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ACRONYMS APPENDIX C.

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ACRONYMS APPENDIX C.
APPENDIX C. ACRONYMS
ABS
ABWR
AC
ac
ACI
ACLCO
ACM
ACRS
ACSR
ADAMS
ADG
ADS
AEA
AFEM
AFIP
AFT
AFU
AHS
AHU
AISC
AISI
AL
ALARA
ALT
ALWR
AMS
ANI
ANS
ANSI
AOC
AOE
AOF
AOO
AOP
AOSC
AOV
AP
APE
APLHGR
APRM
ARI
ARM
ARMS
ARP
ARS
ART
ARTNDT
auxiliary boiler system
Advanced Boiling Water Reactor
availability control
alternating current
American Concrete Institute
availability control limiting condition for operation
availability controls manual
Advisory Committee on Reactor Safeguards
availability control surveillance requirement
Agencywide Documents Access and Management System
ancillary diesel generator
automatic depressurization system
Atomic Energy Act
acoustic finite element model
automatic fixed in-core probe
as found tolerance
air filtration unit
auxiliary heat sink
air-handling unit
American Institute of Steel Construction
American Iron and Steel Institute
analytical limit
as low as reasonably achievable
as-left tolerance
Advanced Light Water Reactor
alarm management system
authorized nuclear inspector
American Nuclear Society
American National Standards Institute
present value of averted offsite property damage costs ($)
present value of averted occupational exposure costs ($)
allocation of functions
anticipated operational occurrence
abnormal operating procedure
present value of averted onsite costs ($)
air operated valve
annulus pressurization
present value of averted public exposure ($)
Average Planar Linear Heat Generation Rate
average power range monitor
alternate rod insertion
area radiation monitor
area radiation monitoring system
annunciator response procedure
amplified response spectra
adjusted reference temperature
adjusted reference temperature nil ductility temperature
C-1
ASA
ASCE
ASD
ASHRAE
ASME
AST
ASTM
ATIP
ATLM
ATWS
AV
AWS
B&PV
B&W
BDBA
BDLB
BISI
BL
BMP
BNL
BOC
BOL
BOP
BOPCWS
BPU
BPVC
BRR
BTP
BTU
BV-1
BVZ
BWR
BWROG
BWRVIP
C/C
C-I
C-II
CAM
CAP
CAR
CARS
CAS
CASS
CB
CBGAVS
CBVS
CC-II
CCF
CCFP
Acoustical Society of America
American Society of Civil Engineers
adjustable speed drive
American Society of Heating Refrigerating and Air-Conditioning Engineers
American Society of Mechanical Engineers
alternative source term
American Society of Testing and Materials
automated traversing incore probe
automated thermal limit monitor
anticipated transient without scram
allowable values
American Welding Society
Boiler and Pressure Vessel
Babcock & Wilcox
beyond design basis accident
bottom drainline break
bypassed or inoperable status indication
bulletin
basemat melt penetration
Brookhaven National Laboratory
beginning of cycle
beginning of life
balance of plant
balance-of-plant chilled water subsystem
bypass unit
Boiler and Pressure Vessel Code
baseline review record
branch technical position
British thermal unit
Beaver Valley Unit 1
Black & Veatch Zachry
boiling water reactor
Boiling-Water Reactor Owners Group
Boiling-Water Reactor Vessel and Internals Project
cooling and cleanup
Category I
Category II
continuous air monitor
corrective action program
corrective action request
condenser air removal system
central alarm station
cast austenitic stainless steel
control building
control building general area heating ventilation and air conditioning
subsystem
control building heating ventilation and air conditioning system
Capability Category 2
common-cause failure
conditional containment failure probability
C-2
CCI
CCID
CCIW
CD
CDA
CDF
CDI
CDM
CDS
CET
CEUS
CF
CFD
CFP
CFR
CFS
CFT
CH
CHF
CHPB
CHR
CHUG
CI
CIB2
CIM
CIRC
CIS
CISE
CIV
CJ
CLAVS
CLD
CMAA
CMF
CMS
CO
COE
COL
COLA
COLP
COLR
CONAVS
COTS
CPG
CPI
CPS
core-concrete interaction
core-concrete interactions-dry
core-concrete interactions-wet
confirmation density
control, display, and alarm
core damage frequency
conceptual design information
certified design material
clean drain (non-radioactive) system
containment event tree
Central and Eastern United States
chemistry factor
computational fluid dynamics
containment failure probability
Code of Federal Regulations
condensate and feedwater system
channel functional test
chugging
critical heat flux
Health Physics Branch, Division of Construction Inspection and Operational
Programs
containment heat removal
an oscillatory dynamic loading
confirmatory item
Component Integrity, Performance and Testing Branch 2, Division of
Engineering
communication interface module
circulating water system
containment inerting system
Ciencias de la Seguridas test facility
containment isolation valve
Chapman-Jouguet
clean area heating, ventilation, and air conditioning subsystem
containment load definition
Crane Manufacturer's Association of America
common mode failure
containment monitoring system
condensation oscillation
cost of enhancement ($)
combined license
combined license application
Operator Licensing and Human Performance Branch, Division of Construction
Inspection and Operational Programs
Core Operating Limits Report
contaminated area ventilation system
commercial off the shelf
containment performance goal
containment performance improvement
condensate purification system
C-3
CQVB
Quality and Vendor Branch 2, Division of Construction Inspection and
Operational Programs
CR
control room
CRACS
control room air conditioning systems
CRB
control rod block
CRD
control rod drive
CRDA
control rod drop accident
CRDS
control rod drive system
CREFU
control room emergency filtration unit
CRGT
control rod guide tube
CRHA
control room habitability area
CRHAVS control room habitability area ventilation system
CRHS
control room habitability systems
CS&TS
condensate storage and transfer system
CSDRS
certified seismic design response spectra
CSF
critical safety function
CSGB
Steam Generator Tube Integrity and Chemical Engineering Branch, Division of
Component Integrity
CSI
cesium iodide
CST
condensate storage tank
CUF
cumulative usage factor
CV
check valve
CWS
chilled water system
D/Q
deposition factors
D-RAP
design reliability assurance program
D&S
detect and suppress
DAC
design acceptance criteria
DBA
design basis accident
design-basis event
DBE
DBT
design basis threat
DC
design certification
dc
direct current
design certification application
DCA
DCD
design control document
DCH
direct containment heating
DCIS
distributed control and information system
drywell cooling system
DCS
DDT
deflagration-to-detonation transition
DEG
double-ended guillotine
DF
decontamination factor
DG
diesel generator
DGCAIES diesel generator combustion air intake and exhaust system
DGVS
diesel generators heating, ventilation, and air conditioning subsystem
DHR
decay heat removal
DICS
diverse instrumentation and controls systems
DL
dead load
DLF
dynamic load factor
DMW
dissimilar metal welds
DOE
Department of Energy
DOF
degree of freedom
C-4
DOI
DOT
DPL
DPS
DPV
DQR
DR
DRF
DSS
DTLM
DTM
DW
E-DCIS
EAB
EAC
EB
EBAS
EBVS
ECC
ECCS
EDG
EEB
EER
EERVS
EFDS
EFPD
EFPY
EFU
EGC
EGCB
EL
EMB
EMC
EMI
ENS
EOF
EOL
EOP
EP
EPA
EPG
EPRI
EQ
EQD
ERDS
ERF
ERICP
ERIP
ESBWR
dedicated operator interface
Department of Transportation
design pressure limit
diverse protection system
depressurization valve
dynamic qualification report
decay ratio
design record file
detect and suppress solution
digital trip logic module
digital trip module
drywell
essential distributed control and information system
exclusion area boundary
emergency alternating current
electrical building
emergency bottled air breathing system
electrical building heating, ventilation, and air conditioning system
emergency core cooling
emergency core cooling system
emergency diesel generator
Electrical Engineering Branch, Division of Engineering
electric and electronic rooms
electric and electronic rooms heating, ventilation, and air conditioning
subsystem
equipment and floor drain system
effective full power day
effective full power year
emergency filter unit
Exelon Generation Company
Geoscience and Civil Engineering Branch, Division of Engineering
elevation
Engineering Mechanics Branch
electromagnetic compatibility
electromagnetic interference
Emergency Notification System
emergency operations facility
end of life
emergency operating procedure
emergency planning
Environmental Protection Agency
emergency procedure guideline
Electric Power Research Institute
environmental qualification
environmental qualification document
Emergency Response Data System
emergency response facility
emergency rod insertion control panel
emergency rod insertion panel
economic simplified boiling water reactor
C-5
ESF
ESP
EVE
F
F/D
FA
FAC
FAPCS
FAT
FATT
FB
FBFPVS
FBGAVS
FBVS
FCI
FCISL
FCM
FCU
FDA
FE
FEA
FEM
FEMA
FHA
FIRS
FIV
FM
FMCRD
FMEA
FOAK
FOAKE
FOSTS
FPE
FPM
FPP
FPRA
FPS
FPWS
FR
FRA
FRS
FS
FSAR
FSER
FSR
FSWYD
FTDC
FTS
FV
FW
engineered safety feature
early site permit
ex-vessel steam explosions
Fahrenheit
filter/demineralizer
function allocation
flow-accelerated corrosion
fuel and auxiliary pools cooling system
factory acceptance tests
fracture appearance transition temperatures
fuel building
fuel building fuel pool area heating, ventilation, and air conditioning subsystem
fuel building general area heating, ventilation, and air conditioning subsystem
fuel building heating, ventilation, and air conditioning system
fuel-coolant interaction
fuel cladding integrity safety limit
file control module
fan cooling unit
final design approval
finite element
finite element analysis
finite element model
Federal Emergency Management Agency
fire hazards analysis
foundation input response spectrum
flow-induced vibration
Factory Mutual
fine motion control rod drive
failure mode and effects analysis
first-of-a-kind
first-of-a-kind engineering
fuel oil storage and transfer systems
fire pump enclosure
first principle model
fire protection program
fire probabilistic risk assessment
fire protection system
fire protection water system
Federal Register
functional requirements analysis
floor response spectra
full-scale
final safety analysis report
final safety evaluation report
fuel storage rack
fire in switchyard
fault-tolerant digital controller
fuel transfer system
Fussell-Vesely
feedwater
C-6
FWCS
FWIV
FWL
FWLB
FWRB
FWS
FWSC
FWTCS
G
GALL
GDC
GDCS
GDCSP
GDLB
GE
GEH
GI
GIST
GL
GMAW
GMRS
GSI
GT
GTAW
GTS
GW/MTU
GWMS
HA
HAZ
HCLPF
HCU
HCW
HED
HELB
HELSA
HEPA
HF
HFE
HFEITS
HIC
HMR
HP
HPCF
HPCI
HPM
HPCME
HPNSS
HPS
HRA
HRO
feedwater control system
feedwater isolation valve
feedwater line
feedwater line break
feedwater runback
firewater storage
fire water service complex
feedwater temperature control system
acceleration of gravity
generic aging lessons learned
general design criterion
gravity-driven cooling system
gravity-driven cooling system pool
gravity-driven cooling system line break
General Electric
General Electric – Hitachi Nuclear Energy
generic issue
gravity-driven integrated systems test
generic letter
gas metal arc welding
ground motion response spectrum
generic safety issue
gamma thermometer
gas tungsten arc welding
generic technical specification
gigawatts/metric ton of uranium
gaseous waste management system
human action
heat-affected zone
high confidence of low probability of failure
hydraulic control unit
high-conductivity waste
human engineering discrepancy
high-energy line break
high-energy line separation analysis
high-efficiency particulate air
human factors
human factors engineering
human factors engineering issue tracking system
high-integrity containers
Hydrometeorological Reports
high pressure
high pressure core flooder
high pressure coolant injection
human performance monitoring
high pressure core melt ejection
high pressure nitrogen gas supply system
Health Physics Society
human reliability analysis
high regulatory oversight
C-7
HSI
HSS
HVAC
HWCS
I&C
I/O
IA
IAS
IASCC
IBC
IBF
IC
ICE2
ICEA
ICGT
ICHT
ICLB
ICMGT
ICMH
ICP
ICS
ICSB
ID
IE
IEC
IEEE
IESNA
IFTS
IGSCC
IICI
ILRT
IMCC
IN
INPO
IORV
IOT
IP
IPC
IPE
IPEEE
ISA
ISG
ISI
ISLOCA
ISM
ISO
IST
ISV
ITA
human-system interface
high safety significance
heating, ventilation, and air conditioning
hydrogen water chemistry system
instrumentation and control
input/output
instrument air
instrument air system
irradiation-assisted stress corrosion cracking
International Building Code
isolation bypass function
isolation condenser
Instrumentation, Controls and Electrical Engineering Branch 2, Division of
Engineering
Insulated Cable Engineers Association
incore guide tube
isolation condenser heat transfer
isolation condenser line break
incore monitor guide tube
in-core monitor housing
independent control platform
isolation condenser system
Instrumentation and Control Systems Branch, Division of Engineering
identification
infrequent event
International Electrotechnical Commission
Institute of Electrical and Electronic Engineers
Illuminating Engineering Society of North America
inclined fuel transfer system
intergranular stress corrosion cracking
inadvertent isolation condenser initiation
integrated leak rate test
induction motor controller cabinet
information notice
Institute of Nuclear Power Operations
inadvertent opening of relief valves
infrequent operational transients
implementation plan
isolation power center
individual plant examination
individual plant examination of external events
Information, Systems, and Automation Society
interim staff guidance
inservice inspection
intersystem loss-of-coolant accident
independent support motion
International Organization for Standardization
inservice testing
integrated system validation
inspections tests and analyses
C-8
ITAAC
ITP
JCWS
KKM
KWU
L/D
l/s
LBB
LBHS
LCO
LCS
LCW
LD&IS
LDW
LFCV
LHGR
LIA
LLC
LLHS
LLW
LOCA
LOFWH
LOOP
LOPP
LP
LPCI
LPCS
LPRM
LPZ
LRF
LRO
LRS
LRT
LSFT
LSSS
LTR
LTSP
LVDT
LWMS
LWR
MBTU
MCC
MCCI
MCPR
MCR
MCRBP
MCRP
MDRFP
MEB
MFLPD
Inspections, tests, analyses, and acceptance criteria
initial test program
jacket cooling water system
Kashiwazaki Kariwa
Kraftwerk Union Aktiengesellschaft
length to diameter ratio
liters per second
leak before-break
large-bore hydraulic snubbers
limiting condition for operation
local control station
low conductivity waste
leak detection and isolation system
lower drywell
low flow control valve
linear heat generation rate
load interpolation algorithm
limited liability company
light-load handling system
low level waste
loss-of-coolant accident
loss of feedwater heating
loss-of-offsite power
loss of preferred power
low pressure
low pressure coolant injection
low-pressure core spray
local power range monitor
low population zone
large release frequency
low regulatory oversight
liquid radwaste system
leak rate test
logic system function test
limiting safety system setting
licensing topical report
limiting and trip setpoints
linear variable differential transformer
liquid waste management system
light water reactor
one million BTU
motor control center
molten core-coolant interaction
maximum critical power ratio
main control room
main control room back panel
main control room panel system
motor-driven reactor feed pump
modified energy balance
maximum fraction of limiting power density
C-9
MGL
MJ
MLHGR
MMIS
MOD
MOV
MP
MPa
MRBM
MS
MSIS
MSIV
MSIVF
MSIVLCS
MSL
MSLB
MSLI
MSR
MSS
MT
MTCS
MUX
MW
MWR
MWS
N/A
N-DCIS
N-S
NA
NB
NBS
NCIG
ND
NDE
NE-DCIS
NEI
NEMA
NEP
NFPA
NGI
NICWS
NMS
NOAA
NPHS
NPP
NPS
NPSH
NRC
NRHX
NRS
multiple Greek letter
megajoules
maximum linear heat generation rate
man-machine interface system
motor operated disconnect
motor operated valve
medium power
megapascals
multichannel rod block monitor
main steam
main steam isolation system
main steam isolation valve
main steam isolation valve closure with flux scram
main steam isolation valve leakage control system
main steamline
main steamline break
main steam line isolation
moisture separator reheater
main steam system
magnetic particle
main turbine control system
multiplexer
megawatt
metal water reaction
makeup water system
not applicable
nonsafety-related distributed control and information system
north-south
not acceptable
nuclear boiler
nuclear boiler system
Nuclear Construction Issue Group
normal distribution
nondestructive examination
nonessential distributed control and information system
Nuclear Energy Institute
National Electrical Manufacturers Association
nonexceedance probability
National Fire Protection Association
new generic issue
nuclear island chilled water system
neutron monitoring system
National Oceanic and Atmospheric Administration
normal power heat sink
nuclear power plant
nominal pipe size
net positive suction head
Nuclear Regulatory Commission
nonregenerative heat exchanger
not risk-significant
C-10
NS
NSAC
NSR
NSSS
NTSP
NTSPF
NUMARC
NWL
NWS
O&M
OBCV
OBE
OCS
ODCM
OEM
OER
OGS
OHLHS
OIS
OLD
OLMCPR
OLP
OLU
OPDRV
OPRM
ORNL
OSC
P&ID
P/T
PA
PA/PL
PABX
PAM
PAR
PARS
PAS
PASS
PBLE
PBRS
pC
PCC
PCCS
PCD
PCF
PCP
PCT
PDA
PDM
PFRA
PG
nonseismic
Nuclear Safety Analysis Center
non-safety-related
nuclear steam supply system
nominal trip setpoints
final nominal trip setpoint
Nuclear Utilities Management and Resources Council
normal water level
National Weather Service
operation and maintenance
overboard control valve
operating-basis earthquake
operational condition sampling
offsite dose calculation manual
original equipment manufacturer
operating experience review
offgas system
overhead heavy-load handling system
oxygen injection system
output logic device
operating limit minimum critical power ratio
online procedure
output logic unit
operation with potential to drain the reactor vessel
oscillation power range monitor
Oak Ridge National Laboratory
operational support center
piping and instrumentation diagram
pressure/temperature
protected area
plant page/party-line
private automatic branch exchange
postaccident monitoring
passive autocatalytic recombiner
passive autocatalytic recombiner system
plant automation system
postaccident sampling stations
plant-based load evaluation
performance-based seismic response spectrum
pico coulombs
passive containment cooling
passive containment cooling system
plant configuration database
plant computer functions
process control program
peak cladding temperature
piping dynamic analysis
project design manual
plant-level functional requirements analysis
power generation
C-11
PGA
PH
PID
PIP
PIRT
PIV
PL
PLC
PMC
PMF
PMP
PMWP
POS
POV
PPS
PRA
PRMS
PRNM
PS
PSB
PSD
PSI
PSS
PSTF
PSW
PSWS
PT
PTLR
PUMA
PWR
Q-DCIS
QA
QAP
QAPD
QG
QMS
R/A
RACS
RAI
RAP
RAPI
RAT
RAW
RB
RBCC
RBV
RBVS
RC&IS
RCBS
RCC
peak ground acceleration
precipitation hardening
proportional, integral, derivative
plant investment protection
phenomena identification and ranking table
pressure isolation valve
primary local membrane stress
programmable logic controller
performance monitoring and control
probable maximum flood
probable maximum precipitation
probable maximum winter precipitation
plant operational state
power-operated valve
preferred power supply
probabilistic risk assessment
process radiation monitoring system
power range neutron monitor
pool swell
Power Systems Branch, Division of Safety Systems
power spectra density
preservice inspection
process sampling system
pressure suppression test facility
plant service water
plant service water system
liquid penetrant
pressure and temperature limits report
Purdue University Meteorological Association
pressurized water reactor
safety-related distributed control and information system
quality assurance
quality assurance program
quality assurance program description
quality group
quality management system
reliability/availability
rod action control subsystem
request for additional information
reliability assurance program
rod action and position information
reserve auxiliary transformer
risk achievement worth
reactor building
rod brake controller cabinet
reactor building vibration
reactor building heating ventilation and air conditioning system
rod control and information system
refueling cavity bellows seal
remote communication cabinet
C-12
RCCV
RCCW
RCCWS
RCIC
RCPB
RCS
RCSLD
REMP
REPAVS
RES
RETS
RFI
RFP
RG
RH
RHEB
RHR
RHX
RIP
RIS
RMS
RMU
ROAAM
RPS
RPT
RPV
RPVSB
RRPS
RRS
RSA
RSAC
RSB
RSPC
RSS
RSW
RT
RTD
RTIF
RTNDT
RTNSS
RTP
RTS
RV
RVMSP
RW
RWB
RWCR
RWCRVS
RWCU
reinforced concrete containment vessel
reactor closed-cooling water
reactor component cooling water system
reactor core isolation cooling
reactor coolant pressure boundary
reactor coolant system
reactor coolant system leakage detection
radiological environmental monitoring program
refueling and pool area heating ventilation and air conditioning subsystem
Office of Nuclear Regulatory Research
radiological effluent technical specification
radio frequency interference
reactor feed pump
regulatory guide
relative humidity
Hydrological Engineering Branch, Division of Site and Environmental Reviews
residual heat removal system
regenerative heat exchanger
reactor internal pump
regulatory issue summary
radiation monitoring subsystem
remote multiplexing unit
risk-oriented accident analysis methodology
reactor protection system
recirculation pump trip
reactor pressure vessel
reactor pressure vessel support bracket
reference rod pull sequence
required response spectra
reactor shield annulus
Siting and Accident Consequences Branch, Division of Site and Environmental
Reviews
Reactor Systems Branch, Division of Safety Systems
rod server processing channel
remote shutdown system
reactor shield wall
radiographic testing
resistance temperature detector
reactor trip and isolation function
reference temperature nil ductility temperature
regulatory treatment of non-safety systems
rated thermal power
reactor trip system
reactor vessel
reactor vessel materials surveillance program
radwaste
radwaste building
radwaste control room
radwaste control room heating, ventilation, and air conditioning subsystem
reactor water cleanup
C-13
RWDS
RWE
RWGA
RWGAVS
RWM
RWMS
RWVS
S&T
SA
SACF
SAD
SAM
SAMA
SAMDA
SAMG
SAR
SAS
SAT
SAW
SB
SB&PC
SBO
SBWR
SC
SCC
SCG
SCMP
SCP
SCRAM
SCRRI
SDC
SDG
SDGLS
SDGSAS
SDM
SDOE
SDP
SDS
SDV
SE
SER
SERG
SFAT
SFP
SFPCS
SFRA
SGI
SGTR
SI
SInstP
radioactive waste drain systems
rod withdrawal error
radwaste general area
radwaste general area heating, ventilation, and air conditioning subsystem
rod worth minimizer
radioactive waste management system
radwaste heating, ventilation, and air conditioning system
shell & tube
service air
single active component failure
software architecture descriptions
startup administrative manual
severe accident mitigation alternatives
severe accident mitigation design alternatives
severe accident management guideline
safety analysis report
service air system
site acceptance test
submerged arc welding
service building
steam bypass and pressure control
station blackout
simplified boiling-water reactor
structure and component
stress corrosion cracking
startup coordinating group
software configuration management plan
setpoint control program
prompt reactor trip
selected control rod run in
shutdown cooling
standby diesel generator
standby diesel generator lubrication system
standby diesel generator starting air system
shutdown margin
secure development and operational environment
software development plan
system design specification
scram discharge volume
safety evaluation
safety evaluation report
Steam Explosions Review Group
system factory acceptance test
spent fuel pool
spent fuel pool cooling system
system functional requirements analysis
safeguards information
steam generator tube rupture
International System of Units
software installation plan
C-14
SIntP
SIP
SIS
SIT
SIU
SJAE
SL
SLC
SLCS
SLMCPR
SMA
SMACNA
SMP
SMPM
SMT
SOC
SOMP
SOP
SP
SPC
SPCS
SPDS
SPLB
SPTM
SQA
SQAP
SQAPM
SR
SREC
SRI
SRM
SRNM
SRO
SRP
SRS
SRSB
SRSS
SRV
SRVD
SS
SSAM
SSC
SSE
SSI
SSLC
SSP
SST
STP
STRAP
software integration plan
software installation plan
structural integrity shutdown
structural integrity test
signal interface unit
steam jet-air ejector
safety limit
standby liquid control
standby liquid control system
safety limit minimum critical power ratio
seismic margins analysis
Sheet Metal and Air Conditioning Contractors’ National Association
software management plan
software management program manual
scale model test
state of charge
software operations and maintenance plan
software operations plan
suppression pool
suppression pool cooling
suppression pool cooling system
safety parameter display system
Plant Systems Branch, Division of Safety Systems
suppression pool temperature monitoring
software quality assurance
software quality assurance plan
software quality assurance program manual
surveillance requirement
standard radiological effluent controls
select rod insert
staff requirements memorandum
startup range neutron monitor
senior reactor operator
Standard Review Plan
software requirements specifications
Reactor Systems, Nuclear Performance and Code Review Branch, Division of
Safety Systems and Risk Assessment
square root of the sum of the squares
safety relief valve
safety relief valve discharge
specific subscale
seismic anchor movement
structures, systems, and components
safe-shutdown earthquake
soil-structure interaction
safety system logic control
software safety plan
shear stress transport
software test plan
scram time recording and analysis panel
C-15
STrngP
STRP
STS
SV
SVT
SVVP
SWMS
T-AT
T-H
T&M
TA
TAF
TAP
TASS
TB
TBAS
TBCE
TBDRE
TBE
TBLOE
TBS
TBV
TBVS
TCCWS
TCV
TEDE
TEMA
TER
TG
TGCS
TGSS
TI
TID
TIP
TLU
TMI
TMSS
TR
TS
TSC
TSCVS
TSFA
TSL
TSM
TSTF
TSV
UAT
UCL
UDW
UHS
software training plan
scram time recording panel
standard technical specifications
safety valve
software validation test
software verification and validation plan
solid waste management system
transient without negative reactivity insertion
thermal-hydraulics
test and maintenance
task analysis
top of active fuel
task action plan
turbine auxiliary steam system
turbine building
turbine building air supply
turbine building compartment exhaust
turbine building decontamination room exhaust
turbine building exhaust
turbine building lube oil area exhaust
turbine bypass system
turbine bypass valve
turbine building heating, ventilation, and air conditioning system
turbine component cooling water system
turbine control valve
total effective dose equivalent
Tubular Exchanger Manufacturers Association
technical evaluation report
turbine generator
turbine generator control system
turbine gland seal system
temporary instruction
technical information document
traversing in-core probe
trip logic unit
Three Mile Island
turbine main steam system
topical report
technical specifications
technical support center
technical support center heating, ventilation, and air conditioning subsystem
top of the stored fuel assemblies
technical specification leakage
technical specifications monitor
Technical Specifications Task Force
turbine stop valve
unit auxiliary transformer
upper confidence limit
upper drywell
ultimate heat sink
C-16
UL
UPS
URD
URI
URS
US
USE
USI
USM
USNRC
UT
V&V
VAC
VB
VBIF
VBIV
VDC
VDU
VFTP
VHRA
VLA
VLC
VLU
VPF
VRLA
VS
VT
VW
WBGT
WDP
WG
WNP-2
WRC
WW
ZIS
ZPA
Underwriter's Laboratories
uninterruptible power supplies
utility requirements document
unresolved item
ultimate rupture strength
United States
upper-shelf energy
unresolved safety issue
uniform support motion
United States Nuclear Regulatory Commission
ultrasonic
verification and validation
volts alternating current
vacuum breaker
vacuum breaker isolation function
vacuum breaker isolation valve
volts direct current
video display unit
ventilation filter testing program
very high radiation area
vented lead acid
vent line clearing
voter logic unit
vane passing frequency
valve-regulated lead-acid
ventilation stack
vertical
vent wall
wet bulb globe temperature
wide display panel
water gauge
Washington Nuclear Plant Unit 2
Welding Research Council
wetwell
zinc injection system
zero period acceleration
C-17
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