IR 05000327/1978041
| ML19276E595 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/03/1979 |
| From: | Conlon T, Vandoorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19276E582 | List: |
| References | |
| 50-327-78-41, NUDOCS 7903200038 | |
| Download: ML19276E595 (5) | |
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Report No.:
50-327/78-41 Docket No.:
50-327 License No.: CPPR-72 Category: A3 Licensee: Tennessee Valley Authority Facility Name: Sequoyah Nuclear Plant, Unit 1
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Inspection at: Daisy, Tennessee Inspection Conducted: December 11 and 13-15, 1978 Inspector:
P. K. VanDoorn Reviewed by:
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/ F Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Inspection Summary Inspection on December 11, 13-15, 1978 (Report No. 50-327/78-41)
Areas Inspected:
Preservice inspection program, procedures and work activities. The inspection involved 28 inspector-hours onsite by one inspector.
Results: Of the three areas inspected, no apparent items of noncompliance or deviations were identified in one area; two apparent items of noncom-pliance vere identified in two areas (Infraction - UT procedure failed to provide for code required daily calibration - Paragraph 6; Infraction -
Failure to follow procedural instrument calibration requirements -
Paragraph 7).
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RII Rpt. No. 50-327/78-41 1-1 k
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y DETAILS I Prepared by
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P. K. VanDoorn, Metallurgical Edgineer Da e Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Dates of Inspection: December 11, 13-15, 1978 Reviewed by:_
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/f g T. E. Conlon, Chief ate Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch 1.
Persons Contacted a.
Tennessee Valley Authority (TVA)
- J. M. Ballentire, Power Plant Superintendent G. G. Stack, Project Manager, Construction C. R. Brimer, Outage Director
- G. L. Belew, Mechanical Engineer
- K. E. Vanhorn, Engineering Aid R. H. Daniels, Level III Examiner J. L. Goodner, Engineering Aid b.
Lambert, MacGill and Thomas, Inc. (LMT)
J. Hill, UT Supervisor
- Denotes those present at the exit interview.
2.
Licensee Actions on Previous Inspection Findings Licensee actions on previous inspection findings were not inspected.
3.
Unresolved items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Two unresolved items disclosed during the inspection are discussed in paragraph 5.
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RII Rpt. No. 50-327/78-41 1-;
4.
Exit laterview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection to summarize the scope and findings of the inspection. The two unresolved items described in paragraph 5 and the two noncompliances described in paragraphs 5 and 6 were discussed in detail. The licensee acknowledged the inspector's findings.
5.
Preservice Inspection - Review of Program The applicable code for the preservice inspection (PSI) program is the ASME Boiler and Pressure Vessel Code Section XI, 1974 Edition plus Addenda through the summer of 1975.
The inspector reviewed the preservice program through Revision 5 to determine if requirements were being met.
The procedures listed in paragraph 5 also form a portion of the PSI program and were reviewed for programatic requirements as part of the program review.
The areas reviewed were as follows:
appropriate program approval; specification of quality requirements such as examination reports, acceptance criteria, and required documentation; procedu re/ document control and review; generation of material certifications; identification of systems and components covered by the program including examination category and extent of inspection; establichment of inspection procedures; availability of procedures to QA and QC personnel; control of special processes; personnel qualification; controls on acceptance criteria and evaluation and reporting of results; equipment calibration.
No items of noncompliance or deviations were identified.
6.
Preservice Inspection - Review of Procedures a.
The applicable Code is delineated in paragraph 4.
TVA has contracted the LMT company to pe rfo rm the manual ultrasonic testing (UT) portion of the PSI program. The inspect ar reviewed TVA procedure SQ-UT-1, Rev. 1 - Ultrasonic Examination of Nuclear Coolant System Piping and LMT procedure UT-2, Rev. 11 - Nuclear Prese rvice Ultrasonic Examination of Ferritic Butt Welds and Adjacent Base Metal in the 21/2-inch and Greater Thickness Range to determine if requirements were being met.
Areas reviewed were as follows: procedure approval; qualification of NDE personnel; methods and extent of examinations; type of
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RII Rpt. No. 50-327/78-41 I-3 equipment used including frequency range, linearity accuracy, signal attenuation accuracy, size of search units, and beam angles; calibrations; DAC curves; reference level and scanning level requirements; methods of demonstrating penetration; establishment of evaluation limits; methods of recording indications; and establishment of appropriate records such as data sheets, strip chart recordings, equipment data and calibration, and material certifications as applicable.
b.
During observation of UT activities on reactor coolant pipe welds the inspector noted that a technique other than that which is normally applied to pipe welds was being applied. The technique consisted of a refracted 40-degree longitudinal wave inspection rather than the normally used shear wave inspection.
The inspector was informed that this method was necessary due to the inherent limitations provided by the cast stainless steel material used for reactor coolant piping. The inspector was also informed that this method was more limited than the shear wave method in its ability to locate indications but was the best method that has been developed to date for the cast material.
Although the equipment used for this method is involved in the procedures under general equipment lists, the inspector considers that the procedures used for this inspection should specifically describe this special method and its inherent limits in order that the personnel cognizant over these procedures are made well aware of the technique being utilized. This is Unresolved Item No. 78-41-01 - Documentation of special UT process used for RC piping inspection.
c.
During review of procedural requirements for linearity calibrations for UT of piping and subsequent review of calibration records it was noted that these calibrations were not always performed on a daily basis. The inspector was informed that it was LMT's policy to perform these calibrations daily although the applicable Code (ASME Section V which is referenced by Section XI) only requires these calibrations every 90 days (three months). The applicable procedure (SQ-UT-1) contains only the 90 day requirement. This item will remain open until it can be determined if daily calibrations are to be performed and if so, they (calibrations) should be prescribed by the procedure. This is Unresolved Item 78-41-02.
d.
The ASME Boiler and Pressure Vessel Code Section XI, Appendix 1, paragraph I-4230, IR74 Edition through Summer 1975 Addenda requires daily UT insErument calibrations for amplitude linearity
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RII Rpt. No. 50-327/78-41 I-4 and amplitude control linearity for UT of ferritic pressure vessels 21/2-inch and greater in thickness. During review of the applicable precedure (UT-2, Rev. 11) the inspector noticed that this daily calibration requirement was not delineated in the procedure.
This is in noncompliance with 10 CFR, Appendix B, Criterion IX as implemented by the FSAR, paragraph 17.1A.9. This item is Infraction No. 78-41-03 - Failure to provide controls for linearity calibrations for UT of ferritic vessels 2 1/2-inch and greater in thickness.
No items of noncompliance or deviations, except as delineated in paragraph 6.d., were identified.
7.
Preservice Inspection - Observation of Work and Work Activities The applicable Code is delineated in paragraph 4.
The inspector a.
observed manual UT examinations of specific welds to determine if requirements were being met.
Specifically observed were 45 shear wave inspection of pressurizer nozzle to vessel welds RCW-15, -18 and -20; and refracted L-wave inspection of reactor coolant weld RC-6 and portions of weld RC-4SI. Areas reviewed included personnel qualifications; conf o rmance to the PSI program; familiarity of examination 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 calibration; DAC curves; scanning and reference sensitivity; and methods and levels for recording and evaluating indications.
b.
Ultrasonic test procedure UT-2, Rev. 11, paragraph VII states
" Ultrasonic testers shall have their proper internal
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alignment and calibration verified within 90 days of use.
On December 11, 1978, the inspector observed UT tester Serial No.
130-063-D being used for testing of pressurizer nozzle to vessel welds RCW-15, -18 and -20.
On December 13, 1978, during review of calibration certification for UT tester Serial No. 130-063-D the inspector noticed that the most recent calibration was performed on September 6,1978. This is in r.oncompliance with 10 CFR 50, Appendix B, Criterion V as implemented by the FSAR, paragraph 17.1A.S.
This item is Infraction No. 78-41-04 - Failure to follow procedure for calibration and internal alignment of UT tester.
No items of noncompliance or deviations, except as delineated in paragraph 7.b., were filentified.
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