ML17215A775
| ML17215A775 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/26/1985 |
| From: | Bibb H, Crlenjak R, Elrod S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17215A776 | List: |
| References | |
| 50-335-85-03, 50-335-85-3, 50-389-85-03, 50-389-85-3, NUDOCS 8503190308 | |
| Download: ML17215A775 (6) | |
See also: IR 05000120/2002016
Text
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UNITEDSTATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323
Report Nos.:
50-335/85-03
and 50-389/85-03
Licensee:
Florida Power and Light Company
9250 West Flagler Street
Miami, FL
33102
Docket Nos.:
50-335
and 50-389
Facility Name:
St. Lucie
1 and
2
License Nos.:
and
Inspection
Conducted:
January
20 - February
16,
1985
Inspectors:
r
Ja
Aced 8
Date Signe
Approved by:
S.
.
ro
,
ection
ie
Division of Reactor Projects
ate
igne
2.z
PW
ate
~gne
SUMMARY
Scope:
This routine,
unannounced
inspection
entailed
179 resident
inspector-
hours
onsite
in the
areas
of plant operation,
surveillance
observation,
maintenance
observation,
and procedure/drawing
review.
8503190308
850226
ADOCK 05000335
8
REPORT DETAILS
Persons
Contacted
Licensee
Employees
- C. M. Wethy, Plant Manager
- J. H. Barrow, Operations
Superintendent
T. A. Dillard, Maintenance
Superintendent
L. W. Pearce,
Acting Operations
Supervisor
N.
G. Roos, guality Control Supervisor
C. F. Leppla, Instrument
& Control Supervisor
C. A. Pell, Acting Technical
Department Supervisor
H. F. Buchanan,
Health Physics
Supervisor
J.
G. West, Security Supervisor
J. Barrow, Fire Prevention
Coordinator
J. Scarola, Assistant Plant Superintendent-Electrical
- J. Walls, guality Control Department
- N. Weems, guality Assurance
Supervisor
Other
licensee
employees
contacted
included
construction
craftsmen,
technicians,
operators, shift technical
advisors,
security force members
and
office personnel.
Exit Interview
The resident
inspectors
attended
entrance
and exit interviews
conducted
during the inspection period by Region II inspector
B. R. Crowley.
The resident
inspectors
also
conducted
interim interviews with licensee
management
during the inspection
period
and held
an exit interview at the
conclusion of the inspection.
The inspector
discussed
the
scope of the
inspection
and his findings with the licensee.
Persons
indicated with an asterisk
(*) in paragraph
1 above attended
one or
more interviews.
The licensee
did not identify as proprietary
any of the materials
provided
to or reviewed by the inspector(s)
during this inspection.
Licensee Action on Previous
Enforcement Matters
Closed
- Unit 2
(Unresolved
Item 389/84-37-01)
- Apparent
disagreement
between
Safety
Injection
Tank
(SIT)
"Green
Band" Limits and Technical
Specification
Maximum Limits.
The inspector
reviewed the Shift Technical
Adviser's
response
submitted
on February
12,
1985 and agreed that the upper
edge of the
green
band
and
the
HI-HI alarm setpoint
correspond
to SIT
volumes less
than the technical specification upper limit.
0
Unresolved
Items
2
.Unresolved
Items were not identified during this inspection.
Operational
Safety Verification
The inspector
observed control <room operations,
reviewed applicable logs
and
conducted
discussions
with Control
room operators
during the report period.
The
inspector
verified the operability of selected
emergency
systems,
reviewed tagout
records
and verified proper return to service of affected
components.
Tours of the reactor,
auxiliary and turbine building were
conducted
to observe
plant equipment conditions,
including potential fire
hazards,
fluid leaks,
and
excessive
vibrations
and
to verify that
maintenance
requests
had
been
initiated for
equipment
in
need
to
maintenance.
The inspector,
by observation
and direct interview, verified
that the physical security plan was being implemented in accordance
with the
station security plan.
General
Status
6.
Both units
operated
at
100% output throughout
the period
except for
a
one-day
shutdown
(Saturday
5 Sunday,
February
9 - 10) of Unit 2 to repair
some minor oil leaks
on
pump.
A meeting
was held in Miami
at
the corporate
headquarters
to present
the
NRC's findings
from the
recently
conducted
Systematic
Assessment
of Licensee
Performance
(SALP)
(ref. Report Nos. 50-335/85-02
and 50-389/85-02).
Maintenance
Observation
Station
maintenance
activities
of selected
safety-related
systems
and
components
were observed/reviewed
to ascertain
that they were conducted
in
accordance
with requirements.
The following items were considered
during
this review:
the limiting conditions for operations
were met, activities
were
accomplished
using
approved
procedures,
functional
testing
and/or
calibrations
were
performed prior to returning
components
or systems
to
service; quality control
records
were maintained; activities were
accom-
plished
by qualified personnel;
parts
and materials
used
were properly
certified;
and radiological controls
were
implemented
as required.
Work
requests
were reviewed to determine status of outstanding
jobs and to assure
that priority is assigned
to safety-related
equipment maintenance
which may
affect system performance.
The inspector
personally
observed
work on the following components
and
subsequently
reviewed
the
completed
paperwork to assure
completeness
and
'ccuracy.
PWO-726
PWO-727
PW0<<736
IWV-08-13, Repair Valve Seat
IWV-08-12, Repair Valve Seat
IWV-08-12, Inspect Internals
7.
Surveillance Observation
During the inspection
period,
the inspector verified plant operations
in
compliance with at least
sixteen different technical
specifications
(TS)
requirements.
Typical of these
were confirmation of compliance with the
TS
for reactor
coolant chemistry, refueling water tank, containment
pressure,
control
room ventilation
and
IIIC and
DC electrical
sources.
The inspector
verified that testing
was performed in accordance
with adequate
procedures,
test instrumentation
was calibrated, limiting conditions for operations
were
met,
removal
and restoration of the affected
components
were accomplished,
test results
met requirements
and were reviewed
by personnel
other than the
individual directing the test,
and that any deficiencies identified during
the testing
were properly reviewed
and resolved
by appropriate
management
personnel.
8.
Procedure/Drawing
Review
The following procedures
were reviewed by the inspector:
EP 1-0120040,
Rev.
EP 1-0120034,
Rev.
EP 1-0030131,
Rev.
EP 1-0030132,
Rev.
EP 1-0030130,
Rev.
OP 2-1400063,
Rev.
15 - Natural Circulation/Cooldown
13 - Reactor Coolant
Pump - Off Normal Operation
21 - Plant Annunciator
Summary
1 - Anticipated Transient Without Scram
20 - Reactor
Trip/Turbine Trip
3 - Sequence
of Events
Recorder
Program Loading
Several
errors
were noted, mostly of an editorial nature,
and were reported
to
gC personnel
for correction
in subsequent
revisions.
The
number of
errors,
however,
points out the
need for continued diligence
and attention
to detail
when reviewing documents prior to issue.
The following drawings
were
reviewed
and it was noted that
some erroneous
valve positions
had
been corrected
as requested
by the inspector:
2998-G-088,
Rev.
14 - Containment
Spray
I% Refueling Water Systems
(Unit 2)
8770-G-088,
Rev.
15 - Containment
Spray
5 Refueling Water Systems
(Unit 1)
0