Safety Considerations of Nuclear Fuel Cycle Facilities November, 2016 Directorate General of Nuclear...
Transcript of Safety Considerations of Nuclear Fuel Cycle Facilities November, 2016 Directorate General of Nuclear...
22 November, 2016
Directorate General of Nuclear Power Fuel
Pakistan Atomic Energy Commission
Safety Considerations of
Nuclear Fuel Cycle Facilities
Dr. Syed Waseem Akhtar
Director (Nuclear Power Fuel)
Outline
Introduction
Nuclear Safety Policy
Applicable Codes and Standards Criteria
Classification of Codes and Standards
PNRA Regulations and Guides
USNRC Regulations and Guides
Conclusion
Nuclear Power & Fuel Cycle Programme
KANUPP
Operation start
1972
First local fuel
bundle loaded
in KANUPP
--1976-- 1980
C-1 Operation Start
Also DGRE Project
325 MWe
2000
NPP & Fuel
Supply Contracts
Signed
1991
C-1 PWR
from China
Contract
Signed for C-2
2004
C-2 PWR
from
China
2007 2011
C-2 operation &
connected to grid
325 MWe
2013
Energy Plan to
8,800 MWe
NPPs by 2030
K 2/3 Inaugurated
(Gen-III PWRs)
2 x 1100 MW
2013
Revised Energy
Plan for 40,000 MW
NPPs by 2050
2 x 340MW
C-3/4 operation &
connected to
2016-17 2021-22
K-2/3 operation &
connected to grid
Production
Start of NPFC?
1. Introduction
* Tentative Plan
Plant Size
(MWe)
Plant Type Construction
Starts
Operation
Year
Cumulative
Capacity
K-1 125 PHWR 1966 1972 100
C-1 325 PWR 1992 2000 425
C-2 340 PWR 2004 2011 765
C-3 340 PWR 2010 Oct. 2016 1105
C-4 340 PWR 2011 2017 1445
K-2 1100 APWR 2014 2021 2545
K-3 1100 APWR 2015 2022 3645
P-1 to
P-4*
(1100 or
1400)
APWR ----- ------ 9000 MWe
by 2030
Nuclear Power Programme
1. Introduction
Introduction
“Nuclear Fuel Cycle” means all the operation associated
with the production of fuel for nuclear energy, including:
Exploration and Mining
Processing & Conversion of Uranium or Thorium ores
Enrichment of Uranium
Fabrication of nuclear fuel
Operation of nuclear reactor (including research reactor)
Storage and/or Reprocessing of spent fuel
Waste management activities (including decommissioning)
Pakistan has an “open” uranium fuel cycle (no reprocessing) for NPPs
Pakistan Nuclear Regulatory Authority (PNRA) is responsible
for licensing, safety and security of all civil nuclear facilities.
PAEC is determined to follow the principle of Safety First &
Quality First during all stages from siting to decommissioning
of Nuclear power and fuel cycle facilities
Safety requirement are consistent with international safety
standards, however, continuous improvements are being
pursued for enhancing safety of the nuclear industry
Nuclear Safety Policy
Applicable Codes and Standards Criteria
All nuclear installations, for the purposes of siting, design, construction,
commissioning, operation and decommissioning shall conform to the
existing PNRA regulations
In areas where the PNRA regulations are not available, relevant latest US
NRC regulations shall be applicable. Alternately, the licensee may chose
to follow the latest revisions of the applicable IAEA Safety Standards.
In case, the nuclear safety standards of another country (China) are
proposed to be followed, the applicant/licensee shall demonstrate to
the entire satisfaction of the Authority that the standards, proposed to
be followed, offer the same or better standards of safety, security,
quality and reliability than would have been offered by the nuclear
safety and security standards mentioned above at (a) and (b).
Classification of Codes and Standards
LAW PNRA Ordinance 2001
PNRA Regulations (PAK/909, PAK/910, PAK/911 etc.)
USNRC Codes and Regulations
IAEA Safety Codes and Standards Regulations
US NRC / IAEA Safety Guides, NUREG etc. Guides
Standards International Standards and Recommendations
IAEA, ASME, ASTM, IEEE, ISO, ICRP, ANS, ANSI etc.
Other Documents WASH, IAEA TECDOCs, etc
Mandatory
“Shall”
Recommended
“Should”
Voluntary
“May”
Rules Source/Document Status
PNRA Regulations and Guides
PAK No. Applicable PNRA Regulation
PAK/900 Regulations on Licensing Fee by Pakistan Nuclear Regulatory
Authority
PAK/904 Regulations on Radiation Protection
PAK/909 Rev.1 Regulations for Licensing of Nuclear Installation(s) in Pakistan
PAK/910 Regulations on the Safety of Nuclear Installations – Site
Evaluation
PAK/914 Regulations on Management of a Nuclear or Radiological
Emergency
PAK/915 Regulations on Radioactive Waste Management
PAK/916 Regulations on the Safe Transport of Radioactive Material
RG No. Applicable PNRA Regulatory Guides
RG-916.01 Transport of Radioactive Material by Road in Pakistan.
USNRC Regulations and Guides
Reg. No. Applicable USNRC Regulation
10 CFR Part 40 Domestic licensing of Source Material
10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities
10 CFR Part 70 Domestic licensing of special nuclear material (NFC)
10 CFR Part 73 Physical protection of plants and materials (NFC)
10 CFR Part 74 Material control and accounting of special nuclear material (NFC)
10 CFR Part 76 Certification of gaseous diffusion plants (Enrichment plant)
10 CFR App.E to Part 50
Emergency Planning & Preparedness for Production/Utilization Facilities
RG- No. Applicable USNRC Regulatory Guides /Other Documents
R.G 3.25 Standard Format & Content of SAR for Uranium Enrichment Facilities
R.G 3.39 Standard Format and Content of License Applications for Plutonium Processing and Fuel Fabrication Plants
R.G 3.40 Design Basis Floods for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants
R.G 3.67 Standard Format & Content for Emergency Plan for NFC & Materials Facilities
R.G 3.71 Nuclear Criticality Safety Standards for Fuels and Material Facilities
R.G 4.9 Preparation of Environmental Reports for Uranium Enrichment Facilities
NUREG-1520 SRP for the Review of a License Application for a Fuel Cycle Facility
IAEA Regulations and Guides
REQ. No. Applicable IAEA Requirements
NS-R-3 (Rev. 1) Site Evaluation for Nuclear Installations
NS-R-5 (Rev. 1) Safety of Nuclear Fuel Cycle Facilities
GSR Part 3 Radiation Protection and Safety of Radiation Sources: Int'ernational Basic Safety Standards
GSR Part 4 (Rev. 1) Safety Assessment for Facilities and Activities
GSR Part 5 Predisposal Management of Radioactive Waste
GSR Part 7 Preparedness and Response for a Nuclear or Radiological Emergency
Guide No. Applicable IAEA Guides
SSG-12 Licensing Process for Nuclear Installations
SSG-18 Meteorological and Hydrological Hazards in Site Evaluation for Nuclear
Installations
SSG-27 Criticality Safety in the Handling of Fissile Material
SSG-35 Site Survey and Site Selection for Nuclear Installations
SSG-5 Safety of Conversion Facilities and Uranium Enrichment Facilities
SSG-6 Safety of Uranium Fuel Fabrication Facilities
SSG-9 Seismic Hazards in Site Evaluation for Nuclear Installations
GSG-2 Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency
GS-G-2.1 Arrangements for Preparedness for a Nuclear or Radiological Emergency
Ch. 1: General Information (facility, process, site)
Ch. 2: Organization and Administration (policies, procedures and
qualifications of key management positions)
Ch. 3: Integrated Safety Analysis (identifies potential accident
sequences, prevention & mitigation through design,
management)
Ch. 4: Radiation Protection (methods for radiation protection and
their estimation of occupational radiation exposures)
Ch. 5: Nuclear Criticality Safety (criticality accidents related to
storage, handling, and processing of licensed materials)
Ch. 6: Chemical Process Safety (chemical hazards related to
storage, handling, and processing of licensed materials)
Safety Analysis Report- Format and Contents
Ch. 7: Fire Safety (program development & implementation)
Ch. 8: Emergency Management (protection plan)
Ch. 9: Environmental Protection (measures for protection)
Ch.10: Decommissioning (as per safety requirements & principles)
Ch.11: Management Measures (provide assurance for safety function
availability to prevent accidents & mitigate consequences)
Ch.12: Material Control and Accounting (to detect and protect
against the loss, theft, or diversion of special nuclear material)
Ch.13: Physical Protection (so that nuclear materials do not cause an
unreasonable risk to the public health and safety)
Safety Analysis Report- Format and Contents
Post-Fukushima Safety Reassessment
Focus on external events, severe accident and emergency preparedness
1. Adequacy of reviewed external events
2. Plan against flooding and response capabilities
3. Plan against earthquake and response capabilities
4. Effectiveness of quality assurance program
5. Adequacy of Fire protection system
6. Robustness of the plant against overlapping extreme natural events
7. Robustness of the plant design (defense in depth) in case of SBO
8. Prevention & mitigation of severe accidents and reliability assessment
9. Public information and communication (Perception maker)
10. Effective environment monitoring & emergency response systems
11. Other possible weaknesses (population/industrial growth near Plant)
PNPFC Project
S. No. Project Feed Material Product
2.
Fuel
Fabrication
Plant
UO2 powder,
Zr-4, SS &
inconel
Fuel Assembly (FA) and Associated Core
Components (ACCs) for NPPs
1.
Chemical
Processing
Plant
U3O8, Zr sand,
UF6 (E/D) UF6(N) gas, UO2(E) powder, Zr-4 Ingots
3. Seamless
Tube Plant Zr-4 & SS ingots Zr-4 / SS tubes, rods etc.
4.
Fuel
Testing
Project
Fuel
Components /
Specimens
R&D Infrastructure for Testing /
Qualification of Fuel (Mechanical and
Thermal Hydraulic.)
5.
Fuel
enrichmen
t Plant
UF6 (N) gas UF6 Gas (E)
Objective: Production of PWR Fuel for CNPPs (C1-C4)
Near-term Future Tasks
Installation of Meteorological Tower and Ground Station
Site Studies(Demography, meteorology, external hazard, geo-technical and hydrological studies)
NOCs
Background Radiation Analysis
Data Collection
Field Surveys
Site Evaluation Report Preparation
Environmental Impact Assessment Report (EIAR) Preparation
QAP for Siting
PSAR Preparation
Emergency Preparedness Plans etc.
1. Mining and Milling
2. Refining and Conversion
3. Enrichment
4. Fuel Fabrication (UOX)
5. Fuel Transportation (Fresh, other material)
6. Spent Fuel Storage
7. SNF Reprocessing Incl. Recycled Material Storage;
8. Fabrication of Recycled Nuclear Fuels Material
9. Radioactive Waste Management (Processing/Storage/Disposal
10. Decommissioning Of NFCF
Suggested Areas for INPRO Updating
Latest revision of safety standards should be used as reference
Quality Assurance &Quality Control aspects may also be considered
Enrichment may be separated from Refining & Conversion
In the light of Fukushima accidents experience safety reassessment
aspects may also be considered
Pakistan is committed to develop safety culture for its nuclear facilities
Capacity building of safety experts / human resources with IAEA
support is essential to continuously build strong safety culture
Recommendations