fanr-nsd-enec-rpt-00311-2014

PART 1 - INSPECTION SUMMARY
FEDERAL AUTHORITY FOR
NUCLEAR REGULATION
NUCLEAR FACILITY INSPECTION REPORT
(FANR-NSD-ENEC-RPT-00311-2014)
LICENSEE/FACILITY
REPORT NUMBER:
ENEC/Barakah NPP
FANR-NSD-ENEC-RPT-00311-2014
LOCATION: Barakah NPP, Western
Region, Abu Dhabi
LICENCE NUMBER(S):
FANR/NF/2012/001; FANR/NF/2010/001; 002A
DATE(S) OF INSPECTION:
9-11/06/2014 – 23-25/06/2014
LICENSEE/PRIME CONTRACTOR REPRESENTATIVES:
Jassim Dawood (ENEC); James Freel (ENEC)
FANR INSPECTION TEAM:
Mark Tyrer, Ramakanta Mishra, Kirk Redwine, Khalid al Naqbi, Saud bin Khadim, Denis Paris
FACILITY STATUS:
Regulated activities under Licenses:
FANR/NF/2012/001; FANR/NF/2010/001;
002A
MAJOR LICENSEE ACTIVITIES THAT OCCURRED
DURING INSPECTION:
Manufacturing and Construction for Barakah 1&2 NPP
INSPECTION SCOPE:
The scope of this inspection included assessment of the Licensee’s Management and Quality Assurance
Systems related to: Handling shipping and storage; receiving inspection; preservation and maintenance;
Quality Verification Document (QVD) all for Steam Generators (SG) for Unit 1; Preservation and
maintenance of Reactor Vessel for Unit 1; ENEC’s Construction Inspection & Test Plan (CITP) status;
Containment Liner Plate (CLP) manufacture and installation, and follow-up on previous inspection findings.
DOCUMENTS APPLICABLE TO THE INSPECTION:
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Federal Law by Decree No. 6 of 2009
•
FANR/NF/2010/001;002A Licence Applications and FANR licence conditions
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FANR/NF/2012/001 Construction Licence and Licence Conditions
•
FANR-REG-01 Regulation for Management Systems for Nuclear Facilities
•
FANR-REG-03 Regulation for Design of Nuclear Power Plants
•
FANR-REG-06 Regulation for Application for a Licence to Construct a Nuclear Facility
•
FANR RG-002 Application of Management Systems for Nuclear Facilities
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PART 1 - INSPECTION SUMMARY
FEDERAL AUTHORITY FOR
NUCLEAR REGULATION
NUCLEAR FACILITY INSPECTION REPORT
(FANR-NSD-ENEC-RPT-00311-2014)
REPORT SUMMARY
The inspection covered a review of selected site activities to verify adherence to ENEC’s Management
System as described in its Management System Manual (PG-MAN-000-01 Rev 2); ENEC’s Quality
Assurance Programme described in its Quality Assurance Manual (QA-MAN-111-01, Rev 4); KEPCO’s
Quality Assurance Programme described in KEPCO Quality Assurance Manual (KEPCO QAM, Rev 7) and
HSJV’s Quality Assurance Manual (HSJV QAM-001, Rev 9). The selection of ongoing site activities
included handling shipping and storage; receiving inspection; preservation and maintenance; Quality
Verification Document (QVD) all for Steam Generators (SG) for Unit 1; Preservation and maintenance of
Reactor Vessel for Unit 1; ENEC’s Construction Inspection & Test Plan (CITP) status; Containment Liner
Plate (CLP) manufacture and installation FANR inspectors also followed up on previous inspection findings.
Inspectors reviewed applicable relevant sections of the ENEC & KEPCO/HSJV Quality Assurance Manuals,
the QA Program implementing procedures, Construction Package Specification, and associated documents
and records against the applicable Requirements in ASME NQA-1, 1994 (1995 Addenda), applicable
ASME/KEPIC construction Codes and FANR-REG-01, Regulation for Management Systems for Nuclear
Facilities. Inspectors reviewed site work plan procedures/quality control instructions (WPP/QCI), inspection
and test plans and associated records for the ongoing site activities covered by this inspection. Specifically
Inspectors reviewed the Quality Verification Documents (QVD) for Unit 1 steam generators on a sample
basis. Inspectors interviewed members of ENEC, KEPCO, HSJV and Doosan management and staff
responsible for the implementation of relevant Quality Assurance Programme elements in site activities.
FANR inspectors identified six findings, as follows:
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Failure to document the results of an inspection on the installation of the Unit 2 containment building
floor liner plate.
The as-built drawings for the Unit 1 steam generators are not included in QVD as part of the owner
lifetime records.
Ultrasonic test report of a steam generator weld joint does not provide location and details of
recorded indication of potential defect.
The support stools and spreader beams used in the transport and handling of the steam generators
have not been designed, manufactured and inspected in accordance with code requirements.
The non-conforming condition associated with the pressure gauges on the steam generator inert gas
system utilized for preservation was not correctly identified.
Failure to comply with the manufacturer’s specified requirements regarding preservation of the Unit 1
Reactor Vessel.
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