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Seismic Evaluation of Safety Systems at the Savannah River Reactors

Seismic Evaluation of Safety Systems at the Savannah River Reactors
Author:
Publisher:
Total Pages: 11
Release: 1989
Genre:
ISBN:

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A thorough review of all safety related systems in commercial nuclear power plants was prompted by the accident at the Three Mile Island Nuclear Power Plant. As a consequence of this review, the Nuclear Regulatory Commission (NRC) focused its attention on the environmental and seismic qualification of the industry's electrical and mechanical equipment. In 1980, the NRC issued Unresolved Safety Issue (USI) A-46 to verify the seismic adequacy of the equipment required to safely shut down a plant and maintain a stable condition for 72 hours. After extensive research by the NRC, it became apparent that traditional analysis and testing methods would not be a feasible mechanism to address this USI A-46 issue. The costs associated with utilizing the standard analytical and testing qualification approaches were exorbitant and could not be justified. In addition, the only equipment available to be shake table testing which is similar to the item being qualified is typically the nuclear plant component itself. After 8 years of studies and data collection, the NRC issued its ''Generic Safety Evaluation Report'' approving an alternate seismic qualification approach based on the use of seismic experience data. This experience-based seismic assessment approach will be the basis for evaluating each of the 70 pre-1972 commercial nuclear power units in the United States and for an undetermined number of nuclear plants located in foreign countries. This same cost-effective developed for the commercial nuclear power industry is currently being applied to the Savannah River Production Reactors to address similar seismic adequacy issues. This paper documents the results of the Savannah River Plant seismic evaluating program. This effort marks the first complete (non-trial) application of this state-of-the-art USI A-46 resolution methodology.


Seismic Probabilistic Risk Assessment for K Reactor at the DOE Savannah River Site

Seismic Probabilistic Risk Assessment for K Reactor at the DOE Savannah River Site
Author:
Publisher:
Total Pages: 10
Release: 1993
Genre:
ISBN:

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The evaluation of the risk of core melt for the K Reactor indicated an improvement in the strength of the plant as the result of analyses and structural upgrades done for the reactor to satisfy requirements of the NRC USI A-46 unresolved safety issue. The evaluation for operator errors used the THERP methodology and applied this method to conditions required as the result of earthquakes. The evaluation indicated the strength of structures and equipment was stronger after the walk down and analyses were completed than before, although physical changes to the system were minimal. The net result of the re-analysis indicated the overall yearly risk of core melt frequency from earthquakes decreased from 1.2 x 10−4 per year to 7.5 x 10−5. The uncertainty analysis indicated the 95 percentile value was 1.2 x 10−4, and the five percentile value was 5.5 x 10−5. The seismic hazard for the site used an evaluation of the Lawrence Livermore (LLNL) and the Electric Power Research Institute (EPRI) Hazard analysis for the plant site, with generic soils factors from the EPRI study. This hazard was determined from the two studies by comparing the predicted hazards with the historical record, and deleting those predictions that did not come close to the historical record.


Methodologies for Seismic Safety Evaluation of Existing Nuclear Installations

Methodologies for Seismic Safety Evaluation of Existing Nuclear Installations
Author: IAEA
Publisher: International Atomic Energy Agency
Total Pages: 109
Release: 2020-08-26
Genre: Technology & Engineering
ISBN: 920106022X

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Experience shows that an assessment of the seismic capacity of an existing operating facility can be required for a number of reasons, for example identification of potential seismic vulnerabilities based on operating experience events or the periodic safety review programme. This publication covers the seismic safety evaluation programmes to be performed on existing nuclear installations in order to ensure that the required fundamental safety functions are available, with particular attention to the safe shutdown of reactors. It includes lessons learned based on the IAEA Action Plan on Nuclear Safety following the Fukushima Daiichi accident, and updated methodologies for seismic safety evaluation of nuclear installations.


Evaluation of Seismic Safety for Nuclear Installations

Evaluation of Seismic Safety for Nuclear Installations
Author: IAEA
Publisher: International Atomic Energy Agency
Total Pages: 81
Release: 2024-02-07
Genre: Technology & Engineering
ISBN: 9201302231

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This Safety Guide provides recommendations on the seismic safety evaluation of nuclear installations. It addresses all types of new and existing nuclear installations. This Safety Guide presents three assessment methodologies: the deterministic approach, generally known as seismic margin assessment (SMA), seismic probabilistic safety assessment (SPSA), and a combination of SMA and SPSA known as ‘probabilistic safety assessment (PSA) based SMA. This Safety Guide provides specific recommendations on applying a performance-based graded approach to the seismic safety evaluation of nuclear installations other than nuclear power plants. It also covers the relation between seismic safety margins and defense-in-depth (DiD) level 3 and level 4. For new nuclear installations, this Safety Guide provides recommendations to assess adequacy of seismic margin to avoid cliff edge effects considering DiD level 3 and level 4. This publication is intended for use by regulatory bodies, operating organizations, and designers of nuclear installations.


Savannah River Site Seismic Qualification Program Boundary Selection

Savannah River Site Seismic Qualification Program Boundary Selection
Author:
Publisher:
Total Pages: 7
Release: 1991
Genre:
ISBN:

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The Savannah River Site Seismic Qualification Program utilizes methodology developed by the Seismic Qualification Utilities Group and endorsed by both the Nuclear Regulatory Commission and the Department of Energy. The systems selected for seismic upgrade prior to restart will ensure that following a seismic event, the reactor can be safely shut down, decay heat removal can be maintained, and the reactor status can be monitored for a minimum of seventy-two hours. Systems selected were reviewed to establish the boundaries of seismic qualification. Program implementation is being conducted in two phases. Phase on will be conducted prior to restart. It will include evaluating accident prevention systems and selected monitoring and mitigation systems and upgrading as necessary to ensure compliance with DOE requirements. Phase two will evaluate/upgrade other mitigation systems after restart to provide enhanced assurance of reactor safety.


Grouted Support Plates in Reactor Buildings at the Savannah River Site

Grouted Support Plates in Reactor Buildings at the Savannah River Site
Author:
Publisher:
Total Pages: 9
Release: 1991
Genre:
ISBN:

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The Westinghouse Savannah River Company (WSRC) conducted a seismic evaluation of the grouted support plates in the reactor buildings at the Savannah River Site (SRS) in response to issues raised from an earlier analysis. Researchers conducted the tests in a reactor building that was no longer in use and transferred the results to other reactor buildings. This paper discusses tests, results, analysis, and modifications made to achieve seismic qualification. 4 refs.


Priority Ranking of Safety-related Systems for Structural Enhancement Assessment at Savannah River Site

Priority Ranking of Safety-related Systems for Structural Enhancement Assessment at Savannah River Site
Author:
Publisher:
Total Pages: 10
Release: 1992
Genre:
ISBN:

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In order to extend the service life of safety related structures and systems in a logical manner, a Structural Enhancement Program was initiated to evaluate the structural integrity of eight (8) systems, namely: Cooling Water System, Emergency Cooling System, Moderator Recovery System supplementary Safety System, Water Removal System, Service Raw Water System, Service Clarified Water System, and River Water System. Since the level of importance of each system to reactor operations varies from one system to another, the scope of structural integrity evaluation for each system should be prioritized accordingly. This paper presents the assessment of system priority for structural evaluation based on a ranking methodology and specifies the level of structural evaluation consistent with the established priority. The effort was undertaken by a five-member panel representing four (4) major disciplines, including. structures, reactor engineering/operations, risk management and materials. The above systems were divided into a total of thirty-five (35) subsystem. These subsystems were then ranked with six (6) attributes, namely: Safety Classification, Degradation Mechanisms, Difficulty of Replacement, Failure Mode, Radiation Dose to Workers and Consequence of Failure. Each attribute was assigned a set of consequences or events with corresponding weighting scores. The results of the ranking process yielded two groups of subsystems, categorized as Priority I and II subsystems. The level of structural assessment was then formulated accordingly. The prioritized approach will allow more efficient allocation of resources, so that the Structural Enhancement Program can be implemented in a cost-effective and efficient manner.


Energy Research Abstracts

Energy Research Abstracts
Author:
Publisher:
Total Pages: 782
Release: 1995
Genre: Power resources
ISBN:

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