IR 05000296/1980038
| ML18025B378 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/03/1981 |
| From: | Girard E, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18025B377 | List: |
| References | |
| 50-296-80-38, NUDOCS 8103120436 | |
| Download: ML18025B378 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report No.
50-296/80-38 Licensee:
Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Faci lity Name:
Browns Ferry Docket No.
50-296 License No.
DPR-68 Inspection at Browns Ferry site near Decatur, AL Inspector EX E: H.
rard Approved by:
A.
. Herdt, Section Chief RCES Branch Date Signed ate Signed SUMMARY Inspection on December 2-5, 1980 Areas Inspected, This routine, announced inspection involved
inspector-hours on site in the areas of review of inservice inspection (ISI) data for pumps, review of reactor vessel fatigue useage factors, observation of inservice inspection work, and review of inservice inspection procedure.
Results No violations or deviations were identifie <<>-'-; I C~<'i* 4'
DETAILS Persons Contacted Licensee Employees
"H. L. Abercrombie, Plant Manager J. Swindell, Outage Director J. Rinne, Assistant Outage Director R. McPherson, Mechanical Engineer R. Callegari, ISI Coordinator R. Seals, Level II Examiner Other Organization
- C. Manzari, Authorized Nuclear Inspector, Hartford Steam Boiler NRC Resident Inspector
"R. Sullivan
"J. Chase
- G. Paulk
'Attended exit interview 2.
Exit Interview 3.
The. inspection scope and findings were summarized on" December 5,
1980, with those persons indicated in Paragraph 1. above.
Licensee Action on Previous Inspection Findings Not inspected.
Unresolved Items 5.
Unresolved items were'.not identified during this inspection.
Independent Inspection Review of I'nservice Inspection Data for Pumps.
The. inspector reviewed monthly data. for tests performed to verify com-pliance limits described'n Surveillance Instructions 3. 1.3 through.
3.1.6 for RHRSW, EECW, HPCI and RCIC, pumps.
Data was reviewed for June through November 198 b.
Review of Reactor Vessel Fatigue Useage Factors Section 6.6.A of the Technical Specification requires determination and reporting of fatigue useage factors for the reactor pressure vessel.
These factors are used in determining the need for additional inservice inspection.
The inspector reviewed the January 1980 monthly operating report to verify that the factors had been determined and reported.
Within the areas inspected no violations or deviations were identified.
6.
I'nservice Inspection - Observation of Work and Work Activities The inspector observed the ISI activities to determine their conformance with regulatory requirements and licensee procedures.
The code applicable for ISI is ASME Section XI (74S75).
The specific areas observed by the inspector are described below:
a.
Personnel qualification records were reviewed for two Level I',
two Level II's and one Level III examiner.
b.
Shear wave UT examination of welds DRWC 3-1 and -1A, DSRWC 3-4 and -7, and THPCI 3-66 were observed for use of approved procedure (N-UT-1) and specified equipment, examination personnel knowledgeable of requirements and properly qualified, data properly recorded, and conformance with procedure technical attributes (apparatus, coverage, scanning rate, calibration, search unit size and frequency, beam angles, DAC curve, and.reference. levels and recording method).
c'.
Visual exagjnatipn.iof the five above listed welds (as specified in UT procedure.
N-UT-1 Rev.
4 and the FSAR)
was observed for proper method, lighting, surface cleanliness and review of results.
h Within the areas examined, no violations or deviations were identified.
7.
Inservice Inspection - Review of Procedure The licensee's required ISI nondestructive examinations for this outage were limited to ultrasonic and visual examinations of piping welds.
The inspector examined the licensee's procedure for the examinations and determined that it-had not: been revised since. its review in NRC Inspection Report No.
50'-260/80"28..
Within the: areas. examined, no. violations, or deviations were identifie si'
'