IR 05000010/1975015
| ML20037B001 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/23/1975 |
| From: | Key W, Ledoux J, Lee E K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20037B000 | List: |
| References | |
| 50-010-75-15, 50-10-75-15, NUDOCS 8008280642 | |
| Download: ML20037B001 (6) | |
Text
.
.
)
- -.
.-
-
.
,
U. S. NUCLEAR REGULATORY COMMISSION j
OFFICE OF' INSPECTION AND ENFORCEMENT
. '
fs
REGION III
.
,
Report of Construction Inspect 1on IE Inspection Report No. 050-010/75-15
.
?
Licensee: Commonwealth Edison Company P.O. Box 767
Chicago, Illinois 60690
-
Dresden Nuclear Power Station, Unit 1 License No. DPR-2
Morris, Illinois Category:
C
.
Type of Licensec:
BWR (GE) - 200 MWe Type of Inspection:
Special, Announced
.
Dates of Inspection:
September 2, 25 and October 10, 1975
_
h$jf[ -
. /
/
f Principal Inspector:
E. W. K. Lee IS/*5//8
/
"
(Date)
,
.s
,
,a aps ' o
'
Accompanying Inspector:
W. J. Key
".
(September 25 and October 10, 1975)
(Date)
Other Accompanying Personnel: None. -
.
< >
'
'
/' #
/ p 7Q,s
.-
,.
/
>
Reviewed By:
J. C. LeDoux, Senior Reactor. Inspector Construction Engineering (Date)
,
,
e
%
8008280[VQ I"
.
.
.
.:
,
...
,-.
SUMMARY OF FINDINGS
.
gs
.
Inspection Summary
.
.
Inspection on September 2, 25 and October 10 (75-15):
Investigate pfpe crack in the six-inch cleanup dcmincralizer and unloading heat exchanger return line; review In-scevice Inspection (ISI) Program for this ISI, NDE procedures and personnel qualifications, material certification, and equipment calibration; review six-inch cicanup demineralizer and f
unloading return line repair procedure, welding procedure, NDE procedure, and observed cutting of the six-inch line.
.
Enforcement Items
.
Nonc identified.
.
Other Significant Items A.
Systems and Components s
The licensee discovered a crack in.the six-inch cleanup dcmineralizer and unloading heat exchanger return line.
Replacement of portion of the six-inch line and ISI are,in progress.
(Report Details,
.
~~
Paragraph 1)
,
_
B.
Facility Items 1.
Unresolved Matter - Documentary evidence to show that tapes used on, surfaces of stainicss steel have been evaluated and found
, acceptable was unavailable at the site.
(Report Details, Paragraph 2)
2.
Discrepancy between Table IS-251 of the 1971 edition of the ASME Beller and Pressurc Vessel (BP&V) code,Section XI and Table 4.6.1 of the Technical Specification, relative to
,
inspection requirement for Category M-2 valves.
(Report
Details, Paragraph 3)
C.
Managerial Items
.
None.
D.
Noncompliance Identified and Corrected by Licensec
None.
.
,
-2-
.
-
7..
.
-
,
-
- -- -
.
".
-
E.
Deviations
-
,
None.
-
F.
Status of Previously Reported Unresolved Items
.
..
'
Not applicable.
,
Management Interview A.
The following persons attended the management interview at the end of the inspection.
,
Commonwealth Edison Company (CE)
.
J. S. Abel, Administration Assistant B. B. Stephenson, Station Superintendent B.
Matters discussed and comments', on the part of management personnel, were as follows:
1.
The inspector stated that documentary evidence, to show that tapes used on surf aces of stainless steel have been evaluated and found acceptable, was,, unavailable at the site.
The licensee agrees to investigate. This matter remains unresolved pending review during*a subsequent" inspection.
(Report Details,
_
'
j Paragraph 2)
I 2.
The inspector stated that ISI requirement for Category M-2 valves, committed by the technical specification, appears to
,be different from ASME B&PV Code,Section XI.
The inspector further stated that this matter will be referred to IE:HQ and RL for resolution.
(Report Details, Paragraph 3)
3.
The inspector stated procedures and personnel qualifications, relative to ISI and repair of the six-inch line, have been
'
reviewed, and they appear t,o.be acceptable.
(Report Details, Paragraph 4)
!
i j
..
.
O l
d
l-3-
-
!
'
r'
.
- -
f.
!
,
..
-.r F
--,,b
.aume
.a
'
.
.
o.
.
.
,
!
".
REPORT DETAILS t
,-
-
.
-
l Persons Contacted
,,
l The following individuals, in addition to those listed under the Management Interview Section of this. report, were contacted during l
the inspection.
Commonwealth Edison Company (CE')
'
F. Highland, Cognizant Engineer'
~
'
-
l M. Terrell, Outage Planner
-
T. Watts, Technical Staff Supervisor R. C. Herbert, Technical Staff Engineer R. J. Harrison, Lead Engineer (Unit 1)
l Nuclear Services Corporation ('NSC)
-
i L. V. Bowne, Inspector - Nondestructive Testing J. E.-Hill, Inspector - Nondestructive Testing V. Lovelace, Inspector - Nondestructive Testing
.
Phillips Getschow (P-C)
'
..
-
.
M. Kelly, Site Quality Assurance Manager Results of Inspection
.
1.
The inspector was informed that a crack was discovered by the licensee on Monday, September 1, 1975, in the six-inch cicanup demineralizer and unloading heat exchanger return line of Loop A.
The crack is located at the heat affected zone of the pipe, near the thermal sleeve to pipe weld at the~ tie-in to the 18" special cast elbow of Loop B of the recirculation pump discharge line.
The crack is approximately one-inch long, and at an angle of 10-to-15 degrees to the weld joint. The cause of the crack has not been determined. The licensee is replacing the six-inch line up to the isolation valve (MO-122). Four field welds and six shop welds are p~lanned. The pertinen,t section of the failed pipe l
will be analyzed by the licensee's Operational Ana,1ysis Department.
i 2.
The inspector observed the two-part red stock identification tag
!
. vas taped onto a six-inch stainless steel cibow, using " Scotch 880 l
Filament Tape."
Upon questioning the licensee relative to the
-
'
.
O-4-b
.
.
...
-
,w.
--
> s
- -.
-
.
-
.
- *
suitability of using " Scotch 880 Filament Tape" directly on
-
.
'
stainicss steel surfaces, the licensee agreed to investigate.
This matter remains unresolved, pending review during a subsequent
-
-
inspection.
.
3.
Table IS-251 of the 1971 edition of the ASME B&PV Code, Section**
'
,
XI, requirca that the internal surface of onu, disassembled
valve in each of the Category M-2 groups of valves of the same
"
- constructural design, manufacturing method, manuf acturce, and r
performing similar functions in the system, be visually examined
'
Jur-.
during each inspection interval.
(An inspection interval for c.
Drendun Unit 1 is 3-1/3 years.) Furthermore, CE Iceter dated November 11, 1971, to Dr. Peter A. Morris, Director, Division of Reactor Licensing, stated, in part, that ".
. The number
...
of valves, manufacture, type, and function are as listed in Table 1.
Valves as noted are scheduled to be visually inspected
'
"
internally 1n 1973 and 1975..
...
.
Table 4.6.1 of the Technical $pecifications commits valves in twelve systems (ASME B&PV Code,Section XI, Category M-2) be examined once during an inspection interval, if they are disassembled for maintenance. Of those valves in the twelve systems, one valve in the primary steam and one check valve in the primary feedwater were inspected during a Fall 1,973 ISI, waiver for valves in four
-
systems were requested by the licensee on March 25, 1975, one four-inch valve in the cicanup syst'em is scheduled for inspection during
-
this ISI; valves in the remaining systems will not be inspected during this inspection interval unless they are disassembled for maintenance and maintenance on the remaining valves is not being planned. It appears that discrepancy exists between ASME Section XI gnd the Technical Specification.
The inspector stated this matter will be referred to IE:l!Q and RL for resolution.
,
4.
The inspector reviewed the following documents and determined them to be acceptabic and in accorda,nc,e with the applicable code requirements:
a.
CE Procedure No. NDT-C-2, Revision 9, dated January 2,1975,
" Ultrasonic Inspecticn of Pipe Welds."
b.
CE Procedure No. NDT-D-1, Revision 1, January 2, 1975, " Procedure i ce
-
, for Non-aqueous Red Dye Liquid Penetrant Examination of Reactor
'
.
rVessel Safe Ends."
'
.
.
we t-5-
-
.
e b
.
_ _
i
..
._7_______..
_. _ _ _.. _.. - _.
.
.
....
c.
Qualification of NSC's NDE personnel records.
-
,
(~-
d.
Material certification for UT couplant under Purchase Order
-
No. 1347 dated March 18, 1975.
_
_
~
e.
Developer material certification, batch No. SB014.
f.
Cleaner material certification, batch No. 5E003.
g.
Penetrant material certification, batch No. SE086.
I h.
Material certificate for six-inch, schedule 80 pipe with heat No. 180411.
-
.
i.
P-G Welding Procedure No. IA-MA-88, Revision 4, dated July 21, 1975.
.
J.
Superior Industrial X-Ray Company Radiographic Inspection Procedure'No. RT-1 dated April 7, 1975.
(This procedure has not been approved by CE).
k.
Two P-G welders' qualification records.
1.
Four Superior Industrial X-Ray Company ?!DE Level II (RT
-
and PT) personnel qualific,ation records.
-
m.
CE repair procedure attached to Work Repair No. 9052 for the six-inch cleanup demineralizer and unloading heat exchanger line, 5.
The inspector established that the UT electronic equipment (Serial No. 130-60-D) used for this ISI, indicated calibration was. current, and transducers and test blocks were in accordance with specifications.
6.
The inspector determined the setup of cutting equipment and the cutting operation to be acceptable.
. -
l l
.
.
I
,
'
!
'
-6-j l
-
I
,
F
.