IR 07100025/2012001

Notice of Violation from Insp on 871025-1201.Violation Noted:On 870920,individual Holding Senior Operator License on Similar Facility & Not Participating in Approved Training Program Allowed to Manipulate Controls of Reactor

ML20237C127
Person / Time
Site:	Braidwood, 07100025
Issue date:	12/14/1987
From:	Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20237C119	List: IR 05000456/1987042 IR 07100025/2012001 ML20237C117
References
50-456-87-42, NUDOCS 8712210047
Download: ML20237C127 (1)

Text

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NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-456 As a result of the inspection conducted from October 25 through December 1, 1987 and in accordance with the " General Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1987), the following violation was identified:

10CFR50.54(1) states,"Exceptasprovidedin55.13ofthischapter,the licensee may not permit the manipulation of the controls of any facility by anyone who is not a licensed operator or senior operator as provided in Part 55 of this chapter."

10 CFR 55.13. " General exemptions," states, "The regulations of this part do not require a license for an individual who -

"(a) Under the direction and in the presence of a licensed operator or senior operator, manipulates the controls of -

"(2) A facility as part of the individual's training in a facility licensee's training program as approved by the Commission to qualify for an operator license. under this part."

10 CFR 55.53, " Conditions of licenses," states, "Each license contains and is subject to the following conditions whether stated in the license or not:

"(a) Neither the license nor any right under the license may be enigned or otherwise transferre "(b) The license is limited to the facility for which it is issued "

Contrary to the above, on September 20, 1987, an individual holding a senior operator license on a similar facility and not participating in an approved training program was allowed to manipulate the controls of (and thereby make reactivity changes to) the Braidwood Unit I reactor. At the time, the reactor was in Mode 1 and at 34's powe This is a Severity Level IV violation (Supplement I). (50-456/r37042-01(DRP))

Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation: (1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieve Consideration may be given to extending your response time for good cause show Dated DEC141M b W. L. Forney, Cl@r ' C Reactor Projects Branch 1 8712210047 871214 PDR I

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