Potential loca at high- and low-pressure interfaces from fire damage.

Potential for loss of shutdown cooling while at low reactor coolant levels.
Published: (1990)

Depressurization of reactor coolant systems in pressurized-water reactors.
Published: (1987)

Potential for degradation of the emergency core cooling system and the containment spray system after a loss-of-coolant accident because of construction and protective coating deficiencies and foreign material in containment.
Published: (1998)

Fire protection findings on loss of seal coolant to Westinghouse reactor coolant pumps.
Published: (2005)

Loss of decay heat removal due to loss of fluid levels in reactor coolant system.
Published: (1986)

Loss of emergency boration capability due to nitrogen gas intrusion.
Published: (1987)

Diversion of the residual heat removal pump seal cooling water flow during recirculation operation following a loss-of-coolant accident.
Published: (1989)

Undetected loss of reactor coolant.
Published: (1987)

Possible sudden loss of RCS inventory during low coolant level operation.
Published: (1988)

Clarification of TMI action plan item II.k.3.31.
Published: (1983)

Potentially inadequate performance of ECCS in PWRs during recirculation operation following a LOCA.
Published: (1988)

Potential for loss of minimum flow paths leading to ECCS pump damage during a LOCA.
Published: (1985)

Recent operating experience on loss of reactor coolant inventory while In a shutdown condition.
Published: (1990)

Potential for common-mode failure of high pressure safety injection pumps or release of reactor coolant outside containment during a loss-of-coolant accident.
Published: (1990)

Loss of decay heat removal--10 CFR 50.54(f).
Published: (1988)

Inter-system discharge of reactor coolant.
Published: (1990)

Loss of residual heat removal (RHR) while the reactor coolant system (RCS) is partially filled.
Published: (1987)

Numerical analysis of mixing factors in the RPV of VVER-440 reactor using the TRACE code /
by: Heralecky, P. (Petr)
Published: (2010)

Final report - evaluation of chemical effects phenomena in post-LOCA coolant /
Published: (2009)

Unanalyzed post-LOCA release paths.
Published: (1986)

Unisolatable reactor system coolant leak following repeated applications of leak sealant.
Published: (1993)

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

RELAP5 and TRACE calculations of LOCA in PWR /
by: Prosek, Andrej
Published: (2017)

Assessment of current test methods for post-LOCA cladding behavior /
by: Billone, Michael C.
Published: (2012)

Degraded ability to isolate the reactor coolant system from low-pressure coolant systems in BWRS.
Published: (1986)

Sensitivity analyses of a hypothetical 6 inch break, LOCA in Ascó NPP using RELAP/MOD3.2 /
Published: (2010)

Safety system response to loss of coolant and loss of offsite power.
Published: (1993)

Knowledge base report on emergency core cooling sump performance in operating light water reactors /
by: Natesan, K. (Krishnamurti), 1942-
Published: (2014)

Potential for gas binding of high-pressure safety injection pumps during a loss-of-coolant accident.
Published: (1988)

Intersystem LOCA outside containment.
Published: (1992)

Fuel behavior under abnormal conditions /
by: Meyer, R. O. (Ralph O.)
Published: (2013)

Potential failure of BWR backup manual scram capability.
Published: (1980)

Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2 /
by: Batet, L., et al.
Published: (2001)

TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6 /
by: Coddington, P., et al.
Published: (1992)

A computer code for fire protection and risk analysis of nuclear plants /
by: Singhal, A. K., et al.
Published: (1988)

Evaluation of fire models for nuclear power plant applications, cable tray fires : international panel report /
Published: (2002)