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Languages : en
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PROCEEDINGS OF THE SEVENTH NRC/ASME SYMPOSIUM ON VALVE AND PUMP TESTING... NUREG/CP-0152, VOL. 4... U.S. NUCLEAR REGULATORY COMMISSION.
Proceedings Of The Fifth NRC/ASME Symposium On Valve And Pump Testing... Held At Hyatt Regency Hotel Washington, DC..., NUREG/CR-0152, Vol. 2... U.S. Nuclear Regulatory Commission
Author: U.S. Nuclear Regulatory Commission
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Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Proceedings of the 4th NRC/ASME Symposium on Valve and Pump Testing
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Category :
Languages : en
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Book Description
The 1996 Symposium on Valve and Pump Testing, jointly sponsored by the Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the U.S. Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers of this Proceedings have been cataloged separately.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The 1996 Symposium on Valve and Pump Testing, jointly sponsored by the Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the U.S. Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers of this Proceedings have been cataloged separately.
Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Session 1A--Session 2C
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Languages : en
Pages : 532
Book Description
The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. This document, Volume 1, covers sessions 1A through session 2C. The individual papers have been cataloged separately.
Publisher:
ISBN:
Category :
Languages : en
Pages : 532
Book Description
The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. This document, Volume 1, covers sessions 1A through session 2C. The individual papers have been cataloged separately.
Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Volume 2, Session 3A--Session 4B.
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Languages : en
Pages : 353
Book Description
The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers have been cataloged separately.
Publisher:
ISBN:
Category :
Languages : en
Pages : 353
Book Description
The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers have been cataloged separately.
Proceedings of the Eighth NRC/ASME Symposium on Valve and Pump Testing, Washington D.C., July 12-14, 2004
Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing
Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants
Author: U.s. Nuclear Regulation Comion
Publisher: CreateSpace
ISBN: 9781500374747
Category : Technology & Engineering
Languages : en
Pages : 36
Book Description
In this NUREG, the staff of the U.S. Nuclear Regulatory Commission (NRC) discusses the applicable regulations for the inservice testing of pumps and valves and the examination and testing of dynamic restraints (snubbers) at commercial nuclear power plants. The information in NUREG-1482, “Guidelines for Inservice Testing at Nuclear Power Plants,” Revision 0, issued April 1995, and Revision 1, issued January 2005, has described this topic in the past. This NUREG report replaces Revision 0 and Revision 1 to NUREG-1482 and is applicable, unless stated otherwise, to all editions and addenda to the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (OM Code), which Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b) incorporates by reference. In addition, the staff discusses other inservice test program topics such as the NRC process for the review of the OM Code, conditions on the use of the OM Code, and interpretations of the OM Code.
Publisher: CreateSpace
ISBN: 9781500374747
Category : Technology & Engineering
Languages : en
Pages : 36
Book Description
In this NUREG, the staff of the U.S. Nuclear Regulatory Commission (NRC) discusses the applicable regulations for the inservice testing of pumps and valves and the examination and testing of dynamic restraints (snubbers) at commercial nuclear power plants. The information in NUREG-1482, “Guidelines for Inservice Testing at Nuclear Power Plants,” Revision 0, issued April 1995, and Revision 1, issued January 2005, has described this topic in the past. This NUREG report replaces Revision 0 and Revision 1 to NUREG-1482 and is applicable, unless stated otherwise, to all editions and addenda to the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (OM Code), which Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b) incorporates by reference. In addition, the staff discusses other inservice test program topics such as the NRC process for the review of the OM Code, conditions on the use of the OM Code, and interpretations of the OM Code.
Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing: Session 1A - session 2C
Proceedings of the Eighth NRC/ASME Symposium on Valve and Pump Testing
Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Publisher:
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Category : Nuclear power plants
Languages : en
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Book Description
Publisher:
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Category : Nuclear power plants
Languages : en
Pages :
Book Description