ML20199L002

Notice of Violation from Insp on 860318-0505

ML20199L002
Person / Time
Site:	Vermont Yankee
Issue date:	07/03/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20199K999	List: IR 05000271/1986008 ML20199K991 ML20199L002
References
50-271-86-08, 50-271-86-8, NUDOCS 8607090290
Download: ML20199L002 (2)

Text

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APPENDIX A NOTICE OF VIOLATION Vermont Yankee Nuclear Power Corporation Docket No. 50-271 Vermont Yankee Nuclear Power Station License No. DPR.-28 Vernon, Vermont As a result of the inspection conducted on March 18 - May 5, 1986, and in accord-ance with the revised NRC Enforcement Policy (10 CFR 2, Appendix C), published in the Federal Register on March 8, 1984 (49 FR 8583), the violation discussed below was identified.

The licensee procured and accepted into stores 35 contact blocks from.the NAMCO Controls Co. under purchase order (P0) 20145 in 1983. All 35 blocks were accepted as satisfactory based on a sampling review during receipt inspection. While re-building reactor protection system (RPS) and position indication switches for the main steam isolation valves (MSIVs) in January 1986, licensee technicians noted cracks and chip defects on 15 of the 35 contact blocks from P0 20145. Nonconform-ance Report (NCR) 86-07 was issued per plant QA procedures to address the finding and was closed on 3/19/86 following actions to remove defective contact blocks from stores and the MSIV switches and return them to the vendor. The licensee submitted a report dated 3/28/86 per 10 CFR Part 21 indicating that a defect may exist with respect to use of the contact block kits in safety related reactor circuits, in that, although not tested in the damaged condition, it was judged possible that the defective blocks could have resulted in a failure of the RPS trip inputs. NRC review from March 27 - April 8, 1986 of switch blocks installed in the MSIVs and NAMCO parts in Stores, identified components with defects of the type previously evaluated by the licensee as questionable in quality and therefore unacceptable for use in safety related circuits. The parts with defects were identified after the licensee had completed his planned corrective actions on the valves.

A. 10 CFR 50, Appendix B. Criterion XV - Nonconforming Materials, Parts or Com-ponents, requires that measures be established to control nonconforming mate-rials in order to prevent their inadvertent use or installation. Criterion XVI of 10 CFR 50 - Corrective Actions, requires the licensee to establish measures to assure that conditions adverse to quality such as defective mate-rial be promptly identified and corrected, including actions to preclude the recurrence of significant conditions.

Sections XV and XVI of the licensee Quality Assurance Manual, Topical Report Y0QAP-I-A Revision 15 establishe's measures to assure the requirements of 10 CFR 50 are met. YOQAP Section XV.C.1 states that satisfaction of the require-ments of Criterion XV shall be assured through the identification, inspection and segration of nonconforming items. YOQAP Section XVI.B.3 states the satis-faction of the requirements of Criterion XVI shall be assured by plant actions to identify the cause of conditions adverse to quality and the implementation of corrective actions. Nonconformance Report (NCR) 86-07 was written on 1/1/86 to document the identification of 15 defective contact blocks purchased in 1983. The NCR was dispositioned as satisfactorily closed on 3/19/86 fol-8607090290 860703

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Appendix A 2 lowing segregation and return of the 15 defective blocks back to the vendor for credit, and pending completion of actions to perform a followup evaluation of the vendor QA program.

Contrary to the above, nonconforming materials were not controlled to prevent inadvertent use or installation, in that NRC inspection from March 27 - April 8, 1986 identified the following defective NAMC0 parts: Stores - 2 parts (of

18) with crack defects; MSIVs - 8 parts (of 32) with chip defects. Addition-ally, required measures were not taken to prevent recurrence of installation or use of such potentially defective materials, in that the licensee's cor-rective actions per NCR 86-07 did not address inspection / review of similar (bakelite) parts in Stores to verify whether similar defects existed.

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

Pursuant to the provisions of 10 CFR 2.201, Vermont Yankee Nuclear Power Corpora-tion of Vernon, Vermont, is hereby required to submit to this office within thirty days of the date of the letter transmitting this Notice, a written statement of explanation in reply, including for each violation: (1) corrective steps which

' have been taken and the results achieved; (2) corrective steps that will be taken to avoid further violations; and (3) the date when corrective actions will be com-pleted. Where good cause is shown, consideration will be given to extend your response time.