ML20244E246

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Notice of Violation from Insp on 890418-20.Violations Noted: Failure to Perform weld-repair in Accordance W/Asme Code Section IX Requirements & Failure to Establish Measures for Control & Identification Matls to Prevent Misapplication
ML20244E246
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/07/1989
From: Julian C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20244E228 List:
References
50-338-89-13, 50-339-89-13, NUDOCS 8906200228
Download: ML20244E246 (2)


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  • ENCLOSURE 1 NOTICE OF VIOLATION Virginia Electric and Power Company Docket Nos. 50-338, 50-339 North Anna License Nos. NPF-4 and NPF-7 During the Nuclear Regulatory Commission (NRC) inspection conducted on April 18-20, 1989, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1989), the violations are listed below:

A.

10 CFR Part 50, Appendix B, Criterion IX, as implemented by the VEPC0 QA Topical (VEP-1-5A), requires that " Measures shall be established to assure that special processes, including welding, heat treating...., are controlled and accomplished by qualified personnel using qualified procedures in accordance with applicable codes, standards, specifications, criteria, and other special requirements."

ASME Boiler and Pressure Vessel Code,Section IX, 1983 Edition, identifies l post weld heat treatne.it (PWHT), as one of the essential variables of the gas tungsten ARC welding (GTAW) process and subparagraph %W-407.1 of subject code requires that a new procedure qualification. record (PQR), be generated when PWHT is either added to or deleted from production welding.

Contrary to the above, on April 14,1989 PQR 109C, dated May 1988 which was qualified for PWHT production welds, was selected for the weld repair of valve S/N 02-TV-MS-2018 rather than one requiring no PWHT as required by subject code.

This is a Severity Level IV violation (Supplement I and applies only to Unit 2. l l

B.

10 CFR 50, Appendix B, Criterion VIII, as implemented by the VEPC0 QA Topical Report (VEP-1-5A), requires that measures shall be established for the identification control of materials. . . . . .to prevent the use of incorrect or defective materials.

Contrary to the above, on April 20, 1989, two different heats of bare metal wire produced per ASME Specification SFA5.18 and procured per VEPC0 Specification FMS-102 were supplied in two different conditions - as welded impact tested (HT#F8525) and stress relieved impact tested (HT#065496). The material was not segregated or discreet?y identified and the procedures for controlling welding materials contained no provision for identification and/or segregating these materials.

8906200228 890607 PDR G ADOCK 05000338 PNU

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Virginia Electric and Power Company 2 Docket Nos. 50-338, 50-339 North Anna License Nos. NPF-4 and NPF-7 This is a Severity Level IV violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, Virginia Electric and Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Desk Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, North Anna, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Notice of Violation" and should include [for each violation]: (1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time. If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION Caudie A. Julian, Chief Engineering Branch Division of Reactor Safety Dated at! Atlanta, Georgia this idayofJune1989 l

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