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High pressure cation exchange is used routinely at the Transuranium Processing Facility (TRU) to separate decigram quantities of transplutonium elements that have been produced in the High Flux Isotope Reactor. The process is based on chromatographic elution from Dowex 50W-X8 resin using ammonium alpha-hydroxyisobutyrate (AHIB) as the eluent [I). Since 1967, a total of 4.6 g of 252cf, 0.5 g of 249 B k, 19 m g o f 253 ESj and 10 pg of 257p m (estimated) have been separated at TRU using this procedure. Original development of this process at ORNL was done by Campbell and Buxton (J2,3)» and was later adapted for processing at high activity levels at TRU by Baybarz, et al (4_). The use of high pressure with very small resin has helped mitigate two problems associated with processing highlyradioactive solutions of transplutonium elements. First, radiation damage is reduced since higher flow rates and quicker separations are possible; and second, radiolytic gassing is suppressed.

Es capture cross sections/Thermal cross sections and resonance integrals!Formation of ls,m Esand" 4 *Es AbstractIntegral neutron cross sections have been measured for 2S3 Es. The partial thermal capture cross sections and resonance integrals forming the 39.3-hour 2 S4m Es and the 276-day 2 54g Es relative to cobalt standards are reported. Analysis of alpha spectra in experiments measuring 254m Es formation gives σ^, = 178 ± 15 and / = 3750 ± 200 barns. Mass spectrographs analyses in experiments measuring 254g Es formation give a t h = 5.8 ± 0.7 and / = 114 ±7 barns.In this paper we describe the measurement of the neutron capture cross section of 253 Es. 253 Es captures neutrons to form the 39.3-hour isomer, 2S4m Es, as well as the 275.7-day ground state 254g Es. (See Fig. 2.) Because of the marked difference in the spin states of these two nuclides, no isomeric transition has been detected in the decay of 254m Es to form 254g Es. Thus, neutron capture in 2S3 Es to form 254g Es provides the only pathway to that isotope. Capture in 253 Es to form 254m Es has the consequence of lowering the 2S4g Es yield by burning out the 253 Es target.

SUMMARY

Attachment 1 provides justification, as required in 10 CFR 73.5, that the exemption would not endanger life or property or the common defense and security, and is otherwise in the public interest. The changes proposed in this exemption are not required to address an immediate safety or security concern, but rather are being submitted in response to the referenced NRC letter requesting FirstEnergy Corp. to evaluate the applicability of the current 10.CFR 73.55 to TMI Unit 2.

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The Submerged Demineralizer System (SDS) flowsheet for decontamination of the high-activity-level water at the Three Mile Island Unit 2 Nuclear Power Station was evaluated at Oak Ridge National Laboratory in a study that included filtration tests, ion exchange column tests, and ion exchange distribution tests. The contaminated waters, the SDS flowsheet, JWw_ " and the experiments made are described. The experimental results were used to predict the SDS performance and to indicate potential improvements.