Doses to offsite individuals and at-risk populations from Savannah River Site (SRS) releases for the period 1954--1989 have been estimated. These data have been generated in response to questions regarding the overall impact of SRS operations on the offsite environment. These data are comprehensive in the sense-that all known measured and calculated atmospheric and liquid release values have been included in the assessment. This work should not be interpreted as a formal dose reconstruction as current sites-specific-data used. Three key assumptions were for these doses which affect their interpretation: (1) persons in the at-risk populations were assumed to have remained at their designated locations continuously from 1954--1989, (2) it was assumed that these individuals will live for years following 1989, and (3) the Beaufort-Jasper water treatment plant was assumed to have operated continually since 1954 even though operations actually began in 1965. Dose estimates for several at-risk individuals and populations are listed in Table 4. A comparison of the doses from the SRS and other sources of ionizing radiation in the environment has also been included.

Current criteria for criticality safety for spent fuel shipping and storage casks are conservative because no credit is permitted for the effects of burnup of the fuel inside the cask. Cask designs that will transport and store large numbers of fuel assemblies (20 or more) must devote a substantial part of their payload to criticality control measures if they are to meet this criteria. The Department of Energy is developing the data necessary to support safety analyses that incorporate the effects of burnup for the next generation of spent fuel shipping casks. The efforts described here are devoted to the development of acceptance criteria that will be the basis for accepting safety analyses. Preliminary estimates of the uncertainties of the effects of burnup have been developed to provide a basis for the consideration of critically safety criteria. The criticality safety margins in a spent fuel shipping or storage cask are dominated by the portions of a fuel assembly that are in low power regions of a reactor core, and the reactor operating conditions are very different from spent fuel storage or transport cask conditions. Consequently, the experience that has been gathered during years of reactor operation does not apply directly …

A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.

Letter opinion issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Jim Mattox, regarding a legal question submitted for clarification; Whether the board's composition violates article XVI, section 30a, of the Texas Constitution.

Doses to offsite individuals and at-risk populations from Savannah River Site (SRS) releases for the period 1954--1989 have been estimated. These data have been generated in response to questions regarding the overall impact of SRS operations on the offsite environment. These data are comprehensive in the sense-that all known measured and calculated atmospheric and liquid release values have been included in the assessment. This work should not be interpreted as a formal dose reconstruction as current sites-specific-data used. Three key assumptions were for these doses which affect their interpretation: (1) persons in the at-risk populations were assumed to have remained at their designated locations continuously from 1954--1989, (2) it was assumed that these individuals will live for years following 1989, and (3) the Beaufort-Jasper water treatment plant was assumed to have operated continually since 1954 even though operations actually began in 1965. Dose estimates for several at-risk individuals and populations are listed in Table 4. A comparison of the doses from the SRS and other sources of ionizing radiation in the environment has also been included.