IR 05000313/1990040

Insp Repts 50-313/90-40 & 50-368/90-40 on 901015-19.No Violations or Deviations Noted.Areas Inspected:Inservice Insp Work Activities & Insp of Action on Previously Identified Insp Finding

ML20062D583
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/29/1990
From:	Barnes I, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20062D582	List: IR 05000313/1990040 ML20062D576
References
50-313-90-40, 50-368-90-40, NUDOCS 9011130371
Download: ML20062D583 (4)

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APPENDIX V.S. NUCLEAR REGULATORY COMMISSION

REGION IV

HRC Inspection Report: 50-313/90-40 Operating Licenses: DPR-51 50-368/90-40 NPF-6 Dockets: 50-313 50-368 Licensee: Entergy Operations, In Route 3, Box 137G Russel_1ville, Arkansas 72801 Facility Name: ArkansasNuclearOne(ANO), Units 1and2 Inspection At: ANO, Russellville, Arkansas inspection Conducted: October 15-19, 1990 Inspector: 8w /o/2 9 /t o p W. M. McNeill, Reactor Inspector, Materials Date and Quality Programs Section, Division of Reactor Safety

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Approved: I8 % eoA9/9 o T. Barnes, cnief, Materials and quality Date Programs Section' Division of Reactor Safety

Inspection Summary Inspection Conducted October 15-19. 1990 (Report 50-313/90-40).

l Areas Inspected: Routine, unannounced inspection of inservice inspection work activitie Results: Within the area inspected, no violations or deviations were identifie Eased on the observations of the available work in process, it appeared that

'the inservice inspection program was adequate and effectively implemente Inspection Conducted October 15-19, 1990 (Report 50-368/90-40)

Areas Inspected: Routine, unannounced inspection of action on a previously identified inspection findin Results: Unresolved item 368/8939-02 was satisfactorily close DR ADOCKOSOOg3 L

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DETAILS PERSONS C0llTACTED 1.1.- Entergy Operations. In *D. Boyd, Licensing Specialist

• P. Campbell,InserviceInspection(ISI) Engineer

• M. Cooper, Licensing Specialist

• R. Clark, Licensing Specialist

• G..Dobbs, Supervisor Engineering

• C Eubanks, Lead Enginee fl.-A. Finney, Level III

• J. Fisicaro, Manager, Licensing C. Forpahl, ISI Coordinator L. Humphrey, General Manager iluclear Quality

• D. James, Supervisor, Licensing R. King, Supervisor, Licensing

• R. Lane, Manager, Engineering Standards and Programs

• D. Lomax, Superintendent Engineering Programs

• K. Mulling, Containment Leak Rate Testing Engineer J. Ray,. Level III

• R.-Rispoli, Supervisor, Fire Protection

• J. Taylor. Brown, Quality Ccntrol/ Quality Engineering Superintendent

• J. Vanderorift, Unit 1 Plant Manager 1.2 Babcock & Wilcox (B&W)

L. Bryant, Task Leader R. Barnes, Level III-1.3 U.S.-Testing company, In R. Jackson, Level II R. itcClain, Level III 1.4 Hartford Steam Boiler Inspection and Insurance Company H. Erb, Authorized Nuclear Inspector 1.5 NRC

• C, Warren, Senior Resident Inspector

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• L. Smith, Resident Inspector

• Denotes those persons that attended the exit neeting on October 19, 199 i

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-3-1 ACTION ON A PP,EVIOUSLY IDENTIFIED IllSPECTION FINDING (92701)

(Closed)UnresolvedItem(368/8939-02): Revision of the inservice inspection (ISI) program for the second 10-year interval to require records of weld profiles, coverage plots of the examination volume, and assurance that all ultrasonic examination reflectors greater than 50 percent oi Distance Amplitude Curve (DAC)arerecorde The licensee has issued a procedure, 1415.007, that requires profiles to be made of welds and the areas of coverage established. A review by a licensee consultant of previous 151 data concluded that all reflectors required to be recorded were indeed recorded. This iten is considered close . INSERVICE INSPECTION (73753)

l The objective of this inspection was to ascertain whether performance of ISI l examinations and repair of components are in accordance with regulatory and l American Society of Mechanical Engineers (ASME) Code requirements, and '

correspondence between NRC and the licensee concerning relief requests. The inspector reviewed Unit 1 Technical Specifications, the Inservice Inspection Program Plan, Revision 19. and the following procedures:

Procedure 1415.004, " Liquid Penetrant Examination ASME Section IX, 1980/w81,"

Revision 0

Procedure 1409.276, " Inservice Inspection by B&W in AN0-1 A & B OTSG Tubing,"

Revision 0 It was noted that the Unit 1 ISI program plan is to be reviewed and revised by March 1992. This was committed to as corrective actions in Unit 2 Licensee Event Report 90-1 The inspector witnessed the performance of liquid penetrant examination (PT) of the thrre circunferential welds of line CCA-9-1 1/2, numbered FW 3C1, FW 401, and FF 802; and eddy current testing (ECT) of the once-through steam generator tubing. In addition, the inspector reviewed the radiographs of six circunferential

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weids of line CCA-5-2 1/2, numbered FW 61CC2, FW 62BC1, FW 94C1, FW 109 BC1,

'cW 114C1, and FW 115C1. All six of these welds are considered an ASME repair / replacement activit It was noted by the inspector that examination personnel appropriately complied with the examination, calibration, and documentation requirements of the approved procedures. The use of the correct ECT calibration standard was verified by the inspector. The inspector also checked the personnei certifications to verify that personnel were appropriately cualified for the examinations performed. The equipment used (Pi materials, and ECT probes) was found_to be approprietely certified and instruments calibrated as require The inspector noted a questionable practice in that radiographic reader sheets did not always have all indications found on film recorded and dispositione The licensee agreed to have all indications recorded and dispositione __

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The licensee identified to the inspector that an employee had expressed a concern about the effectiveness of ISI ultrasonic testing. In particular, the concern was that use of flat search units would result in a signal amplitude loss because of rocking and the subsequent loss of contact with small diameter pipe surfaces. The ASME Code controls this potential problem by specifying the maximum diameter of the search unit to be used for a given wall thickness. A search of the ISI records found that' search units used for the

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last Unit 2 outage met procedure and ASME Code requirements. A demonstration *

was performed with a 2 1/2-inch diameter calibration standard in both axial and circumferential directions. It was found that the amount of signal amplitude ,

loss caused by loss of contact when a flat search unit was rocked did not cause the signal to fall below the reference DAC, when complying with the ASME Code

. requirement for manual scanning using an additional six' decibels of sensitivity gain. The DAC is used as a reference level for establishing the indications to be investigated and recorded. In summary, this means that a flaw would be properly detected and evaluated even if-the search unit was rocked. Subsequent to the inspection, the inspector was informed that the licensee has elected to use contoured shoes for inspection of small diameter pipin The ISI activities were found to be satisfactory. No violations or deviations E were identifie , EXIT INTERVIEW An exit meeting was held on 0ctober 19, 1990,.with those individuals denoted in i

. paragraph 1 in which the inspection findings were summarized. The licensee did '

. not identify as proprietary.any of the information provided to, or reviewed by the inspecto i l

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