Experience of NRSC on
Providing Technical
Support to ANRA
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 …
Regulatory Infrastructure Model in Armenia
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……and
services…education and training
services…national and international R&D
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N&RSC was established in 2002
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Initial staff was 5 specialists:
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Thermal hydraulic analysis specialists (2)
Seismic and structure analysis specialist (1)
Systems analysis (1)
Support (1)
Main mission:
◦ Provide technical support to ANRA.
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No funding from the Government
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Current staff: 30
◦ Doctors: 7
◦ PhD students: 4
◦ Engineers: 9
◦ IT specialists: 4
◦ Management & Administration: 6
Average age: 35
Director
Adviser
Chief Accountant
Project Manager, QMS
officer
Deputy Director
Nuclear Safety
Radiation Safety
Nuclear Information
Technological systems and
components
Radiation Protection and
Dosimetery
Nuclear information
Neutronics and Nuclear Fuel
Radioactive waste and
decommissioning
Information technologies
Thermal hydraulics
Risk Assessment
Structural Integrity and
Seismic Safety
Support
Atmospheric
dispersion, dose
calculation
Confinement
thermal-hydraulic,
hydrogen, aerosol,
isotope behavior
Thermal-hydraulic,
core melting
Isotope composition,
criticality analysis, 3D
kinetics, SS core analysis ,
cross-sections library
Mitigati
on
Confine
ment
Core
cooling
Control
of
reactivity
Tools: RADTRAD
v3.03, RASCAL v3.0.5,
PUMA v2
Tools: MELCOR
v1.8.6, COCOSYS
v2.4
Tools: RELAP5 v3.3,
TRACE v5, MELCOR
v1.8.6
Tools: ORIGEN, TRITON,
MONTEBURNS, KENO-VI,
MCNPX, PARCS, HELIOS
Gamma
spectrometry,
X-ray testing,
Individual
dosimetery,
Workplace
monitoring,
Orphan sources
identification
МКС-АТ6101С - γ
spectrometer
Radiagem-2000 - α,
β, γ meter
InSpector 1000 - γ, n
meter, γ
spectrometer.
IdentiFinder –NH, γ
spectrometer
EBERLINE E-600, γ
meter
Unfors Xi – X-Ray
meter, QA/QC X-ray
devices.
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Cooperative Agreement between US NRC and
CAMP Agreement
IAEA
EC JRC
GRS, Germany
SERCO, UK
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Thermal hydraulic analyses:
◦ Application of new safety analysis
methodologies:
◦ Tools:(the code and training
provided by US NRC)
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RELAP5 mod 3.2.2
MELCOR 1.8.5
TRACE (2009)
RADTRAD
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Core Physics:
◦ Application of state-of-art methods for
development of hexagonal model of
VVER-440 fuel assemblies and core;
◦ Tools:
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ORIGEN-S, KENO-VI,
PARCS-RELAP, TRITON, SCALE
HELIOS
TRANSURANUS
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Seismic and structural
analyses:
◦ Reactor building and DG building
models development
◦ Tools:
 Stardyne analysis package
 SuperSASSI
 SOLVIA
735
1103
1102 1095
919
761
1100
685
1075
1722
1044
1050
1020
1087
479
366
518
1069
913
492
680
1091
534
155
500
141
388
297
110
133
622
772
120
154
33
220
118
Z
22
X
1
11
Y
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Probabilistic analyses:
◦ PSA level 1 study for ANPP Unit
2:
 Training provided by US NRC and
IAEA.
◦ Tools:
 Riskspectrum
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Radiologic measurements:
◦ Training of specialists:
 Environmental Radiation Monitoring (air sampling, alpha, beta
contamination);
 Gamma spectrometry;
 X-ray tasting.
◦ Tools:
 Radiometric and dosimetric measurement equipment.
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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.
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Safety case study for replacement of PRZ
SVs
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Analysis of primary side feed and bleed
operation for ANPP Unit 2
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Analysis of cases potential for cold
overpressurization of reactor vessel
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Jet Vortex Condenser analysis
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Licensing of the ANPP Unit 2 long term
operation:
◦ Review of ANPP U2 Safety Analysis Report (Selected
chapters)
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Licensing of Dry Spent Fuel Storage:
◦ Review of Safety Analysis Report for Dry Spent Fuel
Storage (selected chapters)
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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.
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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.
Z
Y
X
Z
Y
X
Output Set: BODY-ZContour: Solid Z Normal Stress
Probabilistic analyses:
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◦ PSA models development:
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Internal IEs, Fire IEs, Flood IEs, External IEs;
◦ PSA applications:
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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).
AC-3RA
@AC-3RA-8
ACNBSA03LF
@AC-3RA-9
@AC-3RA-10
ACNCBR09RO
ACNBSA03LM
ACNCBR11GC
AC-RA2
ACNCBR10RO
ACNTR23THF
AC-T3
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Participation as a consortium member in the
project for development of comprehensive
safety upgrading program for ANPP
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Basic engineering design on ECCS modernization
Radiological consequence analysis
Fire PSA
RIA analysis on shutdown mode
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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 VVER440 fuel. For that 3D Monte
Carlo depletion analysis was
performed by MONTEBURNS
code that couples MCPX and
ORIGEN codes.
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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.
Radiological
measurements:

Workplace monitoring.
Individual monitoring:

Measurement and archiving of
individual doses;

Tools: HARSHAW 4500 TLD.
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Measurements during emergency
conditions and post-emergency
monitoring;
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Identification of unknown
sources.
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Regulatory Documents (laws, regulations,
guidelines)
Inventorization
Regulatory Information System (RIS)
Regional Offices
Equipment
Plant Decommissioning Regulatory
Licensing Plan
Seminars and Trainings
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Action program for regulatory infrastructure
upgrade
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Siting safety requirement
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Design safety requirements
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Procedures for review of submittals
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SAR structure and content requirements
• Coolant mixing in RPV
– Local criticality and PTS
Structural analyses
and aging factors
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• Stress analyses of
confinement
– What is the maximum
overpressure or
under-pressure limit
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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:
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Licensing of new facilities
Licensing of design changes
Development of regulations
Control of sources.
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All above mentioned become true because of
essential help from:
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IAEA
US NRC
GRS
JRC