ML17319B126
| ML17319B126 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/15/1981 |
| From: | Dubry N, Hayes D, Swanson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17319B124 | List: |
| References | |
| 50-315-81-28, 50-316-81-32, NUDOCS 8201060564 | |
| Download: ML17319B126 (10) | |
See also: IR 05000315/1981028
Text
U.S.
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports
No.
50-315/81-28;
50-316/81-32
Docket Nos.
50-315;
50-316
Licenses
No. DPR-58;
Licensee:
American Electric Power Service Corporation
Indiana and Michigan Electric Company
2 Broadway
New York, Ny
10004
Facility .Name:
D.
C.
Cook Nuclear Plant, Units 1 and
2
Inspected At:
D.
C.
Cook Site,
Bridgman, MI
Inspection
Conducted:
ovember l through December
15,
1981
Inspectors:
E.
R.
Swanson
Iz ~s. 8'/
l2-r. -s
Approved By:
D. W. Hayes,
Chief
Reactor Projects
Section
1B
Ins ection
Summar
Ins ection on November l throu h December
15
1981
(Re orts No. 50-315/81-28;
50-316/81-32)
Areas Ins ected:
Routine, onsite regular and backshift inspection conducted
by resident inspectors.
Areas inspected
included:
Followup on Previous Inspection
Findings, Operational
Safety, Surveillance,
Maintenance,
Licensee
Event Reports,
Plant Trips,
and Significant Events
and Independent
Inspection.
The Inspection
involved a total of 188 inspection-hours
onsite by two NRC inspectors
including
29
inspector-hours
onsite during off-shift hours.
Results:
Of the seven areas
inspected
no items of noncompliance or deviations
were identified in six areas.
One item of noncompliance
was identified in
one area.
(Failure to maintain N-List up-to-date,
paragraph
2).
82010b05b4
811221
ADOCK 05000315
8
DETAILS
1.
Persons
Contacted
- D. Shaller,
Plant Manager
- B. Svensson,
Assistant Plant Manager
- E. Townley, Assistant Plant Manager
E. Smarrella,
Technical Superintendent
- J. Stietzel, Quality Assurance
Supervisor
- H. Chadwell, Operations
Superintendent
R. Dudding, Maintenance
Supervisor
The inspectors
also contacted
a number of licensee
employees
and inform-
ally interviewed operators,
technicians,
and maintenance
personnel
during
the inspection.
- Denotes
those present 'during exit interviews.
2.,
Followu
on Previous
Ins ection Findin s
(Closed)
315/80-01-01;
316/80-01-01,
N-List (Safety related items)
not maintained.
The inspector reviewed the licensee's
response
to
the noncompliance
(AEP:NRC:00414
May 28, 1980)
and verified that a
computerized list is being maintained utilizing the referenced
AEPSC
QA procedure.
However, the list had been updated recently but a review of the list
for the inclusion of the N-Train Batteries
revealed that they had
not been placed
on the list.
These batteries
supply power to safety
related valves
and components.
They were added by a design
change
(RFC-2222)
completed during the same time frame the upgrading work
was being done on the N-List (early 1980).
This omission is contrary
to the N-List procedure
(QAP-131) which states
that "All N items for
the D.
C.
Cook Nuclear Plant shall be listed on the D.
C.
Cook N-List,"
and this is a violation of procedural controls
as set forth in the
Appendix to the transmittal letter.
Further, this omission was the
only item the inspector attempted
to locate in the list and many
other omissions
may exist.
The thoroughness
and adequacy of the
licensee's
corrective actions were discussed
at the management
meeting on December
9, 1981.
(50-315/81-28-01;
50-316/81-32-01)
0 erational Safet
Verification
The inspector observed control room operations,
reviewed applicable
logs,
and conducted
discussions
with control room operators
about
observed
equipment line-ups
and indications,
work in progress,
scheduled
tests
and jobs during the period of November
1 through December
15,
1981.
These observations
were done to identify significant changes
and trends,
verify the operability of selected
emergency
systems,
review out of
'service
equipment logs, verify that limiting conditions for operations
(LCO) were being met,
and that affected
components
were properly
returned to service.
During this inspection period the inspector walked down accessible
portions of the'omponent
cooling water systems
and emergency diesel
generator
systems.
The reviews
and observations
were conducted
to verify that facility
operations
were in conformance with- the requirements
of the licenses,
technical specifications,
10 CFR,
and administxative procedures.
During this inspection period, which included backshifts,
the inspector
conducted
tours of accessible
areas
and observed
the control rooms,
turbine building, auxiliary building, security facility, the yard area,
lighting, vehicular control, badging
and escorting,
and portal monitor-
ing.
The observations
also
encompassed
plant equipment conditions
including job order's for equipment in need of repair, fire hazards,
and housekeeping.
Surveillance
Observations
The'nspector
observed
technical specifications
required surveillance
testing on the Overtemperature
and Overpower Protection
Set and
verified that testing was performed in accordance
with adequate
pro-
cedures,
that test instrumentation
was calibrated,
that limiting
conditions for operation were met, that removal and restoration of
the affected
components
were accomplished,
that test results
conformed
with, technical specifications
and procedure
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.
The inspector also witnessed portions of the following test activ-
ities:
1 THP6030 IMP.095
1 THP4030
~ 005
12 THP6010. Km'435-.-2.
2 THP6030 IMP.231
2 OHP4030
STP.017
2 OHP4030
STP.005
1 THP4030
STP.077
Delta T/T average Protection Set II Calibra-
tion ~,
Overtemperature
and Overpower Protection Set
II Surveillance Test.
Supplied Air Respirator Inspection.
Power Range Nuclear .Instrumentation Calibration.
System Test
(TDAFP)
Pump Operability Test
(RHR Recarculating
Flow Reset).
Diesel Generator
1 AB Undervoltage Protection
Surveillance Test (monthly).
w,v ~
t 'f,
gg
12 THP6030 IMP142
2 THP4030 STP.112
5.
Maintenance
Observation
Fire Detection Instrumentation
and Cardox
System Surveillance Testing.
Pressurizer
Pressure
Protection
Set II
Surveillance Test (monthly) .
I
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,
and industry
codes or standards,
and in conformance with technical, specifications.
The following items were considered
during this review: The limiting
conditions for operation were met while components
or systems
were
removed from service;
approvals
were obtained before initiating the
work; activities were accomplished
using approved
procedures
and
were inspected
as applicable;
functional testing and/or calibrations
were performed before returning
components
or systems
to service;
quality control records
were maintained; activities were accomplished
by qualified personnel;
parts
and materials
used were properly
certified; and radiological controls
and fire prevention controls
were implemented.
Work requests
were reviewed to determine status of outstanding
gobs
and
to assure
that 'priority is assigned
to safety related
equipment main-
tenance
which may affect system performance.
The following maint'enance activities were observed/reviewed:
Unit
1
Delta T/T average Protection
Set IV Calibration
Maintenance
Repair Procedure for Limitorque
Valve Operators.
THP6030 IMP.097
12 MHP5021.001.006
Unit
2
Maintenance
Procedure for Inspection
and Repair
of Crosby Nozzle Relief Valves.
MHP5021.001.011
Two Inch and Over Safety Valve Setpoint Veri-
cation by Bench Test.
12 MHP5021.001.034
Following completion of maintenance
on, the Component
Cooling Water system
the inspector verified it had been returned to service properly.
On November 3,
1981 Unit 1 experienced
a feed flow/steam flow mismatch
reactor trip from 100% power caused
by loss of the west main feed
pump.
The feed
pump tripped on low oil pressure
which resulted
from improper
shifting of the lube oil strainer.
The inspector reviewed the event
and verified that the proper corrective actions were taken.
Subsequent
to the reactor trip, Unit 1 remained
shutdown for an ex-
tended maintenance
outage to work on some of the TMI Task Action
Plan items.
The unit was returned to power at 0815 on November 15,
1981.
An overtemperature
delta temperature
(OTdT) trip on Unit 1 occurred
on November 17, 1981.
The loop
3 T-average
and delta
T instrument
had been oscillating sporatically before the event
and this combined
with a spurious signal from loop 4 resulted in a reactor trip.
There
was
no Safety Injection signal generated.
The inspector
determined
the status of the reactor
and safety systems
by observing control room indications
and discussed
plant parameters
with licensee
personnel.
The inspector verified proper
communica-
tions were established
and reviewed the corrective actions
taken by
the licensee.
All systems
functioned
as. expected,
and the plant was returned
to
power at 1144 on November 18, 1981.
Si nificant Events
and Inde endent Ins ection
tl
The inspector monitored the emergency drill held on November 18,
1981.
This included observation of the licensee's
emergency
response
plan
utilization, coordination
and communication between
the control room,
the
TSC (Technical Support Center),
OSA (Operational Staging Area),
and
AEPSC.
With few exceptions
the drill progressed
rapidly and smoothly.
The most significant exception was the problem of establishing
a number
of communication hookups in the
TSC and timeliness of information being
disseminated
from the TSC.
These were addressed
during the critique.
The inspector also looked into un'planned
and unmonitored releases
occurring during this inspection period.
Attention was given to this
area because
of the elevated iodine levels the licensee is experiencing
in the reactor coolant system.
Licensee
Event
Re orts Followu
Through direct observation,
discussions
with licensee
personnel
and
review of records,
the following event reports
were reviewed to deter-
mine that reportability requirements
were fulfilled, immediate correct-
ive action was accomplished,
and corrective action to prevent recurrence
had been accomplished in accordance
with technical specifications.
un~a
1
RO 81-013/03X-1
RO 81-018/03L-0
Both Source
Range Nuclear Instruments inoper-
able.
(Revision)
Loss of Source
Range Detector voltage.
RO 81-027/03L-0
RO 81-027/03X-1
RO 81-029/03L-0
RO 81-029/03X-1
ILRT failure due to valve repair during
stabilization period.
ILRT failure due to valve repair during
stabilization period. (revision)
Pressurizer
heat'up rate exceeded
100 /hr.
Pressurizer
heat
up rate exceeded
100 /hr.
(revision)
Unit 2
RO 81-005/01T-0
RO 81-005/01T-1
RO 81-050/01T-0
RO 81-053/03L-0
Spray Additive Tank found below minimum level.
Spray Additive Tank found below minimum level.
(revision)
Check valve SI-152S found to have no disc.
due to missing clevis pin.
(Open) Unit 2
RO 81-059/03L-0 Pressurizer
pressure
below minimum
(T.S. 3.2.5).
As discussed
with plant management
this event report
is devoid of any corrective actions in spite of the investigations
that have been undertaken
to determine
the root cause.
Several signi'f-
icant material conditions
and personnel
errors were identified,yet no
proposed or planned corrective actions were discussed.
During a management
meeting on December
9,
1981 the inspector
was
informed that there is an ongoing engineering
study to determine what,
if anything,
should be done with the pressurizer
heaters;
that job
orders have been written to work on the pressurizer
spray valves
during the next outage;
and that precautions
have been added to the
standard
clearance
form used when returning equipment to service.
The licensee
plans to revise this event report when their corrective
actions are more clearly formulated.
9.
Exit Interview
The inspector
met with licensee representatives
(denoted in paragraph
1)
throughout the month and at the conclusion of the inspection
and
summarized
the scope
and findings of the inspection activities.
The
licensee
acknowledged
the item of noncompliance
(paragraph
2) and dis-
cussions relative to Licensee
Event Reports
contained in Paragraph
8.