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NuclearPlantJournal.com Nuclear Plant Journal, March-April 2015
New
Documents
NRC
1 .
NUREG-2169.
Nuclear Power
Plant Fire Ignition Frequency and Non-
Suppression Probability Estimation Using
the Updated Fire Events Database: United
StatesFireEventExperienceThrough2009
.
This
report
documents
the
development of updated fire ignition
frequencies (FIFs) and non-suppression
probability (NSP) estimates as potential
improvements for nuclear power plant
(NPP) fire probabilistic risk assessment
(FPRA) applications. This research follows
prior Electric Power Research Institute
(EPRI) research aimed at providing an
updated methodology to estimate FIFs and
collect more recent fire event data.
Fire ignition frequencies and non-
suppression probabilities were previously
developed
in
the
NUREG/CR-6850/
EPRI 1011989,
EPRI/NRC-RES Fire PRA
Methodology for Nuclear Power Facilities,
Final Report
, and revised in Supplement 1
to NUREG/CR-6850/EPRI 1019259,
Fire
Probabilistic Risk Assessment Methods
Enhancements
. In this report, the FIF
estimation benefits from an enhanced
methodology and incorporates updated data
from EPRI’s updated Fire Events Database
(FEDB). The report also updates low-power
and shutdown (LPSD) FIFs from those
published in NUREG/CR-7114,
A Framework
for Low Power/Shutdown Fire PRA – Final
Report
. NSP estimates are calculated using
the existing methodology and have been
updated with new fire event experience.
2. Environmental Impact Statement for
Combined Licenses (COLs) for Turkey
Point Nuclear Plant Units 6 and 7, Draft
Report for Comment, February 2015
.
NUREG-2176, Vol. 1.
This environmental impact statement
(EIS) has been prepared in response
to an application submitted to the U.S.
Nuclear Regulatory Commission (NRC)
by Florida Power and Light Company
(FPL) for two combined construction
permits and operating licenses (combined
licenses or COLs). The proposed actions
related to the FPL application are (1) NRC
issuance of COLs for two new power
reactor units (Units 6 & 7) at the Turkey
Point Nuclear Power Plant site in Miami-
Dade County, Florida, and (2) U.S. Army
Corps of Engineers (USACE) decision to
issue, deny, or issue with modifications a
Department of the Army (DA) permit to
perform certain dredge and fill activities
in waters of the United States and to
construct structures in navigable waters
of the United States related to the project.
The NRC, its contractors, and USACE
make up the review team. The National
Park Service (NPS) is also a cooperating
agency on this EIS but does not now
have a request to take any specific
regulatory action. Due to this unique set
of circumstances, impact determinations
made in this EIS should only be attributed
to the review team.
This EIS documents the review
team’s analysis, which considers and
weighs the environmental impacts of
constructing and operating two new
nuclear units at the Turkey Point site and
at alternative sites, including measures
potentially available for reducing or
avoiding adverse impacts.
3. Impact of Variation in Environmental
Conditions on the Thermal Performance
of Dry Storage Casks, Draft Report for
Comment, February 2015
. NUREG-2174.
During the certification review of
the underground long-term spent fuel dry
storage cask design, the Office of Nuclear
Material Safety and Safeguards (NMSS)
and the Office of Nuclear Regulatory
Research of the U.S. Nuclear Regulatory
Commission (NRC), identified low-
speed wind as an environmental factor
that may affect the thermal performance
of this type of design. This led NMSS to
investigate the impact of wind and other
environmental variables on the thermal
performance of different spent fuel dry
storage cask designs.
During normal conditions of storage,
environmental variables, such as ambient
temperature, solar heating, relative
humidity, elevation, and wind speed
and direction, may affect the thermal
performance of a ventilated dry storage
cask. The thermal evaluation of a dry
storage cask generally assumes a set of
fixed environmental factors (e.g., average
annual ambient temperature, quiescent
conditions, sea level) that will bound all
sites in the continental United States.
However, for some sites, using average
values may not be adequate, because more
adverse ambient conditions could exist
for prolonged periods of time, allowing a
storage system to reach new steady-state
conditions that could result in higher
spent fuel cladding temperatures as
compared to the steady-state conditions
analyzed in the cask’s safety analysis
report (SAR) for normal conditions of
storage. For cases with predicted small
thermal margin, these adverse ambient
conditions could result in peak cladding
temperatures exceeding recommended
limits for normal conditions of storage.
This report evaluates the thermal
impact of varying environmental
conditions on spent fuel dry storage
casks. In addition, the report investigated
the transient thermal behavior of a dry
storage cask when it is subjected to a
sudden boundary condition change,
starting from the bounding conditions
described in the SAR.
The above NUREG-series publications
and other NRC records can be electronically
accessed at NRC’s Public Electronic Reading
room at
EPRI
1.
Evaluation for Installing or Upgrading
Cathodic Protection Systems: A Guide for
CathodicProtection forBuriedPipingand
Tanks
. Product ID: 3002005067. Published
March 2015.
Many cathodic protection (CP)
systems were designed with an expected
life of 20–25 years, and, as nuclear power
plants (NPPs) continue to age, these
systems will reach—and in some cases
extend beyond—their original design life.
Additionally, some sites do not have CP
systems, and consideration is often made
on the cost benefit of installing CP to
protect buried assets. This report provides
guidance and methodologies that an NPP
representative who is responsible for
buried piping and tanks can use to evaluate
a site for using CP. The report will help a
CP system owner determine the need and
implementation of installing and upgrading
the CP for buried piping and tanks.
The above EPRI document may be
ordered by contacting the Order Center
at (800) 313-3774, Option 2, or email at
