ML17262A521
| ML17262A521 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/30/1991 |
| From: | Baunack W, Oliveira W, Taylor D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17262A520 | List: |
| References | |
| 50-244-91-11, NUDOCS 9106200251 | |
| Download: ML17262A521 (20) | |
See also: IR 05000244/1991011
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report
No.
Docket No.
License
No.
Licensee:
50-244/91-11
50-244
Rochester
Gas 5 Electric Co.
49 East Avenue
Rochester
14649
Facility Name:
Inspection At:
Inspection
Conducted:
R.
E. Ginna Nuclear
Power Plant
Ontario
A ril 22 - 26
1991
Inspectors:
. Taylor, Reactor
Engineer
PS,
date
W. Baunack,
Sr.
Reactor Engineer,
OPS,
d te
W. Oliveira, Reactor
Engineer,
OPS,
date
Approved b
.
B
um
rg, Chief, Perfor
nce
Programs
Section,
Operations
Branch,
date
Ins ection Summar:
Ins ection
on A ril 22 - 26
1991
Ins ection
Re ort
~/
Areas Ins ected:
Routine unannounced
safety inspection
by three region-based
inspectors
to review the status of maintenance
program weaknesses
identified
during the Maintenance
Team Inspection
(MTI) Re ort No. 50-244/90"80
- to
update
the status of items
opened
by Safety
System Functional
Inspection
(SSFI)
Report
No. 50-244/89-81;
and to review maintenance
procedure
improvements
initiated by the licensee.
Results:
No deficiencies
were identified.
Maintenance
program weaknesses
have
been
adequately
addressed
and improvements
in these
areas
have
been
implemented.
A 4-year project to improve maintenance
procedures
has
been
initiated.
Adequate controls
and reviews are in place to release
previously
quarantined
maintenance
procedures.
9106200251
910606
ADOCK 05000244
0
0
DETAILS
1.0
Persons
Contacted
Attachment I provides
a listing of persons
contacted
during the inspection.
2.0
~Back round
In response
to the Maintenance
Team Inspection
(MTI) report 50-244/90-80,
the licensee,
in their letters
dated August
16 and September
19,
1990,
provided written responses
to identified violations and observed
weaknesses.
The violations identified during the MTI were adequately
addressed
and
closed
by
NRC inspection reports
50-244/90-22
and 50-244/91-07.
This
inspection
reviewed the licensee's
initiatives to correct the observed
weaknesses
identified in the MTI report.
Also, this inspection
reviewed
the progress
made in resolving the remaining
open
items identified by
Safety
System Functional
Inspection
(SSFI) Report
No. 50-244/89-81.
On
December
12,
1990,
safeguards
logic instrumentation
was disabled for
about twenty minutes during the conduct of maintenance.
This event
occurred,
due in part, to a procedural
deficiency.
In response
to the
event
and
as part of the licensee's
corrective actions,
administrative
controls were placed
on approximately
270 procedures
to prevent their
use
until
a thorough review of each could be performed (quarantine
process).
This inspection
assessed
licensee
controls for reviewing and releasing
these
procedures
from quarantine.
The documentation
reviewed to verify
items described
in this report are listed in Attachment II.
3.0
Licensee Action to Previousl
Identified Items
92701
and
92702
3. 1
Maintenance
Team Ins ection
MTI
Weaknesses
3.1.1
Weakness
No.
1
Maintenance
Records
are Difficult to
Retrieve
During the MTI, a programmatic
weakness
with the inability
to readily retrieve equipment historical
records
was
identified.
The weakness
was
a result of Central
Records
storing completed work orders
(WOs), s'igned procedures,
and
drawings in separate
locations.
To evaluate if improvement
'has
been
made in this area,
the inspector
reviewed governing
administrative
procedures,
observed
WO packages
being reviewed
for entry into historical files and retrieved
and reviewed
selected
WOs from the film library in Central
Records.
A
review of Administrative Procedure
A-1603.7,
"Work Order
Close Out," indicated adequate
instructions
are provided to
appropriate
personnel
for final
WO package
review and
history retention.
Additionally, the
WO packages
selected
for review were easily attained
from Central
Records
and
were complete.
Based
on the above information, this
weakness
is considered
adequately
resolved.
r
3.1.2
Weakness
No.
2
Potential
Exists for Miscommunications
due to Sound
Powered
Phone Limitations
The MTI identified weaknesses
with the licensee's
sound
powered
phone
communications
system.
There
was
a lack of
Administrative controls governing
use of the system
and the
system,
being
a
one channel.
system,
was noted
as being
congested.
To address
this problem,
the licensee
created
"Ginna Maintenance
and Testing
Communications
Standard."
The purpose of the standard is to assure
that maintenance
personnel
using. the open chahnel
communications
system,
communicate
in a clear concise
manner.
Additionally, the
standard
was written to prevent or reduce
the probability
of communication errors which could result in mistakes
being
made while performing maintenance
or tests.
A review
of records
indicated that training had
been
conducted to
implement the standard.
The licensee is also changing
the
communication
system to
a multiple channel
system.
The
design
engineer for this system expects it to be operable
by June
1991.
Based
on the licensee's
initiative to
install
a multi-channel
communication
system,
this issue is
considered
resolved.
3.1.3
Weakness
No.
3
There
has
been
a Lack of Evaluation of
Total Trainin
Needs
The MTI identified that the licensee's
training program
was
directed
toward technician skill enhancements.
The lack
of an assessment
to determine
the training needs for all
personnel
associated
with maintenance activities was
a
weakness.
To address
this, concern,
the licensee
retained
a
consultant to conduct
a training. needs analysis.
The
analysis
was performed for HYAC repairman
(a
new position
at the station),
stockroom personnel,
maintenance
planners,
maintenance
foreman,
and
personnel.
Based
on this analysis,
certain training needs
were identified
for HYAC repairman,
stockroom personnel,
maintenance
planners,
and.foreman.
Training for steam generator
personnel
and personnel
associated
with additional
maintenance
related activities was found to be. adequate.
Curriculums are being prepared
to implement training in the
areas
where additional training was indicated.
Based
on
the action taken, this issue is considered
resolved.
3.2
Licensee Action on Previousl
Identified Safet
S stem Functional
Ins ection
Items
A followup on the status
of the remaining
open
SSFI items initially
reported in Inspection
Report 50-244/89-81
and updated
in Inspection
Report 50-244/90-26
was performed.
A summary
and update of the
items are provided below:
0 en
Unresolved
Item 50-244/89-81-01
The SSFI identified a concern with the potential
loss of
cooling water to both diesel
engines resulting
from damage
to
a non-safety
and non-seismic
service water discharge
pipe during or following a seismic event.
The licensee's
response
to this .concern
stated that this event is beyond
the design
and licensing basis of the plant.
However, to
address
this matter they would include the potential
loss
of service
water to the diesel
generator
due to blockage of
the 10" Service Mater discharge
line in the Ginna
Probablistic Risk Assessment
(PRA).
The
PRA is being
conducted to address
Generic Letter (GL) 88-20, "Initiation
of the Individual Plant Examination (IPE) for Severe
Accident Vulnerabilities - 10 CFR 50.54 (f)," and its
supplements.
RGEE committed to providing the
NRC with
results of a level
2
PRA no later than
September
1,
1992.
The inspector
concluded that inclusion of this event into
the
PRA addresses
this issue;
however, until
a determination
is made
as to whether this event is beyond the design
and
licensing basis of the plant, this item is to remain
unresolved.
0 en
Unresolved
Item 50-244/89-81-03
The SSFI noted that
an evaluation
performed
by a consultant
indicated that Residual
Heat
Removal
(RHR)
pump Net Positive
Suction
Head
(NPSH)
may not be adequate
under
some
modes of
operation.
Further,
the licensee's
evaluation
and
determination of the adequacy of the consultants
calculation
was incomplete.
RG5E has since
reviewe'd the vendors
calculation per NSL-OOO-DA027,
Accident Conditions."
This review has
been
submitted to
their Mechanical
Engineering
Group for approval.
This item
is to remain unresolved
pending
licensee
approval
and
NRC
review of licensee results.
0 en
Violation 50-244/89-81-06
The SSFI identified
a violation of facility Technical Specification 6.8.1,
which requires testing of safety
related
components
in accordance
with established
procedures.
Specifically, the licensee failed to periodically test
(MCCBs) and did not establish
an acceptance
criteria for undervoltage
relay alarms.
To
address
the
MCCB violation, the licensee
has established
a
trial program for periodically testing
The trial
program is scheduled
to begin in the
summer of 1991.
In
addition, the licensee
has
been actively involved with EPRI
and
NUMARC in the
MCCB effort and
has initiated an industry
survey to determine
the level of practice for periodically
testing
This item is to remain
open pending
implementation
and evaluation of the licensee's
test program
for MCCB; and evaluation of the licensee's
corrective action
to establish
acceptance
criterial for undervoltage
relay
alarms.
3.2.4
0 en
Unresolved
Item 50-244/89-81-08
The SSFI noted the qualification basis for equipment located
in the
RHR room postulates
a
RHR pump seal failure 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
after the beginning of the recirculation
phase.
The SSFI
team questioned. the basis for the
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> since the
environmental
conditions would be more harsh at the beginning
of the recirculation
phase.
In the licensee's
response,
RG&E stated that the passive failure of a
RHR pump seal
is
assumed
to occur at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
consistent with SRP 15.6;-5.
However, to address
this matter, this item is being further
evaluated
by
RGEE through the
PRA effort.
This effort
is currently scheduled for completion
by September
1,
1992.
This item is to remain unresolved
pending further review by
NRC.
4.0
Maintenance
Team Ins ection
MTI
Followu
An MTI was conducted April 2 - 6,
and April 16 - 20,
1990.
During that
inspection,
issues
were noted which were not categorized
as violations or
weaknesses.
These
issues
included deficiencies
noted
by the team or
areas
in which the licensee
was in the process
of making major
improvements
which the
team considered
in making their findings.
Progress
in these
areas
was reviewed during this inspection.
4. 1
The team noted that
as
a result of a rigorous self-assessment
of the
site maintenance
program certain
measures
to upgrade
the overall
program were necessary.
One of these
measures
was the establishment
of a root cause
analysis
program.
The licensee
has
prepared
two
procedures
intended to control root cause analysis.
One is an
administrative
procedure describing the overall program.
The other
is intended to describe
the actions required of the maintenance
staff to implement the program.
A draft of the former procedure is
out for comment to upper management.
The, latter procedure
has
been
prepared
in draft but is awaiting further progress
toward the
issuance
of the former procedure.
Overall, progress
has
been
made
toward the establishment
of a root cause
analysis
program.
However,
progress
has
been
slow due to efforts having been directed to higher
priority issues.
4.2
The MTI noted
shop areas
were congested
with extraneous
reading
materials,
tools that were not returned to storage,
and trash
littered work benches
and tables.
The team further concluded
the
licensee's
inspection
program was ineffective in identifying this
deficiency.
To address
this concern,
the licensee
has placed
an
-increased
emphasis
on facility tours.
I
A new maintenance
department
guideline
has
been
issued describing
maintenance
supervisors
monitoring of work practices
and equipment
condition.
This guideline is in addition to maintenance
department
procedure
M-1306, Ginna Station Material Condition Inspection
Program.
This program establishes
13 zones
and provides for weekly inspections
by five maintenance
department disciplines.
The inspectors
reviewed
the maintenance
department
guideline .for monitoring of work practices
and equipment condition and verified by record, its
users
Although
still conjested
due to space limitations, improvement
was noted in
shop area cleanliness.
r
Additional inspection responsibilities
are prescribed for the safety
coordinator, fire protection,
health. physics,
and the duty
engineer.
Also, based
on discussions
with personnel,
both senior
site
and corporate
management
frequently inspect areas
of the
facility.
Efforts have
been
made since the MTI to improve the site
inspection
program.
4.3
The MTI noted
a number of different types of labeling
and tagging
throughout
the plant;
however,
a program of color coded
component
tagging
had
been initiated and
was being extended to the entire plant.
The tagging
program is being controlled by Ginna Station
Procedure
A-56. 1,
System
and
Component
Labeling
and Control of Operator Aids.
This program
has
progressed
significantly since the MTI.
Currently,
tagging in the containment is
90K. complete,
and balance
of plant
tagging is estimated
to be
50io complete.
4.4
The NTI noted that
a formal policy regarding
the standards
of conduct
expected
by management
of it's employees
regarding
such
items
as
procedure
adherence
had not been officially promulgated.
This issue
has
been resolved.
The licensee
has completed
a major revision to
Ginna Station Procedure
A-503, Plant Procedure
Adherence
Requirements.
This procedure
now clearly delineates
the requirements
for the proper
use of and adherence
to plant procedures.
4.5
The MTI noted that during execution of station work orders the area
of the work order form that was to contain descriptive
information
on the work completed
was at times found incomplete or provided
sketchy information.
This matter
has
been
addressed.
Ginna Station
Procedure
A-1603.5,
Work Order Execution,
Section 3.4 Work
Completion,
has
been revised to require that
upon completion of the
work order,
each section
(as found condition, action taken,
as left
condition) must be'omplete
and accurate
with sufficient detail to
allow a clear understanding
of the work that occurred.
In addition,
the proper completion of work orders
has
been
addressed
in continuing
training and emphasized
in shop meetings.
A random
sample of completed
work orders indicated that improvements
have
been
made in this area.
4.6
The MTI identified certain deficiencies
in the control of slings.
These deficiencies
included slings being past
due for inspection,
slings which could not be accounted for, and certain procedural
problems.
The licensee
has taken
steps to correct these
deficiencies.
Steps
which have
been
taken include
a revision to
Ginna Station Procedure
A-1301, Maintenance
and Inspection of
Material Handling Equipment.
The procedure
now clearly provides
instructions for the maintenance
and 'inspection of slings at the
station.
A color code
system
has'been
established
for the
verification of currency of inspection of rigging equipment,
and
special training concerning rigging equipment
has
been
conducted
for
people in the inventory control group.
4.7
In addition to the programmatic
issue
concerning training needs
(discussed
earlier in paragraph
3. 1.3}, the MTI also identified a
number of minor issues
associated
with maintenance training.'hese
issues
included
no formal managers/supervisors
approval of the annual
training schedule,
training conducted at section
and
shop meetings
not being documented,
certain procedural
inadequacies,
and ineffective
"procedure
adherence
training."
The licensee
has
taken
steps to
resolve
these
issues.
Manager/Supervisor
approval of the
1991 annual
training schedule
was verified.
A complete
1991 master training
schedule
has
been
issued.
Training conducted at section
and
shop
meetings is
now being documented.
Some procedure
changes
have
been
made
and more are planned
when
a consultant's
work on the training
program is completed.
Changes
have
been
made in the conduct of
"procedure
adherence
training" to make it more effective.
4.8
The licensee
is in the process
of establishing
a reliability centered
maintenance
(RCM) program.
The MTI noted
12
RCM system analysis
reports
had been completed.
The licensee
is making progress
toward
the full implementation of this program.
Currently,
21
RCM system
analysis
reports
have
been completed.
In addition,
as
system reports
are being completed,
applicable
procedures
are being revised to
include recording of feedback
information needed for the
RCM program.
In summary,
the licensee
has
made
a determined effort to improve deficiencies
identified in the MTI.
Areas in which improvements
were warranted
were
identified and action items were assigned for the initiation and tracking
of corrective actions.
5.0
Plant Walkdowns
Walkdown inspections
were conducted to observe the material condition of
the plant, work activities in progress,
and adherence
to work control
measures.
Areas of the plant inspected
included the Auxiliary Building,
emergency diesel
generator
rooms, battery
rooms,
Turbine Building, Service
1
Water Building, and the Intermediate Building.
With the exception of the
Intermediate
Building, the material condition of the plant was very good.
A large
amount of outage
work was still in progress
in the Intermediate
Building.
Numerous maintenance activities,
as well as the performance
of a Feedwater
System hydrostatic test,
were observed.
The 'use of procedures
and/or work
orders
were evident.
Good housekeeping
practices
were noted.
Maintenance
work areas
were maintained
in a safe
and controlled manner
and adequately
posted.
Supervisory
personnel
were observed at work sites to provide
guidance
and to evaluate
unexpected
conditions.
Both site
and corporate
management
personnel
were observed
in the plant.
Deficient conditions
were identified and properly tagged.
Health physics
controls were observed
to be adequate.
6.0
uarantined
Procedure
Review
On December
12,
1990,
safeguards
logic instrumentation
was disabled for
about twenty minutes during the conduct of maintenance.
This event occurred,
due in part, to
a procedural
deficiency.
The
NRC conducted
a special
safety inspection
( IR 50-244/90-31)
because
of the safety significances
of
the event.
As part of the response
to this event,
the licensee
took
initiative to place administrative controls
on approximately
270 procedures.
These controls restricted their use until
a thorough review of the procedure
had been
performed (quarantine
process).
The quarantine
process
was
initiated to ensure that plant procedures
having the potential to adversely
affect the plant receive
an extensive
review prior to their use.
The
quarantine
included calibration,
emergency
maintenance,
periodic test,
protective relay,
and refueling
shutdown surveillance
procedures.
As of
April 17,
1991,
the licensee
has
reviewed
and released
131 of these
procedures
from quarantine.
To determine if the controls used to release
these
procedures
are adequate,
the inspector
examined the review process.
The licensee's
review process
consists
of reviews similar to the pre
review/PORC approval
process
normally used
by the licensee.
However, this
review includes specific "quarantine
procedure
review guidelines" to be
used
by personnel
assigned
to perform the reviews.
In addition to
maintenance
department,
the operations
department
reviews
each
procedures
A Nuclear Assurance
Group review is also specified.
After reviews are
complete the procedures
are sent to
PORC.
A review of the procedure
review guidelines indicated that, if followed, these guidelines
should
accomplish their goal of ensuring that procedures
do not have
an adverse
effect
on plant operations.
However,
the licensee's
Nuclear Assurance
group determined,
by sampling procedures
already through the review cycle,
that guidelines
were not always being met.
Four of twenty-eight procedures
sampled
by the group were deficient with respect to the guidelines.
Based
on the audit findings, additional
reviews of previously reviewed procedures
were conducted,
Where deficiencies
were found corrective action
was taken.
The licensee
stated that additional audits of procedures
would be conducted
to ensure
continued compliance with the review guidelines.
Initial deficiencies
associated
with the quarantine
procedure
review
process
were effectively identified through the licensee's
nuclear
assurance
organization.
Based
on the licensee's
review and audit process,
the controls in place to release
procedures
from quarantine
are considered
to be adequate.
7.0
Maintenance
Procedure
U
rade
Pro
ram
MPUP
The licensee
has initiated
a majar effort to upgrade
maintenance
procedures.
The Maintenance
Procedure
Upgrade Project
(MPUP) is being performed
by
a
contractor
and is designed to develop maintenance
procedures
for all plant
critical components.
The scope
includes the development of about
860
procedures
and is scheduled
to.be completed'by
the middle of 1994.
Adequate
resources
appear to be available to accomplish
the project;
however,
several
project schedule
dates
have already
been
changed
due to
delay's with its initiation.
Current plans include the completion of a
pilot project at which time the
MPUP will be evaluated
and improvements
initiated.
Development
and approval of thirty procedures
make
up the pilot
which is scheduled
to be completed
by June
1,
1991.
The pilot previously
called for the completion of 50 procedures
by March 1,
1991.
Higher
priorities and delays in selecting
a contractor attributed to the original
schedule
not being met.
The project is headed
by
RGEE and contractor
project managers.
The contractor
has
17 dedicated
personnel
involved with
MPUP.
The inspectors
review of the project indicated that
a systematic
approach
to developing
procedures
is being used.
This approach
incorporates
validation and reviews into the process.
Draft procedures
reviewed
showed
considerable
improvement with respect
to quality and clarity over old
maintenance
procedures.
The
new procedures
clearly identify purposes,
references,
prerequisites
and statements
such
as notes,
cautions
and
warnings.
Drawings .are incorporated within the procedures.
Step
by step
instructions with major and minor steps
are provided in the body of the
procedures.
The major steps
are designed
to be. used
by experienced
mechanics/technicians.
Inexperienced
users
are provided greater detail
by expanding
the major steps with minor steps.
Following the inspectors
review,
comments
were discussed
with the
MPUP
project managers.
In addition,
one concern
was discussed
with licensee
management.
There appeared
to be
no method in place to evaluate "like" procedures
for
changes.
For example,
there
are
7 ALOYCO 8" 150 lb valves identified by
the licensee
as needing corrective maintenance
procedures.
A procedure
will be generated
for each.
No method currently exists to evaluate all
procedures
associated
with ALOYCO 8" 150 lb valves if a change is initiated
to one.
The inspector
noted that past
problems
have resulted at Ginna
from "like" procedures differing,
The licensee
acknowledged
the comment
and stated it would be considered.
4.
~ '
~
~
10
Licensee
management
was informed of the
scope
and purpose of the
inspection at
an entrance
meeting conducted
on April 22,
1991.
The findings of the inspectors
were discussed
periodically with licensee
representatives
during the course of the inspection.
An exit was
conducted
on April 26,
1991, at which time the findings of the inspectors
were presented.
ATTACHMENT I
PERSONS
CONTACTED
Rochester
Gas
5 Electric Company
"S. Adams, Technical
Manager
G. Cain, Director, Maintenance
Support
Systems
G. Daniels, Electrical Supervisor
T ~ Daniels,
PRA Manager,
Nuclear Safety and Licensing
"C. Edgar,
Manager, Electrical/IEC
.
"D. Fi lkins,
HP 5 Chemistry Manager
"J. Fisher,
Maintenance
Planning
and Scheduling
Manager
N. Goodenough,
Maintenance
Corrective Action Analyst
"P. Gorski, Manager,
Mechanical
Maintenance
"J. Huff, Maintenance
Training Manager
"M. Lilly, Manager,
Nuclear Assurance
"T. Marlow, Superintendent
Support Services
"J..St.Martin, Corrective Action Coordinator
"R. Mecredy,
Vice President,
Ginna Nuclear Production
- G. Meier, Department
Manager,
Production Division Training
- F. Mis, Health Physicist
- C. Rioch, Modification Liaison Engineer
T. Schuler,
Operations
Manager
"M. Shaw,
Manager,
Material
8 Procurement
- J. Widay, Superintendent
Ginna Production
~P. Wilkens, Department
Manager,
Nuclear Engineering
Services
United States
Nuclear
Re viator
Commission
- N. Perry,
Resident
Inspector
During the course of this insepction the inspectors
contacted
other
members of
the licensee's
Technical,
Nuclear Assurance,
Operations
and Training staffs.
- Denotes those present at the exit meeting held on April 26,
1991.
ATTACHMENT II
DOCUMENTS REVIEWED
PROCEDURES
A-'56 F 1; Rev.
7,
A-503, Rev.
20,
A-1301,
Rev.
11,
A-1603.5,
Rev.
1,
A-1603.7,
Rev.
1,
CMP-37-01-02C,
CMP-OOO-DA027,
Project Work Plan
System
and Component
Labeling,and Control of Operator Aids
Plant Procedure
Adherence
Requirements
Maintenance
and Inspection of Material Handling Equipment
Work Order Execution
Work Order Closeout
Draft, 709C,
Va1ve Maintenance
During Accident Conditions
and Quality Assurance
Plan
(March 4,
1991)
ENTER-OFFICE
CORRESPONDENCE
i
Jan.
17,
1991,
Jan.
22,
1991,
Feb.
5, 1991,
March 30,
1991,
April 16,
1991,
Maintenance Office and
Shop Housekeeping
Interim Guidelines for Operations,
Review of Temporary
and
Permanent'CNs
to All Plant Procedures
December
12,
1990 Event Follow-up
Quarantine
Procedure
Reviews
Quarantine
Procedure
Reviews
Changes
Letter dated Jan.
30,
1990,
Request for Proposal
No.
3000
Letter dated July 10,
1990,
Request for Supplemental
Information for Proposal
No. 3000
Letter dated
September
19.,
1990,
Response
to Maintenance Activity Weaknesses
Identified in Inspection
Report
No. 50-244/90-80
Ginna Maintenance
and Testing Communications
Standard
Maintenance
Department
Quarantine
Procedure
Review Guidelines
Commitment Action and Tracking System Report (April 23,
1991)
Mechanical
Maintenance Training Schedule
Maintenance
Department Guidelines for Supervision
Work Practice
and Equipment
Condition Monitoring, Rev.
3
0
t
I,
1