IR 05000315/1991003
| ML17328A903 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/12/1991 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17328A902 | List: |
| References | |
| 50-315-91-03, 50-315-91-3, NUDOCS 9102180037 | |
| Download: ML17328A903 (6) | |
Text
g U.
S.
NUCLEAR REGULATORY COMMISSION
REGION III
Report No.:
50-315/91003(DRS)
Docket No.:
50-315 License No.:
DPR-58 Licensee:
Indiana Michigan Power Company 1 Riverside Plaza Columbus, OH 43216 Facility Name D.
C.
Cook Nuclear Plant, Unit 1 Inspection At:
D.
C.
Cook Site, Bridgman, MI 49127 Inspection Conducted:
February 6-7, 1991 Inspector:
o87~
~K. D. Ward Date Approved By:
iM/~~
D.
H. Danielson, Chief Materials and Processes Section Date Ins ection Summar Ins ection on Februar 6-7 1991 Re ort No 50-315 91003 DRS Areas Ins ected:
Routine unannounced safety inspection of inservice inspection (ISI) activities including review of program (73051),
procedures (73052),
work activities (73753),
and data review (73755).
Results No violations or deviations were identified.
Based on the results of the inspection, the NRC inspector noted the following:
The licensee adequately demonstrated the ability to properly implement the ISI program, including the eddy current examinations of the steam generator tubes.
The licensee's staffing of the ISI group was adequate, and the personnel were very knowledgeable and conscientious.
Records were found to be complete and well maintained.
102180037 910212 PDR ADOCK 05000315 G
1.
Persons Contacted DETAILS American Electric Power Service Cor oration AEP Indiana Hichi an Power Com an I
- J. Droste, Engineering Superintendent
+J. Fitchok, ISI Coordinator U.
S. Nuclear Re ulator Commission NRC J.
Isom, Senior Resident Inspector
- D. Passehl, Resident Inspector The NRC inspector., also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the exit interview on February 7,
1991.
Inservice Ins ection ISI Unit 1 Review of Pro ram 73051 Westinghouse Electric Corporation (W), Southwest Research Institute (SWRI), and Indiana Michigan Power Company (I&M)
personnel performed the ISI in accordance with ASME Section XI, 1983 Edition, Summer 1983 Addenda.
The staff size was sufficient to ensure that the ISI work was adequately performed.
The licensee did not submit a request for relief from the ASME Code this outage.
The NRC inspector reviewed a Factory Mutual Engineering audit dated November 20, 1990, and other surveillance of ISI activities conducted by qualified personnel to verify compliance with the ISI program.
The ISI program was found to be in compliance with licensee commitments.
b.
Review of Procedures 73052 All applicable ISI procedures were approved by the Authorized Nuclear Inservice Inspector (ANII) and were reviewed by the NRC inspector.
The ultrasonic examination (UT) manual pulse echo detection instruments and transducers of various angles, sizes, and frequencies were used.
The ISI procedures were found to be in accordance with ASME Section V, 1983 Edition, Summer 1983 Addend c.
Data Review and 'Evaluation 73755 (1)
General The examination data was within the criteria as outlined in the applicable NDE procedures and ASME Code requirements.
The NRC inspector's review included examination of documents relative to NDE equipment, data, and evaluations.
(2)
Edd Current Examinations
~ET The Zetec MIZ-18A Data Acquisition and the Echoram Unix System were used to conduct the ET.
The results were as follows:
Steam Generator Tubes
~Plu ed Tubes Plugged Previousl ll
13
64
57
180 148 142 167 No tubes were sleeved this outage.
All generator tube plugs were Inconel
$/690.
of the new steam Work Activities 73753 The following recordable indications were observed:
(1)
SWRI personnel performing magnetic parti'cle examinations (MT) on pipe weld
$/1-FW-10-175 found a small linear surface indication in the 14" diameter, 3/4" thick pipe adjacent to the weld. It was determined that the linear indication was made by the pipe extrusion process in the fabrication shop.
In accordance with ASME Code,Section XI, Paragraph IWB-3514.2, UT is allowed to be performed on this area if a surface indication was identified by MT.
The UT found the indication to be acceptable in accordance with the Code.
(2)
SWRI personnel performing visual examinations (VT) on the reactor pressure vessel washers
$/10 and
$/13, found a recordable indication on each washer.
Washer
$/10 contained a small tool nick that was determined not to be detrimental to continued service.
Washer
$/13 had slight rust that was cleaned and neolubed and returned to service.
All the other washers were found to be -acceptable.
The NRC inspector reviewed the qualifications and certifications of all inspection personnel that were on site performing ISI to ensure conformance with SNT-TC-1 ensure conformance with SNT-TC-1A.
No violations or deviations were identified.
3.
"Exit Interview The NRC inspector met with site representatives (denoted in Paragraph 1)
at the conclusihn of the inspection on February 7, 1991.
The NRC inspector summarized the scope and findings of the inspection noted in this report.
The NRC inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the NRC inspector during the inspection.
The licensee did not identify any such documents/processes as proprietar 'I
'