Nuclear Plant Journal Outage Management ... - Digital Versions

New Documents
EPRI
1. Nuclear Maintenance Applications
Center: Preservation of Failed Parts to
Facilitate Failure Analysis of Nuclear
Power Plant Components. Product ID:
1016907, Published March, 2009.
Equipment failure analysis and damage
mode determination are cornerstones
for improving equipment reliability.
Methods and techniques for performing
failure analysis are becoming more sophisticated
and are used to prevent recurring
equipment failures. Maintenance and
engineering personnel usually perform at
least initial troubleshooting and disassembly
of failed components.
2. Nuclear Maintenance Applications
Center: Tiered Valve Maintenance Program,
Product ID: 1018015, Published
March, 2009.
Thousands of valves of various types
with various actuators perform a variety
of functions in a nuclear power plant.
These valves require varying degrees
of corrective, predictive, and preventive
maintenance, depending on their safety
significance, economic impact, or other
factors such as operating environment or
historical performance.
3. Steam Generator Management Program:
Automated Analysis of Array
Probe Eddy Current Data, Product ID:
1018559, Published March, 2009.
Utilities perform eddy current tests
on nuclear power plant steam generator
(SG) tubes to detect degradation. This
report summarizes the status of ongoing
research to develop signal-processing
algorithms that automate the analysis of
eddy current test data.
4. US Steam Turbine Valve Metallurgy
Guide, Product ID: 202+89+, Published
March, 2009.
This report provides nuclear and
fossil plant personnel with current
information on the metallurgical aspects
of the steam turbine valve components
used in U.S. power plants.
5. Materials Reliability Program:
Inspection and Evaluation Guidelines for
Reactor Vessel Bottom-Mounted Nozzles
in U.S. PWR Plants (MRP-206), Product
ID: 1016594, Published March, 2009.
This report presents inspection and
evaluation guidelines for reactor vessel
bottom-mounted nozzles in U.S. pressurized
water reactor (PWR) plants.
6. Quantifying Corrosion Products Removed
from Fuel Assemblies by Ultrasonic
Fuel Cleaning, Product ID: 1018718,
Published April, 2009.
Ultrasonic Fuel Cleaning (UFC) is a
mechanical cleaning process developed
by EPRI to remove corrosion product
deposits (crud) that have formed on
nuclear fuel assemblies during the
operating cycle. This report documents
the effort and procedure that will allow
utilities to determine the mass of crud
removed during UFC.
7. BWRVIP-210: BWR Vessel and Internals
Project, XGEN Engineering Jet
Pump Restrainer Bracket Repair Design,
Product ID: 1018868, Published April,
2009.
The purpose of this work is to develop
conceptual designs for modification of
jet pump restrainer brackets to provide
rigid lateral restraint of the jet pump inlet
mixers.
8. International Review Team Report: A
Peer Review of the Yucca Mountain IM-
ARC Total System Performance Assessment
EPRI Model, Product ID: 1018711,
Published April, 2009.
The intent of this peer review is to
provide an independent evaluation of
EPRI’s TSPA code, IMARC, in light of
EPRI’s role as an independent third party
to the Yucca Mountain process.
9. Program on Technology Innovation:
Information Integration for Equipment
Reliability at Nuclear Plants, Product ID:
1018910, Published April, 2009.
The nuclear power industry has made
notable advances in the effectiveness of
the equipment reliability process over the
last decade. As the plants’ equipment and
workforce age, it will be even more challenging
to sustain and improve current
high levels of equipment performance.
10. Surface Analysis of Pressurized
Water Reactor Steam Generator Tubing
Specimens: Results of Surface and
Microstructural Analysis of Tubes from
Diablo Canyon 1, Oconee 2, Seabrook,
and Vogtle 1 and 2 PWRs, Product ID:
1018720, Published April, 2009.
The amount and composition of surface
oxides present on the surface of pressurized
water reactor (PWR) reactor coolant
system (RCS) components can have a
major impact on fuel assembly corrosion
product deposits during the operating
cycle. This study analyzes primary side
surface oxides of steam generator tubes
from five U.S. PWRs.
The above documents may be obtained
from EPRI Order and Conference Center,
1300 West WT Harris Blvd., Charlotte,
NC 28262; telephone: (800) 313-3774,
email: orders@epri.com.
Publication
The ASTM International technical
publication, STP 1492, Effects of Radiation
on Materials: 23 rd International Symposium,
features 18 peer-reviewed papers
focused on the irradiation embrittlement
of reactor pressure vessel steels. The new
research provides a broad perspective on
the development and application of trend
curves used to predict fracture toughness
transition temperatures in irradiated reactor
pressure vessel steels. ISBN: 978-0-
8031-3421-8, 237 pages. Price: $74.
Contact: ASTM Customer Service,
telephone: (610) 832-9585, fax: (610)
832-9555, email: service@astm.org.
Nuclear Plant Journal, May-June 2009 www.nuclearplantjournal.com 17