ML21280A028
| ML21280A028 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/04/2021 |
| From: | NRC Region 4 |
| To: | Entergy Corp |
| References | |
| Download: ML21280A028 (27) | |
Text
Welcome!
The meeting will begin shortly.
1 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
Supplemental Inspection Public Exit and Regulatory Performance Meeting To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
2 U.S Nuclear Regulatory Commission - Region IV October 4, 2021 Grand Gulf Nuclear Station (GGNS)
Agenda
- Opening Remarks and Introductions
- Overview of Reactor Oversight Process
- Discussion of Yellow Performance Indicator
- Supplemental Inspection Objectives and Scope
- Supplemental Inspection Results
- Entergy Response
- NRC Closing Comments
- Q&A 3
Facilitator Patricia Vossmar Senior Reactor Inspector, Region IV To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
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95002 Team Leader / Presenter April Nguyen Senior Resident Inspector, Region III To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
5
NRC Representatives To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
6 Scott Morris Regional Administrator, Region IV Michael Hay Deputy Director, Division of Reactor Projects Jason Kozal
- Chief, Projects Branch C
Grand Gulf Nuclear Station
Introductions
7 Bob Franssen GGNS Site Vice President, Entergy Operations Inc.
To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
NRC Opening Remarks 8
To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
Scott Morris Regional Administrator, Region IV
Grand Gulf Nuclear Station To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
9 95002 Exit and Regulatory Performance Meeting
NRC Mission Statement The NRC licenses and regulates the nation's civilian use of radioactive materials to provide reasonable assurance of adequate protection of public health and safety and to promote the common defense and security and to protect the environment.
10 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
10
NRC Reactor Oversight Process (ROP)
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11 Licensee
Response
Regulatory
Response
Degraded Performance Multiple /
Repetitive Degraded Cornerstone Unacceptable Performance Column I Column II Column III Column IV Column V NRC Action Matrix Licensee Response column is baseline inspection (issues of very low safety significance)
Increase in number of findings or performance indicators of significance moves licensee to the right in the matrix Moving to the right leads to increased NRC Oversight (Supplemental Inspections, higher level engagement with plant management)
2020 Yellow Performance Indicator May 25, 2020 scram - Turbine Overspeed Trip August 8, 2020 manual scram - Turbine Control Valve Degraded Operation August 24, 2020 scram - Reactor Feedwater Pump Trip November 6, 2020 scram - Turbine Trip due to Low Generator Cooling Water Flow December 11, 2020 scram - Improper Control of Generator Cooling Water 12
95002 Inspection - Objectives
- Ensure root and contributing causes of performance issues are understood.
- Independently assess and ensure extent-of-condition and extent-of-cause are identified.
- Ensure completed corrective actions to address and preclude repetition of performance issues are timely/effective.
- Ensure planned corrective actions to preclude repetition direct timely and effective actions.
- Independently determine if safety culture traits caused or significantly contributed to the performance issues.
13 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
95002 Inspection - Team
- Senior Resident Inspector (Lead)
- 3 Senior Resident Inspectors
- 1 Resident Inspector
- 1 Operations Engineer
- 1 Reactor Engineer (observer)
- 3 Safety Culture Experts 14 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
95002 Inspection - Conduct
- Dates: August 23 - September 17, 2021
- Onsite Inspection: Plant Tours, Interviews, Observations, Verification of corrective actions
- Document Reviews
- Independent review of Root Cause Evaluations
- Related issue review: Independent Extent of Cause and Extent of Condition sampling
- Independent Safety Culture Review (IP 40100)
Focus Group and individual Management interviews Review of third-party safety culture assessment 15 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
Common Cause Assessment for Degraded Cornerstone
- Four of the Five Scrams were the result of modifications made to the Turbine Control System (TCS).
- The common root cause was Engineering Leadership did not fully align the organization around roles and responsibilities for the TCS modification missing an opportunity to provide greater rigor to the design change.
- The key corrective action to preclude repetition (CAPR) was to develop and implement a Roles and Responsibility Matrix to establish, communicate, and track specific requirements for each participating individual through each portion of the modification process.
16 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
Licensee Key Corrective Actions Created Requirement to Construct Risk Analysis Tables for Engineering Changes Created Specific Methods to Verify Critical Procurement Characteristics Implemented an Oversight Plan for Supplemental Engineering Performed a Turbine Control System vulnerability study to determine if the underlying causes of recent TCS failures extended to other components in the system Reinforced Standards and Expectations in the Corrective Action Program to Ensure Timely and Effective Evaluation and Resolution of Issues Improved Behaviors by Focusing on Questioning Attitude, Leadership Engagement, Excellent Standards, Risk Recognition and Mitigation, and Ownership of Issues 17 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
95002 Inspection - Results
- Inspection Objectives Met
- Four General Weaknesses
- Green Violation - Criterion XVI for Recurring Engineering Issues that led to the Yellow PI
- Green Violation - Operator Error that led to December 11th Scram
- Green Finding with Three Examples -
Engineering Design Issues that led to 3 Scrams 18 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
95002 Inspection - Results cont'd
- Four General Weaknesses
- Ineffective corrective actions to preclude repetition of Scrams
- Missed opportunities to effectively use Operating Experience to mitigate/prevent events
- Narrow scope for extent-of-condition and extent-of-cause reviews
- Gap of risk awareness in application of CAPRs 19 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
95002 Inspection Results
- Safety Culture
- The station, overall, exhibited signs of a positive Safety Conscious Work Environment.
- The team independently identified a few safety culture traits that could have contributed to the performance issues.
- Consistent and persistent messaging will help to ensure Nuclear Safety Culture plays a role in all day-to-day activities that take place on-site.
20 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
95002 Inspection - Summary
- The Team determined that the licensees problem identification, causal analysis, and corrective actions sufficiently addressed the performance issues that led to the Yellow performance indicator.
- Several Weaknesses and Observations were provided to the licensee to ensure sustainable improvements in performance.
- Future inspections planned to review not-yet-completed corrective actions and effectiveness of CAPRs.
21 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
Grand Gulf Nuclear Station
Response
22 Bob Franssen GGNS Site Vice President, Entergy Operations Inc.
To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
Action Matrix - Next Steps
- Perform Onsite 95002 Inspection
- Complete and Objectives Met
- Conduct Public Performance Assessment Meeting
- Completed Tonight
- Assess Colors of Current Performance Indicators and Inspection Findings
- Will be Green in 3Q2021 Once Finalized
- Issue 95002 Inspection Report and Follow-up Assessment Letter
- within 45 days 23 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
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24
Contacting the NRC
- Report an emergency
- (301) 816-5100 (call collect)
- Report a safety concern
- (800) 695-7403
- Allegation@nrc.gov
- General information or questions
- www.nrc.gov
- Select What We Do for Public Affairs To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
25
NRC Closing Remarks 26 To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
Scott Morris Regional Administrator, Region IV
Q & A Members of the public are invited to participate in this meeting after the formal presentation. Signal the phone bridge moderator by pressing *1 if you want to ask a question.
To hear the audio portion of this presentation, dial 888-323-9703 and enter participant code 1786567#
If we were not able to answer your question, submit an E-mail to the NRC to Patricia.Vossmar@nrc.gov or Jason.Kozal@nrc.gov.