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OSU Reactor Sharing Program FY 1995 annual report

Description: This is the annual report of the activities supported under the Oregon State University Reactor Sharing Program, award number DE-FG06-NE38137. The beginning date for the award was September, 30, 1995 and the end date was September 29, 1996. Work conducted under this award is internally administered at the Radiation Center through a project tasking system. This allows for excellent quality control for the work which is performed from the point of initial contact, through the reactor application,… more
Date: October 1, 1996
Creator: Higginbotham, J.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical specification action requirements for AFW system failures: Method development and application to four PWR plants

Description: Failures in the auxiliary feedwater (AFW) system of pressurized water reactors (PWRs) are considered to involve substantial risk whether a decision is made to either continue power operation while repair is being done, or to shut down the plant to undertake repairs. Technical specification action requirements usually require immediate plant shutdown in the case of multiple failures in the system (in some cases, immediate repair of one train is required when all AFW trains fail). This paper pres… more
Date: September 1, 1996
Creator: Mankamo, T.; Kim, I.S.; Yang, Ji Wu & Samanta, P.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Optimization and implementation study of plutonium disposition using existing CANDU Reactors. Final report

Description: Since early 1994, the Department of Energy has been sponsoring studies aimed at evaluating the merits of disposing of surplus US weapons plutonium as Mixed Oxide (MOX) fuel in existing commercial Canadian Pressurized Heavy Water reactors, known as CANDU`s. The first report, submitted to DOE in July, 1994 (the 1994 Executive Summary is attached), identified practical and safe options for the consumption of 50 to 100 tons of plutonium in 25 years in some of the existing CANDU reactors operating t… more
Date: September 1, 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear reactors built, being built, or planned: 1995

Description: This report contains unclassified information about facilities built, being built, or planned in the US for domestic use or export as of December 31, 1995. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE; from the US Nuclear Regulatory Commission (NRC); from the US reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from US and foreign e… more
Date: August 1, 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Handbook of methods for risk-based analysis of technical specifications

Description: Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operations (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements are based on deterministic analyses and engineering judgments. Improvements in these requirements are facilitated by the availability of plant-specific Probabilistic Risk Assessments (PRAs). The US Nuclear Regulatory Commission (USNRC) Office of Research sponsored research to… more
Date: September 1, 1996
Creator: Samanta, P. K.; Kim, I. S.; Mankamo, T. & Vesely, W. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Core damage frequency perspectives based on IPE results

Description: In November 1988, the US Nuclear Regulatory Commission (NRC) issued Generic Letter 88-20 requesting that all licensees perform an individual Plant Examination (IPE) to identify any plant-specific vulnerability to severe accidents and report the results to the Commission. This paper provides perspectives gained from reviewing 75 Individual Plant Examination (IPE) submittals covering 108 nuclear power plant units. Variability both within and among reactor types is examined to provide perspectives… more
Date: August 1, 1996
Creator: Dingman, S. E.; Camp, A. L.; LaChance, J. L. & Drouin, M. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A compilation of reports of the Advisory Committee on Reactor Safeguards: 1995 annual. Volume 17

Description: This compilation contains 44 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1995. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports b… more
Date: April 1, 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Licensed operating reactors: Status summary report, data as of December 31, 1995. Volume 20

Description: The US Nuclear Regulatory Commission`s monthly summary of licensed nuclear power reactor data is based primarily on the operating data report submitted by licensees for each unit. This report is divided into two sections: the first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 availability factors, capacity factors, and forced outage rates are simple arithmetic averages. Section 2 items in the cumulative column are generally … more
Date: June 1, 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lessons learned from early criticality accidents

Description: Four accidents involving the approach to criticality occurred during the period July, 1945, through May, 1996. These have been described in the format of the OPERATING EXPERIENCE WEEKLY SUMMARY which is distributed by the Office of Nuclear and Facility Safety. Although the lessons learned have been incorporated in standards, codes, and formal procedures during the last fifty years, this is their first presentation in this format. It is particularly appropriate that they be presented in the foru… more
Date: June 1, 1996
Creator: Malenfant, R.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, Tennessee Valley Authority. Supplement number 20

Description: This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (A… more
Date: February 1, 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modeling patterns in data using linear and related models

Description: This report considers the use of linear models for analyzing data related to reliability and safety issues of the type usually associated with nuclear power plants. The report discusses some of the general results of linear regression analysis, such as the model assumptions and properties of the estimators of the parameters. The results are motivated with examples of operational data. Results about the important case of a linear regression model with one covariate are covered in detail. This ca… more
Date: June 1, 1996
Creator: Engelhardt, M.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Completely automated nuclear reactors for long-term operation

Description: The authors discuss new types of nuclear fission reactors optimized for the generation of high-temperature heat for exceedingly safe, economic, and long-duration electricity production in large, long-lived central power stations. These reactors are quite different in design, implementation and operation from conventional light-water-cooled and -moderated reactors (LWRs) currently in widespread use, which were scaled-up from submarine nuclear propulsion reactors. They feature an inexpensive init… more
Date: January 1, 1996
Creator: Teller, E.; Ishikawa, M. & Wood, L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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An analysis of the impacts of economic incentive programs on commercial nuclear power plant operations and maintenance costs

Description: Operations and Maintenance (O and M) expenditures by nuclear power plant owner/operators possess a very logical and vital link in considerations relating to plant safety and reliability. Since the determinants of O and M outlays are considerable and varied, the potential linkages to plant safety, both directly and indirectly, can likewise be substantial. One significant issue before the US Nuclear Regulatory Commission is the impact, if any, on O and M spending from state programs that attempt … more
Date: February 1, 1996
Creator: Kavanaugh, D.C.; Monroe, W.H. & Wood, R.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Savannah River Site production reactor technical specifications. K Production Reactor

Description: These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This repo… more
Date: February 1, 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Review and Updates of the Risk Assessment for Advanced Test Reactor Operations for Operating Events and Experience

Description: Annual or biannual reviews of the operating history of the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory (INEL) have been conducted for the purpose of reviewing and updating the ATR probabilistic safety assessment (PSA) for operating events and operating experience since the first compilation of plant- specific experience data for the ATR PSA which included data for operation from initial power operation in 1969 through 1988. This technical paper briefly discusses the… more
Date: August 1, 1996
Creator: Atkinson, S. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of a risk-based inservice inspection program for a liquid metal reactor

Description: The emerging application of risk-based assessment technology to the operation and maintenance of nuclear power plants holds considerable promise for improving efficiency and reducing operating costs. EBR-II is liquid-metal-cooled fast reactor which operated for thirty years before shutting down in September 1994 due to program termination. Prior to the shutdown of EBR-II, an in-service inspection (ISI) program was developed that exploited certain advantages of the liquid-metal reactor design, e… more
Date: May 1, 1996
Creator: King, R. W. & Buschman, H. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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