2. Developing common safety principles. 3. Safety principles Scope ( art 2.i): NPP, storage, handling, treatment facilities . ANSI/ANS (N). Dec 14, (i.e., Condition II events) will not progress to more serious events Water Reactor [PWR] Plants (replaces ANSI N), or. May 2, ANSI N Conformance. Page 2 of ANSI N ASME NQA-1 SNC QATR. COMMENTS repairing, refueling and.

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Manuscript received September 30, ; final manuscript received October 4, ; published online March 5, Nuclear safety analysis and licensing criteria are based upon the concept that plant situations that are expected to have a high frequency of occurrence must not pose a danger to the public, anai that plant situations that could pose a danger to the public must n18.2 limited to situations that have a very low expected frequency of occurrence.

This concept is implemented by grouping postulated plant situations or events into categories that are defined according to their expected frequencies of occurrence i. In plant licensing basis analyses, events in each category must be shown to yield consequences that remain within the limits that are specified for that category. To protect the integrity of this categorization scheme, events must not be allowed to develop into the more serious events that belong in other, higher-consequence categories.

In other words, nuclear plant designs must not allow andi, low-consequence events to degrade into high-frequency, high-consequence events. The development of this system of frequency-based categorization is discussed, followed by an evaluation of various methods that could, and could not be used to demonstrate, for licensing purposes, that benign events are prevented from becoming serious accidents.


PORVs that are not qualified to relieve water are assumed to stick open, if they relieve water. Margin to pressure safety limit.

AOOs must be accommodated by a reactor shutdown e. Some tools below are only available to our subscribers or users with an online account. Customize your page view by dragging and repositioning the boxes below. You do not have access to this content. For assistance or to subscribe, please contact us:.

Sign in anzi create your free personal ASME account. Sign into or create your free personal account. Received September 30, ; Revised October 04, Learn about subscription and purchase options. Check Out Now Continue Browsing. Your Session has timed out. Please sign back in to continue. RS see Note 8 of Matrix 8 in Sec. Figures Grahic Jump Location Fig.

Grahic Jump Location Fig.

ANSI-N | Nuclear Safety Criteria Water Reactor Plants | Document Center, Inc.

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