ML13045A893

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Notification of Part 21 Report - Defective Raw Material Used to Manufacture Valve Stems
ML13045A893
Person / Time
Site: Wolf Creek, Callaway  Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 02/01/2013
From: Martin D
Dresser-Rand
To:
Office of Nuclear Reactor Regulation
References
Download: ML13045A893 (3)


Text

02/12/2013 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page I Part 21 (PAR) Event# 48745 Rep Org: DRESSER-RAND Notification Date / Time: 02/12/2013 16:52 (EST)

Supplier: DRESSER-RAND Event Date / Time: 02/01/2013 (EST)

Last Modification: 02/12/2013 Region: 1 Docket #:

City: WELLSVILLE Agreement State: Yes County: License #:

State: NY NRC Notified by: D. G. MARTIN Notifications: ANTHONY DIMITRIADIS R1DO HQ Ops Officer: DONALD NORWOOD BOB HAGAR R4DO Emergency Class: NON EMERGENCY PART 21 RX GROUP E-MAIL 10 CFR Section:

21.21 (d)(3)(i) DEFECTS AND NONCOMPLIANCE PART 21 REPORT - DEFECTIVE RAW MATERIAL USED TO MANUFACTURE VALVE STEMS Dresser-Rand is reporting that one of its vendors supplied annealed material instead of the specified heat-treated material. Dresser-Rand used the defective raw material to manufacture valve stems for Terry Type Emergency Feedwater pump drive turbines. Dresser-Rand has verified that the annealed material is not acceptable for the finished product.

The two customers (Wolf Creek Nuclear Plant and Callaway Nuclear Plant) that received the affected parts have been notified of this issue and have confirmed that the components in question are not in service at their facilities.

The remaining material and affected parts have been quarantined at the Dresser-Rand plant in Wellsville, NY.

All questions should be addressed to:

Joe Menichino Manager, Navy/Nuclear Product Engineering 37 Coat Street Wellsville, New York, 14895 Phone: (585) 596-3406 jamenichino@dresser-rand.com

DRESSER-RAND 37 Coata SrGQL WellsvilIe, NY 14595-0592 Ph; 5851596-3100 FAX: 5851593-5815 February,12, 2013 To: NRC Operations Center Facsimile (301) 816-5151 In accordance with 10 CFR see. 21.21(d), Dresser-Rand Company hereby notifies the Commission that it has obtained information indicating that one of its vendors supplied defective material that is now in components at two licensed facilities.

The vendor inadvertently supplied annealed material instead of the specified beat-treated material. Dresser-Rand used the defective raw material to manufacture valve stems for Terry Type Emergency Feedwater pump drive turbines. Dresser-Rand has verified that the annealed material is not acceptable for the finished product.

The two customers that received the affected parts have been notified ofthis issue andfhave confirmed that the components in question are not in service at their facilities. The remaining material and affected parts have been quarantined at ourplant in Wellsville, NY.

Our initial written report on this matter is attached. A final report will be provided in accordance with 10 CFRPart 21.

Please address all questions regarding this matter to:

Joe Menichino Manager, Navy / Nuclear Product Engineering Dresser-Rand Government Business Unit 37 Coat Street Wellsville New York 14895 T: (585) 596-3406 / M: (585) 307-4125 IF: (585) 596-3319 jamenichino@dresser-rand.com Sincerely.

D. G. Martin General Manager

Attachment:

Initial Report No. 45

INITIAL REPORT IOCFR PART 21 REPORT OF A POTENTIAL SAFETY HAZARD Report No. 45 Page 1 of i PREPARED BY: J.A. Menichino Date: 2-1-2013 File No:

Mgr, Navy/Nuclear Product TITLE: Engineering . Serial No: Various Type:

PART NAME: Inconel Valve Stem Part No: See List, Pg. 2 Dwg. No: See List, Pg..2 Rev. Level: See List, Pg. 2 DESCRIPTION OF DEFECT:

Raw material heat treatment condition must be validated. Inconel valve stems are made from heat treated AMS 5663M Inconel Bar raw material. Vendor certification for certain heat numbers of this material indicate annealed condition was supplied.

ENGINEERING EVALUATION & RECOMMENDATIONS:

1- Identify all AMS 5663M raw material heat numbers supplied in the annealed condition.

2- Identify all DR part numbers that were made using the affected heat numbers.

3- Investigate the impact of the use of annealed versus heat treated raw material for all items made from this heat of raw material. Justify use of the annealed alternate material or proceed with a recall if the annealed alternate material is found to be unacceptable.

4- If the annealed raw' material is acceptable this is not a reportable safety hazard.

5- If the annealed raw material is unacceptable this is a reportable safety hazard (recall).

6- If recall is required identify all customers that purchased parts made the from the affected heat number(s) of this raw material, 7- If recall is required notify customers and recall non-compliant parts.

8- If recall is required complete DR Final Report NNSOP1200FI Evaluation/Recommendation Prepared By: J.A. Menichino

Title:

M r, Navy/Nuclear Product Engineering . Datw. 2/1/2013 Approved By: Dale Smith

Title:

Government Business Unit Director Date: \ ,h DISPOSITION, CHECK ONE:

[ Yes, this constitutes a safety hazard and requires a Final Report be prepared (EF-O66)

-- No, this does not constitute a safety hazard and does not require any further reporting.

Reviewed by D-R We sponte icer:

Signature:

Title:

6/ti Date:. _,i_____

RETURN TO MANAGER NUCLEAR PRODUCT ENGINEERING NNSOP12001F2, Initial Report 10 CFR Part2l Report of a Potential Safety Hazard, REV. 00, 07NOV11, Ref. NNSOP-1-2-001