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REGDOC-3.6, Glossary of CNSC Terminology - Acronyms

Appendix A: Acronyms and Abbreviations

ACR (RAC)
annual compliance report
AECL (EACL)
Atomic Energy of Canada Limited
ALARA (ALARA)
as low as reasonably achievable
ALI (LAI)
annual limit on intake
AM (GV)
aging management
AMP (SAP ou PGV)
administrative monetary penalty Note: AMP has also been used for aging management program / aging management plan but is now reserved for administrative monetary penalty
ANO (ONA)
authorized nuclear operator; see reactor operator
ANS (ANS)
American Nuclear Society
ANSI (ANSI)
American Nuclear Standards Institute
AOO (IFP)
anticipated operational occurrence
ASDV (VDVA)
atmospheric steam discharge valve
ASME (ASME)
a professional association, founded as the American Society of Mechanical Engineers
BATEA (MTEAR)
best available technology and techniques economically achievable
BDBA (AHD)
beyond-design-basis accident
BDBE (SHD)
beyond-design-basis earthquake
BDBT (MHD)
beyond-design-basis threat
BDCP (PCSE)
by-difference correction principle
BE (IA)
below expectations; see safety performance rating methodology
BEAU (BEAU)
best estimate and uncertainty (BEAU) method
Bq (Bq)
becquerel
BWR (REB)
boiling water reactor
CANDU (CANDU)
CANada Deuterium Uranium
CASA (ESAC)
criticality accident sequence assessment
CCF (DCC)
common-cause failure
CCME (CCME)
Canadian Council of Ministers of the Environment
CEAA 2012 (LCEE 2012)
Canadian Environmental Assessment Act, 2012
CEDO (OAEA)
certified exposure device operator
CEPA (LCPE)
Canadian Environmental Protection Act, 1999
CHF
critical heat flux
Ci (Ci)
curie; see becquerel
CM
configuration management or corrective maintenance
CMD (CMD)
Commission member document
CNS (CSN)
Convention on Nuclear Safety
CNSC (CCSN)
Canadian Nuclear Safety Commission
COPC (CPP)
contaminant of potential concern
CRDM
control rod drive mechanism
CRNC (VNCJ)
criminal records name check
CRO (OSC)
control room operator; see reactor operator
CSA (CSA)
Canadian Standards Association; now called CSA Group
CSC (CSC)
criticality safety control; see nuclear criticality safety control
CSDV (SEVC)
condenser steam discharge valve
CSI (CSI)
criticality safety index
CVC (CVC)
compliance verification criteria
D (D)
absorbed dose
DA (AD)
derived activity
DAC (LDCA)
derived air concentration
DBA (AD)
design-basis accident
DBE (SR)
design-basis earthquake
DBT
design-basis threat
DCF (FCD)
dose conversion factor
DEC (CAD)
design extension conditions
DGR (DGP)
deep geological repository
DIL (NED)
derived investigational level
DO
designated officer
DRL (LRD)
derived release limit
E (E)
effective dose
EA (EE)
environmental assessment
ECCS (SRUC)
emergency core cooling system
EFPD (JEPP)
equivalent full-power day
EFPH (HEPP)
equivalent full power hour.
EHRS (SEUC)
emergency heat removal system
EIR (RIE)
event initial report
EIS (EIE)
environmental impact statement
Ekg (kgE)
effective kilogram
ELAP (PPACA)
extended loss of AC power
EME (EAU)
emergency mitigating equipment
EMS (SGE)
environmental management system
EO
enabling objective
EPR (EPE)
environmental protection review
EPREV (EPREV)
Emergency Preparedness Review (an IAEA service)
EPS (AEU)
emergency power supply
EQ (QE)
environmental qualification
ERA (ERE)
environmental risk assessment
ERO (OIU)
emergency response organization
ESC (CSU)
emergency support centre
ESWS (SSUAE)
emergency secondary water supply system
eV (eV)
electron volt
FAI (MPF)
Fukushima action item
FERP (PFIU)
Federal Emergency Response Plan
FFD
fitness for duty
FINAS (FINAS)
fuel incident notification and analysis system
FLORC (PRCR)
fast loss of reactivity control
FNEP (PFUN)
Federal Nuclear Emergency Plan
FS (ES)
fully satisfactory; see safety performance rating methodology
FV (FV)
Fussell‑Vesely; see importance measures
FY (exerice)
fiscal year
GAI (DG)
generic action item
GAR (REG)
global assessment report; see global assessment
GBq (GBq)
gigabecquerel, that is, 109 becquerels; see becquerel
GSS (EAG)
guaranteed shutdown state
GWD (GWj)
gigawatt‑days
Gy (Gy)
gray
HAC
hypothetical accident conditions
HCLPF
high confidence of low probability of failure
HDR (HDD)
high dose rate (HDR) brachytherapy remote afterloader
HEU (UHE)
high-enriched uranium
HEUNL (NULHE)
highly enriched uranyl nitrate liquid
HF (FH)
human factors
HFE (IFH)
human factors engineering; see human factors in design
HOP (RHO)
human and organizational performance
HT (HT)
equivalent dose
HTO (HTO)
hydrogenated tritium oxide; also called tritiated water
HTS
primary heat transport system
HVL (CDA)
half‑value layer
HVT (CDA)
half‑value thickness; see half‑value layer
H/X (H/X)
hydrogen-to-fissile atomic ratio
IAA (LEI)
Impact Assessment Act
IAEA (AIEA)
International Atomic Energy Agency
I&C (IC)
instrumentation and control
ICAO (OACI)
International Civil Aviation Organization
ICRP (CIPR)
International Commission on Radiological Protection
ICRU (CIUMR)
International Commission on Radiation Units and Measurements
IEMP (PISE)
Independent Environmental Monitoring Program
IFB
irradiated fuel bay; see wet storage bay
IIP (PIMO)
integrated implementation plan
IL (NE)
investigational level
IMRT (RCMI)
intensity modulated radiation therapy
INES (INES)
International Nuclear and Radiological Event Scale
INFCIRC (INFCIRC)
Information Circular (IAEA publication)
INPO (INPO)
Institute of Nuclear Power Operations
IPPAS (SCIPP)
International Physical Protection Advisory Service
IRD (DRI)
immediate rapid deployment
IRRS (SEIR)
Integrated Regulatory Review Service
IRS (IRS)
International Reporting System for Operating Experience
ISAR (ISAR)
industrial safety accident rate
ISI
in‑service inspection
ISO (ISO)
International Organization for Standardization
ISR (EIS)
integrated safety review; see periodic safety review
KI (KI)
potassium iodide
LBB (FAR)
leak before break
LBLOCA (APRPGB)
large-break loss-of-coolant accident; see loss-of-coolant accident
LCH (MCP)
licence conditions handbook
LCMP (PGV)
lifecycle management plan; see aging management program / aging management plan
LDRM (MRFD)
low dispersible radioactive material
LET (TLE)
linear energy transfer
LEU (UFE)
low-enriched uranium
LLOCA (APMRP)
large loss-of-coolant accident; see loss-of-coolant accident
LLRD (PRLP)
long-lived radioactive dust
LLW (DFA)
low-level waste
LOCA (APRP)
loss-of-coolant accident
LOE (ELE)
limit of operating envelope
LOF
location outside facilities
LPO
last person out
LPSWOS (CESBP)
low‑pressure service water open system
LRF (FGER)
large release frequency
LTO
long‑term operation
LWR (REO)
light‑water reactor
MAPS
minimum allowable performance standards
MBA (ZBM)
material balance area
MB Code (code MB)
measurement basis code
MBq (MBq)
megabecquerel, that is, 106 becquerels; see becquerel
MCR (SCP)
main control room
MDC (CDM)
material description code
MeV (MeV)
megaelectron volt
MMC (CMM)
minimum measurable concentration
MMR (MRM)
micro modular reactor; see reactor facility
MRO (ME)
medical review officer
MSDS (FS)
material safety data sheet
MSIV (VIPV)
main steam isolation valve
MTL (NME)
minimum testing level
MTU (MTU)
metric tonne of uranium
MU (UM)
monitor unit
MUF
material unaccounted for; see inventory difference
NCB (OCN)
National Non‑Destructive Testing (NDT) Certification Body
NCS (SCN)
nuclear criticality safety
NCSE (ESCN)
nuclear criticality safety evaluation
NDR (FDN)
National Dose Registry
NDT (END)
non‑destructive testing; see also National Non‑Destructive Testing (NDT) Certification Body
NEM (GUN)
nuclear emergency management
NEO (OUN)
Nuclear Emergency Organization
NEW (TSN)
nuclear energy worker
NOA
NOA – NO ADVERSE INFO or Notice of Assessment (NOA) – INSUFFICIENT INFO
NPP
nuclear power plant
NPT (TNP)
Treaty on the Non-Proliferation of Nuclear Weapons (also referred to as the Non-Proliferation Treaty or the Nuclear Non-Proliferation Treaty)
NRC
National Research Council or U.S. Nuclear Regulatory Commission
NSCA (LSRN)
Nuclear Safety and Control Act
NSG (GFN)
Nuclear Suppliers Group
NSO (ASN)
nuclear security officer
OBT (TLCO)
organically bound tritium
OJT
on-the-job training
OLC
operational limits and conditions
OP&P (LCE)
operating policies and principles
OPEX (OPEX)
operating experience
PAR
passive autocatalytic recombiner; also called passive autocatalytic hydrogen recombiner
PAS (EAP)
personal air sampler
PBD (DEP)
pressure boundary degradation
PDR (DDP)
pulsed dose rate
PEOC (CPOU)
Provincial Emergency Operations Centre
PET (TEP)
positron emission tomography
PHTS (CCP)
primary heat transport system
PI
performance indicator
PIE (EIH)
postulated initiating event
PIF (FIP)
potential intake fraction
PIV (VSP)
physical inventory verification
PPE (EPI)
personal protective equipment
PPS (SPP or AEP)
physical protection system or preferred power supply
PRA (EPS)
probabilistic risk analysis or probability risk assessment; see probabilistic safety assessment
PROL (PERP)
power reactor operating licence
PRV (VDV)
primary relief valve
PSA (EPS)
probabilistic safety assessment
PSAR (RPAS)
preliminary safety analysis report
PSR (BPS)
periodic safety review
PWR (REP)
pressurized water reactor
QM (GQ)
quality management
R (R)
response
RAW (RAR)
risk achievement worth; see importance measures
RCA
root-cause analysis
RCM (MAF)
reliability-centred maintenance
RCS (SRR)
reactor coolant system
RDR (RRR)
risk decrease ratio; see importance measures
RIR (RAR)
risk increase ratio; see importance measures
RPPE (EPIR)
radiation personal protective equipment
RRW (RRR)
risk reduction worth; see importance measures
RSDS (FSR)
radiation safety data sheets
RSO (RRP)
radiation safety officer
SA (SA)
satisfactory; see safety performance rating methodology
SAD
source axis distance
SAM (GAG)
severe accident management (SAM) program
SAMG (LDGAG)
severe accident management guidelines; see severe accident management (SAM) program
SAR (RAS)
safety analysis report
SAT (ASF)
systematic approach to training
SBO (PETC)
station blackout
SCA (DSR)
safety and control area
SCDF (FDGC)
severe core damage frequency
SCO (SCO)
surface contaminated object
SCR (SCA)
secondary control room
SD (arrêt)
shutdown
SDCS (CRA)
shutdown cooling system
SGECS (SRUGV)
steam generator emergency cooling system
SHP
senior health physicist
SI (SI)
International System of Units (Système international d’unités)
SIS (SIS)
systems important to safety
SM (GQ)
shift manager; see plant shift supervisor
SMR (VMS ou PRM)
scheduled maintenance release or security monitoring room or small modular reactor (see reactor facility)
SNF
spent nuclear fuel; see used nuclear fuel
SOE (PES)
safe operating envelope
SOR (BA)
shutoff rod
SPI
safety performance indicator
SRS (SRS)
safety-related systems
SS
shift supervisor; see plant shift supervisor
SSC (SSC)
structures, systems and components
SSD
source skin distance
SSS
safe shutdown state
SStrA (ERMCE)
site selection threat and risk assessment
Sv (Sv)
sievert
TBI (ICT)
total body irradiation
TBq (TBq)
terabecquerel, that is, 1012 becquerels; see becquerel
TI (IT)
transport index
TIE (IET)
toxicity identification and evaluation
TLA
time-limited assumptions
TLD (DTL)
thermoluminescent dosimeter
TLO
terminal learning objective
TNA (ABF)
training needs analysis
TP
trip parameter
TRA (EMR)
threat and risk assessment
TVL (CAD)
tenth‑value layer
U (U)
uranium or use factor
UA (IN)
unacceptable; see safety performance rating methodology
USL (LSSC)
upper subcritical limit
U.S. NRC (U.S. NRC)
U.S. Nuclear Regulatory Commission
VC (CV)
valued component
VEC (CVE)
See valued component
VSLORC
very slow loss of reactivity control
WANO (WANO)
World Association of Nuclear Operators
WHMIS (SIMDUT)
Workplace Hazardous Materials Information System
WL (WL)
working level
WLM (WLM)
working level month
WP
work package
WPAS (WPAS)
workplace air sampler
wR (wR)
radiation weighting factor
wT (wT)
tissue weighting factor

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