ML17251A129
| ML17251A129 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 06/08/1988 |
| From: | Eapen P, Prividy L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17251A128 | List: |
| References | |
| 50-244-88-10, NUDOCS 8806220149 | |
| Download: ML17251A129 (32) | |
See also: IR 05000244/1988010
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Repor t No.
50-244/88-10
Docket No.
50-244
License
No.
Licensee:
Rochester
Gas
and Electric Cor oration
49 East
Avenue
Rochester
14649
Facility Name:
R.
E. Ginna
Inspection At:- Ontario
Inspection
Conducted:
Ma
16 - 20
1988
I
Inspectors:
t .. f.~>~
L. J. Prividy,
R
ctor Engineer,
NRR Personnel:
E. J. Sullivan, Chief, Inservice Testing
Assessment
Section,
Y.
C. Li, Mechanical
Engineer,,
~/lklux
date
Approved by:
P.
K. Eapen,
Chief
Special
Test Programs
date
Section
Ins ection Summar:
Announced
Ins ection
Ma
16 - 20
1988
Re ort No.
~/
Areas Ins ected:
Inspection of licensee's
implementation of Inservice Testing
(IST
activities to assess
the adequacy
and to verify adherence
to regulatory
requirements
and licensee
commitments.
The inspection
included organization
review, discussions
with cognizant personnel,
review of documentation,
witnessing of pump
and valve tests
and observation
of selected
component
maintenance activities.
Results:
Section
3. 1 indicates
an apparent violation of 10 CFR 50.55a(g)
which
requires, adherence
to ASME Code,
Section
XI for IST of pumps
and valves.
Four'unresolved
items are provided in Sections 4.0, 5.0 and 6.0 concerning
comments
on the
IST program.
The inspection findings indicate
an apparent
8806220i49
880610
ADOCK 05000244
0
DETAILS
1.0
Persons
Contacted
Rochester
Gas
and Electric Cor oration
~C. Anderson,
QA Manager
"J. Bodine, Nuclear Assurance
Manager
- D. Gent,
Results
and Test Supervisor
"G. Joss,
Results
and Test
Foreman
- T. Marlow, Maintenance
Manager
- T. Meyer, Superintendent,
Ginna Support Services
- R. Smith, Chief Engineer
- S. Spector,
Superintendent,
Ginna Station
J. Widay, Technical
Manager
P. Wilkens, Nuclear Engineering
Manager
- G. Wrobel, Senior Engineer,
Nuclear Engineering
- N. Perry,
Resident
Inspector
Denotes
those
present at the exit interview on May 20,
1988.
The inspector
also contacted
other licensee
employees
during the course
of the inspection.
2.0
Administration of Inservice Testin
Pro
ram
The licensee
is currently implementing its second
10-year interval
program for safety related
pumps
and valves for the period January
1,
1981.'hrough
December
31,
1989.
This program is defined
and controlled by the
licensee
by including i't as Appendix
C to the Ginna Station Quality
Assurance
(QA) Manual.
Revision 8, dated October
1,
1987 is the current
revision to the
IST program.
The original version (Revision
0 of Appendix
C to the
QA Manual) of the
IST Program
was submitted to the
NRC on
September
4,
1980,
in compliance with the requirements
of 10 CFR 50.55a.
It committed to ASME Code,
Section
XI
,
1977 Edition through the
Summer
1978 Addenda.
An
NRC safety evaluation report which endorsed
the valve
program
was issued
on May 26,
1981.
Appendix
C of the
QA Manual provides the necessary
testing
inform'ation
that is requi red to implement
ASME Code,
Section
XI requirements
for the
listed
pumps
and valves.
The testing information for the valves is
provided in the form of valve tables.
These tables refer to many notes
which identify exceptions
to the testing
requirements
of Article IWV of
ASME Code,
Section XI.
It is the
immediate responsibility of the Ginna Station Results
and Test
(R&T) supervisor
and the
R&T foreman to implement the IST program
and
develop test procedures
which will define the specific test for each
pump
and valve in the program.
Overall responsibility rests with the Technical
Manager to whom the
R&T Supervisor reports.
Most of the required testing
is accomplished
by the performance of Periodic Test (PTs) under the control
of the
R&T foreman
and his test personnel.
The inspectors
performed detailed reviews of various completed
PTs (see
Attachment A) for procedure
content
and to determi'ne
the adequacy
of the
actual
pump and valve test data
taken during prior tests.
This
information was reviewed from an overall
IST programmatic
standpoint
and
more specifically as it pertained
to the
pump and valve portions of the
program.
Also the inspectors
witnessed
the performance of five PTs.
2.1
Findin
s and Conclusions
The
R&T personnel
perform the detailed testing operations
(e.g.
valve operation
and data recording) locally at the equipment while
in constant
communication with the licensed operators
in the Control
Room.
The
R&T foreman is usually in the Control
Room coordinating
the activities of his test personnel
and Control
Room personnel.
The inspectors
observed this overall test coordination
on May 17,
1988, during the performance of the testing of the Standby Auxiliary
(SAFW) pumps
and the Auxiliary Feedwater
(AFW) pumps.
Detailed inspector observations
concerning this test witnessing
are
included below in Section 3.0 and 4.0.
The inspector discussed
with R&T personnel
the licensee'
system for
scheduling
various
IST tests to meet the frequency requirements
of
ASME Code,
Section XI.
Pump testing is general.ly
done
on
a monthly
basis while the plant is operating
.
During these
pump tests
many
associated
valves in the
system are also tested.
Other valve testing
is performed quarterly, cold shutdown or refueling bases,
as
applicable.
The monthly testing is manually tracked
on
a status
board
which occupies
a complete wall in the
R&T office.
Color coding is
utilized to highlight such significant testing conditions
as
more
frequent testing of certain valves that might be required if increased
valve stroke times occurred that are abnormal.
Special
tracking of
valves that can only be stroked during cold shutdown is kept by the
R&T supervisor to meet the intent of ASME Code,
Section XI.
The
testing for these
cold shutdown valves is provided in several
separate'Ts.
The inspector
noted that the licensee
practice of monthly pump
testing which also includes
many valve tests is
a strength
since this
practice
goes well beyond the quarterly frequency
requirement
in ASME
Code,
Section XI.
Discussions with RET personnel
indicated that test results
are
adequately
reviewed.
Both the
R&T foreman
and supervisor
review the
test results.
Any system or component abnormalities identified
during the tests
are
immediately brought to'he attention of the
Control
Room licensed operators.
Resolution of such abnormalities
would be notated
in the "comments" section of the procedure.
After
final review of the test results,
the completed
procedure is
forwarded to Central
Records for permanent
record keeping.
During the preparation for this inspection,
the inspectors identified
several
technical
concerns,
such as,
the possible
lack of fu11-stroke
exercising of certain
and leak testing of pressure
boundary isolation valves.
These
concerns
were provided to. the
licensee prior to this announced
inspection.
The inspector also
requested
that cognizant engineering
personnel
be
made available to
discuss
and resolve
these
concerns.
'As discussed
in Section 3.0
below,
several
of the possible
check valve concerns
were confirmed by
the on-site inspection.
Cognizant corporate
engineering
personnel
were not generally available to discuss
these
concerns.
These
check
valve concerns
led the inspection
team to the conclusion of a perceived
licensee
weakness
in engineering
support
since correct check valve
testing requirements
were not adequately
defined to meet the require-
ments of ASME Code,
Section XI.
Because
of the deficiencies identified
in check valve testing,
the inspector's
also concluded that the
licensee
had not responded
adequately
to the information provided in
'NPO
and
NRC Information Notice 86-01 in this regard.
1
The inspectors
determined that,
from an
IST programmatic
standpoint,
the licensee
was generally performing the testing within the required
frequencies.
Also, the required
IST data were being obtained
and
reviewed.
However, specific findings indicate that management
involve-
ment is warranted to ensure
adequate
engineering
support for proper
definition of check valve testing consistent with the requirements
of
ASME Code,
Section XI.
3.0
Valve Testin
Pro
ram
The valve testing
requirements
of the
IST program are
implemented
through
periodic tests
(PTs), which are well written and clear to follow from an
IST standpoint.
Acceptance criteria are clearly defined in the procedures.
The inspector
reviewed the completed
procedures
listed in Attachment
A and
determined
in general that:
acceptance
criteria were met;
proper review and approval's
were obtained;
data evaluations
were performed;
position indication devices'ere
checked;
fail-safe operation of valve actuators
was properly checked
where applicable;
and
disposition of failures
was adequate
~
Also, the inspection
sampled
several prior valve maintenance activities to
determine
the licensee's
practice concerning
post maintenance
testing.
The inspector determined that satisfactory
post maintenance
testing
consistent with the requirements
of ASME Code,
Section
XI had
been
accomplished
for:
Letdown high pressure relief valve - RV-203.
(MSIV) 3516 and 3517.
The inspectors
witnessed
various valve testing that was accomplished
in
conjunction with the
AFW and
SAFW pump testing per PT-16
and PT-36, re-
spectively.
Specific areas of concern
were identified especially regarding
check valve testing.
requires
an
IST Program for safety
related
pumps
and valves to meet the requirements
of the
ASME Code,
Section
XI.
However, certain valves
were omitted from the
IST program
and also
certain
check valves were inadequately
tested.
Both of these
matters
are
apparent violations of NRC requirements
(50-244/88-10-01)
and they are
discussed
in further detail below.
3.1
~Findin
n
A.
Multi le
Exam les of Inade uate Testin
of Check Valves
Section
XI of the
ASME Code requires full-stroke tests for check
valves.
Full-stroke testing
may be verified using flow.
The
NRC staff position is that verification of the
maximum flow rate
through the valve as defined in the plant's safety analyses
would
be
an adequate
demonstration
of the full-stroke requirement.
Any lesser
flow rate is considered partial-stroke exercising
unless it can
be
shown (by some
means
such
as
measurement
of the
differential pressure
across
the valve), tgat the check valve's
disc position at the lower flow rate would permit maximum
required flow through the valve.
If the licensee
cannot
meet
the requirements
of the
ASME Code,
10 CFR 50.55a .requires
the
licensee
to submit appropriate relief requests
to the
NRC.
The
inspector
noted the following examples
where the licens'ee's
program .did not conform to the full-stroke requirements
of ASME
Code,
Section
XI or the licensee
did not'submit appropriate
relief requests
to the
NRC.
( 1)
Check Valve 9627A
8 B:
These 4-inch valves are located at
the service water suction inlet for the
SAFW pumps
1C and
1D and and they are
an integral part of the seismic Category
I source of water for these
pumps.
The inspector witnessed
testing of these
valves per PT-36.
The check valve test
consists
of supplying service water pressure
upstream of
the check valve with all valves shut downstream of the
check valve except
a 3/4-inch vent valve (9630A/B). 'low
through this vent valve and attached plastic tubing was
estimated
to be between
2-3
gpm which is significantly less
than the required
200
gpm and essentially constitutes
a
part-stroke
exercise
of the check valve.
While Article
IWV-3522 of ASME Code,
Section
XI requires part-stroke
exercising of check valves if full stroke exercising is
not practical
during normal plant operation, it requires
full-stroke exercising during cold shutdowns.
However, the
inspector determined that
no other exercising tests
were
being conducted for these
and they had not
been disassembled
since their original installation around
1981.
This is especially
a concern for the service water
application
as the water quality is conducive to silt
buildup in the valve.
The inspector identified this concern
to the licensee's
representatives.
The licensee
provided
a
quick response
to the inspector's
concern
by disassembly,
inspection,
cleaning
and reassembly
of both check valves
on
May 19 and 20,
1988.
The inspector witnessed
the work
performed
on check valve 9627A.
The valve internals
were
in very good condition, considering
the application, with
only minor amounts of 'rust evident.
The valve disc/seating
surfaces
were in good condition.
Also, there
was strong
evidence that the check valve disc
had
been stroking fully
due to peen
marks noted at the valve disc/disc
stop mating
surface.
The inspector
was informed by maintenance
person-
nel that similar results
were found for check valve 9627B.
As
a result of these
inspections
the immediate question of
check val,ve operabiliiy was resolved.
The licensee
indicated
that long range corrective action
was being pursued
which
may entail
annual
disassembly
and inspection of the check
valve internals.
The
IST program indicates that
SAFP
SW valves
9627 A/B are
exercised quarterly.
Per
PT-36 these
valves are only
partial-stroke
exercised
using
a 3/4" test line.
The
Code,
Section XI, requires full stroke exercising 'quarterly
at power or during cold shutdown.
The licensee
has not
submitted
an appropriate relief request.
(2)
(3)
Check Valves 862AEB:
These 6-inch valves are located at
the discharge
of each containment
spray
(CS)
pump.
Review
of the
CS system
procedure
(PT-3) indicated that the flow
rate through check valve 862A or
B in conjunction with its
pump test
was
38
gpm which is significantly less
than the
minimum design flow of 1200
gpm as stated
in the
FSAR.
The licensee
indicated that
no other tests
were being
conducted for these
However, the licensee
noted that these
valves contained
an external
position
indicator for the check valve disc which could be
used to
demonstrate
full-stroke exercising.
Utilization of this
feature
had not been
included in PT-3.
On May 20,
1988,
the licensee
adequately
demonstrated
to the inspectors
full-stroke exercising of these
check valves using this
external
position indicator.
The licensee
indicated that
the long range corrective action would consist of upgrading
PT-3 to include this testing.
RHR Dischar
710A/B and 853A/B
and
Suction
854
from the
RMST:
The inspector
reviewed procedure
PT-2.2
used for the monthly testing of
the
RHR system
pumps
and valves.
This procedure
requires
that
a flow'rate of 200
gpm be established.
The inspector
noted that this flow rate only accomplishes
partial-stroke
exercising of check valves
710A and B, 853A and
B, and 854
since the
RHR pump design flow rate specified in Table
5.4-6 of the
FSAR is 1560
gpm.
The licensee
indicated
that these
do experience
design
flow rates
during refueling operations
when the refueling cavity is
filled.
However, current procedures
do not take credit
for such operations
as demonstrating full stroking of
these
The licensee
indicated that this
issue required further evaluation.
The IST Program indicates that
RHR valve 710 A/B, 853 A/B
and 854 are exercised quarterly.
Per PT-2.2 these
valves
are only partial-stroke
exercised
monthly.
Various other.
procedures
result in partial-stroking of these
valves at
other frequencies.
The
ASME Code,
Section XI, requires
full-stroke exercising quarterly.
If these
valves cannot
be ful-1-stroke exercised
quarterly at power or during cold
shutdown,
10 CFR 50.55a requires that relief from the
Code
requirements
be included in the IST program.
The licensee
has not submitted
a relief request to the
NRC.
(4)
(6)
(7)
SI Accumulator Discharge
Check Valves 842A/B and 867A/B
The inspector
reviewed procedures
PT-2. 10. 1 and PT-2. 10.7
which describe
the exercising of these
PT-2 '0. 1 requires that
a flow rate of 300
gpm be
established
during
a refueling outage
to verify the
opening of check valves
867A and
B.
PT-2
~ 10.7 requires
that the opening of. check valves
842A and
B be verified
using
a 3/4-inch
RWST test linc'll of these
check
valves must
be capable
of discharging fluid from the
within the time specified in the safety
analysis
which is considerably
higher than the flow rate
established
in the above procedures.
However,
the flow
rates
obtained during both procedures
only accomplish
partial-stroke
exerci sing for the respective
The licensee
indicated that since they have requested
relief from full stroke exercising, this item will not be
addressed
until the relief request is dispositioned
as
part of the
IST program review.
The
IST program indicates that SI pumps discharge
check
valves
870 A/B and 889 A/B are exercised
quarterly.
Per
PT-2. 1 these
valves are only partial-stroke
exercised
using
a 3/4" test line.
The
ASME Code,
Section
XI requires
full-stroke exercising quarterly at power or during cold
shutdown.
The licensee
has not submitted
an appropriate
relief request
to the
NRC.
The
IST program indicates that High Head Safety, Injection
877 A/B and 878 F/H are leak rate tested
every
forty months.
Per discussion with the plant personnel
and
review of the associated
PAID, the inspectors
learned that
valves
877 A/878
F and 877B/878
H are being leak rate tested
in series.
It was noted that there is no test connection
between
the two check valves in series
which would make
individual leak rate testing possible.
The
ASME Code,
Section XI, requires
check valves that perform
a pressure
isolation function to be leak rate tested individually at
least
once every two years.
The licensee
has not submitted
an appropriate relief request to the
NRC.
The
IST program indicates that Service Water
Pump Discharge
valves
4601,
4602,
4603
and
4604 are exercised quarterly.
Per discussion with the plant personnel
and review of the
associated
P8 ID; it was noted that there is
no flow instru-
ment installed at the
pump discharge
of, the service water
pumps.
PT-2.7 requires that
a flow rate of 1100
gpm be
established
through the associated
containment recircula-
tion fan unit during the
pump testing.
Measuring this flow
10
rate does not verify full-stroke exercising of these
check
valves.
The
ASME Code,
Section XI, paragraph
IWV-3522
requires that these
valves
be full-stroke exercised
quarter-
ly which the licensee
in this case
does not verify.
The
licensee
has not submitted
an appropriate relief request
to
the
NRC.
B.
Valves Not in IST Pro
ram
Check Valves 3992
and 3993
'The inspector
observed
from a review of the
IST program
that the main feedwater
3992 and
3993 were not
included in the
IST program.
However,
these
two check
valves
have
a safety related function to close to prevent
diversion of auxiliary feedwater
back through the main
system.
Reverse
flow testing is required to
demonstrate
the ability of the valves to close
by ASNE
Section XI, IWV-3522.
The inspector
noted that such valves
need to be evaluated
to assure
that the safety related
systems will function,
when called upon.
In response
to this concern,
the licensee
noted that recent
maintenance
(2/22/87 for 3992 and 3/10/86 for 3993)
had
been
performed
on both valves with only minor internal
repairs required.
The licensee
indicated that the long
term approach
to satisfying the
IST requirements
may be to
perform periodic disassembly
and inspection of these
valves.
(2)
3504B and
350SB
These
are 6-inch check valves located
downstream of steam
admission
MO valves
3504A and 3505A which direct steam
from
each
upstream of each
NSIV to the turbine
driven
AFW pump.
Downstream of the check valves the piping
connects
to
a
common line and then to the
AFW pump turbine.
The inspector
noted that neither check valve was included
in the
IST program.
The licensee
indicated that this was
an inadvertent error and would be corrected.
During the performance of the turbine driven
AFW pump
testing the inspector
noted several
inadequacies
with PT-3
regarding
the testing for check valves
3504B and
3505B as
follows: (I) neither
valve was tested for reverse
flow
seating capability (i.e., in the check position)
and (2)
the valves were not individually tested for forward flow.
Since the check valves
have external
counterweight
arms
which are attached
to the check valve disc,
the licensee
took immediate
steps
to individually assess
valve
operability by using thi s external
counterweight
arm.
" Check
valve
3505B operated freely.
However,
check valve 3504B
was binding in that the disc would remain in the position
to which it was forced when operating
the counterweight
arm.
The counterweight
arm apparently
was not functioning
as designed
to keep the check valve disc in the closed
position during its normal, non-flow condition.
Valve
3504B was declared
on May 18,
1988,
and mainte-
nance work was initiated to replace
the packing which
exists in the packing gland around the counterweight
actuator shaft.
It was postulated
that this packing
was
causing
the check valve binding problem.
The packing
was
removed
on May 19,
1988, but check valve 3504B still evi'-
denced binding and did not fully operate.
At the
end of
the inspection
3504B was still inoperable
and the licensee
was preparing to do further maintenance
on the valve.
The
inspector
noted that uncertain
check valve operation
in the
check position presented
a potentially significant safety
issue.
If the turbine driven
AFW pump is assumed
to be
operating
in conjunction with a main
steam line break
accident
and either check valve fails to seat in the check
position,
the intact steam generator
could feed the break
at the faulted
Although this matter
was
discussed
with the licensee,
no formal response
was received
which evaluated
the safety significance of this item relative
to the accident
analyses.
Concerning the issue of not individually testing the check
valves for forward flow, the inspector
noted that PT-16 was
performed with steam flow supplied simultaneously
from both
to the
AFW pump turbine.
Periodic testing
in this manner
does
not assure
detection of a failure in,
one check valve when the other is functional.
The licensee
indicated that PT-16 would be upgraded
to individually test
these
check valves for forward flow and reverse. flow.
3.2
Other Observations
Concernin
Valve Testin
Discussions
with RKT personnel
indicate that the licensee
practice
concerning
the
maximum allowable stroke times for power operated
valves
was reasonable
and conservative.
The method basically
consists
of establishing
an average
stroke time based
on
3 valve
strokes.
The average
stroke time is increased
by a factor of 1.25
for valves with a stroke time greater
than
10 seconds
and 1.5 for
valves with a stroke time less
than
10 seconds
to obtain
maximum
allowable stroke times.
12
The review of several
procedures
indicated that the licensee
did
perform full-'stroke exercising of some check valves.
Procedure
PT-2.8 for the component cooling water system requires that check
valves
723A and
B be exercised
by establishing
a flow rate of 2500
gpm which is an acceptable
full-stroke exercising.
Similarly
procedures
PT-16
and 36 demonstrate
full-stroke exercising for the
Condensate
Storage
Tank suction
and the
pump discharge
by establishing
a flow rate of 200
gpm and 400
gpm for
the motor driven
and turbine driven pumps,
respectively.
4.0
Pum
Testin
Pro
ram
Similar to the valve testing
program,
implementation of the
pump testing
requirements
of the
IST program is achieved
through the performance of PTs
which are well written and clear to follow from an
IST standpoint.
Acceptance criteria are clearly defined
and are basically contained
on" an
individual inservice test data
sheet for each
pump at the
end of the
procedure.
In addition to reviewing many
PTs with the associated
data
which had already
been
performed,
the inspectors
witnessed
S pump tests
three
AFM pump tests
per PT-16
and two
SAFW pump tests
per PT-36.
The inspector
reviewed the completed
procedures
listed in Attachment
A and determined
in general
that:
acceptance
criteria were established;
proper review and approvals
were obtained;
data evaluation
were performed;
instrumentation
was calibrated;
and,
dispositions of failures were adequate.
Also, the inspector
reviewed the post maintenance
testing
performed
on the "A" Safety Injection (SI)
pump subsequent
to the
r epai rs
(pump disassembly
to install
new mechanical
seals)
completed
on Narch
6,
1988.
The SI
pump test per
PT 2. 1 was performed
and it
reconfirmed that the prior pump acceptance
criteria were still valid.
e
The inspector
had several
observations
as
a result of the
pump test
witnessing
as detailed
below.
4.1
Findin<is
Good coordination
between
the test personnel
and Control
Room, licensed
operators
was
a strength.
Constant
and close
phone
communication
was
maintained
throughout
each test.
It was evident that the test
personnel
were knowledgeable
and well experienced
as evidenced
by the
deliberate
and careful controlled warmup procedure for the turbine
driven
AFW pump test.
13
Each of the
5 pump tests
observed
was conducted
such that full flow
(typically 200
gpm to each
testing resulted with
pump run time of approximately
15 minutes.
This type of testing is
considered
to be
a strength
from a
pump performance
and
standpoint.
The inspectors
observed vibration measurements
taken during the
pump testing
on May 17,
1988.
Measurements
were
taken in the horizontal
and vertical directions
on both the inboard
and outboard bearings.
This practice
exceeds
the
Code requirement of
taking readings
on only one bearing
and in the vertical or horizontal
direction with highest baseline vibration amplitude.
This approach
represents
good engineering
practice
and would likely,reveal
pump
degradation
sooner
than
by following Code requirements.
The inspector
reviewed several
pump record
sheets
incorporated into
the procedures
for the testing of pumps
and valves in the
IST program.
The acceptable
range
on these
sheets
permits simultaneous
plus or
minus deviation from the reference
values for both pressure
and flow.
The
ASME Code Section XI, paragraph
IWP-3100, requires that the
system resistance
be varied until either the measured
pressure
or
flow rate equals
the reference
value
and that the other parameter
be
measured.
However,
based
on discussions
with test personnel
and test
witnessing,
the inspectors
determined that actual testing
was meeting
the
Code requirement
and
a procedure clarification would be
appropriate
to resolve
the above discrepancy.
This item will be
carried
as unresolved
(50-244/88-10-02)
pending the licensee's
action
to clarify the affected procedures.
5.0
Review Comments
on Current
IST Pro
ram
During the inspection,
the inspector
had several
observations
concerning
the
IST program.
The more significant i.tems were previously mentioned
concerning
the omission .of certain clieck'alves
from the
IST program
and
inadequate
testing of certain check valves.
Other items were discussed
with the licensee
where certain observations/questions
pertinent to the
IST program were presented.
These
are items requiring resolution during
the forthcoming
NRC staff review of the next
10-year interval
IST program.
The specific items are detailed
below and they will be carried
as
unresolved
items
as applicable
pending the formal
NRC staff review of the
IST program.
5. 1
Full-Stroke Exercisin
of MSIVs
The MSIVs (valves
3516
and 3517) are designated
in the
IST program
to be full-stroke exercised
on
a refueling cycle basis.
While this
is consistent with the plant technical
specifications, it is not
consistent with the
ASME Code,
Section
XI which stipulates
a cold
14
shutdown (not refueling) frequency for those valves where quarterly
exercising is not practical during plant operation.
The inspector
requested
the licensee
to evaluate this matter
and determine their
basis for the .full-stroke exercising
frequency of the MSIVs.
This
item is unresolved
(50-244/88-10-03)
pending the licensee's
action
to resolve this issue;
5.2
Testin
of Service Water Solenoid Valves for AFW Pum
Lube
Oil Coolers
These valves are designated
as
4324,
4325
and 4326.
They serve to
warn the operator of potential
clogging of the filter in the service
water piping upstream of the lube oil cooler for each
AFW pump.
The
valves
appear
to have
a safety related function but they are not
~
currently included in the
IST program.
However,
these
valves are
tested
monthly with the
AFW pump testing in PT-16.
Since the valves
are being periodically tested
and they appear to have
a safety
related function, the inspector
requested
the licensee
to evaluate
inclusion of these
valves in the
IST program.
This item is unresolved
(50-244/88-10-04)
pending completion of the licensee's
evaluation.
5.3
Inclusion of Manual
Valves
4098
4344
and
4345 Into IST Pro
ram
These
manual
valves
are normally closed
and when opened
they direct
service water flow to the suction of each
AFW pump.
The valves are
not currently included in the
IST program
even though they are being
full stroke exercised
monthly in PT-16.
Since these
valves must
change positions to serve their safety related function, they should
be formally included in the
IST program.
The licensee
indicated
that valves
4098,
4344 and
4345 would be included in the IST program.
6.0
General
Comments
Concernin
Basis of IST Pro
ram
The. inspectors
performed
a preliminary review of the Ginna
IST program.
Also several
procedures
were reviewed during the inspection.
This review
revealed
a lack of understanding
of the check valve stroking requirements
and omission of key information from the testing
program.
Specifically,.
the
IST program does
not indicate
how
a check valves is exercised, i.e.,
partial stroke and/or full stroke including its associated
frequency.
Also, the program does not identify what is the safety-related
position of
the check valve, i.e.,
open,
closed,
or open
and closed.
It is not
possible,
for example,
to determine
from the program whether
reverse
flow
testing is being performed.
These deficiencies
in the program resulted in
reverse
flow testing not being performed in general,
and full stroke
exercising
not being performed in many cases.
These deficiencies will be
carried
as
an unresolved
item (50-244/88-10-05)
pending resubmittal of the
IST program for formal
HRC review.
15
In addition,
valve number
9705A,
on Process
and Instrumentation
diagram
(P8 ID) No.
33013 Revision 2,
was incorrectly identified as
9075A.
Upon
identification of this concern,
the licensee
representatives
agreed
to
review and revise this P&ID.
7.0
A/
C Involvement in IST Pro
ram
The inspector
reviewed the
1986
and
1987 audit reports
completed
by the
licensee's
QA group for the
IST program.
Also the inspector
reviewed
a
sample of surveillance
reports
issued
in 1988 by the
QC group for certain
IST activities.
Based
on these
reviews
and discussions
with licensee
personnel
ihe inspector
observed
the following:
The licensee's
QA and
QC independent
oversight
and assessment
of the
IST activities resulted
in certain findings.
However,
these findings
have not been significant to the extent that the major elements
of
the
IST program
have not'een
affected.
Finding resolution
and
conclusion
have
been
such that component operability
has not been
addressed
since the causes
for the findings (a missed surveillance or
an incorrect instrument reading)
have
been classified
as isolated
problems.
Generally
each
PT includes instructions to notify QC prior to the
test.
QC surveillance
personnel
were present
to monitor the
5 pump
tests
that were performed
on May 17,
1988 per PT-16 and 36.
However,
discussions
with QC personnel
indicated that there
was
a random
selection of PTs for QC involvement based
on available
QC manpower.
In conclusion,
while there is
some level of QA/QC coverage for the
activities, it appears
that this coverage
is not adequate
to identify and
correct
such problems
as those discussed
in previous sections
of this
report.
8.0
Unresolved
Item
Unresolved
items are matters
about which more information is required to
ascertain
whether they are acceptable,
deviations. or violations.
Four
unresolved
items were identified during this inspection
and they are
discussed
in sections
4, 5,
and 6.
9.0
Mana ement Meetin
s
Licensee
management
was informed of the
scope
and purpose of the
inspection at the entrance
meeting conducted
on May 16,
1988.
The
findings of the inspection
were discussed
with licensee
representatives
during the course of the inspection.
An exit meeting
was conducted
on
May 20,
1988 at the conclusion of the inspection
(see
section
1.0 for
16
attendees)
at which time the licensee
management
was informed of the
inspection results.
Region I management
attended this exit meeting
by
way of teleconferencing.
At no time during this inspection
was written material
provided to the
licensee.
The licensee
did not indicate that proprietary information was
involved within the
scope of this inspection.
'
Attachment
A
Documents
Reviewed
1.
Maintenance
Items
Procedure
No. M-11. 12. 1,
Rev. 8,
1A Safety Injection
Pump Mechanical
Inspection
Procedure
No. M-37.38. 1,
Rev.
7, Safety
and Relief Valve Inspection
and Maintenance for Valve No.
RV-203
Maintenance
Work Request
88-3720,
Repack Indicator Arm for Valve
3504B,
dated
May 18,
1988
Maintenance
Work Requests
88-3747
and 88-3748,
"B" and "A"
Containment
Spray Discharge
Check Valve Full Stroke with Position
.
Indicator, dated
May 20,
1988
2.
Vendor Drawin
s of Swin
Anchor Darling Drawing W8522289,
Rev.
B, 6" - 300 Stainless
Steel
with Position Indicator (862A and
B)
Anchor Darling Drawing W7820112,
Rev.
A, 6" 600 Carbon Steel with
Counterweight
(3504B and
3505B)
Borg-Marner Drawing 73490,
4" - 300 Carbon Steel
(9627A and
B)
A/
C
Re orts
QC Surveillance
Reports
88-0792
and 88-0811, Auxiliary Feedwater
System,
dated April 28,
1988 and
May 18,
1988
QC Surveillance
Reports
88-0789
and 88-0810,
Standby Auxiliary
System
Flow Check,
dated April 27,
1988
and
May 18,
1988
QA Audit Report 86-29,
Ginna Surveillance
Testing
and
Pump
and Valve
Testing
Programs,
dated July 21,
1986
QA Audit Report 87-47,
Ginna Surveillance Testing
and
Pump
and Valve
Testing
Programs,
dated October
14,
1987
4.
Monthl
Pum
Test Data for Period
Ma
1987 throu
h A ril
1988 for:
PT-16 Auxiliary Feedwater
Pumps
PT-36 Standby Auxiliary Feedwater
Pumps
PT-2. 1 Safety Injection
Pumps
PT-2.2
RHR Pumps
PT-2.7 Service Water
Pumps
PT-2.8
Component
Cooling Water
Pumps
PT-3.0 Containment
Spray
Pumps
'