ML16161A733
| ML16161A733 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/06/1986 |
| From: | Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| Shared Package | |
| ML16161A734 | List: |
| References | |
| RTR-REGGD-01.150, RTR-REGGD-1.150 NUDOCS 8606190526 | |
| Download: ML16161A733 (2) | |
See also: IR 05000269/1986011
Text
- III)
Docket Nos. 50-269
.
License Nos. DPR-38
Duke /9 er Company
ATTN,/ Mr. H. B. Tucker, Vice President
Nuclear Production Department
422 South Church Street
Charlotte, NC 28242
Gentlemen:
SUBJECT:
INSPECTION REPORT NOS. 50-269/86-11
This refers to the Nuclear Regulatory Commission (NRC)
inspection conducted by
N. E. Economos on March 20 -
21,
1986.
The inspection included a review of
activities authorized for your Oconee facility.
At the conclusion of the
inspection, the findings were discussed with those members of your staff identi
fied in the enclosed inspection report.
Areas examined during the inspection are identified in the report. Within these
areas,
the inspection consisted of selective examinations of procedures and
representative records, interviews with personnel, and observation of activities
in progress.
Within the scope of the inspection, no violations or deviations were identified.
On May 2, 1986,
NRR issued a Safety Evaluation Report entitled Oconee Unit 1,
Duke Power Company,
Safety Evaluation of the Ultrasonic Flaw Indication Detected
in the Reactor Pressure Vessel.
Your attention is directed to the provisions
delineated in the conclusion of the SER which requires that the following infdr
mation be submitted before June 16, 1986.
1.
Submit the additional information requested by the staff during the
April 21, 1986 meeting and contained in the summary section of this report.
2.
Submit a technical report summarizing your on-going ultrasonic testing
program on the vessel mockup at the Mt. Vernon facility.
In addition, the staff considers several ultrasonic reflectors, which are pre
sumed to be flaw indications, to be conditionally acceptable in accordance with
Subparagraph IWB-3122.4 of Section XI of the ASME Code and, therefore, requires
augmented inservice inspections based on 10 CFR 50.55a(g)(4).
Also the staff
requires that the best available techniques and instrumentation be used during
the next scheduled refueling outage inspection to evaluate these indications.
The staff requires that you provide a report at least six months before the next
scheduled refueling outage describing detailed plans for this inspection.
63606190526 860606
ADOCK 05000269
G
IU6
Duke Power Company
2
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2,
Title 10,
Code of Federal Regulations, a copy of this letter and its enclosure
will be placed in the NRC Public Document Room.
Should you have any questions concerning this letter, please contact us.
Sincerely,
Original Signed by m. Sinkule
Virgil L. Brownlee, Chief
Reactor Projects Branch 3
Division of Reactor Projects
Enclosure:
NRC Inspection Report
fc w/encl:
M. S. Tuckman, Station Manager
> cc w/encl:
RC Resident Inspector
H. Nicolaras, NRR
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