ML20045H969

Notice of Violation from Insp on 930614-18.Violation Noted:Replacement of Steam Generator Feedwater Cracked Piping Components Suitability Evaluation Was Inadequate in That It Did Not Provide Evaluation of Suitability

ML20045H969
Person / Time
Site:	Sequoyah
Issue date:	07/07/1993
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20045H965	List: IR 05000327/1993024 ML20045H964 ML20045H969
References
50-327-93-24, 50-328-93-24, NUDOCS 9307220196
Download: ML20045H969 (2)

Text

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l ENCLOSURE 1 NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos.:

50-327 and 50-328 Sequoyah Nuclear Plant License Nos.: DPR-77 and DPR-79 During an NRC inspection conducted on June 14-18, 1993, a violation of NRC requirements was identified.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," the violation is listed below:

10 CFR 50.55a (g) requires in part, that, "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components

....must meet the requirements.... set forth in Section XI of editions of the ASME Boiler and Pressure Vessel Code......" ASME Section XI, Paragraph IWA-7220, requires that, prior to authorizing the installation of a replacement, the owner shall conduct an evaluation of the suitability of the replacement.

4 If the replacement is because of a failure, the cause of the failure shall be considered and, if the cause of the failure appears to be a design deficiency, the specification for the replacement shall reflect appropriate corrective provisions.

10 CFR 50, Appendix B, Criterion V, requires in part, that, " Activities affecting quality shall be prescribed by documented instructions, procedures, and drawings of a type appropriate to the circumstances and shall be accom-plished in accordance with these instructions...."

Paragraph 3.4 of Site Standard Practice SSP-6.9, Repair / Replacement of ASME Section XI Components, requires that a suitability evaluation be performed using Appendix D Replacement Checklist.

Contrary to the above, on June 15, 1993, it was determined that, for replacement of steam generator feedwater cracked piping components in 1992:

(1) The suitability evaluation was inadequate in that it did not provide evaluation of suitability for operations with the "like for like" replacement materials (the components were found to be cracked again during the current outage), and (2) For Unit 2, Appendix D to Procedure SSP-6.9 was not used.

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

Pursuant to the provisions of 10 CFR 2.201, Tennessee Valley Authority 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 II, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, i

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 9307220196 930707 PDR ADOCK 05000327 G

PDR

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Tennessee Valley Authority 2

Docket Nos.:

50-327 and 50-328 Sequoyah Nuclear Plant License Nos.: DPR-77 and DPR-79 corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.

If an adequate reply is not received within the time specified in this Notice, an order or 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.

Dated at Atlanta, Georgia this 7th day of July 1993 I

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