Armen Amirjanyan, Suren BznuniNuclear & Radiation Safety Canter (www.nrsc.am)

 

Experience of NRSC on Providing Technical Support to ANRA

CONCLUSIONS OF THE CONFERENCE:

1. The RB’s authoritative function, 2. Technical and

scientific advisory expert function. 3. …development and

maintenance of an appropriate knowledge base and associated tools …

NRSC

Regulatory Infrastructure Model in Armenia

2. Technical and scientific advisory expert function

3. development and maintenance of an appropriate knowledge base and associated tools……and services…education and training services…national and international R&D

1. The RB’s authoritative function

ANRA

N&RSC was established in 2002

Initial staff was 5 specialists: ◦ Thermal hydraulic analysis specialists (2)◦ Seismic and structure analysis specialist (1)◦ Systems analysis (1)◦ Support (1)

Main mission:◦ Provide technical support to ANRA.

No funding from the Government

Beginning

Current staff: 30◦Doctors: 7 ◦PhD students: 4 ◦Engineers: 9 ◦IT specialists: 4◦Management & Administration: 6

Average age: 35

Current Staff

StructureDirector

Deputy Director

Nuclear Safety Radiation Safety Nuclear Information

Adviser

Project Manager, QMS officer

Technological systems and components

Neutronics and Nuclear Fuel

Risk Assessment

Structural Integrity and Seismic Safety

Radioactive waste and decommissioning

Radiation Protection and Dosimetery

Nuclear information

Information technologies

Chief Accountant

Support

Thermal hydraulics

Main capabilities

Mitigation

Confinement

Core cooling

Control of

reactivity Tools: ORIGEN, TRITON,

MONTEBURNS, KENO-VI, MCNPX, PARCS, HELIOS

Tools: RELAP5 v3.3, TRACE v5, MELCOR

v1.8.6Thermal-hydraulic,

core melting

Confinement thermal-hydraulic, hydrogen, aerosol, isotope behavior

Atmospheric dispersion, dose

calculation

Tools: MELCOR v1.8.6, COCOSYS

v2.4

Tools: RADTRAD v3.03, RASCAL

v3.0.5, PUMA v2

Isotope composition, criticality analysis, 3D

kinetics, SS core analysis , cross-sections library

In addition…МКС-АТ6101С - γ spectrometerRadiagem-2000 - α, β, γ meterInSpector 1000 - γ, n meter,  γ spectrometer.IdentiFinder –NH, γ spectrometer EBERLINE  E-600, γ meterUnfors Xi – X-Ray meter, QA/QC X-ray devices.

Gamma spectrometry, X-ray testing, Individual dosimetery, Workplace monitoring, Orphan sources identification

Cooperative Agreement between US NRC and CAMP Agreement

IAEA EC JRC GRS, Germany SERCO, UK

Development of Capabilities

Thermal hydraulic analyses: ◦ Application of new safety

analysis methodologies: ◦ Tools:(the code and training

provided by US NRC) RELAP5 mod 3.2.2 MELCOR 1.8.5 TRACE (2009) RADTRAD

Development of Capabilities

Development of capabilities Core Physics:

◦ Application of state-of-art methods for development of hexagonal model of VVER-440 fuel assemblies and core;

◦ Tools: ORIGEN-S, KENO-VI, PARCS-RELAP, TRITON, SCALE HELIOS TRANSURANUS

Seismic and structural analyses: ◦ Reactor building and DG building

models development◦ Tools:

Stardyne analysis package SuperSASSI SOLVIA

Development of Capabilities

XY

Z

1

11

22

33

366

155110

120133388141

220

154

297

118

500

388

534

518479

492 680

685

772622

735

761

919

9131020

110311021095

10751100

1091

1069

10501087

10441722

Probabilistic analyses:◦ PSA level 1 study for ANPP Unit

2: Training provided by US NRC and

IAEA.◦ Tools:

Riskspectrum

Development of Capabilities

Development of Capabilities Radiologic measurements:

◦ Training of specialists: Environmental Radiation Monitoring (air sampling, alpha, beta

contamination); Gamma spectrometry; X-ray tasting.

◦Tools: Radiometric and dosimetric measurement equipment.

Support to ANRA’s licensing process Support to Armenian NPP modernization

program Support to ANRA’s Radiation sources

program Support to ANRA for preparation to the new

unit licensing.

Major Activities

Safety case study for replacement of PRZ SVs

Analysis of primary side feed and bleed operation for ANPP Unit 2

Analysis of cases potential for cold overpressurization of reactor vessel

Jet Vortex Condenser analysis

Support to ANRA

Licensing of the ANPP Unit 2 long term operation:◦ Review of ANPP U2 Safety Analysis Report

(Selected chapters)

Licensing of Dry Spent Fuel Storage:◦ Review of Safety Analysis Report for Dry Spent

Fuel Storage (selected chapters)

Support to ANRA

Support to ANPP Reactivity Induced

Accident were analyzed by PARCS-RELAP coupled code:

CA Ejection, Withdrawal, Drop;

Boron dilution; Incorrect connection of an

inactive loop; Inadvertent loading of a

fuel assembly into wrong position.

Support to ANPP Seismic and structural analyses

◦ ANPP Seismic Re-Evaluation Program: Site Response Analysis; Reactor and DG buildings Floor response analysis

(reviewed by BNL) Soil and Structure Capacity Evaluation Extreme wind and snow impact assessment for

ANPP vent. stack and reactor building roof.XY

Z

XY

Z

Output Set: BODY-ZContour: Solid Z Normal Stress

Probabilistic analyses:◦ PSA models development:

Internal IEs, Fire IEs, Flood IEs, External IEs;

◦ PSA applications: Modernisation prioritisation Training materials for ANRA newcomers; Emergency response procedures; Participation in SDP notebooks

development (with BNL); Accident scenarios development for cold

overpressure analysis.◦ Collaboration with EC JRC (ageing

PSA).

Support to ANPP

AC-3RA

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@AC-3RA-8

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@AC-3RA-9

Íåò ïèòàíèÿ îò 23Ò

ACNCBR09RO

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ACNCBR10RO

Îòêàç âûêëþ÷àòåëÿ Â2-23Ò"À" îñòàâàòüñÿ çàêðûòûì

ACNTR23THF

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AC-T3

Íåò ïèòàíèÿ îò Ò-3

@AC-3RA-10

Íåò ðåçåðâíîãî ïèòàíèÿ

ACNCBR11GC

Îòêàç âûêëþ÷àòåëÿ Âð-3ÐÀ îò ÐÀ-2 çàêðûòüñÿ

AC-RA2

Íåò ïèòàíèÿ íà ðåçåðâíîì øèíîïðîâîäå ÐÀ-2

ACNBSA03LF

Îòêàç ñåêöèè 3ÐÀ âî âðåìÿ ðàáîòû

ACNBSA03LM

Íåãîòîâíîñòü ñåêöèè 3ÐÀ èç-çà ðåìîíòà

Participation as a consortium member in the project for development of comprehensive safety upgrading program for ANPP◦ Basic engineering design on ECCS modernization◦ Radiological consequence analysis◦ Fire PSA◦ RIA analysis on shutdown mode

Support to ANPP

Other Activities Database of isotopic

composition of VVER-440 fuel was developed for MELCOR model.

TRANSURANUS code subroutine TUBRP was updated to deal with hexagonal geometry of VVER-440 fuel. For that 3D Monte Carlo depletion analysis was performed by MONTEBURNS code that couples MCPX and ORIGEN codes.

Emergency response procedures for ANRA:

MELCOR model development and analyses of severe accidents for ERC procedures development

Development of ANRA emergency response center procedures for prognoses of source terms.

Other Activities

Radiological measurements:

◦ Workplace monitoring.◦ Individual monitoring:

Measurement and archiving of individual doses;

Tools: HARSHAW 4500 TLD. ◦ Measurements during

emergency conditions and post-emergency monitoring;

◦ Identification of unknown sources.

Other Activities

Regulatory Documents (laws, regulations, guidelines)

Inventorization Regulatory Information System (RIS) Regional Offices Equipment Plant Decommissioning Regulatory

Licensing Plan Seminars and Trainings

Radiation Sources Program

Action program for regulatory infrastructure upgrade

Siting safety requirement

Design safety requirements

Procedures for review of submittals

SAR structure and content requirements

New Unit Program

What is next? • Coolant mixing in RPV – Local criticality and PTS

What is next? Structural analyses and aging factors

What is next? • Stress analyses of

confinement–What is the

maximum overpressure or under-pressure limit

In Armenia technical support capabilities were created in several important areas of nuclear safety in relatively short time.

TSO provided and continue to provide essential help to RB in the areas:◦ Licensing of new facilities◦ Licensing of design changes◦ Development of regulations◦ Control of sources.

Conclusion

All above mentioned become true because of essential help from:◦ IAEA◦ US NRC◦ GRS◦ JRC

Appreciations