ML17286B025
| ML17286B025 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 08/15/1991 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17286B023 | List: |
| References | |
| 50-397-91-16, GL-89-10, NUDOCS 9108300005 | |
| Download: ML17286B025 (39) | |
See also: IR 05000397/1991016
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report
No. 50-397/91-16
Docket No. 50-397
License
No.
Licensee:
Washington Public Power Supply System
Facility Name:
Washington Nuclear Plant Unit 2
Inspection at:
WNP-2 Site,
Richland,
Inspection
Conducted:
May 20,
1991 through June
21,
1991
Inspectors:
D. Corporandy,
Reactor
Inspector
(RV)
C. Myers, Resident
Inspector
(RV)
T. Scarbrough,
Senior Mechanical
Engineer
(NRR)
C. Clark, Reactor Inspector
(RV)
Consultant:
Approved by:
~Summar:
R. Cain,
MOV Inspector (Contractor,
INEL)
I
lrsc
,
1e
Reactor Safety Branch
a
e
sgne
Ins ection Durin
The Period
Ma
20-June
21
1991
(Re ort No. 50-397/91-16)
Areas Ins ected
This inspection
reviewed the licensee's
program
or sa ety-related
motor-operated
valves.
(SIMS Issue GL-89-10).
Temporary Instruction 2515/109
was
used
as guidance for the inspection.
Results:
General
Conclusions
and
S ecific Findin
s
Inspection findings at this stage of development of the licensee's
program
identified a number of areas
of weakness.
Certain areas clearly deviate
from the licensee's
GL 89-10 commitments.
Other areas, if implemented
as
planned,
may constitute further deviations.
A summary of significant findings and the sections of the report which discuss
them are provided below.
9108300005
910816
ADOCK 05000397
8
t
e
i
1.
Emergency Operating
Procedures
(EOPs) not reviewed to establish
scope of MOV program.
(Section
4. 1).
2.
Plant specific procedures
not reviewed in Design Basis
Review (DBR)
(Section 4.2).
3.
Nominal reactor pressure utilized in DBR (Section 4.2).
4.
Mispositioning not addressed
in DBR (Section 4.2).
5.
No consideration of rate of loading (Section 4.3).
6.
No consideration
of high ambient temperatures
(Section 4.3).
7.
Thermal overload devices
not controlled as
MOV switch settings
(Section
4.3).
8.
No consideration
of seismic/dynamic effects (Section 4.3).
9.
Jumpers
not controlled on Master Data Sheets
(MDS) (Section 4.8. 1).
10.
Diagnostic accuracy not verified (Section 4.8.3).
Summar
of Violations:
One Level IV violation was identified for failure to document spring pack
relaxation
on a Problem Evaluation Report (Enforcement
Item 50-397/91-16-08.
Refer to Section 4.6).
Summar
of Deviations:
Two deviations
were identified:
The first, for deviating from the licensee
s
GL 89-10 commitments
(Deviation Item 50-397/91-16-02.
Refer to Sections
4.2
and 4.3).
The second,
for deviating from the licensee's
commitment to size
motors for degraded
voltage conditions of 80K of nominal voltage.
(Deviation
Item 50-397/91-16-03.
Refer to Section 4.3).
0 en Items
Summar
Eleven
new followup items were identified.
TABLE OF
CONTENTS
Section
1.
Persons
Contacted
2.
Background
3.
Inspection
Plan
4.
MOV Program
Review
4.1
Scope
4.2
Design Basis
Reviews
4.3
MOV Sizing and Switch Setting Calculations
4.4
Design Basis Differential Pressure
and Flow Testing
4.5
Periodic Verification of MOV Capability
4.6
MOV Failures,
Corrective Actions and Trending
4.7
Schedule
4.8
Other
MOV Program Areas Addressed
4.8. 1 Control of MOV Switch Settings
4.8.2 Training
4.8.3 Diagnostics
4.8.4 Modifications
4.8.5 Maintenance
4.8.6 Industry Experience
and Vendor Information
4.8.7 Inservice Testing
4.8.8 Implementation of Supplement
3 Recommendations
5.
Summary of Overall
Program Administration
6.
Exit Meeting
.Pa(ac
1
10
12
16
17
18
19
19
20
22
DETAILS
Persons
Contacted
Washin ton Publi'c Power
Su
'1
S stem
~J.
D. Arbuckle, Compliance
Engineer
~P.
McBurney,
QA Engineer
- M. Grindel,
HOV Engineering Coordinator,
Generation
Engin
~ *L. Harrold, Assistant Plant Manager
- J. Baker, Plant Manager
"D. J.
Mand,
Lead Engineer,
Plant Technical
- R. Webring, Plant Technical
Manager
"P. Macbeth,
Nuclear Systems
and Analysis Manager
"S.
L. Berry,
HOV Program Coordinator
"T. Hoyle, Supervisor,
Code Programs
"A. Hosier,
Licensing Manager
"G.
C. Sorensen,
Regulatory
Programs
Manager
"J.
D.
Harmon, Maintenance
Manager
- W. E. Milbrot, Nuclear Engineer,
"B.
R.
Nowack, Principal
Engineer
"N. Porter,
Manager, Electrical/I8C
"J., Fu,
NSA Engineer
"W. Waddel,
Manager,
P8S
"G. Gelhaus,
Assistant Plant Technical
Manager
"J.
W. Massey,
Engineer,
OEA
"S.
L. Washington,
Compliance Supervisor
"S.
E. Cueto,
Senior Maintenance Trainer
C.
M. Powers, Director of Engineering
R.
L. Koenigs,
Manager,
Generation
Engineering
J. Trobaugh, Electrical Maintenance
Supervisor
T. Meade, Electrical
Group Supervisor,
Plant Technical
J. Wyrick, Outage
Planning
D. J. Pisarcik, Assistant Health Physics/Chemistry
Manager
B. Evans,
MOV Maintenance
Coordinator
eering
" Attended Exit Heeting
The inspectors
also interviewed other licensee
and contractor personnel
during the course of the inspection.
t
~
i
f
Back round
Generic Letter (GL) 89-10, "Safety-Related
Motor-Operated
Valve Testing
and Surveillance,"
dated
June 28,
1989 requested
that licensees
establish
a program to ensure that switch settings for safety-.related
motor-operated
valves
(MOVs) and certain other
MOVs in safety-related
systems
are selected,
set
and maintained properly.
Supplement
1 to GL 89-10 provided the results of public workshops
on the implementation of
the Generic Letter.
Supplement
2 to GL 89-10,
dated August
3
1990,
stated that inspections of programs
developed in response
to 5L 89-10
would begin January
1, 1991.
In response
to concerns
raised
by the results of NRC sponsored
MOY tests,
Supplement
3 to GL 89-10,
dated October 25, 1990,
requested
that boiling
water reactor
(BWR) licensees
evaluate
the capability of MOYs used for
containment isolation in the steam supply lines to the High Pressure
Coolant Injection and Reactor
Core Isolation Cooling (RCIC) Systems,
in
the supply line to the Reactor Water Cleanup
(RWCU) System,
and in the
lines to the isolation condenser,
as applicable.
Supplement
3 requested
that all licensees
consider the applicability of the information obtained
from the NRC-sponsored tests to other
MQYs within the scope of GL 89-10
and to consider this information in the development of priorities for
implementing the Generic Letter program.
GL 89-10 requested
that licensees
submit
a response
by December
28,
1989.
The WNP-2 response
to the Generic Letter, dated
December
22, 1989, stated
that the recommendations
of GL 89-10 would be completed for those
that can
be tested in-situ at design basis
pressure
and flow by June
28,
1994.
For those
MOVs that cannot
be tested in such
a manner,
the
licensee
committed to implement the "two-stage
approach" outlined in the
Generic Letter, but indicated that the second
stage
might not be
completed within the
5 year period.
The
NRC staff reply, dated
December
12, 1990,
acknowledged
the licensee's
commitment to implement the
recommendations
and schedule of GL 89-10 with the single exception of the
completion of the second
stage of the program within the five year
period.
The
NRC staff encouraged
the licensee to carefully review
available data with particular emphasis
on those valves
whose design
capabilities
are close to the operating requirements.
Ins ection Plan
The inspection
was performed in accordance
with Temporary Instruction
2515/109,
"Inspection Requirements
for Generic Letter 89-10,
Safety-Related
Motor-Operated Yalve Testing and Surveillance,"
dated
January
14,
1991.
The inspection
focused
on Part
1 of the temporary
instruction (TI) which involves
a review of the program being established
by the licensee in response
to GL 89-10.
The inspectors
did not address
Part
2 of the TI, which involves
a review of program implementation,
except to assist in evaluating the licensee's
GL 89-10 program.
The inspectors
reviewed the licensee's
program commitments
as established
in their December
22,
1989 response,
as well as their
December
12,
1990
response
to Supplement
3.
The inspectors
reviewed the licensee's
program
description entitled Motor Operated
Valve Program Plan,
dated July 16,
1990',
and other licensee
documentation,
and discussed
the program in
detail with licensee
personnel.
The inspectors
also observed
ongoing
maintenance
and testing of the licensee's
MOVs.
4.
MOV Pro
ram Review
4.1
~Sco
e
GL-89-10 Recommendations
and Licensee
Commitments
recommended
that all safety-related
MOVs and other
that are position-changeable
in safety-related
piping systems
be
included within the scope of the licensee's
GL 89-10 program.
Supplement
1 to the Generic Letter defined "position-changeable"
as
any
MOV in a safety-related
piping system that is not blocked from
inadvertent operation
from the control
room.
In their response
to
GL 89-10, the licensee
committed to the scope of the program
as
recommended
in GL 89-10.
Observations
The licensee
based
the scope of their program
on the
BMR owner's
group
(BMROG) generic identification of safety related valves
required to perform active design basis safety functions.
The
licensee
supplemented
the gener)c analysis with a plant specific
analysis (calculation NE-02-88-06,
R.O.
dated 10/13/88) of all 479
MOVs in the plant.
These
reviews identified 163 NOYs, including 115
gate valves,
33 globe valves
and 15 butterfly valves,
which the
licensee
considered to be within the scope of their GL 89-10
program.
All of the 163
NOVs were equipped with Limitorque
actuators.
The remaining 316
NOVs outside the scope of GL 89-10
continue to be maintained
under previously established
practices.
The inspectors
found that the licensee
did not utilize any measures
to prevent inadvertent mispositioning from the control
room as part
of their program.
As such,
the scope of the program did not exclude
any valves
based
on compensatory
measures
to preclude
mispositioning.
After reviewinq several
of the licensee's
piping and instrument
drawings,
the inspectors
found instances
where
some
MOYs in safety
related
systems
had been excluded
from the licensee's
program scope.
The inspectors
found no documented justification for
their exclusion.
In one case
(RMCU MOVs beyond the containment
isolation valves), it appeared
that exclusion of the
NOVs could be
justified.
The licensee
committed to review all safety related
that had been excluded
from the
GL 89-10 program
and to provide
documented justification.
(Followup Item 50-397/91-16-01).
The inspectors
also found that the licensee
had not reviewed
emergency
operatinq procedures
(EOPs) in establishing
the scope of
their program.
This fai lure to review EOPs is a deviation from
the recommendations
given in the
NRC response
to auestion
6 of
Supplement
1 to GL 89-10.
(Deviation Item 50-397191-16-02).
4.2
Conclusions
Based
on the above deviation
and followup item, the inspectors
determined that the scope of the licensee's
program
had not .yet been
adequately
established.
Desi
n Basis
Reviews
GL 89-10 Recommendations
and Licensee
Commitments
Recommended
Action "a" of GL 89-10 requested
the review and
documentation of the design basis for the operation of each
MOV to
determine the maximum differential pressure
and flow (and other
factors)
expected for both normal operations
and abnormal
conditions.
The licensee
committed to follow the recommendations
of
Observations
The inspectors
discussed
the performance of design basis
reviews
with licensee
personnel
and reviewed Supply System Engineering
Standard
NES-8 (REV. 0, 9/18/89), "Differential Pressure
Calculations for Motor Operated Valves," as well as several
design
basis
review packages.
At the time of the inspection,
the licensee
had completed
151 design basis
reviews of MOV's within its GL 89-10
program.
However, the licensee
had not included all appropriate
factors,
such
as flow and temperature
effects.
The licensee
recognized that
some factors
beyond differential pressure
needed to
be addressed
in its calculations
(e.g. fluid deceleration)
and
committed to more fully address
design basis factors.
This will be
a followup item for future inspections.
The licensee
applied the results of calculations
by the
BWR Owners
Group of differential pressures
predicted to be experienced
by MOVs
in generic
BWR systems.
The licensee
had not verified that those
determinations
of differential pressure
by the
BWR Owners'roup
were applicable to WNP-2.
in particular, the licensee
had not
evaluated
normal,
abnormal,
surveillance testing,
and emergency
operating procedures
to ensure that the
BWR Owners'roup
values
bound the worst case operating conditions that might be seen
by MOVs
at WNP-2.
For example,
the licensee
found during surveillance testing that
HPCS-V-23 could not close against the surveillance differential
pressure
which was greater
than the assumed
design basis
differential pressure.
The design basis
maximum differential
pressure
(DP) had been
based
on simultaneous initiation of HPCS-V-23
closure
and core spray injection valve opening.
This design basis
conditioh resulted in a maximum
DP less
than the shutoff head of the
HPCS pump, since
some pressure
reduction could be credited to the
.
opening of the injection valve.
Eventually the torque switch
setting
was increased
to accommodate
surveillance test conditions.
However, the original design basis
pressure
listed on the Master
Data Sheet
(HDS) remained
unchanged.
The inspectors
found that this
indicated that the licensee
had established
the maximum operating
requirements
for the
MOV based solely on the original design
basss
conditions.
While not .requesting that the original desiqn basis
conditions
be exceeded,
GL 89-10 recommends
that the design basis
review should conservatively establish worst case operating
conditions
under normal
and abnormal
events.
As a result of the problems
encountered
with HPCS-V-23, the licensee
had initiated a program to review surveillance
and testing
requirements
to ensure that differential pressures
experienced
during those activities were bounded
by the design-basis
differential pressures.
The licensee
was cautioned that, in the
execution of their program, if the worst case differential pressures
are not applied in determining adequate
sizing and switch settings
for MOVs within the
GL 89-10 program, this would constitute
a
departure
from the guidance
given in Supplement
1 for satisfying
recommended
action
a" of GL 89-10.
This will be
a followup item
for future inspections.
The inspectors
found that, in some instances,
the licensee
had
assumed
nominal reactor pressure
as the maximum differential
pressure
across
valves in lines that directly communicate with the
reactor vessel.
The licensee
had not demonstrated
that nominal
reactor pressure
bounds the
maximum reactor pressure
minus pressure
loss in piping from the reactor vessel
to the valve.
The licensee
committed to perform a review to ensure that nominal reactor
pressure
bounds the worst case differential pressure
across
the
valve.
The licensee's
use of nominal reactor pressure
as the design
basis for operability rather than the maximum differential pressure
at the
MOY is a deviation from recommended
action "a" of GL 89-10.
(Deviation Item 50-397/91-16-02).
The licensee
indicated that, for MOVs within the
GL 89-10 program,
the design-basis
differential pressure
is determined only for the
safety function direction of the valve.
The licensee
considered
an
MOV that must be closed to perform its safety function to have
a
close safety function direction.
Similarly, the licensee
considered
an
MOV that must be open to perform its safety function to have
an
open safety function direction.
Under the licensee
s classification
method,
some
HOVs have both open
and close safety function
.directions.
In those
cases it was not apparent that the licensee
had determined
the
maximum differential pressure
for the open safety
function direction.
The licensee
committed to ensure that the
appropriate
design basis factors are specifically determined for
HOVs with an open safety function direction.
This will be
a
followup item for a future inspection.
If an
MOV has only one safety function direction, the licensee
indicated that the differential pressure for that direction is
applied to the non-safety function direction as well.
The
inspectors
discussed
with the licensee
the possibility that the
differential pressure for the non-safety function direction could be
greater than the differential pressure for the safety function
i
I
t
i
I
f
t
'f
0'
direction.
For such
a circumstance,
the licensee
needs to ensure
that the
MOV will be able to operate
in its non-safety function
direction or that the
MOY will not be damaged
such that it is
incapable of moving to,its safety position.
This will be a.followup
item for future inspections.
The licensee
indicated that the potential for mispositioning to
cause differential pressure
higher than that provided by the
Owners
Group had not been spec>fically addressed.
While recognizing
that the condition had been corrected,
the inspectors
noted tfiat the
surveillance test failure of HPCS-Y-23 was
an example of where
mispositioning could cause
operating conditions exceeding
those
established
on the Master Data Sheet.
This failure to consider the
effects of mispositioning is a deviation from the recommendations
given in the
NRC response
to question
15 of Supplement
1 to GL 89-10.
(Deviation Item 50-397/91-16-02).
The followup items identified in this section
on design basis
reviews will be tracked
as Followup Item 50-397/91-16-03.
Conclusions
The inspectors
determined that the licensee
had not yet adequately
developed
plans
and procedures
for the performance of design basis
reviews.
MOV Sizin
and Switch Settin
Calculations
GL 89-10 Recommendations
and Licensee
Commitments
Recommended
action "b" of Generic Letter 89-10 requested
licensees
to review,
and to revise
as necessary,
the methods for selecting
and
setting all
MOY switches.
The licensee
committed to follow the
recommendations
of GL 89-10.
Observations
The inspectors
discussed
the licensee's
process for sizing
MOVs and
setting their switches
and reviewed
WNP-2 Calculation Method
NE-02-90-17
(Rev. 0).
The inspectors
reviewed several
calculation
packages
to evaluate
the development of the licensee's
program
and the licensee's
response
to Supplement
3 to GL 89-10.
The inspectors
found that the licensee
had not incorporated
the best
available data
from industry operating experience
and research
results in their selection of valve factors to be used in the
calculation of minimum required thrust.
In particular, the licensee
continued to use
a low valve factor of 0.3 in most of their
calculations of required
minimum thrust to operate
flexwedge gate
valves.
The inspectors
informed WNP-2 of a recent industry
experience
in which the
use of a 0.3 valve factor had resulted in a
70K test failure rate under high differential pressure
and flow
conditions.
Further, Calculation NE-02-87-29,
Rev.
0 indicated that
a valve factor of 1.0 would be assumed
in calculations of thrust
requirements
for globe valves.
This is less conservative
than the
Limitorque recommendation
of 1. 1 for the valve factor for globe
valves.
However, the globe valve calculations
reviewed by the
inspectors
did use
a 1..1 valve factor.
The inspectors
emphasized
that the
use of low valve factors places
a
heavy reliance
on the performance of design basis testing of NOVs
in-situ at MNP-2 in order to verify the licensee's
methodology for
sizing
HOVs and setting their switches.
The licensee will be
expected to justify its assumed
valve factors, especially in cases
where the assumed
valve factor is less
than the industry typical
value.
Further,
the inspectors
cautioned that the licensee will
need to be prepared to evaluate their methodology,
including
appropriate
consideration of NOV operability,
when results of design
basis testing are obtained.
This is particularly true for instances
where the calculation packages
indicate that the
HOYs are marginally
sized
and set.
The licensee's
FSAR indicated that Class lE motors would be sized to
erform adequately
when supplied with 80K of nominal voltage.
owever, for MOVs that were found to be inadequately
sized for the
80K bounding value, the licensee
used
a specific plant degraded
voltage calculation to establish
the actual
expected worst case
voltage condition.
For example,
RCIC V-8 appeared
to be inadequately
sized to perform it's design function when supplied with 80K of
nominal voltage.
Consequently,
a degraded
voltage of 87K was
used
to calculate motor torque requirements
for RCIC V-8.
This degraded
voltage is less conservative
than the 80K value given in the section
on "Minimum Voltage" for Class
1E motors
on page 8.3-30 of the
MNP-2
FSAR and is, therefore,
an apparent deviation from the licensee's
FSAR commitment.
(Deviation Item 50-397/91-16-04)
The inspectors
recommended that the licensee
ensure
the adequacy of
their degraded
voltage studies.
For example,
the licensee
should
ensure that appropriate
ambient temperatures
have
been
assumed
in
calculations of voltage losses
from cabling.
The staff will review
the licensee's
evaluation of degraded
voltage in future inspections.
(Followup Item 50-397/91-16-05).
MNP-2 Calculation Hethod NE-02-90-17
(Rev.
0) requires that
a 10K
thrust margin be included above the calculated
minimum requirements.
However, the licensee
considered this to be an administrative
conservatism
and not mandatory.
For example,
the licensee
included
only a 5X thrust margin in Manual Calculation NE-02-90-17
(Rev.
1)
for RMCU-V-1 and 4.
The inspectors
noted that the licensee
had not
identified a required margin to account for "rate of 1oadinq"
effects.
The licensee will be expected to address
these effects
and
to ensure that adequate
margin exists in the sizing of MOVs and
setting of their torque switches.
This will'be a followup item for
future inspections.
The licensee
had not identified any margin to account for variations
in operating characteristics
caused
by seismic/dynamic
loading.
Further, the licensee
had not included the negative
impact of high
ambient temperatures
on motor output.
These omissions constitute
a
deviation from the recommendations
given in the
NRC response
to
uestion
15 of Supplement
1 to GL 89-10,
(Deviation Item
0-397/91-16-02)
WNP-2 Calculation Method NE-02-90-17
(Rev.
0) stated that
a stem
friction coefficient of 0.2 would be used in MOV sizing
calculations.
However, in Manual Calculation NE-02-90-17
(Rev.
1)
for RWCU-V-l, the licensee
assumed
a stem friction coefficient of
0.20 to calculate
the lower bound value of the thrust window and
0.15 to calculate the upper
bound value of the thrust window.
The inspectors
cautioned the licensee
regarding the assumption of
differe'nt stem friction coefficients.
The assumption of 0. 15 as the
stem friction coefficient could be nonconservative,
unless specific
maintenance
and lubrication requirements
and frequencies
are
implemented to ensure
the continued high efficiency of motor torque
to stem thrust conversion.
The licensee typically sets thrust within the design window on
freshly lubricated
MOVs using data from diagnostic
equipment.
Provisions
should
be made to include
a margin associated
with the
difference in thrust based
on differences
between
minimum and
maximum expected
stem to stem nut friction.
The licensee will be expected to justify their use of stem friction
coefficients lower than the typical value of 0.20 and to demonstrate
that
MOV design margins include consideration of MOV performance
as
affected
by any expected
changes
in stem to stem nut friction (e.g.
during the time between
MOV lubrication service intervals).
This
will be a followup item for future inspections.
WNP-2 Calculation Method NE-02-90-17
(Rev.
0) stated that the
maximum torque switch setting will be based
on the minimum of the
actuator
gear rating, the Limitorque maximum recommended
switch setting,
and the motor pullout torque at degraded
voltage.
Limitorque Update 89-01 identified that maximum torque switch
setting includes valve manufacturer limits, if they were available.
The licensee will be expected to confirm that valve components
have
been considered
in the determination of limiting conditions for
maximum allowable torque switch setting.
This will be
a followup
item for future inspections.
The licensee's
program description stated that thermal
overload
devices
are utilized in accordance
with Regulatory Guide 1. 106,
"Thermal Overload Protection for Electric Motors on Motor-Operated
Valves."
The Program Plan also indicated that thermal overload
protection of motors would not be addressed
in the program.
The inspectors
reviewed the licensee's
original criteria for sizing
and setting thermal
overloads in Technical
Memorandum
1129 (August
ll, 1978) from Burns and
Roe, Inc.,
as well as
EES-5
(Rev. 0),
"Selection of Fuses
and. Overloads for Protection of 460
VAC and
125-250
VDC Motors."
Those
documents
indicated that the purpose of
the criteria for'electing fuses
and thermal overload relay heaters
was to protect motors
and circuits from short circuits and overloads
and to avoid nuisance tripping of motors.
The Burns
and
Roe
memorandum
noted,
however, that there
was
a chance of burnout of
small motors if the valve became
jammed
and torque
and limit
switches did not operate.
The licensee
places
a high degree of
reliance
on thermal
overload protection for its motors because
torque switches
are jumpered or bypassed for 90 to 95% of valve
stroke in the safety direction for MOVs.
As the Burns
and
Roe
criteria appeared
to take credit for the presence
of torque
switches;
the inspectors
requested
the licensee to review their
thermal
overload protection criteria to ensure that appropriate
consideration
has
been given to the applicability of the criteria at
WNP-2.
In particular, the inspectors
emphasized
consideration of
the following areas:
Thermal overload devices
(TOLs) and fuses
are sized based
on
full load amps
(FLAs), which is the cur rent which the motor
draws
when operating at running torque,
which is nominally
rated
by the manufacturer at 20K of the rated motor torque.
In
the
MOV applications at
WNP 2,
FLAs greater
than
20K value were
often encountered
due to line pressure
and packing loads.
The
licensee
was cautioned to consider the actual
FLA in the
application calculations.
The licensee
should verify that the
use of rated
FLA adequately
bounds
expected
normal
and design
basis conditions.
The licensee
did not consider
motor ambient temperature
in
sizing the TOLs.
The allowable temperature
rise of 40'C was
based
on an initial ambient temperature
of 40'C (104'F).
In
certain locations
and under certain operating
modes, initial
ambient conditions
may exceed
40
C.
Also, repeated
cycling of
the
MOV may be restricted
by this limit, requiring cool off
time between cycles for the motor temperature
to return to
ambient conditions.
The licensee
committed to review their thermal
overload protection
to ensure that it has established
adequate
control of thermal
overload protection for MOVs and that the criteria are, appropriate
for WNP-2.
The licensee's
failure to address
the impact of thermal
overload switch settings
on the capability of the
MOUs to perform
their designated
safety function(s)
was
a deviation from the
recommendations
in the
NRC response
to question
21 of Supplement
1
to GL 89-10.
(Deviation Item 50-397/91-16-02).
Some
WNP-2
MOVs required motor performance
calculated
beyond the
"knee" of the manufacturer's
motor performance
curves.
NRC
sponsored
tests
have
shown that beyond the
knee of the motor
performance
curve, motor performance
under degraded
voltage
10
conditions
can
be far less
than that predicted
by the manufacturer's
performance
data.
WNP-2 is expected to provide justification when
their design calculations
take credit for motor performance
beyond
the
knee of the motor performance
curve.
This will be
a followup
item for a future inspection.
The followup items identified in this section will be tracked
as
Followup Item 50-397/91-16-06,
except
as identified in the above
discussion.
Conclusions
The inspectors
determined that the licensee
had not yet adequately
developed
plans
and procedures
for performing calculations to verify
proper sizing of MOVs and to set their'switches.
Desi
n Basis Differential Pressure
and Flow Testin
GL 89-10 Recommendations
and Licensee
Commitments
Recommended
action "c" of the generic letter requested
licensees
to
test
MOVs within the generic letter program in-situ under their
design basis differential pressure
and flow conditions.
If testing
in-situ under those conditions is not practicable,
alternate
methods
may be used to demonstrate
the capability of the
MOV.
A two-stage
approach
was suggested
for situations
when design basis testing
in-situ is not practicable
and when
an alternate
method of
demonstrating
MOV capability cannot
be justified at this time.
With
the two-stage
approach,
a licensee
would evaluate
the capability of
the
MOV using the best data available
and then would work to obtain
applicable test data within the schedule of the generic letter.
The
licensee
committed to follow the recommendations
of GL 89-10.
However, the licensee
requested
a schedule
extension for MOVs
subjected
to the two-stage
approach for operability verification.
According to the licensee,
the schedule
extension
would be necessary
to complete the testing portion of their two-stage
approach
MOVs.
Observations
The licensee
indicated that all
MOVs in the
GL 89-10 program will
undergo static diagnostic tests.
The licensee
committed to test
MOVs under design basis differential pressure
and flow conditions,
where practicable.
The licensee
had not determined
which MOVs are
practicable to test under these worst case conditions.
e
The licensee's
program plan indicated
a possible
grouping which
would be
a deviation from the licensee's
commitment to test
MOVs,
where practicable.
If the licensee
proceeds
with the plan for
grouping,
a justification for this deviation from their commitment
to GL 89-10 needs to be considered.
The licensee
had not conducted
any differential pressure
tests in
response
to GL 89-10 at the time of the inspection.
The licensee
was behind their design basis testing schedule,
which called for
t
t
l
tl
4.5
approximately
30K of the differential pressure
tests to be completed
by the time of the inspection.
The licensee
had not developed
procedures
for differential pressure
testing.
This testing will be
important in verifying the licensee's
methodology for establishing
NOV size
and switch settings (particularly, in light of the
licensee's
use of low valve factors).
The lice'nsee
was cautioned
that if differential pressure
testing casts
doubt on the
MOV sizing
or switch settings, all
NOYs in the program would need to be
promptly addressed.
The licensee
had tested
several
marginally-sized
MOVs under zero
flow and degraded
voltage conditions but did not have quantitative
information regardinq the amount of margin available.
The licensee
was considering testing
some of these
MOVs under
maximum
differential pressure
under degraded
voltage conditions.
This will
be
a followup item for future inspection
(Followup Item
50-397/91-16-07).
Conclusions
Due to the lack of progress
in this area,
the inspectors
determined
that the licensee
had not yet adequately
developed
plans
and
~
~
rocedures for demonstrating
the capability of MOVs through design
asis differential and flow testing.
Periodic Verification of NOV Ca abilit
GL 89-10 Recommendations
and Licensee
Commitments
Recommended
action "d" of the generic letter requested
that
licensees
prepare
or revise procedures
to ensure that adequate
switch settings
are determined
and maintained throughout the life of
the plant.
Paragraph "j" of the generic letter recommended
that the
surveillance interval
be based
on the safety importance of the
as well as its maintenance
and performance history, but that the
interval not exceed
5 years or 3 refueling outages.
Further,
the
capability of the
MOV would need to be verified, if the
MOV )s
replaced,
modified, or overhauled to an extent that the existing
test results
are not representat'ive
of the
MOV.
The licensee
committed to follow the recommendations
of GL 89-10.
Observations
In its Motor Operated
Valve Program Plan,
the licensee
indicated
that it intended to conduct static testing of each
MOV every
5 years
in an effort to ensure
the continued
adequacy of MOV torque switch
settings.
The inspectors
stated that the
use of static testing
alone to verify continued capability of an
MOV to operate
under
worst case differential pressure
and flow conditions
was not
considered
adequate
because
of the uncertain relationship
between
the performance of an
MOV under static conditions
and under design
basis conditions.
The inspectors
considered this to be a followup
item.
The
NRC staff will evaluate
the licensee
s justification for
II
,l
,l:~
f
12
the use of static testing during future inspections
on
a case-by-
case basis.
The licensee
had not developed
documented criteria for conducting
post-maintenance
testing for MOVs within i.ts
GL 89-10 program.
The
licensee will be expected to provide justification for the testing
performed following each
MOV maintenance activity to verify the
capability of the
MOV to operate
under design basis conditions.
The
inspectors
considered this to be a followup item.
The
NRC staff
will evaluate
the specific justification for individual post-
maintenance
tests
during future inspections
of this activity.
The followup items i'dentified in this section will be tracked
as
Followup Item S0-397/91-16-08.
Conclusions
Due to the lack of progress'in this area,
the inspectors
determined,
that the licensee
had not yet adequately
developed
plans
and
procedures
for periodic verification of the capability of MOVs.
MOV Failures
Corrective Actions
and Trendin
GL 89-10 Recommendations
and Licensee
Commitments
Recommended
action "h" of the generic letter requested
that
licensees
analyze or justify each
MOY failure and corrective action.
The documentation
should include the results
and history of each
as-found deteriorated
condition, malfunction, test, inspection,
analysis,
repair, or alteration.
All documentation
should
be
retained
and reported in accordance
with plant requirements.
This
data should
be periodically examined
(every
2 years
or after each
refueling outage after program implementation)
as part of the
monitoring and feedback effort to establish
trends of MOY
operability.
These trends
could provide the basis for a licensee
revision of the testing frequency established
to verify periodically
adequate
MOV capability.
The generic letter indicated that
a
well-structured
and component-oriented
system is necessary
to track,
capture,
and share
equipment history data.
The licensee
committed
to follow the recommendations
of GL 89-10.
Observations
The licensee is currently'rending
MOV failures but needs
to
formally document their program.
At present,
Maintenance
Mork
Requests
(MWRs) and Problem Evaluation Reports
(PERs) are received
by the
MOV coordinator for trending.
The inspectors
emphasized
the
importance of not missing opportunities to trend
degradedlaccelerated
wear conditions
as well as failures.
The inspectors
noted that the licensee
looks for trends in MOV type
as well as type of service application
and that the licensee
compares their data with industry trends.
The inspectors
encouraged
~
l
the licensee to incorporate
these attributes
when they formally
document their program.
It was noted that last year the'icensee
identified 69
MOV failures.
According to the licensee,
this number
had decreased
during the
years at WNP-2, and this indicated
some
success
in the licensee's
root cause
analysis
and corrective actions.
The inspectors
considered
the number still to be excessive.
It appeared that the
licensee's
engineering staff needed to become
more involved in the
process
of assessing
MOY failures, corrective actions,
and trending.
Through discussions
with maintenance
personnel,
the inspectors
found
that several
instances
of degraded
spring packs
had been recently
encountered
during the refurbishment
and testing of several
Fuel
Pool Cooling (FPC)
MOVs.
This condition was identified by the
maintenance
personnel
as spring pack collapse resulting in a loss
of preload in the spring pack.
A loss of preload in the spring pack
can cause
the actuator
to torque out prematurely
under
maximum
DP
conditions before the valve has
completed its required safety
function.
The deficiency represents
a significant condition adverse
to quality in assuring
the design basis operability of the
MOV.
As a result of three instances
of the
same degradation
in six FPC
valves,
the licensee initiated replacement of all spring packs in
safety related
MOVs during refurbishment
under their GL89-10
program.
The inspector
reviewed Maintenance
Work Requests
MWR AR3151,
AR3152,
and AR314 for FPC-MQ-175,
181A, and 172 respectively.
The
inspectors
found that in each instance
the spring packs
had been
replaced
due to collapsed spring pack washers.
However, the
inspector
found that the degraded
conditions
had not been
documented
on a
PER as required by license procedure 1.3.12, "Plant Problems
Plant Problem Evaluation Request."
As a result,
no root cause
evaluation
was performed.
The generic implications
on the
operability of other valves were not addressed.
The conditions
were
not reviewed for reportability or Part 21 applicability.
This failure to follow procedures
for the identification of
significant conditions adverse to quality is an apparent violation.
(fnforcement
Item 50-397/91-16-09)
Conclusions
The inspectors
determined that the licensee
had not yet adequately
developed
plans
and procedures
for analyzing
MOV failures,
justifying corrective actions,
and trending.
14
4.7
4.8
Schedule
GL 89-10 Recommendations
and Licensee
Commitments
GL 89-10 requested
that licensees
complete. all design-basis
reviews,
analyses,
verifications, tests,
and inspections that were initiated
in order to satisfy the generic letter
recommended
actions
by June
28, 1994, or 3 refueling outages after December
28, 1989, whichever
is later.
The licensee
committed to follow the recommendations
of
However, the licensee
requested
a schedule
extension for
NOVs subjected to the two-stage
approach for operability
verification.
According to the licensee,
the schedule
extension
would be necessary
to complete the testing portion of their
two-stage
approach
NOVs.
Observations
The licensee's
equality Assurance
Organization identified a number of
areas
where the
MOV program
had fallen behind schedule.
According
to the licensee's
program description,
approximately
30X of the
design basis testing should
have
been
completed
by the time of the
inspection.
At the time of the inspection,
none of the tests
had
been performed nor had any procedures
for design basis testing
been
developed.
The inspectors
observed that the licensee's
current program schedule
places
a heavy reliance
on maximum
DP testing towards the end of the
5 year schedule to confirm the adequacy of their design setpoint
verification methodology.
In the meantime,
the design verification
program continues at rssk with low valve factors,
wh>ch have
been
found, in some cases,
to be nonconservative.
It appears
that the
licensee
has little room in their schedule for a contingency plan,
if the desiqn basis tests fail to corroborate
the design values
calculated
)n the current program.
As evidenced
by the program's
current status,
licensee
management
appears
to have underestimated
the resources
required for th>s program.
Conclusions
The inspectors
determined that the licensee
had not yet adequately
established
a schedule for the completion of the
recommended
actions
of GL 89-10.
(Followup Item 50-397/91-16-10).
Other
MOV Pro
ram Areas Addressed
4.8.1 Control of MOV Switch Settin
s
The licensee
uses
a Master Data Sheet
(NDS) under procedure
No.
1.4. 13 to control the allowable range of thrust values
and
torque switch settings.
On each Master Data Sheet,
the
licensee
provides
a minimum thrust value that must be exceeded
by the thrust readings
obtained
from the
NOVATS diagnostic
equipment during valve stroke testing.
For the
max>mum
allowable actuator output, the licensee
provides
a maximum
15
thrust value and torque switch setting
on the Master Data
Sheets.
The inspectors identified several
concerns
regarding the
licensee's
development of their Master Data Sheets
and control
of NOV switch settings.
Some of the Master Data Sheets
reviewed did not provide
complete information.
when setting
MOV switches,
the plant
technician
must ensure that neither the
maximum thrust value
nor the maximum torque switch settings
are exceeded.
The
inspectors
noted that the licensee
had not consistently
provided clear guidance to plant and contractor personnel
on
this limitation.
For example, for an
MOV with an open safety function direction,
the licensee
did not indicate the design basis differential
pressure
nor the minimum thrust requirements
on the Master Data
Sheet,
but rather simply indicated
NA (for "Not Applicable" ) on
the data sheets for those parameters.
The licensee
indicated that torque switches for an
NOV with an
open safety function direction have their open torque switch
jumpered out of the circuit.
However, the inspectors
found
that the torque switch jumpers
were not controlled under the
Master Data Sheet.
The inspectors
cautioned that the
installation of the hardwire jumper is equivalent to
establishing
a lOOX torque
sw>tch bypass setting
and appears
to warrant inclusion on the Master Data Sheet.
In the past,
the licensee
had not maintained
adequate
control of such
torque switch jumpers (e.g.,
see
Licensee
Event Reports
87-24 and 89-11).
The licensee
needs to maintain control of
its jumpering of torque switches
because
of its reliance
on
those
jumpers for the appropriate
operation of the
NOV.
In
discussions
with licensee
personnel, it appeared that the
licensee's
position on the use of jumpered torque switches
was
in response
Torque Switch Electrical
Bypass Circuit for Safeguard
Service Valve Notors."
The
NRC
staff guidance in GL 89-10 constitutes
the most recent staff
position for providing assurance
that
MOVs are capable of
reliably performing their intended functions.
The licensee
should consider the appropriateness
of the use of jumpered
torque switches in light of an integrated
approach to ensuring
the proper performance
of HOVs at WP-2.
The inspectors identified an instance
where the Master Data
Sheet for RCIC-V-63 was inconsistent with Table I in the
Program Plan regarding the open safety function of the valve.
The licensee
had identified instances
where torque switch
settings
were higher than the setting allowed by Limitorque for
particular
MOVs.
In the case of MS-Y-16, the high setting
resulted in valve damage.
The licensee
had completed
a PER,
which provided evidence of its review of plant documentation
on
i
k
~II
4
~,
16-
torque switch settings.
The
PER concluded that the extent of
this problem was limited.
The licensee
has
been performing
degraded
voltage tests
on those valves to determine
whether the
motors could deliver the
demanded
torque at the as-found
settings.
Such
a test of RHR-V-48B revealed that the motor
could not deliver the
demanded
torque under degraded
voltage
conditions.
The licensee
had not- completed their evaluation of
RHR-V-48B operability at the time of the inspection exit
meeting.
The
NRC will review the results of the licensee's
evaluations
during a future inspection.
In MNP-2 Operational
equality Assurance
Surveillance
Report
2-91-009,
the licensee
found that the plant procedure
controlling the Master Data Sheets
was not well understood
by
plant personnel
and identified other problems involvinq the
Master Data Sheets.
The licensee
had
an internal
commitment to
resolve the issues identified in the equality Assurance
Surveillance
Report by June 10, 1991.
The
NRC staff will
review the licensee's
response
to that equality Assurance
Surveillance during a future inspection.
In light of the above concerns
regardinq the licensee's
Master
Data Sheets,
the inspectors
discussed
with the licensee
the
importance of adequate
and justifiable control of MOV output
and switch settings.
In that the licensee relies
on jumpered
torque switches for some
MOVs, the licensee
needs
to provide
positive control over the presence
and functionality of those
jumpers.
The inspectors
requested
that the licensee
review its
control of MOV output and switch settings
to ensure that its
controls are clear to plant and contractor personnel.
The
licensee
committed to review this area
and to make
improvements
as necessary.
Concerns identified in this section will be addressed
in a
future inspection
and tracked
as Followup Item 50-397/91-16-11.
4.8.2 ~Trainin
The inspectors
discussed
the licensee's
traininq activities in
this area with licensee
personnel,
reviewed training outlines
and records,
and toured the traininq facility.
The inspectors
did not identify any problems in th)s area.
The licensee
allowed contractor personnel
to receive training
on site or
be certified as adequately trained
by the applicable
contractor.
Operational
Assurance
Surveillance
Report 2-90-002
reported that
MOVATS had failed to adequately train its
technicians
and
gC personnel
with respect to electrical
cable
splicing for MOVs.
In discussing this failure with the
inspectors,
the licensee
demonstrated
that the deficiency in .
the training of MOVATS personnel
had been identified by
licensee quality assurance
personnel
and that prompt attention
f
0
I<,
l
17
had been qiven to ensuring that
MOVATS personnel
receive onsite
training sn the deficient areas.
4.8.3
~Di
ti
The licensee
uses
MOVATS diagnostic
equipment to obtain values
for the thrust delivered by the motor operator in opening
and
closing the valve.
The licensee relies
on the accuracy
values
~
~
~
rovided by MOVATS for this equipment but has not verified the
OVATS published accuracy.
It is also
known that
MOVATS
accuracy differs between the opening
and closing direction of
the
MOV.
The licensee
does not appear to consider this
information.
MOVATS Engineering
Ressort 5.0
(REV. 0, January
1991),
"Equipment Accuracy Summary, 'rovides
guidance for the
consideration of rate of loading effects that might reduce the
available thrust delivered
by the motor operator
under high
differential pressure
conditions.
The inspectors
noted that
the licensee
had not responded
to this report.
The licensee
committed to evaluate
the current industry testing
of MOVATS equipment
and to incorporate the results of that
testing,
as necessary.
The inspectors
also
recommended
that the
licensee
evaluate
rate of loading effects
and va]ve stem
directional effects to ensure
adequate
margin exists in the
capability of the motor operator to open
and close valves within
the
GL 89-10 program.
This will be
a followup item for future
inspections.
(Followup Item 50-397/91-16-12).
4.8.4 Modifications
Modification packages
were reviewed by the inspectors.
The
packages
appeared
thorough
and complete.
The detailed
checklists
provided with the packages
were helpful and appeared
to be a useful tool towards establ>shing
thorough
considerations
of the critical issues
affected
bv the
modifications.
No problems
were identified in this area.
4.8.5 Maintenance
The inspectors
observed portions of overhaul
and testing
activities.
In general,
the overhaul activities were found to
be well controlled.
In discussions
with the maintenance
personnel,
the inspectors
found all to be knowledgeable
and
familiar with MOV problem areas.
Further,
the inspector
observed detailed procedures
in use during the maintenance
activities.
The inspectors
observed
several
deficiencies
which were brought
to the attention of the maintenance
supervisor for resolution.
a.
a wiring lug interfering with a torque switch arm
b.
a missing arc guard
on a torque switch
c.
failure to remove
a storage
desiccant
pack from a
K
f,I
i,
,l
I
d.
e.
h.
MOV switch compartment
failure to remove spring pack calibration tags after
replacement
with a different spring pack
failure to replace limiter plates
when
a lower
maximum torque switch setti.ng
was specified
an actuator oriented vertically with the spring pack
on the bottom
T-drains installed at the high point of a motor
(drain not required for environmental qualification)
motor nameplate
data that disagreed
with the
The inspectors
found that deficiencies
encountered
during
overhaul activities were not consistently
documented
as
required
by plant procedures.
Informal tracking of the
frequency of such problems
was apparently
used to some extent
in lieu of documentation
on each work package.
The inspectors
found this to be another
example of weakness
in documenting
~
deficiencies.
This subject
was discussed
in detail in section
4. 6 of this report.
4.8.6 Industr
Ex erience
The underlying premise of GL 89-10 is that industry experience
and research
has
shown that the
use of industry standard
equations to predict
MOV performance
may not be conservative.
The approach outlined in GL 89-10 is: first
to verify the
existence of sufficient margin to reestablish
adequate
assurance
of MOV operability in light of recent industry
insights;
and,
second,
to the extent practicable,
to assure
that safety related
MOVs are tested at maximum design
conditions in order to demonstrate
operability.
MNP-2 continues to use the old industry standard
equations
and
valve factors
and does not account for motor performance at
elevated
temperature,
fluid flow rate, fluid temperature,
and
seismic/dynamic effects.
This places
heavy reliance
on the
design basis testing portion of the program.
The licensee
was
cautioned that failure of a
MQV to perform its safety function
under design basis test conditions would subject not only a
"failed" MOV to an evaluation for operability, but also all
other
MOYs which use the
same design methodology.
MNP-2 is the only Region
V operating nuclear power plant which
does
not participate in the Region
V MOV users
group.
Some of
the deficiencies
observed at MNP-2 had already
been identified
at other Region
V nuclear plants.
The licensee
program for the receipt
and distribution of
Limitorque supplied information and the incorporation of
industry experience
was reviewed.
The licensee
had established
an active interface with vendors to solicit technical
update
information.
Designated
licensee
recipients
had been
identified to be included
on distribution mailing lists.
Plant
personnel
were periodically reminded of plant requirements
I
19
regarding the receipt
and handling of unsolicited vendor
technical
information.
All Limitorque Maintenance'Updates
had been received
by the
plant and had been included within their vendor information
program.
The inspectors
emphasized
the necessity for appropriate
review
of applicable
vendor information on a timely basis to assure
that the best available
data is disseminated
and used within
the program.
4.8.7 ~li
T ti
WNP-2 stroke time acceptance
criteria did not consider motor
speed
changes
under load or degraded
voltage conditions.
In
the case of DC MOVs this will significantly affect motor speed
and,
hence,
The inspectors
recommended that the
licensee
review their acceptance
criteria for DC MOVs to ensure
that they are appropriate
under design basis conditions.
motor speed is both load and voltage dependent.
If the design
basis
DC MOV safety function is time critical and credits
operations of the
MOV under
maximum
DP and degraded
voltage
conditions,
the acceptance
criteria for testing should either
demonstrate
acceptable
time under those design basis conditions
or account for the anticipated effect by including an appropriate
margin within the test acceptance
criteria.
The inspectors
noted that the static zero pressure
for some
MOVs were already close to
FSAR acceptable
stroke
times.
This will be
a followup item for future inspections.
(Fo1 1 owup Item 50-397/91-16-13)
4.8.8
Im lementation of Su
lement
3 Recommendations
The licensee
provided responses
to Supplement
3 of GL 89-10 in
letters
on December 12, 1990,
and March 12, 1991.
In the March
12 response,
the licensee
indicated that
2 MOVs in the
system
(RWCU-V-1 and 4) and
2 MOVs in the
RCIC system
(RCIC-Y-8
and V-63) were within the scope of Supplement
3 to GL 89-10 at
WNP-2.
The licensee
stated that the sizing and setpoint
calculations for the
RWCU MOVs had been re-performed
using
a
valve factor consistent with information obtained
from the
NRC-sponsored
MOY tests.
The licensee
stated that the
MOVs would be diagnostically tested
under static conditions
during the Spring 1991 outage.
The licensee
stated that the
calculations for the
RCIC MOVs continued to use the typical
industry valve factor for flexwedge gate valves,
but that the
torque switches
were bypassed for 98X of the closing stroke.
The licensee
stated that due to its similarity with one of the
valves in the
NRC sponsored
tests,
RCIC V-63 had been evaluated
in light of the Supplement
3 information.
The evaluation
verified RCIC V-63 to have sufficient thrust capability.
20
The inspectors
reviewed the available
MOV calculations
and
raised several
concerns
to the licensee.
First, because
Manual
Calculation NE-02-87-29 (Rev.O) for RCIC-V-63 had not been
updated, it was not appare'nt that RCIC-V-63 had been evaluated
for thrust capability.
Second,
during the course of the
inspectors'uestions
on RCIC-V-8, the licensee identified an
error in Manual Calculation NE-02-90-17
(Rev. 1) for RCIC-V-8
regarding failure to consider voltage loss
between
the motor
control center
(MCC) and the motor operator.
(Note that this
report already identifies Deviation Item 50-397/91-16-04 for
qualifying the motor for 87K degraded
voltage,
the voltage at
the
MCC, rather than
SOX degraded
voltage at the motor operator
as committed in the licensee's
FSAR.)
Third, the licensee
had
not considered
rate of loading effects in their
calculations.
The licensee
committed to re-evaluate
the
calculations for the 4 MOVs within the scope of Supplement
3 to
GL 89-10 and to resubmit
a response
to the generic letter
supplement, if necessary.
The inspectors
also reminded the
licensee of the obligation to evaluate
the operability of those
MOVs upon concluding their calculations.
This wH 1 be
a
followup item for future inspections.
(Followup Item
50-397/91"16-14)
5.
Summar
of Overall
Pro
ram Administration
Based
upon the status of the licensee's
GL 89-10 program
and weaknesses
observed in the licensee's
technical
approach to reestablish
adequate
confidence of MOV operability, the following areas
are deserving of the
licensee's
prompt attention.
The current
MOV program does not adequately utilize industry
knowledge
and exper)ence.
2)
3)
The level of Supply System
management
attention
and commitment
to the
MOV program to assure
technical
work quality and test
program progress
needs
improvement.
The gA organization
needs to improve in their level of
oversight of program activities to assure that deficient
conditions are well documented,
that commitments to the
NRC are
followed, and that any deficiencies
are brought promptly to the
attention of senior
management.
A brief discussion of examples of observed deficiencies
in these
areas
follows:
Need for im roved utilization of industr
knowled
e and ex erience
e un er ylng premise
o
-
)s
a
)n us ry, experience
and research
has
shown that the industry standard
equations
to
predict
MOV performance
may not be conservative.
If
, tII
21
WNP-2 continues to use the old industry standard
equations
and
valve factors
and does not account for motor performance at
elevated
temperature,
fluid flow rate, fluid temperature,
and
seismic/dynamic effects.
This places
heavy reliance
on the
design basis testing portion of the program.
The inspectors
cautioned the licensee that failure of a
MOV to perform its
safety function under design basis test conditions would
subject not only a "failed
MOV to an evaluation for
operability, but also all other
MOVs which use the
same
design
methodology.
WNP-2 is the only Region V operating nuclear
power plant which
does not participate in the Region
V MOV users
group.
Some of
the deficiencies
observed at WNP-2 had already
been identified
at other Region
V nuclear plants.-
Need for im roved mana
ement attention
and commitment to
e
ro ram
ome
ime ago
e
e
icensee
s origina
V Coordinator
was taken ill.
Approximately 6 months
lapsed during his recuperation
in which little was accomplished
towards completing the licensee's
GL 89-10 commitments.
It
appeared that management
and oversight of the
MOY program at
WNP-2 had languished
in the interim.
WNP-2's allocation of resources
for the program appears
sparse.
At the time of the inspection,
only one engineer,
the
new
Coordinator,
was fully dedicated to the program,
and most of
his efforts had been
focused
on problems
encountered
during the
current outage.
According to the licensee's
program description,
approximately
30X of the
MOV design basis testing should
have
been
completed
by the time of the inspection.
At the time of the
inspection,
none of these tests
had been per'formed.
The
situation was
compounded
by the fact that test procedures
had
not been developed.
Need for im roved
A oversi ht of
ro ram activities
and
e icienc
ocumen
a ion
po
c ec
s
y
e
organization
a
i en i ie
signi scant findings which indicated program
weaknesses
symptomatic of an inadequate
program.
Two years of
this five year program
had passed.
Yet a comprehensive
audit
of the program
had not been performed,
nor was it clear that
identified problems
had been brought fully to the attention of
senior management.
The following were examples of significant findings by the gA
organization that should
have alerted
gA to inadequacies
in the
MOV program:
gA Surveillance
Report
No. 2-91-009 identified failures to
meet schedules
and
INPO commitments for MOV testing
and
refurbishment.
The report attributed
some of these
failures to lack of manpower.
22
The technical
assessment
group identified errors in
several
Master Data Sheets
(MDS} and discrepancies
in the
MDS procedures.
The
MDS are
key to contro11ing
settings
which affect
MOV performance
and ultimately
operab> lity.
The following were deficiencies that could have
been identified
had
a comprehensive
audit of the
MOV program been performed.
As mentioned in the text of this report, the inspectors
identified several
apparent
deviations
1n the licensee's
GL 89-10 commitments to the
NRC.
A number of problems
had been inadequately
documented
and
evaluated.
A number of MOV actuator deficiencies
had been
dealt with for a long time on a maintenance
level.
Significant spring pack relaxation
was observed in three
safety related
MOV actuators.
Yet contrary to WNP-2
procedures,
observed deficiencies
were not properly
documented
by cognizant engineering
personnel.
The licensee's
design verification procedures
were in need
of improvement.
6.
~Eit
M ti
The inspectors
met with the licensee
management
representatives,
denoted
in paragraph
1,
on June 7, 1991.
The scope of the inspection
and the
inspectors'indings
were discussed.
The inspectors identified that
additional information would be reviewed in order to complete the
inspection.
Review of the additional information necessary
to complete
the inspection
was concluded
on June
21, 1991.