14
NuclearPlantJournal.com Nuclear Plant Journal, September-October 2015
New
Documents
EPRI
1.
EPRI's Product Mapping to
International Atomic Energy Agency's
(IAEA) International Generic Ageing
Lessons Learned (IGALL) Aging
Management
Program
Categories.
Product ID: 3002005485. Published July,
2015.
The Electric Power Research
Institute’s (EPRI’s) technical reports have
longsupportedutilitiesindevelopingaging
management programs (AMPs) to ensure
on-going safe and reliable operation.
The reports provide the technical
foundation on aging mechanisms,
their root causes, opportunities for
mitigating aging degradation, tools to
detect and monitor aging degradation,
and processes to repair the degradation.
More recently, the International Atomic
Energy Agency (IAEA) has developed a
set of recommended aging management
programs for nuclear power plants. This
guidance is called the International
Generic Ageing Lessons Learned
(IGALL) and is modeled after a report
developed by the United States Nuclear
Regulatory Commission (NRC) to
support the development and evaluation
of aging management programs as part
of the license renewal process. In an
effort to facilitate the use of current EPRI
state-of-knowledge technical information
in the development of IGALL AMPs,
this report provides a mapping of EPRI
technical reports to the AMPs defined in
IGALL.
2.
Nuclear Maintenance Applications
Center: Safety and Relief Valve Testing
and Maintenance Guide - Revision of
TR-105872
. Product ID: 3002005362.
Published August, 2015.
This report presents a comprehensive
overview of the maintenance aspects
of self-activated and power-operated
pressure relief devices used in nuclear
power plants. A major revision to
EPRI report TR-105872, it updates
content throughout the guide and adds
information on a number of topics not
addressed in the original report.
3.
Welding and Repair Technology
Center: Excavate and Weld Repair
Demonstration Mockup Results -
Preliminary Report
. Product ID:
3002005518. Published August, 2015.
Excavate and weld repair (EWR) is
an alternative for repair or mitigation of
butt welds in Class 1 piping systems and
components that are susceptible to stress
corrosion cracking (SCC). The EWR
methodology excavates a portion of the
outside thickness of the original butt
weld and replaces the removed material
with weld metal that is resistant to SCC.
The 2010 Electric Power Research
Institute (EPRI) report, Topical Report:
Application of the Excavate and Weld
Repair Process for Repair and Mitigation
of Alloy 182 and 82 in PWRs (MRP-
291) (1021012), developed under the
EPRI Materials Reliability Program,
establishes the technical basis of the
EWR methodology for Alloy 82/182
butt welds, which represents Phase 1
of the EWR project that is the subject
of this report. This preliminary report
represents Phase 2 of the project, which
includes fabrication of mockups, residual
stress simulations and modeling, and
residual stress measurements. Phase 3
will include implementation guidelines,
an American Society of Mechanical
Engineers (ASME) Code Case, and an
examination mockup for validation and
demonstration of the EWR concept.
4.
Program on Technology Innovation:
Coated Molybdenum-Alloy Cladding for
Accident-Tolerant Fuel: Progress Report
.
Product ID: 3002005557. Published
August, 2015.
Events at Fukushima and Three Mile
Island (TMI) underscored the need for
superior materials capable of reducing
hydrogen generation and delaying core
melting. To achieve this, EPRI has been
investigating cladding materials such
as molybdenum (Mo) alloys that may
enhance tolerance to fuel and core damage
under station blackout accidents. Such
materials may eliminate fuel integrity
concerns under design basis loss-of-
coolant accident (LOCA) events and
also provide margins for beyond design
basis LOCA events. The combination of
superior high-temperature mechanical
properties and acceptable neutronic
properties make Mo alloys ideal for light
water reactor (LWR) fuel cladding for
enhancing tolerance to severe accidents
and for use in systems that demand
structural integrity.
5.
Electronic Collection of As-Found
Component Data: Final Report
. Product
ID: 3002005591. Published September,
2015.
The nuclear power industry has been
collecting As-Found Condition (AFC)
component data in conjunction with
established Preventative Maintenance
(PM) programs for many years. The AFC
data should be a significant input into the
“Living” aspect of the PM program in
that the data is trended and periodically
reviewed to determine if changes in PM
task scope and frequency are warranted.
The process most often used for collection
of AFC data is described in INPO AP-
913, “Equipment Reliability Process
Description” which asks the maintenance
craft to assign an As-Found Condition
Code commensurate with the observed
condition of the component associated
with the PM task upon start of the job.
This process has proven very difficult to
implement successfully due to reported
AFC code inconsistency, inadequate data
quality, and inefficiencies associated with
the review and analysis of the feedback
provided.
In an effort to improve the As Found
data collection process, a software tool
was developed by the project team and
installed on a hand held device, the
craft carried into the field during the
performance of PM tasks and used to
collect the required data. The use of the
hand held device and data collection
software tool was piloted at the Oak
Ridge National Laboratory High Flux
Isotope Reactor (HFIR) facility. The
pilot entailed use of the hand held device
by the HFIR maintenance craft for the
collection of required as-found condition
data which was then reported to the
PM reviewers (System Engineers) via a
web based software application which
allowed upload of the data and reporting
for review and analysis.
The above EPRI documents may be
ordered by contacting the Order Center
at (800) 313-3774, Option 2, or email at
.
