ANS 58.14
Safety and Pressure Integrity Classification Criteria for Light Water Reactors
Organization:
ANS - American Nuclear Society
Year: 2011
Abstract: This standard specifies criteria for the safety classification of items (SSCs and parts, including consumables) in a LWR nuclear power plant as safety-related (Q), non-safety-related with augmented requirements (A), or non-safety-related (N). In addition, pressure integrity classification criteria are provided for the assignment of Classes 1, 2, 3, 4, or 5 to pressure-retaining3) items.
Purpose
This standard has two purposes. The first is to provide criteria for the safety classification of items in LWR nuclear power plants. The second is to provide criteria for the assignment of pressure integrity classes to pressure-retaining items.
The application of the criteria specified in this document is intended to ensure that the safety and pressure integrity classifications of an item are based on its functions.
The classification criteria specified in this standard
(1) establish an objective, technically sound rationale for the determination of safety and pressure integrity classifications;
(2) include provisions for ensuring that all items required by the licensing design basis are appropriately classified;
(3) allow maximum compatibility with plantspecific designs, policies, and procedures;
(4) achieve consistency (i.e., minimize classification differences among similar items in the plant) among utilities, vendors, designs, and regulators, and with current industry and regulatory practices.
3) The scope of pressure-retaining items with respect to this standard is discussed in Sec. 5.
Purpose
This standard has two purposes. The first is to provide criteria for the safety classification of items in LWR nuclear power plants. The second is to provide criteria for the assignment of pressure integrity classes to pressure-retaining items.
The application of the criteria specified in this document is intended to ensure that the safety and pressure integrity classifications of an item are based on its functions.
The classification criteria specified in this standard
(1) establish an objective, technically sound rationale for the determination of safety and pressure integrity classifications;
(2) include provisions for ensuring that all items required by the licensing design basis are appropriately classified;
(3) allow maximum compatibility with plantspecific designs, policies, and procedures;
(4) achieve consistency (i.e., minimize classification differences among similar items in the plant) among utilities, vendors, designs, and regulators, and with current industry and regulatory practices.
3) The scope of pressure-retaining items with respect to this standard is discussed in Sec. 5.
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contributor author | ANS - American Nuclear Society | |
date accessioned | 2017-09-04T15:03:38Z | |
date available | 2017-09-04T15:03:38Z | |
date copyright | 01/01/2011 | |
date issued | 2011 | |
identifier other | KWOCOEAAAAAAAAAA.pdf | |
identifier uri | https://yse.yabesh.ir/std/handle/yse/855 | |
description abstract | This standard specifies criteria for the safety classification of items (SSCs and parts, including consumables) in a LWR nuclear power plant as safety-related (Q), non-safety-related with augmented requirements (A), or non-safety-related (N). In addition, pressure integrity classification criteria are provided for the assignment of Classes 1, 2, 3, 4, or 5 to pressure-retaining3) items. Purpose This standard has two purposes. The first is to provide criteria for the safety classification of items in LWR nuclear power plants. The second is to provide criteria for the assignment of pressure integrity classes to pressure-retaining items. The application of the criteria specified in this document is intended to ensure that the safety and pressure integrity classifications of an item are based on its functions. The classification criteria specified in this standard (1) establish an objective, technically sound rationale for the determination of safety and pressure integrity classifications; (2) include provisions for ensuring that all items required by the licensing design basis are appropriately classified; (3) allow maximum compatibility with plantspecific designs, policies, and procedures; (4) achieve consistency (i.e., minimize classification differences among similar items in the plant) among utilities, vendors, designs, and regulators, and with current industry and regulatory practices. 3) The scope of pressure-retaining items with respect to this standard is discussed in Sec. 5. | |
language | English | |
title | ANS 58.14 | num |
title | Safety and Pressure Integrity Classification Criteria for Light Water Reactors | en |
type | standard | |
page | 77 | |
status | Active | |
tree | ANS - American Nuclear Society:;2011 | |
contenttype | fulltext |