This book wall I:)nllNu'edali in account of work sponsored by en a_iency of the United States Goverrtment. NeitP_erthe United $tatu Government nor any agency thereof, nor any of their employeeS, rr_kes any werrsrtty, exlocess or imDlied, or assumes any legal iilbility or rt_:onsibi_ity for the eccurecy, completeness, or usefulnus of any _nform_tion, OPl_ratul, product or f_roceu discJosed, or re_rwents Chatits us_ wouJd ., t_ot infringe DrivateiV own_ rightS. Refer_c_ herein to any sl:mcific commercial 13roduct, prooNI, or service by trodo name, trade,irk, rrtanufecturer, or otherwise, ¢IOU not _'i_Y constitute or im_y its ec_d_t, recommendation, or favoring by the United Stlltos Government 04' any ag_c_ thereof. The views snd ol;)inions of " authors exl:)mued herein do not necemmrily state or reflect those of the United StaNm Goverrtr_mt or orty sgency thereof.

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87185 and Live)m'ore, California 94550 ./" Sandia is a m)lt(rogram laboratory ope~ated by Sandia Corporation, a Lockheed,Martin Company, for t?elrnited States Department of Energy~der Contract DE-AC04-94AL85000. r A-d~osure of invention relating to the subject of this publication has

The Three ^ile Island Unit-2 reactor building atmosphere was sampled prior to the reactor building purge. Samples of the containment atmosphere were obtained using specialized sampling equipment installed through penetration R-626 at the 358-foot (109-meter) level of the TMI-2 reactor building. The samples were subsequently analyzed for radionuclide concentration and for gaseous molecular components (0^, Np, etc.) by two independent laboratories at the Idaho National Engineering Laboratory (INEL). The sampling procedures, analysis methods, and results are summarized in this report. 85 3 The concentration of Kr present was found to be 1.02 ± 0.05 uCi/cm 3 at STP or 0.88 ± 0.04 wCi/cm at TMI-2 reactor building conditions. Samples 90 137 134 of suspended particulate contained Sr, Cs, and Cs at levels of 1.9 X 10"^° ± 0.3 X 10"^° wCi/sm"^, 8.4 x 10"^° ± 0.9 x 10"^° yCi/cm^, and 1.3 x 10"^*^ ± 0.1 x 10"^° MCi/cm'^, respectively. Tritium and ^\ activity levels were 4.7 x 10"^ ± 0.8 x 10"^ MCi/cm"^ and 3.5 x lo"''-7 3 ± 0.9 X 10 wCi/cm. Measured concentrations or detection limits for these and 26 other radionuclides are reported. Additionally, the relative concentrations of the stable gaseous components, determined by mass spectrometry, are reported. 11 ACKNOWLEDGMENTS This sampling program was conducted as a joint effort of EG&G Idaho, Inc., Exxon Nuclear Idaho Co., Inc., General Public Utilities/Metropolitan Edison, and personnel of other technical companies providing support to General Public Utilities/Metropolitan Edison. The authors wish to acknowledge the radiochemical analysis work performed by C. W. Filby and her laboratory staff and the staff of the Mass Spectrometry Laboratory under G. W. Webb. The neutron activation analyses were performed by C. P. Willis and F. A. Hohorst. Very special thanks are extended to Michael Pavelek and

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