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Category:Letter type:NL
MONTHYEARNL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-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-24-0201, 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-24-0238, 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-24-0134, 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-23-0877, 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 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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.. Southern Nuclear Dennla R. Madlaon Vice President* FM ey Joseph M. Farley Nuclear Plant 7388 Nolth Slate Hwy 95 COlumbia, Alabama 36319 334.814.4511 tal 334.814.4575 tax June 20, 2018 drmadlsoOsouthemco.com Docket Nos.: 50-348 NL-18-0782 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 and Unit 2 Reply to a Notice of Violation: EA-17-187
Reference:
NRC letter to Southern Nuclear Operating Company, Joseph M. Farley Nuclear Plant -Inspection Report 0500034812018013 and 05000364/2018013; Investigation Report No. 2-2017-oo3; and Notice of Violation (EA-17-187)
Ladies and Gentlemen:
In accordance with the provisions of 1o 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 concurs 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, Licensing Manager, at 334.814.5448.
Respectfully submitted, fo~'YY~ '
D. A. Madison DRMIRGS
Enclosure:
Reply to Violation EA-17*187 cc: Regional Administrator, Region II NRA 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*187 Enclosure Reply to Violation EA-17-187
U.S. Nuclear Regulatory Commission Enclosure to NL-18-0782 Reply to Violation EA-17 -187 - Page 1 RESTATEMENT OF VIOLATION 10 CFR 20.1703 states, in part, if the licensee assigns or permits the use of respiratory protection equipment to limit the intake of radioactive material, (a) The licensee shall use only respiratory protection equipment that is tested and certified by the National Institute for Occupational Safety and Health (NIOSH) except as otherwise noted in this part.
(b) If the licensee wishes to use equipment that has not been tested or certified by NIOSH
... the licensee shall submit an application to the NRC for authorized use of this equipment except as provided in this part. The application must include evidence that the material and performance characteristics of the equipment are capable of providing the proposed degree of protection under anticipated conditions of use. This must be demonstrated either by licensee testing or on the basis of reliable test information.
(e) The licensee shall also consider limitations appropriate to the type and mode of use.
The licensee shall use equipment in such a way as not to interfere with the proper operation of the respirator.
TS 5.4.1.a, Procedures, requires in part, written procedures to be established, implemented and maintained covering the applicable procedures recommended in RG 1.33, Rev. 2, Feb.
1978, Appendix A. Section 7.e.(5), Respiratory Protection, requires procedures for respiratory protection.
Licensee procedure NMP-HP-514, Operation of the 3M AirMate Hood and Powered- Air Purifying Respirator (PAPR) Blower Unit, Version 1.1, provides the following:
Section 5.1.2.2 states, "The [respiratory protective] equipment shall be used in such a way as to not interfere with the proper operation of the respirator."
Section 5.1.3 states, "Only equipment certified by the National Institute for Occupational Safety and Health (NIOSH) or approved by the NRC shall be used when credit is taken for the use of respirators to protect personnel against radioactive material. The 3M Air-Mate Hood and PAPA Blower Unit has been NIOSH approved underTC-21C-635."
Section 5.1.16 states, "DO NOT USE parts not described within this procedure. This action will violate the NIOSH approval (TC-21C-635). The unit MUST be used with the parts described in this procedure regardless of the desired use."
Section 5.1.19 states, "Repair and/or modification of this equipment outside the guidance in this procedure MUST be performed by a qualified individual. Improper repairs or modifications may reduce the effectiveness of the unit and violate the NIOSH approval."
Contrary to the above, on September 8, 2016, the station altered a respiratory protective device in such a way that it interfered with the proper operation of a respirator. Specifically, an SNC Corporate Fleet Radiation Protection Manager, an SNC Corporate Lead Health Physicist, and a Farley Radiation Protection Supervisor directed a Radiation Protection technician to place a
U.S. Nuclear Regulatory Commission Enclosure to NL-18-0782 Reply to Violation EA-17 -187 - Page 2 cover over the power switch of a PAPA which subsequently interfered with the proper operation of the respirator worn by a worker. It was determined that the three licensee officials willfully engaged in the use of parts not described in the site's procedure and thus created an assembly that was not tested and approved by NIOSH or authorized by the NRC. The unauthorized alteration of the respirator inhibited a contract employee's ability to properly operate the PAPA while working in the spent fuel transfer canal. The three licensee officials engaged in deliberate misconduct in violation of 10 CFR 50.5(a)(1), which caused SNC to be in violation of 10 CFA 20.1703(a), (b) and (e), and SNC Procedure NMP-HP-514.
REASON FOR THE VIOLATION Upon reviewing the event, the station concluded that the cause of the event was the failure to follow procedures for respirator use. Although the intent was to protect the worker from inadvertently losing air, the direction to willfully violate the procedure and alter the PAPA is in violation of the CFR.
CORRECTIVE STEPS THAT HAVE BEEN TAKEN AND RESULTS ACHIEVED Following the event, a worker stand-down was conducted along with a Human Performance Review Board to identify lessons learned such that they could be applied organizationally to ensure worker safety. The event was communicated site-wide to all supervisors and above to inform them of the event and included organizational shortfalls of perceived time pressure, lack of attention in proper body positioning, and the unapproved altering of a respirator (bump preventer).
Additionally, SNC evaluated the type of PAPA that was being used across the fleet and adopted the use of an additional type of PAPA specifically for use in tight spaces and not prone to accidental bumping of the power switch. A new procedure was also developed to support the use of the new respirator.
Since the event, there have been no incidents of accidental bumping, emergency egress, or any identified altering of a respirator during the use by any worker.
CORRECTIVE STEPS THAT WILL BE TAKEN There are no additional corrective steps that are necessary for the station to be in compliance with the regulations.
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.