12-28-2016 | On 11/1/2016 at 1743, Farley declared an Alert based on ammonia levels on the radiation side of the Auxiliary Building in the Recycle Evaporator room. The declaration was based on toxic gas emergency action level ( EAL) HA3 which states, "Release of toxic, asphyxiant, or flammable gases within or contiguous to a VITAL AREA which jeopardizes operation of systems required to maintain safe operations or establish or maintain safe shutdown." The source was identified as a failed valve in Auxiliary Steam supply to the Recycle Evaporator system, which had previously been abandoned in place. The ammonia leak was subsequently isolated. Ammonia levels were reduced and the event was terminated at 2340 on 11/1/2016. The failure was determined to be due to ammonia- copper interaction in the brass valve material.
This report is being submitted under 10 CFR 50.73(a)(2)(x) for an event that hampered site personnel in performance of duties necessary for operation of the power plant due to a toxic gas release. |
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Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) 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 ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public 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 ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals 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 ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report 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 IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) 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 IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 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 IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) 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 ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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 ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 2024-01-30
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000364/LER-2017-0052018-01-11011 January 2018 Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector, LER 17-005-00 for Joseph M. Farley Nuclear Plant, Unit 2, Regarding Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector 05000364/LER-2017-0042017-12-22022 December 2017 I OF 3, LER 17-004-00 for Joseph M. Farley Nuclear Plant, Unit 2 Regarding Turbine-Driven Auxiliary Feedwater Pump Steam Admission Valve Air Leak Resulted in a Condition Prohibited by Technical Specifications 05000364/LER-2017-0032017-12-20020 December 2017 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits, LER 17-003-00 for Joseph M. Farley, Unit 2, Regarding Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000364/LER-2017-0022017-12-19019 December 2017 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits, LER 17-002-00 for Joseph M. Farley, Unit 2, Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000364/LER-2017-0012017-08-21021 August 2017 2B Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak without Makeup Capability, LER 17-001-00 for Farley, Unit 2, Regarding 28 Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak without Makeup Capability 05000348/LER-2016-0072017-06-0707 June 2017 Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters, LER 16-007-01 for Joseph M. Farley, Unit 1, Regarding Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters 05000348/LER-2016-0092017-02-0202 February 2017 Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications, LER 16-009-00 for Joseph M. Farley Nuclear Plant, Units 1 and 2 Regarding Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications 05000348/LER-2016-0082017-01-23023 January 2017 Manual Reactor Trip Due to Generator Voltage Swings, LER 16-008-00 for Farley, Unit 1, Regarding Manual Reactor Trip Due to Generator Voltage Swings 05000348/LER-2016-0052016-12-28028 December 2016 Toxic Gas Event, LER 16-005-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Toxic Gas Event 05000348/LER-2016-0042016-12-19019 December 2016 Unapproved Environmental Qualification Material Caused Inoperability of One Containment Cooling Train, LER 16-004-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Unapproved Environmental Qualification Material Caused lnoperability of One Containment Cooling Train 05000348/LER-2016-0062016-12-19019 December 2016 Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump, LER 16-006-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump 05000348/LER-2016-0032016-12-12012 December 2016 Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band, LER 16-003-00 for Farley, Unit 1, Regarding Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band 05000348/LER-2016-0022016-11-30030 November 2016 Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve, LER 16-002-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve 05000348/LER-2016-0012016-06-0909 June 2016 Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications, LER 16-001-00 for Farley, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications 05000364/LER-2015-0012016-01-13013 January 2016 Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications due ,to a Design Issue, LER 15-001-01 for Farley, Unit 2, Regarding Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications Due to a Design Issue NL-13-1525, Special Report 13-001-00 for Joseph M. Farley, Unit 2, Regarding Nonfunctional Radiation Monitor R-60B2013-07-26026 July 2013 Special Report 13-001-00 for Joseph M. Farley, Unit 2, Regarding Nonfunctional Radiation Monitor R-60B NL-11-2445, LER 11-S01-00 for Joseph M. Farley, Unit 1 Regarding Loss of Power to Security Systems2012-01-0909 January 2012 LER 11-S01-00 for Joseph M. Farley, Unit 1 Regarding Loss of Power to Security Systems NL-08-0756, Special Report 2008-002-00, Inoperable Radiation Monitor R-60B2008-05-0909 May 2008 Special Report 2008-002-00, Inoperable Radiation Monitor R-60B NL-08-0659, Special Report 2008-001-00, Inoperable Radiation Monitor R-29B2008-04-25025 April 2008 Special Report 2008-001-00, Inoperable Radiation Monitor R-29B NL-05-2234, Special Report No. 2005-001-00 for Joseph M. Farley Nuclear Plant - Unit 1 Re Inoperable Radiation Monitor R-60B2005-12-0606 December 2005 Special Report No. 2005-001-00 for Joseph M. Farley Nuclear Plant - Unit 1 Re Inoperable Radiation Monitor R-60B 2018-01-11
[Table view] |
Reported lessons leamed are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.goy, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
A. PLANT IDENTIFICATION
Westinghouse - Pressurized Water Reactor
B. DESCRIPTION OF EVENT
On 11/1/2016 at 1743, Farley declared an Alert based on ammonia levels on the radiation side of the Auxiliary Building in the Recycle Evaporator (REV) Room. The declaration was based on toxic gas emergency action level (EAL) HA3 which states, "Release of Toxic, Asphyxiant or Flammable Gases Within or Contiguous to a VITAL AREA Which Jeopardizes Operation of Systems Required to Maintain Safe Operations or Establish or Maintain Safe Shutdown." The toxic gas was identified as ammonia. The source was identified as a failed valve [ISV] in the auxiliary steam system [SA] supply to the REV system [WD], which had previously been abandoned in place. The ammonia leak was subsequently isolated.
Ammonia levels were reduced and the event was terminated at 2340 on 11/1/2016. The event was entered into the corrective action program as Condition Report 10293519.
C. UNIT STATUS AT TIME OF EVENT
Farley Unit 1 was in Mode 2, 1% power Farley Unit 2 (unaffected unit) was in Mode 1, 100% power
D. CAUSE OF EVENT
The direct cause of the event was determined to be degradation of valve [ISV] N1P20V0913, "Condensate Return from Recycle Evaporator Strainer Blowdown Valve." The valve degradation was determined to be due to ammonia induced copper corrosion. Ammonium hydroxide and Hydrazine are added to the secondary side of the steam generators during outage and non-outage conditions. The Hydrazine reacts in the steam generators and produces ammonia, which is carried over in steam. Steam traps in the steam system provide influent flow to the Auxiliary Steam Condensate Tank (ASCT) [TK]. The ASCT vents to atmosphere on the Main Steam Valve Room roof. In addition, the ASCT has a flow path to valve N1P20V0913 due to leak by of a check valve [ISV]. Valve N1P20V0913 is a brass component and the ammonia reacts with the copper in the brass, which degraded the valve over time to provide a flow path the environment. Start-up activities led to additional input flow to the ASCT. This additional input and backflow to N1P20V0913 caused ammonia to enter Room 180 of the Unit 1 Auxiliary Building.
The root cause (RC-1) of this event was inadequate isolation and abandonment of the REV system allowing a backflow path to valve N1P20V0913. When the REV system was abandoned in place in approximately the 1992 timeframe, the guidance for abandonment was not clear. With no maintenance or monitoring of the abandoned system, leak-by from check valve N1P20V005 allowed the flow path to valve N1P20V0913. If the REV system had been effectively abandoned the in place, this backflow path would not have been available. Since that time the process has been improved; however, the need to employ that process for the REV system was not previously recognized.
A second root cause (RC-2) of this event was determined to be the legacy process which allowed for installation of a brass valve N1P20V0913 in a steam system. Operating experience existed as early as 1984, though no formal review process appeared to be in place at the time. A Significant Event Notification (SEN) was published in 1992 describing the ability of ammonia in steam carry-over to react with copper and co
- er allo s. The SEN does not appear to have been considered for this system.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.goy, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. It a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
This event was determined to be reportable under 10 CFR 50.73(a)(2)(x), "Any event that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases," because plant personnel were evacuated from the area. During normal operation, this area is required to be entered to perform rounds and fire watch duties. Equipment in the area is not typically required to be operated for normal plant operation.
Under accident conditions, multiple means are available to provide emergency boration of the reactor coolant system via actions taken in the Control Room. However, in beyond design basis scenarios, operators may need to enter the area to manually operate valves to provide emergency boration if operation from the control room is not available.
The safety significance of this event is considered to be very low because plant personnel were evacuated from the area; there were no radioactive or toxic gas releases to the public; and, the risk of an accident requiring emergency boration via manual actions in the affected area is low.
F. CORRECTIVE ACTION
Immediate corrective action was to evacuate plant personnel, locate and secure the source of the ammonia leak, and ventilate the area.
The REV system will be properly mechanically isolated per current plant modification and configuration change processes.
The engineering design change process will be revised to provide enhanced guidance on material interactions.
G. ADDITIONAL INFORMATION
1) Previous Similar Events: None 2) Commitment Information: No commitments are made in this correspondence.
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05000364/LER-2016-001 | Manual Reactor Trip due to High Steam Generator Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000348/LER-2016-001 | Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications LER 16-001-00 for Farley, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000348/LER-2016-002 | Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve LER 16-002-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000348/LER-2016-003 | Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band LER 16-003-00 for Farley, Unit 1, Regarding Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000348/LER-2016-004 | Unapproved Environmental Qualification Material Caused Inoperability of One Containment Cooling Train LER 16-004-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Unapproved Environmental Qualification Material Caused lnoperability of One Containment Cooling Train | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000348/LER-2016-005 | Toxic Gas Event LER 16-005-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Toxic Gas Event | 10 CFR 50.73(a)(2)(x) | 05000348/LER-2016-006 | Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump LER 16-006-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000348/LER-2016-007 | Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters LER 16-007-01 for Joseph M. Farley, Unit 1, Regarding Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000348/LER-2016-008 | Manual Reactor Trip Due to Generator Voltage Swings LER 16-008-00 for Farley, Unit 1, Regarding Manual Reactor Trip Due to Generator Voltage Swings | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000348/LER-2016-009 | Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications LER 16-009-00 for Joseph M. Farley Nuclear Plant, Units 1 and 2 Regarding Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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