ML20040F405
| ML20040F405 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/13/1982 |
| From: | Key W, Landsman R, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20040F397 | List: |
| References | |
| 50-373-81-51, NUDOCS 8202090162 | |
| Download: ML20040F405 (3) | |
See also: IR 05000373/1981051
Text
~
.
l
.
U.S. NUCLEAR REGULATORY COMMISSION
'
REGION III
'
Report No. 50-373/81-51
Docket No. 50-373
License No. CPPR-99
,
Licensee: Commonwealth Edison Company
'
Post Office Box 767
Chicago, IL 60690
Facility Name: LaSalle County Station, Unit 1
Meeting At: Region III office, Glen Ellyn, IL
Meeting Conducted: December 22, 1981
/- 7- EI 2-
'
Inspectors:
R. B. Landsman
WV\\
_
W. J. Key
lf/R/Z)
@.Q,Wh v
^
/
/b
Approved By:
C. C. Williams, Chief
Plant Systems Section
/
'
Inspection Summary
Meeting on December 22, 1981 (Report No. 50-373/81-51)
Areas Inspected: This was a special announced meeting to discuss the
licensee's response to the NRC concerns about LaSalle County as-built
structural design drawings. This meeting involved a total of 44
inspector-hours at the Region III office by eleven NRC inspectors.
Results: No items of noncompliance or deviations were identified.
8202090162 820127
{DRADOCK 05000373
.
.
DETAILS
1.
Attendees
Ccmmonwealth Edison Company
B. Lee, Vice President
L. De1 George, Manager of Nuclear Licensing
D. Skoza, Engineering Staff, LaSalle Construction
B. Stephenson, Project Manager, LaSalle
B. Shelton, Station Nuclear Engineering Department
R. Cosarro, Construction Superintendent, LaSalle
D. Shamblim, Staff Assistant, Project Manager, LaSalle
A. Kleinrath, Manager of Station Construction
J. Maley, Manager of Projects
C. Sargent, Licensing
W. Shewski, Manager QA
T. Quaka, Site QA Superintendent
R. Rose, Supervisor Construction Engineering - Structural
Sargent & Lundy
R. Mazza, Project Di ector
K. Kostal, Assistant Ma.'ager - Structural Department
V. Reklatis, Structural Project Engineer
NRC
J. Keppler, adminstrator
A. Davis, Assistant Administrator
C. Norelius, Director, DETI
R. Spessard, Director, DRPI
I. Jackiw, Chief, Test Program Section
R. Walker, SRI, LaSalle
S. Shepley, RI, LaSalle
F. Hawkins, Reactor Inspector
A. Bournia, NRR Project Manager
2.
Meeting
The meeting was initiated by Region III to discuss the licensee's
progress to date on the issues raised from the ongoing Region III
inspection of as-built structural design drawings.
The licensee presented the results of an accelerated inspection
effort conducted in the primary containment drywell to determine
if the as-built structural steel in the drywell is consistent
with final design packages. The licensee's inspection effort was
initiated as a result of the NRC Region III inspection findings.
The licensee stated that they had conducted visual inspections of
I
l
l
\\
l
-2-
i
_
_.
.
_
m
.
_
_
.O
263 structural steel beams in the drywell. All of the structural
a
steel beams inspected had been modified in some manner (i.e., a
design change had been made to' the structural steel) via a field
change request (FCR). The licensee performed all inspections using
the FCR's as acceptance criteria and Sargent and Lundy design per-
sonnel as inspectors.
The licensee's findings frc>m these inspections indicated that two
other deficiencies of a minor nature were found in the 263 beams
inspected. These two defiuiencies are in addition to the one found
by NRC Region III inspection activity.
fhe licensee stated that none
of the defects, including the one found by NRC Region III personnel,
would have resulted in tailure of a component to perform its safety
function.
The licensee also stated that the errors and discrepancies found in
the "as-built" drawings by the NRC inspection effort were the result
of a lack of understanding as to what constitutes a final design
package. The licensee stated that the final design package, which
would accurately represent the "as-built" condition, consists of
FCR's, shop drawings, and the supporting calculations.
The meeting ended with the licensee verbally committing to do the
following:
>
a.
Continue inspecting structural steel placement in the primary
!
containment drywell until 100% of the accessible structural
steel affected by FCR's can be confirmed to be consistent with
final design packages.
,
b.
Provide the NRC with a statistical based sampling program of
structural steel outside of the primary containment drywell to
be reinspected to confirm that the structural steel construction
is consistent with the final design package.
c.
Provide the NRC with a clear definition of what constitutes a
i
final design package.
d.
Review their current procedures for updating drawings to see if
they can be modified to incorporate a requirement for more timely
updating of drawings to incorporate design changes /FCR's.
1
I
-3-
__ . - - ,
_ -
. . . - . .
_.
_ _ _ . _
-_