Page 15 - May-June 2013

Nuclear Plant Journal, May-June 2013 NuclearPlantJournal.com 15
New
Documents
EPRI
1. Ion Exchange Filter Transition
Plan for BWRs and PWRs. Product ID:
3002000371. Published March, 2013.
This report includes an interim
review of plant experiences with various
cation exchange membranes to determine
if new filters are comparable and suitable
for nuclear power plant chemistry
applications. Gaps in performance and
impacts to recommendations in EPRI
reports BWRVIP-190: BWR Vessel and
Internals Project, BWR Water Chemistry
Guidelines - 2008 Revision (1016579),
Pressurized Water Reactor Primary Water
Chemistry Guidelines (1014986) and
Pressurized Water Reactor Secondary
Chemistry Guidelines – Revision 7
(1016555) are identified.
2. Materials Reliability Program:
Assessment of the Current Status and
Completeness of Work on Inner and Outer
Diameter Stress Corrosion Cracking of
Austenitic Stainless Steels in PWR Plants
(MRP-352). Product ID: 3002000135.
Published March, 2013.
Field experience with austenitic
stainless steel in operating pressurized
water reactors (PWRs) has, in general,
been good, with a relatively small
number of failures due to stress corrosion
cracking (SCC) observed worldwide.
The objective of this report is to review
the completeness and direction of the
current research into SCC in austenitic
stainless steels and to identify gaps in
understanding that need to be addressed
by future research activities.
3. Depletion Reactivity Benchmark for
the International Handbook of Evaluated
Reactor Physics Benchmark Experiments.
Product ID: 3002000306. Published
April, 2013.
The International Handbook of Eval-
uated Reactor Physics Benchmark Exper-
iments (IRPhE)-evaluated benchmark is
for hot full-power reactor conditions and
zero cooling time. The evaluated bench-
marks benefitted from a rigorous review
by the OECD/NEA experts’ group. Sever-
al improvements resulted from the review,
but no significant changes to the EPRI-
published cold benchmarks generated for
criticality analyses were required. The
full evaluation, reproduced as an appen-
dix in this report, has been accepted as a
draft for the 2013 release of the IRPhE. It
is anticipated that the benchmarks will be
fully accepted for the 2014 IRPhE release
when the results of an ongoing project,
the Benchmarks for the Evaluation and
Validation of Reactor Simulations project
conducted at the Massachusetts Institute
of Technology, are incorporated into the
evaluation documented in this report.
4. BWRVIP-271NP: BWR Vessel and
Internals Project, Testing and Evaluation
of the Browns Ferry Unit 2 120° Capsule.
Product ID: 3002000078. Published
April, 2013.
In the late 1990s, a BoilingWater
Reactor Vessel and Internals Project
(BWRVIP) Integrated Surveillance
Program (ISP) was developed to improve
the surveillance of the U.S. BWR
fleet. This report describes testing and
evaluation of the Browns Ferry Unit 2
120° capsule. These results will be used
to monitor embrittlement as part of the
BWRVIP ISP.
5. Steam Generator Management
Program: Flaw Tolerance Evaluation
of the Steam Generator Channel Head.
Product ID: 3002000411. Published
April, 2013.
There are two cracking scenarios
of concern: cracks propagating from
the divider plate assembly through the
channel head cladding and into the
low-alloy steel, and cracks initiating in
the tubesheet and propagating through
the tube-to-tubesheet weldments. Both
scenarios represent a potential breach
of the primary pressure boundary of
the channel head assembly. This report
addresses only the first cracking scenario
and its potential impact on the structural
integrity of the steam generator channel
head.
6. PipeRuptureFrequencies for Internal
Flooding Probabilistic Risk Assessments:
Revision 3. Product ID: 3002000079.
Published April. 2013.
Thisreportupdatesa2010EPRIreport
(1021086) on piping system failure rates
for use in probabilistic risk assessments
(PRAs) involving internal plant flooding
and high-energy line breaks (HELBs)
and represents the third revision to this
pipe failure rate handbook. These failure
rate estimates are intended to satisfy
requirements of the American Society
of Mechanical Engineers (ASME) and
American Nuclear Society (ANS) PRA
Standard RA-Sa-2009. The estimates also
support an EPRI PRA Scope and Quality
project to provide guidelines on internal
flooding analysis and are intended for
use in conjunction with separate EPRI
guidelines for performing an internal
flooding PRA (1019194).
7. Plant Manager’s Guide for BWR
Source Term Control and Reduction.
Product ID: 3002000820. Published
April, 2013.
This guide is the result of a
collaborative effort between INPO and
EPRI to provide boiling water reactor
(BWR) plant managers a simplified
how-to on radiation field source term
reduction. The goal is to reduce radiation
fields through source term reduction
efforts and ultimately aid in improving
collective radiation exposure. The content
was collected from plant experience and
technical studies to help plant managers
understand, manage, and reduce source
term at their plant.
8. Boiling Water Reactor Chemistry
Summary: 2012 Update. Product ID:
3002000410. Published April, 2013.
This report documents the latest
median values for key boiling water
reactor (BWR) reactor water, feedwater,
and condensate parameters. Median,
rather than average, values were used for
most parameters to minimize the bias due
to transient conditions. It compares the
results with action levels, needed values,
and goals (or good practice values)
from BWRVIP-190: BWR Vessels and
Internals Project, BWR Water Chemistry
Guidelines – 2008 Revision (EPRI report
1016579).
The above EPRI documents may be
ordered by contacting the Order Center
at (800) 313-3774 Option 2 or email at
orders@epri.com.