ML20134P505

Notice of Violation from Insp on 961026-1216.Violation Noted:Licensee Failed to Take Actions to Correct Deficiency of Loose Muffler

ML20134P505
Person / Time
Site:	Fermi
Issue date:	02/06/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20134P501	List: ML20134P498 ML20134P505 ML20134P507
References
50-341-96-13, NUDOCS 9702260005
Download: ML20134P505 (3)

Text

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NOTICE OF VIOLATION '

Detroit Edison Company Docket No. 050-341 Fermi 2 License No. NPF-43 During an NRC inspection conducted from October 26 through December 16,1V violations of NRC requirements were identified. in accordance with the "Generat Statement of Policy and Procedure for NRC Enforcement Actions,"

NUREG 1600, the violations are listed below:

1. 10 CFR 50, Appendix B, Criterion XVI, " Corrective Actions," required in part, that 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. j Contrary to the above, on January 11,1996, the licensee determined that a baffle plate inside the Emergency Diesel Generator (EDG) 12 muffler was loose, but failed to take action to correct the deficiency in a timely manner commensurate with the safety significance of the system.

This is a Severity Level IV Violation (Supplement 1).

2. 10 CFR 50.59, " Changes, Tests and Experiments," permitted the licensee to make l changes in the facility as described in the Safety Analysis Report, without prior Commission approval unless the proposed change involved a char.ge in the technical specifications or an unreviewed safety question. It further required that a change to the facility described in the Safety Analysis Report, which does involve a change in technical specifications, shall be submitted in an application for amendment of license per 50.90.

Contrary to the above, on November 11,1996, the licensee failed to submit a technical specification change which was required to ensure that mechanical overpower limits for the new core would be met during a rod withdrawal error i event as described in the Safety Analysis Report.

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

3. 10 CFR 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings,"

required in part, that activities affecting quality be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and be accomplished in accordance with these instructions, procedures, or drawings.

Contrary to the above, on November 6,1996, Surveillance Procedures 44.030.251 and 44.030.253, " Reactor Vessel Water Level Channel A/C Logic Tests," were inadequate in that they failed to verify that electricallead KK18 was properly connected after removalin the procedure.

This is a Severity Level IV Violation (Supplement 1).

9702260005 970206 PDR ADOCK 05000341 0 PDR

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Notice of Violation i

4. 10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings," l required in part,that a:tivities affecting quality be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and be accomplished in accordance with these instructions, procedures, or drawings.

a. Abnormal Operating procedure 20.000.21, " Reactor Scram," Revision 38, l required in part, that the operator verify that a Scram Discharge Volume  :

Level High alarm was received, followed by the Scram Discharge Volume High water level scram, and then reset the scram.

b. Operations Conduct Manual, Chapter 5, " Control of Equipment," Revision 5, Step 2.1, requires in part, that only operations personnel shall operate plant systems and equipment.

Contrary to the above:

a. On December 4,1996, an operator failed to accomplish the Abnormal Operating Procedure 20.000.21 as prescribed. The operator reset the scram before receiving both the Scram Discharge Volume Level High alarm and scram.

b. On October 30,1996, plant personnelinstead of operations personnel operated the spent fuel pool manual fill valves and overfilled the pool.

i This is a Severity Level IV violation. (Supplement 1) l l

Pursuant to the provisions of 10 CFR 2.201, the Detroit 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, Region lil, and a copy to the NRC Resident inspector at the facility j that is subject of this 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 violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and M) the date when full compliance will be achieved. Your response may 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.

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s Notice of Violation  ;

2 Because your response will be placed in the NRC Publec Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards j information so that it can be placed in the PDR without redaction. If personal privacy or j

. proprietary information is necessary to provide an acceptable response, then please l l provide a bracketed copy of your response that identifies the information that should be protected and a reacted 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 l

withholding (e.g. explain why the disclosure of information will create an unwarranted l i

invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to I support a request for witnholding confidential commercial or financial information). If l l safeguards information is necessary to provide an acceptable response, please provide the l level of protection described in 10 CFR 73.21. l l l R

Dated at Lisle, Illinois, l

, this 6th day of February 1997 i

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