ML18005A695
| ML18005A695 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 10/20/1988 |
| From: | Conlon T, Merriweather N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18005A692 | List: |
| References | |
| 50-400-88-27, NUDOCS 8811090278 | |
| Download: ML18005A695 (25) | |
See also: IR 05000400/1988027
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W., SUITE 2900
ATLANTA,GEORGIA 30323
Report No.:
50-400/88-27
Licensee:
Carolina
Power and Light Company
P.
0.
Box 1551
Raleigh,
NC
27602
Docket No.:
50-400
Facility Name:.
Shearon Harris
License No.:
Inspection
Conducted:
August
1 ;19,
1988
Inspectors:
M~~is'i'm
N. Merriweat er,
Team Lea er
EZ'=
Da e Si
ned
/>
Da
e Sig ed
Team Members:
M. Jacobus,
Consultant
Engineer,
Sandia
National Laboratories
C. Kido, Consultant
Engineer,
Idaho National
Engineering
Laboratory
C. Paulk,
Reactor Inspector,
Region II
C. Smith, Reactor Inspector,
Regi.on II
N
Approved by:
T.
E. Conlon, Chief
Plant Systems
Section
Engineering
B'ranch
Division of Reactor Safety
SUMMARY
Scope:
Results:
This routine,
announced
inspection
was
conducted
in the
area
of
Environmental
Qualification
(EQ)
of Electrical
Equipment
which
included:
a
review of Carolina
Power
and Light Company's
imple-
mentatation
of
a program to meet the requirements
of 10 CFR 50.49;
walkdown inspections
of equipment
inside containment;
preventative
and
corrective
EQ maintenance;
EQ procurement;
and
followup
on
previous inspection
issues
and commitments.
In the
areas
inspected,
one violation and
one unresolved
item were
identified.
The violation involves the failure to maintain the qualified status for
certain
EQ equipment.
The root cause for the violation may be the
result of inadequate
training and/or procedures.
The unresolved
item
involves the licensee's
commitment to do additional testing to extend
the qualified life of the coils in Target
Rock Solenoid valves that are
both continously energized,
and
on hot process
piping.
L0
Poli
AOOCK 0 000400
9
This inspection
was
considered
to
be
Phase II of the previous
Eg
inspection
which
was
conducted
in
Narch
1988.
The
previous
inspection
concentrated
on
Eg equipment
located
in the Steam
Tunnel
and the Reactor Auxiliary Building due to the fact that the plant was
operating
preventing
containment
walkdowns.
The
team
concluded
during- the inspection that the licensee
had
implemented
a
program
which
meets
the
requirements
of
The
team
also
concluded
that
the licensee's
training
programs
on
Eg were
weak.
During this
inspection,
the
team
concluded
that
the
licensee
continues
to have
an adequate
Eg program.
The program is considered
to be average
and is not outstanding
at this point.
However, there
are certain initiatives that are-currently
ongoing which will greatly
enhance
their Eg program.
These initiatives include
changes
in the
Eg organization
and responsibilities
to better interface with other
departments
and
organizations
on
Eg
matters
(such
as
design,
maintenance,
procurement
and scheduling)
performing walkdowns of Eg
equipment,
and
conducting
engineering
surveys
of
Eg equipment's
ambient
temperatures
during
power operati'on for age related effects
on
Eg equipment,
and followup on
NRC issues.
The
weaknesses
identified in the
licensee's
Eg
program
related
specifically to
Eg maintenance
and training.
The licensee
performed
maintenance
on
Eg equipment
which failed to maintain the qualified
status
of the
equipment.
The training
provided
the craft
was
considered
marginal
and
procedures
may also
have
been
inadequate.
Staffing for
Eg has
been
increased
with a proposed
new position in
the newly described
organization.
All these
actions
may enhance
the
licensee's
Eg program over the years
to come.
REPORT
DETAILS
Persons
Contacted
Licensee
Employees
- P. Brady, Senior Engineer,
Harris Plant Modification Unit
- C. Crawford, Representative,
On-Site Nuclear Station
(ONS),
- R. Cuthbertson,
Senior Specialist,
Technical
Support
- E. Evans, Project Engineer,
Nuclear Engineering.Department
(NED)
- C. Gibson, Director, Program
and Procedures
- C. Hinnant, Plant General
Manager
- M. A. Kite, Senior Specialist,
Technical
Support
- J. Lewis, Senior Engineer,
NED
- C. McKenzie,'Principal
gA Engineer
- T. Nelson, Senior Specialist,
NED
- F. Nowak, Senior Engineer,
NED
- L.Oakley, Senior Engineer,
Technical
Support
- L. Olsen, Project Specialist,
Technical
Support
- A. Roberts,
Senior Specialist,
Technical
Support
- W. Russell,
Project Engineer,
- P. Salas,
Senior Engineer,
Licensing
- J. Sipp,
Manager
- C. Sweely, Project Engineer,
NED
- D. Tibbitts, Director, Regulatory
Compliance
- R. Van Metre, Manager,
Technical
Support
- M. Wallace, Senior Specialist,
Regulatory Compliance
- R. Watson,
Vice President,
Harris Nuclear Project
- L. Woods,
Engineering Supervisor,
Technical
Support
- P. Yandow, Senior Engineering,
NED
- R. Zula, Project Engineer,
Technical
Support
Other
licensee
employees
contacted
during this
inspection
included
craftsmen,
engineers,
operators,
mechanics,
security
force
members,
technicians,
and administrative
personnel.
Other Organizations
- D. Rhyne,
Patel
Engineers
NRC
- P. Fredrickson,
Chief, Project Section
1A, Division of Reactor Project
- C. Hehl, Deputy Director, Division of Reactor Projects
- E. Merschoff,
Deputy Director, Division of Reactor
Safety
- M. Shannon,
Resident
Inspector
- Attended exit interview
2.
Evaluation Of Licensee's
Program
For gualification Of Electrical
Equipment
Located In Harsh Environments
A special
team inspection
was
performed
during the
week of March 7-11,
1988,
to assess
the licensee's
implementation of a
program to meet
the
requirements
of
During that
inspection, files for 23
equipment
items
were
reviewed
and
found acceptable
with
some
minor
discrepancies.
A walkdown was performed of equipment located in the
steam
tunnel
and auxiliary building with
some
maintenance
concerns
being
identified.
Due to the operational
status
of the plant walkdowns of
equipment,
inside
containment
could not
be
accomplished;
however,
the
licensee's
Eg
program
appeared
to
be
adequate.
This inspection
was
considered
a continuation of the first inspection concentrating
on those
inside
containment
components
which were not examined
during the first
round
Eg inspection.
Similar to the first inspection,
the
NRC inspectors
examined files
as
the
basis
for qualification for
Eg equipment
inside
containment;
performed
walkdown
inspections
of
equipment
(inside
containment
only); continued
the review of the
Eg maintenance
program;
examined
the licensee's
procurement
program for
Eg components
and
spare
parts;
reviewed
Eg training;
and examined
what actions
had
been
taken
on
previous
inspection
concerns.
The results
of the inspection
and -the
conclusions
reached
are discussed
below:
a ~
Maintenance
During this
inspection,
work requests
that
had
been
closed
out
(either by completion or cancellation)
and those that had been
issued
since
March 1988,
were reviewed.
At first there
appeared
to be many
problems
in the
area
of Eg.
This
was
because
many of the work
requests
identified "unqualified" components,
"unknown" components,
and missing components.
The
"unqualified"
and
"unknown"
components
were
associated
with
Limitorque motor operators.
The number of these
items
was alarming
since
the licensee
stated
that
a
1005 walkdown of environmentally
qualified Limitorque operators
had
been
performed
in
1986.
Upon
questioning
by the inspector,
the licensee
was able to show for the
1986
data
that
the
questionable
item
was
not
"unknown"
or
"unqualified."
These
items were identified by the licensee
during the performance of
EPT-072;
Valve Actuator
Inspection
Guidelines.
The
procedure
requires
the performer to annotate
what is found.
When
something
was
found that
was
questionable,
the technician
would
indicate the item was
"unknown" or "unidentified".
The procedure
does
not
provide
any
acceptance
criteria
to determine
what
would
be
acceptable
or to identify any discrepancies.
The procedure
requires
the
Eg Coordinator
or
Designee
to resolve
any discrepancies,
yet
there is no acceptance
criteria or reference list of acceptable
items
for this person to use in meeting this signoff requirement.
3'everal
factors are involved in this issue.
The individuals that are
performing
the
procedure
are
not
adequately
trained
in
Eg,
the
procedure
does
not provide
any acceptance
criteria for determining
what is acceptable,
and management
appears
to have only" a handful of
. people
knowledgeable
in Eg.
Unless the technicjans
and electricians
understand
Eg
and
the
requirements
for maintaining
equipment
qualified, qualification issues will arise.
In this instance,
ther e
was
no hardware
problem, but there
was
a problem with the training of
personnel
responsible for performing
Eg related activities.
0
During
the
review of the
work requests,
a
problem with motor
operators
missing T-drains
was identified.
The following scenario
indicates
that although corrective
actions
were
taken,
they were
considered
inadequate
to prevent similar problems
from
recurring.'n
1986,
WRSA 86-BMBS1
was written to correct
a cable termination
problem in the limit switch for Yalve No.
The work request,
did not specify what was required to maintain the limit switch in
a
qualified configuration;
WRY 87-AMPE1 was
issued April 24,
1987, to
re-establish
the environmental
qualification of the limit switch
by
replacing
the .front cover
The
work
was
completed
on
August 6,
1987.
On
August 7,
1987,
NCR 87-098
was
issued
and it identified the
problem with WRSA 86-BMBSl as not meeting the requirements
of MMM-012
which
states "if the
work request
is
on a[n]
Environmentally
gualified component...the
planner will determine if the environmental
boundary will be
degraded
by the
maintenance
action
and
provide
planning instructions
as
necessary
to restore
the
Eg boundary."
The
root- cause
was identified as'[i]ncorrect planning of
WR 86-BMBSl did
not include
Eg requirements".
The corrective actions
were to issue
WR87-AMPE1 and to provide training.
On August 21,
1987,
Planners
were trained
on
EQ requirements
and the
processing
of work requests
involving Eg.
Classes
to indoctrinate
18C
and
Electrical
personnel
were
scheduled
to
begin
in
,
September
1987.
On, or about,
September
17,
1987,
the motor operated
valve
the
Main
Steam
supply to the
Turbine Driven Auxiliary Feedwater
(TDAFW) pump from the "B" main steam line, was replaced
in accordance
with
WR 87-BCLY1.
On February
29,
1988,
WR 88-AEKE1 was initiated to replace
the motor
operator for valve
the
AFW isolation valve to the
"B" S/G"
from the
pump.
The
work request
did
not
require
the
electricians
to
remove
the T-drains
from the old motor and install
them
on the
new motor, however,
they did.
This is another
example of
the work request
not being completed with the necessary
information
to ensure electrical
equipment maintains
environmental qualification.
On March 2,
1988,
WR 88-AEgMl was written to install the T-drains
on
the operator
motor for valve
which were
not installed in
September
1987.
On April 15,
1988, it was
"discovered"
by the licensee
that the
missing T-drains
was
a "qualification problem:
and
SOOR 88-068
was
initiated.
WR 88-AE(Ml was performed
on April 15,
1988,
and T-drains
were
installed
in the limit switch
housing,
not
the
motor
as
instructed
by the
WR.
On April 21,
1988,
WR 88-AIXH1 was initiated based
on
a review of
88-AEKE1.
The review identified that
no T-drains
were
removed
from
supply
and it was
assumed
that
none were, therefore,
installed
on
Workmen were dispatched
to perform the work request
but
found the T-drains already installed
and cancelled
the work request.
On June
23,
1988,
WR 88-APgS1
and
SOOR 88-114 were initiated due to-
the T-drains
being installed
in the limit switch housing
on
The
T dr ains were correctly installed in the motor on June 23,
1988.
The above scenario
shows that the licensee identified
a problem with
the maintenance
of
Eg equipment.
Although corrective actions
were
taken,
the scenario
shows that those
actions
were inadequate
since
there
continues
to
be
problems
with
Eg maintenance.
Specifically,
technicians
and/or electricians
not adequately
trained to ensure that
environmental qualification is maintained after performing work, and
work planners
not providing adequate
instructions for maintaining
environmental
qualification.
This
is identified
as
Violation
88-27-01,
Failure
to
Take
Adequate
Corrective
Actions for
Eg
Problems.
The maintenance
of the licensee's
Eg program is not as strong
as it
should
be.
Improvements
must
be
made
in training,
procedural
compliance,
and
procedures
in order to avoid problems
in the future.
This will require
more
management
support
and
involvement than is
present
at this time.
Eg Personnel
Training
The
Eg inspection
conducted
March 7-11,
1988, identified deficiencies
in the
Eg training of licensee
personnel.
At the
time of the
inspection,
licensee
management
was
in the
process
of reviewing
lesson
plans
gA6084G,
and
gA6085G in preparation for development of a
formalized
Eg training program.
A commitment date of Nay 15,
1988,
was
also
given
as
the starting
date
for implementation
of the
training
program.
Based
on
review of objective
evidence
and
discussions
with licensee
training staff the inspector verified that
a formalized
Eg training program
had
been
developed
and
implemented
for non-craft personnel
in accordance
with licensee
commitments.
Requirements
for providing training,
continuing
training,
and
on-the-job
training for maintenance
personnel
is specified
in
procedure
TI-113.
Pursuant
to review of this procedure
during the
first round
Eg inspection,
the inspector determined that
a formalized
training
program
had
not
been
established
for indoctrination
and
training
of Electrical
and
Instrumentation
and
Control
(I8C)
personnel
in the requirements
of Harris
Eg program.
This deficiency
was
previously
recognized
by the Electrical
Craft
and
Technical
Steering
committee in late
1987.
They recommended
that gualification
Checkout
Cards
(gCCs)
that define specific
tasks
related
to the
implementation of the
Eg program
be developed
and
used for craft
Eg
training.
The inspector
determined that the
above
recommendation
has
not been
acted
upon
by licensee
management.
Additionally, the Electrical
and
I8C maintenance
personnel
have not been indoctrinated
and trained in
the
requirements
of the
Eg program to
an extent similar to 'that
provided non-craft
personnel.
Licensee
management
has identified
deficiencies
in the implementation of the
Eg maintenance
program.
A
prime contributor to these deficiencies
was identified as lack of Eg
training of the craft.
Corrective
actions
completed
included
development
and presentation
of a one
hour. course
(No. CT1010H), to
maintenance
personnel.
Licensee
management
further indicated that
long term corrective action in the form of continuing training on the
requirements of the
Eg program was presently
being established.
This
would involve expansion
of course
CT101H in lieu of the use of gCCS
and
would
be
given periodically every
two years.
The licensee
indicated that training will begin
on or around
February
1989.
Eg Equipment Replacement
and Spare Parts
Procurement
A review of the
implementation
of the
procurement
program
was
performed
to verify conformance
with applicable
industry
codes
and
standards
and regulatory requirements.
The following environmentally
qualified
equipment,
selected
for physical
inspection
during
the
plant walkdown,
was chosen for this review.
E ui ment Descri tion
SFD.
Ta
No.
ASCO Solenoid .Valve
CP-5:005
Pressurizer
Safety Valve
Position Indicators
(CR0534)
NAMCO limit Switch
(CV Purge Valve)
Target
Rock Valves
ZS-R530SAB
1CP-5:004
E ui ment Descri tion
cont
SFD.
Ta
No.
Barton Transmitter
(Model 764)
Barton Transmitter
(Model
763)
LT-474
PT-455
Barton Transmitter
(Model 752)
FT-414
Purchase
Orders
(PO) for the
above
equipment
were retrieved
by the
Licensee
Engineering
Technical
Support
group via on-line
Supply
Inventory
System
computer
network.
The
inspector
reviewed
the
purchase
orders
and verified that applicable
technical
and quality
requirements
required
for environmentally qualified equipment
had
been
specified.
Additionally, the review was
performed
to ensure
that reference
to an
Eg Test Report,
and the requirement of 10 CFR 21
had
been
included.
No deficiencies
were identified during this
effort.
Procedure
number
TMM-104, paragraph
5.4.4.
defines
"Off-the-Shelf"
item as
commercial
grade
and provides criteria for commercial
grade
items that are similar to 10 CFR 21.3(4)(a-l).
Paragraph
5.4 of this
procedure further specifies
the method for determining the technical,
quality,
and regulatory
requirements
for procurement
documents
and
delineate
the applicable guality Classes
on which these
requirements
are to
be
imposed.
Guidance for the determination of guality Class
of
replacement
parts,
equipment
and
material
is
shown
on
Attachment
E.
This attachment
permits
the procurement of coomercial
grade
replacement
parts for end use in basic
components.
Interviews
were
conducted
with licensee
personnel
to determine
the
technical
adequacy
of the
process
for commercial
grade
items
prior
to their
use
in basic
components.
The
inspector
determined
that
CP8L
Corporate
equality
Assurance
Manual,
Section 5.5.a
requires
that
an engineering
evaluation
be performed
prior to
the
use
of an "Off the Shelf"
item.
The
procurement
evaluation
process
specified
in Section
4.3.4 of the
manual
is
intended
to meet this engineering
evaluation
requirement
and allows
for the
preparation
of purchase
requisitions
in accordance
with
approved
procedures,
or alternatively,
by performance of a specific
engineering
evaluation.
Section
4.3.4 of the Corporate
guality
Assurance
Manual also states
that
once
an item has
been evaluated
to
,be acceptable
for off-the-shelf use the original specification
does
not
remain
as
the
governing
purchasing
criteria,
and
vendors
supplying off-the-shelf items
are not required to be
on the approved
Suppliers List.
Direct
replacement
parts
are
procured
by part
number
via
the
preparation
of purchase
requisitions
in accordance
with procedure
TMM-104.
Guidance
for
performing
'the
required
engineering
evaluations
are
delineated
in Attachments
A,
B,
and
C of this
procedure.
Pursuant
to review of these
attachments
and discussions
with licensee
personnel
the
inspector
determined
that
adequate
procurement
controls
have
not
been
developed
and
implemented
to
verify
the critical
characteristic
data
of
commercial
grade
replacement
parts
intended for use in
Eg applications.
The existing
procurement
controls for replacement
parts
do not ensure identifica-
tion of select critical characteristics.
Licensee
management
stated
that ordering replacement
parts
by part number
guarantees
receipt of
like-in-kind replacements.
However,
because
the
replacement
parts
are
procured
commercial
grade
no documentation
are required
to
be
provided
by the
vendor
to assure
that
the
replacement
parts
are
identical
to the original parts..
The inspector
made
a random selection of commercial
grade
replacement
parts
used
by the licensee
in
Eg applications
to verify conformance
with technical
and regulatory requirements.
The parts selected
were
primarily non-electrical
replacement
parts,
and lubrication
oil.
The inspector
determined
that the licensee
has established
a
chemical
and
consumable
control
program
for
replacement
parts
identified
as
consumables.
Applicable requirements
of this program
are
imposed
during the
procurement
of bulk commercial
grade
items
such
as gaskets,
O-rings,
'and lubricants.
The requirements
provide
for identification of chemical characteristics
of the material and/or
special,
or limited use associated
with the material
because
of plant
specific
requirements.
No
Eg deficiencies
were identified during
this review.
The
inspector
selected
a
broader
sample
consisting
of electrical
replacement
parts.
Documentation
associated
with the part
numbers
selected
were transmitted
to the
Regional
Office
by the licensee
after completion of the inspection.
The following purchase
orders
and supporting
documents
were reviewed.
PO No.
44109700
198507BT
"1 91108 8F
46813 1BT
425388AR
Part
No.
727-653-73
725-619-12
725-631-82
726-048-87
726-039-96
Material Description
Si licone
Caulk
,Groove Pin
Limit Switch Rotor
Terminal Block
Silicone Gasket
The licensee
uses
various
methods
to ensure
recei pt of like-in-kind
replacement
parts.
The
replacement
parts
were
procured
by part
number from the original equipment manufacturer
who in some instances
provided
compliance.
The Certificate of Compliance certified that
the
materials
met
all
the
requirements
of
the
PO
and
specification.
Additional
controls,
demonstrated
for
PO
No.
191108BF,
the procurement of only nuclear grade replacement
parts
which are
then
used in both standard
and nuclear applications.
The
limited engineering
evaluations,
performed
for determination
of
replacement
parts
critical characteristics,
do
not
appear
to
adversely
affect
the
procurement
of like-for-like parts.
The
purchase
order
imposes
instructions that there shall
be
no change in
part
numbers
or item description
unless
approved
by the purchaser.
Design
changes
initiated
by the
vendor
needs
to
be reported
and
should state
whether the
new part number services
the
same fit, form
and function
as
the old part
number.
Additionally,'he receipt
inspection
process
provides for verification of easily identified
physical
characteristics,
part
number;
and
when
ne'cessary,
verification of performance characteristics
by performance of special
tests.
Based
on the
sample
reviewed,
the inspector
concluded that
technical
and quality requirements. for like-in-kind replacement
parts
are maintained
during implementation of the procurement
program.
No
EQ deficiencies
were identified -during this review.
QA/QC Interface
Nonconformance
Report
No.87-098,
was written on August 7,
1987; to
document
a significant deficiency in the
implementation of the
maintenance
program.
The
problem
involved
degradation
of the
environmental
qualification
boundaries
of
equipment
caused
by
maintenance
activities.
The
root
cause
was
determined
to
be
inadequate
training of both the maintenance
planners
and maintenance
craft personnel
in requirements
of Harris
EQ program.
Corrective
actions
taken, to
resolve
this
deficiency
are
described
in
paragraph
"b" above.
Additional corrective action,
implemented the week of August 8,
1988,
=to correct
the
above
deficiency
included
restructuring
the
Technical
Support organization.
An additional staff positions
have
been
added with responsibilities for administrative control of the
maintenance
program.
The objective of the
reorganization
is to
provide centralized
control for implementation of the
EQ maintenance
program.
Functional responsibilities,
levels of authority,
and lines
of internal
and
external
interface
communications
will also
be
specified to better coordinate
and assess
the effectiveness
of the
program.
Pursuant
to discussions
with licensee
management
the inspector
was
informed
that
procedure
PLP-108,
"Environmental
Qualification
Program," wi 11
be revised to reflect the above organizational
change.
A commitment date of October 1,
1988,
was
given for completion of
this
revision.
The
inspector
also
reviewed
section
4.4.2
of
procedure
PLP-108,
and verified that
inadequacies
in the
program
description identified during the first round
EQ inspection
had
been
corrected.
The corrective
action
was
completed
in accordance
with
the licensee prior commitment.
Within this area,
no violations or deviations
were identified.
Eg Documentation Files
and Walkdown Items
The
NRC inspectors
examined files for 28 equipment
items,.where
an
item is
defined
as
a
specific
type of electrical
equipment,
designated
by manufacturer
and model, which is representative
of all
identical
equipment in
a plant area. exposed
to the
same environmental
service conditions.
The inspector selectively reviewed areas
such
as
(1) required post-accident
operating time compared to the duration of
time
the
equipment
has
been
demonstrated
to
be qualified,
(2) similarity of tested
equipment
to that installed in the plant,
(3) adequacy
of test
conditions
enveloping, calculated
accident
profile conditions,
(4) aging
calculations
for qualified life
determination,
(5) temperature
related effects
on instrument accuracy
due to decreases
in insulation resistance,
(6) evaluation of test
anomalies,
and (7) applicability of Eg problems reported in IEBs/IENs
and their resolution.
The results of the file reviews
and walkdown
items will be
discussed
in detai
1 in the paragraphs
that follow;
however,
in general,
the files were considered
adequate.
(I)
General Electric Vulkene
Supreme
Mire (E(DP 6.10)
The inspector
reviewed
the- file for General
Electric Vulkene
Supreme
SIS wire used outside
containment for control applica-
tions.
The qualification basis
was
Category I.
The
worse
case
steam
environment is in the steam
tunnel
where the
peak
temperature
reaches
437'F for about ten minutes,
followed
by a fairly rapid return to much lower temperatures.
A thermal
lag analysis
(File
No. 2202.006,
not reviewed) yielded
a peak
temperature of'28'F.
The radiation dose is 43 Hrad normal
and
I Mrad,accident.
The
cable
was qualified to
nominal
conditions
and is reported tin
FRC report
All plant
parameters
were
enveloped.
The tested
cable
was
identical
to the
cable
purchased
for the plant.
Good
IR
performance
was indicated
by the
steam test.
No findings were
identified.
(2)
Rockbestos
Coaxial
Cable
(E(DP 6.7)
The inspector
reviewed
the file for Rockbestos
coaxial
cable
used for instrumentation circuits, including the General
Atomics
radiation
monitor inside
containment.
Cables
used
include
RSS-6-104/LD,
RSS-6-105/LD,
and RSS-6-108/LD.
The qualification
basis
was
Category I.
The plant parameters
were
enveloped
by the test
and the
LD/LE similarity analysis
was
included
in the file.
Performance
(IR) of the
cable
is
addressed
elsewhere '(in General
Atomics radiation monitor file,
not reviewed).
No findings were identified.
(3)
Instrument
Loop Accuracy Calculations
(EgDP 90. 1)
10
(4)
The inspector briefly reviewed
the
instrument
loop accuracy
calculations
of
EgDP 90.1.
This file contains
the basis
and
justification for data
supplied
to Westinghouse
for input to
loop accuracy
calculations.
The reviewed calculation
does
not
include
any, degraded
IR calculations.
Cable lengths
and
IRs
used
for cables,
connectors,
and
splices
are
determined
in the
package
and justified based
on
peak expected
containment
temperature.
No findings were identified.
Rockbestos
Instrumentation
and Control Wire (E(DP 6.8)
The inspector
reviewed the file for Rockbestos
chemically
XLPE
(Type XXL-760D) insulated
600V control
and thermocouple
cable.
The control
cable
is used
in Limitorques
and the thermocouple
cable is
used
in Westinghouse
The qualification
basis
was
Category I.
The plant parameters
were
enveloped
by
the
test
conditions.
Insulation
resistance
performance
was satisfactory
during the test.
No findings were
identified.
(5)
Rockbestos
Instrument
and Control Wire (EgDP 6.9)
The inspector
reviewed
the file for Rockbestos
radiation
XLPE
insulated
cable.
All information for this cable is the
same
as
for the chemically
XLPE cable
in
4 above.
No findings were
identified.
Okonite Okozel
Cable
(EgDP 6. 13)
The inspector
reviewed the. file for okonite cable insulated with
Okozel,
an
ETFE flouropolymer (Tefzel).
The qualification basis
was
Category I.
The cable
is
used for internal
jumpers
and for field cable terminators for Target
Rock Solenoid
valves.
This cable
was purchased
and installed
as
a result of
IEN 84-68.
The cable is rated at 150'C in dry locations with a
qualified life of ten years.
The cable
type designation
are
Z
and
ZW.
The only area
questioned
was that of documentation
required to support
Category
I qualification.
Prior to the end
of the inspection,
additional
documentation
was
obtained
and
will be added to the file.
The
new documentation
was considered
adequate
for Category I qualification.
No findings
were
identified.
(7)
Anaconda Control Cable
(EgDP 6.11)
The inspector
reviewed the package for Anaconda
NSIS switchboard
and
control wire.
The qualification basis
was
NUREG-0588/
Category I.
The cable
has
FR-EP. insulation
and
a
CPE jacket.
The test
parameters
enveloped
the
plant
parameters
with
a
qualified life of 40 years
at 71'C.
The
two test
specimens
identical
to the
cable
used
in the plant both carried
rated
voltage
and
current with IRs
in excess
of 107L.
The test
results
are reported
in
FRC report F-C4969-1.
No findings were
identified.
(8)
(9)
(Io)
(II)
Anaconda
Power Cable
(EgDP 6.6)
d
The inspector briefly reviewed
the file for Anaconda
medium
voltage
(15
kV) power cable.
The cable is specifically excluded
from safety-related
use in the containment or main steam tunnel,
resulting in a peak accident
temperature of only 133'F and less
than
1 Mrad radiation.
No findings were identified.
Anaconda
Instrumentation
Cable
(E(DP 6.2)
The inspector
reviewed
the file for Anaconda
instrument
and
thermocouple
extension
cable.
The, qualification
basis
was
NUREG-0588/Category I.
The test conditions
enveloped
the plant
parameters
with
a qualified life of
40
years
at
71'C.
Submergence
testing
was
included.
The
cable
uses
FR-EP
insulation
and
a
CPE jacket.
The tested
cables
are similar to
those
used
in the plant with the only significant difference
being
conductor
materials
in
some
of
the
plant
cables
(thermocouple
extension wire).
IR performance
during the
30 day
LOCA was better than
106L.
The test results
are reported in
FRC
reports
No findings were identified.
Eaton Thermocouple
Extension
Wire (EgDP 6.3)
The
inspector
reviewed
the file for Eaton
(Samuel
Moore)
thermocouple
extension
wire using
an
FR-EPDM insulation.
The
qualification basis
was
NUREG-0588/Category I.
gualification
was
based
on tested
specimens
with the
same insulation material.
IR
performance
during
the test
remained
better
than
I ML.
Submergence
testing
was included
and all plant parameters
were
enveloped.
No findings were identified.
Bishop Electrical
Tape
(EgDP 16.2)
(>2)
The
inspector
briefly
reviewed
the file for
Bishop
semiconducting
electrical
tape
used
for
600
V
and
15
kV
terminations.
The
qualification
basis
was
NUREG-0588/
Category II.
The tape is not used for safety applications
in
the
containment
and main
steam
tunnel,
giving
a peak accident
tempertaure
of 167'F.
The
only significant qualification
parameter
is
43 Mrad of aging which is enveloped
by a 200 Mrad
radiation test.
No findings were identified.
Scotch Electrical
Tape
(EgDP 16.4)
The
inspector briefly reviewed
the file for Scotch
semi-
conducting
electrical
tapes.
The qualification
basis
was
12
(13)
NUREG-0588/Category II.
The
cable
is
not
used
in safety
applications
in the containment
and
main
steam
tunnel,
making
the
maximum accident
temperature
167'F.
A Radiation aging dose
of 43 Mrad was enveloped
by test.
No findings were identified.
Okonite Electrical
Tape
(EQDP 16.3)
The inspector
reviewed
the file for Okonite T-95
and
No.
35
electrical
tapes
used for splices
and terminations
outside of
the containment
and main steam tunnel.
The worst case
accident
temperature
is 167'F.
The qualification basis
was
NUREG-0588/
Category I.
The
normal
aging
dose
of
43
Nrad
was
easily.
enveloped
by test.
No findings were identified.
(14) AIW Cable
(EQDP 6.5)
The
inspector
reviewed
th'e file for
AIW cable
used
for
instrumentation
and control
applications
outside
containment.
The qualification basis
was
NUREG-0588/Category I.
Both the
tested
and installed cables
are single conductor with 30 mil .of
EPDN insulation.
The test profile enveloped
the plant require-
ments.
IRs
measured
during the
steam
exposure all exceeded
108L.
No findings were identified.
(>5)
(I6)
RdF Temperature
Elements
(EQDP 39.8)
The inspector
reviewed the file for RdF model
21205
RTDs used to
monitor
RCS hot
and
cold leg temperatures.
The qualification
basis
was
NUREG-0588/Category I.
The test units were identical
to
those
used
in
the plant.
Qualification
was
based
on
supplement
2-E06A of WCAP-8687.
Aging was
performed for 264
hours
at 400'F giving
a qualified life of 23 years
at
100'C
(50'C
ambient
+
50'C
heat
rise
due
to
process
fluid).
Performance
was monitored
by measuring, the detector
outputs
and
monitoring
insulation
resistance
to
ground
periodically
(specification of I NL minimum).
Because
of testing
problems,
the cable to the detector
was installed in sealed
conduit to get
the unit to pass.
The plant requires
the installation of
a
Conax
T8 sealed
termination
head with a
Conax
ECSA to address
the sealing
requirement.
The qualified life determination
is
still pending verification of service
temperature.
No findings
were identified.
BIW Triaxial Cable
(EQDP 6. 1)
The inspector
reviewed
the package for BIW triaxial cable with
Tefzel
insulation.
The qualification basis
was
NUREG-0588/
Category I.
Testing
to
envelope
the
plant conditions
was
performed
but the
documentation
in the file was
considered
inadequate
to support
Category
I qualification.
Specifically,
the
items of Section
8.3 of
were
not fully
13
(I7)
addressed.
However, this item was previously accepted
by
NRR in
Supplement
4, Section 3.11.4.
Target
Rock Solenoid Valves
(E(DP 3. I)
The
inspector
reviewed
the file for Target
Rock
799 series
solenoid
valves.
The qua'lification
basis
was
NUREG-0588/
Category I.
The valves
are primarily sampling
system contain-
ment isolation
valves.
Some of the
valves
are continuously
energized
and/or
subject to process
heat rise during
normal
operation.
Typically, the valves all closed at the beginning of
an accident,
but there still may
be process
heat rise.
The
licensee
performed
calculations
which
showed
very
short
'ualified
lives for
some of the valves
(on the order of one
month),
based
on the artificial aging performed.
An analysis,
based
on testing
done
on
a valve
removed
from Sequoyah
after'ive
years of continuously energized
service,
was
used to extend
th'e
minimum qualified life to one cycle.
Two questions
wer e
posed
to the licensee.
First, the valve
removed
from Sequoyah
did not appear
to be
one which would be subject to process
heat
rise,
resulting
in
a question
of the applicability of the
Sequoyah
valve.
Second, .it was, not clear what process fluid
temperature
was
used
in the Target
Rock test,
resulting in
a
question
of whether
the
plant valves
cou'Id
be
exposed
to
temperatures
above their qualification when accident conditions
are combined with process
heat rise.
The licensee
is addressing
the first question
through
on-going
evaluation
and
a test
program using naturally-aged
valves being removed from the plant
during the current outage.
The second
question
was adequately
addressed
by considering
the accidents
where the valves would be
needed,
their required
state
during these
accidents,
and the
actual
accident profile.
The question of qualified life and the
results
of additional
testing will be
reviewed at
a future
inspection.
Therefore,
this
item is
considered
unresolved
pending
the results of the testing to be performed
on the coils
removed
during this outage
and documentation
of the results
by
NED in the
E(DP (Unresolved
Item (URI) 50-400/88-27-02).
(18) Limitorque Actuators
(Dual Voltage),
Equipment
Tag Nos.
and,lCS-470
(Inspection Plan TI 2500/17)
The
Phase
1
Eg inspection
held
March 7-11,
1988, identified
50-400/88-04-01,
Nylon
type
Crimp
Connectors
on
Dual
Voltage
Limitorque Actuators.
At the
close
of that
inspection,
the
licensee
committed
to obtain qualification
documentation
for the
nylon crimp connectors
or
remove
the
connectors
and replace
them with qualified splices.
The purpose
of the
Phase
2 equipment
walkdown was to physically inspect the
dual voltage limitorque actuators
inside containment,
determine
if the
nylon
connectors
were
being
used,
and
evaluate
the
licensee's
basis for qualification of these
connectors.
14
There
are
two dual
voltage Limitorque actuators
(1CC-,249
and
inside
containment.
The
walkdown of these
valves'erified
that the mounting configuration was consistent
with the
tested
configuration.
The T-drains
and
grease
reliefs
were
found to be properly installed.
The equipment
was identified by
the manufacturer's
nameplate
as
a
dual
voltage
model.
The
licensee. stated that the nylon connectors for both were replaced
with Raychem splices.
The inspection of
1CS-470 verified that
Raychem splices
were
installed
on the motor lead connections.
When questioned,
the
~ licensee
could not identify the type of connectors
since
the
connectors
were not saved.
The licensee
stated that there
was
documentation
available
from Limitorque which indicated that
only Thomas
and Betts connectors
were supplied in the actuators.
Aging qualification could
be
demonstrated
by
a separate
test
report
on
the
motor.
Although,
these
documents
were
not
reviewed, it appeared
that
the
connectors
were qualifiable.
This finding was identified
as
a potential violation,
on the
basis
that
at
the
time of the
inspection
the
Eg file was
deficient in showing the qualification of the nylon connectors,
however, it is not clear that the licensee
should
have
been
aware
of this
problem
considering
the
location of these
connectors.
Therefore,
a violation will not be cited.
(I9)
Component
was
not
inspected
internally
since
the
licensee
stated that the
same
Raychem splices
were installed to
replace the nylon connectors.
Limitorque Actuators
Equipment
Tag Nos.
IED-94,
and 1SI-246 (TI 2500/17)
The
above
Limitorque actuators
were
inspected
for mounting
configuration, T-drains,
grease reliefs,
nameplate
information,
and internal wiring.
The installed configuration
was
found to
be consistent
with the
tested
configuration.
All walkdown
concerns
were addressed
prior to the close of the inspection.
The inspection of 1RH-40 discovered
a small
leak of red grease
inside
the
housing for the limit switches.
The
licensee
identified the grease
as Mobil 28 and stated that orientation of
the
actuator
prevented
the
grease
from reaching
the
switch
contacts.
Work ticket
WR5A 88AUJSI
was
issued
to clean
the
housing.
Valves
and
were
found to
have
terminal
boards
wired at adjacent
points, while 1SI-246
was wired at alternate
points.
When questioned,
the licensee
explained
that either
wiring configuration
was
acceptable,
since
Limitorque report
80119 supported
the
use
the
GE, marathon,
and
Buchanon terminal
blocks
in their worst
case
wiring configuration
(adjacent
points).
15
There were several
Raychem splices
where the shim protruded
from
the sleeve
and other
c'ases
where the sl'eeve
overlapped
the shim.
When questioned
the licensee
stated that the
Raychem installa-
tion Guide was used
as the basis for the plant 'procedures
-WP-210
and
EMP-3.
The installation
guide indicates that
an accident
location
requires
a 2-inch
seal
length.
In
a single
installation
the
shim may
be overlapped
or protrude
from the
insulation
The seal
lengths
of several
splices
were
measured
and found acceptable.
Barton Transmitter
Models
763
and
765,
Equipment
Nos.
LT-474,
LT-477, 1RC-455,
and
The above transmitters
were inspected for mounting configuration
'and wiring and found acceptable.
Raychem splices
were used for
all connections.
Single
were
used
and
appeared
to
be
properly installed.
There
were
no concerns
identified during
the walkdown.
(21)
(22)
Tag Nos.
TE-1313
and TE-1314
The
above
were
inspected for mounting configuration
and
wiring and found acceptable.
Raychem splices
were used for all
connections.
Single shims were used
and appeared
to be properly
installed.
The locations of all Minco RTDs were identified and
found to
be
above
flood level.
There
were
no
concerns
identified during the walkdown.
Reliance
Motors,
Equipment
Tag
Nos.
1CV-E002:004
and
ICV-E002:005
As a result of the
Phase
1
Eg inspection,
the licensee
committed
to inspect
the
Re'liance
motors
and
remove
the grease
lines to
the sealed
bearings.
However,
subsequent
to that commitment the
licensee
determined that the motor had double shielded
bearings
for which the use of grease
lines
was specified.
The licensee
surveyed
knowledgeable
personnel
at
Shearon
Harris
and other
plants for advice
on lubrication of the motor bearings,
but the
results
were inconclusive.
The licensee
took the conservative
approach
and committed to install the grease
lines
on the motors
during the outage.
The work tickets were identified and found
acceptable.
The licensee will void the original work tickets to
remove the grease
lines.
This explanation
was acceptable.
The
motors
were not inspected
during the walkdowns
due to limited
time.
(23) Hydrogen Recombiner
Equipment
Tag No.
The
equipment
was
inspected
for mounting configuration
and
wiring and
found acceptable.
The
5
and
I
Raychem
splice
=
16
(2~)
configuration appeared
to be properly 'installed.
There were no
concerns
identified during the walkdown.
Electrical
Assembly,
Equipment
Tag
Nos.
and
(25)
These
assemblies
were
inspected
for mounting
configuration
and wiring and
found acceptable.
Penetra4ion
(and
other
in
the vicinity) could
not
be
identified from the back panel,
which required
someone
to crawl
around
the
assemblies
in order
to
locate
the
equipment
tags.
There
was
a concern
that personnel,
exposure
would be incr eased
anytime
someone
needed
to identify a specific
assembly.
The licensee
issued
WRSA 88-AUNG1
and
committed to lable the penetrations
on the
back side of each
enclosure.
This was acceptable.
The inspection of Penetration
1AB-1255 discovered
several
black
wires with the
bare, conductor
showing where the insulation
was
stripped back.
When questioned,
the licensee
explained that the
Raychem splices
associated
with these
cables
were supplied
by
as part of the electrical
assembly.
Installation was done in accordance
with the
Raychem guidelines.
The shield
on all cables
spliced
by Westinghouse
are covered for
isolation purposes
only.
This explanation
was acceptable.
GEMS
Transmi tter,
Equipment
Tag
Nos.
LE-01CT-7160ASA
and
LE-01CT-7160ASB
(26)
The
equipment
was
inspected
for mounting configuration
and
wiring and
found acceptable.
Raychem
splices
were
used
and
appeared
to be properly installed.
The junction box was filled
with silicon oil as
required
to seal
the terminations for the
sensors.
No concerns
were identified during the walkdown.
Eg Cable Identification
During the
walkdown portion of the inspection,
the inspector
obtained
cable identification
numbers
from the cable
connected
to selected
Eg equipment.
The licensee
was then
asked
to show
that
the
installed
cable
was .qualified
by their existing
'qualification
documentation.
With the 'cable
identification
number,
the licensee
referenced
the applicable pull card which
showed
the
cable routing,
reel
number
and termination
points
along with
a receipt
inspecti'on report which shows the bill of
materials
number for the installed cable.
The bill of materials
number
was
shown
on the
Eg Master List which identified the
Eg
file which established
the qualification for that cable.
.With
this
sampling,
the
inspector
determined
that
adequate
traceability
existed
for the
cables
requiring
environmental
qualification.
17
(27)
Samples of Target
Rock Solenoid Valves,
ASCO Solenoid Valves and
Namco Limit Switch installations
were
examined
in various
locations inside containment for manufacturer
and model
number,
orientation,
installation,
and interfaces (i.e.,
cable splice
and
entrance
seals).
No concerns
were identified during the
walkdown.
Since
the
inspection
the
licensee
has
reported
several
concerns
regarding
the
qualified
status
of their
installed Target
Rock valves
as
a result of cracked insulation
on
Reed Switch lead wires, cracked terminal blocks
and lack of
~
similarity between
tested
configuration
versus
vendor supplied
components
(i.e.,
terminal
blocks
and wiring).
All these
components
are
internal
to the
device.
Licensee
plans
to
replace all questionable
parts prior to restart.
f.
Followup of Licensee's
Commitments
Resulting
From the
Phase I
" Inspection
At the conclusion of the
Phase I
EQ inspection,
there
were
numerous
action
items which the licensee
committed to perform.
During the
Phase
2
EQ inspection
the
INEL inspectors
examined
the
EQ files,
change
requests,
and
work requests
to verify that
the
licensee
fulfilled its
commitment to resolve
these
items.
These
documents
were reviewed
and discussed
with the licensee
to verify that the
concerns
were adequately
addressed.
The Phase
2 inspection verified that the basis for corrective action,
qualification analyses,
s'afety analyses,
revisions to the
EQ files,
and
internal
reviews
were
performed
and
accepted
by the licensee
before
the
Phase
1 action
items
were considered
closed.
Discussion
with the
licensee
and
a brief walkdown of the 'central
files
determined
that
the
document
control
was
acceptable.
All work
requests
resulting
from the initial inspection
were
found to
be
completed or scheduled for completion during the outage.
Other
NRC
Inspectors
verified the licensee's
commitments for
EQ training and
replacement
equipment.
The following documents
were reviewed with respect
to updating the
files and found acceptable:
EQDP 3.3
Limitorque Actuators
EQDP 8.2
GA High Range Monitor
EQDP 8.3
'GEMS Transmitter
EQDP 8. 11 Barton Transmitter
763 and
764
EQDP 15. 1 Westinghouse
Electrical penetration
2959,
2960,
3036,
3037,
3038,
3039,
3040,
3041,
3042,
3078
and
3414
With the
exception of the Limitorque crimp connectors,
all action
items resulting from the previous
inspection
were reviewed
and found
to be closed or awaiting closure during the outage.
18
3.
Action On Previous
Inspection
Findings
(92701)(92702)
a ~
(Closed)
URI 50-400/88-04-01,
Nylon Type
Crimp Connectors
On
Dual
Voltage Limitorque Actuators'TI 2515/75)
During the first round
Eg inspection,
the possible
use of nylon type
crimp connectors
in dual voltage Limitorque operators
was identified.
The
licensee
identified four valves
(two inside
and
two outside
containment)
with
dual
voltage
operators
and
possible
crimped
connectors.
The information that
was available to the licensee
was
not adequate
to establish qualification of the crimp connectors.
The
licensee,
therefore,
committed
to either obtaining
the
necessary
documentation
or to remove all the nylon type crimped connectors
and
replace
them with qualified splices.
The . licensee
issued
Work Requests
88-ATS41
and
88-ATSZ1 for 1CS-470
and
1CC-249, respectively,
to remove the nylon type crimp connectors.
The work requests
were completed
a few days prior to this
inspection.'ven
though the licensee
was aware of =the qualification issue
and its
importance,
the nylon type crimp connectors
that were
removed
from
the
motors
had
been
thrown
away.
However,
recent
information
obtained
during
an
inspection
of
(NRC
Report
No.
99900100/88-01)
seems
to indicate that only
joints were used.
The test report the licensee
referenced
during the first inspection
(Limitorque Test
Report
B0003)
could only
be
used
to establish
qualification of the
connectors
for six to twelve months
had the
connectors
been
Thomas
and Betts
RB-4 or
6 models for use outside
containment.
Without the
removed
connectors,
the licensee
could not
clearly establish qualification of the affected motor operators
.to any
test
report.
The
licensee's
failure
to
have
qualification
-documentation
in
a file for the
TSB connectors
is
an
apparent
violation of the
Eg rule; however,
as stated earlier in the paragraph
2.e. 18.,
no vi'olation will be cited
because it is not clear the
licensee
should have
been
aware of this problem.
While the
connectors
were being
replaced
on
the licensee
identified that the T-drains were missing
on the motor.
Work request-
88-ATSXI was performed
on August 13,
1988, to install the T-drains
on
the motor.
The licensee
was asked
to provide
a scenario of when the
T-drain
issues
had
occurred.
For
1CS-470, it was
found that
WR86-BFPV1
had
been
performed to install T-drains
on the motor.
Even
though
the
work request
had
been
signed off as
being
completed,
1CS-470 did not have T-Drains installed
when it was being worked on
in August
1988.
Although this T-drain issue
was identified
by the licensee, it is
considered
as another
example of Violation 88-27-01.
This is due to
the fact that the licensee
had
been notified that
NRC would look at
this particular valve during this inspection.
'
19
b.
4.
Exit
(Closed)
Inspector
Followup Item 86-88-03,
Continue
Review of Cable
-Splicing Program
and TI2500/17, Inspection
Guidance for Meat Shrinkable
Tubing
Documentation
to qualify the
Raychem 'heat
shrinkable
tubing
was
reviewed
and
documented
in
NRC Inspection
Report No. 50-400/88-04
as
being acceptable.
A walkdown of a sample of splices
was performed
by
the
inspectors
as well
as
a review of the licensee's
activities
regarding
Raychem heat shrinkable splices.
The
walkdown did
not identify
any splices
in
an
unqualified
configuration.
The licensee
had identified
some splices
prior to
this
inspection
that, did not
meet
the
bend
radius
specified
in
procedure
ENP-3 for installing the heat shrink tubing.
Although the
procedure
was
not followed,
the splices
were qualified
by the
qualification package.
The licensee
has taken corrective actions to
require
gC inspection
hold points during this installation of the
Raychem splices.
It should
be noted that
had this been identified by NRC, it would have
resulted
in the citing of
a violation for failure to follow
procedures.
However, since this was identified by the licensee, it
fits in the Severity
Level IV or
V category, it did not require
reporting,
corrective
actions
have
been
taken,
and it was
not
a
repeat violation.
No violation will be cited in this case.
Based
on the results
of the
walkdowns
and
the previous
document
reviews,
these
items are considered
closed.
Interview
The inspection
scope
and results
were summarized
on August 19,
1988, with
those
persons
indicated
in Paragraph
1.
The inspectors
described
the
areas
inspected
and
discussed
in detail
the inspection
results listed
below.
Proprietary
information is
not contained
in this report
and
dissenting
comments
were not received from the licensee.
The following new items were identified during this inspection:
Violation 50-400/88-27-01,
The
licensee
failed to
take
adequate
corrective action to ensure that maintenance
did not violate the
Eg
boundaries
of Eg equipment,
paragraph
2.a.
Unresolved
Item 50-400/88-27-02,
EgDP 3. 1 is the qualification file
for Target
Rock
790 Series
Solenoid
Valves.
The licensee
performed
aging calculations
which
showed
very short qualified lives for the
continuously energized
valves
(on the order of one month),
based
on
the artificial aging of tested
samples.
The licensee
extended
the
qualified life to
a cycle based
on a
TVA report.
The
NRC questioned
20
the
use of the
TVA report
because
the licensee failed to show the
'similarity between their installation (i.e;, continuously energized
on
hot
process
pipe)
and
TYA's installation, at
Sequoyah.
The
licensee
committed to do additional testing
on naturally-aged
valves
being
removed
from
the
plant, during
the
current
outage,
paragraph
2.e.17.