Spanish Approach to Large Decommissioning Projects

2011 ◽  
Author(s):  
Juan Luis Santiago ◽  
Alejandro Rodri´guez
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Research ◽  
Lessons Learned ◽  
Research Centre ◽  
Nuclear Facilities ◽  
Material Management ◽  
Site Remediation ◽  
Key Aspects

The Spanish experience related to the decommissioning of nuclear facilities includes the decommissioning of the Vandello´s I Nuclear Power Plant, the decommissioning of the CIEMAT Nuclear Research Centre and the decommissioning of the Jose´ Cabrera Nuclear Power Plant. This paper reviews the key aspects of these projects and describes the lessons learned related to preparatory activities, auxiliary facilities, decommissioning technologies, material management and site remediation and release.

Update on Jose´ Cabrera NPP Decommissioning

2011 ◽  
Author(s):  
Nieves Marti´n ◽  
Manuel Rodri´guez
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Steam Generator ◽  
Nuclear Power ◽  
Storage Facility ◽  
Spent Fuel ◽  
Nuclear Facilities ◽  
Material Management ◽  
Primary Loop ◽  
Dry Storage

ENRESA is the National Spanish Agency responsible of the dismantling of Nuclear Facilities, previous Transfer of ownership of the facility from the Utility to ENRESA. On April 30th 2006, Jose´ Cabrera Nuclear Power Plant (Fig. 1) was definitively shutdown, and two years later, on April 30th 2008, ENRESA requested the transfer of the ownership of the Plant from the Ministry along with the corresponding authorization for performance of the Dismantling and Decommissioning Plan. On February 1st 2010, ENRESA was authorized to initiate the dismantling of Jose´ Cabrera NPP, once the spent fuel has been stored on-site at a dry storage facility (ISFSI). Currently, preparatory activities are underway, including the modification of systems and auxiliary facilities for waste and material management. Main challenges of the project include the removal of major components (vessel, steam generator, pressurizer, main pump and primary loop), and the use of large containers (CE-2b) to reduce segmentation of activated parts.

Research of Screening and Grading Method of Ageing Sensitive Objectives in Nuclear Power Plant

2014 ◽  
Vol 543-547 ◽  
pp. 858-861
Author(s):  
Xiao Tian Liu ◽  
Yong Wang ◽  
Shao Rui Niu ◽  
Yan Zhao Zhang ◽  
Zhen Hao Shi ◽  
...  
Keyword(s):  
Fuzzy Logic ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Lessons Learned ◽  
Nonlinear Coupling ◽  
Highly Nonlinear ◽  
Ageing Management ◽  
First Time

This first step of ageing management in nuclear power plant is to determine the objectives and their priorities. The characteristics of the objectives are complex and highly nonlinear coupling. A fuzzy logic based screening and grading method have been developed in this research for the first time which combined the genetic ageing lessons learned and field expert experience to resolve the problem. The method have been approved of highly applicability and applied to ageing management in multiple nuclear power plants.

Use of Shear Lugs for Anchorage to Concrete

2009 ◽  
Author(s):  
Peter J. Carrato ◽  
Martin Reifschneider
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Design Method ◽  
American Concrete Institute ◽  
Significant Activity ◽  
Lateral Loads ◽  
Nuclear Facilities ◽  
Shear Loads ◽  
Full Scale Tests

Anchoring structures, systems and components to concrete is a significant activity in the design and construction of a nuclear power plant. Early in this decade the Concrete Capacity Design method (CCD) was adopted by the American Concrete Institute (ACI) for use in the structural design for both commercial and nuclear facilities. This design method and associated qualification tests brings new challenges to designing efficient means for anchoring to concrete structures. Although the CCD method provides guidance on many aspects of concrete anchorage there are a few areas, pertinent to nuclear power plant construction, that are not covered or require significant interpretation of the most recent codes. This paper will focus on the design of shear lugs used to resist significant lateral loads. Results from laboratory tests of shear lugs are presented. These full scale tests considered the interaction of tension and shear loads on the performance of shear lug assemblies. Recommendations for the efficient use of shear lugs are provided.

Accident at Fukushima Dai-Ichi Nuclear Power Plant: Lessons Learned for the Czech Republic

2014 ◽  
Author(s):  
Ladislav Vesely ◽  
Vaclav Dostal
Keyword(s):  
Czech Republic ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Human Performance ◽  
Lessons Learned ◽  
Injection System ◽  
Human Errors ◽  
The Czech Republic ◽  
Main Error

Accident at Fukushima Dai-Ichi nuclear power plant significantly affected the nuclear industry at time when everybody was expecting the so called nuclear renaissance. There is no question that the accident has at least slowed it down. Research into this accident is taking place all over the world. In this paper we present the findings of research on Fukushima nuclear power plant accident in relation to the Czech Republic. The paper focuses on the analysis of human performance during the accident. Lessons learned from the accident and main human errors are presented. First the brief factors affecting the human performance are discussed. They are followed by the short description of activities on units 1–3. The key human errors in the accident mitigation are then identified. On unit 1 the main error is wrong understanding and operation of isolation condenser. On unit 2 the main errors were unsuccessful depressurization with subsequent delay of coolant injection. On unit 3 the main error is the shutdown of high pressure cooling injection system without first confirming that different means of cooling are available. These errors lead to fuel damage. On unit 1 the fuel damage was probably impossible to prevent, however on unit 2 and 3 it could be probably prevented. The lessons learned for the Czech Republic were presented. They can be summarizes as follows: be sure that plant personnel can and knows how to monitor and operate the crucial plant components, be sure that the procedures on how to fulfill the critical safety functions are available in the symptomatic manner for situations when there is no power available at the plant, train personnel for these situations and have sufficient human resource available for these situations.

Technical Workforce Education and Training Program at Abu Dhabi Polytechnic: Integration of Academia and Industry Requirements

2018 ◽  
Author(s):  
Anthony Hechanova
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Training Program ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Education And Training ◽  
Lessons Learned ◽  
Abu Dhabi ◽  
Pressurized Water ◽  
And Training

The United Arab Emirates (UAE) is a developing affluent nation. The leaders of the UAE announced the pursuit of peaceful nuclear power in 2008 and by the end of the following year established its Nuclear Energy Program Implementing Organization (the Emirates Nuclear Energy Corporation (ENEC)), Federal Authority for Nuclear Regulation (FANR), and ordered four APR-1400 pressurized water reactors from the Korean Electric Power Company (KEPCO). Nuclear Engineering programs were initiated soon afterwards at Khalifa University for graduate students and the University of Sharjah for undergraduate students. The technical workforce including nuclear power plant local operators and chemistry and radiation protection personnel was established by ENEC and the Institute of Applied Technology as an inaugural program of Abu Dhabi Polytechnic (AD Poly) in 2011. This paper describes the development of the dual education and training program at AD Poly, the experience of the initial cohorts who conducted their training at the APR-1400 units at the Shin Kori Nuclear Power Plant in Korea, and the current program between the AD Poly Abu Dhabi campus and the new Barakah Nuclear Power Plant based on lessons learned from the earlier years.

Concept for the Guarantee of the Integrity of Bolted Flanged Connections in a German Nuclear Power Plant

2008 ◽  
Author(s):  
Manfred Schaaf ◽  
Friedrich Schoeckle ◽  
Jaroslav Bartonicek
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Data Base ◽  
Nuclear Power ◽  
Test Laboratory ◽  
Third Party ◽  
Nuclear Facilities ◽  
Systematic Treatment ◽  
Bolted Flange ◽  
Test Loading

In nuclear facilities in Germany a systematic treatment of all sealing connections which are opened during the annual shutdowns is performed since several years. Special attention is paid to a design which meets specifications of the bolted flange connections (BFC’s). Apart from the use of suitable and certified materials this includes also the calculation of the required torques in accordance to the present rules. For the calculation procedure the nuclear code KTA 3211.2 (draft 2003) is applied which allows a tightness proof of the BFC, besides a stress analysis. For this calculation, experimentally achieved gasket characteristics according to DIN 28090-1 are required, which are either supplied by the gasket manufacturers or determined in the amtec test laboratory. The geometry and material data of each BFC are stored in a special data base. In addition, the data of the operating state as well as the design and test loading cases are included in the data base, so that all inputs for a later calculation are available. The results of the calculation which must be checked and approved by an expert third-party are stored in the flange data base, too (assembly state settings of each flange connection). On this base individual flange data sheets can be provided to the flange fitter teams that include all necessary information for assembly of each BFC (bolts, nuts, gasket, geometry and material specifications, lubricant, etc.).

Lifting Operation Safety Management in AP1000 Nuclear Plant Project

2013 ◽  
Author(s):  
Xiaogang He ◽  
Shell Shortes
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Management Practices ◽  
Safety Management ◽  
Lessons Learned ◽  
Plant Design ◽  
Modular Construction ◽  
Increased Risk ◽  
Culture Development

As a third-generation nuclear power plant design, construction of the Westinghouse AP1000 incorporates the characteristics of modular construction and the “Open-Top” lifting method, which results in many kinds of lifting operations, whose potential failure creates increased risk to key equipment and construction personnel. Lifting by its very nature is high risk. Based on traditional safety management practices utilized at the project, lift operation characteristics were analyzed, and procedures and processes developed to manage the risk. These developed aspects included: lifting operation procedures; a construction scheme review/approval process; work planning/risk mitigation; equipment inspections; personnel certification requirements; training; crew management; special inspections; lessons learned utilization; discipline management; emergency management; and safety culture development. The authors believe that the safety management approaches discussed in this paper can provide guidance in conducting safe lift operations in other nuclear power plant projects.

Sign in / Sign up

Export Citation Format

Share Document