ML17332A735
| ML17332A735 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/05/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17332A734 | List: |
| References | |
| 50-316-95-05, 50-316-95-5, NUDOCS 9504240039 | |
| Download: ML17332A735 (3) | |
See also: IR 05000131/2003020
Text
Company
Donald C.
Cook Nuclear
Power Plant
Docket No. 50-316
License
No.
DRP-74
As
a result of the inspection
conducted
from January
31 through March 20,
1995,
a violation of NRC requirements
was identified.
In accordance
with the
"General
Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix
C (1994), the violation is listed below:
Procedure
and Program,
states
in part that
written procedures
shall
be established,
implemented,
and maintained
covering the applicable procedures
recommended
in Appendix "A" of
Regulatory
Guide 1.33,
Rev 2, February
1978.
Regulatory
Guide 1.33, guality Assurance
Program Requirements
(Operations),
Appendix A, states
that safety-related
maintenance
activities should
be covered
by written procedures.
Procedure
No. 12NHP5021.001.051,
Rev 6, Control of Temporary On-Line
Leak Sealing,
Attachment 4, requires
the leak sealing
package
received
from the vendor to be reviewed
by AEP Nuclear Design Group.
This
includes verifying that contractor
documents
and calculations
are
adequate
and correct for the proposed
leak repair.
Contrary to the above:
a.
Calculations
and work procedures
documented
in Furmanite Procedure
No. N-95036, Revision 2, dated
February
22,
1995:
(1)
Did not specify that
a minimum effective thread length of
0.41 inches
had to be attained for the installation of the
3/8-inch shutoff adapters,
as required for auxiliary
connections
by the original design
code for the valve,
American National Standard
b.
(2)
Did not consider design basis loading due to seismic or
actuator thrust,
and utilized 1/8-inch diameter holes,
instead of the actual 3/8-inch diameter holes
when
calculating the resulting valve body longitudinal stress.
Calculations
documented
in Furmanite
Procedure
No. N-95105,
Revision 2, dated
February
28,
1995:
Failed to consider the load induced in the six flange bolts due to
the moment caused
by the calculated thrust force.
The above
examples
are considered
a Severity Level
IV violation
(Supplement
1).
(50-315/95005-04;
50-316/95005-04(DRP))
'P5Q424003'P
"750405
ADOCK 050003%5
8
Notice of Viol ati on
Pursuant to the provisions of 10 CFR 2.201,
Donald C.
Cook is hereby required
to submit
a written statement
or explanation to the
U. S. Nuclear Regulatory
Commission,
ATTN: Document Control Desk, Washington,
D. C.
20555 with a copy
to the Regional Administrator,
Region III, and
a copy to the
NRC Resident
Inspector
at the facility that is the subject of this Notice,
within 30 days
of the date of the letter transmitting the Notice of Violation (Notice).
This
reply should
be clearly marked
as
a "Reply to a Notice of Violation" and
should include for each violation:
(1) the reason for the violation, or, if
contested,
the basis for disputing the violation, (2) the corrective steps
that have
been
taken
and the results
achieved,
(3) the corrective steps that
will be taken to avoid further violations,
and (4) the date
when full
compl'iance will be achieved.
If an adequate
reply is not received within the
time specified in the Notice,
an order
may be issued to show cause
why the
license
should not be modified,
suspended,
or revoked,
or why such other
action
as
may be proper should not be taken.
Where good cause is shown,
consideration will be given to extending the response
time.
Dated at Lisle, Illinois
this 5th day of April 1995
li
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