IR 05000424/1993024

Insp Repts 50-424/93-24 & 50-425/93-24 on 931004-08.No Violations Noted.Major Areas Inspected:Unit 2 Isi,Review of Radiographic Film & EC ET Exam of SG Tubes

ML20059K581
Person / Time
Site:	Vogtle
Issue date:	10/27/1993
From:	Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20059K529	List: IR 05000424/1993024 ML20059K525
References
50-424-93-24, 50-425-93-24, NUDOCS 9311160102
Download: ML20059K581 (7)

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UNITED STATES

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e NUCLEAR REGULATORY COMMISSION REGloN 11 ,

,; E 101 MARIETTA STREET, N.Wc. SUITE 2900 5 j ATLANTA, GEORGIA 303234199

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Report Nos.: 50-424/93-24 and 50-425/93-24 Licensee: Georgia Power Company *

P. O. Box 1295 ,

Birmingham, AL 3520I Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and NPF-81 Facility Name: Vogtle I and 2 t

Inspection Conduc d: October , 1993 Inspector: fr a , ru ,/O-27-73 N. EcToomos ~ ' V Date Signed Approved by: Y A[# 7 3 J B ake, Chief Date Signed at rials and Processes Section

, n ineering Branch Division of Reactor Safety SUMMARY Scope:

This routine, announced inspection was conducted in the areas of Unit 2 inservice inspection (ISI), a review of radiographic film for Unit 2 and Eddy Current (ET) examination of steam generator (S/G) tube Results:

By observation of the ISI work effort and review of procedures relative to this area, the inspector ascertained that the licensee _is meeting code requirements and regulatory commitments. Personnel directing and performing ISI work, appear to be well trained to carry-out their assigned tasks. Eddy Current of steam generator tubes was conducted by Westinghouse Nuclear Services Division (WNSD). The inspection plan and Data Analysis Guidelines contain adequate conservatism to give reasonable assurance that suspect tubes will be identified and dispositioned in a satisfactory manner. In the Auxiliary feeedwater system, four single seat globe stop lift check valves were replaced _ with dual seat check valves, see paragraph Within the areas inspected violations or deviations were not identifie .

9311160102 931104'

PDR ADDCK 05000424 G PDR

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REPORT DETAILS ,

' Persons Contacted Licensee Employees

• J. Beasley, General Manager S. Chestnut, Manager Engineering Technical Support

• C. Christiansen, SAER Supervisor J. Churchwell, Senior Engineer ISI/SNC

• D. Cordes, Senior Nuclear Specialist SNC ,

• G. Fredrick, Manager Maintenance

• Gabbard, Nuclear Specialist Technical Support

• G. Hooper, Engineering Supervisor Technical Support

• D. Hudson, Senior Engineer

• Kitchens, Assistant General Manager Plant-Support

• Sheibani, Nuclear Safety and Compliance Supervisor W. Smith, Senior Plant Engineer Technical Support J. Swartzwelder, Manager Outages & Planing  ;

Other licensee employees contacted during this inspection included craftsmen, engineers, technicians, and administrative personne ,

NRC Resident Inspectors

• P. Balmain, Resident Inspector

• R. Starkey, Resident Inspector

• Attended exit interview Inservice Inspection (ISI) Unit-2 The inspector reviewed procedures, records, and observed work activities indicated below, to determine whether ISI was being conducted in accordance with applicable procedures, regulatory requirements, and licensee commitments. The applicable code for ISI on Unit 2 is the American Society of Mechanical Engineers-(ASE) Boiler and Pressure Vessel (B&PV) Code,Section XI,1983 Edition with Addenda through Summer -

1983. Unit 2 is presently in its third outage of the second period-of the first inspection interval. Westinghouse Electric Corporation (W)

had the generator (SG) tubin Southern Nuclear Operating Company (SNOC) had the responsibility for the remainder of the ISI activitie SNOC utilized Lambert, MacGill, and Thomas (LMT) Inc., personnel to assist in performing the nondestructive examinations'(NDE). Review of ISI Procedures, (73052)

The inspector reviewed the procedures listed below for technical content, proper approvals, requirements for qualification of NDE personnel, method of recording, evaluating and dispositioning of findings, and compilation of required record ,

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SNC-AUX-H/F/V-300 (R8) Procedure (Written Practice) for Qualification and Certification of Nondestructive Examination Personnel

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SNC-UT-V-404 (R6) Manual Ultrasonic Examination of Full-Penetration Welds SNC-UT-V-406 (R4) Manual Ultrasonic Examination of Cast Stainless Steel Full-Penetration Welds SNC-UT-V-411 (RS) Manual and/or Mechanized Ultrasonic Examination of Pressure Vessel Welds (2 Inches to 12 Inches in Thickness)

85066-C (R2) Radiography Examination SNC-MT-V-505 (R3) Dry Powder Magnetic Particle Examination: Yoke Method SNC-PT-V-411 (R2) Color Contrast, Solvent-Removable Liquid Penetrant Examination Procedure All procedures reviewed appeared to contain sufficient technical information for performing the specific examination and adequately recording and  ;

dispositioning adverse finding Observation of Work Activities, (73753) )

At the time of this inspection, most scheduled ISI examinations had been complete From those components remaining to be done, the inspector selected the following activities for observation of the examination effort.

l Weld N Examination Component Comments Method 20204-021-19 UT/PT 6" Elbow to Pipe See note 3 20204-021-20 UT 6" Pipe to Elbow See note 4 21301-016-01 UT/MT 10" Branch Com See note 1 to Pipe 21301-016-01 UT/MT 6" Outlet to See note 2 Flange

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Note: 1 Root condition observed with 60* transduce Note: 2 Code acceptable indication outside code required examination weld volume. Same condition observ,td during preservice examinatio ~

Note: 3 Root and counterbore geometry 360*.

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Note: 4 360* intermittent geometr The above examinations were observed to determine whether approved procedures were being followed, examination personnel were knowledgeable of the examination method and operation of the test equipment, and the examination results were being properly interpreted, recorded and dispositioned as require Within the area examined, no violation or deviation was identifie Eddy Current Examination of S/G Tubing Unit 2 (73753)

At the time of this inspection, the ET examination of the. tubes, in SG(s) 1 and 4, planned for this outage had been completed. The inspector met with the licensee's site cognizant senior engineer and discussed technical aspects of the inspection, obtained a summary report on the subject activity and related data 1.e., :

Analysis Guidelines and quality records. Westinghouse (W), was the prime contractor, in charge of data acquisition and analysi ;

controlling documents reviewed were as follows:  :

• Eddy Current Data Analysis Site Specific Guidelines A. Vogtle Units 1 & 2

• DAT - GYD-001 Rev. 6 Westinghouse Analysis Guideline. The latter, addresses personnel qualification requirements, -

system calibration and setup techniques, reporting requirements, evaluation of signals and resolution >

Discussion: Unit 2 has four W model "F" recirculating U-tube steam generators, each containing 5626 tubes. The tubes are made of Inconel-600 thermally treated material with an outside diameter of 13/16 inches and 0.040 wall ,

thickness. Tube support plates are made of 1.12" thick ferritic stainless steel type 405 material. The support plates have quatrefoil-design holes for improved water circulation and diminished oxide build-up. Baseline examination was performed in July'of 1988 and resulted in the plugging of two tubes. Since then, the major factor of tube degradation has been wear at the antivibration bar intersections. A summary of the scope of the examination is .

as follows:  !

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Bobbin Coil })G_1 SG 4

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Tubes with Antivibration Indications, Undefinable signals and distorted Indications 15 24 :

Random Selection (50%) from tubes not tested during previous two  ;

Outages 2812 2809-Rows 1-4 hot & cold legs full ,

length sample from tubes not tested on previous outage (2R2) 155 172 >

Support Plate Indications (test full length) 1

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Only one tube was examined with the rotating pancake coil probe to .

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confirm an indication located at the baffle plate tube elevatio Subsequent visual inspection determined the tube damage could have ,

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been caused by a loose part. The tube was not plugged. The total number of tubes plugged in the four steam generators of Unit 2 was as follows:  ;

SIG Tubes Plucced 1 2 2 4 *

3 1 4 8  :

Qualification records were reviewed for the following ET examiner ' Level ' III 4 Level II 6 Level II Analysts 4 Level I 2 In addition, the inspector reviewed calibration' records for three MIZ-18A remote data acquisition units, S/N 152, 803 and 163 to verify that they were within applicable specification tolerance ,

requirements and dat '

Within the areas examined violations or deviations were not identifie ;

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5 Plant Modifications (37700)

This modification consists of replacing the 4"O single seat globe stop i lift check valves, 2-1302-UA-0113, 0114, 0115 and 0116 with dual seat (hard and soft) globe stop lift check valves in the Auxiliary Feedwater System. The check valves are being replaced to provide better sealing under all pressure conditions which will reduce the potential for steam binding of the auxiliary feedwater pumps. In addition, this will also reduce maintenance requirements to prevent valve leakage. Through discussions with cognizant licensee personnel the inspector ascertained that the valve replacement had been completed and the new welds >

radiographed as required by code. The subject modification was performed under design change request No. 92-V2N0ll60-0-1 which referenced ASME Code Section XI, 1983 Edition with Addenda through Summer 198 Field work activities are controlled through Nuclear Plant j7- .

Maintenance Work Order 29301525-28 and corresponding travelers used to sign-off milestones, and hold points during field installatio Within these areas the inspector reviewed the applicable weld procedure and corresponding procedure qualification records, welder qualifications, filler metal certifications and the applicable weld process control sheets for each of the four replacement valves. In ;

addition, the inspector reviewed the radiographs of the new welds to -

ascertain whether they were prepared , evaluated and maintained in accordance with the applicable code requirements and licensee procedures. Welds for which radiographs were reviewed were as follows:

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Weld N Valve Size Comments 030-W-07Cl- 2-1302-04-113 4.5" x 0.432" Satisfactory '

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• 031-W-04C1 2-1302-U4-114 4.0"x 0.438" " >

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05C1 i 032-W-04Cl 2-1302-04-115 4.5" x 0.460" "

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029-W-08C1 2-1302-04-116 4.0" x 0.438 "

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• Both welds on this valve underwent multiple repairs to remove fabrication flaws. Final radiographs showed that the repaired welds were satisfactor ;

The hydrostatic test required by IWC-5000 of the code, has been deferred until ,

the next scheduled system hydro as permitted by code case N-416, Alternate l Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Pipin !

Within the areas inspected violations or deviations were not identifie j

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4. Licensee Action on Previous Enforcement Matter (92702)' j (Closed) Violation 424,425/91-27-01 Failure to Include All -!

Applicable ASME Code Acceptance Criter_ta in Radiographic Procedure: .,

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No. 85066-C q

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The licensee's letter of response dated December 20,-1991 has been 1 reviewed' and determined acceptable by Region II-staff. The  !

citation was issued when the inspector of record determined that i the approved radiographic procedure did-not include code specific : 1 acceptance criteria (NB-5320, NC-5320), relative to fabrication 1 related indications see 424, 425/91-2 , l-i By review of the subject procedure the inspector. verified that it d had been revised to include the missing' acceptance criteria

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information and, a review of radiographs indicated they met j code / procedural requirements as ' applicable. This item is close j (Closed) Violation 424, 425/91-27-02,LInadequate Control, Handling 1

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and Identification of Radiographic Film'and Associated Records.~

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The licensee's letter of response ~ dated December-.20,1991 has been l'

reviewed and determined acceptable by Region II staff. . The citation was issued when the inspector.of record identified  ;

certain radiographs missing required ~ identification. Film _ y packages of radiographed welds were missing required records and, D in certain cases, file / radiographs and the controlling QA Records ';

administrative procedure, failed to address control of_ radiographs t

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and associated records, see 424, 425/91-27.-

By review of applicable procedures, radiographic film packages and i radiographs, the inspector verified that the licensee has corrected the subject deficiencies and is in compliance with i applicable requirements. This item is close !

5. Exit Interview l The inspection scope and results were summarized on October 8,1993, j with those persons indicated in paragraph 1. The inspector describe a the areas inspected. Although reviewed during this inspection,  ;

proprietary information is not contained in this report. No dissenting  !

comments were received from the license y i

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