IR 05000339/1979017
| ML19274F018 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/28/1979 |
| From: | Conlon T, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19274F016 | List: |
| References | |
| 50-339-79-17, NUDOCS 7906070114 | |
| Download: ML19274F018 (5) | |
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UNITED STATE 3
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Report No. 50-339/79-17 Licensee: Virginia Electric and Power Company P. O. Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Power Station, Unit 2 Docket No. 50-339 License No.
CFPR-78 Inspection at Louisa unty, Virginia -
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Inspector:
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7[S.5/79 Approved by:
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lon, Section Chief, RCES Branch
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Inspection on March 6-8, 1979 Areas Inspected This routine, unannounced inspection involved 17 inspector-hours onsite in the areas of preservice inspection of reactor vessel welds and steam generator
"C" tube work observation, data review and evaluation.
Results Of the two areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted a.
Licensee Employees
- W.
R. Cartwright, Station Manager
- H. L. Travis, Senior Engineer Technician - NDE
- W. R. Madison, NRC Coordinator Other licensee employees contacted during this inspection included
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technicians.
b.
Other Organizations Westinghouse - Nuclear t-vices Division (W)
N. A. Bollingmo, Level II Examiner J. J. Stepek, Level II Examiner Automation Industries (CONAM)
K. Lofgren, Data Analyst NRC Resident Inspector M. S. Kidd
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 8, 1979, with those persons indicated in Paragraph I above. Inspection areas included preservice inspection of reactor vessel welds and steam generator tube eddy current examination.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. New unresolved items identified during this inspection are discussed in paragraph 8.
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Independent Inspection Effort Discussions with the licensee concerning frequency of calibration s
requirements as they relate to section 4.5.1 of }[ procedure ISI-205 R/2 reported under inspector followup item (IFI) 78-21-01 in paragraph 5.b(2)
of report RII:78-21 cleared the inspector's concern.
The question concerning deletion of straight beam examination of pipe welds and adjacent base metal during inservice inspections discussed
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under IFI (78-21-01) in paragraph 5.b.(1) of the above mentioned report remains open and will be reviewed further during a future RII inspection.
6.
Preservice Inspection (PSI), Observation of Work and Work Activities This inspection was perforiced in order to conclude the work observation phase of the PSI activities. Previous work effort in this area was documented in reports RII:78-21 and 78-24.
At the time of this inspection
}[ was in the process of examining the reactor vessel with their remote control, ultrasonic inspection tool.
In general, the preservice examination is being conducted in accordance with the requirements of Section XI of the ASME Code, 1974 Edition up to and including the Summer 1975 addenda.
Details of the Reactor vessel examination are contained in }[ procedures ISI-52, R/6, 2/6/77 including its appendices and WMF-INSP-201, R/0, 9/1/76.
System calibration was performed earlier and was discussed in report RII;78-37. The inspector observed the ultrasonic examination of the first segment of the lower head to shell weld. The scan covered approxi-mately seven (7) feet of weld with straight and angle beam transducers.
The scanned weld segment was between -15.2330 and -71.6780 coordinates, as measured from the reactor vessel zero stud hole which was used as the datum point. Within this area the inspector observed amplitude control and amplitude linearity checks and, scanning of t'he aforementioned weld.
There were no recordable indications identified. The inspection program procedure, applicable drawings, equipment and personnel certifications /
qualifications were reviewed. Within this area the inspector noted that the location of the four core support lugs inside the vessel precluded examination of the entire weld volume.
Examination of the inaccessible areas will be performed manually.
The limited automated inspection of this area will be noted in the final report as having been performed on a best effort basis. Also it was noted that equipment calibration records, did not identify two instruments included in the console being
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used. These were identified as (a) dual transigate - H S/N and (b)
DAC unit S/N 79.
The licensee stated that this discrepancy appears to
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be an oversight and would make arrangements to have the instrument record (s) available for RII's review on a future inspection.
The inspector stated this would be identified as inspector followup item inspected no items of noncompliance or (79-17-01).
Within the areas deviations were identified.
7.
Data Review and Evaluation Records of NDE examinations, equipment,. personnel and calibration standards were reviewed to ascertain whether storage facilities were consistent with code and regulatory requirements, the examination was as described in the PSI program, data were within acceptance criteria and, indications requiring further evaluation were dispositioned consistent with code requirements.
The inspector discussed UT record storage facilities and provisions for record control. The records selected for review related to the following items / components.
Weld System / Item Figure Size Remark Bottom-15.2330 Clear Head to to Shell Reactor Vessel-71.678 4 and 5 RHR-HOT LEG VGB-1-4101 14"dia.
Clear 2 and 3 BW CVCS-Let Down VGB-1-4108 2"dia.
Clear SD and 6BW CVCS-Let Down VGB-1-4108 2"dia.
Clear 4 and 5 CVCS-Let Down VGB-1-4108 2"dia.
Clear 1,2,3 RHR VGB-2-2500 14"dia.
Clear 1 to 6 Regen.
and 7 to 12 Heat X/1r VGB-2-1500 Welds Noz-zles and clamps Clear Specifically these records were reviewed to determine whether they contained or referenced examination results and data sheets, examination equipment data, calibrations results, inspection material identification, evaluation where applicable, extent of examination / coverage, programatic deviations.
In addition, the reactor vessel weld records were reviewed
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for informatit : pertaining to examination technique and coverage, accept-
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ance criterit, documentation of findings consistent with code requirements.
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~4-Records related to pipe welds were reviewed for information pertaining to. instrument calibration, documentation of findings, evaluation and
' cumentation of their disposition by qualified personnel as required,
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Within these areas complete weld examination / coverage as appropriate.
the inspector noted that; (1) volumetric examination of the entire bottom head to shell weld was not possible with the automated tool
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becaut : of the core support lugs located in that area. This portion will be scanned manually and recorded as such; (2) full coverage of the weld between the upper shell and the transition below the flange may not The licensee stated that this matter be possible because of geometry.
would be discussed further with W in order to obtain more details on the extent of coverage under the present scanning techniq'. Coverage and results will be documented as required by the code.
Within the areas inspected no items of noncompliance or deviations vexe identifico.
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8.
Eddy Current Examination - Work Observation, Data Review and Evaluation Preservice eddy current examination of steam generator tubes was in at the time of this inspection.
The examination is being progress conducted by VEPC0 in accordance with procedure NDT - 14.1, Revision 1, dated October 11, 1976, which references Regulatory Guide 1.83 and SNT -
TC - 1A supplement E.
Data interpretation is performed by CONAM's level II data analyst under contract with VEPCO. The inspector reviewed the approved procedure, calibration standard, equipment and personnel certifi-cations; witnessed instrument calibration with standard #5e, observed examination of steam generator "C" tubes R18c47 thru R23c4i as performed from the hot leg side over the "U" bend and down to the 7th support of the cold leg side of the generator.
Discussions with the licensee and the analyst disclosed that numerous pronounced permeability change signals have been identified and documented.
These appear to exist between the 2nd and 6th supports on the cold side but the greatest concentration was found between the 3rd and 4th supports.
The analy>t stated (snd demonstrated) that in many instances the magnitude of these signals saturated the CRT screen. The presence of this condition was discussed with the licensee who agreed to provide information relative to the cause and possible affect of this condition on the service life of these tubes.
This was identified as unresolved item 79-17-02.
Within the areas inspected no items of noncompliance or deviations, were identified.
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