ML17317B500
| ML17317B500 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/28/1979 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17317B498 | List: |
| References | |
| 50-315-79-10, 50-316-79-07, 50-316-79-7, NUDOCS 7908290529 | |
| Download: ML17317B500 (5) | |
See also: IR 05000315/1979010
Text
U.S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-315/79-10;
50-316/79-07
Docket No. 50-315;
50-316
License
No. DPR-58;
Iicensee:
American Electric Power Service
Corporation
and Michigan Power
Company
2 Broadway
New York, NY
10004
Facility Name:
D.
C.
Cook Nuclear Power Plant, Units
1 and
2
Inspection At:
D.
C.
Cook Site,
Bridgman, Michigan
Inspection
Conducted:
May 21-24,
1979
Inspector:
W. J.
Key
Approved By:
D.
. Danielson,
Chief
Engineering Support Section
Ins ection Summar
Ins ection on
Ma
21-24
1979
(Re ort No. 50-315/79-10
50-316/79-07)
piping.
Observation of feedwater pipe crack repair activities.
The
inspection involved
a total of 28 inspector-hours
on site by one
NRC
inspector.
Results:
Of the two areas
inspected,
no apparent
items of noncompliance
or deviations
were identified in one area;
one apparent
item of noncom-
pliance
was identified in one area (infraction - failure to .develop
repair procedures prior to starting work - Paragraph
1).
DETAILS
Persons
Contacted
and Michi an Power
Com an
(IBM)
+D. Shaller, Plant Manager
- B. Svensson,
Assistant Plant Manager
- J. Stietzel, Quality Assurance
Supervisor
G. Montenegro, Quality Control Supervisor
H. Bolinger, Assistant ISI Coordinator
American Electric Power Service
Cor oration
(AEP)
J. Jensen,
NSSS Engineer
D. Patience,
Metallurgist
Michi an De artment of Labor
A. Kozlowski, Boiler Division Supervisor
- Denotes those present at the exit interview.
Functional or Pro
ram Areas Ins ected
1.
S stem Pi in
Cracks - Units
1 and
2
Due to unidentified nonradioactive
leakage of about
3
GPM into the
containment building, Unit 2 was shut
down on May 19,
1979.
The
licensee's
inspection revealed
through wall cracking in the 16" 90
elbow on feedwater
system loops
1 and 4.
The cracking is circumferential
and up stream of the weld joining the elbow to the steam generator
nozzle.
On May 21,
1979, the inspector arrived on site to examine the cracking
and to review the licensee's
repair activities.
The inspector
observed
excavation of the defective areas in process;
excavation
had started
on May 20,
1979.
A review of the licensee's
activities
to date indicated that the extent
and cause of cracking had not been
determined
and procedures
to adequately
control the repair activities
had not been established
as required by Technical Specification 6.8.1
and
This is an item of noncompliance identified
in Appendix A.
(316/79-07-01)
The licensee
stopped excavation of the defective areas
and developed
special procedures
for the repair activities.
- 2-
Additional excavation of the defective areas failed to clear the
defects.
The licensee
then performed radiographic
examination of
the Unit 2 loops
1 and
4 affected
areas
and revealed
more extensive
cracking.
The affected areas
of loops
2 and
3 were radiographed.
The licensee
then radiographically
examined the
same
area
on three
loops of Unit 1 and revealed
cracking as in Unit 2.
Due to water
in loop 4, this area
could not be examined by the end of this inspection.
The inspector
reviewed the radiographs,
confirming that all were
cracked.
Limited ultrasonic examination
was performed by Southwest
Research
Institute
(SWRI) with confirmed reflectors
from the cracked
area of
the elbow.
A boat sample
was
removed from Unit 1, loop 3, for
analysis, half was sent to Chicago Service Laboratory and half was
sent to Westinghouse.
Other samples
were taken from Unit 1, loop 2,
Unit 2, loops 1, 2, 3,
and 4.
The
NRC was supplied with a ring
sample
from Unit 2, loop 2, for independent
analysis.
Except
as noted,
no items of noncompliance
or deviations
were identified.
2.
Review of As Build Documentation
The inspector
reviewed the original installation documentation of
fit-up and welding of the elbow to steam generator
nozzles.
Documentation indicates that installation was in accordance
with
procedures,
and the radiographic film of welds
shows
them to meet
code acceptance
requirements.
3.
Review of Re air Procedures
The inspector
reviewed the following procedures
that are to be used
for feedwater piping repair activities.
a.
Procedure
No.
12 MHP-SP-001, Revision 0, dated
May 28,
1979,
titled "Special Procedure for Steam Generator
Feedwater Inlet
Nozzle Elbow Repair."
This procedure will be revised
as needed
when more analysis information is generated.
b.
Instruction No. PMI-1010, Revision 3, dated August 30,
1976,
titled "Organization and Responsibilities
of AEPSC and
IBM
Power Companies."
c.
Welding Procedure
No. 23.88,
23 '8a,
and 1.3e.
No items of noncompliance
or deviations
were identified.
a
4.
Exit Interview
The inspector
met with licensee
representatives
(denoted in the
Persons
Contacted
paragraph)
at the conclusion of the inspection
on
May 24,
1979.
The inspector
summarized
the scope
and findings of
the inspection,
and discussed,
in detail, the item of noncompliance
identified in Appendix A of this report.
4
1 ~
a