Safety evaluation of Westinghouse topical reports dealing with elimination of postulated pipe breaks in PWR primary main loops.

LBLOCA analysis in a Westinghouse PWR 3-loop design using RELAP5/MOD3 /
by: Sánchez, J. I., et al.
Published: (2001)

Overpressurization of containment of a PWR plant after a main steam line break.
Published: (1979)

Degradation or loss of charging systems at PWR nuclear power plants using swing-pump designs.
Published: (1986)

Asymmetric blowdown loads on PWR primary systems : resolution of generic task action plan A-2 /
by: Hosford, S. B. (Steve B.)
Published: (1981)

Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators : held at Fuji Institute of Education and Training, Japan, May 28-June 2, 1978 /
Published: (1982)

Cracking in main steam lines.
Published: (1981)

EB 80-04 analysis of a PWR main steam sine break with continued feedwater addition.
Published: (1980)

Contaminants and stagnant conditions affecting stress corrosion cracking in stainless steel piping in pressurized water reactors.
Published: (2011)

Main steam isolation valve guide rail failure at Waterford Unit 3.
Published: (1988)

Spatial effects and uncertainty analysis for rod ejection accidents in a PWR /
by: Avvakumov, A., et al.
Published: (2007)

Inadequate inservice testing of main steam isolation valves.
Published: (1985)

Probability of pipe fracture in the primary coolant loop of a PWR plant /
Published: (1981)

PWR low temperature overpressure protection.
Published: (1982)

Safety concerns associated with pipe breaks in the BWR scram system.
Published: (1981)

Safety concerns associated with pipe breaks in the BWR scram system.
Published: (1981)

Safety concerns associated with pipe breaks in the BWR scram system.
Published: (1981)

Safety concerns associated with pipe breaks in the BWR scram system.
Published: (1985)

SCDAP/RELAP5 thermal-hydraulic evaluations of the potential for containment bypass during extended station blackout severe accident sequences in a Westinghouse four-loop PWR /
Published: (2010)

Concrete pressure pipe.
Published: (2008)

Undetected installation errors in main steam line pipe tunnel differential temperature-sensing elements at boiling water reactors.
Published: (1989)

Overexposures in PWR cavities.
Published: (1982)

Complete loss of main and auxiliary feedwater at a PWR designed by Babcock & Wilcox.
Published: (1985)

Simplified piping and pressure vessel design.
by: Cibulka, Alois, 1890-
Published: (1952)

New information regarding insulation material performance and debris blockage of PWR containment sumps.
Published: (1990)

Systems summary of a Westinghouse pressurized water reactor nuclear power plant /
by: Masche, George
Published: (1971)

Process piping : ASME Code for Pressure Piping, B31 /
Published: (2011)

Potential loss of effective volume for containment recirculation spray at PWR facilities.
Published: (1990)

Entry Into PWR cavity with retractable incore detector thimbles withdrawn.
Published: (1986)

Failure to detect freespan cracks in PWR steam generator tubes.
Published: (2003)

Control rod drive (CRD) guide tube support pin failures at Westinghouse PWRS.
Published: (1982)

Overexposure of diver in pressurized water reactor (PWR) refueling cavity.
Published: (1984)

Main steam isolation valve closure logic.
Published: (1985)

Unit startup with degraded high pressure safety injection system.
Published: (1986)

Undetected modification of flow characteristics in the high pressure safety Injection system.
Published: (1993)

RHR valve misalignment causes degradation of ECCS in PWRS.
Published: (1987)

GSI-191 PWR sump screen blockage chemical effects tests : thermodynamic simulations /
Published: (2006)