IR 05000395/1993013

Insp Rept 50-395/93-13 on 930412-16.No Violations or Deviations Noted.Major Areas Inspected:Isi,Sg Tube Specimen Removal,Sg Replacement Project & Flow Accelerated Corrosion

ML20035H327
Person / Time
Site:	Summer
Issue date:	04/26/1993
From:	Blake J, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20035H324	List: IR 05000395/1993013 ML20035H323
References
50-395-93-13, NUDOCS 9305040219
Download: ML20035H327 (9)

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UallTED STATES g

WUCLEAR REGULATORY COMMisslON

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101 MARf ETTA STREET N.W.

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ATLANT A GEORGI A 30323

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Report No.:

50-395/93-13 Licensee: South Carolina Electric & Gas Company Columbia, SC 29218 Docket No.:

50-395 License No.: NPF-12 Facility Name: Summer Inspection Cond t y il 12-16, 1993 Y ff Inspector: /

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W jf M einsorge P.

Date/Si'gned pactorInspecty Approved by:

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( BJitke, Chief Date Signed

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Ma) r}41s and Process Section Entj neering Branch Division of Reactor Safety

SUMMARY Scope:

This routine, announced inspection was conducted in the areas of Inservice Inspection (ISI), steam generator tube specimen removal, the steam generator replacement project, and Flow Accelerated Corrosion (FAC).

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Results:

With the exception of a few discrepancies in the ISI area, records supported the accomplishment of activities consistent with regulatory and procedural

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requirements.

In the area of the steam generator replacement project activi-

ties observed were consistent with procedural requirements. The licensee has

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established an effective FAC program and continues to maintain high energy

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carbon steel piping systems within acceptable wall thickness limits.

In the areas inspected, no violations or deviations were identified.

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9305040219 930428 ADOCK0500g5 PDR G

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REPORT DETAILS 1.

Persons Contacted Licensee Employees

• R. Clary, Manager, Steam Generator Project

• H. Fowlkes, Manager, Nuclear Licensing & Operating Experience

• S. Hunt, Manager, Quality Services

• D. Lavigne, General Manager, Nuclear Safety

• H. Quinton, General Manager, Engineering Services

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%. Torres, Associate Manager, Quality Control

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• K. Woodward, Manager, Training Other licensee employees contacted included engineers, technicians, mechanics, security force members, and office personnel.

NRC Resident Inspectors

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• R. Haag, Senior Resident Inspector (SRI)

L. Keller Resident Inspector (RI)

• Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragraph.

2.

Inservice Inspection (ISI)

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The inspector reviewed documents and records, and observed activities, as indicated below, to determine whether ISI was being conducted in i

accordance with applicable procedures, regulatory requirements, and f

licensee commitments. The applicable code for ISI, is the A P B&PV Code,Section XI, 1977 Edition with Addenda through Summer 1978 (77S78).

The plant has completed the seventh fuel cycle, and is in the second outage (Refueling Outage (RF0) 7), of the third 40 month period, of the first ten year ISI interval (02,P3,II). The plant received its operating license August 6,1982 and commenced commercial operations on January 1,1984.

The-licensee, South Carolina Electric and Gas (SCE&G)

l Company, has contracted with Ebasco to perform liquid penetrant-(PT),

magnetic particle (MT), visual (VT), and ultrasonic (UT) examinations

under the umbrella of the Ebasco Quality Assurance (QA) program. Some

MT, PT, VT, and UT examinations were performed by SCE&G, under their own

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QA program.

Eddy Current (E"; examination of, and tube removal from, the

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Steam Generators (S/Gs), was accomplished by Babcock and Wilcox (B&W)

under the umbrella of the B&W QA Program.

Evaluation of the removed S/G

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tube samples is being performed by Westinghouse (W).

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ISI Program Review, (73051)

l The inspector reviewed the following documents relating to the ISI

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program to determine whether the plan had been approved by the

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licensee and to assure that procedures and plans had been estab-j

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lished for the applicable activities. Documents were reviewed for

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technical content.

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Documents Reviewad j

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(RI)

NDE Plan Interval 1, Exam Period 3 l

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Observation of Work and Work Activities, (73753)

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Because the window of opportunity to observe active examination l

activities had passed, the inspector reviewed records of work

activities, reviewed certification records of NDE equipment'and

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materials, reviewed NDE personnel qualifications for personnel who had been utilized in the ISI examinations during this outage, and i

repairs and replacements. The reviews conducted by'the inspector j

are documented below.

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PT Examination Records Reviewed i

Inspection Reports Nos. VCSP-843 to VCSP-847 l

VCSP-849-to VCSP-851

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VCSP-853 to VCSP-856

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VCSP-866 to VCSP-871

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VCSP-874 to VCSP-877

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VCSP-884 to VCSP-886-i VCSP-892 to VCSP-899

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VCSP-901 to VCSP-904-

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o On several PT reports, the penetrant material batch numbers

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were not completely legible or were in error.

o Penetrant Materials

1 Penetrant: 321J47, 423J47, 428J48.

l Cleaner / Remover: 723L4,'431H4, 46F4, D46F4 l,

Developer: 45F6, 415B6,'828C6

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Certification documentation for Penetrant Batch No. 428J48, was..

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not retrievable. The licensee' indicated that that batch number-

had never. existed on the Summer site, and was documented in

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Thermometers.

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S/N:

FS-3268, FS-3282, FS-2284,:FS-2275

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MT Examination Records Reviewed

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I Inspection Reports Nos. VCSM-1294 to VCSM-1305 o

MT examination report No. VCSM-1301, the report of fluorescent HT examinations of bolting materials, included ultraviolet light intensity meter readings to substantiate adequate ultra-

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violet light intensity levels for the examinations. The report does not indicate which light meter was used, and thus there is no traceability to the calibration of that unidentified meter.

Without a paper trail to the meter calibration records the ultraviolet light intensity data is questionable.

e Relative to the MT examinations, the inspector reviewed certifica-tion documentation for the following MT Yokes, dry powder, prepared bath, UV Meters, and ten Lbs. test weights.

Yokes S/N:

2043, 192 Dry Powder Magnaflux 8A Red Batch No.87A030 Prepared Bath

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Magnaflux 14AM Batch 90A01K UV Meters S/N: 410700

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Ten Lbs. Test Weights

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LOT 14A UT Examination Records Reviewed Inspection Reports Nos.

VCSU-992 to VCSU-993 VCSU-1008 to VCSU-1014

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VCSU-1083 to VCSU-1085 VCSU-1090 VCSU-1098 to VCSU-Il06 VCSU-1108 l

VCSU-1111 to VCSU-1116 VCSU-Ill8 to VCSU-1166 VCSU-Il68 to VCSU-1183 VCSU-1185 to VCSU-ll87

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o The method of identifying UT instrument serial numbers and model numbers in many cases was not consistent.

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Relative to the UT examinations the inspector reviewed certification documentation for the following UT calibration blocks and standards, UT instruments, transducers, and complement.

UT Calibration Blocks and Standards CGE-3, CGE-4, CGE-5, CGE-II, CGE-12, CGE-13, CGE-14, CGE-15, CGE-16,

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CGE-19, CGE-21, CGE-22, CGE-30, CGE-37

UT Instruments

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S/N: 136-700I, 136-703I, 212525, 31459-136, 783, 1606, 27276-815,

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21322

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Transducers

S/N: E04501, D03783, G03519, 00258, B1033, C0266, G13737, B15900, K23705, D12127, 90808, 00290, B04717, B0342, 05604, J08808, F12437, 20917, 20976, G08236, 20887, D29157, F18752, 05604 Couplant Batch Nos. 9084, 9092, 8868 Visual Examination Records Examined Inspection Reports Nos. VCSV-5720 VCSV-5790 VCSV-5868 to VCSV-5891 NDE Examiners

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The inspector reviewed the following NDE examiner qualification, certification and visual acuity records.

Ebasco i

RB PT-II, UT-II, VT1-II, VT2-II, VT3&4-II PDD PT-II, MT-II, UT-I

MSS PT-III, UT-III, VT1-III, VT2-III, VT3&4-III

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RCD PT-II, MT-II, UT-II RM PT-II, MT-II, UT-II, VTI-II, VT3&4-II WS PT-II, MT-II, RT-II WJC PT-II, MT-II, UT-II, VT1-II, VT2-II, VT3&4-II MES PT-II, MT-II, UT-II MDR PT-III, MT-II, UT-III, VT1-II, VT2-I", VT3&4-II JBF PT-II, MT-II, UT-II, VT1-11, VT3&4-II i;MP PT-II, MT-II, UT-II, VT1-II

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Ebasco Cont'd

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JBV PT-II, MT-II, UT-II, VT1-II, VT3&4-II l

JMH PT-II, MT-II, UT-III

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JSB PT-II,'MT-II, UT-II, VT1-II, VT2-II, VT3&4-II j

JRW PT-II, MT-II, UT-II, VT1-II, VT2-II, VT3&4-II

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DRR PT-II, MT-II, UT-II, VT1-II, VT2-II, VT3&4-II SCE&G l

BM UT-II JCH PT-II, MT-II, VT-II

ARC RT-III, PT-III, MT-III, UT-III j

Repairs and Replacement Records

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WR-202850116 Fabricate and install Component Cooling (CC) system j

Pipe Support CCH-5042 l

WR-202850106 Fabricate and install strut on CC Pipe' Support

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CCH-1544

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WR-221140253 Install orifice and relocate Valve IXP-9098B-HR

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I At the time of this inspection, records supporting the accomplishment of'

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the ET examination of the S/G tubing and UT examination of the Reactor

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Pressure Vessel were not available for inspection, as they.had not been

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l Except as noted above, records supported the. accomplishment of activities

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consistent with regulatory and procedural requirements.

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In the areas inspected, no violations or deviations were identified.

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3.

Steam Generator Tube Specimen Removal The licensee had three tube specimens removed from the "B" S/G (R28C41,

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R33C20, and R42C43). The tubes were cut three inches'below the-first hot

.i leg support plate (02H)', and removed from the hot-leg side.. The-i inspector reviewed procedures and records as-indicated below:

l Procedures Reviewed

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ID Revision-Title

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B&W-1151433A (RI9)

SG Tube Pull Field Procedure / Operating i

Instructions

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Procedures Reviewed Cont'd i

ID Revision Title

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B&W-1195428A (R3)

Welch-Allyn Video Probe Operating i

Instructions

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B&W-1195484A (R2)

Operating Instructions for Tube Cleaning Prior to Tube Relaxation With Goodway

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Pneumatic Cleaning System

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t B&W-1204850A (R4)

RSG Tube Relaxation Weld Head Operating

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Instructions Using the Flex-Torch System j

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B&W-1198512A (R3)

Operating Instructions for the Remote Tube l

Pull Jack Using The Manual Control Box

B&W-1217054A (R4)

Tube Pull Sample Handling Procedure

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I The inspector viewed video tapes of the removal operations. The

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inspector examined selected records including tool accountability data i

sheets and open system logs.

Activities observed were consistent with procedural requirements.

In the areas inspected, no violations or deviations were identified.

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4.

Steam Generator Replacement Project

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f SCE&G has selected Bechtel Power Corporation (BPC) as the' prime contrac-L tor for the replacement of their S/Gs. Power Cutting Incorporated _(PCI)

i a subsidiary of )! is collecting data, using the CMS-3000 laser coordinate.

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measurement system from the Chesapeake Laser Systems of Lanham, MD. This i

data will be incorporated into an existing computer model of the reactor containment building.

This information will be used to engineer the delivery of the existing and replacement S/Gs through the equipment hatch and surrounding area.

In addition PCI will be templating the Reactor Coolant system nozzle connections.to the ~ existing S/Gs, the connection of

the column supports to the existing and replacement S/Gs, and the Reactor

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Coolant nozzles on the replacement S/Gs to facilitate installation, weld'

end~ preparation, and fitup.

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The Chesapeake Laser System Coordinate Measurement System CMS-3000 is a i

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servo controlled tracking laser interferometer measuring tool. The tracker follows a retro target while giving real. time coordinate informa'-

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' tion to the retro center location. The retro center is measured in

spherical. coordinates where distance from the tracker axis to the retro

center is determined by laser interferometer, the azimuth angle is

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determined by the laser rotary encoder in the azimuth axis and the l

elevation angle in the elevation rotary encoder.

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The inspector reviewed procedures, interviewed licensee and contractor

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personnel, and observed a portion of the data collection activities

associated with the "C" cubical shield wall, in the reactor containment

building.

Procedures Reviewed ID Revision Title PCI PI-6514-05 (RI)

As-Built Survey of Reactor Building Access

Hatch Area Using Laser Coordinate Measuring

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System

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Records support accomplishment of activities consistent with procedural requirements.

In the areas inspected, no violations or deviations were identified.

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Flow Accelerated Corrosion (FAC) (49001)

The licensee has established a FAC inspection program which fully

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implements the EPRI (Electric Power Research Institute) CHECHATES l

computer code, including T-Dat, industry experience, and previous inspec-

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tion data as predictive tools for the determining and prioritizing inspection locations.

During RF0 7, the licensee planned to examine 50 components in their FAC-

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program. At this writing the licensee has identified two components for replacement:

12" 90' elboy EX-02-E09 (NCN 4716) and 12" 90* elbow EX-02-E07 (NCN 4710).

Both elbows are in the Extraction system. The sample has now expanded to 57 components, and examination continues.

In the small bore area, the licensee has monitored the Main Steam Drains and the Extraction Steam Drains over the past two cycles and noted them to be problem areas.

For this reason the licensee is in the process of a change out of approximately 1200 linear feet of Main Steam Drains (l" to 21") carbon steel pipe and approximately 800 linear feet of Extraction Steam Drains (l" to 21") carbon steel pipe with 21Cr-Mo pipe.

The inspector conducted interviews with licensee personnel, reviewed NCN Nos. 4710 and 4716, and examined one of the removed elbows.

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The licensee has established an effective FAC program and continues to maintain high energy carbon steel piping systems within acceptable wall thickness limits.

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Exit Interview The inspection scope and results were summarized on April 16, 1993, with those persons indicated in paragraph 1.

The inspector described the areas inspected. Although reviewed during this inspection, proprietary information is not contained in this report.

Dissenting comments were not received from the licensee.

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Acronyms and Initialisms 77S78

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1977 Edition Summer 1978 Addenda ASME

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American Society of Mechanical Engineers BPC

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Bechtel Power Corporation B&PV

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Boiler and Pressura Vessel B&W Babcock and Wilcox

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CC

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Component Cooling CMS

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Coordinate Measuring System EPRI

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Electric Power Research Institute ET

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Eddy Current FAC

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Flow Accelerated Corrosion ID

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Identification ISI

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Inservice Inspection NDE

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Nondestructive Examination MT

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Magnetic Particle NCN Nonconformance Notice

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Number NPF

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Nuclear Power Facility NRC

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Nuclear Regulatory Commission PCI

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Power Cutting Incorporated P.E.

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Professional Engineer PT Liquid Penetrant

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QA

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Quality Assurance R

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Revision RF0

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Refueling Outage RI

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Resident Inspector RT

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Radiography S/N

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Serial Number SRI

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Senior Resident Inspector UT

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Ultrasonic VT

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Visual UV

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Ultraviolet

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W Westinghouse Company

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