ML17254A332
| ML17254A332 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/08/1985 |
| From: | Durr J, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17254A328 | List: |
| References | |
| 50-244-85-05, 50-244-85-5, NUDOCS 8504180415 | |
| Download: ML17254A332 (9) | |
See also: IR 05000244/1985005
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report
No.
50-244/85-05
Docket No.
50-244
License
No.
Priority
Category
C
Licensee:
Rochester
Gas
and Electric Cor oration
49 East Avenue
Rochester
14649
Facility Name:
R.
E. Ginna Nuclear
Power Plant
Inspection At:
Ontario
Inspection
Conducted:
Februar
4-8
1985
Inspectors:
R. A. McBrearty, Reactor
gineer
date I ifI~
Approved by:
J.
P. Durr, Chief, Engineering
Branch,
date
Ins ection
Summar
Ins ection
on Februar
4-8
1985
Re or t No. 50-244/85-05
Areas Ins ected:
Routine,
unannounced
inspection of activities associated
with
modifications to the spent fuel storage
racks.
The inspection
involved 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />
on site by one regional
based
inspector.
Results:
One violation was identified (failure to calibrate
measuring
equip-
ment used for acceptance
testing of modified spent fuel racks).
85041804i5 8504'~
ADOCK 05000244
Q
- DETAILS
1.0
Persons
Contacted
J.
Cook, Responsible
Engineer
N. Goodenough,
Project
QC Engineer
'T. McFee, Construction
Engineer
K. Nassauer,
QC Supervisor
"J.
B. Neis, Liaison Engineer
"B. A. Snow, Superintendent
- Nuclear Production
- S.
M. Spector,
Assistant Superintendent
~J.
T. St. Martin, Modification Test Coordinator
"R.
W. Vanderweel,
Project Manager
Modifications
- T. Mieand, Construction
Engineer
Nuclear
Power Services
J.
Green,
QA Supervisor
U.S. Nuclear
Re ulator
Commission
"M. A. Cook, Senior Resident
Inspector
- Denote those present at the exit meeting.
S ent Fuel
Pool
Stora
e Rack Modification
The
licensee
proposes
to
increase
the
storage
capacity
by modifying
six (6) of the
nine (9) existing "flux trap" type storage
racks currently
in the
SFP to high density "fixed poison"
type
storage
racks.
This will
double
the
storage
capacity of the modified racks
from 420 to 840 storage
cells.
The
capacity
of the
three
(3)
remaining "flux trap"
type
racks
( 176 storage cells) will remain
unchanged.
The
NRC Safety Evaluation
Report
(SER) supporting
License
Amendment
No.
65
permitting the modification was issued
on November
14,
1984.
The licensee
is permitted to increase
the capacity of the
from the current capacity
of 595 fuel assemblies
to 1016 fuel assemblies.
Fabrication
of the modified racks is governed
by Technical
Specification
N-50,
Revision
0, which specifies
that welding will meet
ASME Section
IX
and Section III, Subsection
NF,
1980 edition.
The inspector
reviewed procedures,
drawings,
and quality records,
and
made
observations
at
the
work site
to ascertain
that
the modification
meets
regulatory requirements
and licensee
commitments.
a.
Review of Im lementin
Procedures
The
following procedures
were
included
in the
inspector's
review:
~
Procedure
No. SM-3666.1,
Revision
1,
"SFP
Rack Modification Hold
Down Bolt Removal"
~
Procedure
No.
SM-3666.3,
Revision
3,
"Rigging
and
Designated
Travel Paths"
~
Procedure
No.
SM-3666.4,
Revision
2,
"Spent
Fuel
Pit
Racks
Decontamination"
~
Procedure
No.
SM-3666.5,
Revision
1,
"SFP
Rack
In Guide
Bending"
~
Procedure
No.
SM-3666.6,
Revision
2,
"Spent
Fuel
Pit
Rack
Modification Rack No."
~
Procedure
No.
SM-3666.8,
Revision
1,
"Seismic Restraint
Removal
and
Base
Shimming"
~
Procedure
No.
SM-3666.9,
Revision
2,
"Rigging
and
Designated
Travel
Paths
For Racks
Number
1 and 2"
~
Procedure
No.
SM-3666.2,
Revision
1,
"Racks
Number
1
and
2
Sidepull Structural Modification"
~
Procedure
No.
HP-13.5,
Revision
1,
"Health Physics
Requirements
Associated
With Diving Operations"
The inspector
found that
step
by step instructions
were provided for
the removal of racks
from the
SFP,
rack decontamination,
the required
modifications,
inspection
and
the return to the
SFP of ..the modified
racks.
The instructions
included
health
physics
precautions
to
be
taken while divers were in the pool, rigging and lifting techniques,
and the requirement for training of those individuals performing the
lifting and rigging operations.
No violations were identified.
b.
ualit
Assurance
A / ualit
Control
C
Activities
The inspector
reviewed
licensee
QA/QC records to ascertain
that fuel
rack modification activities
were included in the licensee's
program
and that regulatory
requi rements
were
met.
The inspector's
review .
included the following:
QA Surveillance
Reports
of survei llances
done at U.S.
Tool
and
Die, Incorporated,
on September
18,
1984,
September
28,
1984 and
October 25,
1984.
Surveillance
Report
No.
85.0037,
dated
January
12,
1985
Surveillance
Report
No.
85.0038,
dated
January
12,
1985
gC
Surveillance
Report
No.
84.0883,
dated
December
4,
1984
gC
Surveillance
Report
No.
84.0886,
dated
December
5,
1984
~
Nonconformance
Report
(NCR)
No.
G84-154,
dated
December
4,
1984
Engineering
Change
Notice
(ECN)
No.
3666.6,
dated
January
4,
1985
The
inspector
found that
gC Surveillance
Report
No.
85.0883 identi-
fied that the Dillon Load Cell,
S/N LAB-2791, which was
used for the
drag
force acceptance
test of SFP
Rack No.
3 (placed in pool at rack
No.
5 location
and
now designated
as
rack
No.
5 - old rack
No
~
3),
was
not calibrated
prior to
use.
The test
was
done
on
December
3,
1984 and the surveillance report is dated
December
4,
1984,
as is the
applicable
Drag
Test
Data
Sheet.
Nonconformance
Report
(NCR)
No.
G84-154
was
generated
by Project
gC to follow-up the
surveillance
report.
Corrective action
recommended
by Engineering
to disposition
the
was
to calibrate
the
load cell
by adding
a
50
pound test
weight to the
dummy fuel cell
and observe
proper deflection.
gC Sur-
veillance
Report
No.
84.0886
documented
the
use of the test
weight,
and
noted that the scale deflection
was approximately
50 pounds.
The
report further notes
that the disposition
of
G84-154
takes
ex-
ception
to the calibra ion requirements
of procedure
No.
A-1201
and
describes
a
method
to demonstrate
a limited degree
of
measurement
accuracy
by adding
a
50
pound weight to the
dummy cell
and observing
scale deflection.
The
one
point verification is
not
considered
adequate
to calibrate
instrument
range linearity or deviation at other points
on the range.
A search
of
ASTN documents
indicates
an
adequate
calibration
must
cover the full range of the instrument.
Subsequent
to
the
gC finding
and
limited
one
point verification,
three
additional
racks
were
accepted
based
on
the
use
of the
same
uncalibrated
load cell.
The accepted
racks
are
as follow:
Rack Desi nation
Date of Dra
Test
Data Sheet
"Rack No.
5 (Old Rack No. 3)
Rack No.
3 (Old Rack No. 5)
Rack No.
1
Rack No.
2 (Old Rack No. 4)
"gC finding associated
with this rack.
12/4/84
1/4/85
1/11/85
1/25/85
The inspector
examined Dillon Load Cell
S/N
LAB 2701
and found
no
evidence
of
calibration
stickers
or
tags
to
indicate
the
acceptability
of calibration
and
control
status
of
the
equipment.
The
inspector
stated
that
because
the
load cell
was
used
to accept
safety related
components,
the equipment
should
have
been calibrated
and
controlled
in
accordance
with
Procedure
A-1201
entitled
"Calibration
and
Control
of
Measuring
and
Test
Equipment,
Plant
Instruments
and
Equipment."
Failure
to calibrate
the
load cell is
considered
a violation (244/85-05-01).
In addition to the
above
the inspector
examined
the Dillon Load Cell
with respect
to its appropriateness
for the use to which it was put.
The inspector
found that the instrument
was
used
on the
0-3000
pound
range
which
is
graduated
in
20
pound
increments
with
no
minor
graduations.
Readings
which fall
between
the
graduations
must
be
int'erpolated,
and
because
of
the
small
distance,
approximately
0.050",
between
the graduations
these
readings
are unprecise.
Specification
F-8,
which
has
been
incorporated
into
Rochester
Gas
and Electric
Corp.
Specification
N-50
as
Appendix
C,
requires
that
insertion
and
withdrawal
drag
shall
not
exceed
50
pounds.
No tolerance
is
provided for drag
forces
greater
than
50
pounds.
A licensee
commitment to evaluate all drag
forces
in excess
of 50
pounds
on
a case-by-case
basis is documented
by the
NRC Safety
Evaluation
dated
11/14/84.
The
licensee's
ability to
meet
the
F-8
requirement
and
his
NRC
commitment with the
instrument
in
use
was
questioned
by the inspector,
and is co>>sidered
unresolved
pending the
licensee's
action demonstrating
that Dillon Load Cell
LAB-2791 can
be
read to the required accuracy
(244/85-05-02).
Review of ualit
Records
To
ascertain
that
licensee
purchase
requirements
were
met for the
high density spent fuel racks,
the following were reviewed:
U.S.
Tool
and Die, Inc., (U.S.
TED) Documentation
Check List for
Shipment ¹1, ¹2 and ¹3
USTED Certificate of Conformance
dated 9/28/84
Bisco Products,
Inc., Certificate of Conformance
dated ll/29/84
certifying
that
Boraflex
material
meets
or
exceeds
design
requirements
RGKE Safety Analysis
RG&E Source
Acceptance
Inspection
Reports
for Shipment ¹1, ¹2
and ¹3
~
gC Final Inspection
Report for the following:
1.
Rack ¹2 - old Rack ¹4
2.
Rack ¹1
3.
Rack ¹3 - old Rack ¹5
4.
Rack ¹5 - old Rack ¹3
~
Material
Test
Reports
for
SS-304
inserts,
1/16"
sheet,
1/8"
plate,
1/4" plate,
1/2" plate
and 3/4" plate
The
records
indicated
that
the
required
documentation
was provided
including certificates
of
conformance
for
the
neutron
absorbing
material
(Boraflex)
and
that
dimensional
requirements
were
met.
No violations were identified.
3.
Unresolved
Items
Unresolved
items
are matters
about
which more information is required to
ascertain
whether
they
are
acceptable
items,
violations,
or deviations.
An unresolved
item is discussed
in paragraph
2b of this report.
4.
Exit Interview
The
inspector
met with licensee
representatives
(denoted
in paragraph
1)
at the
conclusion
of the
inspection
on
February
8,
1985.
The inspector
summarized
the
scope
and findings of the
inspection.
At
no
time during
this
inspection
was written material
provided
by the
inspector
to the
licensee.