IR 05000316/1981027
| ML17319B076 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/27/1981 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17319B075 | List: |
| References | |
| 50-316-81-27, NUDOCS 8111090684 | |
| Download: ML17319B076 (5) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-316/81-27 Docket No. 50-316 License No. DRP-74 Iicensee:
American Electric Power Service Corporation Indiana 8 Michigan Power Company 2 Broadway New York, NY 10004 Facility Name:
D.
C.
Cook Nuclear Plant, Unit 2 Inspection At:
D.
C.
Cook Site, Bridgman, MI Inspection Conducted:
October 15-16, 1981 Inspector:
W. J.
Key g~ aZ /I Approved By:= b.H. Danielson, Chief Materials and Processes Section jd P7 d-)
Ins ection Summar Ins ection on October 15-16 1981 (Re ort No. 50-316/81-27)
equipment certification and personnel certifications.
This inspection in-volved a total of 12 inspector-hours by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
Siii090684 811028 PDR ADOCK 05000316
DETAILS Persons Contacted Indiana and Michi an Power Com an
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L. Townley, Assistant Plant Manager A. Svensson, Assistant Plant Manager F. Stietzel, QA Supervisor L. Dudding, Maintenance Superintendent H. Bolinger, ISI Coordinator LE Otte, Assistant ISI Coordinator Functional or Pro ram Areas Examined 1.
Procedure Review The following Westinghouse eddy current examination procedures were reviewed for conformance to NRC and ASME Code requirements.
MRS 2.2.2 Gen-2:
Installation and Removal of Temporary Nozzle Covers.
MRS 2.4.2 Gen-19:
Installation and Removal of Eddy Current Positioning Devices.
MRS 2.4.2 Gen-23:
Multi-Frequency Eddy Current Inspection of Steam Generator Tubing Pre and Inservice.
MRS 2.3.2 Gen-13:
Plugging Procedure.
MRS 2.2.2 Gen-6:
Post-Activity Sign-Off for Area Cleanliness.
No items of noncompliance or deviations were identified.
2.
Personnel Certification Review The following personnel records were reviewed for qualification in accordance with NRC and ASME Code requirements.
ET D. R. Francis R. P. Hazen J. E. Mills J.
M. Zevchak R. H. Ingraham IIIIIIII Zetec E. J.
Hako ET IIA No items of noncompliance or deviations were identifie N
Material and E ui ment Certifications The following equipment was examined for certification and calibration requirements.
MIZ 12, Display Module - A/N-061/019 Vector Analyzer III Module - A/N-006 Oscilloscope S/N-B133650 M1Z-12 Mixer Module A/N-161/160 In-line Standards S/N-0101.I-32-W Absolute Standard, Heat No. 7735, gR No.
1335-7 4.
Documentation Review During a pressure test of steam generator 2-1, it was noted that water was leaking around row 1, column 79 tube.
On October, 8,'981, a 3x8 grid of tubes in rows 1, 2, and 3, columns 75 thru 83 were eddy current examined.
This examination did not detect a defect in the tube in row 2, column 79, indicating that the tube was leaking through a circumferential crack in the tube.
On October 10, 1981, all tubes in row 2 were eddy current examined.
Westinghouse and Zetec recommended plugging the tube in row 74 based on data collected from the Trogan Nuclear Plant.
The following tubes in steam generator 2-1 were plugged.
Row
Column 74, 78, and
The following inconel 600 plugs from heat number NX 1989 were used to plug the tubes.
Plug S/N 8563-8564-8567-8565-8566-8568-cold leg cold leg cold leg hot leg hot leg hot leg No items of noncompliance or deviations were identified.
-3-
5.
Exit Interview The inspector met with licensee representatives (denoted under Persons Contacted)
at the conclusion of the inspection on October 16, 1981.
The inspector summarized the purpose and findings of the inspection.