ML993500376
| ML993500376 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1999 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| RG01.105 Rev 3 | |
| Download: ML993500376 (8) | |
Text
0RRt
==
U.S.
==
NUCLEAR
==
REGULATORY
==
COMMISSION
==
Revision
==
3
==
December
==
1999
==
!REGULATORY
==
GUIDE
==
OFFICE
==
OF
==
NUCLEAR
==
REGULATORY
==
RESEARCH
==
REGULATORY
==
GUIDE
==
1.105
==
(Draft
==
was
==
DG-1045)
==
SETPOINTS
==
FOR
==
SAFETY-RELATED
==
INSTRUMENTATION
==
A.
==
INTRODUCTION
==
Criterion
==
13,
==
"Instrumentation
==
and
==
Control,"'
==
of
==
Appendix
==
A,
==
"General
==
Design
==
Criteria
==
for
==
Nuclear
==
Power
==
Plants,"
==
to
==
10
==
CFR
==
Part
==
50,
==
"Domestic
==
Licensing
==
of
==
Production
==
and
==
Utilization
==
Facilities,"
==
requires,
==
among
==
other
==
things,
==
that
==
instrumentation
==
be
==
provided
==
to
==
monitor
==
variables
==
and
==
systems
==
and
==
that
==
controls
==
be
==
provided
==
to
==
maintain
==
these
==
variables
==
and
==
systems
==
within
==
prescribed
==
operating
==
ranges.
==
Criterion
==
20,
==
"Protection
==
System
==
Functions,"
==
of
==
Appendix
==
A
==
to
==
10
==
CFR
==
Part
==
50
==
requires,
==
among
==
other
==
things,
==
that
==
the
==
protection
==
system
==
be
==
designed
==
to
==
initiate
==
operation
==
of
==
appropriate
==
systems
==
to
==
ensure
==
that
==
specified
==
acceptable
==
fuel
==
design
==
limits
==
are
==
not
==
exceeded.
==
Paragraph
==
(c)(1)(ii)(A)
==
of
==
§
==
50.36,
==
"Technical
==
Specifications,"
==
of
==
10
==
CFR
==
Part
==
50
==
requires,
==
in
==
part,
==
that,
==
where
==
a
==
limiting
==
safety
==
system
==
setting
==
is
==
specified
==
for
==
a
==
variable
==
on
==
which
==
a
==
safety
==
limit
==
has
==
been
==
placed,
==
the
==
setting
==
be
==
so
==
chosen
==
that
==
automatic
==
protective
==
action
==
will
==
correct
==
the
==
abnormal
==
situation
==
before
==
a
==
safety
==
limit
==
is
==
exceeded.
==
It
==
also
==
requires,
==
among
==
other
==
things,
==
that
==
the
==
licensee
==
notify
==
the
==
NRC
==
if
==
the
==
licensee
==
determines
==
that
==
an
==
automatic
==
safety
==
system
==
does
==
not
==
function
==
as
==
required.
==
The
==
licensee
==
is
==
required
==
to
==
then
==
review
==
the
==
matter
==
and
==
record
==
the
==
results
==
of
==
the
==
review.
==
1
==
For
==
the
==
full
==
text
==
of
==
the
==
General
==
Design
==
Criteria
==
and
==
other
==
sections
==
of
==
the
==
regulations
==
cited
==
in
==
this
==
guide,
==
see
==
10
==
CFR
==
Part
==
50,
==
"Domestic
==
Licensing
==
of
==
Production
==
and
==
Utilization
==
Facilities."
==
Regulatory
==
guides
==
are
==
issued
==
to
==
describe
==
and
==
make
==
available
==
to
==
the
==
public
==
such
==
information
==
as
==
methods
==
acceptable
==
to
==
the
==
NRC
==
staff
==
for
==
implementing
==
specific
==
parts
==
of
==
the
==
NRC's
==
regulations,
==
techniques
==
used
==
by
==
the
==
staff
==
in
==
evaluating
==
specific
==
problems
==
or
==
postulated
==
accidents,
==
and
==
data
==
needed
==
by
==
the
==
NRC
==
staff
==
in
==
its
==
review
==
of
==
applications
==
for
==
permits
==
and
==
licenses.
==
Regulatory
==
guides
==
are
==
not
==
substitutes
==
for
==
regulations,
==
and
==
compliance
==
with
==
them
==
is
==
not
==
required.
==
Methods
==
and
==
solutions
==
different
==
from
==
those
==
set
==
out
==
in
==
the
==
guides
==
will
==
be
==
acceptable
==
if
==
they
==
provide
==
a
==
basis
==
for
==
the
==
findings
==
requisite
==
to
==
the
==
issuance
==
or
==
continuance
==
of
==
a
==
permit
==
or
==
license
==
by
==
the
==
Commission.
==
This
==
guide
==
was
==
issued
==
after
==
consideration
==
of
==
comments
==
received
==
from
==
the
==
public.
==
Comments
==
and
==
suggestions
==
for
==
improvements
==
in
==
these
==
guides
==
are
==
encouraged
==
at
==
all
==
times,
==
and
==
guides
==
will
==
be
==
revised,
==
as
==
appropriate,
==
to
==
accommodate
==
comments
==
and
==
to
==
reflect
==
new
==
information
==
or
==
experience.
==
Written
==
comments
==
may
==
be
==
submitted
==
to
==
the
==
Rules
==
and
==
Directives
==
Branch,
==
ADM,
==
U.S.
==
Nuclear
==
Regulatory
==
Commission,
==
==
==
20555-0001.
==
Regulatory
==
guides
==
are
==
issued
==
in
==
ten
==
broad
==
divisions:
==
1,
==
Power
==
Reactors;
==
2,
==
Research
==
and
==
Test
==
Reactors;
==
3,
==
Fuels
==
and
==
Materials
==
Facilities;
==
4,
==
Environmental
==
and
==
Siting;
==
5,
==
Materials
==
and
==
Plant
==
Protection;
==
6,
==
Products;
==
7,
==
Transportation;
==
8,
==
Occupational
==
Health;
==
9,
==
Antitrust
==
and
==
Financial
==
Review;
==
and
==
10,
==
General.
==
Single
==
copies
==
of
==
regulatory
==
guides
==
(which
==
may
==
be
==
reproduced)
==
may
==
be
==
obtained
==
free
==
of
==
charge
==
by
==
writing
==
the
==
Distribution
==
Services
==
Section,
==
U.S.
==
Nuclear
==
Regulatory
==
Commission,
==
==
==
20555-0001,
==
or
==
by
==
fax
==
to
==
(301)415-2289,
==
or
==
by
==
==
to
==
DISTRIBUTION@NRC.GOV.
==
Many
==
regulatory
==
guides
==
are
==
also
==
available
==
on
==
the
==
internet
==
at
==
NRC's
==
home
==
page
==
at
==
<WWW.NRC.GOV>.
==
P
==
V--
==
A?
==
to
==
~i--r.
==
)e-__
==
-
==
L)
==
_L
==
V
==
U
==
This
==
guide
==
describes
==
a
==
method
==
acceptable
==
to
==
the
==
NRC
==
staff
==
for
==
complying
==
with
==
the
==
NRC's
==
regulations
==
for
==
ensuring
==
that
==
setpoints
==
for
==
safety-related
==
instrumentation
==
are
==
initially
==
within
==
and
==
remain
==
within
==
the
==
technical
==
specification
==
limits.
==
The
==
guide
==
is
==
being
==
revised
==
to
==
endorse
==
Part
==
1
==
of
==
ISA-$67.04-1994,
==
"Setpoints
==
for
==
Nuclear
==
Safety-Related
==
Instrumentation."2
==
This
==
standard
==
provides
==
a
==
basis
==
for
==
establishing
==
setpoints
==
for
==
nuclear
==
instrumentation
==
for
==
safety
==
systems
==
and
==
addresses
==
known
==
contributing
==
errors
==
in
==
the
==
channel.
==
The
==
information
==
collections
==
contained
==
in
==
this
==
regulatory
==
guide
==
are
==
covered
==
by
==
the
==
requirements
==
in
==
10
==
CFR
==
Part
==
50,
==
which
==
were
==
approved
==
by
==
the
==
Office
==
of
==
Management
==
and
==
Budget,
==
approval
==
number
==
3150-0011.
==
The
==
NRC
==
may
==
not
==
conduct
==
or
==
sponsor,
==
and
==
a
==
person
==
is
==
not
==
required
==
to
==
respond
==
to,
==
a
==
collection
==
of
==
information
==
unless
==
it
==
displays
==
a
==
currently
==
valid
==
==
control
==
number.
==
B.
==
DISCUSSION
==
Instrument
==
setpoint
==
uncertainty
==
allowances
==
and
==
setpoint
==
discrepancies
==
have
==
led
==
to
==
a
==
number
==
of
==
operational
==
problems.
==
Operating
==
experience
==
indicates
==
that
==
setpoints
==
for
==
safety
==
related
==
instrumentation
==
may
==
allow
==
plants
==
to
==
operate
==
outside
==
the
==
limiting
==
conditions
==
of
==
operation
==
specified
==
in
==
their
==
technical
==
specifications.
==
Licensees
==
have
==
discovered
==
conflicts
==
between
==
existing
==
setpoints
==
and
==
engineering
==
calculations.
==
The
==
causes
==
for
==
these
==
setpoint
==
discrepancies
==
were
==
problems
==
with
==
industry
==
practices
==
that
==
led
==
to
==
errors
==
in
==
calibration
==
procedures
==
and
==
a
==
lack
==
of
==
understanding
==
of
==
the
==
relationship
==
of
==
the
==
setpoint
==
to
==
the
==
allowable
==
value.
==
Additional
==
problems
==
noted
==
included
==
varying
==
setpoint
==
methodologies
==
for
==
engineering
==
calculations,
==
a
==
lack
==
of
==
a
==
consistent
==
definition
==
of
==
allowable
==
value
==
between
==
different
==
setpoint
==
methodologies,
==
and
==
improper
==
understanding
==
of
==
the
==
relationship
==
of
==
the
==
allowable
==
value
==
to
==
earlier
==
setpoint
==
terminology,
==
procedures,
==
and
==
operability
==
criteria.
==
Further
==
problems
==
were
==
noted
==
when
==
procedures
==
(the
==
setpoint
==
process)
==
(1)
==
failed
==
to
==
provide
==
an
==
adequate
==
margin
==
between
==
the
==
instrument
==
as-left
==
criteria
==
and
==
the
==
values
==
(trip
==
set
==
point
==
or
==
allowable
==
values)
==
required
==
per
==
the
==
technical
==
specifications,
==
(2)
==
did
==
not
==
always
==
reflect
==
current
==
design
==
criteria,
==
and
==
(3)
==
did
==
not
==
ensure
==
that
==
revised
==
instrument
==
loops
==
were
==
verified
==
to
==
the
==
original
==
design
==
requirements
==
or
==
that
==
instrument
==
modifications
==
were
==
evaluated
==
for
==
their
==
effect
==
on
==
setpoint
==
calculations.
==
It
==
has
==
also
==
been
==
noted
==
that
==
licensees
==
do
==
not
==
typically
==
verify
==
whether
==
setpoint
==
calculation
==
drift
==
assumptions
==
have
==
remained
==
valid
==
for
==
the
==
system
==
surveillance
==
interval.
==
ISA-$67.04
==
was
==
revised
==
in
==
1987
==
to
==
provide
==
clarification
==
and
==
to
==
reflect
==
industry
==
practice.
==
The
==
term
==
"trip
==
setpoint"
==
was
==
made
==
consistent
==
with
==
the
==
terminology
==
used
==
by
==
the
==
NRC
==
staff.
==
The
==
standard
==
was
==
revised
==
further
==
in
==
1994.
==
The
==
effects
==
of
==
uncertainty
==
allowances
==
and
==
discrepancies
==
in
==
setpoints,
==
along
==
with
==
operational
==
experience,
==
were
==
appropriately
==
addressed
==
during
==
this
==
revision
==
of
==
ISA-$67.04.
==
This
==
revision
==
of
==
the
==
standard
==
also
==
reflects
==
the
==
Improved
==
Technical
==
Specification
==
program
==
(a
==
cooperative
==
effort
==
between
==
industry
==
and
==
the
==
NRC
==
staff)
==
and
==
reflect
==
current
==
industry
==
practice.
==
This
==
standard
==
provides
==
a
==
basis
==
for
==
establishing
==
setpoints
==
for
==
nuclear
==
instrumentation
==
for
==
safety
==
systems
==
and
==
addresses
==
known
==
contributing
==
2Copies
==
may
==
be
==
obtained
==
from
==
the
==
Instrument
==
Society
==
of
==
America,
==
67
==
Alexander
==
Drive,
==
Research
==
Triangle
==
Park,
==
NC
==
20779.
==
2
==
errors
==
in
==
a
==
particular
==
channel
==
from
==
the
==
process
==
(including
==
the
==
primary
==
element
==
and
==
sensor)
==
through
==
and
==
including
==
the
==
final
==
setpoint
==
device.
==
The
==
term
==
"trip
==
setpoint"
==
is
==
retained
==
in
==
ISA-S67.04-1994.
==
However,
==
Figure
==
1
==
in
==
==
$67.04-1994
==
(for
==
convenience,
==
this
==
figure
==
has
==
been
==
reproduced
==
as
==
Figure
==
1
==
in
==
this
==
guide)
==
has
==
been
==
revised
==
to
==
depict
==
region
==
"E,"
==
"a
==
region
==
of
==
calibration
==
tolerance."
==
The
==
calibration
==
tolerance
==
uncertainties
==
depicted
==
by
==
region
==
"E"
==
should
==
be
==
defined
==
and
==
accounted
==
for
==
in
==
the
==
licensee's
==
setpoint
==
methodology.
==
A
==
trip
==
setpoint
==
value
==
identified
==
to
==
be
==
outside
==
region
==
"E"
==
regardless
==
of
==
direction
==
requires
==
readjustment
==
to
==
satisfy
==
the
==
setpoint
==
methodology
==
and
==
uncertainties
==
identified
==
in
==
Figure
==
1
==
(acceptable
==
as-left
==
condition).
==
It
==
should
==
be
==
noted
==
that
==
this
==
standard
==
does
==
not
==
define
==
"nominal"
==
trip
==
setpoint.
==
The
==
trip
==
setpoint
==
as
==
depicted
==
in
==
Figure
==
1
==
is
==
consistent
==
with
==
the
==
term
==
"nominal"
==
trip
==
setpoint
==
as
==
shown
==
about
==
a
==
defined
==
calibration
==
tolerance
==
band.
==
Figure
==
1
==
of
==
the
==
standard
==
provides
==
setpoint
==
relationships
==
for
==
nuclear
==
safety-related
==
setpoints.
==
The
==
figure
==
denotes
==
relative
==
position
==
and
==
not
==
direction,
==
but
==
it
==
should
==
be
==
noted
==
that
==
the
==
uncertainty
==
relationships
==
depicted
==
by
==
Figure
==
1
==
do
==
not
==
represent
==
any
==
one
==
particular
==
method
==
(direction,
==
combination,
==
or
==
relationship
==
of
==
uncertainty
==
groupings)
==
for
==
the
==
development
==
of
==
a
==
trip
==
setpoint
==
or
==
allowable
==
value.
==
Section
==
4
==
of
==
ISA-$67.04-1994
==
states
==
that
==
the
==
safety
==
significance
==
of
==
various
==
types
==
of
==
setpoints
==
for
==
safety-related
==
instrumentation
==
may
==
differ,
==
and
==
thus
==
a
==
less
==
rigorous
==
setpoint
==
determination
==
method
==
may
==
be
==
applied
==
for
==
certain
==
functional
==
units
==
and
==
limiting
==
conditions
==
of
==
operation
==
(LCOs).
==
A
==
setpoint
==
methodology
==
can
==
include
==
such
==
a
==
graded
==
approach.
==
However,
==
the
==
grading
==
technique
==
chosen
==
by
==
the
==
licensee
==
should
==
be
==
consistent
==
with
==
the
==
standard
==
and
==
should
==
consider
==
applicable
==
uncertainties
==
regardless
==
of
==
the
==
setpoi'nt
==
application.
==
Additionally,
==
the
==
application
==
of
==
the
==
standard,
==
using
==
a
==
"graded"
==
approach,
==
is
==
also
==
appropriate
==
for
==
non-safety
==
system
==
instrumentation
==
for
==
maintaining
==
design
==
limits
==
described
==
in
==
the
==
Technical
==
Specifications.
==
Examples
==
may
==
include
==
instrumentation
==
relied
==
on
==
in
==
emergency
==
operating
==
procedures
==
(EOPS),
==
and
==
for
==
meeting
==
applicable
==
LCOs,
==
and
==
for
==
meeting
==
the
==
variables
==
in
==
Regulatory
==
Guide
==
1.97,
==
"Instrumentation
==
for
==
Light-Water-Cooled
==
Nuclear
==
Power
==
Plants
==
To
==
Assess
==
Plant
==
and
==
Environs
==
Conditions
==
During
==
and
==
Following
==
an
==
Accident."3
==
The
==
industry
==
consensus
==
standard
==
==
"Guidelines
==
for
==
the
==
Verification
==
and
==
Validation
==
of
==
Scientific
==
and
==
Engineering
==
Computer
==
Programs
==
for
==
the
==
Nuclear
==
Industry,"
==
provides
==
helpful
==
information
==
on
==
the
==
qualification
==
of
==
setpoint
==
methodology
==
software.
==
ISA-$67.04-1982
==
has
==
been
==
used
==
by
==
licensees
==
for
==
setpoint
==
methodology
==
and
==
instrument
==
drift
==
evaluations.
==
ISA-$67.04-1994
==
provides
==
limited
==
guidance
==
on
==
drift
==
evaluations
==
and
==
uncertainty
==
term
==
development
==
for
==
the
==
evaluation
==
of
==
an
==
instrument
==
surveillance
==
interval.
==
The
==
3Single
==
copies
==
of
==
regulatory
==
guides,
==
both
==
active
==
and
==
draft,
==
may
==
be
==
obtained
==
free
==
of
==
charge
==
by
==
writing
==
the
==
Office
==
of
==
Administration,
==
Attn:
==
Reproduction
==
and
==
Distribution
==
Services
==
Section,
==
U.S.
==
Nuclear
==
Regulatory
==
Commission,
==
==
==
20555,
==
or
==
by
==
fax
==
to
==
(301)415-2289,
==
or
==
by
==
==
to
==
<DISTRIBUTION@NRC.GOV>.
==
Copies
==
are
==
also
==
available
==
for
==
inspection
==
or
==
copying
==
for
==
a
==
fee
==
from
==
the
==
NRC
==
Public
==
Document
==
Room
==
at
==
2120
==
L
==
Street
==
NW.,
==
==
DC;
==
the
==
PDR's
==
mailing
==
address
==
is
==
==
Stop
==
LL-6,
==
==
==
20555;
==
telephone
==
(202)634-3273;
==
fax
==
(202)634-3343.
==
3
==
Safety
==
Limit
==
Analytical
==
Limit
==
Note:
==
This
==
figure
==
is
==
intended
==
to
==
provide
==
relative
==
position
==
and
==
not
==
to
==
imply
==
direction.
==
A
==
I
==
C
==
Allowable
==
Value
==
L
==
(LSSS)
==
B
==
F
==
Trip
==
Setpoint
==
I
==
E
==
(LSSS)
==
D
==
r
==
Normal
==
A.
==
Allowance
==
described
==
in
==
paragraph
==
4.3.1
==
B.
==
Allowance
==
described
==
in
==
paragraph
==
4.3.1
==
C.
==
Region
==
where
==
channel
==
may
==
be
==
determined
==
==
D.
==
Plant
==
operating
==
margin
==
E.
==
Region
==
of
==
calibration
==
tolerance
==
(acceptable
==
as
==
left
==
condition)
==
described
==
in
==
paragraph
==
4.3.1
==
Figure
==
1.
==
Nuclear
==
Safety-Related
==
Setpoint
==
Relationships
==
(Reproduced
==
from
==
ISA-67.04-1994)
==
4
==
staff
==
has
==
generally
==
accepted
==
drift
==
evaluations
==
based
==
on
==
statistical
==
prediction
==
techniques.
==
However,
==
significant
==
variability
==
has
==
been
==
observed
==
in
==
licensees'
==
surveillance
==
interval
==
evaluations
==
with
==
regard
==
to
==
drift,
==
setpoint
==
methodology,
==
and
==
completeness.
==
The
==
following
==
concerns
==
were
==
identified
==
during
==
the
==
NRC
==
staff
==
review,
==
but
==
they
==
have
==
been
==
resolved
==
during
==
the
==
development
==
of
==
ISA-S67.04-1994.
==
a
==
Limited
==
instrument
==
drift
==
data
==
were
==
included
==
in
==
the
==
licensee
==
setpoint
==
study.
==
a
==
Drift
==
data
==
account
==
for
==
all
==
data
==
points
==
from
==
a
==
surveillance
==
calibration
==
(i.e.,
==
nine-point
==
check)
==
as
==
independent
==
data,
==
but
==
inadequate
==
justification
==
is
==
provided
==
for
==
this
==
assumption.
==
Drift
==
data
==
points
==
also
==
included
==
interim
==
calibrations.
==
a
==
A
==
large
==
number
==
of
==
data
==
points
==
was
==
provided
==
for
==
a
==
limited
==
number
==
of
==
instruments.
==
a
==
Flawed
==
outlier
==
analysis
==
resulted
==
in
==
valid
==
data
==
being
==
removed
==
from
==
the
==
data
==
set.
==
==
Drift
==
dependency
==
on
==
time
==
was
==
assumed
==
to
==
be
==
negligible
==
over
==
the
==
interval
==
selected,
==
and
==
inadequate
==
justification
==
was
==
provided
==
when
==
extrapolating
==
to
==
an
==
extended
==
surveillance
==
interval
==
(e.g.,
==
24
==
months).
==
==
Setpoint
==
methodology
==
assumes
==
normal
==
distribution
==
of
==
data
==
when
==
such
==
an
==
assumption
==
was
==
not
==
verified.
==
0
==
Instrumentation
==
evaluations
==
(historical,
==
maintenance,
==
drift)
==
were
==
incomplete.
==
==
Drift
==
projections,
==
including
==
those
==
based
==
on
==
regression
==
analyses,
==
may
==
not
==
account
==
for
==
penalties
==
for
==
uncertainty
==
projection
==
(extended
==
surveillance
==
interval-drift)
==
beyond
==
the
==
time
==
range
==
for
==
the
==
data
==
collected.
==
==
Instrument
==
application
==
and
==
process
==
or
==
installation
==
variables
==
were
==
not
==
evaluated.
==
==
The
==
uncertainties
==
assumed
==
for
==
instrumentation,
==
including
==
primary
==
elements,
==
were
==
subsequently
==
not
==
verified
==
or
==
controlled
==
through
==
surveillance
==
testing,
==
qualification,
==
or
==
maintenance
==
programs.
==
==
The
==
acceptability
==
of
==
pooling
==
generic
==
drift
==
data
==
with
==
plant-specific
==
data
==
or
==
weighing
==
the
==
data
==
according
==
to
==
the
==
source
==
of
==
the
==
data
==
was
==
not
==
justified.
==
==
All
==
available
==
applicable
==
data
==
were
==
not
==
utilized
==
in
==
the
==
analysis.
==
Section
==
4.3
==
of
==
ISA-S67.04-1994
==
states
==
that
==
the
==
limiting
==
safety
==
system
==
setting
==
(LSSS)
==
may
==
be
==
the
==
trip
==
setpoint,
==
an
==
allowable
==
value,
==
or
==
both.
==
For
==
the
==
standard
==
technical
==
specifications,
==
the
==
staff
==
designated
==
the
==
allowable
==
value
==
as
==
the
==
LSSS.
==
In
==
association
==
with
==
the
==
trip
==
setpoint
==
and
==
limiting
==
conditions
==
for
==
operation
==
(LCOs),
==
the
==
==
establishes
==
the
==
threshold
==
for
==
protective
==
system
==
action
==
to
==
prevent
==
acceptable
==
limits
==
being
==
exceeded
==
during
==
design
==
basis
==
accidents.
==
The
==
==
therefore
==
ensures
==
that
==
automatic
==
protective
==
action
==
will
==
correct
==
the
==
abnormal
==
situation
==
before
==
a
==
safety
==
limit
==
is
==
exceeded.
==
A
==
licensee,
==
with
==
justification,
==
may
==
propose
==
an
==
alternative
==
==
based
==
on
==
its
==
particular
==
setpoint
==
methodology
==
or
==
license.
==
5
==
The
==
standard
==
provides
==
for
==
the
==
accounting
==
of
==
measurement
==
and
==
test
==
equipment
==
(MTE)
==
uncertainties,
==
but
==
==
criteria
==
are
==
not
==
specifically
==
identified
==
within
==
the
==
standard.
==
Criteria
==
XI
==
and
==
XII
==
in
==
Appendix
==
B
==
to
==
10
==
CFR
==
Part
==
50
==
provide
==
requirements
==
for
==
quality
==
regarding
==
testing.
==
Regulatory
==
Guide
==
1.118,
==
"Periodic
==
Testing
==
of
==
Electric
==
Power
==
and
==
Protection
==
Systems,"
==
provides
==
guidance
==
on
==
periodic
==
surveillance
==
testing.
==
Part
==
II,
==
"Methodologies
==
for
==
the
==
Determination
==
of
==
Setpoints
==
for
==
the
==
Nuclear
==
Safety
==
Related
==
Instrumentation,"
==
of
==
ISA-S67.04-1994
==
is
==
not
==
addressed
==
by
==
this
==
regulatory
==
guide.
==
C.
==
REGULATORY
==
POSITION
==
Conformance
==
with
==
Part
==
1
==
of
==
ISA-S67.04-1994,
==
"Setpoints
==
for
==
Nuclear
==
Safety-Related
==
Instrumentation,"
==
with
==
the
==
following
==
exceptions
==
and
==
clarifications,
==
provides
==
a
==
method
==
acceptable
==
to
==
the
==
NRC
==
staff
==
for
==
satisfying
==
the
==
NRC's
==
regulations
==
for
==
ensuring
==
that
==
setpoints
==
for
==
safety-related
==
instrumentation
==
are
==
established
==
and
==
maintained
==
within
==
the
==
technical
==
specification
==
limits.
==
1.
==
Section
==
4
==
of
==
ISA-$67.04-1994
==
specifies
==
the
==
methods,
==
but
==
not
==
the
==
criterion,
==
for
==
combining
==
uncertainties
==
in
==
determining
==
a
==
trip
==
setpoint
==
and
==
its
==
allowable
==
values.
==
The
==
95/95
==
tolerance
==
limit
==
is
==
an
==
acceptable
==
criterion
==
for
==
uncertainties.
==
That
==
is,
==
there
==
is
==
a
==
95%
==
probability
==
that
==
the
==
constructed
==
limits
==
contain
==
95%
==
of
==
the
==
population
==
of
==
interest
==
for
==
the
==
surveillance
==
interval
==
selected.
==
2.
==
Sections
==
7
==
and
==
8
==
of
==
Part
==
1
==
of
==
ISA-$67.04-1994
==
reference
==
several
==
industry
==
codes
==
and
==
standards.
==
If
==
a
==
referenced
==
standard
==
has
==
been
==
incorporated
==
separately
==
into
==
the
==
NRC's
==
regulations,
==
licensees
==
and
==
applicants
==
must
==
comply
==
with
==
that
==
standard
==
as
==
set
==
forth
==
in
==
the
==
regulation.
==
If
==
the
==
referenced
==
standard
==
has
==
been
==
endorsed
==
in
==
a
==
regulatory
==
guide,
==
the
==
standard
==
constitutes
==
a
==
method
==
acceptable
==
to
==
the
==
NRC
==
staff
==
of
==
meeting
==
a
==
regulatory
==
requirement
==
as
==
described
==
in
==
the
==
regulatory
==
guide.
==
If
==
a
==
referenced
==
standard
==
has
==
been
==
neither
==
incorporated
==
into
==
the
==
NRC's
==
regulations
==
nor
==
endorsed
==
in
==
a
==
regulatory
==
guide,
==
licensees
==
and
==
applicants
==
may
==
consider
==
and
==
use
==
the
==
information
==
in
==
the
==
referenced
==
standard
==
if
==
appropriately
==
justified,
==
consistent
==
with
==
current
==
regulatory
==
practice.
==
3.
==
Section
==
4.3
==
of
==
ISA-S67.04-1994
==
states
==
that
==
the
==
limiting
==
safety
==
system
==
setting
==
(LSSS)
==
may
==
be
==
maintained
==
in
==
technical
==
specifications
==
or
==
appropriate
==
plant
==
procedures.
==
However,
==
10
==
CFR
==
50.36
==
states
==
that
==
the
==
technical
==
specifications
==
will
==
include
==
items
==
in
==
the
==
categories
==
of
==
safety
==
limits,
==
limiting
==
safety
==
system
==
settings,
==
and
==
limiting
==
control
==
settings.
==
Thus,
==
the
==
==
may
==
not
==
be
==
maintained
==
in
==
plant
==
procedures.
==
Rather,
==
the
==
==
must
==
be
==
specified
==
as
==
a
==
technical-specification-defined
==
limit
==
in
==
order
==
to
==
satisfy
==
the
==
requirements
==
of
==
10
==
CFR
==
50.36.
==
The
==
==
should
==
be
==
developed
==
in
==
accordance
==
with
==
the
==
setpoint
==
methodology
==
set
==
forth
==
in
==
the
==
standard,
==
with
==
the
==
==
listed
==
in
==
the
==
technical
==
specifications.
==
4.
==
ISA-$67.04-1994
==
provides
==
a
==
discussion
==
on
==
the
==
purpose
==
and
==
application
==
of
==
an
==
allowable
==
value.
==
The
==
allowable
==
value
==
is
==
the
==
limiting
==
value
==
that
==
the
==
trip
==
setpoint
==
can
==
have
==
when
==
tested
==
periodically,
==
beyond
==
which
==
the
==
instrument
==
channel
==
is
==
considered
==
==
and
==
corrective
==
action
==
must
==
be
==
taken
==
in
==
accordance
==
with
==
the
==
technical
==
specifications.
==
The
==
6
==
allowable
==
value
==
relationship
==
to
==
the
==
setpoint
==
methodology
==
and
==
testing
==
requirements
==
in
==
the
==
technical
==
specifications
==
must
==
be
==
documented.
==
D.
==
IMPLEMENTATION
==
The
==
purpose
==
of
==
the
==
section
==
is
==
to
==
provide
==
information
==
to
==
applicants
==
and
==
licensees
==
regarding
==
the
==
NRC
==
staffs
==
plans
==
for
==
using
==
this
==
regulatory
==
guide.
==
Except
==
in
==
those
==
cases
==
in
==
which
==
an
==
applicant
==
or
==
licensee
==
proposes
==
an
==
acceptable
==
alternative
==
method
==
for
==
complying
==
with
==
specified
==
portions
==
of
==
the
==
NRC's
==
regulations,
==
the
==
methods
==
described
==
in
==
this
==
guide
==
will
==
be
==
used
==
in
==
the
==
evaluation
==
of
==
submittals
==
in
==
connection
==
with
==
applications
==
for
==
construction
==
permits,
==
operating
==
licenses,
==
and
==
combined
==
licenses.
==
It
==
will
==
also
==
be
==
used
==
to
==
evaluate
==
submittals
==
from
==
operating
==
reactor
==
licensees
==
who
==
voluntarily
==
propose
==
to
==
initiate
==
system
==
modifications
==
if
==
there
==
is
==
a
==
clear
==
nexus
==
between
==
the
==
proposed
==
modifications
==
and
==
this
==
guidance.
==
VALUE/IMPACT
==
STATEMENT
==
A
==
draft
==
value/impact
==
statement
==
was
==
published
==
with
==
the
==
draft
==
proposed
==
Revision
==
3
==
of
==
this
==
guide
==
when
==
it
==
was
==
published
==
for
==
public
==
comment
==
(DG-1045,
==
October
==
1996).
==
No
==
changes
==
were
==
necessary,
==
so
==
a
==
separate
==
value/impact
==
statement
==
for
==
the
==
final
==
guide
==
has
==
not
==
been
==
prepared.
==
A
==
copy
==
of
==
the
==
draft
==
value/impact
==
statement
==
is
==
available
==
for
==
inspection
==
or
==
copying
==
for
==
a
==
fee
==
in
==
the
==
NRC's
==
Public
==
Document
==
Room
==
at
==
2120
==
L
==
Street
==
NW.,
==
==
==
under
==
task
==
DG-1045.
==
7
==
UNITED
==
STATES
==
NUCLEAR
==
REGULATORY
==
COMMISSION
==
==
==
20555-0001
==
OFFICIAL
==
BUSINESS
==
PENALTY
==
FOR
==
PRIVATE
==
USE,
==
$300
==
uiv
==
SN
==
V
==
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==
Oz
==
zo
==
ow
==
'-4
==
%'o0
==
1b
==
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==
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==
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==
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