IR 05000270/1980019
| ML15251A144 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/01/1980 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15251A142 | List: |
| References | |
| 50-270-80-19, IEB-79-13, NUDOCS 8007310501 | |
| Download: ML15251A144 (4) | |
Text
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RE 0UNITED STATES NUCLEAR REGULATORY COMMISSION Ai
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report No. 50-270/80-19 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name:
Oconee Nuclear Station License No. DPR-47 Inspection at Oconee ite near Seneca, South Carolina Inspect r:
M
S B. R y
Date Signed Approv d by:
V A. R. Herdt, Section Chief, RC&ES Branch Signed SUMMARY Inspection on June 17-18, 1980 Areas Inspected:
This routine announced inspection involved 14 inspector-hours onsite in the areas of IE Bulletin 79-13 inspection activitie Results:
No items of noncompliance or deviations were identifie o)/'
DETAILS Persons Contacted Licensee Employees J. E. Smith, Station Manager
- J. M. Davis, Superintendent of Maintenance
- R. T. Bond, Licensing Project Engineer
- R. J. Brackett, Station Senior QA Engineer
- D. W. Dalton, Technical Support Supervisor, QA C. B. Aycock, Resident Manager, Construction, SSD T. C. Matthews, Technical Specialist, Licensing Group
- T. E. Cribbe, Licensing Engineer K. R. Wilson, Systems Engineer, Licensing (General Offices)
NRC Resident Inspectors F. Jape D. Myers
- Attended exit interview
. Exit Interview On June 18,, 1980, the inspector met with the licensee representatives noted in paragraph 1 above at the conclusion of the inspection and summarized the scope and findings of the inspection of IEB 79-13 activities. The licensee agreed to submit a letter to R by June 19, 1980, justifying the code rejectable indications and no further RT (see par ).
The inspector pointed out that the final report should include feedwater system support inspection result.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
IE Bulletins (IEB)
(Open)
EB 79-13, Cracking in Feedwater System Pipin The inspector examined IEB 79-13 inspection activities as described below:
-2 Radiographic (RT) Inspection Paragraph 2.b of revision 2 to the bulletin requires volumetric examina tion of all auxiliary feedwater nozzle to piping welds and the first adjacent outboard pipe-to-pipe welds (risers).
At the time of the inspection, the licensee had completed the RT inspection of the welds in accordance with ASME Section III, subsection NC 5000 as required by the bulletin. The licensee's level II examiner had rejected eight of the welds (4 on generator A and 4 on generator B) for various types of original construction defects. All film had been mailed off-site to the licensee's consultant for final review and therefore were not available for the inspector's revie The inspector reviewed the radiographic reader sheets and noted the following tabulation of defects for the rejected welds:
GENERATOR NOZZLE WELD FILM DEFECTS 2A
Flg. to Eli 0-1 LOF 3-0 LOF
Flg. to Eli All Slag, POR, LOP
Flg. to Eli 0-1 Slag, Tun Slag, Por, Tun LOF
Fig. to Eli 3-0 Slag, POR, Tun B
Pipe-to-Pipe 4-0
Flg. to Eli 2-3 LOP, Tun POR, LOP, Tun Pipe-to-Pipe 0-1 LOF 1-2 POR, LOF 3-4 LOP, LOF 4-0 LOF 2B
Flg. to Pipe 3-4 Slag, POR During review of the reader sheets and the status of the bulletin, the inspector noted the following:
(1) The code rejectable indications had not been reported to RI The licensee indicated that their review was not considered complete until after their consultant completed his revie (2) The pipe-to-pipe welds (third weld from generator) had been radiographed instead of the ell to pipe welds (2nd weld from generator) as intended by the bulleti Discussions with the licensee revealed that the wrong welds were inspected because of confusion about interpretation of the wording of the bulleti Based on the operating history of the unit, i.e., number of intermittent cold auxiliary feedwater injections (see paragraph of the bulletin) and the RT results from all Babcock and Wilcox (B&W)
plants inspected, the licensee proposed not to perform any further RT inspections on Unit The licensee agreed to provide RII by June 19, 1980, a letter justifying continued operation of the plant with the code rejectable indications and without further RT of the other auxiliary feedwater weld The inspector discussed with licensee presonnel the status of inspec tion of the feedwater system supports as required by paragraph of the bulleti The licensee stated that all inspection had been completed as a part of IEB 79-1 The results from these inspections for the feedwater system willbe reported for IEB 79-1 Within the areas inspected, no items of noncompliance or deviations were identified