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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML18341A2472018-12-0606 December 2018 Mirion Technologies - 10 CFR Part 21.21 Report Re Relays Defect ML18302A2282018-10-19019 October 2018 Itt Enidine - USNRC 10CFR Part 21 Notification ML18078A5362018-01-31031 January 2018 Crane Nuclear, Inc. - Interim Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem (Update) ML17243A1362017-08-28028 August 2017 Fisher Information Notice, (FIN) 2017-04 - Erroneous Rotary Seating Torque Calculation in Flowscanner Software ML17228A0482017-08-14014 August 2017 Final 10 CFR Part 21.21 Report Re Defect of Manual Flow Controller Used at Fort Calhoun Nuclear Station 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 ML17114A0702017-04-13013 April 2017 Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards 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 ML16294A2642016-10-18018 October 2016 Part 21 Report - Defective Current to Pressure Transducers ML16278A4712016-09-22022 September 2016 Notification of 10 CFR Part 21 Condition, Masterpact Breaker Fail to Close ML16281A2702016-09-22022 September 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML16243A4742016-08-26026 August 2016 Potential Part 21 Unqualified Component in Certain Allen Bradley Timing Relays ML16232A6042016-08-15015 August 2016 Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML16238A1862016-08-15015 August 2016 Update - Report of Potential l0CFR Part 21, Allen Bradley Timing Relay Model 700RTC-NRC Event Number 51030, Accession Number ML15134A016 ML16154A2072016-05-26026 May 2016 Part 21, Azz/Nli Nuclear Logistics, Inc., Potentially Unqualified Component in Certain Allen Bradley Timing Relays Model 700RTC ML16194A1992016-05-25025 May 2016 Azz/Nli - Update - Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML16111A4202016-04-0808 April 2016 Part 21 Report No. P21-04302015, Rev. 1 Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays, Per Browns Ferry, Ginna, Millstone, Nine Mile Point, North Anna, Ft. Calhoun, Perry, River Bend, South Texas Project ML16035A2542016-01-26026 January 2016 Canberra Industries, Inc. - Interim 10 CFR Part 21.21 Report Regarding Modification Kit for Manual Flow Controller, Relay, Time Delay, Motor, Pump ML15341A3282015-12-0101 December 2015 Part 21 Report Regarding Improper Silver Plating During Refurbishment of AK-25 Type Circuit Breakers, Per Fort Calhoun, Unit 1 ML15205A2932015-07-20020 July 2015 Potential Part 21 Report Regarding Bradley Failure to Document Design Change, Per Fort Calhoun Station ML15134A0162015-05-0101 May 2015 Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML15159A5682015-04-30030 April 2015 Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML15014A0612015-01-0808 January 2015 Notification of Potential Part 21 Re Failure of Sbm Type Switches 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 ML14069A4672014-02-26026 February 2014 Part 21 Report Involving a Potential Manufacturing Defect in Replacement Masterpact Cradles ML14071A4772014-02-26026 February 2014 Report of Potential Defect Per 1OCFR Part 21 Primary Disconnect Assembly ML13346A0272013-10-0808 October 2013 Ultra Electronics Nuclear Sensors & Process Instrumentation, 10 CFR21 Final Report - Linear Indications/Cracks in Flange Forging, Model Ne 13DM Pressure Transmitter ML13238A2532013-08-21021 August 2013 Notification of Potential Part 21 Report - Foxboro Power Supply Potential Failures Due to Defective the Wraps and Holders ML13191A5712013-06-28028 June 2013 10CFR21 Interim Report - Linear Indications/Cracks in Flange Forging, Model N-E13DM Pressure Transmitter ML13190A3612013-06-28028 June 2013 Part 21 Interim Report - Linear Indications/Cracks in Pressure Transmitter Flange Forging ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13102A3032013-04-10010 April 2013 Part 21 Involving a Potential Weld Defect ML13091A3872013-03-28028 March 2013 Part 21 Report - Foxboro Power Supply Potential Failure 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 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 ML12283A2432012-10-0505 October 2012 Part 21 - Steam Generator Tube Wear Adjacent to Retainer Bars ML12199A2222012-07-11011 July 2012 Part 21- Failed Auxiliary Contactor Affecting Diesel Generator LIC-11-0034, Part 21 Notification - Identification of Defect2011-04-19019 April 2011 Part 21 Notification - Identification of Defect ML1108100642011-03-21021 March 2011 Notification of Potential Part 21 Re Defective KPR-14G-125 Relays Discovered During Bench Testing ML1009200932010-03-25025 March 2010 10 CFR21 Notification of a Potential Weld Defect ML0930603952009-10-30030 October 2009 Transnuclear, Inc. - Submittal of Thirty Day Written Report of a Potential Deviation and Failure to Comply Associated with Unsubstantiated Certified Materials Test Reports for Certain Small Parts Utilized in Products Fabricated 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 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 2018-12-06
[Table view] Category:Letter
MONTHYEARLIC-24-0017, ISFSI - Phase 1 Final Status Survey Report to Support Approved License Termination Plan, Revision 1; and Technical Support Document for the Ludlum 44-20 Detector Sensitivity2024-11-21021 November 2024 ISFSI - Phase 1 Final Status Survey Report to Support Approved License Termination Plan, Revision 1; and Technical Support Document for the Ludlum 44-20 Detector Sensitivity LIC-24-0015, Response to Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (DQAP) – Clarification of Request for Additional Information Response2024-11-20020 November 2024 Response to Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (DQAP) – Clarification of Request for Additional Information Response LIC-24-0016, Independent Spent Fuel Storage Installation - 2024 Decommissioning Funding Plan Required 72.30(c) Updated Financial Information2024-11-19019 November 2024 Independent Spent Fuel Storage Installation - 2024 Decommissioning Funding Plan Required 72.30(c) Updated Financial Information ML24318C2532024-11-18018 November 2024 Acceptance of Requested Licensing Action License Amendment Request to Revise the License Termination Plan (L-2024-LLA-0095) IR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-24-0013, Independent Spent Fuel Storage Installation - Intent to Submit a Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update2024-10-10010 October 2024 Independent Spent Fuel Storage Installation - Intent to Submit a Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update LIC-24-0014, Independent Spent Fuel Storage Installation - Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update2024-10-10010 October 2024 Independent Spent Fuel Storage Installation - Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update LIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 – (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request IR 05000285/20230032023-07-10010 July 2023 – NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 – Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, SHPO; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 2024-09-18
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Nuclear Sensors & Process Instrumentation Round Rock, Texas, USA / www.ultra-nspi.com Ultra Electronics. Nuclear Sensors & Process Instrumentation is a business name of Weed Instrumenl Co., Inc.
October 8, 2013 I0CFR21 ATTN:Document Control Clerk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-001
Subject:
10CFR21 Final Report - Linear Indications/Cracks in Flange Forging, Model N-E 13DM Pressure Transmitter
References:
I. I OCFR21 Interim Report - Linear Indications/Cracks in Flange Forging, Model N-E 13DM Pressure Transmitter, June 28, 2013, Log # 2013-37-00.
- 2. 10CFR21 Second Interim Report - Linear Indications/Cracks in Flange Forging, Model N-E 13DM Pressure Transmitter, August 28, 2013, Log # 2013-37-01.
Ultra Electronics, NSPI, in conjunction with Omaha Public Power District (OPPD), Fort Calhoun Station FC- 1-5 Plant, recently identified the existence of linear indications/cracks in the body flange forging on a model N-E13DM pressure transmitter. Ultra Electronics, NSPI has concluded a 10CFR21 investigation to document the root cause for the indications/cracks and provide an engineering evaluation of the reported condition.
Evaluations and tests have been conducted that confirmed that new or installed N-E13DM pressure transmitters are able to perform their intended safety functions. Ultra Electronics, NSPI has determined that no substantial safety hazard exists as a result of the reported condition.
- Regards, Adam Gaither Vice President, Engineering Ultra Electronics, NSPI Ultra Electronics, Nuclear Sensors & Process Instrumentation 707 Jeffrey Way P.O. Box 300 Round Rock, TX 78680-0300 U.S.A.
Telephone (512) 434-2800 Fax (512) 434-2951
Nuclear Sensors & Process Instrumentation Round Rock, Texas, USA / www.ultra-nspi.com Ultra Electronics, Nuclear Sensors & Process Instrumentation is a business name of Weed Instrument Co., Inc.
Enclosure 10CFR-21 Investigation of Linear Indications/Cracks in Flange Forgings of the Model N-E13DM Pressure Transmitter DESCRIPTION OFDEFICIENCY Linear indications/cracks were discovered in the flange forging on three N-E 13DM pressure transmitters recently supplied by Ultra Electronics, NSPI to Omaha Public Power District (OPPD), Fort Calhoun Station FC-1-5 Plant. These transmitters with the identified indications had been received by Fort Calhoun but were not installed. Ultra Electronics, NSPI determined that one crack identified by OPPD penetrated the forging beyond the minimum design wall thickness and initiated a 10CFR-21 investigation.
CAUSE OF DEFICIENCY Ultra Electronics, NSPI conducted thermal and seismic testing to determine if the indications/cracks will propagate during its 20 year qualified life, and engaged a third party metallurgical research laboratory to evaluate the forgings for a root cause analysis. The following includes a list of significant findings from the 10CFR-21 investigation.
- The crack that penetrated the forging beyond the minimum design wall thickness was formed along inclusions in the material. The forging process likely caused the material to separate along these inclusions.
" The indications in other forgings appeared to be entrapped material; strings of oxide inclusions or slag formed during the casting process.
These indications were located in areas of high stress and are typical forging imperfections referred to as cold-shuts or laps. These are not cracks.
" The forging die was worn out and needed to be replaced. This worn die was identified as the cause of the laps and other surface irregularities.
These surface irregularities were removed by the forging vendor using a grinder.
SAFETY IMPLICATIONS Thermal and seismic testing to the service conditions expected in the 20 year qualified life of an N-E13DM transmitter demonstrated that the identified indications/cracks on a suspect forging Ultra Electronics, Nuclear Sensors & Process Instrumentation 707 Jeffrey Way P.O. Box 300 Round Rock, TX 78680-0300 U.S.A.
Telephone (512) 434-2800 Fax (512) 434-2951
Nuclear Sensors & Process Instrumentation Round Rock, Texas, USA / www.ultra-nspi.com Ultra Electronics, Nuclear Sensors & Process Inslrumentalion is a business name of Weed Instrument Co., Inc.
did not change size or propagate. As a result of evaluations and testing described previously, Ultra Electronics, NSPI has determined that no substantial safety hazards or impacts to safety-related systems, structures or components were identified regarding this issue.
CORRECTIVE ACTIONS Starting on 6/19/2013, corrective and preventative actions were initiated to contain possible safety issues:
- Additional receiving inspections were implemented that rejected forgings with grinding below the surface normal or cracks of any kind.
- A new forging die was ordered and ownership of the die transferred to the forging vendor to ensure that it will be maintained correctly in the future.
With these actions, Ultra Electronics, NSPI is confident that this investigation can be closed and there are no safety issues to report.
Ultra Electronics, Nuclear Sensors & Process Instrumentation 707 Jeffrey Way P.O. Box 300 Round Rock, TX 78680-0300 U.S.A.
Telephone (512) 434-2800 Fax (512) 434-2951