IR 05000266/1981021
| ML20033C522 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/13/1981 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20033C515 | List: |
| References | |
| 50-266-81-21, NUDOCS 8112030352 | |
| Download: ML20033C522 (7) | |
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'U.S. NUCLEAR REGULATORY COMMISSION REGION III-Report No. 50-266/81-21 Docket No._50-266 License No.:DPR-24
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Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee,WI.p3201 Facility Name: Point Beach. Nuclear Plant, Unit 1 Inspection At: Point Beach Site, Two Creeks, WI Inspection Conducted: -October 28,'1981 b".If// stav
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Inspector:
K D. Ward
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Approved By:
D. H. Danielson, Chief
'I Materials & Processes Section Inspection Summary Inspection on October 28, 1981 (Report No. 50-266/81-21)
Areas Inspected: Review oc inservice inspection (ISI) procedures, work activities, nondestructive examination (NDE) personnel certifications and data. The inspection involved a total of 6 inspector-hours onsite by one NRC inspector.
Results: ' No items of noncompliance or deviations were identified.
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t DETAILS Persons Contacted Wisconsin Electric Power Company (WEPCo)
- G. Reed, Manager Nuclear Operations
- R.
Link, Superintendent Engineer, Quality and Regulatory
- J.
Schweitzer, ISI Engineer G. Sherwood, Nuclear Plant Engineer Hartford Steam Boiler Engineering and Insurance Company F. Roose, Authorized Nuclear Inservice Inspector (ANII)
The inspector also contacted and interviewed othe'r licensee and contractor employees.
- Denotes those present at the exit interview.
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Functional or Program Areas Inspected 1.
General WEPCo requested Westinghouse Electric Corporation, Nuclear Service Division to perform the eddy current examination (ET) on the steam generator (SG) tubes, also Southwest Reasearth Institute and WEPCo Quality Assurance Department to perform the ISI in accordance with ASME Section XI, 1974 Edition, Summer 1975 Addenda for the closeout of Unit 1 first 10-year ISI requirements, and ASME Section XI, 1977 Edition, Summer 1979 Addenda or items pertaining to the first outage of the second 10-year interval.
During.ats outage, inservice mechanized radiographic and remote visual examinations will be performed of the following girth welds of the Loop B Reactor Coolant Pump (RCP), Unit I which will satisfy the applicable requirements of the following documents:
Girth Welds A-Weld (Top) - 12-5/8 inches below flange seal surface B-Weld (Middle) - 44 1/2 inches below flange seal surface C-Weld (Bottom) - 74 inches below flange seal surface Applicable Codes ASME Section XI, 1974 Edition, Summer 1975 Addenda, as pertains
- .o RCP visual examination.
ASME Section V, 1974 Edition, Summer 1975, Addenda for visual examination requirements.
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ASME Section XI, 1977 Edition, Summer 1979, Addenda, as pertains to RCP volumetric examinations.
ASME Section V, 1977 Edition, Summer 1979 Addenda for radiographic examination requirements.
The examinations will be performed by Southwest Research Institute (SwRI) personnel using the Electric Power Research Institute (EPRI)
Miniature Accelerator X-ray device (MINAC) system. Onsite consultation and assistance will be provided via EPRI contract by staff members of Rochester Gas and Electric' Company (RG&E), Schonherg Radiation Corporation,.and J. A. Jones Applied Research Company. Film processing services will be provided by Midwest Inspection Service, Limited,-under the cognizance of SwRI.
The Point Beach RCP is a Westinghouse Model 93 design. RG&E has performed MINAC examinations of a Model 93 pump at their Ginna Nuclear Power Station. The examination plan was prepared utilizing the experi-ence gained at Ginna and is based on the bes; information available at the time of writing. As-built conditions at Point Beach deviating from the parameters specified in the plan will be incorporated into the plan on site. Such information will be entered into the log. sheets and data
- sheets to serve as permanent records supplementing the radiographs and video tapes generated during the examinations.
The MINAC system consists of a portable linear accelerator capable of generating a 20-degree'X-ray cone with an output of approximately 90 R/ minute at 1 meter at an energy level of 3.2 MEV. The device which was developed by Schonberg Radiation Corporation is positioned inside the RCP by a remotely operated manipulator device developed by RG&E.
Prior to performance of the examinations described in this plan, Wisconsin Electric Power Company (WEPCo) and SwRI personnel attended a comprehensive training course utilizing the MINAC system on a full-scale Model 93 oump mock-up conducted by the J. A. Jones Applied Research Compan y at the EPRI NLE Center.
The casing welds and 1/2 inch of base metal will be examined along its entire weld length by positioning the MINAC head for 28 individual exposures for weld A (top weld), 29 exposures for weld B (middle), and 33 expcsures for weld C (bottom).
The MINAC/ Manipulator System is equipped with high-intensity lights, a high-resolution video camera mounted on the device, and monitors and video recording equipment located in the control consoles. The system has image enhancement capabilities and will be utilized to perform visual examinations of the RCP pressure boundary internal surfaces following each series of radiographic exposures. A certi-fied visual examiner will view the monitor during these scans, and the scans will be recorded on video tape. Any relevant indications will be recorded on visual examination data sheets. Any limitations to the visual examination due to pump or device configurations will
.Uso be identified on the visual examination data sheets.
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e 2.
Program and Procedure Review The inspector reviewed the following program and procedures:
Project Plan for the 1981 Inservice Examination,. Unit 1,
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81-WEP-PBH-1-1-0.
WEPCo, Qualification and Training of NDE Personnel, NED-3,
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Revision 2.
WEPCo, Visual Dye Penetrant Inspection of Weldments, NDE-400,
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Revision 0.
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WEPCo, Liquid Penetrant Examination Record, NDE-Form 450.1,
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Revision 0.
WEPCo, Visible Dye Penetrant Inspection of Reactor Coolant Pump
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Flywheel, NDE-450.1, Revision 1.
WEPCo, Visible Dye Penetrant Inspection Method, NDE-451,
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Revision 1.
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WEPCo, Visual Examination of Nuclear Power Plant Components,
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NDE-750, Revision 0.
WEPCo, Operations Group System and Component Section XI Inservice
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Hydrostatis Testing, PBNP 4.12.19, Revision 0.
W, Installation and Removal of Temporary Nozzle Covers, MRS 2.2.2,
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GEN-2, Revision 3.
W, Mechancial Plugging of Steam Generator Tubing & Tube Holes,
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MRS 2.3.2, GEN-13, Revision 0.
W, Ultrasonic Sludge Depth Measurement in Steam Generator,
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SP 2.4.2, GEN-7, Revision 0.
W, Eddy Current Inspection of Steam Generator Tubing, Preservice
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and Inservice, MRS 2.4.2, GEN-18, Revision 2.
W, Installation and Removal of Eddy Current Positioning Devices,
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MRS 2.4.2, GEN-19, Revicion 0.
W, Installation and Removal of Steam Generator Tube Identification
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Templates, MRS 2.4.2, GEN-26, Revision 0.
W, Tube / Hole Plugging Using Manual Gas Tungsten Arc Welding
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NPT-23, Revision 5.
W, Explosive Plug Repair Using Manuai Gas Tungsten Arc Welding,
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NPT-27, Revision 3.
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SWRI, Recordira Indications During Ultrasonic Examinations of
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Pressure Vessel Welds, IX-FE-118-0.
SWRI, Measuring and Recording Search Unit During Ultrasonic
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Examinations of Pressure Vessel Welds, IX-FE 219-0.
SWRI, Onsite NDT Records Control X-FE-101-1.
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SWRI, Data Storage and Retrieval, XVII-AS-101-1.
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SWRI, Liquid Penetrant Examination Color Contrast Method,
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NDT-200-1, Revision 5.
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SWRI, Dry Power Magnetic Particle Examination, NDT-300-1,
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Ravision 20.
SWRI, Fluorescent Magnetic Particle Examination, NDT-300-2,
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Revision 29.
SWRI, Radiographic Examination of Nuclear Power Plant Components
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Utilizing the "Minac" System, NDT-400-4, Revision 0.
SWRI, Manual Ultrasonic Examination of Pressure Vessel Components
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and Vessel Welds, NDT-700-5, Revision 5.
SWRI, Mechanized Ultrasonic Examination of Ferritic Vessels
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Greater Than 2 inches in Thickness, NDT-700-6, Revision 9.
SWRI, Visual Examination of Nuclear Reactor Components by Direct
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or Remote Viewing, NDT-900-1, Revision 48.
SWPI, Visual Examination of Support Members and Structures for
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Piping, Valves, and Pumps by Direct or Remote Viewing, NDI-900-4, Revision 22.
SWRI, Remote Visual Examination Utilizing the Minac System,
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NDT-900-8, Revision 0.
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No items of noncompliance or deviations were identified.
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Material and Equipment Certification The inspector reviawed the certification documents relative to the following items:
Ultrasonic instruments, calibration blocks, transducers and a.
couplant b.
Liquid penetrant, magnaflux materials, penetrant, cleaner and developer c.
Eddy current, equipment.
No items of noncompliance or deviations were identified.
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4.
NDE Personnel Certifications The inspector reviewed the following NDE personnel certifications in accordance with SNT-TC-1A, 1975 Edition:
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Name F1 R. Cottrell I.
J. Mills-I G. Miller I
R. Hazen
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II J. Zevchak I
SWRI Name'
PT VT UT L. Reaves II II II R. Williams I
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I R. Gabehart I
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II-J. Smith I
II R. Niemeyer II II II B. Roberds I
P. Turner I
I S. Todd II II D. Gaines I
WEPC0 Name PT VT UT R. Vooren III II R. Rettmann II III No items of noncompliance r,r deviations were identified.
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Observation of Work Activities The inspector observed the work and had discussions with personnel durin review of the following activities. These observations e
included, performance of the examinations, and the documentation.
Eddy current examination of several tubes in steam generator
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"A" and "B" Visual examination of valve 720 bolting RAR Return; # 4 and # 7
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pipe restraints AC-6-51-1002 No items of noncompliance or deviations were identified.
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6.
Review of Data Report and Audits The inspector reviewed data reports and determined-that they demon-strated that the QA/QC requirements were met.
WEPCo audits of SWRI activities were reviewed.
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No items of noncompliance or deviations were identified.
Exit Interview the inspector met with site representatives (denoted in Persons Contacted
,aragraph) at the conclusi'on of the inspection. Tha inspector summarized the scope and findings of the inspection noted in this report.
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