ML18005A690
| ML18005A690 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/28/1988 |
| From: | Bradford W, Fredrickson P, Shannon M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18005A688 | List: |
| References | |
| 50-400-88-33, NUDOCS 8811090273 | |
| Download: ML18005A690 (17) | |
See also: IR 05000400/1988033
Text
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Report No.:
UNITED STATES,
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323
50-400/88-33
Licensee:
Carolina
Power
and Light Company
P. 0.
Box 1551
Raleigh,
NC 27602
Docket No.:
50-400
License No.:
Facility Name:
Harris
1
Inspection
Conducted:
August 29 - September
20,
1988
Inspectors:
W. H. Bradford
M.
.
han
Approved By:
P.
E. Fredrickson,
Chief, Section
1A
Division of Reactor Projects
D te
S gned
0
Da
e Sig ed
ro
N
Da
e Sig ed
SUMMARY
Scope:
Results:
This
routine safety
inspection
involved the
areas
of operational
safety
verification,
monthly
surveillance
observation,
monthly
maintenance
observation,
radiological
protection
program;
physical
security program,
licensee
events reports,
design
changes
and modifi-
cation,
and refueling activities.
In the
areas
inspected,
one violation was identified:
Failure to
follow approved fire protection procedures
- paragraph
2.
8=:21090273
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EiR
I-'IDOCK 050004C>O
Q
REPORT
DETAILS
Persons
Contacted
Licensee
Employees
R. A. Watson,
Vice President,
Harris Nuclear Project
- C. S. Hinnant, Plant General
Manager
C.
R. Gibson, Director,
Programs
and Procedures
- D. L. Tibbitts, Director, Regulatory Compliance
C.
S.
Bohanan,
Director, Special
Program
R.
B.
Van Metre, Manager,
Technical
Support
- T. C. Morton, Manager,
Maintenance
- J.
M. Collins, Manager,
Operations
- J. R. Sipp, Manager,
Environmental
and Radiation'Monitoring
D. A. Braund, Supervisor,
Security
T.
F. Lentz,
Systems
Engineering
W. R. Wilson, Reactor/Performance
Engineering
- L. J.
Woods, Testing
and Maintenance
Support
W. H. Batts, Supervisor,
Mechanical
Maintenance
J.
H. Smith, Supervisor,
Operations
Support
C.
S. Olexik, Supervisor,
Shift'Operations
G. L. Forehand,
Director,
QA/QC
E.
E. Willett, Manager,
Outages
and Modifications
Other
licensee
employees
contacted
included
technicians,
operators,
mechanics,
securitv
force
members,
engineering
personnel
and office
personnel.
- Attended exit intervie>>
No:e:
and abbreviations
used in the report are listed in para-
graph
11.
Operational
Safety Veri ication (71707)
The inspectors
observed
control
room operations,
reviewed applicable
logs
and
conducted
discussions
with control
room operators
during the report
period.
Also, the operability of selected
emergency
systems
was verified,
tagout
records
were
reviewed
and
proper return to service
of affected
components
was verified.
Tours of the plant were
conducted
tc observe
plant equipment conditions,
including fluid leaks
and excessive
vibrations
and general
housekeeping
efforts.
The inspectors verified compliance with
selected
LCO and results of selected
surveillance tests.
The verifica-
tinns
were
accomplished
by direct observation
of monitoring instrumenta-
tion, valve positions,
switch positions,
accessible
pipe snubbers,
and
review cf completed
logs, records,
and chemistry results.
The licensee's
compliance with LCO action statements
was reviewed
as events
occurred.
The inspectors
routinely attended
meetings with certain
licensee
manage-
ment and observed
various shift turnovers.
These
meetings
and discussions
provided
a daily status
of plant operations,
maintenance,
and testing
activities in progress,
as well
as
discussions
of significant problems.
The inspectors
reviewed
the shift foreman's
log, control
room operator's
log,
clearance
center
tag
out logs,
system
status
logs, chemistry
and
health physics logs,
and control status
boards.
The inspectors
noted that
the operators
appeared
to be alert
and aware of changing plant conditions.
During
a routine plant inspection,
the inspector
noted that
a designated
was
breached
and
was
not identified in the
licensee's
breached fire protection penetration
program.
This discrepancy
led to
a
review of the fire protection
program for fire watches
and fire barrier
penetration control.
Procedure
"Fire Protection
Minimum Requirements
and Mitigating
Actions", requires
the licensee
to establish
hourly fire watch patrols in
areas
where
equipment
is required to be operable
when fire barriers
are
degraded.
Surveillance
and security
access
records
from September
2 to
September
10,
1988,
were
reviewed.
The inspector
found that
on eight
occasions
the interval
between fire patrols
exceeded
the acceptable
time
of one hour and fifteen minutes.
The following list contains
examples
of
this discrepancy
and is not intended to be all inclusive:
Date
Time
Time Between Patrols
September
2,
1988
September
2,
1988
September
2,
1988
2:00 a.m.
6:00 a.m.
3:00 p.m.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,
32 minutes
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,
52 minutes
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,
52 minutes
Also,
on September
9,
1988, it was found that two electrical
conduit runs
were
open in several
places,
thus degrading
two separate
one -
3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> barrier
and
one -
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> barrier.
The fire protection
group
was not aware of the breaches
in the fire walls.
The conduit numbers
were
B 18755X
and
B
18755XX
and
breached
the
"B" emergency
diesel
generator
building
3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire wall and the
"B" electrical
room
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire wall.
Procedure
OMM-003, "Equipment Inoperable
Record", requires
the licensee
to
complete
an equipment
record
and to immediately deliver it to
the shift foreman
when
a fire protection
component
becomes
Fire protection
components (i.e.,
the
two fire barriers)
were inoperable
in the
"B" diesel
generator
building and
an equipment
record
was not completed
as required.
The identified penetrations
have
since
been
placed
in the fire protection
surveillance
program.
No other
degraded
were
found during
the course
of the inspection.
It was
noted
by the inspector that fire
watch patrols
had
been established
in the diesel
generator building due to
other degraded
The failure to perform hourly fire watch patrols
and
the failure to
identify and control
breaches
are collectively considered
to
be
a failure to follow the fire protection
program procedures
and is
identified as Violation
400/88-33-01.'rocedure
"Duties of
a
establishes
the
basic
responsibilities
of
which
includes
documenting
hourly
inspections
and states
the inspection
should consist
not only of looking
for fires, but looking for undue fire hazards.
A total of approximately
150 ins'pections
were
reviewed
and twenty
one inspections
were
found to
have
taken
less
than thirty seconds.
One inspection
was
found to take
nine
seconds
as
documented
by the security
computer.
The fire watch
patrols
were not adequate
because
of the duration of the inspections
and
the licensee
was in effect relying solely on the fire detection
system;
therefore,
not
meeting
the
intent of the
compensatory
surveillance
requirements
of the fire protection
program.
The licensee
had also
made
this determination,
and
implemented
measures
to improve the fire watch
program.
An electronic
key system
was installed
and requires
the fire
watch to walk through the designated
area.
Also, patrol
maps
have
been
developed
and it is the responsibility of the fire watch to inspect
the
area
per the patrol
map.
At this time, the concern with inadequate fire
inspections
appears
to be resolved.
As discussed
above,
the licensee
is dependent
upon compensatory
measures
in order to meet
the fire protection
program
requirements.
The fire
patrol
program
has
become
manpower
intensive
due
to fire protection
equipment
being inoperative,
degraded
or requiring engineering
evaluation.
The inherent
problem with excessive
fire watches
was discussed
with the
licensee
and the licensee
stated
that corrective actions
were being taken
to resolve this concern.
The concern with using
a number of compensatory
measures
in order to meet
the fire protection
program is identified as
Inspector
Followup Item 400/88-33-02.
One violation and
no deviations
were identified.
Nonthly Surveil lance Observation
(61726,
71709)
The inspectors
witnessed
the licensee
conducting maintenance
surveillance
test activities
on safety-related
systems
and
components
to verify that
the licensee
performed the activities in accordance
with licensee
require-
ments.
These
observations
included witnessing
selected
portions of each
surveillance,
review 'of
the
surveillance
procedure
to
ensure
that
administrative
controls
were
in force,
determining
that
approval
was
obtained prior to conducting the surveillance test,
and verifying that the
individuals conducting
the test
were qualified in accordance
with plant
approved
procedures.
Other observations
included ascertaining
that test
instrumentation
used
was
calibrated,
data
collected
was within the
specified requirements
of Technical Specifications,
any identified discre-
pancies
were properly noted,
and the
systems
were correctly returned
to
service.
Portions
of the following test activities
were
observed
or
reviewed
by the inspectors:
Diesel
Generator
Instrument
Calibration,
Rev.
2.
Diesel
Generator
1B-SB Lube Oil Instrument Calibration.
Diesel
Generator
1B-SB Lube Oil Sump Tank Low Level
Calibration.
OST-1006
OST-1013
OST-1819
Boron Flow Path Verification.
1A-SA Emergency
Diesel Generator Operability Test.
Fuel Handling Building Crane Interlocks
and Operability
Test.
No violations or deviations
were identified.
Monthly Maintenance
Observation
(62703)
Station
maintenance
activities of safety-related
systems
and
components
were observed/reviewed
to ascertain
that they were conducted
in-accordance
with approved
procedures,
regulatory guides,
industry codes
and standards,
and
were in conformance with Technical Specifications.
Items considered
during
the
review included:
verification that limiting conditions for
operations
were met while components
or systems
were
removed
from service;
approvals
were obtained prior to initiating the work; approved
procedures
were used;
completed
work was
inspected
as applicable;
functional testing
and/or
calibrations
were
performed
prior to returning
components
or
systems
to service; quality control
records
were maintained; activities
were
accomplished
by qualified
personnel;
parts
and
materials
were
properly certified;
and radiological
and fire prevention
controls
were
implemented.
Work requests
were also reviewed to determine
the status
of
outstanding
jobs to assure
that priority was assigned
to safety-related
equipment maintenance
which may affect system
performance.
On August 29,
1988,
the inspector witnessed
bench troubleshooting of the
inverter that
had previously failed
on August 12,
1988.
No
problems
had
been identified with the
power source,
loads
or
internal
to
the
inverter
except
the
output transistors.
Overload
conditions
and loss of input power tests
were performed
and the inverter
functioned properly.
One output transistor
was shorted
and the companion
transistor
experienced
an
identical
failure to
the
August 12,
1988
failure.
Root
cause
has
been
determined
to
be
a
.random transistor
failure.
Portions of the following activities were observed
or reviewed:
FHP-20
PM-E005
BZZ-33
Fuel Handling Bridge Crane Repair.
6.9
KY 1200/2000
Amperage Air Circuit Breaker Preventative
Maintenance,
Revision 4.
Work Request for 1B Bus Outage.
No violations or deviations
were identified.
Radiological Protection
Program
(71709)
Selected activities of the licensee's
Radiological Protection
Program were
reviewed
by the inspectors
to verify conformance with plant procedures
and
NRC regulatory requirement.
The areas
reviewed included:
organization
and
management
of the plant's
health
physics staff;
"ALARA" implementa-
tion; Radiation
Work Permits
(RWPs) for compliance to plant procedures;
personnel
exposure
records;
observation of work and personnel
in radiation
areas
to verify compliance to radiation protection procedures;
and control
of radioactive materials.
No violations or deviations
were identified.
Physical
Security Program
(71881)
Licensee's
compliance
to the
approved
security plan'as
reviewed
by the
inspectors.
The inspectors
verified by observation
and interviews with
security force
members
that measures
taken to assure
the physical protec-
tion of the facility met current requirements.
Areas
inspected
included:
organization
of the security
force;
establishment
and
maintenance
of
gates,
doors,
and isolation zones;
access
control;
and badging procedures.
No violations or deviations
were identified.
Licensee
Event Reports
(92700)
The following Lice'nsee
Event
Reports
(LER) were
reviewed for potential
generic
problems
to determine
trends,
to determine
whether
information
included
in the
report
meets
the
NRC reporting
requirements
and
to
consider
whether
the corrective action
discussed
in the report
appears
appropriate.
The licensee
action
was
reviewed to verify that the event
has
been
reviewed
and
evaluated
by the
licensee
as
required
by the
Technical
Specifications;
that
corrective
action
was
taken
by
the
licensee;
and that safety limits, limiting safety setting
and
LCOs were
not
exceeded.
The
inspector
examined
the incident report,
logs
and
records,
and
interviewed
selected
personnel.
The following reports
are
considered
closed:
LER 86-01
LER 86-09
LER 87-05
LER 87-06
LER 87-08
LER 87-09
LER 87-11
LER 87-12
LER 87-13
Turbine Building Stack Monitor.RM-ITY-3536-1 Inoperable.
Inadequate
Safety Injection Signal
Due to Procedure
Inadequacy.
Reactor Trip/Condensate
Pump Trip Caused
by "Low Discharge
Pressure."
1B-SB Chiller Start Failure.
Reactor Trip - Loss of Main Feedwater.
Containment
Leak Detection Radiation Monitor Inoperable.
6.9
KV Onsite Distribution.
Reactor Trip During Turbine Rotor Instrumentation Testing.
Reactor Trip - Loss of Feedwater.
LER 87-14
LER 87-17
LER 87-18
LER 87-22
LER 87-23
LER 87-24
Containment Integrity; Containment Isolation Valve Open for
Longer Than Allowed by Technical Specification.
Reactor Trip - Loss of Feedwater.
Technical Specification Violation - Missed
Flow Rate
Estimates.
Isolated Miniflow Path for 1C-SAB Charging/Safety
Injection A.
Reactor Trip - Loss of Heater Drain
Pump "B".
No violations or deviations
were identified.
8.
Design,
Design Changes,
and Modification (37700)
a 0
Permanent Modifications
The
inspectors
reviewed
selected
design
changes
and modifications
which were determined
by the licensee
to not require
NRC approval to
ascertain
that the design
changes
and modifications are in conform-
ance
with the
requirements
of the
TS
and
Items
reviewed
included verification that:
design
changes
were
reviewed
and
approved
in accordance
with
design
changes
were
controlled
by approved
procedures;
operability tests
were conducted;
LCO requirements
were
met while components
or systems
were
removed
from service to accomplish
the design
changes;
as-built drawings
were
changed
or controlled to reflect the design
changes;
and, preventive
maintenance,
surveillance
test
and
operating
procedures
had
been
revised
or were
scheduled
to
be revised
to reflect design
changes.
The following design
changes
and modifications
were
reviewed
or
observed
to verify that
the work was
being conducted
in accordance
with appropriate
construction
documents,
inspected
by gC inspectors,
tested
in accordance
with appropriate
test
procedures,
and appro-
priate fire prevention
and housekeeping
controls
were implemented.
PCR-2109
PCR-2992
PCR-3029
PCR-3185
PCR-3297
PCR-3509
PCR-3521
Leakage.
Boron Injection Tank Bypass
Line Plugging.
"C" Charging
Pump Recirculation Valve.
(RVLIS) Reactor
Vessel
Level Indication System
Isolation Valve Installation.
Soft Seat
Replacement
(Anchor-Darling).
Drip Leg Line Reroute.
Check Valve 1AF-68 Hinge Pin Seal
Weld.
No violations or deviations
were identified.
The inspectors will continue
to review other design
changes
and modifications.
9..Refueling Activities (60710)
The
inspectors
observed
refueling activities
and
reviewed
certain
documentation
and procedures
to verify that the activities were controlled
and
conducted
in accordance
with Technical
Specifications
and
approved
procedures.
This
inspection
included,
but is
not limited to,
the
following:
Approved procedures
were
used for fuel accountability.
Core monitoring was performed throughout the fuel movement.
Mater levels
and boron concentration
were maintained.
Containment integrity was maintained.
Communication
between
refueling stations
and
the control
room were
maintained.
A qualified senior reactor
operator
supervised
the refueling opera-
.ion
and
the refueling
personnel
were qualified to perform the
refueling functions.
No violations or deviations
were identified.
10.
Exit Interview
The
inspection
scope
and
findings
were
summarized
during
management
interviews
throughout
the report period
and
on September
22,
1988, with
the plant
manager
and
selected
members
of his staff.
The inspection
findings were discussed
in detail.
The licensee
acknowledged
the inspec-
tion findings listed
below
and
did not identify as
proprietary
any
material
reviewed
by the inspection during this inspection.
Item Number
400/88-33-01
400/88-33-02
Descri tion/Reference
Para
ra
h
VIOLATION - Failure to Follow the Fire
Protection
Program
Procedures
(paragraph
2).
IFI - Concern With Using
a Number of Compensatory
Measures
in Order to iieet the Fire Protection
Program
(paragraph
2)..
11.
List of Acroynyms and Abbreviations
AFM
ALARA-
LCO
As Low As Reasonably
Achievable
Fuel Handling Procedure
. Fire Protection
Program
Limiting Condition for Operation
LER
OMM
OST
PN
RN
TS
Licensee
Event Report
Maintenance
Surveillance Test
Operations
Management
Manual
Operations
Surveillance Test
'Plant
Change
Request
Preventative
Maintenance
Radiation Monitor
Radiation
Work Permit
Technical Specification
4