Framtome Magazin 4/02 - AREVA
Framtome Magazin 4/02 - AREVA
Framtome Magazin 4/02 - AREVA
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Advanced Nuclear Power<br />
T H E M A G A Z I N E O F F R A M A T O M E A N P<br />
N O 4 May 20<strong>02</strong><br />
FOCUS<br />
Nuclear<br />
Components:<br />
Making<br />
the Right<br />
Decision<br />
OTHER<br />
HIGHLIGHTS<br />
>> Digital Turbine I&C<br />
Improves Plant<br />
Availability<br />
>> HTP X5 Fuel<br />
Assemblies for PWR<br />
Plants: Advanced<br />
Economic and Reliable<br />
Design<br />
>> Choose the Leader For<br />
All Your RV Head Needs<br />
>> Jeumont SA, Highest Quality<br />
From a World Leader in<br />
Component Manufacturing
The Future for Nuclear<br />
Component Manufacturing<br />
After having focused on the Projects & Engineering, Nuclear Services, and Nuclear<br />
Fuel business groups in previous issues, this fourth edition of Advanced Nuclear Power<br />
concentrates on the role of and challenges facing Framatome ANP’s Mechanical<br />
Equipment business group.<br />
This business group is made up of two French entities; the Chalon Saint Marcel<br />
plant that fabricates only nuclear heavy components, and Jeumont SA, a wholly-owned<br />
Framatome ANP subsidiary, that specializes in reactor coolant pumps and<br />
motors and control rod drive mechanisms. With over 272 steam generators,<br />
113 reactor vessels, 68 pressurizers, 220 reactor coolant pump motors and<br />
4,400 control rod drive mechanisms to their credit, these two entities clearly<br />
position Framatome ANP as a leading global nuclear component manufacturer.<br />
After a long period of new reactor manufacturing, the market has entered a phase<br />
of plant service life extension and component replacement. Our mechanical engineering<br />
market – previously dominated by EDF investments – has opened up and become more<br />
competitive. The US, in particular, has a high potential for replacement components<br />
over the next ten years due to aging plants and plant life extensions. The nuclear<br />
renaissance, expected in the future, will create renewed demand for heavy components.<br />
Customers today, due to market deregulation and a more competitive environment,<br />
demand new types of contracts with their suppliers; contracts that are financially<br />
attractive, simpler and more comprehensive. Clients increasingly are interested in all-<br />
inclusive service packages covering supply of replacement components, the replacement<br />
operation itself and the associated engineering and licensing studies. Framatome ANP,<br />
with outstanding manufacturing capabilities, engineering and licensing, installation and,<br />
equally important, the follow-on service and maintenance, can meet these requirements.<br />
Joël Pijselman<br />
Senior Executive Vice-President<br />
C O
N T E N T S<br />
10<br />
FOCUS<br />
Nuclear<br />
Components:<br />
Making the<br />
Right Decision<br />
4Projects & Engineering<br />
4 Digital Turbine I&C Improves Plant Availability<br />
5 Kozloduy 3 and 4: Assessing Remaining Service Life of Systems,<br />
Components and Structures<br />
8 Mechanical<br />
Equipment<br />
8 Jeumont SA, Highest<br />
Quality From a World<br />
Leader in Component<br />
Manufacturing<br />
20<br />
Nuke Notes<br />
6 Nuclear Fuel<br />
6 HTP X5 Fuel Assemblies for<br />
PWR Plants: Advanced Economic<br />
and Reliable Design<br />
14 Mark-B12 Fuel: A Fuel for<br />
All Seasons<br />
15<br />
Nuclear Services<br />
15 Framatome ANP Responds<br />
to Emergency Scope<br />
16 Choose the Leader for All<br />
Your RV Head Needs<br />
18 COMBO: A New System for<br />
Continuous Measurement of<br />
Boron Concentration<br />
19 Oskarshamn 1: New Fuel<br />
Pool Connections Installed<br />
During Plant Operation<br />
>> Framatome ANP Now Wears <strong>AREVA</strong> Group Colors<br />
As you probably noticed, Framatome ANP – an <strong>AREVA</strong> and Siemens<br />
company – has a new logo. It is now in the form of a red stylized “A”<br />
that is the <strong>AREVA</strong> logo. The “A” symbol denotes the common identity of<br />
all the <strong>AREVA</strong> Group companies and reinforces Framatome ANP’s role<br />
in the creation of the new world leader in nuclear power.
Projects & Engineering<br />
>><br />
Example:<br />
Overspeed Protection<br />
Digital Turbine I&C<br />
Improves Plant Availability<br />
Increasing use is<br />
now being made of<br />
Framatome ANP’s digital<br />
instrumentation and<br />
control (I&C) platforms,<br />
TELEPERM XS and<br />
TELEPERM XP, for<br />
upgrading I&C equipment<br />
provided for turbine<br />
protection and control.<br />
Testing TELEPERM XS turbine<br />
control equipment (2-channel<br />
configuration)<br />
The new turbine I&C equipment<br />
reduces the number of high-maintenance<br />
hydraulic components. Turbine speed<br />
is monitored by three channels and<br />
the emergency stop valve is actuated<br />
by a 2-out-of-3 logic. The channels are<br />
automatically functionally tested at<br />
cyclical intervals, ensuring that faults<br />
are detected in a timely manner.<br />
The most recent examples include<br />
the replacement of the turbine<br />
control system at Biblis, Units A and<br />
B (Germany) and at Oskarshamn 3<br />
(Sweden). In addition, replacement of<br />
the turbine protection equipment<br />
at Biblis B, Brunsbüttel, Philippsburg 1<br />
and Grafenrheinfeld (all in Germany),<br />
Gösgen (Switzerland) and Forsmark 3<br />
(Sweden) were performed by Framatome<br />
ANP. Other German nuclear power<br />
plants as well as a plant in the US<br />
have expressed interest in using the<br />
TELEPERMTM XS safety I&C equipment<br />
and TELEPERM XP process<br />
control system at their turbine generator<br />
sets.<br />
The new system-wide implemented<br />
multi-channel configuration in<br />
conjunction with replacement of<br />
hydraulic components (i.e. replacing<br />
the hydraulic turbine-trip device<br />
with a turbine-trip block with three<br />
integrated solenoid valves) has been<br />
proven to increase the availability<br />
of the turbine generator set and thus of<br />
the plant as a whole. In addition,<br />
a multi-channel configuration is<br />
provided for the I&C equipment and<br />
mechanical components for turbine<br />
control functions.<br />
Test via turbine<br />
test equipment<br />
For turbine applications,<br />
TELEPERM XS and TELEPERM XP<br />
not only provide the necessary multichannel<br />
capability (for 2-, 3- or 4channel<br />
configurations), but also meet<br />
the requirements essential for efficient<br />
turbine control, such as fast response,<br />
good dynamic behavior and highprecision<br />
control. In the case of<br />
TELEPERM XS, for example, this is<br />
due to the fact that the I&C platform<br />
originally was designed to meet the<br />
requirements associated with reactor<br />
protection and control, such as multichannel<br />
capability, seismic resistance<br />
and electromagnetic compatibility.<br />
Fulfillment of these requirements by<br />
the TELEPERM XS platform has<br />
been verified through qualification to<br />
the standards of the German Nuclear<br />
Safety Standards Commission (KTA)<br />
as well as generic approval from the US<br />
Nuclear Regulatory Commission for<br />
US-oriented markets. New turbine I&C<br />
systems, employing TELEPERM XS<br />
and TELEPERM XP, profit just<br />
as much from the excellent design<br />
features and capabilities of Framatome<br />
ANP’s digital I&C.
Projects & Engineering<br />
Kozloduy 3 and 4: Assessing<br />
Remaining Service Life of Systems,<br />
Components and Structures<br />
Since deregulation of the<br />
European energy market,<br />
demands that nuclear<br />
power plants should meet<br />
uniform safety standards<br />
are growing louder and<br />
louder. Over the years,<br />
one of the aims of the<br />
Bulgarian VVER plant,<br />
Kozloduy, has been not<br />
only to upgrade individual<br />
features of the plant<br />
pertinent to safety (based<br />
on IAEA recommendations)<br />
but also to generally bring<br />
all plant components,<br />
systems and structures<br />
in line with internationally<br />
recognized safety standards,<br />
essentially creating<br />
a new VVER 440 reactor<br />
design. Because this<br />
approach involved various<br />
exemplary and innovative<br />
efforts, it serves as a<br />
model for pioneering a<br />
new safety philosophy.<br />
Developing an Aging-<br />
Management Program<br />
A custom-tailored aging management<br />
program is an extremely interesting<br />
option in this context as it contributes<br />
towards maintaining plant safety at a<br />
high level over the plant’s entire design<br />
service life and beyond. At the same<br />
time, it also is reasonable to expect<br />
economic advantages resulting from<br />
higher reliability and availability.<br />
With this in mind, a special program<br />
was jointly developed by experts<br />
from Kozloduy and Framatome ANP<br />
and is being implemented by a<br />
consortium formed of Framatome<br />
ANP and the Russian company,<br />
Atomstroyexport. The primary goals of<br />
the program are to:<br />
• perform an independent assessment<br />
of the remaining service life of plant<br />
components, systems and structures<br />
that conforms to international<br />
experts’ acceptance criteria,<br />
• identify the need for further investigations<br />
or analyses in certain cases,<br />
• find solutions for improving safety<br />
that are economical at the time.<br />
Part of a Comprehensive<br />
Backfitting Program<br />
The aging-management program is part<br />
of a comprehensive backfitting project<br />
for Units 3 and 4 of the Kozloduy<br />
plant and comprises three phases:<br />
• In the first phase, the remaining<br />
service life of representative<br />
components, systems and structures<br />
(relevant to safety and availability)<br />
is determined at both plant units,<br />
using state-of-the-art techniques.<br />
• In the second phase, a computerized<br />
system is developed to handle<br />
all relevant component and system<br />
data – both original construction<br />
data and data recorded during plant<br />
operation (e.g. loads and environmental<br />
conditions) – as well as<br />
information obtained from in-service<br />
inspections and replacement activities.<br />
• In the final phase, an aging-management<br />
program is generated to<br />
detect, evaluate and mitigate relevant<br />
aging degradation mechanisms and<br />
to identify locations in the plant<br />
where they are likely to occur.<br />
The 18-month project is scheduled<br />
for completion in June 20<strong>02</strong>. So far,<br />
the customer is very satisfied with<br />
the way the project is progressing and<br />
with the promising results obtained<br />
to date.
Nuclear Fuel<br />
>><br />
HTP X5 Fuel Assemblies for<br />
PWR Plants: Advanced Economic<br />
and Reliable Design<br />
Recent years have<br />
witnessed a continuous<br />
rise in the performance<br />
requirements for nuclear<br />
fuel assemblies: nuclear<br />
plant operators today<br />
want the highest possible<br />
reliability with optimum<br />
fuel utilization and flexible<br />
operation. Framatome<br />
ANP has successfully<br />
achieved these goals with<br />
the development of its<br />
HTP X5 fuel assembly<br />
for PWRs.<br />
Designed for Enrichments<br />
up to 5 wt.% U-235<br />
Optimum fuel utilization and maximum<br />
fuel assembly reliability are key factors<br />
for reducing nuclear fuel cycle costs<br />
and thus enhancing the competitiveness<br />
of nuclear power. The employment<br />
of higher-enriched fuel and high<br />
operational reliability of fuel assemblies<br />
in reactors with demanding power<br />
histories were two of the main objectives<br />
in fuel assembly development.<br />
Framatome ANP’s new fuel assembly,<br />
HTP X5 (High Thermal Performance<br />
eXtended up to 5 wt. %) for PWRs is<br />
designed for enrichments of up to 5 wt. %<br />
U-235 and permits fuel assembly<br />
burnups of around 70 MWd/kgU and<br />
fuel rod burnups of up to 75 MWd/kgU.<br />
Our HTP X5 fuel assembly: Leader in fuel economy and reliability<br />
Comprehensive Experience<br />
in the Use and Management<br />
of HTP Fuel Assemblies<br />
By the end of 2001, 3,340 HTP<br />
fuel assemblies were installed in 22<br />
PWR plants built by various vendors<br />
in Europe, Asia and the US, predominantly<br />
in reactors using 17x17 lattice<br />
fuel assemblies. A maximum fuel<br />
burnup of 56 MWd/kgU was achieved<br />
with these assemblies. Despite the everincreasing<br />
rate of achieved burnup,<br />
the operating performance of these<br />
fuel assemblies has been exceptional.<br />
High Reliability Despite<br />
Continuously Increasing<br />
Discharge Burnups<br />
The continual increase in discharge<br />
burnup is clear testimony to high<br />
reliability. In the last 20 years, the<br />
average discharge burnup of peak<br />
reload batches of PWR fuel assemblies<br />
has risen by more than half to over<br />
50 MWd/kgU. With the advanced<br />
HTP fuel assemblies now already in<br />
use, discharge burnups of 55 MWd/kgU<br />
will be achieved in the near future.<br />
The materials and design of the HTP<br />
fuel assembly have been optimized<br />
such that within two annual cycles,<br />
burnups of some 35 to 40 MWd/kgU<br />
are possible without any operational<br />
limitations.<br />
Over a number of operating<br />
cycles, the superiority of the HTP line<br />
contact fuel rod support has been<br />
proven, even at positions in the reactor<br />
6 Advanced Nuclear Power N O 4 May 20<strong>02</strong>
core in which failed rods were frequently<br />
encountered in assemblies<br />
equipped with traditional spring-anddimple<br />
spacers. No rod failures have<br />
occurred since the HTP fuel assemblies<br />
were installed at these locations.<br />
HTP X5 Characteristics<br />
The term, “HTP,” refers to both a<br />
spacer type and the entire fuel assembly<br />
design, equipped with this spacer<br />
as a main component.<br />
Spacers:<br />
The unique, innovative design of<br />
Zirconium HTP spacers combines fuel<br />
rod support and coolant flow mixing<br />
in a single component. The curved<br />
flow channels increase coolant mixing<br />
and improve thermal-hydraulic<br />
behavior. The line-contact fuel rod<br />
support across four double lines<br />
ensures a large contact area and thus<br />
optimum resistance to grid-to-rod<br />
fretting: No fuel rod damage due to<br />
fretting has been observed over<br />
a period of 15 years. In the HTP X5<br />
fuel assembly, the innovative Inconel<br />
spacer derived from the HTP<br />
spacer design is used at the bottom<br />
spacer position where high loads<br />
are incurred.<br />
Bottom end fitting:<br />
To contain debris and thus prevent<br />
fretting damage to the fuel rods, the<br />
fuel assembly bottom end fittings are<br />
optionally fitted with an integrated<br />
debris filter or with FUELGARD TM .<br />
Cladding tubes:<br />
Increased requirements placed on<br />
advanced reactor operation require<br />
cladding tube materials with excellent<br />
corrosion resistance, low hydrogen<br />
uptake and assured mechanical properties.<br />
Our advanced M5 TM cladding is<br />
designed to fulfill all PWR operational<br />
requirements even under the most<br />
demanding plant conditions<br />
(temperature, void, power history etc.)<br />
up to the maximum burnup one can<br />
achieve with 5 wt. % U-235.<br />
“New Generation<br />
Fuel Assembly”<br />
Framatome ANP conducted extensive<br />
testing and lead design programs<br />
Nuclear Fuel<br />
working closely with its customers,<br />
to enable continuous improvements<br />
in fuel economy and reliability.<br />
Working with customer needs,<br />
Framatome ANP will develop,<br />
through the “New Generation PWR<br />
Fuel Assembly” project, a new PWR<br />
fuel assembly design based on previous<br />
design experience and operational<br />
feedback in the coming years.
Mechanical Equipment<br />
>><br />
Jeumont SA, Highest Quality<br />
From a World Leader in<br />
Component Manufacturing<br />
The strong market<br />
share of Jeumont SA<br />
and its total integration<br />
of design and manufacturing<br />
processes in<br />
its business lines gives<br />
the company a clear<br />
competitive advantage<br />
vis-à-vis operator<br />
availability, reactivity and<br />
quality requirements.<br />
Jeumont, a wholly-owned<br />
Framatome ANP subsidiary, has<br />
more than 220 reactor coolant pumps<br />
and 4,400 control rod drive mechanisms<br />
(CRDM) in operation worldwide.<br />
Although much older than its<br />
parent company – it was created at the<br />
end of the 19th century – Jeumont<br />
has held a Westinghouse license since<br />
the beginning of the 1970s to manufacture<br />
reactor coolant pumps, reactor<br />
coolant pump motors and control rod<br />
drive mechanisms (CRDMs). Its com-<br />
Vertical integration plus many years experience ensures CRDM quality<br />
ponents are providing outstanding<br />
service worldwide in France, the US,<br />
Asia and South Africa. The company<br />
has never ceased striving continuously<br />
to improve the performance and<br />
service life of nuclear power plants<br />
worldwide.<br />
Improved Design Results<br />
in 100 Percent Availability<br />
The vertical integration of all its<br />
industrial processes enhances Jeumont’s<br />
ability to ensure the high quality<br />
and consistency of all its products.<br />
In addition, dedicated workshops for<br />
pumps, motors, CRDMs and shaft<br />
seals ensure that the most experienced<br />
engineers and technicians work<br />
in their area of specialization for the<br />
highest quality product.<br />
Based on specifications drawn up<br />
by Framatome ANP engineering<br />
teams, Jeumont designs, manufactures<br />
and tests complete and coherent reactor<br />
coolant pump sets that optimize<br />
cost effectiveness and time schedules.<br />
8 Advanced Nuclear Power N O 4 May 20<strong>02</strong>
Over the years, many innovations have<br />
resulted in a pump availability rate of<br />
100 percent without replacing main<br />
motor components. Integrated sensors<br />
(to measure vibrations, flow, temperature,<br />
etc.) for in-service monitoring,<br />
and intermediary spool pieces on all<br />
types of pumps facilitate and reduce<br />
maintenance by avoiding motor<br />
removal. A new stator design eliminates<br />
rewind and replacement. Updated<br />
oil pumping systems improve bearing<br />
performance. All these design<br />
improvements help Jeumont pumps<br />
easily withstand more than 4000<br />
startups.<br />
Increased Service Life<br />
of CRDMs Benefits<br />
Plant Operators<br />
After Framatome ANP designs and<br />
validates the use of CRDMs, the<br />
Jeumont facility completes the detailed<br />
manufacturing design and the manufacturing<br />
itself, all on the same site.<br />
Using original basic specifications,<br />
the company significantly improved<br />
the manufactured models, for example<br />
by increasing service life from 2.5<br />
million steps to almost 8 million.<br />
Furthermore, these products require<br />
no maintenance, allowing users to<br />
constantly adapt to the power increases<br />
required by the grid. These design<br />
and operational features enable<br />
operators to run their units with load<br />
follow over a 60-year service life.<br />
The Prestigious “N Stamp”<br />
from ASME<br />
In December 2001, Jeumont was<br />
awarded N and NPT certification by<br />
the American Society of Mechanical<br />
Engineers (ASME). This certification<br />
enables the company to manufacture<br />
reactor coolant pumps and CRDMs<br />
in accordance with third-party<br />
manufacturer specifications<br />
to position Jeumont as the<br />
supplier of choice for reactor<br />
coolant pumps and motors<br />
and CRDMs.<br />
The North American<br />
Market<br />
Jeumont delivered reactor<br />
coolant pump motors<br />
and spare stators and has<br />
performed and continues to<br />
perform upgrading and<br />
maintenance operations at<br />
more than eight US power<br />
plants. The creation of a<br />
hot workshop on the US<br />
Lynchburg (Virginia) site,<br />
similar to Europe’s largest<br />
hot workshop, Somanu<br />
in France, is just one<br />
aspect of the close working<br />
relationship between<br />
Jeumont and Framatome<br />
ANP in the US.
F O C U S<br />
>><br />
Nuclear<br />
Components<br />
Making the Right Decision
Most nuclear plants<br />
throughout the world were<br />
built more than 20 years<br />
ago. It is not unusual<br />
for major components to<br />
begin experiencing age<br />
and corrosion-related<br />
problems. Nuclear plant<br />
executives increasingly<br />
are facing tough decisions<br />
that are complicated by<br />
the prospect, at least in<br />
the US, of extending<br />
their licenses another 20<br />
years. Deregulation is<br />
one factor driving nuclear<br />
power plants to increase<br />
their output, reduce costs<br />
and operate at peak<br />
efficiency. As a result, the<br />
market for replacement<br />
components is growing.<br />
For example, in 2001,<br />
there were approximately<br />
$75 million to $100<br />
million in orders in the US.<br />
Forecasts call for orders<br />
to increase to approximately<br />
$200 million<br />
for the next three years.<br />
Until recently, when normal wear<br />
or corrosion-related problems<br />
surfaced, the decision to repair was<br />
relatively easy. Today, however, these<br />
aging plants are being forced to spend<br />
increasing amounts of time and effort<br />
in analyzing the pros and cons of<br />
repairing or replacing. If repair is performed,<br />
how long will it last? Is it<br />
cost-effective? Over what time period?<br />
If the plant intends to extend its<br />
license another 20 years, what impact<br />
does that decision have on the repair/<br />
replacement equation? If a decision is<br />
made to replace a component, then<br />
the issue becomes managing the<br />
existing component in such a way that<br />
maximum efficiency is maintained<br />
during the time it takes to<br />
F O C U S<br />
Accumulator under construction at the Chalon Saint Marcel facility<br />
manufacture the new component.<br />
Framatome ANP is the premier supplier<br />
in the world who can help plant<br />
management through the entire process:<br />
initial inspection and analysis, evaluation<br />
and cost/risk analysis, engineering<br />
for the actual manufacturing and<br />
installation of a replacement component.<br />
Replacement Often Most<br />
Cost Effective<br />
Components that are particularly susceptible<br />
today are reactor vessel (RV)<br />
heads and steam generators (SG). The<br />
susceptibility of Alloy 600 to water<br />
corrosion causes numerous problems<br />
for these components. In the past, one<br />
solution for SG problems was plugging<br />
tubes or sleeving tubes to restore<br />
their efficiency. However, only so<br />
many tubes can be plugged before<br />
capacity is affected. In addition,<br />
inspection (and repairing) of tubes at<br />
every outage significantly impacts<br />
cost and schedule. Since the original<br />
SGs were installed, improved materials<br />
for tubes have been developed that<br />
are less susceptible to corrosion.<br />
These new developments directly<br />
impact the analysis of the repair<br />
versus replacement equation.<br />
Many plants are opting to<br />
replace major components rather<br />
than continuing to inspect and repair<br />
them because of the overwhelming<br />
positive impact to their operational<br />
budgets, particularly if the plant<br />
intends to file for license renewal.<br />
Two US Plants Opt for<br />
Replacement<br />
Callaway, a US plant owned and<br />
operated by AmerenUE, recently<br />
ordered four steam generators from<br />
Framatome ANP to be delivered<br />
in 2005. When asked why they chose<br />
Framatome ANP, Tim Herrmann,<br />
Superintendent Engineering Steam<br />
Generator Replacement and Project<br />
Manager for SGR, commented,<br />
“Framatome ANP offered an innovative<br />
design that supports our needs<br />
and enhances our plant… We came<br />
to Framatome ANP with one frame<br />
of reference and left with a different<br />
and better solution.”<br />
Callaway’s steam generators<br />
will be manufactured in Framatome<br />
ANP’s Chalon Saint Marcel manufacturing<br />
plant, the foremost reactor<br />
component supplier in the world, with<br />
90 units manufactured and installed.<br />
Advanced Nuclear Power N O 4 May 20<strong>02</strong> 11
F O C U S<br />
Reactor<br />
vessel leaving<br />
Chalon Saint<br />
Marcel for<br />
installation at<br />
Civaux<br />
12 Advanced Nuclear Power N O 4 March 20<strong>02</strong>
Callaway personnel, while visiting<br />
that facility, were impressed with the<br />
attention to detail, the clean room,<br />
and the constant inspection and analysis<br />
during each step of the manufacturing<br />
process. Since Chalon Saint Marcel<br />
has established a web server for communicating<br />
design specifications, engineering<br />
documentation and manufacturing<br />
progress, customers can access<br />
information on their particular component<br />
in real time.<br />
In 1999, the Chalon Saint Marcel<br />
plant delivered a reactor pressure vessel<br />
as well as three steam generators and a<br />
pressurizer to the Ling Ao Unit 1 station<br />
in China and another to the Ling<br />
Ao Unit 2 station in 2000. They completed<br />
construction of the two Civaux<br />
1450 MWe N4 units in 1997 and<br />
1999. They currently are fabricating<br />
two replacement steam generators for<br />
Prairie Island that will be delivered in<br />
2004. Of the 28 new LWRs (non VVER)<br />
that have been started up since 1990,<br />
13 were built by Framatome ANP.<br />
Chalon Saint Marcel<br />
Manufactures Only Nuclear<br />
Components<br />
Established in 1975, the Chalon Saint<br />
Marcel facility has fabricated over 400<br />
PWR heavy components, including<br />
reactor pressure vessels and internals,<br />
steam generators (272), pressurizers<br />
(68), reactor vessel closure heads<br />
(113), accumulators, piping for reactor<br />
coolant systems and component support<br />
structures. Due to the facility’s<br />
flexible design, the demands of multiple<br />
customers, i.e. multiple types of<br />
components, can be manufactured<br />
simultaneously.<br />
Because the facility has continuously<br />
manufactured only nuclear components,<br />
all R&D efforts focus on<br />
improving the technology, welding<br />
techniques, and materials used in the<br />
components. In particular, the<br />
Technical Center specializes in welding<br />
and related technologies as well as<br />
metallurgy and surface treatment.<br />
Their non-destructive examination<br />
(NDE) innovations and technologies<br />
ensure minutely detailed inspection of<br />
all component parts and welds. The<br />
Center also analyses corrosion chemistry<br />
and develops new materials to<br />
minimize its effects.<br />
Design automation, engineering<br />
and manufacturing are the key to the<br />
Chalon Saint Marcel’s reputation for<br />
F O C U S<br />
quality and service. Deep-drilling<br />
machines for tubesheets, multi-spindle<br />
drilling machines for tube support<br />
plates and automated broaching<br />
machines ensure uniformity and<br />
consistency. Controlled access and<br />
pressurized clean rooms for the tube<br />
installation process (tubing, welding,<br />
hydraulic expansion, etc.) ensure that<br />
no foreign materials are introduced<br />
into the steam generators during the<br />
manufacturing process.<br />
Framatome ANP’s wealth of<br />
worldwide experience in service,<br />
engineering and maintenance helps<br />
customers effectively manage their<br />
aging plants. If replacement components<br />
are required, the premier nuclear<br />
heavy component manufacturing<br />
facility in the world can manufacture<br />
them to the customer’s specification<br />
at a competitive cost, deliver it on<br />
time, and ensure that the installation<br />
requires minimum outage time.<br />
Framatome ANP, through its extensive<br />
experience and expertise, can assist<br />
customers beginning with the decision<br />
analysis process through purchasing,<br />
licensing, manufacturing, installation<br />
and follow-on service for the life<br />
of the component.
Nuclear Fuel<br />
>><br />
Mark-B12 Fuel :<br />
A Fuel for All Seasons<br />
Recently, the first batch of<br />
Framatome ANP’s new Mark-B12<br />
fuel assembly design was delivered,<br />
loaded and is now operating at Three<br />
Mile Island. A second batch has been<br />
delivered to Davis-Besse for loading in<br />
their upcoming cycle later this year.<br />
The new design features the<br />
advanced alloy M5TM fuel rod cladding<br />
and guide tubes proven to experience<br />
lower growth and lower corrosion<br />
than previous designs using Zircaloy 4.<br />
M5 guide tubes also are expected<br />
to reduce fuel assembly distortion and<br />
thereby allow smoother insertion of<br />
control rods, a critical factor in plant<br />
operation and shutdown.<br />
“The M5 alloy used in cladding<br />
and structure supports higher burnups,<br />
and longer fuel cycles,” said Dennis<br />
Gottuso, manager of North American<br />
Business and Product Development<br />
for Framatome ANP. “We feel that we<br />
are supporting nuclear power by<br />
developing designs that meet and<br />
exceed our customers’ needs.”<br />
“With the challenging two-year<br />
cycles we are designing for TMI,<br />
we were pushing Zirconium (Zr)-4 to<br />
its limits,” said Bob Jaffa, Senior<br />
Engineer for Exelon Nuclear. “M5<br />
cladding gives us much-needed margin<br />
to corrosion limits and we are optimistic<br />
that the M5 guide tubes and the<br />
Mark-B12 holddown spring will reduce<br />
distortion. Also, the heavier uranium<br />
loading in the Mark-B12 better suits<br />
our cycle design needs. For the long<br />
run, we want to be in position to<br />
have a core loaded with fuel capable<br />
of extended burnups when burnup<br />
extension becomes a reality.”<br />
The Beginning<br />
Years of research and development in<br />
new materials preceded the debut of<br />
the Mark-B12 fuel assemblies. First<br />
“An improved fuel design for B&W reactors with better fuel economy and superior corrosion and debris resistance.”<br />
came the search for an alloy that could<br />
withstand severe operating conditions<br />
that would be required in the future –<br />
a future we now see all too clearly.<br />
Higher neutron fluxes, heat fluxes,<br />
and extreme temperatures are the order<br />
of the day as plants strive to increase<br />
capacity and availability to the grid.<br />
Beginning more than a decade<br />
ago, Framatome ANP and its partner<br />
Cezus, narrowed their alloy search<br />
from 20 to six alloys for continued<br />
research and testing. The M5 alloy<br />
underwent a rigorous development<br />
program that identified and controlled<br />
critical constituent and processing<br />
parameters. The resulting alloy<br />
microstructure is highly stable and<br />
provides the best in-reactor cladding<br />
and structural component performance<br />
of any zirconium alloy tested. The M5<br />
is a ternary Zr-1% Nb-0 alloy that out<br />
performed the other test alloys under<br />
the required, severe conditions such as<br />
high lithium, high power density, high<br />
temperature, and sub-cooled boiling.<br />
In addition, the M5 alloy was<br />
found to be such a reliable product that<br />
Framatome ANP went on to use it<br />
in producing guide tubes for reactors.<br />
The Future: Here at Last<br />
The nuclear power industry is<br />
changing daily, and plant owners and<br />
operators are watching their financial<br />
margins closely, looking to uprate,<br />
run at higher peaking rates, and to<br />
keep plants running longer. Thanks to<br />
the thinner M5 cladding and “fatter”<br />
fuel pellets, the Mark-B12 is able to<br />
“go the distance.”<br />
“The uranium loading for this<br />
fuel was increased 5 percent over previous<br />
designs to support longer operating<br />
cycles and higher burnups. The Mark-<br />
B12 can help reduce batch size for<br />
fuel, and allow plant operators flexi-<br />
bility in operations,” Gottuso said.<br />
“M5, the cladding that helps the Mark-<br />
B12 achieve its high performance is not<br />
only available for B&W-type plants,<br />
but also for Westinghouse, and soon,<br />
Combustion-Engineering plants<br />
as well,” said Gottuso. “Our goal is<br />
to provide the nuclear power industry<br />
with the most advanced fuel that can<br />
not only meet the industry’s needs,<br />
but improve the operability of any<br />
PWR.”
Framatome ANP Responds<br />
to Emergency Scope<br />
In October 2001, during a bobbin<br />
eddy current inspection (ECT) of<br />
steam generator tubing at AmerGen’s<br />
Three Mile Island (TMI), Unit 1,<br />
located in Pennsylvania, wear indications<br />
were discovered in the B generator<br />
on four tubes at the secondary face of<br />
the upper tubesheet. The four tubes<br />
surrounded a tube that previously<br />
was plugged.<br />
Since the wear indications were<br />
significant, the ECT analysts surmised<br />
that the cause might be a severed tube.<br />
Once the plug was removed from the<br />
upper tubesheet, a visual inspection<br />
confirmed that the tube had indeed<br />
severed at the upper tubesheet<br />
secondary face.<br />
To understand the cause,<br />
AmerGen decided to remove tube<br />
samples (tube harvest) so that a<br />
destructive examination could be done<br />
for failure analysis. Framatome ANP<br />
received a call on Friday, October 19,<br />
2001 asking for help. Since this was a<br />
first-of-a-kind (FOAK) effort, a team<br />
was quickly formed and a preliminary<br />
plan was mapped out to accomplish<br />
the tube harvest.<br />
The plan involved removing the<br />
SG secondary manway cover and<br />
elliptical wrapper cover to gain access<br />
and allow removal of tube sections<br />
from the secondary side. Cutting the<br />
sections would take place from the<br />
primary side but retrieval and accountability<br />
of the pieces would be from<br />
the secondary side.<br />
The team developed tooling,<br />
mockups, video and other support<br />
items in 4 days. The site team went<br />
through training in Lynchburg and<br />
the final execution plan was completed<br />
in 3 days. One week after the initial<br />
request, the team deployed to site<br />
to begin equipment staging and<br />
Special remotely operated<br />
tool designed especially for<br />
the TMI tube harvest.<br />
setup, and site training.<br />
Tube section removal work<br />
began on October 28th. The team<br />
encountered stuck studs on the<br />
secondary manways, and the studs on<br />
the elliptical wrapper cover had never<br />
been removed since plant startup.<br />
The team also discovered tube sections<br />
that had swelled considerably larger<br />
than design. Furthermore, the nonharvested<br />
section of the tube had to be<br />
left in a condition suitable for future<br />
operation. The sections removed<br />
were ECT tested as a baseline for the<br />
laboratory destructive exams including<br />
metallurgical evaluation and pressure<br />
testing. The entire process, even with<br />
the stuck studs and swelled tubing,<br />
was completed in two days.<br />
The process removed all of the<br />
planned tube sections except one;<br />
the only section not removed was<br />
a 4" (10 cm) long section of the tube<br />
within the upper tubesheet region.<br />
This section was roll expanded in<br />
place to capture it and prevent it from<br />
becoming a loose part. Based on<br />
subsequent testing and analysis of the<br />
Nuclear Services<br />
Close–up of the clamp on the<br />
special tool to hold the tube<br />
in place during the operation.<br />
other sections removed, it turned<br />
out that removal of this 4" section was<br />
not necessary. Testing and analysis<br />
revealed the cause to be attributed to a<br />
combination of three factors; 1) Tube<br />
expansion from water within the tube,<br />
2) OD intergranular attack (IGA) and<br />
3) Flow-induced vibration from high<br />
cross flow. Identification of the cause<br />
of this failure was key to AmerGen’s<br />
plan for mitigation that allowed for<br />
the plant’s return to power operation.<br />
Rich Freeman, steam generator<br />
program engineer at TMI, commented,<br />
“Framatome did a very good job of<br />
preparing and executing the removal<br />
of these tubing sections from the secondary<br />
side of our generator. Removal<br />
of these sections was important and<br />
helped us to discern the cause of our<br />
tubing degradation.”
Nuclear Services<br />
>><br />
Choose the Leader<br />
for All Your RV Head Needs<br />
Framatome ANP has supplied<br />
more replacement RV heads with<br />
improved design features than<br />
any other manufacturer<br />
Over the last several years, an<br />
increasing number of PWR<br />
plants have experienced stress corrosion<br />
cracking in the area of their control<br />
rod drive mechanism (CRDM) nozzles<br />
and their accompanying welds. The<br />
problem first was discovered in France,<br />
and lately highly susceptible US<br />
plants are being required by the NRC<br />
to perform inspections and make<br />
repairs if problems are found.<br />
Framatome ANP was involved<br />
with this problem since its inception.<br />
As a result, the company has the most<br />
experience and has developed specific<br />
inspection and repair technologies,<br />
tailored to each plant type, to address<br />
the problem. Of the 27 inspections<br />
performed to date in the US,<br />
Framatome ANP completed 24 and<br />
has another seven scheduled for spring<br />
20<strong>02</strong>. This past fall, inspections<br />
were performed on eight RV heads,<br />
representing three different designs:<br />
four Westinghouse plants, three<br />
Babcock & Wilcox plants and one<br />
Combustion Engineering (CE) plant.<br />
Because of this in-depth experience,<br />
Framatome ANP can perform not<br />
only the inspections and repairs,<br />
but also assist customers in analyzing<br />
the factors that must be taken into<br />
account to make sound decisions<br />
about which option, including replacement,<br />
makes the most economical<br />
and operational sense.<br />
16 Advanced Nuclear Power N O 4 May 20<strong>02</strong>
Minimal Dose Inspections<br />
for All Types of Plants<br />
During the fall 2001 outages, different<br />
technologies were used, sometimes<br />
in combination to complete the<br />
inspections. Innovative remote tooling<br />
enabled low-dose bare head visual<br />
and head penetration nozzle ultrasonic<br />
(UT) inspections. Rotating UT,<br />
delivered from under the RV head,<br />
supported nozzle flaw characterization.<br />
In spring 20<strong>02</strong>, the company<br />
will introduce an ultrasonic inspection<br />
technique that verifies the existence of<br />
the leak path forming at the interface<br />
between the outer surface of the<br />
CRDM nozzle and the reactor head<br />
base material adjacent to the nozzle<br />
outer surface. Based on empirical data<br />
taken from Framatome ANP’s database<br />
of 128 nozzle inspections from seven<br />
plants, the leak path UT technique<br />
is equivalent to or better than the<br />
bare head visual inspection performed<br />
to identify leaking nozzles. This<br />
innovation will save dose and time.<br />
Speedy Repairs Reduce<br />
Outage Time<br />
In addition, specialized equipment<br />
was designed to reduce dose levels by<br />
automating the procedures for repairing<br />
CRDM nozzles. In the fall outage<br />
alone, 24 CRDM nozzles and eight<br />
thermocouples were repaired at four<br />
different plants using the remote ID<br />
temperbead repair technique. To maximize<br />
the life of the repair, Framatome<br />
ANP uses a remediating technique<br />
on the weld heat-affected zone.<br />
Using a Midland head mock-up<br />
at Framatome ANP’s testing facility in<br />
Lynchburg also enabled the company<br />
to design specialized tools and techniques<br />
for both inspection and repair<br />
as well as train personnel prior to<br />
deployment. For example, a method<br />
to raise the insulation of the RV<br />
head at one customer’s plant enabled<br />
a bare head inspection and eliminated<br />
the need to perform an underhead<br />
inspection.<br />
Replacement: A Viable<br />
Option For Long-Term<br />
Operations<br />
Companies experiencing the highest<br />
number of flaws are seriously considering<br />
replacing their RV heads. Since<br />
the delivery time for a replacement<br />
RV head is longer than one cycle,<br />
Framatome ANP, working in partnership<br />
with the customer, develops<br />
innovative solutions that reduce lead<br />
time for replacement heads.<br />
Framatome ANP was contracted<br />
to supply three RV head replacements<br />
in the US. These will be fabricated<br />
in the Chalon Saint Marcel plant. This<br />
plant is fully qualified and has never<br />
missed a delivery schedule in over 35<br />
years of continuous manufacturing of<br />
heavy nuclear components. To meet<br />
customer requirements, the facility can<br />
manufacture either single or two-piece<br />
heads and fit up is warranted to mate<br />
with existing plant equipment with<br />
no impact to the reactor vessel flange,<br />
RV stud or CRDM operations. Most<br />
importantly, of the 113 RV heads<br />
manufactured and delivered, none<br />
has experienced crack initiation in the<br />
CRDM J-groove weld. For that reason,<br />
Framatome ANP offers a warranty<br />
on all replacement RV heads.
Nuclear Services<br />
>><br />
COMBO: A New System for<br />
Continuous Measurement of<br />
Boron Concentration<br />
In PWRs, a boric acid solution<br />
is added to the reactor coolant to<br />
control reactivity. As core burnup<br />
increases, the boric acid content<br />
in the coolant is gradually reduced.<br />
Monitoring of the boron concentration<br />
in systems conveying reactor coolant<br />
for purposes of reactivity control is<br />
important for plant safety, particularly<br />
when the plant is in the shutdown<br />
condition and during core loading.<br />
Framatome ANP has developed<br />
a system called COMBO (continuous<br />
measurement of boron concentration)<br />
that is installed on a pipe or vessel,<br />
with no system modifications necessary.<br />
This makes COMBO ideal for backfitting<br />
as well – in all types of PWRs.<br />
On-Line Monitoring<br />
Offers Advantages<br />
Today, it is standard practice to<br />
measure boric acid concentration in<br />
PWR coolant on a non-continuous<br />
basis via chemical analysis (titration),<br />
necessitating extensive laboratory<br />
support. However, continuous monitoring<br />
has a number of advantages:<br />
• On-line monitoring of boron<br />
concentration in the reactor coolant<br />
system and reactor auxiliary systems<br />
enables operating crews to respond<br />
much more rapidly to disturbances,<br />
thereby delivering an important<br />
safety enhancement.<br />
• Plant economy is improved due to<br />
shorter shutdown and startup<br />
times, and to reduced personnel<br />
and material resources.<br />
Positive Operating<br />
Experience Already Gained<br />
in the Field<br />
The system performed for the first<br />
time at Grafenrheinfeld (Germany)<br />
from 1996 to 1999. The measuring<br />
equipment, characterized<br />
by its small dimensions and ease<br />
and speed of installation, was installed<br />
directly on the main piping of the<br />
volume control system.<br />
A total of 18 COMBO systems<br />
have been monitoring boron concentration<br />
in the coolant treatment<br />
and cleanup system at the VVER-type<br />
PWR units, Mochovce 1 and 2<br />
(Slovak Republic) since 1998 and<br />
1999, respectively. Plants equipped<br />
with VVER-type reactors, in particular,<br />
have a greater need for boron<br />
monitoring in the reactor auxiliary<br />
systems due to the system design and<br />
configuration specific to these plants.<br />
A further COMBO system was<br />
installed in 20<strong>02</strong> at Isar 2 (Germany)<br />
for monitoring the fuel pool.
Between October 1 and 15, 2001,<br />
Framatome ANP installed<br />
two new penetrations in the wall of<br />
the fuel pool at Sweden’s oldest<br />
nuclear power plant – the 445MWe<br />
BWR unit Oskarshamn 1. The<br />
penetrations, which have a nominal<br />
diameter of 8" (DN 200), are needed<br />
for connecting the fuel pool to<br />
the residual heat removal system that<br />
has been redesigned as part of<br />
Oskarshamn’s ongoing “MOD” modernization<br />
program. The purpose of<br />
the new connections is to provide the<br />
plant with two additional fuel pool<br />
cooling trains that can be placed in<br />
operation if the system normally used<br />
for pool cooling should fail.<br />
Since the entire reactor core will<br />
be unloaded to the fuel pool when<br />
the unit is shut down in 20<strong>02</strong> for the<br />
main scope of the modernization<br />
work, the two penetrations had to<br />
be installed while the plant was still<br />
on line. Because the fuel pool cooling<br />
system extracts the pool water from<br />
the upper region of the pool for<br />
cooling, it was not possible to lower<br />
the water level in the pool. Hence<br />
all activities had to be carried out<br />
underwater using a special caisson to<br />
provide a dry working area at the<br />
pool wall. Thanks to the experience<br />
and knowledge gained from a similar<br />
project performed in 1997 at the<br />
Swiss nuclear power plant Gösgen,<br />
the work was able to be completed<br />
much faster than expected – in 15<br />
days instead of the 23 days originally<br />
planned. According to Anders<br />
Ahrenius, sub-project manager for<br />
the plant operator, OKG Aktiebolag,<br />
the decisive factor here was “the<br />
excellent work done by the team<br />
from Framatome ANP.”<br />
The main goal of the MOD<br />
project is to bring Oskarshamn 1 in<br />
line with today’s safety standards and<br />
to enable the unit to continue generating<br />
power economically for many<br />
years to come. The complete modernization<br />
program that spans several<br />
years, is scheduled for completion by<br />
the fall of this year.
Brazil<br />
Angra 2: Integrated<br />
Maintenance Service<br />
Minimizes First Refueling<br />
Outage Duration<br />
Framatome ANP received a broad-scope<br />
order for service work to be performed<br />
during the first annual refueling outage<br />
(in March 20<strong>02</strong>) at the Angra 2 nuclear<br />
power plant. In addition to service<br />
work on the reactor floor and for the<br />
fuel assemblies, maintenance work also<br />
will be performed on valves, pumps<br />
and pump motors. The emergency<br />
diesel generating units, electrical and<br />
I&C systems, HVAC systems, and<br />
reactor coolant pumps of the 1309 MWe<br />
PWR plant also will undergo a<br />
comprehensive inspection.<br />
All major inspection work will be<br />
performed in close cooperation with<br />
the Brazilian partner and customer, the<br />
state-owned Eletrobrás Termonuclear<br />
S.A. (ELETRONUCLEAR), as<br />
well as experienced subcontractors<br />
from Germany and Brazil. In total,<br />
more than 1,000 specialists will be<br />
involved in the outage. Thanks to the<br />
integrated service concept developed<br />
by Framatome ANP and the strong<br />
commitment of the utility, manpower<br />
and time scheduling for all companies<br />
and independent experts involved<br />
is coordinated for an outage duration<br />
of less than thirty days. The services<br />
package also includes non-outagerelated<br />
maintenance activities that will<br />
be performed throughout the year<br />
20<strong>02</strong> with the plant on line.<br />
Looking Ahead to Angra 3<br />
One year after the start of commercial<br />
operation at Angra 2, the Brazilian<br />
government authorized the plant owner<br />
and operator, Eletrobrás Termonuclear<br />
S.A. (ELETRONUCLEAR), to start<br />
preparing for the resumption of<br />
NukeNotes<br />
construction work at Angra 3. Initial<br />
tasks consist of nuclear and environmental<br />
licensing, adapting supply<br />
contracts and negotiating required<br />
financing. ELETRONUCLEAR<br />
already has invested US $750 million<br />
in this project. Completion of Angra 3<br />
is estimated to cost another US<br />
$1.7 billion.<br />
The contract for Angra 2 and 3 was<br />
awarded in 1976 under the terms of the<br />
German-Brazilian intergovernmental<br />
agreement on cooperation for the<br />
peaceful use of nuclear energy. However,<br />
money shortages caused work on<br />
Angra 3 to be halted in the mid-1980s.<br />
Angra 2 and 3 are both PWR units<br />
of the 1300 MWe class.<br />
Canada<br />
Steam Generator<br />
Secondary-Side Cleaning<br />
at Pickering B<br />
Framatome ANP performed the<br />
steam generator secondary-side<br />
chemical cleaning of Units 5, 6 and 8<br />
of Pickering B Nuclear Power Station,<br />
a CANDU plant operated by Ontario<br />
Power Generation (OPG). The main<br />
goal of the cleaning project was to<br />
prevent or significantly reduce boiler<br />
tube degradation caused by corrosion<br />
product deposition.<br />
Our patented, high-temperature<br />
cleaning process was selected on<br />
the basis of its short application time<br />
and high efficiency, and because it does<br />
not require any plant modifications.<br />
All 36 steam generators were<br />
cleaned during maintenance outages<br />
within less than 12 months. More than<br />
18,849 lbs. (8550 kg) of deposits were<br />
removed. This was the third steam<br />
generator cleaning project successfully<br />
performed for OPG.<br />
Cleaning of the Unit 7 steam<br />
generator secondary sides is scheduled<br />
for early 2003, again using Framatome<br />
ANP’s proven high-temperature process.<br />
China<br />
Ling Ao Unit 1<br />
Achieves First Criticality<br />
On Schedule<br />
Six years ago Framatome ANP and its<br />
Chinese partners established a schedule<br />
for the Ling Ao nuclear power units<br />
being constructed in China. Ling Ao<br />
Unit 1 achieved first criticality on<br />
February 4, 20<strong>02</strong>, a few days ahead of<br />
schedule. Zero power core compliance<br />
tests were passed on February 7, thus<br />
allowing power escalation.<br />
Ling Ao control room<br />
20 Advanced Nuclear Power N O 4 May 20<strong>02</strong>
Chinese Safety<br />
Authority NNSA Approves<br />
18-Month Fuel Cycles<br />
for Daya Bay NPP<br />
Daya Bay Units 1 and 2 received a<br />
licensing permit from National Nuclear<br />
Safety Administration (NNSA) in<br />
December 2001 to operate both plants<br />
in 18-month fuel cycles, beginning<br />
with cycle 9. This approval is the<br />
culmination of three years’ engineering<br />
work performed by Framatome ANP<br />
with participation by Nuclear Power<br />
Institute of China (NPIC) and<br />
Guangdong Nuclear Power Joint<br />
Venture Company Limited (GNPJVC).<br />
Cycle 9 specific reload safety evaluations<br />
of both Units and recent start-up tests<br />
results for Unit 2 also met the safety<br />
criteria, confirming the generic safety<br />
demonstration.<br />
New design tools, such as<br />
SCIENCE for nuclear design and<br />
CATHARE for LOCA analyses now<br />
being licensed in China, probably will<br />
open future opportunities for nuclear<br />
power plant performance optimization<br />
and for a continued successful<br />
collaboration.<br />
France<br />
Safety Injection Valve<br />
Replacement<br />
Framatome ANP received an order<br />
from Electricité de France (EDF) for<br />
the replacement of a safety injection<br />
check valve and the up-stream elbow,<br />
at Fessenheim 1 in 20<strong>02</strong>. This unusual<br />
replacement follows inspections,<br />
during which indications were found<br />
in the seat of the valve and in the<br />
first weld of the elbow.<br />
A soft chemical decontamination<br />
process will be implemented to<br />
reduce man Rem exposure. Due to the<br />
elbow replacement, the fit-up sequence<br />
will use a Romer 3D arm that will<br />
be positioned on the valve flange.<br />
This manipulator will provide accurate<br />
measurements, to ensure correct<br />
positioning of the cutting and beveling<br />
of the spool piece. This technique was<br />
successfully used for a Residual Heat<br />
Removal System partial replacement.<br />
Once everything is properly positioned,<br />
an automatic tungsten inert gas (TIG)<br />
welding technique, assisted by video<br />
surveillance, will be implemented. A<br />
volumetric inspection will be performed<br />
at the end of the operation.<br />
Japan<br />
UF6-UO2 Conversion<br />
Contract for FBFC<br />
FBFC, a wholly-owned Framatome<br />
ANP subsidiary, signed a multiyear<br />
contract with the Japanese company<br />
Nuclear Fuel Industries Ltd. (NFI) for<br />
conversion services. This operation<br />
consists in transforming uranium<br />
hexafluoride (UF6) – enriched in<br />
Europe – into UO2 powder. Delivery<br />
is scheduled to begin in 20<strong>02</strong>.<br />
Sweden<br />
Nuke Notes<br />
Modernization of Control<br />
Rod Control System<br />
Completed at Forsmark 3<br />
Framatome ANP has modernized<br />
the control system of the control rod<br />
drive mechanisms (CRDM) with<br />
the TELEPERM TM XS digital safety<br />
instrumentation and control system<br />
at Forsmark 3 Nuclear Power Station,<br />
a BWR plant that went into operation<br />
in 1985. This is the first time<br />
TELEPERM XS has been implemented<br />
in the CRDM control system of an<br />
ABB Atom (now Westinghouse Atom)<br />
nuclear power plant. The new control<br />
system provides increased availability,<br />
better and more timely information on<br />
plant conditions, and automatic,<br />
screen-aided CRDM maintenance.<br />
In addition to the highly automated<br />
control system for the drive mechanisms<br />
of the 169 control rods and the related<br />
new calibration functions, the plant<br />
was backfitted with new switchgear and<br />
several PC-based auxiliary systems.<br />
Framatome ANP also supplied a<br />
maintenance database, a local operating<br />
station and a workshop system. The<br />
operation and monitoring functions<br />
were implemented using the<br />
TELEPERM XP instrumentation<br />
and control system.<br />
Advanced Nuclear Power N O 4 May 20<strong>02</strong> 21
Nuke Notes<br />
South Africa<br />
New Industrial Partners<br />
Continuing its strategy of local<br />
development in South Africa,<br />
Framatome ANP has acquired major<br />
shareholdings in two local companies:<br />
• Lesidi Nuclear Services (LNS) to<br />
assemble the resources required<br />
for maintenance operations and<br />
project management,<br />
• Signum Design and Engineering<br />
Consultants to perform<br />
modification studies.<br />
These investments move Framatome<br />
ANP closer to ESKOM, its customer<br />
and the operator of both Koeberg<br />
units, designed by Framatome ANP.<br />
In addition, it conforms with South<br />
Africa’s policy of developing local<br />
enterprises, while guaranteeing that<br />
the customer receives quality service.<br />
Koeberg nuclear power plant<br />
Taiwan<br />
First Decontamination<br />
Performed<br />
In autumn 2001, Framatome ANP<br />
successfully completed its first<br />
decontamination project in Taiwan at<br />
Unit 1 of Kuosheng Nuclear Power<br />
Station, a BWR plant. Both reactor<br />
coolant recirculation loops and the<br />
internals of three reactor coolant<br />
recirculation pumps were decontaminated<br />
using our world-renowned<br />
Chemical Oxidation-Reduction<br />
Decontamination (CORD ® ) UV<br />
process together with Framatome<br />
ANP’s Automated Mobile/Modular<br />
Decontamination Apparatus<br />
(AMDA ® ). The average decontamination<br />
factors achieved in the two<br />
RCC loops were calculated to be 50.8<br />
and 35.5, respectively, and for the<br />
RCC pump internals to be 127,<br />
76 and 69.<br />
The Framatome ANP CORD ®<br />
UV process is characterized by its high<br />
efficiency and low waste generation,<br />
as only chemicals are used that break<br />
down into water and carbon dioxide<br />
under ultraviolet light. For plant<br />
operators, this translates into a<br />
considerable reduction in personnel<br />
occupational exposures and low waste<br />
treatment costs.<br />
United States<br />
Integration of Fuel Services<br />
Proceeds Smoothly<br />
When the nuclear power operations of<br />
Siemens merged with Framatome in<br />
January 2001, the fuel manufacturing<br />
facilities in Richland, Washington<br />
and Lynchburg, VA were combined.<br />
The past year has been devoted to an<br />
in-depth analysis of both operations to<br />
determine the most efficient method<br />
to maximize operations while continuing<br />
to provide advanced technology<br />
and service to customers.<br />
A plan has been developed to consolidate<br />
several operations that will be<br />
implemented over the next three years.<br />
By going slowly and deliberately and<br />
by developing step-by-step, detailed<br />
work plans and schedules, Framatome<br />
ANP is committed to ensuring ontime<br />
delivery of NCR-free assemblies,<br />
even if it means maintaining duplicate<br />
lines until the transition is complete.<br />
A key ingredient in the plan is<br />
customer participation. Customers will<br />
be kept aware of each step, will have<br />
the opportunity to provide input to<br />
the plan in an on-going manner<br />
and can contribute their ideas and suggestions<br />
for minimizing disruptions.<br />
Framatome ANP is committed to<br />
continuing its normal R&D efforts<br />
and maintaining its schedules and<br />
quality as it goes through this process<br />
to provide the best fuel available in<br />
the US today.<br />
22 Advanced Nuclear Power N O 4 May 20<strong>02</strong>
Framatome ANP, Inc.<br />
to Purchase Duke<br />
Engineering and Services<br />
Framatome ANP Inc. signed an<br />
agreement to purchase Duke<br />
Engineering and Services Inc., a<br />
subsidiary of Duke Energy located in<br />
Charlotte, North Carolina. Duke<br />
Engineering is a leading engineering<br />
and technical services firm with<br />
1,250 employees, headquartered in<br />
Charlotte, NC.<br />
The purchase will include three<br />
Duke Engineering business groups.<br />
The Nuclear Group focuses on<br />
nuclear engineering, plant upgrades,<br />
instrumentation and control and spent<br />
fuel storage engineering. The Federal<br />
Editorial Staff of Advanced Nuclear Power magazine:<br />
Annie Wallet – Publisher<br />
Susan Hess – Editor-in-Chief<br />
Martha Wiese – Managing Editor<br />
Bill Warner – Creative Director<br />
Regional Editors – Christine Fischer, Vincent Join-Lambert, Martha Wiese<br />
Graphic Design – O’Connor Group<br />
Contributing Writers:<br />
Franz Ammann, Wolfgang Breyer, Yvonne Broy, Dominique Ebalard, Manfred Erve, Yves Fanjas, Ernst Gell, Gilles Goyau,<br />
Michel Jaubert, Sabine Kueny, Linda Leech, Isabelle Morlaes, Thierry Piérard, Jens Reinel, Frank Schindhelm,<br />
Arnd Schüßler, Joachim Specht, Martha Wiese<br />
Framatome ANP-Worldwide Offices<br />
Tour Framatome<br />
92084 Paris La Défense Cedex<br />
France<br />
Tel.: +33 1 47 96 00 00<br />
Fax: +33 1 47 96 36 36<br />
info@framatome-anp.com<br />
Group provides engineering and site<br />
management for several Department<br />
of Energy nuclear sites. The Energy<br />
and Environmental Group serves the<br />
hydro, gas transmission and fossil<br />
energy markets.<br />
Framatome ANP Inc.’s President<br />
and CEO, Tom Christopher said,<br />
“The synergy between Framatome<br />
ANP Inc. and Duke Engineering will<br />
be excellent because of Duke<br />
Engineering proficiencies and our<br />
strategic goals in the energy industry.<br />
As the world leader in nuclear engineering,<br />
nuclear fuel and nuclear services,<br />
this addition enables us to significantly<br />
broaden our business portfolio<br />
in the US.”<br />
Bruce Williamson,<br />
Duke Energy, and<br />
Tom Christopher,<br />
Framatome ANP, Inc.<br />
at the signing<br />
3315 Old Forest Road<br />
Lynchburg, VA 24501<br />
USA<br />
Tel.: +1 434 832 3000<br />
Fax: +1 434 832 0622<br />
info@framatech.com<br />
Freyeslebenstr.1<br />
D-91058 Erlangen<br />
Germany<br />
Tel.: +49 9131 18 95374<br />
Fax: +49 9131 18 94927<br />
info@framatome-anp.de<br />
The following are trademarks of Framatome ANP: ALLIANCE, Fuelgard, M5, Mark-BW, and TRAPPER. TELEPERM is a trademark of Siemens.<br />
Nuke Notes<br />
Framatome ANP/Entergy<br />
Team to Perform License<br />
Renewal at D. C. Cook<br />
Framatome ANP, teamed with Entergy,<br />
was awarded the contract for license<br />
renewal work at American Electric<br />
Power Company’s D.C. Cook nuclear<br />
power plant. The work will be implemented<br />
over several years culminating<br />
in the preparation and presentation of<br />
the license renewal documentation to<br />
the Nuclear Regulatory Commission<br />
(NRC) for approval.<br />
Aside from responsibility for<br />
license renewal work at all Entergy<br />
nuclear power plants, the team also was<br />
awarded a similar contract at FirstEnergy<br />
Corporation’s Davis-Besse plant.<br />
Advanced Nuclear Power N O 4 May 20<strong>02</strong> 23<br />
©20<strong>02</strong> Framatome ANP, Inc.
U4-V1-<strong>02</strong>-ENG<br />
ENHANCING YOUR COMPETITIVENESS<br />
At Framatome ANP, an <strong>AREVA</strong> and Siemens company,<br />
we’re constantly working to help your nuclear plant<br />
operate more efficiently, safely, and economically.<br />
With a worldwide team of nearly 13,000, we deliver<br />
advanced technology and responsive services to<br />
improve your performance and profitability. From<br />
comprehensive outage services management to<br />
the most innovative tooling and technology, we offer<br />
the expertise to reduce your outage times. Our<br />
YOU’RE RIGHT TO ASK FOR MORE.<br />
www.framatome-anp.com<br />
I&C modernization<br />
at Beznau, Switzerland<br />
high burnup fuel for both BWR and PWR plants<br />
provides increased margins and extreme reliability.<br />
And you can count on our field proven digital I&C,<br />
replacement components and vast engineering knowhow<br />
to deliver competitive solutions for successful<br />
plant modernization and uprates. So whatever your<br />
plant needs are, let us put the power of experience<br />
to work enhancing your competitiveness.<br />
Framatome ANP, COGEMA and FCI now form the <strong>AREVA</strong> Group, the world leader in the nuclear energy and interconnect sectors.