from about 60% of the collected soil samples from these areas that were analyzed for 239-2405 on BM aliquots by LFE laboratories. For the remaining 40% of the samples, aliquots from the sieved soil were sent to LASL and LFE for analyses, some of which have not yet been analyzed. If there are significant differences in plutonium concentra- tions between BM and sieved aliquots, then at least three options are available for future action: (1) have LASL and Lab X analyze the sieved aliquots already shipped to them, adjusting, if possible, their plutonium concentrations to what would be expected if they had analyzed BM fraction aliquots; (2) recall the sieved aliquots from LASL and Lab X, replacing them with new BM fraction aliquots from stored library samples; or (3) accept as final the preliminary estimates of plutonium inventory for TTR and B, given in Gilbert et al. this report. C, and D Sites in Area 11 (1975) and for A Site of Area 11 given in These alternatives will be discussed following our presentation of the data. Estimates of 239-240Pu inventory reported in Gilbert et al. (1975) for Area 13 (Project 57) on the NTS are based entirely on BM aliquots and hence are not in need of correction. This is also true for the estimated inventory reported for Area 5 except for 18 samples in stratum 2 analyzed by Lab X on sieved aliquots. Hence, the discussion in this paper is also relevant to these 18 samples. ANALYSIS OF DATA FROM "'A SITE," AREA 11 The land area defined here as A Site is shown in Fig. 1 and the three strata drawn on the basis of Ge(Li) scans for 2355 on soil collected on a grid system are given in Fig. average concentrations of 239-2405, 2. 2355 and 2384 in random soil and associated vegetation are given in Table 1. concentrations in vegetation for 2341 2355 + 236y + 238 U). 2355, 238), amounts) of (0-5 cm) at A Site. Estimates of Table 2 gives average 2354, and total U (234y + Table 3 gives the estimated inventories (total , 235y + 2385 and 239-240 Pu in surface soil The uranium inventories are estimated separately for natural uranium and for uranium from the safety-shot device. 121