ML20133A329

Notice of Violation from Insp on 961001-03,28-30 & 1107. Violations Noted:Licensee Failed to Take Prompt Action Prior to Returning Potentially Defective Steam Generator Tubes to Svc

ML20133A329
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	12/23/1996
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20133A321	List: IR 05000295/1996013 ML20133A317 ML20133A329
References
50-295-96-13, 50-304-96-13, NUDOCS 9612310051
Download: ML20133A329 (2)

Text

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4 NOTICE OF VIOLATION Commonwealtii Edison Company Docket Nos. 50-295;50-304 l

Zion Nuclear Generating Station License Nos. DPR-39; DPR-48 '

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During an NRC inspection conducted on October 1-3, 28-30, and November 7,1996, violations 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- l l

1. Criterion XVI. " Corrective Action," of 10 CFR Part 50, Appendix B, requires that measures shall be established to assure that conditions adverse to quality, such as l failures, malfunctions, deficiencies, deviations, defective material and equipment, '

and nonconformances are promptly identified and corrected.

I Contrary to the above, in February 1995 and in October 1995, the licensee failed to {

take promp't corrective action prior to returning potentially defective steam  !

generator tubes to service. Corrective action (an operability assessment) was not implemented until March of 1996 for the Unit 2 indications and corrective action (plugging affected steam generator tubes) was not implemented until February of 1996 for the Unit 1 indications.

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

2. 10 CFR 50, Appsndix B, Criterion V, " Instructions, Procedures, and Drawings,"

states that activities affecting quality shall be prescribed by documented instructions, prc.:edures, or drawings, of a type appropriate for the circumstances.

10 CFR 50.55a(g)(4)(ii) requires the inservice examination of components to comply with the ASME Code incorporated by reference.

ASME Code,1980 Edition Winter 1981 Addenda,Section XI, Table IWF-2500-1, requires a VT-3 inspection on component supports that includes the support up to the building structure.

ASME Code,Section XI, paragraph IWA-2213(b) requires that, "The VT-3 visual examination may require, as applicable to determine structural integrity, the measurement of clearances, detection of physical displacement, structural adequacy of supporting elements.. .."

Contrary to the above, on September 5,1996, procedure VT-3/4-1, revision 2, "VT-3/4 Visual inspection Performed for Section XI," was used for an inspection and did not specify acceptance criteria for clearances between the building structure and the pipe support baseplate.

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

9612310051 961223 PDR ADOCK 05000295 0 PDR

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Notice of Violation  !

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Pursuant to the provisions of 10 CFR 2,201, Commonwealth Edison is hereby required to ,

submit a written statement of explananon to the U.S. Nuclear Regulatory Commission,  !

ATTN: Document Control Desk, Washington D.C. 20555, with a copy to the Regional l Administrator, Region Ill, and a copy to the NRC Resident inspector at the facility that is

! the 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 "lieply 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 I 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 or include previous docketed correspondence, if the correspondence adequately l

addresses the required response. If an adequate reply is not received within the time  ;

i specified in this Notice, an order or a Demand for Information may be issued as to why the l j license should not be modified, suspended, or revoked, or why such other action as may l

I,a proper should not be taken. Where good cause is shown, consideration will be given to i extending the response time. Because your response will be placed in the NRC Public '

4 Document Room (PDR), to the extent possible, it should not include any personal privacy, I proprietary, or safeguards information so that it can be placed in the PDR without redaction. However, if you find it necessary to include such information, you should  ;

j clearly indicate the specific information that you desire not to be placed in the PDR, and j provide the legal basis to support your request for withholding the information from the -

public. j

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I Dated at Lisle, Illinois, this 23rd day of December 1996 i

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