|
---|
Category:Letter
MONTHYEARML24289A0312024-11-0808 November 2024 – Issuance of Amendments Related to the Removal of License Condition 2.F as Part of the Consolidated Line-Item Improvement Process (CLIIP) IR 05000416/20240032024-11-0606 November 2024 Integrated Inspection Report 05000416/2024003 IR 05000416/20240112024-10-16016 October 2024 – Fire Protection Team Inspection Report 05000416/2024011 ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24257A0172024-09-17017 September 2024 Request for Withholding Information from Public Disclosure Unit 1 IR 05000416/20240122024-09-17017 September 2024 License Renewal Post Approval Phase 2 Inspection Report 05000416/2024012 ML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program IR 05000416/20244022024-09-0909 September 2024 Security Baseline Inspection Report 05000416/2024402 05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24235A0832024-08-22022 August 2024 Evaluations Performed in Accordance with 10 CFR 50.54(q) for Changes to Emergency Planning Documents IR 05000416/20240052024-08-21021 August 2024 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-28028 May 2024 Automatic Actuation of Reactor Protection System ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24100A0692024-04-0909 April 2024 Report of Changes or Errors to 10 CFR 50.46 Analysis ML24094A0992024-04-0303 April 2024 (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams 05000416/LER-2024-001, High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close2024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24058A3512024-02-28028 February 2024 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000416/20230062024-02-28028 February 2024 Annual Assessment Letter for Grand Gulf Nuclear Station - Report 05000416/2023006 IR 05000416/20233012024-02-26026 February 2024 NRC Examination Report 05000416-2023301 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground2024-02-13013 February 2024 Reactor Scram Due to Generator Stator Fault to Ground ML24043A1892024-02-12012 February 2024 Spent Fuel Storage Radioactive Effluent Release Report for 2023 ML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24043A0732024-01-29029 January 2024 2024-01 Post Examination Comments IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 IR 05000416/20234012024-01-18018 January 2024 Cyber Security Inspection Report 05000416/2023401 (Public) 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-28028 May 2024 Automatic Actuation of Reactor Protection System 05000416/LER-2024-001, High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close2024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground2024-02-13013 February 2024 Reactor Scram Due to Generator Stator Fault to Ground 05000416/LER-2023-001-01, Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification2023-11-30030 November 2023 Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification 05000416/LER-2023-001, Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification2023-08-0303 August 2023 Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification 05000416/LER-2022-003, Manual Reactor Scram Due to Trip of the a Reactor Feedwater Pump2023-02-16016 February 2023 Manual Reactor Scram Due to Trip of the a Reactor Feedwater Pump 05000416/LER-2022-002, Loss of Secondary Containment During Standby Gas Treatment System Testing Due to Boundary Leakage2022-12-19019 December 2022 Loss of Secondary Containment During Standby Gas Treatment System Testing Due to Boundary Leakage 05000416/LER-2021-001-01, Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate2022-11-30030 November 2022 Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate 05000416/LER-2022-001, For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 232022-08-29029 August 2022 For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 23 05000416/LER-2021-005, Oscillation Power Range Monitors (Oprms) Technical Specification Noncompliance2022-02-0202 February 2022 Oscillation Power Range Monitors (Oprms) Technical Specification Noncompliance 05000416/LER-2021-004, Procedure Inadequacy Resulted in Core Monitoring System Miscalibration and Violation of Technical Specification2022-01-19019 January 2022 Procedure Inadequacy Resulted in Core Monitoring System Miscalibration and Violation of Technical Specification 05000416/LER-2021-003, High Pressure Core Spray Declared Inoperable2021-11-0404 November 2021 High Pressure Core Spray Declared Inoperable 05000416/LER-2020-003-01, Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram2021-08-19019 August 2021 Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram 05000416/LER-2020-006-02, Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram2021-08-19019 August 2021 Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram 05000416/LER-2020-004-01, Automatic Reactor Scram Due to Reactor Feed Pump Trip2021-08-19019 August 2021 Automatic Reactor Scram Due to Reactor Feed Pump Trip 05000416/LER-2020-002-02, Reactor Scram Due to Main Turbine Trip2021-08-19019 August 2021 Reactor Scram Due to Main Turbine Trip 05000416/LER-2020-005-02, Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor Scram2021-08-19019 August 2021 Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor Scram 05000416/LER-2021-002, Core Monitoring System Software Modeling Error Resulted in Conditions Prohibited by Technical Specifications2021-08-16016 August 2021 Core Monitoring System Software Modeling Error Resulted in Conditions Prohibited by Technical Specifications 05000416/LER-2021-001, Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate2021-05-14014 May 2021 Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate 05000416/LER-2020-006-01, Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram2021-04-0101 April 2021 Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram 05000416/LER-2019-006-01, Failure to Meet Technical Specification 5.5.7 for B Train Standby Gas Charcoal Filter Media Efficiency2021-02-18018 February 2021 Failure to Meet Technical Specification 5.5.7 for B Train Standby Gas Charcoal Filter Media Efficiency 05000416/LER-2020-005-01, Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram2021-02-18018 February 2021 Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram 05000416/LER-2020-006, Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram2021-02-0909 February 2021 Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram 05000416/LER-2020-005, Re Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram2021-01-0202 January 2021 Re Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram 05000416/LER-2020-004, Automatic Reactor Scram Due to Reactor Feed Pump Trip2020-10-20020 October 2020 Automatic Reactor Scram Due to Reactor Feed Pump Trip 05000416/LER-2020-003, Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram2020-10-0606 October 2020 Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram 05000416/LER-2016-0082017-08-16016 August 2017 Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable, LER 16-008-001 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable 05000416/LER-2016-0092017-08-16016 August 2017 Entry into Mode of Applicability with the Oscillation Power Range Monitor Upscale Settings Incorrectly Set, LER 16-009-01 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set 05000416/LER-2017-0012017-03-28028 March 2017 High Pressure Core Spray (HPCS) Jockey Pump Trip, LER 17-001-00 for Grand Gulf, Unit 1, Regarding High Pressure Core Spray Jockey Pump Trip 05000416/LER-2016-0012016-05-16016 May 2016 Valid Engineered Safety Feature Actuation and Temporary Loss of Residual Heat Removal, LER 16-001-00 for Grand Gulf, Unit 1, Regarding Valid Engineered Safety Feature Actuation and Temporary Loss of Residual Heat Removal GNRO-2014/00049, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package, Revision 112014-07-31031 July 2014 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package, Revision 11 ML12157A1822012-05-23023 May 2012 Attachment 9 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment L Labeled Reporting Documentation - Unit 2 Sumps. ML0627100452005-08-22022 August 2005 Final Precursor Analysis - Grand Gulf, Unit 1 2024-08-26
[Table view] |
LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable |
Event date: |
|
---|
Report date: |
|
---|
Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
---|
4162024003R00 - NRC Website |
|
text
~ entergy GNRO2024-00029 August26,2024 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150 Jeffery A. Hardy Manager Regulatory Assurance Grand Gulf Nuclear Station Tel: 802-380-5124 10 CFR 50.73 SUBJECT:
Grand Gulf Nuclear Station, Unit 1 Licensee Event Report 2024-003-00, Feedwater Inlet Check Valve Incorrectly Determined Operable Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 Renewed License No. NPF-29 Attached is Licensee Event Report (LER) 2024-003-00, Feedwater Inlet Check Valve Incorrectly Determined Operable. This report is being submitted in accordance with 1 O CFR 50.73(a)(2)(i)(B), as an operation of condition which was prohibited by the plant's Technical Specifications.
This letter contains no new Regulatory Commitments. Should you have any questions concerning the content of this letter, please contact me at 802-380-5124.
Sincerely, 9A~\\?2 JAH/saw Attachments: Licensee Event Report 2024-003-00
GNRO2024-00029 Page 2 of 3 cc:
NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
GNRO2024-00029 Page 3 of 3 Attachment Licensee Event Report 2024-003-00
Abstract
On April 2, 2022, at 0301 CT, while the plant was in MODE 4 with all control rods inserted during a refuel outage, Grand Gulf Nuclear Station identified a failed post work leakage rate test of Feedwater Inlet Check Valve, 1 B21 F032B. An operability evaluation of the valve was performed, and the valve was inappropriately determined to be operable. The valve was returned to service, and the plant returned to MODE 1 at the end of the refuel outage.
On June 27, 2024, NRC inspectors identified a Green finding and associated Non-Cited Violation of Technical Specification 3.6.1.3, "Primary Containment Isolation Valves" (PCIV) for failure to ensure each PCIV was operable.
Valve 1 B21 F032B failed the leakage rate test due to degradation and wear of the valve seat. The operator failed to properly evaluate the operability due to a lack of understanding of the Primary Containment Leakage Rate Testing (Appendix J) program requirements.
There was no impact on the health and safety of the public or reactor safety. The feedwater isolation shutoff valve 1 B21 F065B would have maintained leakage rates for the containment penetration; therefore, there was no significant risk to containment integrity.
Plant Conditions
- 2. DOCKET NUMBER YEAR 416 2024
- 3. LEA NUMBER SEQUENTIAL NUMBER 003 REV NO.
00 At the time of the event, Grand Gulf Nuclear Station was in MODE 4 (Cold Shutdown) with all control rods inserted at zero percent reactor power. The station was performing a post-work leakage rate test on Feedwater Inlet Check Valve 1821F032B.
Description of Event
On April 2, 2022, during the performance of the post work leakage rate test of the Feedwater Inlet Check Valve 1821 F032B, a failing leakage rate of 7650 milliliters per minute was observed. A Condition Report was issued per procedure, and an operability evaluation was performed using the past operability, the technical specification surveillance requirement, and the Primary Containment Leakage Rate Testing (Appendix J) program requirements. An incorrect assumption about the Appendix J requirements was made, and it was determined that the identified leakage was within the allowable leakage rate based on the surveillance requirements. The operability evaluation incorrectly determined that Feedwater Inlet Check Valve 1821 F032B, was operable, and the valve remained in service for the 24-month fuel cycle.
On June 27, 2024, as part of the Biennial Problem Identification and Resolution Inspection Report 05000416/2024010, the NRC inspectors identified a Green finding and associated Non-Cited Violation of Technical Specification (TS) 3.6.1.3, "Primary Containment Isolation Valves" (PCIV) for failure to ensure each PCIV was operable following a failed leakage rate test of 1821 F032B during a refueling outage. A violation of TS 3.0.4 was also identified for making a mode change without meeting the requirements to do so as a result of not meeting TS 3.6.1.3.
Reportability
This report is made in accordance with 10 CFR 50.73(a)(2)(i)(B) for an operation of condition which was prohibited by the plant's Technical Specifications. TS LCO 3.6.1.3 requires each PCIV to be OPERABLE. Due to incorrect operability evaluation, Required Actions C and E were not taken.
Cause(s)
The direct cause of the event was degradation and wear of the valve's seat which resulted in the failed leakage rate test.
An additional cause of insufficient knowledge of the Appendix J program requirements by the Senior Reactor Operators (SROs) was also identified as the cause of the incorrectly performed operability evaluation.
Corrective Actions
Completed Actions: Repairs to the valve seat were made during 2024 refuel outage. Post-work leak rate testing was completed satisfactorily and indicated a leak rate of zero millimeters per minute.
Planned Actions: Update Operability Training for SROs with a focus on Code testing requirements.
Safety Significance
There was no impact on the health and safety of the public or reactor safety. The feedwater isolation shutoff valve 1821 F065B would have maintained leakage rates for the containment penetration; therefore, there was no significant risk to containment integrity.
Previous Similar Events
LEA 2023-001-01 Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification LER 2021-001-01 Primary Containment Outer Airlock Door Inoperable Due To Unacceptable Leak Rate Page 2 of 2