Emergency Response Guideline Development

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Description

Task 5 of the collaborative effort between ORNL, Brazil, and Westinghouse for the International Nuclear Energy Research Initiative entitled “Development of Advanced Instrumentation and Control for an Integrated Primary System Reactor” focuses on operator control and protection system interaction, with particular emphasis on developing emergency response guidelines (ERGs). As in the earlier tasks, we will use the IRIS plant as a specific example of an integrated primary system reactor (IPSR) design. The present state of the IRIS plant design – specifically, the lack of a detailed secondary system design – precludes establishing detailed emergency procedures at this time. However, we ... continued below

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296 KB

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Storrick, Gary D. September 30, 2007.

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Description

Task 5 of the collaborative effort between ORNL, Brazil, and Westinghouse for the International Nuclear Energy Research Initiative entitled “Development of Advanced Instrumentation and Control for an Integrated Primary System Reactor” focuses on operator control and protection system interaction, with particular emphasis on developing emergency response guidelines (ERGs). As in the earlier tasks, we will use the IRIS plant as a specific example of an integrated primary system reactor (IPSR) design. The present state of the IRIS plant design – specifically, the lack of a detailed secondary system design – precludes establishing detailed emergency procedures at this time. However, we can create a structure for their eventual development. This report summarizes our progress to date. Section 1.2 describes the scope of this effort. Section 2 compares IPSR ERG development to the recent AP1000 effort, and identifies three key plant differences that affect the ERGs and control room designs. The next three sections investigate these differences in more detail. Section 3 reviews the IRIS Safety-by-Design™ philosophy and its impact on the ERGs. Section 4 looks at differences between the IRIS and traditional loop PWR I&C Systems, and considers their implications for both control room design and ERG development. Section 5 examines the implications of having one operating staff control multiple reactor units. Section 6 provides sample IRIS emergency operating procedures (EOPs). Section 7 summarizes our conclusions.

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296 KB

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  • Report No.: STD-AR-07-2 (rev. 3)
  • Grant Number: FG07-05ID14690
  • DOI: 10.2172/933169 | External Link
  • Office of Scientific & Technical Information Report Number: 933169
  • Archival Resource Key: ark:/67531/metadc899122

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  • September 30, 2007

Added to The UNT Digital Library

  • Sept. 27, 2016, 1:39 a.m.

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Storrick, Gary D. Emergency Response Guideline Development, report, September 30, 2007; United States. (digital.library.unt.edu/ark:/67531/metadc899122/: accessed August 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.