IR 05000301/1981009
| ML19352A817 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/19/1981 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19352A816 | List: |
| References | |
| 50-301-81-09, 50-301-81-9, NUDOCS 8106020178 | |
| Download: ML19352A817 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INVESTIGATION AND ENFORCEffENT
REGION III
Report No. 50-301/81-09 Docket No. 50-301 License No. DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53201 Facility Name: Point Beach Nuclear Plant, Unit 2 Inspection At: Point Beach Site, Two Creeks, WI Inspection Conducted: April 22, 28, and May 4, 1981 Inspector:
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6//f/O Approved By:
D. H. Danielson, Chief Materials & Processes Section Inspection Summary Inspection on April 22, 28, and May 4, 1981 (Report No. 50-301/81-09 Areas Inspected: Review of inservice inspection (ISI) procedures, work activities, ondestructive examination (NDE) personnel certifications and data. This inspection involved a total of 16 inspection-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Wisconsin Electric Power Company (WEPCo)
- G. Reed, Manager Nuclear Operations
- R. Link, Superintendent Engineer, Quality and Regulatory
- J. Schweitzer, ISI Engineer
- F. Leman, Office Supervisor M. Keehan, Nuclear Plant Engineer G. Sherwood, Nuclear Plant Engineer M. Logan, Nuclear Plant Engineer Westinghouse Electric Corporation (W)
V. Burke, Site Coordinator Southwest Research Institute (SWRI)
R. Weber, Project Engineer Hartford Steam Boiler Engineering and Insurance Company F. Rooae, Authorized Nuclear Inspector (ANII)
The inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the exit interview.
Functional or Program Areas Inspected 1.
General a.
WEPCo requested Westinghouse Electric Corporation, Nuclear Service Division to perform the eddy current examination (ET)
on the steam generator (SG) tubes, also Southwest Research Institute and WEPCo Quality Assurance Department to perform the ISI in accordance with ASME Section XI, 1974 Edition Summer 1975 Addenda.
b.
This is the seventh outage of the first ten year plan.
2.
Procedure Review The inspector reviewed the following procedures:
W, Dye Penetrant Examination 843503A, Revision 11,
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September 19, 1979.
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W, Steam Generator Tubesheet Sludge Lancing, MRS 2.2.2
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GEN-1, Revision 1, Marca 4, 1974.
W, Weld Repair of Steam Generator Tubes / Plugs, MRS 2.3.2
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GEN-6, Revision 0, January 11, 1979.
W, Explosive Plug Removal, MRS 2.3.2 GEN-7, Revision 2
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February 27, 1980.
W, Explosive Plugging of Steam Generator Tubes, MRS 2.3.2
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GEN-9, Revision 2, September 31, 1979.
W, Transportation, Storage, and Disposition of Explosives,
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MRS 2.3.2 GEN-11, Revision 2, March 5, 1980.
W, Steam Generator Tube Removal (Series 44 and 51) MRS 2.3.2
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GEN-12, Revision 0, December 17, 1979.
W, Positive Identification of Steam Generator tubes by
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Eddy Current Inspection, MRS 2.4.2 GEN-5, Revis'.on 1, December 17, 1974.
W, Eddy Current Inspection of Steam Generator Tubes, MRS 2.4.2
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GEN-9, Revision 5, October 17, 1974.
W, Eddy Current Inspection of Steam Generator Tubes Hand
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Probing, MRS 2.4.2 GEN-11, Revision 0, August 1, 1975.
l SWRI, Measuring and Recording Search Unit Location and Maximum
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Signal Amplitude Data During Ultrasonic Weld Examinations, 1X-FE-104-2, March, 1978.
SWRI, Recording Data from Direct Visual Liquid Penetrant and
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Magnetic Particle Examination of Welds, IX-FE-105-0, September, 1978.
SWRI, Recording Data from Direct Visual, Liquid Penetrant,
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and Magnetic Particle Examination, IX-FE-116-0, July, 1980.
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SWRI, Recording Indications from Ligaments, Bolting, and
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Piping Weld Examination, IX-FE-117-0, August, 1980.
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SWRI, Measuring and Recording Search Unit During Ultrasonic
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Examinations of Pressure Vessel Welds, IX-FE-119-0, January, 1981.
SWRI, Onsite NDT Records Control X-FE-101-1, June,1980.
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SWRI, Control of Nuclear Inspection Equipment and Materials,
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XIII-AG-101-1, April, 1980.
SWRI, Data Storage and Retrieval, XVII-AG-101-1, January,1981.
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WEPCo, Manual Ultrasonic Examination Vessel to Nozzles, NDE:
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155, Revision 0, April 10, 1981.
WEPCo, Visible Dye Penetrant Inspection of Reactor Coolant
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Pump Flywheel, NDE: 450, Revision 1, March 3, 1981.
WEPCo, Visible Dye Penetrant Inspection of Weldments, NDE:
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451, Revision 0, April 6, 1981.
No items of noncompliance or deviations were identified.
3.
Material and Equipment Certification l
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following items:
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Ultrasonic' instruments, calibration blocks, transducers and I
couplant.
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b.
Liquid penetrant, Magnaflux materials, penetrant, cleaner and developar.
c.
Eddy current, equipment.
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No items of noncompliance or deviations were identified.
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I 4.
NDE Personnel Certifications
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The inspector reviewed the following NDE personnel certifications in accordance with SNT-TC-1A, 1975 Edition:
WEPCo W
Name MT PT UT Name ET J. Rettmann III III III J. Chapla II R. Ver Vooren III III I
G. Testa I
E. Hamrock I
V. Burke I
G. Miller I
SWRI Name MT PT UT VT T. Trude I
I II R. Forman I
II II II R. Ries I
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L. Villa I
II II II R. Williams I
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I No items of noncompliance or deviations were identified.
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5.
Observation of Work Activities The inspector observed the work and had discussions with personnel during review of the following activities. These observations included calibrations, performance of the examinations and the documentation, Ultrasonic examination of circumferential weld, upper head a.
to upper shell on pressurizer, b.
Eddy current examination of several tubes in steam generator "B."
No items of noncompliance or deviations were identified.
6.
Review of Data Reports and Audits The inspector reviewed data reports demonstrating that the
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QA/QC requirements were met also WEPCo audits of W and SWRI.
Approximately 75% of the tubes in SG "A" were ET and approxi-mately 99% of the tubes in SG
"B" were ET.
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The following are SG tubes that were plugged during this outage in Unit 2:
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"A" Steam Generator Inlet
"B" Steam Generator Inlet Row Column
% Through Wall Row Column
% Through Wall-
22
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60
24
7
66
24
6
41
29
6
41
31
6
46
33
6
46
39
14
46
41
22
46
41
24
46 l
41
26
41
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43
26
41
44
22
44
44
15
54
44
9
53
44
6
46
45
8
50
45
23
47
49
25
42 i
62
19
46
71
17
41
73
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s Tube row 15, column 73 was removed and will be metallurgically examined by W for information only.
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No items of noncompliance or deviations were identified.
Exit Interview The inspector met with site representatives (denoted in Persons Contacted Paragraph) at-the conclusion of the inspection. The inspector summarized
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the scope and findings of the inspection noted in this report.
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