Terminology

ACRS

Advisory Committee on Reactor Safeguards - A US Nuclear Regulatory Commission statutory committee that reviews applications for nuclear facility licenses, both original and renewal licenses

ADAMS

Agency wide Documents Access and Management System - The official recordkeeping system, through which the U.S. Nuclear Regulatory Commission (US NRC) provides access to the "libraries" or collections of publicly available documents

ALE

Adverse Local Environments - Local environments where the temperature or radiation level is greater than anticipated in the plant design. Typically used when assessing aging of electrical cables.

AM

Aging Management

AMC

Aging Management Coordinator - A position in the organization of a nuclear power plant who is responsible for ensuring the inspections committed to in a license renewal application are performed.

AMP

Aging Management Program

AMR

Aging Management Review

ART

Adjusted Reference Temperature

ASME

American Society of Mechanical Engineers

ASN

Autorité de sûreté nucléaire - French Nuclear Regulatory Body

ATWS

Anticipated Transients Without Scram - A scenario where a scram system fails to work during an event of a reactor anticipated transient

BWR

Boiling Water Reactor

BWROG

Boiling Water Reactor Owners Group

BWRVIP

Boiling Water Reactor Vessel Internals Program - The BWRVIP is an industry program for General Electric boiling water reactors that has developed procedures for performing inspections of reactor vessel internals.

CANDU

Canada Deuterium Uranium

CAP

Corrective Action Program - A program that specifies and implements corrective actions when aging degradations are identified.

CASS

Cast Austenitic Stainless Steel

CFR

Code of Federal Regulations - The US federal government regulations. 10 CFR 54 is the regulation for renewal of nuclear power plant operating licenses.

CLB

Current Licensing Basis - 10 CFR 54.3 under references

CMAA

Crane Manufacturers Association of America

CSN

Spain´s Regulatory Authority

CT

Calandria Tube - A PWHR component

CUF

Cumulative Usage Factor - The Cumulative Usage Factor is part of the fatigue analysis for metal fatigue.

DPT

Dye Penetrant Test - A method to detect cracks on external surfaces of components using a liquid dye. Also known as Penetrant Test.

EAF

Environmentally Assisted Fatigue - A degradation mechanism given by a reduction in fatigue life in the reactor water environment compared with the in-air environment.

ENSREG

European Nuclear Safety Regulators Group - An independent, expert advisory group of experts in national nuclear safety, radioactive waste safety or radiation protection from all Member States in the European Union and representatives of the European Commission

EPRI

Electric Power Research Institute

EQ

Environmental Qualification - A process for ensuring that equipment will be capable of withstanding the ambient conditions that could exist when the specific function to be performed by the equipment is actually called upon to be performed under accident conditions.

ER

Environmental Reports - Environmental Reports are the part of a US license renewal application that evaluates the environmental impact of operation of the plant for an additional 20 years.

ERWG

Equipment Reliability Working Group

EVT

Enhanced Visual Test

FP

Fire Protection

FSAR

Final Safety Analysis Report

GALL

Generic Aging Lessons Learned - The US NRC GALL Report is NUREG-1801. The US NRC Subsequent License Renewal GALL is NUREG-2191

GEIS

Generic Environmental Impact Statement - NUREG-1437. The US NRC generic assessment of the environmental impact of operation of nuclear power plants during the license renewal term. Each applicant prepares a supplement to the GEIS for the plant.

GSI

Generic Safety Issues

HAZ

Heat Affected Zone - The area on either side of a metal weld where the properties of the metal are affected by the welding process.

HELB

High Energy Line Break - A postulated event of ruptures of high energy piping.

I&C

Instrumentation and Control

IAEA

International Atomic Energy Agency

IERWG

International Equipment Reliability Working Group

IGALL

International Generic Ageing Lessons Learned - An IAEA's publication: SRS-82

ILCM

Integrated Life Cycle Management

INPO

Institute of Nuclear Power Operations

IP

Inspection Procedure

IPA

Integrated Plant Assessment

LCM

Life Cycle Management

LOCA

Loss of Coolant Accident

LR

License Renewal

LRA

License Renewal Application - The document submitted by the plant licensee under 10 CFR 54 to extend the operating license of the plant from 40 to 60 years.

LR-ISG

License Renewal Interim Staff Guidance

LRTF

License Renewal Task Force

LTO

Long Term Operation

LTOP

Low-Temperature Overpressure Protection - PWRs have a Low-Temperature Overpressure Protection analysis that includes a fatigue analysis that is a TLAA for License Renewal

MEB

Metal Enclosed Bus

MIC

Microbiologically Influenced Corrosion - A degradation mechanism of corrosion influenced by microorganisms.

MR

Maintenance Rule - US NRC Maintenance Rule 10 CFR 50.65

MT

Magnetic Particle Test - A nondestructive testing method using a magnetic field to identify shallow surface discontinuities.

NDE

Non Destructive Examination

NEA

Nuclear Energy Agency - An intergovernmental agency that facilitates co-operation among countries with advanced nuclear technology infrastructures operating within the framework of the Organization for Economic Co-operation and Development (OECD)

NEI

Nuclear Energy Institute

NPP

Nuclear Power Plant

NRC

Nuclear Regulatory Commission - The US federal government agency that regulates nuclear power plants

NSR

Nonsafety-Related

NUREG

US NRC regulatory guide

OE

Operating Experience

OEM

Original Equipment Manufacturer

OTI

One-Time Inspections - One-time inspections of selected components or structures to verify effectiveness of AMPs monitoring chemistry: water chemistry, fuel oil and lubricating oil.

PDCA

Plan-Do-Check-Act - A management method for continuous improvement with the following steps: plan, do, check, act.

PEO

Period of Extended Operation - The Period of Extended Operation is the time period between the end of the original plant operating license and the end of the plant renewed license. In US plants, this will typically be 20 years.

PHWR

Pressurized Heavy Water Reactor

PIEGE

Integrated Plan for the Evaluation and Management of Aging - Basic document required for the evaluation of the long-term operation of the plant conducted by the Spanish regulatory body, which includes the activities of the Aging Management, scope and screening, aging management review and aging management programs, and additionally the necessary time-based aging analyses for the review of the analyses performed with defined design life hypotheses.

PM

Preventive Maintenance

PSA

Probabilistic Safety Assessment

PSR

Periodic Safety Review

PT

Pressure Tube - A PWHR component

P-T

Pressure-Temperature limit

PTS

Pressurized Thermal Shock

PWR

Pressurized Water Reactor

PWROG

Pressurized Water Reactor Owners Group

PWSCC

Primary Water Stress Corrosion Cracking

QA

Quality Assurance

RG

Regulatory Guide - A US NRC guidance document.

RHWG

Reactor Harmonization Working Group - A working group within WENRA.

RIS

Regulatory Issue Summary - US NRC regulatory issue summaries are used to communicate and clarify information to licensees.

ROP

Reactor Oversight Program - The US NRC program for regulating the operation of nuclear power plants. After a renewed license is issued, this includes inspections specifically for license renewal commitments.

RPV

Reactor Pressure Vessel

RR

Research Reactors

RT

Radiography Test - A nondestructive testing method using X-rays to detect flaws in a component or to measure the component's wall thickness.

RTF

Run to Failure

SAMA

Severe Accident Mitigation Alternatives

SAMDA

Severe Accident Mitigation Design Alternatives

SBO

Station Blackout - An accident condition where a nuclear plant is disconnected from the outside electrical power grid and the plant's emergency diesel generators fail to provide power to the plant's electrical system.

SCC

Stress Corrosion Cracking

SDS-1

Shutdown System 1 - Primary shutdown system of PHWR that uses mechanical neutron-absorbing shut off rods.

SE

Safety Evaluation

SER

Safety Evaluation Report

SF

Safety Fundamentals

SFP

Spent Fuel Pool

SLR

Subsequent License Renewal - The extension of the original license from 40 years to 60 years is known as License Renewal. Extensions of the license beyond 60 years are known as Subsequent License Renewal.

SLRA

Subsequent License Renewal Application - The document submitted by the plant licensee under 10 CFR 54 to extend the operating license of the plant beyond 60 years in 20 year increments. 10 CR 54 has no limits on the number of license extensions that can be approved for a plant.

SPEO

Subsequent Period of Extended Operation - The time period when a license is extended after the first period of extended operation. In the US, there is no limit to the number of subsequent periods of operation.

SPV

Single Point Vulnerability

SR

Safety-Related

SRP

Standard Review Plan - A US NRC guidance document for review of a submittal by a licensee of a nuclear power plant.

SRP-LR

Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants - US NRC document used to review a license renewal application. NUREG-1800 for the first license extension. NUREG-2192 for subsequent license renewal.

SRS

Safety Reports Series

SSC

Systems, Structures, and Components

SSG

Specific Safety Guide - IAEA's documents with safety guidance on a specific topic.

SSR

Specific Safety Requirements - IAEA's documents with safety requirements on a specific topic.

TLAA

Time Limited Aging Analyses - See the TLAA subpage for the definition and explanation of TLAAs.

TPR

Topical Peer Review - A topical peer review organized by ENSREG with aim to incorporate lessons learned following the accident at the Fukushima Daiichi NPP in 2011.

UFSAR

Updated Final Safety Analysis Report - The Updated Final Safety Analysis Report is the version of the FSAR that has been revised during the operation of the plant and is the most recent version.

US

United States of America

U.S.A.

United States of America

USE

Upper Shelf Energy - The temperature at which metal changes from brittle to ductile failure.

UT

Ultrasonic Test - A nondestructive test method using ultrasonic waves to determine the thickness of a component and to detect cracks or other degradation.

WANO

World Association of Nuclear Operators

WENRA

Western European Nuclear Regulators Association - An association of European nuclear regulators with objective of co-operation and exchanging of experience in significant safety issues.

WO

Work Order - A document used to authorize and control maintenance repairs, inspections, testing, and other work in a nuclear power plant.

WWER

Water-water energetic reactor