ML17348B245
| ML17348B245 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/12/1991 |
| From: | Hunt M, Shymlock M, Casey Smith, Taylor P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17348B243 | List: |
| References | |
| 50-250-91-35, 50-251-91-35, NUDOCS 9111220056 | |
| Download: ML17348B245 (5) | |
See also: IR 05000250/1991035
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UNITEDSTATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323
Report Nos.:
50-250/91-35
and 50-251/91-35
Licensee:
Florida Power
and Light Company
9250 West Flagler Street
Miami,
FL
33102
Docket Nos.:
50-250
and 50-251
Facility Name:
Turkey Point
3 and
4
Inspection
Conducted:
August 26-30,
1991
Inspectors:
M.
.
unt
P..
yo
License Nos.:
and
ate
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ne
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WJ
ate Signed
t
C.
F. Smith
Approved by:
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hym oc,
ie
Plant Systems
Section
Engineering
Branch
Division of Reactor Safety
a
e S)gned
ll-iZ
ate
igne
SUYiNARY
Scope:
This routine
announced,
inspection
was
conducted
in the
areas
of equipment
qualification, chemical
and volume control system calculations,
sequencer
relay
failure evaluations
and power mismatch circuitry.
Results:
0
In the areas
inspected,
one violation was identified.
Violation 50-250,251/91-35-01,
Failure to maintain current
and
accurate
Eg
Documentation
Package
(Paragraph
2a).
The
review of
CVCS calculations
and
the
operation
of the
power
mismatch
circuitry was initiated during the inspection.
These
areas
required further
inspection
at
FPSL
Corporate
Engineering/Design
Groups.
Accordingly the
inspection
results
for these
areas
are
documented
in
NRC Inspection
Report
50-250,
251/91-45.
91112~c;0056
91111'DR
ADDCIi 050002".yo
8
REPORT
DETAILS
1.
Persons
Contacted
Licensee
Employees
- J. Aries, Vice President Assistant
- S. T. Hale, Engineering
Manager
- J. Hartzog,
SPEAKOUT Superviso
J.
Hardy,
I8C Supervisor
, H. Johnson,
Operations
Supervisor - Nuclear
- L. W. Pearce,
Plant Manager
- T. F. Plunkett,
Vice President
- D. R. Powell, Licensing Superintendent
Other
licensee
employees
contacted
during this
inspection
included
engineers,
operators,
and administrative
personnel.
NRC Resident
Inspectors
- R. Butcher
L. Trocine
- Attended exit interview
2.
Engineering/Design Activities (37700)
a.
Review of Environmental qualification Files
The
inspectors
reviewed
16
Documentation
Packages
(Doc Pacs)
to
verify the status of the documentation
used to establish
qualifications
for
selected
equipment
and
to
evaluate
the
effectiveness
of the
change
process
used for revising/updating
the
Doc'acs.
Based
on
these
reviews
the
inspectors
determined
that
changes
to
the
Doc Pacs
involving editorial
type
changes
are
generally
completed
in
an expeditious
manner.
Changes
involving
design
basis
information,
however,
need
to be accomplished
through
the
design
controls
and
implemented
via
PC/M
packages.
Most of the
Doc
Pacs
were determined
not to be current
'ecause
of
PC/M packages
that were still in the
process
of being
implemented
or not yet closed out.
The inspectors
performed
independent
design reviews of selected
PC/Ms
to verify the traceability for the plant modifications,
the design
basis
information specified
in the
PC/M,
and
to
comfirm that
provisions
had
been
made
to incorporate
these
changes
in the
Doc
Pacs.
Additionally, the
Nuclear
Safety
Evaluations
performed
pursuant to the requirements
of 10 CFR 50.59 were critically reviewed
to ensure
that
no degradation
of environmental
qualifications
had
occurred
during the
PC/Ms preparation.
The following Doc Pacs
and
related
PC/Ms were reviewed:
Doc Pac 6.0
Doc Pac 6.2
Doc Pac
10. 0
Doc Pac
17.2,
Doc Pac
24. 1
Doc Pac 26.0
Doc Pac 31.5
Doc Pac 33.0
PC/M 90-494, Revision
1
PC/M 90-484, Revision
1
PC/M 81-157,
CRN-12
PC/M 85-35,
CRN-)56
PC/M 85-36,
CRN-J72
PC/M 85-109
PC/M 90-484,
Revision
1
PC/M 89-206
PC/M 88-468
PC/M 91-029
PC/M 88-463
Based
on the above reviews, the inspectors
identified two issues
with
potential
safety concerns.
The first involved Doc Pac 6.2 and
PC/Ms
85-35
and
85-36
where
a modification
was
made
in the field by the
licensee
to
CONAN RTDs identified as
model
Pursuant
to this field modification
a similarity analysis
was not performed to
demonstrate
that the installed
RTDs were environmentally qualified
per
This issue
was
resolved
when the vendor
transmitted
information to
the licensee
which provided
a basis for
similarity to, the tested
specimen.
The other
issued
involved
a
deficiency in the Safety Evaluation of PC/M 85-109 which failed to
provide
a design
basis for installing
a signal
transmitter
in
a
potential radiation harsh
environment.
This issue
was resolved
when
the
licensee
provided
a
design
basis
radiation
dose
calculation
contained
in
Doc
Pac
1001,
Appendix
Q, which clearly demonstrated
that the instrument location is in a radiation mild environment.
The inspectors
concluded that eight Documentation
Packages
were not
current
during
the inspection,
in that Plant
Change
Modification
Packages
were
not closed
out in
a timely manner
to facilitate
revision
of
the
Documentation
Packages.
Additionally, design
controls
inadequacies,
such
as failure to implement the requirements
of Plant
Change
Modification 81-157,
Change
Notice
No.
12,
has
resulted in
EQ documentation
inaccuracies
since at least August 1989,
in that
EQ qualification requirements
for
RTDS are
shown to
be
simultaneously
satisfied
by different Documentation
Packages.
The
inspectors
identified this area
as Violation (50-250, 251/91-35-01),
Failure to maintain current
and accurate
EQ Documentation
Packages
as
required
by
FPIIL management
in recognition of these
concerns
in the
EQ Program controls
issued
a
memorandum
from the
Engineering
Project
Manager,
dated
August 30,
1991,
identifying
actions
planned to ensure
EQ documentation
is accurate
and kept up to
date.
The inspector
reviewed objective evidence
presented
by the licensee
to
prove that
some staff
members
had
been
indoctrinated
in the
requirements
of the
EQ Program.
A formal
EQ Training Program
has not
b.
been
developed
by the licensee.
The inspectors
were informed that
actions
required to do so were presently
ongoing.
It is licensee's
management's
intention
to
- have
all
personnel
involved
in
Eg
activities properly trained,
however,
'a schedule
for completing
Eg
training of site
personnel
has
not been established
because
of the
present
dual unit outage.
Sequencer
Relay Failure Evaluation
Review
During the
performance
of Pre-operational
Test
0804.043
(logic
. testing)
for Sequencer
3B the coil
on
a stripping
relay short
circuited.
The failure was determined to be generic for this type of
relay
and all relays
in the sequencers
spares
at Turkey Point were
replaced.
Subsequently
a
second
relay failure
occurr'ed
during
testing.
Trouble shooting determined that contacts, on the relay were
dislodged
and shorted to adjacent contacts.
Investigation
revealed
that
a manufacturing
defect
existed
in
a
series
of relays
assembled
during the March
1989 to September
1990
period.
The defect
was
improper installation of insulating
tape
between
the coil
and
the
inner winding terminal.
The inspection
findings resulted
in the
sequencer
vendor,
and
ASEA Brown Boveri,
(ABB) notifying the
NRC of
a potential
generic
defect
per
10 CFR Part 21 for relay model
RXMH-2.
The licensee verified that the only
other
relays
of this
model
were in the Unit
3
Emergency
Diesel
Generator
(EDG) Idle Start
System.
After the discovery of the
generic
defect
the
vendor
furnished
replacement
relays
for all
sequencers
and
spares
with the
proper
installation of insulating
tape.
The
second
relay failure was analyzed
by ABB and it was determined
that
a manufacturing deficiency
does
not exist and that the probable
root cause
was shipping
damage.
To eliminate
the
second
identified failure
mechanism all
RXMH-2
relays
were
inspected
and functionally tested
to verify proper
installation
of
the
contacts.
Applicable
portions
of
the
pre-operational
tests
were repeated
to verify proper reinstallation
of the relays in each
sequencer.
3.
Exit Interview
The inspection
scope
and results
were summarized
on August 30,
1991, with
those
persons
indicated
in paragraph
1.
The inspectors
described
the
areas
inspected
and discussed
in detail the inspection results.
Although
reviewed during this inspection,
proprietary information is not contained
.
in this report.
Subsequent
to
the
inspection
a
telecon
between
C. Julian
(Chief,
Engineering
Branch)
and L.
W. Pearce,
Turkey Point Plant Manager
was held
to identify the
concerns
with the
Eg
Documentation
Packages
as
a
violation.
Violation 250,
251/91-35-01,
Failure to maintain current
and accurate
Eg
Documentation
Packages
as required
by 10 CFR 50.49.