ML17138B806
| ML17138B806 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/13/1980 |
| From: | Durr J, Mcgaughy R, Reynolds S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138B800 | List: |
| References | |
| 50-387-80-17, 50-388-80-11, NUDOCS 8102240155 | |
| Download: ML17138B806 (8) | |
See also: IR 05000387/1980017
Text
U.S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION
AND ENFORCEMENT
Region I
50-387/80-17
8
0
II
. ~80-888
80-11
50-387
Docket No.
50-388
License
No.
CPPR-102
Priority
50-387/B
Category
50-388/A
Licensee:
Power and Light Company
2 North Ninth Street
Allentown, Pennsylvania
18101
Facility Name.
Susquehanna
Units
1 and
2
Inspection at:
Ber'wick,8 'Pennsyl vani a
Inspection
conducted:
July 8-11,
1980
Inspectors:
.
Du r, Reactor
Inspector
S.
D. Reynold
, Reactor
Inspector
t
signed
g~
date signed
Approved by:
.
M. McGaughy
C.
, Projects
Section,
RC8E
B
ch
date signed
da
e signed
Ins ection Summar:
Unit: No.
1 Ins ection
on Jul
8-11
1980
(Re ort No. 50-387/80-17)
Areas
Ins ected:
A routine, unannounced-inspection
of outstanding
items, pipinq,
an
we ding activities.
The inspection involved 26 inspector-hours
on site
by two
.
NRC Regional
inspectors.
Results:
No items of noncomp1iance
were identified.
Unit No.
2 Ins ection on Jul
8-11,
1980 (Report Ilo. 50-388/80-11)
Areas
ns ecte:
routine,
unannounce
snspectson
o
outstan
ing items, piping,
an
we
ing activities.
The insnection involved 27 inspector-hours
on site by two
regional inspectors.
Results:
No items of noncompliance
were identified in 2'of the areas
examined.
One
item of noncompliance.was
identified in one of the areas
(infraction-failure to
properly inspect concrete placements,
para.
2}.
Region I Form 12
(Rev. April 77}
8 2 OP.P gID/Z5',r
~, ~
C
DETAILS
1.
Persons
Contacted
Penns
lvania Power
and Li ht
Com an
- R. A. Beckley,
Coordinator-NDE Training and Program
E. ll. Carroll, Senior
NQA Analyst
- S. L. Denson,
Project Construction
Manager
- P. Kyner, Resident
Nuclear Quality Assurance
Engineer
J. Lindberg,
NQA Analyst
Bechtel
K. Durland, Assistant
- M. A. Drucker,
QA Engineer
G. Finnan,
Lead Engineer
Melding QC
J.
Fr~.nks,
General
Foreman,
Hangers
F. Hand,
Lead Civil Engineer
J.
Hudock, Senior Field Engineer,
Civil
J.
Kempster,
Field Engineer, Civil
- H. F. Lilligh, Project Quality Assurance
Engineer
- K. G. Stout, Project Field
QC Engineer
ll. Thackaberry,
Lead Engineer Civil, OC
NRC Resident
Ins ectors
- R. M. Gallo, Senior Resident
Inspector
- G. G.
Rhoads,
Resident
Inspector
- Denotes those
persons
present at the exit interview.
Other craftsmen
and technicians
were interviewed
as necessary
when the inspection
interfaced with their work.
2.
Plant Tour (Unit
1
and 2)
The inspectors
toured the Unit Nos.
1
and
2 reactor buildings, primary
containments,
and the Unit No.
2 suppression
chamber.
They observed
work in-progress,
completed work, and interviewed craftsmen
and technicians
concerning their activities.
3
.
The inspector
observed
an imperfection in the Unit No.
2 primary
containment
concrete shell.,
A 4 foot long by approximately
1 1/2"
wide flaw in the concrete
extends horizontally across
X-
50B.
This appears
to be located at the construction joint for concrete
placement
391-W-21
as depicted
on drawing ZC-391, Revision 3.
The
,
flaw is filled with loose debris
such
as bits of wood and loose
sand
which would have resulted
from improper cleaning of the joint before
concrete
placement.
A review of Field Inspection
Plan C-8-1, 2,
3 - 391-W-21 for this
-'lacement indicates .that
a preplacement
cleanliness
inspection
was
made.
Furthermore,
item 17 of the Concrete
Post Placement
Report does
not reflect that repairs
were necessar).
There is
a handwritten note
stating,
"Upon complete
removal of forms
an inspection will be made
'nd
repairs if necessary will be documented
on FIPC-8-3C-391-W-21."
The licensee
was unable to locate
any evidence that this inspection
was performed.
The Technical Specification for Forming, Placing, Finishing,
and
Curing of Concrete,
C-8, papragraph
18.
Inspection,
requires
inspections
be performed for cleanup before concrete
placement
and for imperfections
afte~ form removal.
The failure to properly perform these
inspections
is an Item of Noncompliance
(388/80-11-01).
A wall penetration
in Unit 2, Area 30, elevation 670',
as depicted
on
drawing X-30-2, was observed
to have several
reinforcement
bars
damaged
from core drilling operations.
Further investigation into the documentation
and repair of these defects
disclosed that recent similar problems
had
initiated several
corrective actions.
The licensee
issued
MCAR-1-48 describing cut rebar in the east refueling
pool girder resulting from core drilling.
This resulted in modifications
to Field Procedure
FP-C-1 requiring seria)ization
and logging of
excavation
checksheets
and review by the
Lead Civil Engineer.
However,
interviews and discussions
with the engineering staff indicated that
field engineers,
other than civil, were required to detemine if rebar
had
been cut or damaged.
When this was pointed out as
a weakness
in
the program,
the licensee
issued
an Interoffice Memorandum,
dated July
10,
1980, altering field procedure
FP-C-1 to require the
Lead Civil
Engineer to "...verify the cut rebar information..." The inspector
had
no further questions
concerning this matter at this time.
Licensee's
Action on Previousl
Identified Ins ection Findin
s
(Closed)
Unresolved
Item (387/80-12-02)
Piping system turnover.
The
NRC inspector
expressed
concern that piping systems
were being turned
over for filling and flushing prior to the supports
receiving final
inspection.
The concern
was that dynamic forces during flushing could
over stress
the pipe.
The inspector
reviewed the Bechtel letter,
dated
June
27,
1980, Subject:
Pipe Supports for Safety Related
Systems.
The Project Engineer
has reaffirmed that the dynamic loads are negligible,
valve closure
times are in excess of 10 seconds,
and systems
are
designed
to be full of water when
pumps are started.
Based on'he
foregoing information, this matter is closed.
.
s.
Safet
Related
Pi e'Su
orts and Restraints
(Unit No.
1)
In inspection report 78-02 the
NRC inspector identified a condition in
which the cap,screws
joining the rear bracket to body of mechanical
shock suppressors
did not have .full thread
engagement.
The licensee
generated
Nonconformance
Report
No., 2721 which documented
the condition
and dispositioned
the corrective actions required.
The corrective
actions
were to replace. the short screws in installed
and stored
restraints
and to alert the manufacturer.
The inspector
reviewed the
ITT Grinnell letter, dated
June 2,
1978,
acknowledging
the problem and
directing replacement of the short fasteners.
"An inspection of 6 installed
and
1 stored restraints verified that
short fasteners
have
been replaced.".',This will Be further
inspected
on
a random basis
during future plant tours.
The .inspector selected
pipe supports
GBC-101-H105,
128,
and
188 for
examination of bolting materials.
The drawings for these
supports
.specify
ASME material specifications
SA-193 gr.
B-7 and
SA194 gr.
2H
for the nut and bolt materials.
The specification requires that the
materials
be marked with these
designations
so they are readily identifiable.
The inspector
was unable to locate
these
markings for
some bolts
and
nuts
on pipe supports
GBC-101-H188 and 189.
This item is considered
unresolved
pending determination of the bolt and nut materials
and the
inspection status of the supports
(387/80-17-01).
Observation of'i e Weldin
Activities (Unit No. 2)
The. NRC inspector selected
typical welding activities associated
with
piping outside the reactor coolant pressure
boundary for detailed
review and inspection.
Eight Bechtel welds were selected
and reviewed
to determine that welding was in accordance
with BOAM Rev 4 3/76 and
the
ASME Section III requirements
and that welding was conducted in
accordance
with a traveler,
welds were properly identified, the
WPS
met
ASME Code requirements,
welding parameters
specified were followed,
welding equipment
was in adequate
condition, welders
mark was marked,
welders properly qualified,
and weld history record
keeping
was adequate.
The Unit 2 pipe welds that were observed
in process
were
as follows:
ACTIVITY
DLA-202-1
FW19
FW27
GBB-215-1
FW4
DBC-201-1
FW47
DLA-204-1
FW3
GBC-201-9
FW2
GBC-201-11
FW12
Nipple socket fillet to HPSI
pump
PT of end prep welding
Small pipe weld
Fitup of joint
Fitup with tack welds
and root pass
Intermediate
weld pass
Intermediate
weld pass
Joint fitup
No items of noncompliance
were identified.
'.
Review of Weldin
Material Control
The
NRC inspector reviewed the welding filler metal control system.
The procedures
for purchasing
welding materials
to meet
ASME Code
requirements
in Bechtel
WFMC-1
Rev
2 4/76
and
BQAM Rev 4 3/76 were
reviewed.
Representative
material test result cer tification for 12
lots'nd/or heats of filler metals
were reviewed for conformance
to
ASME Code and Bechtel
requirements.
The inspector expressed
concern that the weld rod control program may
not be adequate
in that
no mechanism
is currently functioning to
assess
its effectiveness.
The licensee
stated that steps
were being
taken to reinforce this area.
No items of noncompliance
were identified.
Review of ualit
Records of Com leted Field Helds
The
NRC inspector reviewed the Bechtel quality: records of 7 welds in
Unit
1 and'1
weld in Unit 2 to verify that- the records
covering required
inspections
met
BQAM requirements,
were complete,
reflected
adequate
weld quality,
and that the total weld history records
were adequate
.
and met ASME Section III requirements.
The completed
weld history
records
packages
reviewed were
as follows:
HELD 8
DBC-102-1
DBC-102-1
DLA-102-1
GBB-111-1
DCB-202-1
DCA-102-2
DCA-107-2
DBA-101-2
DCB-102-1
DCB-102-1
DBB-101-1
DBB-101-1
FW2
FW2Rl
FH15
FW3
FW3
FWl
FH7
FH1
FH2
FW2R1
FH5
FW5R1,
R2,
R3
SIZE
3"OD
X 0.438"
12"OD x 0..687"
4"OD x 0.237"
18 "OD x, 0. 562"
4.5"OD x 0.300"
12"OD x 0.613"
6"OD x 0.432"
60Dx0432
24"OD x 0.941
HPS
Pl-AT-LH
Pl-AT-LH
Pl-AT-LH (CVN)
Pl-AT-LH
P8/Pl-AT-Ag
P8-AT-Ag
P8-AT-Ag
Pl-AT-LH
P8-AT-Ag
Pl-AT-LL-I
8.
No items of noncompliance
were identified.
Review of HPS and Weldin
Related
OA Documents
The
NRC inspector
reviewed Bechtel welding procedure
specifications
(WPS), procedure qualification records
(PQR's) specific to the
tlPS
documents,
Bechtel
Field Fabrication
and Installation of Nuclear
Piping documents
and the Bechtel
f'orms that constitute
the weld history
record.
The documents
reviewed:
WPS P8-AT-Aa,
Rev
2
WPS Pl-AT-LH
WPS Pl-AT LH (CVN)
WPS P8-AT-Ag-I
PQR-8,-19,-20,-11,-17,
BQAM Rev 4 3/16 with
WD-l, HR-5,
WR-6 forms
.The documents
were reviewed to assure
compliance with the minimum ASME
rules.
No items of noncompliance
were identified.
9.
Unresolved
Items
Unresolved
items are matters
about which more information is required
to ascertain
whether it is an item of noncompliance,
a deviation, or
acceptable.
An unresolved
item identified in this report is discussed
in paragraph
4.
10.
Exit Interview
The inspector
held
an exit interview
licensee
(devoted
in paragraph
1) on
of the inspection.
He discussed
the
In addition, further information was
. conversation
on July 18,
1980.
with representatives
of the
July ll, 1980, at the conclusion
scope
and findings of the inspection.
exchanged
in a subsequent
telephone
@+i iA
0