ML20198N298

Notice of Violation from Insp on 970715-0827.Violation Noted:Corrective Actions Taken by Licensee Were Not Adequate to Preclude Repetition of Event Involving Inadequate Staffing of Control Room

ML20198N298
Person / Time
Site:	Dresden
Issue date:	10/24/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20198N273	List: ML20198N270 ML20198N298 ML20198N303
References
50-010-97-13, 50-10-97-13, 50-237-97-13, 50-249-97-13, NUDOCS 9711030258
Download: ML20198N298 (2)

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NOTICE OF VIOt.ATION Commonwealth Edison Company Docket Nos. 50-237;50 249 Dresden Nuclear Power Station, Units 2 and 3 License Nos. DPR 19; DPR 25 i

During an NRC Inspection conducted from July 15 to August 27,1997, vlotations of NRC requirements were identified, in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions, NUREG.1600, the violations are listed below:

1.

Criterion XVI of Appendix B to 10 CFR Part 50 states, in part, that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected in the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition.

A.

Contrary to the above, corrective actions taken by the licensee were not adequate to preclude the repetition of an event involving inadequate staffing of the centrol room. Specifically, on August 17,1997, the Unit 2 unit supervisor left the control room without being relieved, reducing the control room staff level below specified levels. A similar event occurred on February 26,1997.

i B.

Contrary to the cbove, corrective actions taken by the licensee were not adequate to preclude repetition of an event involving the failure to enter the required action statement of a Technical Specification. Specifically, on August 21,1997, operators applied Technical Specification 3.2.F instead of 3.2.A, which was more limiting. A similar event occurred on January 23,1997.

C.

Contrary to the above, corrective actions taken by the licensee were not adequate to preclude repetition of an event invoMog an unrestrained 4 kV breaker.

Cpecifically, from July 22,1977, when the inspectors informed the licensee that a 4-kV breaker near a saftty-related bus was unrestrained, until approximately July 28,1997, the licensee did not correct the deficient breaker condition. A similar event, for which a violation was issued, occurred on January 18,1996.

This is a Severity Level IV violation (Supplement I).

2.

Dresden Station Technical Specification 6.8.a requires that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, references radiation protection procedures, which include a radiation work permit system.

Dresden Administrative Procedure (DAP) 12 25, " Radiation Work Permit Program,"

Revision 06, Step F.1.f.(3), requires that personnel, " Verify understanding of work area dose rates and contamination levels and location of low dose rate waiting areas."

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Nodce of Violation 2

Contrary to the above, on August 8,1997, personnel who performed turbine building equipment rounds did not read radiation protection sutvey maps or otherwise verify dose rates for the Unit 2 Turbine Building Elevation 601 general area prior to working in that area. The survey map for the area had a waming posted over the map stating that radiological conditions had changed and that radiation protection personnel must be consulted for a current survey.

This is a Severity Level IV violation (Supplement IV).

1' Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison Company 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, J

Region lit, and a copy to the NRC Resident inspector at the facility that is the subject of this i

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 i

violation: (1) the reason for the violation, or, if cnntested, the basis for disputing the violation,

12) 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 rreay 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.

Because ycur 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 redactions. If personal privacy or proprietary information is i

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 4

detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarran;ed 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 Lisle, Illirais, this 24th day of October 1997.

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