ALARP
|
As Low As Reasonably Practicable
|
APET
|
Accident progression event tree
|
ASN
|
Nuclear Safety Authority
|
BDBA
|
Beyond Design Basis Accident
|
BDBEE
|
Beyond-Design-Basis External Event
|
BWR
|
Boiling Water Reactor
|
CET
|
Containment event tree
|
CRT
|
Common risk target
|
CSIP
|
Complex (Integrated) Program of Ukrainian NPPs Safety Improvement
|
CST
|
Condensate storage tank
|
DCH
|
Direct containment heating
|
DiD
|
Defence in depth
|
ECCS
|
Emergency core cooling system
|
EDMG
|
Extensive damage mitigating guidelines
|
ELAP
|
Extended loss of alternating current (ac) power
|
EOP
|
Emergency operating procedure
|
EPG
|
Emergency procedure guidelines
|
FCVS
|
Filtered containment vent system
|
FLEX
|
Diverse and flexible coping strategies
|
FSGs
|
FLEX Support Guidelines
|
HPCI
|
High-pressure coolant injection
|
HRA
|
Human reliability assessment
|
IC
|
Isolation Condenser
|
IE
|
Initiating event
|
FLEX
|
Diverse and Flexible Coping Strategies
|
FSGs
|
FLEX Support Guidelines
|
IVR
|
In-vessel retention
|
LERF
|
Large early release frequency
|
LOCA
|
Loss-of-coolant accident
|
LUHS
|
Loss of Ultimate Heat Sink
|
L2 PSA
|
Level 2 probabilistic safety analysis / assessment
|
NPP
|
Nuclear power plant
|
PARs
|
Passive autocatalytic recombiners
|
PDS
|
Plant damage state
|
PFS
|
Performance Shaping Factor
|
PORV
|
Power Operated Relief Valve
|
PRISE
|
Primary to secondary leak
|
PRZ
|
Pressurizer
|
PSR
|
Periodic safety review / re-assessment
|
PWR
|
Pressurized Water Reactor
|
R&D
|
Research and Development
|
RCIC
|
Reactor core isolation cooling
|
RCS
|
Reactor coolant system
|
RPV
|
reactor pressure vessel
|
SAM
|
Severe accident management
|
SAMG
|
Severe accident management guideline
|
SBO
|
Station Black Out
|
SGTR
|
Steam Generator Tube Rupture
|
SFD
|
Spent fuel damage
|
SFP
|
Spent fuel pool
|
SG
|
Steam generator
|
SRV
|
Safety and Relief Valves
|
TSO
|
Technical Safety Organization
|
WOG
|
Westinghouse Owner Group
|
