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| {{#Wiki_filter:1> AREVA -NRC meeting. Atlanta May 28, 2008 2> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc. | | {{#Wiki_filter:> AREVA - NRC meeting. Atlanta May 28, 2008 1 Presentation to the NRC On the Causes and Corrective Actions of the AREVA NP Mount Athos Road Shipment of Fuel Cleaning Equipment to the Watts Bar Plant Exceeding Transportation Radiation Limits Ron Land VP Manufacturing Operations Dominique Grandemange Plant Manager Valerio Dunn Fuel Services Project Manager Geoffrey Wertz EHS&L Manager AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 2 |
| Presentation to the NRC On the Causes and Corrective Actions of the AREVA NP Mount Athos Road Shipment of Fuel Cleaning Equipment to the Watts Bar Plant Exceeding Transportati on Radiation Limits Ron LandVP Manufacturing OperationsDominique Grandemange Plant Manager Valerio DunnFuel Services Project ManagerGeoffrey Wertz EHS&L Manager 3> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc. | | |
| Presentation Agenda | | Presentation Agenda |
| >Background | | > Background |
| >Fuel Cleaning Equipment Overview | | > Fuel Cleaning Equipment Overview |
| >Timeline / Ri sk Assessment | | > Timeline / Risk Assessment |
| >Causal Analysis/Corrective Actions | | > Causal Analysis/Corrective Actions |
| >Conclusions 4> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.BackgroundOn February 4, 2008, WB received a shipment of fuel cleaning equipment sent from the AREVA NP Inc, Mount Athos Road (MAR) facility. The receipt radiation survey indicat ed that Box 455 had a localized "hot spot" which exceeded the transportation requirements of 10 CFR 71.47. | | > Conclusions AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 3 |
| 5> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.
| | |
| Fuel Cleaning Equipment OverviewPurpose/Use: | | ===Background=== |
| *Ultrasonic cleaning system used to remove material deposits from the fuel cladding to reduce Axial Offset Anomaly improving thermal performance | | On February 4, 2008, WB received a shipment of fuel cleaning equipment sent from the AREVA NP Inc, Mount Athos Road (MAR) facility. The receipt radiation survey indicated that Box 455 had a localized hot spot which exceeded the transportation requirements of 10 CFR 71.47. |
| *Secondary benefit to reduce plant source term -dose reductionSystem Design Considerations: | | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 4 |
| *Underwater components electro polished to support decontamination due to potential contamination | | |
| *Specific container design incorporates shipping restraints and shielding of anticipated high dose components Fuel Cleaner Fuel AssemblyUltrasonic Transducer Housing Fuel Cleaner Filtration UnitPrimary Underwater Components:Filtration UnitUltrasonic Transducer Housing for Two Fuel Assemblies 6> AREVA -NRC meeting. Atlanta May 28, 2008Jan-08Feb-08Nov-07Dec-0710/24/07 Equipment shipped from Palisades.Highest contact reading on Box 455 was 80 mr/hr.10/26/08MAR receipt survey 80 mr/hr.1/31/08 Pre-shipment survey: FH remained 450 mr/hrHighest contact reading on Box 455 was 40mr/hr.Activity Timeline Pre-ShipmentInappropriate Action - 4Lessons learned from past events not applied.12/13/07 MAR equipment survey performed. Filter Housing (FH) - 450 mr/hr on contact.Pump - 7 R/hr - replaced.Pre-operational checkout - 12 hrs of operation (flushing) prior to package for shipment to WB. No change in radiation levels (fixed).Inappropriate Action - 2Containment of high activity material not sufficient for transport.Inappropriate Action - 3Equipment shipped on a flatbed trailer. | | Fuel Cleaning Equipment Overview Purpose/Use: |
| 7> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Jan-08Mar-08Apr-08Feb-082/6-9/08 MAR RP Tech to WB to perform surveyreadings.2/4/08 WB received shipment with Box 455: hot spot reading 2000 mr/hr, 150 mr/hr at 4 inches below box (top of trailer bed), and 5-7 mr/hr beneath trailer.Discussed shipment with WB staff - equipment was being handled safelyReviewed shipment itinerary from trucking companyPerformed risk review and concluded no immediate risk to driver, public nor workers.WB unloaded the Box 455. Activity Timeline Post-Shipmen t2/9/08 Source material located in Box 455 and removed using duct tape.Box 455 returned to 1-2 mr/hr.2/19/08Source material returned to MAR.Reading 800 mr/hr behind 3/16" plate, 14 mr/hr at 1', and 2 mr/hr at 36".Isotopic Analysis -long-lived corrosion products.Inappropriate Action - 1 Waited to send HP to WBInappropriate Action - 5 No formal HP training on DRP.
| | * Ultrasonic cleaning system Primary Underwater used to remove material Components: |
| 8> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Summary of Survey ResultsGood Gamma Survey Data Consistency With No External Beta Contamination FoundMAR Survey DataWB Survey DataDetector : TELEPOLEDetector : TELETECTOR(gamma readings)800 mr/hr on contact2000 mr/hr gamma and beta on contact 25 mr/hr at 12 inches150 mr/hr at 4 inches No smearable contaminationNo smearable contaminationDetector : TELEPOLEDetector : RSO-5800 mr/hr on contact1500 mr/hr on contact (open window)70 mr/hr at 12 inches800 mr/hr on contact (closed window)Detector : TELEPOLE1 to 2 mr/hr on contactDetector : TELEPOLE1100 mr/hr on contactDetector : TELEPOLE800 mr/hr on contact14 mr/hr at 12 inchesOn hot spot removed from BOX 455 with 3/16" plate Performed at MAR OUTSIDE of box 455 Performed at WB INSIDE of box 455 Performed at WBINSIDE of BOX 455 after removal of "Hot Spot" Performed at WBOn hot spot removed from BOX 455 Performed at MAR 9> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Safety SignificanceSurvey data illustrated graphicallyConclusion of Risk Assessment : No Undue Risk to the Public or Truck Driver 10> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Causal Analysis & Corrective Actions
| | deposits from the fuel Filtration Unit cladding to reduce Axial Offset Anomaly improving thermal Ultrasonic Transducer performance Housing for Two Fuel Assemblies |
| >Two Apparent CausesAC #1 -The procedure for pre-shipment surveys did not have an activity threshold for additional consideration of containment of high activity material prior to transport.AC #2 -The procedure for pre-shipment surveys did not have any specific requirements for consideration of additional packaging or use of a closed conveyance | | * Secondary benefit to reduce plant source term - dose reduction System Design Considerations: |
| | * Underwater components electro polished to support decontamination due to potential contamination |
| | * Specific container design incorporates shipping restraints and shielding of anticipated high dose Fuel Cleaner Filtration Unit components Fuel Cleaner Fuel Assembly Ultrasonic Transducer Housing AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 5 |
| | |
| | Activity Timeline Pre-Shipment 12/13/07 Inappropriate Action - 2 MAR equipment surv ey performed. |
| | Containment of high activity Filter Housing (FH) - 450 mr/hr on material not sufficient for contact. transport. |
| | Pump - 7 R/hr - replaced. |
| | Pre-operational checkout - 12 hrs of Inappropriate Action - 3 operation (flushing) prior to package for Equipment shipped on a flatbed shipment to WB. No change in trailer. |
| | radiation lev els (fixed). |
| | Inappropriate Action - 4 Lessons learned from past events not applied. |
| | Nov-07 Dec-07 Jan-08 Feb-08 10/24/07 Equipment shipped from 1/31/08 Palisades. Pre-shipment surv ey: |
| | Highest contact reading on FH remained 450 mr/hr Box 455 was 80 mr/hr. |
| | 10/26/08 Highest contact reading on MAR receipt surv ey 80 mr/hr. Box 455 was 40mr/hr. |
| | > AREVA - NRC meeting. Atlanta May 28, 2008 6 |
| | |
| | Activity Timeline Post-Shipment 2/4/08 WB received shipment w ith Box 455: hot spot reading 2000 mr/hr, 150 mr/hr at 4 inches below box 2/9/08 (top of trailer bed), and 5-7 mr/hr beneath trailer. |
| | Source material located Discussed shipment w ith WB staff - equipment w as in Box 455 and removed being handled safely using duct tape. |
| | Box 455 returned to 1-2 Review ed shipment itinerary from trucking company mr/hr. |
| | Performed risk review and concluded no immediate risk to driver, public nor w orkers. |
| | WB unloaded the Box 455. Inappropriate Action - 5 No formal HP training on DRP. |
| | Jan-08 Feb-08 Mar-08 Apr-08 Inappropriate Action - 1 2/6-9/08 2/19/08 Waited to send HP to WB MAR RP Source material returned to MAR. |
| | Tech to WB Reading 800 mr/hr behind 3/16" plate, 14 mr/hr to perform at 1', and 2 mr/hr at 36". |
| | survey Isotopic Analysis -long-lived corrosion readings. products. |
| | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 7 |
| | |
| | Summary of Survey Results MAR Survey Data WB Survey Data OUTSIDE of box 455 Detector : TELEPOLE Detector : TELETECTOR (gamma readings) 800 mr/hr on contact 2000 mr/hr gamma and beta on contact 25 mr/hr at 12 inches 150 mr/hr at 4 inches Performed at WB No smearable contamination No smearable contamination INSIDE of box 455 Detector : TELEPOLE Detector : RSO-5 800 mr/hr on contact 1500 mr/hr on contact (open window) |
| | Performed at WB 70 mr/hr at 12 inches 800 mr/hr on contact (closed window) |
| | INSIDE of BOX 455 after removal Detector : TELEPOLE of "Hot Spot" Performed at WB 1 to 2 mr/hr on contact On hot spot removed Detector : TELEPOLE from BOX 455 Performed at MAR 1100 mr/hr on contact On hot spot removed Detector : TELEPOLE from BOX 455 with 3/16" plate 800 mr/hr on contact Performed at MAR 14 mr/hr at 12 inches Good Gamma Survey Data Consistency With No External Beta Contamination Found AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 8 |
| | |
| | Safety Significance Survey data illustrated graphically Conclusion of Risk Assessment : |
| | No Undue Risk to the Public or Truck Driver AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 9 |
| | |
| | Causal Analysis & Corrective Actions |
| | > Two Apparent Causes AC #1 - The procedure for pre-shipment surveys did not have an activity threshold for additional consideration of containment of high activity material prior to transport. |
| | AC #2 - The procedure for pre-shipment surveys did not have any specific requirements for consideration of additional packaging or use of a closed conveyance trailer. |
| | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 10 |
| | |
| | Causal Analysis & Corrective Actions |
| | > Corrective Action #1 Established pre-shipment radiation survey activity thresholds. |
| | * Thresholds trigger additional management review |
| | * Applicable to all MAR equipment shipments. |
| | > Corrective Action #2 Clarified roles and responsibilities for RP and operations personnel to ensure proper packaging of all radioactive equipment. |
| | * Enhanced ownership of equipment packaging. |
| | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 11 |
| | |
| | Causal Analysis & Corrective Actions |
| | > Corrective Action #3 Added requirement to perform extensive surveys of highly contaminated equipment, for example: |
| | * Reactor Cavity |
| | * Below the Reactor Head |
| | * Spent Fuel Pool |
| | > Corrective Action #4 Fuel Cleaning Equipment is transported in a closed conveyance. |
| | > Above requirements added to SL-1600, Shipment and Receipt of Radioactive Material. |
| | > CAs 1 - 4 are completed AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 12 |
| | |
| | Contributing Causes & Corrective Actions |
| | > CC #1 - Extent of Condition Review had not been performed using previous MAR receipt shipments which exceeded transportation limits. |
| | > Corrective Action |
| | #1 - Performed an external assessment of RP practices in shipment preparation - complete. |
| | * Results matched internal ACA findings. |
| | #2 - Open CA to perform a Lessons Learned Review. |
| | * Implemented through CAP and audit process. |
| | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 13 |
| | |
| | Contributing Causes & Corrective Actions |
| | > CC #2 - RP technicians did not have formal training on Discrete Radioactive Particles (DRP). |
| | > Corrective Actions |
| | #1 - Procedure SL-1291,Discrete Radioactive Particle Control created |
| | #2 - RP technicians were trained on the procedure. |
| | #3 - Formal DRP Training Program developed. |
| | #4 - Initial & Recurring Training added to the RP annual curriculum. |
| | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 14 |
| | |
| | Contributing Causes & Corrective Actions |
| | > CC #3 - There was a 2 day delay in dispatching a MAR RP technician to support the event investigation. |
| | > Corrective Action Requirement to dispatch an RP technician immediately if a transportation container exceeds any transportation limit. |
| | Requirement added to procedure SL - 1600. |
| | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 15 |
|
| |
|
| trailer.
| | Corrective Action Summary |
| 11> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Causal Analysis & Corrective Actions
| | > Corrective Actions 1 - 4 are complete. |
| >Corrective Action #1Established pre-shipment radiation survey activity thresholds.
| | > Subsequent Lessons Learned Review will validate apparent and contributing causes and ensure effectiveness of CA implementation. |
| *Thresholds trigger additional management review
| | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 16 |
| *Applicable to all MAR equipment shipments.
| |
| >Corrective Action #2Clarified roles and responsibilities for RP and operations personnel to ensure proper packaging of all radioactive equipment. | |
| *Enhanced ownership of equipment packaging.
| |
| 12> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Causal Analysis & Corrective Actions
| |
| >Corrective Action #3Added requirement to perform extensive surveys of highly contaminated equipment, for example:
| |
| *Reactor Cavity
| |
| *Below the Reactor Head
| |
| *Spent Fuel Pool
| |
| >Corrective Action #4 Fuel Cleaning Equipmentis transported in a closed conveyance.
| |
| >Above requirements added to SL-1600, "Shipment and Receipt of Radioactive Material."
| |
| >CA's 1 -4 are completed 13> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Contributing Causes & Corrective Actions
| |
| >CC #1 -Extent of Condition Review had not been performed using previous MAR "receipt" shipments which exceeded transportation limits.
| |
| >Corrective Action#1 -Performed an external assessment of RP practices in shipment preparation -complete. | |
| *Results matched internal ACA findings.#2 -Open CA to perform a Lessons Learned Review.
| |
| *Implemented through CAP and audit process.
| |
| 14> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Contributing Causes & Corrective Actions
| |
| >CC #2 -RP technicians did not have formal training on Discrete Radi oactive Particles (DRP).
| |
| >Corrective Actions #1 -Procedure SL-1291,"Discrete Radioactive Particle Control" created#2 -RP technicians were trained on the procedure.#3 -Formal DRP Training Program developed.#4 -Initial & Recurring Training added to the RP annual curriculum.
| |
| 15> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Contributing Causes & Corrective Actions
| |
| >CC #3 -There was a 2 day delay in dispatching a MAR RP technician to support the event investigation.
| |
| >Corrective ActionRequirement to dispatch an RP technician immediately if a transportation container exceeds any transportation
| |
|
| |
|
| limit.Requirement added to procedure SL -1600.
| | Conclusions |
| 16> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Corrective Action Summary
| | > MAR recognizes the potential risk this event as important. In this case, the risk to the public or workers was very low. |
| >Corrective Actions 1 -4 are complete.
| | > MAR causal analysis investigation was comprehensive. |
| >Subsequent Lessons Learned Review will validate apparent and contributing causes and ensure effectiveness of CA implementation.
| | > Corrective actions were comprehensive and complete. |
| 17> AREVA -NRC meeting. Atlanta May 28, 2008AREVA NP Inc.Conclusions
| | AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 17}} |
| >MAR recognizes the potential risk this event as important. In this case, the risk to the public or workers was very low. | |
| >MAR causal analysis investigation was comprehensive. | |
| >Corrective actions were comprehensive and complete.}} | |
|
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24312A1432024-11-0707 November 2024 SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24312A0532024-11-0707 November 2024 FLEX HP Pump SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24284A0042024-10-16016 October 2024 Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24225A2542024-08-14014 August 2024 August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating ML24137A2872024-05-16016 May 2024 Pre-Submittal Meetingfor Proposed License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources - Operating to Clarify Requirements for Diesel Generator Testing ML24127A0412024-05-0606 May 2024 May 6, 2024 Meeting Slides ML24067A2832024-03-27027 March 2024 2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides ML24044A0872024-02-14014 February 2024 TVA Slides - Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request to Revise TS 3.7.11, Main Control Room Area Chilled Water System ML23291A1562023-10-18018 October 2023 NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides ML23264A0412023-09-27027 September 2023 NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides ML23251A1252023-09-12012 September 2023 Pre-submittal Meeting for License Amendment Request, Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specification Surveillance Requirement 3.9.5.1 ML23251A1212023-09-12012 September 2023 RHR Flow Rate Reduction During Mode 6 Operation at 23 Ft. Refueling Water Level Technical Specification Change NON-PROPRIETARY Slides ML23178A0832023-07-10010 July 2023 Pre-submittal Meeting Slides for License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23052A0362023-02-22022 February 2023 February 22, 2023, Pre-Submittal Meeting for the License Amendment Request for Increased Tritium Production at Watts Bar (EPID L-2023-LRM-0010) - Meeting Slides ML23044A5182023-02-15015 February 2023 Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension ML23041A3562023-02-15015 February 2023 February 15, 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension (EPID L-2022-LRM-0098) (Slides) ML22318A1042022-11-14014 November 2022 Pre-submittal Meeting for American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 Slide Presentation ML22157A4132022-06-0606 June 2022 Plants - Pre-Submittal Teleconference for Proposed Amendment Request Regarding the Change for the Sequoyah and Watts Bar Nuclear Plants Technical Specification 3.4.12 Meeting Slides ML22102A3032022-04-12012 April 2022 Pre-submittal Meeting for Request for Exemption from Requirements of 10 CFR 26.205(d)(4) and 10 CFR 26.205(d)(6) Slide Presentation ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML21343A0282021-12-14014 December 2021 TVA Slide Presentation Regarding Pre-Submittal Meeting for Proposed Revision to Capsule Withdrawal Schedule ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21250A3652021-09-0808 September 2021 Meeting Slides - Watts Bar Nuclear Plant Unit 2, Presubmittal Teleconference for Proposed License Amendment to Revise the Updated Final Safety Analyses Report (UFSAR) to Use a Tube Support Plate Locking/Displacement Analysis ML21217A2872021-08-19019 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed License Amendment Request Re Application to Modify Technical Specification 3.7.8 Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board ML21229A1992021-08-19019 August 2021 Mid-Cycle SG Outage Strategy (EPID L-2021-LRM-0067) (Slides) ML21231A0972021-08-18018 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed LAR Regarding Application to Modify Watts Bar Units 1 and 2 Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board Cleaning ML21117A0722021-04-27027 April 2021 Meeting Slides for April 28, 2021 Meeting with TVA ML21096A1312021-04-0707 April 2021 Pre-submittal Meeting for Inservice Testing (IST) Program Request for One-Time Extension of Test Frequency of WBN Unit 1 Group 6 Relief Valves ML21041A1552021-02-11011 February 2021 Meeting Slides for February 11, 2021 Meeting with TVA ML20345A0262020-12-10010 December 2020 Replacement Steam Generator Project Planned License Amendment Request (Lars). LAR Descriptions and Submittal Schedule Meeting Slides ML20329A3722020-11-24024 November 2020 Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 5.9.9, Steam Generator Tube Inspection Report, to Use Popcd Methodology ML20302A1232020-10-28028 October 2020 Pre-Submittal Meeting Slides Non-Voluntary Application to Modify WBN Unit 1 and Unit 2 TS Surveillance Requirement 3.6.15.4, Shield Building ML20239A8672020-08-27027 August 2020 Pre-Submittal Meeting Slides License Amendment Request for Technical Specification 5.7.2.19 ML20175A0552020-06-23023 June 2020 TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting ML20125A3242020-05-0505 May 2020 Pre-Submittal Meeting Slides for License Amendment Request - Main Control Room Chiller Completion Time Extension ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel ML20009C3962020-01-0808 January 2020 Pre-Submittal Telecon for Expedited License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation ML19347B0722019-12-12012 December 2019 TVA and Xcel Energy Slides for Joint Presubmittal Meeting to License Amendment Requests to Adopt WCAP-17661, Revision 1 ML19282A0082019-10-0909 October 2019 TVA Slides for Pre-Submittal Meeting for License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values ML19255H5522019-09-12012 September 2019 August 27, 2019, Summary of Public Meeting - Tennessee Valley Safety Conscious Work Environment Update at Watts Bar, Docket 50-390 and 50-391 ML19298A0042019-09-12012 September 2019 Presentation Slides for 9/12/19 Public Meeting ML19252A0532019-09-0909 September 2019 TVA Presentation Slides: Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request Revised Offsite Electrical Power Sources ML19235A2712019-08-23023 August 2019 2019 TVA Watts Bar Nuclear Plant Public Meeting Slides 08-27-2019 (TVA Slides) ML19235A2882019-08-23023 August 2019 2019 WBN SCWE Public Meeting Slides 8-27-2019 (NRC Slides) ML19178A2462019-07-0101 July 2019 Presentation Material for July 1, 2019 Pre-submittal Meeting with TVA on Full Spectrum LOCA Methodology for Watts Bar, Units 1 and 2 ML19161A2412019-06-11011 June 2019 Pre-Application Meeting for Proposed License Amendment Request (LAR) Regarding Change to the WBN Unit 2 Technical Specifications (TS) 3.4.17, Steam Generator Tube Integrity and 5.7.2.12 Steam Generator Program ML19161A2392019-06-10010 June 2019 Plants Pre-Submittal Meeting for Proposed License Amendments Hydrological Analysis Updates June 10, 2019 ML19142A3602019-05-21021 May 2019 May 9, 2019 Summary of Public Meeting; Watts Bar Nuclear Plant 2024-08-15
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24312A1432024-11-0707 November 2024 SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24312A0532024-11-0707 November 2024 FLEX HP Pump SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24284A0042024-10-16016 October 2024 Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24225A2542024-08-14014 August 2024 August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating ML24184B9162024-07-10010 July 2024 U.S. NRC Meeting Slides for Meeting with Tennessee Valley Authority Regarding NRC Questions Regarding Scope of Nuclear Quality Assurance Program ML24137A2872024-05-16016 May 2024 Pre-Submittal Meetingfor Proposed License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources - Operating to Clarify Requirements for Diesel Generator Testing ML24127A0412024-05-0606 May 2024 May 6, 2024 Meeting Slides ML24067A2832024-03-27027 March 2024 2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides ML23291A1562023-10-18018 October 2023 NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides ML23264A0412023-09-27027 September 2023 NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides ML23251A1252023-09-12012 September 2023 Pre-submittal Meeting for License Amendment Request, Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specification Surveillance Requirement 3.9.5.1 ML23251A1212023-09-12012 September 2023 RHR Flow Rate Reduction During Mode 6 Operation at 23 Ft. 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> AREVA - NRC meeting. Atlanta May 28, 2008 1 Presentation to the NRC On the Causes and Corrective Actions of the AREVA NP Mount Athos Road Shipment of Fuel Cleaning Equipment to the Watts Bar Plant Exceeding Transportation Radiation Limits Ron Land VP Manufacturing Operations Dominique Grandemange Plant Manager Valerio Dunn Fuel Services Project Manager Geoffrey Wertz EHS&L Manager AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 2
Presentation Agenda
> Background
> Fuel Cleaning Equipment Overview
> Timeline / Risk Assessment
> Causal Analysis/Corrective Actions
> Conclusions AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 3
Background
On February 4, 2008, WB received a shipment of fuel cleaning equipment sent from the AREVA NP Inc, Mount Athos Road (MAR) facility. The receipt radiation survey indicated that Box 455 had a localized hot spot which exceeded the transportation requirements of 10 CFR 71.47.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 4
Fuel Cleaning Equipment Overview Purpose/Use:
- Ultrasonic cleaning system Primary Underwater used to remove material Components:
deposits from the fuel Filtration Unit cladding to reduce Axial Offset Anomaly improving thermal Ultrasonic Transducer performance Housing for Two Fuel Assemblies
- Secondary benefit to reduce plant source term - dose reduction System Design Considerations:
- Underwater components electro polished to support decontamination due to potential contamination
- Specific container design incorporates shipping restraints and shielding of anticipated high dose Fuel Cleaner Filtration Unit components Fuel Cleaner Fuel Assembly Ultrasonic Transducer Housing AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 5
Activity Timeline Pre-Shipment 12/13/07 Inappropriate Action - 2 MAR equipment surv ey performed.
Containment of high activity Filter Housing (FH) - 450 mr/hr on material not sufficient for contact. transport.
Pump - 7 R/hr - replaced.
Pre-operational checkout - 12 hrs of Inappropriate Action - 3 operation (flushing) prior to package for Equipment shipped on a flatbed shipment to WB. No change in trailer.
radiation lev els (fixed).
Inappropriate Action - 4 Lessons learned from past events not applied.
Nov-07 Dec-07 Jan-08 Feb-08 10/24/07 Equipment shipped from 1/31/08 Palisades. Pre-shipment surv ey:
Highest contact reading on FH remained 450 mr/hr Box 455 was 80 mr/hr.
10/26/08 Highest contact reading on MAR receipt surv ey 80 mr/hr. Box 455 was 40mr/hr.
> AREVA - NRC meeting. Atlanta May 28, 2008 6
Activity Timeline Post-Shipment 2/4/08 WB received shipment w ith Box 455: hot spot reading 2000 mr/hr, 150 mr/hr at 4 inches below box 2/9/08 (top of trailer bed), and 5-7 mr/hr beneath trailer.
Source material located Discussed shipment w ith WB staff - equipment w as in Box 455 and removed being handled safely using duct tape.
Box 455 returned to 1-2 Review ed shipment itinerary from trucking company mr/hr.
Performed risk review and concluded no immediate risk to driver, public nor w orkers.
WB unloaded the Box 455. Inappropriate Action - 5 No formal HP training on DRP.
Jan-08 Feb-08 Mar-08 Apr-08 Inappropriate Action - 1 2/6-9/08 2/19/08 Waited to send HP to WB MAR RP Source material returned to MAR.
Tech to WB Reading 800 mr/hr behind 3/16" plate, 14 mr/hr to perform at 1', and 2 mr/hr at 36".
survey Isotopic Analysis -long-lived corrosion readings. products.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 7
Summary of Survey Results MAR Survey Data WB Survey Data OUTSIDE of box 455 Detector : TELEPOLE Detector : TELETECTOR (gamma readings) 800 mr/hr on contact 2000 mr/hr gamma and beta on contact 25 mr/hr at 12 inches 150 mr/hr at 4 inches Performed at WB No smearable contamination No smearable contamination INSIDE of box 455 Detector : TELEPOLE Detector : RSO-5 800 mr/hr on contact 1500 mr/hr on contact (open window)
Performed at WB 70 mr/hr at 12 inches 800 mr/hr on contact (closed window)
INSIDE of BOX 455 after removal Detector : TELEPOLE of "Hot Spot" Performed at WB 1 to 2 mr/hr on contact On hot spot removed Detector : TELEPOLE from BOX 455 Performed at MAR 1100 mr/hr on contact On hot spot removed Detector : TELEPOLE from BOX 455 with 3/16" plate 800 mr/hr on contact Performed at MAR 14 mr/hr at 12 inches Good Gamma Survey Data Consistency With No External Beta Contamination Found AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 8
Safety Significance Survey data illustrated graphically Conclusion of Risk Assessment :
No Undue Risk to the Public or Truck Driver AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 9
Causal Analysis & Corrective Actions
> Two Apparent Causes AC #1 - The procedure for pre-shipment surveys did not have an activity threshold for additional consideration of containment of high activity material prior to transport.
AC #2 - The procedure for pre-shipment surveys did not have any specific requirements for consideration of additional packaging or use of a closed conveyance trailer.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 10
Causal Analysis & Corrective Actions
> Corrective Action #1 Established pre-shipment radiation survey activity thresholds.
- Thresholds trigger additional management review
- Applicable to all MAR equipment shipments.
> Corrective Action #2 Clarified roles and responsibilities for RP and operations personnel to ensure proper packaging of all radioactive equipment.
- Enhanced ownership of equipment packaging.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 11
Causal Analysis & Corrective Actions
> Corrective Action #3 Added requirement to perform extensive surveys of highly contaminated equipment, for example:
> Corrective Action #4 Fuel Cleaning Equipment is transported in a closed conveyance.
> Above requirements added to SL-1600, Shipment and Receipt of Radioactive Material.
> CAs 1 - 4 are completed AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 12
Contributing Causes & Corrective Actions
> CC #1 - Extent of Condition Review had not been performed using previous MAR receipt shipments which exceeded transportation limits.
> Corrective Action
- 1 - Performed an external assessment of RP practices in shipment preparation - complete.
- Results matched internal ACA findings.
- 2 - Open CA to perform a Lessons Learned Review.
- Implemented through CAP and audit process.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 13
Contributing Causes & Corrective Actions
> CC #2 - RP technicians did not have formal training on Discrete Radioactive Particles (DRP).
> Corrective Actions
- 1 - Procedure SL-1291,Discrete Radioactive Particle Control created
- 2 - RP technicians were trained on the procedure.
- 3 - Formal DRP Training Program developed.
- 4 - Initial & Recurring Training added to the RP annual curriculum.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 14
Contributing Causes & Corrective Actions
> CC #3 - There was a 2 day delay in dispatching a MAR RP technician to support the event investigation.
> Corrective Action Requirement to dispatch an RP technician immediately if a transportation container exceeds any transportation limit.
Requirement added to procedure SL - 1600.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 15
Corrective Action Summary
> Corrective Actions 1 - 4 are complete.
> Subsequent Lessons Learned Review will validate apparent and contributing causes and ensure effectiveness of CA implementation.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 16
Conclusions
> MAR recognizes the potential risk this event as important. In this case, the risk to the public or workers was very low.
> MAR causal analysis investigation was comprehensive.
> Corrective actions were comprehensive and complete.
AREVA NP Inc. > AREVA - NRC meeting. Atlanta May 28, 2008 17