ML15224A619
| ML15224A619 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/17/1990 |
| From: | Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A618 | List: |
| References | |
| 50-269-89-37, 50-270-87-37, 50-270-89-37, 50-287-87-37, 50-287-89-37, NUDOCS 9002020228 | |
| Download: ML15224A619 (2) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-269, 50-270, 50-287 Oconee License Nos. DPR-38, DPR-47, DPR-55 During the Nuclear Regulatory Commission (NRC)
'inspection conducted on November 27 - December 1, 1989, a violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1989), the violation is listed below:
10 CFR 50, Appendix B, Criterion II, requires in-part that the quality assurance program shall provide control over activities affecting the quality of the identified structures,
- systems, and components to the extent consistent with their importance to safety.
Duke Power Company Quality Assurance Procedure QA-513, Revision 6, entitled "Control of Inservice Inspection Plans and Reports," paragraph 5.0 states, in-part, that each plan shall include a detailed listing of welds or components to be examined including their classification, category, item number, examination procedure and the calibration standard to be used.
Paragraph 5.6 of the Quality Assurance procedure also states in-part that the quality assurance engineer shall review each inservice inspection plan for conformance to the ASME Section XI code.
Contrary to the above, on November 28, 1989 the inspector observed that Oconee's Unit 3 inservice inspection plan for second period of the second interval was not in conformance with the ASME Section XI Code in that it listed a calibration block (#40367) for the examination of item number B05.050.012, weld No. 3PSP-1 which had a surface finish not representative of the surface of the pipe to be examined in that, surface cracks and material surface separations were observed on the calibration block.
In addition, the calibration block was not the same nominal diameter or nominal thickness as the pipe to be examined and did not have a notch calibration reflector all of which is required by ASME Section XI, Appendix III and Supplement 7.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Oconee, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will 9002020228T~
900117!E~:D2
Duke Power Company 2
Docket Nos. 50-269, 50-270, 50-287 Oconee License Nos. DPR-38, DPR-47, DPR-55 be taken to avoid further violations, and (5) the date when full compliance will be achieve--.
Where good cause is shown, consideration will be given to extending the response time. If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other actioh as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION Caudle A. Julian, Chief Engineering Branch Division of Reactor Safety Dated at Atlanta, Georgia this 17th day of 19.)