ML14094A445
| ML14094A445 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Palo Verde, Catawba, Wolf Creek, Point Beach, Cooper, Prairie Island, Callaway, Clinton, San Onofre  |
| Issue date: | 04/01/2014 |
| From: | Grandusky E Dresser-Rand |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 48745 | |
| Download: ML14094A445 (5) | |
Text
Od/O1/2O l d Pnop I 04f)10/2014 UL.S. Nuclear R latiaor~ Commission flnerationn Center Event R nnrt Pnwl 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: 04/01/2014 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
04/01/2014 U.S. Nuclear Regulatory 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 R1 DO (Dentel), R3DO (Dickson), R4DO (Powers), and the Part 21 Group via email.
- *
- UPDATE FROM ED GRANDUSKY TO CHARLES TEAL AT 1510 EST ON 2/28/14 * *
- 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.
04/01/2014 U.S. Nuclear Regulatory Commission Operations Center Event Report Page 3
- * *UPDATE FROM ED GRANDUSKY TO JEFF ROTTON AT 1520 EDT ON 04/01/2014 ***
The following information is excepted from a facsimile provided by Dresser-Rand:
Specifications for valve stems provided to Palo Verde (Part Number W800743-001), Tihange 2 (Part Number W800746-001), Catawba (Part Number W800746-001), and Davis Besse (Part Number (W800746-001) call for the material to be heat treated AMS 5663M Inconel Bar. Certifications associated with another heat number of material indicate that the vendor supplied material in an annealed condition (AMS 5662M). The lower mechanical properties of the AMS 5662M could lead to shorter operating life for these stems.
The material certification for all Inconel valve stems has been reviewed back to the first Inconel stem made by Dresser-Rand. No new corrective actions were deemed necessary. The four sites listed above should locate and return the valve stems immediately to Dresser-Rand for evaluation.
Notified R2DO (Vias), R3DO (Passehl), R4DO (Gepford), and the 10CFR Part 21 Group via email.
- Apr, 1, 2014 3:20PM No. 09 5 1 P. I DRESSER RAND DRESSER-RAND COMPANY 37 Coats Street Wellsville, NY 14895-0592 Phone (716) 596-3631 Fax (716) 593-3369 April 1, 2014 Fax#: 301-816-5151 Nuclear Regulatory Commission
Subject:
10CFRS0art 21 Reporting of defects Find attached our final report of defect. This report is Dresser -Rand number 46.
Please call if additional information is required Ed Grandusky Manager Gov't Aftermarket Engineering (585) 596-3631 Office (716) 498-7522 Cell
Apr. 1. 2014 3:20PM No. 0951 P. 2 FINAL REPORT 10CFR PART 21 REPORT OF A POTENTIAL SAFETY HAZARD Report No.
46 Page 1 of I PREPARED BY:
Ed Grandusky File No:
Various Serial No:
Various Manager Gov't Aftermarket TITLE: Engineering Type:
Various Ref:
Report #45 PART NAME:
Inconel Valve Stem DR Part No:
Various DR Dwg No:
Various Rev. Level:
Various
- 1. DESCRIPTION OF DEFECT OR NON-COMPLIANCE As previously identified in Reports Log # 2013-008-00 and Log # 2013-008-01, specifications for these valve stems call for the material to be heat treated AMS 5663M Inconel Bar.
Certifications associated with another heat number of material indicate that the vendor supplied material in an annealed condition (AMS 5662M),
- 2. POTENTIAL SAFETY HAZARD OR NON-COMPLIANCE The lower mechanical properties of the AMS 5662M could lead to shorter operating life for these stems.
- 3. NUMBER AND LOCATION OF ALL COMPONENTS Nuclear Site Client PO#
D-R P/N" Qty D-R Order No.
Ship Date Palo Verde 40568ABC 500525835 W800743-001 3
CSS 417027 4/2/2009 Tihange 2 40814A 63913/RU W800746-001 2
CSS 424709 10/13/2009 Catawaba 40096AB 00121072 W800746-001 1 CSS 454423 3/11/2010 Davis Besse 37686AB 00123023 W800746-001 2
CSS 462246 3/11/2010
- 4. CORRECTION ACTION BY:
Staff COMPLETED BY 3/27/2014 This condition was discovered because of the corrective actions defined on Dresser-Rand report no. 45. The material certification for all Inconel valve stems has been reviewed back to the first Inconel stem made by Dresser-Rand. No new corrective actions were deemed necessary.
See Part 21 Reports Log # 2013-008-00 and 2013-008-01 for previous Corrective Actions.
- 5. ADVICE TO EFFECTED CLIENT RELATED TO THIS REPORT The 4 sites identified in section 3 should locate and return the valve stems to Dresser-Rand immediately for evaluation.
NNSOP1200IFl (Final Report 10 CFR Part 21 Report of a Potential Safety Hazard), REV. 00, 25JUN08 Reference NNSOP-1-2-001