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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML17194A8252017-07-11011 July 2017 Part 21 Report Re Wedge Pin Failure in Anchor Darling Motor Operated Double Disc Gate Valves with Threaded Stem to Upper Wedge Connections ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML15103A2442015-04-0606 April 2015 Part 21 Report - Deviation of Hk Circuit Breaker Close Latch Spring 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 ML14113A3982014-04-17017 April 2014 Part 21 - Bearing Defect ML14303A5262014-03-28028 March 2014 Interim Part 21 Report - Misaligned Separators in LCR-25 Standby Batteries ML14079A3532014-03-17017 March 2014 Notification of Part 21 Re Bearing Defect ML14042A2022014-02-0505 February 2014 Part 21 Report Regarding Unqualified Material Used in Electrical Penetration Assemblies ML13277A0102013-09-23023 September 2013 Interim Report Update for Component ASME Material Supplied by Mirion Technologies (Conax Nuclear), Inc. (Mtcn), as Part of Containment Electric Penetration Assemblies (EPA) ML13246A0842013-08-23023 August 2013 Notification of Potential Defect & Interim Report Regarding a Potential Defect of Materials Supplied to Operating Us Nuclear Power Plants by Mirion Technologies (Conax Nuclear) Inc. (Mtcn) with Containment Electric Penetration Assemblies ML13238A2532013-08-21021 August 2013 Notification of Potential Part 21 Report - Foxboro Power Supply Potential Failures Due to Defective the Wraps and Holders ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13093A1532013-04-0202 April 2013 Part 21 Report - Foxboro Power Supply Potential Failures Due to Defective Tie Wraps and Holders ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML13029A4982013-01-18018 January 2013 Notification of Part 21 Report Re Belden Epdm Lead Wire Used in Rewind of Environmentally Qualified (EQ) Form-wound Motors Is Not Fully Qualified ML13002A0292012-12-21021 December 2012 Tennessee Valley Authority, Part 21 Report - Belden Wire Used on Environmentally Qualified Form-Wound Motors Not Fully Qualified ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML12283A2462012-09-28028 September 2012 Part 21 - Fairbanks Morse Opposed Piston EDG Oil Pump Leak 3F0812-05, Interim Report of the Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2)2012-08-21021 August 2012 Interim Report of the Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2) ML12123A0892012-04-27027 April 2012 Abb, Inc., Notification of Potential Part 21 Report - Hk Circuit Breaker Studs Failed to Meet Specification 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 ML12058A1412012-02-23023 February 2012 Part 21 Report - Rosemount Nuclear Instruments, Inc., Pressure Transmitter with Nonzero Based Calibrations ML11186A9042011-06-30030 June 2011 Notification of Potential Part 21 Appendix R Analyses Fails to Recognize Hot-Short Failure Resulting in the Loss of an Essential Electrical Bus 3F0411-04, Notification of Potential Deficiency Report Re - Interim Report of the Evaluation of a Deviation Pursuant to 10 CFR 21.21(A)(2)2011-04-26026 April 2011 Notification of Potential Deficiency Report Re - Interim Report of the Evaluation of a Deviation Pursuant to 10 CFR 21.21(A)(2) 3F0909-05, 10 CFR 21 Report, Concerning Spare Safety-Related Limitorque Actuator Motor with Magnesium Rotor Purchased from Areva Np, Inc., in 2007 and Received in 20082009-09-25025 September 2009 10 CFR 21 Report, Concerning Spare Safety-Related Limitorque Actuator Motor with Magnesium Rotor Purchased from Areva Np, Inc., in 2007 and Received in 2008 ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0831900172008-11-12012 November 2008 Notification of Potential Part 21 on All Dimensionally Verified Commercial Grade Items Processed Per Fisher Manufacture Procedure Fmp 2K28 ML0823901062008-08-25025 August 2008 Notification of Potential Part 21 on Failure of F and G Switches ML0809906342008-04-0404 April 2008 Part 21 Notification Regarding Failure to Comply with the Requirements for Dedication of Commercial Grade Items ML0732000862007-11-0909 November 2007 Notification of Potential Part 21 Report Conval Valves Weld Qualifications ML0727504702007-09-21021 September 2007 MPR Associates, Inc. - Report of Defect in Accordance with 10 CFR 21 ML0710002292007-04-0606 April 2007 Rosemount Nuclear Instruments, Inc., Submittal of Notification Under 10 CFR Part 21 for Certain Model 1152 Pressure Transmitters 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 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 2019-10-25
[Table view] Category:Letter type:
MONTHYEAR3F0623-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-06-0101 June 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0423-03, 2022 Annual Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Annual Radiological Environmental Operating Report 3F0423-02, 2022 Annual Radioactive Effluent Release Report2023-04-18018 April 2023 2022 Annual Radioactive Effluent Release Report 3F0423-01, 2022 Individual Monitoring NRC Form 5 Report2023-04-0404 April 2023 2022 Individual Monitoring NRC Form 5 Report 3F0323-03, Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2023-03-31031 March 2023 Decommissioning Funding Plan for Independent Spent Fuel Storage Installation 3F0323-02, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20222023-03-29029 March 2023 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2022 3F0323-01, Onsite Property Insurance Coverage2023-03-0202 March 2023 Onsite Property Insurance Coverage 3F0123-01, Proof of Financial Protection2023-01-26026 January 2023 Proof of Financial Protection 3F1222-01, Nuclear Power Station - License Amendment Request 262 Addition of License Condition 2.C.21, License Termination Plan2022-12-12012 December 2022 Nuclear Power Station - License Amendment Request 262 Addition of License Condition 2.C.21, License Termination Plan 3F0522-03, Notification of Revised Decommissioning Cost Estimate2022-05-26026 May 2022 Notification of Revised Decommissioning Cost Estimate 3F0522-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20222022-05-17017 May 2022 Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022 3F0422-02, 2021 Annual Radiological Environmental Operating Report2022-04-0606 April 2022 2021 Annual Radiological Environmental Operating Report 3F0322-01, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20212022-03-30030 March 2022 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2021 3F0322-03, Drug and Alcohol Testing Error at HHS-Certified Laboratory, Per 10CFR26.719(c)(1)2022-03-10010 March 2022 Drug and Alcohol Testing Error at HHS-Certified Laboratory, Per 10CFR26.719(c)(1) 3F0322-02, 2021 Individual Monitoring NRC Form 5 Report2022-03-0707 March 2022 2021 Individual Monitoring NRC Form 5 Report 3F0222-01, ADP CR3, LLC - Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2022-02-0909 February 2022 ADP CR3, LLC - Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb) 3F0222-02, Onsite Property Insurance Coverage2022-02-0909 February 2022 Onsite Property Insurance Coverage 3F0122-01, License Amendment Request to Remove from the Facility Operating License, Appendix B, Environmental Protection Plan (Non-Radiological) Technical Specifications2022-01-26026 January 2022 License Amendment Request to Remove from the Facility Operating License, Appendix B, Environmental Protection Plan (Non-Radiological) Technical Specifications 3F0122-02, Proof of Financial Protection2022-01-17017 January 2022 Proof of Financial Protection 3F0122-03, Complex - Environmental Protection Plan Report: 2021 Sea Turtle Rescue and Recovery Summary Report2022-01-17017 January 2022 Complex - Environmental Protection Plan Report: 2021 Sea Turtle Rescue and Recovery Summary Report 3F1021-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-10-21021 October 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0921-02, Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004 (Minor) (Rev. 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Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10CFR21.21 September 25, 2009 3F0909-05 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - 10 CFR 21 Report
Dear Sir:
Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc. (PEF), is submitting this correspondence to provide a 30-day written report to the NRC, pursuant to 10 CFR 21.21, concerning a spare safety-related Limitorque actuator motor with a magnesium rotor purchased from AREVA NP, Inc., in 2007 and received in 2008. The Attachment to this submittal contains the required 30-day report.
The potentially reportable condition was identified on July 31, 2009. The reportability evaluation was completed on August, 28, 2009. The FPC Responsible Officer was notified of the reportability evaluation results on August 31, 2009. The 2-day facsimile required pursuant to 10 CFR 21.21 was transmitted to the NRC Operations Center, and receipt of the facsimile was confirmed (Event No. 45317) on September 1, 2009. Limitorque was notified of FPC's intention to report the enclosed issue to the NRC under 10 CFR 21.21.
No new commitments are contained in this submittal.
If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Supervisor, Licensing and Regulatory Programs at (352) 563-4796.
Sincerely, lms W. Holt Plant General Manager Crystal River Unit 3 JWH/dwh
Attachment:
10 CFR 21 Report xc: NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Progress Energy Florida, Inc.
Crystal River Nuclear Plant ,
15760 W. Power Line Street Crystal River, FL 34428
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER - UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT 10 CFR 21 REPORT
U. S. Nuclear Regulatory Commission Attachment 3F0909-05 Page 1 of 3 10 CFR 21 REPORT 10 CFR 21.21(d)(4) requires that the 30-day written report shall include, but need not be limited to, the following information, to the extent known:
(i) Name and address of the individual or individuals informing the Commission.
Progress Energy Florida, Inc. (PEF)
Florida Power Corporation (FPC)
Crystal River Unit 3 (CR-3) 15760 West Power Line Street Crystal River, Florida 34428-6708 (ii) 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 a defect.
The basic component is a spare safety-related Limitorque SB-3/SMB-3 actuator motor (Motor Serial Number 7497004-001T1AL; Limitorque Part No. R-403-F04-0821) with a magnesium rotor that was purchased as Quality Level 1 (QL-1).
(iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
The spare safety-related Limitorque SB-3/SMB-3 actuator motor with a magnesium rotor was purchased from AREVA NP, Inc., under Purchase Order No. 337566 in 2007 and received in 2008. Limitorque purchased the motor from the Baldor Electric Company, doing business as the Reliance Electric Company, as commercial grade and dedicated the motor as safety-related.
(iv) 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.
CR-3 personnel performed a pre-installation video probe inspection of a spare safety-related Limitorque SB-3/SMB-3 actuator motor with a magnesium rotor. This inspection was not part of an FPC receipt inspection. Visual indications were observed in the outboard end of the motor which were cause for rejection based on specified acceptance criteria. The specific indication was a cracked weld with dislodged metal in the outboard end of the motor. The piece of dislodged metal was visible in the end ring hub and was not moveable with the video probe head.
Based on the location of the piece of dislodged metal, the object could significantly damage the motor windings and short out the motor. This could occur within seconds of the first start of the motor or any subsequent starts. Failure timing would depend on where the object is thrown when the motor starts, how and where it ricochets within the end bell, and where it lands when the motor is secured.
The spare safety-related Limitorque actuator motor with a magnesium rotor was designated for use in Decay Heat Removal System (DH) pump DHP-1A Low Pressure Injection (LPI) isolation valve DHV-5. The safety function of DHV-5 is to automatically
U. S. Nuclear Regulatory Commission Attachment 3F0909-05 Page 2 of 3 open on a 500 pound per square inch gauge (psig) LPI actuation signal, allowing water to be injected into the core.
NUREG-0302, "Remarks Presented (Questions/Answers Discussed) at Public Regional Meetings to Discuss Regulations (10 CFR Part 21) for Reporting of Defects and Noncompliance," Revision 1, Page 21.3(d)-8, states the following:
"Quality assurance inspections or tests performed by the licensee cannot be counted upon to prevent installation of defective basic components. In evaluating deviations the assumption which must be made is that the component is installed in the facility, then if it could create a substantial safety hazard it must be reported to the NRC as a defect."
NUREG-0302, Page 21.3(k)-2, states the following: "The loss of safety function of a basic component is considered a major reduction in the degree of protection provided to the public health and safety. It is possible that the defect might also exist in the redundant basic component, which could result in a loss of safety function. The existence of a defective basic component, considering a single failure of its counterpart redundant basic component, could result in a loss of safety function. Actually, the counterpart component need not fail. It could be removed from service for other reasons such as routine preventive maintenance or inspection."
Using the above guidance from NUREG-0302, it is assumed that the spare actuator motor, with the cracked weld and dislodged metal in the outboard end of the motor, is installed in the plant and returned to service. Assuming a single active failure of the redundant train component (DHV-6) during a limiting plant event, failure of DHV-5 could potentially result in no LPI flow to the reactor core during a hypothetical limiting Large Break Loss of Coolant Accident. This condition would represent a loss of a safety function to the extent that there would have been a major reduction in the degree of protection provided to ensure public health and safety.
Based on the above, CR-3 concludes that the identified deviation is reportable pursuant to 10 CFR 21.21 as a defect associated with a substantial safety hazard.
(v) The date on which the information of such defect or failure to comply was obtained.
CR-3 personnel performed a pre-installation video probe inspection of the spare safety-related Limitorque SB-3/SMB-3 actuator motor with a magnesium rotor on July 31, 2009.
(vi) In the case of a basic component which contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations of this part.
There are thirteen (13) spare safety-related Limitorque actuator motors with magnesium rotors on hand in the warehouse that are designated for use in the plant.
U. S. Nuclear Regulatory Commission Attachment 3F0909-05 Page 3 of 3 Catalog Identification (CAT ID) Number CAT ID 63280477 1 CAT.ID 65380481 1 CAT ID 67881087 1 CAT ID 9220137082 1 CAT ID 63280192 1 CAT ID 61960476 1 CAT ID 62980473 3 CAT ID 63280652 1 CAT ID 9220110861 1 CAT ID 61960482 1 CAT ID 63280479 1 (vii) 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.
FPC Immediate Corrective Action The thirteen (13) spare safety-related Limitorque actuator motors with magnesium rotors in stock had previously been placed on HOLD pending evaluations due to a previous CR-3 Corrective Action Program Nuclear Condition Report (NCR 174428) associated with the failure of the magnesium rotor for Main Feedwater block valve FWV-29.
The spare safety-related Limitorque actuator motor with a magnesium rotor designated for use in DHV-5 was returned to the vendor (AREVA NP, Inc.) for evaluation and replacement.
Limitorque Root Cause Unknown Limitoraue Corrective Actions Unknown (viii) 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.
Licensees should perform a video probe inspection of any spare safety-related Limitorque actuator motors with a magnesium rotor as part of their receipt inspection.