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Category:Deficiency Report (per 10CFR50.55e and Part 21)
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2023-09-06
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Text
0310212014 U.S. Nuclear Renoulatorv Commission Operations Center Event Report Pa-ve I Part 21 (PAR) Event # 48745 Rep Org: DRESSER-RAND Notification Date I Time: 02/12/2013 16:52 (EST)
Supplier: DRESSER-RAND Event Date I Time: 02/01/2013 (EST)
Last Modification: 02/28/2014 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
- UPDATE FROM JOE MENICHINO TO CHARLES TEAL ON 3/11/13 AT 1614 EDT * **
The following was excerpted from a facsimile received from Dresser-Rand:
"DESCRIPTION OF DEFECT OR NON-COMPLIANCE
)67/9
0310212014 U.S. NuclearRegulatoty Commission Operations Center Event Report Page 2 "Specific designs of steam turbine control valve stems are made from heat treated ASM 5663M Inconel Bar raw material. Certifications associated with heat numbers of certain inventory of this material indicate that the material vendor incorrectly supplied material in an annealed condition (AMS 5662M).
"POTENTIAL SAFETY HAZARD OR NON-COMPLIANCE "Valve stems are used to control steam turbine speed and power. The valve stems must be free to move within the guiding assembly during operation. Stems are made using materials that have the correct material properties to reduce the risk of failure. The use of inconel raw stock in an annealed condition is unacceptable for steam turbine valve stems due to the risk of unacceptable wear and strength characteristics which could lead to sticking or tensile failure in the mating guide bushings within the valve assembly.
"ADVICE TO EFFECTED CLIENT RELATED TO THIS REPORT "For those affected sites identified, locate and return the material to Dresser-Rand immediately."
Affected facilities include Point Beach, Clinton, Wolf Creek, Cooper, Callaway, San Onofre, and Prairie Island.
Notified R1DO (Dentel), R3DO (Dickson), R4DO (Powers), and the Part 21 Group via email.
The following was excerpted from a facsimile received from Dresser-Rand:
"DESCRIPTION OF DEFECT:
"This is an addendum to Part 21 Reports Log# 2013-008-00 and Log# 2013-008-01. Another Vendor certification has been discovered for valve stem material that indicates the annealed condition-Inconel was supplied in lieu of the heat treated that is specified.
"ENGINEERING EVALUATION & RECOMMENDATIONS:
"1- Complete review of all Vendor certification for this material to make certain no more.
Discrepant material was used in the manufacture of these stems.
"2- Identify all DR part numbers that were made using the affected heat numbers.
"3- Notify affected customers and recall non-compliant parts.
"Potential Affected Part Numbers:
"800777-001 Rev. NA "800768-701 Rev. A "800768-702 Rev. A "800858-001 Rev. E "800740-701 Rev. A "800746-001 Rev. B "800739-001 Rev. NA "800743-001 Rev. A "801061-701 Rev. A "800741-701 Rev. B "800744-001 Rev. NA "800745-001 Rev. NA "800748-001 Rev. A "800742-001 Rev. B" Notified R1DO (DeFrancisco), R3DO (Kunowski), R4DO (Hagar), and the Part 21 Group via email.
03/02/2014 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page I Feb. 28. 2014 3:10PM No, 0308 - P. 1 DRESSER-RAND COMPANY DRESSER- RAND 37 Coats Street Wellsville, NY 14896-0592 Phone (716) 596-3631 Fax (716) 593-3369 Feb. 28, 2014 Nuclear Regulatory Commission Attention: Mr. Keith Munmaw NSWCCD Code 934
Subject:
10CFR50art 21 Reporting of defects Find attached an initial report of defbct.
Please call if additional information is required Ed Grandusky Manager Gov't Aftennarket Engineering (585) 596-3631 Office (116) 498-7522 Cell
0' Feb. 28. 2014 3:10PM No. 0308 P. 2 INITIAL REPORT 10CFR PART 21 REPORT OF A POTENTIAL SAFETY HAZARD Report No. 46 Page I of 2 PREPARED BY: E_ J Grandusky Date: 2-20-2014 File No: N/A TITLE: Mgr, Govt. Aftermarket Engineering Serial No: Various Type:
PART NAME: Inconel Valve Stem Part No: See Below Dwg. No: See Below Rev. Level: See Below DESCRIPTION OF DEFECT:
This is an addendum to Part 21 Reports Log # 2013-008-00 and Log # 2013-008-01.
Another Vendor certification has been discovered for valve stem material that indicates the annealed condition- Inconel was supplied in lieu of the heat treated that is specified.
ENGINEERING EVALUATION & RECOMMENDATIONS:
1- Complete review of all Vendor certification for this material to make certain no more discrepant material was used in the manufacture of these stems.
2- Identify all DR part numbers that were made using the affected heat numbers.
3- Notify affected customers and recall non-compliant parts.
Evaluation/Recommendation Prepared By: E. J. Grandusky
Title:
Mgr, Govt. Aftermarket Engineering Date: 2-28-2014 Approved By: Dale Smith
Title:
General Mgr. Government Business Unit Date: 2-28-2014 DISPOSITION, CHECK ONE:
EIXIJ Yes, this constitutes a safety hazard and requires a Final Report be prepared (EF-066)
FI-- No, this does not constitute a safety hazard and does not require any further reporting.
Reviewed by D-R Wellsville R n ible Officer:
Signature:\ _ , -
Title:
General Mgr. Government Business Unit Date: 2-28-2014 RETURN TO MANAGER NUCLEAR PRODUCT ENGINEERING Potential Affected Part Numbers:
800777-001 Rev. NA 800743-001 Rev. A 800768-701 Rev. A 801061-701 Rev. A 800768-702 Rev. A 800741-701 Rev. B 800858-001 Rev. E 800744-001 Rev. NA 800740-701 Rev. A 800745-001 Rev. NA 800746-001 Rev. B 800748-001 Rev. A 800739-001 Rev. NA 800742-001 Rev. B I
NNSOP12001F2, Initial Report 10 CFR Part 21 Report of a Potential Safety Hazard, REV. 00, 07NOV11, Ref. NNSOP-1-2-001
