Nuclear Plant Journal, May-June 2008

New Documents
Book
Nukenomics, by Ian Jackson.
The restructuring of Britain’s nuclear
industry, and the resulting implications
for the private sector, are explained in
Nukenomics – The commercialisation
of Britain’s nuclear industry, was
published on April 25, 2008. This
Nuclear Engineering International
special publication describes the major
trends and market forces that are actively
shaping the future development of the
nuclear industry today, by explaining
not just what things are happening
but, more fundamentally, why. ISBN:
978190377559. Price: £20.00.
Contact: telephone: 44 20 8269
7773, email: info@neimagazine.com.
EPRI
1. Guidelines for Reducing the Time and
Cost of Turbine-Generator Maintenance
Overhauls and Inspections Volume 2:
Repair Procedures, Product ID: 1016345,
Published March 2008.
Up to 70% of the outages planned for
conventional steam power plants involve
work on the turbine. The challenge for
the engineer is to improve performance
and extend reliability while eliminating
unproductive activities from the
maintenance outage schedule. This report
provides general guidelines for planning
and performing maintenance on steam
turbines during outages.
2. Guidance on Use of Simulation to
Support Digital I&C and Control Room
Modifi cations, Product ID: 1015088,
Published March 2008.
This report presents guidance for
evaluating and selecting alternative
simulation approaches to support digital
instrumentation and control (I&C) and
control room modifications beginning
early in the modification process.
3. Rancho Seco Reactor Vessel
Segmentation Experience Report, Product
ID: 1015501, Published March 2008.
This report details the engineering
evaluations leading to the segmentation
and disposal of the Reactor Vessel (RV).
It describes the key elements of the
project with emphasis on planning and
conducting the segmentation activities
that played a major role in the success of
this project.
4. Steam Generator Management
Program: PWR Steam Generator Tube
Wear-Alloy 690/Supports, Product ID:
1014991, Published March 2008.
This report describes the test
hardware and techniques used to obtain
the data; test results of alloy 690 against
stainless steel 409, 405, and 410; and
the resulting wear coefficients. The
report provides insight into the wear
phenomenon through an investigation of
the surface of worn tubes.
5. Steam Turbine Blade Failure Root
Cause Analysis Guide, Product ID:
1014137, Published March 2008.
The report provides both an overview
and step-by-step approach to identifying
the damage mechanisms most common to
turbine blade failures. It proceeds to show
how damage mechanisms are related to
the operating history prior to the blade’s
failure and how they are evaluated to
establish their role as principal (root)
causes versus secondary contributors.
6. Final Status Survey and Site Release
Experience Report, Product ID: 1015500,
Published March 2008.
This report provides detailed
information concerning the preparation
of release criteria a utility must meet
prior to the release of the site, and the
experiences obtained in performing the
Final Status Surveys which demonstrate
the site meets that release criteria. This
report draws on the experiences gained
at a number of sites that have achieved
release of the site from the NRC license,
and from other sites in the final stage of
obtaining that release.
7. Losses of Offsite Power at U.S.
Nuclear Power Plants — 2007, Product
ID: 1016484, Published April 2008.
This report supplements EPRI
Technical Report 1014901, Loss of Offsite
Power — 2006. That report provides a
database and overview analysis of losses
of offsite power at U.S. nuclear generating
units for the 10-year period 1997 through
2006. This supplement provides loss of
offsite power data for the year 2007 and
limited overview data and analysis for the
10-year period 1998 through 2007. These
data provide insights into the causes of
losses of offsite power at nuclear power
plants.
8. BWRVIP-186: BWR Vessel and
Internals Project, Effect of Water
Chemistry and Temperature Transients
on the IGSCC Growth Rates in BWR
Components, Product ID: 1016485,
Published April 2008.
The oxidizing nature of the boiling
water reactor (BWR) environment,
coupled with high tensile residual stresses,
have led to intergranular stress corrosion
cracking (IGSCC) events. This report
summarizes the available information on
the effect of water chemistry transients on
crack growth rates of Type 304 stainless
steel and nickel-base weld metal Alloy
182. The report also provides crack growth
rate equations and tables for evaluating
the amount of crack extension that may
have occurred during a transient in either
normal water chemistry or hydrogen
water chemistry environments.
The above documents may be obtained
from EPRI Order and Conference Center,
1300 West WT Harris Blvd., Charlotte,
NC 28262; telephone: 800-313-3774
press 2, email: orders@epri.com.
www.
NPJOnline.
com
Nuclear Plant Journal, May-June 2008 http://www.NPJOnline.com 21