ML15261A384
| ML15261A384 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/22/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15261A383 | List: |
| References | |
| 50-269-98-10, 50-270-98-10, 50-287-98-10, NUDOCS 9901210078 | |
| Download: ML15261A384 (2) | |
Text
NOTICE OF VIOLATION Duke Energy Corporation Docket No. 50-269,270,287 Oconee 1, 2, and 3 License No. DPR-38,47,55 During an NRC inspection conducted from October 18 to November 28, 1998, two violations of NRC requirements were identified. In accordance with the "General Statement of Policy and Procedures for NRC Enforcement Actions," NUREG 1600, the violations are listed below:
A.
10 CFR 50, Appendix B, Criterion XVI, requires that measures shall be established to assure that conditions adverse to quality such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.
10 CFR 50, Appendix B, Criterion V, requires, in part, that activities affecting quality be prescribed by documented instructions, procedures, or drawings and shall be accomplished in accordance with these instructions, procedures, or drawings. Licensee Power Chemistry Materials Guide, Revision 25 requires removal of all Class II material from stainless steel and nickel alloy surfaces prior to operation of the system above 200 degrees Fahrenheit.
Contrary to the above, corrective actions taken in response to a condition adverse to quality were inadequate. Specifically, a condition adverse to quality was identified on March 4, 1998, by the NRC and documented in Inspection Report 50-269,270,287/98-02 relative to failure to remove lagging adhesive on stainless steel piping, valves, and fasteners (without first being analyzed and approved), in accordance with the Power Chemistry Materials Guide. Subsequently, as of November 6, 1998, licensee corrective actions in response to the previous condition adverse to quality were determined to be inadequate, in that the licensee failed to remove lagging adhesive from the Unit 1 low pressure injection pump 1A flange and flange fasteners and the Unit 1 reactor building spray pump 1A flange and flange fasteners. These components were aligned such that they could have experienced temperatures in excess of 200 degrees Fahrenheit.
This is a Severity Level IV violation (Supplement 1).
B.
10 CFR 50, Appendix B, Criterion Ill, Design Control, states, in part, that the design control measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled.
The licensee's quality standards for separation of redundant safety-related cables were specified and contained in the Cable and Control Board Separation Criteria Document OSS-0218.00-00-0019, Revision 3, dated December 19, 1997. This standard requires in Sections 5.3.4 and 7.0, that different colored cables shall be precluded from making contact with each other.
9901210078 981222 ENCLOSURE 1 PDR ADOCK 05000269 0
NOV 2
Contrary to the above, up until November 3, 1998, the design control measures for Modification NSM ON-32885/0 did not ensure that the above quality standards for cable separation were included and that deviations from the quality standard were controlled.
As a consequence, different colored safety-related cables were installed in direct contact with each other inside terminal boxes TB2345 and 2346, and at the main control room panel board indicators 3HPI P0360/P0021, and the deviations from the standard had not been controlled and evaluated by design.
This is a Severity Level IV Violation (Supplement 1).
The NRC has concluded that information regarding the reason for the violations, the corrective actions taken and planned to correct the violations and prevent recurrence and the dates when full compliance will be achieved are already adequately addressed on the docket in this report.
However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately reflect your corrective actions or your position. In that case, or if you choose to respond, clearly mark your response as a "Reply to a Notice of Violation," and send it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
Dated at Atlanta, Georgia this 2 2 ND day of 1998