IR 05000327/1979006
| ML19270F732 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/09/1979 |
| From: | Conlon T, Vandoorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19270F729 | List: |
| References | |
| 50-327-79-06, 50-327-79-6, NUDOCS 7903210043 | |
| Download: ML19270F732 (3) | |
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Report No..
50-327/79-06 Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Facility Name:
Sequoyah Nuclear Plant, Unit 1 Docket No.: 50-327 License No.-
CPPR-72 Inspection at Sequoyah Nuclear Plant near Daisy, Tennessee G
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P. K.' VanDoorn Date Signed Approved by w Mr'b2, '
d!C/ '/ 9 T. E. Conlon, Section Chief, RC&ES Branch Date Signed'
SUMMARY Inspection on January 16 through January 19, 1979 Areas Inspected This routine announced inspection involved 26 inspector-hours onsite in the areas of preservice inspection program, procedures, work activities and records.
Results No apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees J. M. Ballentine, Plant Superintendent
- C.
E. Cantrill, Assistant Plant Superintendent
- W. E. Andrews, QA Staff Supervisor R. H. Daniels, Level III Examiner E. D. Crane, PSI Coordinator Other licensee employees contacted included three technicians.
Southwest Research Institute (SwRI)
E. C. Leonard, Project Director
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 19, 1979 with those persons indicated in Paragraph 1 above.
The inspector followup item described in paragraph 5 below was discussed in detail.
3.
Licensee Action on Previous Inspection Findings Not Inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort a.
The inspector observed UT calibration activities for pressurizer seam weld W-P1 to determine if Code and procedure requirements were being met.
The applicable Code for preservice inspection (PSI) is the ASME Boiler and Pressure Vessel Code Section XI, 1974 edition plus addenda through the summer of 1975.
b.
The inspector observed re-UT of pipe weld RHRS-119 by TVA personnel.
The inspector also reviewed the TVA contractor's PSI report for this weld. This report indicated an indication of 100% DAC maxi-mum with significant metal travel. TVA's inspection verified the presence of the indication. TVA did not decide during the inspection
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-2-if the veld would be repaired. Therefore, disposition of this indication will be an inspector followup item until TVA action on this item can be reviewed. Inis is item No. 50-327/79-06-01.
No itens of noncompliance or deviations were identified.
6.
Preservice Inspection - Review of Program The inspector reviewed the SwRI Project Plan No. 78-TVA-SNP-1-1-0 for the reactor vessel inspection to determine if work and inspection procedures for PSI were established, qualified, and available to inspection personnel and that these procedures were complete, reviewed, approved, and controlled. The applicable Code for PSI is identified in paragraph 5.a.
No items of noncompliance or deviations were identified.
7.
Preservice Inspection - Review of Procedures The applicable Code is identified in paragraph 5.a.
The inspector reviewed in detail procedures SwRI-NDT-700-6, Revision 1 (" Mechanized Ultrasonic Examination of Ferritic Vessels 2 1/2" or greater in Thickness") and SwRI-NDT-300-2, Revision 23 ("Flourescent Magnetic Particle Examination") to determine if inspections were adequately controlled and Code requirements were delineated. The following areas were considered in the review:
(UT) procedure approval; qualification of NDE personnel; methods a.
and extent of examinations; type of equipment used for UT including frequency range, linearity accuracy, signal attenuatic, accuracy, size of search units, and beam angles, calibrations; DAC curves; reference level and scanning level requirements; methods of demon-strating penetrations; establishment of evaluation limits; methods of recording indications; and establishment of appropriate records such as data sheets, strip chart recordings, magnetic tape recordings, video tape recordings, equipment data and calibrations, and material certifications.
b.
(MT) Procedure approval; qualification of NDE personnel; extent of examination; method / technique specified including surface preparation, specification of continuous current, particles and liquid medium, surface temperature, viewing conditions, overlap, field directions, pole spacing for yoke method, lifting power requirements, and black light requirements; and specification of acceptance criteria.
No items of noncompliance or deviations were identifie.
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Preservice Inspection - Observation of Work and Work Activities The applicable code is identified in paragraph 5.a.
The inspector observed the counter-clockwise transverse 45 degree and 60 degree UT scan of reactor vessel circumferential seam weld W-04-05 and flourescent magnetic particle (MT) inspection of reactor vessel stud No. 33 to determine if NRC, procedure and Code requirements were being met.
Areas reviewed included the following:
a.
(UT) personnel qualifications; conformance to PSI program and procedures; familiarity of personnel with methods and equipment; reference points; type of apparatus used including frequency range, size and type of search units, linearity, and beam angles; method employed including extent of coverage; equipment calibrations; DAC curves; scanning and reference sensitivity; methods and levels for recording and evaluating indications; and automated recording of examinations by strip chart recorders, magnetic tape and video tape.
b.
(MT) Confo rmance to program and procedure; familiarity of per-sonnel with methods and equipment; reference points; examination by continuous method; particles including liquid medium; surface temperature; viewing conditions; examination overlap; field directions; yoke pole spacing; yoke lifting power; and examination results.
No items of noncompliance or deviations were identified.
9.
Preservice Inspection - Data Review and Evaluation The applicable Code is identified in paragraph 5.a.
The inspector reviewed the temporary filing system for reactor vessel inspections; records of UT inspection of lower head meridional weld numbers W2B and W2C; and records of MT inspection of reactor vessel stud numbers 3, 5A, 10, 13, 15, 16, 19, 20, 21, 22, 2'
24A, 25, 26, 27A, 28, 29, 30A, 31, 35, 36, 37, 47 and 61 to determine if applicable requirements were being met. Areas reviewed included: conformance to program and proce-dures; acceptance criteria; recording and evaluation of results/ findings; equipment data; calibration data; identification of couplant; availability of films and tapes; extent of examination; and records of any deviations from the program or procedures.
No items of noncompliance or deviations were identified.