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IEEE 382
IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations
Year: 2006
Abstract: Foreword
(This introduction is not part of IEEE Std 382-1996, IEEE Standard for Qualification of Actuators for Power-Operated Valve Assemblies With Safety-Related Functions for Nuclear Power Plants.)
Applicants for a construction permit or operating license for a nuclear generating station are required to provide assurance that systems, components, and structures are adequate for their service conditions to comply with the Code of Federal Regulations 10 CFR 50, Appendix B Quality Assurance Criteria, and Criterion III Design Control. Each applicant has the responsibility to ensure that this or any other standard, if used, is pertinent to the application and that the integrated performance of the station is acceptable. Implementation of this standard requires the applicant to produce documentary evidence to ensure that the valve actuator can perform its intended function.
Typical design basis event conditions for principal reactor types are presented as one source of parameters for generic-type tests. If the actual conditions of a specific application differ, it will be the obligation of the user to specify these actual conditions.
The numerical values presented in this standard envelop current industry design with respect to radiation types and levels; seismic levels; temperature, pressure, and humidity levels; post-accident periods of operability; spray initiation, and duration. Composition of environment may change in the future, so the user is cautioned to verify the suitability of these values for each application.
This revision was prepared by Working Group SC2.3 of the Nuclear Power Engineering Committee of the IEEE Power Engineering Society. The membership of the working group at the time this revision was completed included the following:
Ivan Wilkinson, Chair
Robert Arnold
Nissen M. Burstein
Sal P. Carfagno
Walter J. Denkowski*
W. F. Murray
Clyde T. Nieh
*Deceased 1995
The following persons were on the balloting committee:
Wes W. Bowers
Dan F. Brosnan
Nissen M. Burstein
Aris S. Candris
S. P. Carfagno
Robert C. Carruth
Robert L. Copyak
Gary L. Doman
Edward F. Dowling
Arthur R. DuCharme
Rich E. Dulski
Jay Forster
J. R. Fragola
John M. Gallagher
Wil C. Gangloff
Louis W. Gaussa
Luis C. Gonzalez
Lawrence P. Gradin
J. K. Greene
Britton P. Grim
Robert E. Hall
Joe Hazeltine
Gregory K. Henry
Sonny Kasturi
James T. Keiper
J. Donald Lamont
Alex Marion
John R. Matras
R. B. Miller
Burt Nemroff
Newell S. Porter
Neil P. Smith
Donald J. Spellman
Peter B. Stevens
James E. Stoner
Peter Szabados
James E. Thomas
John T. Ullo
Raymond Weronick
G. O. Wilkinson
Mark S. Zar
James B. Zgliczynski
When the IEEE Standards Board approved this standard on 21 March 1996, it had the following membership:
Donald C. Loughry, Chair
Richard J. Holleman, Vice Chair
Andrew G. Salem, Secretary
*Member Emeritus
Also included are the following nonvoting IEEE Standards Board liaisons:
Satish K. Aggarwal
Alan H. Cookson
Chester C. Taylor
Kristin M. Dittmann
IEEE Standards Project Editor
This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components.
(This introduction is not part of IEEE Std 382-1996, IEEE Standard for Qualification of Actuators for Power-Operated Valve Assemblies With Safety-Related Functions for Nuclear Power Plants.)
Applicants for a construction permit or operating license for a nuclear generating station are required to provide assurance that systems, components, and structures are adequate for their service conditions to comply with the Code of Federal Regulations 10 CFR 50, Appendix B Quality Assurance Criteria, and Criterion III Design Control. Each applicant has the responsibility to ensure that this or any other standard, if used, is pertinent to the application and that the integrated performance of the station is acceptable. Implementation of this standard requires the applicant to produce documentary evidence to ensure that the valve actuator can perform its intended function.
Typical design basis event conditions for principal reactor types are presented as one source of parameters for generic-type tests. If the actual conditions of a specific application differ, it will be the obligation of the user to specify these actual conditions.
The numerical values presented in this standard envelop current industry design with respect to radiation types and levels; seismic levels; temperature, pressure, and humidity levels; post-accident periods of operability; spray initiation, and duration. Composition of environment may change in the future, so the user is cautioned to verify the suitability of these values for each application.
This revision was prepared by Working Group SC2.3 of the Nuclear Power Engineering Committee of the IEEE Power Engineering Society. The membership of the working group at the time this revision was completed included the following:
Ivan Wilkinson, Chair
Robert Arnold
Nissen M. Burstein
Sal P. Carfagno
Walter J. Denkowski*
W. F. Murray
Clyde T. Nieh
*Deceased 1995
The following persons were on the balloting committee:
Wes W. Bowers
Dan F. Brosnan
Nissen M. Burstein
Aris S. Candris
S. P. Carfagno
Robert C. Carruth
Robert L. Copyak
Gary L. Doman
Edward F. Dowling
Arthur R. DuCharme
Rich E. Dulski
Jay Forster
J. R. Fragola
John M. Gallagher
Wil C. Gangloff
Louis W. Gaussa
Luis C. Gonzalez
Lawrence P. Gradin
J. K. Greene
Britton P. Grim
Robert E. Hall
Joe Hazeltine
Gregory K. Henry
Sonny Kasturi
James T. Keiper
J. Donald Lamont
Alex Marion
John R. Matras
R. B. Miller
Burt Nemroff
Newell S. Porter
Neil P. Smith
Donald J. Spellman
Peter B. Stevens
James E. Stoner
Peter Szabados
James E. Thomas
John T. Ullo
Raymond Weronick
G. O. Wilkinson
Mark S. Zar
James B. Zgliczynski
When the IEEE Standards Board approved this standard on 21 March 1996, it had the following membership:
Donald C. Loughry, Chair
Richard J. Holleman, Vice Chair
Andrew G. Salem, Secretary
*Member Emeritus
Also included are the following nonvoting IEEE Standards Board liaisons:
Satish K. Aggarwal
Alan H. Cookson
Chester C. Taylor
Kristin M. Dittmann
IEEE Standards Project Editor
This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components.
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| contributor author | IEEE - The Institute of Electrical and Electronics Engineers, Inc. | |
| date accessioned | 2017-09-04T16:06:39Z | |
| date available | 2017-09-04T16:06:39Z | |
| date copyright | 39057 | |
| date issued | 2006 | |
| identifier other | RZCWYBAAAAAAAAAA.pdf | |
| identifier uri | https://yse.yabesh.ir/std/handle/yse/69865 | |
| description abstract | Foreword (This introduction is not part of IEEE Std 382-1996, IEEE Standard for Qualification of Actuators for Power-Operated Valve Assemblies With Safety-Related Functions for Nuclear Power Plants.) Applicants for a construction permit or operating license for a nuclear generating station are required to provide assurance that systems, components, and structures are adequate for their service conditions to comply with the Code of Federal Regulations 10 CFR 50, Appendix B Quality Assurance Criteria, and Criterion III Design Control. Each applicant has the responsibility to ensure that this or any other standard, if used, is pertinent to the application and that the integrated performance of the station is acceptable. Implementation of this standard requires the applicant to produce documentary evidence to ensure that the valve actuator can perform its intended function. Typical design basis event conditions for principal reactor types are presented as one source of parameters for generic-type tests. If the actual conditions of a specific application differ, it will be the obligation of the user to specify these actual conditions. The numerical values presented in this standard envelop current industry design with respect to radiation types and levels; seismic levels; temperature, pressure, and humidity levels; post-accident periods of operability; spray initiation, and duration. Composition of environment may change in the future, so the user is cautioned to verify the suitability of these values for each application. This revision was prepared by Working Group SC2.3 of the Nuclear Power Engineering Committee of the IEEE Power Engineering Society. The membership of the working group at the time this revision was completed included the following: Ivan Wilkinson, Chair Robert Arnold Nissen M. Burstein Sal P. Carfagno Walter J. Denkowski* W. F. Murray Clyde T. Nieh *Deceased 1995 The following persons were on the balloting committee: Wes W. Bowers Dan F. Brosnan Nissen M. Burstein Aris S. Candris S. P. Carfagno Robert C. Carruth Robert L. Copyak Gary L. Doman Edward F. Dowling Arthur R. DuCharme Rich E. Dulski Jay Forster J. R. Fragola John M. Gallagher Wil C. Gangloff Louis W. Gaussa Luis C. Gonzalez Lawrence P. Gradin J. K. Greene Britton P. Grim Robert E. Hall Joe Hazeltine Gregory K. Henry Sonny Kasturi James T. Keiper J. Donald Lamont Alex Marion John R. Matras R. B. Miller Burt Nemroff Newell S. Porter Neil P. Smith Donald J. Spellman Peter B. Stevens James E. Stoner Peter Szabados James E. Thomas John T. Ullo Raymond Weronick G. O. Wilkinson Mark S. Zar James B. Zgliczynski When the IEEE Standards Board approved this standard on 21 March 1996, it had the following membership: Donald C. Loughry, Chair Richard J. Holleman, Vice Chair Andrew G. Salem, Secretary *Member Emeritus Also included are the following nonvoting IEEE Standards Board liaisons: Satish K. Aggarwal Alan H. Cookson Chester C. Taylor Kristin M. Dittmann IEEE Standards Project Editor This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components. | |
| language | English | |
| title | IEEE 382 | num |
| title | IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations | en |
| type | standard | |
| page | 42 | |
| status | Active | |
| tree | IEEE - The Institute of Electrical and Electronics Engineers, Inc.:;2006 | |
| contenttype | fulltext |