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dc.contributor.authorRudland, David L.
dc.contributor.authorCumblidge, Stephen
dc.contributor.authorNg, Ching
dc.contributor.authorAnzalone, Reed
dc.date.accessioned2022-05-08T08:37:24Z
dc.date.available2022-05-08T08:37:24Z
dc.date.copyright12/6/2021 12:00:00 AM
dc.date.issued2021
dc.identifier.issn0094-9930
dc.identifier.otherpvt_144_03_031501.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4284141
dc.description.abstractIn Dec. 2017, a four-loop 1300 MW Electricite de France (EdF) plant in France, Belleville Unit 2, experienced a complete wear through and separation of one of their thermal sleeves at a rodded control rod drive mechanism (CRDM) location. During low power physics testing and rod drop testing, the plant had difficulty stepping the control rod into the core. The rod was freed by exercising the drive rod but was then stopped prior to full insertion during the rod drop test. The failure to insert the rod was caused by the worn thermal sleeve flange remnant. In response to this operational experience, Westinghouse notified the U.S. Nuclear Regulatory Commission (NRC) of this defect pursuant to the requirements of title 10 of the Code of Federal Regulations (10 CFR) Part 21 and published a nuclear safety advisory letter (NSAL) that provides details on the thermal sleeve flange issue and inspection recommendations. In their notification, Westinghouse determined that there was no immediate safety concern, but a substantial safety concern may be possible in the unlikely event that there is interference with the movement of more than one control rod. This paper summarizes the NRC staff's safety analysis of this issue. The staff conducted detailed probabilistic and risk analyses and followed up with a smart sample inspection of the industry's thermal sleeve inspection programs to verify the analysis assumptions. The staff found the risk of core damage to be low, their assumptions appropriate, and the industry was following the details of the NSAL appropriately.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titlePredicting the Impact of CRDM Thermal Sleeve Flange Wear in Westinghouse Pressurized Water Reactors
dc.typeJournal Paper
dc.journal.volume144
dc.journal.issue3
dc.journal.titleJournal of Pressure Vessel Technology
dc.identifier.doi10.1115/1.4052898
dc.journal.fristpage31501-1
dc.journal.lastpage31501-7
dc.page7
dc.treeJournal of Pressure Vessel Technology:;2021:;volume( 144 ):;issue: 003
dc.contenttypeFulltext


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