Monica Hurley: Revision 0; Reviewed by Garry Young

2024-10-10T15:16:24Z

Revision 0; Reviewed by Garry Young

← Older revision		Revision as of 15:16, 10 October 2024
Line 247:		Line 247:
	;QA		;QA
	:Quality Assurance		:Quality Assurance

			;RAI
			:Request for additional information

	;RG		;RG

Monica Hurley: 1 revision imported: Initial page creation

2024-10-04T19:12:26Z

1 revision imported: Initial page creation

← Older revision	Revision as of 19:12, 4 October 2024
(No difference)

en>Monica Hurley: Created page with "{{DISPLAYTITLE:LTO Acronyms and Descriptions}} NOGLOSSARY ;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 pub..."

2024-06-11T05:36:59Z

Created page with "{{DISPLAYTITLE:LTO Acronyms and Descriptions}} __NOGLOSSARY__ ;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 pub..."

New page

{{DISPLAYTITLE:LTO Acronyms and Descriptions}}

__NOGLOSSARY__
;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. [https://www.nrc.gov/reading-rm/doc-collections/cfr/part054/index.html 10 CFR 54] is the regulation for renewal of nuclear power plant operating licenses.

;CLB
:Current Licensing Basis - [https://www.nrc.gov/reading-rm/doc-collections/cfr/part054/part054-0003.html 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 [https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1801/index.html NUREG-1801]. The US NRC Subsequent License Renewal GALL is [https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr2191/index.html NUREG-2191]

;GEIS
:Generic Environmental Impact Statement - [https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1437/index.html 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: [https://www.iaea.org/publications/13475/ageing-management-for-nuclear-power-plants-international-generic-ageing-lessons-learned-igall 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 [https://www.nrc.gov/reading-rm/doc-collections/cfr/part054/index.html 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| 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 [https://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-0065.html 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| 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 [https://www.nrc.gov/reading-rm/doc-collections/cfr/part054/index.html 10 CFR 54] to extend the operating license of the plant beyond 60 years in 20 year increments. [https://www.nrc.gov/reading-rm/doc-collections/cfr/part054/index.html 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. [https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1800/index.html NUREG-1800] for the first license extension. [https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr2192/index.html 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| TLAA subpage]] for the definition and explanation of [[TLAA| 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

Terminology - Revision history

Monica Hurley: Revision 0; Reviewed by Garry Young

Monica Hurley: 1 revision imported: Initial page creation