ML20247D668

Notice of Violation from Insp on 971216-980309.Violations Noted:Weld Procedure Wps GT-SM/1.1-1 Pb,Rev 4,used to Fabricate SG Replacement Main Steam & Feedwater Welds,Did Not Meet Requirements of QW-409.1

ML20247D668
Person / Time
Site:	Point Beach
Issue date:	05/05/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20247D666	List: IR 05000301/1998005 ML20247D660 ML20247D668
References
50-301-98-05, 50-301-98-5, NUDOCS 9805180018
Download: ML20247D668 (3)

Text

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l NOTICE OF VIOLATION '

I l Wisconsin Electric Power Company Docket No. 50-301 Point Beach Nuclear Plant License No. DPR-27 i

During an NRC inspection conducted from December 16,1997, through March 9,1998, four l

violations of NRC requirements were identified. In accordance with NUREG-1600, " General l Statement of Policy and Procedure for NRC Enforcement Actions," the violations are listed l below- >

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1. 10 CFR 50, Appendix B, Criterion IX," Control of Special Processes," requires, in part, {

that measures shall be established to assure that special processes, including welding, i l and heat treating, are controlled and accomplished by qualified personnel using qualilled l procedures in accordance with applicable codes, and standards.

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The 1995 Edition of the American Society for Mechanical Engineers Code,Section IX, Paragraph QW-409.1, requires that "A change in the type of current or polarity, an increase in heat input, or an increase in volume of weld metal deposited per unit length of weld, [is not allowed) over that qualified."

(a) Contrary to the above, in November and December of 1996, weld procedure  ;

WPS GT-SM/1.1-1 PB, Revision 4, used to fabricate steam generator replacement main steam and feedwater welds, did not meet the requirements of .

QW-409.1 Specifically, this weld procedure authorized welding with an increase l in heat input over that which had been qualified.

This is a Severity Level IV violation (Supplement I). (VIO 00-301/98005-01(DRS))

(b) Contrary to the above, in November of 1996, weld procedure WPS GT-SM-BU/1.3-1 PB, Revision 1, used to perform welding on the steam generator feedwater nozzle weld, did not meet the requirements of QW-409.1.

Specifically, this weld procedure authorized welding with an increase in heat input over that which had been qualified.

This is a Severity Level IV violation (Supplement 1). (VIO 50-301/98005-02(DRS))

2. 10 CFR 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings" requires l that activities affecting quality shall be prescribed by documented instructions and l

procedures and shall be accomplished in accordance with those instructions and procedures.

Contrary to the above, activities affecting quality were not performed in accordance with documented procedures, in that, on December 9 and 10,1996, post weld heat treatments were applied to two main steam welds, FW-6 on steam generators A and B, which had material thicknesses of 1.3 inches; however, the procedure prescribing heat treatment, WPS GT-SM/1.1-1 PB Revision 4, cordained no instructions for material thickness below 1.5 inches.

This is a Severity Level IV violation (Supplement I). (VIO 50-301/98005-03(DRS))

9805180018 980505 PDR ADOCK 05000301 G PDR

s Notice of Violation 2

3. 10 CFR 50, Appendix B, Criterion XVil, " Quality Assurance Records," requires, in part, that sufficient records shall be maintained to fumish evidence of activities affecting quality.

Contrary to the above, as of March 9,1998, records for the welding processes used on Unit 2 steam Generators, were not sufficient to furnish evidence of activities affecung quality in the following instances:

1 (a). Weld Data Card (WDC) 3042-A-2 and WDC 3042-B-2 for steam generator A and B feedwater nozzle welds, listed a weld procedure which was not used to fabricate the weld.

(b) WDC 3081-B-7 for a feedwater weld, did not record the correct weld procedure revision used to fabricate the weld.

'(c) WDC 3081-A-2 for a main steam weld, did not record the correct weld procedure revision used to fabricate the weld.

This is a Severity Level IV violation'(Supplement I). (VIO 50-301/98005-04a,b,c(DRS))

Pursuant to the provisions of 10 CFR 2.201, Wisconsin Electric Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory j Commission, ATTN: Document Control Desk, Washington,' DC 20555 with a copy to the l Regional 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

, l 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 or severity level; (2) the corrective steps that have been taken and the i 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 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.

If you contest this enforcement action, you should also provide a copy of your response to the

. Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

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l Notice of Violation 3 Because your 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 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 l l response that deletes such information. If you request withholding of such material, you muS1 I specifically identify the portions of your response that you seek to have withheld and provide iri detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted 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 l provide the level of protection described in 10 CFR 73.21.

Dated at Lisle, Illinois this 5th day of May 1998 l

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