ML15118A174
| ML15118A174 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/27/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15118A173 | List: |
| References | |
| 50-269-96-17, 50-270-96-17, 50-287-96-17, NUDOCS 9702100348 | |
| Download: ML15118A174 (3) | |
Text
NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-269, 270, and 287 Oconee 1, 2, and 3 License Nos. DPR-38, 47, and 55 During an NRC inspection conducted on November 17, 1996 - December 28. 1996, three 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.
Technical Specification 6.4.1 requires that the station shall be operated and maintained in accordance with approved procedures. Written procedures with appropriate check-off lists and instructions shall be provided for the following conditions:
Normal startup, operation, and shutdown of the complete facility and all systems and components involving nuclear safety of the facility.
Preventive or corrective maintenance which could affect nuclear safety or radiation exposure to personnel.
Operations Procedure OP/2/A/1103/02, Filling and Venting the RC System, provides instructions to fill and vent the RC system. Enclosure 4.13, Valve Checklist, requires 2RC-196, 2B Once Through Steam Generator (OTSG) Hot Leg High Point Vent Valve, to be open.
Maintenance Procedure IP/0/B/203/1G, Low Pressure Injection System Inaccessible Flow Instruments Calibration, Enclosure 11.4.1, required that the pressure transmitter for valve 3LP-2 be returned to service prior to exiting the procedure.
Contrary to the above, the station was not operated and maintained in accordance with approved procedures, in that:
- 1.
On December 10, 1996, valve 2RC-196 was found in the closed position. This caused inadequate venting and the formation of a void in the 2B OTSG hot leg piping.
- 2.
On October 12, 1996, the isolation valve associated with the low pressure transmitter for valve 3LP-2 was found shut. This prevented normal valve operation during a-unit shutdown.
Additional operator and maintenance actions would have been necessary in certain emergency situations if valve operation was required.
This is a Severity Level IV Violation (Supplement I) applicable to Units 2 and 3 only.
ENCLOSURE 1 9702100348 970127 PDR ADOCK 05000269 G
B.
10 CFR 50 Appendix B, Criterion V,"Instructions Procedures and Drawings" as implemented by the Duke Power Company Topical Report Quality Assurance Program (Duke-1-A), requires in part that activities affecting quality shall be accomplished in accordance with prescribed procedures, instructions or drawings.
Oconee Station Procedure QAL-5, Table C Rev. 0, requires that ASME Code Class 3 welds, tested per ASME Code Case N-416-1, in lieu of the hydrostatic pressure test required by paragraph IWA-4000, shall have surface examinations performed on the root and final pass. Also, following the examination and prior to or immediately upon returning to service, a visual examination (VT-2) shall be performed in conjunction with a system leakage test, at nominal operating pressure and temperature.
Contrary to the above, on October 17, 1996, activities affecting quality were not accomplished in accordance with prescribed procedures.
Specifically, eight new Code Section XI Class 3 welds that were fabricated during Nuclear Station Modification (NSM) 52972, Low Pressure Service Water "B" Line Header modification did not undergo surface examination at the root and final pass as required.
This is a Severity Level IV Violation (Supplement I) applicable to Unit 1 only.
C.
10 CFR 50 Appendix B, Criterion XII, Control of Measuring and Test Equipment (M&TE), as implemented by the Duke Power Quality Assurance Topical Report (Duke 1-A) section 17.3.2.9. Measuring and Test Equipment Control, requires that items and processes determined to be acceptable based on measurements made with devices subsequently found to be out of calibration are to be re-evaluated. Additionally. Table 17.0-01 of the QA Topical Report references Regulatory Guide 1.28, QA Program Requirements, which incorporates ANSI N45.2-1977. Section 13 of ANSI N45.2, Control of Measuring and Test Equipment, requires that when M&TE are found to be out of calibration, an evaluation shall be made of the validity of previous inspection or test results for acceptability.
Contrary to the above, on November 21, 1996, it was identified that items and processes determined to be acceptable based on measurements made by M&TE devices were not appropriately re-evaluated following identification that the devices were out of calibration. Numerous examples were identified in which the evaluations were not performed.
Other examples were identified in which the evaluations were not adequate.
This is a Severity Level IV Violation (Supplement I) applicable to Units 1, 2, and 3.
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear ENCLOSURE 1
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 Oconee Nuclear Station, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information).
If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Atlanta, Georgia this 27th day of January 1997 ENCLOSURE 1