IR 05000266/1985008

Insp Repts 50-266/85-08 & 50-301/85-08 on 850429-30.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp Procedures,Work Activities,Ndes,Personnel Certification & Split Pin Replacement

ML20128B069
Person / Time
Site:	Point Beach
Issue date:	06/17/1985
From:	Danielson D, David Jones NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20128B002	List: IR 05000266/1985008 ML20128B000
References
50-266-85-08, 50-266-85-8, 50-301-85-08, 50-301-85-8, IEB-78-12, NUDOCS 8507030113
Download: ML20128B069 (6)

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I U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-266/85008(DRS); 50-301/85008(DRS)

Docket Nos. 50-266; 50-301 Licenses No. OPR-24; DPR-27 Licensee: Wisconsin Electric Power Company 1 231 West Michigan Milwaukee, WI 53203 ( Facility Name: Point Beach Nuclear Plant, Units 1 and 2 l

l Inspection At: Point Beach Site, Two Creeks, WI Inspection Conducted: April 29-30 and June 6, 1985 l

l Inspector: . Jones 6 /7 85 Date/

Approved By:

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D. H. Danielson, Chief C l

l Materials and Processes Section Datd l

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Inspection Summary l Inspection on April 29-30 and June 6, 1985 (Reports No. 50-266/85008(DRS); i 50-301/85008(DRS)) l Areas Inspected: Routine, unannounced safety inspection to review inservice inspection (ISI) procedures, work activities, nondestructive examinations (NDE), personnel certifications; and split pin replacement. The inspection involved a total of 14 inspector-hours onsite and 16 inspector-hours offsite, by one NRC inspecto Results: No violations or deviations were identifie gDR ADOCK 05000266 PDR

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DETAILS Persons Contacted Wisconsin Electric Power Company (WEPCo)

• J. Zach, Manager P8NP

• J. Knorr, Regulatory Engineer

• R. Link, Superintendent, Engineering, Quality and Regulatory

• Pullins, ISI Engineer 8. Falk, Split Pin Replacement Site Coordinator J. Schweitzer, Mechanical Maintenance Engineer

• F. Flentje, Supervisor Staff Services Southwest Research Institute (SWRI)

V. Morton, Supervisor NDE Field Services 8. Weiss, Inspection Engineer

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Westinghouse (W)

G. Ellis, Split Pin Replacement Site Coordinator The inspector also contacted and interviewed other licensee and contractor employee * Denotes taose present at the exit intervie . ' Licensee Action On IE Bulletins (Closed) IE Bulletin 78-12 (266/78-12-88, 266/78-12-18, 266/78-12-28):

Atypical weld material in reactor pressure vessel welds. In compliance with the subject bulletins, the ifcensee and his supplier (Babcock and Wilcox) have submitted to the NRC the required information. The NRC reviewed the final response dated July 6, 1979 and found it acceptabl This item is considered close . Licensee Action on Previous Inspection Findings I (Closed) Unresolved Item (266/84-12-01): Implementation and adequacy of valve shaft examination The licensee removed and inspected (hardness, liquid penetrant, and visual) the Unit 1 main steam stop (2017, 2018) and nonreturn (2017A, 2018A) valve shafts. One main steam stop valve shaft (2018) exhibited cracking beneath the disk arm shaft, at the ends of two key seats, approximately 1/2" in length and 5/16" in depth. The hardness checks on the cracked shaft indicated harder areas than the other three shafts. It was speculated that the combination of hard areas in the shaft and an incident involving the wiping shut of the valve induced the crackin .

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The cracked valve shaft was replace Future incidents of a main steam stop valve wiping shut will initiate an inspection of the valve shaft for damage. The inspector considers this corrective action acceptabl This item is close . Inservice Inspection, Unit 1 General Information This is the fourth outage of the second ten year plan. Westinghouse Electrical Corporation (W), Nuclear Service Division performed the Eddy Current Examination (ET) on the steam generator tubes, Southwest Research Institute (SWRI) and WEPCo quality assurance department performed the ISI in accordance with ASME Section XI, 1977 Edition, Summer 1979 addend Eddy Current Examination was performed on steam generators A and B and no tubes were required to be plugge Program / Procedure Review

The inspector reviewed the following program / procedures:

. WEPCo, Visible Dye Penetrant Inspection of Weldment,

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NDE-451, Revision 3

. WEPCo, Visual Examination of Nuclear Power Plant Components, NDE-750, Revision 5

. WEPCo, Magnetic Particle Examination Dry Powder Yoke Method, NDE-350, Revision 3

. W, Installation and Removal of Temporary Nozzle Covers, MRS 2.2.2, GEN-2, Revision 6

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. W, Installation and Removal of Eddy Current Single Position Fixture W Design, MRS 2.4.2, GEN-22, Revision 1

. W, Multi-Frequency Eddy Current Inspection of Heat Exchanger Tubing - Preservice and Inservice, MRS 2.4.2, GEN-23, Revision 5

. W, Installation and Removal of Steam Generator Tube Identification Templates, MRS 2.4.2, GEN-26, Revision 3

. W, Control of Field Service Activities, OPR-610-3, Revision 3

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. SWRI, Project Plan for the 1985 Inservice Examination of Point Beach Nuclear Plant, Unit 1, 85-WEP-PBH-1-1-0, Revision 0, April 1985

. SWRI, Onsite NDE Records Control, X-FE-101-2

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. SWRI, Deviations to Nuclear Projects Operating Procedures, IX-FE-101-3

. SWRI, Weld Joint Identification Marking on Nuclear Power Plant Piping, IX-FE-103-2

. SWRI, Recording Indications During Ultrasonic Examinations of Pressure Vessel Welds, IX-FE-118-1

. SWRI, Recording Data From Direct Visual, Liquid Penetrant, and Magnetic Particle Examination, IX-FE-116-0, Change 4

. SWRI, Recording Indications from Ligaments, Bolting, Piping and ;

Vessel Weld Examinations, IX-FE-117-3

. SWRI, Control of Nuclear Inspection Equipment and Materials, XIII-AG-101-2

. SWRI, Data Storage and Retrieval, XVII-AG-101-1, Change 1

. SWRI, Solvent-Removable Liquid Penetrant Color Contrast Examination, NDT-200-1/57, Deviation 2

. SWRI, Dry Powder Magnetic Particle Examination, NDT-300-1/25

. . SWRI, Fluorescent Magnetic Particle Examination, NDT-300-2/37, Deviation 4

. SWRI, Manual Ultrasonic Examination of Nuclear Reactor Pressure

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Vessel Flange Ligaments, NDT-600-5/36, Deviation 4

. SWRI, Manual Ultrasonic Examination of Pressure-Retaining Studs and Bolts 2 Inches or Greater in Diameter Containing Access Holes, NDT-600-18/34, Deviation 11

. SWRI, Manual Ultrasonic Examination of Pressure-Retaining Welds in Heat Exchangers, NDT-600-30/15, Deviation 2

. SWRI, Manual Ultrasonic Examination of Austenitic Pressure Piping Welds, NDT-600-31/13, Deviation 4

. SWRI, Manual Ultrasonic Examination of Ferritic Pressure Piping Welds, NDT-600-41/7, Deviation 1

. SWRI, Visual Examination of Nuclear Power Plant Components, NDT-900-7/10 No violations or deviations were identifie c. Material and Equipment Certification The inspector reviewed the certification documents, relative to the following items:

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(1) Ultrasonic instruments, calibration blocks, transducers and couplant (2) Liquid penetrant, Magnaflux materials, penetrant, cleaner and developer (3) Magnetic particle, Magnaflux materials and equipment (4) Eddy current equipment No violations or deviations were identifie NDE Personnel Certifications And Observation Of Work Activities The inspector reviewed NDE personnel certifications in accordance with SNT-TC-1A, 1975/1980 edition The inspector also observed the work and had discussions with personnel during the following calibration:

. Ultrasonic calibration for shear wave examination of the pipe-to-branch connection (W13) on the pressurizer surge line off B loop, in accordance with SWRI procedure 600-31, Revision 13, Deviation 14, " Manual Ultrasonic Examination of Austenitic Pressure Piping Welds."

No violations or deviations were identifie . Split Pin Replacement General The Unit 1 control rod guide tube support pins were replaced by Westinghous Design modifications were incorporated into the replacement support pins to minimize the potential for intergranular stress corrosion and subsequent crackin The inconel replacement support pins were solution annealed followed by a single aging heat treatment to provide additional resistance to corrosion crackin A parabolic radius at the shank-to-shoulder juncture provides additional structural integrity to the pi The preload requirement for torquing the nut on the pin ranges from 120 to 130 foot pound The combination of these two design features results in an approximate 40 percent stress reduction in the pin shank-to-shoulder regio Review Of Procedure The inspector reviewed the following procedure:

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l W Split Pin Replacement at Point Beach, Unit 1 (WEP), MP2. WEP-1, Revision 0 No violations or deviations were identifie . Exit Interview The inspector met with representatives (denoted in Persons Contacted paragraph) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspections noted in this repor The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietar . .- - _ _ . _ , . - _ - _ - - . _ _ - - . -. . __ - . _ ,