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Category:Letter type:NL
MONTHYEARNL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-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-24-0259, 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-24-0340, 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-24-0321, 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-23-0716, 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-23-0713, 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-23-0704, 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 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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~ Southern Nuclear Dennis R. MadiiOfl VIce Pnlsldent *Farley Joseph M. Farley Nuclear Plant 7388 North State Hwy 95 Columbia. Alabama 36319 334 814.4511 let 334 81 44575 lax June 20, 2018 dnnsd1so0 southemco.com Docket Nos.: 50.348 NL-18-0859 5().364 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Farley Nuclear Plant - Unit 1 and Unit 2 Replv to a Notice of Violation: EA-17-204
Reference:
NRC letter to Southern Nuclear Operation Company, Joseph M. Farley Nuclear Plant -Inspection Report 0500034812018014 and 0500036412018014; Investigation Report No. 2*2017-014; and Notice of Violations (EA-17-204}
Ladies and Gentlemen:
In accordance with the provisions of 10 CFR 2.201, the Nuclear Regulatory Commission (NRC) has issued to Southern Nuclear Operating Company (SNC) a violation, as restated in the enclosure. SNC acknowledges and conaus with the violation. This letter constitutes the required response submittal.
This letter contains no new NRC commitments. If you have any questions, please contact Gene Surber, Ucenslng Manager, at 334.814.5448.
RespectfuUy submitted,
\
~.C'7/~.._
D. R. Madison DRMIRGS
Enclosure:
Reply to Violation EA-17-204 cc: Regional Administrator, Region II NRR Project Manager- Farley Nuclear Plant Senior Resident Inspector- Farley Nuclear Plant RType: CFA04.054
Joseph M. Farley Nuclear Plant- Unit 1 and Unit 2 Reply to a Notice of Violation; EA-17-204 Enclosure Reply to Violation EA-17-204
U. S. Nuclear Regulatory Commission Enclosure to NL-18-0859 Reply to Violation EA-17-204- Page 1 RESTATEMENT OF VIOLATION During an NRC investigation completed on November 16,2017, the following violations of NRC requirements were identified:
- !* SL IV NOV 05000348,05000364/2018014-02; Failure to Provide Complete and Accurate Information Related to System Operator Rounds A. Technical Specification 5.4.1.a, states that 'Written procedures shall be established, implemented, and maintained covering the following activities: The applicable procedures recommended in RG 1.33, Rev. 2, Appendix (App.). A, Feb. 1978."
Regulatory Guide (RG) 1.33, Revision (Rev.) 2, App. A, lists typical safety-related activities that should be covered by written licensee procedures. Item 1.h names administrative procedures for log entries and record retention as one of the written procedures licensees should cover.
Farley Procedure, NMP-OS-007-001, "Conduct of Operations Standards and Expectations,"
Version 14.4, sets forth standards and expectations on various Plant Operations topics, and Section 4.13 sets forth standards and expectations on log keeping and watch station rounds.
- Section 4.13.2(2), Narrative Logs, states, "Log entries are made in a timely manner. Entries provide enough detail for events to be reconstructed at a later date. A log is a legal document and is therefore accurate, factual, complete and clear."
- Section 4.13.2(3), Watch Station Rounds, states, The recording of operating logs is performed during Watch Station Rounds in accordance with an approved schedule. Required readings are taken unless the associated equipment or system is out of service. Readings not taken are noted with a documented reason."
Farley Procedure, FNP-0-SOP-0.11, 'Watch Station Tours and Operator Logs," Version 27.0, provides guidance for conducting watch station tours and use of Operator logs.
Section 6.0, Records, states, "Documents created using this procedure will become QA Records when completed unless otherwise stated."
REASON FOR THE VIOLATION The station conducted a Root Cause of the event. At SNC, personal accountability is a trait of a positive nuclear safety culture. All individuals are expected to take personal responsibility for nuclear safety and uphold the highest levels of integrity. The Root Cause Team determined that the SO's actions of willful falsification of logs during operator rounds was the root cause.
U. S. Nuclear Regulatory Commission Enclosure to NL-18-0859 Reply to Violation EA-17 -204 - Page 2 CORRECTIVE STEPS THAT HAVE BEEN TAKEN AND RESULTS ACHIEVED A Root Cause was conducted and the team (ACT} reviewed the SO information along with an extent of condition review in the areas of fire watches, security, and chemistry. No falsification or integrity issues were identified during the extent of condition review.
The ACT concluded that the falsification of plant records would have been less likely to occur and may have been detected earlier if OE had been effectively implemented and corrective actions for previous integrity issues at FNP had been more broadly applied to other areas.
The SO's involved in the falsification were performance managed. Additionally, the SNC fleet developed and implemented a procedural requirement to perform periodic random verification of records for Operators, Fire watches, and Security Officers rounds to verify that employees are entering the rooms required for their associated logs and the times spent in the rooms is adequate to perform the assigned duties.
Based on the Vogtle event occurring in late 2016, which precipitated the FNP extent of condition investigation, SNC conducted fleetwide training on Upholding our Values (Integrity). This training was based on the research of Professor Dan Ariely, a behavioral economist from Duke University.
The Training included the four Integrity significance factors described in Dr. Ariely's research:
Rationalization, Timely Consequences, Opportunities, and Ethical Reminders.
SNC revised NMP-OS-007-007, Rounds and Log Keeping:
- a. Revise step 3.7.3 to specifically state the operator must review the rounds face to face with the supervisor at the completion of the rounds to discuss any issues.
- b. Revise step 4.2.1.8 to require face to face debriefings.
- c. Added a statement requiring the operator taking logs with the handheld device to use their personal login only (not another person's login).
To better ensure management oversight of SO activities, SNC has revised NMP-OS-007, Conduct of Operations, to clarify that the chain of command for SO's is a single supervisor authority.
SNC enhanced the Operating Experience Program (NMP-GM-008) to better facilitate thorough Extent of Condition reviews. The changes to the procedure provided guidance for an extent of condition review for NRC items like Generic Letters, Information Notices, Bulletins, Regulatory Issue Summaries and other sources of operating experience. The purpose of this action was to ensure that work organizations/disciplines beyond those specifically described in these types of operating experience documents are appropriately considered for actions.
SNC also enhanced the Corrective Action Program through the revision of NMP-GM-002-GL03 (Cause Analysis Guideline) to require that an extent of condition be performed on integrity analysis.
In addition, SNC revised the Corrective Action Program Instruction procedure (NMP-GM-002-001) to have CAs evaluated for potential integrity issues. If a potential integrity issue were to be identified, the procedure directs the performer to notify the appropriate Department Manager.
U.S. Nuclear Regulatory Commission Enclosure to NL-18-0859 Reply to Violation EA-17 -204 - Page 3 Following completion of the corrective actions, Farley documented two events in which an employee recognized and reported a potential integrity issue. In both instances, a non-supervisor employee identified the issue and took the appropriate actions to report the issue to management.
This demonstrates that station employees have internalized the referenced training and expectations regarding integrity at FNP.
CORRECTIVE STEPS THAT WILL BE TAKEN Farley will continue to perform audits of rounds as a long-term corrective action in accordance with the newly developed procedure for rounds verification (NMP-AD-051) and perform the previously discussed log-keeping and oversight activities.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Corrective Actions to address the identified violation are complete. Farley is in full compliance with applicable regulatory requirements.