IR 05000369/1987038

Insp Repts 50-369/87-38 & 50-370/87-38 on 870928-1002.No Violations or Deviations Identified.Major Areas Inspected: Inservice Insp,Acceptance of NDE & Preservice Insp Activities

ML20236E940
Person / Time
Site:	McGuire, Mcguire
Issue date:	10/23/1987
From:	Blake J, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20236E933	List: IR 05000369/1987038 ML20236E930
References
50-369-87-38, 50-370-87-38, IEB-87-001, IEB-87-1, NUDOCS 8710300072
Download: ML20236E940 (14)

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UNITED STATES I

'o NUCLEAR REGULATORY COMMISSION f" T3- REGION il ;

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j; 101 MARIETTA STREET. ,

t; ATL ANTA, GEORGI A 30323 -

%,,.....f l Report Nos.: 50-369/37-38 and 50-370/87-38 f

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-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~ '

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' Inspection 'te - September 28 - October 2, 1987 Inspecto . /. 5 7 R ' 'Newsome Dite Signed Approved /o 3 7 J f.'Blake, Chief- .

Dste Signed 4terials and Processes Section ivision of Reactor' Safety

SUMMARY Scope: This ' routine, announced inspection- was in the areas of Inservice-Inspection (ISI) Unit i, acceptance NDE and Preservice Inspection (PSI)-

Activities associated with the deletion of' the High llead Safety Injection System Unit 1, and records review and NDE activities associated with IE

Bulletin 87-0 Result No violations or deviations were identified.

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REPORT DETAILS l Persons Contacted Licensee Employees

• 0. J. Rains, Maintenance Superintendent / Nuclear Power Division

• H. Hamilton, Superintendent Technical Services

• Sample, Superintendent of Integrated Scheduling i

• N. McGraw, Compliance Engineer

• N. G. Atherton, Compliance Production Specialist

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• W. G. Goodman, Quality Assurance

• G. Underwood, Inservice Inspection (ISI)

T. Troutman, ISI Coordinator

• R W. Rider, Maintenance Engineer

• T. Bumgardnerer, Maintenance Technician Other licensee employees contacted included engineers, technicians, mechanics, security force members, and office personne Other Organizations R. Patterson, NDE Supervisor, Babcock & Wilcox M. Gallagher, Eddy Current Analyst Level III, Babcock & Wilcox NRC Resident Inspectors

• T. Orders, Senior Resident Inspector

• S. Guenther, Resident Inspector

• D. J. Nelson, Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were summarized on October 2, 1987, with those persons indicated in that above paragraph. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters f This subject was not addressed in the inspection.

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i I Unresolved Items l Unresolved items were not identified during this inspection.' l S. . Inservice Inspection (ISI) and Preservice Inspection (PSI) Unit 1 The .-inspector examined documents, activities, and records - as indicated below to determine whether PSI /ISI was being conducted in accordance with applicable procedures, regulatory requirements and licensee commitment (

The applicable code for ISI is American Society of Mechanical Engineers i Boiler and Pressure Vessel (ASME B&PV) Code,Section XI, 1980 edition with i addenda through Winter.198 Duke Power nondestructive examination (NDE) i personnel are performing the liquid penetrant (PT), magnetic particle ];

(MT), and visual (VT) examinations while Babcock and Wilcox (B&W)

personnel are performing the ultrasonic (UT) and eddy current (ECT) i examinations for Duke Powe ,

l Inservice Inspection, Programmatic Review (73051) I The insp'ector reviewed the below listed documents relating to the ]

licensee s Inservice Inspection (ISI) program (Plan) for the current-outage in the areas of: program approval; QA program requirements including organizational structure; audit requirements; general QA requirements (examination reports, control of daviations from established program; quality documentation and identification of components); work and quality inspection procedures; control of processes; corrective action; document control; control of examinations and examination equipment; quality records; inspection scope; inspection intervals; personnel qualifications; and, NDE records including provisions for storag Document Title i l

Procedure NDE-C R0 Calibration / Verification of NDE l Equipment  !

l Procedure NDE-B R12 Training, Qualification and i Certification of NDE Personnel Procedure NDE-A R8 Nondestructive Examination Program I Procedure l

Inservice Inspection Plan R9 Unit 1 Outage 4 Inspection Plan Details

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Procedure QCL-5 R8 Control of Preservice and Inservice Inspection Activities Review of Procedure (73052)

(1) The inspector reviewed the procedures indicated below to determine whether the procedures were consistent with regulatory I

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l requirements and licensee commitment The procedures were also i reviewed in the areas of procedure approval, requirements for qualification of NDE personnel, and compilation of required ,

records; and if applicable, division of responsibility between the licensee and contractor personnel if contractor personnel are involved in the ISI effor I Procedure ID' Title NDE-40 R8 Ultrasonic Examination Procedure and Techniques for Thickness Measurements, Lamination Detection, and Stud Location NDE-25 R10 Magnetic Particle Examination Procedure and Techniques l NDE-35 R9 Liquid Penetrant Examination ;

ISI-125 R5 Ultrasonic Examination for Intergranular Stress Corrosion Cracking In Stainless Steel or Nickel Base Alloy Piping

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ISI-130 R23 Ultrasonic Examination of Vessel Welds and Nozzle Inside Radius Sections QCL-13 R5 ISI Visual Examination, VT-1 i QCL-14 R7 ISI Visual Examination, VT-3 and VT-4 I NDE-12 R5 General Radiography Procedure for Preservice and Inservice Inspection ISI-120 R25 Ultrasonic Examination of Piping and (

Vessel Welds Joining Similar and j Dissimilar Materials i

1S1-424 R10 Multifrequency Eddy Current  !

Examination of .750-inch OD x i

.044-inch Wall RSG tubing for i Detection of Tube Wear at Support Plate ISI-464 R4 Technical Procedure for the Evaluation i of Eddy Current Data of Nuclear Grade !

Steam Generator Tubing for Wear i Fretting ISI-463 R6 Technical Procedure for the Evaluation l of Eddy Current Data Generated from i the Multi-Element Probe 1 l

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' All procedures listed above had been previously reviewed by NRC-during . previous outages for Unit 1. During Lthe current Linspection. only changes to previously reviewed ' documents were reviewe (2). The inspector reviewed - the ' ultrasonic ' procedures NDE-40,  ;

ISI-125, ISI-130 and ISI-120 to ascertain whether they had been

reviewed and approved; in accordance with the licensee' established QA procedures. The above procedures'were reviewed for technical adequa.cy and conformance with ASME, -Section V a Article 5 and other license commitments / requirements in the- a below listed areas: type of apparatus used; extent of coverage of weldment; calibration requirements; search units; beam angles; .DAC curves; reference ' level for monitoring

, discontinuities; method. for demonstrating penetration;-limits for evaluating and recording indications; recording significant ,

indications and; acceptance limit l

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(3) The inspector reviewed the ECT procedures ISI-424, ISI-464 a'nd'

ISI-463 for technical content relative to: multichannel -s examination unit, multichannel examination indication equipment is specified, examination sensitivity,' material permeability, 'a method of examination, method of calibration and calibration '

sequence, and acceptance criteri (4) -The inspector reviewed the PT procedure NDE-35 to ascertain whether it had been reviewed and approved in accordance with the J licensee's established QA procedures. The above procedure was ~l

- reviewed for technical. adequacy and conformance with ASME, 8 Section V, Article 6, and other licensee commitments / j requirements in the below listed areas: specified method; .i penetrant material identification; penetrant materials analyzed - l for sulfur; penetrant materials analyzed for total halogens.; a acceptable pre-examination surface; drying time; method of d penetrant application; surface temperature; solvent removal; surface drying prior to developing; type of developer; examination technique; evaluation techniques; and procedure requalificatf or . i

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(5) The inspector reviewed the MT procedure NDE-25 to ascertain j whether it had been reviewed and approved in accordance with the 1 licensee's established QA procedures. The above procedure was l reviewed for technical adequacy and for conformance with ASME )

Section V, Article 7, and other licensee commitments / {

requirements in the below listed areas: examination methods;  ! contrast of dry powder particle color with background; surface )

temperature; suspension medium and surface temperature for wet j particles; viewing conditions; examination overlap and 1 directions; pole or prod spacing; current or lifting power )

L,w) and; acceptance criteri I l

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(6) The inspector reviewed the _ visual . examination procedures to determine whether they contained sufficient instructions to assure that the following parameters were specified and i controlled within the limits permitted by the applicable code, l, standard, or any additional specification requirement; ~ method -

direct visual, remote visual or translucent visual; application  !

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. hydrostatic testing, fabrication procedure, visual examination u of welds, leak- testing, etc. ; how visual examination 'is to be performed, type of surface condition available; method or tool for surface preparation, if any, whether direct or remote viewing is used, if any; sequence of performing: examination,-

when applicable; data to be tabulated, if any; acceptance-criteria is specified and consistent with the applicable code section or. controlling specification; and report form j completion.;

(7) The inspector reviewed the radiographic (RT) procedure to determine whether it contained sufficient information to assure that the following parameters were specified and.- controlled within the : limits permitted by the applicable code, or any additional specification requirement: type 'of. material _to be radiographer; material and weld surface condition requirements; type of radiation source, effective focal spot or effective source size; film brand or type; number of films in ' cassette; minimum source' to film distance; type and thickness ' of'

intensi_fying screens and filters;- quality of radiographs; film density and cont'rast for single and composite viewing; use of l

. densitometers for assuring compliance with film density requirements; . system of radiograph ' identification; ' use of location markers; ' methods of reducing and testing for back-scatter; selection of penetrometer including penetrometer placement; number of penetrometer; shims under penetrometer; radiographic technique for double wall viewing; and, evaluation and disposition of radiograph l c. Observation of Work and Work Activities (73753B) l The inspector was unable to observe work activities due to health l physics restriction of ISI activities during this inspection period 1 and the deferral of some examinations to a later outage. The 3 inspector reviewed certification records of equipment, materials, and -)

NDE personnel which had been and will be utilized during the required )

ISI/ PSI examinations during this outage. The reviews conducted by j the inspector are documented belo l l

(1) Examiner Qualification l l

The inspector reviewed the qualification documentation for the I below listed Duke Power (DP) and B&W examiners in the following l areas: employer's name; person certified; activity qualified to l perform; effective period of certification; signature of l

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employer's designated representatives'; basis used for ,

certification; and annual visual acuity, color vision '

examination and periodic decertificatio Method'- Level VT Company Examiner UT PT MT RT EC 1 23 4 3

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i (2) The following listed ultrasonic equipment and materials certification records were reviewed:

Ultrasonic Instruments  ;

Manufacturer /Model Serial N T-K/SM-100 1346 T-K/SM-100 1343 T-K/SM-100 1348 Ultrasonic transducers with serial numbers 32381 and 3274 Ultrasonic Couplant Batch No. 8662 and 8552

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l Ultrasonic Calibration Blocks Identification N Description Application- '

50219 12" dia. SS Pipe Weld i 50376 7.3" thick CS RV Closure Head 8-SS Step Block SS Thickness (3) The inspector reviewed the below listed liquid penetrant materials certification records to ascertain if the sulfur and i halogen content of the material was within acceptable content limit ,

Materials Batch Number Liquid Penetrant 79H023 and 85LO45 Cleaner / Remover 87E001 Developer 85K080

'(4) The inspector reviewed the certification documentation for two  ;

eddy current calibration standards with' serial numbers 50285 and 50379, ISI/ PSI Data Review and Evaluation (73755)(73055)

l (1) Records of completed nondestructive examinations were selected  !

and reviewed to ascertain whether: the method (s), technique and l

. extent of the examination complied with the ISI plant and applicable NDE procedures; findings were properly recorded and evaluated by qualified personnel; programmatic deviations were ,

recorded as required; personnel, instruments, calibrations blocks and NDE materials (penetrants, couplants) were j designated. Records selected for this review are listed belo '

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Item / Weld N ISI Item N NDE Method 1NI1F-264* B09.040.114 PT IND1F-21A C05.011.215 PT IND12A-1 C05.011.216 PT INDIF-170 C05.011.239 PT IND-76A-2 C05.011.243 PT IND-69-1 C05.011.250 PT INCFE5340* B07.050.009 VT '

1RCP-IC-H* B07.060.007 VT INV-1A* B07.070.205 VT 1MCA-CA-H276 D02.020.001 VT <

IMCR-NC-578 F01.01.044 VT 1MCR-NC-603 F01.01.058 VT 1MCR-NI-509 F01.01.311 VT IMCR-NI-585 F01.01.352 VT

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Item / Weld No, ISI Item N NDE Method (cont'd)

IMCAFW-13 F01.02.311 VT IMCAND-H324 F01.02.576 VT INIP-643* B09.011.434 UT INI-645* 809.011.444 UT i

1NCIF-109 E03.001.004 UT 1RCP-1B E01.001.002 UT INC-102-1 E03.001.005 UT INC-102-2 E03.001.006 UT

• Current examination results were compared with preservice examination results. No major discrepancies were note Item / Weld N PSI Reference Method NTIFW-38-1 MCFI-1NF38 PT NTIFW-38-3 MCFI-INF38 PT NTIFW-38-4 MCFI-1NF38 PT NTIF-644 MCFI-1NI-62 PT NTIF-636 MCFI-1NI-79 PT NTIF-108 MCFI-1NC-47 PT NC1F-106 MCFI-INC-47 PT NI1F-2898 MCFI-INI-80 PT NI1F-2897 MCFI-INI-79 PT INI-458-1 MCFI-INI-79 PT INI-462-3 MCFI-INI-62 PT (2) Eddy Current Examination of Steam Generator Tubing (a) The inspector reviewed records of the eddy current examinations indicated belo The reviews were compared with the applicable procedures and the Code in the following areas: the multichannel Eddy Current Examination equipment has been identified; method for maximum sensitivity is applied; material permeability has been recorded; method of examination has been recorded; examination equipment has been calibrated in accordance with the applicable performance reference; amplitede and phase has been calibrated with the proper applicable calibration reference and is recalibrates at predetermined frequency; 100% coverage of steam generator tubes occurs during the examination; and acceptance criteria is specified or referenced and is consistent with the procedure or the ASME B&PV Cod Results are consistent with acceptance criteri .. . _ _ _ _ _ . _ - _ _ _ _ _ _ _

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SG-A SG-B SG-C SG-0 Row Column- Row Column Row Column Row Column 49 46 16 111 27 57 49 60 49 47 33 98 12 67 49 58 49 49 26 68 25 66 49 57 46 71 37 72 49 57 49 56 46 62 42 77 33 98 8 3 46 55 42 76 49 48 9 3 46 53 42 60 49 47 10 3 j 45 60 42 51 49 '46 19 12 45 63 42 52 49 43 4 12 .

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45' 66 42 50 28 38 16 73 14 25 42 51 28 37 13 65 14 28 47 82 28 36 19 62 30 '27 47 83 28 35 15 59 20- 38 48 82 28 31- 49 75 25 38 2 114 49 71 49 81 35 38 2 106 49 39 8 23 ,

49 35 17 107 27 57 17 24  !

49 37 26 103 45 31 8 36 49 40 27 102 36 91 3 73 49 53 26 107 3 104 10 85 45 28 26 68 14 98 18 90 40 77 31 49 11 37 6 35 20 97 31 54 28 32 17 12 1 45 61 23 73 28 33 15 12 ,

45 65 10 50 28 34 9 12 l (b) The inspector performed an independent verification of the reported analysis of selected tubing in SG-A. A sample of the data, some having rr. portable indication and some with no reported indications, was re-evaluated, using B&W equipmen This analysis verification was conducted in '

order to confirm the validity of the reported tubing conditio The analysis verification generally agreed with <

the reported result The tubes selected for analysis verification are listed below:

Row Column 48 37 48 35 48 41 45 42 45 47 l 47 61 l

(c) Discussions with B&W and licensee personnel indicated that the current data analysis procedure employed did not require that the data be evaluated by more than one ,

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analyst. B&W indicated that their contract did not include provisions for them to have the examination data analyzed by more than one analyst and, therefore, no second. analysis of the data was accomplished by them. The inspector pointed out. to the licensee that although there is no requirement to conduct a second evaluation of the data, that the economical consequences associated with a missed leaking tube through the use of-a single analysis could be i very profound. The probability L of this occurring is l documented in IE Information Notice 84-49. Further !

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discussions with the licensee indicated that Duke Power was in the process of qualifying some of their personnel to perform eddy current data analysis and will be utilizing j these examiners once the program is establishe The NRC inspector indicated to the licensee, that unless these examiners were going to be re-evaluating 100% of the data, I that it still wculd only amount to a sampling and that '

provisions for a second-evaluation of all data should b included as part of their eddy current examination program as this ha:: become common. practice through out most of the industry. The inspector 'strongly recommended that the 4 in-house data analysis program be given high priority and that a second analysis of the examination data be 1 accomplished commencing with tho'next required eddy current l examination No violations or deviations were identified in this area of inspection, g i Upper Head Safety Injection Piping Deletion Radiography Unit 1 (57090) j Radiography activities associated with the welds generated by the deletion j of piping in the safety injection system were reviewed as documented i below, j The inspector reviewed radiographer procedure NDE-10 Rev."16 ' General Radiography Procedure," to determine whether it contained sufficient !

information to assure that the following parameters were specified and controlled within the limits permitted by the applicable code, or ]i any additional specification requirement: type of material to be I radiographer; material and weld surface condition requirements; type i of radiation source, effective focal spot or effective source size; I film branch or type; number of films in cassette; minimum source to film distance; type and thickness of intensifying screens and filters; quality of radiographs; film density and contrast for single ,

l and composite viewing; use of densitometers for assuring compliance '

with film density requirements; system of radiograph identification; use of location markers; methods of reducing and testing for 4 back-scatter; selection of penetrameters including penetrometer !

placement; number of penetrameters; shims under penetrameters; radiographic technique for double wall viewing; and, evaluation and l disposition of radiograph l

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11 The inspector performed an independent evaluation of the below listed finally accepted welds to determine if radiographic film quality was in accordance with the applicable procedure and Code requirements and-to specifically verify the following: penetrometer type, size, and placement; penetrometer sensitivity; film density and density variation; film identification; film quality; and weld coverag Weld ID Drawing N Film View Evaluated NI1F-644 MCFI-INI-62 0-1, 1-2, 2-3, 3-4, 4-5, 5-0 NI1F-2898 MCFI-1NI-80 0-1, 1-2, 2-3, 3-4, 4-5, 5-0 NI1FW-50-5 MCFI-INI-50 0-1, 1-2, 2-3, 3-4, 4-5, 5-0 ,

NI1FW-50-1 MCFI-1NI-50 0-1, 1-2, 2-3, 3-4, 4-5, 5-0 The inspector reviewed the examination records for the above listed welds to determine compliance with procedure requirements for examination records and to determine if the reported disposition of the welds was consistent with the independent evaluation and in compliance with the applicable Code and specification requirement The inspector found no discrepancies, A review of qualification records for three radiographic examination personnel was accomplished to determine whether the qualification records reflect the employer's name, person certified, activity qualified to perform, level of qualification, effective period of certification, basis used for certification, and annual visual acuit The inspector confirmed the calibration status for densitometers 26083 and 285 The inspector reviewed the weld process sheets for welds NI1F-644 and ;

NI1F-2898 and weld material issue slips for weld rod #951997 (work request), material ER308-1/8", heat / lot #464390 to ascertain if the ;

documents were complete and accurat )

l Within the areas examined, no violations or deviations were identifie . IE Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants Units 1 and 2 The licensee has officially responded to the requirements of Bulletin 87-01; however, a final review of the response has not yet been completed within the NRC. The inspector conducted a review of documentation and data relative to the actions being generated as a result of this bulleti j The inspector also observed work being performed as a result of actions J being taken by the licensee. The documentation reviews and observations j conducted by the inspector are documented in the following subparagraph l l Plan Review The inspector reviewed the below listed documents relating to the inspection plan in the areas of: plan approval; general QA requirements; examination procedures; control of examinations and :

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,! t o4 PT/0/8/47U(5M ?drEdPc In.spectirp of Piping Wall Thickness

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Pipe Eqos1cd Con'rol Program Manual (second draft)

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McGuin\NMiear Station Pipe Erosion Study August,1987

, 7 't \ 3 The inspector,. reviewed C1tras6nic Procedure NDE-40 R This procedure is being utilized to'obtain the thickyess readings. required by the licensees inspection plan. 'The procedures was reviewed in the i areas of procedure approval, requirements for qualification of NDE 4( personnel, and compilation of required record I The inspector ob3 nva6approximately 400 thickness readings being taken on the 1 tea.s li'stepj belcw. The inspector also reviewed certification recoras of 3quipment, materials, and NDE personnel be{ng udlized during the examination of these item o

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jestLocation Drawing N \

14S-59 7,

1408-19.02-00

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, ,Tht' inspector conddt;ed ar, independent verification on several of t / thickness readings Oken on the above test locations. The

!? verification readirigd kre uade fc.110 wing the completion of the 7 /_ examinations conducted by if;.ensee personnel and with the use of the licensee's equipment, cadp y et, and calibration bloc The

< verification readings obtained were within an acceptable tolerance i

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" range althougl(lacement.rainor to transducer p ' deviations wer,e noted that could be attributed i.' s s e The inspector reviewed the thickne s data and associated records for

" the Unit 1 test locations indicateu b?. low. The data was reviewed to l determine whether the reptrted thinne.i;r/ was dnnsistent with the data  !

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$i '() compliancewithchqu/rimentsforexaminationrecord g f\(f ,

Test Location Drawing N I' '

1HSIA 1408-19.01-00 1HS9 1408-19.01-01 1HS52 M 08 19'. 01-00 (

1HS59 140M'19. 0E-00 ,

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1HS100 1400M9.02-01 > S

\. Discussions with licensee pecsonnel and a review of the completed data from Unit 2 shows that replacement of three items was necessary i

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in Unit 2 and that currently in Unit 1, three items are scheduled for 3 .-

< replacement due to the wall thickness being very near minimum in two ,

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- cases and' the wall thickness ' being below minimum .in one cas The schedule' examinations for Unit I have.not yet been complete In!this area of inspection, no violations'or deviations were identified.'

8. . .NRC Information Notice. No. 87-36, ' Significant . Unexpected Erosion of Feedwater; Lines (August 9,1987)

Discussions with' site personnel . indicated that they had no_ knowledge of

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.this notic The inspector suggested that' they make an effort -to determine what actions.they will be tak'.ng with regard to:the notice since the areas highlighted by the notice are on straight runs of pipe:in safety-related portions of Class 2 piping inside . containment. Further,

'wi.th Unit 1 down for refueling, this would be an opportune time.to examin the piping -in that unit. -The inspector indicated thatLtheir. actions

. relating to this notice would be reviewed during a future inspectio . Inspector Followup Items (IFI)'

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.(Closed) IFI 369, 370/85-05-03, Demonstrate Capability of Transducer to Detect a-Notch Reflector'in Centrifuga11y Cast Stainless Steel. Licensee representatives visited the Region II offices- on October 2,1987, and demonstrated-in the capability the centrifuga11 of their cast stainless equipCCSS)

steel (mentcalibration to detect blocks notch.and reflectors on a CCSS block containing actual crack This matter is considered closed.

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