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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24088A1142024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Report 23-02 Re Synchro-Start Mini-Gen Signal Generator NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers ML22307A0602022-11-0303 November 2022 EN 56200 - Fairbanks Morse Re Basic Component Which Fails to Comply or Contains a Defect ML20028D3802020-01-13013 January 2020 10CFR21 Notification for Ashcroft 2-1/2 & 3-1/2 1009, 63mm 2008, 63mm & 100mm 1008 Industrial Gauges, Weksler 3-1/2 Regal Gauges ML19190A0442019-06-0707 June 2019 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19158A1312019-05-31031 May 2019 Paragon Energy Systems LLC -10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML17340A3922017-11-28028 November 2017 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0119, Rev. 0 ML17333A3792017-11-21021 November 2017 Engine Systems, Inc. 10 CFR 21 Reportable Notification on a Power Supply (P/N 2938604) ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16125A3602016-04-26026 April 2016 Part 21 - Hydraulic Snubber Seal Material Deviation Interim Report ML15089A4372015-03-20020 March 2015 Part 21 - Dual Alarm Modules That May Contain Faulty Diodes in Single State Relays ML14274A0522014-09-22022 September 2014 Final Report 10CFR Part 21 Evaluation Regarding Misaligned Separators in LCR-25 Standby Batteries, Revision 1 - Original Letter Did Not Include the List of Affected Utilities ML13211A1682013-07-26026 July 2013 Westinghouse, Notification of Potential Existence of Defects Pursuant to 10 CFR Part 21 Inconsistency Between the Intended Design Functionality of the Shield Passive Thermal Shutdown Seal (SDS) and That Observed During Post-Service Testing ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13092A1182013-03-29029 March 2013 Notification of Potential Part 21 Interim Report on the Failure of an Emergency Diesel Generator Excitation System ML13063A4432013-03-0101 March 2013 10 CFR Part 21 Report Notification, Dual Alarm Modules and Single Alarm Modules ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers ML12283A2462012-09-28028 September 2012 Part 21 - Fairbanks Morse Opposed Piston EDG Oil Pump Leak ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12097A3162012-03-0202 March 2012 Part 21 Report - Rosemont Pressure Tranmitters Out of Tolerance Condition ML11251A1982011-09-0606 September 2011 Notification Under 10 CFR Part 21 on Certain Rosemount Model 1153 Series B, 1164 and 1154 Series H Pressure Transmitters, May Not Perform Their Intended Safety Function ML1108400372011-03-23023 March 2011 Notification of Potential Part 21 Report Concerning Valve Plunger Guide Malfunction ML1031304232010-11-0808 November 2010 Notification of Potential Part 21 from Curtiss Wright Flow Control Co., on UPS Motherboard Failed Pre-Service Inspection ML1016001892010-06-0404 June 2010 Notification of Potential Part 21 on Final Report Dresser-Rand No. 042 ML1013803972010-05-13013 May 2010 Part 21 Report - Lugs on Digital Filter Improperly Soldered ML1004700232010-02-0101 February 2010 Title 10 Code of Federal Regulation Part 21 Notification: Service Water Pump (2E) Failure at Farley Nuclear Station ML1002903682010-01-27027 January 2010 Sulzer Pumps, Inc. Part 21 Report (Event #45666) Re Defect in Pump Shaft Journal Coating Caused Service Water Pump (2E) Failure at Farley Nuclear Station ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0903300562009-01-27027 January 2009 Notification of Potential Part 21 Report from Fisher Controls International, Part Not Evaluated for All Critical Characteristics ML0833301872008-11-21021 November 2008 Notification of Potential Part 21 Re Tyco Electronics, Transfer of Information - CII-012 ML0828403842008-10-0303 October 2008 10 CFR Part 21 Reporting Thread Sealant Issue ML0823901062008-08-25025 August 2008 Notification of Potential Part 21 on Failure of F and G Switches NL-07-1959, 10 CFR 21 Report, Notification of Potential Defect Associated with Areva Model MA-VR-350 4160 V Circuit Breakers2007-11-14014 November 2007 10 CFR 21 Report, Notification of Potential Defect Associated with Areva Model MA-VR-350 4160 V Circuit Breakers ML0727504702007-09-21021 September 2007 MPR Associates, Inc. - Report of Defect in Accordance with 10 CFR 21 ML0710101252007-04-0909 April 2007 Fairbanks Morse Engine, Part 21 Notification - Diesel Cam Roller Bushing Failures ML0710002292007-04-0606 April 2007 Rosemount Nuclear Instruments, Inc., Submittal of Notification Under 10 CFR Part 21 for Certain Model 1152 Pressure Transmitters ML0706802882007-03-0707 March 2007 Notification of Potential Part 21 on Defect in E7000 Relays ML0713703092007-03-0707 March 2007 Velan, Inc., Piston Check Cv Information ML0627702242006-09-27027 September 2006 Part 21 Report from Tyco Valves & Controls LP, Improper Valve Springs in Pressure Relief Valves ML0614300172006-05-20020 May 2006 Sulzer Pumps (Us), Inc. Is Reporting Deviation from Technical Requirements for Components to Be Used in Nuclear Safety Related Applications ML0536403292005-12-28028 December 2005 Notification of Deficiency Report (10 CFR Part 21) for Rosemount Nuclear Instruments Transmitters ML0517902372005-06-24024 June 2005 Part 21 Notification - Critical Power Determination for G314 and GE12 Fuel with Zircaloy Spacers, 06/24/2005 ML0501102232005-01-0707 January 2005 Non-Emergency Event Report, Overstress Condition on Single Failure Proof Crane Trolleys ML0312001162003-04-21021 April 2003 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR 21-0086, Rev. 0 ML0215102952002-05-15015 May 2002 10 CFR 21 Notification - Potential Defect Fan Assemblies for UPS Systems ML0215502492002-05-10010 May 2002 Letter from W. G. Hampton Subject: 10CFR Part 21 Notification-Potenial Defect Involving Fan Assemblies Used in Forced Air Cooled Uninterruptible Power Supply Systems 2024-02-25
[Table view] Category:Letter
MONTHYEARNL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 2024-09-05
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Text
Sulzer Pumps (US) Inc.
Customer Support Services Donald B. Spencer, P.E.
General Manager, Nuclear Services th 200 SW Market St., 4 Floor Portland, OR 97201 Director, Office of Nuclear Regulation Document 2010-001 Revision 1 U.S. Nuclear Regulatory Commission Washington, DC 20555 February 1, 2010 (Revision 1)
(Original January 27, 2010)
Subject:
Title 10 Code of Federal Regulation Part 21 Notification:
Service Water Pump (2E) Failure at Farley Nuclear Station
Dear Sir or Madam,
Pursuant to Title 10, Code of Federal Regulations, Part 21, reporting requirements, Sulzer Pumps (US)
Inc is reporting that a basic component (Service Water Pump (2E)) at the Farley Nuclear Station located in the state of Alabama contains a defect. Per part 21.21(4), the following information is required for this notification:
- 1. Name and address of the individual or individuals informing the Commission:
Response
Donald B. Spencer, P.E.
General Manager, Nuclear Services 4126 Caine Lane Chattanooga, TN 37421
- 2. Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains defect:
Response
Facility: Farley Nuclear Plant Basic Component: Unit 2 Service Water Pump (2E)
- 3. Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect:
Response
Sulzer Pumps (US) Inc, Chattanooga Nuclear Service Center
- 4. Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply:
Response
Defect of pump shaft journal coating resulting in failure of basic component (Service Water Pump 2E).
Page 1/4
- 5. The date on which the information of such defect or failure to comply was obtained:
Response
December 5, 2009
- 6. In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part:
Response
Sulzer Pumps (US) Inc, Chattanooga Service Center received Farley Purchase Order QP060449 for eleven (11) Service Water Pumps. The following table outlines current status of the pumps on this order:
Serial Number Status Ship Date Location 08C02139 Shipped 12/18/07 Farley 08C02140 Shipped 5/19/08 Farley 08C02141 Shipped 11/5/08 Farley 08C02142 In Manufacturing N/A Sulzer Chattanooga 08C02143 In Manufacturing N/A Sulzer Chattanooga 08C02144 In Manufacturing N/A Sulzer Chattanooga Originally Shipped Sulzer Chattanooga 08C02145 Failed in Plant 11/14/06 for evaluation 08C02146 Shipped 8/3/07 Farley 08C02147 Shipped 7/30/08 Farley 08C02148 In Manufacturing N/A Sulzer Chattanooga 08C02149 In Manufacturing N/A Sulzer Chattanooga Other Licensees where similar shaft coating condition may exist (Revision 1):
Location Service Status Sulzer Serial Number(s)
Duane Arnold Essential Service Water Shipped NTL1039 / 40, (head, line and pump shafts) NB6701 Duane Arnold River Water Shipped NRW6511 / 15 (pump shaft, 1 head shaft)
Duane Arnold RHR Service Water Shipped NRT-5570 / 71 (pump shaft) NRX-6542 / 43 NC6527 TVA/ Sequoyah Emer. Raw Cooling Water Shipped NH1221 / 28 (line shafts, upper line shaft)
Vermont Yankee Emer. Service Water Shipped Sulzer Job: 08C02642 (refurbished head shaft) VY PO# 10156608 Page 2/4
- 7. The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action:
Response
A joint root cause evaluation has been completed by Sulzer Pumps (US) and Farley. Corrective actions will include replacement parts with updated and corrected design. Sulzer is developing a manufacturing schedule to implement the corrective actions (estimated completion for schedule, 1st Quarter 2010).
For the other licensee installations where this defect may exist, Sulzer will review shaft designs and existing documentation from coating supplier(s) to determine corrective action required (estimated completion date Feb. 12, 2010).
- 8. Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being or will be given to purchasers or licensees:
Response
A comprehensive root cause report has been jointly developed and accepted by Sulzer and Farley.
- 9. In the case of an early site permit, the entities to whom an early site permit was transferred:
Response
Not applicable.
Very truly yours, Donald B. Spencer, P.E.
General Manager, Nuclear Services CC: Mauricio Bannwart, President, Sulzer Pumps (US) Inc Warren Brandon, Manager Nuclear Service Center, Sulzer Pumps (US) Inc Tommy Craig, SNSC Quality Assurance Manager, Sulzer Pumps (US) Inc Roy Horner, Vice President CSS, Sulzer Pumps (US) Inc Tom Milton, Southern Company, Licensing Karl Strand, SPUSA Quality Assurance Manager, Sulzer Pumps (US) Inc Art Washburn, SNSC Engineering Manager, Sulzer Pumps (US) Inc General Manager Supply Chain Management Southern Nuclear Operating Company 42 Inverness Center Parkway Post Office Box 1295, BIN 243 Birmingham, AL 35201 Attn: Nuclear Supply Chain Admin Specialist Materials Management Records Control Duane Arnold Energy Center 3277 DAEC Road Palo, IA 62324 DAEC_Supplier@fpl.com Page 3/4
Attn: Manager, Operating Experience TVA Nuclear Nuclear Assurance and Licensing 1101 Market St.
Chattanooga, TN 37402-2801 Attn: Alan Ettlinger, Manager, Operating Experience & Corrective Action Entergy Nuclear Operations Echelon One 1340 Echelon Parkway Jackson, MS 39213 Page 4/4