ML20207G851

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Notice of Violation from Investigation Rept A4-1998-042 on 990127.Violation Noted:After 980528,ES Feemster,Initiated Reactor Simulator Training Attendance Record Indicating Attendance at 980528 Training Session Not Attended
ML20207G851
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 06/07/1999
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20207G798 List:
References
NUDOCS 9906140093
Download: ML20207G851 (2)


Text

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! 6 NOTICE OF VIOLATION Edwin S. Feemster Docket No. 55-9590 License No, SOP-43304-2 lA 99-007 During an NRC investigation completed January 27,1999, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, Revision 1, the violation is !isted below:

10 CFR 55.53(d), describing the conditions upon which operator and senior operator licenses are granted, states that "The license is subject to, and the licensee shall observe, all applicable rules, regulations, and orders of the Commission."

NRC License SOP-43304-2, issued to Edwin S. Feemster and effective February 19, 1995, states While performing licensed duties, you shall observe the operating procedures and other conditions specified in the facility license which authorizes operation of the facility."

10 CFR 50.9, states, in part, that information provided to the Commission by a (facility) licensee, or required by the Commission's regulations to be maintained by the (facility) licensee, shall be complete and accurate in all material respects.

10 CFR 55.59(c)(5)(i) states, in part, that the facility licensee shall maintain records documenting the participation of each licensed operator and senior operator in the requalification program.

Contrary to the above, sometime after May 28,1998, Edwin S. Feemster, a senior operator, initialed a reactor simulator training attendance record, indicating his attendance at a May 28,1998 training session that he did not attend. This record is material because it is used by the facility licensee to show that licensed operators and senior operators have fulfilled the training requirements of the operator requalification program.

This is a Severity Level 111 violation (Supplement Vil).

The NRC has concluded that no response is required because you no longer hold an NRC reactor operator's license. 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, DC 20555 with a copy to the Regional Administrator, Region IV,611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, 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, with the basis for your denial, to the Director, Office of Enforcement, United States Nuclear ,

Regulatory Commission, Washington, DC 20555-0001.

!! you choose to respond, your response will be placed in the NRC Public Document Room (PDR). Therefore, to the extent possible, the response should not include any personal privacy, l

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9906140093 990607 PDR MISC i

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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, l

t 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 I

that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of inforination 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.

l Dated this 7th day of June 1999 I

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