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Historical Background

Potential stress corrosion cracking (SCC) of reactor vessel (RV) closure studs was raised as a GSI in December

DESCRIPTION

Historical Background

BWRs are equipped with SRVs to control primary system pressurization.

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Historical Background

This issue was identified in a DL/NRR memorandum[1]which called for an assessment of the hig

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Historical Background

Combustible gases such as H₂, propane, and acetylene are used during normal operations of nuclear power plants in limited quantities and for

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Historical Background

Issue B-63, which was resolved and implemented as MPA B-45, required leak-testing of the check valves that isolate those low pressure systems that are c

DESCRIPTION

In the prioritization of Issue 22, "Inadvertent Boron Dilution," it was found that inadvertent boron dilution events during cold shutdown operation do not constitute a significant ri

DESCRIPTION

Historical Background

The issue of using the most recent NOAA procedures for determining probable maximum precipitation (PMP) was raised

Historical Background

In January 1984, AEOD issued a special study report (AEOD/S401)[1]describing the number of events t

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Historical Background

Issue 50 addressed several areas of concern with BWR water level instrumentation and its resolution involved voluntary implementation of water level mea

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Historical Background

Once-through steam generators (OTSGs) are a feature unique to B&W reactor designs.