ML17284A774
| ML17284A774 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/30/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17284A773 | List: |
| References | |
| 50-397-98-19, NUDOCS 9810070173 | |
| Download: ML17284A774 (2) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Washington Public Power Supply System Washington Nuclear Project-2 Docket No.:
50-397 License No.:
NPF-21 During an NRC inspection conducted on July 19 through August 29, 1998, one violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
10 CFR 50.59(a)(1) states, in part, that the holder of an operating license authorizing operation of a production or utilization facilitymay make changes in the procedures as described in the safety analysis report, without prior Commission approval, unless the proposed change involves a change in the Technical Specifications incorporated in the license or an unreviewed safety question.
Technical Specification 3.8.1.10, diesel generator load rejection test, states, in part, that this surveillance shall not be performed in Modes 1 or 2.
Contrary to the above, on August 7, 1998, while operating in Mode 1, the licensee approved a change to procedures as described in the safety analysis report, without prior Commission approval, that involved a change in the Technical Specifications incorporated in the license.
Specifically, the licensee approved Procedure 8.3.405, Revision 0, "Diesel Generator (DG-2) Operability Verification Following Voltage Regulator Changeout," which included the performance of a full load rejection test of the Division II emergency diesel generator while the plant was operating in Mode 1..
This is a Severity Level IVviolation (Supplement I).
The NRC has concluded that information regarding the reasons for the violation, and the corrective actions taken nd planned to correct the violation to prevent recurrence, is already adequately addressed on the docket in this inspection report.
However, you are required to submit a written statement or explanantion 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 IV, and a copy to the NRC Resident Inspector at the facilitythat is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
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, DC 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
'P810070i73 9'80930 PDR ADQCK 05000397 G
PDR 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 Arlington, Texas this 30th day of September 1998