Improper seating of reactor vessel surveillance capsules.

Pressurized thermal shock in nuclear power plants : good practices for assessment : deterministic evaluation for the integrity of reactor pressure vessel.
Published: (2010)

Analysis of reactor vessel radiation effects surveillance programs /
by: Steele, L. E. (Lendell E.), 1928-
Published: (1970)

Radiation embrittlement and surveillance of nuclear reactor pressure vessels : an international study : a conference /
Published: (1983)

Assessment and management of ageing of major nuclear power plant components important to safety : PWR pressure vessels, 2007 update.
Published: (2007)

Guide to the periodic inspection of nuclear reactor steel pressure vessels. : Report of a meeting on periodic inspection of nuclear reactor steel pressure vessels held in Stockholm, Sweden, 21-25 Oct. 1968.
Published: (1969)

Status of USA nuclear reactor pressure vessel surveillance for radiation effects /
Published: (1983)

Dynamic analysis of pressure vessel and piping components : presented at the Energy Technology Conference, Houston, Texas, September 18-23, 1977 /
Published: (1977)

Three Mile Island reactor pressure vessel investigation project : achievements and significant results : proceedings of an open forum sponsored by the OECD Nuclear Energy Agency and the United States Nuclear Regulatory Commission, Boston (USA), 20-22 October 1993.
Published: (1994)

Inadvertent reactor vessel overfill.
Published: (1988)

Implementation of regulatory guide 1.150, Ultrasonic testing of reactor vessel welds during preservice and inservice examinations, revision 1.
Published: (1983)

Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension /
Published: (1993)

Recent experience with degradation of reactor pressure vessel head.
Published: (2002)

Dynamic range uncertainties in the reactor vessel level instrumentation.
Published: (1997)

Thermal shock to reactor pressure vessels.
Published: (1981)

Inadvertent containment spray and reactor vessel draindown at Millstone Unit 1.
Published: (1994)

Themally induced pressurization of nuclear power facility piping.
Published: (1996)

Potential failures of auxiliary steam piping and the possible effects on the operability of vital equipment.
Published: (1990)

Recurring inspection of nuclear reactor steel pressure vessels. : Report of a Panel, held in Pilsen, Czechoslovak Socialist Republic, 3-7 Oct. 1966 /
Published: (1968)

Possible indicators of ongoing reactor pressure vessel head degradation.
Published: (2002)

Inadvertent loss or improper actuation of safety-related equipment.
Published: (1985)

Design of the reactor pressure vessel support system.
Published: (1978)

Quasi-laminar indicators in reactor pressure vessel forgings.
Published: (2013)

Defects in load-bearing welds on lifting devices for vessel head and internals.
Published: (1983)

Potential problems with Crosby safety relief valves used on diesel generator air start receiver tanks.
Published: (1990)

Integrated chemical effects test project /
Published: (2007)

Potential error in high steamline flow setpoint.
Published: (1990)

Partial bypass of shutdown cooling flow from the reactor vessel.
Published: (1996)

Trends in reactor pressure vessel and circuit development /
Published: (1980)

Improper equipment settings due to the use of nontemperature-compensated test equipment.
Published: (1996)

Symposium on Seismic Analysis of Pressure Vessel and Piping Components ; presentations from ASME First National Congress on Pressure Vessels and Piping, San Francisco, California, May 1971 /
Published: (1971)

Design of reactor containment systems for nuclear power plants : Safety guide /
Published: (2004)

Methodology for estimating fabrication flaw density and distribution, reactor pressure vessel welds /
by: Schuster, G. J.
Published: (2009)

Long term low power operation in pressurized water reactors.
Published: (1984)

Pressure vessel codes : their application to nuclear reactor systems /
Published: (1966)

Reactor vessel closure head studs remained detensioned during plant startup.
Published: (2012)

Resolution of generic issue 79, "Unanalyzed reactor vessel (PWR) thermal stress during natural convection cooldown".
Published: (1992)