ML20236N091

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Notice of Violations from Insp on 980421-0608.Violations Noted:On 980424,licensee Failed to Implement Specific Fire Protection Program Requirements in That Welding Machine Was Left Unattended & Energized in Fuel Handling Bldg
ML20236N091
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 07/06/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20236N089 List:
References
50-456-98-08, 50-456-98-8, 50-457-98-08, 50-457-98-8, NUDOCS 9807150004
Download: ML20236N091 (2)


Text

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NOTICE OF VIOLATION I

l Commonwealth Edison Company Docket Nos.: 50-456;50-457 Braidwood Nuclear Plant License Nos.: NPF-72; NPF-77

- During an inspection conducted from April 21 through June 8,1998, two violations of NRC 5 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. 10 CFR Part 50, Appendix B, Criterion XVI, " Corrective Actions," requires, in part, that measures be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances 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.

Contrary to the above, as of April 19,1998, the licensee's corrective action measures for a violation cited in inspection Report 50-456/97012 were not effective in preventing the repetitive unauthorized use of non-environmentally qualified components in safety-related motor control centers, a significant condition adverse to quality. On April 9,1998, following NPC questioning, the licensee identified additional non-environmentally qualified safety-related components installed in a motor control center that would be subject to a harsh environment following an accident.

This is a Severity Level IV violation (Supplement 1) (50-456/98008-02(DRP);

50-457/98008-02(DRP)).

2. Technical Specification 6.8.1.g requires that written procedures be established, implemented, and maintained for activities associated with implementation of the Fire Protection Program Control of welding machines and hot work are included in the Fire Protection Program.

Braidwood Administrative Procedure 1100-15 " Fire Prevention When Welding, Cutting, Grinding or Performing Open Flame Work (Hot Work)," Revision 8, Step C.2.8, states,

" Ensure welding machines are de-energized, cylinder valves are isolated, and hoses are depressurized when the assigned workers are not in the immediate area, or when these ,

items are not in use (i.e., during breaks, lunch, end of day, eto.)." i Contrary to the above:

a. On April 24,1998, the licensee failed to implement specific fire protection program requirements in that a welding machine was left unattended and energized in the fuel handling building.

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9807150004 990706 PDR ADOCK 05000456 G PDR

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.. Notice of Violation ' . ' b. On May 1,1998, the lic' ensee failed to implement specific fire protection program requirements in that an oxygen hose and an acetylene hose were left unattended and pressurized.

This is a Severity Level IV violation (Supplement 1) (50-456/98008-03(DRP);

50-457/98008-03(DRP)).

Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison 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,--

U.S. Nuclear Regulatory Commission, Region lil,801 Warrenville Road, Lisle, Illinois 60532, and a copy to the NRC Resident inspectors at the Braidwood Station within 30 days of the date of the letter transmitting this Notice of Violation (Notice).' This reply should be cleariy marked as a

" Reply to a . Notice of Violation" and should include for each violation: (1) the reason for the . -l

- violation, or, if contested,' the basis for disputing the violation, (2) the corrective steps that have l

i 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 l or include previous docketed correspondence, if the correspondence adequately addresses the

l. 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.

L If you contest this enforcement action, you should also provide a oopy of your response to the l 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, to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the Public Document Room 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 mgg specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withhold.ing (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information <1' required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financialinformation). If safeguards information is necessary to provide an acceptable response, l

please provide the level of protection described in 10 CFR 73.21.  !

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- Dated at Lisle, Illinois ~

this 6 day of July 1998 j l

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