Author: Chuck FergusonPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages :
Book Description
Westinghouse Rod Control System Corrective Maintenance Guide
Author: Chuck FergusonPublisher:
ISBN:
Category : Nuclear fuel rods
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
Miswiring in a Westinghouse Rod Control System
Author: Control Rod Guide Tube Wear in Operating Reactors
Author: R. RiggsPublisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 92
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.
Detection and Mitigating Rod Drive Control System Degradation in Westinghouse PWRs
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
A study of the effects of aging on the Westinghouse Control Rod Drive (CRD) System was performed as part of the US NRC's Nuclear Plant aging Research (NPAR) Program. For the study, the CRD system boundary includes the power and logic cabinets associated with the manual control rod movement, and the control rod mechanism itself. The aging-related degradation of the interconnecting cables and connectors and the rod position indicating system also were considered. This paper presents the results of that study pertaining to the electrical and instrumentation portions of the CRD system including ways to detect and mitigate system degradation.
Potential problem with Westinghouse rod control system and inadvertent withdrawal of a single rod control cluster assembly
Author: Aging Assessment of the Westinghouse PWR Control Rod Drive System
Author: William GuntherPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages :
Book Description
Rod Control System Evaluation Program
Author: Tony BakerPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages :
Book Description
Author: