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Category:Letter type:NL
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0235, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0221, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0123, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0828, Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift2023-11-30030 November 2023 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal 2024-09-04
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARNL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-18-0859, Unit 2 - Reply to a Notice of Violation: EA-17-2042018-06-20020 June 2018 Unit 2 - Reply to a Notice of Violation: EA-17-204 NL-18-0782, Unit 2 - Reply to a Notice of Violation: EA-17-1872018-06-20020 June 2018 Unit 2 - Reply to a Notice of Violation: EA-17-187 NL-16-2196, Reply to a Notice of Violation, EA-16-1102016-10-27027 October 2016 Reply to a Notice of Violation, EA-16-110 IR 05000348/20120082013-02-0808 February 2013 Joseph M. Farley Nuclear Plant, Units 1 & 2 - Response to Apparent Violations in Inspection Report 05000348-12-008 & 05000364-12-008: EA-12-240 NL-13-0208, Response to Apparent Violations in Inspection Report 05000348-12-008 & 05000364-12-008: EA-12-2402013-02-0808 February 2013 Response to Apparent Violations in Inspection Report 05000348-12-008 & 05000364-12-008: EA-12-240 NL-07-2175, Reply to a Notice of Violation; EA-07-173, NRC Inspection Report 05000348, 364/20070112007-11-30030 November 2007 Reply to a Notice of Violation; EA-07-173, NRC Inspection Report 05000348, 364/2007011 NL-04-0637, Response to Identified Green Non-Cited Violation (NCV) NRC Integrated Inspection Report 05000348/2003005 and 05000364/20030052004-04-30030 April 2004 Response to Identified Green Non-Cited Violation (NCV) NRC Integrated Inspection Report 05000348/2003005 and 05000364/2003005 2023-09-08
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Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 November 14, 2023 Docket No.: 50-348 NL-23-0825 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant, Unit 1 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection Ladies and Gentlemen:
By letter dated October 19, 2023, the Nuclear Regulatory Commission (NRC) staff notified Southern Nuclear Operating Company (SNC) of a Notice of Violation (NOV) and associated White Finding in Inspection Report 05000348/2023091. The violation states that SNC failed to identify and correct a condition adverse to quality resulting in the inoperability of the 1B emergency diesel generator (EDG). SNC has implemented corrective steps and completed a root cause evaluation of the issue. Pursuant to the provisions of 10 CFR 2.201, SNC submits the required response to the violation as the Enclosure to this letter.
SNC is ready to support a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, the week of December 11, 2023. This was discussed with Mr. Alan Blamey by phone on November 10, 2023.
This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce, at 205-992-6468.
Respectfully submitted, Jamie Coleman Regulatory Affairs Director JMC/jdj
Enclosure:
Response to Notice of Violation EA-23-080
U. S. Nuclear Regulatory Commission NL-23-0825 Page 2 cc: Regional Administrator, Region ll NRR Project Manager - Farley Nuclear Plant Senior Resident Inspector - Farley Nuclear Plant RTYPE: CFA04.054
References:
- 1. Joseph M. Farley Nuclear Plant - Integrated Inspection Report (05000348/2023002 and 05000364/2023002 and Apparent Violation, dated August 10, 2023 (EA-23-080)
- 2. Joseph M. Farley Nuclear Plant - NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation, dated August 31, 2023 (EA 080)
- 3. Joseph M. Farley Nuclear Plant - Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter - NRC Inspection Report 05000348/2023091), dated October 19, 2023 (EA-23-080)
Joseph M. Farley Nuclear Plant, Unit 1 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection Enclosure Response to Notice of Violation EA-23-080
Enclosure to NL-23-0825 Response to Notice of Violation EA-23-080 Response to Notice of Violation EA-23-080 Restatement of Violation 05000348/364 - 2023091 During an NRC inspection conducted from April 1 to June 30, 2023, a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
x Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix B, Criterion XVI, Corrective Action, states, in part, measures shall be established to assure that conditions adverse to quality, such as nonconformance are promptly identified and corrected.
x Technical Specifications (TS) Limiting Condition of Operations (LCO) 3.0.1. requires in part, that LCOs shall be met during the modes of applicability. TS LCO 3.8.1, AC Sources, requires, in part, two operable emergency diesel generator (EDG) sets capable of supplying the onsite Class 1E distribution systems while in Modes 1, 2, 3, or 4.
Contrary to the above, on November 4, 2022, the licensee failed to identify and correct a condition adverse to quality associated with nonconforming work instructions for the installation of a lube oil coupling assembly for the unit 1B EDG following a coupling assembly failure and substantial lube oil leak. In addition, between December 7, 2022, to March 3, 2023, while the plant was in the modes of applicability the 1B EDG was inoperable.
Specifically, the licensee did not adequately disposition the failure via troubleshooting WO SNC 1399361 used to implement corrective actions in accordance with procedure NMP-GM-002-001, Corrective Action Program Instructions, version 43.0. The disposition was inadequate because the licensee failed to adhere to its troubleshooting standards and did not evaluate available evidence surrounding the coupling assembly failure after the immediate cause of the failure could not be identified during implementation of WO SNC1399361. As a result, following the failure on November 4, 2022, repairs to the EDG were limited to replacement of the coupling assembly in accordance with the existing nonconforming work instructions. This resulted in the inoperability of the EDG due to a similar failure on February 26, 2023, during a surveillance run. With the 1B EDG inoperable the licensee failed to meet the LCO in accordance with TS 3.0.1 and 3.8.1 between December 7, 2022, and March 3, 2023.
The violation is associated with a White Significance Determination Process finding. Southern Nuclear Company (SNC) does not contest the violation.
Reason for the Violation SNC does not contest the violation and offers the following discussion regarding the circumstances which resulted in the violation.
On February 26, 2023, the 1B Emergency Diesel Generator (EDG) lube oil pump outlet coupling connection developed an oil leak when the lube oil piping moved and became separated at a flexible coupling location. The root cause was determined to be inadequate piping restraint which allowed the discharge piping to move and subsequently separate from the coupling. In addition, troubleshooting process deficiencies and implementation weaknesses led to the station failing to identify and correct the lube oil system failure mode in November 2022. The E-1
Enclosure to NL-23-0825 Response to Notice of Violation EA-23-080 root cause analysis concluded that FNP leaders oversight of the 1B EDG circulating lube oil leak evaluation and resolution activities was less than adequate and significantly contributed to this incident.
Corrective Steps Taken and Results Achieved Immediate steps were taken to restore the 1B EDG to operable status by modifying the existing lube oil pipe restraint for the 1B EDG and installing a new additional restraint. Subsequent corrective actions to improve the rigid piping restraints and replace the lube oil pump outlet coupling with hard-piped connections have been implemented for the 1B EDG as well as the other EDGs that have similar piping restraints and coupling connections (specifically, the 1-2A and 2B EDGs). The corrective actions taken have been effective as evidenced by no leakage in the circulating lube oil system.
To address gaps in organizational response, behaviors, and leadership oversight, FNP has revised procedures to clearly define roles, responsibilities and required documentation for issue response, troubleshooting, and corrective actions addressing conditions adverse to quality. The corrective actions of the troubleshooting root cause have been observed to strengthen the organizational responses and behaviors necessary to prevent recurrence.
Corrective Steps to be Taken In addition to effectiveness reviews for the completed corrective actions, FNP will develop and implement a Case Study for this incident. The case study will address multiple departments and levels of management to include responsibilities and documentation requirements of the enhanced troubleshooting and incident response team process. The case study will be completed no later than March 14, 2024.
Additionally, FNP plans to perform teaching and learning sessions to promote alignment and awareness of Maintenance and Engineering personnel and managers for this incidents root cause evaluation including the changes to procedures and necessary behaviors to address gaps in organizational response and oversight by December 2023.
Date When Full Compliance Will Be Achieved Full compliance was achieved on March 3, 2023 when the 1B EDG was restored to operable.
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