ML17325A626
| ML17325A626 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/22/1988 |
| From: | Harrison J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17325A627 | List: |
| References | |
| NUDOCS 8802260179 | |
| Download: ML17325A626 (7) | |
See also: IR 05000316/1988002
Text
(,I
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION III
Report
No. 50-316/88002(DRS)
Docket No. 50-316
License
No.
Licensee:
American Electric Power Service Corporation
and Michigan Power
Company
1 Riverside
Plaza
Columbus,
OH
43216
Facility Name:
D.
C.
Cook Nuclear Plant, Unit 2
Inspection At:
D.
C.
Cook Site,
Bridgman, Michigan
Inspection
Conducted:
December
3,
1987, January
15,
and February 4-5,
1988
Inspector:
Ja
obson
Date
Approved By:
D. H. Danielson,
Chief
Materials
and Processes
Section
Date
Ins ection
Summar
Ins ection on December
3
1987
Januar
15
Februar
4-5
1988
Re ort No. 50-316/88002
Areas Ins ected:
Routine,
unannounced
safety inspection of the procedures,
personnel
qualifications,
and results of the Unit 2 eddy current examination
of the
(73755)
and the Auxiliary Building crane
upgrade for
replacement
(37702).
Results:
No violations or deviations
were identified.
8802260i79
o 0316
ADOCK 0500
G
DETAILS
Persons
Contacted
American Electric Power Service
Cor oration
AEPSC
and Michi an
Power
Com an
IEM
J. Rutkowski, Assistant Superintendent
- Production
"J. White, Site Project Manager
S.
Hodge,
Engineering
Manager
W. Modry, Supervising
Designer Structural
T. McElroy, Plant Project Engineer
R. Rickman, Supervisor,
ISI/NPRDS
T. Postlewait,
Technical
Engineering
Supervisor
J. Droste,
Maintenance
Supervisor
"T. Ossmundsen,
Construction Supervisor
E. Morse,
NDE Supervisor
J. Steinhauser,
Assistant
NDE Supervisor
J. Winckel,
QA Coordinator
Construction
C.
Rapp, Site Manager
R. Perks,
Construction/Engineering
Manager
MK - Fer uson
A. Walcutt, Site
QA Manager
R.
Wilkerson, Assistant Project Manager
M. Cepkauskas,
Project Engineer
- Attended the exit meeting
on February
5,
1988.
Re air Project
The upcoming replacement
of the Unit 2 Steam Generators
requires
modifications to the exi sting Auxiliary Building crane.
The modification
includes replacing the existing
150T/20T trolley with a 150T trolley
designed to Single-Failure-Proof
(SFP) requirements,
and installation of
a
new
SFP crane with 150T and
20T trolleys.
Additionally, the existing
crane rail girder will be upgraded to accommodate
the higher design
wheel
loads
and
a second
holding brake
and
an inching mechanism will be added
to the bridge drive.
The modifications are being performed to meet the
requirements
of NUREG-0612
and 0554 and to permit the movement of the Steam
Generators
in and out of the Auxiliary Building.
The
NRC inspector
reviewed the
AEP design drawings
S-SGR-12-3123-1,
Revision 2,
and S-SGR-12-3128-0,
Revision
1 for the crane rail girder
upgrade
and visually inspected
the in-process
work on several
occasions.
During the installation of the web stiffener plates,
cracking of some
attachment
welds occurred.
The cracking
was caused
in part by improper
weld preheat
and the highly restrained
nature of the weld joint design.
Cracked welds were
removed
and rewelded utilizing proper preheat
and weld
peening
techniques.
To lessen
the chance of cracking additional welds,
the joint design
and attachment
techniques
were modified.
The
NRC
inspector
reviewed the
AEP design sketch
S-SGR-SSk
112187
and inspected
the installation
on several
occasions.
As
a result of the
new design
and
installation techniques,
no further weld cracking occurred.
Several
Condition Reports,
issued to resolve girder base
metal linear indications
and other construction
problems of a minor nature were reviewed
and found
to be adequately
resolved.
The
NRC inspector
reviewed the following welder qualifications
and
associated
radiographs:
Welder No.
C-68
C-133
C-136
C-148
C-158
C-163
C-169
C-177
Film No.
R 2310
R 2059-60
R 2136
R 2152
R 2164
R 2169
R 2279
R 2310
All qualifications
and associated
radiographs
were found to be
acceptable'nd
in accordance
with the
AWS Dl. 1 Structural
Code.
In addition, the
contractor's
Welding Procedure
CS-1004
was reviewed
and found acceptable.
The
AEP "Welder Performance Qualification" Specification
DCC NE 154
QCN,
Revision
3 was reviewed
by the
NRC inspector
and found to lack sufficient
detail with regard to the qualification and record keeping of both
in-house
maintenance
welders
and construction contract welders.
This
issue will remain
an unresolved
item pending review of a forthcoming
administrative procedure
(316/88002-01).
The
NRC inspector
reviewed the following MK-Ferguson procedures
to be
utilized on the Steam Generator
Repair Project:
Design Control
Receipt Inspection
Qualification and Certification of
Inspection
Personnel
SQP-3.1,
Revision
0
FQP-7.1,
Revision
0
FQP-2.1,
Revision
0
In addition, the
NRC inspector
reviewed the following D. C. Cook Project
Procedures:
SGRP Site Technical
Document
Control
SGR Project Organization
Work Package
System
SGR
PP 06-02, Revision
1
SGR
PP 01-01, Revision
0
'GR
PP 05-04, Revision
1
All procedures
reviewed were found to comply with applicable
codes,
standards
and licensee
commitments.
Unit 2 Polar Crane
A walkdown survey of the Unit 2 polar crane
was performed
by the licensee
in October
1,
1987.
This walkdown 'disclosed
several
structural
deviations including the following:
Loose or missing rail plate hold down nuts
Rail splice weld cracks
(two locations)
Bottom rail flange crack
Rail plate hold
down bolts cut off (two locations)
The structure is designed
as
Class I and
was analyzed
by the licensee
in
the as-found condition.
The structure
was analyzed
using the natural
frequencies for the crane derived
by the crane manufacturer.
The
calculation
(3195-170-FC)
demonstrated
that the deviations
do not affect
the shear capacity of the anchorage
and therefore,
the seismic
qualification remains
unchanged.
With regard to the uplift load from the
wheel truck up-kick-plate, the rail is capable of transferring
the load
from the cut-off bolts locations,
to adjacent
elements.
The shear
capacity of the structure
was found to be unaffected
by the cracked rai 1
splices
and bottom flange.
Though the seismic qualification remains
unchanged,
the licensee
has elected to weld repair the cracks
and repair
the cut-off bolts.
All loose or missing hold down nuts will be tightened
or replaced
as required.
/
The
NRC inspector
reviewed the walkdown surveillance report and the
calculations
supporting
the as-found condition.
The calculations
were
found to be acceptable
and
a review of the repairs will be performed
upon completion.
This will remain
an
open item pending review of the
repairs
(316/88002-02) .
Unit 2 Edd
Current Examination
During September
1987,
Combustion Engineering
(CE) conducted
eddy current
examinations of Unit 2 Steam
Generators
21, 22, 23,
and 24.
All
unplugged
tubes
were examined
from the hot leg tube end,
through the hot
leg seventh
support plate.
All tubes
examined received
an analysis
by
Conam in addition to the
CE analysis.
Indication resolutions
were
performed
by both
CE and
Conam Level III personnel.
Multifrequency testing equipment
was utilized to allow filtering of tube
support signals
and to permit limited dent assessment
in a single
pass of
the probe through the tube.
A 2etec
MIZ-18 and
a digital data cartridge
recorder
was utilized with a differential bobbin coil probe.
The
recorded
data
was analyzed with the aid of a Zetec
DDA-4 digital data
analyzer.
A total of 3229 tubes
were examined, resulting in the required plugging
of the following:
SG 421
14 tubes
IIi22
17 tubes
SG 823
17 tubes
SG 824
30 tubes
To date,
Unit 2 has
a total of 951 tubes or 7.02K taken out of service
due to tube degradation.
The
NRC inspector
reviewed the following CE procedures:
Cook-410-004,
Revision
0 - Procedure for Multifrequency Eddy Current
Examination of Non-ferromagnetic
Tubing Using Zetec
MI2-18 Equipment.
Cook-410-005,
Revision
0 - Eddy Current Data Analysis Procedure
Evaluation of Westinghouse
Tubing.
NgAI 2.4, Revision
4 - Certification Program for Nondestructive
Examination Personnel.
The procedures
were found to be in accordance
with the
ASME Boiler and
Pressure
Vessel
Code,Section XI, 1983 Edition with Summer
1983 Addenda
and the intent of USNRC Regulatory
Guide 1.83.
A sample of personnel
qualifications were reviewed
and found to comply
with SNT-TC-lA, 1980 Edition and
5.
~0en Items
Open items are matters
which have
been discussed
with the licensee,
which
will be reviewed further by the inspector,
and which involves
some action
on the part of the
NRC or licensee
or both.
Open items disclosed
during
this inspection
are discussed
in Paragraph
3.
6.
Unresolved
Items
An unresolved
item is
a matter about which more information is required
in order to ascertain
whether it is acceptable
item,
an open item,
a
deviation, or a violation.
Unresolved
items disclosed during this
inspection
are discussed
in Paragraph
2.
7.
Exit Interview
The Region III inspector
met with licensee
representatives
(denoted
in
Paragraph I) at the conclusion of the inspection.
The inspector
summarized
the purpose
and findings of the inspection.
The licensee
representatives
acknowledged this information.
The inspector also
di scussed
the likely informational content of the inspection report with
regards
to documents
or processes
reviewed during the inspection.
The
licensee
representatives
did not identify any such documents/processes
as
proprietary.