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MONTHYEARL-MT-13-111, ISFSI - Thirty (30) Day Notification for the Fourth and Fifth Dry Shielded Canisters Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel2013-11-0404 November 2013 ISFSI - Thirty (30) Day Notification for the Fourth and Fifth Dry Shielded Canisters Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel Project stage: Request L-MT-13-114, Interim Notification for Dry Shielded Canister MNP-61 BTH-1-B-2-016 Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel2013-11-15015 November 2013 Interim Notification for Dry Shielded Canister MNP-61 BTH-1-B-2-016 Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel Project stage: Request ML14006A0042013-12-13013 December 2013 Trivis, Inc., Part 21 Interim Report - Nonconforming Dry Shielded Calster Welds - Potential Substantial Safety Hazard Project stage: Request ML14042A2012014-01-29029 January 2014 Part 21 Report Regarding Non-Destructive Testing Did Not Meet Procedural Requirements Project stage: Request ML14199A3702014-07-16016 July 2014 Exemption Request for Dry Shielded Canisters 11 - 16 Due to Nonconforming Dye Penetrant Examinations Project stage: Request L-MT-14-082, Exemption Request for Dry Shielded Canisters 11-16 Dye Penetrant Examinations, Supplemental Information2014-11-0303 November 2014 Exemption Request for Dry Shielded Canisters 11-16 Dye Penetrant Examinations, Supplemental Information Project stage: Supplement L-MT-14-104, Withdrawal of Exemption Request for Dry Shielded Canisters 11 - 16 Due to Nonconforming Dye Penetrant Examinations, Supplemental Information2014-12-16016 December 2014 Withdrawal of Exemption Request for Dry Shielded Canisters 11 - 16 Due to Nonconforming Dye Penetrant Examinations, Supplemental Information Project stage: Withdrawal L-MT-15-056, Redacted - Calculation 1042-0205, Revision 1, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation.2015-09-10010 September 2015 Redacted - Calculation 1042-0205, Revision 1, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation. Project stage: Other 2014-01-29
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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARL-MT-21-035, Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System2021-05-0707 May 2021 Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System ML19091A0502019-03-21021 March 2019 Engine Systems, Inc. 10 CFR 21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0124, Rev. 0, Excitation Transformers for Vickers Voltage Regulator System ML19087A2522019-03-21021 March 2019 Engine Systems, Inc. - 10 CFR 21 Reportable Notification on Excitation Transformers for Vickers Voltage Regulator System ML19042A0802019-01-25025 January 2019 Part 21 Report No. 10CFR21-0124-INT; Rev. 0 - Saturable Reactor (Magnetic Amplifier) for Vickers Voltage Regulator System, P/N 8408218-ESI L-MT-18-012, Interim Report of a Deviation or Failure to Comply2018-02-12012 February 2018 Interim Report of a Deviation or Failure to Comply L-MT-18-008, Initial and Final Part 21.21(d)(4) Report Notification of Failure to Comply or Existence of a Defect Regarding Westinghouse Breaker Cubicle2018-02-0101 February 2018 Initial and Final Part 21.21(d)(4) Report Notification of Failure to Comply or Existence of a Defect Regarding Westinghouse Breaker Cubicle ML17212A6282017-07-24024 July 2017 Lake Engineering Co. - Potentially Degraded Snubber SF1154 Hydraulic Fluid Second - Interim Notification Per 10 CFR Part 21 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 ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 L-MT-17-031, Interim Report of a Deviation or Failure to Comply Regarding New Relay Coil GE Part Number 6306774G12017-04-20020 April 2017 Interim Report of a Deviation or Failure to Comply Regarding New Relay Coil GE Part Number 6306774G1 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 L-MT-17-005, Interim Report of a Deviation or Failure to Comply2017-01-17017 January 2017 Interim Report of a Deviation or Failure to Comply ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16321A4502016-08-31031 August 2016 Part 21 Notification - Flowserve Swing Check Valves ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance ML16139A8342016-05-10010 May 2016 Electroswitch - Transmittal of 10CFR Part 21 Reporting of Defects and Noncompliance Regarding Vendor Inspection of Electroswitch Corporation Docket No. 99900833 ML15265A4182015-09-21021 September 2015 Sor, Inc. - Part 21 Notification of Deviation - ML15251A212 Irradiation Certification with Insufficient Margin 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 ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14212A4012014-07-18018 July 2014 Final Report - 10 CFR Part 21 Evaluation Regarding Cracking in KCR-13 Standby Battery Jars ML14134A1222014-05-0909 May 2014 Notification of Potential Part 21 Report - Cracking in KCR-13 Standby Battery Jars ML14139A0172014-04-28028 April 2014 Updated Interim Report - Inability to Complete 10CFR Part 21 Evaluation Regarding Cracking in KCR-13 Standby Battery Jars ML14042A2022014-02-0505 February 2014 Part 21 Report Regarding Unqualified Material Used in Electrical Penetration Assemblies ML14042A2012014-01-29029 January 2014 Part 21 Report Regarding Non-Destructive Testing Did Not Meet Procedural Requirements ML13358A3062013-12-20020 December 2013 Interim Report - Inability to Complete 10CFR Part 21 Evaluation Regarding Cracking in KCR-13 Standby Battery Jars ML14006A0042013-12-13013 December 2013 Trivis, Inc., Part 21 Interim Report - Nonconforming Dry Shielded Calster Welds - Potential Substantial Safety Hazard ML13358A0462013-12-13013 December 2013 Report of Potential Substantial Safety Hazard in Accordance with Title 10 Code of Federal Regulation, Part 21 ML13340A3822013-12-0505 December 2013 Part 21 Reportable Condition Notification: Failure of Relay Logic Card Modules in 2 Out of 4 Voters 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 ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML13042A0962013-02-0808 February 2013 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Error in Main Steam Line High Flow Calculational Methodology ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology 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 ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12177A0562012-06-21021 June 2012 Part 21 - Reliability Degradation of Resistors in Trip Units and Readout Assemblies ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12058A1412012-02-23023 February 2012 Part 21 Report - Rosemount Nuclear Instruments, Inc., Pressure Transmitter with Nonzero Based Calibrations ML12040A2832012-02-0707 February 2012 Notification of Potential Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML12038A0282012-02-0202 February 2012 Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12032A2402012-02-0101 February 2012 Notification of Potential Part 21 - 60-Day Interim Report Notification: Failure of CRD Collet Retainer Tube/Outer Tube Weld ML11341A0602011-12-0505 December 2011 Notification of Potential Part 21 Involving Defective Spring Clips Used as Seismic Restraints on Two Scientific Modules ML11340A1002011-12-0505 December 2011 Letter 10 CFR Part 21 Notification Report, CON2000 and RTD2100 Spring Clips 2021-05-07
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MONTHYEARML24025A9362024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000263/20230042024-01-31031 January 2024 Integrated Inspection Report 05000263/2023004 ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20244012024-01-22022 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401 L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000263/20234022023-12-13013 December 2023 Security Baseline Inspection Report 05000263/2023402 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20230032023-11-13013 November 2023 Integrated Inspection Report 05000263/2023003 and 07200058/2023001 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 ML23291A1102023-10-23023 October 2023 Environmental Audit Summary and RCIs and RAIs ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23248A2092023-09-18018 September 2023 Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection IR 05000263/20230102023-09-0707 September 2023 Commercial Grade Dedication Inspection Report 05000263/2023010 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 ML23214A2412023-08-31031 August 2023 Letter: Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application IR 05000263/20230052023-08-30030 August 2023 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005) L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 ML23241A9732023-08-21021 August 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application (Docket No. 50-263) L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence ML23215A1312023-08-0909 August 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000263/20230022023-08-0707 August 2023 Plantintegrated Inspection Report 05000263/2023002 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 ML23198A0412023-07-28028 July 2023 LRA Availability Letter ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan IR 05000263/20235012023-07-13013 July 2023 Emergency Preparedness Inspection Report 05000263/2023501 2024-01-31
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- 12-13-13;11'42AM; # 1/ 5 ATRIVIS Inc. The compIle solution provider 200 Beacon Parkway West Birmingham, AL 35209 Phone 205-621-0106 Fax: 205-621-1108 Date: 12/13/13 To: NRC Operations Center From: David Bland, President Fax; 301-816-5151 RE: 10CFRZ1 Interim Report Pages: 5 (including cover)
To Whom It May Concern:
Following this cover page, please find attached our Interim Report for a 10CFR21 notification regarding the failure of personnel to comply with Nondestructive Examination procedures on Dry Shielded Canister field closure wel&d at Monticello Nuclear Generating Plant.
A copy of this report will be mailed to the NRC Document Control Desk.
Feel free to contact me with any questions David Bland, President TriVis Inc
12-13-13;11:42AM; # 2/ 5 ATRIVISbn 7he eonV-e soludonpod'der.
December 13, 2013 Ltr No: 12751 - NRC - 001 Document Control Desk U. W. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Report of Potential Substantial Safety Hazard in accordance with Tide 10 Code of Federal Regulation, Part 21 To Whom It May Concern:
The purpose of this letter is to inform the staff of a condition identified during dry storage loading operations at the Monticello Nuclear Generating Plant (MNGP) currently underway in which quality control personnel failed to follow required liquid penetrant testing (PT) procedures in the examination of the NUHOMS canister field closure welds. This condition involves the failure of the subject personnel to adhere to the PT procedure 12751-MNGP-QP-9.202, Rev I Color ContrastLiquid Penetrant(PT)Examination Using the Solvent Removable Method, which is a Quality procedure within the TriVis Inc Quality Program and approved for use at MNGP.
PT testing is required by the CoC Technical Specifications (Tech Specs) to comply with ASME B&PV Code Section 3, Division 1, Article NB-5000. Article NB-5000 states that all NDE exams shall be performed in accordance with detailed written procedures. Therefore, this procedural noncompliance has created the uncertainty that the PT examinations performed, along with the associated field closure welds are in violation of the Code and the CoC.
Further background information is contained within Interim Report attached to this letter. Per 10CFR21.21, this Interim Report includes a description of the condition, the extent of condition evaluation, corrective actions taken to date and future corrective actions. In addition, TriVis will continue to work with the site Licensee to finalize and correct any issues which this may have caused to the NUHOMS dry storage systems involved and will provide a final evaluation to the Commission by January 31, 2014.
Should you have any additional questions regarding t s matter I can be reached at (205) 621-0106.
David W Bland President TriVis Inc.
cC. Lee Samson, Xcel Nuclear - Monticello Leonard Sueper, Xccl Nuclear 2(g) i*.tcon I'ark%,av W,:-t u IIirninogham. AJibaimi 352'09 I'h111)v (205) i,21 .I106
12-13-13;11:42AM; # 3/ 5 ENCLOSURE 10 CFR 21 Interim Report - Nonconforming Dry Shielded Canister Welds Name and Address of the Individual Making the Interim Report David Bland President TriVis Inc 200 Beacon Parkway West Birmingham, AL 35209 Description of the Deviation or Failure to Comply that is being Evaluated On October 17, 2013, a nondestructive examination (NDE) liquid penetrant test (LPT) was performed on the final weld pass of the Outer Top Cover Plate (OTCP) on Transnuclear Model NUHOMS-61BTH Dry Shielded Canister (DSC) #16 at Monticello Nuclear Generating Plant (MNGP). An NRC inspector observed part of this activity and questioned whether the dwell times for the penetrant and developer used by a NDE Level II employee of TriVis Inc. (hereafter Trivis) were sufficient to meet procedural requirements. Upon evaluating recorded video of the work location, it was determined that the dwell times for both the penetrant and the developer of the OTCP weld on DSC
- 16 were not in compliance with the TriVis NDE LPT Procedure. An extent of condition review of previous LPT exams conducted on DSCs-1 1 through -16 revealed additional examinations that were not in compliance with the dwell times specified by the procedure as well as other procedural discrepancies. All of these examinations were performed by two contract NDE Level II examiners employed by TriVis.
Evaluation Status The DSCs provide a containment vessel to ensure confinement of spent fuel radionuclides under normal and accident conditions. The subject welds form part of the containment vessel.
All six DSCs in question have been declared inoperable due, by Monticello station personnel, for the failure to satisfy NUHOMS Technical Specification 1.2.5 of Certificate of Compliance 1004, Amendment 10, which requires all DSC closure welds except those subjected to full volumetric inspection to be dye penetrant tested in accordance with the requirements of the ASME Boiler and Pressure Vessel Code Section 111. At this time there is no reason to suspect the integrity of the closure welds themselves based on the successful completion of the other Technical Specification required testing. This event did not result in challenges to fission product barriers and did not adversely affect the health and safety of the public.
Page I of 3
12-13-13;11:42AM; # 4/ 5 Identity of the firm supplying the basic component which fails to comply or contains a defect TriVis Inc.
200 Beacon Parkway West Birmingham AL, 35209 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.
TriVis NDE personnel repeatedly failed to follow the dwell time as well as other procedural requirements for LPT examination of welds during the installation of the field welded components of DSCs-1 1 through 16.
The date on which the information of such defect or failure to comply was obtained.
October 17, 2013 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.
TriVis has determined that the condition exists only with DSCs 11-16 at MNGP.
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.
All work activities related to the dry fuel storage campaign at MNGP were stopped upon discovery of this condition. Northern States Power Company- Minnesota (NSPM) issued a stop work order for TriVis.
An extent of condition review was conducted to determine the impact of the issue on previous loading campaigns at NSPM. The review concluded the individuals involved had not previously performed NDE activities on site.
NSPM issued a supplier finding report to TriVis and it is currently being addressed as part of this evaluation.
Corrective actions and the timeline to restore the six affected DSCs to an operable status are being developed by NSPM, TriVis and other industry experts.
Page 2 of 3
12-13-13;11:42AM; # 5/ 5 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.
TriVis has determined that the two NDE personnel had not previously been employed by TriVis. Thus, TriVis does not consider any DSCs previously loaded at MNGP or any other site to be in question.
In the case of an early site permit, the entities to whom an early site permit was transferred.
Not applicable.
Date on which Evaluation will be Completed The evaluation will be completed by January 31, 2014 or a follow-up interim report will be submitted.
Page 3 of 3
U.S. Nuclear Regulatory Commission OperationsCenter
49628 TRIVIS INC.
21.21 (a)(2) INTERIM EVAL OF DEVIATION Friday, December 13, 2013 Page I of I
1211312013 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Pa--e I Part 21 (PAR) Event# 49628 Rep Org: TRIVIS INC. Notification Date I Time: 12/13/2013 14:37 (EST)
Supplier: TRIVIS INC. Event Date / Time: 12/13/2013 (CST)
Last Modification: 12/13/2013 Region: 1 Docket #:
City: BIRMINGHAM Agreement State: Yes County: License #:
State: AL NRC Notified by: DAVID BLAND Notifications: RICHARD SKOKOWSKI R3DO HQ Ops Officer: HOWIE CROUCH PART 21 GROUPS EMAIL Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 (a)(2) INTERIM EVAL OF DEVIATION PART 21 REPORT - NON-DESTRUCTIVE TESTING DID NOT MEET PROCEDURAL REQUIREMENTS The following information was summarized from the report submitted by TriVis via facsimile:
David Bland, President of TriVis Inc. reported that two contract Non-Destructive Evaluation (NDE) Level II examiners, employed by TriVis, failed to meet NDE procedural requirements for weld testing on the Outer Top Cover Plate (OTCP) on six Transnuclear Model NUHOMS-61 BTH Dry Shield Canisters (DSC) at the Monticello Nuclear Generating Plant.
An NRC inspector observed part of this activity and questioned whether the dwell times for the penetrant and developer used by a NDE Level II employee of TriVis were sufficient to meet procedural requirements. Upon evaluating recorded video of the work location, it was determined that the dwell times for both the penetrant and the developer of the OTCP weld on DSC #16 were not in compliance with the TriVis NDE LPT [Liquid Penetrant Test] Procedure. An extent of condition review of previous LPT exams conducted on DSCs-1 1 through -16 revealed additional examinations that were not in compliance with the dwell times specified by the procedure as well as other procedural discrepancies.
All six DSCs were declared inoperable at the time of discovery. All work activities associated with dry fuel storage at Monticello were stopped. A timeline and corrective actions are being developed by TriVis and the licensee.
The two NDE Level II examiners were not previously employed by TriVis and did not perform any other NDE activities at Monticello.
Evaluations will be completed by January 31, 2014 or a follow-up interim report will be submitted.
12/13/2013 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page2 Part 21 (PAR) Event# 49628 The licensee notified the NRC Resident Inspector.