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Category:Meeting Briefing Package/Handouts
MONTHYEARML24228A2312024-08-15015 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 ML24191A0642024-07-16016 July 2024 TVA Pre-Submittal Conference Presentation for Proposed LAR Regarding a Revision to Sequoyah Fuel Handling Accident Analysis, Deletion of TS 3.9.4 and Modification of TS 3.3.6 - July 16, 2024 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 ML24117A0352024-05-0202 May 2024 TVA Sequoyah Nuclear Plant - 1B Emergency Diesel Generator Regulatory Conference May 02, 2024 -Presentation Slides ML24037A0252024-02-0808 February 2024 Pre-Submittal Presentation - 02/08/2024 - Proposed License Amendment Request Change to the Sequoyah Nuclear Plant Technical Specifications 3.8.1 and 3.8.2 ML23345A1662023-12-13013 December 2023 Tennessee Valley Authority - Pre-submittal Meeting for Conversion of Nuclear Quality Assurance Plan from ANSI N45.2-1971 to ASME NQA-1-2015 (EPID L-2023-LRM-0103) - 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 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 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 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 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) ML23044A5182023-02-15015 February 2023 Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension 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 ML21308A4932021-11-0808 November 2021 Pre-submittal Meeting Presentation - License Amendment Request to Revise Sequoyah Operating License to Use Fire and Seismic PRA Models for 10 CFR 50.69 Risk-Informed Categorizations (EPID L-2021-LRM-0109) (Slides) 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) ML21252A3632021-09-15015 September 2021 Pre-Submittal Meeting for License Amendment Request to Eliminate the High Negative Flux Rate Trip 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 ML21229A1992021-08-19019 August 2021 Mid-Cycle SG Outage Strategy (EPID L-2021-LRM-0067) (Slides) 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 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 ML21061A0892021-03-0202 March 2021 TVA Presentation Slides for March 2, 2021, Public Meeting to Discuss Sequoyah Alternative Request 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 ML20196L6892020-07-16016 July 2020 TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request ML20196L7922020-07-16016 July 2020 Corrected TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request ML20203M0572020-07-16016 July 2020 Updated TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request ML20175A0552020-06-23023 June 2020 TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting ML20163A6952020-06-12012 June 2020 Bpg Presentation on TVA SCWE Final 2 ML20125A3242020-05-0505 May 2020 Pre-Submittal Meeting Slides for License Amendment Request - Main Control Room Chiller Completion Time Extension ML20108E9082020-04-16016 April 2020 Presentation Slides for Sequoyah Nuclear Plant, Unit 2 - Exigent License Amendment Request TS 4.2.2, Control Rod Assemblies, Pre-Submittal Conference Call - April 16, 2020 ML20050C8662020-02-20020 February 2020 February 20, 2020 - Pre-Submittal Meeting Presentation - Permanent Operation with Control Rod H8 Removed ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel ML20024D2112020-01-27027 January 2020 Pre-Submittal Meeting for License Amendment Request (LAR) Revised Steam Generator (SG) Inspection Intervals - January 27, 2020 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 ML19325C7142019-12-0202 December 2019 November 15,2019, Summary of Conference Call with Tennessee Valley Authority to Discuss Submittal of Exigent License Request (EPID L-2019-LLA-0239) for Sequoyah Nuclear Plant, Unit 1 2024-08-15
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Enclosure 2 Handouts and Presentations Discussed during the November 16, 2017 ROP WG Public Meeting Dated December 8, 2017
Licensee Event Report -
Online Data Collection November 2017
Licensee Event Report System
- Result of the TMI lessons learned
- 10 CFR 50.73 is NRCs systematic way of collecting event data from operating power reactors
- Reactor events and problems believed to be significant and useful to the NRC in its effort to identify and resolve threats to public safety
- Designed to provide information necessary for
- Engineering studies of operational anomalies
- Trends and patterns analysis of operational occurrences
- Other analysis to aid in identifying accident precursors
- Davis-Besse lessons learned emphasized the importance of continuously collecting and evaluating this information
End Users of LER Data
- Office of Nuclear Reactor Regulation (NRR)
- Mitigating Systems Performance Index
- Operating Experience Clearinghouse
- System and component studies
- Human factors studies
- Communication (e.g., Regional and other staff requests, Information Notices)
- Office of Nuclear Regulatory Research (RES)
- SPAR Model development
- Accident Sequence Precursor Program
- System and component studies (e.g., initiating events, LOOP, Scrams)
End Users of LER Data (cont.)
- External Stakeholders (e.g. Public)
- Research and reference material
- Component and system studies generated from LER review
- Significance Determination Process
- Event review
Current LER Workflow
- Licensees submit reports pursuant to 10 CFR 50.73 requirements
- Submitted in accordance with §50.4
- By electronic submission (e.g., by EIE)
- Either method generally results in report getting printed out and scanned before being added to ADAMS
- Resulting in loss of data quality
- NUREG 1022 provides guidance on filling out Form 366, which includes structured fields
Current LER Workflow (cont.)
- Licensees fill out structured form fields, but structure is lost upon scanning and ADAMS processing
- NRC staff screens and reviews all LERs, but further analysis is limited because of the time commitment for data extraction
Proposed LER Workflow
- Voluntary online report submittal tool
- Licensees would use a web interface to enter the same information that is currently collected via the DCD and EIE.
- Tool will generate an LER to be added to ADAMS
- Provide appropriate interfaces to be used for NRC needs (NRR, RES, Regions, Public Search tool)
LER Online Submittal Benefits
- Increased information quality
- Data automatically separated into fields that populate tables
- 100% of data captured
- Data is easily searchable from initial entry
- Consistent document quality
- Increased accessibility of LER information for all stakeholders
- Streamline process to reduce cost and burden to licensees and NRC
Next Steps
- Perform cost analysis
- Develop application
- Consider expanding to other reports
- 50.72
- Part 21
Demonstration UPDATE ON NUCLEAR SAFETY CULTURE MONITORING November 16, 2017
OUR OBJECTIVES
- 1. Update the NRC on the status of industrys initiative to monitor nuclear safety culture
- 2. Discuss typical approaches employed today
- 3. Answer any questions the NRC may have 2
TOPICS
- 1. Timeline of NSCM developments
- 2. NEI 09-07, Rev. 1 Options
- 3. Survey of Current Approaches
- 4. Path Forward 3
TIMELINE
- 1. Dec. 2010 - NSCM initiative approved
- 2. Oct. 2011 - Initiative/NEI 09-07 implemented
- 3. Mar. 2014 - NEI 09-07 R1 published
- 4. Dec. 2015 - DNP IO RE-012 mentions potential elimination of NSCMP
- 5. Jul. 2016 - DNPSC retains NSCMP
- 6. Sep. 2016 - ROPTF briefing on NSCM
- 7. Dec. 2016 - DNP publishes EB to streamline oversight 4
NEI 09-07 R1 OPTIONS
- 1. Nominal Process - NSCMP feeding SLT
- 2. Combined Meeting - NSCMP/SLT meet as one
- 3. Line Departments Lead
- 4. SLT Subcommittee
- 5. Other Bodies Lead 5
NEI 09-07 R1 OPTION 1 6
NEI 09-07 R1 OPTION 2 External Review Fleet/Corporate (e.g., NSRB) Review Site Response Policies Communication Program Modifications Internal Actions Site Leadership Team Training Regulator Assessments External Benchmarking Nuclear Safety Culture Confidentiality Regulatory Oversight Monitoring Panel Combined Meeting Employee Workforce Concerns Issues (including IP 71152 PI&R)
Corrective Action Program Nuclear Safety Industry QA/Self Assessment/
CAP Trends Culture Self Evaluations Benchmarking Assessment NRC Inspection Performance Operating Results Trends Experience 7 Typical Inputs
NEI 09-07 R1 OPTION 3 External Review Fleet/Corporate (e.g., NSRB) Review Site Response Policies Communication Program Modifications Internal Actions Site Leadership Team Training Regulator Regulatory Oversight Assessments External Human Resources Benchmarking Other Input Human (including IP 71152 PI&R)
Sources Performance Nuclear Safety Culture Monitoring Panel Data Performance Improvement Industrial Safety Chemistry &
Operations Maintenance Security Radiation Protection Support Support Functions Functions (Typical)
(Typical)
Line Line Departments Departments (Typical)
(Typical) 8
NEI 09-07 R1 OPTION 4 9
NEI 09-07 R1 OPTION 5 10
SURVEY OF CURRENT PRACTICES
- Informal survey of three basic questions
- Which of the five options are you following?
- How do you do nuclear safety culture assessments?
- Fleets: Entergy, Exelon, Duke, Dominion, NextEra, Southern, Xcel
- Single site operators: AEP, Ameren, DTE, Energy NW, Luminant, PGE, SCANA, STPNOC, WCNOC 11
SURVEY RESULTS
- Option 1 (separate NSCMP and SLT) and Option 2 (combined NSCMP/SLT meeting) predominate
- Option 3 (line department lead) is favored by Duke and Energy NW
- Option 4 (SLT subcommittee) forthcoming at STP 12
LESSONS LEARNED
- 1. The Cultural Landscape Has Changed -
a) Awareness of safety culture concepts, language and implications is widespread now b) Many processes touch on culture (e.g., OR, PI, NSRB, INPO) c) We talk about it; we train on it; we practice it
- 2. The Conversational Landscape Has Changed -
a) Conversations relevant to culture monitoring and management take place in a variety of routine and ad hoc meetings and assessments.
b) These catch culturally significant information upstream and outside the designated culture monitoring process.
13
LESSONS LEARNED
- 3. Our Approach Has Changed -
a) Cognitive analysis (i.e., team and management conversations about cultural implications of events and observations) is our tool of choice.
b) Conversations have proven more effective than quantitative analysis as a means of recognizing culturally important events and trends.
- 4. Our Appreciation for Culture Has Changed -
a) Cultural health is recognized as a critical attribute of a high functioning organization b) Discussions about cultural health help the management team to bond on this important attribute
- 5. As a Result, Nuclear Safety Culture Monitoring -
a) Provides an added layer of oversight and influence b) Substantiates nascent observations arising elsewhere, and ensures they are recognized.
14
PATH FORWARD
- Industry sees the value of culture monitoring and management, using NEI 09-07 as guidance, and remains committed to doing so.
- Industry will continue to experiment with different approaches and benchmark one another to improve effectiveness and efficiency of culture monitoring processes, and guard against getting complacent 15
Questions?
NEI
Contact:
James Slider, jes@nei.org (202) 739-8015