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Systematic evaluation program review of NRC Safety Topic VI-10. A associated with the electrical, instrumentation and control portions of the testing of reactor trip system and engineered safety features, including response time for the Dresden station, Unit II nuclear power plant

Description: This report documents the technical evaluation and review of NRC Safety Topic VI-10.A, associated with the electrical, instrumentation, and control portions of the testing of reactor trip systems and engineered safety features including response time for the Dresden II nuclear power plant, using current licensing criteria.
Date: November 1, 1980
Creator: St. Leger-Barter, Gerald
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Systematic evaluation program review of NRC Safety Topic VI-7. 3 associated with the electrical, instrumentation and control portions of the ECCS actuation system for the Dresden II Nuclear Power Plant

Description: This report documents the technical evaluation and review of NRC Safety Topic VI-7.A.3, associated with the electrical, instrumentation, and control portions of the classification of the ECCS actuation system for the Dresden II nuclear power plant, using current licensing criteria.
Date: November 1, 1980
Creator: St. Leger-Barter, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Overview of United States Department of Energy activities to support life extension of nuclear power plants

Description: Today, 109 nuclear power plants provide over 20 percent of the electrical energy generated in the US The operating license of the first of these plants will expire in the year 2000; one-third of the operating licenses will expire by 2010 and the remaining plant licenses are scheduled to expire by 2033. The National Energy Strategy assumes that 70 percent of these plants will continue to operate beyond their current license expiration to assist in ensuring an adequate, diverse, and environmental… more
Date: November 1, 1993
Creator: Harrison, D. L. & Rosinski, S. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391): Supplement No. 19

Description: Supplement No. 19 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with (1) additional information submitted by the applicant since Supplement No. 18 was issued, … more
Date: November 1, 1995
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Integrated systems analysis of the PIUS reactor

Description: Results are presented of a systems failure analysis of the PIUS plant systems that are used during normal reactor operation and postulated accidents. This study was performed to provide the NRC with an understanding of the behavior of the plant. The study applied two diverse failure identification methods, Failure Modes Effects & Criticality Analysis (FMECA) and Hazards & Operability (HAZOP) to the plant systems, supported by several deterministic analyses. Conventional PRA methods were also us… more
Date: November 1, 1993
Creator: Fullwood, F.; Kroeger, P. & Higgins, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Licensed reactor nuclear safety criteria applicable to DOE reactors

Description: This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides… more
Date: November 1, 1993
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced liquid-metal-reactor development at ANL during the 1980s

Description: The fundamental long-term rationale for the liquid-metal reactor (LMR) remains unchanged - to provide for resource extension by consuming the more abundant isotope of uranium. The design goals for the next generation of breeder reactors include a concerted effort to provide engineering solutions that can positively impact on the technical issues and on the public perception issues that harry the current generation of commercial power reactors. The work at Argonne National Laboratory since late … more
Date: 1990-11~
Creator: Wade, David C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Licensee contractor and vendor inspection status report: Quarterly report, July--September 1997. Volume 21, Number 3

Description: A fundamental premise of the US Nuclear Regulatory Commission (NRC) licensing and inspection program is that licensees are responsible for the proper construction and safe and efficient operation of their nuclear power plants. The Federal government and nuclear industry have established a system for the inspection of commercial nuclear facilities to provide for multiple levels of inspection and verification. Each licensee, contractor, and vendor participates in a quality verification process in… more
Date: November 1, 1997
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure, Volume 1, Final report

Description: With the issuance of the final Decommissioning Rule (July 27, 1988), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. T… more
Date: November 1, 1995
Creator: Konzek, G.J.; Smith, R.I.; Bierschbach, M.C. & McDuffie, P.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Volume 2, Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, Final report

Description: With the issuance of the final Decommissioning Rule (July 27, 1998), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. T… more
Date: November 1, 1995
Creator: Konzek, G.J.; Smith, R.I.; Bierschbach, M.C. & McDuffie, P.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An overview of FFTF (Fast Flux Test Facility) contributions to Liquid Metal Reactor Safety

Description: The Fast Flux Test Facility has provided a very useful framework for testing the advances in Liquid Metal Reactor Safety Technology. During the licensing phase, the switch from a nonmechanistic bounding technique to the mechanistic approach was developed and implemented. During the operational phase, the consideration of new tests and core configurations led to use of the anticipated-transients-without-scram approach for beyond design basis events and the move towards passive safety. The future… more
Date: November 1, 1990
Creator: Waltar, A. E. & Padilla, A., Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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