MCS-006 0 to 6 27724 23.8 3.21 1.62 1.52 6.67 2.75 2.30 MCS-007 0 to 6 32095 28.6 4.05 1.42 1.59 4.94 3.91 MCS-008 0 to 6 27586 26.7 _ 3.73 1.63 1.99 3.56 3.85 1.69 MCS-009 O to6 36346 21.9 4.16 1.95 1.90 3.10 3.95 2.22 Note 1: Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a Non-standard preparations of sample for homogeneous mixture and dxying.
3
UVAP Continuing Characterization:
Pond Sediment Summary A pond, covering a surface area of approximately 1600 m2 and ranging in depth from approximately 2 to 4 m, is located just to the south of the University of Virginia Reactor Facility.
During Reactor Facility operation this pond received discharges from certain laboratory drains, floor drains, and other sources of non-sanitary wastewater from the building. Run off from the adjacent land areas drain directly into this pond; an overflow from the nearby storm drain also empties into the pond.
The pond was drained to expose and permit the sediments to dry for improved access and to facilitate radiological monitoring and sediment sampling. Thickness of sediments varied from a fraction of a meter to 2 meters depending on location.
Survey grid corners were marked, dividing the pond into 10-meter square sections and referenced to the centerline of the dam spillway. Sections containing greater than 25% pond surface were numbered 1 thru 22, starting in the southeastern corner section (Figure 1). Surface gamma scans were initially performed in each 10-meter square section to identify locations of elevated direct radiation. The results were logged per 1.5-meter wide lanes with the highest to lowest noted readings. Survey UVAP-0245 is available in the UVAP files. Any discernable localized increase readings were denoted on the map and physically flagged for bias sampling.
Gamma scans of the drainage stream from the pond were performed for approximately 20 meters below the spillway release point. Samples of sediment were obtained at 3 locations considered representative of the average stream conditions.
Pond sediment samples were obtained from 16 statistical sample points and 18 biased sample locations (Figure 1). A 2-inch diameter bucket auger and 2-inch PVC piping was used to collect samples. Continuous sampling was performed from surface to 6 inches beyond the interface of sediment/original soil or to auger refusal, whichever occurred first. Samples were placed in plastic bags or jars with each sample representing 6-12 inches of sediment depth. To the extent possible, a plastic sleeve was utilized to maintain an open sampling hole. Sampling tools were cleaned and surveyed for contamination, following each sample collection.
Samples of the pond sediments were screened by the onsite gamma spectroscopy system, and ranged from 0.3 pCilg to 4.0 pCi/g Cs-137. One sample indicated Co-60 at 1.6 pCi/g.
Results are shown in Table 1.
Background sediment samples were obtained from the nearby Ragged Mountain Reservoir, upstream on the drainage feeding into the pond, and the soft rock face and fill dirt in the upper parking area. They were screened by the onsite gamma spectroscopy system and results are shown in Table 2.
Samples from the UVAR pond, UVAR drainage and Ragged Mountain Reservoir were scanned for indication of increased direct gamma levels. Boreholes were gamma logged initially at 6", then at 12" intervals to the borehole bottom. Some locations did require insertion of a sealed tube to maintain the borehole open during gamma logging.
Based on the onsite gamma screening, gamma logging and direct beta readings, six of the highest activity samples were sent to the offsite laboratory for analysis. Gamma spectroscopy and 10 CFR Part 61 analyses for transuranics, Sr-90, and other hard-to-detect radionuclides were performed. Results ranged from 2.08 pCi/g to 3.46 pCi/g for Cs-137, no detectable Co-60 above MDC' level, 1.29 pCi/g to 3.61 pCi/g Ra-226, 2.42pCi/g to 4.77pCi/g Th-232, and Pu-241 at 15.8pCi/g. Results are shown in Table 3.
Two background samples were also submitted to the offsite laboratory for analysis.
Results are shown in Table 4.
' MDC is Minimal Detectable Concentration 1
UVAP Continuing Characterization:
Pond Sediment Summary The remaining unanalyzed samples (those not sent to the offsite laboratory) were retained and stored under chain of custody.
Conclusion Based on the results of offsite laboratory analyses, surface measurements, and gamma borehole logs, the levels and ratios of facility-derived contaminants were determined and no areas in the pond were identified to require remediation. This survey satisfies the continuing characterization requirements of Area 13 and 14 from the characterization report, Appendix A of the University of Virginia Reactor Decommissioning Plan.
2
UVAP Continuing Characterization:
Pond Sedient Summary a
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3
UVAP Continuing Characterization:
Pond Sediment Summary Pond Sediment Samples (Onsite results)
Table I Sample number Interval ~~Logging Lgamma Scan can amma SGeoreoscopY
__________ GmaSetocp K-40 Cs-137 Co-60 Pb-212 Pb-214 U-238 Th-232 Ac-228 Inches CPM CPM pCilgm pCi/gm pCigm pCi/gm pC/gm pC/gm pC/gm pCUgm UVA-PD-002 Oto6 7842 22# 28.6 3.7 1.8 2.3 UVA-PD-0O2DUP 0 to 6 *7120 80+ 22.3 2.3 2.6 _
UVA-PD-003 0 to 6 *6760 50+ 15.8 1.2 1.1 UVA-PD-004 0 to 6 *7028 60+ 38.5 0.6 2.5 2.9 UVA-PD-005-1 0 to 6 6795 13.2 0.6 2.2 1.7 UVA-PD-005-2 6 to 18 7648 160+ 21.1 3.3 2.9 2.7 UVA-PD-005-3 18 to 30 6854 29.5 2.2 1.5 1 2.2 UVA-PD-005B1-1 0 to 6 7518 11.2 0.8 2.5 2.8 UVA-PD-005B1-2 6 to 18 8625 200+ 39.6 3.7 2.3 3.3 LWVA-PD-005B1-3 18 to 30 7568 40.6 3.9 2.9 3.3 UVA-PD-005B2-1 0 to 6 7518 12.6 0.9 2.4 1.5 UVA-PD-005B2-2 6 to 18 8625 180+ 12.4 0.6 2.5 3.1 _
UVA-PD-005B2-3 18 to 30 7568 24.2 2.1 0.9 1.8 UVA-PD-005B3-1 0 to 6 8347 23.3 0.3 1.8 1.3 2.1 LWVA-PD-005B3-2 6to 18 7984 17# 13.5 0.4 1.7 1.1 1.7 UVA-PD-006-1 0 to 6 6686 4.2 0.3 0.8 0.7 UVA-PD-006-2 6to 18 8118 30.2 4.2 3.1 UVA-PD-006-3 18 to 30 6699 20# 64.1 4.5 9.6 UVA-PD-0064 30 to 42 7419 37.7 3.6 2.8 UVA-PD-007-1 Oto 6 5243 23.9 0.6 5.1 1.8 UVA-PD-007-2 6 to 18 5463 22.1 3.4 2.5 UVA-PD-007-3 18 to 30 6102 15.9 1.7 1.5 UVA-PD-007-4 30 to 42 7075 140+ 22.5 2.4 2.2 UVA-PD-007B1-1 0 to 6 *7252 20+ 8.4 1.0 2.8 1.8 UVA-PD-007B2-1 0 to 6 4186 _ __ 0.9 3.3 3.8 UVA-PD-007B2-2 6 to 18 4867 22.0 3.1 2.3 2.8 UVA-PD-007B2-3 18 to 30 5689 14# 21.2 2.3 2.4 3.9 UVA-PD-008-1 0 to 6 6938 8.8 2.2 3.7 UVA-PD-008-2 6 to 18 7173 50+ 39.0 3.3 2.8 1.6 UVA-PD-008-3 18 to 30 6936 31.2 2.1 1.6 1.8 UVA-PD-008B1-1 0 to 6 *6459 14.6 0.6 2.1 2.0 WA-PD-008B1-2 6 to 18 *7846 100+ 33.7 2.9 2.4 UVA-PD-008B2-1 0 to 6 4440 4.1 0.2 0.9 0.6 0.7
^ Denotes no PVC liner used for gamma logging
- Denotes 44-9 Beta /Gamma probe readings
+ Denotes 43-68 Beta/Gamma probe reading Gamma Spectroscopy resutts are considered qualitative for screening purposes due to being counted in a Non-standard preparations of sample for homogeneous mixture and drying.
4
UVAP Continuing Characterization:
Pond Sediment Summary Pond Sediment Samples (Onsite results)
Table 1 cont.
Sample number Interval Gamma Scann Gamma Spectoscopy
______Logging GamIpctocp
=____K-40 Cs-137 Co-60 Pb-212 Pb-214 U-238 Th-232 Ac-228 Inches CPM CPM pC0gm pCLgm pCigm pCVgm pCVgm pCGgm pCVgm pC0gm UVA-PD-008B2-2 6 to 18 6388 = 24.7 2.5 1.9 UVA-PiD-008B2-3 18 to 30 6743 17# 33.1 - 3.1 2.6 _
UVA-PD-009-1 0 to 6 *6149 40+ 31.9 - 2.3 2.8 -- 2.2 UVA-PD-009-2 6 to 18 '7210 - 30A - - 1.9 1.4 -
UVA-PD-011-1 0 to 6 *6540 - 18.4 - 4.1 5.2 UVA-PD-011-2 6to 18 *7517 23.7 0.5 2.0 1.4 2.1 UVA-PD-011-3 18 to 30 *9724 100+ 17.0 0.5 2.3 1.9 - 1.8 UVA-PD-01IBl-1 0 to 6 4962 7.8 3.4 2.4 ___
UVA-PD-011B1-2 6 to 18 6475 6.7 0.7 1.7 3.0 UVA-PD-011B1-3 18 to 30 7773 200+ 17.5 1.0 3.0 1.4 UVA-PD-0111B2-1 0 to 6 *6551 - 4.5 - 1.8 .07 UVA-PD-011B2-2 6 to 18 *8341 30+ 0.7 1.7 1.2 WVA-PD-012-1 Oto 6 *6050 11.1 2.27 1.6 1.2 LVA-PD-012-2 6 to 18 *8325 9.3 1.1 I _ 1.1 1.0 UVA-PD-012-3 18 to 30 *9325 80+ 21.7 1.5 1.8 1.2 1.9 A-PD-012DUP-1 0 to 6 *5820 17.4 2.4 2.8 2.3 A-PD-012DUP-2 6 to 18 *4795 14.3 1.7 2.3 2.3 UVA-PD-012DUP-3 18 to 30 *9820 100+ 24.2 1.4 A 2.4 1.4 1.7 UVA-PD-012B1-1 0 to 6 *5430 11.1 0.6 0.5 2.1 0.9 1.5 UVA-PD-012B1-2 6 to 18 *7572 23.4 _ __ 2.7 1.0 2.8 UVA-PD-012B1-3 18 to 30 *7318 18# 12.8 2.0 1.8 _ _1.5 UVA-PD-012B1-4 30 to 42 *8019 = 22.8 4.5 3.7 3.7 UVA-PD-01282-1 0 to 6 '7765 5.9 10.3 UVA-PD-012B2-2 6 to 18 *10897 280+ 40.3 3.7 2.6 4.2 UVA-PD-012B3-1 0 to 6 21.5 2.8 1.7 2.4 UVA-PD-012B3-2 6 to 18 _ 25.7 2.6 1.5 2.5 UVA-PD-012B3-3 18 to 30 13.0 0.9 0.6 UVA-PD-012B4-1 0 to 6 11.3 0.5 0.7 0.4 UVA-PD-012B4-2 6 to 18 27.2 0.3 2.0 1.2 1.9 UVA-PD-012B5-1 0 to 6 = 29.8 3.2 0.9 2.0 0.8 O 2.2 UVA-PD-013-1 0Oto 6 7094 47.6 1.6 2.6 _
UVA-PD-013-2 6 to 18 7620 17# 27.2 2.3 UVA-PD-013-3 18 to 30 7503 51.5 4.4 3.9 UVA-PD-013-4 30 to 42 8383 = 33.1 __1.7
- Denotes no PVC liner used for gamma logging
- Denotes 44-9 Beta IGamma probe readings
+ Denotes 43-68 Beta/Gamma probe reading Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a Non-standard preparations of sample for homogeneous mixture and drying.
5
UVAP Continuing Characterization:
Pond Sediment Summary Pond Sediment Samples (Onsite results)
Table I cont.
Sample number InteIval Gamma Core Gamma Spectroscoy
_____________ Logging Scan GamIpctocp K-40 Cs-137 Co-60 Pb-212 Pb-214 U-238 Th-232 Ac-228 Inches CPM CPM pC0gm pC0gm pC0/gm pC'/gm pC0gm pCGgm pC0gm pC0gm UVA-PD-013B-1 0 to 6 5237 50+ 10.9 1.4 2.6 1.9 UVA-PD-013B-2 6 to 18 7439 10.7 0.5 1.9 1.5 UVA-PD-013B-3 18 to 30 - - 21.3 1.6 - 2.6 -
UVA-PD-014-1 0 to 6 6653 24# 39.5 0.7 5.7 UVA-PD-014-2 6 to 18 8089 52.1 4.8 3.3 UVA-PD-014-3 18 to 30 7854 50.1 4.5 UVA-PD-014-4 30 to 42 5596 20.2 1.2 UVA-PD-014B-1 0 to 6 12.9 1.1 0.8 UVA-PD-015-1 0 to 6 5729 41.3 3.9 UVA-PD-015-2 6to 18 5371 16# 18.6 0.7 - 1.7 UVA-PD-015-3 18 to 30 7854 - 31.0 0.3 2.9 UVA-PD-015-4 30 to 42 7631 33 1.9 UVA-PD-015B-1 0 to 6 4147 12.5 0.7 0.9 _
UVA-PD-015B-2 6 to 18 5615 15.6 0.7 1.6 1.1 UVA-PD-015B-3 18 to 30 7819 50+ 24.9 1.8 1.2 1.6 UVA-PD-015B-4 30 to 42 6426 - 27.8 _ 2.5 2.7 1.6 -
UVA-PD-015B-5 42 to 54 7415 - 28.2 - .2.2 2.6 2.1 WVA-PD-016-1 0 to 6 6070 38.9 22 -
UVA-PD-016-2 6 to 18 7666 204 34.7 3.3 1.9 2.6 UVA-PD-016-3 18 to 30 8015 - 17.0 1.8 1.6 UVA-PD-016-4 30 to 42 8009 19.8 1.6 1.1 LWVA-PD-017-1 0 to 6 *4655 13.0 2.9 6.8 UVA-PD-017-2 6 to 18 *5538 10+ 9.5 1.6 2.3 3.6 UVA-PD-020-1 0 to 6 *5728 24.0 2.5 UVA-PD-020-2 6 to 18 *6503 30.2 2.4 _
UVA-PD-020-3 18 to 30 *7688 270+ 26.3 3.0 UVA-PD-021B-1 0 to 6 *5350 10.0 I 1.0 1.8 UVA-PD-021B-2 6 to 18 *7130 310+ 26.4 2.4 1.9 __1.8 UVA-PD-0218-3 18 to 30 6375 4.7 1.2 2.0 UVA-CR-001 SURFACE 27000 40# 6.75 0.5 0.7 UVA-CR-002 SURFACE 25000 204 12.4 1.1 UVA-CR-003 SURFACE 22000 20#1 12.5 _ __ 0.7 1.0
- Denotes no PVC liner used for gamma logging
- Denotes 44-9 Beta /Gamma probe readings
+ Denotes 43-68 Beta/Gamma probe reading Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a Non-standard preparations of sample for homogeneous mixture and drying.
6
UVAP Continuing Characterization:
Pond Sediment Summary Background soil sample results (Onsite results)
Table 2 Ragged Mountain Reservoir Sediment Samples Gamma Core Sample number Interval Logging Scan Gamma S ectrosco K-40 Cs-137 Co-60 Pb-212 Pb-214 U-238 Th-232 -228 Inches CPM CPM pC/gm pC/gm pCi/gm pCigm p Clpm C/gm UVA-RS-001-1 Oto6 *2031 .10# 17.4 1.0 0.1 UVA-RS-001-2 6 to 18 *2575 10# 20.8 0.1 0.3 0.2 0.3 UVA-RS-001-3 18 to 30 *2626 10# 22.3 0.1 0.2 0.2 0.3 0.2 UVA-RS-002-1 Oto6 *1906 10# 21.5 0.6 0.3 0.1 UVA-RS-002-2 6 to 18 *2618 10# 20.7 0.2 0.2 0.2 UVA-RS-003-1 Oto 6 *2311 10# 30.0 1.2 LVA-RS-003-2 6 to 18 *3637 10# 25.0 l UVA-RS-003-3 18 to 30 *3782 10# 28.4 _ ______
UVA-RS-004-1 Oto 6 '1860 10# 16.5 UVA-RS-004-2 6to18 *2471 155# 18.8 Upstream Creek Background UVA-BKGSL-001 l Oto 6 1_
l 19.0 I l 1.1 0.8 j 0.9 l__ 1.2 UVA-BKGSL-002 0 to6 11 2 25.11 l f 2.0 1 1.7 1 1 2.0 Rock Face Background UVA-BKGSL-003-1 0 to 6 = 45.0 1 3.7 1.6 _ 3.4 UVA-BKGSL-003-2 6 to 18 54.4 _ 3.2 1.2 4.4 2.7 UVA-BKGSL-003-3 18 to 30 46.9 1 3.4 0.8 3.4 Fill Dirt Back round LUVA-BKGSL-004-1 0 to 6 - 32.4 _ _ 3.4 1.1 l 3.7 UVA-BKGSL-004-2 6 to 18 - 35.3 a 4.2 2.05 j 4.5 UVA-BKGSL-004-3 18 to 30 l 39.6 3.6 1.3 1.2 _ 4.0
'Denotes no PVC liner used for gamma logging
- Denotes 44-9 Beta /Gamma probe readings
+ Denotes 43-68 Beta/Gamma probe reading Gamma Spectroscopy results are considered qualitative for screening purposes due to being counted in a Non-standard preparations of sample for homogeneous mixture and drying.
7
UVAP Continuing Characterization:
Pond Sediment Summary Pond Sediment Samples (Offsfte Laboratory)
Table 3 Sample number Interval Gamma Spectroscopy and Part 61 results pCi/g in Inches Ni-63 Pu-238 Pu-239140 Pu-241 Am-241 Cm-242 CM-244 C-14 TO-99 1H-3 UVA-PD005B1-2 6to 18 -4.68E-02 3.30E-03 6.60E-03 7.22E-01 4.71E-03 O.OOE+00 0.00E+00 2.05E-01 -8.77E-02 1.44E+02 Qualfiter/MDA U/ 9.19E-01 U/ 1.98E402 U/ 2.33E-02 J/ 6.79E-01 Ul 1.28E-02 Ut 1.84E402 Ut 1.29E-02 U 7.99E-01 Ut 7.47E-01 J/ 4.67E+01 UVA-PD-11B1-3 IS to 30 3.06E+00 1.74E-02 2.0SE-02 6.81E-01 9.33E-03 0.00E+00 O.OOE+0O 2.75E-02 4.83E-02 2.59E+02 QualifiertMDA J/ 9.63E-01 Ji 1.18E-02 J12.07E-02 U/ 7.09E-01 Ut2.48E-02 Ut 2.02E-02 UW 1.42E-02 UI 8.11E-01 U17.68E-01 JI 9.07E+01 WAM-P012-3 18 to 30 1.07E+00 1.69E-02 3.S6E-03 9.53E-01 2.OOE-02 -1.43E-02 O.OOE+00 3.24E-01 -8.78E-02 1.33E+02 Quallfier/MDA Jt9.02E-01 UI 2.13E-02 Ut 2.13E-02 J1 7.77E401 Jt1.35E-02 U/ 3.44E-02 Ut 1.37E-02 U/ 7.84E-01 UW7.63E-01 J/ 5.34E+01 WA-PD-012B2-2 6 to 18 1.59E-01 O.OOE+00 2.64E-02 1.31 E+01 8.66E-02 O.OOE+0O 4.37E-02 -1.32E-01 -8.48E-02 5.75E+01 QuafifieriMDA _ W 8.17E401 U/ 1.19E-01 U/ 2.49E-01 Jt8.83 U/ 1.17E-01 W 1.69E-01 U/ 1.18E-01 Ut 8.00E-01 Ui7.60E-01 J/ 3.24E+01 UVA-PD-013B-1 0 to 6 2.29E+01 O.OOE+0O 1.682+0101tE-0O O.OOE.00 O.OOE+00 O.OOE+00 -1.90E-02 5.94E-01 1.I1E+01 Qualtfier/MDA 8.73E-01 Ut 2.67E-01 U/ 1.28E-01 1.06E+01 U/ 1.28E-01 U/ 1.85E-01 U/ 1.29E-01 U/ 8.09E-01 U/ 8.04E-01 U/8.96E+01 UVA-PD-021B-2 6 to 18 1.24E-01 6.92E-03 -1.54E-03 1.07E+00 -1.34E-03 0O.OOE+00 O.OOE+00 2.24E-01 -2.04E-01 5.32E+01 Quallfier/MDA W_8.35E-01 UW 1.84E-02 W/2.17E-02 J/8.91E-01 UW3.202-02 U2.61E-02 U 1.83-02 U/ 8.10E-01 WU 7.5S-01 J/4.96E+01 Sample number Interval Gamma Spectroscopy and Part 61 results pCi/g in _ _ _ _ _ __ _ _ _
Inches Co-6o Ca-137 K-40 Ra-226 Th-232 U-238DHP 1-129L Sr-90 Fe-55 UVA-PD-05B1-2 6 tD 18 I1.32E-02 9.80E-02 3.63E+01 2.02E+00 2.64E+00 2.97E+00 -6.47E-03 S.68E-02 -6.58E+01 Qualifier/ MDA UWI.48E-01 U/ 1.64E-01 1.18 2.37E-01 6.59E-01 1.43 Ut 2.05E-01 U/ 6.05E-01 Ul 2.03E+01 WNA-PD-11B1-3 18 to 30 1.11E401 2.22E+00 3.62E+01 3.29E+00 4.77E+00 not 1.73E-01 1.09E41 -3.95E+01 Qualffier/ MDA U 3.08E-01 2.73E-01 1.82 4.80E-01 1.35 Detected W 6.06E-01 U/ 7.22E-01 UI I.80E+01 UVA-PD-012-3 18 to 30 2.23E-02 2.08E+00 2.78.+01 1.69E+00 2.42E+00 2.92E+00 4.33E-02 1.50E-01 -2.60E+01 QuartfierUtMDA WU 1.52E-01 1.18E-01 9.26E-01 2.18E-01 6.00E-01 1.31 U/ 2.16E-01 UW 6.45E-01 U/ 1.55E+01 WA-PD-012B2-2 6 to 18 2.99E-02 -1.62E-02 3.04E+01 1.50E+00 3.01E+00 not 1.21 E-01 3.14E-01 -3.42E+01 Qualifierd MDA W_1.46E-01 UW 1.24E-01 1.27 1.96E-01 5.58E-01 Detected Ut 2.65E-01 Ut 6.01 E-01 UW 2.03E+01 UVA-PD-013B-1 0 to 6 9.53E-01 3.46E+00 2.13E+01 3.61E+00 4.16E+00 not -2.30E-01 4.27E-02 -421E+01 Qualifier) MDA U/ 6.12E-01 3.18E-01 3.17 5.28E-01 1.53 Detected UW4.54E-01 U/ 8.64E-01 Ut 1.79E+01 WA-PD-021B-2 6 to 18 3.89E-02 2.71E-02 2.88E+01 1.29E+00 2.51E+00 not -1.05E-01 8.76E-01 -4.94E+01 Qualifier/ MDA WU 1.36E-01 U/ 1.22E-01 1.13 1.52E-01 5.57E-01 Detected U/ 2.16E-01 J/ 6.17E-01 U/ 1.34E+01
.~~~~I -
J Qualifier - No U qualifier has been assigned and result Is below the reporting limit, contractual required detection limit, or report value is estimated.
U Qualifier - Analyzed for, but the result is less than the MDC/MDA. Total uncertainty or gamma scan software did not identify the nuclide.
MDC/MDA- The Minimum Detectable Concentration I Minimum Detectable Activity 8
UVAP Continuing Characterization:
Pond Sediment Summary Creek Background, Upstream (Offsite Laboratory)
Table 4 Sample number Interval Gamma Spectroscopy and Part 61 results pCi/g Inches NI-63 Pu-238 Pu-239/40 Pu-241 Am-241 Cm-244 Am-243 C-14 To-99 H-S3 UVA4-KGSL-001 0 to 6 0.00 5.75E-03 5.00E-03 I 1.20 3.28E-02 3.29E-02 3.50e-02 6.50 1.OSE-01 O0.OOE+00 Qualifierl MDA U/ 1.00 Ut 4.0e-02 U/ 1.0e402 1.08 U 5.00E-02 U/ 5.0e-02 3.0e-02 4.09 U/ 1.50e-01 U/ 3.09 WVA-BKGSL-002 0to -4.01E-01 3.30E-02 8.99E-03 0.65 I 2.00E-01 4.45E-02 5.10e-2 3.00 5.54E-02 1.85E+00 QuaflfierlDA U 9.2e-01 U/ 5.0e-02 U4.0e-02 1 1.17 5.00E-02 4.0e.02 3.oe-02 2.61 WI 1.60e-01 U/ 3.59 Co-60 Cs-137 K-40 Fe-55 Th-232 U-238DHP 1-129 Sr-90 Th-230 AKGSL-_ _ O 1.36E-011
_to6 2.77E401l 2.26E+01 -9.25E-01 _1.6E+00 L.58E+0 I -2.38E-01 -4.93E-02 3.26 Qualifier/ MIDA U/ 2.70e-01 2.30e-01 1.69 U/ 1.67 3.0e-02 9.0e-02 Ul 6Ae-01 UI 1.40e-01 2.0e-02 WVA-BKGSL-402 to6 2.45E-02 I 3.81 E-02 l 2.93E+01 4.09E-01 I 1.92E+00 1.65E+00 1.22E-01 l 2.12E-01 1.55 QualifierIMDA W/1.20e-01 U/ 1.30e-01 1.11 U/ 1.22 2.0e-02 8.Oe-02 U/4.0e-01 1.90e-01 3.0e-02 UQualifier - Analyzed for, but the result is less than the MDC/MDA. Total uncertainty or gamma san software did not identify the nudide.
MDC/MDA- The Minimum Detectable Concentration I Minimum Detectable Activity 9