IR 05000269/1978021
| ML15223A332 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/01/1978 |
| From: | Conlon T, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15223A328 | List: |
| References | |
| 50-269-78-21, 50-287-78-22, NUDOCS 7812070320 | |
| Download: ML15223A332 (7) | |
Text
pk RFGco UNITED STATES, aNUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report Nos.:
50-269/78-21 and 50-287/78-22 Docket Nos.:
50-269 and 50-287 License Nos.:
C and C Licensee:
Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
Oconee Nuclear Station, Units 1 and 3 Inspection at:
Seneca, South Carolina Inspection conducted:
September 19-21, 1978 Inspector: N. Economos Reviewed b:2 r
T. E. Conlon, Chief Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Inspection Summary Inspection on September 19-21, 1978 (Report Nos. 50-269/78-21 and 50-287/78-22)
Areas Inspected:
Corrective action on previously identified infraction number 287/78-14-01; ISI activity in Unit 1. The inspection involved 24 inspector-hours on site by one NRC inspecto Results:
Of the two areas inspected no apparent items of noncompliance were identifie o
RII Rpt. Nos. 50-269/78-21 I-1 and 50-287/78-22 DETAILS I Prepared by:c---f (
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N. Economos, Metallurgical Enginee'r Date Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Dates of Inspection:
September 19-21, 1978 Reviewed by: C>-7,66
/
f T. E. Conlon, Chief Date Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Persons Contacted Duke Power Company (DPC)
- R. M. Koehler, Superintendent of Technical Services R. J. Brackett, Station Senior QA Engineer
- J. D. Norton, QA Engineer, Charlotte
- R. T. Bond, Station Technical Services Engineer
- D. J. Vito, Licensing Engineer
- A. J. Hogge, QA Specialist
- P. V. Fant, Assistant QA Engineer P. Waltman, Station ISI Coordinator B. Farmer, Level II NDE Contractor Organization Babcock and Wilcox Construction Company (B&W)
G. Drinkel, ISI Coordinator G. Sechler, Level II NDE Examiner J. J. Johnson, Level II NDE Examiner R. Nelson, Field QA Supervisor In addition to the above, other craft and inspection personnel were interviewe *Denotes those present at the exit intervie.
Licensee Action on Previously Identified Inspection Findings (Closed) Noncompliance Item (287/78-14-01): Failure to control weld rod materia The inspector has reviewed the licensee's response and
RH Rpt. Nos. 50-269/78-21 1-2 and 50-287/78-22 corrective action to prevent the recurrence of this problem. A walk through inspection of work areas involving welding disclosed that procedural requirements were being enforced. This item is close.
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 deviation Unresolved items disclosed during the inspection are discussed in Paragraph 4a, 5.
Independent Inspection Effort Radiographic Examination of Feedwater Welds (Unit 1)
Volumetric examination (RT) of field fabricated feedwater welds 41E, 41D on ISO-4 inside the A cavity was conducted on the night shift of September 21, 197 The inspector witnessed the preparation/setup for the shooting of weld No. 41E and later reviewed the radiographs for both welds, 41E and 41D. Within this area the inspector verified conformance with Radiographic procedure NDE-10 Revision 0 and applicable construction code B3 The film review disclosed that both welds were free of rejectable indications except for a small area between stations 0 to 1 in weld 41E. This area contained an apparent slag/porosity type indication which the licensee agreed to reshoot for verification and possible repair as require This was identified as an unresolved item until R:II has had the opportunity to review the reshot during a future inspection. This was assigned unresolved item number (269/78-21-01). Walk Through Inspection (Unit 1)
Certain areas inside containment where pipe and/or hanger welding was in progress were inspected for weld material control and housekeeping. No items of noncompliance or deviations were identifie.
Fourth Refueling Outage Inservice Inspection -
Unit I Observation of Work and Work Activities Nondestructive examinations/activities during this outage were being conducted by B&W under contract with DP Components scheduled for examination during the outage included reactor vessel closure studs and certain attachment welds; pressurizer
- RII Rpt. Nos. 50-269/78-21 1-3 and 50-287/78-22 shell seams, nozzles, studs, lugs and nuts; once through steam generator (OTSG), tubes, seams, nozzles, skirt welds, studs, nuts and bolts; pressure piping welds, supports and hangers. The controlling document is B&W's ISI Manual, Outage Number 4, which had been approved by B&W's Level III Examiner and the licensee's cognizant QA representativ Section XI of the ASME Code 1974 Edition through Summer 1975 addenda, establishes the nondestructive examination requirements including acceptance criteri The inspector witnessed, in part, the examination of the following items:
Figure Item NDE Comments B1.1 Closure Washers and Bushings Visual Clear B1. Closure Studs MT Clear B1. Closure Studs UT Clear
- B3. Circular Seam lB S/G UT
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- B3. lB S/G, Outlet Noz. W axis UT
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- B3. lB S/G, Outlet Noz. Y axis UT
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- Witnessed instrument calibration prior to examinatio Within this area the inspector verified personnel qualifications; implementation of and compliance with applicable procedure require ments; ultrasonic apparaus and system calibration including distance-amplitude correction (DAC) curve construction; use of required calibration block; use of specified search unit; technique scanning of area of interes In addition, the inspector observed the eddy current (ET) examination of OTSG, 1A tubes46-117, 46-118 and 46-119, together with system calibration performed at approxi mately 17:30 hours on September 20, 197 This was done with calibration standard, s/n 40346 and recorded on form "ET Cali bration Sheet", number 2 All instruments used in the examination including strip chart, recorders, magnetic tape, machines, scopes, etc., exhibited calibration stickers indicating they were in calibration. In the areas inspected no items of noncompliance or deviations were identifie Data Review and Evaluation Records of nondestructive examinations conducted during this outage were selected for a review to determine whether they were consistent with applicable code and procedure requirements and if they contained or referenced applicable data sheets, examination
RII Rpt. Nos. 50-269/78-21 1-4 and 50-287/78-22 equipment data, calibration sheets, extent of examination, evalua tions including programatic deviations, findings disposition and reexamination following repair as applicable, certification of materials (UT compliant, MT and PT materials)
used during surface and volumetric examination This effort was performed for the following items:
Figure Item NDE Comment Reactor Vessel B1. Closure Studs MT Clear BI.1 Closure Washers U
Clear and Bushings B1. Closure Studs UT Clear Pressurizer B2. Shell to Long. Seam UT Clear B2. Shell to Shell UT Clear Arc Seam B2. Relief Nozzle UT Clear B2. Htr. Bundle Stnds UT Clear B2. Htr. Bundle Nuts U
Clear Pressure Piping B4.1. Press. Tap No UT Geometry S.E. Al Section B4.1.15.1/
Al discharge UT, PT Clear B4.1.16 B4.1.25 A2 Dis. Pump PT Clear S.E. to El In addition the inspector verified through this record review, code required calibration checks; proper recording of identified UT indications; data evaluation by qualified personnel as applicabl For the OTSG tubes discussed above, the inspector reviewed the records related to the examination including personnel qualifications for completeness and accurac In response to questions concerning the outcome of the ET examination on the OTSG tubes, the licensee stated that approximately 3% or 950 tubes per OTSG were selected for examination during this outag Examination results were as follows:
RII Rpt. Nos. 50-269/78-21 1-5 and 50-287/78-22 OTSG1A An analysis of the ET data disclosed that three (3) tubes in OTSG IA contained imperfections which exceeded the plugging limit of 40% wall thickness -
these were as follows:
Row Tube
% Wall Location Penet/on
3 50-60 14th Support
7 60-70 14th Support
14 35-70 14th Support Also, tube 77-17, located in the lane area of the OTSG appears to be loose and will be stabilized prior to startup. The licensee is examining an additional 220 tubes, located around the above mentioned tubes as a precautionary measure to generate more information in this are OTSG lB Analysis of the ET data from this generator disclosed that seven (7) tubes exhibited indications with wall penetrations of 35-45%
and 17 tubes with indications J40% of wall thickness. Tube location and extent of wall penetration was as follows:
Average Penetration 40%
Row Tube
% Wall Location/Support
51 35-45%
14 to 15
43 40%
35 107 40%
90 129 35-45
98 125 35-45
55 125 35-45
90 125 35-45
Average Penetration J40%
127
14
2 40-50
54
50-60
8
40-50
9
45-55
12
60-65
RII Rpt. Nos. 50-269/78-21 1-6 and 50-287/78-22 150
40-50
85 126 45-55
86 127 45-55
89 125 60-65
93 119 45-50
98 125 40-50
101 121 70-80
113 121 40-50
55 124 50-60
64 125 70-80
53 125 40-50
A number of these tubes had been identified on previous ISI inspec tions as having indications with a severity well within the acceptable limi Because of these findings, the inspector discussed with the licensee his plans for further tube inspections. However the position taken by the licensee at this time was that their present Topical does not commit them to RG 1.83 and, that on June 21, 1977, they had submitted to NRR, a proposed revision to the technical specification (TS) which contained an alternate plan for OTSG tube examination. Therefore, the present OTSG tube inspection plan was based on that submittal, which they assume to be acceptable unless NRR advises them otherwise. The inspector stated that this matter would be identified as unresolved item number 269/78-21-02 pending NRR's response to the submitta.-
Exit Interview The inspector met with the licensee denoted in paragraph I at the conclusion of the inspection. The inspector identified the areas inspected which included: observation and record review of ISI activities; closing of noncompliance, 287/78-14-0 The licensee acknowledged the inspection findings.