ML15261A379
| ML15261A379 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/23/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15261A378 | List: |
| References | |
| 50-269-98-15, 50-270-98-15, 50-287-98-15, EA-98-552, NUDOCS 9901200362 | |
| Download: ML15261A379 (2) | |
Text
NOTICE OF VIOLATION Duke Energy Corporation Docket Nos. 50-269, 50-270, 50-287 Oconee 1, 2, and 3 License Nos. DPR-38, DPR-47, DPR-55 EA 98-552 During an NRC inspection conducted on November 2-6, November 16-20, and December 11, 1998, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedures for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
10 CFR 50.71(e) requires that each licensee periodically update the Final Safety Evaluation Report (FSAR) to assure that the information included in the FSAR contains the latest material developed. This update shall include all changes necessary to reflect information and analyses submitted to the Commission by the licensee.
Contrary to the above, the licensee failed to update the FSAR to assure that the information included in the FSAR contained the latest material developed and updates did not include all changes necessary to reflect information and analyses submitted to the Commission by the licensee as evidenced by the following examples:
- 1.
From approximately 1982 to November 18, 1998 the FSAR statement that the emergency feedwater (EFW) system can "perform its safety-related function in the event of a single failure coincident with a secondary pipe break and the loss of normal station auxiliary AC power" was inaccurate because certain exceptions to that design criteria were not stated. For example, the EFW system was not designed to perform a safety-related function in the event of certain secondary pipe breaks (of main feedwater or 300 psig auxiliary steam) in the turbine building that would disable the three trains of safety-related switchgear and the EFW system.
The licensee had described these pipe break scenarios to the NRC in a 1973 high energy line break analysis report. A mitigation strategy, which relied on use of the station auxiliary service water (ASW) pump and on powering a high pressure injection pump from the ASW switchgear, had been approved by the NRC.
However, the licensee had not updated the FSAR to include the results of the 1973 analysis.
- 2.
From 1995 to November 18, 1998, the FSAR statement that "once started, the EFW pumps will continue to run until manually stopped by the operators" was inaccurate because the turbine-driven EFW pump would be stopped automatically on a low steam generator pressure of 500 psig. The licensee had not appropriately updated the FSAR following modification ON-2873, Main Steam Line Break Modification, which had been installed on Units 1, 2, and 3 in 1995, 1996, and 1997, respectively.
This is a Severity Level IV Violation (Supplement 1).
99 05000269 PDR
NOV 2
Pursuant to the provisions of 10 CFR 2.201, Duke Energy Corporation is hereby required to submit a written statement or explanation 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). 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 or severity level, (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 a 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.
If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, D.C.
20555-0001.
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.
In accordance with 10 CFR 19.11, you may be required to post this Notice within two working days.
Dated at Atlanta, Georgia this 23rd day of December 1998