IR 05000369/1989007

Insp Repts 50-369/89-07 & 50-370/89-07 on 890320-24.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp,Including Review of Procedures,Observation of Work Activities & Evaluation of Eddy Current Testing

ML20245D109
Person / Time
Site:	Mcguire, McGuire
Issue date:	04/17/1989
From:	Blake J, Coley J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20245D104	List: IR 05000369/1989007 ML20245D102
References
50-369-89-07, 50-369-89-7, 50-370-89-07, 50-370-89-7, NUDOCS 8904280110
Download: ML20245D109 (8)

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UNITED STATES NUCLEAR REGULATORY COMMISSION '

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REGION il .

<r 0 101 MARIETTA STREET, U ff , ANTA, GEORGI A 30323

%..../ e Report Nos.: 50-369/07 and 50-370/89-07 Licensee: : Duke Power Company 422. South Church' Street-Charlotte, NC 28242 Docket Nos.: 50-369 and 50-370 License Nos.: NPF-9 and NPF-17

. Facility Name: McGuire 1 and 2-Inspection Conducted: March 20-24, 1989 Inspector: NN n L/ -/ 7- 89 Date Signed Q

. Approved'by: s Iv J. J. Blake, Chi _ef_

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Date Sfgned t fals.and Processes Branch n neering Branch

. Division of Reactor Safety SUMMARY-

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Scope: This special, unannounced inspection was conducted in the areas of inservice ' inspection (ISI):- review of procedures' (Units 1 and 2),

observation of work activities (Unit' 1),iand evaluation of eddy-current testing-(ECT) data (Unit 1). The inspection objectives were:

To determine if the licensee's ' investigation of . the cause of the- 1 steam generatorL tube (18-25) rupture in Unit 1- was proceeding effectively; and to ensure that details which could re' veal the mechanism for the tube failure were identified, and properly evaluated by the license Results:. The licensee appears to have established an effectively managed and technically competent' recovery team to determine'the cause of the steam generator tube rupture and ensure that necessary corrective actions are taken' to prevent this type of failure from recurrin The licensee made a strong effort to be responsive to the inspector's '

requests for information during this inspection.

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REPORT DETAILS Persons Contacted Licensee Employees

• J. Day, Associate Engineer, Compliance

• C, Hendrix, Manager, Nuclear Support

• D Mayes, Maintenance Engineer

• C. Robinson, Maintenance Engineer

• M. Sample, Maintenance Superintendent Other licensee employees contacted during this inspection included craftsmen, engineers, operators, mechanics, security force members, technicians, and administrative personne Other Organizations Babcock & Wilcox (B&W)

T. Richards - Product Manager, ISI NRC Resident Inspector

• R. Croteau

• Attended exit interview Inservice Inspection & Repair of Steam Generator Tube Rupture On March 7, 1989, a steam generator tube rupture event occurred on McGuire Unit 1. Currently a tube rupture outage is underway which will perform the necessary steam generator inspections and repairs. In order to ensure that an integrated and all-encompassing approach is taken for investi-

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gation of the tube failure and recovery actions the licensee has estab-lished a Steam Generator Tube Rupture Recovery Tea The purpose of the Recovery Team is to coordinate all efforts toward determining the cause of the tube rupture, provide technical leadership and implement a recovery program.

l l The inspector reviewed the recovery team's objectives and on-going progress. In addition the inspector reviewed eddy current procedures for

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l technical content and observed examination activities including a visual examination of the inconel tubes from the secondary side of the steam generato Examiner's certifications, qualifications and performance, were reviewe Equipment calibration records, preservice eddy current data / evaluations, and the data analysis process for the current eddy current examinations which utilized a multi-frequency bobbin coil, examinations of tubes in the

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same heat as the ruptured tube using a non-magnetic bias bobbin coil, examinations using a rotating pancake coil (RPC) and profilometry examinations were reviewed by the inspecto The applicable code for the examination and repair activities on Unit 1 is the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME B&PV) Code, Section XI,1980 Edition with Addenda through Winter 198 Specific procedures, work activities, and data analyzed are delineated below: Review of Procedures (Units 1 and 2) (73052)

The inspector reviewed the following eddy current examination i procedures, eddy current data evaluation procedures and eddy current analysis guidelines to ensure the methods of examination, recording, evaluating, and dispositioning findings are established and reporting requirements are in compliance with applicable code requirement Procedure N Ti tle B&W Procedure No. 151-460, Kev. 14 Technical Procedure for the Evaluation of Eddy Current Data of Nuclear Grade Steam Generator Tubing B&W Procedure No. ISI-424, Rev. 14 Multi-frequency Eddy Current Examination of

.750 "0D. x .044" Wall RSG Tubing for ASME Examination and Wear at Tube Support Plates B&W Procedure No. 151-463, Rev. 6 Technical Procedure for the Evaluation of Eddy Current Data Generated from the Multi-element Probe B&W Procedure No. 151-464, Rev. 4 Technical Procedure for the Evaluation of Eddy Current Data of Nuclear Grade Steam Generator Tubing for Wear Fretting B&W Procedure No. ISI-510, Rev. 6 Eddy Current-360/RDAU System Operating Procedure Procedure for Unscheduled Outage Eddy Current Analysis 3,89, Rev. 2, Dated 3-14-89 Guidelines for McGuire Nuclear  !

Station Unit 1

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The above procedures were al:;o reviewed to ensure that they had been

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approved by authorized licensee personnel, qualifications of nondestructive examination personnel were specified and in accordance with the licensee's approved ISI program; and methods of examination, extent, and technique were adequately described and in conformance with the requirements of ASME, B&PV Code, Section V, and special requirements imposed by joint NRC or industry initiatives and l licensee commitment The inspector's review of the above procedures revealed a strong program for eddy current examination and data evaluation of inconel tubes in Westinghouse Steam Generators at the McGuire facilit b. Observation of Work and Work Activities (Unit 1)(73753)

The inspector observed work activities and reviewed certification records of equipment and nondestructive examination personnel .which were being utilized during this unscheduled outage. However, the emphasis of this inspection was not on eddy current data collection, since the licensee had committed to 100% eddy current examination of the tubes in all four generators, but rather to the evaluation of the collected data. B&W's work activities were observed only on a surve). 'ance basis in the following two areas:

- Eddy current data collection

- Visual examination of Steam Generator B, Tube 18-25, using a boroscope, from the secondary side of B Steam Generato Examiner qualification documentation for Duke Power (DP), B&W, and Zetec examiners listed below were reviewed in the following areas; employees name; person certified; activity qualified to perform; effective period of certification; signature of employers designated representative; basis used for certification; and annual visual acuity, color vision examination; and periodic decertificatio ,

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Company Examiner Level of Eddy Current Certification DP TBA L-11 DP GGB L-11A DP CRB L-11 DP MWB L-11A DP WB L-11 DP CBC L-11A ,

DP MKD L-11A DP TH L-11A DP MBT L-11A I i

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L l Company Examiner Level of Eddy Current Certification (cont'd)-

B&W PRC L-11 B&W PRC L-11'

B&W MWD L-1 (Trainee)

B&W GCG L-1 B&W CRH L-11A &L-11 B&W EPL L-11A B&W ACM L-11 B&W RLM L-(Trainee)

B&W SDM L-1(Trainee)

B&W JDM L-11 B&W JC0 L-1 B&W TAR L-111 B&W GKS- L-11 B&W HLS L-11A B&W . MMS L-11A & L-11 B&W JBW L-11A Zetec PAA L 1.1A & L-11 Zetec MAB L-:'.1A & L-11

'Zetec DRD L-11

, Zetec DJH L-11A & L-11 Zetec CSH L-11A & L-11 Zetec KJW L-111 & L11A Zetec KDS L-11 & L-11A Zetec GLW L-11 & L-11A Equipment calibration certification, for the following ECT equipment was also examined by the inspecto Instrument Serial N MIZ 18RDAU SN-180 MIZ 18RDAU SN-006 MIZ 18RDAU SN-071 MIZ 18RDAU SN-074 MIZ 18RDAU SN-131 i

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MIZ 18RDAV SN-186 Within the areas examined, violations or deviations were not identifie Eddy Current Data Review and Evaluation (Unit 1) (73755)

The inspector observed the examiners evaluations of the following inconel tubes to determined whether the testing results were consistent with the applicable acceptance criteria:

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k Both Company S. G.# Row Column Type Duke D 14 28 Bobbin Coil Duke D 14 27 Bobbin Coil Duke D 14 26 Bobbin Coil Duke D 14 25 Bobbin Coil Duke D 14 24 Bobbin Coil Dukc D 14 23 Bobbin Coil Duke D 14 22 Bobbin Coil Duke D 14 21 Bobbin Coil Duke D 14 20 Bobbin Coil Duke D 14 19 Bobbin Coil Duke D 14 18 Bobbin Coil Duke D 14 17 Bobbin Coil Duke D 14 16 Bobbin Coil Duke D 14 15 Bobbin Coil Duke D 14 14 Bobbin Coil Duke D 14 13 Bobbin Coil Duke D 14 12 Bobbin Coil Duke D 14 11 Bobbin Coil Duke D 14 10 Bobbin Coil Duke D 14 9 Bobbin Coil Duke D 14 8 Bobbin Coil Duke D 14 7 Bobbin Coil Duke D 14 6 Bobbin Coil Duke D 14 5 Bobbin Coil Duke D 14 4 Bobbin Coil Duke D 14 3 Bobbin Coil Duke D 13 3 Bobbin Coil Duke D 13 4 Bobbin Coil Duke D 13 5 Bobbin Coil

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Duke D 13 6 Bobbin Coil Duke D 13 7 Bobbin Coil Duke D 13 8 Bobbin Coil Duke D 13 9 Bobbin Coil Duke D 13 10 Bobbin Coil Duke D 13 11 Bobbin Coil Duke D 13 12 Bobbin Coil Duke D 13 13 Bobbin Coil Duke D 13 14 Bobbin Coil Duke D 13 15 Bobbin Coil Duke D 13 16 Bobbin Coil Duke D 12 24 Bobbin Coil Duke D 12 23 Bobbin Coil Duke D 12 22 . Bobbin Coii Duke D 12 19 Bobbin Coil Duke D 12 18 Bobbin Coil Duke Bobbin Coil l

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Company S. G.# Row Column Type

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B B 19 27 360' Rotating Pancake Coil B&W B 19 26 360 Rotcting Pancake Coil B&W B 19 25 360 Rotating Pancake Coil B&W B 19 24 360 Rotating Pancake Coil B&W B 19 23 360 Rotating Pancake Coil B&W 8 20 23 360 Rotating Pancake Coil B&W B 20 24 360 Rotating Pancake Coil

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B&W B 20 25 360 Rotating Pancake Coil B&W B 20 26 360 Rotating Pancake Coil B&W B 20 27 360 Rotating

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Pancake Coil B&W B 17 25 360 Rotating Pancake Coil B&W B 17 26 360 Rotating Pancake Coil B&W B 17 27 360" Rotating Pancake Coil B&W B 16 27 360 Rotating Pancake Coil B&W 8 16 26 360 Rotating Pancake Coil B&W B 16 25 360' Rotating I' Pancake Coil B&W B 16 24 360 Rotating Pancake Coil B&W B 16 23 360 Rotating Pancake Coil B&W B 13 34 360 Rotating Pancake Coil i B&W B 21 38 360 Rotating Pancake Coil B&W B 7 24 360 Rotating Pancake Coil B&W B 47 46 360 Rotating Pancake Coil

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H Both Company S. G.# : Row Column Type (cont'd)

B&W B 43 52 _360' Rotating

, Pancake Coil

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Duk B *18 25 Bobbin Coil 360 . Rotating

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, B&W- B *18 25

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Pancake Coil B&W B *18 25 Profilometry

• NOTE: Evaluation of Ruptured Tube Other tubes - using various techniques were also examined . by the inspector on 'a surveillance basi At the conclusion of :the inspection the status of ECT was as delineated below:

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No. F/L INSPECTIONS PLANNED 4470 4770 4505 4446 No.. TUBES' DATA ACQUIRED 0 4770 677 4446

No. TUBES ANALYZED-PRIMARY 0 4770 587' 4446 No.. TUBES ANALYZED-SECONDARY 0 4700 587 4446 No. TUBES AWAITING RERUN *JDES W/ EDDY-360 PLANNED 65 -208 M BCS W/ EDDY-360 ACQUIRED- 40 208 iUBES F/ EDDY-360 PRIMARY 40 208

. TUBES'W/CODY-360 SECONDARY 40 208-Within the areas examined, violations or deviations were not identifie . Exit Interview The inspection scope and results were summarized on March 24, 1989,.with those persons indicated in parag nph 1. The inspector described the areas inspected and discussed in detail the inspection result Although reviewed during this inspec+. ion, proprietary information is not contained in this repor Dissenting comments wer9 not received from the license v -

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