ML20206U461

Forwards Analytical Results of Samples Described in Apps G, H & I of Rept 70-0824/85-08,closeout Insp & Confirmatory Survey for Phase I,Bldg C on 851009-11 & 1118-21 & Results of Spiked Samples Prepared by Contractor

ML20206U461
Person / Time
Site:	07000824
Issue date:	06/24/1986
From:	Barr K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Ayers P BABCOCK & WILCOX CO.
References
NUDOCS 8607100495
Download: ML20206U461 (13)

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%L40 JUN 2 41996 Babcock nd Wilcox Company '

ATTN: Dr. Paul S. Ayres, Manager Lynchburg Technical Operations Research and Development Division P. O. Box 11165 Lynchburg, VA 24506-11165 -

Gentlemen:

SUBJECT:

NRC CONFIRMATORY SAMPLE RESULTS, PHASE I 0F BUILDING C -

REPORT NO. 70-824/85-08 Our letter of February 13, 1986, transmitted the results of our closeout inspection and confirmatory survey for Phase I of your Building C conducted during the period October 9-11 and November 18-21, 1985. The samples described in Appendices G, H and I of the report were sent to a contractor for analysis.

After the onsite inspection, arrangements were also made for you to receive for analysis a spiked sample that had been prepared by our contractor. The enclosures to this letter report the analytical results of those samples. These results have also been provided to the Uranium Fuel Licensing Branch, Office of Nuclear Material Safety and Safeguards, who will communicate with you directly concerning the evaluation of those results.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC's Public Document Room.

Should you have any questions concerning this letter, please contact us.

Sincerely, Kenneth P. Barr, Chief Nuclear Materials Safety and Safeguards Branch Division of Radiation Safety and Safeguards

Enclosures:

1. Special Sample Results from Confirmatory Survey

2. Soil Sample Results from Confirmatory Survey

3. Spiked Sample Results 860710o495 860624 '

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I l ENCLOSURE 1 SPECIAL SAMPLE RESULTS FROM CONFIRMATORY SURVEY Appendix G to Inspection Report No. 70-824M5-08 contained a description of 15 special samples that were obtained during the confirmatory survey (Table 1).

The samples were forwarded to the Department of Energy's Radiological Environmental Sciences Laboratory (RESL) for analysis. All samples were initially counted for gross alpha and beta radioactivity and isotopic identification by gamma spectroscopy (Table 2). Two of the samples were then processed by chemical separation and counted on a surface barrier detector (Table 3).

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l TABLE 1 SPECIAL SAMPLE LOCATIONS AND DESCRIPTIONS Sample No. Date Location Description 1 11/20/85 Pit under Lab 50, grid 1778 Sludge from pit sump 2 11/20/85 North wall of Lab 44 Paint from backside of electrical conduit 3 11/20/85 South ceiling of Lab 44 Paint from exterior of water pipe 4 11/21/85 Southeast corner of front Cloth wipe inside hallway of ventilation duct 5 11/21/85 Ventilation portal between . Approximate 4" X 4" Labs 27 and 50 patch from furnace filter 6 11/21/85 West side of Lab 43 Cloth wipe inside of ventilation duct 7 11/21/85 Ceiling of Lab 43 Sediment from dead-Jeg of sprinkler s header - approxi-mately one pint of water filtered through a-#41 filter 8 11/21/85 Front hallway wall east of Concrete and paint door 6, grid 377 9 11/21/85 Office 1, east wall, grid II Concrete and paint 10 11/21/85 Lab 43, north wall, east of Concrete and paint door grid 1059 11 11/21/85 - Lab 44, south wall, east of Concrete and paint door, grid 1291 12 11/21/85 Lab 27, north wall, grid 832 Concrete and paint 13 11/21/85 Lab 25, north wall, grid 501 Concrete and paint

?S 11/21/85 Lab 52, north wall, grid 1571 Concrete and paint C

15 11/21/85 Lab 53, floor, grid 1678 Concrete from around sump

TABLE 2 SPECIAL SAMPLE ANALYSIS foci /cm)

Sample No. Gross Alpha Gross Beta Co-60 U-235 Pa-243m An-241 Cs-137 1 1714 1215 ND ND ND ND 0.0810.12 2 412 714 ND ND ND ND 0.310.2 3 3817 1116 ND ND ND ND 0.0310.08 4a 3516 4816 ND ND ND ND 814 Sa 320140 158114 ND ND ND ND 313 6a 2114 2614 ND ND ND ND 313 7a 1312 311 ND ND ND ND 1.110.05 8 2014 3315 ND ND ND ND 0.2010.15 9 1413 2315 ND ND ND ND O.0910.15 10 712 1214 ND ND ND ND O.0910.09 11 1012 2515 ND ND ND ND O.0510.10 12 21t4 2915 ND ND ND ND O.1610.13 13 1614 3816 ND ND ND ND 0.0710.10 14 1013 813 ND ND ND ND 0.1310.22 15 1914 1114 ND ND ND ND 0.1310.09

a. Results are reported in pCi/ Sample

b. ND = None Detected D. .W - O

TABLE 3 PROCESSED SPECIAL SAMPLE ANALYSIS Sample No. Am 241 Pu-R38 Pu-239/240 Th-228 Th-230 Th-232 U-234/233 U-235 U-238 3(pci/ge) 10.610.3 0.8710.05 30.910.9 0.5810.06 0.5510.06 0.6410.06 3.7210.14 0.1910.03 1.2310.07 5(pci/ sample) 6.310.14 0.7010.2 32.111.2 1.7010.3 0.9010.4 1.5010.3 85.0012 3.7010.3 35.9011.2

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ENCLOSURE 2 S0IL SAMPLE RESULTS FROM CONFIRMATORY SURVEY Appendix H to Inspection Report No. 70-824/85-08 contained a description of 14 soil samples collected within the excavations under Phase I of Building C.

Appendix I of the report contained a description of 9 samples taken from drums of soil which the licensee had previously analyzed and two background soil samples.

All samples were forwarded to DOE /RESL for analysis. All samples were initially counted for gross alpha and beta radioactivity and isotopic identification by gamma spectroscopy (Table 1). Eight of the samples were then processed by chemical separation and counted on a surface barrier detector (Table 2). A comparison was then performed of the results of the latter analysis for six of the drum samples and the corresponding licensee results (Table 3).

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TABLE 1 .

EXCAVATION. DRUM AND BACKCRCUND S0ll SAMPLE ANALYSIS Gamma Isotoolc Sample ID Gross Alpha Gross Beta Co-60 U-235 Pa-243m Am-241 Cs-137 pCi/qm pCi/qm pCi/qm pCl/qm pCi/qm pCi/qm DCi/qm SN1132 (Soil #1) a-813 a512 ND .091.06 -1.312.1 ND .011.04 SN1133 (Soil #2) a-311 a613 ND .091.06 514 ND .051.04 SN1134 (Soil #3) a-712 a1115 ND .101.07 Si5 ND .091.05 SN1135 (Soil #4) a-311 a412 ND .071.06 814 ND .151.05 SN1136 (Soil #5) a-712 a814 ND .001.07 016 ND .041.05 SN1137 (Soil #6) a-010.3 a1015 ND 101.06 -314 ND .151.05 SN1138 (Soil #7) a-211 a814 ND .211.07 515 ND .15i 05 SN1139 (Soil #8) a-211 a914 ND .051.04 515 ND .221.06 SN1140 (Soil #9) e-1.010.3 a312 ND .021.07 915 ND 101.04 SN1141 (Soil #10) a-1.010.3 a713 ND .011.07 -515 ND .021.05 SN1142 (Soil #11) a-912 a1015 .691.09 .011.05 -113 ND .251.07 SN1143 (Soil #12) a-1.010.3 a412 ND .0516 -214 ND .011.05 SN1144 (Soll #13) a-813 a814 ND .141.06 015 ND .101.08 S91145 (Soil #14) a-411 a814 ND .041.06 513 ND .051.05

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SN1146 (Soil PDPD 308) a2116 a713 ND .291.06 -1.513.9 1.79i.16 .001.05 SN1147 (Soil PDPD 383) -

a3218 a1516 ND .291.07 015 2.91.2 .011.02 SN1148 (Soil PDPD 542) a-712 a713 ND .051.06 -114 ND .101.04 SN1149 ( Soll PDPD 836) a215 a1115 ND .011.06 414 ND 161.05 SN1150 (Soil PDPD 1834) a0.010.3 a1215 ND .211.06 -1.613.3 ND .021.03 r -

SN1151 (Soil PDPD 1917) a2015 a713 ND .271.06 614 1.531.14 .121.04 SN1152 (Soil Background 2214 1215 ND .011.06 -614 ND 0.91.05 23-5-2)

SN1153 (Soil Background) 1914 1415 ND .071.07 -215 ND .331.06 SN1154 (Soil PDPD 312) 896124 a1918 ND .491.06 1115 4.910.2 .041.04 SN1155 (Soil PDPD 420) 8126131 a1717 ND .461.07 -214 8.513 .041.05 SN1156 (Soil PDPD 1173) a-211 a814 ND .061.06 114 1.07i.16 .051.05

a. Soil background gross alpha and beta levels have been subtracted,

b. Results a re reported in pCl/ Sample, t

c. ND - none detected.

d. Other isotopes identified in some samples by gamma spectroscopy were Ac-228, K-40, Pb-212, and Pb-214.

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TABLE 2 PROCESSED SAMPLE ANALYSIS (DCi/cm)

Am-241 Pu-2)$ Pu-239/240 Th-228 Th-230 Th-R3R U-234/233 U-235 U-236 SN1146 1.491.05 .111.01 4.501.14 1.131.05 1.131.05 1.111.05 6.461.17 .271.02 1.771.06 SN1147 2.421.08 .261.02 9.01.3 .941.05 .931.05 .971.05 9.11.2 .361.02 3.481.10 SN1151 1.371.05 181.01 6.81.2 .931.05 .911.05 .911.05 8.81.2 .421.03 3.611.10 SN1152 * .00171.0035 .01.002 .0021.002 1.041.04 .991.04 1.131.05 1.111.04 .041.01 1.051.03 SN1153 .0061.004 .0021.002 .0141.003 1.211.05 1.241.05 1.111.05 1.281.04 .071.01 1.241.04 SN1154 4.21.2 471.06 13.81.5 1.391.12 1.421.14 1.241.12 9.61.3 .381.06 4.41.2 SN1155 7.51.3 1.121.09 40.111.2 2.031.16 1.431.13 1.711.13 13.81.4 .781.08 4.51.2 SN1156 .931.03 .061.01 3.801.11 1.001.04 .971.04 1.001.04 1.361.04 .071.01 1.281.04

• Result of substraction of statistical backgroJDd Value.

b + _% = 0

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TABLE 3 BW LRC/NRC COMPARISONS dmC1/om)

Am241 Pu (239.238.240) Th232 U (233. 234. 231)

SampIe BMf .N_RQ BMf MRQ _BM! j[RQ BMf !LRQ SN1154 3.08 4.2 16.57 14.27 .99 1.24 17.04 9.98 SN1155 5.74 7.5 30.89 40.22 1.14 1.71 22.58 14.58 SN1156 1.28 .93 6.92 3.86 .95 1.00 3.44 1.43 SN1146 .95 1.49 4.09 4.61 1.76* 1.11 4.21* 1.73 SN1147 1,71 2.42 7.38 9.26 1.76* .97 2.01* 9.46 SN1151 .95 1.37 4.10 6.98 1.76* .91 4.98* 9.22

• Includes mean background o __ .

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ENCLOSURE 3 SPIKED SAMPLE RESULTS As a check of the licensee's analytical techniques, DOE /RESL prepared a spiked sample and forwarded it to the licensee for analysis. The licensee's results were compared to the spiked values (Table 1) using the criteria in Table 2.

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TABLE 1 NRC SPINED SOIL SAMPLE Ratio Compa ris ion Istone B&W. pCi/am NRC. pCi/or Resolution Licensee /NRC Compa ri son Pu-239 <3520* 7.3 1 51 14 NA No Compa rison Am-241 6.6 4.7 i .33 14 1.41 Ag reement Nb-94 97.8 71 1 5.0 14 1.37 Ag reement

• Licensee used indirect methods to account for plutonium during decontamination surveys.

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TABLE 2 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This table provides criteria for comparing results of capability +,ests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.

In these criteria, the judgement limits are variable in relation to the comparison of the NRC's value to its associated uncertainty. As that ration, referred to in this program as " Resolution," increases, the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decreases.

RATIO = -LICENSEE VALUE NRC REFERENCE VALUE Resolution Agreement

<4 0.4 - 2.5 4-7 0.5 - 2.0 -

8 - 15 0.6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25

>200 0.85 - 1.18 s, c o

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