IR 05000155/1987003

Insp Rept 50-155/87-03 on 870106-08 & 0317-19.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp Work Activities,Including Generic Ltr 84-11

ML20205H392
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/26/1987
From:	Danielson D, David Jones NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20205H376	List: IR 05000155/1987003 ML20205H370
References
50-155-87-03, 50-155-87-3, GL-84-11, NUDOCS 8704010041
Download: ML20205H392 (5)

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l, U.S. NUCLEAR REGULATORY COMMISSION l

REGION III

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Report No. 50-155/87003(DRS)

Docket No. 50-155 License No. DPR-06 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name: Big Rock Point Nuclear Plant Inspection At: Big Rock Point site, Charlevoix, Michigan Inspection Conducted: January 6-8 and March 17-19, 1987 Inspector- D. E. Jones 3)lt-)/7 Date Approved By: D. H. Danielson, Chief _3 26/ O Materials and Processes Section D_ ate I_n,spection Summary Inspection on January 6-8 and March ~-17-19,1987(_R_ey_ortNo. 50-155/87003 Areas InspectedTToutine

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t unannounced Tnsp_ection of i,nserVice

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ISIins'peFtisnl iio~rE activities including NRC Generic Letter 84-11 inspection (73051,73052, 73753,and73755)

Results: No violations or deviations were identifie g y $$$$ISS PDR PDR G

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DETAILS 1. Persons Contacted Consumers Power Company _iC_PCol

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D. Hoffman, Plant Superintendent

• L. Monshor, QA Superintendent

• R. Alexander, Technical Engineer

• G. Withrow, Engineering and Paintenance Superintendent

• M. Acker, ISI Coordinator D. Zeigler, Special Projects Supervisor J. Toskey, General Engineer D. Hice, Senior Technologist Factory Mutual __ Engineering R. Riegler, ANII N_u_c_ lear Regulatory Commission

• S. Guthrie, Senior Resident Inspector The inspector also contacted and interviewed other licensee and contractor employee * Denotes those present at the final exit interview on March 19, 198 . Inservice Inspection General CPCo utilized the Laboratory and Field Technical Services Department,NondestructiveTestingServicesDivision(L&FTS-NDT),

and contracted with Combustion Engineering's Outage Services Department (CE) to perform the ISI in accordance with ASME Section XI, 1977 Edition, Summer 1978 Addenda. This is the fourth outage of the second ten-year pla CE performed the visual (VT-3) examination of the reactor pressure vessel (RPV) and ultrasonic examination of selected main recirculating system welds for intergranular stress corrosion cracking (IGSCC). The balance of the ISI was performed by CPCo L&FTS-ND The visual equipment used for the remote VT-3 of the vessel was the CE Remote Activated Floating Television System (RAFTS). RAFTS is a floating, air operated, telescoping device with a pivoting camera that enables the examiner to manipulate the assembly and camera to examine the accessible areas of the vessel interior above the fue .

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The remote viewing system employs a high resolution CCTV camera, lights, monitor and recorder capable of resolving a 1/32" wide black l line on an 18% neutral gray card. All remote visual exams were '

recorded on video tape with audio commentar A master-slave technique was used for the manual ultrasonic examinations. Ultrasonic instruments were used for the primary or main control units and oscilloscopes were used as slave units or monitors for the individual scanning. This allowed the individual scanning to view the RF presentation of the primary unit, but did not allow him to make changes or adjustments to the presentation or calibration of the control unit. The A-scan presentation of the main control unit was recorded on video tape.

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CPCo performed additional ultrasonic examinations of IGSCC susceptible piping to satisfy NRC concerns about the adequacy of the sample size of prior exams performed to meet the guidelines of NRC Generic Letter 84-11. The UT examinations included 20 welds that had never been examined and 12 welds that had been previously examined, for a total of 32 welds. All welds examined, including those previously examined, were found to be acceptable. The following table is the licensee's revised sampling plan:

Total IGSCC No. Of Welds No. of Additional Pipe . Susceptible Previously Welds Selected Size Welds Examined For 1987 Outage

24" 2 2 20" 4 0* 0*

17" 14 4 4 14" 30 6 5 6" 14 3 3 5" 19 3 4 4" 16 3 4 TOTAL 99 21 20 l

• Severely restricted accessibility All of the above pipe sizes represent the main recirculating system, except for the 6", which is the shutdown cooling syste IGSCC ultrasonic examination personnel (CE) responsible for interpretation of the examination results were qualified at the EPRI NDE Center to the requirements of IE Bulletin 83-02 as specified by NRC Generic Letter 84-1 Program Review The NRC inspector reviewed L&FTS-NDT Services 1987 Big Rock Point Inservice Examination Program Plan, No. NDT-PP-15 Revision 0, and the Big Rock Point Plant Inservice Inspection Outage Plan, Revision 1, and found them to be acceptabl ._ . _ _ _ _ . _ ___ _ _ __ . --

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c. Procedure Review The inspector reviewed the following procedures:

CPCo, Radiographic Examination of Welds, NDT-RT-01, Revision 4 CPCo, Visual Examination, NDT-VT-01, Revision 4 CPCo, Liquid Penetrant Examination - Nonstandard Temperature, NDT-PT-02, Revision 0

CPCo, Liquid Penetrant Examination, NDT-PT-01, Revision 4

• CPCo, Ultrasonic Examination of Studs, Bolts and Pins, NDT-UT-07, Revision 1 CPCo, Ultrasonic Thickness Measurements, NDT-UT-02, Revision 2

CPCo, Ultrasonic Examination of Ferric, Austenitic Piping and Branch Connection Welds, NDT-UT-01, Revision 4

CE, Procedure For A VT-3 Visual Examination of a Reactor Vessel, Rock-ISI-065, Revision 0

CE, Ultrasonic Detection Procedure For Discrimination of IGSCC, Rock-ISI-016, Revision 0 No violations or deviations were identifie d. NDE Personnel Certifications And Observation Of Work Activities The NRC inspector reviewed several NDE personnel certifications in accordance with SNT-TC-1 The NRC inspector also observed the work and had discussions with personnel during visual examination of Pipe Restraint Nos. 6-RCW-302-8PR, and 6-RCW-302-10PR, performed in accordance with CPCo Procedure NDT-VT-01, Revision 4. " Visual Examination."

The NRC inspector reviewed the video tape with audio connentary of the following IGSCC ultrasonic examinations, perfcmed in accordance with CE Procedure, Rock-ISI-016, Revision 0, " Ultrasonic Detection Procedure for Discrimination of IGSCC":

24-MRS-121-1 Reducer-To-Tee 17-MRS-114-7 Elbow-To-Reducer 5-MRS-132-2 Pipe-To-Elbow ,

5-MRS-132-3 Elbow-To-Pipe l 5-MRS-132-4 Pipe-To-Valve l 5-MRS-132-7 Elbow-To-Pipe 5-MRS-132-8 Pipe-To-Tee 4-MRS-141-2 Pipe-To-Elbow 4-MRS-141-3 Elbow-To-Pipe 4-MRS-141-6 Pipe-To-Elbow

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The NRC inspector reviewed the video tape of the visual examination of the reactor pressure vessel, (flange mating surface, flange shell section and upper shell section), perfomed in accordance with CE Procedure, Rock-ISI-065, Revision 0, " Procedure for a VT-3 Visual Examination of a Reactor Vessel."

No violations or deviations were identifie Review Of Data, Material And E,qujpme_n_t Certif_ icatjon_s

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The NRC inspector reviewed the following documents and detennined that the applicable QA/QC requirements were met:

ISI data reports, including radiographic film review of safety-relief nozzle, nozzle-to-flange Weld No. 3-MSS-107- * Ultrasonic instruments, calibration blocks, transducers, surface thennometers, and couplant certification *

Liquid penetrant, cleaner and developer certification Radiographic equipment, densitometers, density strip, and penetrameters certification No violations or deviations were identifie . IEN 86,-10j,__, Feee _dwa_ter,and_

r Main _ eJ, team, Pipjng Thickness Measurements

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CPCo also performed 21 ultrasonic thickness measurements, in accordance with CPCo Procedure NDT-UT-02 Revision 2. " Ultrasonic Thickness Measurements", on selected elbows, high flow T's and reducers of feedwater and main steam piping. The measurements verified normal wall thicknes . Exit Interview

! The inspector met with site representatives (denoted in persons contacted paragraph) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report. The inspector also discussed the likely informational content of the inspection report l with regard to documents of processes reviewed by the inspector during the j inspection. The licensee did not identify any such documents / processes as proprietary.

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