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| | number = ML15254A277 | | | number = ML15254A277 |
| | issue date = 09/08/2015 | | | issue date = 09/08/2015 |
| | title = Sequoyah, Unit 1 - Part 21 Notification Re Westinghouse Corporation Deviation from Contract Service | | | title = Part 21 Notification Re Westinghouse Corporation Deviation from Contract Service |
| | author name = Carlin J T | | | author name = Carlin J |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000September 8, 201510 CFR 21.21(d)(3)(ii)ATT-IN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Sequoyah Nuclear Plant, Unit 1Facility Operating License No. DPR-77NRC Docket No. 50-327 | | {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 September 8, 2015 10 CFR 21.21(d)(3)(ii) |
| | ATT-IN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Facility Operating License No. DPR-77 NRC Docket No. 50-327 |
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| ==Subject:== | | ==Subject:== |
| Westinghouse Corporation Deviation From Contract ServiceIn accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 21,"Reporting of Defects and Noncompliance," the Tennessee Valley Authority is providingthe required written notification of a deviation in a basic component associated withprocured services for reactor vessel specimen relocation. The enclosure to this letterprovides the information required in 10 CFR 21.21 (d)(4).There are no regulatory commitments contained in this letter. Should you have anyquestions concerning this submittal, please contact Mrs. Erin Henderson, SequoyahSite Licensing Manager, at (423) 843-7170.e PresidentSequoyah Nuclear Plant | | Westinghouse Corporation Deviation From Contract Service In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 21, "Reporting of Defects and Noncompliance," the Tennessee Valley Authority is providing the required written notification of a deviation in a basic component associated with procured services for reactor vessel specimen relocation. The enclosure to this letter provides the information required in 10 CFR 21.21 (d)(4). |
| | There are no regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact Mrs. Erin Henderson, Sequoyah Site Licensing Manager, at (423) 843-7170. |
| | e President Sequoyah Nuclear Plant |
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| ==Enclosure:== | | ==Enclosure:== |
| Part 21 Notification of Westinghouse Corporation Deviation FromProcurement Specificationscc: NRC Regional Administrator- Region IINRC Senior Resident *Inspector -Seq uoyah Nuclear Plant ENCLOSURESEQUOYAH NUCLEAR PLANT (SQN), UNIT 1PART 21 NOTIFICATION OF WESTINGHOUSE CORPORATIONDEVIATION FROM PROCUREMENT SPECIFICATIONS(i) Name and address of the individual or individuals informing the Commission.Mr. John T. CarlinTennessee Valley AuthorityVice President, Sequoyah Nuclear Plant Unit 1Post Office Box 2000Soddy-Daisy, TN 37384(ii) Identification of the facility, the activity, or the basic component supplied for such facilityor such activity within the United States which fails to comply or contains a defect.Sequoyah Nuclear Plant, Unit 1Facility Operating Licensing No, DPR-77NRC Docket No. 50-327Basic Component: Westinghouse Electric Company service contract, P0 393260-1Relocate Reactor Vessel Surveillance Capsules dated July 13,2012, to relocate reactor pressure vessel surveillance capsulesusing specific Westinghouse procedure and tooling.(iii) Identification of the firm constructing the facility or supplying the basic component thatfails to comply or contains a defect.Westinghouse Electric Company1000 Westinghouse DriveCranberry Township, Pennsylvania 16066(iv) Nature of the defect or failure to comply and the safety hazard that is created or could becreated by such defect or failure to comply."TVA contracted with the Westinghouse Electric Company (WEC), in part, to providerelocation of reactor pressure vessel (RPV) material surveillance capsules. Thepurchase order for relocation services included: relocation of two reactor vesselsurveillance capsules in Units 1 and 2; qualified, trained supervision and personnel toperform the relocation; necessary procedures, drawings, and other requireddocumentation; technical review of required revisions of SQN procedures to support thecapsule relocation and SQN work documents controlling the capsule relocation; and allnecessary and backup tooling to perform the relocation of the samples and activitiesnecessary to process in and utilize the tooling. The purchase order specified that theseactivities be conducted under the requirement of 10 CFR 21.El1-3 During performance of services in the SQN Unit 1 end of cycle (EOC) RI19 outage (Fall2013), the WEC discontinued use of specified tooling and procedure requirements.These changes were made absent formal processes and without notification to TIVA untilafter conduct of the service.Following the Unit I RI19 outage and at the beginning of the operating cycle (Fall 2013),SQN operators received alarms multiple times from the Loose Parts Monitoring System.As a result, SQN conducted evaluations for continued operations wherein it wasdetermined that operations could continue and not have adverse affects on the systems,structures and components associated with the reactor coolant system (RCS). A planfor continued monitoring was established, with no additional anomalies identified duringthe operating cycle.During the SQN Unit I end of cycle (EOC) R20 outage (Spring 2015), inspections of theUnit I reactor vessel internals revealed that the RPV material surveillance capsules Sand W had become dislodged from their intact designated baskets. The RPV materialsurveillance capsules were destroyed, and the capsule fragments and their contents hadbeen distributed within the RPV during the operating cycle."I-A re-evaluated the condition after identifying the physical loose parts that were in theRCS during the previous operating cycle and those parts that potentially remain in RCSduring the current operating cycle. TVA concluded that, if left uncorrected, a substantialsafety hazard could have been created in the previous operating cycle or could becreated in the current operating cycle by the capsule fragments and their content,although the potential is characterized as low. Based on the evaluation the followingcondition could have or could occur: fuel cladding damage as a result of fretting orlocalized departure from nucleate boiling from flow reductions; reduced peak cladtemperature margin due to blocked and/or reduced flow; RCS pressure boundarydamage due to fretting; unanalyzed loads on the RPV and internals created byclearance loss resulting in wear, deformation, or fracture; interference with control rodand rod cluster control assemble operation; and cladding corrosion resulting fromchemical interaction of specimen materials.(v) The date on which the information of such defect or failure to comply was obtained.Discovery date: June 3, 2015. The condition was initially reported to the NRC on August7, 2015, via the Emergency Notification system under Event Notification No. 51298.(vi) In the case of a basic component which contains a defect or fails to comply, the numberand location of these components in use at, supplied for, being supplied for, or may besupplied for, manufactured, or being manufactured for one or more facilities or activitiessubject to the regulations in this part.TVA contracted with WEC to provide relocation of two RPV material surveillancecapsules in each Unit at SON. The capsule relocations for Unit I occurred in Fall 2013and for Unit 2 in Spring 2014, each during an EOC R19 refueling outage. WVA hasservice contracts with WEC for various technical and field service activites.E2-3 (vii) The corrective action which has been, is being, or will be taken; the name of theindividual or organization responsible for the action; and the length of time that has beenor will be taken to complete the action.TVA conducted an extensive foreign object search and recovery initiative to recover theRPV material surveillance capsules and contents prior to concluding the SQN Unit 1 endof cycle (EOC) R20 outage. There is approximately 74 items that remain unaccountedfollowing the refueling outage. These items are believed to be in the vacuum filters usedin retrieval of contents or located in the remains of surveillance capsules. Reconciliationof the remaining items is on going. TVA intends to strengthen it's procedure foroversight of supplemental personnel by September 2015. TVA has includedrequirements for conducting a pull test on future relocated RPV material surveillancecapsules.(viii) Any advice related to the defect or failure to comply about the facility, activity, or basiccomponent that has been, is being, or will be given to purchasers or licensees.None.(ix) In the case of an early site permit, the entities to whom an early site permit wastransferred.Not applicableE3-3}} | | Part 21 Notification of Westinghouse Corporation Deviation From Procurement Specifications cc: NRC Regional Administrator- Region II NRC Senior Resident *Inspector - Seq uoyah Nuclear Plant |
| | |
| | ENCLOSURE SEQUOYAH NUCLEAR PLANT (SQN), UNIT 1 PART 21 NOTIFICATION OF WESTINGHOUSE CORPORATION DEVIATION FROM PROCUREMENT SPECIFICATIONS (i) Name and address of the individual or individuals informing the Commission. |
| | Mr. John T. Carlin Tennessee Valley Authority Vice President, Sequoyah Nuclear Plant Unit 1 Post Office Box 2000 Soddy-Daisy, TN 37384 (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. |
| | Sequoyah Nuclear Plant, Unit 1 Facility Operating Licensing No, DPR-77 NRC Docket No. 50-327 Basic Component: Westinghouse Electric Company service contract, P0 393260-1 Relocate Reactor Vessel Surveillance Capsules dated July 13, 2012, to relocate reactor pressure vessel surveillance capsules using specific Westinghouse procedure and tooling. |
| | (iii) Identification of the firm constructing the facility or supplying the basic component that fails to comply or contains a defect. |
| | Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 (iv) Nature of the defect or failure to comply and the safety hazard that is created or could be created by such defect or failure to comply. |
| | "TVA contracted with the Westinghouse Electric Company (WEC), in part, to provide relocation of reactor pressure vessel (RPV) material surveillance capsules. The purchase order for relocation services included: relocation of two reactor vessel surveillance capsules in Units 1 and 2; qualified, trained supervision and personnel to perform the relocation; necessary procedures, drawings, and other required documentation; technical review of required revisions of SQN procedures to support the capsule relocation and SQN work documents controlling the capsule relocation; and all necessary and backup tooling to perform the relocation of the samples and activities necessary to process in and utilize the tooling. The purchase order specified that these activities be conducted under the requirement of 10 CFR 21. |
| | El1-3 |
| | |
| | During performance of services in the SQN Unit 1 end of cycle (EOC) RI19 outage (Fall 2013), the WEC discontinued use of specified tooling and procedure requirements. |
| | These changes were made absent formal processes and without notification to TIVA until after conduct of the service. |
| | Following the Unit I RI19 outage and at the beginning of the operating cycle (Fall 2013), |
| | SQN operators received alarms multiple times from the Loose Parts Monitoring System. |
| | As a result, SQN conducted evaluations for continued operations wherein it was determined that operations could continue and not have adverse affects on the systems, structures and components associated with the reactor coolant system (RCS). A plan for continued monitoring was established, with no additional anomalies identified during the operating cycle. |
| | During the SQN Unit I end of cycle (EOC) R20 outage (Spring 2015), inspections of the Unit I reactor vessel internals revealed that the RPV material surveillance capsules S and W had become dislodged from their intact designated baskets. The RPV material surveillance capsules were destroyed, and the capsule fragments and their contents had been distributed within the RPV during the operating cycle. |
| | "I-Are-evaluated the condition after identifying the physical loose parts that were in the RCS during the previous operating cycle and those parts that potentially remain in RCS during the current operating cycle. TVA concluded that, if left uncorrected, a substantial safety hazard could have been created in the previous operating cycle or could be created in the current operating cycle by the capsule fragments and their content, although the potential is characterized as low. Based on the evaluation the following condition could have or could occur: fuel cladding damage as a result of fretting or localized departure from nucleate boiling from flow reductions; reduced peak clad temperature margin due to blocked and/or reduced flow; RCS pressure boundary damage due to fretting; unanalyzed loads on the RPV and internals created by clearance loss resulting in wear, deformation, or fracture; interference with control rod and rod cluster control assemble operation; and cladding corrosion resulting from chemical interaction of specimen materials. |
| | (v) The date on which the information of such defect or failure to comply was obtained. |
| | Discovery date: June 3, 2015. The condition was initially reported to the NRC on August 7, 2015, via the Emergency Notification system under Event Notification No. 51298. |
| | (vi) 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. |
| | TVA contracted with WEC to provide relocation of two RPV material surveillance capsules in each Unit at SON. The capsule relocations for Unit I occurred in Fall 2013 and for Unit 2 in Spring 2014, each during an EOC R19 refueling outage. WVA has service contracts with WEC for various technical and field service activites. |
| | E2-3 |
| | |
| | (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. |
| | TVA conducted an extensive foreign object search and recovery initiative to recover the RPV material surveillance capsules and contents prior to concluding the SQN Unit 1 end of cycle (EOC) R20 outage. There is approximately 74 items that remain unaccounted following the refueling outage. These items are believed to be in the vacuum filters used in retrieval of contents or located in the remains of surveillance capsules. Reconciliation of the remaining items is on going. TVA intends to strengthen it's procedure for oversight of supplemental personnel by September 2015. TVA has included requirements for conducting a pull test on future relocated RPV material surveillance capsules. |
| | (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. |
| | None. |
| | (ix) In the case of an early site permit, the entities to whom an early site permit was transferred. |
| | Not applicable E3-3}} |
|
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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24008A0692024-01-0404 January 2024 Part 21 Report No. 10CFR21-0137, Rev. 0 for Reportable Notification for an Emo Cylinder Liner with Bore Deficiency, P/N 9318833 (Component of Power Assembly P/N 40124897), S/N 20M0938 ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24002A7112023-12-28028 December 2023 Interim Part 21 Report of a Deviation or Failure to Comply - Lube Oil Scavenging and Fuel Oil Engine Driven Pump ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23060A0412023-03-0101 March 2023 Part 21 Interim Report of a Deviation or Failure to Comply Associated with a Limitorque Actuator ML23025A2532023-01-25025 January 2023 Part 21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML23024A0292023-01-24024 January 2023 Part 21 Interim Report of a Deviation or Failure to Comply Associated with a Limitorque Actuator ML21225A0812021-08-0404 August 2021 Lake Engineering Co., Final Report Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML21014A2342020-12-0707 December 2020 Fourth Interim Notification Per 10 CFR Part 21 Re Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML20042E2522020-01-31031 January 2020 EN 54485 Target Rock Redacted Update to Part 21 Report on Defect of Modification of Valve Component and Main Disc Lift Misadjustment ML20029D1612020-01-21021 January 2020 10 CFR Part 21 Report, Notification of a Defect Modification of a Valve Component and Main Disc Lift Misadjustment ML20021A0452020-01-0303 January 2020 Lake Engineering Co. - Interim Notification Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. 16DLVS852 ML19190A0442019-06-0707 June 2019 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19106A1062019-04-12012 April 2019 Ametek Solidstate Controls - Notification of Potential Defect - 10 CFR Part 21 ML18087A0022018-03-21021 March 2018 Crane Nuclear, Inc. - Final Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem 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) ML17311A9092017-10-31031 October 2017 Interim Report for Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem ML17206A0402017-07-14014 July 2017 Part 21 - Defective Safety Related Valves ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 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 ML16188A3742016-06-30030 June 2016 Part 21 - Inadequate Swaging and Adherence of Silicone O-Ring and Silicone PAD Soft Seat Main Disc and Pilot Disc Assemblies ML16154A2062016-05-18018 May 2016 Part 21 Report - Defect in a Signal Converter Transformer ML15254A2772015-09-0808 September 2015 Part 21 Notification Re Westinghouse Corporation Deviation from Contract Service ML15223B2642015-08-0606 August 2015 Part 21 Report - Notification of Deviation Regarding Hk Circuit Breaker Pivot Pin ML15103A2442015-04-0606 April 2015 Part 21 Report - Deviation of Hk Circuit Breaker Close Latch Spring ML15099A0432015-04-0202 April 2015 Amendment to Event Number 50299, 10 CFR Part 21 Notification, Potentially Defective Pressure & Temperature Switches ML15099A0422015-04-0202 April 2015 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML15049A4582015-02-0606 February 2015 Thermo Gamma-Metrics, LLC - Part 21 Report Regarding Shutdown Margin Monitor Environmental Qualification Noncompliance ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification 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 ML14213A0992014-07-24024 July 2014 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML14126A5002014-05-0202 May 2014 Part 21 Report Re Check Valves with Missing Jam Nuts ML13165A3422013-06-12012 June 2013 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 ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers 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 ML12058A1412012-02-23023 February 2012 Part 21 Report - Rosemount Nuclear Instruments, Inc., Pressure Transmitter with Nonzero Based Calibrations ML1035001742010-12-15015 December 2010 Notification of Potential Part 21 Re 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1029305052010-10-20020 October 2010 GE Hitachi Nuclear Energy - Notification of Potential Part 21 60-Day Interim Report: Crack Indications in Marathon Control Rod Blades ML1015301082010-05-28028 May 2010 Notification of Potential Part 21 Re Interim Report - Inability to Complete 10 CFR Part 21 Evaluation Regarding Post Corrosion for Dcu Batteries ML1015305642010-05-28028 May 2010 Part 21 Notification from C & D Technologies, Inc., Post Corrosion on Dcu Batteries ML1009200932010-03-25025 March 2010 10 CFR21 Notification of a Potential Weld Defect ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0823901062008-08-25025 August 2008 Notification of Potential Part 21 on Failure of F and G Switches 2024-01-04
[Table view] Category:Letter
MONTHYEARML24304A8492024-10-31031 October 2024 December 2024 Requalification Inspection Notification Letter IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 ML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 2024-09-08
[Table view] |
Text
Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 September 8, 2015 10 CFR 21.21(d)(3)(ii)
ATT-IN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Facility Operating License No. DPR-77 NRC Docket No. 50-327
Subject:
Westinghouse Corporation Deviation From Contract Service In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 21, "Reporting of Defects and Noncompliance," the Tennessee Valley Authority is providing the required written notification of a deviation in a basic component associated with procured services for reactor vessel specimen relocation. The enclosure to this letter provides the information required in 10 CFR 21.21 (d)(4).
There are no regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact Mrs. Erin Henderson, Sequoyah Site Licensing Manager, at (423) 843-7170.
e President Sequoyah Nuclear Plant
Enclosure:
Part 21 Notification of Westinghouse Corporation Deviation From Procurement Specifications cc: NRC Regional Administrator- Region II NRC Senior Resident *Inspector - Seq uoyah Nuclear Plant
ENCLOSURE SEQUOYAH NUCLEAR PLANT (SQN), UNIT 1 PART 21 NOTIFICATION OF WESTINGHOUSE CORPORATION DEVIATION FROM PROCUREMENT SPECIFICATIONS (i) Name and address of the individual or individuals informing the Commission.
Mr. John T. Carlin Tennessee Valley Authority Vice President, Sequoyah Nuclear Plant Unit 1 Post Office Box 2000 Soddy-Daisy, TN 37384 (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.
Sequoyah Nuclear Plant, Unit 1 Facility Operating Licensing No, DPR-77 NRC Docket No. 50-327 Basic Component: Westinghouse Electric Company service contract, P0 393260-1 Relocate Reactor Vessel Surveillance Capsules dated July 13, 2012, to relocate reactor pressure vessel surveillance capsules using specific Westinghouse procedure and tooling.
(iii) Identification of the firm constructing the facility or supplying the basic component that fails to comply or contains a defect.
Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 (iv) Nature of the defect or failure to comply and the safety hazard that is created or could be created by such defect or failure to comply.
"TVA contracted with the Westinghouse Electric Company (WEC), in part, to provide relocation of reactor pressure vessel (RPV) material surveillance capsules. The purchase order for relocation services included: relocation of two reactor vessel surveillance capsules in Units 1 and 2; qualified, trained supervision and personnel to perform the relocation; necessary procedures, drawings, and other required documentation; technical review of required revisions of SQN procedures to support the capsule relocation and SQN work documents controlling the capsule relocation; and all necessary and backup tooling to perform the relocation of the samples and activities necessary to process in and utilize the tooling. The purchase order specified that these activities be conducted under the requirement of 10 CFR 21.
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During performance of services in the SQN Unit 1 end of cycle (EOC) RI19 outage (Fall 2013), the WEC discontinued use of specified tooling and procedure requirements.
These changes were made absent formal processes and without notification to TIVA until after conduct of the service.
Following the Unit I RI19 outage and at the beginning of the operating cycle (Fall 2013),
SQN operators received alarms multiple times from the Loose Parts Monitoring System.
As a result, SQN conducted evaluations for continued operations wherein it was determined that operations could continue and not have adverse affects on the systems, structures and components associated with the reactor coolant system (RCS). A plan for continued monitoring was established, with no additional anomalies identified during the operating cycle.
During the SQN Unit I end of cycle (EOC) R20 outage (Spring 2015), inspections of the Unit I reactor vessel internals revealed that the RPV material surveillance capsules S and W had become dislodged from their intact designated baskets. The RPV material surveillance capsules were destroyed, and the capsule fragments and their contents had been distributed within the RPV during the operating cycle.
"I-Are-evaluated the condition after identifying the physical loose parts that were in the RCS during the previous operating cycle and those parts that potentially remain in RCS during the current operating cycle. TVA concluded that, if left uncorrected, a substantial safety hazard could have been created in the previous operating cycle or could be created in the current operating cycle by the capsule fragments and their content, although the potential is characterized as low. Based on the evaluation the following condition could have or could occur: fuel cladding damage as a result of fretting or localized departure from nucleate boiling from flow reductions; reduced peak clad temperature margin due to blocked and/or reduced flow; RCS pressure boundary damage due to fretting; unanalyzed loads on the RPV and internals created by clearance loss resulting in wear, deformation, or fracture; interference with control rod and rod cluster control assemble operation; and cladding corrosion resulting from chemical interaction of specimen materials.
(v) The date on which the information of such defect or failure to comply was obtained.
Discovery date: June 3, 2015. The condition was initially reported to the NRC on August 7, 2015, via the Emergency Notification system under Event Notification 51298.
(vi) 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.
TVA contracted with WEC to provide relocation of two RPV material surveillance capsules in each Unit at SON. The capsule relocations for Unit I occurred in Fall 2013 and for Unit 2 in Spring 2014, each during an EOC R19 refueling outage. WVA has service contracts with WEC for various technical and field service activites.
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(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.
TVA conducted an extensive foreign object search and recovery initiative to recover the RPV material surveillance capsules and contents prior to concluding the SQN Unit 1 end of cycle (EOC) R20 outage. There is approximately 74 items that remain unaccounted following the refueling outage. These items are believed to be in the vacuum filters used in retrieval of contents or located in the remains of surveillance capsules. Reconciliation of the remaining items is on going. TVA intends to strengthen it's procedure for oversight of supplemental personnel by September 2015. TVA has included requirements for conducting a pull test on future relocated RPV material surveillance capsules.
(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.
None.
(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.
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