IR 05000348/1980001
| ML19309C812 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/19/1980 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19309C805 | List: |
| References | |
| 50-348-80-01, 50-348-80-1, IEB-79-17, NUDOCS 8004090291 | |
| Download: ML19309C812 (4) | |
Text
'o,,
UNITED STATES
NUCLEAR REGULATORY COMMISSION
"
n (,
,E REGION 11
^#
101 MARIETTA ST N.W., SUITE 3100 W
o ATLANTA, GEORGIA 30303
FEB 211980 Report No. 50-348/80-01 Licensee: Alabama Power Company 600 North 18th Street Birmingham, Alabama 35202 Facility Name: Joseph M. Farley Plant, Unit 1 Docket No. 50-348 License No. NPF-2 Inspection at Farley Site near Dothan, Alabama
-
'
/,l
. /,/'
'
~
N. Ec
'.
<<. s u m.,-i (-
-
a f lA !.f,lf'y' *
.:
_)"
Inspector:
!
'
ogs -
Da'te'Si ned Approved by: c'
/}
O f[.
A. R. Herdt, Section Chief, RC&ES Branch D4te Signed SUMMARY Inspection on January 30-31, 1980 Areas Inspected This routine, announced inspection involved 14 inspector-hours on site in the areas and activities relative to IE Bulletin 79-17 (Pipe cracks in stagnant borated water systems at PWR plants).
Results
,
No items of noncompliance or deviations were identified.
8004090 2R /
... -.-- j
.
<
DETAILS 1.
Persons Contacted Licensee Employees
- J. H. Woodard, Assistant Plant Manager
- H. N. Morey, Operation's Superintendent
- K. W. McCracken, Technical Superintendent
- L. M. Stinson, Systems Performance Supervisor
- J. W. Kale, QA Engineer
- R. M. Coleman, General Plant Engineer I
- G. S. Waymire, Jr., Engineer
,
Other Organizations Southern Company Services (SCS)
- E. R. Burns, Engineer II Mechanical Design Nuclear Section Westinghouse Electric Corporation, Nuclear Services Division (W)
G. E. Conrad, Coordinator NRC Resident Inspector W. H. Bradford
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 31, 1980, with those persons indicated in Paragraph 1 above. The inspector identified areas inspected which included observation of NDE activities review of related pro-cedures and records.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were 1ot identified during this inspection.
5.
IE Bulletin No. 79-17 Pipe Cracks in Stagnant Borated Water Systems at PWR Plants This inspection ef fort was performed in order to observe surface and volu-metric examinations (Visual, Liquid Penetrant and Ultrasonic) on selected welds being performed in response to IE Bulletin 79-17.
Administrative
.
-2-
controls and the programatic aspects of this activity were reviewed during an earlier inspection that was documented in IE:RII Report 50-348/79-46.
The work was performed by W under vendor order number BM-26499-AR4. The ultrasonic examination procedure used for this program was demonstrated successfully on Three Mile Island (TMI) weld specimens with known inter-gramular stress corrosion crack (ISCC) indications in the heat affected zone (HAZ). This demonstration was documented on W memorandum QA-79-CDC-242, dated September 25, 1979.
Procedures used to perform surface and visual examinations were taken from the inservice inspection program manual which complies with ASME Code Sections V and XI (74S75) requirement =. The proce-dures under discussion are as follows:
NSD-ISI-90, Rev. I
" Manual Ultrasonic Procedures for Inves-Ligating for Presence of Intergranular Corrosion".
.
NSD-ISI-8, Rev. 7, Amendment 1 " Visual Examination Procedure".
NSD-ISI-11, Rev. 9, Amendment 3" Liquid Penetrant Examination Procedure".
Weld selection was made by SCS and the selection list forwarded to RII for review on November 27, 1979. APC0 onsite personnel and the SCS cognizant engineer provided technical support and coordination for the program. QA surveillance of field activities was provided by APCO's QA group. Welds observed during surface and volumetric examination were as follows:
Weld No.
System Dwg./ ISO Size Ultrasonic Examinations (UT)
High Head SCC-7 4" x.53" Safety Injection (HHSI)
137 Residual Heat SCC-23 8" x.322" Removal (RHR)
138 RHR SCC-23 8" x.322" 139 RHR SCC-23 8" x.322" Liquid Penetrant Examinations (PT)
2, 3, 4, RHR SCC-6 3" x.216" 5 and 6 Linear type indications were noted on the pipe side of the HAZ in welds 3 and 6 above.
These were removed with light grinding and subsequent PT i
showed the areas in question to be clear.
All examinations were performed in accordance with procedural requirements by personnel who appeared to be adequately qualified to perform their assigned tasks.
Equipment, material and personnel certifications were found to be in order. Records of completed examinations were reviewed for
)
completness and accuracy.
,
{
I
. - -
.
-3-Within the areas inspected no items of noncompliance or deviations were identified.
,
&