Published 2018 | Version v1
Miscellaneous

PWROG SAMG validation: lessons learned

  • 1. Pressurized Water Reactors Owners Group (PWROG), Pittsburgh, Pennsylvania (United States)

Description

In February 2016 the Pressurized Water Reactor Owners Group (PWROG) issued a new set of Severe Accident Management Guidelines (SAMGs) that were applicable to the three United States (US) Pressurized Water Reactor (PWR) Nuclear Steam Supply System (NSSS) designs and included post-Fukushima lessons learned as well as insights from the updated Electric Power Research Institute (EPRI) Technical Basis Report (TBR). As part of that publication of the 2016 PWROG SAMGs, the PWROG performed validations at each of the three US PWR NSSS designs. Following the publication, the US PWRs made a commitment to the US Nuclear Regulatory Commission (NRC) to implement the PWROG SAMG (ML16032A029). This implementation includes a plant-specific validation of the plant-specific SAMG based on the new US PWROG SAMG. Specifically, this paper will discuss the lessons learned from the plant-specific PWROG SAMG validations that have been performed at the time of publication. In addition, this paper will also discuss the PWROG SAMG maintenance program that has been established to incorporate the lessons learned from the plant-specific SAMG validation into the generic US PWROG SAMG. (author)

Availability note (English)

Available as a slide presentaton only.
Part of:
7th International workshop on CANDU safety association for sustainability (CANSAS-2018). International severe accident management conference (ISAMC 2018)

Additional details

Publishing Information

Publisher
Canadian Nuclear Safety Commission
Imprint Place
Ottawa, Ontario (Canada)
Imprint Title
7th International workshop on CANDU safety association for sustainability (CANSAS-2018). International severe accident management conference (ISAMC 2018)
Imprint Pagination
225 Megabytes
Journal Page Range
[17 p.]

Conference

Title
7. International Workshop on CANDU Safety Association for Sustainability; ISAMC 2018: International Severe Accident Management Conference
Acronym
CANSAS-2018
Dates
15-18 Oct 2018
Place
Ottawa, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
51015982
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCIDENT MANAGEMENT; FUKUSHIMA ACCIDENT ARCHIVE; PWR TYPE REACTORS; REACTOR ACCIDENTS; RECOMMENDATIONS; US NRC
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; MANAGEMENT; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information