Peer Review of NRC Standardized Plant Analysis Risk Models Page: 3 of 10
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Knudsen, J. K., et. al
Report indicated that many of these comments can be addressed and/or corrected with currently planned
updates and minimal need for additional resources, if any. However, at this time, a lack of plant specific
documentation and data precludes addressing all the comments. The effort discussed below concentrates
on identifying the proper response to all the findings and suggestions from the peer review report.
Priority will be given to addressing findings and suggestions that: 1) are beneficial to the users; 2) can be
addressed without additional plant information; and 3) do not require new technology development. The
peer review of the PWR and BWR SPAR models will lay the ground work that will be applied to improve
all 77 SPAR models since the SPAR models are fairly standardized.
2. Background
A Peer Review was performed on a BWR SPAR model PRA during the week of August 171 -
20h 2009 (ref. 2) and a PWR SPAR model Probabilistic Risk Analysis (PRA) (ref. 3) during the week of
October 5h - 8h 2009 and at the Idaho National Laboratory (INL). The peer review was performed using
the NEI 05-04 (ref. 4) process and the American Society of Mechanical Engineers (ASME) Standard for
Probabilistic Risk Assessment for Nuclear Power Plant Applications and applicable addendums, ASME
RA-S-2002, ASME RA-Sa-2003, ASME RA-Sb-2005; in accordance with Regulatory Guide 1.200, Rev.
1 (ref. 1 and 5).
The peer review process is designed to assess the technical quality and adequacy of the SPAR
model. The review of the technical quality and adequacy of the SPAR model is important because of the
spectrum of potential risk-informed applications they are designed to perform. The SPAR model peer
review was a full-scope review of all technical elements for internal events of the PWR and BWR SPAR
model. The technical elements for at-power PRA for internal events are documented in ASME RA-Sb-
2005. These technical elements are:
" Initiating Events Analysis (IE);
" Accident Sequence Analysis (AS);
" Success Criteria (SC);
" Systems Analysis (SY);
" Human Reliability Analysis (HR);
" Data Analysis (DA); and
" Quantification (QU)
Internal flooding and large early release factors (LERF) are not developed in the PWR and BWR
SPAR models; therefore, these technical elements were deemed not applicable and not evaluated in the
review.
PRA configuration control requirement was also evaluated in the peer review process. The
ASME Standard does not have a specific technical element for this review; therefore, this element is
based on PRA maintenance and update identified in NEI 05-04. To facilitate review comments for this
technical element, it was given the designator of MU for PRA maintenance and update. This technical
element is identified and discussed in NEI 05-04.
For each of the technical elements, a set of high level requirements (HLRs) are developed. These
HLRs set minimum requirements for a PRA to be defined as technically acceptable. The HLRs are the
top level of information that defines in general terms the requirements needed to meet the technical
element. However, the actual evaluation or review of a PRA is against more detailed supporting
requirements. Supporting requirements are developed for each of the defined HLR and they contain the
details to assess the wide applications of PRA models. In other words, the PRA is evaluated for technicalPage 2 of 9
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Koonce, Anthony; Knudsen, James & Buell, Robert. Peer Review of NRC Standardized Plant Analysis Risk Models, article, March 1, 2011; Idaho Falls, Idaho. (https://digital.library.unt.edu/ark:/67531/metadc839539/m1/3/: accessed April 26, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.