Detecting and mitigating rod drive control system degradation in Westinghouse PWRs

Author

Gunther, W. ; Sullivan, K.

Author_Institution

Brookhaven Nat. Lab., Upton, NY, USA

Volume

38

Issue

6

fYear

1991

fDate

12/1/1991 12:00:00 AM

Firstpage

1760

Lastpage

1765

Abstract

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. The authors present the results of that study pertaining to the electrical and instrumentation portions of the CRD system, including ways to detect and mitigate system degradation

Keywords

ageing; control systems; fission reactor core control and monitoring; fission reactor safety; nuclear power stations; nuclear reactor quality assurance; Westinghouse PWRs; aging; connectors; control rod mechanism; interconnecting cables; manual control rod movement; rod drive control system degradation; Aging; Assembly; Coils; Connectors; Control systems; Degradation; Grippers; Inductors; Integrated circuit interconnections; Logic;

fLanguage

English

Journal_Title

Nuclear Science, IEEE Transactions on

Publisher

ieee

ISSN

0018-9499

Type

jour

DOI

10.1109/23.124173

Filename

124173