DESCRIPTION

Historical Background

PORVs and block valves were originally designed as non-safety components in the reactor pressure control system for use onl

DESCRIPTION

Historical Background

Cracks were found in the normal make-up high pressure injection (MU/HPI) nozzles of several B&W plants following an inspection of the 8 B&W plants

DESCRIPTION

Historical Background

In an evaluation of INPO/NSAC Significant Operating Experience Report 81-17,

DESCRIPTION

Following the SGTR event at Ginna on January 25, 1982, increased staff effort was placed on developing means to mitigate and reduce steam generator tube

DESCRIPTION

Historical Background

Following the steam generator tube rupture (SGTR) event at Ginna in January 1982,[1]the staff

DESCRIPTION

Historical Background

Increasing attention has recently been focused on the integrity of RCP seals due to loss of cooling to the seals both in co

DESCRIPTION

Historical Background

Protection systems in nuclear power plants are required to meet the design criteria of IEEE-279, "Criteria for Protection Systems for Nuclear Power Genera

DESCRIPTION

Historical Background

BWRs are required to be operated within set thermal limits to maintain the integrity of the fuel cladding during postulated

DESCRIPTION

This issue was raised in November 1981 by the Materials Engineering Branch (MTEB), DE/NRR, and was based on the concern that NRC provides no control regu

DESCRIPTION

Historical Background

The SRVs of a BWR plant provide protection against overpressurization of the reactor primary system. During normal operatio