Author: Electric Power Research InstitutePublisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages :
Book Description
Rod Control System Maintenance Guide for Westinghouse Pressurized Water Reactors
Author: Electric Power Research InstitutePublisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages :
Book Description
Aging Mechanisms in the Westinghouse PWR (Pressurized Water Reactor) Control Rod Drive System
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 5
Book Description
An aging assessment of the Westinghouse Pressurized Water Reactor (PWR) Control Rod System (CRD) has been completed as part of the US NRC's Nuclear Plant Aging Research, (NPAR) Program. This study examined the design, construction, maintenance, and operation of the system to determine its potential for degradation as the plant ages. Selected results from this study are presented in this paper. The operating experience data were evaluated to identify the predominant failure modes, causes, and effects. From our evaluation of the data, coupled with an assessment of the materials of construction and the operating environment, we conclude that the Westinghouse CRD system is subject to degradation which, if unchecked, could affect its safety function as a plant ages. Ways to detect and mitigate the effects of aging are included in this paper. The current maintenance for the control rod drive system at fifteen Westinghouse PWRs was obtained through a survey conducted in cooperation with EPRI and NUMARC. The results of the survey indicate that some plants have modified the system, replaced components, or expanded preventive maintenance. Several of these activities have effectively addressed the aging issue. 2 refs., 2 figs., 2 tabs.
Westinghouse Rod Control System Corrective Maintenance Guide
Author: Chuck FergusonPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages :
Book Description
Maintenance of Process Instrumentation in Nuclear Power Plants
Author: H.M. HashemianPublisher: Springer Science & Business Media
ISBN: 3540337040
Category : Technology & Engineering
Languages : en
Pages : 309
Book Description
This book provides a training course for I and C maintenance engineers in power, process, chemical, and other industries. It summarizes all the scattered literature in this field. The book compiles 30 years of knowledge gained by the author and his staff in testing the I and C systems of nuclear power plants around the world. It focuses on process temperature and pressure sensors and the verification of these sensors’ calibration and response time.
Systems Summary of a Westinghouse Pressurized Water Reactor Nuclear Power Plant
Author: George MaschePublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 262
Book Description
Requirements Specification for Rod Control System Upgrade
Author: J. A. NaserPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages :
Book Description
Standardized Technical Specifications for Westinghouse Pressurized Water Reactors
Author: P. C. WagnerPublisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages : 588
Book Description
Standard Technical Specifications for Westinghouse Pressurized Water Reactors
Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor RegulationPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 616
Book Description
Technical Progress Report, Pressurized Water Reactor (PWR) Project for the Period ...
Author: The Shippingport Pressurized Water Reactor
Author: Publisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages : 48
Book Description
A total of 193 annotated references to unclassified reports on the design, development and construction of the Shippingport Pressurized Water Reactor is presented. Author, subject, and report number indexes are included.